CORRECTION: APRIL is the final month that the user fee for the MCNP5 package will be waived for requesters who received a prior version of MCNP from RSICC. Complete a request form and select the MCNP5 (C00710MNYCP00) package. In the comments field, please state your name and the installation at which you received the earlier version for verification.
RSICC had three visitors from BNFL Instrument Inc. February 2, 2004. David Heath, General Manager, Santa Fe, New Mexico; Ralph Brittelli, Jr., Manager of Eastern Operations - Atlanta Office, and Jack Frye, Eastern Region Sales Representative, Oak Ridge, Tennessee. Discussions included their operations and business with detectors. RSICC discussed our operations and our software within the nuclear instrumentation areas.
Environmental engineering professor Dr. W. Emmett Bolch, passed away at the end of December. He was an expert in radiological techniques, environmental monitoring, radiation protection and radon. Prof. Bolch received his Ph.D. in health physics at the University of California, Berkeley. After coming to the University of Florida in 1966, he taught countless students and supervised numerous graduate students over his 37-year career. He directed a variety of research programs in radiological health, including a 20-year contract with Florida Power Corporation for environmental surveillance of the Crystal River nuclear plant. Prof. Bolch was the recipient of three Teacher-of-the-Year awards at UF and was named a fellow of the National Health Physics Society in 2002. By request, contributions should be made to the Hospice House of Gainesville, 4200 NW 90th Boulevard, Gainesville, FL. 32606.
(taken from the Nuclear & Radiological Review, Winter 2004).
Two new and three newly frozen packages were added to the computer code and data collection this month. Three were foreign contributions.
Lawrence Livermore National Laboratory, Livermore, California, contributed a newly frozen version of this code system for evaluating accidents involving radioactive materials. The HOTSPOT 2.05 codes were created to provide Health Physics personnel with a fast, field-portable calculational tool for evaluating accidents involving radioactive materials. HOTSPOT codes are a first-order approximation of the radiation effects associated with the atmospheric release of radioactive materials.
Four general programs, PLUME, EXPLOSION, FIRE, and RESUSPENSION, calculate a downwind assessment following the release of radioactive material resulting from a continuous or puff release, explosive release, fuel fire, or an area contamination event. Additional programs deal specifically with the release of plutonium, uranium, and tritium to expedite an initial assessment of accidents involving nuclear weapons. The FIDLER program can calibrate radiation survey instruments for ground survey measurements and initial screening of personnel for possible plutonium uptake in the lung.
HOTSPOT is a hybrid of the well-established Gaussian Plume Model, widely used for initial emergency assessment or safety analysis planning of a radionuclide release. Virtual source terms are used to model the initial atmospheric distribution of source material following an explosion, fire, resuspension, or user-input geometry. ICRP Publication 30 Respiratory Tract and ICRP 30 Part IV Systemic models are the basis for the Dose Conversion Factors (DCF). ICRP 26/30 Tissue Weighting Factors are used for the 50-year Committed Effective Dose Equivalent DCF values. HOTSPOT incorporates Federal Guidance Reports 11, 12 and 13 (FGR-11, FGR-12, FGR-13) Dose Conversion Factors for inhalation, submersion, and ground shine.
HOTSPOT runs on personal computers under Windows and is a full 32-bit Windows 95/98/00/XP/NT Application. The included executable was created with Microsoft Visual Basic 6.0 Professional. No source files are included in the package which is transmitted on CD in a ZIP file. Reference: Hot205.HLP electronic help file (November 2003). BASIC; Pentium (C00644IBMPC03).
Japan Atomic Energy Research Institute, Tokai-mura, Ibaraki-ken, Japan, contributed an updated version of this code system for analyzing decay and build-up characteristics of spallation products. The update includes some bug fixes to the code and the addition of a new report, JAERI-Data/Code 2001-016, which is written in Japanese with some appendices written in English.
DCHAIN-SP 2001 estimates the nuclide inventories and radiation environment of high energy accelerator related facilities and was designed to resolve issues regarding spallation neutron utilization facilities. DCHAIN-SP2001 is an update of DCHAIN-SP. For analyzing the decay and build-up characteristics of spallation products, DCHAIN-SP was developed on the basis of CCC-370/DCHAIN2 by revising the decay data and implementing the neutron cross section data. The decay data are newly processed from the data libraries of EAF 3.1, FENDL/D-1 and ENSDF. The neutron cross section data taken from FENDL/A-2 are also prepared to take account of the transmutation of nuclides by the neutron field at the produced position. DCHAIN -SP solves the time evolution of decay and build-up of nuclides in every decay chain by the Bateman method. It can calculate the nuclide inventory, radioactivity, decay heat and gamma-ray energy spectra on the basis of the nuclide production rate calculated by the nucleon-meson transport code NMTC/JAERI97. The package is transmitted on CD as a compressed Unix tar file. The Sun SPARC Compiler Fortran 77 Ver. 4.0 was used for code development. The code was tested at RSICC on Sun Ultra-SparcStation, Dec/Alpha 500au, IBM RS/6000 590, and on an AMD Athlon running RedHat Linux 7.3 with GNU Fortran 0.5.26. References: JAERI-Data/Code-99-008 (March 1999) and JAERI-Data/Code 2001-016 (In Japanese) (February 2001). Fortran 77, Unix system, Sun, DEC, and HPUX (C00712MNYWS01).
Polytechnic of Milan, Milano, Italy, contributed this code system which is based on the Los Alamos National Laboratory code MCNP4C (formerly distributed by RSICC as CCC-700). MCNP-PoliMi was developed to simulate time-analysis quantities. In particular, the PoliMi code includes the correlation between neutron interaction and the corresponding photon production. Conversely to the technique adopted by standard MCNP, MCNP-PoliMi samples secondary photons according to the neutron collision type. A post-processing code, i.e. the Matlab script "postmain," is included and can be tailored to model specific detector characteristics. These features make MCNP-PoliMi a versatile tool to simulate particle interactions and detection processes.
MCNP-PoliMi is operable on Windows-based PCs and is transmitted in a winzip file on CD. The included executable was created with Compaq Visual Fortran Professional Edition 6.6 on a Pentium IV under Windows XP Professional. The MDAS parameter inside the code was set to 16,000,000 (16 Mwords). The plot feature is not included in the distributed executable.
Cross sections are not included in this package. The user is advised to select available ENDF-based MCNP libraries (60C), or those with the most detailed photon production description for the particular problem. DLC-200/MCNPDATA (or equivalent) is suitable for use with MCNP-PoliMi. Reference: "User's Manual," Polytechnic of Milan, Italy (November 25, 2002). Fortran 77; Intel-based PCs. (C00718PC58600).
The Institute of Nuclear Techniques, Budapest University of Technology and Economics, Budapest, Hungary, contributed a newly frozen release of this code system for analysis of correlation matrices used in neutron spectrometry. ACORNS allows the user to verify whether the covariance and correlation matrices used in activation neutron spectrometry are positive definite, that is the eigenvalues of the matrix concerned are all positive. Depending on the available data, diagonalization of the covariance/relative covariance/correlation matrices of neutron spectra/reaction rates/cross sections is performed. The input is qualified on the basis of the eigenvalues. Optionally, the program performs factor analysis to help learn the common reasons for correlations of the quantities investigated.
This release was developed and tested on personal computers and is expected to run on any computer which has a Fortran 90 compiler. Included PC executables were created with Lahey/Fujitsu Fortran 95 Release 5.60 under the Windows 95 operating system. A standard Fortran 90 compiler is required to run on other computers. The codes were tested at RSICC under Windows XP. ACORNS is distributed on a CD in a WinZIP file which includes electronic documents, source code, PC executables and sample problem. References: Budapest University of Technology and Economics (April 2003), BME-TR-RES-10/86(January 1986), and BME-TR-RES-2182 (March 1982). Fortran 90: Personal computers (P00264IBMPC01).
Sandia National Laboratories, Albuquerque, New Mexico, and the U.S. Nuclear Regulatory Commission, Washington, DC, contributed this code system for sector population, land fraction and economic estimation. SECPOP2000 calculates estimated population and economic data about any point (specified by longitude and latitude) that lies within the continental United States. The previous version, SECPOP90, (distributed by RSICC as PSR-378) supports two types of analysis: site and regional. Site analysis provides population and economic data estimates for any location within the continental United States. Calculation results can be displayed, printed, or saved as a rosette, a table, a MACCS2 (MELCOR Accident Consequence Code System) site file, or a MACCS2-like comma-separated-variable file. Regional analysis assesses compliance of available sites against siting parameters (i.e., specific population density criteria). Regional analysis is not supported in SECPOP2000 because some of the software packages originally used for regional analysis are no longer available. SECPOP2000 uses the latest (2000) census data, which provide greater resolution than 1980 and 1990 census data. This greater resolution is achieved by employing over eight million census-block data points and performing the sector population estimates directly from these points. This is an increase of approximately two million data points over the 1990 census data.
SECPOP2000 runs on Pentium or faster Intel processors under Windows 98™, NT™, 2000™, and XP™ operating systems. The included executable was compiled with Visual Basic Version 6.0 with service pack 5 including TrueDBGrid Pro 7.0. The package is transmitted on a CD which includes a setup.exe file that will install the executables, document and directories with census data, site data, and plotting data. Source files are not included. Reference: NUREG/CR-6525, Rev. 1 (August 2003). Visual Basic; Pentium (P00527PC58600).
As years have gone by many different codes and applications have been sent to RSICC for stewardship. We currently have over 1700 analytical code and data packages and distribute as many each year to 73 countries in the world. To help 'categorize' each package, we have developed a database of 'Subject Categories' to attach applications to the packages at RSICC. Doing so requires investigation into each code package, user feedback from end use statements, and extensive RSICC staff experience and analysis so that we can deliver useful information each month on the 30 different categories we have identified thus far. Links to the package abstracts are embedded into the WWW version of the RSICC Newsletter. Feedback from our Newsletter community is very valuable so please direct your comments and/or suggestions to PDC@ORNL.GOV. March's code focus is Isotope Generation & Decay.
RSICC attempts to keep its users/contributors advised of conferences, courses, and symposia in the field of radiation protection, transport, and shielding through this section of the newsletter. Should you be involved in the planning/organization of such events, feel free to send your announcements and calls for papers via email to FINCHSY@ornl.gov with "conferences" in the subject line by the 20th of each month. Please include the announcement in its native format as an attachment to the message. If the meeting is on a website, please include the url.
Every attempt is made to ensure that the links provided in the Conference and Calendar sections of this newsletter are correct and live. However, the very nature of the web creates the possibility that the links may become unavailable. In that case, please call or mail the contact provided. Below is a condensed list of the conferences only listed chronologically. More details (if available) are listed alphabetically following the table.
American Nuclear Energy Symposium 2004
The United States Department of Energy and the American Nuclear Society are pleased to announce the next Americas Nuclear Energy Symposium (ANES 2004), which will take place Sunday through Wednesday, October 3- 6, 2004, at the Deauville Beach Resort in Miami Beach, Florida.
ANES 2004 will feature the theme "Building Bridges to Greater Cooperation." The symposium will provide you with the latest information about the use and development of nuclear energy technology throughout the Americas. The format will include open panel discussions, case studies, technical breakout sessions, and an exhibit of international organizations, not to mention great opportunities to network.
ANES 2004 will include sessions on nuclear reactors; technology development and deployment; production, disposal and usage of isotopes; fuel cycle and waste management; new applications; finance; and environmental, infrastructure and communications issues.
Another successful event is anticipated with the largest number of participants yet attending from across Canada, the Caribbean, Latin America and the United States. Please visit the website at http://anes.fiu.edu for frequent updates.
This workshop will be held at McGill University, Montreal, Canada, from May 3-5, 2004, and aims to bring together medical physicists and researchers to discuss development, clinical implementation and clinical evaluation of Monte Carlo treatment planning techniques in radiotherapy. The meeting will have both invited speakers and proffered contributions and is designed to have plenty of opportunity for informal and in-depth discussions.
For details regarding registration, program, invited speakers, abstract submission, etc, please consult the workshop website: http://mctp.medphys.mcgill.ca. Early registration is encouraged as the number of participants will be limited to around 100.
The 1st International Symposium on Radionuclide Therapy and Radiopharmaceutical Dosimetry will take place in conjunction with the annual European Association of Nuclear Medicine (EANM) congress in Helsinki, Finland, September 4-8, 2004.
The format of the meeting has evolved from a series of seven interesting and important radiopharmaceutical and dosimetry symposia held approximately every 5 years since 1970, with distribution of published proceedings. The last meeting ("7th International Radiopharmaceutical Dosimetry Symposium") was held in Nashville, Tennessee in 2002.
The decisions of the scientific committee and the set-up of the program for Helsinki will be coordinated by the EANM Task Group on Dosimetry and EANM Therapy Committee. All organisational matters will be handled by the EANM.
A call for abstracts (also electronic) will go out in a few months, with authors notified of outcome in approximately May 2004. Contributors will be asked either to bring an electronic version of their manuscript to the meeting in September 2004 or to submit it within two months after the meeting; early plans are to have extended peer-reviewed abstracts published as a supplement to a journal.
Michael Lassmann, Chair T/G Dosimetry EANM, Lassmann@nuklearmedizin.uni-wuerzburg.de
Val Lewington, Chair Therapy Committee, firstname.lastname@example.org
The 5th International Conference on Nuclear Option in Countries
In view of the good response and success of the previous Dubrovnik conferences devoted to the needs and interests of countries with small or medium nuclear systems and electricity grids, the Dubrovnik 2004 conference will serve the same general purpose, with concentration on the topics which invited most interest in the previous conference. The Conference will consider the nuclear option from the point of view of resources, costs, technological, organizational and educational requirements, and environmental advantages. It will also focus on matters related to operational safety, fuel cycle, waste management and decommissioning.
The important goal of the Dubrovnik 2004 conference is to serve as a forum to promote regional co-operation and exchange of experience in the use of nuclear power and fuel cycle facilities among the small or medium European countries interested in the nuclear option.
The Conference will be held September 27-30, 2004, at the Chamber of Commerce of the Republic of Serbia, Belgrade, Serbia & Montenegro. For more information visit http://www.vin.bg.ac.yu/YUNS/Yunsc2004.html.
HCI-2004 will be the 12th conference in an international series taking place every two years around the world. This years will be in Vilnius, Lithuania, September 6-10, 2004. Born in Stockholm in 1982, HCI became a major forum for the presentation and discussion of important new research results in the physics of the Highly Charged Ions. The conference will continue to emphasize basic, fundamental science at the atomic and molecular level, and its applications to important technology challenges. The opportunity will be given to provide insights in other disciplines where HCI-physics have strong impact like Nuclear Physics, Material Science, Radiation Chemistry, Radiobiology, etc.
Some important dates are: deadline for abstracts April 15, 2004; deadline for grant applications April 15, 2004; student housing reservation May 15, 2004; early registration deadline May 15, 2004. For more information, please email email@example.com or see the website: http://www.itpa.lt/hci2004/.
The ANS Topical Meeting on the Technology of Fusion Energy will be held September 14-16, 2004, in Madison, Wisconsin. You are cordially invited to submit one-page abstract(s) describing work that is new, significant, and relevant to both magnetic and inertial fusion technologies. A Microsoft Word template that can be used to create the abstract is available on the TOFE website: http://fti.neep.wisc.edu/tofe.
The 16th Topical Meeting on the Technology of Fusion Energy (TOFE) will continue the tradition of stand-alone topical meetings originated in the early 1970's, continued through the 80's, and re-established in the year 2000 in Park City, Utah. The scope of the TOFE meeting is to provide a forum for sharing the exciting new progress that has been made in fusion research as well as presenting the future of the national and worldwide fusion program.
The two and a half day program of the 16th TOFE meeting will have plenary, oral, and poster sessions, including a mix of invited oral papers and a significant number of contributed oral and poster papers. Key deadlines follow: one-page abstracts (May 1, 2004); nominations for ANS-FED awards (May 31, 2004); notification to authors (June 1, 2004); early registration deadline (August 10, 2004); hotel reservation cutoff date (August 10, 2004); full papers due at the meeting (September 14, 2004).
The International Conference on Nuclear Data for Science and Technology will be held September 26-October 1, 2004, in Santa Fe, New Mexico. This is an OECD-Nuclear Energy Agency Conference, which is held approximately every 3 years. Recent conferences in this series were in Antwerp (1982), Santa Fe (1985), Mito (1988), Jüelich (1991), Gatlinburg (1994), Trieste (1997) and Tsukuba (2001). This International Conference focuses on nuclear data, their production, dissemination, testing and application. The data are produced through both experiment and theoretical models; they are compiled and evaluated to form data libraries for use in applications; and they are tested through benchmark experiments and a very wide range of applications. This Conference includes all of these activities with the goal of improving nuclear data for applications including fission and fusion energy, accelerator driven systems, accelerator technology, spallation neutron sources, nuclear medicine, environment, space, non-proliferation, nuclear safety, astrophysics and cosmology, and basic research. Please see the web site for more information: http://t16web.lanl.gov/nd2004/.
The Tenth International Conference on Radiation Shielding (ICRS-10) and the Thirteenth Topical Meeting of the Radiation Protection and Shielding Division of the American Nuclear Society (RPS 2004) will be held May 9-14, 2004, in Funchal, Madeira Island (Portugal).
The local organization has been assigned to ITN (the Nuclear and Technological Institute, in Lisbon), a laboratory of the Portuguese Ministry of Science and Higher Education. At the international level, the joint organization is co-sponsored by the Nuclear Energy Agency (NEA) of the Organization for Economic Co-operation and Development (OECD), the Radiation Protection and Shielding Division
(RPSD) of the American Nuclear Society (ANS), and the Radiation Safety Information Computational Center (RSICC, Oak Ridge National Laboratory).
It is anticipated that this will be the most important event in the areas of Radiation Shielding and Radiation Protection during 2004. For further information please refer to the Conference website at the following URL http://www.itn.mces.pt/ICRS-RPS. Please don't hesitate to contact the Conference Secretariat at firstname.lastname@example.org.
In addition, if you would be interested in serving on the Scientific Program Committee, and contribute to the success of the meeting by either submitting or encouraging colleagues to submit papers, and participating in the technical review process, please contact the Conference Secretariat at the above email and provide your name, organization, email and topics of interest or expertise. The Organizing Committee welcomes your comments and suggestions to make your meeting a success.
The ICCR 2004 meeting will be held May 10-13, 2004, in Seoul, Korea. Your active participation and contribution will make this conference successful. Additional information is available from the ICCR 2004 conference secretariat at Hanjin Travel Service Co., Ltd. (tel +82-2-726-5554, fax +82-2-778-2514, email email@example.com, url http://www.iccr.info).
Introductory classes are for people who have little or no experience with MCNP. This class surveys the features of MCNP so the beginning user will be introduced to the capabilities of the program, and will have hands-on experience at running the code to solve simple problems. Course topics include Basic Geometry, Source Definitions, Output (Tallies) Specification and Interpretation, Advanced Geometry (repeated structures specification), Variance Reduction Techniques, Statistical Analysis, Criticality, Plotting of Geometry, Tallies, and Particle Tracks, and Neutron/Photon/Electron Physics.
The intermediate to advanced class will be held for people who have used MCNP and want to extend their knowledge and understanding of the code system.
The class will be based on MCNP5 and will cover the new capabilities of version 5. Attendees may elect to receive the new package. If you have previously received an older registered version of MCNP from RSICC, you may request that the MCNP5 package be sent to you at no charge. If you have not received an older version of MCNP from RSICC, you will be charged the applicable transmittal fee.
The other capabilities of MCNP will also be covered, including basic and advanced geometry, source definitions, tallies, data, variance reduction, statistical analysis, criticality, plotting of geometry, and particle tracks, neutron/photon/electron physics.
All classes provide interactive computer instruction. Time will be available to discuss individual questions and problems with MCNP experts or to pursue in more detail topics mentioned in the talks. Please note that other classes are offered based on MCNP. The classes mentioned here are the only ones that are taught by the people who develop and write MCNP.
The Visual Editor is a powerful visualization tool that can be used to rapidly create complex Monte Carlo N Particle (MCNP5) geometry models, including lattices, universes, fills, and other geometrical transformations. The Visual Editor can:Display MCNP5 geometries in multiple plot windows,
Create surfaces and cells to build a geometry,
Create materials using the local xsdir file,
Store commonly used materials in a material library,
Sub-divide large cells into smaller cells,
Create cells containing universes and lattices,
Interactively set cell importances from the plot window, and
Display source points and collision points in the plot window.
Training class is scheduled March 15-19, 2004, in Richland, Washington. The class will focus on the use of the visual editor, with an overview of MCNP. The fifth day is optional and will focus on using the Visual Editor and MCNP to do some example problems.
The class combines teaching on MCNP physics, along with instructions on how to use the Visual Editor. Computer demonstrations and exercises will focus on creating and interrogating input files with the Visual Editor. Demonstrations of advanced visualization work using MCNP will also be made. The class will be taught on Pentium computers running Windows 2000. Attendees are encouraged to bring their own input files for viewing and modifying in the visual editor. For a more detailed description of this course, click here. Further information on this class can be located at: http://www.mcnpvised.com/train.html, or by contacting Randy Schwarz (email firstname.lastname@example.org).
Organizer: HQC Professional Services Contact: email@example.com
More Information: http://mcnpxworkshops.com
MCNPX homepage: http://mcnpx.lanl.gov
MCNPX is the LANL all-particle, all-energy (eV-TeV) Monte Carlo transport code based on MCNP4C, LAHET, CEM, etc. MCNPX has been in active development since 1995, sponsored by the particle accelerator community. It has now become an accepted tool for a broad range of applications by nuclear engineers, physicists, and scientists. The MCNPX development effort has expanded the use of the Los Alamos tools to applications such as APT, waste transmutation, accelerator shielding and health physics, particle beam cancer therapy, space shielding and cosmic ray analysis, single event effects in semiconductors, radiography, and more detailed analysis of the effects of light and heavy ions in matter. In addition, the entire functionality of MCNP4C is retained. New variance reduction and data analysis techniques, many adapted from high energy accelerator methodologies, have also been added, such as the extensive 'mesh tally' capability which allows up to 3-d plotting of particle tracks, fluence and fluence-derived quantities, energy deposition, next event estimator generation contributions and particle sources.
The workshops include hands-on instruction, generally on PC Windows machines. Subject to participant export approval for the MCNPX beta test team, participants will be able to access the Fortran-90 version of MCNPX 2.4, the LA150 (150 MeV) cross-section data for over 40 isotopes for incident neutrons and protons, and 12 for photonuclear interactions, and a notebook of viewgraphs. Follow-up consultation for class participants will be provided.
Classes are taught by experienced MCNPX code developers and instructors. More information on code versions and capabilities is available at MCNPX Workshops web site http://mcnpxworkshops .com.
The Chicago Section of the American Nuclear Society is pleased to announce that it will host the PHYSOR-2004 Topical Meeting, April 25-29, 2004, in Chicago, Illinois. The meeting is co-sponsored by the Reactor Physics Division of the ANS, OECD Nuclear Energy Agency, European Nuclear Society, Canadian Nuclear Society, and the Brazilian National Atomic Energy Commission. The conference will be held at the Hyatt Regency in downtown Chicago.
The title for the meeting is "The Physics of Fuel Cycles and Advanced Nuclear Systems: Global Developments." The technical program will cover more than 15 topical focus areas. You are invited to visit the meeting website at www.physor2004.anl.gov to obtain updated information and to download a copy of the meeting announcement. Contact: Ray Klann, Technical Program Co-Chair, at 630-252-4305 or firstname.lastname@example.org.
FEE: $1,450 per person
PLACE: The MESA Complex, Room 130, University of New Mexico-Los Alamos Campus
Monte Carlo type calculations are ideally suited to solving a variety of problems in radiation protection and dosimetry. This course is aimed at the health physicist, medical physicist, and rad engineer with no prior experience with Monte Carlo techniques. The focus is almost entirely on the application of MCNP™ to solve a variety of practical problems in radiation shielding and dosimetry. The intent is to "jump start" the student toward using MCNP productively. Extensive interactive practice sessions are conducted on a personal computer. Topics will include an overview of the MCNP code and the Monte Carlo method, input file preparation, geometry, source definition, standard MCNP tallies, interpretation of the output file, exposure and dose rate calculations, radiation shielding, photon skyshine, detector simulation and dosimetry. Students will be provided with a comprehensive class manual and a diskette containing all of the practice problems. This course has been granted 32 Continuing Education Credits by the AAHP, and 4.5 CM points by the American Board of Industrial Hygiene. The course is offered by the Health Physics Measurements Group at the Los Alamos National Laboratory and is co-sponsored by RSICC.
Registration is available online at: http://drambuie.lanl.gov/~esh4/mcnp.htm. Make checks payable to the University of California (checks must be in U.S. dollars on a U.S. bank) and mail together with name, address, and phone number to: Los Alamos National Laboratory, Group HSR-4, MCNP Class, David Seagraves, Mail Stop J573, Los Alamos, NM 87545.
Inquiries regarding registration and class space availability should be made to David Seagraves, 505-667-4959, fax: 505-665-7686, e-mail: email@example.com. Technical questions may also be directed to Dick Olsher, 505-667-3364; e-mail: firstname.lastname@example.org.
Please note that this course is separate from and independent of the courses being offered by the MCNP and MCNPX Teams at LANL.
The SCALE staff at Oak Ridge National Laboratory (ORNL) will be offering three training courses this spring, April 26-30, May 3-4, and May 5-7, 2004. The courses will emphasize hands-on experience solving practical problems on PCs. There will be workgroups of two persons each. Courses are open to both new and experienced SCALE users. Registration must be submitted by March 26, 2004. After that date a surcharge of $300 will be added to the fee.
Classes are cosponsored by RSICC which offers a discounted price of $200 (single user license) to all attendees for the SCALE software and manual on CD.
Registration forms should be submitted from the Web. Registration via fax is also acceptable. The registration fee may be paid by check, bank transfer, or credit card (VISA or MasterCard only). Course agendas and description information are found at http://www.ornl.gov/sci/scale/trcourse.html. Class size is limited and courses are subject to cancellation if minimum enrollment is not obtained one month prior to the course. Course fees are refundable up to one month before each class.
Foreign nationals must register at least eight weeks in advance to obtain security clearance. For further information, contact Kay Lichtenwalter, email@example.com, 865-574-9213.
Contact information: Tel 215-728-5665, Fax: 215-728-4789; Email: firstname.lastname@example.org
Venue: Radiation Oncology, FCCC, Philadelphia, PA
Date: April 8-10, 2004
The course registration fee is $1600, which covers the course materials, two lunches, two dinners and refreshments. A set of software is free for the attendee. Discounts for students are available. Hotel information is available upon request.
The short course is designed to train future Monte Carlo RTP users and researchers in the use of Monte Carlo treatment planning software. The course will include didactic instruction and hands-on workshops. The course is specially suited for previous EGS4 and OMEGA/BEAM course participants, who want to expand their research into clinical RTP. A working knowledge of a Unix-based system is expected to run the Monte Carlo RTP software.
Enrollment will be limited to 20 people to facilitate instruction at the hands-on labs. So please register early. Registration will be strictly on a first-come basis. Please contact Dr. Jinsheng Li, at email@example.com or see the website: http://www.fccc.edu/clinical/radiation_oncology/ monte_carlo_course.html.
Monte Carlo 2005 will be held April 17-21, 2005, (Sunday-Thursday). The theme of the conference will be "The Monte Carlo Method: Versatility Unbounded in A Dynamic Computing World".
The conference site is the Chattanooga Marriott and Convention Center in Chattanooga, Tennessee. The conference will be hosted by the American Nuclear Society (ANS) Oak Ridge/Knoxville Section, with ANS Radiation Protection and Shielding Division (RPSD) as the sponsoring division and Mathematics and Computations Division (MCD) as a co-sponsor. Co-sponsors will also include Oak Ridge National Laboratory (ORNL), Radiation Safety Information Computational Center (RSICC) and the Organization for Economic Cooperation and Development (OECD) Nuclear Energy Agency Data Bank (NEADB).
The Monte Carlo method and its applications have been frequently addressed at several major conferences and workshops organized in recent years in the area of nuclear applications. Monte Carlo topics have included radiation shielding, radiation physics, medical physics, and high energy physics. Significant developments have taken place in computational and data issues, resulting in state-of-the-art computer codes and tools. Monte Carlo 2005 is the next in a series devoted to the topic, following Monte Carlo 2000 which was held in Lisbon, Portugal, in October 2000.
Conference topics will include: Methods Advancements (Physics) (proton transport, neutron transport, gamma transport, electron transport, heavy ion transport); Nuclear Data Advancements (proton transport, neutron transport, gamma transport, electron transport, heavy ion transport); Mathematical and Computational Advances (experiments & benchmarks, mathematical advances, computational advances, visualization); Applications (reactor, medical, accelerator, neutron science, dosimetry, shielding, fuel cycle, waste management, space & aviation, fusion, criticality safety, non-nuclear applications).
The website is http://MonteCarlo2005.org. Full papers are due September 10, 2004. For information contact Bernadette Kirk (firstname.lastname@example.org, 865-574-6176), General Chair, or Jeff Johnson (email@example.com, 865-574-5262), Technical Chair.
The Twelfth International Symposium on Reactor Dosimetry will be held May 8-13, 2005, in Gatlinburg, Tennessee.
This Symposium is held approximately every three years to provide a forum for the interchange of state-of-the-art techniques, data bases and standardization of radiation metrology. The Symposium will be of value to those involved in reactor dosimetry, including researchers, manufacturers and representatives from industry, utilities and regulatory agencies.
This Symposium is jointly sponsored by ASTM International, the European Working Group on Reactor Dosimetry (EWGRD), and the Atomic Energy Society of Japan (AESJ). It is organized by ASTM Committee E10 on Nuclear Technology and Applications and EWGRD.
The Symposium will be organized into oral and poster presentations, informal round-table workshops and tutorials. The meeting language will be English. No translations will be provided.
All papers presented at the Symposium will be subject to peer-review before acceptance for publication in the on-line Journal of ASTM International. Registrants will receive a complimentary CD of the papers presented at the Symposium. For more information visit the website at: http://reactordosimetry.com/.
PHYSOR 2004 Reactor Physics Topical Meeting, Apr. 25-29, 2004, Chicago, IL. Jointly sponsored by the Reactor Physics Division of the ANS and the Nuclear Energy Agency of the OECD and others. Contact: Ray Klann (tel 630-252-4305, email firstname.lastname@example.org, url http://www.physor2004.anl.gov/).
9th Workshop on Monte Carlo Simulation of Radiotherapy Treatment Sources Using the BEAM Code System, Apr. 26-29, 2004, Ottawa, Canada. Contact: Dave Rogers (tel 613-520-2600 x4374, fax 613-520-4061, email email@example.com, url www.physics.carleton.ca/~drogers/BEAM/course/brochure.html).
Current Topics in Monte Carlo Treatment Planning, May 3-5, 2004, McGill University, Montreal, Canada. Contacts: Jan Seutjens and Frank Verhaegen (tel 514-934-8052, url http://mctp.medphys.mcgill.ca).
International Conference on Radiation Shielding (ICRS-10) and Topical Mtg. on Radiation Protection & Shielding (RPS 2004), May 9-14, 2004, Funchal, Madeira Island (Portugal). Contact: Conference Secretariat (email firstname.lastname@example.org, url http://www.itn.mces.pt/ICRS-RPS).
5th Intl. Conference on Nuclear Option in Countries with Small and Medium Electricity Grids, May 16-20, 2004., Dubrovnik, Croatia, Contact Prof. Nenad Debrecin (tel +385- 1-6312-399, email email@example.com, url http://hnd.zvne.fer.hr/Dubrovnik2004).
Practical MCNP for the HP, Medical Physicist, and Rad Engineer, June 7-11, 2004, Univ. of New Mexico, Los Alamos Campus. Contact: David Seagraves, (tel 505-667-4959, fax 505-665-7686, e-mail firstname.lastname@example.org. Technical questions may also be directed to Dick Olsher, 505-667-3364; e-mail email@example.com, url http://drambuie.lanl.gov/~esh4/mcnp.htm).
1st International Symposium on Radionuclide Therapy and Radiopharmaceutical Dosimetry, Sept. 4-8, 2004, Helsinki, Finland. Contact: Michael Lassmann or Val Lewington, (emails lassmann@ nuklearmedizin.uni-wuerzburg.de; vjlewington@ hotmail.com).
16th American Nuclear Society Topical Meeting on the Technology of Fusion Energy, Sept. 14-16, 2004, Madison, WI. (url http://fti.neep.wisc.edu/tofe).
International Conference on Nuclear Data for Science and Technology "ND2004", Sept. 26-Oct. 1, 2004, Santa Fe, NM. (Contact: http://t16web.lanl.gov/nd2004/).
5th International Conference of Yugoslav Nuclear Society (YUNS) - 2004, Sept. 27-30, 2004, Belgrade, Serbia & Montenegro. Contact: Dr. Milan Pesic, (tel 381-11-245-82-22/ext. 681, email firstname.lastname@example.org, url http://www.vin.bg.ac.yu/YUNS/index.htm).
11th World Congress on Neutron Capture Therapy (ISNCT-11), Oct. 11-15, 2004, Boston, MA. Contact: Robert G. Zamenhof (tel 617-636-1681, fax 617-636-5867, email email@example.com, url http://meetingsandconferences.com/ISNCT-11/).
Monte Carlo 2005 Topical Meeting, Apr. 17-21, 2005, Chattanooga, TN. Contact: Bernadette Kirk (tel 865-574-6176, fax 865-241-4046, email firstname.lastname@example.org, url http://meetingsandconference.com /MonteCarlo2005).
The nuclear systems literature (shielding, safety, materials) cited below has been reviewed and placed in the RSICC Information Storage and Retrieval Information System (SARIS), now searchable on the RSICC web server (http://www-rsicc.ornl.gov/SARIS.html). We now include medical physics in addition to material science, radiation dosimetry, radiation safety, reactor dynamics, reactor safeguards, risk assessment, waste management, fuel cycle, fusion and plasmas, high energy particle transport, and shielding. This early announcement is made as a service to the nuclear sciences community. Copies of the literature are not distributed by RSICC. They may generally be obtained from the author or from a documentation center such as the National Technical Information Service (NTIS), Department of Commerce, Springfield, Virginia 22161.
Ann. Nucl. Energy, 31, 459-480. . . Minimizing the Gamma Radiation Effects to Spent Fuel Pool Walls. . . .Tippayakul, C. et al. . . . March 2004. . . Penn. State University, PA; Exelon, Corp., USA.
Ann. Nucl. Energy, 31, 481-516. . . Probabilistic Safety Analysis of a Greek Research Reactor. . . .Aneziris, O.N. et al. . . . March 2004. . . National Center for Scientific Research DEMOKRITOS, Aghia Paraskevi, Greece.
Ann. Nucl. Energy, 31, 517-540. . . Development, Assessment and Application of TRAC-BF1/v2001.2 for Beyond Design Basis BWR LOCA Transients. . . .Analytis, G.Th. et al. . . . March 2004. . . Paul Scherrer Institute, Villigen, Switzerland.
Ann. Nucl. Energy, 31, 541-576. . . Minimum Critical Mass and Flat Flux in a 2-Group Model. . . .Lewins, J. . . . March 2004. . . University of Cambridge, United Kingdom.
Ann. Nucl. Energy, 31, 577-582. . . The Photon Attenuation Coefficients of Barite, Marble and Limra. . . .Akkurt, I. et al. . . . March 2004. . . Suleyman Demirel University, Isparta, Turkey.
Ann. Nucl. Energy, 31, 583. . . Book Review: Understanding Radioactive Waste, R. L. Murray; 5th Edition, Paperback, 231 Pages, Battelle Press, Columbus, OH, 2003, ISBN 1-57477-135-3. . . .Putte, D.V. . . . March 2004. . . Electrowatt-Ekono, West Sussex, United Kingdom.
Ann. Nucl. Energy, 31, 713-722. . . Comparison Between HELIOS Critical-Depletion Calculations and a PWR Thorium Cell Burnup Benchmark. . . .Nunez-Carrera, A. et al. . . . May 2004. . . Comision Nacional de Seguridad Nuclear y Salvaguardias, Navarte, Mexico; Universidad Nacional Autonoma de Mexico, Mor., Mexico; Universidad Metropolitana, Vicentia, Mexico.
Ann. Nucl. Energy, 31, 723-736. . . Analysis of a PWR Core Baffle Considering Irradiation Induced Creep. . . .Altstadt, E. et al. . . . May 2004. . . Institute of Safety Research, Dresden, Germany; E.ON Nuclear Power, Hannover, Germany.
Ann. Nucl. Energy, 31, 737-745. . . Cold and Thermal Neutron Scattering Cross Sections of Liquid H2 and D2. II: Improvement on Coherent Scattering. . . .Morishima, N. et al. . . . May 2004. . . Kyoto University, Japan.
Ann. Nucl. Energy, 31, 747-772. . . Development of the VVER Core Loading Optimization System. . . .Guler, C. et al. . . . May 2004. . . Penn. State University, University Park, PA; SKODA, Plzen, CzechRepublic.
Ann. Nucl. Energy, 31, 773-788. . . On-Line Channel Instability Localisation with Fuzzy Rule-Based Systems. . . .Tambouratzis, T. et al. . . . May 2004. . . Institute of Nuclear Technology, Athens, Greece; Aristotle University of Thessaloniki, Greece.
Ann. Nucl. Energy, 31, 789-803. . . Using a Multi-State Recurrent Neural Network to Optimize Loading Patterns in BWRs. . . .Ortiz, J.J. et al. . . . May 2004. . . ININ, Mexico; University Granada, Spain.
Ann. Nucl. Energy, 31, 805-811. . . Radiation Effects on the Resolution (MTF) of the Scintillator Coupled CMOS APS Array Imager for Non-Destructive Test X-Ray Imaging. . . .Kim, K.H. et al. . . . May 2004. . . KAIST, Daejeon, South Korea.
Ann. Nucl. Energy, 31, 813-821. . . ADS Subcriticality Evaluation Based on the Generalized Reactivity Concept. . . .Gandini, A. . . . May 2004. . . University of Rome, Italy.
Ann. Nucl. Energy, 31, 823. . . Addendum to "On the Collision Probability for the Infinite Cylinder". . . .Corngold, N. . . . May 2004. . . California Institute of Technology, Pasadena, CA.
Ann. Nucl. Energy, 31, 825-847. . . Cell Homogenization Methods for Pin-By-Pin Core Calculations Tested in Slab Geometry. . . .Yamamoto, A., et al. . . . May 2004. . . Nagoya University, Japan.
Ann. Nucl. Energy, 31, 849-869 . . Development of Automated Operating Procedure System Using Fuzzy Colored Petri Nets for Nuclear Power Plants. . . .Lee, S.J. et al. . . . May 2004. . . Korea Advanced Institute of Science and Technology, Daejeon, South Korea.
Ann. Nucl. Energy, 31, 871-890. . . LWR Spent Fuel Transmutation in a High Power Density Fusion Reactor. . . .Sahin, S. et al. . . . May 2004. . . Gazi Universitesi, Ankara, Turkey.
Ann. Nucl. Energy, 31, 891-909. . . Computing Neutron Detector Response to Power Reactor Mechanical Structure Vibrations. . . .Dobrea, D. et al. . . . May 2004. . . Institute for Nuclear Research, Pitesti, Romania.
Ann. Nucl. Energy, 31, 911-921. . . Thermal Neutron Cross-Sections of Magnesium. . . .Mounier, C. . . . May 2004. . . CEA-Saclay, Gif-sur-Yvette, France.
Ann. Nucl. Energy, 31, 923-931. . . View-CXS Neutron and Photon Cross-Sections Viewer.. . .Subbaiah, K.V. et al. . . . May 2004. . . Safety Research Institute, Tamilnadu, India.
Ann. Nucl. Energy, 31, 933-946. . . The Extinction Problem in a Super-Critical Sphere of Fissile Material. . . .Williams, M.M.R. . . . May 2004. . . Imperial College of Science, Technology, and Engineering, London, United Kingdom.
Ann. Nucl. Energy, 31, 947-960. . . Modeling of the Interfacial Shear in the 3D Momentum Equations of TRAC-BF1. . . .Analytis, G. Th. . . . May 2004. . . Paul Scherrer Institute, Villigen, Switzerland.
Fusion Eng. Design, 70, 1-3. . . International Science and Technology Center, A Decade of Joint Efforts for a Safer World. . . .Kroening, M. . . . January 2004. . . International Science & Technology Center, Moscow, Russia.
Fusion Eng. Design, 70, 5-11. . . Efficiency Measurement of 6LiD Converter of Thermal to Fast Neutrons of (DT), (6LiD) Fusion with 14 MeV Energy in IVV-2M Reactor Experimental Channel. . . .Zouev, Yu. N. et al. . . . January 2004. . . Russian Federal Nuclear Center, Snezhinsk, Russia; Sverdlovsk Branck of NIKIET, Russia.
Fusion Eng. Design, 70, 13-33. . . Gas Dynamic Trap as High Power 14 MeV Neutron Source. . . .Bagryansky, P.A. et al. . . . January 2004. . . Budker Institute of Nuclear Physics, Novosibirsk, Russia; Institute of Technical Physics, Snezhinsk, Russia.
Fusion Eng. Design, 70, 35-43. . . Fusion in the Magnetically Compressed Targets. . ..Mokhov, V.N. et al. . . . January 2004. . . Russian Federal Nuclear Center, Sarov, Russia.
Fusion Eng. Design, 70, 45-56. . . The Development of Low Aspect Ratio Tokamaks in Russia. . . .Azizov, E.A. et al. . . . January 2004. . . RF State Scientific Center, TRINITI, Troitsk, Russia; RSC Kurchatov Institute, Moscow, Russia; Efermov Institute of Electrophysical Apparatus, St. Petersburg, Russia.
Fusion Eng. Design, 70, 57-66 . . The Effect of Tritium and Neutron Irradiation on the Structure and Properties of Reactor Steels and Alloys. . . .Sagaradze, V.V. et al. . . . January 2004. . . Institute of Metal Physics, Ekaterinburg, Russia; Russian Federal Nuclear Center, Snezhinsk, Russia.
Fusion Eng. Design, 70, 67-77. . . Tritium Permeation Through Martensitic Steel from Li17Pb83 in In-Pile Reactor Experiments. . . .Shestakov, V. . . . January 2004. . . Scientifically Research Institute of Experimental and Theoretical Physics, Almaty, Kazakhstan.
Fusion Eng. Design, 70, 79-85. . . Creep Surge Effect Under Cyclic Irradiation of Structural Materials for Fusion Reactors.. . .Tsepelev, A.B. . . . February 2004. . . Russian Academy of Sciences, Moscow, Russia.
Fusion Eng. Design, 70, 87-93. . . Fabrication of CaO Insulator Coatings by MOCVD for Application in Vanadium/Lithium Blankets. . . .Zeng, Z. et al. . . . February 2004. . . Argonne National Laboratory, Argonne, IL.
Fusion Eng. Design, 70, 115-122. . . Trends in Computing Systems for Large Fusion Experiments. . . .How, J.A. et al. . . . February 2004. . . Euratom-CEA, St. Paul lez Durance, France; Euratom-UKAEA, Abingdon, UK; Euratom-ENEA, Padova, Italy.
Fusion Eng. Design, 70, 123-129. . . Radiochemical Reactions Between Tritium Oxides and Carbon Monoxide. . . .Shu, W.M. et al. . . . February 2004. . . JAERI, Ibaraki, Japan.
Fusion Eng. Design, 70, 141-153. . . Positron Annihilation Investigations of Defects in Copper Alloys Selected for Nuclear Fusion Technology. . . .Slugen, V. et al. . . . February 2004. . . Slovak University of Technology, Bratislava, Slovak Republic; Charles University, Prague, Czech Republic; Universitat der Bundeswehr Munchen, Neubiberg, Germany.
Fusion Eng. Design, 70, 155-162 . . Monte Carlo Based Operational and Shutdown Dose Rate Calculations of HT-7U Tokamak. . . .Chen, Y. et al. . . . February 2004. . . Institut fur Reaktorsicherheit, Karlsruhe, Germany; Institute of Plasma Physics of Chinese Academy of Sciences, Anhui, China.
Fusion Eng. Design, 70, 163-173. . . Application of Glow Discharges for Tritium Removal from JT-60U Vacuum Vessel. . . .Nakamura, H. et al. . . . February 2004. . . JAERI, Ibaraki, Japan; Kyoto University, Japan; Nagoya University, Nagoya, Japan.
Fusion Eng. Design, 70, 175-183 . . Development of Plasma Stored Energy Feedback Control and Its Application to High Performance Discharges on JT-60U. . . .Oikawa, T. et al. . . . February 2004. . . JAERI, Ibaraki, Japan; Osaka University, Osaka, Japan.
J. Nucl. Mater., 324, 1-5. . . Production of Uranium-Molybdenum Particles by Spark-Erosion. . . .Cabanillas, E.D. et al. . . . January 2004. . . Consejo Nacional de Investigaciones Cientificas y Tecnicas, Buenos Aires, Argentina; Comision Nacional de Energia Atomica, Buenos Aires, Argentina; Universidad de Buenos Aires, Argentina.
J. Nucl. Mater., 324, 6-22. . . Structure of Zirconium Alloy Oxides Formed in Pure Water Studied with Synchrotron Radiation and Optical Microscopy: Relation to Corrosion Rate. . . .Yilmazbayhan, A. et al. . . . January 2004. . . Penn. State University, University Park, PA; Westinghouse Electric Co., Pittsburgh, PA; Argonne National Laboratory, IL.
J. Nucl. Mater., 324, 23-32. . . Effect of the Irradiation-Annealing-Irradiation Cycle on the Mechnaical Properties of Pure Copper and Copper Alloy. . . .Fabritsiev, S.A. et al. . . . January 2004. . . D.V. Efremov Scientific Research Institute of Electrophysical Apparatus, St. Petersburg, Russia; Scientific Research Institute of Atomic Reactors, Dimitrovgrad, Russia.
J. Nucl. Mater., 324, 33-40. . . Effect of Microstruture on the Cleavage Fracture Strength of Low Carbon Mn-Ni-Mo Bainitic Steels. . . .Im, Y-R., et al. . . . January 2004. . . Seoul National University, South Korea; Pohang Univeristy of Science and Technology, Pohang, South Korea; Hanbat National University, Taejon, South Korea; KAERI, Taejon, South Korea.
J. Nucl. Mater., 324, 41-51. . . Simulations of Low Energy Cascades in FCC Pu Metal at 300 K and Constant Volume. . . .Valone, S.M. et al. . . . January 2004. . . Los Alamos National Laboratory, Los Alamos, NM.
J. Nucl. Mater., 324, 52-61. . . Development of a Fundamental Crack Tip Strain Rate Equation and Its Application to Quantitative Prediction of Stress Corrosion Cracking of Stainless Steels in High Temperature Oxygenated Water. . . .Peng, Q.J. et al. . . . January 2004. . . Tohoku University, Sendai City, Japan.
J. Nucl. Mater., 324, 62-70. . . Microstructural Development and Radiation Hardening of Neutron Irradiated Mo-Re Alloys.. . .Nemoto, Y. et al. . . . January 2004. . . JAERI, Ibaraki-ken, Japan; Tohhoku University, Sendai City, Japan; Okayama University of Science, Okayama, Japan.
J. Nucl. Mater., 324, 71-75. . . Studies on the Corrosion Behavior of Cerium-Implanted Zirconium. . . .Peng, D.Q. et al. . . . January 2004. . . Tsinghua University, Beijing, China.
J. Nucl. Mater., 324, 77-89. . . The Change in Tensile Properties of Wrought LCAC Molybdenum Irradiated with Neutrons. . . .Cockeram, B.V. et al. . . . January 2004. . . Bettis Atomic Power Laboratory, West Mifflin, PA; Oak Ridge National Laboratory, Oak Ridge, TN.
J. Nucl. Mater., 324, 90-96. . . Modelling of Copper Precipitation in Iron During Thermal Aging and Irradiation. . . .Christien, F. et al. . . . January 2004. . . Ecole Polytechnique, Palaiseau, France.
J. Nucl. Mater., 324, 97-115. . . Modelling the Alteration Gel Composition of Simplified Borosilicate Glasses by Precipitation of an Ideal Solid Solution in Equilibrium with the Leachate. . . .Munier, I. et al. . . . January 2004. . . Ecole et Obnservatoire des Sciences de la Terre, Strasbourg, France; Ecole des Mines, Nantes, France.
J. Nucl. Mater., 324, 116-124. . . Failure Predictions for Nuclear Graphite Using a Continuum Damage Mechanics Model. . . .Zou, Z. et al. . . . January 2004. . . University of Manchester, United Kingdom.
J. Nucl. Mater., 324, 125-133. . . Mechanical Properties of Delta-Stabilized Pu-1.0 wt% Ga Alloys. . . .Robbins, J.L. . . . January 2004. . . Lawrence Livermore National Laboratory, Livermore, CA.
J. Nucl. Mater., 324, 134-139. . . Etching of Uranium Oxide with a Non-Thermal, Atmospheric Pressure Plasma. . . .Yang, X. et al. . . . January 2004. . . University of California, Los Angeles, CA; Surfx Technologies, Los Angeles, CA.
J. Nucl. Mater., 324, 140-151. . . Dynamic Strain Aging and Grain Size Reduction Effects on the Fatigue Resistance of SA533B3 Steels. . . .Huang, J.Y. et al. . . . January 2004. . . National Central University, Chung-Li, Taiwan; Institute of Nuclear Energy Research, Lungtan, Taiwan; Taiwan Power Company, Taipei, Taiwan.
J. Nucl. Mater., 324, 152-164. . . Role of Neoformed Phases on the Mechanisms Controlling the Resumption of SON68 Glass Alteration in Alkaline Media. . . .Ribet, S. et al. . . . January 2004. . . Commissariat a l'Energie Atomique, Bagnols-sur-Ceze, France.
J. Nucl. Mater., 324, 165-176. . . Comments on the Stability of Zirconium Hydride Phases in Zircaloy. . . .Lanzani, L. et al. . . . January 2004. . . CNEA, Buenos Aires, Argentina.
J. Nucl. Mater., 324, 177-182. . . Oxidation Behaviour of Uranium in the Internally Gelated Urania-Ceria Solid Solutions - XRD and XPS Studies. . . .Kumar, K.S. et al. . . . January 2004. . . Bhabha Atomic Research Centre, Tamil Nadu, India; Indira Gandhi Centre for Atomic Research, Tamil Nadu, India; IAEA, Vienna, Austria.
J. Nucl. Mater., 324, 183-188. . . Safe Trapping of Cs in Heat-Treated Zeolite Matrices. . . .Bosch, P. et al. . . . January 2004. . . Universita di Napoli Federico II, Napoli, Italy.
J. Nucl. Mater., 324, 189-197. . . Bulk and Young's Modulus of Doped UO2 by Synchrotron Diffraction Under High Pressure and Knoop Indentation. . . .Pujol, M.C. et al. . . . January 2004. . . Joint Research Centre, Karlsruhe, Germany; Charles University, Prague, Czech Republic.
J. Nucl. Mater., 324, 198-202. . . Post-Irradiation Studies on LWR-MOX Fuel Fabricated by the Optimized Co-Milling Process.. . .Kleykamp, H. . . . January 2004. . . Forschungszentrum Karlsruhe, Germany.
J. Nucl. Mater., 324, 203-214. . . Cathodoluminescence Imaging of Oxidised Zirconium Alloys. . . .Yueh, H.K. et al. . . . January 2004. . . University of Toronto, Ontario, Canada.
J. Nucl. Mater., 324, 215-219. . . Calorimetric Measurements on Uranium-Plutonium Mixed Oxides. . . .Kandan, R. et al. . . . January 2004. . . Indira Gandhi Centre for Atomic Research, Tamil Nadu, India.
J. Nucl. Mater., 325, 1-12. . . Helium Diffusion in Uranium and Plutonium Oxides.. . .Ronchi, C. et al. . . . February 2004. . . Joint Research Center, Karlsruhe, Germany.
J. Nucl. Mater., 325, 13-17. . . Corrosion Behavior of Fe-Ni-Cr Alloys in the Molten Salt of LiCl-Li2O at High Temperature. . . .Cho, S.H. et al. . . . February 2004. . . KAERI, Taejon, South Korea; Dalian University of Technology, China.
J. Nucl. Mater., 325, 18-25. . . Thermal Expansion Studies on Inconel-600 by High Temperature X-Ray Diffraction. . . .Raju, S. et al. . . . February 2004. . . Indira Gandhi Centre for Atomic Research, Kalpakkam, India.
J. Nucl. Mater., 325, 26-33 . . Stress-Reorientation of Hydrides and Hydride Embrittlement of Zr-2.5 wt% Nb Pressure Tube Alloy. . . .Singh, R.N. et al. . . . February 2004. . . Bhabha Atomic Research Centre, Mumbai, India; Indian Institute of Technology, Mumbai, India.
J. Nucl. Mater., 325, 34-43. . . Electrochemical Behaviors of Uranium and Plutonium at Simultaneous Recoveries into Liquid Cadmium Cathodes. . . .Uozumi, K. et al. . . . February 2004. . . Central Research Institute of Electric Power Industry, Tokyo, Japan; JAERI, Ibaraki-ken, Japan.
J. Nucl. Mater., 325, 44-52. . . Master Equation and Fokker-Planck Methods for Void Nucleation and Growth in Irradiation Swelling. . . .Surh, M.P. et al. . . . February 2004. . . Lawrence Livermore National Laboratory, Livermore, CA.
J. Nucl. Mater., 325, 53-60 . . Recrystallization and Precipitation Behavior of Low-Activation V-Cr-Ti Alloys After Cold Rolling. . . .Heo, N.J. et al. . . . February 2004. . . Graduate University for Advanced Studies, Gifu, Japan; National Institute for Fusion Science, Gifu, Japan.
J. Nucl. Mater., 325, 61-77. . . The Development of Grain-Face Porosity in Irradiated Oxide Fuel. . . .White, R.J. . . . February 2004. . . RW Consulting, Gloucestershire, United Kingdom.
J. Nucl. Mater., 325, 79-86. . . Hydrogen Embrittlement of a V4Cr4Ti Alloy Evaluated by Different Test Methods. . . .Chen, J. et al. . . . February 2004. . . Southwestern Institute of Physics, Chengdu, PR China; National Key Laboratory of Nuclear Fuel and Materials, Chengdu, PR China; National Institute for Fusion Science, Gifu, Japan.
J. Nucl. Mater., 325, 87-93 . . Chemical Form of Tritium Released from Solid Breeder Materials. . . .Nishikawa, M. et al. . . . February 2004. . . Kyushu University, Fukuoka, Japan.
J. Nucl. Mater., 325, 94-106. . . The Effect of Oversized Solute Additions on the Microstructure of 316SS Irradiated with 5MeV Ni++ Ions of 3.2 MeV Protons. . . .Gan, J. et al. . . . February 2004. . . Argonne National Laboratory - West, Idaho Falls, ID; Pacific Northwest National Laboratory, Richland, WA; University of Michigan, Ann Arbor, MI.
J. Nucl. Mater., 325, 107-117. . . A Model for Fission-Gas-Bubble Behavior in Amorphous Uranium Silicide Compounds. . . .Rest, J. . . . February 2004. . . Argonne National Laboratory, Argonne, IL.
J. Nucl. Mater., 325, 118-128. . . Irradiation Behaviour of Uranium Silicide Compounds. . . .Finlay, M.R. et al. . . . February 2004. . . Australian Nuclear Science and Technology Organisation, Menai, Australia; Argonne National Laboratory, Argonne, IL.
J. Nucl. Mater., 325, 129-133 . . Measurement of Gd Content in (U,Gd)O2 Using Thermal Gravimetric Analysis. . . .Kim, K.S. et al. . . . February 2004. . . KAERI, Daejon, South Korea; Chungnam National University, Daejon, South Korea.
J. Nucl. Mater., 325, 134-140. . . Novel Approach for the Bulk Synthesis of Nanocrystalline Yttria Doped Thoria Powders Via Polymeric Precursor Routes. . . .Ganesan, R. et al. . . . February 2004. . . Indira Gandhi Centre for Atomic Research, Kalpakkam, India; Pondicherry University, India; Indian Institute of Technology, Mumbai, India.
J. Nucl. Mater., 325, 141-147. . . Effect of Titania Addition on Hot Hardness of UO2.. . .Sengupta, A.K. et al. . . . February 2004. . . Bhabha Atomic Research Centre, Mumbai, India.
J. Nucl. Mater., 325, 148-158. . . Helium Thermal Diffusion in a Uranium Dioxide Matrix. . . .Roudil, D. et al. . . . February 2004. . . CEA VALRHO Maracoule, Bagnols-sur-Ceze, France; CEA SACLAY, Gif-sur-Yvette, France.
J. Nucl. Mater., 325, 159-168. . . Fabrication of (Th,U)O2 Pellets Cotaining 3Mol% of Uranium by Gel Pelletisation Technique. . . .Pai, R.V. et al. . . . February 2004. . . Bhabha Atomic Research Centre, Mumbai, India.
J. Nucl. Mater., 325, 169-173. . . Electron Spin Resonance Measurement of Irradiation Defects in Vitreous Silica Irradiated with Neutrons. . . .Moritani, K. et al. . . . February 2004. . . Kyoto University, Kyoto, Japan.
J. Nucl. Mater., 325, 174-179 . . The Second Order Raman Spectroscopy in Carbon Crystallinity. . . .Lee, Y-J. . . . February 2004. . . National Institute of Advanced Industrial Science and Technology, Ibaraki, Japan.
J. Nucl. Mater., 325, 180-187. . . Diffusion Reaction Between Zircaloy-2 and Thoria.. . .Sengupta, P. et al. . . . February 2004. . . Bhabha Atomic Research Centre, Mumbai, India.
J. Nucl. Mater., 325, 188-194. . . A General Equation of State for Dense Liquid Alkali Metals. . . .Eslami, H. . . . February 2004. . . Persian Gulf University, Boushehr, Iran.
J. Nucl. Mater., 325, 195-201 . . Immobilization of Interstitial Loops by Substitutional Alloy and Transmutation Atoms in Irradiated Metals. . . .Cottrell, G.A. et al. . . . February 2004. . . Culham Science Centre, Oxon, United Kingdom.
J. Nucl. Mater., 325, 202-209 . . Chemical Diffusion in Uranium Dioxide - Influence of Defect Interactions. . . .Ruello, P. et al. . . . February 2004. . . Ecole Centrale Paris, Chatenay Malabry, France; Commissariat a l'Energie Atomique, St.-Paul-lez-Durance, France.
J. Nucl. Mater., 325, 210-216. . . Microwave Process for Sintering of Uranium Dioxide. . . .Yang, J.H. et al. . . . February 2004. . . KAERI, Daejeon-si, South Korea.
J. Nucl. Mater., 325, 217-222 . . Excellent Corrosion Resistance of 18Cr-20Ni-5Si Steel in Liquid Pb-Bi. . . .Kurata, Y. et al. . . . February 2004. . . JAERI, Ibaraki-ken, Japan.
Nucl. Eng. Design, 227, 133-142. . . Probability Assessment of Graphite Brick in the HTR-10. . . .Yu, S. et al. . . . January 2004. . . Tsinghua University, Beijing, China.
Nucl. Eng. Design, 227, 143-153. . . Biaxial Behavior of Plain Concrete of Nuclear Containment Building. . . .Lee, S-K. et al. . . . January 2004. . . B&T Engineering Co. Ltd., Anyang, South Korea; Korea Electric Power Research Institute, Daejeon, South Korea; Chungbuk National University, Chongju, South Korea.
Nucl. Eng. Design, 227, 155-160 . . Effect of Shot Peening on Promary Water Stress Corrosion Cracking of Alloy 600 Steam Generator Tubes in an Operating PWR Plant. . . .Hur, D.H. et al. . . . January 2004. . . KAERI, Daejeon, South Korea; Korea Institute of Nuclear Safety, Daejeon, South Korea; Hanyang University, Seoul, South Korea.
Nucl. Eng. Design, 227, 161-174. . . Formulation of a New Integranular Creep Damage Model for Austenitic Stainless Steels. . . .Michel, B. . . . January 2004. . . CEA Cadarache, St.-Paul-lez-Durance, France.
Nucl. Eng. Design, 227, 175-183. . . Lead Extrusion Dampers for Reducing Seismic Response of Coolant Channel Assembly. . . .Parulekar, Y.M. et al. . . . January 2004. . . Bhabha Atomic Research Centre, Mumbai, India.
Nucl. Eng. Design, 227, 185-193 . . Earthquake Response of Inelastic Structures. . . .Parulekar, Y.M. et al. . . . January 2004. . . Bhabha Atomic Research Centre, Mumbai, India.
Nucl. Eng. Design, 227, 195-207 . . Performance Validation on the Prototype of Control Rod Driving Mechanism for the TRR-II Project. . . .Chyou, Y-P. et al. . . . January 2004. . . Institute of Nuclear Energy Research, Tao-Yuan, Taiwan.
Nucl. Eng. Design, 227, 209-217. . . Lifetime Evaluation of Graphite Components for HTGRs. . . .Oku, T. et al. . . . January 2004. . . University of the Air, Ibaraki-ken, Japan; JAERI, Ibaraki-ken, Japan.
Nucl. Eng. Design, 227, 219-238. . . Investigation on Condensation in Presence of a Noncondensable Gas for a Wide Range of Reynolds Number. . . .Maheshwari, N.K. et al. . . . January 2004. . . Bhabha Atomic Research Centre, Mumbai, India; Tokyo Institute of Technology, Tokyo, Japan.
Nucl. Eng. Design, 227, 239-253 . . Spreading Under Variable Viscosity and Time-Dependent Boundary Conditions: Estimate of Viscosity from Spreading Experiments.. . .Foit, J.J. . . . January 2004. . . Institut fur Kern- und Energietechnik, Karlsruhe, Germany.
Nucl. Eng. Design, 227, 257-271. . . Numerical Prediction of Crack Propagation by an Enhanced Element-Free Galerkin Method.. . .Lee, S-H. et al. . . . February 2004. . . Yonsei University, Seoul, South Korea.
Nucl. Eng. Design, 227, 273-280. . . Effect of Temperature on Graphite Oxidation Behavior. . . .Xiaowei, L. et al. . . . February 2004. . . Tsinghua University, Beijing, China; CEA Cadarache, France.
Nucl. Eng. Design, 227, 281-284. . . Oxidation Behaviour of an HTR Fuel Element Matrix Graphite in Oxygen Compared to a Standard Nuclear Graphite. . . .Moormann, R. et al. . . . February 2004. . . Forschungszentrum Julich, Germany.
Nucl. Eng. Design, 227, 285-300. . . Axial Offset Control of PWR Nuclear Reactor Core Using Intelligent Techniques. . . .Boroushaki, M. et al. . . . February 2004. . . Sharif University of Technology, Tehran, Iran; Tehran University, Tehran, Iran.
Nucl. Eng. Design, 227, 301-312. . . Quasi 3-D Measurements of Turbulence Structure in Horizontal Air-Water Bubbly Flow. . . .Yang, J. et al. . . . February 2004. . . Xi'an Jiaotong University, Shaanxi, PR China.
Nucl. Eng. Design, 227, 313-322. . . Finite Element Analysis of Fluid-Structure Interaction in Pipeline Systems. . . .Sreejith, B. et al. . . . February 2004. . . Indian Institute of Technology Madras, Chennai, India; Indira Gandhi Centre for Atomic Research, Kalpakkam, India.
Nucl. Eng. Design, 227, 323-329 . . Interactions of I2 and CH3I with Reactive Metals Under BWR Severe-Accident Conditions.. . .Glanneskog, H. . . . February 2004. . . Chalmers University of Technology, Goteborg, Sweden.
Nucl. Eng. Design, 227, 331-347. . Inverse Method for Temperature and Stress Monitoring in Complex-Shaped Bodies. . . .Duda, P. et al. . . . February 2004. . . University of Stuttgart, Germany; Cracow University of Technology, Cracow, Poland.
Nucl. Eng. Design, 227, 349-354 . . Reliability of Systems Subject to Common-Cause Hazards. . . .Salem, A.M. et al. . . . February 2004. . . College of Education for Girls, AL-Qassim, Saudi Arabia; Tata University, Tanta, Egypt.
Nucl. Eng. Design, 228, 3-13. . . Short-Term Rupture Studies of Zircaloy-4 and Nb-Modified Zircaloy-4 Tubing Using Closed-End Internal Pressurization. . . .Zhou, Y. et al. . . . March 2004. . . North Carolina State University, Raleigh, NC.
Nucl. Eng. Design, 228, 15-20. . . Dynamic Response Analysis for Fuel Assemblies Under Earthquake and LOCA Accidents. . . .Xie Yongcheng et al. . . . March 2004. . . Shanghai Nuclear Engineering R&D Institute, Shanghai, China.
Nucl. Eng. Design, 228, 21-34. . . Characterization of Neutron Field in the Experimental Fast Reactor JOYO for Fuel and Structural Material Irradiation Test. . . .Aoyama, T. et al. . . . March 2004. . . Japan Nuclear Cycle Development Institute, Ibaraki-ken, Japan.
Nucl. Eng. Design, 228, 35-46. . . Comparative Effects of Structural and Material Parameters Variablity on Pellet-Cladding Interaction in a PWR Fuel Rod. . . .Retel, V. et al. . . . March 2004. . . Universite de Franche-Comte, Besacon, France; EDF, Moret-sur-Loing, France.
Nucl. Eng. Design, 228, 47-54. . . Effects of Irradiation and Deisgn Basis Accident Conditions on Thermal Properties of Epoxy Coating System for Nuclear Power Plant. . . .Park, S-J. et al. . . . March 2004. . . Korea Research Institute of Chemical Technology, Taejon, South Korea.
Nucl. Eng. Design, 228, 55-72. . . Methods for Assessing NPP Containment Pressure Boundary Integrity. . . .Naus, D.J. et al. . . . March 2004. . . Oak Ridge National Laboratory, Oak Ridge, TN; Georgia Institute of Technology, Atlanta, GA; U.S. NRC, Washington, DC.
Nucl. Eng. Design, 228, 73-79. . . Regulatory Strategy for Effective Application of Periodic Safety Review System. . . .Shin, T-M. et al. . . . March 2004. . . Chungju National University, Chungju, South Korea; Korea Institute of Nuclear Safety, Teajon, South Korea.
Nucl. Eng. Design, 228, 81-96. . . Nondestructive Monitoring of Structural Materials Using Automated Ball Indentation (ABI) Technique. . . .Murty, K.L. et al. . . . March 2004. . . North Carolina State University, Raleigh, NC; Indira Gandhi Center for Atomic Research, Kalpakkam, India.
Nucl. Eng. Design, 228, 97-106. . . The Development of Validation Methodology of Multi-Axial Creep Damage Constitutive Equations and Its Application to 0.5Cr0.5Mo0.25V Ferritic Steel at 590 Degrees C.. . .Xu, Q. . . . March 2004. . . The University of Huddersfield, United Kingdom.
Nucl. Eng. Design, 228, 107-117. . . Effect of Axial Restraint on Mechanical Behavior and Average Crack Spacing of Reinforced Concrete Flexural Members. . . .Yi, S-T. et al. . . . March 2004. . . Chung Cheong University, Chungbuk-do, South Korea; Kangnung National University, Kangwon-do, South Korea.
Nucl. Eng. Design, 228, 119-127. . . Strength and Fracture Toughness of Heavy Concrete with Various Iron Aggregate Inclusions. . . .Kan, Y-C. et al. . . . March 2004. . . Chaoyang University of Technology, Taichung County, Taiwan; Institute of Energy Research, Taipei, Taiwan.
Nucl. Eng. Design, 228, 129-142. . . CEA and JNC Approaches for Creep-Fatigue Evaluation of Weldments and Intercomparison Through Benchmark Analyses. . . .Kasahara, N. et al. . . . March 2004. . . Japan Nuclear Cycle Development Institute, Ibaraki-ken, Japan; CEA-Saclay, Gif-sur-Yvette, France.
Nucl. Eng. Design, 228, 143-150. . . Fracture Assessment of a Brittle RPV Under Cold Loading. . . .Sattari-Far, I. et al. . . . March 2004. . . Det Norske Veritas, Stockholm, Sweden.
Nucl. Eng. Design, 228, 151-159. . . Influences of the Dynamic Strain Aging on the J-R Fracture Characteristics of the Ferritic Steels for Reactor Coolant Piping System. . . .Kim, K.C. et al. . . . March 2004. . . Doosan Heavy Industries & Construction Co., Gyeongnam, South Korea.
Nucl. Eng. Design, 228, 161-177. . . Low Cycle Fatigue of Welded Joints: New Experimental Approach. . . .Madi, Y. et al. . . . March 2004. . . Exoles des Mines de Paris, France; Centre d'Etudes de Saclay, Gif-sur-Yvette, France; Lermes-Universite, Aubierre, France.
Nucl. Eng. Design, 228, 179-194. . . Low-Cycle Fatigue of Welded Joints: Coupled Initiation Propagation Model. . . .Madi, Y. et al. . . . March 2004. . . Ecoles des Mines de Paris, France; Lermes-Universite, Aubierre, France; Centre d'Etudes de Saclay, Gif-sur-Yvette, France.
Nucl. Eng. Design, 228, 195-205 . . Safety Evaluation of Rehabilitation of Delaminated Containment Dome. . . .Basu, P.C. et al. . . . March 2004. . . Atomic Energy Regulatory Board, Mumbai, India; University of Mumbai, India.
Nucl. Eng. Design, 228, 207-223. . . Design and Ultimate Behavior of RC Plates and Shells. . . .Min C-S. . . . March 2004. . . Dongguk University, Seoul, South Korea.
Nucl. Eng. Design, 228, 225-244. . . Study on Steel Plate Reinforced Concrete Panels Subjected to Cyclic In-Plane Shear. . . .Ozaki, M. et al. . . . March 2004. . . Kansai Electric Power Co., Osaka, Japan; Japan Atomic Power Co.,Tokyo, Japan; Obayashi Corp., Tokyo, Japan.
Nucl. Eng. Design, 228, 245-259. . . Prediction of Moisture Migration and Pore Pressure Build-Up in Concrete at High Temperatures. . . .Ichikawa, Y. et al. . . . March 2004. . . Kajima Corp., Tokyo, Japan; Imperial College, London, United Kingdom.
Nucl. Eng. Design, 228, 261-272. . . Heat and Mass Transfers in a Concrete Wall with Composite Liner Under Accidental Conditions. . . .Billard, Y. et al. . . . March 2004. . . INSA de Lyon, Villeurbanne, France; EDF/SEPTEN, Villeurbanne, France.
Nucl. Eng. Design, 228, 273-281. . . Sleeve-Type Expansion Anchor Behavior in Cracked and Uncracked Concrete. . . .Kim, S-Y. et al. . . . March 2004. . . Korea Institute of Nuclear Safety, Taejon, South Korea; Korea University, Seoul, South Korea.
Nucl. Eng. Design, 228, 283-304. . . Degradation Assessment of Structures and Passive Components at Nuclear Power Plants. . . .Braverman, J.I. et al. . . . March 2004. . . Brookhaven National Laboratory, Upton, NY; Georgia Institute of Technology, Atlanta, GA; Oak Ridge National Laboratory, Oak Ridge, TN; US NRC, Washington, DC.
Nucl. Eng. Design, 228, 305-317. . . Seismic Analysis of Heavy-Liquid-Metal-Cooled Reactor Vessels. . . .Buongiorno, J. et al. . . . March 2004. . . Idaho National Engineering and Environmental Laboratory, Idaho Falls, ID.
Nucl. Eng. Design, 228, 319-343. . . Investigation Upon the Dynamic Structural Response of a Nuclear Plant on Aseismic Isolating Devices. . . .Micheli, I. et al. . . . March 2004. . . Ansaldo Energia, Genova, Italy; ENEA, Bologna, Italy.
Nucl. Eng. Design, 228, 345-366. . . A NRC-BNL Benchmark Evaluation of Seismic Analysis Methods for Non-Classically Damped Couple Systems. . . .Xu, J. et al. . . . March 2004. . . Brookhaven National Laboratory, Upton, NY; US NRC, Washington, DC.
Nucl. Eng. Design, 228, 367-376. . . Seismic Tests of a Pile-Supported Structure in Liquefiable Sand Using Large-Scale Blast Excitation. . . .Kamijo, N. et al. . . . March 2004. . . Tokyo Electric Power Co., Yokohama, Japan; Kobori Research Complex Inc., Tokyo, Japan; University of Southern California, Los Angeles, CA.
Nucl. Eng. Design, 228, 377-392. . . Seismic Qualification of Expansion Anchors to Canadian Nuclear Standards. . . .Ghobarah, A. et al. . . . March 2004. . . McMaster University, Ontario, Canada; Atomic Energy of Canada L td., Ontario, Canada.
Nucl. Eng. Design, 228, 393-400. . . Safety Analysis of Ulchin Nuclear Power Plant Against Nihonkai-Chubu Earthquake Tsunami.. . .Cho, Y-S., et al. . . . March 2004. . . Hanyang University, Seoul, South Korea; Korea Institute of Nuclear Safety, Daejon, South Korea; National Institute for Disaster Prevention, Seoul, South Korea.
Nucl. Eng. Design, 228, 401-414 . . Simulation of Scaled Vessel Failure Experiments and Investigation of a Possible Vessel Support Against Failure. . . .Willschutz, H.-G. . . . March 2004. . . Institute of Safety Research, Dresden, Germany.
Nucl. Eng. Design, 229, 1-14. . . Analysis of Mechanical Load on Cladding Induced by Fuel Swelling During Power Ramp in High Burn-Up Rod by Fuel Performance Code FEMAXI-6. . . .Suzuki, M. et al. . . . April 2004. . . JAERI, Ibaraki, Japan.
Nucl. Eng. Design, 229, 15-23. . . Application of CANDLE Burnup to Block-Type High Temperature Gas Cooled Reactor. . . .Ohoka, Y. et al. . . . April 2004. . . Tokyo Institute of Technology, Tokyo, Japan.
Nucl. Eng. Design, 229, 25-46. . . Analysis of Natural Circulation Phenomena in VVER-1000. . . .Mousavian, S.K. et al. . . . April 2004. . . Sharif University of Technology, Tehran, Iran; Universita di Pisa, Pisa, Italy.
Nucl. Eng. Design, 229, 47-58. . . An Experimental Investigation on the Critical Heat Flux Enhancement by Mechanical Vibration in Vertical Round Tube. . . .Lee, Y.H. et al. . . . April 2004. . . Korea Advanced Institute of Science and Technology, Daejeon, South Korea.
Nucl. Eng. Design, 229, 59-73. . . The Case of An Oscillating Manometer with Variable Density and Dissipation: Experimental and Numerical Study. . . .Suresan, H. et al. . . . April 2004. . . Indian Institute of Technology, Chennai, India.
Nucl. Eng. Design, 229, 75-80. . . Experimental Thermohydraulic Stability Map of a Freon-12 Boiling Water Reactor Facility with High Exit Friction. . . .de Kruijf, W.J.M. et al. . . . April 2004. . . Delft University of Technology, Delft, The Netherlands.
Nucl. Eng. Design, 229, 81-89. . . A Genetic Algorithm Solution for a Nuclear Power Plant Risk-Cost Maintenance Model. . . .Jiejuan, T. et al. . . . April 2004. . . Tsinghua University, Beijing, PR China.
Nucl. Eng. Design, 229, 91-100. . . Establishment of an Optimal Decontamination Process by the Newly Designed Semi-Pilot Equipment. . . .Kim, K. et al. . . . April 2004. . . KEPRI, Daejon, South Korea; Ebara Industrial Cleaning Co. Ltd., Kawasaki, Japan.
Nucl. Eng. Design, 229, 101-111 . . A Study on a Magnetic Separation of Radioactive Corrosion Products from NPP Using Permanent Magnets. . . .Song, M.C. et al. . . . April 2004. . . Korea Advanced Institute of Science and Technology, Daejeon, Sou th Korea.
Nucl. Sci. Eng. 146, 1-12. . . Experimental Determination of the Ratio of 238U Capture to 235U Fission in LEU-HTR Pebble-Bed Configurations. . . .Koberl, O. et al. . . . January 2004. . . CEA/Cadarache, St.-Paul-lez-Durance, France; Paul Scherrer Institute, Villigen, Switzerland; Institute of Technology, Lausanne, Switzerland.
Nucl. Sci. Eng. 146, 13-50. . Impact of Nuclear Data Uncertainties on Transmutation of Actinides in Accelerator-Driven Assemblies. . . .Aliberti, G. et al. . . . January 2004. . . Argonne National Laboratory, Argonne, IL.
Nucl. Sci. Eng. 146, 51-70. . . Using the Schwinger Variational Functional for the Solution of Inverse Transport Problems. . . .Favorite, J.A. . . . January 2004. . . Los Alamos National Laboratory, Los Alamos, NM.
Nucl. Sci. Eng. 146, 71-87. . . Calculating Nuclear Power Plant Vulnerability Using Integrated Geometry and Event/Fault-Tree Models. . . .Peplow, D.E. et al. . . . January 2004. . . Oak Ridge National Laboratory, Oak Ridge, TN; Defense Threat Reduction Agency, Alexandria, VA.
Nucl. Sci. Eng. 146, 88-98 . . An Order Coding Genetic Algorithm to Optimize Fuel Reloads in a Nuclear Boiling Water Reactor. . . .Ortiz, J.J. et al. . . . January 2004. . . Instituto Nacional de Investigaciones Nucleares, Edo, Mexico; University of Granada, Spain.
Nucl. Sci. Eng. 146, 99-105. . . Slowing-Down Dynamics of Fast Particles in Plasmas via the Fokker-Planck Equation. . . .Anderson, D. et al. . . . January 2004. . . Chalmers University of Technology, Goteborg, Sweden.
Nucl. Sci. Eng. 146, 106-119. . . Calculation and Analysis of n + 112,114-120,122,124,natSn Reactions. . . .Han, Y. . . . January 2004. . . China Institute of Atomic Energy, Beijing, China.
Nucl. Technol., 145, 1-10. . . Monte Carlo Modeling of the Texas A&M University Research Reactor. . . .Kim, C-H. et al. . . . January 2004. . . Hanyang University, Seoul, Korea; Texas A&M University, College Station, TX.
Nucl. Technol., 145, 11-17. . . A Simple and Efficient Control Rod Cusping Model for Three-Dimensional Pin-by-Pin Core Calculations. . . .Yamamoto, A. . . . January 2004. . . Nuclear Fuel Industries, Osaka, Japan.
Nucl. Technol., 145, 18-27. . . Steam Line Break and Station Blackout Transients for Proliferation-Resistant Hexagonal Tight Lattice Boiling Water Reactor. . . .Rohatgi, U.S. et al. . . . January 2004. . . Brookhaven National Laboratory, Upton, NY; Purdue University, West Lafayette, IN.
Nucl. Technol., 145, 28-43 . . Integral Thermal-Hydraulics Tests for the Safety Evaluation of VVER-440/213 Nuclear Reactors and Safety Code Validation. . . .Szabados, L. . . . January 2004. . . KFKI Atomic Energy Research Institute, Budapest, Hungary.
Nucl. Technol., 145, 44-56. . . Feasibility of Increasing the Advanced Test Reactor's Maximum Lobe Power By Adding An Accumulator Injection System. . . .Polkinghorne, S.T. et al. . . . January 2004. . . Idaho National Engineering and Environmental Laboratory, Idaho Falls, ID.
Nucl. Technol., 145, 57-66. . . Thermal Behavior of the Reactor Vessel Penetration Under External Vessel Cooling During a Severe Accident. . . .Kang, K-H. et al. . . . January 2004. . . KAERI, Daejeon, Korea.
Nucl. Technol., 145, 67-81. . . Uranium Transport in a High-Throughput Electrorefiner for EBR-II Blanket Fuel. . . .Ahluwalia, R.K. et al. . . . January 2004. . . Argonne National Laboratory, Argonne, IL.
Nucl. Technol., 145, 82-101. . . Application of Polymers for the Long-Term Storage and Disposal of Low- and Intermediate-Level Radioactive Waste. . . .Bonin, H.W. et al. . . . January 2004. . . Royal Military College of Canada, Ontario, Canada.
Nucl. Technol., 145, 102-114 . . Experimental and Analytical Studies on the Penetration Integrity of the Reactor Vessel Under Extermal Vessel Cooling. . . .Park, R-J. et al. . . . January 2004. . . KAERI, Daejeon, Korea.
Nucl. Technol., 145, 115-137. . . Transient Fuel Behavior and Failure Condition in the CABRI-2 Experiments. . . .Sato, I. et al. . . . January 2004. . . Japan Nuclear Cycle Development Institute, Ibaraki-ken, Japan; Centre d'Etude de Cadarache, St.-Paul-lez-Durance, France; Institut fur Reaktorsicherheit, Karlsruhe, Germany.
Nucl. Sci. Eng. 146, 121-140. . . Variational Variance Reduction for Monte Carlo Eigenvalue and Eigenfunction Problems. . . .Densmore, J.D. et al. . . . February 2004. . . Los Alamos National Laboratory, Los Alamos, NM; University of Michigan, Ann Arbor, MI.
Nucl. Sci. Eng. 146, 141-151 . . An Integral Form of the Variational Nodal Method.. . .Smith, M.A. et al. . . . February 2004. . . Argonne National Laboratory, Argonne, IL; Northwestern University, Evanston, IL; University of Missouri, Rolla, MO.
Nucl. Sci. Eng. 146, 152-175. . . Conditions for a Minimum Critical Mass in a Nuclear Reactor and Considerations on Goertzel's Theorem in Transport Theory. . . .Williams, M.M.R. . . . February 2004. . . Imperial College of Science, London, United Kingdom.
Nucl. Sci. Eng. 146, 176-187. . . A Hybrid Nodal Diffusion/SP3 Method Using One-Node Coarse-Mesh Finite Difference Formulation. . . .Lee, C-H. et al. . . . February 2004. . . Purdue University, West Lafayette, IN.
Nucl. Sci. Eng. 146, 188-199. . . Benchmarking MCNP and WIMS/RFSP Against Measurement Data - I: Deuterium Critical Assembly. . . .Choi, H. et al. . . . February 2004. . . Korea Atomic Energy Research Institute, Taejon, Korea.
Nucl. Sci. Eng. 146, 200-208. . . Measurement of Differential Thick-Target Neutron Yields of C, Al, Ta, W(p,xn) Reactions for 50-MeV Protons. . . .Aoki, T. et al. . . . February 2004. . . Tohoku University, Sendai, Japan.
Nucl. Sci. Eng. 146, 209-220. . . Neutron Capture Cross-Section Measurement of 99Tc by Linac Time-of-Flight Method and the Resonance Analysis. . . .Kobayashi, K. et al. . . . February 2004. . . Kyoto University, Osaka, Japan; Kyushu University, Fukuoka, Japan.
Nucl. Sci. Eng. 146, 221-236. . . Calculation of the Complete Sets of Nuclear Data for n+92,94,96Mo Below 20 MeV. . . .Cai, C. . . . February 2004. . . Nankai University, Tianjin, China.
Nucl. Sci. Eng. 146, 237-244. . . Investigation of the Outgoing Tritons Angular Distribution in the 9Be(nt1y)7Li Reaction at 14.9 MeV by the Line Shape Analysis of the 0.4776-MeV Gamma Transition.. . .Zhou, H. et al. . . . February 2004. . . Beijing Normal University, Beijing, China; A. F. Ioffe Physical-Technical Institute, St. Petersburg, Russia.
Nucl. Sci. Eng. 146, 245-247. . . Accurate Relations Between the Neutron Current Densities and the Neutron Fluxes. . . .Ronen, Y. . . . February 2004. . . Ben-Gurion University of the Negev, Beer-Sheva, Israel.
Nucl. Sci. Eng. 146, 248-255. . . BOT3P - Bologna Transport Analysis Pre-Post-Processors Version 3.0. . . .Orsi, R. . . . February 2004. . . ENEA-FIS-NUC, Bologna, Italy.