Printable PDF file of this newsletter available at: http://www-rsicc.ornl.gov/NEWSLETTER.html.
Radiation Measurement Applications (IRRMA-V)
Congratulations to Dr. Yousry Azmy, ORNL, for being elected to
Fellow Membership of the American Nuclear Society. The ANS is recognizing
Dr. Azmy's contributions to the advancement of nuclear science and technology
through the years. Dr. Azmy is a member of the Radiation Protection and
Shielding Division and Mathematics and Computation Division. He will be
honored at the Awards Luncheon June 11, in Hollywood, Florida.
RSICC will be offering a few data, processing, and computational tools
free of handling, testing, and other fees associated with package transmittal.
A ***NO FEE*** label will appear next to the package name on the web request
page. The ability to provide these packages at no charge is due in part
to advanced funding from the sponsors. To acquire these tools, follow the
normal registration procedure for first-time or updated users. Then complete
the WWW Request Form. The license and export control statements will need
the user signatures, which is standard procedure.
RSICC wishes to pole the user community on the needs for ACES (Atomic Computational Experts Services) for users needing instant expert consulting via email or phone. Experts are on-hand for immediate help on problem solving and tool use in work supported for the DOE/NNSA/NRC/DOD communities.
If you are interested in this service, please email us with a list of
codes on which you want to receive help. Note the work scope areas to which
you would apply the codes (GenIV, Homeland Defense, Reactor Safety, Consequence
Analysis, Nuclear Criticality Safety, etc.) Please reply by June 30th to
A very significant error in the beryllium metal cross-section data contained
in the 238- and 44-Group ENDF/B-V libraries was recently discovered by
SCALE users at ORNL. Several critical experiments that involved beryllium
metal as the reflector were found to have > 1% difference in calculated
k-eff values between different versions of SCALE (4.3 vs. 4.4a). The Be
metal data in SCALE 4.4 and 4.4a contains a factor of 2 scaling error in
the Be thermal scattering transfer arrays. This error can result in non-conservative
errors in calculated k-eff values of greater than 1%. Users should download
the corrected data from the SCALE
Download page and install according to the directions provided in the
file. This error is NOT present in SCALE 4.3. For more information,
read the discussion on page
395 of the SCALE Notebook.
The Intense Pulsed Neutron Source (IPNS) at Argonne National Laboratory was honored with the American Nuclear Society's Nuclear Historic Landmark Award on May 13 during a ceremony at Argonne's Illinois laboratory. ANS President Dr. Gail H. Marcus presented the award.
The ANS Historic Landmark Award identifies and memorializes sites or facilities where outstanding physical accomplishments instrumental in the development and implementation of, and the peaceful uses of, nuclear technology took place.
IPNS, a pulsed spallation neutron source sponsored by the U.S. Department of Energy, has served the scientific community with effective and efficient slow-neutron scattering capabilities since 1981. It functions as a national user facility, and accepts proposals from the world community of chemists, materials scientists, physicists, biologists and engineers.
The IPNS, which has achieved a remarkable lifetime-average record of reliability of more than 95 percent, was a trailblazer in the new generation of neutron research facilities, and it continues to serve science as the community grows into new installations.
The ANS Historic Landmark Award has been presented to 56 sites and facilities since 1985, and has recognized nuclear achievements across the globe such as the Experimental Breeder Reactor I in 1985, the High Flux Beam Reactor in 1987 and France's first nuclear reactor, ZOE, in 1994.
Released May 7, 2002, ANS
--- The Nuclear Energy Research Advisory Committee (NERAC) and the Generation IV International Forum (GIF) have prepared the following information for release this past month: "TECHNOLOGY GOALS FOR GENERATION IV NUCLEAR ENERGY SYSTEMS." Approved by Generation IV Roadmap NERAC Subcommittee (GRNS) on April 13, 2001. For Presentation to NERAC on May 1, 2001 http://gen-iv.ne.doe.gov/pdf/finalgenivgoals_may01.pdf.
The Generation IV technology goals derive from a set of guiding principles:
--- Recent news from http://gen-iv.ne.doe.gov/
Generation IV www site of the DOE Office of Nuclear Energy, Science and
Technology, describes in detail the international need for new nuclear
power and the evolution of nuclear power as a 'roadmap'. This roadmap describes
the origination of the term GEN IV reactors, the deployment schedule, and
the GIF, Generation IV International Forum formation.
Over the next 18 years, generating capacity of electricity is expected to increase 40 percent to meet the growing demand for energy. To meet this staggering increase, the near-term deployment of 40 to 50 new nuclear power plants will be required, says the American Nuclear Society.
Not only would the increased deployment of nuclear power plants help satisfy a growing demand for energy in the United States, it would benefit the environment and protect the atmosphere from emissions that many scientists believe is promoting global warming.
Nuclear energy accounts for about 70 percent of all the emission-free electric generation in the United States, says a position statement adopted by the ANS board of directors. Failure to build new nuclear power plants would mean a significant increase in the emission of greenhouse gases and harmful particulates; more rapid depletion of finite fossil fuels; decreased diversification of fuels; and growing reliance on foreign suppliers.
Nuclear energy, the second largest source of energy, contributes 20 percent of the United States' electricity production. To satisfy National Energy Policy goals of energy security and protecting against global climate changes produced by greenhouse gas emissions, the share of nuclear energy will have to increase.
"If we are to achieve any degree of control over the ever increasing emissions of greenhouse gases and harmful particulates, we must increase the share of our electricity mix from renewable fuels such as nuclear, hydropower, solar, wind and others," says the ANS position statement.
Released May 1, 2002, ANS
Dr. Ely M. Gelbard died April 18, 2002. His undergraduate work was at the City College of New York and after World War II he earned his Ph.D. in physics from the University of Chicago. During the war, he served in the US Army Air Corps as a radar technician. He was a Senior Scientist at Argonne National Laboratory and a Fellow of the American Nuclear Society.
Ely started his postgraduate career when the use of digital computers to solve the neutron balance equations for fission reactor core design and analysis was just starting to receive wide application. At Bettis during the mid 50's and 60's, he participated in the efforts which put the numerical methods for the solution of the finite difference form of the neutron transport equation on a firm mathematical basis, and he devised several approximation schemes that were suitable for numerical methods and also developed efficient algorithms for their solution. While at Bettis, he earned international stature in the field, authoring important papers in many variants of the solution procedures (spherical harmonics, Sn, synthetic methods, and Monte Carlo), including the book, "Monte Carlo Principles and Neutron Transport Problems," with J. Spanier.
Since 1972, when Dr. Gelbard joined Argonne National Laboratory, fast reactors have been the focus of ANL's reactor program, with its emphasis on more accurate computation of the neutron spectrum. His work in this area produced fundamental advances in the analysis of neutron streaming, collision probabilities, improvements in Monte Carlo methods, and neutron diffusion and transport within the nodal approximation. He also brought improved iterative solution strategies to bear on the equations of single-phase computational thermal-hydraulics analysis of passively safe metal-cooled reactor systems. He was consulted by many at ANL, at other labs, and at universities on a wide variety of technical issues, and invariably provided important insights.
Ely's sustained record of high productivity of the highest quality technical work attracted a series of bright and vigorous visiting scholars and students whose participation magnified his work. He excelled at distilling complex technical issues to their essence, then performing the relevant mathematical analysis and, finally, computationally confirming the analysis. Ely was always careful, honest, and thoroughly scrupulous in his work. He earned the ANS Special Award for Computer Methods for the Solution of Problems in Reactor Technology, the ANS Mathematics and Computations Division Distinguished Service Award, the ANS Reactor Physics Division Eugene Wigner Award, and the University of Chicago Distinguished Performance Award.
In spite of his great stature and many accomplishments, Ely was a mild and modest gentleman who always gave full credit to others' work, and was very approachable and an excellent listener. His technical questions at meetings were insightful, probing, and gentle. He also pursued the understanding of others' points of view in personal and political matters with both intellect and sensitivity. Ely's restaurant adventures at meetings and other venues have provided a rich array of gastronomic experiences and many fond memories to his many friends in our profession.
Thanks to Dr. Roger Blomquist for supplying RSICC with the above information.Alvin Radkowsky, 86, ANS Fellow and member since 1978 passed away February 17, 2002, in Israel. His work led to major advances in nuclear submarine and aircraft carrier technology and in the deployment of commercial nuclear power. He became the original chief scientist for the U.S. Naval Nuclear Propulsion Division and headed the design teams for the Navy's nuclear submarines, aircraft carriers, and other surface ships in 1950. Radkowsky headed the design team that built the Shippingport station, the first full-scale civilian nuclear power plant and invented the seed-blanket type core that was utilized in the plant and which also formed the basis for the light water breeder reactor. In 1992, he formed what is now Washington, DC-based Thorium Power, Inc. He was elected to the National Academy of Engineering in 1991, and received the ANS Alvin M. Weinberg Award in November 2001.
Four U.S. Nuclear Regulatory Commission (NRC) software packages transferred from the Energy Science and Technology Software Center, Oak Ridge, Tennessee, to RSICC were processed this month. Please browse the computer code abstracts available at RSICC's web site for more information on these packages.
Two changes were made to the computer code collection this month. One newly frozen was released and one correction was made.
OP SYS: Windows
Oak Ridge National Laboratory, Oak Ridge, Tennessee, contributed a newly frozen version of this isotope generation and depletion code system which was developed for the Nuclear Regulatory Commission and the Department of Energy to satisfy a need for an easy-to-use standardized method of isotope depletion/decay analysis for spent fuel, fissile material, and radioactive material. It can be used to solve for spent fuel characterization, isotopic inventory, radiation source terms, and decay heat. ORIGEN-ARP is an automated sequence to perform isotopic depletion/decay calculations using the ARP and ORIGEN-S codes of the SCALE system. The sequence includes the ORIGEN-ARP for Windows graphical user interface (GUI) that prepares input for ARP (Automated Rapid Processing) and ORIGEN-S. ARP automatically interpolates cross sections for the ORIGEN-S depletion/decay analysis using enrichment, burnup, and, optionally moderator density, from a set of libraries generated with the SCALE SAS2 depletion sequence. Library sets for four LWR fuel assembly designs (BWR 8x8, PWR 14x14, 15x15, 17x17) are included. The libraries span enrichments from 1.5 to 5 wt% U-235 and burnups of 0 to 60,000 MWD/MTU. Other libraries (e.g., DLC-210/CANDULIB-AECL) are available from RSICC. SCALE users can generate their own libraries for other fuel assembly designs. The interpolated cross sections from ARP are passed to ORIGEN-S to perform the depletion/decay calculations. The ORIGEN-ARP sequence includes the post-processing utility module OPUS to generate ASCII plot data files and the PlotOPUS Windows GUI to plot the data.
ORIGEN-ARP 2.00 (February 2002) differs from the previous release ORIGEN-ARP 1.0 (July 2001) in the following ways:
1. The neutron source and energy spectrum routines were replaced with computational algorithms and data from the SOURCES-4B code (RSICC package CCC-661) to provide more accurate spontaneous fission and (alpha,n) neutron sources, and a delayed neutron source capability was added.
2. The printout of the fixed energy group structure photon tables was removed. Gamma sources and spectra are now printed for calculations using the Master Photon Library only.
This package is intended for users who do not need the entire SCALE package. SCALE users can download the components that are not distributed in SCALE 4.4a (OrigenArp GUI, OPUS, and PlotOPUS) from the ORIGEN-ARP page at the SCALE web site http://www.ornl.gov/origen-arp/origen-arp.html. Note that the CCC-371/ ORIGEN2.1 package is no longer being developed, and all new ORIGEN users are advised to request the ORIGEN-ARP package.
ORIGEN-ARP runs on Pentium personal computers with a minimum of 32 MB
RAM under Windows 95/NT or later. Fortran executables included in the package
were created using the Lahey F90 Fortran compiler version 4.00e in a DOS
window of Windows 2000. Makefiles, source files, and batch files are also
included in the package. The OrigenArp GUI was created using Microsoft
Visual C++, and PlotOPUS was created with Microsoft Visual Basic and GigaSoft
ProEssentials. The self-extracting WinZip files are transmitted on CD.
References: Readme.pdf, sections of NUREG/CR-0200, Rev. 6 and 7 (ORNL/NUREG/CSD-2/R6),
Vols. I, II, and III (March 2000 and April 2002). Fortran 90 and Basic;
PC (Pentium or later), Windows 95/NT or later (C00702/PC586/01).
OP SYS: Unix; Windows
Oak Ridge National Laboratory, Oak Ridge, Tennessee, contributed a corrected version of this code system for multilevel R-matrix fits to neutron and charged-particle cross-section data using Bayes' equations. Minor corrections were made to ensure portability of some of the SAMMY codes. SAMDIS, which is used to calculate statistical properties of resonance parameters, was corrected; under certain circumstances, the code had not been counting the number of resonances properly.
Users should be aware that Version M6-Beta is essentially a pre-release of version M6. In order to make the incident-charged-particle version available as soon as possible, no attempt has been made to complete the update of the documentation (users' manual). Though "old" features of the code, and the new incident-charged-particle capability, have been thoroughly tested prior to this release, implementation is in preliminary stages.
The code runs on IBM RS/6000, DEC Alpha computers under both Open/VMS and OSF1 operating systems, Sun UltraSparc, HP, PC using RedHat Linux operating system, and on the PC running Windows. The included PC executables were created on a Dell Dimension 4100 operating under Windows 2000 with Compaq Visual Fortran Professional Edition 6.5. All Unix and Linux systems require a Fortran compiler to create executables. SAMMY-M6-Beta was tested on the following machines:
IBM RS/6000 Model 270 AIX 4.3.3 with XLF 7.1 and XLC 4.4
SAMMY is transmitted on a CD with both Unix and Windows distribution
files. The Unix tar file contains source codes, scripts, tutorials, and
test cases for Unix and Linux users. The self-extracting compressed Windows
file contains source codes, executables, batch files, and test cases for
Windows PC users. Reference: ORNL/TM-9179/R5 (October 2000). Fortran; DEC
Alpha (Unix and VMS), IBM RS/6000, SUN, HP, PC (P00158/IRISC/08).
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 'Main 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 devised thus far. Feedback from our Newsletter community is very valuable so please direct your comments and/or suggestions to PDC@ORNL.GOV.
This month we present Computation and Data Coefficients for the main category of analytical tool packages at RSICC. Links to the package abstracts are embedded into the WWW version of the RSICC Newsletter. Next month we will focus on DOSE Computation and Factors.
Hamilton Hunter - RSICC Director
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 alphabetically. 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. More details are listed after
The University of New Mexico announces their 2002 schedule for Criticality Safety Courses. Dates are: July 9-11 for the Double Contingency & Criticality Safety Evaluation Workshop, July 15-19 is the Short Course, and July 23-25 is the Manager's Course.
For more detailed information about the 2002 Course offerings for Criticality
Safety and online registration, check out the web page at http://www-chne.unm.edu/crit/information.htm
or contact Cheryl Brozena at the University of New Mexico, Albuquerque
(tel 505-277-2225, fax 505-277-5433, email email@example.com).
The Fifth International Topical Meeting on Industrial Radioisotope and Radiation Measurement Applications (IRRMA-V), June 9-14, 2002, will be in Bologna, Italy.
This Conference, held for the first time in Europe, is the fifth in a series of topical meetings sponsored by the American Nuclear Society for the purpose of bringing together scientists and engineers from around the world who share an interest in radiation and radioisotope measurement applications. Attendees will have opportunities to share ideas having to do not only with industrial uses of radiation and radioisotopes but also with basic research and applications in related fields such as medicine, art and archaeometry, environment, analytical techniques, and new trends in sources and detector development.
More information on the scientific program, the conference site, the city of Bologna, the list of invited speakers, the call for papers, and on-line registration can be found on the conference web site http://www.irrma.unibo.it/.
The first announcement of "The 11th International Conference on Fusion
Reactor Materials (ICFRM-11)," which will be held in Kyoto, Japan Dec.
7-12, 2003, is now available on the ICFRM-11 website at: http://icfrm.iae.kyoto-u.ac.jp.
For further information, contact ICFRM-11 secretariat at firstname.lastname@example.org
or phone +81-774-38-3597, fax +81-774-38-3467.
Preparations for the American Nuclear Society's Advances in Nuclear Fuel Management III Topical Meeting to be held in Hilton Head Island, South Carolina, during the period of October 5-8, 2003, have now begun in earnest. You are invited to serve on the Meeting's Technical Program Committee (TPC). In this capacity your commitment will include:
1. Electronically submit one or more papers, and encourage colleagues
to do the same
Please return the following information (name, affiliation, phone, alternative email if preferable, topics of interest) to Youssef A. Shatilla at email@example.com.
Please remember that the success of this meeting depends on your active support and involvement.
Finally, please bookmark the conference web site: http://rpd.ans.org/nfm.htm
and visit it occasionally for news and updates. Comments and suggestions
are most welcome.
The American Nuclear Society, in cooperation with the U.S. Department of Energy and the Fusion Engineering Division of the Atomic Energy Society of Japan will hold the 15th Topical Meeting on Technology of Fusion Energy. This meeting will be held as an embedded topical of the American Nuclear Society 2002 winter meeting, held November 17-21, 2002, in Washington, DC.
The purpose of this meeting is to bring together specialists in the area of fusion energy to discuss current work and future challenges in the area of fusion technology. In addition to bringing together the varied expertise of this aggressive research area, special sessions are planned to focus on similarities and differences between the inertial and magnetic fusion energy concepts and the interface between materials and design communities. The technical program will include paper and poster presentations as well as invited speakers.
Co-sponsors of this meeting are INEEL, LLNL, NRL, ORNL, and Kyoto University.
For more information, visit
This is the "Second Announcement and Call for Papers" for the IAEA Technical Meeting on Physics and Technology of Inertial Fusion Energy Targets and Chambers, which will be held at the General Atomics main site in San Diego, California, June 17-19, 2002. The Technical Meeting will include invited and contributed papers on all aspects of the following:
1. Target design and physics, including fast ignition,
We would greatly appreciate your efforts in further distributing this
announcement to your colleagues. Detailed meeting information including
Abstract Submittal, Participation Procedures, Hotels, Social Events, etc.
can be found at the meeting website http://web.gat.com/conferences/iaea-tm/
main.html. Contacts: Dan Goodin, Chair, General Atomics (fax 858-455-3181,
e-mail firstname.lastname@example.org), Art
Nobile, Co-Chair, Los Alamos National Laboratory (e-mail email@example.com).
To mark the beginning of the second century of nuclear science, the American Nuclear Society's Mathematics and Computation Division 2003 Topical Meeting is organized around the theme: Nuclear Mathematical and Computational Sciences: A Century in Review, A Century Anew. The conference will be held at the Park Vista Hotel, Gatlinburg, Tennessee, April 6-10, 2003. It is co-sponsored by the American Nuclear Society's Reactor Physics, and Radiation Protection and Shielding Divisions, as well as the ANS Oak Ridge/Knoxville Local Section, Oak Ridge National Laboratory's Radiation Safety Information Computational Center, the Nuclear Energy Agency of the OECD, Korean Nuclear Society, and the Canadian Nuclear Society.
As the Conference's title suggests, the technical sessions are arranged in two major components. The Anew component includes the typical mix of contributed papers in regular sessions and invited papers in special sessions. Members of the Technical Program Committee have been extended an invitation to help organize special sessions on timely topics and to stimulate paper submission by colleagues. As is customary for M&C topical meetings, full papers must be submitted for review by October 21, 2002. Additional instructions to authors, including format requirements, will be posted on the Conference's web site (see below) at a later date.
The Review component of the conference is a marked departure from the standard Plenary Session format. It is comprised of eight invited lectures by world-renowned leaders in selected topics. Each half-day of conference sessions will commence with one such lecture extending for one hour, followed by a 15-minute Question/Answer session, a 15-minute break, then the regular and special sessions proceed.
The complete list of topics and invited lecturers is:
The topics were selected to provide broad coverage of the major areas of research in nuclear mathematical and computational sciences in the twentieth century. The lectures will capture for future students and researchers a snapshot of what the field looked like at the turn of the century and how it got to that point since its inception. The stature of the invited lecturers promises to make this lecture series a unique opportunity for nuclear scientists and engineers to "hear it from the lion's mouth"!
The conference's web site is: http://meetingsandconferences.com/MC2003/.
It will be updated with new information as it becomes available. Please
bookmark and visit it occasionally for news and updates. Comments and suggestions
are most welcome. Contact: Yousry Azmy 865-574-8069, firstname.lastname@example.org
or Bernadette Kirk 865-574-6176,
announcement on SCALE 5 workshop, that will be held immediately before
the M&C Conference.)
The Fourth Meeting of the International MACCS Users Group (IMUG) will be held on September 6, 2002, in the Principality of Monaco. The focus of the Fourth IMUG Meeting will be the exchange of technical information relating to the application of MACCS, MACCS2, and COSYMA codes to relevant problems involving atmospheric dispersion of radioactive materials and resulting consequences.
There is no fee to participate in the meeting; however, for planning purposes, advance registration is requested. Everyone, including COSYMA users, is invited to present a paper. Please visit the website www.bnl.gov/est/IMUG2002/default.htm, and http://www.bnl.gov/est/IMUG2002/Latest_News.htm to find out about IMUG, register for the meeting or request notification of web updates. The website will be updated as additional information becomes available.
***Please make your hotel arrangements as soon
as possible. There is a block of rooms being held at the Columbus
Monaco Hotel for this meeting, but there is another large conference being
held in Monaco the same week. The hotel registration form can be
found by going to: http://www.bnl.gov/est/IMUG2002/HotelRegistrationForm.PDF.
The MCNP code developers will present several classes in 2002 in the
United States and two classes in Europe. The dates for these classes are:
The introductory class is for people who have little or no experience with MCNP. The intermediate to advanced class will be held for people who have used MCNP and want to extend their knowledge and gain depth of understanding.
The classes will be based on MCNP5. The code and data package will be available through RSICC at a reduced rate to class participants. The new capabilities of version 5 will be covered.
The other capabilities on MCNP will also be covered, including: basic geometry 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 learning. 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 (MCNP 4C2) geometry models, including lattices, universes, fills, and other geometrical transformations. The Visual Editor can:
Display MCNP 4C2 geometries in multiple plot windows
Two five-day classes will be held in 2002: June 17-21, and September 9-13, both in Richland, Washington. These classes 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.
Class will include computer demonstrations and exercises that will focus on creating and interrogating input files with the Visual Editor. Advanced visualization work using MCNP will also be demonstrated. The class will be taught on Pentium computers running the Linux operating system and Windows NT. Class attendees can use either the Linux or Windows version of the visual editor. Attendees are encouraged to bring their own input files for viewing and modifying in the visual editor. Further information on these classes can be located at: http://www.mcnpvised.com/train.html, or by contacting Randy Schwarz (email email@example.com).
Three classes are scheduled for 2003: March 17-21, June 23-27,
and September 8-12, all in Richland, Washington.
Lead Teachers: Drs. John Hendricks, Gregg McKinney, Laurie Waters
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 directly by experienced MCNPX code developers and
instructors. For more information on code versions and their capabilities,
go to the MCNPX Workshops web site http://mcnpxworkshops.com.
RSICC is co-sponsoring an intermediate level workshop on "Computing Radiation Dosimetry" which will be held June 22-23, 2002, and "Training Course on MCNP-X" to be held June 24-28, 2002, in Lisbon, Portugal.
The workshop on "Computing Radiation Dosimetry" with embedded training course on MCNPX - Monte Carlo Code System for Multiparticle & High Energy Applications, will take place at the Instituto Tecnológico e Nuclear (ITN), Sacavém, Lisbon.
During the weekend of June 22-23 a series of tutorial lectures will be held. From June 24 through June 28, a daily tutorial lecture will be delivered by a senior expert on a subject related to the MCNPX module(s) being taught that day.
The workshop and training course will be focusing on computational issues and state-of-the-art techniques in dosimetry, radiation protection, radiation shielding, biophysics, medical physics, etc.
The training course and workshop are organized by I.T.N. (Nuclear and Technological Institute, in Lisbon). At the international level formal sponsorship has been granted from:
- The Nuclear Science Committee of the Nuclear Energy Agency (NEA) of
the Organization for Economic Co-operation and Development (OECD)
For more information, please visit the web site: http://itn1.itn.pt/MCNPX/.
The Department of Nuclear Engineering at the University of Tennessee-Knoxville
is offering two short courses for radiation transport and criticality safety
specialists during Tennessee Industries Week (TIW-37), August 12-16, 2002.
Fee: 1200 Euro (course at PTB) and US$1100 (course at Los Alamos), which includes a CD with a complete set of notes and unfolding software, as well as refreshments and a dinner for the participants.
A training course on neutron spectra unfolding is being organized by the Neutron Dosimetry section of the Physikalisch-Technische Bundesanstalt (PTB), Braunschweig, Germany, in collaboration with the Health Physics Measurements Group (ESH-4) of the Los Alamos National Laboratory (LANL). Additional support is provided by the Helmholtz-Fonds e.V. The course will be given in August 2002 at PTB in Braunschweig, Germany, and in September 2002 in Los Alamos, New Mexico, USA.
We will emphasize practical aspects of unfolding. The course is intended for those who do spectrometry in neutron or mixed neutron/photon fields and who need to analyze their data using unfolding procedures. In the morning sessions we will have a series of lectures which will provide an introduction to unfolding as well as allow for discussions concerning the theory of unfolding. In the afternoon sessions the participants will work on specific examples at PC workplaces using unfolding software provided by PTB (the HEPRO package of unfolding codes and the MAXED code). We will focus on Bonner-sphere measurements for our discussion of few-channel unfolding, and liquid scintillation spectrometer (NE-213) measurements for our discussion of multi-channel unfolding.
The number of participants is restricted by the limited number of PC
workplaces at our disposal at each of the training centers. We therefore
encourage you to register as soon as possible. For online registration
and further information please visit our web site at: http://www.ptb.de/utc2002/.
The 48th Annual Radiobioassay and Radiochemical Measurements Conference will be held November 11-15, 2002, at the Marriott (formerly the Hyatt Regency) in Knoxville, Tennessee. This conference is a continuation of an informal conference that has a long history. Over the past 47 years, the conference has also been known as:
Annual Bioassay and Analytical Chemistry Conference,
The objectives of the Conference (as adapted from the proceedings of the First Annual Bioassay and Analytical Chemistry Conference) are as follows:
1. To bring everyone up-to-date on some of the latest developments in
the field of bioassay, analytical, and environmental radiochemistry;
For more information, please visit the web site at: http://www.bioassay.org/2002/.
This online course is designed to teach current techniques for calculating the radiation dose from radionuclides administered in nuclear medicine. Lectures include Internal Dose Assessment Techniques, Resources for Internal Dose Assessment in Nuclear Medicine, Kinetic Modeling, Standard Kinetic Models and Phantoms, Extrapolation of Animal Data, Bone Marrow Dosimetry, Study Design for Radiopharmaceutical Dose Assessment, Patient Specific Dosimetry, and Small Scale and Microdosimetry. Problem-solving exercises and a comprehensive online exam are included. Users completing the exam will receive a certificate of completion. Users may also interact with instructors by email about any aspect of the course. The cost of this course is $495; access to the course is through www.internaldosimetry.com.
For questions or comments contact either of the course instructors,
Dr. Michael G. Stabin, (tel 615- 322-3190, fax 615-322-3764, email firstname.lastname@example.org)
or Dr. Richard B. Sparks (tel 865- 938-4949, fax 865-947-1550, email email@example.com,
url http://www.creative development.com,
The SCALE staff at Oak Ridge National Laboratory (ORNL) will be offering
two training courses this fall (October 14-18 and October 21-25)
at ORNL. The courses will emphasize hands-on experience solving practical
problems on PCs. There will be workgroups of two persons each. No prior
experience in the use of SCALE is required to attend. The registration
fee is $1800 for one course or $3000 for both courses ($300 discount if
you register at least one month before the course). A copy of the SCALE
software and manual on CD may be obtained for an additional fee of $700,
and the KENO3D 3-D visualization tool on CD is available for $800 (single
license). Registrations will be accepted on a first-come basis. Registration
forms submitted directly from the Web are preferred. Registration via fax
or email is also acceptable. The registration fee must be paid by check,
travelers checks, bank transfer, or credit card (VISA or MasterCard only).
The agenda and registration form are on the web page at
Contact: Kay Lichtenwalter (tel 865-574-9213, email firstname.lastname@example.org).
The first workshop on SCALE 5 is being planned in conjunction with the American Nuclear Society M&C 2003 Topical Meeting in Gatlinburg, Tennessee. The workshop will be hosted by Oak Ridge National Laboratory in nearby Oak Ridge, Tennessee. The course is scheduled for the week of March 31 - April 4, 2003, immediately before the M&C 2003 meeting.
The workshop will feature some of the new modules to be released in
SCALE 5, such as the SEN3 3-D sensitivity/uncertainty sequence and the
STARBUCS burnup credit sequence for criticality safety. The workshop will
emphasize hands-on experience solving practical problems on PCs. There
will be workgroups of two persons each. No prior experience in the use
of SCALE is required to attend. The registration fee is $1,800 (there is
a $300 early registration discount). You can register online at www.ornl.gov/scale/register_scale5.html
as part of your M&C 2003 registration. The early registration deadline
is February 28, 2003. (See announcement on M&C 2003 Conference).
ANS Annual Meeting, The Revival of the Nuclear Power Option, June 9-13, 2002, Hollywood, FL (url http://www.ans.org/).
Topical Meeting: Industrial Radiation and Radioisotope Measurement Applications IRRMA-V A Class IV Topical, June 9-14, 2002, Bologna, Italy, co-sponsored by the American Nuclear Society. Contact: Prof. Jorge Fernandez, Chair (e-mail: email@example.com, url www.irrma.unibo.it).
IAEA Technical Meeting on Physics and Technology of Inertial Fusion Energy Targets and Chambers, June 17-19, 2002, San Diego, CA. Contact: Dan Goodin (tel 858-455-2977, email dan.goodin@gat. com, url http://web.gat.com/conferences /iaea-tm/main.html).
14th International Conference on High-Power Particle Beams and 5th International Conference on Dense Z-Pinches, June 23-28, 2002, Albuquerque, NM (email for general inquiries firstname.lastname@example.org; url http://www.sandia.gov/BeamsDZP).
Snowmass Fusion Summer Study, July 8-19, 2002, Snowmass Village, CO (url http://fire.pppl.gov/snowmass02.html).
Spectrum 2002, Exploring Science-Based Solutions and Technologies, 9th Biennial International Conference on Nuclear and Hazardous Waste Management, Aug. 4-8, 2002, Reno, NV. Contact: Dr. Richard Jacobsen (email email@example.com, url www.ans.org/spectrum).
11th International Symposium on Reactor Dosimetry, Aug.
18-23, 2002, Brussels, Belgium. Contact: J. Adams (tel 301-975-6205,
fax 301-926-1604, email firstname.lastname@example.org,
Fourth Meeting of the International MACCS Users Group (IMUG), Sept. 6, 2002, in the Principality of Monaco (url http://www.bnl.gov/est/IMUG2002).
22nd Symposium on Fusion Technology - SOFT, Sept. 8-13, 2002, Helsinki, Finland. Contact: Symposium Secretary Mrs. Merja Asikainen (tel +358 9 456 6854; fax +358 9 456 7002; email: email@example.com; url http://www.vtt.fi/val/soft2002/).
YUNSC 2002 - The 4th International Conference of Yugoslav Nuclear Society, Sept.30-Oct.3, 2002, Belgrade, Yugoslavia. Contact (tel ++381 11 454-796; fax ++381 11 444-74-57; email firstname.lastname@example.org. ac.yu, url www.vin.bg.ac.yu/YUNS).
8th Annual Workshop on Monte Carlo Simulation of Radiotherapy
Treatment Sources using the BEAM Code System, Sept. 30-Oct. 3, 2002,
Ottawa, Canada. Contact: Blake Walters, Ionizing Radiation Standards, National
Research Council of Canada, Ottawa, Canada, K1A 0R6 (tel 613-993-2715,
fax 613-952-9865, e-mail
nrc.ca, url www.irs.inms.nrc.ca/inms/
2002 International Topical Meeting on Probabilistic Safety Assessment (PSA '02), Oct. 6-10, 2002, Detroit, MI. Contact: Rebecca Steinman (phone 734-930-7500, email email@example.com, url http://www-ners.engin.umich.edu/PSAConf/).
PHYSOR 2002, Oct. 7-10, 2002, Seoul, Korea, sponsored by the American Nuclear Society and hosted by the Korean Nuclear Society. Contact: Prof. Nam Zin Cho (tel +82-42-869-3819, fax +82-42-869-5859, email firstname.lastname@example.org, url http://physor2002.kaist.ac.kr).
First Asian and Oceanic Congress for Radiation Protection (AOCRP-1), Oct. 20-24, 2002, Seoul, Korea, sponsored by the Korean Association for Radiation Protection (KARP). Contact: Dr. Myung-Jae Song (tel +82-42-870-0202, fax +82-42-870-0269, email email@example.com, url www.aocrp-1.com).
The 48th Annual Radiobioassay and Radiochemical Measurements Conference, Nov. 11-15, 2002, Knoxville, Tennessee. Contact Tom Rucker (tel 865-481-2993, email firstname.lastname@example.org url http://www.bioassay.org/2002/.)
15th ANS Topical Meeting on the Technology of Fusion Energy, Nov. 17-21, 2002, Washington, DC. (url www.ans.org/).
International Symposium on Standards and Codes of Practice in
Medical Radiation Dosimetry, Nov. 25-28, 2002, IAEA, Vienna. Contact:
Dr. Ken R. Shortt (tel +43 1 2600 21664, fax +43 1 26007 21662, email
ANS Topical Meeting, Nuclear Mathematical and Computational Sciences:
A Century in Review, A Century Anew, Apr. 6-10, 2003, Gatlinburg, TN.
Co-sponsored by the American Nuclear Society's Reactor Physics, and Radiation
Protection and Shielding Divisions, as well as the ANS Oak Ridge/Knoxville
Local Section, Oak Ridge National Laboratory's Radiation Safety Information
Computational Center, the Nuclear Energy Agency of the OECD, the Korean
Nuclear Society, and the Canadian Nuclear Society. Contacts: Yousry Azmy
(tel 865-574-8069, email email@example.com)
or Bernadette Kirk (tel 865-574-6176, email firstname.lastname@example.org,
International Conference on Supercomputing in Nuclear Applications,
SNA 2003, Sept. 22-24, 2003, Paris, France. Organizers: CEA, SFANS,
co-organizer: OECD/NEA. (email SNAemail@example.com,
American Nuclear Society's Advances in Nuclear Fuel Management
III Topical Meeting, Oct. 5-8, 2003, Hilton Head Island, South Carolina.
Contact: Youssef A. Shatilla (email firstname.lastname@example.org,
The 11th International Conference on Fusion Reactor Materials
(ICFRM-11), Dec. 7-12, 2003, Kyoto, Japan. Contact ICFRM-11 secretariat
( tel +81-774-38-3597, fax +81-774-38-3467, email email@example.com,,
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). 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. For literature listed as available from INIS contact INIS Clearinghouse, International Atomic Energy Agency, P.O. Box 100, A-1400 Vienna.
ANL-01/15 . . . Alternative Implementations of the Monte Carlo Power Method. . . . Blomquist, R.N.; Gelbard, E.M. . . . December 2001 . . . Argonne National Laboratory, Argonne, IL.
Ann. Nucl. Energy, 29, 1625-1632 . . . Heat Generation and Corresponding Energy Saving in Shielding Materials Due to Different Geometry Radioactive Sources. . . . Bakos, G.C.; Tsagas, N.F. . . . September 2002 . . . Democritus University of Thrace, Xanthi, Greece.
Ann. Nucl. Energy, 29, 1633-1640 . . . HELIOS: Analysis of MOX Critical Experiments. . . . Kriangchaiporn, N.; Ivanov, K.N.; Stamm'ler, R.J.J. . . . September 2002 . . . Pennsylvania State University, University Park, PA; Studsvik Scandpower AS, Norway.
Ann. Nucl. Energy, 29, 1641-1660 . . . Investigation of the Effects of the Resonance Absorption in a Fusion Breeder Blanket. . . . ahin, S.; ahin, H.M.; Yildiz, K. . . . September 2002 . . . Gazi Üniversitesi, Ankara, Turkey.
Ann. Nucl. Energy, 29, 1661-1687 . . . The Effect of Random Geometry on the Time Constant of a Multiplying System. . . . Williams, M.M.R. . . . September 2002.
Ann. Nucl. Energy, 29, 1689-1706 . . . Inherent Shutdown Capabilities in Accelerator-Driven Systems. . . . Eriksson, M.; Cahalan, J.E. . . . September 2002 . . . Royal Institute of Technology, Stockholm, Sweden; Argonne National Laboratory, Argonne, IL.
Ann. Nucl. Energy, 29, 1707-1720 . . . Evaluation of the Unresolved Resonance Range of 238U. . . . Maslov, V.M.; Porodzinskij, Yu.V.; Baba, M.; Hasegawa, A. . . . September 2002 . . . Radiation Physics and Chemistry Problems Institute, Minsk-Sosny, Belarus; Tohoku University, Sendai, Japan; Tokai Research Establishment, Japan; Atomic Energy Research Institute, Ibaraki-ken, Japan.
Ann. Nucl. Energy, 29, 1721-1733 . . . Assessment of Core Characteristics During Transition from 37-Element Fuel to CANFLEX-NU Fuel in CANDU 6. . . . Jeong, C.J.; Suk, H.C. . . . September 2002 . . . Korea Atomic Energy Research Institute, Taejon, South Korea.
Ann. Nucl. Energy, 29, 1735-1745 . . . A Computer Program with Graphical User Interface to Plot the Multigroup Cross Sections of WIMS-D Library. . . . Thiyagarajan, T.K. et al. . . . September 2002 . . . Bhabha Atomic Research Centre, Mumbai, India.
Ann. Nucl. Energy, 29, 1747-1764 . . . A Multi-Particle Model Applicable to Social Issues - Time-Evolution of Japanese Public Opinion on Nuclear Energy. . . . Ohnishi, T. . . . October 2002 . . . Wakasa Wan Energy Research Center, Tsuruga, Japan.
Ann. Nucl. Energy, 29, 1765-1778 . . . Higher Order Analytical Nodal Methods in Response-Matrix Forumlation for the Multigroup Neutron Diffusion Equations. . . . Guessous, N.; Akhmouch, M. . . . October 2002 . . . Ecole Normale Supérieure de Fès, Fès, Morocco; FST-Fes-Saiss, Fès, Morocco.
Ann. Nucl. Energy, 29, 1779-1794 . . . Characterization and Optimization Analysis of a BNCT Biological Facility. . . . Quinteiro, G.F.; Calabrese, C.R. . . . October 2002 . . . Comisión Nacional de Energía Atomica-CAC, Buenos Aires, Argentina.
Ann. Nucl. Energy, 29, 1795-1807 . . . A Signal Pattern Matching and Verification Method Using Interval Means Cross Correlation and Eigenvalues in the Nuclear Power Plant Monitoring Systems. . . . Chang, Y-W.; Seong, P-H. . . . October 2002 . . . Korea Power Engineering Co., Daejeon, South Korea; Korea Advanced Institute of Science and Technology, South Korea.
Ann. Nucl. Energy, 29, 1809-1826 . . . The Effect of Tube Rupture Location on the Consequences of Multiple Steam Generator Tube Rupture Event. . . . Jeong, J.H.; Kweon, Y.C. . . . October 2002 . . . Cheonan College of Foreign Studies, Choongnam, South Korea; Sunmoon University, Choongnam, South Korea.
Ann. Nucl. Energy, 29, 1827-1836 . . . An On-Line Fuel Management Method Using in-Core Detector Readings for CANDU Reactors. . . . Jeong, C.J. . . . October 2002 . . . Korea Atomic Energy Research Institute, Taejon, South Korea.
Ann. Nucl. Energy, 29, 1837-1853 . . . Numerical Methods for the Generation of the Spectrum of the Multigroup Slab-Geometry Discrete Ordinates Operator in Neutron Transport Theory. . . . Pimenta de Abreu, M. . . . October 2002 . . . Instituto Politecnico, Nova Friburgo, Brazil.
Ann. Nucl. Energy, 29, 1855-1869 . . . An Exponential Spectral Nodal Method for One-Speed X, Y-Geometry Deep Penetration Discrete Ordinates Problems. . . . de Mello, J.A.M.; Barros, R.C. . . . October 2002 . . . COPPE/UFRJ, Rio de Janeiro, Brazil; Instituto Politecnico, Nova Friburgo, Brazil.
Ann. Nucl. Energy, 29, 1871-1889 . . . Neutronic Analysis of PROMETHEUS Reactor Fueled with Various Compounds of Thorium and Uranium. . . . Yapici, H.; Übeyli, M.; Yalçin, S. . . . November 2002 . . . Erciyes Üniversitesi, Kayseri, Turkey; Gazi Üniversitesi, Ankara, Turkey; Bahçeehir Üniversitesi, Istanbul, Turkey.
Ann. Nucl. Energy, 29, 1891-1917 . . . Parallel Channel Instabilities in Boiling Water Reactor Systems: Boundary Conditions for Out of Phase Oscillations. . . . Muñoz-Cobo, J.L.; Podowski, M.Z.; Chiva, S. . . . November 2002 . . . Polytechnic University of Valencia, Spain; Rensselaer Polytechnic Institute, Troy, NY; Jaume I University, Castellon, Spain.
Ann. Nucl. Energy, 29, 1919-1932 . . . Double-Strata High Burnup Fuel Performance in Light Water Reactors. . . . Barchevtsev, V.; Artisyuk, V.; Ninokata, H. . . . November 2002 . . . Tokyo Institute of Technology, Tokyo, Japan.
Ann. Nucl. Energy, 29, 1933-1951 . . . On the Use of the Conjugate Gradient Method for the Solution of the Neutron Transport Equation. . . . Gupta, A.; Modak, R.S. . . . November 2002 . . . Bhabha Atomic Research Centre, Mumbai, India.
Ann. Nucl. Energy, 29, 1953-1965 . . . Design of an Overmoderated Fuel and a Full MOX Core for Plutonium Consumption in Boiling Water Reactors. . . . Francois, J.L.; del Campo, C.M.; Hernandez, J. . . . November 2002 . . . Universidad Nacional Autónoma de Mexico, Jiutepec, Mexico; Instituto Politécnico Nacional, Mexico.
Ann. Nucl. Energy, 29, 1967-1975 . . . Sensitivity Analysis for AHWR Fuel Cluster Parameters Using Different WIMS Libraries. . . . Kumar, A; Kannan, U.; Srivenkatesan, R. . . . November 2002 . . . Bhabha Atomic Researach Centre, Mumbai, India.
Ann. Nucl. Energy, 29, 1977-1988 . . . Calculation of the Cross-Sections for Fast Neutrons and Gamma-Rays in Concrete Shields. . . . El-Sayed Abdo, A. . . . November 2002 . . . Atomic Energy Authority, Cairo, Egypt.
Fus. Eng. Des., 60, 99-103 . . . Exact Solutions of Problems About Optimum Compression of Gas By Cylindrical and Spherical Shock Waves. . . . Farshi, E.; Trubnikov, B.A. . . . May 2002. . . Kyushu University Kasuga, Fukuoka, Japan; Kurchatov Institute, Moscow, Russia.
Fus. Eng. Des., 60, 119-125 . . . A Novel Approach to Linearization of the Electromagnetic Parameters of Tokamaks with an Iron Core. . . . Fu, P.; Liu, Z.Z.; Zou, J.H. . . . May 2002 . . . Chinese Academy of Science, Hefei, China; Xian Jiaotong University, Xian, China.
Fus. Eng. Des., 60, 127-140 . . . A New Optimized Design Concept of the Switching Network Resistors of the Large ITER-FEAT Tokamak. . . . Bareyt, B.; Bulgakov, S. . . . May 2002 . . . ITER EDA, Ibaraki-ken, Japan; Efremov Scientific Research, St. Petersburg, Russia.
Fus. Eng. Des., 60, 141-155 . . . Copper Vapor Laser Application for Surface Monitoring of Divertor and First Wall in ITER. . . . Buzhinskij, O.I. et al. . . . May 2002 . . . Troitsk Institute for Innovation and Fusion Research, Moscow, Russia; Kurchatov Institute, Moscow, Russia; Joint-Stock Company, Altech, Russia.
Fus. Eng. Des., 60, 157-166 . . . Plasma-Lithium Interaction in the CDX-U Spherical Torus. . . . Antar, G.Y. et al. . . . May 2002 . . . University of California San Diego, La Jolla, CA; Princeton Plasma Physics Laboratory, Princeton, NJ; Oak Ridge National Laboratory, Oak Ridge, TN.
Fus. Eng. Des., 60, 167-178 . . . Neutral Transport Baffling Studies for SST-1. . . . Jaishankar, S.; Warrier, M.; Deshpande, S.P.; SST Team. . . . May 2002 . . . Institute for Plasma Research, Gujarat, India.
Fus. Eng. Des., 60, 179-190 . . . Eddy Current Experiments with Closely Placed Solid Boxes Simulating a Next Step Fusion Device. . . . Abe, M. et al. . . . May 2002 . . . Hitachi Ltd., Ibaraki, Japan; JAERI, Ibaraki, Japan.
Fus. Eng. Des., 60, 191-209 . . . Computational Study on Eddy Current Characteristics in a Super Conducting Tokamak. . . . Abe, M. et al. . . . May 2002 . . . Hitachi Ltd., Ibaraki, Japan; JAERI, Ibaraki, Japan.
Fus. Eng. Des., 60, 211-216 . . . Neutral Particle Analyzer with Feedback Control System on HT-7 Tokamak. . . . Sheng Xia Liu, et al. . . . May 2002 . . . Academia Sinica, Anhui, China.
IAEA, 43, 1-60 . . . Quarterly Journal of the International Atomic Energy Agency. . . . . . . December 2001 . . . IAEA, Vienna, Austria.
IAEA-NDS-153 . . . Theoretical Evaluation of Neutron and Proton Induced Fission Cross-Sections for Pb-Pu Targets in Energy Range 20-200 MeV. . . . Yavshits, S. . . . February 2002 . . . V. G. Khlopin Radium Institute, St. Petersburg, Russia.
ICRC 2001 Proceedings . . . The Evolution of Galactic Cosmic Ray Element Spectra from Solar Minimum to Solar Maximum: ACE Measurements. . . . Davis, A.J. et al. . . . 2001 . . . California Institute of Technology, Pasedena, CA; Washington University, St. Louis, MO; NASA/Goddard Space Flight Center, Greenbelt, MD.
J. Nucl. Mater., 302, 73-88 . . . Present Limits and Improvements of Structural Materials for Fusion Reactors - A Review. . . . Tavassoli, A.-A.F. . . . April 2002 . . . DMN/Dir, CEA Saclay, Gif-sur-Yvette, France.
J. Nucl. Mater., 302, 89-95 . . . Positron Annihilation Studies of Neutron Irradiated and Thermally Treated Reactor Pressure Vessel Steels. . . . Slugen, V.; Kögel, G.; Sperr, P.; Triftshäuser, W. . . . April 2002 . . . Slovak University of Technology, Bratislava, Slovak Republic; Universität der Bundeswehr Munchen, Neubiberg, Germany.
J. Nucl. Mater., 302, 96-103 . . . Concentration Dependent Diffusion of Carbon in Tungsten. . . . Schmid, K.; Roth, J. . . . April 2002 . . . Max-Planck-Institut für Plasmaphysik, Garching, Germany.
J. Nucl. Mater., 302, 104-108 . . . Effect of TiO2 Addition on Crack Propagation of Alloy 600 and Its Penetration into Crevices in Caustic Solution. . . . Kim, U.C. et al. . . . April 2002 . . . Korea Atomic Energy Research Institute, Daejon, South Korea.
J. Nucl. Mater., 302, 109-124 . . . On the Nuclear Oxide Fuel Densification, Swelling and Thermal Re-Sintering. . . . Paraschiv, M.C.; Paraschiv, A.; Grecu, V.V. . . . April 2002 . . . Institute for Nuclear Research, Pitesti, Romania; University of Bucharest, Romania.
J. Nucl. Mater., 302, 125-134 . . . An Efficient Model for the Analysis of Fission Gas Release. . . . Bernard, L.C.; Jacoud, J.L.; Vesco, P. . . . April 2002 . . . Framatome, Lyon, France.
J. Nucl. Mater., 302, 135-142 . . . Effects of Oxygen, Hydrogen and Neutron Irradiation on the Mechanical Properties of Several Vanadium Alloys. . . . Chen, J. et al. . . . April 2002 . . . Southwestern Institute of Physics, Chengdu, China; National Key Laboratory of Nuclear Fuel and Materials, Chengdu, China.
J. Nucl. Mater., 302, 143-155 . . . Microstructure Modelling of Ferritic Alloys Under High Flux 1 MeV Electron Irradiations. . . . Hardouin Duparc, A. et al. . . . April 2002 . . . CEA-CNRS-Ecole Polytechnique, Palaiseau, France; CNEA, Buenos Aires, Argentina.
J. Nucl. Mater., 302, 156-164 . . . Application of Neutron Radiography for Estimating Concentration and Distribution of Hydrogen in Zircaloy Cladding Tubes. . . . Yasuda, R. et al. . . . April 2002 . . . JAERI, Ibaraki-ken, Japan.
J. Nucl. Mater., 302, 165-174 . . . Ab Initio Study on the Mechanism of Hydrogen Release from the Silicate Surface in the Presence of Water Molecule. . . . Nakazawa, T. et al. . . . April 2002 . . . JAERI, Ibarak-ken, Japan; OECD Halden Reactor Project, Halden, Norway; Nippon Advanced Technology Co., Ltd., Ibaraki-ken, Japan.
J. Nucl. Mater., 302, 175-184 . . . Study of the / Phase Transformation of Zy-4 in Presence of Applied Stresses at Heating: Analysis of the Inherited Microstructures and Textures. . . . Gey, N. et al. . . . April 2002 . . . Université de Metz, Metz, France; Ecole des Mines, Nancy, France; CEA Saclay, Gif-sur-Yvette, France.
J. Nucl. Mater., 302, 185-192 . . . On Irradiation Embrittlement and Recovery Annealing Mechanisms of Cr-Mo-V Type Pressure Vessel Steels. . . . Ilola, R.; Nadutov, V.; Valo, M. Hänninen, H. . . . April 2002 . . . Helsinki University of Technology, Finland; Kurdyumov Institute of Metal Physics of the Academy of Scences of Ukraine, Kiev, Ukraine; VTT Industrial Systems, VTT, Finland.
J. Nucl. Mater., 302, 193-205 . . . Systematic Study of Formation of Soft and Hard Zones in the Dissimilar Weldments of Cr-Mo Steels. . . . Sudha, C.; Terrance, A.L.E.; Albert, S.K.; Vijayalakshmi, M. . . . April 2002 . . . Indira Gandhi Centre for Atomic Research, Kalpakkam, India.
J. Nucl. Mater., 302, 206-210 . . . Sputtering of Nano-Crystalline Gold by High Energy Heavy Ions. . . . Matsunami, N. et al. . . . April 2002 . . . Nagoya University, Japan; JAERI, Ibaraki-ken, Japan; Ibaraki University, Japan.
J. Nucl. Mater., 302, 211-216 . . . Fatigue Behavior of 20% Cold-Worked 316 Stainless Steel Under in Situ Irradiation with 17 MeV Protons at 60C. . . . Murase, Y.; Nagakawa, J.; Yamamoto, N. . . . April 2002 . . . National Institute for Materials Science, Ibaraki-ken, Japan; Kyushu University, Fukuoka, Japan.
J. Nucl. Mater., 302, 217-219 . . . Thermal Behaviour of Hydrogen in Zircaloy Corrosion Layers. . . . Hermann, A. . . . April 2002 . . . Paul Scherrer Institute, Villigen, Switzerland.
J. Nucl. Mater., 302, 220-223 . . . Void Migration in Fusion Materials. . . . Cottrell, G.A. . . . April 2002 . . . EURATOM/UKAEA, Oxon, United Kingdom.
J. Nucl. Mater., 302, 224-226 . . . The Effect of UV Light Irradiation on the Removal of Tritium from the Codeposited Carbon-Tritium Layer in Fusion Reactors. . . . Venhaus, T.J.; Penzhorn, R.D.; Causey, R.A.; Bekris, N. . . . April 2002 . . . Los Alamos National Laboratories, Los Alamos, NM; Tritium Laboratory, Karlsruhe, Germany; Sandia National Laboratories, Livermore, CA.
J. Nucl. Mater., 302, 227-231 . . . Density Decrease of Oxidatively Sintered UO2-5wt%CeO2 Pellets During Resintering in H2 Atmosphere. . . . Kim, S.H.; Joung, C.Y.; Kim, H.S.; Na, S.H.; Lee, Y.W. . . . April 2002 . . . Korea Atomic Energy Research Institute, Taejon, South Korea.
J. Radiat. Res. Radiat. Process., 19, 81-91 . . . Attenuation and Scattering of Gamma-Ray Through Andesite and Felsite. . . . Mahmoud, H.M.; Armia, E. . . . May 2001 . . . South Valley University, Qena, Egypt.
J. Radiat. Res. Radiat. Process., 19, 127-132 . . . Growth Inhibition of Melanoma In Vivo by Combining Oncostatin M Gene Transfection with Localized Radiation: A Gene-Radiotherapy Strategy for Tumor. . . . Lu Xing et al. . . . May 2001 . . . Academy of Military Medical Sciences, Beijing, China.
J. Radiat. Res. Radiat. Process., 19, 148-152 . . . Oxidation of Guanine and Guanosine by No.2 Radical at Basic pH. . . . ZHANG Zhouen et al. . . . May 2001 . . . Fudan University, Shanghia, China; Chinese Academy of Sciences, Shanghai, China.
J. Radiat. Res. Radiat. Process., 20, 47-54. . . . Expression of MMP1 and TIMP1 in the Healing Process of General and Radiation-Combined Wounds and Its Effects on This Process. . . . GU Qingyang et al. . . . February 2002 . . . Academy of Military Medical Sciences, Beijing, China.
KEK-MSL Report 1999 . . . KEK-MSL Report 1999. . . . Higemoto, W. ed. . . . 1999 . . . KEK, Ibaraki-ken, Japan.
KEK Proceedings 2000-5 . . . Chiral Dynamics in Particle and Nuclear Physics. . . . Hosaka, A., eds. et al. . . . June 2000 . . . High Energy Accelerator Research Organization, Ibaraki-ken, Japan.
KEK Proceedings 2000-9 . . . Proceedings of the Photon Factory Workshop on the Physics of Charge, Spin, and Orbital Ordered Systems. . . . Murakami, Y.; Hirota, K., eds. . . . June 2000 . . . High Energy Accelerator Research Organization, Ibaraki-ken, Japan.
KEK Proceedings 2000-17 . . . Proceedings of the APPI Winter Institute. . . . Fujii, Y. ed. . . . August 2000 . . . High Energy Accelerator Research Organization, Ibaraki-ken, Japan.
KEK Proceedings 2000-19 . . . Workshop on Di-Lepton Experiments at the 50-GeV PS. . . . Chiba, J.; Sawada, S., eds. . . . October 2000 . . . High Energy Accelerator Research Organization, Ibaraki-ken, Japan.
KEK Proceedings 2000-20 . . . Proceedings of the Second International Workshop on EGS. . . . Hirayama, H.; Namito, Y.; Ban, S., eds. . . . December 2000 . . . High Enegy Accelerator Research Organization, Ibaraki-ken, Japan.
KEK Proceedings 2001-19 . . . Proceedings of the KEK Theory Meeting on Physics at Linear Colliders. . . . Hagiwara, K.; Okamura, N., eds. . . . August 2001 . . . High Energy Accelerator Research Organization, Ibaraki-ken, Japan.
KEK Report 2000-7; SLAC R-559 . . . International Study Group Progress Report on Linear Collider Development. . . . none listed . . . April 2000 . . . High Energy Accelerator Research Organization, Ibaraki-ken, Japan.
Nucl. Eng. Des., 214, 1-12 . . . Optimization of Operation and Maintenance of Nuclear Power Plant by Probabilistic Fracture Mechanics. . . . Maeda, N. et al. . . . May 2002 . . . University of Tokyo, Japan.
Nucl. Eng. Des., 214, 13-23 . . . Investigation on the Interaction Effect of Two Parallel Axial Through-Wall Cracks Existing in Steam Generator Tube. . . . Park, Y.W.; Song, M.H.; Lee, J.H.; Moon, S.I.; Kim, Y.J. . . . May 2002 . . . Korea Institute of Nuclear Safety, Taejon, Republic of Korea; Sungkyunkwan University, Suwon, Republic of Korea.
Nucl. Eng. Des., 214, 25-34 . . . Development of Advanced CRDM Without Canopy Seal Welds. . . . Takanabe, K.; Miyake, T.; Nagura, Y. . . . May 2002 . . . Mitsubishi Heavy Industries, Ltd, Kobe & Takasago, Japan.
Nucl. Eng. Des., 214, 35-40 . . . Seismic Analysis and Fracture Evaluation of Stabilized Core Shroud. . . . Huang, C-C. et al. . . . May 2002 . . . Institute of Nuclear Energy Research, Taoyuan, Taiwan; Taiwan Power Co., Taipei, Taiwan.
Nucl. Eng. Des., 214, 41-45 . . . Improvement of the Strain Concentration Factor for Simplified Elastic-Plastic Analysis. . . . Nomoto, S.; Nakamura, T. . . . May 2002 . . . Kansia Electric Power Co., Osaka, Japan.
Nucl. Eng. Des., 214, 47-56 . . . Effect of Specimen Configurations on the Fracture Resistance Curve. . . . Seok, C-S.; Kim, S-Y. . . . May 2002 . . . Sungkyunkwan University, Suwon, South Korea.
Nucl. Eng. Des., 214, 57-71 . . . Aseismic Evaluation for Aging Degradation of Nuclear Power Plant Components. . . . Kobayashi, K. . . . May 2002 . . . Tokyo Electric Power Co., Tokyo, Japan.
Nucl. Eng. Des., 214, 73-81 . . . A Parametric Study on Pressure-Temperature Limit Curve Using 3-D Finite Element Analyses. . . . Lee, T-J.; Choi, J.B.; Kim, Y.J.; Park, Y.W. . . . May 2002 . . . Sungkyunkwan University, Suwon, South Korea; Korea Institute of Nuclear Safety, Taejon, South Korea.
Nucl. Eng. Des., 214, 83-89 . . . The Experiences of Non-Code Repairs for Nuclear Safety-Related Piping in Taiwan. . . . Ting, K.; You, J.S. . . . May 2002 . . . Lunghwa University of Science and Technology, Taoyuan, Taiwan; Atomic Energy Council, Taipei, Taiwan.
Nucl. Eng. Des., 214, 91-101 . . . Simulation of Stress Corrosion Crack Growth in Steam Generator Tubes. . . . Shin, K.I.; Park, J.H.; Kim, H-D.; Chung, H-S. . . . May 2002 . . . Chunghuk National University, Chunghuk, Republic of Korea; Korea Electric Power Research Institute, Daejon, Republic of Korea.
Nucl. Eng. Des., 214, 103-112 . . . Probabilistic Analysis of Core Shroud Cracks. . . . Wu, W-F.; Tsai, C-H.; Tu, K-C.; You, J-S. . . . May 2002 . . . National Taiwan University, Taipei, Taiwan; National Tsin-Hua University, Hsinchu, Taiwan; Institute of Nuclear Energy Research, Lungtan, Taiwan.
Nucl. Eng. Des., 214, 113-126 . . . Research and Development Related to PFM for Aged Nuclear Components. . . . Shibata, K. et al. . . . May 2002 . . . JAERI, Ibaraki-ken, Japan; Fuji Research Institute Corp., Tokyo, Japan; University of Tokyo, Japan.
Nucl. Eng. Des., 214, 127-136 . . . Fracture Strength and Behavior of Carbon Steel Pipes with Local Wall Thinning Subjected to Cyclic Bending Load. . . . Miyazaki, K. et al. . . . May 2002 . . . Mechanical Engineering Research Laboratory, Ibaraki, Japan; Hitachi Ltd., Ibaraki, Japan.
Nucl. Eng. Des., 214, 137-145 . . . The Stress Intensity Factor Study of an Elliptical Cracked Shaft. . . . Shih, Y-S.; Chen, J-J. . . . May 2002 . . . Chung-Yuan Christian University, Chung-Li, Taiwan; Institute of Nuclear Energy Research, Taiwan.
Nucl. Eng. Des., 214, 147-149 . . . Japanese Fitness-for-Service Code for Nuclear Power Plants - Summary of Flaw Evaluation Procedures. . . . Kobayashi, H.; Kashima, K. . . . May 2002 . . . Tokyo Institute of Technology, Tokyo, Japan; Central Research Institute of Electric Power Industry, Tokyo, Japan.
Nucl. Eng. Des., 214, 151-161 . . . Development of an Ultra Sonic Phased Array System for Nondestructive Tests of Nuclear Power Plant Components. . . . Song, S-J.; Shin, H.J.; Jang, Y.H. . . . May 2002 . . . Sungkyunkwan University, Suwon Kyungkee, Republic of Korea.
Nucl. Eng. Des., 214, 163-172 . . . Experience of the Integrity Assessment of the Highly Embrittled Reactor Pressure Vessel for the Life Extension. . . . Hong, S-Y.; Jang, C.; Jeong, I-S. . . . May 2002 . . . Korea Electric Power Research Institute, Daejon, South Korea.
Nucl. Eng. Des., 215, 1-14 . . . Analysis of a Feed and Bleed Procedure Sensitivity Study, Performed with the SIPACT Simulator, on a French 900 MWe NPP. . . . Pochard, R.; Jedrzejewski, F.; Mazauric, X.; Carteron, P.Y. . . . June 2002 . . . CEA, Gif-sur-Yvette, France.
Nucl. Eng. Des., 215, 15-25 . . . Investigation of the Transition from Forced to Natural Convection in the Research Reactor Munich II. . . . Skreba, S.; Sprünken, H. Unger, H. . . . June 2002 . . . Ruhr-University Bochum, Germany.
Nucl. Eng. Des., 215, 27-38 . . . Natural-Convection Studies for Advanced CANDU Reactor Concepts. . . . Dimmick, G.R. et al. . . . June 2002 . . . AECL, Ontario, Canada.
Nucl. Eng. Des., 215, 39-50 . . . Restart of Natural Circulation in a PWR-PKL Test Results and S-RELAP5 Calculations. . . . Umminger, K.; Mandl, R.; Wegner, R. . . . June 2002 . . . Framatome, Erlangen, Germany.
Nucl. Eng. Des., 215, 51-67 . . . Effects of Ship Motions on Natural Circulation of Deep Sea Research Reactor DRX. . . . Ishida, T.; Yoritsune, T. . . . June 2002 . . . JAERI, Ibaraki-ken, Japan.
Nucl. Eng. Des., 215, 69-85 . . . Natural Circulation Characteristics of a Marine Reactor in Rolling Motion and Heat Transfer in the Core. . . . Murata, H.; Sawada, K-I.; Kobayashi, M. . . . June 2002 . . . National Maritime Research Institute, Tokyo, Japan.
Nucl. Eng. Des., 215, 87-98 . . . Analytical Modeling of Flashing-Induced Instabilities in a Natural Circulation Cooled Boiling Water Reactor. . . . Van Bragt, D.D.B. et al. . . . June 2002 . . . Delft University of Technology, JB Delft, The Netherlands.
Nucl. Eng. Des., 215, 99-110 . . . Natural Circulation Flow Behavior at Reduced Inventory in a VVER Geometry. . . . Puustinen, M. . . . June 2002 . . . VTT Energy, Lappeenranta, Finland.
Nucl. Eng. Des., 215, 111-126 . . . Use of a Natural Circulation Map for Assessing PWR Performance. . . . D'Auria, F.; Frogheri, M. . . . June 2002 . . . University of Pisa, Italy; ANSALDO Nucleare, Genova, Italy.
Nucl. Eng. Des., 215, 127-137 . . . Study on the Stability Behaviour of a Natural Circulation Pressure Tube Type Boiling Water Reactor. . . . Nayak, A.K. et al. . . . June 2002 . . . Bhabha Atomic Research Center, Mumbai, India; Tokyo Institute of Technology, Tokyo, Japan.
Nucl. Eng. Des., 215, 139-152 . . . Experimental Observations on the General Trends of the Steady State and Stability Behaviour of Single-Phase Natural Circulation Loops. . . . Vijayan, P.K. . . . June 2002 . . . Bhabha Atomic Research Centre, Mumbai, India.
Nucl. Eng. Des., 215, 153-170 . . . On the Analysis of Thermal-Fluid-Dynamic Instabilities Via Numerical Discretization of Conservation Equations. . . . Ferreri, J.C.; Ambrosini, W. . . . June 2002 . . . Autoridad Regulatoria Nuclear, Buenos Aires, Argentina; University of Pisa, Italy.
Nucl. Eng. Des., 215, 171-185 . . . Simple Evaluation Method for Radiation Streaming Through Bent Ducts Having Arbitrary Rectangular Sections and a Plane Radiation Source. . . . Maki, K. . . . June 2002 . . . Hitachi Ltd., Ibaraki-ken, Japan.
Nucl. Eng. Des., 215, 187-198 . . . Theoretical and Experimental Study on Density Wave Oscillation of Two-Phase Natural Circulation of Low Equilibrium Quality. . . . Guanghui, S.; Dounan, J.; Fukuda, K.; Yujun, G. . . . June 2002 . . . Xi'an Juaotong University, People's Republic of China; Kyushu University, Fukuoka, Japan.
Nucl. Eng. Des., 215, 199-216 . . . A Study of the Performance of Void Fraction Correlations Used in the Context of Drift-Flux Two-Phase Flow Models. . . . Coddington, P.; Macian, R. . . . June 2002 . . . Paul Scherrer Institute, Villigen PSI, Switzerland.
Nucl. Eng. Des., 215, 217-242 . . . A Porosity Method to Describe the Influence of Internal Structures on a Fluid Flow in Case of Fast Dynamics Problems. . . . Robbe, M-F.; Bliard, F. . . . June 2002 . . . CEA, Gif-sur-Yvette, France; Socotec Industrie, Montigny le Bretonneux, France.
Nucl. Eng. Des., 215, 243-250 . . . Heat Transfer Effects on Flow Past an Impulsively Started Semi-Infinite Vertical Plate with Uniform Heat Flux. . . . Muthucumaraswamy, R.; Ganesan, P. . . . June 2002 . . . Sri Venkateswara College of Engineering, Sriperumbudur, India; Anna University, Chennai, India.
Nucl. Eng. Des., 215, 251-256 . . . Cognitive Model Research of Nuclear Power Plant Operators. . . . Fang Xiang, Zhao Bingquan, Jiang Shengyao . . . June 2002 . . . Tsinghua University, Beijing, China.