Radiation Measurement Applications (IRRMA-V)
From time to time we receive information between publications of RSICC Newsletters that we feel should be in the current publication. We obviously cannot update the few hard copies that have been mailed out, but can update the web version. The "" or "" article(s) will be marked in the table of contents. So, visit the newsletter throughout the month to see if there's anything new! Also, there is now a PDF printable version available on our NEWSLETTER web page: http://www-rsicc.ornl.gov/NEWSLETTER.html.
SATIF will be held April 10-12, 2002, at Stanford Linear Accelerator Center. A copy of the official version of the announcement and proposed program is available in PDF format at: http://www.nea.fr/html/science/ satif/nscdoc0203.pdf.
The RAdiation Dose Assessment Resource (RADAR) web site http://www.doseinfo-radar.com/ is a new excellent resource for internal and external dose. This site contains a large quantity of information available for browsing and free download on topics related to internal and external dose assessment.
Internal Dose Assessment - This includes decay data for >800 radionuclides, dose factors (like MIRD S values or ICRP SEEs) for 19 phantoms for these >800 nuclides, specific absorbed fractions for these phantoms, dose estimates and kinetic model data for radiopharmaceuticals, IAEA dose conversion factors for inhalation or ingestion of hundreds of nuclides, fetal doses for various radiopharmaceuticals and situations in nuclear medicine, information on radiopharmaceuticals excreted in breast milk.
External Dose Assessment - This includes dose tables for external point sources, beta doses to skin, doses from immersion in air or ground contamination, external dose from medical sources and patient consent language templates.
There is other free information as well; the site will be undergoing revisions as new material can be added. There are some fee-based services, including on-line training courses and contacts with consultants.
Contact: Michael G. Stabin, PhD, CHP, Assistant Professor of Radiology and Radiological Sciences at Vanderbilt University, (tel 615-343-0068, fax 615-322-3764, e-mail firstname.lastname@example.org).
Dr. J. A. Wang participated in the Atucha-I NPP RPV Safety Analysis Workshop in Lima, Argentina, from February 25-27, 2002, where he reviewed the Atucha-I surveillance program presented by Atucha-I Power Station Operator, Argentina Nuclear Regulatory Authority (ARN), and National Atomic Energy Commission of Argentina (CNEA). Twenty-two participants, including an invited foreign team from three countries, attended the Atucha-I Workshop. The foreign team consisted of four members, including Wang, from the United States representing ORNL, two representatives from Germany representing Framatome and GRS, respectively, and one from Finland representing VTT.
The Atucha-I Workshop and ARN meetings were designed to resolve the issues regarding the validity of Atucha-I surveillance data and Framatome VAK accelerated surveillance data as applied to the RPV integrity study of Atucha-I NPP. The current status and future recommendations for the Atucha-I surveillance program were summarized at the end of the workshop by the foreign team.
Subsequent to the Atucha-I Workshop, Wang and the German GRS representative participated in the meetings that were held at ARN on the RPV Integrity of Atucha-I NPP in Buenos Aires, Argentina, on February 28-March 1, 2002. From Atucha-I surveillance data and based on ARN's evaluation, Atucha-I should have reached the end of lifetime at the end of 2002. However, in light of new methods of evaluating reference temperature and the additional surveillance data from the German VAK program and IAEA JM data, the operating lifetime of Atucha-I needs to be reassessed. Several recommendations to update the dosimetry program and fluence evaluation, and regulatory safety margin for VAK accelerated data, were made by Wang during the meetings.
Muriel Landis, wife of John Landis, passed away on February 24, 2002. John was ANS President from 1971-72. He and Muriel established the John & Muriel Landis Scholarships and were constant contributors to the ANS Public Education Program. They recently moved to Roanoke, VA, from Boston, MA. Donations may be made to the following: Moravian College, 1200 Main Street, Bethlehem, PA 18018. John's address is 2131 Chestnut Oak Court, Roanoke, VA 24018.
Four U.S. Nuclear Regulatory Commission (NRC) software packages transferred from the Energy Science and Technology Software Center, Oak Ridge, Tennessee, to RSICC were added to the RSICC computer code collection. Please browse the computer code abstracts available at RSICC's www site for more information on these packages.
Two new packages, two additions, and one newly frozen package were
added to the computer code software and data collection. Two are foreign
Los Alamos National Laboratory, Los Alamos, New Mexico, updated the SOURCES package with the addition of the Los Alamos SOURCES Tape1 Creator and Library Link (LASTCALL) Version 1. Intended to supplement the SOURCES manual, LASTCALL is a simple graphical user interface designed to minimize common errors made during input. The optional application, LASTCALL, consists of a single dialog window launched from an executable (lastcall.exe) on Windows-based personal computers. SOURCES4B determines alpha,n; spontaneous-fission; and beta-n delayed neutron sources and spectra due to the decay of radionuclides. SOURCES 4B calculates alpha-n source rate and spectra for homogeneous medium, interface and alpha beam problems and can also calculate alpha-n source rate and spectra in a thin neutron-producing region between two alpha-producing regions.
SOURCES-4B runs on many computers including Sun, IBM RS/6000 and
personal computers. A LASTCALL executable compiled using Compaq Visual
Fortran Standard Edition Version 6.6.0 under Windows 2000 on a personal
computer is included. No source is provided for LASTCALL, and no Unix version
is available. The package is transmitted on a CD which includes the source,
PC executables, data libraries, and test cases in a self-extracting compressed
Windows file. The package is also transmitted in a GNU compressed tar file.
References: LA-8869-MS (June 1981), LA-UR-00-5016 (2000) and LA-UR-02-709
(2002). Fortran 77; Sun and PC (C00661/MNYCP/03).
The Universitat de Barcelona and the Universitat Politècnica de Catalunya in Barcelona, Spain, and Universidad Nacional de Cordoba, Argentina, through the Nuclear Energy Agency Data Bank, Issy-les-Moulineaux, France, contributed a newly frozen version of this code system to perform Monte Carlo simulation of electron-photon showers in arbitrary materials. The adopted scattering model gives a reliable description of radiation transport in the energy range from a few hundred eV to about 1GeV. PENELOPE generates random electron-photon showers in complex material structures consisting of any number of distinct homogeneous regions (bodies) with different compositions.
The present version 2001 contains substantial changes/improvements to the previous versions 1996 and 2000. As for the physics, the model for electron/positron elastic scattering has been revised. Bremsstrahlung emission is now simulated using partial-wave data instead of analytical approximate formulae. Photoelectric absorption in K and L-shells is described from the corresponding partial cross sections. Fluorescence radiation from vacancies in K and L-shells is now followed. Refinements have also been introduced in the electron/positron transport mechanics, mostly to account for the energy dependence of the mean free paths for hard events. The simulation routines have been re-programmed in a more structured (and readable) way, and new example MAIN programs have been written with a more flexible input and expanded output.
PENELOPE can be run on almost any operating system supporting a Fortran
77 compiler (Unix, MS-DOS, Windows95, Windows NT, VMS, etc.). Note that
a Fortran compiler is required on all systems to build problem-specific
executables; therefore, no executables are included in the package. The
code was tested at RSICC on a PC Pentium under WindowsME using GNU Fortran
G77 v0.5.25. The package is transmitted on a CD which contains source files,
test case input files, documentation and data files written in a self-extracting,
compressed Windows file. Reference: Workshop Proceedings, Issy-les-Moulineaux,
France ISBN:92-64-18475-9 (November 2001). Fortran 77; DEC Alpha, Sun,
and PC (C00682/MNYCP/02).
The University of Tennessee, Nuclear Engineering Dept., Knoxville, Tennessee, and Oak Ridge National Laboratory, Oak Ridge, Tennessee, contributed this discrete ordinates code system. TDTORT solves the time-dependent, three-dimensional neutron transport equation with explicit representation of delayed neutrons to estimate the fission yield from fissionable material transients. This release includes a modified version of TORT from the C00650/MFMWS/01 DOORS3.1 code package plus the time-dependent TDTORT code. GIP is also included for cross-section preparation. The codes read ANISN-format cross-section libraries, which are not included in the package.
TDTORT was developed on Sun workstations. It was compiled, and test
cases were run on DEC Alpha Digital Unix workstations and personal computers
under Linux. Fortran and C compilers are required for installation on Unix
systems. Executables created with the Portland Group Inc. Workstation 3.3
f77 compiler are included for Linux users. The package is transmitted as
a GNU compressed Unix tar file on CD. The tar file contains the source
files for TDTORT, TORT, and GIP, plus Linux executables, test cases, information
file, and scripts. References: Ph.D. Dissertation, The University of Tennessee
(August 1997), and ORNL/TM-13221 (October 1997), and ORNL/TM-8362 (September
1982). Fortran 77 and C; Sun Ultra; DEC OSF/1, PC under Linux (C00709/MNYWS/00).
The Idaho National Engineering & Environmental Laboratory, Idaho
Falls, Idaho, contributed an addition to the SAPHIRE 7.06 package. Included
in the addition are two files associated with the GEM help-file and the
GEM icon. SAPHIRE is a collection of programs developed for the purpose
of performing those functions necessary to create and analyze a complete
Probabilistic Risk Assessment (PRA) primarily for nuclear power plants.
The programs included in this suite are the Integrated Reliability and
Risk Analysis System (IRRAS), the System Analysis and Risk Assessment (SARA)
system, the Models And Results Database (MAR-D) system, and the Fault tree,
Event tree and P&ID (FEP). Previously these programs were graphical
editors released as separate packages. These programs include functions
to allow the user to create event trees and fault trees, to define accident
sequences and basic event failure data, to solve system and accident sequence
fault trees, to quantify cut sets, and to perform uncertainty analysis
on the results. The code runs on IBM-PC compatible computers running Windows
95, 98, NT. The package is transmitted on CD and includes the executable
modules and sample problem input data. Reference: NUREG/CR-6116 Vols. 1,
2, 3, 4, 5, 7, and 8 (December 1993). MODULA-2; IBM PC 486 (P00405/PC486/03).
The Institute of Physics and Power Engineering, Obninsk, Russia,
and NRG Nuclear Research and Consultancy Group, Petten, The Netherlands,
through the OECD NEA Data Bank, Issy-les-Moulineaux, France, contributed
the MENDL-2P data libraries. These neutron reaction data can be used for
nuclear activation and transmutation applications at energies up to 100
MeV. This distribution contains the NEA Data Bank IAEA-1376/01 and IAEA-1376/02
packages. The Medium Energy Nuclear Data Library MENDL-2P proton induced
intermediate energy cross sections were generated by Shubin, Lunev, Konobeyev
and Dityuk at IPPE. The library is distributed in the original format and
also in another format that has been converted to ENDF-6 and verified through
the ENDF-6 utility codes CHECKR, FIZCON and PSYCHE (PSR-333/CHENDF 6.12).
This was done by A.J. Koning, ECN Petten. No retrieval program is included.
The package is transmitted on a CD which contains a self-extracting, compressed
Windows file with the data libraries and documents in PDF format. References:
IAEA-NDS-204 (January 1998), IAEA-NDS-136 Rev. 1 (July 1995), INDC(CCP)-385
(May 1995). ASCII format; IBM PC (D00207/MNYCP/00).
As years have gone by many different codes and applications have been sent to RSICC for stewardship. We currently have over 1500 analytical code 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 Space Nuclear Physics 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. We hope you enjoy this new feature! Next month we will focus on Medical Applications.
Hamilton Hunter - RSICC DirectorALKASYS-PC
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. 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.
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/ and in the attached announcement and call for papers.
For more information please contact: Chairman Prof. Jorge E. Fernandez, Laboratory of Montecuccolino-DIENCA, University of Bologna, via dei Colli, 16 - 40136 Bologna, Italy (tel +39-051.644.1718, fax +39-051.644.1747, e-mail email@example.com) (also for any request of information and inclusion in the mailing list).
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 firstname.lastname@example.org.
Please remember that success of this meeting depends on your active
support and involvement. Finally, please bookmark the conference web site:
and visit it occasionally for news and updates. Comments and suggestions
are most welcome.
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 web site http://web.gat.com/conferences/iaea-tm/
main.html. Contacts: Dan Goodin, Chair, General Atomics (fax 858-455-3181,
Art Nobile, Co-Chair, Los Alamos National Laboratory (e-mail email@example.com).
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
to find out about IMUG, register for the meeting or request notification
of web updates. The website will be updated as additional information becomes
The MCNP code developers will present several classes in 2002 in
the United States and two classes in Europe. The dates for these classes
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, that has a tentative release date of April 2002. 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
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.
All 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.
Dates: August 5-7, 2002 in Braunschweig, Germany
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 on-line registration
and further information please visit our web site at: http://www.ptb.de/utc2002/.
DATE: May 6-10, 2002 FEE: $1,850 per person with the MCNP™ code package
Monte Carlo-type calculations are ideally suited to solving a variety of problems in radiation protection and dosimetry. This course is aimed at the HP, 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 overview of the MCNP code and the Monte Carlo method, basic concepts, 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. The course fee includes a complete MCNP code package, distributed directly from the Radiation Safety Information Computational Center (RSICC). Students will also 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 ESH-4, MCNP Class/David Seagraves, Mail Stop G761, Los Alamos, NM 87545.
Inquiries regarding registration and class space availability should
be made to David Seagraves, 505-667-3241, fax: 505-665-6071, e-mail: firstname.lastname@example.org.
Technical questions may also be directed to Dick Olsher, 505-667-3364,
This on-line 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 on-line exam are included. Users completing the exam will receive a certificate of completion. Users may also interact with instructors by e-mail 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 email@example.com)
or Dr. Richard B. Sparks (tel 865- 938-4949, fax 865-947-1550, email firstname.lastname@example.org,
Argonne National Laboratory will conduct a training course on the
RESRAD family of risk assessment codes. This CRCPD and DOE cosponsored
training course will be conducted on May 1-4, 2002 at Argonne National
Laboratory. The latest probabilistic versions of RESRAD 6.1 and RESRAD-BUILD
3.1 will be used. The tentative agenda of this workshop can be found on
the RESRAD web site http://web.ead.anl.gov/resrad/
training/AgendaMay2002.htm. Space is limited. For more information,
or contact Carole Ealy at 630-252-5677 (email:
The Division's biennial Topical Meeting is rapidly approaching. It
is scheduled for April 14-18, 2002, in Santa Fe, New Mexico. RPSD 2002
is co-sponsored by the Health Physics Society, the OECD/NEA, and RSICC.
In addition to an exciting technical program, there are workshops, tours,
and various social events planned. There are also special registration
opportunities for students, emeritus members of ANS, exhibitors, and guests.
For additional information on RPSD 2002, check the Conference Web site
or send an e-mail to email@example.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 e-mail 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 http://www.ornl.gov/scale/trcourse.html.
Contact: Kay Lichtenwalter (tel 865-574-9213, email firstname.lastname@example.org).
The 10th in a series will be held May 21-23, 2002, at the University of Michigan, Ann Arbor. The program will emphasize research and recent development in ionizing radiation measurements. Proposed session topics are: radiation sources, including secondary target sources; detectors and detection systems; data acquisition and data analysis systems and methods; radiation spectroscopy; particle-induced X-ray emission and radiation-induced fluorescence; analytical standards and elemental analysis; new and
unique applications of ionizing radiation; industrial radiography
and tomography; nuclear methods in space exploration and planetary science.
For more information see the website at:
or contact David K. Wehe at email@example.com.
Thirty-Eighth Annual Meeting of the National Council on Radiation Protection and Measurements, Apr. 10-12, 2002, Arlington, VA. Contact: William M. Beckner (tel 301-657-2652, fax 301-907-8768, url www.ncrp.com).
Back to the Future of Nuclear Technology, 2002 ANS Student Conference, Apr. 10-13, 2002, University Park, PA. Contact: Frank Buschman (tel 814-865-6351, email firstname.lastname@example.org, url www.clubs.psu.edu/ANS).
12th Biennial RPSD Topical Meeting, Apr. 14-18, 2002, Santa Fe, NM. Hosted by the ANS Trinity Section and cosponsored by the Health Physics Society, L'Organisation de cooperation et de developpement/L'Agence pour l'energie nucleaire (OECD/AEN, and RSICC. Contact: (email rpsd2002@lanl. gov, url www.lanl.gov/RPSD2002/).
International Youth Nuclear Congress 2002, Apr. 16-20, 2002, Taejon, Korea. Contact: Alexandre Tsiboulia or Han Seong Son (email email@example.com,firstname.lastname@example.org, url http://www.iync.org).
Seventh International Radiopharmaceutical Dosimetry Symposium, Apr. 17-19, 2002, Nashville, TN. Contact: Michael Stabin (email email@example.com, url http://www.doseinfo-radar.com/ symphome.html).
MCNPX Intermediate Workshop, Apr. 19-24, 2002, Santa Fe/Los Alamos, NM. Contact: Bill Hamilton (tel 505-662-9097, email firstname.lastname@example.org, url http://mcnpxworkshops.com for details). *We will take Sunday off.
MCNP, EGS4 & BEAM Users Group Meeting, Apr. 22-24, 2002, Stoke-on-Trent, England. Contact: Craig Edwards (MCNEG Chairman) (tel + 44 (0) 1782 554070, fax + 44 (0) 1782 845140, email email@example.com, url www.mcneg.org.uk).
International Conference on Wire System Aging, Apr. 23-25, 2002, Rockville, MD. Contact: Technical information: Jit Vora (tel 301-415-5833, fax 301-415-5151, email firstname.lastname@example.org); registration information: Susan Monteleone (tel 631-344-7235, fax 631-344-3957, email email@example.com, url http://www.bnl.gov/icwsa).
Radiation Transport Calculations Using the EGS Monte Carlo System,
Apr. 29-May 2, 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 firstname.lastname@example.org,
Practical MCNP for the HP, Medical Physicist, and Rad Engineer, May 6-10, 2002, Los Alamos, NM. Contact: David Seagraves (tel 505-667-3241, fax 505-665-6071, email email@example.com, url http://drambuie.lanl.gov/ ~esh4/mcnp.htm; technical questions to Dick Olsher, 505-667-3364, firstname.lastname@example.org).
Symposium on Radiation Measurements and Applications, May
21-23, 2002, Ann Arbor, MI. Contact: General Chair David K. Wehe (tel 734-764-6215,
email email@example.com, url http://rma-symposium.engin.umich.edu/).
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: firstname.lastname@example.org).
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 email@example.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://lithos.gat.com/snowmass/).
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).
Fourth Meeting of the International MACCS Users Group (IMUG), September 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: firstname.lastname@example.org; 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 email@example.com, url http://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
2002 International Topical Meeting on Probabilistic Safety Assessment (PSA '02), Oct. 6-10, 2002, Detroit, MI. Contact: Rebecca Steinman (phone 734-930-7500, email firstname.lastname@example.org, 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 email@example.com, 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 firstname.lastname@example.org, url http://www.aocrp-1.com).
15th ANS Topical Meeting on the Technology of Fusion Energy, Nov. 17-21, 2002, Washington, DC. (url http://www.ans.org/).
International Symposium on Standards and Codes of Practice in
Medical Radiation Dosimetry, November 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, September 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 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.
Ann. Nucl. Energy, 29, 1019-1039 . . . Development of a Solution Method for the Differential Equations Arising in the Biosphere Module of the BNFL's Suite of Codes MONDRIAN. . . . Williams, M.M.R.; Thorne, M.C.; Thomson, J.G.; Paulley, A. . . . June 2002 . . . Williams Scientific Services Ltd., Surrey, UK; Mike Thorne and Associates, Ltd., West Yorks, UK; BNFL, Cheshire, UK.
Ann. Nucl. Energy, 29, 1041-1054 . . . A Practical Procedure of Bilinear Weighted Core Kinetics Parameters Computation for the Purpose of Experimental Reactivity Determination. . . . Christoskov, I.D.; Petkov, P.T. . . . June 2002 . . . University of Sofia, Sofia, Bulgaria; Institute of Nuclear Research and Nuclear Energy, Sofia, Bulgaria.
Ann. Nucl. Energy, 29, 1055-1071 . . . Deterministic Adjoint Transport Applications for He-3 Neutron Detector Design. . . . Sjoden, G.E. . . . June 2002. . . (no place of business given).
Ann. Nucl. Energy, 29, 1073-1083 . . . Nuclear Reactor Power and Flux Distribution Fitting from a Diffusion Theory Model and Experimental Data. . . . Pomerantz, M.E.; Calabrese, C.R.; Grant, C. . . . June 2002 . . . Central Nuclear Embalse, Cordoba, Argentina; Comisión Nacional de Energía Atómica, Buenos Aires, Argentina.
Ann. Nucl. Energy, 29, 1085-1104 . . . New Investigations of the Criticality Property of Pure 232U. . . . Ganesan, S.; Sharma, A.R.; Wienke, H. . . . June 2002 . . . Bhabha Atomic Research Centre, Mumbai, India; Institute for Plasma Research, Gujarat State, India; SCK-CEN, Belgian Nuclear Research Center, Mol, Belgium.
Ann. Nucl. Energy, 29, 1105-1117 . . . Polynomial Nodal Method for Solving Neutron Diffusion Equations in Hexagonal-Z Geometry. . . . Zimin, V.G.; Baturin, D.M. . . . June 2002 . . . Moscow Engineering Physics Institute, Moscow, Russia.
Ann. Nucl. Energy, 29, 1119-1130 . . . On the Use of Lead as a Neutron Filter. . . . Adib, M.; Naguib, K.; Ashry, A. Fathalla, M. . . . June 2002 . . . AEA, Cairo, Egypt; Ain Shams University, Cairo, Egypt.
Ann. Nucl. Energy, 29, 1131-1136 . . . Heat Generation and Corresponding Rise in Temperature Due to Absorption of Thermal Neutrons in Several Shielding Materials. . . . Ibrahim, M.A. . . . June 2002 . . . AEA, Cairo, Egypt.
Ann. Nucl. Energy, 29, 1141-1150 . . . Determination of a Closed-Form Solution for the Multidimensional Transport Equation Using a Fractional Derivative. . . . Zabadal, J.; Vilhena, M.T.; Segatto, C.F.; Pazos, R.P. . . . July 2002 . . . Universidade Federal do Rio Grande do Sul, Porte Alegre, Brazil, Pontificia Universidade Catolica do Rio Grande do Sul, Brazil.
Ann. Nucl. Energy, 29, 1151-1155 . . . On the Collision Probability for the Infinite Cylinder. . . . Corngold, N.R. . . . July 2002 . . . California Institute of Technology, Pasadena, CA.
Ann. Nucl. Energy, 29, 1157-1169 . . . Measurements of Neutron Capture Cross-Section of Indium in the Energy Region from 0.003 eV to 30 keV. . . . Yoon, J.; Ro, T.; Lee, S.; Yamaoto, S.; Kobayashi, K. . . . July 2002 . . . Dong-A University, Pusan, South Korea; Kyoto University, Osaka, Japan.
Ann. Nucl. Energy, 29, 1171-1194 . . . A Nodal Modal Method for the Neutron Diffusion Equation. Application to BWR Instabilities Analysis. . . . Miró, R.; Ginestar, D.; Verdú, G.; Hennig, D. . . . July 2002 . . . Universidad Politécnica de Valencia, Spain; Paul Scherrer Institute, Villigen PSI, Switzerland.
Ann. Nucl. Energy, 29, 1209-1224 . . . Measurement of the Activation Cross-Sections of (n,np+d) Reactions for Lanthanide Isotopes in the Energy Range Between 13.4 and 14.9 MeV . . . Sakane, H.; Kasugai, Y.; Shibata, M.; Ikeda, Y.; Kawade, K. . . . July 2002 . . . Nagoya University, Nagoya, Japan; JAERI, Ibaraki-ken, Japan.
Ann. Nucl. Energy, 29, 1241-1252 . . . The Interaction of Fast Neutrons with Hafnium. . . . Smith, A.B. . . . July 2002 . . . Argonne National Laboratory, Argonne, IL.
Ann. Nucl. Energy, 29, 1253-1259 . . . Reactivity Worth of the Thermal Column of a MTR Type Swimming Pool Research Reactor Using Low Enriched Uranium Fuel. . . . Khan, L.A.; Ahmad, N. . . . July 2002 . . . Pakistan Institute of Engineering and Applied Sciences, Islamabad, Pakistan.
Ann. Nucl. Energy, 29, 1261-1298 . . . Void Fraction Propagation in a Bubbly Two-Phase Flow with Expansion Effects. . . . Espinosa-Paredes, G. et al. . . . July 2002 . . . Universidad Autonoma Metropolitana-Iztapalapa, México D.F., Mexico; Centro Nacional de Investigacion y Desarrollo Technologico, Mor., C.P., Mexico; Instituto de Investigaciones Eléctricas, Mor., Mexico.
Ann. Nucl. Energy, 29, 1315-1325 . . . Lumped Parameters Analysis of Coupled Kinetics and Thermal-Hydraulics for Small Reactors. . . . Housiadas, C. . . . July 2002 . . . Demokritos National Centre for Scientific Research, Athens, Greece.
Ann. Nucl. Energy, 29, 1327-1344 . . . Core Reload Optimization for Equilibrium Cycles Using Simulated Annealing and Successive Linear Programming. . . . Mahlers, Y.P. . . . July 2002 . . . Institute for Nuclear Research, Kiev, Ukraine.
Ann. Nucl. Energy, 29, 1345-1364 . . . Direct Deterministic Method for Neutronics Analysis and Computation of Asymptotic Burnup Distribution in a Recirculating Pebble-Bed Reactor. . . . Terry, W.K.; Gougar, H.D.; Ougouag, A.M. . . . July 2002 . . . Idaho National Engineering and Environmental Laboratory, Idaho Falls, ID.
Ann. Nucl. Energy, 29, 1365-1371 . . . Evaluation of the Photo-Neutron Source in the Syrian Miniature Neutron Source Reactor. . . . Khamis, I. . . . July 2002 . . . Atomic Energy Commission of Syria, Damascus, Syria.
Ann. Nucl. Energy, 29, 1373-1380 . . . The Stochasticity Treatment on the Reactivity and Criticality Thickness in Slab Geometry. . . . Anli, F. . . . July 2002 . . . KSÜ, K.Maras, Turkey.
J. Nucl. Mater., 301, 1-7 . . . The Accelerator Driven System Strategy in Japan. . . . Kurata, Y.; Takizuka, T.; Osugi, T.; Takano, H. . . . February 2002 . . . JAERI, Ibaraki-ken, Japan.
J. Nucl. Mater., 301, 8-14 . . . The Pb-Bi Cooled XADS Status of Development. . . . Cinotti, L.; Gherardi, G. . . . February 2002 . . . Ansaldo Nuclear Division, Genova, Italy; ENEA, Bologna, Italy.
J. Nucl. Mater., 301, 15-22 . . . Radiation Effects in Structural Materials of Spallation Targets. . . . Jung, P. . . . February 2002 . . . Institut für Festkörperforschung, Jülich, Germany.
J. Nucl. Mater., 301, 23-27 . . . Temperature Effect on the Corrosion Mechanism of Austenitic and Martensitic Steels in Lead-Bismuth. . . . Benamati, G.; Fazio, C.; Piankova, H.; Rusanov, A. . . . February 2002 . . . ENEA, Bologna, Italy; IPPE, Kaluga Region, Russia.
J. Nucl. Mater., 301, 28-34 . . . Corrosion Studies in Liquid Pb-Bi Alloy at JAERI: R&D Program and First Experimental Results. . . . Kurata, Y.; Futakawa, M.; Kikuchi, K.; Saito, S.; Osugi, T. . . . February 2002 . . . JAERI, Ibaraki-ken, Japan.
J. Nucl. Mater., 301, 35-39 . . . Corrosion and Deposition of Ferrous Alloys in Molten Lead-Bismuth. . . . Deloffre, Ph.; Terlain, A.; Barbier, F. . . . February 2002 . . . CEA-Saclay, Gif-sur-Yvette, France.
J. Nucl. Mater., 301, 40-46 . . . Results of Steel Corrosion Tests in Flowing Liquid Pb/Bi at 420-600 C After 2000 H. . . . Müller, G. et al. . . . February 2002 . . . Institute for Pulsed Power and Microwave Technology, Karlsruhe, Germany.
J. Nucl. Mater., 301, 47-52 . . . Development of an Oxygen Sensor for Molten 44.5% Lead-55-5% Bismuth Alloy. . . . Fernández, J.A.; Abellà, J.; Barceló, J.; Victori, L. . . . February 2002 . . . Universitat Ramon Llull, Barcelona, Spain.
J. Nucl. Mater., 301, 53-59 . . . Impurities and Oxygen Control in Lead Alloys. . . . Courouau, J.-L. et al. . . . February 2002 . . . CEA Cadarache, St. Paul lez Durance, France; CEA Saclay, Gif-sur-Yvette, France.
J. Nucl. Mater., 301, 60-63 . . . Preliminary Studies on PbO Reduction in Liquid Pb-Bi Eutectic by Flowing Hydrogen. . . . Ricapito, I.; Fazio, C.; Benamati, G. . . . February 2002 . . . ENEA, Bologna, Italy.
J. Nucl. Mater., 301, 64-69 . . . Atomistic Simulation of Liquid Lead and Lead-Bismuth Eutectic. . . . Celino, M.; Conversano, R.; Rosato, V. . . . February 2002 . . . ENEA, Roma, Italy; Istituto Nazionale di Fisica Della Materia, Unitá di Ricerca Roma, Italy.
J. Nucl. Mater., 301, 70-76 . . . Liquid Metal Embrittlement of the Martensitic Steel 91: Influence of the Chemical Composition of the Liquid Metal. Experiments and Electronic Structure Calculat . . . Legris, A.; Nicaise, G. Vogy, J.-B.; Foct, J. . . . February 2002 . . . Université des Sciences et Technologies de Lille, Villeneuve D'Ascq, France.
J. Nucl. Mater., 301, 81-89 . . . Effects of Annealing on Tensile Property and Corrosion Behavior of Ti-Al-Zr Alloy. . . . Kim, T-K.; Choi, B-S.; Jeong, Y-H.; Lee, D-J.; Chang, M-H. . . . March 2002 . . . KAERI, Daejeon, South Korea.
J. Nucl. Mater., 301, 90-97 . . . Reaction of Zircaloy-4 with Tellurium Under Different Oxygen Potentials. . . . Arima, T.; Masuzumi, T.; Furuya, H. Idemitsu, K. Inagaki, Y. . . . March 2002 . . . Kyushu University, Hakozaki, Japan.
J. Nucl. Mater., 301, 98-107 . . . Tritium Removal from Codeposits on Carbon Tiles by a Scanning Laser. . . . Skinner, C.H. et al. . . . March 2002 . . . Princeton University, Princeton, NJ; JAERI, Ibaraki-ken, Japan.
J. Nucl. Mater., 301, 108-117 . . . The Effect of Non-Metallic Inclusions on the Fracture Toughness Master Curve in High Copper Reactor Pressure Vessel Welds. . . . Oh, Y-J.; Lee, B-S.; Hong, J-H. . . . March 2002 . . . KAERI, Taejon, South Korea.
J. Nucl. Mater., 301, 118-121 . . . Hardness and Microstructural Studies of Electron Beam Welded Joints of Zircaloy-4 and Stainless Steel. . . . Ahmad, M. et al. . . . March 2002 . . . Pakistan Institute of Nuclear Science and Technology, Islamabad, Pakistan.
J. Nucl. Mater., 301, 122-128 . . . Competition Between Disorder Creation and Annealing in Fluoroapatite Nuclear Waste Forms. . . . Chaumont, J.; Soulet, S.; Krupa, J.C.; Carpena, J. . . . March 2002 . . . Centre de Spectrométrie Nucléaire, Orsay Campus, France; CEA-Cadarache, St. Paul-lez-Durance, France; Institut de Physique Nucleaire, Orsay, France.
J. Nucl. Mater., 301, 129-141 . . . Disorder-Induced Melting in Nickel: Implication to Intergranular Sulfer Embrittlement. . . . Heuer, J.K.; Okamoto, P.R.; Lam, N.Q.; Stubbins, J.F. . . . March 2002 . . . Argonne National Laboratory, Argonne, IL; University of Illinois at Urbana-Champaign, Urbana, IL.
J. Nucl. Mater., 301, 142-152 . . . Evolution of the Uranium Local Environment During Alteration of SON68 Glass. . . . Jollivet, P.; Den Auwer, C.; Simoni, E. . . . March 2002 . . . CEA, Bagnols-sur-Ceze, France; Institut de Physique Nucléaire, Orsay, France.
J. Nucl. Mater., 301, 153-164 . . . Hydride Blister Formation in Zr-2.5wt%Nb Pressure Tube Alloy. . . . Singh, R.N.; Kishore, R.; Sinha, T.K.; Kashyap, B.P. . . . March 2002 . . . Bhabha Atomic Research Centre, Mumbai, India; IIT Powai, Mumbai, India.
J. Nucl. Mater., 301, 165-169 . . . Carbothermal Route for Preparation of Boron Carbide Powder from Boric Acid-Critic Acid Gel Precursor. . . . Sinha, A.; Mahata, T.; Sharma, B.P. . . . March 2002 . . . Bhabha Atomic Research Centre, Navi Mumbai, India.
J. Nucl. Mater., 301, 170-182 . . . EPMA and SEM of Fuel Samples from PWR Rods with an Average Burn-Up of Around 100 MWd/kgHM. . . . Manzel, R.; Walker, C.T. . . . March 2002 . . . Framatome ANP, Erlangen, Germany; European Commission Joint Research Centre, Karlsruhe, Germany.
J. Nucl. Mater., 301, 183-186 . . . Gibbs Energy of Formation of Solid Ni3TeO6 from Transpiration Studies. . . . Ali(Basu), M. et al. . . . March 2002 . . . Bhabha Atomic Research Centre, Mumbai, India.
J. Nucl. Mater., 301, 187-192 . . . Effects of Dopants on Properties and Microstructure of Doped Graphite. . . . Zhang, G. et al. . . . March 2002 . . . Chinese Academy of Sciences, Taiyuan Shanxi and Hefei Anhui, PR China.
J. Nucl. Mater., 301, 193-202 . . . A New Technique for the Prediction of Non-Linear Material Behavior. . . . Wang, J.A.; Rao, N.S. . . . March 2002 . . . Oak Ridge National Laboratory, Oak Ridge, TN.
J. Nucl. Mater., 301, 203-209 . . . Hydrogen Absorption-Desorption Properties of UZr0.29 Alloy. . . . Shuai, M. et al. . . . March 2002 . . . China Academy of Engineering Physics, Sichuan, PR China.
J. Nucl. Mater., 301, 210-219 . . . Kinetic Theory of the Growth of the Circular Oxidation Islands on the UO2 Surface. . . . Kolá, M. . . . March 2002 . . . AECL, Whiteshell Laboratories, MB, Canada.
J. Nucl. Mater., 301, 220-222 . . . Activity Coefficients of Dy Dissolved in Liquid Bi. . . . Sheng, J.; Yamana, H.; Moriyama, H. . . . March 2002 . . . Kyoto University, Osaka, Japan.
J. Nucl. Mater., 301, 223-226 . . . Further Considerations on Entropy Estimations of Actinide Compounds: AmCl3 and AmCl2. . . . Konings, R.J.M. . . . March 2002 . . . Joint Research Centre, Karlsruhe, Germany.
J. Nucl. Mater., 301, 227-232 . . . Thermally Activated Deformation of Irradiated Reactor Pressure Vessel Steel. . . . Böhmert, J.; Müller, G. . . . March 2002 . . . Instutut für Sicherheitsforschung Abt., Dresden, Germany.
J. Nucl. Mater., 301, 233-236 . . . Chemical Analysis of Flakes from the Joint European Torus. . . . Kleykamp, H. . . . March 2002 . . . Institut für Materialforschung I, Karlsruhe, Germany.
J. Nucl. Mater., 301, 237-241 . . . Solidification of Sr-Containing Stripping Solutions in Titanate Ceramics. . . . Bao, W.; Xu, S.; Li, L.; Song, C.; Zhang, J.; Zhu, Y. . . . March 2002 . . . Tsinghua University, PR China.
J. Nucl. Mater., 301, 242-244 . . . Thermal Expansion of UO2 and Simulated DUPIC Fuel. . . . Kang, K.H.; Ryu, H.J.; Song, K.C.; Yang, M.S. . . . March 2002 . . . KAERI, Taejon, South Korea.
Nucl. Eng. Design, 213, 97-110 . . . Experiments on the Interactions of Molten ZrO2 with Water Using TROI Facility. . . . Song, J.H. et al. . . . April 2002 . . . KAERI, Taejon, South Korea.
Nucl. Eng. Design, 213, 111-117 . . . Effects of Hold Time and Neutron Irradiation on the Low-Cycle Fatigue Behavior of Type 316-CL and Their Consideration in a Damage Model. . . . Aktaa, J.; Horsten, M.G.; Schmitt, R. . . . April 2002 . . . Forschungszentrum Karlsruhe, Germany; NRG, Petten, The Netherlands.
Nucl. Eng. Design, 213, 119-131 . . . Benchmark Calculations of Neutron Yields and Dose Equivalent from Thick Iron Target for 52-256 MeV Protons. . . . Tayama, R. et al. . . . April 2002 . . . Hitachi Engineering Co., Ibaraki-ken, Japan; JAERI, Ibaraki-ken, Japan.
Nucl. Eng. Design, 213, 133-140 . . . The Development of the Crack Growth Model in Zirconium Claddings in Iodine Environment. . . . Likhanskii, V.V.; Matweev, L.V. . . . April 2002 . . . Institute for Innovation and Fusion Research, Moscow, Russia.
Nucl. Eng. Design, 213, 141-156 . . . Development of 'Pad Element' for Detailed Core Deformation Analyses and Its Verification. . . . Tsukimori, K.; Negishi, H. . . . April 2002 . . . Japan Nuclear Cycle Development Institute, Ibaraki-ken, Japan.
Nucl. Eng. Design, 213, 157-164 . . . About Some Principal Possibilities for Improvement of Electronuclear System's Characteristics. . . . Kiselev, G.V. . . . April 2002 . . . State Scientific Center of the Russian Federation, Moscow, Russia.
Nucl. Eng. Design, 213, 165-182 . . . Core Power Limits for a Lead-Bismuth Natural Circulation Actinide Burner Reactor. . . . Davis, C.B.; Kim, D.; Todreas, N.E.; Kazimi, M.S. . . . April 2002 . . . Idaho National Engineering and Environmental Laboratory, Idaho Falls, ID; MIT, Cambridge, MA.
Nucl. Eng. Design, 213, 183-197 . . . Numerical Simulation of Lateral Phase Distribution in Turbulent Upward Bubbly Two-Phase Flows. . . . Okawa, T.; Kataoka, I.; Mori, M. . . . April 2002 . . . Osaka University, Japan; Tokyo Electric Power Co., Tokyo, Japan.
Nucl. Eng. Design, 213, 199-207 . . . Annular Flow Experiments in Rod Bundles with Spacers. . . . Feldhaus, G.; Azzopardi, B.U.; Zeggel, W. . . . April 2002 . . . Technische Universität Braunschweig, Braunschweig, Germany; University of Nottingham, UK.
Nucl. Eng. Design, 213, 209-221 . . . Electrical Ignition Sources in Nuclear Power Plants: Statistical, Modelling and Experimental Studies. . . . Keski-Rahkonen, O.; Mangs, J. . . . April 2002 . . . VTT Building and Transport, Finland.
Nucl. Eng. Design, 213, 223-239 . . . Computation of Two-Phase Flow in Steam Generator Using Domain Decomposition and Local Zoom Methods. . . . Belliard, M.; Grandotto, M. . . . April 2002 . . . CEA, Cadarache, St. Paul lez Durance, France.
Nucl. Eng. Design, 213, 241-258 . . . Considerations Pertaining to the Achievement of High Burn-Ups in HTR Fuel. . . . Martin, D.G. . . . April 2002 . . . Nuclear Fuels Consultant, Oxon, UK.
Nucl. Eng. Design, 213, 259-271 . . . Effects of Annular Crevices on Pool Boiling Heat Transfer. . . . Kang, M-G.; Han, Y-H. . . . April 2002 . . . Andong National University, Kyungbuk, Republic of Korea.
Nucl. Eng. Design, 213, 273-278 . . . Soft-Measuring Method of the Core Exit Temperature of Coolant for the 200 MW Nuclear Heating Reactor. . . . Meisheng, Z.; Chenwen, M. . . . April 2002 . . . Tsinghua University, Beijing, PR China.
Nucl. Eng. Design, 213, 279-287 . . . Pre-Project Study of a Nuclear Desalination Demonstration Plant for Tan-Tan, Morocco. . . . Wenxiang, Z.; Yajun, Z.; Dafang, Z.; Duo, D. . . . April 2002 . . . Tsinghua University, Beijing, China.
Nucl. Sci. Eng., 140, 111-136 . . . An Algorithm for Parallel Sn Sweeps on Unstructured Meshes. . . . Pautz, S.D. . . . February 2002 . . . Los Alamos National Laboratory, Los Alamos, NM.
Nucl. Sci. Eng., 140, 137-151 . . . Unified Nodal Method Formulation for Analytic Function Expansion Nodal Method Solution to Two-Group Diffusion Equations in Rectangular Geometry. . . . Lee, H.C.; Kim, C.H. . . . February 2002 . . . Seoul National University, Seoul, Korea.
Nucl. Sci. Eng., 140, 152-164 . . . Three-Dimensional Modeling of a Steam-Line Break in a Boiling Water Reactor. . . . Tinoco, H. . . . February 2002 . . . Forsmarks Kraftgrupp, Östhammar, Sweden.
Nucl. Sci. Eng., 140, 165-171 . . . Fluid Mechanics of Taylor Bubbles and Slug Flows. . . . Anglart, H.; Podowski, M.Z. . . . February 2002 . . . ABB Atom AB, Västerås, Sweden; Rensselaer Polytechnic Institute, Troy, NY.
Nucl. Sci. Eng., 140, 172-180 . . . Thermohydraulics Oscillations and Numerical Integration. . . . Ginestar, D.; Verdu, G.; March-Leuba, J. . . . February 2002 . . . Universidad Politécnica de Valencia, Valencia, Spain; Oak Ridge National Laboratory, Oak Ridge, TN.
Nucl. Sci. Eng., 140, 189-194 . . . Neutron Flux Perturbations Due to Infinite Plane Absorbers IV: The Exponential Flux Revisited. . . . Williams, M.M.R. . . . February 2002 (no business address given).