Printable PDF file of this newsletter available at: http://www-rsicc.ornl.gov/NEWSLETTER.html.
Dr. Jy-An Wang will assume the role of RSICC Data Coordinator. We welcome the new effort and capabilities that Jy-An possesses. His vast nuclear materials and science background will be advantageous to his approach and methods.
Our data collection expanded under the direction of John White, and we must continue growing to meet the needs of our user community. RSICC now has over 200 data libraries with applications across dosimetry, fission, fusion, and accelerator applications. With additional possibilities for fission power on the horizon, new high- and low- energy data and dosimetry libraries will be needed.
We also want to congratulate Jy-An on receiving an R&D 100 award
for the Spiral Notch Torsion Test. This project was developed and jointly
submitted by Jy-An Wang, ORNL's Nuclear Science and Technology Division;
Ken Liu, ORNL's Metals and Ceramics Division; and Inventure Laboratories
of Knoxville. It is a portable system that tests fracture toughness and
the strength of materials, including ceramics, composites, polymers, carbon
foam and concrete, to be used in designs. This system is expected to help
engineers set limits in structural designs so that certain materials are
not used in conditions unsuitable to the strengths of that material.
RSICC is pleased to announce that a five-day workshop on Oak Ridge National Laboratory's (ORNL) SAMMY code will be held May 12-16, 2003, in Knoxville, Tennessee. This training course is intended for those who are interested in the theory of neutron cross sections in the resonance region, and in the use of SAMMY for the analysis of experimental neutron-induced cross-section data for extracting values and covariances for resonance parameters. Both novice and experienced SAMMY users would benefit from the intensive and extensive examination of all aspects of resonance parameter analyses.
During the workshop, lectures and computer applications will alternate. Lectures will include both theoretical discussion and practical examples for each topic. The lecturer is Dr. Nancy Larson of the Nuclear Data and Information Analysis Group, Nuclear Science and Technology Division of ORNL, author of the SAMMY code.
Topics include (but are not limited to) the following:
I. R-matrix formalisms (both resolved and unresolved resonance region)
II. Simulation of experimental conditions
III. Mathematical methods used for experimental data-fitting
IV. Reporting results for Evaluated Nuclear Data Files
V. Features in the latest version of the analysis code SAMMY
The workshop will include hands-on computer applications using the latest version of SAMMY (M6). Computer exercises will lead participants through the various features of the code beginning with simple examples and leading to realistic situations. Participants who are experienced SAMMY users are encouraged to bring their own examples as well.
The number of PC workplaces available at the training center restricts
the number of workshop participants accepted. Therefore, we encourage you
to register as early as possible. The SAMMY workshop web site with further
detailed information and on-line registration can be accessed at http://www-rsicc.ornl.gov/SAMMY/intro.html.
Please bookmark the site and visit it occasionally for news and updates
as they become available.
The September 2002 Edition, of the International Handbook of Evaluated
Criticality Safety Benchmark Experiments will be available for distribution
on CD-ROM near the end of September. Twenty-three newly approved evaluations
are included in this version in addition to all previously approved evaluations.
Editorial and technical corrections have been made to some of the previously
approved evaluations, and major revisions were made to three evaluations:
HEU-COMP-THERM-010, HEU-MET-INTER-006, and MIX-COMP-THERM-011. Revision
status of each individual evaluation is noted at the bottom of each page.
In addition, a revision status table noting specific technical revisions
made to each evaluation is included on the CD-ROM in a directory designated
Revision. If you are interested in obtaining a copy of this edition of
the handbook on CD-ROM, you may request a copy by completing the registration
form provided at the ICSBEP internet site (http://www.icsbep.inel.gov/
Nuclear Community Needs for Free Computational Expert Consulting
RSICC wishes to poll the user community on the need for centralized Atomic Computational Expert Services (ACES). If you would benefit by being linked to a consulting expert via email or phone, please send email to email@example.com by September 30th with a list of codes on which you might want to receive expert help. Note the work areas to which you would apply the codes (GenIV, Homeland Defense, Reactor Safety, Consequence Analysis, Nuclear Criticality Safety, etc.). DOE complex experts would be made available to users needing immediate help on those software and data tools for their application and use. ACES would be free of charge to the users.
One U.S. Nuclear Regulatory Commission (NRC) software package transferred from the Energy Science and Technology Software Center, Oak Ridge, Tennessee, to RSICC was processed this month. Please browse the computer code abstract available at RSICC's web site for more information on this package.
Four changes were made to the computer code collection this month: one new package, two additions, and one modification.
Argonne National Laboratory, Argonne, Illinois, updated this reactor analysis code package with the addition of several sample problems, a new Windows executable, and a new Linux version. The VENTURE-PC program solves the usual neutronics eigenvalue, adjoint, fixed source, and criticality search problems. It treats up to three dimensions, maps power density, and does first-order perturbation analysis at the macroscopic cross section level. The BURNER code solves the nuclide chain equations to estimate the nuclide concentrations and burnup at the end of an exposure time or after a shutdown period. This package is a subset of CCC-459/BOLD VENTURE IV.
The Windows distribution contains 2 executables. The new executable is optimized for Pentium IV. It was compiled with Lahey/Fujitsu Fortran 95 V5.70b and tested in a DOS window of Windows2000 and WindowsXP. The other executable, copied from the previous release, was created using Lahey Fortran 90 V4.50h and runs in a DOS window on Windows95/98/NT systems. This executable should be run on Pentium III computers and older.
The new Linux distribution includes an executable compiled with the
Lahey/Fujitsu Fortran 95 Version 6.10a compiler for Linux. This executable
was tested on RedHat Linux 7; it will not run under RedHat Linux 6.1. The
package is distributed on a CD as a self-extracting compressed Windows
file and in a GNU compressed tar file. Included are documentation, source,
executables, sample input and output files. Reference: EGG-2582, University
of Cincinnati (January 1990). Fortran 90 or Fortran 95 with Fortran 77
extensions; PC386, PC486, PC586, & PC686 (C00654/PC586/02).
This multidimensional, finite-difference heat conduction analysis code system from Oak Ridge National Laboratory, Oak Ridge, Tennessee, was updated with minor changes to facilitate installation. The readme file was modified, and the document was added to the distribution CD. There were no changes to source, executables, or data. HEATING can solve steady-state and/or transient heat conduction problems in one-, two-, or three-dimensional Cartesian, cylindrical, or spherical coordinates.
HEATING 7.3 includes some Fortran 90 features. HEATING 7.3 PC executables
were created using Microsoft Powerstation v4.0. HEATING7.3 for Unix and
requires the XLF 3.2 compiler. The package is transmitted on one CD-ROM
with a self-extracting, compressed Windows file and in a GNU compressed
tar file. The distribution files contain HEATING 7.2i and 7.3 source files
for both Unix and DOS, PC executables, script files, and sample cases.
Reference: ORNL/TM-12262 (February 1993; update to Chapter 4, September
1998). HEATING 7.2i: Fortran 77 and C; Unix Workstation or Mainframe or
486PC. HEATING 7.3: Fortran 90 486PC and IBM RS/6000 (P00199/MNYCP/04).
The Association of FZK-Euratom, Institut f. Reaktorsicherheit (IRS), Forschungszentrum Karlsruhe, Karlsruhe, Germany, and Obninsk Institute of Nuclear Power Engineering (INPE) Studgorodok Obninsk, Russia, through the OECD NEA Data Bank, Issy-les-Moulineaux, France, contributed the Intermediate Energy Activation File 2001. A complete activation data library IEAF-2001 was developed in standard ENDF-6 format with neutron-induced activation cross sections for 679 target nuclides from Z=1 (hydrogen) to Z=84 (polonium) and incident neutron energies up to 150 MeV. Using the NJOY processing code, an IEAF-2001 working library was prepared in a 256 energy group structure for enabling activation analyses of the IFMIF D-Li neutron source. This library was applied to the activation analysis of the IFMIF high flux test module (HFTM) using the recent ALARA activation code which is capable of handling the variety of reaction channels open in the energy domain above 20 MeV. The IEAF-2001 activation library was thus shown to be suitable for activation analyses in fusion technology and intermediate energy applications such as the IFMIF D-Li neutron source.
The total number of reaction channels with activation cross-section
data is 134,431. The European Activation File EAF-99 served as basis for
the activation data below 20 MeV neutron energy. Threshold reaction cross-sections
were evaluated on the basis of geometry dependent hybrid exciton and evaporation
models using a modified version of the ALICE code. A groupwise IEAF-2001
data library has been prepared for 256 energy groups in GENDF data format.
The IEAF-2001 CD contains both the pointwise ENDF and the groupwise GENDF
data files. These data can be processed with standard ENDF processing tools
such as NJOY. No Fortran source codes are included. The package is transmitted
on a CD-ROM containing the data files in a PkWare® self-extracting
WINDOWS® executable and a tar file for Unix applications. References:
EFF-DOC-803 (November 2001), EFF-DOC-804 (November 2001), and IRS-Nr. 10/01
- FUSION-Nr. 179 (September 2001). Unix workstations or Windows PC (D00217/MNYCP/00).
Oak Ridge National Laboratory, Oak Ridge, Tennessee, updated this nuclear
data package with data for additional nuclides. The package was developed
in support of the Nuclear Criticality Safety Program (NCSP) to develop
a comprehensive criticality safety program to maintain and ensure subcriticality
of nuclear systems located throughout the DOE complex. These data are provided
in ACER format for use with MCNP and in AMPX master library format for
use with KENO in the 238-group structure. Users should be advised that
the data are preliminary. Extensive benchmark testing has not yet been
performed. Data are included for Al-27, O-16, Si-28, Si-29, Si-30, U-233
and U-235. The package contains no retrieval codes. (M00002/MNYCP/01).
Materials and Radiation Effects
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 identified thus far. Links to the package abstracts are embedded into the WWW version of the RSICC Newsletter. Feedback from our Newsletter community is very valuable so please direct your comments and/or suggestions to PDC@ORNL.GOV.
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 table.
The 11th International Conference on Fusion Reactor Materials (ICFRM-11)
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.
Advances in Nuclear Fuel Management III - Call For Papers
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 ociety 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 www.ans.org/meetings.
The Americas Nuclear Energy Symposium (ANES 2002) will be in Miami, Florida, October 16-18, 2002, and will provide a forum for a hemispheric discussion and exchange focused on issues related to the future of nuclear energy in the Americas. ANES 2002 will build on the success of both ANES 2000 and the ANS Meeting of the Americas in 1998. The program promises to deliver interactive discussions, workshops, case studies, industry updates, and an exposition by leaders in the nuclear industry. One-page summaries of proposed papers may be sent to firstname.lastname@example.org. The American Nuclear Society is responsible for the technical program.
Notification of abstract acceptance will be sent by August 16, 2002.
Full written papers are due by October 16, 2002. Papers will be published
on CD after the event. Visit our website at http://www.anes2002.org
for more information on the symposium.
We are pleased to announce the CALL FOR PAPERS for the "2003 International Congress on Advanced Nuclear Power Plants" (ICAPP '03) which will be held in Cordoba, Spain, May 4-7, 2003, at the Congress Palais. Please make note of the October 15, 2002 deadline for abstracts.
Following the highly successful ICAPP '02 meeting held in Hollywood, Florida, this international congress will bring together international experts of the nuclear industry involved in the operation, development, building, regulation and research related to nuclear power plants. The conference is sponsored by the leading nuclear societies of Europe, Asia and USA.
The program will cover the full spectrum of nuclear power plant issues
from design, deployment and construction of plants to research and development
of future designs and advanced systems. The program is expected to cover
lessons learned from power, research and demonstration reactors from over
50 years of experience with operation and maintenance, structures, materials,
technical specifications, human factors, system design and reliability.
You may visit the ICAPP '03 website at www.ans.org/goto/icapp03
for updated information on the congress and to download a copy of the Call
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.
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 814-865-0039, email@example.com
or Bernadette Kirk 865-574-6176, firstname.lastname@example.org.
announcement on SCALE 5 workshop, that will be held immediately before
the M&C Conference.)
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 understanding of the code system.
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 classes are scheduled March 17-21, 2003, and September 8-12, 2003, both in Richland, Washington. The class will focus on the use of the visual editor, with an overview of MCNP. The fifth day is optional and will focus on using the Visual Editor and MCNP to do some example problems.
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
this class can be located at:
or by contacting Randy Schwarz (email email@example.com).
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 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
SC2002 will be held November 16-22, 2002, in Baltimore, Maryland,
will offer leading edge technology with stunning exhibits and faster-than-lightning
computer systems. Academic and industry researchers draw on this conference
as an arena to feature high-performance computing and networking discoveries
designed to transform terabytes of data into insights about the origins
of our universe, our own genetic makeup, the condition of our planet and
its ecosystems, and how to keep ourselves safe in a dangerous world. For
more information, see http://www.sc2002.org/.
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 with a long history.
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
For more information, please visit the web site at: http://www.bioassay.org/2002/.
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 $1800 (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).
The Forum will be held March 25-26, 2003, at the Crystal Gateway Marriott Hotel, which is conveniently located in Arlington, Virginia.
The Program Committee is now accepting presentation proposals for the Software Quality Forum 2003 (SQF 2003). The Forum offers an exciting opportunity for software professionals in the Department of Energy (DOE), other government agencies, private industry, and academia to share their knowledge about trends and technologies in the acquisition, development, support, and management of software intensive systems. Well-known keynote speakers, tutorials on key Forum topics, a showcase for high-visibility IT projects using cutting-edge technologies, and a vendor exhibit area are included in the program.
This is a tri-annual event sponsored by the Software Quality Assurance Subcommittee (SQAS) of the Quality Managers within the DOE Nuclear Weapons Complex. The 2003 Forum is co-hosted by the DOE Office of the Chief Information Officer and the National Nuclear Security Administration, Office of Advanced Simulation and Computing within the Office of Defense Programs.
Please note the following due dates: submission of proposal, abstract, and biography is November 15, 2002, notification of acceptance is December 31, 2002, final abstract is January 15, 2003, and electronic and paper versions of presentation is due February 1, 2003.
For more information, visit the web site http://cio.doe.gov/sqas.
Look for the "Forum 2003" heading on the left side of the home page. There
will be a website devoted to the SQF 2003 in a week or so, which will be
linked from the above website. If you have questions, send email to Kathleen
Canal at kathleen.canal@ hq.doe.gov.
If interested in submitting a presentation proposal, please contact Brenda
Coblentz, Program Committee Chair, at
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 email@example.com. nrc.ca, url www.irs.inms.nrc.ca/inms/irs/BEAM/beamhome.html).
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 www.aocrp-1.com).
Computed Tomography: Patient Dose Symposium, Nov. 6-7, 2002, Arlington, VA. Contact: William Beckner (tel 301-657-2652, fax 301-907-8768, url http://www.ncrp.com).
The 48th Annual Radiobioassay and Radiochemical Measurements Conference, Nov. 11-15, 2002, Knoxville, Tennessee. Contact: Tom Rucker (tel 865-481-2993, email email@example.com 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 Dosimetry@iaea.org, url www.iaea.org/worldatom/ Meetings/2002/infcn96.shtml).
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 firstname.lastname@example.org) or Bernadette Kirk (tel 814-865-0039, email email@example.com, url ttp://meetingsandconferences.com/MC2003/index.html).
International Conference on Supercomputing in Nuclear Applications, SNA 2003, Sept. 22-24, 2003, Paris, France. Organizers: CEA, SFANS, co-organizer: OECD/NEA. (email SNAfirstname.lastname@example.org, url http://SNA-2003.cea.fr).
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 email@example.com, url http://rpd.ans.org/nfm.htm).
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 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). We now include medical physics in addition to material science, radiation dosimetry, radiation safety, reactor dynamics, reactor safeguards, risk assessment, waste management, fuel cycle, fusion and plasmas, high energy particle transport, and shielding. This early announcement is made as a service to the nuclear sciences community. Copies of the literature are not distributed by RSICC. They may generally be obtained from the author or from a documentation center such as the National Technical Information Service (NTIS), Department of Commerce, Springfield, Virginia 22161. For literature listed as available from INIS contact INIS Clearinghouse, International Atomic Energy Agency, P.O. Box 100, A-1400 Vienna.
KEK-MSL Report 2000 . . . KEK-MSL Report 2000 . . . 2000 . . . High Energy Accelerator Research Organization, Ibaraki-ken, Japan.
KEK Report 2001-2 . . . Simulation Study of Photoelectron Motion in Solenoid Field. . . . Wang, L.; Fukuma, H.; Ohmi, K. . . . May 2001 . . . High Energy Accelerator Research Organization, Ibaraki-ken, Japan.
KEK Report 2001-21 . . . On the Limit of Acceptable Beam Loss for a High Intensity Proton Ring. . . . Yamane, I. . . . February 2002 . . . High Energy Accelerator Research Organization, Ibaraki-ken, Japan.
J. Nucl. Mater., 304, 1-7 . . . Helium Bubble Formation in 800 MeV Proton-Irradiated 304L Stainless Steel and Alloy 718 During Post-Irradiation Annealing. . . . Chen, J.; Romanzetti, S.; Sommer, W.F.; Ullmaier, H. . . . July 2002 . . . Institut fur Festkorperforschung und Projekt, Julich, Germany; INFM Unit of Ancona, Ancona, Italy; Los Alamos National Laboratory, Los Alamos, NM.
J. Nucl. Mater., 304, 8-14 . . . Influence of Dilute Silicon Addition on the Oxidation Resistance and Tensile Properties of Modified Zircaloy-4. . . . Hong, H.S.; Kim, S.J.; Lee, K.S. . . . July 2002 . . . Hanyang University, Seoul, South Korea.
J. Nucl. Mater., 304, 15-20 . . . Sputtering and Ion-Induced Electron Emission of Graphite Under High-Dose Nitrogen Bombardment. . . . Borisov, A.M.; Eckstein, W.; Mashkova, E.S. . . . July 2002 . . . Moscow State University, Moscow, Russia; Max-Planck-Institut fur Plasmaphysik, Garching, Germany.
J. Nucl. Mater., 304, 21-28 . . . Oxidation Behavior of Modified SUS316 (PNC316) Stainless Steel Under Low Oxygen Partial Pressure. . . . Sato, I. et al. . . . July 2002 . . . Japan Nuclear Fuel Cycle Development Institute, Ibaraki-ken, Japan; Kyushu University, Fukuoka, Japan.
J. Nucl. Mater., 304, 29-49 . . . Modelling Intragranular Fission Gas Release in Irradiation of Sintered LWR UO2 Fuel. . . . Losonen, P. . . . July 2002 . . . no corp. author.
J. Nucl. Mater., 304, 50-55 . . . Lithium Reduction of Americium Dioxide to Generate Americium Metal. . . . Usami, T. et al. . . . July 2002 . . . Central Research Institute of Electric Power Industry, Tokyo, Japan; AEA Technology, Oxon, UK.
J. Nucl. Mater., 304, 56-62 . . . Crystal Chemistry of Uranium (V) and Plutonium (IV) in a Titanate Ceramic for Disposition of Surplus Fissile Material. . . . Fortner, J.A.; Kropf, A.J.; Finch, R.J.; Bakel, A.J.; Hash, M.C.; Chamberlain, D.B. . . . July 2002 . . . Argonne National Laboratory, Argonne, IL.
J. Nucl. Mater., 304, 63-72 . . . Phase Relations in the Quaternary Fe-Pu-U-Zr System. . . . Nakamura, K.; Ogata, T.; Kurata, M.; Yokoo, T.; Mignanelli, M. . . . July 2002 . . . Central Research Institute of Electric Power Industry, Tokyo, Japan; AEA Technology, Oxen, UK.
J. Nucl. Mater., 304, 73-82 . . . Thermally and Plastically Induced Residual Strains in Textured Zircaloy-2 Plate. . . . Holden, T.M.; Root, J.H.; Holt, R.A.; Turner, P.A. . . . July 2002 . . . National Research Council of Canada, Ontario, Canada; Atomic Energy of Canada, Ontario, Canada.
J. Nucl. Mater., 304, 83-85 . . . Irradiation Performance of Polytetrafluorethylene (Teflon) in a Mixed Fast Neutron and Gamma Radiation Field. . . . Harling, O.K.; Kohse, G.E.; Riley, K.J. . . . July 2002 . . . MIT, Cambridge, MA.
J. Nucl. Mater., 304, 87-95 . . . Structural Features and Properties of Lead-Iron-Phosphate Nuclear Wasteforms. . . . Reis, S.T.; Karabulut, M.; Day, D.E. . . . August 2002 . . . University of Missouri-Rolla, Rolla, MO; University of Kafkas, Kars, Turkey.
J. Nucl. Mater., 304, 96-106 . . . Solubility of Hydrogen in Zircaloy-4: Irradiation Induced Increase and Thermal Recovery. . . . Vizcaino, P.; Banchik, A.D.; Abriata, J.P. . . . July 2002 . . . Comision Nacional de Energia Atomica, Buenos Aires, Argentina.
J. Nucl. Mater., 304, 107-116 . . . Depletion of Fe and Cr Within Precipitates During Zircaloy-4 Oxidation. . . . Baek, J.H.; Jeong, Y.H. . . . July 2002 . . . Korea Atomic Energy Research Institute, Daejeon, South Korea.
J. Nucl. Mater., 304, 117-128 . . . Kinetics of Nucleation and Coarsening of Colloids and Voids in Crystals Under Irradiation. . . . Dubinko, V.I.; Turkin, A.A.; Vainshtein, D.I.; den Hartog, H.W. . . . August 2002 . . . Kharkov Institute of Physics and Technology, Kharkov, Ukraine; University of Groningen, Groningen, The Netherlands.
J. Nucl. Mater., 304, 129-133 . . . Powder Synthesis and Sintering of High Density Thoria-Yttria Ceramics. . . . Cosentino, I.C.; Muccillo, R. . . . August 2002 . . . Instituto de Pesquisas Energeticas e Nucleares, S. Paulo, Brazil.
J. Nucl. Mater., 304, 134-138 . . . Determination of Fe and Cr Content in Alpha-Zr Solid Solution of Zircaloy-4 with Different Heat-Treated States. . . . Li, C. et al. . . . August 2002 . . . Nuclear Power Institute of China, Sichuan, China; Sichuan University, Sichuan, China.
J. Nucl. Mater., 304, 139-152 . . . Effect of Chromium, Tungsten, Tantalum, and Boron on Mechanical Properties of 5-9Cr-WVTaB Steels. . . . Klueh, R.L.; Alexander, D.J.; Sokolov, M.A. . . . August 2002 . . . Oak Ridge National Laboratory, Oak Ridge, TN; Los Alamos National Laboratory, Los Alamos, NM.
J. Nucl. Mater., 304, 153-160 . . . Use of High Energy Ions for the Mechanistic Study of Irradiation Embrittlement in Pressure Vessel Steels Using Fe-Cu Model Alloys. . . . Morita, K.; Ishono, S.; Tobita, T.; Chimi, Y.; Ishikawa, N.; Iwase, A. . . . August 2002 . . . Tokai University, Kanagawa-Ken, Japan; JAERI, Ibaraki-ken, Japan.
J. Nucl. Mater., 304, 161-175 . . . Thermodynamic Assessment of the Uranium-Oxygen System. . . . Gueneau, C.; Baichi, M.; Labroche, D.; Chatillon, C.; Sundman, B. . . . August 2002 . . . DEN/DPC/SCPA, Gif-sur-Yvette, France; DEN/DEC/SECI, Grenoble, France; DEN/DTE/SIM, Pierrelatte, France; Laboratoire de Thermodynamique et de Physico-Chimie Metallurgiques, St. Martin d'Heres, France; Royal Institute of Technology, Stockholm, Sweden.
J. Nucl. Mater., 304, 176-181 . . . Mass-Spectrometric Determination of Oxygen Potential of Hypostoichiometric Urania-Yttria Solid Solution. . . . Nakajima, K.; Ohmichi, T.; Arai, Y. . . . August 2002 . . . JAERI, Ibaraki-ken, Japan; Research Organization for Information Science and Technology, Ibaraki-ken, Japan.
J. Nucl. Mater., 304, 182-188 . . . Aqueous Corrosion of Aluminum-Based Nuclear Fuel. . . . Kaminski, M.D.; Goldberg, M.M. . . . August 2002 . . . Argonne National Laboratory, Argonne, IL.
J. Nucl. Mater., 304, 189-203 . . . Delayed Hydride Cracking in Zr-2.5Nb Pressure Tube Material. . . . Singh, R.N. et al. . . . August 2002 . . . Bhabha Atomic Research Center, Mumbai, India; Vikram Sarabhai Bhavan, Mumbai, India; Indian Institute of Technology, Mumbai, India.
J. Nucl. Mater., 304, 204-211 . . . An Effective Method for Calculation of Diffusive Flow in Spherical Grains. . . . Hermansson, P.; Massih, A.R. . . . August 2002 . . . FOI, Linkoping, Sweden; Quantum Technologies, Uppsala, Sweden; Malmo University, Malmo, Sweden.
J. Nucl. Mater., 304, 212-220 . . . Molecular Aspects of the Beta-Decay in Tc Clusters. . . . Defranceschi, M.; Berthier, G. . . . August 2002 . . . CEA/DCC/DPE/SPCP, Gif-sur-Yvette, France; LETMEX, Nice, France.
J. Nucl. Mater., 304, 221-236 . . . Low-Temperature Irradiation Behavior of Uranium-Molybdenum Alloy Dispersion Fuel. . . . Meyer, M.K. et al. . . . August 2002.
J. Nucl. Mater., 304, 237-241 . . . Amorphization of MgAl2O4 Spinel Using 1.5 MeV Xe+ Ions Under Cryogenic Irradiation Conditions. . . . Sickafus, K.E.; Yu, N.; Nastasi, M. . . . August 2002 . . . Los Alamos National Laboratory, Los Alamos, NM.
J. Nucl. Mater., 304, 242-245 . . . Oxidation Behavior of U-10 wt% Mo Alloy in Air at 473-773 K. . . . Kang, K.H.; Kim, S.H.; Kwak, K.K.; Kim, C.K. . . . August 2002 . . . KAERI, Taejon, South Korea.
J. Nucl. Mater., 304, 246-248 . . . Phase Constitution and Steam Corrosion Resistance of Binary Zr-S Alloys. . . . Charquet, D. . . . August 2002 . . . CEZUS-Framatome, Ugine, France.
Med. Phys., 29, 1643-1650 . . . Effect of Radiographic Techniques (kVp and mAs) on Image Quality and Patient Doses in Digital Subtraction Angiography. . . . Gkanatsios, N.A.; Huda, W.; Peters, K.R. . . . August 2002 . . . University of Florida, Gainesville, FL; SUNY Upstate Medical University, Syracuse, NY.
Med. Phys., 29, 1651-1660 . . . Material-Specific Analysis Using Coherent-Scatter Imaging. . . . Batchelar, D.L.; Cunningham, I.A. . . . August 2002 . . . University of Western Ontario, Canada.
Med. Phys., 29, 1661-1669 . . . Pulsed-Microwave-Induced Thermoacoustic Tomography: Filtered Backprojection in a Circular Measurement Configuration. . . . Xu, M.; Wang, L.V. . . . August 2002 . . . Texas A&M University, College Station, TX.
Med. Phys., 29, 1670-1677 . . . Empirical Description and Monte Carlo Simulation of Fast Neutron Pencil Beams as Basis of a Treatment Planning System. . . . Bourhis-Martin, E. et al. . . . August 2002 . . . Universitatsklinikum, Essen, Germany; Universitats-Krankenhaus Eppendorf, Hamburg, Germany.
Med. Phys., 29, 1678-1686 . . . Dose Characterization in the Near-Source Region for Two High Dose Rate Brachytherapy Sources. . . . Wang, R.; Li, X.A. . . . August 2002 . . . University of Maryland, Baltimore, MD.
Med. Phys., 29, 1687-1692 . . . Evaluation of Kodak EDR2 Film for Dose Verification of Intensity Modulated Radiation Therapy Delivered by a Static Multileaf Collimator. . . . Zhu, X.R. et al. . . . August 2002 . . . Medical College of Wisconsin, Milwaukee, WI.
Med. Phys., 29, 1693-1697 . . . Output Variation from an Intensity Modulating Dynamic Collimator. . . .Hossain, M.; Houser, C.J.; Galvin, J.M. . . . August 2002 . . . Thomas Jefferson University, Philadelphia, PA.
Med. Phys., 29, 1698-1709 . . . Interation of Digital Fluoroscopy with CT-Based Radiation Therapy Planning of Lung Tumors. . . . Ruschin, M.; Sixel, K.E. . . . August 2002 . . . University of Toronto and Toronto Sunnybrook Regional Cancer Center, Ontario, Canada.
Med. Phys., 29, 1710-1715 . . . A Preliminary Comparative Study of Two Treatment Planning Systems Developed for Boron Neutron Capture Therapy: MacNCTPlan and SERA. . . . Wojnecki, C.; Green, S. . . . August 2002 . . . JRC of European Commission, Petten, The Netherlands; University Hospital Birmingham NHS Trust, Birmingham, United Kingdom.
Med. Phys., 29, 1716-1718 . . . Aliasing Effects in Digital Images of Line-Pair Phantoms. . . . Albert, M. et al. . . . August 2002 . . . Thomas Jefferson University, Philadelphia, PA.
Med. Phys., 29, 1719-1728 . . . Peak Velocity Determination Using Fast Fourier Velocity Encoding with Minimal Spatial Encoding. . . . Galea, D.; Lauzon, M.L.; Drangova, M. . . . August 2002 . . . University of Western Ontario, Ontario, Canada; University of Calgary, Alberta, Canada.
Med. Phys., 29, 1729-1738 . . . Dosimetric Characteristics of Novalis Shaped Beam Surgery Unit. . . . Yin, F-F. et al. . . . August 2002 . . . Henry Ford Hospital, Detroit, MI.
Med. Phys., 29, 1739-1751 . . . A Dual-Energy Subtraction Technique for Microcalcification Imaging in Digital Mammography - A Signal-to-Noise Analysis. . . . Lemacks, M.R. et al. . . . August 2002 . . . University of Texas M.D. Anderson Cancer Center, Houston, TX.
Med. Phys., 29, 1752-1758 . . . A Dosimetric Comparison of Two Multileaf Collimator Designs. . . . Killoran, J.H.; Giraud, J.Y.; Chin, L. . . . August 2002 . . . Harvard Medical School, Boston, MA; CHU de Grenoble, Grenoble, France.
Med. Phys., 29, 1759-1771 . . . Distortion Correction for X-Ray Image Intensifiers: Local Unwarping Polynomials and RBF Neural Networks. . . . Cerveri, P.; Forlani, C.; Borghese, N.A.; Ferrigno, G. . . . August 2002 . . . Politecnico de Milano, Milano, Italy; University of Milano, Milano, Italy.
Med. Phys., 29, 1772-1780 . . . Interinstitutional Variations of Sensitometric Curves of Radiographic Dosimetric Films. . . . Bos, L.J. et al. . . . August 2002 . . . The Netherlands Cancer Institute, Amsterdam, The Netherlands; University of Patras, Patras, Greece; University of Arizona, Tucson, AZ.
Med. Phys., 29, 1781-1788 . . . Commissioning and Quality Assurance of an Optically Guided Three-Dimensional Ultrasound Target Localization System for Radiotherapy. . . . Tome, W.A.; Meeks, S.L.; Orton, N.P.; Bouchet, L.G.; Bova, F.J. . . . August 2002 . . . University of Wisconsin Medical School, Madison, WI; University of Iowa, Iowa City, IA; University of Florida, Gainesville, FL.
Med. Phys., 29, 1789-1796 . . . Spectral Reconstruction of High Energy Photon Beams for Kernel Based Dose Calculations. . . . ; Hinson, W.H.; Bourland, J.D. . . . August 2002 . . . Wake Forest University School of Medicine, Winston-Salem, NC.
Med. Phys., 29, 1797-1806 . . . Using a Tungsten Rollbar to Characterize the Source Spot of a Megavoltage Bremsstrahlung Linac. . . . Schach von Wittenau, A.E.; Logan, C.M.; Rikard, R.D. . . . August 2002 . . . Lawrence Livermore National Laboratory, Livermore, CA.
Med. Phys., 29, 1807-1822 . . . A Knowledge-Based Cone-Beam X-Ray CT Algorithm for Dynamic Volumetric Cardiac Imaging. . . . Wang, G.; Zhoa, S.; Heuscher, D. . . . August 2002 . . . University of Iowa, Iowa City, IA; University of Missouri, St. Louis, MO; Phillips Medical Systems, Cleveland, OH.
Med. Phys., 29, 1823-1831 . . . Exploring the Limits of Spatial Resolution in Radiation Dose Delivery. . . . Otto, K.; Clark, B.G.; Huntzinger, C. . . . August 2002 . . . University of British Columbia and BC Cancer Agency, British Columbia, Canada; Varian Medical Systems, Palo Alto, CA.
Med. Phys., 29, 1832-1838 . . . Effects of Constant Frequency Noise in Magnetic Resonance Imaging with Nonuniform K-Space Sampling. . . . Du, W.; Karczmar, G.S.; Pan, X. . . . August 2002 . . . University of Chicago, Chicago, IL.
Med. Phys., 29, 1839-1846 . . . Comparison of Three High-Resolution Digitizers for Radiochromic Film Dosimetry. . . . Gluckman, G.R.; Reinstein, L.E. . . . August 2002 . . . SUNY at Stony Brook, Stony Brook, NY.
Med. Phys., 29, 1847-1858 . . . IMRT Verification by Three-Dimensional Dose Reconstruction from Portal Beam Measurements. . . . Partridge, M.; Ebert, M.; Hesse, B-M. . . . August 2002 . . . DKFZ Heidelberg, Heidelberg, Germany.
Med. Phys., 29, 1859-1866 . . . Optimization of Ga-67 Imaging for Detection and Estimation Tasks: Dependence of Imaging Performance on Spectral Acquisition Parameters. . . . El Fakhri, G.; Moore, S.C.; Kijewski, M.F. . . . August 2002 . . . Harvard Medical School and Brigham and Women's Hospital, Boston, MA.
Med. Phys., 29, 1867-1880 . . . A Calibration Approach to Glandular Tissue Composition Estimation in Digital Mammography. . . .Kaufhold, J.; Thomas, J.A.; Eberhard, J.W.; Galbo, C.E.; Gonzalez Trotter, D.E. . . . August 2002 . . . General Electric Global Research Center, Niskayuna, NY; Uniformed Services University of the Health Sciences, Bethesda, MD.
Med. Phys., 29, 1881-1891 . . . Numerical Algorithms for Spatial Registration of Line Fiducials from Cross-Sectional Images. . . . Lee, S.; Fichtinger, G.; Chirikjian, G.S. . . . August 2002 . . . Johns Hopkins University, Baltimore, MD.
Med. Phys., 29, 1892-1912 . . . Practical Aspects of Functional MRI (NMR Task Group #8). . . . Price, R.R.; Allison, J.; Massoth, R.J.; Clarke, G.D.; Drost, D.J. . . . August 2002 . . . Vanderbilt University Medical Center, Nashville, TN; Medical X-Ray Center, Sioux Falls, SD; University of Texas Health Science Center, San Antonio, TX; St. Joseph's Health Centre, Ontario, Canada.
Med. Phys., 29, 1913-1915 . . . Medical Physicists Should Assume PACS Responsibilities. . . . Halama, J.R.; Huda, W. . . . August 2002 . . . Loyola University Medical Center, Maywood, IL; SUNY Upstate Medical University, Syracuse, NY.
Med. Phys., 29, 1916 . . . Parker Weights Revisited. . . . Harpen, M.D. . . . August 2002 . . . University of South Alabama, Mobile, AL.
Med. Phys., 29, 1917-1918 . . . Let's Abandon Geometry Factors Other Than That of a Point Source in Brachytherapy Dosimetry. . . . Meli, J.A. . . . August 2002 . . . St. Vincent's Medical Center, Bridgeport, CT.
Med. Phys., 29, 1919-1920 . . . Comment on "Let's Abandon Geometry Factors Other Than That of a Point Source in Brachytherapy Dosimetry" . . . Rivard, M.J. et al. . . . August 2002 . . . Tufts-New England Medical Center, Boston MA; National Institute of Standards and Technology, Gaithersburg, MD; University of Wisconsin, Madison, WI; Radiological Physics Center, Houston, TX; Thomas Jefferson University, Philadelphia, PA; Yale University, New Haven, CT; Washington University, St. Louis, MO.
Med. Phys., 29, 1921 . . . Studies on Developments of Imaging and Analytical Methods and Evaluations of Properties Mainly on Image Quality in MRI (in Japanese). . . . Miyati, T. . . . August 2002 . . . Kanazawa University, Ishikawa, Japan.
Nucl. Eng. Design, 217, 225-236 . . . Creep Prediction of Concrete for Reactor Containment Structures. . . . Song, H-W.; Kim, S-H.; Byun, K-J.; Song, Y-C. . . . September 2002 . . . Yonsei University, Seoul, Republic of Korea; Korea Electric Power Research Institute, Taejon, Republic of Korea.
Nucl. Eng. Design, 217, 237-245 . . . PWSCC of Thermally Treated Alloy 600 Pulled from a Korean Plant. . . . Hwang, S.S.; Hur, D.H.; Han, J.H.; Kim, J.S. . . . September 2002 . . . KAERI, Daejeon, South Korea.
Nucl. Eng. Design, 217, 247-257 . . . Nuclear Cooling Tower Submitted to Shrinkage; Behaviour Under Weight and Wind. . . . Witasse, R.; Georgin, J.F.; Reynouard, J.M. . . . September 2002 . . . URGC-Structures, Villeurbanne, France.
Nucl. Eng. Design, 217, 259-266 . . . Elastoplastic Constitutive Model for Particle-Dispersed Composites Accounting for Interfacial Damage. . . . Chang, H. . . . September 2002 . . . Tsinghua University, Beijing, China.
Nucl. Eng. Design, 217, 267-281 . . . Flow Structure and Bubble Characteristics of Steam-Water Two-Phase Flow in a Large-Diameter Pipe. . . . Yoneda, K.; Yasuo, A.; Okawa, T. . . . September 2002 . . . Central Research Institute of Electric Power Industry, Tokyo, Japan; Osaka University, Osaka, Japan.
Nucl. Eng. Design, 217, 283-288 . . . Application of a Fiber Optic Grating Strain Sensor for the Measurement of Strain Under Irradiation Environment. . . . Kaji, Y. et al. . . . September 2002 . . . JAERI, Ibaraki-ken, Japan.
Nucl. Technol., 139, 91-126 . . . Investigation of the Effect of Fixed Absorbers on the Reactivity of PWR Spent Nuclear Fuel for Burnup Credit. . . . Wagner, J.C.; Sanders, C.E. . . . August 2002 . . . Oak Ridge National Laboratory, Oak Ridge, TN.
Nucl. Technol., 139, 127-144 . . . Fuel-Coolant Interactions: Visualization and Mixing Measurements. . . . Loewen, E.P.; Bonazza, R.; Corradini, M.L.; Johannesen, R.E. . . . August 2002 . . . Idaho National Engineering and Environmental Laboratory, Idaho Falls, ID; University of Wisconsin, Madison, WI.
Nucl. Technol., 139, 145-155 . . . Transport Characteristics of Selected Pressurized Water Reactor Loca-Generated Debris. . . . Maji, A.K. et al. . . . August 2002 . . . University of New Mexico, Albuquerque, NM; Los Alamos National Laboratory, Los Alamos, NM.
Nucl. Technol., 139, 156-166 . . . Building Up an On-Line Plant Information System for the Emergency Response Center of the Hungarian Nuclear Safety Directorate. . . . Vegh, J. et al. . . . August 2002 . . . KFKI Atomic Energy Research Institute, Budapest, Hungary; Hungarian Atomic Energy Authority, Budapest, Hungary.
Nucl. Technol., 139, 175-182 . . . Startup of the Fission Converter Epithermal Neutron Irradiation Facility at the MIT Reactor. . . . Neuton, Jr., T.H.; Riley, K.J.; Binns, P.J.; Kohse, G.E.; Hu, L-W.; Harling, O.K. . . . August 2002 . . . MIT, Cambridge, MA.