LA GRANGE PARK, IL, January 10, 2002--Energy Secretary Spencer Abraham's endorsement of Yucca Mountain as a suitable repository for spent nuclear fuel and high-level nuclear waste is a giant step toward solving one of the most controversial issues involving nuclear energy, says the American Nuclear Society.
"We have high confidence that Yucca Mountain is a suitable site, and we applaud the Department of Energy's recommendation to proceed with the next stage of repository development, the application of a license for repository construction," said ANS Vice President/President-Elect Harold B. Ray. "The pre-closure and post-closure assessments of Yucca Mountain convince us that the combination of site and design features provide public health protection with a considerable margin of safety."
Following the adoption of the Nuclear Waste Policy Act of 1982, DOE was directed to find a site for disposing of highly radioactive materials. Many scientists have concluded that storing such material deep underground is the safest method.
The Yucca Mountain site, located about 90 miles northwest of Las Vegas, NV., is situated in a mountain range with a unique combination of rock characteristics and an extremely deep water table (800 to 1,000 feet below the level of the repository). It has undergone years of study by scientists, engineers and other nuclear experts. One such study was the Yucca Mountain Preliminary Site Suitability Evaluation (PSSE), which incorporated the most recent data from field and laboratory experiments, and examined many alternative models that have never before been explored.
Work performed by the DOE, national laboratories and other government agencies such as the U.S. Geological Survey and the Environmental Protection Agency provided an impressive comprehensive collection of interdisciplinary studies and reports. These studies concluded that the Yucca Mountain site is well suited to become the nation's first geological repository.
"We're confident that the DOE has selected and characterized a site that, with appropriate engineering design and operation, can meet with high confidence the regulatory standard for public health and safety," said Ray. "The PSSE shows that the site can meet the post-closure standard, and the analyses indicate that pre-closure health and safety protection are more than adequate."
ANS' confidence on the Yucca Mountain site is based on several factors, including:
--The project has demonstrated that the natural features of Yucca Mountain contribute very significantly to public health protection;
--The project has adopted a highly robust engineered barrier system employing multiple, independent barriers to provide long-term confinement of radionuclides; and
--DOE and the Nuclear Regulatory Commission will continue to conduct additional research and monitoring activities over the next several decades to further bolster confidence in the safety of the repository.
"We applaud the DOE for conducting such a credible
interdisciplinary analysis demonstrating suitability of the Yucca Mountain
site for this nation's high-level geological repository, and we are prepared
to contribute to the next step of Yucca Mountain," said Ray. "It's clear
the time has come for the administration to prepare a license application
to the NRC for permission to construct and operate Yucca Mountain. This
is an important step for the future of nuclear energy."
ANS News Release
Dr. Theodore U. Marston, Vice President and Chief Nuclear Officer of EPRI located in Palo Alto, CA, wrote Brandon Bailey in response to his article "U.S. Favors Plan to Store Nuclear Waste in Nevada" published January 11, 2002, in the San Jose Mercury News.
Dear Mr. Bailey:
I would like to congratulate you on your well-balanced article on the Nuclear Waste Repository proposal. This is a very controversial topic and the public requires objective reporting so they can develop their own opinions on the subject. One fact that was not included in your article is that the proposed repository is located on the southwest boundary of the Nevada Test Site. Within a distance of 25 to 30 miles from Yucca Mountain most of the 828 underground nuclear tests were conducted. A number of the weapons tests were conducted deep in the ground at or near the water table. It is not feasible to remediate the Nevada Test Site. In contrast, the repository is located about a thousand feet above the water table.
I believe the public has the perception that Yucca Mountain is located in a pristine desert area, rather than in close proximity to where we have already impacted the ground with our nation's nuclear testing program. The addition of the used nuclear fuel in this region will have infinitesimal effect on the habitability of this area for future generations.
Thank you for your time and attention.
Four U.S. Nuclear Regulatory Commission (NRC) software packages which were transferred from the Energy Science and Technology Software Center, Oak Ridge, Tennessee to RSICC were incorporated into the RSICC computer code collection. Please browse the computer code abstracts available at RSICC's www site for more information on these packages.
PSR-437/ORSMAC (U.S. distribution only)
A new package and a newly frozen package were added to the computer code software and data collection.
Oak Ridge National Laboratory, Oak Ridge,
Tennessee, contributed this rapid PC-based tool for estimating pertinent
information needed to guide response team activities and help characterize
some types of nuclear criticality accidents. The concept uses a series
of sliding graphs that function similarly to a slide rule. This tool was
developed with the promise that visual demonstration of trends (e.g., dose
versus time or distance) are helpful to response personnel. The SlideRule
provides rapid assessments for direct radiation approximations and is useful
for solving for parameters that are dependent upon independent specific
parameters such as variable shielding, distances, and anticipated time
related radiation doses to personnel. The SlideRule is designed to provide
estimates of the following:
Oak Ridge National Laboratory, Oak Ridge, Tennessee, contributed a newly frozen version of this code system for multilevel R-matrix fits to neutron and charged-particle cross-section data using Bayes' equations. SAMMY-M6-Beta, release December 2001, differs from previous versions (M5) primarily in that charged particles can be used for both incident and exit channels. The earlier release (M5) did not properly treat incident charged particles, although charged-particle final states were properly treated. SAMMY can now be used to analyze, for example, (n,alpha) or (alpha,n) reactions in addition to previously available options: transmission, elastic (both angle-integrated and differential), fission, inelastic, capture, and absorption cross sections, eta, self-indication, and certain types of integral data. Angle-differential reaction cross sections can also be treated in M6-beta.
Users should be aware that Version M6-Beta is essentially a pre-release of version M6. In order to make the incident-charged-particle version available as soon as possible, no attempt has been made to complete the update of the documentation (users' manual). Though "old" features of the code, and the new incident-charged-particle capability, have been thoroughly tested prior to this release, implementation is in preliminary stages.
The included PC executables were created on a Dell Dimension 4100 operating under Windows 2000 with Compaq Visual Fortran Professional Edition 6.5. All Unix systems require a Fortran compiler to create executables. SAMMY-M6-Beta was tested at RSICC on the following machines:
IBM RS/6000 Model 270 AIX 4.3.3 with XLF
7.1 and XLC 4.4
The package is transmitted on a CD with both
Unix and Windows distribution files. The Unix tar file contains source
codes, scripts, tutorials, and test cases for Unix and Linux users. The
self-extracting compressed Windows file contains source codes, executables,
batch files, and test cases for Windows PC users. Reference: ORNL/TM-9179/R5
(October 2000). Fortran; DEC Alpha (Unix and VMS), IBM RS/6000, SUN, HP,
Workshop/Tutorial (tentative) on AMPX-2000, the latest version of the AMPX cross-section processing system that is developed and maintained by the Oak Ridge National Laboratory (ORNL). AMPX-2000 processes nuclear data evaluations that conform to the Evaluated Nuclear Data File (ENDF/B) format specifications. AMPX-2000 has the capability to process ENDF/B formats through Version VI and generate continuous-energy or multigroup cross-section libraries for neutron and/or photon transport. The objective of the workshop is to introduce new and experienced users to AMPX-2000. The workshop consists of classroom instruction provided by the AMPX code developers with an emphasis on use of the code system to process nuclear data evaluations. The workshop will also provide the participants with the opportunity to use AMPX to process nuclear data evaluations. Upon completion of the workshop, participants will have an understanding of the code system and be able to use AMPX to process ENDF/B evaluations and generate cross-section data for use in radiation transport codes. The proposed Agenda for a 5-day Workshop/Tutorial follows:
Day 1 - The first day will provide an introduction to ENDF/B formats and concepts associated with cross-section data. Followed by an overview of the AMPX-2000 code system that will include a discussion of the modular design philosophy and special features associated with the code system. The history of its sponsorship, major releases, etc., will be covered. In addition, a comprehensive overview of the processing capabilities will be provided. Differences and similarities to the NJOY processing system will be reviewed as appropriate. The remaining part of the first day will be devoted to a description of the AMPX modules and procedures that are used to generate continuous-energy cross sections from ENDF/B evaluations. In addition, the AMPX modules and procedures for processing the ENDF/B collision kinematics data will be described in detail.
Day 2 - Classroom instruction for the second day will focus on the modules and procedures that are used to produce multigroup neutron and photon cross-section libraries. The morning session will emphasize the AMPX modules that relate to producing multigroup data (e.g., generating weighting spectra, resonance-parameter processing, thermal-data processing, etc.). Workshop participants will gain familiarity with the different types of data that are used to provide a multigroup dataset for transport calculations. The afternoon session will be devoted to "hands-on" exercises that emphasize the course material from the first two days of instruction. Participants will have the opportunity to prepare input for producing continuous-energy and multigroup data using AMPX-2000.
Day 3 - The third day will begin with a review of the classroom exercises from Day Two followed by additional discussions on multigroup library processing as needed. New AMPX capabilities for generating probability tables and covariance matrices will be discussed in the morning session. The afternoon session will be devoted to additional classroom exercises related to generating continuous-energy and multigroup data. In addition, workshop participants will have the opportunity to generate probability tables and process ENDF/B uncertainty data with AMPX-2000.
Day 4 - The fourth day will begin with a review of the sample problems of the preceding afternoon session followed by classroom instruction for the various resonance self-shielding treatments that are provided in the AMPX system. The material will build upon the information presented on Day Two and include discussions of modules and procedures that must be used to prepare the appropriate data to be used in the treatments. The afternoon session will provide classroom exercises that make use of the course material presented in the morning session.
Day 5 - The fifth day will provide a review
of the problems investigated on Day Four. A discussion of various AMPX-2000
utility modules will be provided. AMPX-2000 produces data in a wide variety
of formats and has the capability to interface with the NJOY code system.
The material covered on Day Five will focus on the utility modules that
are needed to perform specialized data manipulation tasks (e.g., convert
data between NJOY and AMPX, compare data libraries, constructing and maintaining
a special energy boundary library for group structures, procedures for
constructing specialized 1/ES t functions, AMPX installation procedures
for different computer platforms, etc).
SCALE - Criticality, Shielding, Source Term
(tentative) - see the SCALE official Web page.
Tutorials on deterministic radiation transport
codes (tentatively end of 2002). The intention is to present recently developed
tools for modelling 3D problems, including automated mesh generation, (X-Y-Z),
(R-THETA-Z) and the visualization of the corresponding results to facilitate
interpretation and for improved documentation. Methods for 3D Sensitivity
Analysis / Uncertainty Analysis should also be demonstrated. The Data Bank
Executive Group has strongly recommended the development of such tools.
If you are interested in participating, please fill in the form.
Workshop on Computing Radiation Dosimetry
with embedded training course on MCNPX - Monte Carlo Code System for Multiparticle
& High Energy Applications, to be held at the Instituto Tecnologico
e Nuclear (ITN), Sacavem, Lisbon, Portugal, June 22-28, 2002. During the
weekend of June 22-23, a series of tutorial lectures will be held followed
by a daily tutorial lecture delivered by a senior expert on a subject related
to the MCNPX module(s) being taught that day. The MCNPX specific training
will be delivered June 24-28. If you are interested in participating, please
fill in the form.
MCNP - Introductory or Advanced Course including
MCNP5 Features, March 18-22 at the Imperial College, London.
PENELOPE (electron-photon transport) workshop
with tutorial (2002, RSICC, Oak Ridge, Tennessee, USA).
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 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, are invited to present a paper. Please visit the
to find out about IMUG, register for the meeting or request notification
of web updates. The website will be updated as additional information becomes
MCNP home page: http://www-xdiv.lanl.gov/XCI/PROJECTS/MCNP/index.html
LANL contact: firstname.lastname@example.org
European contact: email@example.com
The MCNP code developers will present several
classes in 2002 in the United States and two classes in Europe. The dates
for these classes are:
The introductory class is for people who have little or no experience with MCNP. The intermediate to advanced class will be held for people who have used MCNP and want to extend their knowledge and gain depth of understanding.
The classes will be based on MCNP5, 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, tallies, 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
Lead Teachers: Drs. John Hendricks, Gregg McKinney, Laurie Waters
Organizer: Hamilton Quality Consulting
More Information: http://mcnpxworkshops.com
MCNPX homepage: http://mcnpx.lanl.gov
MCNPX is the LANL all-particle, all-energy (eV-TeV) Monte Carlo transport code based on MCNP4C, LAHET, CEM, etc. MCNPX has been in active development since 1995, sponsored by the particle accelerator community. It has now become an accepted tool for a broad range of applications by nuclear engineers, physicists, and scientists. The MCNPX development effort has expanded the use of the Los Alamos tools to applications such as APT, waste transmutation, accelerator shielding and health physics, particle beam cancer therapy, space shielding and cosmic ray analysis, single event effects in semiconductors, radiography, and more detailed analysis of the effects of light and heavy ions in matter. In addition, the entire functionality of MCNP4C is retained. New variance reduction and data analysis techniques, many adapted from high energy accelerator methodologies, have also been added, such as the extensive 'mesh tally' capability which allows up to 3-d plotting of particle tracks, fluence and fluence-derived quantities, energy deposition, next event estimator generation contributions and particle sources.
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. Followup 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
DATE: May 6-10, 2002
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
Argonne National Laboratory will conduct a training course on the RESRAD family of risk assessment codes. This DOE-cosponsored workshop will be conducted on March 5-8, 2002. 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/ AgendaMarch2002.htm. Space is limited. For more information, please visit http://web.ead.anl.gov/resrad/training/MarchWrkshp.cfm, or contact Carole Ealy at 630-252-5677 or 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: http://rma-symposium.
engin.umich.edu/ or contact David K. Wehe at email@example.com.
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
Three five-day classes will be held in 2002: March 18-22, June 17-21, and September 9-13, all 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.
These classes 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:
or by contacting Randy Schwarz (email
SAMMY Workshop, Feb. 18-22, 2002, NEA, Paris, France. Contact: (Ali Nouri email firstname.lastname@example.org or Nancy Larson email email@example.com, url www.nea.fr/html/dbdata/sammy.htm).
SAMMY Workshop, Feb. 25-Mar. 4, 2002,
(exact schedule not yet available), Triste, Italy. Small part of the biannual
"Workshop on Nuclear Reaction Data and Nuclear Reactors: Physics, Design
and Safety," Feb 25-Mar. 28. (url
Hardened Electronics and Radiation Technology (HEART) Conference, Mar. 11-15, 2002, Monterey, CA. Contact: Thomas Stringer, chair (tel 719-599-1719, fax 719-599-1991).
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. 14-17, 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).
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 firstname.lastname@example.org, url http://drambuie.lanl.gov/ ~esh4/mcnp.htm; technical questions to Dick Olsher, 505-667-3364, email@example.com).
Symposium on Radiation Measurements and
Applications, May 21-23, 2002, Ann Arbor, MI. Contact: General Chair
David K. Wehe (tel 734-764-6215, email firstname.lastname@example.org,
Topical Meeting: Industrial Radiation and Radioisotope Measurement Applications IRRMA-V A Class IV Topical, June 9-14, 2002, Bologna, Italy, co-sponsored by the American Nuclear Society. Contact: Prof. Jorge Fernandez, Chair (e-mail: email@example.com).
ANS Annual Meeting, The Revival of the Nuclear Power Option, June 9-13, 2002, Hollywood, FL (url http://www.ans.org/).
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
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
2002 International Topical Meeting on Probabilistic Safety Assessment (PSA '02), Oct. 6-10, 2002, Detroit, MI. Contact: Rebecca Steinman (phone 734-930-7500, email email@example.com, url http://www-ners.engin.umich.edu/PSAConf/).
PHYSOR 2002, Oct. 7-10, 2002, Seoul, Korea, sponsored by the American Nuclear Society and hosted by the Korean Nuclear Society. Contact: Prof. Nam Zin Cho (tel +82-42-869-3819, fax +82-42-869-5859, email firstname.lastname@example.org, url http://physor2002.kaist.ac.kr).
First Asian and Oceanic Congress for Radiation Protection (AOCRP-1), Oct. 20-24, 2002, Seoul, Korea, sponsored by the Korean Association for Radiation Protection (KARP). Contact: Dr. Myung-Jae Song (tel +82-42-870-0202, fax +82-42-870-0269, email email@example.com, url 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 Dosimetry@iaea.org,
International Conference on Supercomputing
in Nuclear Applications, SNA 2003, September 22-24, 2003, Paris, France.
Organizers: CEA, SFANS, co-organizer: OECD/NEA. (email
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, 645-647 . . . On the Multiplication Factor and Reactivity Definitions for Subcritical Reactor Systems. . . .Gandini, A. . . . April 2002 . . . University of Rome, Italy.
Ann. Nucl. Energy, 29, 659-671 . . . A Transverse Buckling Based Method in Core Neutronics Models Equivalence. . . . Dall'Osso, A. . . . April 2002 . . . Framatome, Paris La Defense Cedex, France.
Ann. Nucl. Energy, 29, 673-683 . . . Energetics of Core Disruptive Accident for Different Fuels for a Medium Sized Fast Reactor. . . . Singh, O.P.; Harish, R. . . . April 2002 . . . Indira Gandhi Centre for Atomic Research, Tamil Nadu, India.
Ann. Nucl. Energy, 29, 685-700 . . . Neutron Transport in Two Interacting Slabs. . . . Williams, M.M.R. . . . April 2002.
Ann. Nucl. Energy, 29, 701-716 . . . Study on the Control Rod Interaction Effect in RSG Gas Multipurpose Reactor (MPR-30). . . . Hong, L.P.; Taryo, T.; Sembiring, T.M.; Hiroshi, S.; Yoshitaka, N. . . . April 2002 . . . Indonesia National Atomic Energy Agency, Tangerang, Indonesia; Tokyo Institute of Technology, Japan; NAIS, Co. Inc., Ibaraki-ken, Japan.
Ann. Nucl. Energy, 29, 717-750 . . . Applications of an Adjoint Monte Carlo Method to the Underground Migration of Radionuclides Over Large Scales. . . . Smidts, O.F. . . . April 2002 . . . Université Libre de Bruxelles, Brussels, Belgium.
Ann. Nucl. Energy, 29, 761-766 . . . An Upgraded Version of the AMEBA PWR. . . . Novelli, A. . . . April 2002 . . . Politecnico di Milano, Milan, Italy.
Ann. Nucl. Energy, 29, 767-775 . . . An Evaluation of the Americium Insertion in Uo2 Fuel. . . . Costa, A.L.; Pereira, C. . . . April 2002 . . . UFMG, Belo Horizonte, MG, Brazil.
J. Nucl. Mater., 299, 181-198 . . . A Review of the Thermophysical Properties of MOX and UO2 Fuels. . . . Carbajo, J.J.; Yoder, G.L.; Popov, S.G.; Ivanov, V.K. . . . December 2001 . . . Oak Ridge National Laboratory, Oak Ridge, TN; Kurchatov Institute, Moscow, Russian Federation.
J. Nucl. Mater., 299, 199-204 . . . New Aluminium-Rich Alkali Slag Matrix with Clay Minerals for Immobilizing Simulated Radioactive Sr and Cs Waste. . . . Qian, G.; Sun, D.D.; Tay, J.H. . . . April 2002 . . . Nanyang Technological University, Singapore.
J. Nucl. Mater., 299, 205-218 . . . Effect of Neutron Irradiation and Post-Irradiation Annealing on Microstructure and Mechanical Properties of OFHC-Copper. . . . Singh, B.N.; Edwards, D.J.; Toft, P. . . . December 2001 . . . Riso National Laboratory, Roskilde, Denmark; Pacific Northwest National Laboratory, Richland, WA.
J. Nucl. Mater., 299, 219-226 . . . The Structures of Two Sodium Uranyl Compounds Relevant to Nuclear Waste Disposal. . . . Li, Y.; Burns, P.C. . . . December 2001 . . . University of Notre Dame, IN.
J. Nucl. Mater., 299, 227-234 . . . Determination of the Defect Creation Mechanism in the Mono-Silicated Fluoroapatite. Disorder Modeling Under Repository Conditions. . . . Soulet, S.; Carpéna, J.; Chaumont, J.; Krupa, J-C.; Ruault, M-O. . . . December 2001 . . . CNRS-IN2P3, Orsay Campus, France; CEA-Cadarache, Saint-Paul-lez-Durance, France; Institut de Physique Nucleaire, Orsay, France.
J. Nucl. Mater., 29, 235-241 . . . A Working Hypothesis on Oxidation Kinetics of Zircaloy. . . . Yoo, H-I.; Koo, B-J.; Hong, J-O.; Hwang, I-S.; Jeong, Y-H. . . . December 2001 . . . Seoul National University, South Korea; Korea Atomic Energy Research Institute, Daejeon, South Korea.
J. Nucl. Mater., 299, 242-249 . . . Tritium Recovery From Nanostructured LiAlO2. . . . Carrera, L.M. et al. . . . December 2001 . . . Instituto Nacional de Investigaciones Nucleares, Mexico; Universidad Autónoma Metropolitana, Mexico.
J. Nucl. Mater., 299, 250-259 . . . Activation Energy of UO2 and UO2+x Sintering. . . . Dehaudt, Ph.; Bourgeois, L.; Chevrel, H. . . . December 2001 . . . Commissariat à l'Energie Atomique, Grenoble, France.
J. Nucl. Mater., 299, 260-263 . . . Characterization of the New Uranium-Nickel Alloy U10Ni13. . . . Perricone, A.; Noël, H. . . . December 2001 . . . Université de Rennes, France.
J. Nucl. Mater., 299, 264-266 . . . Gibbs Free Energy of Formation of Liquid Lanthanide-Bismuth Alloys . . . Sheng, J.; Yamana, H.; Moriyama, H. . . . December 2001 . . . Kyoto University Kumatori, Osaka, Japan.
J. Nucl. Mater., 299, 267-270 . . . Hardening of Fe-Cu Alloys at Elevated Temperatures by Electron and Neutron Irradiations. . . . Tobita, T.; Suzuki, M.; Iwase, A.; Aizawa, K. . . . December 2001 . . . JAERI, Ibaraki-ken, Japan.
J. Nucl. Mater., 299, 271-273 . . . High Temperature Application of EDTA Solvents for Iron Oxide Removal. . . . Hur, D.H.; Lee, E.H.; Choi, M.S.; Chung, H.S.; Kim, U.C. . . . December 2001 . . . Korea Atomic Energy Research Institute, Daejeon, South Korea; Korea Electric Power Research Institute, Daejeon, South Korea.
J. Nucl. Mater., 299, 274-276 . . . Development of CaF2 Special Refractory Components. . . . Ghosh, A.; Upadhyaya, D.D.; Prasad, R.; Suri, A.K. . . . December 2001 . . . Bhabha Atomic Research Centre, Mumbai, India.
Nucl. Technol., 136, 255-260 . . . Coupling Model: A Common-Cause-Failure Model with Consideration of Interpretation Uncertainties. . . . Kreuser, A.; Peschke, J. . . . December 2001 . . . Gesellschaft für Anlagen, Cologne, Germany.
Nucl. Technol., 136, 261-277 . . . Preliminary Frapcon-3Th Steady-State Fuel Analysis of ThO2 and UO2 Fuel Mixtures. . . . Loewen, E.P.; Wilson, R.D.; Hohorst, J.K.; Kumar, A.S. . . . December 2001 . . . Idaho National Engineering and Environmental Laboratory, Idaho Falls, ID; Cooper Nuclear Station, Brownville, NE; University of Missouri-Rolla, MO.
Nucl. Technol., 136, 278-291 . . . BWR Reload Strategy Based on Fixing Once-Burnt Fuel Between Cycles. . . . Maag, E.M.; Knott, D. . . . December 2001 . . . The Perry Nuclear Power Plant, Perry, OH.
Nucl. Technol., 136, 292-300 . . . Development and Application of the Reactor Coolant On-Line Leakage Evaluation Model for Pressurized Water Reactors. . . . Liang, T.K.S.; Hung, H-J.; Chang, C-J. . . . December 2001 . . . Institute of Nuclear Energy Research, Lung-Tan, Taiwan.
Nucl. Technol., 136, 301-314 . . . Investigating the Stability Characteristics of Natural-Circulation Boiling Water Reactors Using Root Loci of a Reduced-Order Model. . . . Zboray, R.; De Kruuijf, W.J.M.; Van Der Hagen, T.H.J.J.; Van Dam, H. . . . December 2001 . . . Delft University of Technology, JB Delft, The Netherlands.
Nucl. Technol., 136, 315-330 . . . Numerical Methodology to Evaluate Fast Reactor Sodium Combustion. . . . Yamaguchi, A.; Takata, T.; Okano, Y. . . . December 2001 . . . Japan Nuclear Cycle Development Institute, Ibaraki, Japan.
Nucl. Technol., 136, 342-353 . . . Separation of Actinides from LWR Spent Fuel Using Molten-Salt-Based Electrochemical Processes. . . .Karell, E.J. et al. . . . December 2001 . . . Argonne National Laboratory, Argonne, IL.
Nucl. Technol., 136, 354-366 . . . Influence of Finite Absorption of Radionuclides on Radionuclide Migration in an Engineered Barrier System. . . . Matsuo, T.; Yoshida, T. . . . December 2001 . . . Power and Industrial Systems Research and Development Laboratory, Ibaraki-ken, Japan; Hitachi Ltd., Ibaraki-ken, Japan.
Nucl. Technol., 136, 367-370 . . . The Influence of Lewis Acid/Base Chemistry on the Removal of Gallium by Volatility from Weapons-Grade Plutonium Dissolved in Molten Chlorides. . . . Williams, D.F.; Del Cul, G.D.; Toth, L.M.; Collins, E.D. . . . December 2001 . . . Oak Ridge National Laboratory, Oak Ridge, TN; Electrochemical Systems, Knoxville, TN.
Nucl. Technol., 137, 1-10 . . . Feasibility Study of a Proliferation-Resistant Fuel Form for Plutonium Recycling. . . . Aghara, S.K.; Beard, C.A. . . . January 2002 . . . University of Texas, Austin, TX.
Nucl. Technol., 137, 10-27 . . . IIST and BETHSY Counterpart Tests on PWR Total Loss-of-Feedwater Transient with Two Different Bleed-and-Feed Scenarios. . . . Liu, T-J. . . . January 2002 . . . Institute of Nuclear Energy Research, Lungtan, Taiwan.
Nucl. Technol., 137, 28-46 . . . Percolation Cooling of the Three Mile Island Unit 2 Lower Head by Way of Thermal Cracking and Gap Formation. . . . Thomsen, K.L. . . . January 2002 . . . Riso National Laboratory, Roskilde, Denmark.
Nucl. Technol., 137, 47-59 . . . Transmutation of 129I Using An Accelerator-Driven System. . . . Nishihara, K.; Takano, H. . . . January 2002 . . . JAERI, Ibaraki-ken, Japan.
Nucl. Technol., 137, 60-71 . . . Structure and Properties of Chromium- and Zinc-Oxide Layers Formed on Zircaloy-2 in High-Temperature Water. . . . Blajiew, O.L.; Matsuura, C.; Hiroishi, D.; Ishigure, K. . . . January 2002 . . . University of Tokyo, Japan.