Radiation Measurement Applications (IRRMA-V)
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, and the Korean Nuclear Society.
As the Conference's title suggests, the technical sessions are arranged in two major components. The Anew component includes the typical mix of contributed papers in regular sessions and invited papers in special sessions. Members of the Technical Program Committee have been extended an invitation to help organize special sessions on timely topics, and to stimulate paper submission by colleagues. As customary for M&C topical meetings, full papers must be submitted for review by November 1, 2002. Additional instructions to authors, including format requirements, will be posted on the Conference's web site (see below) at a later date.
The Review component of the conference is a marked departure from the standard Plenary Session format. It is comprised of eight invited lectures by world-renowned leaders in selected topics. Each half-day of conference sessions will commence with one such lecture extending for one hour, followed by a 15-minute Question/Answer session, a 15-minute break, then the regular and special sessions proceed.
The complete list of topics and invited lecturers is:
The topics were selected to provide a broad coverage of the major areas of research in nuclear mathematical and computational sciences in the twentieth century. The lectures will capture for future students and researchers a snap shot of what the field looked like at the turn of the century, and how it got to that point since its inception. The stature of the invited lecturers promises to make this lecture series a unique opportunity for nuclear scientists and engineers to "hear it from the lion's mouth"!
The conference's web site is: http://www-rsicc.ornl.gov/mc2003/mc2003.html
It is presently under construction and will be updated with new information
as it becomes available. Please bookmark and visit it occasionally for
news and updates. Comments and suggestions are most welcome. Contact: Yousry
Azmy 865-574-8069, firstname.lastname@example.org
or Bernadette Kirk 865-574-6176, email@example.com.
J. A. Lake, R. G. Bennett of INEEL and J. F. Kotek of
ANL are authors of an article in the Jan. 2002 issue of
entitled "Next Generation Nuclear Power." Discussed are the safety, economics,
and environmental advantages to the GEN-IV advanced reactors being developed
at DOE NE.
The ORNL Fusion Energy Division's Martin Peng, Rajesh Maingi,
and Dennis Strickler were mentioned in a recent Science magazine
article [25 January 2002, Vol 295, p. 602] "Spherical tokamaks are on a
roll." The article discusses promising plasma-confining results from spherically
shaped fusion reactors, as opposed to typical donut-shaped tokamaks. It's
an approach, first suggested by Peng and Strickler in the early '80s.
La GRANGE PARK, Ill. February 15, 2002--President George W. Bush's endorsement of Yucca Mountain as a suitable geological repository is a major step toward the nation's objective of providing safe storage of spent nuclear fuel and high-level nuclear waste, says the American Nuclear Society.
"While this is just one step toward our ultimate goal of seeing the Department of Energy obtain a license for repository construction, it clears a major hurdle toward solving one of the most controversial issues involving nuclear energy," said ANS President Dr. Gail H. Marcus. "Yucca Mountain faces more challenges ahead, but we are confident President Bush made his decision based on measurable scientific data. We have high confidence that Yucca Mountain is a suitable site, and we are ready to help in the process of proceeding to the next stage of repository development."
The next stop for Yucca Mountain is Nevada, where Gov. Kenny Quinn and the state legislature are expected to veto the recommendation. The expected veto would then send the issue to the U.S. Congress for debate and an up-or-down vote in both Houses.
"It is our hope that Congress will recognize the features of Yucca Mountain that our members, as well as the Department of Energy, embraced when endorsing this site: that it has the characteristics and the engineering to exceed the high regulatory standard for public health and safety," said Marcus. "We're convinced, based on pre-closure and post-closure assessments of Yucca Mountain, that the combination of site and design features provide public health protection with a considerable margin of safety."
Work performed by the DOE, national laboratories and other government agencies such as the U.S. Geological Survey and the Environmental Protection Agency provide an impressive comprehensive collection of interdisciplinary studies and reports. Those studies concluded that the Yucca Mountain site is well suited to become the nation's first geological repository.
"Yucca Mountain represents a huge step for the future of nuclear energy," added Marcus. "We applaud President Bush for his commitment to nuclear energy, and his strong endorsement of Yucca Mountain."
More information regarding ANS' position on Yucca Mountain can be found at http://www.ans.org/pi/documents/1002899330.html.
ANS News Release
Three U.S. Nuclear Regulatory Commission (NRC) software packages were transferred from the Energy Science and Technology Software Center, Oak Ridge, Tennessee, to RSICC were added to the RSICC computer code collection. Please browse the computer code abstracts available at RSICC's www site for more information on these packages.
PSR-386/IRRAS 4.16 (US distribution only)
Four new packages were added to the computer code software and data collection. Two of these were foreign contributions.
ENEA - Centro Ricerche, Energia 'E. Clementel,' Bologna, Italy, through the NEA Data Bank, Issy-les-Moulineaux, France, contributed this code package for the activation characterization of materials exposed to neutrons in fusion machines. The main component of the package is the activation code ANITA-4M that computes the radioactive inventory of a material exposed to neutron irradiation, continuous or stepwise. It provides activity, atomic density, decay heat, biological hazard, clearance index and gamma-ray source spectra at shut down and for different cooling times. An interactive utility module, MODBIN, to produce the neutron activation cross section libraries in the required binary ANITA-4M format, is also included. The GRANITA interactive module may plot activation parameters as a function of the cooling time. The main improvements over the previous release (CCC-606/ANITA-4) include:
the number of irradiation time intervals increased to 2000;
ANITA runs on IBM RS/6000 and on personal computers running either Linux
or Windows. An ANITA-2000 executable (called ANITA4M.exe) is included with
the PC version of ANITA-2000. It was created with the Lahey Fortran 95
v5.5 compiler on a P3 under Windows 2000. The distribution CD contains
Fortran source, PC executables, test cases, data, and documentation written
in a GNU compressed Unix tar file and a self-extracting compressed Windows
file. References: ERG FUS TN SIC TR 16/2000 Parts I and II (November 2000).
Fortran; IBM RS/6000, Linux, Windows PC (C00693/MNYCP/00).
The Conservatoire National des Arts et Metiers, Paris, France, through the OECD Nuclear Energy Agency Data Bank, Issy-Les Molineaux, France, contributed this code system to simulate 3D tracer dispersion in the atmosphere. This system includes three programs: CRE_TOPO prepares the terrain data for MESYST; NOABL calculates three-dimensional free divergence windfields over complex terrain, and PAS computes tracer concentrations and depositions on a given domain. The purpose of this work is to develop a realistic and accurate simulation tool for atmospheric dispersion of pollutants over complex terrains. The factional brownian model, which furnishes more accurate concentration values, is introduced to calculate pollutant atmospheric dispersion. The model was validated on SIESTA international experiments.
MESYST can run on the CRAY T3E parallel machine. Fortran and C compilers
are required on all systems. PVM or MPI is required to run in parallel
mode. CRE_TOPO, NOABL, and PAS work under UNICOS/mk 2.0. NOABL also runs
under Solaris 2.3 and MEIKO 1.4.08. Machine-specific statements are provided
in some makefiles for Cray, DEC Alpha and AIX. The codes were not tested
at either the NEA Data Bank or at RSICC. No documentation is available
to guide a user on installation or execution. The transmittal CD contains
a GNU Unix compressed tar file with the reports, source code, makefiles
and sample problems. References: TA-1281: 15/12/1999-27/01/2000 and DOE/ET/20280-3,
UC-60 (September 1978). Fortran 77; Cray, (C00706/MNYWS/00).
The Visual Editor Consultants, Richland, Washington, contributed an updated version of the MCNP Visual Editor that is compatible with the Los Alamos National Laboratory MCNP 4C2 (CCC-701) code. The Visual Editor was developed to make the creation and debugging of MCNP geometries easier. It is a powerful visualization tool that can be used to rapidly create complex geometry models, including lattices, universes, fills, and other geometrical transformations for use with MCNP. The Visual Editor can:
Display MCNP 4C geometries in multiple plot windows.
The package will include executables for Windows NT, Windows 95 and
Linux plus the C code and Fortran patch for Linux/UNIX computers. The Windows
version of the code is now considered the most stable version and is fully
functional. The Windows version has all of the capabilities of the Linux
version except cylindrical duct creation. References: Informal reports
(2002). Pentium and Workstation; Fortran and C (P00500/MNYCP/00).
Argonne National Laboratory, Argonne, Illinois, contributed a new code
system designed for use in predicting the course and consequence of nondestructive
accidents in research and test reactor cores. The original PARET code was
adapted by the Reduced Enrichment Research and Test Reactor (RERTR) Program
to provide transient and thermal-hydraulics analysis for research and test
reactors with both plate and pin type fuel assemblies. The PARET/ANL version
of the code was subjected to extensive comparisons with the SPERT I and
SPERT II (light water and heavy water) experiments. These comparisons were
quite favorable for a wide range of transients up to and including melting
of the clad. The code also provided good agreement with pulsed TRIGA transients
in pin geometry. Revisions include new and more appropriate heat transfer,
DNB and flow instability correlations, improved edits, reactor trips, control
insertion model, decay heat power model, a time-dependent pump flow model,
and a loss-of-flow model with flow reversal. The code now includes a restart
option and generates a summary file for further processing of the results.
Auxiliary support codes are available for generating properties libraries
for both light and heavy water and for post processing of the summary file
data. While the PARET/ANL code does not include a plotting package, the
processed summary data is cast in a format acceptable to most plotting
applications. The code accepts input and generates output in SI units as
an option. The PARET/ANL code is Fortran 77 compatible and runs on both
PCs (Windows and Linux) and UNIX workstations. Executables created with
the Lahey F95 compiler are included for PC users running Windows. All Unix
and Linux systems require a g77 or other Fortran compiler. Reference: ANL/RERTR/TM-16
(March 2001). Sun, PC under Linux and Windows 95, 98, or NT 2000 (P00516/MNYCP/00).
As years have gone by many different codes and applications have been sent to RSICC for stewardship. We currently have over 1500 analytical code packages and distribute as many each year to 73 countries in the world. To help 'categorize' each package, we have developed a database of 'Main Categories' to attach applications to the packages at RSICC. Doing so requires investigation into each code package, user feedback from end use statements, and extensive RSICC staff experience and analysis so that we can deliver useful information each month on the 30 different categories we have devised thus far. Feedback from our Newsletter community is very valuable so please direct your comments and/or suggestions to PDC@ORNL.GOV.
This month we present Accelerator Applications for the main category
of analytical tool packages at RSICC. Links to the package abstracts are
embedded into the WWW version of the RSICC Newsletter. We hope you enjoy
this new feature! Next month we will focus on Space Applications.
Hamilton Hunter - RSICC DirectorBISON-C
PENELOPE 2001 (NEA site)
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.
Fifth International Topical Meeting on Industrial Radioisotope and Radiation Measurement Applications (IRRMA-V), June 9 -14, 2002, in Bologna, Italy. This conference, held for the first time in Europe, is the fifth in a series of topical meetings sponsored by the American Nuclear Society for the purpose of bringing together scientists and engineers from around the world who share an interest in radiation and radioisotope measurement applications. Attendees will have opportunities to share ideas having to do not only with industrial uses of radiation and radioisotopes but also with basic research and applications in related fields such as medicine, art and archaeometry, environment, analytical techniques, and new trends in sources and detector development.
More information on the scientific program, the conference site, the city of Bologna, the list of invited speakers, the call for papers, and on-line registration can be found on the conference web site http://www.irrma.unibo.it/ and in the attached announcement and call for papers.
For more information please contact: Chairman Prof. Jorge E. Fernandez,
Laboratory of Montecuccolino-DIENCA, University of Bologna, via dei Colli,
16 - 40136 Bologna, ITALY (tel +39-051.644.1718, fax +39-051-644-1747,
(also for any request of information and inclusion in the mailing list).
Preparations for the American Nuclear Society's Advances in Nuclear Fuel Management III Topical Meeting to be held in Hilton Head Island, South Carolina, during the period of October 5 - 8, 2003, have now begun in earnest. You are invited to serve on the Meeting's Technical Program Committee (TPC). In this capacity your commitment will include:
1. Electronically submit one or more papers, and encourage colleagues
to do the same.
Please return the following information (name, affiliation, phone, alternative email if preferable, topics of interest) to Youssef A. Shatilla at firstname.lastname@example.org.
Please remember that success of this meeting depends on your active
support and involvement. Finally, please bookmark the conference web site:
and visit it occasionally for news and updates. Comments and suggestions
are most welcome.
This is the "Second Announcement and Call for Papers" for the IAEA Technical Meeting on Physics and Technology of Inertial Fusion Energy Targets and Chambers, which will be held at the General Atomics main site in San Diego, California, June 17-19, 2002. The Technical Meeting will include invited and contributed papers on all aspects of the following:
1. Target design and physics, including fast ignition
We would greatly appreciate your efforts in further distributing this
announcement to your colleagues. Detailed meeting information including
Abstract Submittal, Participation Procedures, Hotels, Social Events, etc.
can be found at the meeting web site http://web.gat.com/conferences/iaea-tm/
main.html. Contacts: Dan Goodin, General Atomics (Chair) (fax 858-455-3181,
e-mail email@example.com), Art
Nobile, Los Alamos National Laboratory (Co-Chair)(e-mail firstname.lastname@example.org).
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 website www.bnl.gov/est/IMUG2002/default.htm
to find out about IMUG, register for the meeting or request notification
of web updates. The website will be updated as additional information becomes
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 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.
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 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.
All workshops include hands-on instruction, generally on PC Windows machines. Subject to participant export approval for the MCNPX beta test team, participants will be able to access the Fortran-90 version of MCNPX 2.4, the LA150 (150 MeV) cross-section data for over 40 isotopes for incident neutrons and protons, and 12 for photonuclear interactions, and a notebook of viewgraphs. Follow-up consultation for class participants will be provided.
Classes are taught directly by experienced MCNPX code developers and
instructors. For more information on code versions and their capabilities,
go to the MCNPX Workshops web site http://mcnpxworkshops.com.
Dates: August 5-7, 2002 in Braunschweig, Germany
A training course on neutron spectra unfolding is being organized by the Neutron Dosimetry section of the Physikalisch-Technische Bundesanstalt (PTB), Braunschweig, Germany, in collaboration with the Health Physics Measurements Group (ESH-4) of the Los Alamos National Laboratory (LANL). Additional support is provided by the Helmholtz-Fonds e.V.
We will emphasize practical aspects of unfolding. The course is intended for those who do spectrometry in neutron or mixed neutron/photon fields and who need to analyze their data using unfolding procedures. In the morning sessions we will have a series of lectures which will provide an introduction to unfolding as well as allow for discussions concerning the theory of unfolding. In the afternoon sessions the participants will work on specific examples at PC-workplaces using unfolding software provided by PTB (the HEPRO package of unfolding codes and the MAXED code). We will focus on Bonner sphere measurements for our discussion of few-channel unfolding, and liquid scintillation spectrometer (NE-213) measurements for our discussion of multi-channel unfolding.
The number of participants is restricted by the limited number of PC-workplaces
at our disposal at each of the training centers. We therefore encourage
you to register as soon as possible. For on-line registration and further
information please visit our web site at: http://www.ptb.de/utc2002/.
DATE: May 6-10, 2002
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 michael.g.stabin@
vanderbilt.edu) or Dr. Richard B. Sparks (tel 865- 938-4949, fax 865-947-1550,
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
OVERVIEW: The Division's biennial Topical Meeting is rapidly approaching. It is scheduled for April 14-18, 2002, in Santa Fe, New Mexico. RPSD 2002 is co-sponsored by the Health Physics Society, the OECD/NEA, and RSICC. In addition to an exciting technical program, there are workshops, tours, and various social events planned. There are also special registration opportunities for students, emeritus members of ANS, exhibitors, and guests.
Mon. Apr. 15: Plenary session in the morning; Guest tour of Santa Fe;
Tues. Apr. 16: Technical sessions morning and afternoon; Conference banquet in the evening
Wed. Apr. 17: Technical sessions morning and afternoon; Guest tour of
Northern New Mexico;
Thurs. Apr. 18: Technical sessions morning and afternoon
Fri. Apr. 19: Tour of the Trinity Site
REGISTRATION: The main registration form for the Conference is at http://www.lanl.gov/PSD2002/registration.shtml. The form allows you to register for the Conference, for the Guest Program, and for Tours, and to purchase additional tickets for social events. The early registration discount is available through March 1. We request that you print the registration form, fill it out, and mail it in to the address indicated.
TECHICAL SESSIONS: Over 200 abstracts have been accepted for presentation at RPSD2002. The following sessions will be included in the final program (available at http://www.lanl.gov/RPSD2002/agenda.shtml).
Accelerator Applications and Shielding
WORKSHOPS: We will offer 4 workshops on Sunday April 14. There will be two in the morning and two in the afternoon. Each workshop will be approximately three hours. The four workshops offered are:
A. "Radiation Serving Society," by Alan Waltar (Texas A&M)
Full information, and a separate registration form, for the Workshops are available at http://www.lanl.gov/RPSD2002/workshops.shtml.
TOURS: Three tours have been planned in association with RPSD2002:
1. Monday April 15: "A Taste of Santa Fe" - 3-4 hour guided tour of Santa Fe by bus. The tour will include stops at museums and art galleries. Use this opportunity to plan the rest of your week in Santa Fe.
2. Wednesday April 17: "Explore Northern New Mexico" - 6-7 hour guided tour with stops at Bandelier National Monument and historic Los Alamos. In Los Alamos you will tour the Bradbury Science Museum and have time for lunch in town.
3. Friday April 19: "The Trinity Site" - a special full-day tour to the White Sands Missile Range in south-central New Mexico to view the site where the first atomic bomb was detonated. The tour will include time at ground zero, as well as at the McDonald Ranch House, where the world's first plutonium core for a bomb was assembled. Representatives of the White Sands Missile Range will conduct the tour. Lunch will be provided at the historic Owl Bar & Café in San Antonio, NM, which served many Los Alamos scientists during the test program. Transportation for this tour will be arranged that travelers can depart and be dropped off from either Santa Fe or Albuquerque.
Check the Website http://www.lanl.gov/RPSD2002/tours.shtml for more details. All tours will have both a minimum and maximum registration. In the event of cancellation, full refunds will be provided. Register for tours on the main Conference registration form.
HOTEL: We encourage you to make your reservations early at the Conference hotel, La Fonda. Information and a reservation form are available at http://www.lanl.gov/RPSD2002/hotel.shtml. You can either fill out a form on line, or print the form and send it to the Hotel. In either event, please make sure to note "RPSD 2002 Topical Meeting" in order to qualify for the special discount offered.
EXHIBITOR: There are opportunities for vendors to exhibit their products at RPSD 2002. Full information is available at http://www.lanl.gov/RPSD2002/exhibitor.shtml. Booth space will be available; there are also various sponsorship opportunities. To highlight the exhibitors, a Conference mixer will be held in the exhibit area on Wednesday evening.
STUDENTS: We strongly encourage student participation at RPSD 2002. The student fees are small and we feel that this will be an excellent opportunity for students to participate in a Technical Conference and to meet potential employers (Los Alamos National Laboratory, at least, plans to have a recruiting booth at RPSD 2002). In addition to reduced registration fees, we will arrange for students to share hotel rooms, and offer some payment to students for helping with technical sessions. See http://www.lanl.gov/ RPSD2002/students.shtml for additional information.
The SCALE staff at Oak Ridge National Laboratory (ORNL) will be offering
courses this fall (October 14-18 and October 21-25) at ORNL. The
courses will emphasize hands-on experience solving practical problems
on PCs. There will be workgroups of two persons each. No prior experience
in the use of SCALE is required to attend. The registration fee is $1800
for one course or $3000 for both courses ($300 discount if you register
at least one month before the course). A copy of the SCALE software and
manual on CD may be obtained for an additional fee of $700, and the KENO3D
3-D visualization tool on CD is available for $800 (single license). Registrations
will be accepted on a first-come basis. Registration forms submitted directly
from the Web are preferred. Registration via FAX or e-mail is also acceptable.
The registration fee must be paid by check, travelers checks, bank transfer,
or credit card (VISA or MasterCard only). The agenda and registration form
are on the web page at http://www.ornl.gov/scale/trcourse.html.
Contact: Kay Lichtenwalter (tel 865-574-9213, email email@example.com).
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 firstname.lastname@example.org.
RESRAD Training Course, Mar.5-8, 2002, Argonne, IL. Cosponsored by DOE. Contact: Carole Ealy (tel 630-252-5677, email email@example.com, url http://web.ead.anl.gov/resrad/training/MarchWrkshp.cfm) Agenda: http://web.ead.anl.gov/resrad/training/AgendaMarch2002.htm.
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. 14-18, 2002, Santa Fe, NM. Hosted by the ANS Trinity Section and cosponsored by the Health Physics Society, L'Organisation de cooperation et de developpement/L'Agence pour l'energie nucleaire (OECD/AEN, and RSICC. Contact: (email rpsd2002@lanl. gov, url www.lanl.gov/RPSD2002/).
International Youth Nuclear Congress 2002, Apr. 16-20, 2002, Taejon, Korea. Contact: Alexandre Tsiboulia or Han Seong Son (email alexts@ippe. obninsk.ru, email@example.com, url http://www.iync.org).
Seventh International Radiopharmaceutical Dosimetry Symposium, Apr. 17-19, 2002, Nashville, TN. Contact: Michael Stabin (email michael.g.stabin@ vanderbilt.edu, 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 registrar@mcnpxwork shops.com, 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 firstname.lastname@example.org, 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 email@example.com); registration information: Susan Monteleone (tel 631-344-7235, fax 631-344-3957, email firstname.lastname@example.org, url http://www.bnl.gov/icwsa).
Radiation Transport Calculations Using the EGS Monte Carlo System, Apr. 29-May 2, 2002, Ottawa, Canada. Contact: Blake Walters, Ionizing Radiation Standards, National Research Council of Canada, Ottawa, Canada, K1A 0R6. (tel 613-993-2715, fax 613-952-9865, e-mail email@example.com, url www.irs.inms.nrc.ca/inms/irs/papers /egsnrc/brochure.html).
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, url http://rma-symposium.engin.umich.edu/).
ANS Annual Meeting, The Revival of the Nuclear Power Option, June 9-13, 2002, Hollywood, FL (url http://www.ans.org/).
Topical Meeting: Industrial Radiation and Radioisotope Measurement Applications IRRMA-V A Class IV Topical, June 9-14, 2002, Bologna, Italy, co-sponsored by the American Nuclear Society. Contact: Prof. Jorge Fernandez, Chair (e-mail: email@example.com).
IAEA Technical Meeting on Physics and Technology of Inertial Fusion Energy Targets and Chambers, June 17-19, 2002, San Diego, CA. Contact: Dan Goodin (tel 858-455-2977, email firstname.lastname@example.org, url http://web.gat. com/conferences/iaea-tm/main.html).
14th International Conference on High-Power Particle Beams and 5th International Conference on Dense Z-Pinches, June 23-28, 2002, Albuquerque, NM (email for general inquiries email@example.com; url http://www.sandia.gov/BeamsDZP).
Snowmass Fusion Summer Study, July 8-19, 2002, Snowmass Village, CO (url http://lithos.gat.com/snowmass/).
Spectrum 2002, Exploring Science-Based Solutions and Technologies, 9th Biennial International Conference on Nuclear and Hazardous Waste Management, Aug. 4-8, 2002, Reno, NV. Contact: Dr. Richard Jacobsen (email firstname.lastname@example.org, 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: 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, url http://www.vin. bg.ac.yu/YUNS).
8th Annual Workshop on Monte Carlo Simulation of Radiotherapy Treatment Sources using the BEAM Code System, Sept. 30-Oct. 3, 2002, Ottawa, Canada. Contact: Blake Walters, Ionizing Radiation Standards, National Research Council of Canada, Ottawa, Canada, K1A 0R6 (tel 613-993-2715, fax 613-952-9865, e-mail email@example.com, url http://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 tpc@physor2002. kaist.ac.kr, 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, url http://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, and the Korean Nuclear Society. Contacts: Yousry Azmy (tel 865-574-8069, email firstname.lastname@example.org) or Bernadette Kirk (tel 865-574-6176, email email@example.com).
International Conference on Supercomputing in Nuclear Applications, SNA 2003, September 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 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, 777-789 . . . The Integral Form of the Neutron Transport Equation for Backward-Forward Scattering in Bare Spheres. . . . Williams, M.M.R. . . . May 2002.
Ann. Nucl. Energy, 29, 791-803 . . . Void Reactivity and Pin Power Calculation for a Typical CANDU Cell Using CPs and a Two-Stratified Coolant Model. . . . Constantin, M.; Balaceanu, V. .. . May 2002 . . . Institute for Nuclear Research, Pitesti, Romania.
Ann. Nucl. Energy, 29, 805-819 . . . Improved Methodology for Generation of Axial Flux Shapes in Digital Core Protection Systems. . . . Lee, G-C.; Baek, W-P.; Chang, S.H. . . . May 2002 . . . Korea Power Engineering Co.; Daejeon, South Korea; KAERI, Daejeon, South Korea; Korea Advanced Institute of Science and Technology, Daejeon, South Korea.
Ann. Nucl. Energy, 29, 821-833 . . . Modeling and Measuring the Effects of Imprecision in Accident Management. . . . Yu, D. . . . May 2002 . . . KAERI, Taejon, South Korea.
Ann. Nucl. Energy, 29, 835-850 . . . Assessment of RELAP5/MOD3.2.2 Against Flooding Database in Horizontal-to-Inclined Pipes. . . . Kim, H.T.; No, H.C. . . . May 2002 . . . Korea Advanced Institute of Science and Technology, Taejon, South Korea.
Ann. Nucl. Energy, 29, 851-874 . . . Analytical SN Solutions in Heterogeneous Slabs Using Symbolic Algebra Computer Programs. . . . Warsa, J.S. . . . May 2002 . . . University of New Mexico, Albuquerque, NM.
Ann. Nucl. Energy, 29, 875-899 . . . High-Order Cross-Section Homogenization Method. . . . Rahnema, F.; McKinley, M.S. . . . May 2002 . . . Georgia Institute of Technology, Atlanta, GA.
Ann. Nucl. Energy, 29, 901-912 . . . Neutronic Calculation to the TRIGA Ipr-R1 Reactor Using the WIMSD4 and CITATION Codes. . . . Dalle, H.M.; Pereira, C.; Souza, R.G.P. . . . May 2002 . . . Cidade Universitaria UFMG, Belo Horizonte, MG, Brazil.
Ann. Nucl. Energy, 29, 913-927 . . . Galerkin Spectral Synthesis Methods for Diffusion Equations with General Boundary Conditions. . . . Neta, B.; Reich, S.; Victory, Jr., H.D. . . . May 2002 . . . Naval Postgraduate School, Monterey, CA; The Technion-Israel Institute of Technology, Haifa, Israel; Texas Tech University, Lubbock, TX.
Ann. Nucl. Energy, 29, 929-935 . . . The Inverse Power Method for Calculation of Multiplication Factors. . . . Allen, E.J.; Berry, R.M. . . . May 2002 . . . Texas Tech University, Lubbock, TX.
Ann. Nucl. Energy, 29, 937-966 . . . Improved Cross-Section Modeling Methodology for Coupled Three-Dimensional Transient Simulations. . . . Watson, J.K.; Ivanov, K.N. . . . May 2002 . . . Pennsylvania State University, University Park, PA.
Ann. Nucl. Energy, 29, 967-981 . . . Solving the Inverse Problem of Parameter Estimation by Genetic Algorithms: The Case of a Groundwater Contaminant Transport Model. . . . Giacobbo, F.; Marseguerra, M.; Zio, E. . . . May 2002 . . . Polytechnic of Milan, Milan, Italy.
Ann. Nucl. Energy, 29, 991-1002 . . . Determination of Aluminium Concentration in Copper-Aluminium Alloys Using -Ray Transmission Techniques. . . . El-Kateb, A.H.; Rizk, R.A.M.; Abdul-Kader, A.M. . . . May 2002 . . . Helwan University, Cairo, Egypt.
Ann. Nucl. Energy, 29, 1003-1012 . . . Sub-Critical Moderator Temperature Reactivity Coefficient: Measurement at Edwin I. Hatch Unit 2 BWR Nuclear Power Plant. . . . Quintero-Leyva, B.; Gibson, E.B.; Miller, R.L. . . . May 2002 . . . Southern Nuclear Operating Co., Inc.; Birmingham, AL.
Ann. Nucl. Energy, 29, 1013-1018 . . . The Relation Between Ternary Fission and Cluster Decay. . . . ; Ronen, Y. . . . May 2002 . . . Ben-Gurion University of the Negev, Beer-Sheva, Israel.
Fus. Eng. Design, 60, 3-15 . . . Dry Wall Chamber Issues for the SOMBRERO Laser Fusion Power Plant. . . . Kulcinski, G.L. et al. . . . January 2002 . . . University of Wisconsin-Madison, WI.
Fus. Eng. Design, 60, 17-25 . . . Analytical Opacity Formulas for ICF Elements. . . . Mínguez, E.; Martel, P.; Gil, J.M.; Rubiano, J.G.; Rodríguez, R. . . . January 2002 . . . Instituto de Fusión Nuclear, Madrid, Spain; Universidad de Las Palmas de Gran Canaria, Spain.
Fus. Eng. Design, 60, 27-36 . . . Developing the Basis for Target Injection and Tracking in Inertial Fusion Energy Power Plants. . . . Goodin, D.T. et al. . . . January 2002 . . . General Atomics, San Diego, CA; University of California, Berkeley, CA; San Diego State University, CA; Los Alamos National Laboratory, Los Alamos, NM.
Fus. Eng. Design, 60, 37-43 . . . An Intregrated Research Plan for the IFE Element of the Virtual Laboratory for Technology. . . . Meier, W.R. . . . January 2002 . . . Lawrence Livermore National Laboratory, Livermore, CA.
Fus. Eng. Design, 60, 45-53 . . . Pulsed Activation of Structural Materials in IFE Chambers. . . . Sanz, J.; Cabellos, O.; Yuste, P.; Reyes, S.; Latkowski, J.F. . . . January 2002 . . . Ciudad Universitaria, Madrid, Spain; Lawrence Livermore National Laboratory, Livermore, CA.
Fus. Eng. Design, 60, 55-63 . . . Results from Systematic Modeling of Neutron Damage in Inertial Fusion Energy Reactors. . . . Perlado, J.M. et al. . . . January 2002 . . . Universidad Politécnica de Madrid, Spain; Lawrence Livermore National Laboratory, Livermore, CA.
Fus. Eng. Design, 60, 65-75 . . . Negative and Positive Influence of Radiation Emitted by Hot Thermonuclear Target on Cluster Ion Beams Moving Toward the Target. . . . Shmatov, M.L. . . . January 2002 . . . Ioffe Physical Technical Institute, St. Petersburg, Russia.
Fus. Eng. Design, 60, 77-83 . . . Simulation Study on Evacuation of Metal Vapor in Laser Fusion Liquid Wall Chamber. . . . Kozaki, Y. et al. . . . January 2002 . . . Osaka University, Japan.
Fus. Eng. Design, 60, 85-91 . . . Progress on Establishing Guidelines for National Ignition Facility (NIF) Experiments to Extend Debris Shield Lifetime. . . . Tobin, M.; Eder, D.; Braun, D. MacGowan, B. . . . January 2002 . . . Lawrence Livermore National Laboratory, Livermore, CA.
Fus. Eng. Design, 60, 93-98 . . . Overview of New High Gain Target Design for a Laser Fusion Power Plant. . . . Bodner, S.E. et al. . . . January 2002 . . . Naval Research Laboratory, Washington, DC.
J. Nucl. Mater., 300, 1-6 . . . Diffusive Transport Parameters and Surface Rate Constants of Deuterium in Incoloy 800. . . . Esteban, G.A. et al. . . . January 2002 . . . ETSIIT, Bilbao, Spain; Joint Research Centre - Ispra, Italy; CIEMAT, Madrid, Spain.
J. Nucl. Mater., 300, 7-14. . . . The Dissolution of Oxide on -Zr(1%Nb) and -Zr(20%Nb) Alloys. . . . Zhang, C.; Norton, P.R. . . . January 2002 . . . University of Western Ontario, Canada.
J. Nucl. Mater., 300, 15-26 . . . Pyrochemical Reduction of Uranium Dioxide and Plutonium Dioxide by Lithium Metal. . . . Usami, T. et al. . . . January 2002 . . . Central Research Institute of Electric Power Industry, Tokyo, Japan; AEA Technology, Oxon, UK.
J. Nucl. Mater., 300, 27-38 . . . Analysis of the Monoclinic-Tetragonal Phase Transition of Zirconia Under Irradiation. . . . Simeone, D.; Gosset, D.; Bechade, J.L.; Chevarier, A. . . . January 2002 . . . Laboratoire de Métallurgie et d'Etude de l Endommagement, Gif-sur-Yvette, France; SRMA, Gif-sur-Yvette, France; IPNI, Villeurbanne, France.
J. Nucl. Mater., 300, 39-46 . . . Neutron Irradiation of Sapphire for Compressive Strengthening. I. Processing Conditions and Compressive Strength. . . . Regan, T.M.; Harris, D.C.; Stroud, R.M.; White, J.R. . . . January 2002 . . . Aspen Systems, Marlborough, MA; University of Massachusetts, Lowell, MA; Naval Air Warfare Center, China Lake, CA; Naval Research Laboratory, Washington, DC.
J. Nucl. Mater., 300, 47-56 . . . Neutron Irradiation of Sapphire for Compressive Strengthening. II. Physical Properties Changes . . . Regan, T.M. et al. . . . January 2002 . . . Aspen Systems, Marlborough, MA; University of Massachusetts, Lowell, MA; Naval Air Warfare Center, China Lake, CA; Johns Hopkins University, Laurel, MD; Naval Research Laboratory, Washington, DC; National Institute of Standards and Technology, Gaithersburg, MD; Case Western Reserve University, Cleveland, OH.
J. Nucl. Mater., 300, 57-64 . . . Thermal Conductivities of Irradiated UO2 and (U,Gd)O2 Pellets. . . . Amaya, M. et al. . . . January 2002 . . . Nippon Nuclear Fuel Development Co., Ibaraki-ken, Japan; Hitachi Ltd., Ibaraki-ken, Japan; Toshiba Corp., Kanagawa-ken, Japan; Nuclear Power Engineering Corp., Tokyo, Japan.
J. Nucl. Mater., 300, 65-72 . . . Effects of Nitrogen on Low-Cycle Fatigue Properties of Type 304L Austenitic Stainless Steels Tested With and Without Tensile Strain Hold. . . . Rho, B.S.; Nam, S.W. . . . January 2002 . . . Korea Advanced Institute of Science and Technology, Taejon, South Korea.
J. Nucl. Mater., 300, 73-81 . . . Active Control of Oxygen in Molten Lead-Bismuth Eutectic Systems to Prevent Steel Corrosion and Coolant Contamination. . . . Li, N. . . . January 2002 . . . Los Alamos National Laboratory, NM.
J. Nucl. Mater., 300, 82-88 . . . Combustion Synthesis of -Lithium Aluminate by Using Various Fuels. . . . Li, F.; Hu, K.; Li, J.; Zhang, D.; Chen, G. . . . January 2002 . . . Shanghai Jiaotong University, Shanghai, China.
J. Nucl. Mater., 300, 89 . . . Erratum to 'The Effects of Moisture on LiD Single Crystals Studied by Temperature-Programmed Decomposition' [J. Nucl. Mater., 295, 193-204]. . . . Dinh, L.N.; Cecala, C.M.; Leckey, J.H.; Balooch,M. . . . January 2002 . . . Lawrence Livermore National Laboratory, Livermore, CA; Lockheed Martin Energy Systems, Oak Ridge, TN.
J. Nucl. Mater., 300, 90 . . . Erratum to 'Dependence of the Non-Swelling In-Reactor Steady-State Creep Component of Austenitic Phase Alloys on the Stacking Fault Energy' [J. Nucl. Mater., 29 . . . Gilbert, E.R.; Foster, J.P. . . . January 2002 . . . Westinghouse Electric Co., Columbia, SC.
J. Nucl. Mater., 300, 91-117 . . . Hydrogen Isotope Retention and Recycling in Fusion Reator Plasma-Facing Components. . . . Causey, R.A. . . . February 2002 . . . Sandia National Laboratories, Livermore, CA.
J. Nucl. Mater., 300, 118-126 . . . A Raman Study of the Nanocrystallite Size Effect on the Pressure-Temperature Phase Diagram of Zirconia Grown by Zirconium-Based Alloys Oxidation. . . . Bouvier, P.; Godlewski, J.; Lucazeau, G. . . . February 2002 . . . Laboratoire d'Electrochimie et de Physico-Chimie des Materiaux et des Interfaces, St. Martin d'Hères, France; CEA, St. Paul-lez-Durance, France.
J. Nucl. Mater., 300, 127-140 . . . Comparison of Microstructural Features of Radiation Embrittlement of VVER-440 and VVER-1000 Reactor Pressure Vessel Steels. . . . Kuleshova, E.A.; Gurovich, B.A.; Shtrombakh, Y.A.; Erak, D.Y.; Lavrenchuk, O.V. . . . February 2002 . . . Kurchatov Institute, Moscow, Russia.
J. Nucl. Mater., 300, 141-150 . . . Aqueous Corrosion of Lanthanum Aluminosilicate Glasses: Influence of Inorganic Anions. . . . Bois, L. et al. . . . February 2002 . . . Laboratoire Pierre Süe, Gif-sur-Yvette, France; Universite Rennes I, Rennes, France; SRSIM, CEA, Gif-sur-Yvette, France.
J. Nucl. Mater., 300, 151-160 . . . Order-Disorder Phase Transition Induced by Swift Ions in MgAl2O4 and ZnAl2O4 Spinels. . . . Simeone, D.; Dodane-Thiriet, C.; Gosset, D.; Daniel, P.; Beauvy, M. . . . February 2002 . . . Laboratoire de Métallurgie et d'Etude de l'Endommagement, Gif-sur-Yvette, France; CEA, St. Paul-les-Durance, France; Laboratoire de Physique de l'Etat Condensé, Le Mans, France.
J. Nucl. Mater., 300, 161-177 . . . Mechanical and Thermomechanical Properties of Commercially Pure Chromium and Chromium Alloys. . . . Holzwarth, U.; Stamm, H. . . . February 2002 . . . Joint Research Centre, Ispra, Italy.
J. Nucl. Mater., 300, 178-191 . . . Influence of Dynamic Strain Aging on the Ductile Tearing of C-Mn Steels: Modelling by a Local Approach Method. . . . Wagner, D.; Moreno, J.C.; Prioul, C.; Frund, J.M.; Houssin, B. . . . February 2002 . . . Laboratoire MSS/MAT, Chatenay Malabry, France; EDF, France; Framatome, France.
J. Nucl. Mater., 300, 192-197 . . . Ultrasonic Study of UO2: Effects of Porosity and Grain Size on Ultrasonic Attenuation and Velocities. . . . Laux, D.; Cros, B.; Despaux, G.; Baron, D. . . . February 2002 . . . Université Montpellier, France; EDF, Moret/Loing, France; CEA, St. Paul-lez-Durance, France.
J. Nucl. Mater., 300, 198-216 . . . Emulation of Neutron Irradiation Effects with Protons: Validation of Principle . . . Was, G.S. et al. . . . February 2002 . . . University of Michigan, Ann Arbor, MI; Argonne National Laboratory-West, Idaho Falls, ID; Oak Ridge National Laboratory, Oak Ridge, TN; Studsvik Nuclear AM, Nyköping, Sweden; Pacific Northwest National Laboratory, Richland, WA; Framatome, Paris La Defénse, France; General Electric Corp. Research and Development, Schenectady, NY.
J. Nucl. Mater., 300, 217-229 . . . Thoria Doped with Cations of Group VB-Syntheis and Sintering. . . . Anathasivan, K. et al. . . . February 202 . . . Indira Gandhi Centre for Atomic Research, Kalpakkam, India.
J. Nucl. Mater., 300, 230-236 . . . In Situ Electrochemical Impedance Spectroscopy of Zr-1%Nb Under VVER Primary Circuit Conditions. . . . Nagy, G.; Kerner, Z.; Pajkossy, T. . . . February 2002 . . . KFKI Atomic Energy Research Institute, Budapest, Hungary; Hungarian Academy of Sciences, Budapest, Hungary.
J. Nucl. Mater., 300, 237-241 . . . Thermodynamic Stability of Na2ZrO3 Using the Solid Electrolyte Galvanic Cell Technique. . . . Subasri, R.; Mathews, T.; Swaminathan, K. Sreedharan, O.M. . . . February 2002 . . . Indira Gandhi Centre for Atomic Research, Kalpakkam, India.
J. Nucl. Mater., 300, 242-254 . . . Amorphization and Recrystallization of the ABO3 Oxides. . . . Meldrum, A.; Boatner, L.A.; Weber, W.J.; Ewing, R.C. . . . February 2002 . . . University of Alberta, Canada; Oak Ridge National Laboratory, Oak Ridge, TN; Pacific Northwest National Laboratory, Richland, WA; University of Michigan, Ann Arbor, MI.
J. Nucl. Mater., 300, 255-265 . . . The Effect of Coatings on Deuterium Retention and Permeation in Aluminum 6061-T6 APT Tritium Production Tubes. . . . Hertz, K.L.; Causey, R.A.; Cowgill, D.F. . . . February 2002 . . . Sandia National Laboratories, Livermore, CA.
J. Nucl. Mater., 300, 266-269 . . . Concentration-Triggered Fission Product Release from Zirconia: Consequences for Nuclear Safety. . . . Gentils, A.; Thome, L.; Jagielski, J.; Garrido, F. . . . February 2002 . . . Centre de Spectrometire Nucleaire et de Spectrometrie de Mass, Orsay Campus, France; Institute of Electronic Materials Technology, Warsaw, Poland; Andrzej Soltan Institute for Nuclear Studies, Swierk/Otwock, Poland.
J. Nucl. Mater., 300, 270-272 . . . Redox Condition in Molten Fluoride Salts Definition and Control. . . . Olander, D. . . . February 2002 . . . University of California, Berkeley, CA.
J. Nucl. Mater., 300, 273-276 . . . Fission Product Precipitates in Irradiated Uranium Carbonitride Fuel. . . . Kleykamp, H. . . . February 2002 . . . Forschungszentrum Karlsruhe, Germany.
J. Nucl. Mater., 300, 277 . . . Erratum to 'On the Role of Grain Boundary Diffusion in Fission Gas Release' [J. Nucl. Mater., 288, 137-147]. . . . Olander, D.R.; Van Uffelen, P. . . . February 2002 . . . University of California, Berkeley, CA.; SCK-CEN, Mol, Belgium.
J. Nucl. Mater., 300, 278 . . . Erratum to 'Overview of Impurity Control and Wall Conditioning in NSTX' [J. Nucl. Mater. 290-293 (2001) 1185-1189] . . . Kugel, H.W. et al. . . . February 2002 . . . Princeton Plasma Physics Laboratory, Princeton, NJ; Oak Ridge National Laboratory, Oak Ridge, TN; Sandia National Laboratories, Albuquerque, NM; Los Alamos National Laboratory, Los Alamos, NM; Columbia University, New York, NY; University of Washington, Seattle, WA; John Hopkins University, Baltimore, MD.
Nucl. Eng. Design, 211, 1-11 . . . A Study of the Effects of the Location of Flashing Inception on Maximum and Minimum Critical Two-Phase Flow Rates: Part I - Experimental. . . . Fraser, D.W.H.; Abdelmessih, A.H. . . . January 2002 . . . University of British Columbia, Vancouver, Canada; University of Toronto, Canada.
Nucl. Eng. Design, 211, 13-26 . . . A Generic Semi-Implicit Coupling Methodology for Use in RELAP5-3D. . . . Weaver, W.L.; Tomlinson, E.T.; Aumiller, D.L. . . . January 2002 . . . Bechtel BWXT Idaho, Idaho Falls, ID; Bechtel Bettis, West Mifflin, PA.
Nucl. Eng. Design, 211, 27-50 . . . Simulation of Hydrogen Deflagration and Detonation in a BWR Reactor Building. . . . Manninen, M.; Silde, A.; Lindholm, I.; Huhtanen, R.; Sjövall, H. . . . January 2002 . . . VTT Energy, Finland; Teollisuuden Voima Oy, Olkiluoto, Finland.
Nucl. Eng. Design, 211, 51-60 . . . Residual Design Strength of Cement-Based Materials for Nuclear Waste Storage Systems. . . . Ulm, F-J.; Heukamp, F.H.; Germaine, J.T. . . . January 2002 . . . Massachusetts Institute of Technology, Cambridge, MA.
Nucl. Eng. Design, 211, 61-68 . . . Fracture and General Yield for Carbon Steel Pipes with Local Wall Thinning. . . . Miyazaki, K. Kanno, S.; Ishiwata, M.; Hasegawa, K.; Ahn, S.H.; Ado, K. . . . January 2002 . . . Hitachi Ltd., Ibaraki-ken, Japan; Yokohama National University, Kanagawa-ken, Japan.
Nucl. Eng. Design, 211, 69-84 . . . Development of LOCA Licensing Calculation Capability with RELAP5-3D in Accordance with Appendix K of 10 CFR 50.46. . . . Liang, T.K.S.; Chang, C-J.; Hung, H-J. . . . January 2002 . . . Institute of Nuclear Energy Research, Lung-Tan, Taiwan.
Nucl. Eng. Design, 211, 245-272 . . . On the Automated Assessment of Nuclear Reactor Systems Code Accuracy. . . . Kunz, R.F.; Kasmala, G.F.; Mahaffy, J.H.; Murray, C.J. . . . February 2002 . . . Pennsylvania State University, University Park, PA.
Nucl. Eng. Design, 211, 91-103 . . . Fracture Behavior of Straight Pipe and Elbow with Local Wall Thinning. . . . Ahn, S-H.; Nam, K-W.; Yoo, Y-S.; Ando, K.; Ji, S-H.; Ishiwata, M.; Hasegawa, K. . . . February 2002 . . . Pukyong National University, Busan, South Korea; Yokohama National University, Japan; Hitachi, Ltd., Japan.
Nucl. Eng. Design, 211, 105-119 . . . Low-Temperature Tensile Properties, Notch and Fracture Toughness of Steels for Use in Nuclear Power Plant. . . . Tuma, J.V. . . . February 2002 . . . Institute of Metals and Technology, Ljubljana, Slovenia.
Nucl. Eng. Design, 211, 121-138 . . . Simulated Model Studies for Solid Waste Storage Surveillance Facility. . . . Verma, V.; Ghosh, A.K.; Kushwaha, H.S. . . . February 2002 . . . Bhabha Atomic Research Centre, Mumbai, India.
Nucl. Eng. Design, 211, 139-151 . . . Direct-Contact Condensation Heat Transfer Model in RELAP5/MOD3.2 With/Without Noncondensable Gases for Horizontally Stratified Flow. . . . Choi, K.Y.; Chung, H.J.; No, H.C. . . . February 2002 . . . Korea Atomic Energy Research Institute, Taejon, South Korea; Korea Advanced Institute of Science and Technology, Taejon, South Korea.
Nucl. Eng. Design, 211, 153-171 . . . On Lattice Boltzmann Modeling of Phase Transition in an Isothermal Non-Ideal Fluid. . . . Norugaliev, R.R.; Dinh, T.N. Sehgal, B.R. . . . February 2002 . . . Royal Institute of Technology, Stockholm, Sweden.
Nucl. Eng. Design, 211, 173-187 . . . Characterization of Heat Transfer Processes in a Melt Pool Convection and Vessel-Creep Experiment. . . . Sehgal, B.R.; Nourgaliev, R.R.; Dinh, T.N. . . . February 2002 . . . Royal Institute of Technology, Stockholm, Sweden.
Nucl. Eng. Design, 211, 189-228 . . . Hydrodynamic Loads on a PWR Primary Circuit Due to a LOCA. . . . Robbe, M-F.; Lepareux, M.; Trollat, C. . . . February 2002 . . . CEA, Gif-sur-Yvette, France; EDF SEPTEN, Villeurbanne, France.
Nucl. Eng. Design, 211, 229-235 . . . Irradiation Behavior of Atomized U - 10wt.% Mo Alloy Aluminum Matrix Dispersion Fuel Meat at Low Temperature. . . . Kim, K-H.; Park, J-M.; Kim, C-K.; Hofman, G.L.; Meyer, M.K. . . . February 2002 . . . Korea Atomic Energy Research Institute, Daejeon, South Korea; Argonne National Laboratory, Argonne, IL; Argonne National Laboratory - West, Idaho Falls, ID.
Prog. Nucl. Energy, 39, 305-319 . . . Design Characteristics and Fabrication of Radioisotope Heat Sources for Space Missions. . . . Rinehart, G.H. . . . 2001 . . . Los Alamos National Laboratory, Los Alamos, NM.
Prog. Nucl. Energy, 39, 321-333 . . . Computing the Three-Dimensional Distribution of the Gamma Dose Rate in the Target Service Cell of the Spallation Neutron Source Using the DOORS Package. . . . Azmy, Y.Y.; Johnson, J.O. Lillie, R.A. Rennich, M.J.; Santoro, R.T. . . . 2001 . . . Oak Ridge National Laboratory, Oak Ridge, TN.
Prog. Nucl. Energy, 39, 335-344 . . . A Visual Environment for System Analysis Codes. . . . Kim, K.D.; Jeong, J-J.; Mo, S.Y.; Lee, Y.G.; Lee, C.B. . . . 2001 . . . Korea Atomic Energy Research Inst., Taejon, Korea; Korea Hydro & Nuclear Power Corp., Pusan, Korea.
Prog. Nucl. Energy, 39, 345-351 . . . Application of Fuzzy Decision Making Method to the Evaluation of Spent Fuel Storage Options. . . . Moon, J.H.; Kang, C.S. . . . 2001 . . . Seoul National University, Korea.
Prog. Nucl. Energy, 39, 353-366 . . . Implications Associated with the Sensitivity Analysis of Fast Flux Transmutation Systems. . . . Hoggett-Jones, C.; Robbins, C.; Gettinby, G. Blythe, S. . . . 2001 . . . University of Strathclyde, Glasglow, UK; Grallator, Derbyshire, UK.
Prog. Nucl. Energy, 39, 367-425 . . . Recent Applications of PSA for Managing Nuclear Power Plant Safety. . . . Wall, I.B.; Haugh, J.J.; Worlege, D.H. . . . 2001.