Printable PDF file of this newsletter available at: http://www-rsicc.ornl.gov/NEWSLETTER.html.
Edna Comolander of Oak Ridge died Thursday, Dec. 26, 2002. She was
among the first staffers of the Radiation Shielding Information Center
(RSIC) as the Center was then known. Betty Maskewitz writes "Hemma was
our first programming-troubleshooter and had a remarkable record for checking
out and packaging computer codes. She was a mathematician and was with
RSIC from its beginning to retirement at age 65. As we received all kinds
of computing technology, Hemma's checking and running into systems errors
on local computing systems helped to test every computer operating system
at K-25 and ORNL. She was an RSIC pioneer."
Russian Research Centre (RRC) - Kurchatov Institute is celebrating the centennial anniversary of the birthdays of two renowned scientists-academicians Igor Kurchatov, it's founder, and Anatoly Petrovich Aleksandrov, who followed him as director. Kurchatov was born in the Urals in 1903 and died in 1960 at the age of 57. He is cited as the founder of Soviet nuclear research and technology. These scientists received many honors from the USSR in their years of service. Aleksandrov served until the 1980's. He was replaced by Academician Evgeny Pavlovich Velikhov. He and N. N. Ponomarev-Stepnoy, his deputy, and others well known in the west, are leading the Russian Institute into the new century.
The 60th anniversary of the Institute will be celebrated in 2003 as well. The research institute, then known as the Order-of-Lenin Kurchatov Institute of Atomic Energy (KIAE), was established in 1943 to develop nuclear weapons for the defense of the USSR during WWII. Research was later extended to include fission and fusion reactions in the development of power engineering.
RSIC began to establish relationships with nuclear research scientists and engineers in the former USSR during a visit in 1969 and RSICC continues to seek opportunities for communication in the ensuing years. At the time a nuclear power delegation led by RSIC visited in 1986, the KIAE research was largely devoted to nuclear reactor safety following the Chernobyl disaster. The early 1990's brought new opportunities for scientific exchange with our Russian colleagues.
RRC Kurchatov Institute, called the first Russian national research center, replaced the former KIAE and reports directly to the government. Current work at the institute includes research on fission and fusion reactors, accelerators, and large computers.
In today's political environment, there should be few barriers to interaction between the scientists of the world. We're proud that RSICC continues to lead the way.
Betty F. Maskewitz
The following was taken from the ANS News, Nov./Dec. 2002 issue.
Nine newly elected Fellows of the American Nuclear Society were recognized
at the Honors and Awards Luncheon held during the 2002 ANS Winter Meeting
last November. The grade of Fellow - the highest grade of ANS membership
- is conferred upon members who have made significant contributions to
the advancement of nuclear science and technology. Please check the ANS
issue for more information on each Fellow. The Fellows are Fan-Bill
Cheung, professor at Pennsylvania State University; Alireza Haghighat,
professor and chair of the Nuclear and Radiological Engineering Dept. at
the University of Florida; Brian K. Hajek, professor and associate
chair of the nuclear engineering program at Ohio State University; K.
Linga Murty, program director, National Science Foundation; Jean-Louis
Nigon, deputy vice president of Cogema; Michael Z. Podowski,
professor at Rensselaer Polytechnic Institute, Robert E. Schenter,
staff scientist at Pacific Northwest National Laboratory; David Stahl,
materials specialist at Framatome ANP; and Michael Todosow, nuclear
engineer at Brookhaven National Laboratory.
Charles B. Meinhold has been selected to give the 27th Lauriston
S. Taylor Lecture at the 2003 Annual Meeting of the National Council on
Radiation Protection and Measurements (NCRP). The lecture, entitled The
Evolution of Radiation Protection: From Erythema to Genetic Risks to Risk
of Cancer to ?, will be a featured presentation at the 39th Annual
Meeting of the NCRP to be held April 9-10, 2003. The lecture will be given
at the Crystal City Marriott, Arlington, Virginia, on the 9th. The lecture
series honors Dr. Lauriston S. Taylor, the founding President of the NCRP.
One new package and one updated with a new PC version were added to
the computer code collection this month.
Los Alamos National Laboratory, Los Alamos, New Mexico, contributed PARTISN (PARallel, TIme-Dependent SN) release 2.99. PARTISN solves the linear Boltzmann transport equation for neutral particles using the deterministic (SN) method. Both the static (fixed source or eigenvalue) and time-dependent forms of the transport equation are solved in forward or adjoint mode. Vacuum, reflective, periodic, white, or inhomogeneous boundary conditions are solved. General anisotropic scattering and inhomogeneous sources are permitted. PARTISN solves the transport equation on orthogonal (single level or block-structured AMR) grids in 1-D (slab, two-angle slab, cylindrical, or spherical), 2-D (X-Y, R-Z, or R-T) and 3-D (X-Y-Z or R-Z-T) geometries.
PARTISN is the evolutionary successor to CCC-547/DANTSYS. User input and cross section format is very similar to that of the DANTSYS code. PARTISN accepts basic multigroup cross sections for isotopes, in either of the standard interface files (ISOTXS or GRUPXS) or in a card-image library whose form is referred to as Los Alamos, ANISN, or FIDO. Standard interface files whose specifications have been defined by the Reactor Physics Committee on Computer Code Coordination are accepted, used, and created by the code. A free-field card-image input capability is provided for the user. The code provides the user with considerable flexibility in using both card-image or sequential file input and in controlling the execution of modules. Note that no cross section data are included in the package.
The current release is designed for UNIX-like systems and is written in ANSI standard F90 with a few C language routines used to interface to the Unix operating system. There is no Windows version, and it has not been run successfully on Sun workstation. PARTISN stresses most F90 compilers, so please ensure that the compiler version you are using is at least as recent as those listed below on which the LANL developers ran the code system.
• Cray CF90 Version 126.96.36.199
RSICC tested this release in parallel and serial modes on an IBM SP3 machine and on an Intel PC running Linux. A non-parallel executable file compiled with Lahey/Fujitsu Fortran 95 L6.10a under Red Hat Linux 7.3 is included in the distribution file.
Parallelization is performed using MPI 1.1. The program is designed
to run on UNIX-like operating systems. In addition to Fortran and C compilers,
program building requires GNUmake (Version 3.74 or later), GNU awk (Version
3.0 or later), and cpp. The package is transmitted on a CD which includes
documentation, source files, a Linux executable, installation procedures,
and a test case in a GNU compressed tar file. References: Transport Methods
Group, Los Alamos National Laboratory (November 2002). Fortran 90 and C;
Cray, SGI, IBM, HP 9000, Alpha, Intel Linux PC (C00707/MNYCP/00).
The COGAP package was updated with the addition of a PC version contributed by Exelon Nuclear, Kennett Square, Pennsylvania. COGAP was developed around 1982 on CDC computers at Los Alamos National Laboratory, Los Alamos, New Mexico. It evaluates nuclear power plant containment hydrogen control systems by determining the node (compartment) concentrations of hydrogen, oxygen, nitrogen, and steam, assumed to be ideal gases. The nodes are assumed to be homogeneous and in chemical equilibrium, that is, lumped-parameter nodes. Effects accounted for include: reaction of zirconium and water; radiolysis of core and sump water; corrosion of zinc, aluminum, and copper; recirculation between compartments; hydrogen recombiners; purging; nitrogen addition; and atmospheric steam. Controls are available to determine when options are initiated, e.g., hydrogen recombiners can be started when the hydrogen concentration reaches a user-specified value or after a user-specified time.
At Exelon Nuclear, the CDC source files were converted to run on a Dell
PII-366 Laptop under Windows 2000 using the Compaq Visual Fortran Version
6.5 compiler. The PC source files and executable were added to the RSICC
CDC package. The new package is transmitted on a CD which includes the
source, information files, Windows executable, test problem input and output,
and referenced document. Reference: NUREG/CR-2847 (LA-9459- MS) (January
1983). Fortran; CDC and PC Windows 95/98/2000 (P00375/MNYCP/01).
As years have gone by many different codes and applications have been
sent to RSICC for stewardship. We currently have over 1700 analytical code
and data packages and distribute as many each year to 73 countries in the
world. To help 'categorize' each package, we have developed a database
of 'Subject Categories' to attach applications to the packages at RSICC.
Doing so requires investigation into each code package, user feedback from
end use statements, and extensive RSICC staff experience and analysis so
that we can deliver useful information each month on the 30 different categories
we have identified thus far. Links to the package abstracts are embedded
into the WWW version of the RSICC Newsletter. Feedback from our Newsletter
community is very valuable so please direct your comments and/or suggestions
to PDC@ORNL.GOV. Many packages in the
RSICC code collection are in this subject category. A few are highlighted
here for your review.
Nuclear System Safety Analysis
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. Should you be involved in the planning/organization of such events, feel free to send your announcements and calls for papers via email to FINCHSY@ornl.gov with "conferences" in the subject line by the 20th of each month. Please include the announcement in its native format as an attachment to the message. If the meeting is on a website, please include the url.
Every attempt is made to ensure that the links provided in the Conference and Calendar sections of this newsletter are correct and live. However, the very nature of the web creates the possibility that the links may become unavailable. In that case, please call or mail the contact provided. Below is a condensed list of the conferences only. More details are listed following the table.
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.
The success of this meeting depends on your active support and involvement.
Finally, please bookmark the conference web site: http://rpd.ans.org/nfm.htm
and visit it occasionally for news and updates. Comments and suggestions
are most welcome.
The American Nuclear Society (ANS) and the European Nuclear Society (ENS) have agreed to bundle their conference activities concerning nuclear fuel. The well established ANS "LWR Fuel Performance Meeting" and the ENS "TopFuel Conference" will from now on be jointly held, alternating the location between the USA and Europe.
The first joined conference will be organized by the local nuclear society
in Germany, the KTG (Kerntechnische Gesellschaft e.V.) from March 16-19,
2003, at Würzburg. The program will comprise invited and contributed
papers. Please visit the website for more information: http://www.topfuel2003.de.
The 2003 IEEE Nuclear and Space Radiation Effects Conference (NSREC) will be held in Monterey, California, July 21-25, 2003. This annual meeting of engineers and scientists presents the latest techniques for enhancing the performance of microelectronic devices and circuits that are used in radiation environments. The final call for papers for the 2003 IEEE Nuclear and Space Radiation Effects Conference (NSREC) is available on the web site at www.nsrec.com. Deadline for submission is February 7, 2003.
Make plans for the 2003 short course in Monterey. Joe Benedetto and his team of professors have put together an interesting program about radiation effects on device scaling. The syllabus is at www.nsrec.com/short.htm.
Forms to nominate an outstanding colleague for the 2003 Radiation Effects Award are at www.nsrec.com/nominate.htm. This award comes with a handsome IEEE plaque and $2000 check.
University professors - Forms are available on the NSREC web site to nominate an outstanding student for the 2003 IEEE NPSS Phelps Continuing Education Grant. The cash award ($500 - $1000) comes with an IEEE certificate and complimentary short course registration. NSREC plans to award two grants this year. See www.nsrec.com/steering.htm.
Keep checking the web site at www.nsrec.com
for the latest NSREC information. Contact Paul Dodd, Sandia National Laboratories,
505-844-1447 if you have questions.
We are pleased to announce the call for papers for the "2003 International Congress on Advanced Nuclear Power Plants" (ICAPP '03) which will be held in Cordoba, Spain, May 4-7, 2003, at the Congress Palais. Please make note of the October 15, 2002 deadline for abstracts.
Following the highly successful ICAPP '02 meeting held in Hollywood, Florida, this international congress will bring together international experts of the nuclear industry involved in the operation,
development, building, regulation, and research related to nuclear power plants. The conference is sponsored by the leading nuclear societies of Europe, Asia, and the USA.
The program will cover the full spectrum of nuclear power plant issues
from design, deployment and construction of plants to research and development
of future designs and advanced systems. The program is expected to cover
lessons learned from power, research and demonstration reactors from over
50 years of experience with operation and maintenance, structures, materials,
technical specifications, human factors, system design, and reliability.
You may visit the ICAPP '03 website at www.ans.org/goto/
icapp03 for updated information on the congress and to download a copy
of the Call For Papers.
The 7th International Conference on Nuclear Criticality Safety (ICNC2003)
will be held October 20-24, 2003, in Tokai-mura, Japan. This conference
has been held approximately every 4 years under the support of OECD/Nuclear
Energy Agency/Nuclear Science Committee. The last conference hosted by
Japan, was the 3rd conference held in Tokyo in 1987. In the Versailles
conference held in 1999, over 300 people from 25 countries participated,
and more than 200 presentations were given on the recent activities in
research work, industrial applications, regulatory studies, and other topics
related to criticality safety. ICNC2003 will provide a good opportunity
for communication among researchers, engineers, plant operators, and regulators.
The Conference will consist of invited talks, contributed talks, and poster
sessions. On the final day of the conference, technical tours to nuclear
facilities are scheduled, and social programs are planned during conference.
Please see the website for more information: http://www.icnc.jp/.
The conference will be held in Oxford, England, September 21-25, 2003. Session M-6 - Applying Strategic Planning, Decision-making, and Risk Reduction Methodologies in EM, includes the following:
-- Applications of strategic planning, decision-making, and/or risk reduction methodologies and tools (e.g., roadmapping) to resolve environmental management issues Innovative approaches to decision-making to resolve problems/issues related to environmental management
-- Innovative approaches to assessing risk and cost-effective reduction of risk for issues related to environmental management
-- Innovative approaches to strategically plan for and implement science and technology (S&T) to resolve environmental barriers to project completion
-- Ways to effectively integrate strategic planning, decision-making, and risk reduction techniques and tools to resolve environmental management issues
-- Methodologies used in developing the sites' plans to meet DOE EM's goals of site closures, cost savings, schedule acceleration, and risk reduction
Additional details on the ICEM conference are on the website at http://www.icemconf.com.
The System Safety Society is pleased to announce the 21st International
System Safety Conference, August 4-8, 2003, in Ottawa, Ontario,
Canada. The conference is an international forum for the technical presentation
and discussion of all aspects and issues regarding system safety engineering
and management. The conference theme is "Broader Perspectives, Focused
Solutions." The emphasis is on the knowledge and skills necessary to create
system safety solutions for increasingly complex technologies and missions.
The range of topics will cover both the art and science of system safety
and the organizational issues influencing the effective management of system
safety in the product life cycle. This is the major conference for system
safety and related professions, with a week of technical sessions, tutorials,
workshops, special events, social affairs, luncheons, and the society's
awards banquet. The conference proceedings are the premier collection of
work in the system safety field. For more information, please visit: http://www.russona.com/issc21/.
The 9th International Symposium on Radiation Physics (ISRP-9) will be
held in Cape Town, South Africa, October 27-31, 2003. This triennial
event will be organized jointly by the International Radiation Physics
Society ( IRPS ) and iThemba Laboratory for Accelerator Based Sciences
( iThemba LABS) [formerly the National Accelerator Centre]. The Symposium
is the latest in a series which began in Calcutta in 1974 and thereafter
continued in Penang (1982), Ferrara (1985), São Paulo (1988), Dubrovnik
(1991), Rabat (1994), Jaipur (1997) and Prague (2000). A 2½ day
"Workshop on Radiation-Based Analytical Techniques" (WoRBAT) will be held
prior to ISRP-9 (October 24-26, 2003) with emphasis on x-ray fluorescence
and diffraction (XRF, XRD) and particle-induced x-ray emission (PIXE).
For more information, please visit www.medrad.tlabs.ac.za/isrp9.htm.
The American Nuclear Society's Mathematics and Computation Topical Meeting, M&C 2003, will be held in Gatlinburg, Tennessee, April 6-10, 2003. The unique setup for this conference, entitled "Nuclear Mathematical and Computational Sciences: A Century in Review, A Century Anew," promises to provide an exciting and unprecedented opportunity for students and professionals in the field to learn about its rich intellectual heritage from leading figures. The Review section of the conference is comprised of eight lectures on selected topics of common interest to the membership of the Mathematics and Computation Division, the primary sponsor of the meeting. The Anew section of the meeting will include contributed and invited papers on standard topics in this series of conferences. Please refer to the conference web site http://meetingsandconferences.com/MC2003/ for details on the lecture series and lecturers, a list of topics for contributed papers and special sessions, author instructions, and general information about the conference.
The web site for M&C 2003 is now open for submitting papers. Please
check the "Call for Papers" link to learn about the topics of interest
in this conference, including special session topics. The "Authors" link
has templates for preparing full papers in MS Word, WordPerfect, and LaTeX.
Please note that abstract submission is not required due to the Math &
Computational Sciences Division's policy of reviewing only full papers
for inclusion in meetings where the division is the primary sponsor. We
look forward to welcoming you to Gatlinburg.
The introductory class is for people who have little or no experience with MCNP. The intermediate to advanced class will be held for people who have used MCNP and want to extend their knowledge and understanding of the code system.
The classes will be based on MCNP5. The code and data package will be available through RSICC at a reduced rate to class participants. The new capabilities of version 5 will be covered.
The other capabilities on MCNP will also be covered, including: basic and advanced geometry, source definitions, tallies, data, variance reduction, statistical analysis, criticality, plotting of geometry, and particle tracks, neutron/photon/electron physics.
All classes provide interactive computer instruction. Time will be available
to discuss individual questions and problems with MCNP experts or to pursue
in more detail topics mentioned in the talks. Please note that other classes
are offered based on MCNP. The classes mentioned here are the only ones
that are taught by the people who develop and write MCNP.
The Visual Editor is a powerful visualization tool that can be used to rapidly create complex Monte Carlo N Particle (MCNP 4C2) geometry models, including lattices, universes, fills, and other geometrical transformations. The Visual Editor can:
Display MCNP 4C2 geometries in multiple plot windows,
Two classes are scheduled June 2-6, 2003, and September 8-12, 2003, both in Richland, Washington. The class will focus on the use of the visual editor, with an overview of MCNP. The fifth day is optional and will focus on using the Visual Editor and MCNP to do some example problems.
Class will include computer demonstrations and exercises that will focus on creating and interrogating input files with the Visual Editor. Advanced visualization work using MCNP will also be demonstrated. The class will be taught on Pentium computers running the Linux operating system and Windows NT. Class attendees can use either the Linux or Windows version of the visual editor. Attendees are encouraged to bring their own input files for viewing and modifying in the visual editor. Further information on this class can be located at: http://www.mcnpvised.com/train.html, or by contacting Randy Schwarz (email email@example.com).
Lead Teachers: Drs. John Hendricks, Gregg McKinney, Laurie Waters
MCNPX is the LANL all-particle, all-energy (eV-TeV) Monte Carlo transport code based on MCNP4C, LAHET, CEM, etc. MCNPX has been in active development since 1995, sponsored by the particle accelerator community. It has now become an accepted tool for a broad range of applications by nuclear engineers, physicists, and scientists. The MCNPX development effort has expanded the use of the Los Alamos tools to applications such as APT, waste transmutation, accelerator shielding and health physics, particle beam cancer therapy, space shielding and cosmic ray analysis, single event effects in semiconductors, radiography, and more detailed analysis of the effects of light and heavy ions in matter. In addition, the entire functionality of MCNP4C is retained. New variance reduction and data analysis techniques, many adapted from high energy accelerator methodologies, have also been added, such as the extensive 'mesh tally' capability which allows up to 3-d plotting of particle tracks, fluence and fluence-derived quantities, energy deposition, next event estimator generation contributions and particle sources.
The workshops include hands-on instruction, generally on PC Windows machines. Subject to participant export approval for the MCNPX beta test team, participants will be able to access the Fortran-90 version of MCNPX 2.4, the LA150 (150 MeV) cross-section data for over 40 isotopes for incident neutrons and protons, and 12 for photonuclear interactions, and a notebook of viewgraphs. Follow-up consultation for class participants will be provided.
Classes are taught by experienced MCNPX code developers and instructors.
More information on code versions and capabilities is available at MCNPX
Workshops web site http://mcnpxworkshops
The "Workshop on Nuclear Data for the Transmutation of Nuclear Waste" will be held September 1-5, 2003, at GSI-Darmstadt, Germany. The workshop is organized on the occasion of the end of the HINDAS research program, a collaboration of several European Institutes working on the subject of "High and Intermediate Nuclear Data for Accelerator Driven Systems." Please note that the topics included in the workshop are not restricted to the HINDAS research program. All contributions to the subject of the workshop are more than welcome.
The workshop time-schedule will be organized in the following way: Monday, September 1, 2003, will be dedicated to a closed HINDAS meeting. On Tuesday, the open sessions will start and last till the end of the workshop on Friday, September 5, 2003.
Those who are interested in participating in the workshop are invited
to register (no fee) before August 1, 2003, using the workshop website
There is also information on workshop topics, accommodations, transportation,
and key dates. Please contact Aleksandra Kelic, A.Kelic@gsi.de
if you have questions.
DATE: June 16-20, 2003 (4.5 days)
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. Students will 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 HSR-4, MCNP Class/David Seagraves, Mail Stop J573, Los Alamos, NM 87545.
This course is offered by the Health Physics Measurements Group at LANL and is a completely separate offering from the other courses offered by other groups at Los Alamos.
Inquiries regarding registration and class space availability should
be made to David Seagraves, 505-667-4959, fax: 505-665-7686, e-mail: firstname.lastname@example.org.
Technical questions may also be directed to Dick Olsher, 505-667-3364,
The Radiation Process Simulation and Modeling User Group (RPSMUG) announces
its annual meeting to be held
April 22-23, 2003, at the National
Institute of Standards and Technology in Gaithersburg, Maryland. The meeting
will consist of technical presentations, round-table discussions and informational
sessions related to the use of mathematical models and simulation in radiation
processing (gamma, electron beam, and x-ray). New RPSMUG officers will
be installed at this time. Please click on announcement
RSICC is pleased to announce that a five-day workshop on Oak Ridge National Laboratory's (ORNL) SAMMY code will be held May 12-16, 2003, in Knoxville, Tennessee. This training course is intended for those who are interested in the theory of neutron cross sections in the resonance region, and in the use of SAMMY for the analysis of experimental neutron-induced cross-section data for extracting values and covariances for resonance parameters. Both novice and experienced SAMMY users would benefit from the intensive and extensive examination of all aspects of resonance parameter analyses.
During the workshop, lectures and computer applications will alternate. Lectures will include both theoretical discussion and practical examples for each topic. The lecturer is Dr. Nancy Larson of the Nuclear Data and Information Analysis Group, Nuclear Science and Technology Division of ORNL, author of the SAMMY code.
Topics include (but are not limited to) the following:
II. Simulation of experimental conditions
III. Mathematical methods used for experimental data-fitting
IV. Reporting results for Evaluated Nuclear Data Files
V. Features in the latest version of the analysis code SAMMY
The workshop will include hands-on computer applications using the latest version of SAMMY (M6). Computer exercises will lead participants through the various features of the code beginning with simple examples and leading to realistic situations. Participants who are experienced SAMMY users are encouraged to bring their own examples as well.
The number of PC workplaces available at the training center restricts
the number of workshop participants accepted. Therefore, we encourage you
to register as early as possible. The SAMMY workshop web site with further
detailed information and on-line registration can be accessed at http://www-rsicc.ornl.gov/SAMMY/intro.html).
Please bookmark the site and visit it occasionally for news and updates
as they become available.
Version 5 of the SCALE software system is scheduled for release in 2003. This half-day tutorial workshop will highlight signficant new computational capabilities in SCALE 5 plus current developments that will appear in later SCALE releases. The workshop will be part of the American Nuclear Society M&C 2003 Topical Meeting in Gatlinburg, Tennessee. The workshop will be hosted by Oak Ridge National Laboratory at the conference hotel in Gatlinburg on Thursday afternoon April 10, 2003, immediately following the final technical sessions of the topical meeting.
The workshop will feature presentations on the following new computational capabilities to be released in SCALE 5:
· SEN3 3-D sensitivity/uncertainty sequence (using KENO V.a)
Plus, the workshop will also feature presentations on the following developments planned for release:
· Continuous energy version of the KENO V.a criticality safety
The registration fee is $200. You can register online at www.ornl.gov/scale/register_scale5.html
or as part of your M&C 2003 registration. The early registration deadline
is February 28, 2003.
The Forum will be held March 24-27, 2003, at the Crystal Gateway Marriott Hotel, which is conveniently located in Arlington, Virginia.
The Program Committee is now accepting presentation proposals for the Software Quality Forum 2003 (SQF 2003). The Forum offers an exciting opportunity for software professionals in the Department of Energy (DOE), other government agencies, private industry, and academia to share their knowledge about trends and technologies in the acquisition, development, support, and management of software intensive systems. Well-known keynote speakers, tutorials on key Forum topics, a showcase for high-visibility IT projects using cutting-edge technologies, and a vendor exhibit area are included in the program.
This is a tri-annual event sponsored by the Software Quality Assurance Subcommittee (SQAS) of the Quality Managers within the DOE Nuclear Weapons Complex. The 2003 Forum is co-hosted by the DOE Office of the Chief Information Officer and the National Nuclear Security Administration, Office of Advanced Simulation and Computing within the Office of Defense Programs.
For more information visit the web site http://cio.doe.gov/sqas.
Look for the "Forum 2003" heading on the left side of the home page. There
will be a website devoted to the SQF 2003 in a week or so, which will be
linked from the above website. If you have questions, send email to Kathleen
Canal at kathleen.canal@ hq.doe.gov.
If interested in submitting a presentation proposal, please contact Brenda
Coblentz, Program Committee Chair, at
The "Supercomputing in Nuclear Applications" SNA-2003 conference will be held in Paris, September 22-24, 2003. The web pages (http://sna-2003.cea.fr/) have been expanded to include information on tours, sightseeing and events scheduled at the time of the conference.
One of the events at SNA-2003 is linked to the museum of "arts et metier",
literally of arts & crafts; art is here used in its primary meaning:
skills acquired through studies and by practice, technical knowledge. In
this museum are displayed among many other items the "supercomputer" of
1642: arithmetical machine by Blaise Pascal, the original pendulum of Foucault
(1851) or the instrument he developed to measure the speed of light (1852),
or a decimal clock with a day of 10 hours each of 100 minutes and a minute
of 100 seconds etc. Abstracts can be submitted
14th Annual U.S. Hydrogen Meeting, Mar. 4-6, 2003, Washington, DC. Contact: Catherine E. Grégoire Padró (tel 303-275-2919, fax 303-275-2905, email email@example.com, url http://www.hydrogenconference.org/).
ANS Topical Meeting, Nuclear Mathematical and Computational Sciences: A Century in Review, A Century Anew, Apr. 6-10, 2003, Gatlinburg, TN. Co-sponsored by the American Nuclear Society's Reactor Physics, and Radiation Protection and Shielding Divisions, as well as the ANS Oak Ridge/Knoxville Local Section, Oak Ridge National Laboratory's Radiation Safety Information Computational Center, the Nuclear Energy Agency of the OECD, the Korean Nuclear Society, and the Canadian Nuclear Society. Contacts: Yousry Azmy (tel 814-865-0039, email firstname.lastname@example.org or Bernadette Kirk (tel 865-74-6176, email email@example.com, url http://meetingsandconferences.com/MC2003/index.html).
Visual Editor for MCNP, Apr. 6, 2003, Gatlinburg, TN. Contact: Randy Schwartz (url http://www.mcnpvised.com/ved/class7.html).
39th NCRP Meeting, Apr. 9-10, 2003, Arlington, VA. Contact: William Beckner (tel 301-657-2652, fax 301-907-8768, url http://www.ncrp.com).
Radiation Process Simulation and Modeling User Group, Apr. 22-23, 2003, Gaithersburg, MD. Contact: Mark Smith (tel 704-587- 8914, email firstname.lastname@example.org).
Radiation Transport Calculations using the EGS Monte Carlo System, May 5-8, 2003, 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, email email@example.com, url http://www.irs.inms.nrc.ca/inms/irs/papers/ egsnrc/brochure.html).
Practical MCNP For The HP, Medical Physicist, And Rad Engineer, June 16-20, 2003, Los Alamos, NM. Contact: David Seagraves (tel 505-667-4959, fax 505-665-7686, email firstname.lastname@example.org, url drambuie.lanl.gov/~esh4/mcnp.htm).
Intercomparison on the Usage of Computational Codes in Radiation Dosimetry, July 14-16, 2003, Bologna, Italy. Contact: Gianfranco Gualdrini (tel 39-051-6098350, fax 39-051-6098003, email guald@bologna. enea.it, url http://www.nea.fr/ download/quados/quados.html).
2003 IEEE Nuclear and Space Radiation Effects Conference (NSREC), July 21-25, 2003, Monterey, CA. Contact: Paul Dodd (tel 505-844-1447, url http://www.nsrec.com).
Workshop on Nuclear Data for the Transmutation of Nuclear Waste, Sept. 1-5, 2003, GSI-Darmstadt, Germany, Contact: Aleksandra Kelic (tel 49-0- 6159-71-2727, fax 49-0-6159-71-2785, email A.Kelic@gsi.de, url http://www-wnt.gsi.de/tramu).
Nuclear Energy for New Europe 2003, Sept. 8-11, 2003, Portorož, Slovenia, Contact: Tomaz Zagar (phone +386-1-588-5450, fax +386-1-561-2335, email PORT2003@ijs.si, url http://www.drustvo -js.si/port2003/).
9th International Conference on Environmental Remediation and Radioactive Waste Management, Sept. 21-25, 2003, Oxford, England. Contact: (url www.icemconf.com).
International Conference on Supercomputing in Nuclear Applications, SNA 2003, Sept. 22-24, 2003, Paris, France. Organizers: CEA, SFANS, co-organizer: OECD/NEA. (email SNA-2003@ cea.fr, 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, SC. Contact: Youssef A. Shatilla (email email@example.com, url http://rpd.ans.org/nfm.htm).
7th International Conference on Nuclear Criticality Safety (ICNC2003), Oct. 20-24, 2003, Contact: Dr. Yoshinori Miyoshi (tel +81-29-282-6671; fax +81-29-282-6798, email firstname.lastname@example.org. jaeri.go.jp, url http://www.icnc.jp/).
9th Triennial International Symposium in Radiation Physics, Oct. 27-31, 2003, Cape Town, South Africa. Contact: Dr. D. T. L. Jones (tel +27-21-843-1336, fax +27-21-843-3382, email Jones@tlabs.ac.za url www.medrad. tlabs.ac.za/isrp9.htm).
The 11th International Conference on Fusion Reactor Materials (ICFRM-11),
Dec. 7-12, 2003, Kyoto, Japan. Contact ICFRM-11 secretariat ( tel +81-774-38-3597,
fax +81-774-38-3467, email email@example.com,
The nuclear systems literature (shielding, safety, materials) cited below has been reviewed and placed in the RSICC Information Storage and Retrieval Information System (SARIS), now searchable on the RSICC web server (http://www-rsicc.ornl.gov/SARIS.html). We now include medical physics in addition to material science, radiation dosimetry, radiation safety, reactor dynamics, reactor safeguards, risk assessment, waste management, fuel cycle, fusion and plasmas, high energy particle transport, and shielding. This early announcement is made as a service to the nuclear sciences community. Copies of the literature are not distributed by RSICC. They may generally be obtained from the author or from a documentation center such as the National Technical Information Service (NTIS), Department of Commerce, Springfield, Virginia 22161. For literature listed as available from INIS contact INIS Clearinghouse, International Atomic Energy Agency, P.O. Box 100, A-1400 Vienna.
Nucl. Eng. Design, 219, 197-206. . . Investigation on Constraint Effect of Reactor Pressure Vessel Under Pressurized Thermal Shock. . . .Kim, J-Su. et al.. . . February 2003. . . Sungkyunkwan University, South Korea; Korea Institute of Nuclear Safety, Taejon, South Korea.
Nucl. Eng. Design, 219, 207-223. . . A Preliminary Design Study for the HYPER System. . . .Park, W.S. et al. . . . February 2003. . . Korea Atomic Energy Research Institute, Daejeon, Republic of Korea.
Nucl. Eng. Design, 219, 225-245. . . Space-Dependent Kinetics Simulation of a Gas-Cooled Fluidized Bed Nuclear Reactor. . . .Pain, C.C. et al. . . . February 2003. . . Imperial College of Science, Technology and Medicine, London; Delft University of Technology, JB Delft, The Netherlands.
Nucl. Eng. Design, 219, 247-252. . . Optimal Power Control System of a Research Nuclear Reactor. . . .Yeung, R.M.K.; Cheung, K.C.; Zhao, F . . . February 2003. . . Xi'an Jiaotong University, Shaanxi, PR China; The University of Hong Kong, Hong Kong.
Nucl. Eng. Design, 219, 253-267. . . Convergence Problems Associated with the Iteration of Adjoint Equations in Nuclear Reactor Theory. . . .Ngcobo, E. . . . February 2003. . . University of South Africa, Pretoria, South Africa.
Nucl. Eng. Design, 219, 269-276. . . Development of Automatic Algorithm for Localizing Loose Parts with A Steam Generator.. . .Kim, J.S. et al.. . . February 2003. . . Korea Atomic Energy Research Institute, Daejon, South Korea; ChungNam National University, Daejon, South Korea.
Nucl. Eng. Design, 220, 17-35. . . Analysis of the Critical Heat Flux in Round Vertical Tubes Under Low Pressure and Flow Oscillation Conditions. Applications of Artificial Neural Network.. . .Su Guanghui et al.. . . March 2003. . . Xi'an Jiaotong University, Xi'an City, PR China; Kyushu University, Fukuoka, Japan; VTT Energy, Espoo, Finland.
Nucl. Eng. Design, 220, 37-50. . . Numerical Investigation of Multi-Dimensional Characteristics in Sodium Combustion. . . .Maekawa, I.; Yamaguchi, A.; Takata, T. . . . March 2003. . . Japan Nuclear Cycle Development Institute, Ibaraki, Japan; Kawasaki Heavy Industries, Tokyo, Japan.
Nucl. Eng. Design, 220, 51-65. . . Comparison of Two Models for a High Temperature Reactor Coupled to A Gas Turbine. . . .Verkerk, E.C.; Kikstra, J.F. . . . March 2003. . . Nuclear Research and Consultancy Group, Petten, The Netherlands; Delft Technical University, CD Delft, The Netherlands.
Nucl. Eng. Design, 220, 67-81. . . Effects of Tube Inclination on Pool Boiling Heat Transfer.. . .Kang, M-G.. . . March 2003. . . Andong National University, Kyungbuk, South Korea.
Nucl. Eng. Design, 220, 83-90. . . Axial-Flow-Induced Vibration for a Rod Supported by Translational Springs at Both Ends.. . .Kang, H.S. et al.. . . March 2003. . . KAERI, Daejon, South Korea.
Nucl. Eng. Design, 220, 91-97. . . Significance of Analytical Modelling for Complete Interpretation of Experimental Modal Analysis: A Case Study.. . .Sinha, J.K.; Moorthy, R.I.K.; Rao, A.R. . . . March 2003. . . Bhabha Atomic Research Center, Kalpakkam, India.
Prog. Nucl. Energy, 41, 1-3. . . An International Cooperation to Improve Delayed Neutron Data. . . .D'Angelo, A. . . . 2002. . . ENEA/CASACCIA, Rome, Italy.
Prog. Nucl. Energy, 41, 5-38. . . Overview of the Delayed Neutron Data Activities and Results Monitored by the NEA/WPEC Subgroup 6.. . .D'Angelo, A. . . . 2002. . . ENEA/ CASACCIA, Rome, Italy.
Prog. Nucl. Energy, 41, 39-69. . . Status of Delayed-Neutron Precursor Data: Half-Lives and Neutron Emission Probabilities.. . .Pfeiffer, B.; Kratz, K-L . . . 2002. . . Universitat Mainz, Germany.
Prog. Nucl. Energy, 41, 71-107. . . Delayed Neutron Study Using ENDF/B-VI Basic Nuclear Data.. . .England, T.R.; Wilson, W.B. . . . 2002. . . Los Alamos National Laboratory, Los Alamos, NM.
Prog. Nucl. Energy, 41, 109-116. . . Possible Fluctuations in the Delayed Neutron Yields in the Resonance Region of U-235.. . .Ohsawa, T.; Oyama, T. . . . 2002. . . Kinki University, Osaka, Japan.
Prog. Nucl. Energy, 41, 117-124. . . Delayed Neutrons as a Probe of Nuclear Charge Distribution in Fission of Heavy Nuclei by Neutrons.. . .Isaev, S.G. et al.. . . 2002. . . Institute of Physics and Power Engineering, Kaluga Region, Russia.
Prog. Nucl. Energy, 41, 125-133. . . Study of Delayed Neutron Decay Curves from Thermal Neutron Induced Fission of 235U and 239Pu. . . .Borzakov, S.B. et al. . . . 2002. . . Joint Institute for Nuclear Research, Dubna, Russia.
Prog. Nucl. Energy, 41, 135-144. . . Experimental Studies of the Absolute Total Delayed Neutron Yields From Neutron Induced Fission of 238U in the Energy Range 1-5 MeV. . . .Piksaikin, V.M. et al.. . . 2002. . . Institute for Physics and Power Engineering, Kaluga Region, Russia.
Prog. Nucl. Energy, 41, 145-201. . . A Summary of Measured Delayed Neutron Group Parameters.. . .Spriggs, G.D.; Campbell, J.M. . . . 2002. . . Los Alamos National Laboratory, Los Alamos, NM.
Prog. Nucl. Energy, 41, 203-222. . . Energy Dependence of Relative Abundances and Periods of Delayed Neutrons from Neutron-Induced Fission of 235U, 238U, 239Pu in 6- and 8-Group Model Representation. . . .Piksaikin, V.M.. . . 2002. . . Institute of Physics and Power Engineering, Kaluga Region, Russia.
Prog. Nucl. Energy, 41, 223-251. . . An 8-Group Delayed Neutron Model Based on a Consistent Set of Half-Lives.. . .Spriggs, G.D.; Campbell, J.M. . . . 2002. . . Los Alamos National Laboratory, Los Alamos, NM.
Prog. Nucl. Energy, 41, 253-283. . . 8-Group Delayed Neutron Spectral Data for Hansen-Roach Energy Group Structure. . . .Spriggs, G.D.; Campbell, J.M. . . . 2002. . . Los Alamos National Laboratory, Los Alamos, NM.
Prog. Nucl. Energy, 41, 285-301. . . Summary on International Benchmark Experiments for Effective Delayed Neutron Fraction (Beff). . . .Okajima, S. et al.. . . 2002. . . JAERI, Ibaraki-ken, Japan; CEA, Saint-Paul-lez-Durance, France.
Prog. Nucl. Energy, 41, 303-315. . . Application of Different Delayed Neutron Data Sets to the Analysis of Rod Drop Experiments on VVER Cores.. . .Svarny, J.. . . 2002. . . SKODA, Plzen, Czech Republic.
Prog. Nucl. Energy, 41, 317-359. . . Recommended Values of the Delayed Neutron Yield for: U-235; U-238 and Pu-239. . . .Fort, E. et al.. . . 2002. . . no address given.
Prog. Nucl. Energy, 41, 361-384. . . Characteristics of Delayed Neutrons: Systematics and Correlation Properties.. . .Piksaikin, V.M. et al.. . . 2002. . . Institute of Physics and Power Engineering, Kaluga Region, Russia.
Prog. Nucl. Energy, 41, 385-389. . . Simulation of Delayed Neutrons Using MCNP. . . .Werner, C.J. . . . 2002. . . Los Alamos National Laboratory, Los Alamos, NM.
Prog. Nucl. Energy, 41, 391-412. . . Conclusions Concerning the Delayed Neutron Data for the Major Actinides.. . .D'Angelo, A.; Rowlands, J.L. . . . 2002. . . ENEA, Rome, Italy.