Printable PDF file of this newsletter available at: http://www-rsicc.ornl.gov/NEWSLETTER.html.
In view of Dr. Callihan's very important work in the field of nuclear criticality experimentation, I asked several of his colleagues to share in a tribute to his work. Because his personality was shaped by his many interests, I asked other associates to share in this tribute as well. Several qualities in his character appeared in each testimony. He was a gentleman, dedicated to his work, generous to his friends and colleagues, precise and careful in the exposition of technical material, an effective diplomat, an enthusiast for the arts (whether it be folk dancing or high opera), and he contributed to his social community as well as the scientific community. "By personality he was superbly suited to be the founder of the field of systematic criticality experimentation" (Weinberg). His respect for words and dedication to their proper use served him well as the founding editor of Nuclear Science and Engineering. As a leader in the definition and evolution of the science of criticality safety, it probably shouldn't come as a surprise that he was also the first male Girl Scout Leader of record in Oak Ridge. Space in this newsletter is limited, so the complete tribute is included as a weblink.
Alice Rice / RSICC
Nuclear Community Needs for Free Computational Expert Consulting
Go back and take a look at Mr. Ford's quote for this month. The loss of legacy knowledge is one of the issues that prompted RSICC's proposal to create a center to assess and meet the needs of those who require a little more than a readme file or an enotebook to get the codes acquired from RSICC up and ready to solve practical problems in radiation shielding, transport, and protection. RSICC wishes to poll the user community on the need for a centralized Atomic Computational Expert Services (ACES). If you would benefit by being linked to a consulting expert via email or phone, please send email to firstname.lastname@example.org by September 30th with a list of codes on which you might want to receive expert help. Note the work areas to which you would apply the codes (GenIV, Homeland Defense, Reactor Safety, Consequence Analysis, Nuclear Criticality Safety, etc.). DOE Complex experts would be made available to users needing immediate help on those software and data tools for their application and use. ACES would be free of charge to the users.
A draft revision of the US NRC's "Advanced Reactor Research Plan" was released under Accession number ML021760135 (see Adams Reading Room at http://www.nrc.gov/reading-rm/ adams/login.html for more details). The report is a direct outgrowth from the Future Licensing and Inspection Readiness Assessment (FLIRA) Report released in October 2001 in response to a Commission request for information on the "Staff Readiness for New Nuclear Plant Construction and the Pebble Bed Modular Reactor."
In the FLIRA report, the staff committed to create a research plan for
the development and guidance of a comprehensive advanced reactor research
program. The plan would help to formulate and direct research programs
which would include the development of a regulatory framework for advanced
designs and the analytical tools and experimental data for the independent
assessment of the safety of new reactor designs.
The Generation IV International Forum (GIF) is a group of representatives from the leading nuclear nations, including Argentina, Brazil, Canada, France, Japan, Republic of Korea, Switzerland, United Kingdom, and the United States, with the missions to facilitate bilateral and multilateral cooperation related to the development of new nuclear energy systems. GIF is a formal, government sanctioned organization committed to the collaborative pursuit of R&D on Generation IV systems. The benefits gained in the GEN IV Forum include sharing expertise, resources, and test facilities to gain efficiencies and avoid duplication. The formal charter for this organization was signed in July 2001.
A Generation IV Technology Roadmap being prepared by GIF member countries
will identify six to eight most promising reactor system and fuel cycle
concepts and the R&D necessary to advance them for commercialization.
The Roadmap, initiated in October 2000, is scheduled for completion in
In a speech to employees at the Department of Energy's (DOE) Idaho National Engineering and Environmental Laboratory (INEEL), Secretary of Energy Spencer Abraham announced a major mission realignment for the lab, establishing the site as the Nation's leading center of nuclear energy research and development. Abraham announced that INEEL would receive an additional $5 million in funding to "jump-start" the transition of the site from Environmental Management to the Office of Nuclear Energy.
The laboratory, which has been managed by the department's environmental management program, will now be reassigned to the Office of Nuclear Energy, Science and Technology, where it will become a major contributor to initiatives such as Generation IV nuclear energy systems and advanced, proliferation-resistant fuel cycle technology.
DOE News Release, July 17, 2002
VESSEL DOSIMETRY AND DYNAMICS
ASSURANCE FOR NUCLEAR ANALYTICAL TOOLS
Two U.S. Nuclear Regulatory Commission (NRC) software packages transferred
from the Energy Science and Technology Software Center, Oak Ridge, Tennessee,
to RSICC were processed this month. Please browse the computer code abstracts
available at RSICC's web site for more information on these packages.
Three changes were made to the computer code collection this month: one new package, one newly frozen package and one correction.
Los Alamos National Laboratory, Los Alamos, New Mexico, contributed a newly frozen version of this code system that determines neutron production rates and spectra from (alpha,n) reactions, spontaneous fission, and delayed neutron emission due to radionuclide decay. In this release the three-region problem was modified to correct several bugs, and new documentation was added to the package. The code is capable of calculating (alpha,n) source rates and spectra in four types of problems: homogeneous media (i.e., an intimate mixture of alpha-emitting source material and low-Z target material), two-region interface problems (i.e., a slab of alpha-emitting source material in contact with a slab of low-Z target material), three-region interface problems (i.e., a thin slab of low-Z target material sandwiched between alpha-emitting source material and low-Z target material), and (alpha,n) reactions induced by a monoenergetic beam of alpha-particles incident on a slab of target material. Spontaneous fission spectra are calculated with evaluated half-life, spontaneous fission branching and Watt spectrum parameters for 44 actinides. The (alpha,n) spectra are calculated using an assumed isotropic angular distribution in the center-of-mass system with a library of 107 nuclide decay alpha-particle spectra, 24 sets of measured and/or evaluated (alpha,n) cross sections and product nuclide level branching fractions, and functional alpha-particle stopping cross sections for Z<106. The delayed neutron spectra are taken from an evaluated library of 105 precursors. The code provides the magnitude and spectra, if desired, of the resultant neutron source in addition to an analysis of the contributions by each nuclide in the problem.
The code was tested on Intel Pentium and Sun. An executable compiled
using Compaq Visual Fortran Standard Edition Version 6.6.0 on a PC running
Microsoft's Windows 2000 Professional (Version 5.0, Service Pack 2) is
included, and an executable created under RedHat Linux 6.1 on an Intel
PC with Portland Group Inc. V3.3-2 compiler is included. SOURCES4C was
also tested on Sun SparcStation under SunOS 5.6 with g77 0.5.23. A Windows
executable for the LASTCALL graphical user interface is included in the
code package; no Unix version of LASTCALL is available. The package is
transmitted in a self-extracting, compressed Windows file and in a GNU
compressed tar file. References: LA-UR-02-1839 (April 2002) and LA-UR-02-1617
(2002). Fortran 77; PC and Sun (C00661/MNYCP/04).
UKAEA/EURATOM Fusion Association, Oxfordshire, United Kingdom, through the OECD NEA Data Bank, Issy-les-Moulineaux, France, contributed this multipurpose activation and transmutation code system. EASY-99 is an updated version of CCC-678/EASY-97. Information on EASY-99 is posted at the UKAEA web site: http://www.fusion.org.uk/. The European Activation System (EASY) is a complete tool for the calculation of activation in materials exposed to neutrons. It can be used for any application (fusion, transmutation, fission and accelerator) where the neutron energy does not exceed 20 MeV. EASY-99 consists of the inventory code FISPACT-99 and the EAF-99 file, which contains various libraries of nuclear data. EASY-99 calculates the response of materials irradiated in a neutron flux. It is designed to investigate fusion devices which will act as intense sources of high energy (14 MeV) neutrons and cause significant activation of the surrounding materials. The EAF-99 library contains 12468 excitations functions involving 766 targets from 1H to 257Fm, in the incident energy range up to 20 MeV. The SYMPAL code has been used to update most of the data. A set of nine different multigroup libraries are provided. Available group structures are: WIMS (69), GAM-II (100), XMAS (172), VITAMIN-J (175) and TRIPOLI(315).
Fortran and C compilers are required to build executables. The source
code was compiled and executed at RSICC on an IBM RS/6000 Model 590 running
AIX version 4.2.1 with XL Fortran 22.214.171.124 and C version 4.3. Makefiles
are provided for Sun, IBM, HP and Intel PC linux systems. This release
does not run on Windows. The package is transmitted on a CD-ROM as a GNU
compressed Unix tar file which contains scripts, source files, test cases,
data libraries and documentation files. References: UKAEA FUS 407 (December
1998), UKAEA FUS 408 (December 1998), UKAEA FUS 409 (December 1998), UKAEA
FUS 410 (December 1998), EDS-0 (December 1998), EDS-3a., EDS-2a (December
1998). Fortran 77 & C; IBM RS/6000, SUN, HP, Linux PC (C00711/MNYCP/00).
Electrotechnical Laboratory, Tsukuba, Ibaraki, Japan, Tohoku University,
Sendai-shi, Japan, and Lawrence Berkeley National Laboratory, Berkeley,
California, contributed a correction to the HIMAC package. The authors
carefully checked numerical data on thick target neutron yield and found
some mistakes. The data of Ne 100 MeV/nucleon were revised and replaced
in the July 2002 update. No other files were changed in this update. HIMAC
contains recent experimental data on differential neutron yields in energy
and angle produced by 100, 155 and 180 MeV/nucleon He, 100, 155, 180 and
400 MeV/nucleon C, 100, 180, 400 MeV/nucleon Ne, 400 MeV/nucleon Ar, Xe
and Fe, 272 and 435 MeV/nucleon Nb and 800 MeV/nucleon Si ions stopping
in thick targets of C, Al, Cu, Pb and Nb. The data are distributed on diskette
in MS-Word files. References: Informal paper (M0001/MNYCP/02).
ENVIRONMENTAL TRANSPORT of RADIONUCLIDES
As years have gone by many different codes and applications have been sent to RSICC for stewardship. We currently have over 1700 analytical code and data packages and distribute as many each year to 73 countries in the world. To help 'categorize' each package, we have developed a database of 'Main Categories' to attach applications to the packages at RSICC. Doing so requires investigation into each code package, user feedback from end use statements, and extensive RSICC staff experience and analysis so that we can deliver useful information each month on the 30 different categories we have identified thus far. Links to the package abstracts are embedded into the WWW version of the RSICC Newsletter. Feedback from our Newsletter community is very valuable so please direct your comments and/or suggestions to PDC@ORNL.GOV.
RSICC attempts to keep its users/contributors advised of conferences, courses, and symposia in the field of radiation protection, transport, and shielding through this section of the newsletter alphabetically. Should you be involved in the planning/organization of such events, feel free to send your announcements and calls for papers via email to FINCHSY@ornl.gov with "conferences" in the subject line by the 20th of each month. Please include the announcement in its native format as an attachment to the message. If the meeting is on a website, please include the url.
Every attempt is made to ensure that the links provided in the Conference
and Calendar sections of this newsletter are correct and live. However,
the very nature of the web creates the possibility that the links may become
unavailable. In that case, please call or mail the contact provided. Below
is a condensed list of the conferences only. More details are listed after
The first announcement of "The 11th International Conference on Fusion
Reactor Materials (ICFRM-11)," which will be held in Kyoto, Japan, Dec.
7-12, 2003, is now available on the ICFRM-11 website at http://icfrm.iae.kyoto-u.ac.jp.
For further information, contact ICFRM-11 secretariat at email@example.com
or phone +81-774-38-3597, fax +81-774-38-3467.
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 the success of this meeting depends on your active support and involvement.
Finally, please bookmark the conference web site: http://rpd.ans.org/nfm.htm
and visit it occasionally for news and updates. Comments and suggestions
are most welcome.
The American Nuclear Society, in cooperation with the U.S. Department of Energy and the Fusion Engineering Division of the Atomic Energy Society of Japan, will hold the 15th Topical Meeting on Technology of Fusion Energy. This meeting will be held as an embedded topical of the American Nuclear Society 2002 winter meeting, held November 17-21, 2002, in Washington, DC.
The purpose of this meeting is to bring together specialists in the area of fusion energy to discuss current work and future challenges in the area of fusion technology. In addition to bringing together the varied expertise of this aggressive research area, special sessions are planned to focus on similarities and differences between the inertial and magnetic fusion energy concepts and the interface between materials and design communities. The technical program will include paper and poster presentations as well as invited speakers.
Co-sponsors of this meeting are INEEL, LLNL, NRL, ORNL, and Kyoto University.
For more information, visit
The Americas Nuclear Energy Symposium (ANES 2002) will be in Miami, Florida, October 16-18, 2002, and will provide a forum for a hemispheric discussion and exchange focused on issues related to the future of nuclear energy in the Americas. ANES 2002 will build on the success of both ANES 2000 and the ANS Meeting of the Americas in 1998. The program promises to deliver interactive discussions, workshops, case studies, industry updates, and an exposition by leaders in the nuclear industry. One-page summaries of proposed papers may be sent to email@example.com. The American Nuclear Society is responsible for the technical program.
Notification of abstract acceptance will be sent by August 16, 2002.
Full written papers are due by October 16, 2002. Papers will be published
CD after the event. Visit our website at http://www.anes2002.org
for more information on the symposium.
To mark the beginning of the second century of nuclear science, the American Nuclear Society's Mathematics and Computation Division 2003 Topical Meeting is organized around the theme Nuclear Mathematical and Computational Sciences: A Century in Review, A Century Anew. The conference will be held at the Park Vista Hotel, Gatlinburg, Tennessee, April 6-10, 2003. It is co-sponsored by the American Nuclear Society's Reactor Physics, and Radiation Protection and Shielding Divisions, as well as the ANS Oak Ridge/Knoxville Local Section, Oak Ridge National Laboratory's Radiation Safety Information Computational Center, the Nuclear Energy Agency of the OECD, Korean Nuclear Society, and the Canadian Nuclear Society.
The conference's web site is: http://meetingsandconferences.com/MC2003/.
It will be updated with new information as it becomes available. Please
bookmark and visit it occasionally for news and updates. Comments and suggestions
are most welcome. Contact: Yousry Azmy 814-865-0039, firstname.lastname@example.org
or Bernadette Kirk 865-574-6176, email@example.com.
announcement on SCALE 5 workshop, that will be held immediately before
the M&C Conference.)
The Fourth Meeting of the International MACCS Users Group (IMUG) will be held on September 6, 2002, in the Principality of Monaco. The focus of the Fourth IMUG Meeting will be the exchange of technical information relating to the application of MACCS, MACCS2, and COSYMA codes to relevant problems involving atmospheric dispersion of radioactive materials and resulting consequences.
There is no fee to participate in the meeting; however, for planning
purposes, advance registration is requested. Everyone, including COSYMA
users, is invited to present a paper. Please visit the website
Please make your hotel arrangements as soon as possible. There is a
block of rooms being held at the Columbus Monaco Hotel for the meeting,
but there is another large conference being held in Monaco the same week.
The hotel registration form can be found by going to: www.bnl.gov/est/IMUG2002/HotelRegistrationForm.PDF.
The introductory class is for people who have little or no experience with MCNP. The intermediate to advanced class will be held for people who have used MCNP and want to extend their knowledge and understanding of the code system.
The classes will be based on MCNP5. The code and data package will be available through RSICC at a reduced rate to class participants. The new capabilities of version 5 will be covered.
The other capabilities on MCNP will also be covered, including: basic geometry and advanced geometry, source definitions, tallies, data, variance reduction, statistical analysis, criticality, plotting of geometry, and particle tracks, neutron/photon/electron physics.
All classes provide interactive computer learning. Time will be available to discuss individual questions and problems with MCNP experts or to pursue in more detail topics mentioned in the talks.
Please note that other classes are offered based on MCNP. The classes
mentioned here are the only ones that are taught by the people who develop
and write MCNP.
The Visual Editor is a powerful visualization tool that can be used to rapidly create complex Monte Carlo N Particle (MCNP 4C2) geometry models, including lattices, universes, fills, and other geometrical transformations. The Visual Editor can:
Display MCNP 4C2 geometries in multiple plot windows,
The class will be held September 9-13, 2002, 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 firstname.lastname@example.org).
Two classes are scheduled for 2003: March 17-21 and
September 8-12, both in Richland, Washington.
Lead Teachers: Drs. John Hendricks, Gregg McKinney, Laurie Waters
MCNPX is the LANL all-particle, all-energy (eV-TeV) Monte Carlo transport code based on MCNP4C, LAHET, CEM, etc. MCNPX has been in active development since 1995, sponsored by the particle accelerator community. It has now become an accepted tool for a broad range of applications by nuclear engineers, physicists, and scientists. The MCNPX development effort has expanded the use of the Los Alamos tools to applications such as APT, waste transmutation, accelerator shielding and health physics, particle beam cancer therapy, space shielding and cosmic ray analysis, single event effects in semiconductors, radiography, and more detailed analysis of the effects of light and heavy ions in matter. In addition, the entire functionality of MCNP4C is retained. New variance reduction and data analysis techniques, many adapted from high energy accelerator methodologies, have also been added, such as the extensive 'mesh tally' capability which allows up to 3-d plotting of particle tracks, fluence and fluence-derived quantities, energy deposition, next event estimator generation contributions and particle sources.
The workshops include hands-on instruction, generally on PC Windows machines. Subject to participant export approval for the MCNPX beta test team, participants will be able to access the Fortran-90 version of MCNPX 2.4, the LA150 (150 MeV) cross-section data for over 40 isotopes for incident neutrons and protons, and 12 for photonuclear interactions, and a notebook of viewgraphs.
Follow-up consultation for class participants will be provided.
Classes are taught by experienced MCNPX code developers and instructors.
For more information on code versions and their capabilities, go to the
MCNPX Workshops web site http://mcnpxworkshops.com.
SC2002, on November 16-22, 2002, in Baltimore, Maryland, will
offer bleeding edge technology with stunning exhibits and faster-than-lightning
computer systems. Academic and industry researchers draw on this conference
as an arena to feature high-performance computing and networking discoveries
designed to transform terabytes of data into insights about the origins
of our universe, our own genetic makeup, the condition of our planet and
its ecosystems, and how to keep ourselves safe in a dangerous world. For
more information, see http://www.sc2002.org/.
The Department of Nuclear Engineering at the University of Tennessee-Knoxville is offering two short courses for radiation transport and criticality safety specialists during Tennessee Industries Week (TIW-37), August 12-16, 2002.
Monte Carlo Analysis: Monte Carlo is often the method of choice to solve complex problems in nuclear criticality safety and radiation shielding. To use Monte Carlo effectively, the analyst must understand the theoretical and computational fundamentals of the method, as well as the computational options available in particular computer tools. Also, it is sometimes advantageous to create new special-purpose Monte Carlo programs to solve particular problems rather than use an existing program. The Monte Carlo course runs five days.
Nuclear Criticality Safety: Engineers, scientists, and technical managers who wish to increase their knowledge and understanding of nuclear criticality safety will be interested in the intensive five-day short course. The topics covered in the course are based primarily on the experience of the five instructors which totals over 120 years of nuclear criticality safety related experience. Such a wealth of experience needs to be shared with the criticality safety community including both new and experienced professionals.
For additional information on all the courses offered during TIW-37,
contact Kristin England at The University of Tennessee, phone (865) 974-5048,
email email@example.com, url www.engr.utk.edu/nuclear/TIW.html.
The 48th Annual Radiobioassay and Radiochemical Measurements Conference will be held November 11-15, 2002, at the Marriott (formerly the Hyatt Regency) in Knoxville, Tennessee. This conference is a continuation of an informal conference with a long history. Over the past 47 years, the conference has also been known as:
Annual Bioassay and Analytical Chemistry Conference,
The objectives of the Conference (as adapted from the proceedings of the First Annual Bioassay and Analytical Chemistry Conference) are as follows:
1. To bring everyone up to date on some of the latest developments in
the field of bioassay, analytical, and
For more information, please visit the web site at: http://www.bioassay.org/2002/.
This online 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 online exam are included. Users completing the exam will receive a certificate of completion. Users may also interact with instructors by email 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 firstname.lastname@example.org)
or Dr. Richard B. Sparks (tel 865- 938-4949, fax 865-947-1550, email email@example.com,
url http://www.creative development.com,
The SCALE staff at Oak Ridge National Laboratory (ORNL) will be offering
two training courses this fall (October 14-18 and October 21-25)
at ORNL. The courses will emphasize hands-on experience solving practical
problems on PCs. There will be workgroups of two persons each. No prior
experience in the use of SCALE is required to attend. The registration
fee is $1800 for one course or $3000 for both courses ($300 discount if
you register at least one month before the course). A copy of the SCALE
software and manual on CD may be obtained for an additional fee of $700,
and the KENO3D 3-D visualization tool on CD is available for $800 (single
license). Registrations will be accepted on a first-come basis. Registration
forms submitted directly from the Web are preferred. Registration via fax
or email is also acceptable. The registration fee must be paid by check,
travelers checks, bank transfer, or credit card (VISA or MasterCard only).
The agenda and registration form are on the web page at
Contact: Kay Lichtenwalter (tel 865-574-9213, email firstname.lastname@example.org).
The first workshop on SCALE 5 is being planned in conjunction with the American Nuclear Society M&C 2003 Topical Meeting in Gatlinburg, Tennessee. The workshop will be hosted by Oak Ridge National Laboratory in nearby Oak Ridge, Tennessee. The course is scheduled for the week of March 31 - April 4, 2003, immediately before the M&C 2003 meeting.
The workshop will feature some of the new modules to be released in
SCALE 5, such as the SEN3 3-D sensitivity/uncertainty sequence and the
STARBUCS burnup credit sequence for criticality safety. The workshop will
emphasize hands-on experience solving practical problems on PCs. There
will be workgroups of two persons each. No prior experience in the use
of SCALE is required to attend. The registration fee is $1800 (there is
a $300 early registration discount). You can register online at www.ornl.gov/scale/register_scale5.html
as part of your M&C 2003 registration. The early registration deadline
is February 28, 2003. (See announcement on M&C 2003 Conference).
The Forum will be held March 25-26, 2003 at the Crystal Gateway Marriott Hotel, which is conveniently located in Arlington, Virginia.
The Program Committee is now accepting presentation proposals for the Software Quality Forum 2003 (SQF 2003). The Forum offers an exciting opportunity for software professionals in the Department of Energy (DOE), other Government agencies, private industry, and academia to share their knowledge about trends and technologies in the acquisition, development, support, and management of software intensive systems. Well-known keynote speakers, tutorials on key Forum topics, a showcase for high-visibility IT projects using cutting-edge technologies, and a vendor exhibit area are included in the Forum program.
This is a tri-annual event sponsored by the Software Quality Assurance Subcommittee (SQAS) of the Quality Managers within the DOE Nuclear Weapons Complex. The 2003 Forum is co-hosted by the DOE Office of the Chief Information Officer and the National Nuclear Security Administration, Office of Advanced Simulation and Computing within the Office of Defense Programs.
Please note the following due dates: submission of proposal, abstract, and biography is November 15, 2002, notification of acceptance is December 31, 2002, final abstract is January 15, 2003, and electronic and paper versions of presentation is due February 1, 2003.
For more information, visit the web site http://cio.doe.gov/sqas.
Look for the "Forum 2003" heading on the left side of the home page. There
will be a website devoted to the SQF 2003 in a week or so, which will be
linked from at 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
Spectrum 2002, Exploring Science-Based Solutions and Technologies, 9th Biennial International Conference on Nuclear and Hazardous Waste Management, Aug. 4-8, 2002, Reno, NV. Contact: Dr. Richard Jacobsen (email email@example.com, url www.ans.org/spectrum).
11th International Symposium on Reactor Dosimetry, Aug. 18-23, 2002, Brussels, Belgium. Contact: J. Adams (tel 301-975-6205, fax 301-926-1604, email firstname.lastname@example.org, url www.sckcen.be/conf/isrd2002).
Fourth Meeting of the International MACCS Users Group (IMUG), Sept. 6, 2002, in the Principality of Monaco (url http://www.bnl.gov/est/IMUG2002).
22nd Symposium on Fusion Technology - SOFT, Sept. 8-13, 2002, Helsinki, Finland. Contact: Symposium Secretary Mrs. Merja Asikainen (tel +358 9 456 6854; fax +358 9 456 7002; email: email@example.com; url http://www.vtt.fi/val/soft2002/).
YUNSC 2002 - The 4th International Conference of Yugoslav Nuclear Society, Sept.30-Oct.3, 2002, Belgrade, Yugoslavia. Contact (tel ++381 11 454-796; fax ++381 11 444-74-57; email firstname.lastname@example.org, url www.vin.bg.ac.yu/YUNS).
8th Annual Workshop on Monte Carlo Simulation of Radiotherapy Treatment Sources using the BEAM Code System, Sept. 30-Oct. 3, 2002, Ottawa, Canada. Contact: Blake Walters, Ionizing Radiation Standards, National Research Council of Canada, Ottawa, Canada, K1A 0R6 (tel 613-993-2715, fax 613-952-9865, e-mail email@example.com, url www.irs.inms.nrc.ca/inms/irs/BEAM/beamhome.html).
2002 International Topical Meeting on Probabilistic Safety Assessment (PSA '02), Oct. 6-10, 2002, Detroit, MI. Contact: Rebecca Steinman (phone 734-930-7500, email firstname.lastname@example.org, url http://www-ners.engin.umich.edu/PSAConf/).
PHYSOR 2002, Oct. 7-10, 2002, Seoul, Korea, sponsored by the American Nuclear Society and hosted by the Korean Nuclear Society. Contact: Prof. Nam Zin Cho (tel +82-42-869-3819, fax +82-42-869-5859, email email@example.com, url http://physor2002.kaist.ac.kr).
First Asian and Oceanic Congress for Radiation Protection (AOCRP-1), Oct. 20-24, 2002, Seoul, Korea, sponsored by the Korean Association for Radiation Protection (KARP). Contact: Dr. Myung-Jae Song (tel +82-42-870-0202, fax +82-42-870-0269, email firstname.lastname@example.org, url www.aocrp-1.com).
The 48th Annual Radiobioassay and Radiochemical Measurements Conference, Nov. 11-15, 2002, Knoxville, Tennessee. Contact: Tom Rucker (tel 865-481-2993, email email@example.com url http://www.bioassay.org/2002/.)
15th ANS Topical Meeting on the Technology of Fusion Energy, Nov. 17-21, 2002, Washington, DC. (url www.ans.org/).
International Symposium on Standards and Codes of Practice in Medical Radiation Dosimetry, Nov. 25-28, 2002, IAEA, Vienna. Contact: Dr. Ken R. Shortt (tel +43 1 2600 21664, fax +43 1 26007 21662, email Dosimetry@iaea.org, url www.iaea.org/worldatom/Meetings/2002/infcn96.shtml).
ANS Topical Meeting, Nuclear Mathematical and Computational Sciences: A Century in Review, A Century Anew, Apr. 6-10, 2003, Gatlinburg, TN. Co-sponsored by the American Nuclear Society's Reactor Physics, and Radiation Protection and Shielding Divisions, as well as the ANS Oak Ridge/Knoxville Local Section, Oak Ridge National Laboratory's Radiation Safety Information Computational Center, the Nuclear Energy Agency of the OECD, the Korean Nuclear Society, and the Canadian Nuclear Society. Contacts: Yousry Azmy (tel 865-574-8069, email firstname.lastname@example.org) or Bernadette Kirk (tel 814-865-0039, email email@example.com, url http://meetingsandconferences.com/MC2003/index.html).
International Conference on Supercomputing in Nuclear Applications, SNA 2003, Sept. 22-24, 2003, Paris, France. Organizers: CEA, SFANS, co-organizer: OECD/NEA. (email SNAfirstname.lastname@example.org, url http://SNA-2003.cea.fr).
American Nuclear Society's Advances in Nuclear Fuel Management III Topical Meeting, Oct. 5-8, 2003, Hilton Head Island, South Carolina. Contact: Youssef A. Shatilla (email email@example.com, url http://rpd.ans.org/nfm.htm).
The 11th International Conference on Fusion Reactor Materials (ICFRM-11),
Dec. 7-12, 2003, Kyoto, Japan. Contact ICFRM-11 secretariat ( tel +81-774-38-3597,
fax +81-774-38-3467, email firstname.lastname@example.org,
The nuclear systems literature (shielding, safety, materials) cited
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Ann. Nucl. Energy, 30, 133-158 . . . Parameter Estimation in Thermalhydraulic Models Using the Multidirectional Search Method. . . . Carlos, S.; Ginestar, D.; Martorell, S.; Serradell, V. . . . January 2003 . . . Polytechnic University of Valencia, Spain.
Ann. Nucl. Energy, 30, 159-173 . . . Power Flattening in Prometheus Breeder Reactor Using Nuclear Fuel and Waste Actinide. . . . Yapici, H.; Übeyli, M. . . . January 2003 . . . Erciyes Üniversitesi, Kayseri, Turkey; Gazi Üniversitesi, Ankara, Turkey.
Ann. Nucl. Energy, 30, 175-187 . . . Utilization of Ilmenite/Epoxy Composite for Neutrons and Gamma Rays Attenuation. . . . Abdo, A.E.; El-Sarraf, M.A.; Gaber, F.A. . . . January 2003 . . . Atomic Energy Authority, Cairo, Egypt.
Ann. Nucl. Energy, 30, 189-209 . . . Investigation of Spatial Coupling Aspects for Coupled Code Application in PWR Safety Analysis. . . . Tokorova, N.K.; Ivanov, K.N. . . . January 2003 . . . Pennsylvania State University, University Park, PA.
Ann. Nucl. Energy, 30, 211-222 . . . A Simple Scheme for the Direct Evaluation of Time-Eigenvalues of Neutron Transport Equation. . . . Modak, R.S.; Gupta, A. . . . January 2003 . . . Bhabha Atomic Research Centre, Mumbai, India.
Ann. Nucl. Energy, 30, 223-242 . . . Reactor Noise in Accelerator Driven Systems. . . . Degweker, S.B. . . . January 2002 . . . Bhabha Atomic Research Centre, Mumbai, India.
Ann. Nucl. Energy, 30, 245-259 . . . Neutronic Investigation of a Hybrid Version of the ARIES-RS Fusion Reactor. . . . Sahin, S. et al. . . . January 2003 . . . Gazi Üniversitesi, Ankara, Turkey; Bahcesehir Üniversitesi, Istanbul, Turkey.
Nucl. Eng. Design, 217, 41-47 . . . Experimental Study on Hydrogen Behavior at a Subcompartment in the Containment Building. . . .Lee, U-J.; Park, G-C. . . . August 2002 . . . Seoul National University, Seoul, Republic of Korea.
Nucl. Eng. Design, 217, 63-80 . . . Model Development for Analysis of the Korea Advanced Liquid Metal Reactor. . . . Chang, W-P.; Kwon, Y-M.; Lee, Y-B.; Hahn, D. . . . August 2002 . . . Korea Atomic Energy Research Institute, Taejon, South Korea.
Nucl. Eng. Design, 217, 81-90 . . . Relation Between Temperature Fluctuation of a Heating Surface and Generation of Drypatch Caused by a Cylindrical Spacer in a Vertical Boiling Two-Phase Upward Flow in a Narrow Annular Channel . . . Fukano, T.; Mori, S.; Akamatsu, S.; Baba, A. . . . August 2002 . . . Kyushu University, Fukuoka, Japan; Hitachi, Ltd., Ibaraki-ken, Japan; Tsukuba Space Center, Ibaraki, Japan.
Nucl. Eng. Design, 217, 91-101 . . . Thermal-Hydraulic Analysis of Accidents Leading to Local Coolant Flow Decrease in the Main Circulation Circuit of RBMK-1500. . . . Kaliatka, A.; Uspuras, E. . . . August 2002 . . . Lithuanian Energy Institute, Kaunas, Lithuania.
Nucl. Eng. Design, 217, 103-110 . . . Hydromechanical Investigation on 3 PWR Upper Plenum Core Structures. . . . Xiuzhong Shen et al. . . . August 2002 . . . University of Shanghai Jiao Tong, Shanghai, China.
Nucl. Eng. Design, 217, 111-127 . . . Analytical Prediction of Friction Factors and Nusselt Numbers of Turbulent Forced Convection in Rod Bundles with Smooth and Rough Surfaces. . . . Su, J.; Freire, A.P.S. . . . August 2002 . . . Universidade Federal do Rio de Janeiro, Brazil.
Nucl. Eng. Design, 217, 129-139 . . . Development and Evaluation of Additional Shutdown System at the Ignalina NPP by Employing RELAP5 Code. . . . Kaliatka, A.; Uspuras, E. . . . August 2002 . . . Lithuanian Energy Institute, Kaunas, Lithuania.
Nucl. Eng. Design, 217, 141-151 . . . Long Time Experience with the Development of HTR Fuel Elements in Germany. . . . Nickel, H.; Nabielek, H.; Pott, G.; Mehner, A.W. . . . August 2002 . . . Research Centre Jülich, Germany; Technical University Aachen, Germany; Framatome ANP, Duisburg, Germany.
Nucl. Eng. Design, 217, 153-166 . . . Inspection Techniques for Primary Pressurized Water Cooler Tubes in the High Temperature Engineering Test Reactor. . . . Takeda, T. et al. . . . August 2002 . . . JAERI, Ibaraki-ken, Japan; Japan Atomic Power Co., Tokyo, Japan.
Nucl. Eng. Design, 217, 167-177 . . . Research Results on the Corrosion Effects of Liquid Heavy Metals Pb, Bi and Pb-Bi on Structural Materials With and Without Corrosion Inhibitors. . . . Ilinev, G. . . . August 2002 . . . Nuclear Research Institute Rez, Czech Republic.
Nucl. Eng Design, 217, 179-206 . . . Review of Quantitative Accuracy Assessments with Fast Fourier Transform Based Method (FFTBM). . . . Prošek, A.; D'Auria, F.; Mavko, B. . . . August 2002 . . . Joef Stefan Institute, Ljubljana, Slovenia; University of Pisa, Italy.
Nucl. Technol., 139, 1 . . . Special Issue on Advanced Nuclear Installation Safety. . . . Hannaman, G.W. . . . July 2002.
Nucl. Technol., 139, 3-9 . . . Passive System Reliability Analysis: A Study on the Isolation Condenser. . . . Burgazzi, L. . . . July 2002 . . . ENEA Via Martiri di Monte Sole, Bologna, Italy.
Nucl. Technol., 139, 10-20 . . . Severe Accident Related Research and Development at Forschungszentrum Karlsruhe for Present and Future Needs. . . . Scholtyssek, W. et al. . . . July 2002 . . . Forschungszentrum Karlsruhe, Germany.
Nucl. Technol., 139, 21-29 . . . The Model of the IBR-2 Pulsed Reactor Dynamics and Investigation of Pulse Energy Stabilization. . . . Popov, A. et al. . . . July 2002 . . . Joint Institute for Nuclear Research, Moscow Region, Russia.
Nucl. Technol., 139, 30-35 . . . Regulatory Concerns on the In-Containment Water Storage System of the Korean Next Generation Reactor. . . . Ahn, H-J.; Lee, J-H.; Bang, Y-S.; Kim, H-J. . . . July 2002 . . . Korea Institute of Nuclear Safety, Taejon, Korea.
Nucl. Technol., 139, 36-41 . . . General Safety Criteria for the Korean Next Generation Reactor. . . . Lee, J-H.; Kim, W-S.; Yune, Y.G.; Lee, J-S. . . . July 2002 . . . Korea Institute of Nuclear Safety, Taejon, Korea.
Nucl. Technol., 139, 50-60 . . . Definition and Analysis of an Experimental Benchmark on Shutdown Rod Worths in LEU-HTR Configurations. . . . Chawla, R.; Joneja, O.P.; Rosselet, M.; Williams, T. . . . July 2002 . . . Swiss Federal Institute of Technology, Lausanne, Switzerland; Paul Scherrer Institute, Villigen-PSI, Switzerland; Elektrizitaets-Gesellschaft Laufenburg, Dietikon, Switzerland.
Nucl. Technol., 139, 72-79 . . . Empirical and Computational Pressure Drop Correlations for Pressurized Water Reactor Fuel Spacer Grids. . . . In, W.K.; Oh, D.S.; Chun, T.H. . . . July 2002 . . . Korea Atomic Energy Research Institute, Daejon, Korea.
Nucl. Technol., 139, 80-88 . . . Criticality Analysis of MOX and LEU Assemblies for Transport and Storage at the Balakovo Nuclear Power Plant. . . . Goluoglu, S.; Primm III, R.T. . . . July 2002 . . . Oak Ridge National Laboratory, Oak Ridge, TN.