Radiation Safety Information Computational Center
|Oak Ridge National Laboratory|
Post Office Box 2008
Oak Ridge, Tennessee 37831-6362
Lockheed Martin Energy Research Corp.
for the U.S. Department of Energy
under contract DE-AC05-96OR22464
Phone No. 423-574-6176
|No. 412||April 1999|
|Farming looks mighty easy when your plow is a pencil and you're a thousand miles from the corn field.--Dwight D. Eisenhower|
The FENDL project started in 1987 and the first version of the library, FENDL-1, was officially released early in 1995. Extensive integral data testing of FENDL-1 led to an improved version designated as FENDL-2 which was finalized for general distribution in January 1999. FENDL-2 represents contributions from ENDF/B-VI (United States), JENDL-3 and JENDL-FF (Japan), BROND-2 (Russian Federation), and EFF-3 (European Union).
The early FENDL meetings were historic in that scientists from the East and West shared details of their respective evaluated nuclear data files for the first time. To help record the historic first meeting in 1987, we have captured two pictures of interest. First, the participants starting from the left are K. Shibata, H. Gruppelaar, V. Goulo, S. Pelloni, G. Reffo, H. Vonach, U. Fischer, D. Seeliger, E. Cheng, J. Schmidt, R. Forrest, C. Dunford, F. Mann, D. Larson, D. Muir, A. Lorenz, R. Feldbacher, and D. Wang. These participants are representative of the four partners in the ITER project. Second, we have a close-up picture of the chalk board showing the elements and/or isotopes of interest and candidate evaluations listed by national projects.
|Participants from the left to right: K. Shibata, H. Gruppelaar, V. Goulo, S. Pelloni, G. Reffo, H. Vonach, U. Fischer, D. Seeliger, E. Cheng, J. Schmidt, R. Forrest, C. Dunford, F. Mann, D. Larson, D. Muir, A. Lorenz, R. Feldbacher, and D. Wang.|
Chalk board showing the elements and/or isotopes of interest and candidate evaluations listed by national projects.
This material was prepared as an account of Government sponsored work and describes a code system or data library which is one of a series collected by the Radiation Safety Information Computational Center (RSICC). These codes/data were developed by various Government and private organizations who contributed them to RSICC for distribution; they did not normally originate at RSICC. RSICC is informed that each code system has been tested by the contributor, and, if practical, sample problems have been run by RSICC. Neither the United States Government, nor the Department of Energy, nor Lockheed Martin Energy Research Corporation, nor any person acting on behalf of the Department of Energy or Lockheed Martin Energy Research Corporation, makes any warranty, expressed or implied, or assumes any legal liability or responsibility for the accuracy, completeness, usefulness or functioning of any information code/data and related material, or represents that its use would not infringe privately owned rights. Reference herein to any specific commercial product, process, or service by trade name, trademark, manufacturer, or otherwise, does not necessarily constitute or imply its endorsement, recommendation, or favoring by the United States Government, the Department of Energy, Energy Systems, nor any person acting on behalf of the Department of Energy or Lockheed Martin Energy Research Corporation.
"For ORNL to support DOE's mission, our researchers are developing scientific simulations that require machine performance at levels of a teraop (1 trillion calculations per second) and beyond," said Thomas Zacharia, director of the Computer Science and Mathematics Division. "By acquiring this IBM machine, we're taking a major step toward that goal."
The initial IBM system is configured to perform 100 gigaops, or a tenth of a teraop; however, it will be upgraded to 400 gigaops within about six months. By about the middle of next year, Zacharia expects the unit to be upgraded to a 1 teraop per second capability.
The new machine will be more than seven times faster than the ORNL's Intel Paragon XP/S 150, which in 1995 was the fastest computer in the world. It will support computational simulations across a broad range of DOE programs.
"The really exciting thing about this machine isn't just the speed of its calculations, but rather the speed of the researchers rushing to use it," said Ed Cumesty, DOE Oak Ridge Operations assistant manager for laboratories.
Over the next few months, computer scientists from ORNL and IBM will be developing new programming tools and techniques to support this highly sophisticated machine. They will also work together to improve data storage and digital library systems with parallel programming environments and Web-based interfaces.
Lawrence Livermore National Laboratory, Livermore, California, contributed a newly frozen version of this coupled neutron-photon, 3-D, combinatorial geometry, Monte Carlo transport code system. TART98 includes both ENDL and ENDF/B-VI data as well as several auxiliary codes (TARTCHEK, EPICSHOW, PLOTTAB, TARTAID) and several utility programs. TART98 includes data for neutron interaction data, neutron induced photon production data, photon interaction data, and neutron self-shielding, multi-band parameter data. TART98 is very fast and supersedes all previous versions. The developer recommends that all users acquire the most recent version and its data files. Details are available at the following url: http://reddog1.llnl.gov/homepage.red/ MC.htm.
This is a complete system to assist with input preparation, run Monte Carlo calculations, and
facilitate analysis of output results. TART98 runs on almost any computer including Cray, IBM
RS/6000, HP, Sun, SGI, Meiko, and DEC Alpha under Unix operating systems. It also runs on
Power MAC and on IBM PC's under either Linux, Windows95 or WindowsNT. Fortran 77 and C
compilers are required for Unix systems. Executables created with the ABSOFT Fortran
compiler are included for Mac and IBM PC under both Windows and Linux. The package is
transmitted on a CD-ROM in compressed tar and DOS self-extracting compressed formats.
References: UCRL-ID-126455, Rev. 2 (Nov. 1998). Fortran 77; Many Computers
Berichte der Kernforschungsanlage Jülich, Federal Republic of Germany, contributed a newly frozen version of this code system for the simulation of reactor life histories. VSOP94, which obsoletes previous versions, is comprised of neutron cross section libraries and processing routines, repeated neutron spectrum evaluation, 2-D diffusion calculation based on neutron flux synthesis with depletion and shut-down features, in-core and out-of-pile fuel management, fuel cycle cost analysis, and thermal hydraulics (at present restricted to Pebble Bed HTRs). Various techniques are employed to accelerate the iterative processes and to optimize the internal data transfer. The code system has been used extensively for comparison studies of reactors, their fuel cycles, and related detailed features. In addition to its use in research and development work for the high temperature reactor, the system has been applied successfully to light water and heavy water reactors. The fuel management module was extended to include the typical features of the pebble bed reactor.
VSOP94 runs on DEC VAX/VMS computers. RSICC tested it on IBM RS/6000 and DEC Alpha
Digital Unix workstations. It was difficult to verify since the original VAX output was not
supplied; however, the DEC and IBM RS/6000 output closely match. The package is transmitted
on CD ROM in compressed tar format. Fortran 77; VAX/VMS, IBM RS/6000, DEC Alpha
The Institute for Nuclear Energy, Istanbul Technical University, Maslak, Istanbul, Turkey, contributed the D2O code system for the fast computation of the thermodynamic and transport properties of heavy water at saturation, in subcooled liquid and superheated vapor states. Specific volume (or density), specific enthalpy, specific entropy, constant-pressure specific heat and temperature at saturation are calculated by a number of piecewise continuous approximation functions of (and their derivatives are calculated with respect to) pressure whereas pressure at saturation is calculated by a piecewise continuous approximation function of temperature for heavy water. Density in subcooled liquid state, specific volume in super-heated vapor state, specific enthalpy, specific entropy and constant-pressure specific heat in both of these states are calculated by some piecewise continuous approximation functions of pressure and temperature for heavy water. The correlations used in the calculation of these thermodynamic properties of heavy water were derived by fitting some appropriate curves to the data given in the steam tables by Hill et al (1981). The whole set of correlations and the approximation method used in their derivation are presented by Durmayaz (1997). Dynamic viscosity and thermal conductivity for heavy water are calculated as functions of temperature and density with the correlations given by Hill et al (1981), by Matsunaga and Nagashima (1983) and by Kestin et al (1984). Surface tension for heavy water is calculated as a function of temperature with the correlation given by Crabtree and Siman-Tov (1993).
The source is written in Fortran 77. It was compiled and tested at RSICC with Lahey
F77L/EM-32 V5.2 on a Pentium running DOS6.22 and Windows95a in a MS-DOS box. The
package is transmitted on one diskette which includes the Fortran source, PC executable and
testcases. Reference: Informal notes (April 1998). Fortran 77; PC (P00398PC48600).
Idaho National Engineering and Environmental Laboratory, Idaho Falls, ID, contributed this collection of programs developed to perform the functions necessary to create and analyze a complete Probabilistic Risk Assessment (PRA). The programs included in this suite, identified as SAPHIRE5.69, are the Integrated Reliability and Risk Analysis System (IRRAS), the System Analysis and Risk Assessment (SARA) system, the Models And Results Database (MAR-D) system, and the Fault tree, Event tree and P&ID (FEP) editors. Previously these programs were released as separate packages. The programs allow the user to create event trees and fault trees, to define accident sequences and basic event failure data, to solve system and accident sequence fault trees, to quantify cut sets, and to perform uncertainty analysis on the results. Other features allow the analyst to generate reports and displays that document the results of an analysis. Since this software is a very detailed technical tool, the user of this program should be familiar with PRA concepts and the methods used to perform these analyses.
SAPHIRE is written entirely in MODULA-2 and uses an integrated commercial graphics
package to interactively construct and edit fault trees. The fault tree solving methods used are
industry recognized top down algorithms. For quantification, the program uses standard methods
to propagate the failure information through the generated cut sets. The package which is
transmitted on one CD-ROM includes an executable which runs in a MS-DOS Window of
Windows95. References: NUREG/CR-6116 Vols 1, 2, 3, 4, 5, 7, and 8 (December 1993).
MODULA-2; IBM PC 386 (P00405PC38600).
The IAEA Nuclear Data Section, Vienna, Austria, contributed a new version of this compendium of reference and processed sub-libraries derived from international evaluated nuclear data files for fusion applications. For more information, see the feature article on page one.
Data are in ENDF-6 and well known processed formats:
REAC, LIBOUT, GENDF (output of NJOY/GROUPR and
NJOY/ GAMINR), MATXS, and continuous energy format
for use in MCNP calculations. No retrieval program is included. The ASCII data can be used on
any computer platform. However, because of the large size of this package, they are distributed
only in Unix compressed tar files on CD-ROM. The entire package is ~250 MB when
compressed and requires an additional ~1 gigabyte of disk space for the uncompressed files.
References:IAEA-NDS-173 Rev. 1 (October 1998), IAEA-NDS-174 (March 1997),
IAEA-NDS-141 Rev. 2 (Oct. 1993), IAEA-NDS-175 Rev. 3 (October 1998), IAEA-NDS-176
Rev. 1 (October 1998), IAEA-NDS (March 1977), and IAEA-NDS-178 Rev.0 (March 1997). All
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. We plan to showcase the preliminary 4C version of MCNP that will be in a pre-release status. The new features to be discussed include:
Other capabilities of MCNP to be covered are: Basic geometry and advanced geometry, Source definitions, Tallies, Data, Variance reduction, Statistical analysis, Criticality, Plotting of geometry, tallies, and particle tracks, and Neutron/photon/electron physics.
All classes provide interactive computer learning, with time 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. For more information and to
register for the LANL classes, contact Judi Briesmeister, email@example.com. For information on the
European classes, contact Enrico Sartori, OECD/NEA, firstname.lastname@example.org.
Code Integration Group (X-CI), Los Alamos National Laboratory
The Symposium theme is dosimetry for the assessment of irradiated reactor materials and reactor
experiments, featuring radiation metrology techniques, databases and standardization. Inquiries
and requests to be added to the mailing list should be sent to one of the following:
North & South America, East & Southeast Asia:
Dr. David W. Vehar
ASTM Program Secretary
Sandia National Laboratories, MS-1136
P.O. Box 5800, Albuquerque, NM 87185-1136, USA
Phone: 505-845-3414, fax: 505-844-0798
Europe, Africa, Asia (other), and Australia:
Dr. Hamid Ait Abderrahim
EWGRD Programme Secretary
Boeretang 200, B-2400 Mol, BELGIUM
Phone: 32-14-332277, fax: 32-14-321529
Dr. T. S. Elleman
Nuclear Engineering Department, Box 7909
North Carolina State University
Raleigh, NC 27695-7909 USA
It is possible to register on-line at www.quantumres.com.
If you are interested in attending the symposium, please contact:
Professor Ladislav Musílek
Czech Technical University in Prague
Faculty of Nuclear Sciences and Physical Engineering
Bøehová 7, 115 19 Praha 1,
Fax: +4202 2320861, e-mail: email@example.com
Additional and updated information may be obtained from http://www.fjfi.cvut.cz/ISRP-8.htm.
If you are interested in Plutonium Futures--The Science and wish to receive the future announcements, including the Call for Papers, complete and submit the on-line Information Request Form (http://www.lanl.gov/orgs/nmt/nmtdo/PuConf2000/2krequest.html). You may also email or write to
Plutonium Futures--The Science
Los Alamos National Laboratory
Nuclear Materials Technology Division
P.O. Box 1663
Los Alamos, NM, USA 87545
Contact: Andria Liesse
Conference E-mail: Puconf2000@lanl.gov
Communicating the Nuclear Advantage, May 30-June 2, 1999, Montreal, Quebec. Contact: Canadian Nuclear Assoc., Suite 475, 144 Front St., Toronto, Ontario Canada M5J 2L7 (phone 416-977-6152 ext. 18; fax 416-979-8356, email firstname.lastname@example.org, url www.cna.ca.
Canadian Radiation Protection Association, May 31-June 3, 1999, Saskatoon, Saskatchewan, Canada. Contact: 1999 CRPA Organizing Committee, Univ. of Saskatchewan, Room 127, Toxicology Research Centre, 44 Campus Drive, Saskatoon, Saskatchewan, Canada S7N 5B3 (phone 306-975-0566, fax 306-975-0494, email email@example.com, web www.safety.ubc.ca/rad/radhome.htm.
ANS Annual Meeting, June 6-10, 1999, Boston, Massachusetts. Contact: ANS, 555 N.Kensington Ave., La Grange Park, IL 60526 USA (phone 708-352-6611, fax 708-352-0499) http://WWW.ANS.ORG/meetings/.
ICNRP '99, Second International Conference Nuclear and Radiation Physics, June 7-10, 1999, Almaty, Kazakhstan. Contact: Kislitsin Sergey, Institute of Nuclear Physics NNC RK, Ibragimov Street,1, Almaty 480082 Kazakhstan (phone 7-3272-545143; 7-3272) 546467, fax 7-3272546517, email firstname.lastname@example.org).
Conference on Radionuclide Metrology and Its Application, June 7-11, 1999, Prague. Contact: Pavel Dryák, Czech Metrological Institute, Radiova 1, CZ 102 00 Prague, Czech Republic (phone 420-2-67008244, fax 420-2-67008466, email email@example.com).
Executive Conference on Nuclear Power Plant Decommissioning and Spent Fuel Management, June 27-30, 1999, Traverse City, Michigan, sponsored by the ANS. Contact: Ken Powers, Big Rock Point Restoration Project, 10269 U.S. 31 N., Charelvoix, MI 49720 (phone 616-547-8388, fax 616-547-8187).
Computational Methods in Reactor Analysis and Shielding, Aug. 16-20, 1999, Knoxville, Tennessee, a short course offered by the University of Tennessee-Knoxville. Contact: Lydia Salmon, Dept. of Nuclear Engineering, University of Tennessee, Knoxville, TN 37996-2300 (phone 423-974-2525, fax 423-974-0668).
Nuclear Criticality Safety, Aug. 16-20, 1999, Knoxville, Tennessee, a short course offered by the
University of Tennessee-Knoxville. Contact: Lydia Salmon, Dept. of Nuclear Engineering,
University of Tennessee, Knoxville, TN 37996-2300 (phone 423-974-2525, fax 423-974-0668).
Monte Carlo Analysis, Aug. 16-20, 1999, Knoxville, Tennessee, a short course offered by the University of Tennessee-Knoxville. Contact: Lydia Salmon, Dept. of Nuclear Engineering, University of Tennessee, Knoxville, TN 37996-2300 (phone 423-974-2525, fax 423-974-0668).
GLOBAL '99, Aug. 29-Sept. 3, 1999, Jackson, Wyoming. Contact: firstname.lastname@example.org; Argonne National Laboratory - West, P. O. Box 2528, Idaho Falls, Idaho, 83401-2528 (phone 208-533-7760, fax 208-533-7863, http://www.anlw.anl.gov/global99/)
3rd International Conference on Isotopes, September 6-10, 1999, Vancouver, Canada. Contact http://www.triumf.ca/3ici/.
Tenth International Symposium on Reactor Dosimetry, Sept. 12-17, 1999, in Osaka, Japan. Contact: Dr. David W. Vehar (phone 505-845-3414, fax 505-844-0798, email email@example.com) or Dr. Hamid Ait Abderrahim (phone 32-14-332277, fax 32-14-321529, email firstname.lastname@example.org).
SCALE Criticality Course (KENO V.a), Sept. 13-17, 1999, INSTN, Saclay, France. Contact: Enrico Sartori, OECD/NEA Data Bank, Le Seine-Saint Germain, 12 boulevard des Iles, F- 92130 Issy-les-Moulineaux, France (phone 33-0-1-4524-1072; fax 33-0-1-4524-1110; email email@example.com).
6th International Conference on Nuclear Criticality Safety, September 20-24, 1999, Versailles, France. Contact: http://www.ipsn.fr/icnc99/.
Half a Century of Radiation Shielding Research and Its Evolution into the Next Era (ICRS-9), Oct. 17-22, 1999, Tsukuba, Japan, sponsored and organized by the Japan Atomic Energy Research Institute. Contact: Yujiro Ikeda, Japan Atomic Energy Research Institute, Tokai Research Establishment, Neutron Science Research Center, Spallation Neutronics Laboratory, Tokai-mura, Naka-gun, Ibaraki-ken 319-11 Japan (phone 81-29-282-6074, fax 81-29-282-5709, email firstname.lastname@example.org, url http://icrs9.tokai.jaeri.go.jp).
Plutonium Futures--The Science, July 10-13, 2000, Santa Fe, New Mexico. Contact: Plutonium Futures--The Science, Los Alamos National Laboratory, Nuclear Materials Technology Division, P.O. Box 1663, MS E500, Los Alamos, NM, USA 87545 (phone 505-665-5981, fax 505-667-7966, email Puconf2000@lanl.gov).
STI/PUB/1037 . . . Physical Protection of Nuclear Materials: Experience in Regulation, Implementation and Operations. . . . 1998 . . . IAEA; email@example.com . . . Proceedings Series.
Health Phys., 76, 355-367 . . . A Biosphere Modeling Methodology for Dose Assessments of the Potential Yucca Mountain Deep Geological High Level Radioactive Waste Repository. . . . Watkins, B.M.; Smith, G.M.; Little, R.H.; Kessler, J. . . . April 1999 . . . QuantiSci. Ltd., Oxfordshire, England; Electric Power Research Institute, Palo Alto, CA.
Health Phys., 76, 388-392 . . . Monte Carlo Estimation of Absorbed Dose to Organs in Diagnostic Radiology. . . . Alonso, M.; Barriuso, T.; Castaneda, M.J.; Diaz-Caneja, N.; Gutierrez, I.; Sarmiento, J.J.; . . . April 1999 . . . University Hospital "Marques de Valdecilla," Santander, Spain; University of Cantabria, Santander, Spain.
Health Phys., 76, 402-412 . . . Some Problems in the Skeletal Dosimetry of Bone-Seeking Radionclides. . . . Lloyd, R.D.; Fisher, D.R.; Schlenker, R.A.; Miller, S.C. . . . April 1999 . . . University of Utah, Salt Lake City, UT; Pacific Northwest National Laboratory, Richland, WA; Madison Research Group, Inc., Willowbrook, IL.
Nucl. Eng. Des., 186, 343-352 . . . IDENT 1D - A Novel Software Tool for an Easy Identification of Material Constitutive Parameters. . . . Le Ber, L. . . . 1998.
Nucl. Eng. Des., 186, 361-368 . . . Experimental Assessment of Neutron Fluence for the Kozloduy Unit 1 Pressure Vessel By Scraps and Cavity Dosimetry. . . . Apostolov, T. . . . 1998 . . . Institute for Nuclear Research and Nuclear Energy, Sofia, Bulgaria.
Nucl. Eng. Des., 186, 23-37 . . . The Role of the PIRT Process in Experiments, Code Development and Code Applications Associated with Reactor Safety Analysis. . . . Wilson, G.E. . . . 1998 . . . Idaho National Engineering and Environmental Laboratory, Idaho Falls, ID.
Phys. Med. Biol., 44, R1-R22 . . . Review of Photon Interaction Cross Section Data in the Medical and Biological Context. . . . Hubbell, J.H. . . . 1999.
Prog. Nucl. Energy, 33, 289-300 . . . A Comparative Study of Analytical Solutions for Some One-Dimensional Transport Equation Approximations. . . . ; Cardona, A.V.; Tullio De Vilhena, M. . . . May 1998 . . . firstname.lastname@example.org.
Prog. Nucl. Energy, 34, 13-75 . . . Soft Computing Technologies in Nuclear Engineering Applications. . . . ; Uhrig, R.E.; Tsoukalas, L.H. . . . September 1998.
Prog. Nucl. Energy, 34, 99-142 . . . 3-D Monte Carlo and Discrete Ordinates Void Coefficient Analysis for the Los Alamos National Laboratory Omega West Reactor Using MCNP and THREEDANT. . . . Durkee, J.W. Jr.; Streetman, J.R.; Sapir, J.L.; Andrade, A. . . . September 1998.
Prog. Nucl. Energy, 34, 413-423 . . . The Linear Boltzmann Equation in Optically Thick Systems with Forward-Peaked Scattering. . . . Larsen, E.W. . . . February 1999.
Prog. Nucl. Energy, 186, 425-430 . . . Unified Approach to Analytical Solutions of Three Inverse Transport Problems. . . . McCormick, N.J. . . . February 1999.
Prog. Nucl. Energy, 34, 453-469 . . . An Insider's Perspective of Fast Reactor Technology. . . . McFarlane, H.F.; Lineberry, M.J. . . . February 1999.
Prog. Nucl. Energy, 34, 489-500 . . . Safety Considerations in Accelerator-Driven Nuclear Systems. . . . Rief, H.; Wider, H. . . . February 1999.
New Publications, 66 . . . Low Doses of Ionizing Radiation: Biological Effects and Regulatory Control: Invited Papers and Discussions. . . . November 1998 . . . IAEA; email@example.com . . . Proceedings Series.
New Publications, 67 . . . Safety Issues for Advanced Protection, Control and Human-Machine Interface Systems in Operating Nuclear Power Plants.. . . November 1998. . . IAEA; firstname.lastname@example.org . . . Safety Reports Series No. 6.
New Publications, 67 . . . Developing Safety Culture in Nuclear Activities - Practical Suggestions to Assist Progress. . . .December 1998. . . IAEA; email@example.com . . . Safety Reports Series No. 11.
New Publications, 67 . . . Evaluation of the Safety of Operating Nuclear Power Plants Built to Earlier Standards - A Common Basis for Judgement. . . December 1998. . . IAEA; firstname.lastname@example.org . . . Safety Reports Series No. 12.
New Publications, 67 . . . Design Measures to Facilitate Implementation of Safeguards at Future Water Cooled Nuclear Power Plants.. . . January 1999 . . . Technical Reports Series No. 392.
New Publications, 67 . . . Operating Experience with Nuclear Power Stations in Member States in 1997. . . January 1999. . . IAEA; email@example.com.
New Publications, 67 . . . Directory of Nuclear Research Reactors 1998 . . . January 1999 . . . IAEA; firstname.lastname@example.org.
New Publications, 67 . . . Nuclear Research Reactors in the World - December 1998 Edition. . . . January 1999 . . . IAEA; email@example.com . . . Reference Data Series No. 3.
No Pub. Desc. . . . Gabriel, T.A. ed. . . . 1999 . . . Proceedings of the Fourth Workshop on Simulating Accelerator Radiation Environments. (SARE4).
No Pub. Desc.. . . ITER Design Basis Plasma Disruption Simulations . . . Jardin, S.C.; Sayer,
R.O. . . . 1998 . . Oak Ridge National Laboratory, Oak Ridge, TN.
1.ORNL is a DOE multiprogram research facility managed by Lockheed Martin Energy Research Corporation.