Radiation Safety Information Computational Center
	Oak Ridge National Laboratory Post Office Box 2008 Oak Ridge, Tennessee 37831-6362 Managed by Lockheed Martin Energy Research Corp. for the U.S. Department of Energy under contract DE-AC05-96OR22464 Phone No. 423-574-6176 FAX 423-574-6182 Internet: PDC@ORNL.GOV WWW: http://www-rsicc.ornl.gov/rsic.html
No. 403	July 1998
He who is false to the present duty breaks a thread in the loom, and you will see the effect when the weaving of a life-time is unraveled.--Channing

Gaerttner LINAC Receives ANS Landmark Award

From the June 1998 Nuclear News--"For over 35 years of generating accurate data for nuclear reactor designs, the Gaerttner LINAC Laboratory at Rensselaer Polytechnic Institute was awarded a Nuclear Historic Landmark Award by ANS. The high-power electron linear accelerator has served government as well as industry applications since the early 1960s, and was one of the first to provide intense pulsed beams of neutrons for time-of-flight experiments."

Robert Block, current director of the laboratory, accepted the award from Ted Quinn, ANS president-elect and RPI alumnus, in an April 3 ceremony hosted by the ANS Eastern New York Section and RPI.

During its many years of operation, the Gaerttner LINAC Laboratory conducted measurements of neutron thermalization, neutron cross-sections on both stable and radioactive isotopes, neutron spectra from large pulsed assemblies, photoneutron production, radiation effects in components, and the effects of intense radiation in microelectronics. The plutonium-239 alpha measurements carried out jointly with the Oak Ridge National Laboratory showed that the steam-cooled intermediate spectrum breeder concept would not be practical because of the high alpha measured in this energy range. "As a result, the breeder program shifted its focus exclusively to the liquid-sodium-cooled LMFBR design. Numerous measurements were carried out in support of the LMFBR, as well as for thermal reactors, and today there is a strong program in low-energy cross-section measurements."

We in the Radiation Safety Information Computational Center have enjoyed a long reciprocal relationship with the staff and students of RPI. We congratulate those who have and are operating the Gaerttner LINAC Laboratory on receiving this award. If you wish to learn more about the Gaerttner LINAC Laboratory you will find additional information at http://www.linac.rpi.edu/

CHANGES TO THE COMPUTER CODE COLLECTION

Four changes or additions were made to the computer code collection during the month. Three new code systems were packaged and added to the collection, and one code system was corrected. Two changes resulted from foreign contributions.

Oak Ridge National Laboratory contributed a replacement for the MORSE portion of this Monte Carlo code system for the design and analysis of calorimeter systems, Spallation Neutron Source (SNS) target systems, etc. CALOR95 was designed to assist experimentalists evaluate and analyze different types of calorimeter systems used in many high-energy physics experiments to determine the energy and direction of incident hadrons, leptons, and photons. The code package contains HETC95, SPECT95, EGS4, MORSE, and other support programs. The MORSE version in earlier releases of CALOR95 did not yield the correct energy balance because absorbed gamma-ray energies were underestimated.

CALOR95 runs on IBM RS/6000 computers and requires the XLF Fortran 77 compiler. It is transmitted on either one CD-ROM, DC 6150 (150 MB), 4-mm DAT (8GB), or 8-mm (2.3GB) cartridge tape in compressed UNIX tar format. References ORNL/TM-11185 (unpublished report) and SDC-92-00257 (May 1992). Fortran 77; IBM RS/6000 (C00610/IRISC/01).

The Faculty of Physics and Nuclear Techniques, University of Mining and Metallurgy, Cracow, Poland, contributed a new code system for one-dimensional transport and burnup calculations. In BISON-C the one-dimensional transport equation is solved by the discrete ordinates method with anisotropic scatterings. Bateman's method is adopted to solve the production-depletion equations for burnable nuclides. A burnup calculation is carried out by performing these two processes iteratively.

The BISON-C system was based on CCC-464/BISON 1.5, which was based on CCC-254/ANISN-ORNL. The new code system extends the original code by providing burnup calculation for fission products and other features like differentiation of time steps and burnup normalization to the required thermal power. The new burnup library, based on JENDL-3, additionally contains the fission product burnup chain and the fission yields for actinides prepared from ENDF-B/VI data files. Included is a cross-section library processing system which is comprised of XSCON, RESPL, and SIGC. BISON-C runs on Unix-based operating systems on IBM RS/6000 and HP and requires a Fortran 77 compiler. It is transmitted on 2 DS/HD diskettes in a compressed Unix tar file. Reference: INT 271/I (1997). Fortran 77; IBM RS/6000 and HP (C00659/MNYWS/00).

Argonne National Laboratory-West, Idaho Falls, Idaho, contributed this computer code system for generalized least-squares evaluation of related cross sections for ENDF/B based on Gauss, Markov, and Aitken. The simultaneous evaluation of the interrelated cross section data of ⁶Li(n,), ⁶Li(n,n), ¹⁰B(n,₀), ¹⁰B(n,₁), ¹⁰B(n,n), ¹⁹⁷Au(n,), ²³⁸U(n,), ²³⁵U(n,f), ²³⁹Pu(n,f), ²³⁸U(n,f) and the thermal constants was part of the evaluation of these data for ENDF/B-VI. The Fortran codes and the data files used for the simultaneous evaluation are included in this package. This experimental data analysis code system, known as GMA, utilizes the generalized least-squares estimation method. Associated codes included are RCL (which is used to edit, list and expand the basic data file) and DAT (which is used to reduce the cross section data to a common energy grid.)

GMA runs on UNIX operating systems on Sun and IBM RS/6000 workstations and on personal computers. Executables created with the LAHEY F77L3/EM-32 5.2 compiler are included to run on PCs in a DOS window of Windows95. The package is transmitted on 2 DS/HD diskettes in both UNIX and DOS compressed formats. References: ANL/NDM-139, (ENDF-358)(1997). Fortran 77, Fortran 90; Pentium-based PC, and Sun and IBM RS/6000 workstations (P00367/MNYCP/00).

The Department of Nuclear Reactions at Moscow State University, Russia, contributed this code system designed for quick and easy estimations of basic stopping characteristics of proton transmission for generation of the source definition (SDEF) portion of the input data for MCNP. It does not generate the full MCNP input file. The MSM-SOURCE code generates the input data for the MCNP code (for 3b and 4 versions), simulating the set of single neutron sources, produced in the sample during the proton transmission. It permits one to extend the possibilities of the MCNP code for consideration of secondary neutrons from the proton interaction with nuclei of the sample substance. The MSM-SOURCE code is applicable for calculations of the proton transport for the incident energies from 0.1 to 1 GeV and various targets 12 < A < 238.

This code is based of the Moving Source Model (MSM) and Bethe stopping theory with the relativistic corrections for protons. It allows the estimations of the proton range, the changes of the proton current and the neutron production versus the depth. The double differential spectra and the multiplicities of nucleons, produced in the primary proton-induced reactions, are obtained.

MSM-SOURCE runs on many computers including personal computers and IBM RS/6000 under either DOS or UNIX. It has been compiled with Microsoft Fortran 5.1, WatCom Fortran, NDP-Fortran, and Lahey compilers on PC. The Lahey Fortran 90 V4.5 compiler was used to create the executable included in the package which is transmitted on one DS/HD (1.44MB) diskette written in DOS format. References: README.TXT (May 1998). Fortran 77; PC 386 or higher processor, IBM RS/6000 (P00369/MNYCP/00).

CONFERENCES, COURSES, SYMPOSIA

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 raf@ornl.gov.

FLINS'98

The Third International FLINS Workshop on Fuzzy Logic and Intelligent Technologies for Nuclear Science and Industry organized by the Belgian Nuclear Research Centre ( SCKCEN) will be held September 14-16, 1998, at the Astrid Park Plaza Hotel in Antwerp, Belgium. FLINS, an acronym for Fuzzy Logic and Intelligent technologies in Nuclear Science, is an international research forum which endeavors to advance the theory and applications of fuzzy logic and novel intelligent technologies in nuclear science and industry.

Following FLINS'94 and FLINS'96, the first and second international workshops on this topic, FLINS'98 aims to bring together scientists, researchers, and people from industry to introduce the principles of intelligent systems and soft computing such as fuzzy logic (FL), neural network (NN), genetic algorithms (GA) and any combinations of FL, NN, and GA, knowledge based expert systems and complex problem solving techniques within nuclear industry and related research fields.

FLINS'98 offers a unique international forum to present and discuss new and useful techniques for nuclear science and industry. Contact: Dr. Da Ruan, FLINS'98 Chair, SCKCEN-FLINS, Nuclear Research Centre, Boeretang 200, B - 2400 Mol, Belgium (phone 32-14-33-2272, fax: 32-14-32-1529, email druan@sckcen.be). Additional information may be found at http://www.sckcen.be/conferences/flins_ 98.html.

The Second International Topical Meeting on Nuclear Applications of Accelerator Technology (AccApp'98) is sponsored by the Accelerator Applications Technical Group of the American Nuclear Society (ANS), and is hosted by the Oak Ridge-Knoxville, Tennessee, Section of the ANS. It will be held in Gatlinburg, Tennessee, during the week of September 20-23, 1998, at the Park Vista Hotel & Conference Center. AccApp'98 will provide a forum for discussion of the uses of particle accelerator technology for nuclear applications. It will focus on production of neutrons and other particles, utilization of these particles for scientific or industrial purposes, production or destruction of radionuclides significant to energy, medicine, defense, or other endeavors, as well as imaging and diagnostics. Relevant information is located at http://www.engr.utk.edu/org/ans/AccApp98.

21st RERTR

The 21st International Meeting on Reduced Enrichment for Research and Test Reactors (RERTR) will be held October 18-23, 1998, in São Paulo, Brazil. Information will be exchanged on the progress of national and international programs to develop low enriched fuels for research and test reactors and to convert the reactors to such fuels. This meeting is organized by the Institute of Research and Development Directorate of the Brazilian Nuclear Energy Commission (CNEN) (IPEN) in cooperation with the International Atomic Energy Agency, Argonne National Laboratory, the Brazilian Nuclear Energy Commission, the Brazilian Association for Nuclear Energy (ABEN), and other sectors of the Brazilian nuclear energy industry. Further information about the meeting is available from Dr. José Rubens Maiorino, Chairman 1998-RERTR Meeting, Comissão Nacional de Energia Nuclear, Instituto de Pesquisas Energéticas e Nucleares, Diretoria de Reatores, Travessa R 400 - Cidade Universitária- CEP: 05508-900, São Paulo - SP - Brazil (phone 55-11-) 816-9111, fax 55-11-816-9432, email rertr98@net.ipen.br), or please visit the webpage at url http://www.ipen.br/r/rertr/rertr.html).

CIRMS

The Seventh Annual Meeting of the Council on Ionizing Radiation Measurements and Standards (CIRMS) will be held at the National Institute of Standards and Technology, Gaithersburg, Maryland, October 19-21, 1998. CIRMS is a non-profit, U.S. Council, with representation from academic, professional and industrial associations and organizations, government agencies and interested individuals. CIRMS provides an opportunity for open discussion of current issues concerning ionizing radiation and future directions of measurements and standards. For more information contact Katy Nardi, (phone 770-622-0026, email KatyNardi@aol.com).

Tenth International Symposium on Reactor Dosimetry

The Tenth International Symposium on Reactor Dosimetry will be held September 12-17, 1999, in Osaka, Japan. This Symposium is held about every three years to provide a forum for the interchange of state-of-the-art techniques, databases and standardization of radiation metrology. The Symposium will be of value to those involved in reactor dosimetry, including researchers, manufacturers and representatives from industry, utilities and regulatory agencies. The Symposium is jointly sponsored by the Atomic Energy Society of Japan (AESJ), the American Society for Testing and Materials (ASTM) and the European Working Group on Reactor Dosimetry (EWGRD). It is organized by ASTM Committee E10 on Nuclear Technology and Applications and EWGRD.

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 of the following:

North and South America, East and 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
email: dwvehar@sandia.gov
Europe, Africa, Asia (other), and Australia:
Dr. Hamid Ait Abderrahim
EWGRD Programme Secretary
SCK/CEN
Boeretang 200, B-2400 Mol, BELGIUM

Phone: 32-14-332277, fax: 32-14-321529
email: haitabde@sckcen.be

"Half a Century of Radiation Shielding Research and Its Evolution into the Next Era" is the theme for the 9th International Conference on Radiation Shielding to be held October 17-22, 1999, in Tsukuba, Japan. It is sponsored and organized by the Japan Atomic Energy Research Institute and co-sponsored by the OECD-Nuclear Energy Agency-Nuclear Science Committee (NEA-NSC), Atomic Energy Society of Japan (AESJ), and the Radiation Safety Information Computational Center (RSICC). Participants in the conference explore the scientific, technological and engineering issues associated with radiation shielding in broad nuclear energy systems, accelerator facilities, space and general environments. Detailed information about the conference may be obtained from 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 keda@fnshp.tokai.jaeri.go.jp) or from the web page at http://icrs9.tokai.jaeri.go.jp.

Calendar

Your attention is directed to the following events of interest.

September 1998

AccApp'98, Sept. 20-23, 1998, Gatlinburg, Tennessee, sponsored by the Oak Ridge-Knoxville, TN, USA Section of the ANS. Contact: Dr. John Haines, Chairman, AccApp '98 Technical Program Committee, Oak Ridge National Laboratory, Oak Ridge, TN 37831-8071, USA (phone 423-574-0966, fax 423-576-7926, email hainesjr@ornl.gov, url http://www.engr.utk.edu/org/ans/AccApp98)

Training Course on the Use of MCNP in Radiation Protection and Dosimetry, Sept. 28-1 Oct. 1998, at the Imperial College of Science, Technology and Medicine, London. Contact: Robert Alan Price, Imperial College of Science, Technology and Medicine, T. H. Huxley School of the Environment, Earth Sciences and Engineering, Applied Modelling and Computation Group, Centre for Environmental Technology, Room 405, Royal School of Mines Building, Prince Consort Rd, London SW7 2BP, UK (phone 44-171-594- 9323, fax 44-171-594-9341, url http://wrench.et.ic.ac.uk/courses/).

October 1998

4th Annual Workshop on Monte Carlo Simulation of Radiotherapy Treatment Sources using the OMEGA/BEAM Code System, Oct. 5-8, 1998, Ottawa, Canada. Contact: Blake Walters, Ionizing Radiation Standards, National Research Council of Canada, Ottawa, Canada, K1A 0R6. (phone 613-993-2715, fax 613-952-9865, email bwalters@irs.phy.nrc.ca, url www.irs.inms.nrc.ca/inms/irs/BEAM/ beamhome.html)

21st International Meeting on Reduced Enrichment for Research and Test Reactors (RERTR) Oct. 18-23, 1998, São Paulo, Brazil. Contact: Dr. José Rubens Maiorino, Chairman 1998-RERTR Meeting, Comissão Nacional de Energia Nuclear, Instituto de Pesquisas Energéticas e Nucleares, Diretoria de Reatores, Travessa R 400 - Cidade Universitária- CEP: 05508-900, São Paulo - SP - Brazil (phone 55-11-816-9111, fax 55-11-816-9432, email rertr98@net.ipen.br; url http://www.ipen.br/r/rertr/rertr.html).

7th Annual Meeting of the Council on Ionizing Radiation Measurements and Standards (CIRMS) Oct. 19-21, 1998, NIST, Gaithersburg, Maryland. Contact: Katy Nardi, (770-622-0026, email KatyNardi@aol.com).

November 1998

Radiation Safety Officer, Nov. 2-6, 1998, Las Vegas, Nevada, a Technical Short Course offering of Nevada Technical Associates. Contact: Nevada Technical Associates, Inc., P.O. Box 90748, Henderson, NV 89009 (phone 702-564-2798, fax 702-558-7672).

April 1999

First Latin American Symposium on Nuclear Tracks and Radiation, April 5-9, 1999, Caracas, Venezuela, Institute for Advanced Studies, Convention Centre. Contact: Professor Laszlo Sajo, Universidad Simon Bolivar, FE-1, Apdo 89000, Caracas, Venezuela, (phone 58-2-906- 3590, fax 58-2-906-3712, email lsajo@fis.usb.ve).

June 1999

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 pdryak@cmi.cz).

September 1999

Tenth International Symposium on Reactor Dosimetry, Sept. 12-17, 1999, in Osaka, Japan. Contact: Dr. David W. Vehar (505-845-3414, fax 505-844-0798, email: dwvehar@sandia.gov) or Dr. Hamid Ait Abderrahim (32-14-332277, fax 32- 14-321529, email haitabde@sckcen.be).

October 1999

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 keda@fnshp.tokai.jaeri.go.jp, url http://icrs9.tokai.jaeri.go.jp.

JUNE ACCESSION OF LITERATURE

The following literature cited has been reviewed and placed in the RSICC Information Storage and Retrieval Information System (SARIS), now searchable on the RSICC web server (http://www-rsicc.ornl.gov/SARIS.html). This early announcement is made as a service to the shielding 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.

RADIATION SHIELDING LITERATURE

ORNL/TM-13170/V2 . . . Characteristics of Spent Fuel from Plutonium Disposition Reactors Vol. 2: A General Electric Boiling-Water-Reactor Design. . . . Ryman, J.C.; Hermann, O.W. . . . April 1998 . . . Oak Ridge National Laboratory, Oak Ridge, TN.

Nucl. Technol., 122, 255-264 . . . Criticality Analysis of the Multiplying Material Inside the Chernobyl Sarcophagus. . . . Maucec, M.; Ravnik, M.; Glumac, B. . . . June 1998 . . . Jozef Stefan Institute, Ljubljana, Slovenia.

Nucl. Technol., 122, 276-283 . . . Fission Gas Release Determination Using an Anti-Compton Shield Detector. . . . Matsson, I.; Grapengiesser, B.; Jansson, P.; Hakansson, A.; Backlin, A. . . . June 1998 . . . ABB Atom AB, Vasteras, Sweden; Uppsala University, Uppsala, Sweden.

Nucl. Technol., 122, 306-317 . . . A Structured Methodology for Waste Management Facility Accident Analysis. . . . Mueller, C.J.; Folga, S.M.; Roglans-Ribas, J.; Nabelssi, B.; Mishima, J. . . . June 1998 . . . Argonne National Laboratory, Argonne, IL; Science Applications International Corp., Richland, WA.

Nucl. Technol., 122, 330-354 . . . Nuclear Applications of Accelerator-Driven Spallation Targets. . . . Van Tuyle, G.J. . . . June 1998 . . . Brookhaven National Laboratory, Upton, NY.