Oak Ridge National Laboratory
Post Office Box 2008 Oak Ridge, Tennessee 37831-6362
managed by Lockheed Martin Energy Systems
for the U.S. Department of Energy
Phone No. 423-574-6176
FAX 423-574-6182
BitNet: PDC@ORNLSTC Internet: PDC@ORNL.GOV
WWW: http://epicws.epm.ornl.gov
370 September 1995
RSIC can now write codes and data libraries on CD-ROM using a 74-minute, 650-MB recordable disk using the ISO-9660 format. While both Unix tar files and DOS files can be read on either operating system, users must specify which operating system they will be running so that we know which version of a package to send. The RSIC Software Directory lists specifications for other media on which we can write in Section VI.
As many of our users know, a signed software license form is now required before any code or data library can be shipped from RSIC. For the convenience of our readers a blank copy of the software license form will be included at the end of each newsletter as well as a blank request form. Simply fill in the blanks with the name and number of the code or data library.
The first announcement and call for papers has been issued for the Fifth International Conference on Applications of Nuclear Techniques. The Conference will be held June 9-15, 1996, in Crete, Greece. The theme of the conference is Neutrons in Research and Industry, and the anticipated topics for contributed papers are:
Materials Research with Neutrons | |
Nuclear Research with Neutrons | |
Neutron Dosimetry | |
Boron Neutron Capture Therapy | |
Neutron Detection | |
Neutron Production | |
Non-Intrusive Non-Destructive Testing | |
Neutron Transport Calculations | |
Signal Processing and Data Reduction |
Three changes were made to the computer code collection during the month. Two new code systems were packaged and added to the collection and an existing code package was modified. One change resulted from a foreign contribution.
CCC-629/SESOIL
OP SYS: DOS
Language: Fortran 77
Computers: PC
Format: DOS
Oak Ridge National Laboratory updated the SESOIL package with some brief background documentation on the modifications made in the February 1995 update. SESOIL is a one-dimensional, vertical transport code system for the unsaturated soil zone. The February release fixed an error that caused the program to bomb when the average monthly air temperature was -10C. The iteration procedure for the mass balance equations in the model was also improved. The previous version would eventually lose some contaminant mass if a simulation of more than several years (>20) were run. This new version takes more iterations but is more accurate. Thus, mass balance is maintained more closely in this version. SESOIL performs long-term simulations of chemical transport and transformations in the soil. The model uses theoretically derived equations to represent water transport, sediment transport on the land surface, pollutant transformation, and migration of the pollutant to the atmosphere and groundwater. The Ryan McFarland Fortran Compiler Version 3.10.01 was used to create the executable included in the package. The Fortran source, executable, and sample input and output are transmitted on one DS/HD 5.25-in. (1.2 MB) diskette in DOS format. Reference: PUBL-SW-200-93 Rev 1.6 (Aug. 1994). Fortran 77; IBM PC (C00629/IBMPC/01).
CCC-643/CITATION 2.0
OP SYS: DOS
Language: Fortran 77
Computers: PC
Format: DOS
ORNL and Atomic Energy of Canada Limited, Chalk River, Ontario, through the Energy Science and Technology Software Center (ESTSC), contributed this nuclear reactor analysis code system. CITATION 2.0 is designed to solve problems using the finite difference representation of neutron diffusion theory treating up to three space dimensions with arbitrary group-to-group scattering. The x-y-z, theta-r-z, hexagonal z, and triagonal z geometries may be treated. Depletion problems may be solved and fuel managed for multi-cycle analysis. Extensive first order perturbation results may be obtained given microscopic data and nuclide concentrations. Statistics problems may be solved and perturbation results obtained with microscopic data. This version of CITATION was released by ORNL as CITATION - Rev. 2, Supplement 3 in July 1972. Only minor modifications were made to it when AECL ported it to the PC in October 1988. No changes were made when the package was recently transferred to RSIC.
CITATION 2.0 runs on IBM PC's and compatibles. The executables were created with the Lahey Fortran compiler under DOS 3. At least 578 KB RAM must be available to run the executables included in the package. Reference: ORNL-TM-2496, Rev. 2 (July 1971). Fortran; IBM PC (C00643/IBMPC/00).
PSR-352/SCAMPI
OP SYS: Unix
Language: Fortran 77
Computers: workstation
Format: tar
Oak Ridge National Laboratory contributed this code system to manipulate multigroup cross section libraries in AMPX format. SCAMPI (SCale and AMpx Processing Interface) was prepared to facilitate the calculational procedure for creating problem-dependent cross sections (working format) from problem-independent multigroup data (master library). It consists primarily of modules derived from PSR-315/AMPX-77 and CCC-545/SCALE4.3. Included in the package are AIM, AJAX, ALE, ALPO, BONAMI, CORECTOL, CSAS, FILTER, GIP, ICE, LAVA, MALOCS, NITAWL, PERFUME, RADE, UNITAB, WAX and XSDRN. The CSASIN full-screen PC input processor that guides the user through the CSAS module input was modified and is included in SCAMPI. The CSAS module was modified to remove the interface with KENO and automatically provide output of an ANISN-formatted working library for use with codes such as CCC-543/TORT-DORT, CCC-254/ANISN-ORNL, or CCC-474/MORSE-CGA. Note that no data libraries are included in this distribution.
SCAMPI runs on Unix workstations. To facilitate installation, makefiles are included for IBM RS/6000, Sun, DEC Alpha and HP. The programs are written in Fortran 77 and C. The package is transmitted on one diskette in a tar file compressed with the GNU gzip command. The CSASIN program is included on a separate DS/HD 3.5-in. (1.44 MB) diskette in DOS format. Reference: portions of ORNL/NUREG/CSD-2/R4 (1995), ORNL/CSD/TM-283 (July 1992), ORNL/TM-12663/V1 (modified 1995). Fortran 77 and C (P00352/MNYWS/00).
One new data library was added to the collection during the month as a result of a foreign contribution.
DLC-182/ABBN-90
OP SYS: Many
Language: Fortran 77
Computers: Many
Format: DOS
The Institute of Physics and Power Engineering, Obninsk, Russia, contributed this package of multigroup constants for calculation of neutron and photon radiation fields and functionals. Basic data were selected from BROND-2, ENDF/B-VI, and JENDL-3 evaluated nuclear data libraries and processed by the GRUCON and PSR-171/NJOY91 codes. ABBN-90 presents data for 28 neutron energy groups (from the thermal to 15 MeV) and for 15 photon groups. For some materials the 299 group constants from the thermal energies and up to 20 MeV are included. Resonance self-shielding effects are taken into account by using Bondarenko self-shielding factors. Nikolaev's subgroup (optimized multiband) parameters are also included and may be used when the spatial dependence of group constants is essential. Thermalization effects are calculated using Westkott's G-factors or thermalized scattering matrices depending on neutron gas temperatures in the energy region below 4.65 eV.
The data are presented in formatted tables. The package includes the CONSYST2 code, developed for converting ABBN-90 data to various formats for use in discrete ordinates codes (CCC-254/ANISN and CCC-543/TORT-DORT, CCC-547/TWODANT-SYS) and Monte Carlo calculations. The executable for CONSYST2 was compiled with the Lahey F77L/EM32 V5.1 compiler. Both source and executable for ABBN-90 are included on three DS/HD (1.44 MB) diskettes in compressed DOS files. (References: IPPE Informal Documents (1994). Fortran 77; PC, Convex, Cyber (D00182/MNYCP/00).
In serving a specialized area of scientific endeavor, it seems important that we note significant events or changes in the activities of people concerned with radiation protection, transport, and shielding in the nuclear industry. We, therefore, continue to carry personal items as they are brought to our attention.
RSIC has learned that Sterret T. "Ted" Perkins died in March 1995. The following tribute from his colleagues is taken from the dedication of TART95: A Coupled Neutron-Photon Monte Carlo Transport Code, UCRL-MA-121319 (July 1995). "For the last quarter century Ted was a major contributor to all aspects of our efforts in particle transport, from evaluating nuclear and atom data, all the way through to the models used in our transport method, including Monte Carlo, Sn, and diffusion. He was both a great theorist and yet at the same time a very practical person; an attribute that is very rare to find in a person. He was also a good friend and he will be sorely missed by all of us."
RSIC 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 to RSIC.
The ENS Topical Meeting: Research Facilities for the Future of Nuclear Energy will be held June 4-6, 1996, in Brussels, Belgium. The meeting is organized jointly by the Belgian Nuclear Society, the Société Française d'Energie Nucléaire, with European Nuclear Society sponsorship. Those scientists who wish to participate should submit an extended abstract by December 31, 1995, on the following topics:
Uses of the current research facilities, | |
Problems specific to research facilities, | |
R&D needs related to power reactor operation and development which includes reactor core and fuel; neutronics, thermohydraulics; pressure vessel; systems (ECCS, I&C, passive systems,...); technology (steam generators, pumps, containment,...); safety, environmental protection; fuel cycle, including reprocessing; and waste management, and | |
Upgrading of existing facilities (ongoing and proposed). New facilities starting, under development or to be developed. |
The conference language will be English and will include invited and contributed papers. Both will be published in the conference transactions which will be distributed at the conference. Further details and any necessary forms may be obtained from Mr. Hamid Ait Abderrahim, CENSCK,Boeretang 200, B-2400 Mol, Belgium (phone 32 14 332277; fax: 32 14 321529; email: ensrffne@sckcen.be).
Your attention is directed to the following events of interest.
October 1995
3rd International Workshop on Dosimetry for Radiation Processing, Oct. 1-6, 1995, Québec, Canada. Contact: John D. Rickey, Far West Technology, Inc., 330 D S. Kellogg, Goleta, CA 93117 USA (phone 805-964-3615; fax 805-964-3162).
Fundamentals of Health Physics, Oct. 2-6, 1995, Knoxville, Tennessee, a course offered by Consultec Scientific, Inc. Contact: Consultec Scientific, Inc., Suite 110, 725 Pellissippi Parkway, Knoxville, TN 37932-3300 (phone 800-269-4333, fax 423-675-4334; email info@consultec.com).
Statistics for Health Physicists Oct. 2-6, 1995, Knoxville, Tennessee, a course offered by Consultec Scientific, Inc. Contact: Consultec Scientific, Inc., Suite 110, 725 Pellissippi Parkway, Knoxville, TN 37932-3300 (phone 800-269-4333, fax 423-675-4334; email info@consultec.com).
International Conference on Radiation Dose Management, Oct. 3-5, 1995, Windermere, United Kingdom. Contact: European Nuclear Society, Belpstrasse 23, CH-3007, Bern, Switzerland.
Radiation Risk, Risk Perception, and Social Constructions Seminar, Oct. 19-20, 1995, Oslo, Norway, sponsored by the Norwegian Radiation Protection Authority and the Swedish Radiation Protection Institute. Contact: Per Strand, Norwegian Radiation Protection Authority, P.O. Box 55, N-1345 Osteras, Norway.
International Symposium on Nuclear Energy, Oct. 20-21, 1995, Bucharest, Romania. Contact: C. Briatianu, Univ. Politechnicadin Bucuresti, Facultateade Inginerie Mecanica, Splaiul Independentei Nr. 313, Sector 6, 77206, Bucharest, Romania (phone 40-1-6314010/224).
Annual Meeting of the Society for Industrial and Applied Mathematics, Oct. 23-26, 1995, Charlotte, North Carolina. Contact: Soc. for Indus. and App. Math., 3600 University City Sciences Center, Philadelphia, PA 19104-2688 (fax 215-386-7999, email meetings@siam.org).
NRRPT Examination Review, Oct. 23-27, 1995, Knoxville, Tennessee, a course offered by Consultec Scientific, Inc. Contact: Consultec Scientific, Inc., Suite 110, 725 Pellissippi Parkway, Knoxville, TN 37932-3300 (phone 800-269-4333, fax 423-675-4334; email info@consultec.com).
ANS Winter Meeting, Oct. 30-Nov. 2, 1995, San Francisco. Contact: ANS, 555 N. Kensington Ave., La Grange Park, IL 60545
November 1995
Pathway Analysis and Risk Assessment for Environmental Compliance and Dose Reconstruction, Nov. 6-10, Kiawah Island, South Carolina, a course offered by Radiological Assessments Corp. Contact: RAC Course Coordination Office, ATTN: Phoebe Boelter, Suite 34, 1715 North Wells St., Chicago, IL 60614. (Phone 312-988-7667, fax 312-649-9383).
International High-Level Radioactive Waste Management, Nov. 11, 1995, Las Vegas, Nevada. Contact: Allen G. Croff, ANS, 555 N. Kensington Ave., La Grange Park, IL 60525.
Radiation Safety, Nov. 13-17, 1995, Evanston, Illinois, a course offered by Northwestern University. Contact: Northwestern University, McCormick Continuing Professional Development, 2145 Sheridan Road, Room 2823, Evanston, IL 60208 (phone 708-491-3365, fax 708-467-3033).
8th Symposium on Neutron Dosimetry: Advances in Nuclear Particle Dosimetry for Radiation Protection and Medicine, Nov. 13-17, 1995, Paris, France. Contact: CEC, DG XII/F/6, Dr. H. G. Menzel, 200 rue de la Loi, Building Arts 3/61, B-1049, Brussels, Belgium (fax 32-2-296-6256).
Environment Safety and Health Conference, Nov. 13-17, 1995, Denver, Colorado. Contact: Eleanor Crampton, U.S. Department of Energy, EH-51, 270CC Washington, DC 20875-0963 (301-903-3732).
Joint Meeting of the American Association of Physicists in Medicine with the Radiological Society of North America, Nov. 26-Dec. 1, Chicago, Illinois. Contact: AAPM, phone 212-661-9404.
Scientific Basis for Nuclear Waste Management XIX: Symposium V of the 1995 Materials Research Society Fall Meeting, Nov. 27-Dec. 1, Boston, Massachusetts. Contact: William M. Murphy, phone 210-522-5263, or Dieter Knecht, phone 208-526-3627.
ANS International Topical Meeting on Managing Plant Life, Nov. 28-30, 1995, Nice, France. Contact: Dr. S. Charbonneau, Tour Fiat, Cedex 16, F-92024, Paris, France.
4th Annual Meeting of the Council on Ionizing Radiation Measurements and Standards (CIRMS), Nov. 28-30, 1995, Gaithersburg, Maryland. Contact: Katy Nardi, phone 301-840-1812.
December 1995
11th International Conference on Packaging and Transportation of Radioactive Materials, Dec. 3-8, 1995, Las Vegas, Nevada. Contact: Laura Dechter, Social & Scientific Systems, Inc., 7101 Wisconsin Ave., Bethesda, MD 20814-4805 (phone 301-986-4870; fax 301-913-0351).
January 1996
29th Midyear Topical Meeting of the Health Physics Society: Naturally Occurring and Accelerator Produced Radioactive Material--Regulation and Risk Assessment, Jan. 7-10, 1996, Scottsdale, Arizona. Contact: HPS Secretariat, Suite 402, 1313 Dolley Madison Blvd., McLean, VA 22101.
96th Annual Meeting of the American College of Nuclear Physicians, Jan. 14-18, 1996, San Juan, Puerto Rico. Contact: American College of Nuclear Physicians, Mr. H. Johnson, Suite 700, 1101 Connecticut Ave. NW, Washington, DC 20036.
February 1996
Waste Management Meeting: HLW, LLW, Mixed Wastes and Environmental Restoration -- Working Towards a Cleaner Environment, Feb. 25-29, 1996, Tucson, Arizona. Contact: WM Symposia, Inc., 245 South Plumer, Suite 19, Tucson, AZ 85719 (fax 520-792-3993).
March 1996
3rd ASME/JSME International Conference on Nuclear Engineering, Mar. 10-13, 1996, New Orleans, Louisiana. Contact: ASME Meetings Dept., P.O. Box 2900, 22 Law Drive, Fairfield, NJ 07007-2900 USA (fax: 201-882-1717 or 201-882-5155; email infocentral@asmi.org).
1996 HEART Conference, Mar. 1821, 1996, Orlando, Florida. Contact: William A. Seidler, JAYCOR, Suite 110, 4970 Corporate Drive, Huntsville, AL 35805 (phone 205-837-9100).
Occupational & Environmental Radiation Protection, March 25-29, 1996, a course offered by the Harvard School of Public Health. Contact: Harvard School of Public Health, Office of Continuing Education, 677 Huntington Ave., LL-23, Dept. B, Boston, MA 02115-6023 (phone 617-432-1171; fax 617-432-1969; email contedu@sph.harvard.edu).
April 1996
Annual Meeting of the National Council on Radiation Protection and Measurements, Apr. 3-4, 1996, Arlington, Virginia. Contact: Natl. Council on Radiation, Protection and Measurements, Suite 800, 7910 Woodmont Ave., Bethesda, MD 20814 (fax 301-907-8768).
U.S. Nuclear Regulatory Commission Regulatory Information Conference, Apr. 9-11, 1996, Washington, D.C. Contact: Anna May Haycraft, U. S. Nuclear Regulatory Commission , Office of NRR, 12H5, Washington, DC 20555 (phone 301-504-3075).
Annual Meeting of the Radiation Research Society, Apr. 13-18, 1996, Chicago, Illinois. Contact: Radiation Research Society, M. G. Watson, Suite 600, 2021 Spring Rd., Oak Brook, IL 60521.
IRPA9, 1996 International Congress on Radiation Protection, Apr. 14-19, 1996, Vienna, Austria. Contact: Congress Secretariat, IRPA9 Congress Organizing Committee, Austropa-Interconvention, P.O. Box 30, A-1043 Vienna, Austria.
Radiation Protection and Shielding Division Topical Meeting on Advancements and Applications in Radiation Protection and Shielding, Apr. 21-25, 1996, Falmouth, Massachusetts. Contact: Keith Spinney, Yankee Atomic Electric Company, 580 Main St., Bolton, MA 01740-1398 (phone 508-568-2039; fax 508-568-3700; email spinney@yankee.com).
International High-Level Radioactive Waste Management Conference, Apr. 29-May 3, 1996, Las Vegas, Nevada, sponsored by the American Nuclear Society. Contact: ANS, Meetings Dept. 555 North Kensington Ave., La Grange Park, IL 60525 (fax 708-352-6464).
June 1996
Management & Disposal of Radioactive Waste, June 10-14, 1996, a course offered by the Harvard School of Public Health. Contact: Harvard School of Public Health, Office of Continuing Education, 677 Huntington Ave., LL-23, Dept. B, Boston, MA 02115-6023 (phone 617-432-1171; fax 617-432-1969; email contedu@sph.harvard.edu).
Planning for Nuclear Emergencies, June 17-21, 1996, a course offered by the Harvard School of Public Health. Contact: Harvard School of Public Health, Office of Continuing Education, 677 Huntington Ave., LL-23, Dept. B, Boston, MA 02115-6023 (phone 617-432-1171; fax 617-432-1969; email contedu@sph.harvard.edu).
Atmospheric Science & Radioactivity Releases, June 24-26, 1996, a course offered by the Harvard School of Public Health. Contact: Harvard School of Public Health, Office of Continuing Education, 677 Huntington Ave., LL-23, Dept. B, Boston, MA 02115-6023 (phone 617-432-1171; fax 617-432-1969; email contedu@sph.harvard.edu).
July 1996
38th Annual Meeting of the American Association of Physicists in Medicine, July 21-25, 1996, Philadelphia, Pennsylvania. Contact: Ms. A. R. Keyser, One Physics Ellipse, College Park, MD 20740-3846 (fax 301-209-0862).
November 1996
International Meeting of the American Nuclear Society and the European Nuclear Society, Nov. 10-15, 1996, Washington, DC. Contact: Meetings, ANS, 555 N. Kensington Ave., La Grange Park, IL 60525 (phone: 708-352-6611; fax: 708-352-6464).
The following literature cited has been ordered for review, and that selected as suitable will be placed in the RSIC Information Storage and Retrieval Information System (SARIS). This early announcement is made as a service to the shielding community. Copies of the literature are not distributed by RSIC. 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.
RSIC maintains a microfiche file of the literature entered into SARIS, and duplicate copies of out-of-print reports may be available on request. Naturally, we cannot fill requests for literature which is copyrighted (such as books or journal articles) or whose distribution is restricted.
This literature is on order. It is not in our system. Please order from NTIS or other available source as indicated.
Book . . . Shielding Specifications for Industrial Radiography Installations and Dosimetry Concepts. . . . Legare, J-M.; Aube, P-B. . . . 1995 . . . Ministere de I'Environnement et de la Fuane, Montreal Quebec, Canada . . . . . . In French.
Fusion Eng. and Design 28, (1995) 734-744 . . . Measurements of 14 MeV Neutron Multiplication in Spherical Beryllium Shells. . . . Von Mollendorff, U.; Alevra, A.V.; Giese, H.; Kappler, F.; Klein, H.; Tayama, R. . . . 1995 . . . Kernforschungszentrum Karlsruhe GmbH, Karlsruhe, Germany; Physikalisch-Technische Bundesanstalt, Braunschweig, Germany.
Health Phys. 68(6), 761-765 . . . Dose-Response Curve for Chromosome Translocations Measured in Human Lymphocytes Exposed to 60Co Gamma Rays. . . . Lucas, J.N.; Hill, F.; Burk, C.; Fester, T.; Straume, T. . . . June 1995 . . . Lawrence Livermore National Laboratory, Livermore, CA.
Health Phys. 68(6), 773-785 . . . Development of a Method for Calibrating in Vivo Measurement Systems Using Magnetic Resonance Imaging and Monte Carlo Computations. . . . Mallett, M.W.; Hickman, D.P.; Kruchten, D.A.; Poston, J. W., Sr. . . . June 1995 . . . Texas A&M University, College Station, TX; Los Alamos National Laboratory, Los Alamos, NM; Lawrence Livermore National Laboratory, Livermore, CA.
Health Phys. 68(6), 845-850 . . . A Comparison of Results for the University of Missouri Research Reactor Radiological Airborne Release Assessments Obtained From PC-Based Computer Programs. . . . Rong, X.; Kutikkad, K.; Langhorst, S.M. . . . June 1995 . . . University of Missouri-Columbia, Columbia, MO.
Health Phys. 68(6), 855-858 . . . Evaluation of Tungsten and Lead Surgical Gloves for Radiation Protection. . . . Vano, E.; Fernandez, J.M.; Delgado, V.; Gonzalez, L. . . . June 1995 . . . Complutense University, Madrid, Spain; San Carlos University Hospital, Madrid, Spain.
Health Phys. 69(1), 1-5 . . . A Review of Some Available Radioactive and Non-Radioactive Substitutes for Use in Biomedical Research. . . . Party, E.; Gershey, E.L. . . . July 1995 . . . The Rockefeller University, New York, NY.
Health Phys. 69(1), 34-45 . . . Variations in Astronaut Radiation Exposure Due to Anisotropic Shield Distribution. . . . Wilson, J.W.; Nealy, J.E.; Wood, J.S.; Qualls, G.D.; Atwell, W.; Shinn, J.L.; Simonsen, L.C. . . . July 1995 . . . NASA Langley Research Center, Hampton, VA; Flight Mechanics Control, Inc., Hampton, VA; Rockwell International, Houston, TX.
Health Phys. 69(1), 93-101 . . . Estimates of Radiogenic Cancer Risks. . . . Puskin, J.S.; Nelson, C.B. . . . July 1995 . . . U.S. Environmental Protection Agency, Washington, DC.
Health Phys. 69(1), 130-136 . . . Shielding and Radiation Safety Around a Superconducting Cyclotron Neutron Therapy Facility. . . . Yudelev, M.; Maughan, R.L.; Dunlap, K. . . . July 1995 . . . Gershenson Radiation Oncology Center, Harper Hospital and Wayne State University, Detroit, MI.
Health Phys. 69(3), 346-355 . . . An Analysis of the Equivalent Dose Calculation for the Remainder Tissues. . . . Zankl, M.; Drexler, G. . . . September 1995 . . . Institut f. Strahlenschutz, Neuherberg, Germany.
Health Phys. 69(3), 378-384 . . . Effects of Elastic and Inelastic Scattering in Giving Electrons Tortuous Paths in Matter. . . . Turner, J.E.; Hamm, R.N. . . . September 1995 . . . Oak Ridge National Laboratory, Oak Ridge, TN.
Nucl. Instrum. Methods, in Phys. Res. A, 356, 403-407 . . . The Confusing Issue of the Neutron Capture Cross-Section to Use in Thermal Neutron Self-Shielding Computations. . . . Blaauw, M.; Blaauw, M. . . . 1995 . . . Delft University of Technology, Mekelweg, Delft, Netherlands.
Nucl. Instrum. Methods in Phys. Res. A 357, 55-63 . . . Radiation Hardness Studies on Silicon Detectors in Fast Neutron Fields. . . . Angelescu, T.; Cheremukhin, A.E.; Ghete, V.M.; Ghiordanescu, N.; Golutvin, I.A.; Lazanu, S.; Lazanu, I.; Mihul, A.; Radu, A.; Susova, N.Yu.; Vasilescu . . . 1995 . . . Bucharest University, Bucharest Magurele, Romania; Joint Institute for Nuclear Research, Dubna, Russian Federation; Institute of Physics and Nuclear Engineering, Bucharest Magurele, Romania.
Nucl. Instrum. and Methods in Phys. Res. A 357, 120-124 . . . Transfer of Physics Detector Models into Computer Aided Design Systems. . . . Hoimyr, N.; Vuoskoski, J. . . . 1995 . . . CERN, Geneva, Switzerland.
Nuclear Safety, 36, 58-67 . . . Modeling and Analysis of Core-Debris Recriticality During Hypothetical Severe Accidents in the Advanced Neutron Source Reactor. . . . Kim, S.-H.; Georgevich, V.; Simpson, D.B.; Slater, C.O.; Taleyarkhan, R.P. . . . June 1995 . . . Oak Ridge National Laboratory, Oak Ridge, TN.
Nuclear Safety, 36, 94-108 . . . Coupled RELAP5 and CONTAIN Accident Analysis Using PVM. . . . Smith, K.A.; Baratta, A.J.; Robinson, G.E. . . . June 1995 . . . Oak Ridge National Laboratory, Oak Ridge, TN; The Pennsylvania State University, University Park, PA.
Nuclear Safety 36, 135-142 . . . Atmospheric Dispersion and the Radiological Consequences of Normal Airborne Effluents from a Nuclear Power Plant. . . . Fang, D.; Sun, C.Z.; Yang, L. . . . June 1995 . . . Tsinghua University, Beijing, People's Republic of China; Suzhou Nuclear Research Institute, Ministry of Electric Power Industry, Suzhou, People's Republic of China.
Nuclear Safety, 36, 142-152 . . . Calculation of Distribution Coefficients for Radionuclides in Soils and Sediments. . . . Puigdomenech, I.; Bergstrom, U. . . . June 1995 . . . Studsvilk Eco and Safety AB, Nykoping, Sweden.
Nucl. Sci. Eng., 120, 1-17 . . . Performance Modeling of Parallel Algorithms for Solving Neutron Diffusion Problems. . . . Azmy, Y.Y.; Kirk, B.L. . . . May 1995 . . . Oak Ridge National Laboratory, Oak Ridge, TN.
Nucl. Sci. Eng., 120, 18-39 . . . Physics Characteristics of Nuclear Power Systems with Reduced Long-Term Radioactivity Risk. . . . Salvatores, M.; Slessarev, I.; Uematsu, M. . . . May 1995 . . . Commissariat a l'Energie Atomique, St-Paul-lez-Durance, France.
Nucl. Sci. Eng., 120, 40-54 . . . Thick-Target Neutron Yield for Charged Particles. . . . Shin, K.; Miyahara, K.; Tanabe, E.; Uwamino, Y. . . . May 1995 . . . Kyoto University, Kyoto, Japan; University of Tokyo, Tokyo, Japan.
Nucl. Sci. Eng., 120, 55-64 . . . Inelastic Neutron Scattering by 235U and 238U Nuclei. . . . Kornilov, N.V.; Kagalenko, A.B. . . . May 1995 . . . Institute of Physics and Power Engineering, Obninsk, Russia.
Nucl. Sci. Eng., 120, 65-71 . . . Behavior and Removal of Radionuclides Generated in the Cooling Water of a Proton Accelerator. . . . Degueldre, C.; Bilewicz, A.; Alder, H.P. . . . May 1995 . . . Paul Scherrer Institute, Villigen- PSI, Switzerland.
Nucl. Sci. Eng., 120, 75-90 . . . P1, P2, and Asymptotic Approximations for Stochastic Transport. . . . Bingjing Su; Pomraning, G.C. . . . June 1995 . . . University of California, Los Angeles, CA.
Nucl. Sci. Eng., 120, 91-101 . . . Application of Piecewise Polynomial Collocation to the Unconstrained Quasi- Static Method for Canada Deuterium Uranium (CANDU) Reactor Space-Time Kinetics. . . . Monier, A. . . . June 1995 . . . ENERTEX, Toronto, Ontario, Canada.
Nucl. Sci. Eng., 120, 102-109 . . . A New MCNP Option: KCORR - The Use of the Correlated Sampling Method to Study Reactivity Effects Due to Changes of a Reactor Arrangement. . . . Gallmeier, F.X. . . . June 1995 . . . Oak Ridge National Laboratory, Oak Ridge, TN.
Nucl. Sci. Eng., 120, 110-123 . . . One-Dimensional Diffusion Theory Kinetics in RELAP5. . . . Terry, W.K.; Nigg, D.W. . . . June 1995 . . . Idaho National Engineering Laboratory, Idaho Falls, ID.
Nucl. Sci. Eng., 120, 136-145 . . . Systematics in Differential Thick-Target Neutron Yields Parameterized by Moving Source Model. . . . Shin, K.; Miyahara, K.; Tanabe, E.; Uwamino, Y. . . . June 1995 . . . Kyoto University, Kyoto, Japan; Institute of Physical and Chemical Research, Saitama, Japan.
Nucl. Sci. Eng., 120, 147-164 . . . A Diffusion-Synthetic Acceleration Technique for the Even-Parity Sn Equations with Anisotropic Scattering. . . . Morel, J.E.; McGhee, J.M. . . . July 1995 . . . Los Alamos National Laboratory, Los Alamos, NM.
Nucl. Sci. Eng., 120, 165-186 . . . Exponential Characteristic Spatial Quadrature for Discrete Ordinates Radiation Transport with Rectangular Cells. . . . Minor, B.; Mathews, K. . . . July 1995 . . . Air Force Institute of Technology/ENP, Wright-Patterson AFB, OH.
Nucl. Sci. Eng., 120, 187-198 . . . Anisotropic Scattering Treatment for the Neutron Transport Equation with Primal Finite Elements. . . . Akherraz, B.; Fedon-Magnaud, C; Lautard, J.J.; Sanchez, R. . . . July 1995 . . . Commissariat a l'Energie Atomique, Gif sur Yvette Cedex, France.
Nucl. Sci. Eng., 120, 199-210 . . . Effects of Linear Polarization and Doppler Broadening on the Exposure Buildup Factors of Low-Energy Gamma Rays. . . . Namito, Y.; Ban, S.; Hirayama, H. . . . July 1995 . . . National Laboratory for High Energy Physics, Ibaraki-ken, Japan.
Nucl. Sci. Eng., 120, 211-222 . . . Approximating Model for Multilayer Gamma-Ray Buildup Factors by Transmission Matrix Method: Application to Point Isotropic Source Geometry. . . . Shin, K.; Hirayama, H. . . . July 1995 . . . Kyoto University, Kyoto, Japan; National Laboratory for High Energy Physics, Ibaraki-ken, Japan.
Nucl. Sci. Eng., 120, 223-230 . . . Neutron Temperature Measurements in a Cryogenic Hydrogenous Moderator. . . . Ball, R.M.; Hoovler, G.S.; Lewis, R.H. . . . July 1995 . . . Babcock & Wilcox, Lynchburg, VA; Consultant, 4502 Boonsboro, Rd., Lynchburg, VA.
Nucl. Technol., 111, 122-132 . . . Neutronics and Engineering Design of the Aqueous-Slurry Accelerator Transmutation of Waste Blanket. . . . Beard, C.A.; Buksa, J.J.; Cappiello, M.W.; Davidson, J.W.; Elson, J.S.; Ireland, J.R.; Krakowski, R.A.; Krohn, B.J.; Sailor, W.C.; Sapir, J.L. . . . July 1995 . . . Los Alamos National Laboratory, Los Alamos, NM.
Nucl. Technol., 111, 133-148 . . . Long-Lived Waste Transmutation in Reactors. . . . Tommasi, J.; Delpech, M.; Grouiller, J-P.; Zaetta, A. . . . July 1995 . . . Commissariat a l'Energie Atomique, St-Paul-lez-Durance Cedex, France.
Nucl. Technol., 111, 149-162 . . . Transmutation of High-Level Radioactive Waste By a Charged-Particle Accelerator. . . . Takahashi, H. . . . July 1995 . . . Brookhaven National Laboratory, Upton, NY.
Nucl. Technol., 111, 169-182 . . . Estimation and Interpretation of keff Confidence Intervals in MCNP. . . . Urbatsch, T.J.; Forster, R.A.; Prael, R.E.; Beckman, R.J. . . . August 1995 . . . University of Michigan, Ann Arbor, MI; Los Alamos National Laboratory, Los Alamos, NM.
Nucl. Technol., 111, 183-196 . . . Validation of KENO V.a with ENDF/B-V Cross Sections for 233U Systems. . . . Dunn, M.E.; Basoglu, B.; Bentley, C.L.; Haught, C.; Plaster, M.J.; Wilkinson, A.D.; Yamamoto, T.; Dodds, H.L. . . . August 1995 . . . University of Tennessee, Knoxville, TN; Japan Atomic Energy Research Institute, Ibaraki-ken, Japan.
Nucl. Technol., 111, 197-218 . . . Analyses of Hypothetical Nuclear Criticality Excursions in 10- and 20-MW Freezer/Sublimer Vessels. . . . Haught, C.F.; Jordan, W.C.; Basoglu, B.; Brewer, R.W.; Wilkinson, A.D.; Dodds, H.L. . . . August 1995 . . . Martin Marietta Utility Services, Piketon, OH; Martin Marietta Energy Systems, Inc.; Oak Ridge, TN; University of Tennessee, Knoxville, TN; Los Alamos National Laboratory, Los Alamos, NM; EG&G Rocky Flats, Golden, Colorado.
Nucl. Technol., 111, 219-226 . . . Analysis of a Hypothetical Criticality Accident in a Waste Supercompactor. . . . Plaster, M.J.; Basoglu, B.; Bentley, C.L.; Dunn, M.E.; Ruggles, A.E.; Wilkinson, A.D.; Yamamoto, T.; Dodds, H.L. . . . August 1995 . . . University of Tennessee, Knoxville, TN.
Nucl. Technol., 111, 227-240 . . . Improved Dose Estimates for Nuclear Criticality Accidents. . . . Wilkinson, A.D., Basoglu, B.; Bentley, C.L.; Dunn, M.E.; Haught, C.F.; Plaster, M.J.; Yamamoto, T.; Dodds, H.L.; Hopper, C.M. . . . August 1995 . . . University of Tennessee, Knoxville, TN; Martin Marietta Utility Systems, Piketon, OH; Japan Atomic Energy Research Institute, Ibaraki-ken, Japan; Martin Marietta Energy Systems, Oak Ridge, TN.
Nucl. Technol., 111, 270-274 . . . Three-Dimensional Neutron Flux Calculations for the VVER Pressure Vessel. . . . Belousov, S.I.; Ilieva, K.D.; Antonov, S.Y. . . . August 1995 . . . Institute for Nuclear Research and Nuclear Energy, Sofia, Bulgaria.
Phys. Review C, 43, 1855-1866 . . . Neutron Production for Thick Targets Bombarded by Alpha Particles: Experiment and Theoretical Analysis of Neutron Energy Spectra. . . . Sarkar, P.L.; Bandyopadhyay, T.; Muthukrishnan, G. . . . April 1991 . . . Bhabha Atomic Research Centre, Calcutta, India; Saha Institute of Nuclear Physics, Calcutta, India.
ANL-TD/CP-85106; CONF-9409107-7 . . . Validation of the WIMSD4M Cross-Section Generation Code with Benchmark Results. . . . Deen, J.R.; Woodruff, W.L.; Leal, L.E. . . . 1995 . . . Argonne National Laboratory, Argonne, IL.
EDF-93-NB-00155 . . . Comparative Study of Polynomial and Analytic Nodal Methods. . . . Bouamrirene, A. . . . October 1993 . . . Electricite de France (EDF), Clamart, France . . . In French.
NUREG/CP-0133-Vol.3, 95-110 . . . VVER-440 Dosimetry and Neutron Spectrum Benchmark. . . . Sajo, E.; Kam, F.B.K. . . . April 1994 . . . Louisiana State University, Baton Rouge, LA; Nuclear Regulatory Commission, Washington, DC.
NUREG-1465 . . . Accident Source Terms for Light-Water Nuclear Power Plants. Final Report. . . . Soffer, L.; Burson, S.B.; Ferrell, C.M.; Lee, R.Y.; Ridgely, J.N. . . . February 1995 . . . Nuclear Regulatory Commission, Washington, DC.
NUREG/CR-6311 . . . Evaluating Prediction Uncertainty. . . . McKay, M.D. . . . March 1995 . . . Los Alamos National Laboratory, Los Alamos, NM.
ANL/FPP/TM-273 . . . Radioactivity Computation of Steady-State and Pulsed Fusion Reactors Operation. . . . Attaya, H. . . . November 1994 . . . Argonne National Laboratory, Argonne, IL.
ANL/FPP/TM-276 . . . Summary Report for ITER Task - D4: Activation Calculations for the Stainless Steel ITER Design. . . . Attaya, H. . . . February 1995 . . . Argonne National Laboratory, Argonne, IL.
ANL/NDM-135 . . . Neutron Scattering from Elemental Uranium and Thorium. . . . Smith, A.B.; Chiba, S. . . . January 1995 . . . Argonne National Laboratory, Argonne, IL.
Ann. Nucl. Energy, Vol. 21, 309-320 . . . Stiffness in Radioactive Decay Chains. . . . Thomas, G.F.; Barber, D.H. . . . 1994 . . . Ontario Hydro Technologies, Toronto, Ontario, Canada.
Ann. Nucl. Energy, 20, 407-414 . . . Numerical Solution of Bateman Systems. . . . Thomas, G.F.; Barber, D.H. . . . 1993 . . . Ontario Hydro Technologies, Toronto, Ontario, Canada.
EPRI TR-104329 . . . Evaluation of Shielding Analysis Methods in Spent Fuel Cask Environments. . . . Broadhead, B.L.; Tank, J.S.; Childs, R.L.; Parks, C.V.; Taniuchi, H. . . . May 1995 . . . Electric Power Research Institute, Palo Alto, CA; Oak Ridge National Laboratory, Oak Ridge, TN.
FERMILAB-Conf-95/037 . . . Backgrounds and Detector Performance at a 2 x 2 TeV (m)+(m)- Collider. . . . Foster, G.W.; Mokhov, N.V. . . . March 1995 . . . Fermi National Accelerator Laboratory, Batavia, IL.
FERMILAB-Conf-95/100 . . . 2 x 2 TeV (m)+(m)- Collider: Lattice and Accelerator-Detector Interface Study. . . . Gelfand, N.M.; Mokhov, N.V. . . . May 1995 . . . Fermi National Accelerator Laboratory, Batavia, IL.
FERMILAB-FN-629 . . . Reduction of Tevatron and Main Ring Induced Backgrounds in the D0 Detector. . . . Butler, J.M.; Denisov, D.S.; Diehl, H.T.; Drozhdin, A.I.; Mokhov, N.V.; Wood, D.R. . . . May 1995 . . . Fermi National Accelerator Laboratory, Batavia, IL.
INDC(CPR)-035 . . . Analyses on Neutron Multiplication Integral Experiments on Beryllium. . . . LIU Lianyan; ZHANG Yuquan . . . December 1994 . . . Institute of Applied Physics and Computational Mathematics, Beijing, P.R. China.
IAEA-NDS-0, Rev. 95/7 . . . Index to the IAEA-NDS-Documentation Series. . . . Lemmel, H.D. . . . July 1995 . . . International Atomic Energy Agency, Vienna, Austria.
IAEA-NDS-7, Rev. 95/7 . . . Index of Nuclear Data Libraries Available for the IAEA Nuclear Data Section. . . . Lemmel, H.D. . . . July 1995 . . . International Atomic Energy Agency, Vienna, Austria.
INDC(NDS)-304 . . . Progress in Fission Product Nuclear Data. . . . Lammer, M. . . . 1994 . . . International Atomic Energy Agency, Vienna, Austria.
INDC(NDS)-313 . . . FENDL Neutronics Benchmark: Neutron Leakage Spectra from Be, Fe, Bp, PbLi Shells with 14MeV Neutron Source. . . . Simakov, S.P.; Devkin, B.V.; Kobozev, M.G.; Talalaev, V.A. . . . December 1994 . . . Institute of Physics and Power Engineering, Obninsk, Russian Federation; International Atomic Energy Agency, Vienna, Austria.
INDC(NDS)-314 . . . FENDL Neutronics Benchmark: Neutron Multiplication Measurements in Beryllium, Beryllium Oxide and Lead with 14-MeV Neutrons. . . . Basu, T.K. . . . December 1994 . . . Bhabha Atomic Research Center, Bombay, India; International Atomic Energy Agency, Vienna, Austria.
INDC(NDS)-336 . . . Report of the IAEA Nuclear Data Section to the International Nuclear Data Committee for the Period 1993/1994. . . . Dunford, C.L. . . . July 1995 . . . International Atomic Energy Agency, Vienna, Austria.
INDC(NDS)-337 . . . A Study into the Reliability of Collapsing SAND-II 640 Multigroup Data Into VITAMIN-J 175 Multigroup Cross Sections. . . . Wienke, H. . . . July 1995 . . . International Atomic Energy Agency, Vienna, Austria.
INDC(PAK)-010 . . . A Computer Code for Nuclear Optical Model Calculations. . . . Gul, K. . . . July 1995 . . . Pakistan Institute of Nuclear Science and Technology, Islamabad, Pakistan; International Atomic Energy Agency, Vienna, Austria.
INDC(SLN)-001 . . . Sensitivity of the B1 Leakage Edit in WIMS-D/4 on the P1 Scattering Matrix. . . . Trkrov, A. . . . December 1994 . . . University of Ljubljana, Institute "Jozef Stefan", Ljubljana, Slovenia.
KEK Preprint 94-196 . . . Effects of Linear Polarization and Doppler Broadening on the Exposure Buildup Factors of Low-Energy Gamma Rays. . . . Namito, U.; Ban, S.; Hirayama, H. . . . February 1995 . . . National Laboratory for High Energy Physics, Ibaraki-ken, Japan.
KEK Preprint 94-194 . . . Approximation Model for Multilayer Gamma-Ray Buildup Factors by Transmission Matrix Methods: Application to Point Isotropic Source Geometry. . . . Shin, K.; Hirayama, H. . . . February 1995 . . . Kyoto University, Kyoto, Japan; National Laboratory for High Energy Physics, Ibaraki-ken, Japan.
NSC/DOC(95) 2 . . . Thick Target Benchmark for Lead and Tungsten. . . . Filges, D.; Nagel, P.; Neef, R.D., Eds. . . . 1995 . . . OECD, Issy les Moulineaux, France.
ORNL/TM-12742 . . . Investigation of Nuclide Importance to Functional Requirements Related to Transport and Long-Term Storage of LWR Spent Fuel. . . . Broadhead, B.L.; DeHart, M.D.; Ryman, J.C.; Tang, J.S.; Parks, C.V. . . . June 1995 . . . Oak Ridge National Laboratory, Oak Ridge, TN.
UKAEA/NID-4d/SEP1-1/1(94) . . . Elemental Compositions of Candidate Structural Materials Including Impurities and Tramp Elements, and Their Effects on Activation Characteristics. . . . Sublet, J-C. . . . July 1994 . . . UKAEA Government Division, Oxfordshire, United Kingdom.
UKAEA/NID-4d/SEP1-1/2(94) . . . ITER Neutronic Analysis, Neutron Wall Loading Distribution and Components Spectral Data. . . . Sublet, J-C. . . . August 1994 . . . UKAEA Government Division, Oxfordshire, United Kingdom.
WHC-EP-0727 . . . Processing of FENDL-PA/1.1. . . . Mann, F. M.; Lessor, D.E.; Carter, L.L. . . . February 1994 . . . Westinghouse Hanford Co., Richland, WA.