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. 615-574-6176
BitNet: PDC@ORNLSTC Internet: PDC@ORNL.GOV
364 March 1995
Among the nine American Nuclear Society (ANS) honored during the 1994 ANS Winter Meeting were long-time RSIC associates. The citation of fellow is given for notable original research or invention in the nuclear field; scientific or technical leadership in a nuclear enterprise of substantial scope; outstanding leadership as a teacher in the nuclear field; outstanding leadership in design, engineering, and operating efforts in the nuclear field; or outstanding efforts in the areas of nuclear health, safety, and regulation. The citations for John (Jack) C. Courtney and Alain Kavenoky follow.
John C. Courtney, professor of nuclear engineering, Louisiana State University, "is a dedicated teacher who played a key role in involving students in National Laboratory programs and launching them into highly productive careers in the nuclear industry. Additionally, he is a nationally recognized authority in radiation shielding and waste management working as visiting scientist at Argonne National Laboratory-West since 1975."
Alain Kavenoky, manager, computers and telecommunications department, Commissariat á l'Energie Atomique, "For leadership in the development of computational methods applied in the design and operation of French light water reactors. These methods have made a significant contribution to the efficiency and safety of this very successful nuclear energy program."
All of us at RSIC know how well-deserved this award is for both Courtney and Kavenoky and add our congratulations to both of them.
Four changes were made to the computer code collection during the month. One new code system was packaged and added to the collection, two existing code packages were replaced with newly frozen versions, and one package was enhanced with additional libraries. One change resulted from a foreign contribution.
OP SYS: DOS, VMS
Language: Fortran 77
The KFKI Institute of Atomic Energy Research in Budapest, Hungary, contributed a newly frozen version of this code system to calculate the production and migration of radionuclides in nuclear reactor systems. TIBSO follows the nuclear transition and the spatial migration of radioactive models. The modeling of such processes is established in a very flexible way, enabling the user to investigate a wide range of problems. Nuclear data libraries from CCC-371/ORIGEN2 are used. Libraries for structural, fission product, and actinide materials are provided as part of the package, which is transmitted on one DS/HD 3.5-in. (1.44 MB) diskette in self-extracting compressed DOS files. Written in Fortran 77, this system has run on PC-386, Vax/VMS, and IBM RS/6000 workstations. References: Informal report (1994). Fortran 77; PC 386, Vax, IBM RS/6000 (C00512/MNYCP/00).\
OP SYS: DOS
Language: Fortran 77, Basic
This environmental radiation dosimetry software system was enhanced with the addition of new data contributed by Westinghouse Hanford Company, Richland, Washington. GENII is a coupled system of seven programs and associated data libraries that comprise the Hanford Dosimetry System (Generation II). The code system estimates potential radiation doses to individuals or populations from both routine and accidental releases of radionuclides to air or water and residual contamination from spills or decontamination operations. The new data improves the treatment of decay chains for calculations of doses from contaminated soil allowed to decay for hundreds of years. Air transport calculations are largely unaffected by these changes due to the short decay times involved. For this release the GENII developer at Pacific Northwest Laboratory authorized the addition of the GENII and APPRENTICE Fortran and Basic source files to the package. (The original distribution included executables only.) Note that no changes have been made to either the source or executable files for this update.
GENII runs on IBM PC/AT or compatible computers equipped with an 80287 math coprocessor and 640K of random access memory. Executables included in the package were created with the Lahey F77L and Microsoft QuickBASIC 3.0 compilers. APPRENTICE also requires the proprietary Komputerwerk FINALLY! Modules library. The package is transmitted on 5 DS/HD 3.5-in. (1.44 MB) diskettes in self-extracting compressed DOS files. References: PNL-6584 (Dec. 1988) and WHC-SD-WM-TI-596 (Nov. 1993). Fortran 77 and Basic; IBM PC (C00601/IBMPC/01).
OP SYS: OS-IV/F4-MSP
Language: Fortran 77, assembler
The Japanese Atomic Energy Research Institute (JAERI) and Nuclear Energy Data Center in Naka-gun, Japan, have enhanced this package with additional codes. BERMUDA contains nine codes to solve the time-independent transport equation for a given fixed source in a variety of geometries. In addition to the original four codes for neutron transport (which have been modified in this version) four gamma-ray transport codes and one adjoint neutron transport code were added to this shielding analysis code system for use with both fusion and fission reactors. A 125-neutron group constants library based primarily on JENDL 2 is included, but gamma-ray cross section and (n,g) production constants for use with the gamma-ray codes are not yet ready for public distribution and should be released late in 1995. BERMUDA is written in Fortran 77 and runs on Facom/VP2600 computers. The package is available on cartridge in tar format. References: JAERI 1327 (May 1992), JAERI-M 93-143 (July 1993), and JAERI 94-002 (July 1994). Fortran 77; Facom/VP2600 (C00616/FV260/01).
OP SYS: OS/VS
Language: Fortran IV, assembler
Computers: IBM 370
Format: DOS, tar
Argonne National Lab., Argonne, Illinois, through the Energy Science and Technology Software Center (ESTSC) contributed the MC**2-2 code system to calculate fast neutron spectra and multigroup cross sections. MC**2-2 solves the neutron slowing-down equations using basic neutron data derived from ENDF/B data files to determine spectra for use in generating multigroup neutron cross sections. This 1981 IBM 370 version, which processes ENDF/B-V data, was recently transferred to RSIC. No changes have been made to the code since it was originally packaged by the Nuclear Energy Software Center (NESC) in 1982. The package is available on cartridge in tar compressed format or on 9 diskettes in DOS self-extracting files. References: ANL-8144 (June 1976) and ANL/AP Memorandum (January 1981). Fortran IV and assembler; IBM 370 (P00350/I0370/00).
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 1996 Radiation Protection and Shielding Division Topical Meeting, Advancements and Applications in Radiation Protection and Shielding, will be held April 21-25 1996, at Sea Crest Resort, in North Falmouth, Massachusetts. The call for papers has been issued by the organizing committee. Those who are interested are encouraged to submit 600-900-word summaries describing significant advancements or innovative applications in the area of radiation protection and shielding. Please submit an original and two copies of the summary to the Technical Program Chair: Keith B. Spinney, Yankee Atomic Electric Company, 580 Main Street, Bolton, MA 01740-1398 (phone: 508-779-6711 X2039; fax: 508-779-6730; e-mail: email@example.com). The deadline for submittal is August 16, 1995. Authors will be notified of selection on or about October 1, 1995. Full camera-ready papers will be due January 19, 1996 for inclusion in the proceedings which will be distributed at the meeting. Paper topics are being accepted for, but are not limited to, the following topics. Please indicate the applicable topic with the summary.
|Transport Theory Analysis|
|Radiation Dosimetry and Material Damage|
|Radioactive Waste Issues|
|Health Physics/Medical Issues|
Members of LANL Radiation Transport Group (X-6) plan to attend the ANS topical meeting in Portland, Oregon (April 30-May 4). A four-hour informal workshop has been established on Sunday, April 30, 1:00-5:00 pm, for those interested in the LARAMIE code system which includes MCNP, DANTSYS, and Justine. The chairmen of this workshop will be Lee Carter (Westinghouse, Hanford) and Bob Little (LANL), who intend to divide the program into (1) the status and future plans of these codes, and (2) medical/environmental/ reactor applications. In addition to the workshop, a suite will be available Monday through Thursday evening for demos and/or consultation.
The Department of Nuclear Engineering at the University of Tennessee-Knoxville is offering several short courses of interest to radiation transport specialists during Tennessee Industries Week (TIW-30), August 1418, 1995.
Computational Methods in Reactor Analysis will familiarize the course participant with computational methods and computer codes currently used to describe the neutronic behavior of nuclear fission reactors. Emphasis will be placed on "understanding" the neutronic models and associated numerical methods currently employed in codes. A good understanding of the models and methods is essential for the successful use of the codes in designing new reactors or improving the performance and safety of existing reactors. Areas to be covered include multi-dimensional diffusion theory methods and perturbation theory methods for applications in reactor statics, space-dependent kinetics, and fuel depletion; transport theory methods including the discrete ordinates method, integral transport theory, and the Monte Carlo method; and cross section generation and processing utilizing the AMPX and SCALE systems developed at ORNL. Special emphasis in the course is placed on the Monte Carlo method because of its widespread use and importance for nuclear system analysis.
Nuclear Criticality Safety is designed for those participants who wish to increase their knowledge and understanding of nuclear criticality safety. Six instructors will share over 130 years of experience with new and experienced professionals in nuclear criticality safety. The course topics include illustrative applications using the SCALE system with emphasis on the Monte Carlo code KENO Va, standards, regulations, review of accidents, hand calculational methods, subcritical limits, code validation techniques, emergency response, process upsets and recovery actions, and transient excursion modeling.
Contemporary Issues in Nuclear Power Reactor Safety presents an overview of evolving issues in nuclear power reactor safety, their potential regulatory impact, and the status of the supporting technology. These areas include risk-based regulation, implementation of severe accident considerations, issues regarding certification of advanced plants, and current research and development. Participants should have a background equivalent to a bachelor's degree in engineering or related physical sciences.
An Introduction to Fusion Technology for the Practicing Engineer presents a comprehensive introduction to Fusion Science and Technology from an engineering point of view. The focus is on practical applications of engineering design and analysis techniques for tokamak research and development programs. Projects such as the International Thermonuclear Experimental Reactor (ITER) will be used to illustrate engineering design and analysis techniques.
For additional information contact T. W. Kerlin, Head of the Dept. of Nuclear Engineering, University of Tennessee, Knoxville, TN 37996-2300 (phone 615-974-2525).
Your attention is directed to the following events of interest.
High Performance Computing '95, Apr. 9-13, 1995, Tucson, Arizona, sponsored by the Society for Computer Simulation. Contact: High Performance Computing '95, Argonne National Laboratory, 9700 S. Cass Ave., Argonne, IL 60439 (email firstname.lastname@example.org).
Applied Health Physics, Apr. 10-May 12, 1995, in Oak Ridge, Tennessee, a five-week course sponsored by Oak Ridge Associated Universities. Contact: Registrar Professional Training Programs, Oak Ridge Associated Universities, P.O. Box 117, Oak Ridge, TN 37831-0117 (phone 615-576-3576 or 615-241-4888; fax 615-576-9383).
31st Annual Meeting of the National Council on Radiation Protection and Measurements, Apr. 12-13, 1995, Arlington, Virginia. Contact: NCRP, Suite 800, 7910 Woodmont Ave., Bethesda, MD 20814-3095 (phone 800-229-2652; fax 301-907-8768).
5th Topical Meeting on Emergency Preparedness and Response, Apr. 18-21, 1995, Savannah, Georgia, sponsored by the American Nuclear Society Savannah River Section. Contact: Charles H. Hunter, Jr., Technical Program Chairman, Westinghouse Savannah River Co., Bldg. 773-A, Aiken, SC 29808 (phone 803-725-2953; fax 803-725-4233).
ICONE-3, The Third International Conference on Nuclear Engineering--Nuclear Power and the Energy Future, Apr. 23-27, 1995, Kyoto, Japan. Contact: Mr. M. Takahashi, Japan Society of Mechanical Engineers, Shinjuku-Sanshin Bldg. 5F, 2-4-9 Yoyogi, Shibuya-ku, Tokyo 151 Japan (phone 81-3-3379-6781; fax 81-3-3379-0934); or W. C. Cleff, Sargent & Lundy, 55 E. Monroe St., Chicago, IL 60603.
SCALE Training Course, Apr. 24-28, 1995, in Oak Ridge, Tennessee, sponsored by the DOE Transportation and Packaging Safety Division and hosted by the Radiation Shielding Information Center (RSIC) at ORNL. Contact: Lindy Norris, Oak Ridge National Laboratory, P.O. Box 2008, Oak Ridge, TN 37831-6370 (phone 615-574-6471).
Radiation Safety, Apr. 24-28, 1995, a training course offered by Northwestern University. Contact: Allison Ando, McCormick School of Engineering, Northwestern University, 2145 Sheridan Road, Evanston, IL 60208-3124 (phone 708-491-3365, fax 708-491-8539).
CEC Workshop: Advanced Methods in Radiation Dosimetry and Measurement, Apr. 24-28, 1995, Bad Honeff, Germany. Contact: GSF-Forschungszentrum f. Umwelt und Gesundheit GmbH, H.G. Paretzke, Ingolstaedter Landstr. 1, D-91465, Neuherberg, Germany.
Decontamination and Decommissioning of DOE and NRC Regulated Facilities, Apr. 24-28, 1995, Denver, Colorado, a short course offered by Technical Management Services, Inc., P.O. Box 226, New Hartford, CT 06057 (phone 203-738-2440; fax 203-738-9233).
International Conference on Mathematics and Computations, Reactor Physics, and Environmental Analyses, Apr. 30-May 4, 1995, Portland, Oregon. Contact: Ms. L. Briggs, Argonne National Laboratory, 9700 S. Cass Ave., Argonne, IL 60439 (phone 708-252-4677, fax 708-252-4620, email email@example.com).
1995 International High-Level Radioactive Waste Management Conference: Progress Toward Understanding, May 1-5, 1995, Las Vegas, Nevada. Contact: Allen G. Croff, American Nuclear Society, 555 N. Kensington Ave., La Grange Park, IL 60525 (fax 708-352-6464).
2nd International Nuclear Technology Forum on Nuclear Energy and Alternative Energy Resources, May 4-6, 1995, Antalya, Turkey. Contact: Chamber of Mechanical Engineers, Sumer Sok. No. 36/1-A, 06440, Demirtepe, Ankara, Turkey (fax 312-231-3165).
Conference on Nuclear Physics at Intermediate Energy, May 8-12, 1995, Trieste, Italy. Contact: ICTP, Italy (phone 39-040-22410; fax 39-040-224163).
Conference and International Symposium on Radionuclide Metrology and Its Applications, May 15-19, 1995, Paris, France. Contact: Laboratoire Primaire des Rayonnements Ionisants, P.O. Box 52, F-91193, Gif-sur-Yvette Cedex, France (fax 33-1-69-08-29-19, email ICRM@BABAORUM.CEA.FR).
Occupational Internal Dosimetry, May 15-19, 1995, Oak Ridge, Tennessee, a short course offered by Oak Ridge Associated Universities. Contact: Registrar, REAC/TS, Oak Ridge Associated Universities, P.O. Box 117, Oak Ridge, TN 37831-0117 (phone 615-576-3131 or 615-241-4888; fax 615-576-9383).
13th International Conference on Nondestructive Evaluation in the Nuclear and Pressure Vessel Industries, May 22-25, 1995, Kyoto, Japan. Contact: ASM Internatl., Member Services Center, Materials Park, OH 44073 USA (fax 216-338-4634).
3rd International Meeting on Nuclear Physics for Protection of the Environment, May 23-28, 1995, Dubna, Russian Federation. Contact: Joint Inst. for Nuclear Research, International Department, Mrs. T. Donskova, 141980, Dubna, Russian Federation (fax: 007-095-975-2381; email: firstname.lastname@example.org).
1st International Conference on Neural, Parallel, and Scientific Computations, May 28-31, 1995, Atlanta, Georgia. Contact: Morehouse College, Dept. of Mathematics, M. Sambandham, 830 Westview Drive, SW, Atlanta, GA 30314 (fax 404-458-7932, email email@example.com).
Fundamentals of Radiation Safety, June 5-9, 1995, San Diego, California, a short course offered by Technical Management Services, Inc., P.O. Box 226, New Hartford, CT 06057 (phone 203-738-2440; fax 203-738-9233).
Air Sampling for Radioactive Materials, June 12-16, 1995, in Oak Ridge, Tennessee, a short course sponsored by Oak Ridge Associated Universities. Contact: Registrar Professional Training Programs, Oak Ridge Associated Universities, P.O. Box 117, Oak Ridge, TN 37831-0117 (phone 615-576-3576 or 615-241-4888; fax 615-576-9383).
ANS Annual Meeting, June 25-29, 1995, Philadelphia, Pennsylvania. Contact: Dickinson M. Smith, PECO Energy Company, MC 63C-3, 965 Chesterbrook Blvd., Wayne, PA 19087-5681 (phone 215-640-6600) or ANS Meetings Dept., 555 N. Kensington Ave., La Grange Park, IL 60525 (phone 708-579-8258).
Environmental Monitoring, June 26-30, 1995, in Oak Ridge, Tennessee, a short course sponsored by Oak Ridge Associated Universities. Contact: Registrar Professional Training Programs, Oak Ridge Associated Universities, P.O. Box 117, Oak Ridge, TN 37831-0117 (phone 615-576-3576 or 615-241-4888; fax 615-576-9383).
Conference on Radiation Protection and Medicine, June 28-30, 1995, Montpellier, France. Contact: European Commission, DG X11/F6, Mr. H. Schibilla, 200 rue de la Loi, Building Arts 3/58, B-1049, Brussels, Belgium (fax 32-2-2966256).
Health Physics Society Summer School on Reactor Health Physics, July 16-21, 1995, Beverly, Massachusetts. Contact: Health Physics Society, 1313 Dolly Madison Blvd., Suite 402, McLean, VA 22101 (phone: 703-790-1745; fax: 703-790-2672).
International Symposium on Physics and Detectors at LHC, July 19-21, 1995, Dubna, Russian Federation. Contact: Joint Inst. for Nuclear Research, T. Donskova, 141980, Dubna, Moscow Region, Russian Federation (fax: 007-095-975-2381; email: firstname.lastname@example.org).
32nd Annual IEEE International Nuclear and Space Radiation Effects Conference, July 21-27, 1995, Madison, Wisconsin. Contact: United Technologies, Microelectronics Center, 1575 Garden of the Gods Road, Colorado Springs, CO 80907 (fax 719-594-8187).
Joint Annual Meeting of the Health Physics Society and the American Association of Physicists in Medicine to Celebrate the X-Ray Centennial, July 23-27, 1995, Boston, Massachusetts. Contact: Health Physics Society, ATTN: Richard J. Burke, Jr., Suite 130, 8000 Westpark Drive, McLean, VA 22102 (phone 703-790-1745; fax 703-790-9063) or American Association of Physicists in Medicine, ATTN: Salvatore Trofi, Jr., One Physics Ellipse, College Park, MD 20740-3846 (phone 301-209-3350; fax 301-209-0862).
10th Brazilian Meeting on Reactor Physics and Thermal Hydraulics (X ENFIR) and the 3rd Brazilian Meeting on Nuclear Applications (III ENAN), Aug. 7-11, 1995, Rio de Janeiro, Brazil. Contact: Wilma S. Bastos, IEN, C.P. 68550, CEP-21945.970, RJ, Brazil (fax 55-21-5902692: email IENRCB@BRLNCC.BITNET).
Computational Methods in Reactor Analysis and Shielding, Aug. 14-18, 1995, Knoxville, Tennessee, a short course offered by the University of Tennessee-Knoxville. Contact: T. W. Kerlin, Dept. of Nuclear Engineering, University of Tennessee, Knoxville, TN 37996-2300 (phone 615-974-2525 (fax 615-974-0668).
Nuclear Criticality Safety, Aug. 14-18, 1995, Knoxville, Tennessee, a short course offered by the University of Tennessee-Knoxville. Contact: T. W. Kerlin, Dept. of Nuclear Engineering, University of Tennessee, Knoxville, TN 37996-2300 (phone 615-974-2525 (fax 615-974-0668).
Safe Use of Radionuclides, August 21-25, 1995, in Oak Ridge, Tennessee, a short course sponsored by Oak Ridge Associated Universities. Contact: Registrar Professional Training Programs, Oak Ridge Associated Universities, P.O. Box 117, Oak Ridge, TN 37831-0117 (phone 615-576-3576 or 615-241-4888; fax 615-576-9383).
5th International Conference on Radioactive Waste Management and Environmental Remediation, Sept. 3-9, 1995, Berlin, Germany. Contact: ASME Headquarters, Ms. L. Friedman, 345 East 47th St., New York, NY 10017-2392 (fax 212-705-7856) or Battelle Pacific Northwest Laboratory, MSIN K1-19, SC Slate, P.O. Box 999, Richland, WA 99352 (fax 509-375-5963).
VOLGA-95, Sept. 4-8, 1995, in Volga, Russia. Contact: Prof. V. Khromov, Department Head, Chairman of Organizing Committee, Prof. V. Naumov, Program Chairman, or Dr. L. Goncharov, Scientific Secretary at the Moscow Engineering Physics Institute, Kashirskoe Shosse 31, Moscow, 115409, Russia (phone +7-095-323-9242; fax +7-095-324-7026; email email@example.com).
4th European Space Power Conference, Sept. 4-8, 1995, Poitiers, France. Contact: ESTEC, Power and Energy Conversion Div., Ms. J. Sanchez-Michielsen, P.O. Box 299, NL-2200, AG Noordwijk, Netherlands, or ESA Publications Division, T. D. Guyenne, NL-2200, AG Noordwijk, Netherlands (fax 31-1719-85433).
International Conference on Evaluation of Emerging Nuclear Fuel Cycle Systems (GLOBAL'95), Sept. 11-14, 1995, Palais des Congres, Versailles, France. Contact: Massimo Salvatores, CE/CADARACHE, DRN, Bat. 707, F-13108 ST. Paul-lez Durance Cedex, France (phone +33 42 25 33 65; fax: +33 42 25 41 42; internet : firstname.lastname@example.org)
Environmental Monitoring, Sept. 11-15, 1995, in Oak Ridge, Tennessee, a short course sponsored by Oak Ridge Associated Universities. Contact: Registrar Professional Training Programs, Oak Ridge Associated Universities, P.O. Box 117, Oak Ridge, TN 37831-0117 (phone 615-576-3576 or 615-241-4888; fax 615-576-9383).
Fifth International Conference on Nuclear Criticality Safety (ICNC'95), Sept. 17-22, 1995, at the Hyatt Regency Hotel in Albuquerque, New Mexico. Contact the General Chair, Norm Pruvost, at 505-667-1448 (fax 505-665-4970).
Applied Health Physics, Sept. 18-Oct. 20, 1995, in Oak Ridge, Tennessee, a five-week course sponsored by Oak Ridge Associated Universities. Contact: Registrar Professional Training Programs, Oak Ridge Associated Universities, P.O. Box 117, Oak Ridge TN 37831-0117 (phone 615-576-3576 or 615-241-4888; fax 615-576-9383).
7th International Conference on Fusion Reactor Materials, Sept. 25-29, 1995, Obninsk, Russian Federation. Contact: Inst. of Physics and Power Engineering, Prof. V. M. Chernov, 249020, Obninsk, Kaluga Region, Russian Federation (fax 007-095-230-2326).
16th Symposium on Fusion Engineering, Sept. 30-Oct. 4, 1995, Urbana, Illinois. Contact: Cella Elliott, Conference Secretary, Fusion Studies Lab., University of Illinois, Urbana, IL 61801 (phone 217-333-2772; fax 217-333-2906; email email@example.com).
International Conference on Radiation Dose Management, Oct. 3-5, 1995, Windermere, United Kingdom. Contact: European Nuclear Society, Belpstrasse 23, CH-3007, Bern, Switzerland.
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 firstname.lastname@example.org).
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.
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.
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).
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.
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: email@example.com).
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. NRC, 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.
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).
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 . . . Reactor Physics Analysis of the Pin- Cell Doppler Effect in a Thermal Nuclear Reactor . . . 1994.
ANL/RERTR/TM-19, 259-266 . . . Dose Analysis in Safety and Site Evaluation for the JMTR Core Conversion of LEU Fuel. . . . . . . July 1993 . . . Japan Atomic Energy Research Institute, Oarai Research Establishment, Ibaraki-ken, Japan; Argonne National Laboratory, Argonne, IL.
ANL/FPP-TM-275 . . . Shakedown Analysis of Fusion Reactor First Wall. . . . Majumdar, S. . . . December 1994 . . . Argonne National Laboratory, Argonne, IL.
ANL/FPP/TM-273 . . . Radioactivity Computation of Steady-State and Pulsed Fusion Reactors Operation. . . . Attaya, H. . . November 1994 . . . Argonne National Laboratory, Argonne, IL.
ASTM STP 1228 . . . Reactor Dosimetry . . . Farrar, H., IV, ed.; Lippincott, E.P., ed.; Williams, J.G., ed.; Vehar, D.W., ed. . .Eighth ASTM-Euratom Symposium on Reactor Dosimetry was held in Vail, Colorado, 29 August - 3 September 1993.
Health Phys. 68, 340-349 . . . Sensitivity of a Mixed Field Dosimetry Algorithm to Uncertainties in Thermoluminescent Element Readings. . . . Kearfott, K.J.; Han, S.; McMahan, K.L.; Samei, E. . . . February 1995 . . . University of Michigan, Ann Arbor, MI; Georgia Institute of Technology, Atlanta, GA; Oak Ridge National Laboratory, Oak Ridge, TN.
Health Phys, 68, 253-260 . . . Absorbed Dose Measurements and Calculations in Phantoms for 1.5 to 50 keV Photons. . . . Nariyama, N.; Tanaka, S-I.; Nakane, Y.; Namito, Y.; Hirayama, H.; Ban, S.; Nakashima, H. . . . February 1995 . . . Ship Research Institute, Tokyo, Japan; JAERI, Ibaraki, Japan; National Laboratory for High Energy Physics, Ibaraki, Japan.
Health Phys. 68, 205-213 . . . Gas Bremsstrahlung and Associated Photon-Neutron Shielding Calculations for Electron Storage Rings. . . . Liu, J.C.; Nelson, W.R.; Kase, K.R. . . . February 1995 . . . Stanford Linear Accelerator Center, Stanford, CA .
Health Phys., 68, 214-224 . . . A Study of the Angular Dependence Problem in Effective Dose Equivalent Assessment. . . . Xu, X.G.; Reece, W.D.; Poston, J.W., Sr. . . . February 1995 . . . Texas A&M University, College Station, TX.
Health Phys., 68, 234-252 . . . Regression Models for the Determination of the Absorbed Dose Rate with an Extrapolation Chamber for Flat Ophthalmic Applicators. . . . Romero, J.T.A.; Payan, J.R.M. . . . February 1995 . . . Instituto Nacional de Investigaciones Nucleares, Mexico.
JAERI-M-94-042 . . . Testing WIMS-D4M Cross Sections and the ANL ENDF/B-V 69-Group Library. . . . . . . March 1994 . . . Argonne National Laboratory, Argonne, IL; JAERI, Japan.
Nucl. Technol., 109, 383-397 . . . Calculation and Benchmarking of an Azimuthal Pressure Vessel Neutron Fluence Distribution Using the Boxer Code and Scraping Experiments. . . . Holzgrewe, F.; Hegedues, F.; Paratte, J.M. . . . March 1995 . . . Paul Scherrer Institut, Switzerland.
Nucl. Sci. Eng., 119, 87-96 . . . Comparison of Energy Deposition Calculations by the LAHET Code System with Experimental Results. . . . Beard, C.A.; Belyakov-Bodin, V.I. . . . February 1995 . . . Los Alamos National Laboratory, Los Alamos, NM; Institute of Theoretical and Experimental Physics, Moscow, Russia.
Nucl. Sci. Eng., 119, 97-107 . . . Intermediate Energy Nuclear Reaction Code Intercomparison: Applications to Transmutation of Long-Lived Reactor Wastes. . . . Nagel, P.; Rodens, J.; Blann, M.; Gruppelaar, H. . . . February 1995 . . . Organization for Economic Cooperation and Development Nuclear Energy Agency, Paris, France; Lawrence Livermore National Laboratory, Livermore, CA; Net.
Nucl. Sci. Eng., 119, 108-115 . . . Methods of Mathematical Statistics for Verification of Hydrogen Content in Zirconium Hydride Moderator. . . . Ponomarev-Stepnoi, N.N.; Bubelev, V.G.; Glushkov, Ye.S,; Kompaniets, G.V.; Nosov, V.I. . . . February 1995 . . . Kurchatov Institute Russian Research Centre, Moscow, Russia.
Nucl. Sci. Eng., 119, 139-143 . . . A Hennart Nodal Method for the Diffusion Equation. . . . Lesaint, P.; Noceir, S.; Verwaerde, D. . . . February 1995 . . . Laboratoire de Calcul Scientifique, Besancon, France; Dept. Physique des Reacteurs, Clamart, France.
Nucl. Technol., 109, 11-20 . . . Analysis of Epithermal Neutron Beam Experiments at the Hifar Reactor. . . . Harrington, B.V.; Constantine, G. . . . January 1995 . . . Australian Nuclear Science and Technology Organization, Menai, Australia.
Nucl. Technol., 109, 54-75 . . . Evaluation of the Uncertainties in the Source Distribution for Pressure Vessel Neutron Fluence Calculations. . . . Haghighat, A.; Mahgerefteh, M.; Petrovic, B.G. . . . January 1995 . . . Pennsylvania State University, University Park, PA.
Nucl. Technol., 109, 87-107 . . . Neutronics and Thermal-Hydraulics Analyses of the Pellet Bed Reactor for Nuclear Thermal Propulsion. . . . Morley, J.J.; El-Genk, M.S. . . . January 1995 . . . University of New Mexico, Albuquerque, NM.
Nucl. Technol., 109, 314-326 . . . Design of Neutron Beams for Neutron Capture Therapy Using a 300-kW Slab Triga Reactor. . . . Hungyuan B. Liu . . . March 1995 . . . Brookhaven National Laboratory, Upton, NY.
NUREG/CR-6214; ORNL-6795 . . . Production and Testing of the VITAMIN-B6 Fine Group and the BUGLE-93 Broad-Group Neutron/Photon Cross-Section Libraries Derived from ENDF/B-VI Nuclear Data. . . . Ingersoll, D.T.; White, J.E.; Wright, R.Q.; Hunter, H.T.; Slater, C.O.; Greene, N.M.; Roussin, R.W.; MacFarlane, R.E. . . . January 1995 . . . Oak Ridge National Laboratory, Oak Ridge, TN; Los Alamos National Laboratory, Los Alamos, NM.
EGG-2596-V6 RELAP5/MOD3 RELAP5/MOD3 Code Manual: Volume 6: Validation of Numerical Techniques in RELAP5/MOD3. . . . Shieh, A.S.; Ransom, V.H.; Krishnamurthy, R. . . . 10/94 . . . EG&G Idaho, Inc. Idaho Falls, ID ; Nuclear Regulatory Commission, Washington, DC . . . OSTI; NTIS (doc only); ESTSC; INIS; GPO. EGG-NRP-11289 DCHAIN DCHAIN: A User-Friendly Computer Program for Radioactive Decay and Reaction Chain Calculations. . . . East, L.V. . . . 05/94 . . . EG&G Idaho, Inc., Idaho Falls, ID . . . INIS (mf only); OSTI; NTIS; GPO. EPRI-TR-103188; CONF-9311154- THERMAL-HYDRAULIC Thermal-Hydraulic Analysis of Light Water Reactors Using Moving Boundaries. . . . Secker, P.A., Jr.; Han, G.Y.; Stanley, T.P. . . . 11/93 . . . University of Arizona, Tucson, AZ . . . EPRI . . . .Proceedings: Second International Seminar on Subchannel Analysis. Health Phys., 68, 119 GENII GENII . . . Maheras, S.J. . . . 01/95 . . RSIC. KNWLD9 17, 1065-1069 In Chinese ALICE Functions of the ALICE Code and Its Utilization. . . . Yuan Shuanggui; Xu Shuwei; Pan Qiangyan; Ou Xiulan . . . 12/93 . . . Academia Sinica, Lanzhou, China. NEBSDV 33, 303-320 MACE The MACE Computer Code for Thermal-Hydraulic Modelling of Gas Cooled Reactors. . . . Ardron, K.H.; Cooper, S. . . . 10/94 . . . . . . Nuclear Electric plc, United Kingdom . NSS/R-336 MASCOT; MOP MASCOT and MOP Programs for Probabilistic Safety Assessment. Pt. K. . . . Mawbey, C.S. . . . 04/94 . . . Engineering Sciences, Epsom, United Kingdom . . . British Library Document Supply Centre. Nucl. Sci. Eng., 119, 108-115 PASPORT Methods of Mathematical Statistics for Verification of Hydrogen Content in Zirconium Hydride Moderator. . . . Ponomarev-Stepnoi, N.N.; Bubelev, V.G.; Glushkov, Ye.S. ; Kompaniets, G.V.; Nosov, V.I. . . . 02/95 . . . . . . Kurchatov Institute Russian Research Centre, Moscow, Russia. NUREG/CP-0133-V2; CONF-931079-V2 COMMIX; PCCS Validation of COMMIX with Westinghouse AP-600 PCCS Test Data. . . . Sun, J.G.; Chien, T.H.; Ding, J.; Sha, W.T. . . . 04/94 . . . Argonne National Laboratory, Argonne, IL . . . INIS (mf only); OSTI; NTIS; GPO. NUREG/CP-0133-V2; CONF-931079-V2 FCI Integrated Fuel-Coolant Interaction Code: Assessment of Stand-Alone Version 6.0. . . . Davis, F.J., Jr. . . . 04/94 . . . Sandia National Laboratories, Albuquerque, NM . . . INIS (mf only); OSTI; NTIS; GPO. NUREG/CP-0133-V2 RASPLAV Current Status and Validation of RASPLAV Code. . . . Chudanov, V.V.; Churbanov, A.G.; Strizhov, V.G.; Vabischevich, P.N. . . . 04/94 . . . Nuclear Regulatory Commission, Washington, DC . . . INIS (mf only); OSTI; NTIS; GPO. NUREG/CP-0133-V2 SCDAP/RELAP5/MOD3.1 SCDAP/RELAP5/MOD3.1 Code Development and Assessment. . . . Allison, C.M. . . . 04/94 . . . Nuclear Regulatory Commission, Washington, DC . . . INIS (mf only); OSTI; NTIS; GPO. . NUREG/CR-6116-V5 SAPHIRE; SARA Systems Analysis Programs for Hands-on Integrated Reliability Evaluations (SAPHIRE), Version 5.0. Volume 5, Systems Analysis and Risk Assessment (SARA) Tutorial Manual. . . . Sattison, M.B.; Russell, K.D.; Skinner, N.L. . . . 0794 . . . EG&G Idaho, Inc., Idaho Falls, ID ; Nuclear Regulatory Commission, Washington, DC . . . INIS (mf only); OSTI; NTIS; GPO. RAL-94-084 PRSCAL The PRSCAL Manual. . . . Hagen, M. . . . 08/94 . . . Keele University, United Kingdom . . . British Library Document Supply Centre. RAL-94-085 PRISMA The PRISMA Operating Program Manual. . . . Hagen, M. . . . 08/94 . . . Keele University, United Kingdom . . . British Library Docuemnt Supply Centre. RAL-94-086 PRISMA GENIE The PRISMA GENIE Data Analysis Manual. . . . Hagen, M. . . . 08/94 . . . Keele University, United Kingdom . . . British Library Document Supply Centre. RAL-94-087 PRSPLOT6 The PRSPLOT6 Manual. . . . Hagen, M. . . . 08/94 . . . Keele University, United Kingdom . . . British Library Document Supply Centre. YTHLDS 15, 133-135 TSPIXE; PIXE TSPIXE-A Program for Quantitative PIXE Analysis of Thick Samples. . . . Dai Zhongning; Ren Chigang; Liu Nianqing . . . 05/93 . . . . . . Fudan University, Shanghai, China.