| 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 |
| No. 397 | January 1998 |
There is no genius in life like the genius of energy and industry.--D. G. Mitchell
Three changes were made to the computer code collection during the month. Two existing code packages were enhanced with additions or corrections to the software, and an existing code package was replaced with a newly frozen version. One change resulted from a foreign contribution.
CCC-643/CITATION-LDI2 OP SYS: DOS LANGUAGE: Fortran 77 COMPUTERS: PC FORMAT: Unix and DOS |
Oak Ridge National Laboratory contributed an addition to this nuclear reactor analysis code system called CITAXSEC, which processes a binary microscopic cross section file to make an ASCII file which CITATION can use directly as part of the input data. |
|
CITATION 2.0 is
designed to solve problems using the finite difference representation of
neutron theory treating up to three space dimensions with arbitrary
group-to-group scattering. In CITATION 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.
The codes run on personal computers equipped with an 80386 processor or better. The executables were created with the Lahey Fortran V5.1 and 5.2 compilers under DOS 6.22. They can be run in a DOS window of Windows95. At least 578 kB RAM must be available to run the executables included in the package. The package which includes source, executables, and test cases is transmitted on two 1.44 DS/HD 3.5-in. diskettes in self-extracting compressed DOS files. No cross sections are included. References: Informal notes (1996) and ORNL-TM-2496, Rev. 2 (July 1971). Fortran; PC (C00643/PC386/01). |
|
CCC-646/SKYSHINE-KSU OP SYS: DOS LANGUAGE: Fortran 77,C COMPUTERS: PC FORMAT: DOS |
Kansas State University, Manhattan, Kansas, contributed modified versions of the programs in the SKYSHINE-KSU package. The new version of McSKY is 2.3. (Earlier versions give incorrect results for a double source shield of different materials.) Minor corrections were made to the other codes in this system. |
|
In SKYSHINE-KSU, the Monte
Carlo method is used to calculate neutron and gamma-ray skyshine
doses using the integral line-beam method. The SKYNEUT,
SKYDOSE, MCSKY codes, and the DLC-188/SKYDATA library are
included to form a comprehensive system for calculating skyshine
doses. The codes run on IBM PC and compatibles and can be easily
ported to almost any computer with a Fortran 77 compiler.
Executable files produced by the Microsoft Fortran compiler (version 5.1) included in the package run in a DOS window of Windows95. Source codes, executable files, response function data files, and files for input and output of sample problems are transmitted on one 3.5-in DS/HD (1.44 MB) diskette written in DOS format. References: KSU Report 9503 (revised 1/97), KSU 9502 (revised 1/98), KSU 9501 (revised 10/97), and KSU Report 271 (June 1995). Fortran 77; IBM PC (C00646/IBMPC/02). |
|
PSR-227/ECIS-95 OP SYS: many LANGUAGE: Fortran 77,C COMPUTERS: many FORMAT: DOS |
The CEN Service de Physique Theorique, Saclay, France, through the OECD NEA Data Bank, Issy-les-Moulineaux, France, contributed a newly frozen version of this code system to solve the coupled differential equations arising in nuclear model calculations. ECIS-95 includes a few minor corrections and a revision of the statistical model which was used in ECIS-94. |
| ECIS-95 runs on many types of Unix workstations and on personal computers under Windows 95, Windows/NT and Linux. A Fortran 77 compiler is required on all systems. Some C routines are used for Unix installation. The package is transmitted on two DS/HD 3.5-in. (1.44 MB) diskettes in self-extracting compressed DOS files. Reference: CEA-N-2722 (September 1994). Fortran 77 and C; Workstations and Personal Computers (P00227/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.
The 1998 ANS Radiation Protection and Shielding Division Topical Conference,
"Technologies for the New Century" will be held in Nashville, Tennessee, April
19-23, 1998. The General Chairman is Robert W. Roussin (rwr@ornl.gov) and the
Technical Chairman is D. T. Ingersoll (dti@ornl.gov). Information about the
conference can be found at http://www-rsicc.ornl.gov/RPS98/rps98.htm. The
program and registration forms are included at the back of this issue of the newsletter.
DORT and TORT Workshop
A two-day workshop on ORNL's neutral particle transport codes, DORT (2D) and TORT (3D), will be conducted April 24-25, 1998, in Nashville immediately following the 1998 RP&S Topical Meeting. The focus of the workshop will be on using the codes, especially the TORT code. Detailed descriptions will be given on all input parameters and output files, and numerous examples will be offered.
In addition, the novice will be introduced briefly to neutron transport methods, especially those based on the discrete ordinates approximation. Also, an overview will be given of the Discrete Ordinates of Oak Ridge System (DOORS), within which DORT and TORT are bundled. Other DOORS codes which perform auxiliary functions will be discussed with particular emphasis on how they can be utilized in complex analyses.
In order to open DOORS (so to speak!) to more advanced usage of these codes, world-recognized experts will be invited to share their expertise and cite examples of how they employ DOORS codes to solve their problems. The last half-day of the workshop will be a hands-on computer lab where participants will get the opportunity to construct an input file, run the codes, and examine the output to verify proper execution under the supervision of experts. Complete details about the workshop program may be found on the web at http://www-rsicc.ornl.gov/RPS98/workshop.html.
Yousry Azmy
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, USA 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.
Papers are solicited in the following areas: applications, design, R&D needs, analytical methods, tools and databases, economics, safety and licensing. The Call For Papers with all relevant information and points of contact is located at http://www.engr.utk.edu/org/ans/AccApp98.
Your attention is directed to the following events of interest.
February 1998
Health Physics Society Midyear Topical Meeting, Feb. 8-11, 1998, Mobile, Alabama. Contact: Health Physics Society, Suite 402, 1313 Dolley Madison Blvd., McLean, VA 22101-3926 (phone 703-790-1745; fax 703-790-2672; email: hpsburkmgt@aol.com).
Radiation Safety Officer, Feb. 9-13, 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).
Medical Dosimetry Review, Feb. 23-27, 1998, a continuing education course offered by the University of Texas at San Antonio. Contact: The University of Texas Health Science Center at San Antonio, Continuing Medical Education, 7703 Floyd Curl Dr., San Antonio, TX 78284-7980 (phone 210-567-4491; fax 210-567-6964).
March 1998
Introduction to Radiation, March 2-6, 1998, a continuing education course offered by the University of Texas Health Science Center at San Antonio. Contact: University of Texas Health Science Center at San Antonio, Continuing Medical Education, 7703 Floyd Curl Drive, San Antonio, TX 78284-7980 (phone 210-567-4491; fax 210-567-6964).
April 1998
34th Annual Meeting of the National Council on Radiation Protection and Measurements, Apr. 1-2, 1998, Arlington, VA. Contact: National Council on Radiation Protection and Measurements, Suite 800, 7910 Woodmont Ave., Bethesda, MD 20814-3095 (phone 301-657-2652).
Technologies for the New Century, 1998 ANS Radiation Protection and Shielding Division Topical Conference, Apr. 19-23, 1998, Nashville, Tennessee. Contact: Dan T. Ingersoll, Oak Ridge National Laboratory, P.O. Box 2008, Oak Ridge, TN 37831-6363 (fax 423-574-9619).
May 1998
Radiation Oncology Resident's Review in Radiation Oncology Physics and Radiation Biology, May 11-15, 1998, a continuing education course offered by the University of Texas at San Antonio. Contact: The University of Texas Health Science Center at San Antonio, Continuing Medical Education, 7703 Floyd Curl Dr., San Antonio, TX 78284-7980 (phone 210-567-4491; fax 210-567-6964).
Physicist's Review in Radiation Oncology Physics, May 11-15, 1998, a continuing education course offered by the University of Texas at San Antonio. Contact: The University of Texas Health Science Center at San Antonio, Continuing Medical Education, 7703 Floyd Curl Dr., San Antonio, TX 78284-7980 (phone 210-567-4491; fax 210-567-6964).
Computational Methods in Reactor Analysis and Shielding, May 18-22, 1998, Knoxville, Tennessee, a short course offered by the University of Tennessee-Knoxville. Contact: Lydia Salmon, Dept. of Nuclear Engineering, University of Tennessee, Knoxville, TN 37996 (phone 423-974-2525; email lsalmon@utk.edu).
Nuclear Criticality Safety, May 18-22, 1998, Knoxville, Tennessee, a short course offered by the University of Tennessee-Knoxville. Contact: Lydia Salmon, Dept. of Nuclear Engineering, University of Tennessee, Knoxville, TN 37996 (phone 423-974-2525; email lsalmon@utk.edu).
Monte Carlo Analysis, May 18-22, 1998, Knoxville, Tennessee, a short course offered by the University of Tennessee-Knoxville. Contact: Lydia Salmon, Dept. of Nuclear Engineering, University of Tennessee, Knoxville, TN 37996 (phone 423-974-2525; email lsalmon@utk.edu).
Radiation Safety Officer's Course, May 18-22, 1998, a continuing education course offered by the University of Texas at San Antonio. Contact: The University of Texas Health Science Center at San Antonio, Continuing Medical Education, 7703 Floyd Curl Dr., San Antonio, TX 78284-7980 (phone 210-567-4491; fax 210-567-6964).
June 1998
Radiation Safety Officer, June 8-12, 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).
3rd International Meeting of Physicists in the Inca Region, June 15-20, 1998, Cusco, Peru. Contact: Jon Broadway, Internatl. Corps on Environment (ICE), Auburn University, 75 Technacenter Drive, Montgomery, AL 36117-6035 (phone: 334-242-2777; fax: 334-242-2755; email: broadway@strudel.aum.edu).
July 1998
Health Physics Society Annual Meeting, July 12-16, 1998, Minneapolis, Minnesota. Contact: Health Physics Society, Suite 402, 1313 Dolley Madison Blvd., McLean, VA 22101-3926 (phone 703-790-1745; fax 703-790-2672; email: hpsburkmgt@aol.com).
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), or http://www.engr.utk.edu/org/ans/AccApp98
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).
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).
DECEMBER 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/rsic.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.
Nucl. Technol., 120, 179-187 . . . Monte Carlo Simulation of the Triga Mark II Benchmark Experiment. . . . Jeraj, R.; Glumac, B.; Maucec, M. . . . December 1997 . . . Jozef Stefan Institute, Ljubljana, Slovenia.
Nucl. Technol., 120, 224-231 . . . Isotropic Analog - A Method for Penetration Dose Rate Analysis. . . . Bhatnagar, S.K. . . . December 1997 . . . U.S. Department of Energy, Germantown, MD.
Nucl. Technol., 120, 254-260 . . . A Multisystem Modeling Approach for Uranium-Series Dating. . . . . . . December 1997 . . . VTT Energy, Finland; University of Helsinki, Finland.
Health Phys., 74, 22-29 . . . Accounting for Errors in Dose Estimates Used in Studies of Workers Exposed to External Radiation. . . . Gilbert, E.S. . . . January 1998 . . . National Cancer Institute, Rockville, MD.
Health Phys., 74, 30-37 . . . Monte Carlo Simulation of in vivo Measurements of 90Sr + 90Y Bremsstrahlung. . . . Uehara, S.; Endo, S.; Takada, J.; Hoshi, M. . . . January 1998 . . . Kyushu University, Fukuoka, Japan; Hiroshima University, Hiroshima, Japan.
Health Phys., 74, 38-47 . . . Neutron Fluence and Energy Spectra Around the Varian Clinac 2100C/2300C Medical Accelerator. . . . Kase, K.R.; Mao, X.S.; Nelson, W.R.; Liu, J.C.; Kleck, J.H.; Elsalim, M. . . . January 1998 . . . Stanford Linear Accelerator Center, Stanford, CA; Varian Corp., Palo Alto, CA; Science Applications International Corp., Santa Clara, CA.
Health Phys., 74, 78-85 . . . Modeling the Migration of Fallout Radionuclides in Soil Using a Transfer Function Model. . . . Kirchner, G. . . . January 1998 . . . University of Bremen, Bremen, Germany.
Health Phys., 74, 96-98 . . . Evidence for Photoneutron Production in the Lead Shielding of a Dedicated Intra-Operative Electron Only Facility. . . . Biggs, P.J. . . . January 1998 . . . Harvard Medical School, Boston, MA.
Health Phys., 73, 894-898 . . . Assessment of Dose Equivalent Due to Neutrinos. . . . Cossairt, J.D.; Grossman, N.L.; Marshall, E.T. . . . December 1997 . . . Fermi National Accelerator Laboratory, Batavia, IL.
Health Phys., 73, 912-918 . . . Leaching of Accelerator-Produced Radionuclides. . . . Baker, S.I.; Bull, J.S.; Goss, D.L. . . . December 1997 . . . Superconducting Super Collider Laboratory, Waxahachie, TX; Nebraska Wesleyan University, Lincoln, NE.
Health Phys., 73, 919-927 . . . An Analytically Based Model for the Simultaneous Leaching-Chain Decay of Radionuclides from Contaminated Ground Surface Soil Layers. . . . Jarzemba, M.S.; Manteufel, R.D. . . . December 1997 . . . Southwest Research Institute-Center for Nuclear Waste Regulatory Analyses, San Antonio, TX; University of Texas at San Antonio, San Antonio, TX.
Health Phys., 73, 932-943 . . . A Practical Neutron Shielding Code Based on Data Base Interpolation. . . . Shiang-Huei Jiang; Rong-Jiun Sheu . . . December 1997 . . . National Tsing Hua University, Hsinchu, Taiwan, R.O.C.
Health Phys., 73, 953-957 . . . A General Algorithm for Radioactive Decay with Branching and Loss from a Medium. . . . Strenge, D.L. . . . December 1997 . . . Pacific Northwest National Laboratory, Richland, WA.
KINR-94-17 . . . Evaluated Nuclear Data File Libraries Use in Nuclear-Physical Calculations. . . . Gritzay, O.O.; Kalatch, N.I.; Kaltchenko, O.I.; et al. . . . 1994.
P3-97-20 . . . Monte Carlo Calculation of the Slow Neutron Background in the Neutron-Neutron Scattering Experiment at the Pulse Reactor BIGR. . . . Budnik, A.D.; et al. . . . 1997.
P9-96-170 . . . The Narrow 70-100 MeV Proton Beams for Eye Tumours Irradiation. . . . Budjashov, Yu.G.; et al. . . . 1996.
E4-96-43 . . . Semiempirical Systematics for Different Hadron-Nucleus Interaction Cross Sections. . . . Gabriel, T.A.; Mashnik, S.G. . . . 1996 . . . Oak Ridge National Laboratory, Oak Ridge, TN.
HDYUEC, 15, 118-122 . . . The Low Level Radioactivity Measurement and Radiation Shield. . . . Chen Duanbao . . . February 1995 . . . Institute of High Energy Physics, Beijing, China. . . in Chinese.
HDYUEC, 16, 18-22 . . . Measurement and Analysis of Complicated Gamma Ray Energy Spectrum for Radiation Field. . . . Wang Yuexing; Ma Xiaolin; Yun Changquan . . . January 1996 . . . Naval Medical Research Institute, Shanghai, China. . . . in Chinese.
HDYUEC, 16, 28-32 . . . The Design of Gamma Thickness Gauge. . . . Liu Yisi; Mo Dawei; Zhou Liye . . . January 1996 . . . Institute of Nuclear Energy Technology of Tsinghua University, Beijing, China. . . . In Chinese.
HDYUEC, 16, 279-282 . . . Phantom Experiment on the Quick Estimation of Personal Dose in External Irradiation. . . . Mao Xiaolin; Wang Yuexing; Lu Yongjie; Yun Changquan . . . April 1996 . . . Naval Medical Research Institute, Shanghai, China. . . In Chinese.
HDYUEC, 16, 260-263 . . . Development and Improvement for MCNP-3B Interactive Plotter. . . . Gao Yanfeng . . . April 1996 . . . Computer Application Institute of Nuclear Industry, Beijing, China. . . .In Chinese.
HDYUEC, 16, 264-266 . . . Automatic Determination of the Important Paths of Particles in Materials of Shield. . . . Zhao Yuwu; Du Fengying; Ma Chi . . . April 1996 . . . Institute of Nuclear Physics and Chemistry, China Academy of Engineering Physics, Chengdu, China. . . . In Chinese.
HDYUEC, 16, 340-344 . . . Monte Carlo Simulation for the Array Detector of Industrial Computed Tomography. . . . Wu Shuxin; Qian Yonggeng; Wang Jingjin . . . May 1996 . . . Tsinghua University, Beijing, China. . . .In Chinese.
Radiat. Prot., 5, 357-364 . . . Influence of Dose and Dose-Rate on Stochastic Effects of Radiation Dose and Dose-Rate Effectiveness Factor. . . . Zhou Yongzeng . . . May 1995 . . . China Institute for Radiation Protection, Taiyuan, China. . . . In Chinese.
Radiat. Prot., 6, 448-451 . . . Source Term Calculation of Gaseous Effluents from PWR Under Normal Operation Conditions. . . . Zhang Shaodong; Zhang Yongxing . . . June 1995 . . . China Institute of Atomic Energy, Beijing, China. . . . In Chinese.
Radiat. Prot., 1, 13-16 . . . Biokinetic and Dosimetric Models of the Task Group on Dose Calculations. . . . Eckerman, K.F. . . . January 1997 . . . Oak Ridge National Laboratory, Oak Ridge, TN. . . .In Chinese.
Radiat. Prot., 3, 161-166 . . . International Recommendations for Managing Environmental Risk from Nuclear Energy Production. . . . ; Clarke, R.H. . . . May 1997 . . .
Radiat. Prot., 3, 167-187 . . . Airborne Monitoring of Radioactivity Level in the Regions Surrounding Qinshan Nuclear Power Plant and Shanghai City. . . . Gu Renkang; Hou Zhenrong; Shen Ensheng; Hu Mingkao . . . May 1997 . . . Airborne Survey and Remote Sensing Center of Nuclear Industry, Shijaizhuang, China. . . .In Chinese.
Radiat. Prot., 3, 192-199 . . . Experimental Studies on Effects of Buildings of Qinshan Nuclear Power Plant on Diffusion of Airborne Radioactive Emissions. . . . Yao Rentai; Zhang Maoshuan; Tao Shuwang; Liu Jinfeng . . . May 1997 . . . China Institute for Radiation Protection, Taiyuan, China. . . . . . . In Chinese.
Radiat. Prot., 3, 212-220 . . . Discussion on the Methods of the Assessment of Radiological Environmental Impact - the Basis of Source-Related Dose Commitment Model for the Assessment of Publi . . . Liu Senlin, Zhang Yongxing . . . May 1997 . . . China Institute of Atomic Energy, Beijing, China. . . .In Chinese.
Radiat. Prot., 3, 225-231 . . . A Comparative Study on Dosimetric Properties of LiF Thermoluminescence Detectors Produced by China. . . . Zheng Junzheng . . . May 1997 . . . Laboratory of Industrial Hygiene, Beijing, China. . . .In Chinese.
Radiat. Prot., 4, 241-248 . . . An Automatic Rotating Calibration System for Personal Dosemeters. . . . Li Jingyun; Guo Wen; Hou Jinbing . . . July 1997 . . . China Institute of Atomic Energy, Beijing, China. . . .In Chinese.
Radiat. Prot., 4, 249-258 . . . Estimation of Annual Atmosphere Diffusion Factor for Qinshan NPP (Phase III) Using Meteorological Correlation Experiment. . . . Hu Erbang, Gao Zhanrong, Zhang Maoshuan . . . July 1997 . . . China Institute for Radiation Protection, Taiyuan, China. . . In Chinese.
Radiat. Prot., 4, 260-268 . . . Intercomparision of Calculation Program for the Radiological Consequences of Normal Airborne Effluent from a Nuclear Facilities. . . . Fang Dong; Zhang Hongyou . . . July 1997 . . . In Chinese.
Radiat. Prot., 4, 269-276 . . . The Calculation Method of Accidental Release of Radioactivity for Nuclear District Heating Reactor and Their Application. . . . Liu Yuanzhong; Cao Jianzhu . . . July 1997 . . . Tsinghua University, Beijing, China. . . .In Chinese.
Radiat. Prot., 4, 281-286 . . . Shielding Design for Testing Room of Large Container Scanner. . . . Liu Yish, Miao Qitian; Zhou Liye . . . July 1997 . . . Tsinghua University, Beijing, China. . . .In Chinese.
Radiat. Prot., 4, 285-292 . . . A Microcomputer Program for Data Management and Data Assessment of Internal Individual Dose. . . . Song Yiyang; He Lihua . . . July 1997 . . . China Institute of Atomic Energy, Beijing, China. . . .In Chinese.
Radiat. Prot., 4, 293-299 . . . PRESDSA: A Computer Program for Shallow Land Disposal of LILW. . . . Zhou Honggui; Wang Zhiming; Wang Jingsheng; Gu Zhijie . . . July 1997 . . . China Institute for Radiation Protection, Taiyuan, China. . . .In Chinese.
Chin. J. Nucl. Sci. Eng., 15, 367-376 . . . Optimization Calculation of the Multiplet Shielding of the Storage Well for A 3x10(5) Curie 60Co Source. . . . Li Xinghong; Chen Junzhen; Sun Jianyong . . . December 1995 . . . Peking University, China. . . .In Chinese.
Chin. J. Nucl. Sci. Eng., 16, 269-283 . . . Disposal of HLW by P-T and the Emerging Advanced Nuclear Systems Without Long-Lived HLW. . . . Li Shounan . . . September 1996 . . . China Institute of Atomic Energy, Beijing, China. . . .In Chinese.
J. Radiat. Res. Radiat. Proc., 14, . . . Dose Rate Measurement Before Commissioning of 60Co Gamma-Irradiation Equipment. . . . Peng Tao; Shong Juzhong; Xie Huaijiang; Kou Qinhe . . . February 1996 . . . Institute of Military Medicine, Shengyang, China. . . .In Chinese.
Proceedings, Vols. 1, 2, 3 . . . 1994 Topical Meeting on Advances in Reactor Physics. . . . April 1994.
NEA/NSC/DOC(94) 11 . . . Overview of Physics Aspects of Different Transmutation Concepts. . . . .1994.
NEA/SEN/NSC/WPPR(96)5; JEF/DOC-658 . . . Evaluation of 242Pu Data for the Incident Neutron Energy Range 0.1 - 6 MeV. . . . Vladuca, G.; Sin, M.; Tudora, A. . . . November 1996 . . . Bucharest University, Bucharest, Romania.
ORNL/RSIC-57 . . . Abstract of Computer Programs and Data Libraries Pertaining to Photon Production Data. . . . White, J.E.; Manneschmidt, J.B.; Finch, S.Y.; Dickens, J.K. . . . December 1997 . . . Oak Ridge National Laboratory, Oak Ridge, TN.
ORNL/TM-13516 . . . R-Matrix Analysis of 235U Neutron Transmission and Cross Sections in the Energy Range 0 to 2.25 keV. . . . Leal, L.C.; Derrien, H.; Larson, N.M.; Wright, R.Q. . . . November 1997 . . . Oak Ridge National Laboratory, Oak Ridge, TN.
E11-97-182 BETA
Program BETA for Simulation of Particle Decays and Reactions.. . .Takhtamyshev, G.G.; Merkulova, T.A.. . .1997. . .No corporate authors..
INDC(CCP)-406 LIPAR-5; MCU
The LIPAR-5 Resonance Parameter Library.. . .Abagyan, L.P.. . .08/97. . .Kurchatov Institute Russian Science Center..
HDYUEC, 4, 260-263; CNII-2016/TL MCNP-3B
Development and Improvement for MCNP-3B Interactive Plotter.. . .Gao Yanfeng. . .07/96. . .Computer Application Inst. of Nuclear Industry, Beijing, China..
Nucl. Sci. Eng., 124, 145-159 PARFLOW
A Parallel Multigrid Preconditioned Conjugate Gradient Algorithm for Groundwater Flow Simulations.. . .Ashby, S.F.; Falgout, R.D.. . .1996. . .Lawrence Livermore National Lab., Livermore, CA..
Radiat. Prot., 3, 293-299 PRESDSA
PRESDSA: A Computer Program for Shallow Land Disposal of LILW.. . .Zhou Honggui; Wang Zhimiing; Wang Jingsheng; Gu Zhijie. . .07/97. . .China Institute for Radiation Protection, Taiyuan, China..
Nucl. Sci. Eng., 124, 125-144
SEANAP; MARIA; COBAYA; SIMULA
Numerical Stability of the Six-Equation, Single-Pressure Model with Viscous Terms.. . .Doster, J.M.; Holmes, M.A.. . .1996. . .North Carolina State University, Raleigh, NC.
Nucl. Sci. Eng., 124, 111-124 SIMTRAN
Methods and Performance of the Three-Dimensional Pressurized Water Reactor Core Dynamics SIMTRAN On-Line Code.. . .Aragones, J.M.; Ahnert, C.; Cabellos, O.. . .1996. . .Polytechnic University, Madrid, Spain..
Health Phys., 73, 932-943 WRNS
A Practical Neutron Shielding Core Based on Data Base Interpolation.. . .Shiang-Huei Jiang; Rong-Jiun Sheu. . .1997. . .National Tsing Hua University, Hsinchu, Taiwan, R.O.C..
<INTERNET ADDRESS www.engr.utk.edu/org/ans/AccApp98
