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
BitNet: PDC@ORNLSTC Internet: PDC@ORNL.GOV
371 October 1995
The East Tennessee area code is changing from 615 to 423. Some of our readers have noted the change already in the newsletter masthead. From September 11, 1995, to February 26, 1996, both area codes (615 and 423) can be used. Beginning February 26, 1996, all calls to East Tennessee must use the 423 area code; calls made to 615 will then be routed to Middle Tennessee exchanges.
This six month period should provide enough time for our customers to make all necessary changes. Remember, this will require changing all autodial setups (modems, faxes, automatic dialers, speed calling, pagers, and cellular phones) for numbers dialed within this region. Some of our clients have experienced problems with using the 423 area code from their calling exchange. You may use 615 until February 26. In the meantime you need to be aware that your local phone company must be notified of the problem you are having so it can be fixed before February 26.
Two changes were made to the computer code collection during the reporting period. One new code package was packaged and added to the collection and an existing code package was replaced with a newly frozen version.
OP SYS: UNIX, DOS Language: Fortran 77, C Computers: PC, Workstations Format: DOS, tar
Oak Ridge National Laboratory, Oak Ridge, Tennessee, contributed a newly frozen version of this modular code system for performing standardized computer analyses for licensing evaluation for UNIX workstations and personal computers. This release obsoletes both CCC-545/SCALE4.2 and CCC-619/SCALE-PC packages. New features in SCALE4.3 include new 238- and 44-group ENDF/B-V derived libraries, KENO-VI, CSAS6, QAD-CGGP (from CCC-493), QADS, new capability for criticality search on material concentrations, enhanced graphical capabilities, new cross-section processing features in NITAWL-II, improved portability, and minor modifications. In its present form, the system has the capability to perform criticality, shielding, and heat transfer analyses using well-established functional modules tailored to the SCALE system. Spent fuel characteristics for these analyses can be obtained from a module that performs a depletion calculation.
The CSAS control module contains criticality safety analysis sequences that calculate the neutron multiplication factor for one-dimensional (XSDRNPM-S) and multidimensional (KENO V.a) system models. The CSAS6 control module contains criticality safety analysis sequences using the KENO-VI module for multidimensional models with more complex geometries. Sequences that provide problem-dependent cross sections for use in stand-alone codes are also available in the CSAS module. Five shielding analysis sequences are provided. SAS1 analyzes general one-dimensional shielding problems via XSDRNPM-S. SAS3 provides a general procedure for cross-section preparation followed by a shielding analysis using the MORSE-SGC Monte Carlo code. The SAS4 module has been tailored to perform a Monte Carlo shielding analysis for a cask-type geometry. An automated scheme is incorporated in SAS4 to generate Monte Carlo biasing parameters that enable SAS4 to calculate accurate doses with reasonable efficiency. The SAS2 module performs both a depletion (to generate source terms) and a one-dimensional radial shielding analysis of a cask-type geometry. The QADS module analyzes three-dimensional gamma-ray shielding problems via the point kernel code, QAD-CGGP. In the workstation version, HTAS1 uses a single set of input to automatically manipulate a general-purpose conduction module (HEATING7.2) to perform a two-dimensional thermal analysis for a specific class of spent fuel casks during normal, fire, and post-fire conditions.
The only functional differences between the workstation and PC packages are
1) thermal codes (HTAS1, HEATING 7, OCULAR) are included in the UNIX package but are NOT included in the PC package.
2) ORIGEN-ARP is distributed only with the PC version. It is a successor to the ORIGNATE input processor for ORIGEN-S and ARP (Automated Rapid Processing) which automatically interpolates cross sections on enrichment and burnup using a set of libraries for four LWR fuel assembly designs. The interpolated cross sections are passed to ORIGEN-S. ORIGNATE is only distributed with the workstation version.
The UNIX version of SCALE-4.3 runs on IBM RS/6000, DEC, SUN, HP, and SGI workstations. Makefiles are included to facilitate installation. SCALE-PC runs on 386, 486, and Pentium personal computers with a math coprocessor and 8 MB of extended memory. A 486 or Pentium PC is recommended. Nominal hard disk requirements vary from 60 MB for a minimum installation to install the executables and data files (except the 238-group library) to 350 MB for a complete installation, including space for compiling, linking, and running sample problems. Executables included in the PC package were created using the Lahey F77L-EM/32 Fortran compiler version 5.20 and the PharLap DOS Extender and virtual memory manager under DOS 6.22.
Workstation version: includes source codes, binary data libraries, makefiles, scripts, and sample problem input and output, for UNIX is transmitted in a GNU compressed tar file on either cartridge tape or CD-ROM, plus OFFSCALE, ORIGNATE, and README in DOS format on diskette.
PC Version: requires one CD-ROM or QIC-80 compatible tape which contains source codes, executables, binary data libraries, and sample problem input and output; written in DOS format compressed with programs of Pkware, Inc.
References: NUREG/CR-0200, Rev. 5 (ORNL/NUREG/CSD-2/R5), Vols. I, II, and III (Draft September 1995), NUREG/CR-5468(ORNL/CSD/TM-270)(May 1990), NE007 (July 1977), NUREG/CR-6182, Vol. 1 (ORNL/TM-12663/V1) (November 1994), NUREG/CR-6182, Vol. 2 (ORNL/TM-12663/V2) (November 1994). FORTRAN 77 and C; IBM RS/6000 DEC, and SUN workstations (C00545/MNYWS/00) and PC486 (C00545/PC486/00).
OP SYS: DOS Language: Pascal Computers: PC Format: DOS
Lawrence Livermore National Laboratory, Livermore, California, through the Energy Science Technology Software Center, Oak Ridge, Tennessee, contributed the HOTSPOT7 codes which are a first-order approximation of the radiation effects associated with the atmospheric release of radioactive materials for short-term (less than 24 hours) release durations. These codes produce a consistent output for the same input assumptions and minimize the probability of errors associated with reading a graph incorrectly or scaling a universal nomogram during an emergency. Four general programs - Plume, Explosion, Fire, and Resuspension - calculate a downwind assessment following the release of radioactive material resulting from a continuous or puff release, explosive release, fuel fire, or an area contamination event. Other programs deal with the release of plutonium, uranium, and tritium to expedite an initial assessment of accidents involving nuclear weapons. Additional programs estimate the dose commitment from the inhalation of any one of the radionuclides listed in the database of radionuclides; calibrate a radiation survey instrument for ground-survey measurements; and screen plutonium uptake in the lung. HOTSPOT uses the Gaussian plume model, and the dosimetric methods of ICRP Publication 30. Version 8 of this system is expected to be released in the near future and will replace Version 7 in the RSIC collection. The system runs on IBM compatible personal computers with a minimum of 512 kbytes of RAM. It can be run as a DOS application within Windows 3.0 or 3.1. It compiles with Borland Turbo Pascal 7.0. Executables are included in the package. Reference: UCRL-MA-106315. IBM PC; Pascal (C00644/IBMPC/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.
Robert G. Thomas received the Health Physics Society's Distinguished Scientific Achieve ment Award. For most of his career he has studied the behavior of radionuclides in humans. As head of the Department of Radiobiology of the Lovelace Foundation for Medical Education and Research for the Atomic Energy Commission, he helped develop the program for studying the effects of inhaled fission products in experimental animals. Though retired from Argonne National Laboratory's Environmental Research Division since 1993, he is still active on a committee of the National Academy of Sciences to oversee the Centers for Disease Control and Prevention in their effort to direct radiation dose reconstruction studies at formerly used Atomic Energy Commission nuclear sites. He also led the U.S. State Department team to Romania to measure the fallout from the accident at the Chernobyl nuclear plant in 1986.
Nicholas Tsoulfanidis received the 1995 Glenn Murphy Award from the Nuclear Engineer ing Division of the American Society for Engineering Education "in recognition of notable professional contributions to the teaching aspects of nuclear engineering." He is a professor of nuclear engineering at the University of Missouri-Rolla and assistant dean of UMR's School of Mines and Metallurgy.
James R. Lilienthal died September 8, 1995. He retired from Los Alamos National Laboratory in 1977. While at Los Alamos he was instrumental in designing the plutonium and uranium facilities for the Chemistry and Metallurgy Division and in the design and construction of the first hot cell lab at what was then Los Alamos Scientific Laboratory. He was also involved in "Mike," the first thermonuclear weapons test, for which he designed part of the instrumentation during "Operation Ivy" on Eniwetok Island in the South Pacific. Before joining Los Alamos, he was chief engineer at Sperry Gyroscope Company. He earned a bachelor's degree in naval architecture and marine engineering from Webb Institute of Naval Architecture and Marine Engineering in 1938.
Since joining the American Nuclear Society in 1958 he had served in various positions, including chair of the Remote Systems Technology Division, member of the Program Committee, Publications Committee, Board of Directors, Executive Committee, Finance Committee, Nominating Committee, and the 1968 International Meeting Steering Committee. He served as ANS President in 1972-73.
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 Fourth International Symposium on Fusion Nuclear Technology will be held April 6-11, 1997, in Meiji Kinenkan, Tokyo, Japan. The symposium focuses on all technical issues related to fusion nuclear technology and will provide an excellent opportunity to report on recent technical progress, discuss key issues and identify means to resolve these issues. The conference will cover both near-term fusion devices and long-term reactor technologies. For those interested in submitting a paper related to technology, experiments, facilities, modeling, analysis and design a list of topics for the conference follows.
|Burning plasma control & operation|
|First wall technology and high heat flux components|
|Fuel cycle and tritium processing|
|Material engineering for FNT|
|Nuclear systems design|
|Safety issues and waste management|
|Models and experiments for FNT|
|Repair and maintenance|
Your attention is directed to the following events of interest.
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.
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).
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.
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).
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 firstname.lastname@example.org).
Radiation Health and Risk, Mar. 11-15, 1996, a course offered by Consultec Scientific at Knoxville, Tennessee. Contact: Consultec Scientific, Inc., Suite 110, 725 Pellissippi Parkway, Knoxville, TN 37932-3300.
Internal Dose Assessment, Mar. 11-15, 1996, a course offered by Consultec Scientific at Knoxville, Tennessee. Contact: Consultec Scientific, Inc., Suite 110, 725 Pellissippi Parkway, Knoxville, TN 37932-3300.
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 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. 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 firstname.lastname@example.org).
Radiopharmaceutical Internal Dosimetry, Apr. 22-26, 1996, a course offered by Oak Ridge Associated Universities at Oak Ridge, Tennessee. Contact: Registrar, RIDIC, Oak Ridge Associated Universities, P.O. Box 117, Oak Ridge, TN 37831-0117 (phone 423-576-3478).
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).
Radiation Transport Using EGS4, June 10-13, 1996, a course offered by Montpellier II University in Montpellier, France. Contact: Jean Barthe, CEA/DTA/DAMRI, BP No 52, 91193 Gif-sur-Yvette, Cedex (phone 33-1-6908-9730; fax 33-1-6908-9533; email email@example.com).
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 firstname.lastname@example.org).
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 email@example.com).
Occupational Internal Dosimetry, June 17-21, 1996, a course offered by Oak Ridge Associated Universities at Oak Ridge, Tennessee. Contact: Registrar, RIDIC, Oak Ridge Associated Universities, P.O. Box 117, Oak Ridge, TN 37831-0117 (phone 423-576-3478).
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 firstname.lastname@example.org).
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).
7th International Symposium on Neutron Capture Therapy for Cancer, Sept. 4-7, 1996, Zurich, Switzerland. Contact: 7th International Symposium on Neutron Capture Therapy for Cancer, Inst. for Medical Radiobiology, August Forel-Strasse 7, CH-8029, Zurich, Switzerland (phone 41-1-3856511; fax 41-1-3856204; email email@example.com).
12th Symposium on Microdosimetry - Interdisciplinary Meeting on Radiation Quality, Molecular Mechanisms, Cellular Effects and Health Consequences of Low Level Ionising Radiation, Sept. 29-Oct. 4, 1996, Oxford, United Kingdom. Contact: European Commission, DG XII/F/6, Dr. H. G. Menzel, rue de la Loi, 200, B-1049, Brussels, Belgium (fax 32-2-296-6256; email H.Menzel@mhsg.cec.be).
9th International Symposium on Capture Gamma-Ray Spectroscopy and Related Topics, Oct. 8-12, 1996, Budapest, Hungary. Contact: Inst. of Isotopes. Nuclear Physics, G. Molnar, P.O. Box 77, H-1525, Budapest, Hungary (fax 36-1-275-4349; email CGS9@ALPHA0.IKI.KFKI.HU).
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).
Meeting of the American Association of Physicists in Medicine and the Radiologists Society of North America, Dec. 1-6, 1996, Chicago, Illinois. Contact: AAPM, One Physics Ellipse, College Park, MD 20749- 3846 (fax 301-209-0862).
Annual Meeting of the American Association of Physicists in Medicine, July 27-31, 1997, Milwaukee, Wisconsin. Contact: American Association of Physicists in Medicine, One Physics Ellipse, College Park, MD 20749-3846 (fax 301-209-0862).
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.
1-94 . . . Spallation Neutron Source with Hard Energy Spectrum for Detector Component Testing at the Dubna Synchrophasotron. . . . Kovalenko, A.D.; Panebratsev, Yu.A.; Yurevich, V.I. . . . 1994 . . . Joint Institute for Nuclear Research, Dubna, Russia.
Book . . . Proceedings of the 1994 Topical Meeting on Advances in Reactor Physics. . . . 1994 . . . American Nuclear Society (ANS), April 11-15, 1994, Knoxville, TN.
Book . . . MOCAL, A Monte Carlo Albedo Code. . . . Morford, R.J.; Carter, L.L.; Siciliano, E.R. . . . 1992 . . . Westinghouse Hanford Co., Richland, WA . . . New Horizons in Radiation Protection and Shielding Topical Meeting Proceedings, April 26-May 1, 1992, Pasco, WA.
Book . . . BREMCALC - A Computer Program for Calculating Electron and Positron Bremsstrahlung. . . . Rittmann, P.D. . . . 1992 . . . Westinghouse Hanford Co., Richland, WA . . . New Horizons in Radiation Protection and Shielding Topical Meeting Proceedings, April 26-May 1, 1992, Pasco, WA.
Book . . . Radiation Protection Factor Calculations Using the VPF Computer Code. . . . Lemay, F.J.; Jamieson, T.J.; Cousins, T. . . . 1992 . . . Science Applications International Corp., Ottawa, Ontario, Canada; Defense Research Establishment Ottawa, Ottawa, Ontario, Canada . . . New Horizons in Radiation Protection and Shielding Topical Meeting Proceedings, April 26-May 1, 1992, Pasco, WA.
Book . . . Invent Your Own Reactor. . . . Mills, C.B. . . . 1992 . . . Self Published.
Book, Volume 1, 2 . . . Proceedings: 8th International Conference on Radiation Shielding. . . . 1994 . . . ANS, April 24-28, 1994, Arlington, TX.
Book, Volume 1, 2 . . . Proceedings of the 1992 Topical Meeting on Advances in Reactor Physics. . . . 1992 . . . ANS, March 8-11, 1992, Charleston, SC.
Book, Volume 1, 2, 154-161 . . . Incorporating the Livermore Photon Interaction Data Base into the Electron- Photon Monte Carlo Transport Code EGS4. . . . Bielajew, A.F.; Cullen, D.E. . . . 1995 . . . National Research Council of Canada, Ottawa, Canada; Lawrence Livermore National Laboratory, Livermore, CA . . . Proceedings International Conference on Mathematics and Computations, Reactor Physics, and Environmental Analyses, April 30-May 4, 1995, Portland, OR.
Book, Volume 1, 2, 857-865 . . . PEREGRINE: An All-Particle Monte Carlo Code for Radiation Therapy. . . . Siantar, C.L.H.; Chandler, W.P.; Rathkopf, J.A.; Svatos, M.M.; White, R.M. . . . 1995 . . . Lawrence Livermore National Laboratory, Livermore, CA . . . Proceedings International Conference on Mathematics and Computations, Reactor Physics, and Environmental Analyses, April 30-May 4, 1995, Portland, OR.
Book, Volume 1, 2, 866-875 . . . Electron Transport in Radiotherapy Using Local-to-Global Monte Carlo. . . . Svatos, M.M.; Ballinger, C.T.; Neuenschwander, H.; Mackie, T.R.; Chandler, W.P., Siantar, C.L.H.; Rathkopf, J.A.; Reckwerdt, P.J. . . . 1995 . . . Lawrence Livermore National Laboratory, Livermore, CA; University of Wisconsin-Madison, Madison, WI; Albany Medical Center, Albany, NY; University of Bern, Bern, Switzerland . . . Proceedings International Conference on Mathematics and Computations, Reactor Physics, and Environmental Analyses, April 30-May 4, 1995, Portland, OR.
Book, Volume 1-5 . . . Advances in Mathematics, Computations, and Reactor Physics, Volume 1-5. . . . 1991 . . . ANS . . . International Topical Meeting, April 28-May 2, 1991, Pittsburgh, PA.
Book, Volumes 1, 2 . . . Proceedings: International Conference on Nuclear Data for Science and Technology. . . . Dickens, J.K., ed. . . . 1994 . . . Oak Ridge National Laboratory, Oak Ridge, TN . . . May 9-13, 1994, Gatlinburg, TN.
Book, Volumes 1-4, Supplementary . . . International Conference on the Physics of Reactors: Operation, Design and Computation. . . . 1990 . . . ANS Section Francaise de L'Ans (SF/ANS) . . . April 23-27, 1990, Marseille, France.
CNIC-00596; CNDC-0008; INDC(CPR)-025/L . . . Communication of Nuclear Data Progress, No. 6. . . . 1991 . . . China Nuclear Information Center (CNIC), Beijing, China.
CNIC-00645; CNIC-0009; INDC(CPR)-027/L . . . Communication of Nuclear Data Progress, No. 7. . . . 1992 . . . CNIC, Beijing, China.
CNIC-00690; CNDC-0010; INDC(CPR)-028/L . . . Communication of Nuclear Data Progress, No. 6, Supplement. . . . 1992 . . . CNIC, Beijing, China.
CNIC-00706; CNDC-0011; INDC(CPR)-029/L . . . Communication of Nuclear Data Progress, No. 8. . . . 1992 . . . CNIC, Beijing, China.
CNIC-00750; CNDC-0012; INDC(CPR)-030/L . . . Communication of Nuclear Data Progress, No. 9. . . . 1993 . . . CNIC, Beijing, China.
CNIC-00810; CNDC-0013; INDC(CPR)-031/L . . . Communication of Nuclear Data Progress, No. 10. . . . 1993 . . . CNIC, Beijing, China.
CNIC-00858; CNDC-0014; INDC(CPR)-032/L . . . Communication of Nuclear Data Progress, No. 11. . . . 1994 . . . CNIC, Beijing, China.
CNIC-00922; CNDC-0015; INDC(CPR)-033/L . . . Communication of Nuclear Data Progress No. 12. . . . December 1994 . . . CNIC, Beijing, China.
CNIC-00922; CNDC-0015; INDC(CPR)-033/L . . . Communication of Nuclear Data Progress, No. 12. . . . 1994 . . . CNIC, Beijing, China.
Chin. J. Comput. Phys., 8, 30-36 . . . Monte Carlo Calculation of the Energy Spectrum of Gamma Rays Emitted in the Three Photon Annihilation of Positrons and Electrons. . . . Cheng Jinrong; Xu Qiang . . . March 1991 . . . In Chinese.
Chin. J. Comput. Phys., 8, 395-406 . . . Monte-Carlo Studies of Radiation Damage in the First Wall Caused by Fusion Neutron. . . . Gao Xinghua; Huo Yukun; Pan Zhengying; Shao Qiyun; Chen Janxin; Wu Sheming . . . December 1991 . . . In Chinese.
Chin. J. Nucl. Sci. Eng., 11, 318-324 . . . The Irradiation Effects Investigation of First Wall for Fusion Reactors. . . . Feng Kaiming . . . December 1991 . . . Chinese Nuclear Society . . . In Chinese.
Chin. J. Nucl. Sci. Eng., 12, 87-92 . . . Progress of Boron Neutron Capture Therapy for Tumors. . . . Chen Shaoneng . . . March 1992 . . . Chinese Nuclear Society . . . In Chinese.
Chin. J. Nucl. Sci. Eng., 13, 226-231 . . . Neutronics Characteristic Analyses of the Tokamak Breeder Blanket. . . . Jiao Yiming . . . September 1993 . . . Chinese Nuclear Society . . . In Chinese.
Chin. J. Nucl. Sci. Eng., 13, 311-321 . . . Neutron Wall Load Distribution and Neutron Current Distribution in the First Wall of Tokamak. . . . Zhang Wenge; Gao Xinghua . . . December 1993 . . . Chinese Nuclear Society . . . In Chinese.
Chin. J. Nucl. Sci. Eng., 14, 175-178 . . . Advances of Neutron Capture Therapy Department of Nuclear Medicine. . . . Zhen Jun; Wang Fengqin; Zhao Huiyang . . . June 1994 . . . Chinese Nuclear Society . . . In Chinese.
Chin. J. Nucl. Sci. Eng., 14, 248-253 . . . Neutronics Study for A LiPb Self-Cooled Breeder Blanket. . . . You Chenglun . . . September 1994 . . . Chinese Nuclear Society.
Chin. J. Nucl. Sci. Eng., 15, 122-128 . . . Research on Shielding Neutron Efficiency of Some Boron - Bearing Fabric and Transparent Resin Materials. . . . Chen Changmao, Liu Jinhua, Su Jingling, et al. . . . June 1995 . . . Chinese Nuclear Society . . . In Chinese.
DNA-TR-90-186 . . . DNA Nuclear Weapons Effects Code Catalog. . . . ; Ivy, G.M. . . . June 1991 . . . Defense Nuclear Agency, Alexandria, VA.
E3-93-466 . . . Systematical Analysis of the Fast Neutron Induced (n,p) Reaction Cross Sections. . . . Khuukhenkhuu, G., et al. . . . 1993 . . . Joint Institute for Nuclear Research, Dubna, Russia.
ECN-C--94-016 . . . European Fusion File EFF-2.4. Final Report on Basic Data File. . . . ; Kopecky, J.; Gruppelaar, H.; Hogenbirk, A.; Van Der Kamp, H.A.J.; Nierop, D. . . . July 1994 . . . ECN, Petten, the Netherlands.
Fusion Technol., 19, Part 2A, 2B, 583-2020 . . . Proceedings of the Ninth Topical Meeting on the Technology of Fusion Energy. . . . May 1991 . . . October 7-11, 1990, Oak Brook, IL.
INDC(JPN)-173/U; JAERI-CONF 95-008 . . . Proceedings of the 1994 Symposium on Nuclear Data. . . . Kawai, M.; Fukahori, T. . . . March 1995 . . . Japan Atomic Energy Research Institute, Ibaraki-ken, Japan . . . November 17-18, 1994, JAERI, Tokai, Japan.
ISFNT-3 . . . Third International Symposium on Fusion Nuclear Technology. . . . 1994 . . . University of California, Los Angeles, CA . . . June 27-July 1, 1994, Los Angeles, CA.
ISFNT-3; Book, Part A, B, C . . . Proceedings of the Third International Symposium on Fusion Nuclear Technology. . . . ; Conn, R.W.; Abdou, M.A.; Casini, G.; Filatov, O.G.; Komarek, P.; Kulcinski, G.L.; Miyahara, A.; Ohta, M., eds. . . . 1995 . . . Fusion Engineering and Design, June 26-July 1, 1994, Los Angeles, CA.
J. Radiat. Res. Radiat. Processing, 12, 232-238 . . . The Calculation of Mean Energy for Electron Beam in the Energy Range of Radiotherapy in Light Media. . . . Jiang Bin; Juo Zhengming . . . November 1994 . . . In Chinese.
KEK Report 90-25, Volume 1, 2 . . . Proceedings of the Eleventh Meeting of the International Collaboration on Advanced Neutron Sources ICANS-XI. . . . Misawa, M.; Furusaka, M.; Ikeda, H.; Watanabe, N., eds. . . . March 1991 . . . KEK, Tsukuba, October 22-26, 1990..
KfK 5072 . . . Development of Calculational Procedures for the Neutron Physics Design of Advanced Pressurized Water Reactors (APWR) with Tight Triangular Lattices in Hexagonal Fuel Assemblies. . . . Broeders, C.H.M. . . . August 1992 . . . Institut fur Neutroninphysik und Reaktortechnik, Kernforschungszentrum, Karlsruhe, Germany . . . In German.
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