| 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 Phone No. 423-574-6176 FAX 423-574-6182 BitNet: PDC@ORNLSTC Internet: PDC@ORNL.GOV WWW: http://epicws.epm.ornl.gov |
380 July 1996
W. Roger Ney
Executive Director, NCRP
This editor's face is red. I must apologize to Norman M. Schaeffer, Theodore Rockwell
III, the Radiation Protection and Shielding Division of the ANS, and to all our newsletter
readers. As indicated last month, Norman Schaeffer won a most prestigious award--the
"Theodore Rockwell III"--not the "Norman Rockwell" as I had stated. Sometimes word
association can be embarrassing.
Alice Rice-Editor
Three changes were made to the computer code collection during the month. Two new code systems were packaged and added to the collection and an existing code package was corrected. | |||||
| CCC-629/SESOIL
OP SYS: DOS Language: Fortran 77 Computers: PC Format: DOS | The developer at Oak Ridge National Laboratory, Oak Ridge,
Tennessee, contributed a corrected version of the SESOIL code
system. A minor change was made to the Fortran source file to correct
erroneous values which were sometimes written to the printed output
for the user-specified, pollutant mass input table. The errors only
printed with a specific (rarely used) option. Since the code actually
used the correct values, no calculated results were affected by this
error. SESOIL, as an integrated screening-level soil compartment model, is designed to simultaneously model water transport, sediment transport, and pollutant fate. It is a one-dimensional vertical transport model for the unsaturated soil zone. The Ryan McFarland Fortran compiler, Version 3.10.01, was used to create the PC executables included in package which can be run as DOS programs from Windows 95. One diskette written in DOS format contains the SESOIL source code, sample input and output data, and executable. References: PUBL-SW-200-93 (Revision 1.6) (August 1994). Fortran 77; IBM PC's and compatibles (C00629/IBMPC/02). CCC-646/SKYSHINE-KSU | OP SYS: DOS Language: Fortran 77 Computers: PC Format: DOS Kansas State University, Manhattan, Kansas, contributed this code
system to calculate neutron and gamma-ray skyshine doses using the
integral line-beam method. SKYSHINE-KSU includes the SKYNEUT,
SKYDOSE and MCSKY codes plus the DLC-188/SKYDATA library
to form a comprehensive system for calculating skyshine doses. | SKYNEUT evaluates the neutron and neutron-induced secondary gamma-ray skyshine doses from an isotropic, point, neutron source collimated by three simple geometries: an open silo, a vertical black (perfectly absorbing) wall, and a rectangular building. The source may emit monoenergetic neutrons or neutrons with an arbitrary multigroup spectrum of energies. SKYDOSE evaluates the gamma-ray skyshine dose from an isotropic, monoenergetic, point gamma-photon source collimated by three simple geometries: a source in a silo, a source behind an infinitely long, vertical, black wall, and a source in a rectangular building. In all three geometries an optional overhead slab shield may be specified. MCSKY evaluates the gamma-ray skyshine dose from an isotropic, monoenergetic, point gamma-photon source collimated into either a vertical cone (i.e., silo geometry) or into a vertically oriented structure with an N-sided polygon cross section. An overhead laminate shield composed of two different materials is assumed, although shield thicknesses of zero may be specified to model an unshielded skyshine source. SKYNEUT and SKYDOSE are based on the integral line-beam method using an improved three-parameter approximation for the line-beam response function. In MCSKY the skyshine dose calculation is based on a Monte Carlo algorithm to evaluate the gamma-ray transport through the source shields and the integral line-beam method to describe the subsequent transport of gamma photons through the atmosphere. The codes were written in Fortran 77 and were tested on an IBM compatible PC. Executable files produced by the Microsoft Fortran compiler (version 5.1) are included. The package is transmitted on a 3.5-in DS/HD (1.4 MB) diskette written in DOS format containing source codes, executable files, response function data files, and files for input and output of example problems. References: KSU Report 9503 (1995), SAND95-1748 (1995), SAND95-1747 (1995), KSU Report 271 (June 1995). Fortran 77; IBM PC (C00646/IBMPC/00).
PSR-361/DETAN | OP SYS: UNIX, DOS Language: Fortran 77 Computers: Many Format: UNIX, DOS The National Institute of Standards and Technology, Gaithersburg,
Maryland, contributed this code system for calculating spectrum-averaged cross sections and detector responses in neutron spectra.
DETAN multiplies an arbitrary neutron spectrum by an arbitrary
energy-dependent neutron detector cross section or response function
and integrates over energy to determine a spectrum-averaged cross
section or response. The code accepts an input neutron spectrum as a
tabulated group spectrum or in one of several analytical forms and
converts the spectrum into a fine-group tabulation. The output gives
either spectrum-averaged cross sections for a number of detector
functions, or a detailed spectrum and response function for a specific
detector response. DETAN runs on Cray, IBM RS/6000, DEC Alpha,
Sun, and SGI computers under Unix-based operating systems. A
Fortran source file for personal computers and an executable created
with the Lahey F77L3-EM/32 v5.1 compiler are also included in the
package. The package is transmitted on one diskette in DOS format.
Reference: NISTIR 5622 (March 1995). Fortran 77; Cray, IBM
RS/6000, DEC Alpha, Sun, SGI, and PC (P00361/MNYCP/00). | |
One addition was made to the data library collection during the month. | |
| DLC-188/SKYDATA OP SYS: DOS Language: Fortran 77 Computers: PC Format: DOS | Kansas State University, Manhattan, Kansas, contributed these
parameters for approximate neutron and gamma-ray skyshine response
functions and ground correction factors. These new compilations
allow the response functions to be evaluated with greater accuracy
over greater energy ranges and over greater source-to-detector
distances than do previous approximations. Moreover, the neutron and
secondary-photon response functions are expressed for the first time in
modern dosimetric units. Finally, approximations are provided to
allow correction of the neutron conical beam response functions for
the effect of the air-ground interface. These data are intended for use in calculation of skyshine doses from point gamma-ray and neutron sources with the integral line-beam method. The CCC-646/SKYSHINE-KSU series of such calculational codes has been developed (SKYDOSE, SKYNEUT, and MCSKY) that can directly use these data for simple geometries. These data can be used in specialized codes for sources with more complex geometries or to estimate the effect of the air-ground interface. Data in this library have been obtained by fitting the response function approximations to values of the response functions calculated, for the most part, by the MCNP code. Line-beam data are presented for gamma-ray and neutron sources, the latter including neutron and secondary-photon components. Conical-beam data are also provided for neutron sources with azimuthal symmetry. Source gamma rays may have energies between 0.02 and 100 MeV, and source neutrons may have energies between 0.01 and 14 MeV. The maximum source-to-detector distance is 3000 m for gamma photons below 10 MeV and 1500 m for photons between 10 and 100 MeV. Data for the neutron response functions are valid to 2500 m. Skyshine doses for photon sources are expressed in air-absorbed rad while doses for neutron sources are in dose equivalent. The package is distributed on one 3.5-in DS/HD (1.4 MB) diskette containing multiple ASCII files of the data. Reference: KSU Report 271 (1995). IBM PC (D00188/IBMPC/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 1997 ANS Nuclear Criticality and Safety Division Topical Meeting, Criticality Safety Challenges in the Next Decade,will be held September 7-11, 1997, in Chelan, Washington. The focus will be on criticality safety challenges in the next decade. In addition to the technical paper sessions plenaries and tutorials are being planned on subjects such as KENO VI, MCNP, and Emergency Response. Contributors are requested to submit brief (500-1000 word) summaries on one of the topics described below (other, related, topics may be considered):
Criticality Safety Challenges in Decommissioning and CleanupCriticality Safety Issues in Weapons ReturnCriticality Safety Challenges in Transport and StorageCriticality Safety Challenges in Administration and TrainingCriticality Safety Challenges in Licensing and Regulatory IssuesCriticality Safety Challenges in Long Term DisposalClose Enough: Criticality Safety Challenges in Accurate Determination of Subcritical Margins
Questions on the technical program should be directed to one of the following: Chuck Rogers (509-372-3532),Denelle Friar (509-372-2891),Valerie Putman(208-526-9529), or Cecil Parks (423-574-5280).
Summaries must be typed in English on one side of the page only. Electronic formats (disk or email) are encouraged. The deadline for submission is November 1, 1996. Please send your summary to:
Criticality Topical Paper Review
ANS-EWS
P.O. Box 941
Richland, WA 99352
General questions on the conference or paper submission may be directed to Scott Finfrock at the above address, by phone at 509-376-4078, by fax at 509-372-3777, or by email at Scott_H_Finfrock@rl.gov.
The Radiation Emergency Assistance Center/Training Site (REAC/TS) in Oak Ridge, Tennessee, is part of the Medical Sciences Division of the Oak Ridge Institute for Science and Education established by the U.S. Department of Energy to undertake national and international programs in science and engineering education, training and management systems, energy and environment systems, and medical sciences. The REAC/TS staff offers several courses in the handling of radiation accidents. A brief description of the courses follows.
Handling of Radiation Accidents by Emergency Personnel is a 3-day course designed for emergency room nurses and physicians who may need to administer initial hospital aid to a radiation accident victim. Lectures, complemented by demonstrations, laboratory exercises, and a simulated radiation accident drill, will emphasize the handling of the victim. Discussions include the fundamentals of radiation, detection and measurement, prevention of the spread of contamination, dose reduction for the victim and attending personnel, and the role of the medical physicist in caring for contaminated accident victims.
Occupational Health in Nuclear Facilities is a 4-day course for nurses, physicians, and others who provide occupational health care to employees of government nuclear facilities. Information will be given on basic radiation sciences, health surveillance and evaluation, on-site emergency management of injuries, and medical implications of chemical, physical, biological, social, and psychological stresses on the ability to work. Interdepartmental relationships and medical, legal, and ethical issues will also be discussed.
Health Physics in Radiation Accidents is a 4-day course for health physicists and radiation protection technologists who may be called upon to respond to accidents involving radioactive materials and injury to personnel. The major topics are radiological emergency procedures and the role of the health physicist in a medical environment.
Medical Planning and Care in Radiation Accidents, a 4-day course designed for physicians, presents an advanced level of information on diagnosis and treatment of acute local and total body radiation exposure, internal and external contamination, combined injuries, and multi-casualty incidents involving ionizing radiation.
Radiopharmaceutical Internal Dosimetry, a 5-day course designed to teach techniques for calculating radiation dose from radionuclides administered in nuclear medicine. Emphasis is given to the use of MIRD calculation techniques and associated documents. Lectures cover the use of the dosimetry system, kinetic models, appropriate corrections and modifications to the basic techniques, techniques for extrapolating animal data to humans, an overview of small scale and microdosimetry techniques, and the use of software for kinetic analysis and dosimetry.
Occupational Internal Dosimetry, a 5-day course to teach current techniques for calculating the radiation dose from internally deposited radionuclides. The course stresses the use of ICRP techniques for dose assessment of workers. In addition to basic dosimetry systems, the course covers dosimetry applications for specialized nuclides, interpretation of bioassay data, and the impact of the new 10CRF20 regulations on this area of health physics, and includes overview lectures discussing bioassay and in-vivo analysis methods.
The course dates and registration information may be obtained from Pat Cooley, Registrar, REAC/TS, Oak Ridge Inst. for Science & Education, P.O. Box 117, Oak Ridge, TN 37831-0117 (phone 423-576-3131).
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.
AECL-10550 . . . Description of the Resonance Treatment in WIMS-AECL. . . . Donnelly, J.V. . . . May 1993 . . . Atomic Energy of Canada Ltd., Pinawa, Canada . . . INIS (mf).
ANL-ED/CP-85772 . . . Lessons Learned from Applying VIM to Fast Reactor Critical Experiments. . . . Schaefer, R.W.; McKnight, R.D.; Collins, P.J. . . . May 1995 . . . Argonne National Lab., Idaho Falls, ID . . . INIS (mf); OSTI; NTIS; GP . . . Nuclear Criticality Technology and Safety Project (NCTSP) Annual Meeting, San Diego, CA, May 17, 1995.
CEA-CONF-12118 . . . Mass Charge Yield Calculation in a Thick Target by Using the Monte Carlo Code FLUKA. . . . Cuendet, P.; Diop, C.M.; Ferrari, A.; Fasso, A. . . . 1994 . . . Centre d'Etudes de Saclay, Gif-sur-Yvette, France . . . INIS (mf) . . . International Conference on Radiation Shielding, Arlington, TX, April 24-27, 1994.
INIS-mf-14668 . . . Evaluation of Neutron Resonance Data and Analysis Techniques for CANDU Type Fuel Bundles. . . . Leszczynski, F. . . . 1989 . . . Centro Atomico Bariloche, Rio Negro, Argentina . . . INIS (mf).
Health Phys., 70, 781-786 . . . The Present System of Quantities and Units for Radiation Protection. . . . Sinclair, W.K. . . . June 1996 . . . National Council on Radiation Protection and Measurements, Bethesda, MD.
Health Phys., 70, 787-797 . . . Stem Cell Responses After Radiation Exposure: A Key to the Evaluation and Prediction of Its Effects. . . . Fliedner, T.M.; Tibken, B.; Hofer, E.P.; Paul, W. . . . June 1996 . . . University of Ulm, Ulm, Germany.
Health Phys., 70, 804-811 . . . Neutron Induced Recoil Protons of Restricted Energy and Range and Biological Effectiveness. . . . Geard, C.R. . . . June 1996 . . . College of Surgeons of Columbia University, New York, NY.
Health Phys., 70, 823-827 . . . Effects of Low Doses of Radiation. . . . Fry. R.J.M. . . . June 1996 . . . Oak Ridge National Laboratory, Oak Ridge, TN.
Health Phys., 70, 828-831 . . . Radiation Physics and Radiobiology. . . . Rossi, H.H. . . . June 1996.
Health Phys., 70, 832-836 . . . Radiobiological Challenges Posed by Microdosimetry. . . . Kellerer, A.M. . . . June 1996 . . . Strahlenbiologisches Institut, Munich, Germany.
Health Phys., 70, 845-851 . . . Microdosimetric-Based Risk Factors for Radiation Received in Space Activities During a Trip to Mars. . . . Zaider, M. . . . June 1996 . . . Columbia University, New York, NY.
Health Phys., 70, 852-858 . . . Relative Biological Effectiveness of Ionizing Radiations Determined in Tissue (RBE) Fails in Assessing Comparative Relative Effectiveness in the Tissue Cells. . . . Feinendegen, L.E.; Bond, V.P.; Sondhaus, C.A. . . . June 1996 . . . Brookhaven National Laboratory, Upton, NY; University of Arizona, Tucson, AZ.
Health Phys., 70, 859-867 . . . Various Approaches to Damage Assessment. . . . Hamilton, L.D. . . . June 1996 . . . Brookhaven National Laboratory, Upton, NY.
Health Phys., 70, 868-876 . . . The Use of Cell-Oriented Factors and the Hit Size Effectiveness Function in Radiation Protection. . . . Sondhaus, C.A.; Bond, V.P.; Feinendegen, L.E. . . . June 1996 . . . University of Arizona, Tucson, AZ; Brookhaven National Laboratory, Upton, NY; Office of Health Effects Research, US Department of Energy, Washington, DC.
Health Phys., 70, 877-882 . . . Current Misinterpretations of the Linear No-Threshold Hypothesis. . . . Bond, V.P.; Wielopolski, L.; Shani, G. . . . June 1996 . . . Brookhaven National Laboratory, Upton, NY; Ben Gurion University, Beer Sheva, Israel.
P16-95-481 . . . Prediction of the Radiation Environment and Shielding for Heavy Ion Accelerators. . . Beskrovnaia, L.G.; Komochkov, M.M. . . . 1995 . . . Joint Institute for Nuclear Research, Dubna, Russia.
CONF-9503140 . . . Proceedings of the Fifth Atmospheric Radiation Measurement (ARM) Science Team Meeting. . . .April 1996 . . . United States Department of Energy, Washington, DC . . . Held in San Diego, CA, March 19-23, 1995.
NEA/NSC/DOC(96)-06; ORNL-6901 . . . OECD/NEA Burnup Credit Calculational Criticality Benchmark Phase I-B Results. . . . DeHart, M.D.; Brady, M.C.; Parks, C.V. . . June 1996 . . . Oak Ridge National Laboratory, Oak Ridge, TN; Sandia National Laboratories, Las Vegas, NV.
AECL-11077....................................................................GEONET; SYVAC3
Analysis Specifications for the CC3 Geosphere Model GEONET. . . . Melnyk, T.W. . . . 04/95 . . . Atomic Energy of Canada Ltd., Pinawa, Canada . . . INIS (mf).
AECL-11078....................................................................BIOTRAC; SYVAC3
Analysis Specifications for the CC3 Biosphere Model BIOTRAC. . . . Szekely, J.G.; Wojciechowski, L.C.; Stephens, M.E.; Halliday, H.A. . . . 12/94 . . . Atomic Energy of Canada Ltd., Pinawa, Canada . . . INIS (mf).
BNL-NUREG-62296; CONF-9508180-1...................................RELAP5 MOD 3.1.1; RELAP5; GIRAFFE
Evaluation of RELAP5 Mod 3.1.1 Code with GIRAFFE Test Facility: Phase 1, Step 2 Nitrogen Venting Tests. . . . Boyer, B.D.; Slovik, G.C. . . . 1995 . . . U.S. Nuclear Regulatory Commission, Washington, DC; Brookhaven National Laboratory, Upton, NY . . . INIS (mf); OSTI; NTIS; GPO . . . International Symposium on the Validation of Systems Transient Analysis Codes. Hilton Head, SC, Aug. 14-15, 1995.
CNIC-00810; CNDC-0013; INDC(CPR)-031/L......................................................................ERES
ERES - A PC Software for Nuclear Data Compilation in EXFOR Format. . . . Li Shubing; Liang Qihang; Liu Tingjin . . . 12/93 . . . Nankai University, Tianjin, China . . . INIS (mf).
CNIC-00810; CNDC-0013; INDC(CPR)-031/L....................................................................
....................................................................MAINPLT
A Code for Processing and Plotting Data and Intercomparison of Evaluated Data for 63Cu. . . . Liu Tong; Zhao Zhixlang . . . 12/93 . . . Chinese Nuclear Data Center, Beijing, China . . . INIS (mf).
CNIC-00858....................................................................UNFTOOLS; UNF
UNFTOOLS - An Auxiliary Plotting Code of UNF Code and the Intercomparison of the Double Differential Cross Section for 56Fe. . . . Liu Tong; Zhao Zhixiang; Zhang Jingshang . . . 06/94 . . . Chinese Nuclear Data Center, Beijing, China . . . INIS (mf).
CNIC-00965......................................................................MADEX; ORDEL; SUBDEX; KEYDEX
Program MADX Creating Index for CPL in CNDC. . . . Liu Ruizhe . . . 06/95 . . . Chinese Nuclear Data Center, Beijing, China . . . INIS (mf).
FUFAEM, 15, 42-47....................................................................FLOWER
Improvement of FLOWER Code and Its Application in Daya Bay. . . . Zhang Shaodong; Zhang Yongxing . . . 01/95 . . . Academia Sinica, Beijing, China.
FZKA-5567....................................................................COSYMA
COSYMA: Health Effects Models. . . . Ehrhardt, J.; Hasemann, I.; Matzerath-Boccaccini, C.; Steinhauer, C.; Raicevic, J. . . . 02/95 . . . Forschungszentrum Karlsruhe GmbH Technik, Germany; Commission of the European Communities, Brussels, Belgium . . . INIS (mf).
IAEA-5701/5....................................................................ShlPR
Intellectual Program Shell ShlPR for Computerized Simulation of Nuclear Reactors. General Description. . . . Zizin, M.N.; Shushakov, A.V.; Dement'eva, D.Yu.; Sushnova, N.V. . . . 1994 . . . Kurchatovskij Inst., Moscow, Russia . . . INIS (mf) . . . In Russian.
IAEA-5736-5....................................................................MCU-3
Program MCU-3 for Calculation of Neutron-Physical Characteristics of Nuclear Reactors Using the Monte-Carlo Method. Volume 3. General Description and Algorithms. Part 1. Physical M . . . Abagyan, L.P.; Glushkov, A.E.; Gomin, E.A.; Kalugin, M.A.; Majorov, L.V.; Yhdkevich, M.S. . . . 1994 . . . Inst. Atomnoj Ehnergii, Russia . . . INIS (mf) . . . In Russian.
IAEA-5739-5....................................................................MCU-3
Program MCU-3 for Monte-Carlo Calculations of Neutron-Physical Characteristics of Nuclear Reactors. Volume 5. Architecture Description. . . . Gomin, E.A.; Gurevich, M.I.; Majorov, L.V. . . . 1994 . . . Inst. Atomnoj Ehnergii, Russia . . . INIS (mf) . . . In Russian.
INIS-mf-14668....................................................................HEMCNT
The HEMCNT Code: A Heterogeneous Monte Carlo Neutron Transport Code for Fission and Fusion Reactor Designs and Neutron Shielding Calculations. . . . Campeau, J.C.; Chang, Jen-Shih . . . 1989 . . . McMaster University, Hamilton, Ontario, Canada . . . INIS (mf).
JAERI-1334......................................................................WSPEEDI; SPEEDI; WSYNOP; GEARN
WSPEEDI (Worldwide Version of SPEEDI): A Computer Code System for the Prediction of Radiological Impacts on Japanese Due to a Nuclear Accident in Foreign Countries.. . . . 09/95 . . . Japan Atomic Energy Research Inst., Tokai, Ibaraki, Japan; Tokai Research Establishment, Ishikawa, Hirohiko, Japan . . . INIS (mf).
LA-UR-95-2065; CONF-951006-18.....................................................................MCNP; PVM
MCNP Load Balancing and Fault Tolerance with PVM. . . . McKinney, G.W. . . . 1995 . . . Los Alamos National Lab., Los Alamos NM . . . OSTI; NTIS; INIS (mf); GPO . . . Winter Mtg. of the American Nuclear Society, San Francisco, CA, Oct. 29 - Nov. 1, 1995.
Nucl. Energ. Agency, 75-Paris, 287-304.....................................................................FLUKA
FLUKA: Performances and Applications in the Intermediate Energy Range. . . . Fasso, A.; Ferrari, A.; Ranft, J.; Sala, P.R. . . . 1989 . . . European Organization for Nuclear Research, Geneva, Switzerland.
NUREG/VP-0142, Vol. 3; CONF-950904-Vol. 3..............................................................CATHARE-2; DASM
The Sensitivity Analysis by Adjoint Method for the Uncertainty Evaluation of the CATHARE-2 Code. . . . Barre, F; de Crecy, A.; Perret, C. . . . 09/95 . . . French Atomic Energy Commission, Grenoble, France . . . OSTI; NTIS; GPO; INIS (mf) . . . Proceed. of the 7th Int'l Mtg. on Nuclear Reactor Thermal-Hydraulics NURETH-7, Saratoga, NY, Sept. 10-15, 1995.
NUREG/CR-5535-Vol. 4....................................................................RELAP5/MOD3
RELAP5/MOD3 Code Manual. Volume 4, Models and Correlations. . . . 08/95 . . . Nuclear Regulatory Commission, Washington, DC . . . NTIS; GPO; INIS (mf).
NUREG/CR-6150-Vol. 1; EGG-2720-Vol.1.......................................................SCDAP/RELAP5/MOD 3.1
SCDAP/RELAP5/MOD 3.1 Code Manual: Interface Theory. Volume 1. . . . Coryell, E.W., ed.; Allison, C.M.; Bema, G.A. . . . 06/95 . . . Nuclear Regulatory Commission, Washington, DC . . . OSTI; NTIS; GPO; INIS (mf).
NUREG/CR-6150-Vol. 3; EGG-2720-Vol.3.......................................................SCDAP/RELAP5/MOD 3.1
SCDAP/RELAP5/MOD 3.1 Code Manual: User's Guide and Input Manual. Volume 3. . . . Coryell, E.W., ed.; Johnsen, E.C., ed.; Allison, C.M. . . . 06/95 . . . Nuclear Regulatory Commission, Washington, DC . . . OSTI; NTIS; GPO; INIS (mf).
NUREG/CR-6150-Vol. 5; EGG-2720-Vol.5.......................................................SCDAP/RELAP5/MOD 3.1
SCDAP/RELAP5/MOD 3.1 Code Manual: Developmental Assessment. Volume 5. . . . Hohorst, J.K., ed.; Johnsen, E.C., ed.; Allison, C.M. . . . 06/95 . . . Nuclear Regulatory Commission, Washington, DC . . . OSTI; NTIS; GPO; INIS (mf).
SAND-95-1324....................................................................KBERT 1.0
User's Guide for the KBERT 1.0 Code: For the Knowledge-Based Estimation of Hazards of Radioactive Material Releases form DOE Nuclear Facilities. . . . Browitt, D.S.; Washington, D.I.; Powers, D.A. . . . 07/95 . . . Sandia National Labs., Albuquerque, NM . . . OSTI; NTIS; GPO; INIS (mf).
YKJIEZ, 29, 1-8.....................................................................KENO; KENO IV; KENO Va; AMPX
Development and Application of Critical Calculation Code KENO. . . . Li Sumei; Jin Wenmian . . . 01/95 . . . Academia Sinica, Beijing, China . . . . . . In Chinese.
YKJIEZ, 29, 449-453....................................................................NJOY-WIMS; NJOY; WIMSR; WIMS; SCN; CCMIT; JEF-1
Establishment of NJOY-WIMS Code System. . . . Zhang Baocheng; Liu Guisheng; Liu Ping; Wang Yaoqing . . . 09/95 . . . Academia Sinica, Beijing, China . . . . . . In Chinese.