Oak Ridge National Laboratory
No. 378 May 1996
Five 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, one code package was corrected, and one code package was enhanced with additional documentation.
OP SYS: UNIX, DOS,
|The documentation for this general purpose Monte Carlo code system
for calculating the time-dependent continuous-energy transport of
neutrons, photons, and/or electrons in three-dimensional geometries was
updated with the addition of a revised Table 1 for Appendix G of the
MCNP4A manual. Users who already have the code package may either
access the updated Appendix G through RSIC's web server under
software or request a copy of this table from RSIC. With this revision,
more information is provided to the user for the continuous-energy and
MCNP4A is available in compressed UNIX tar format on cartridge tape or on 29, 3.5-in. DS/HD (1.44 MB) diskettes in self-extracting compressed DOS files. Either UNIX or DOS format is available on CD-ROM. In addition to the source files, MCNP4A executables are included for personal computer users. These were created on a PC 486 under DOS 6.0 using the Lahey Fortran F77L-EM/32 Version 5.10 compiler. They also run under Windows95. References: LA-12625 (1993), LA-12212, LA-12827-M and Nucl. Sci. Eng. 116: 269-277 (1994). Fortran 77 and C; UNIX workstations, PC 386, Cray, Vax, Sun, DEC, HP and SGI, mainframe and all computers in general; (C00200/ALLCP/03).
OP SYS: many
|Westinghouse Hanford Company contributed a newly frozen version of
this code system to calculate transmutation of materials in a nuclear
environment and produce tables of activities and related quantities. This
release, designated REAC*3, is very similar to REAC*2. In addition to
being more easily ported to different computer systems, the main
1) the fixing of a few minor bugs (the most severe being that the time unit "d" was outputted as "h"),
2) the inclusion of the option to use inputted reaction rates in addition to those calculated from flux and cross sections,
3) the inclusion of zones,
4) the production of input to plotting programs, and
5) the inclusion of filenames (including paths) up to 64 characters in length.
REAC*3 was developed on a Cray and has been tested on other UNIX systems such as IBM RS/6000, DEC Alpha, Sun, and Silicon Graphics Indy. A Fortran compiler is required on these UNIX systems. A PC-486/DX2 version compiled with the Lahey Fortran 90 Version 1.10h compiler is also available. Users should specify either the UNIX or PC version. Approximately 120 MB of disk space is required and at least 20 MB of memory. The package includes Fortran source, scripts, data, test case input and output, plus an executable for the PC version. The UNIX version is transmitted on either one CD-ROM, DC 6150 (150 MB), 4-mm DAT (8 GB), or 8-mm (2.3) GB cartridge tape in a compressed tar file. The PC version is transmitted on one CD-ROM written in DOS format. Reference WHC-EP-0282 (1989). Fortran 77; Cray, IBM RS/6000, DEC Alpha, Sun, SGI (C00443/MFMWS/00) or PC 486 (C00443/IBMPC/00).
OP SYS: UNIX, DOS
|The developers of this modular code system for performing
standardized computer analyses for licensing evaluation have
announced that an error has been discovered with the 44-group
ENDF/B-V cross-section library released with SCALE Version 4.3. The
flux spectrum used to collapse the 44-group library from the 238-group
ENDF/B-V library was not a light water reactor (LWR) fuel pin
spectrum as stated in the report describing the library,
NUREG/CR-6102 (ORNL/TM-12460). This report indicates that the
44-group library released with SCALE-4.3 was to be collapsed using a
flux spectrum from a 17 x 17 pressurized water reactor (PWR) fuel pin
cell calculation performed with XSDRNPM and the 238-group library.
However, the spectrum actually used in the collapse was the spectrum
generated for a special study aluminum/U-235 case with no moderating
material. The two flux spectra are compared in the attached figure.|
Calculations performed at ORNL using approximately 170 LWR fuel critical experiments indicate that the 44-group library released in SCALE-4.3 predicts k-eff about 0.5% higher, on average, than it should when collapsed with the PWR spectrum. Please note that the 44-group validation results presented in NUREG/CR-6102 (ORNL/TM-12460) were generated with a pre-release version of the 44-group library that did not contain this error. In addition, a special issue of the SCALE Newsletter will be published shortly with distribution to all RSIC recipients of SCALE-4.3. The Newsletter will compare the two flux profiles and give results of all critical experiment benchmarks in the 44-group report generated with the two different versions of the 44-group library. The SCALE staff at ORNL apologizes to our users for this error and will do everything possible to correct the error as soon as possible and hopes that the impact upon work performed with this library will be minimal. Please contact email@example.com if you need special assistance or additional information.
The corrected binary version of the library is available on the ORNL anonymous ftp server. Users may access this file via anonymous ftp to infosrv1.ctd.ornl.gov, then cd to pub/rsic/scale, specify binary mode and get the file which is about 11 MB. Switch to ASCII mode and get c545.rme info file which includes details on using it. UNIX users should get scale.rev04.xn44.unix; PC users must get scale.rev04.xn44.dos. Users without ftp access may contact RSIC for a replacement.
The UNIX version of SCALE-4.3 runs on IBM RS/6000, DEC, SUN, HP, and SGI workstations. SCALE-PC runs on 486 and Pentium personal computers with a math coprocessor and at least 8 MB 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.
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/01) and PC486 (C00545/PC486/02).
OP SYS: IBM
|Oak Ridge National Laboratory contributed a newly frozen version of
this Monte Carlo code system for design and analysis of calorimeter
systems, Spallation Neutron Source (SNS) target systems, etc. Minor
enhancements and corrections were made in this release of CALOR95,
which was designed to assist experimentalists in evaluating and
analyzing different types of calorimeter systems used in many high-energy physics experiments to determine the energy and direction of
incident hadrons, leptons, and photons. This code package contains
HETC95, SPECT95, EGS4, MORSE, and other support programs. |
CALOR95 runs on IBM RS/6000 computers and requires a Fortran 77 compiler. It is transmitted on either one CD-ROM, DC 6150 (150 MB), 4-mm DAT (8 GB), or 8-mm (2.3)GB cartridge tape in compressed UNIX tar format. References ORNL/TM-11185 (unpublished report) and SDC-92-00257 (May 1992). Fortran 77; IBM RS/6000 (C00610/IRISC/01).
OP SYS: many
|The University of Wisconsin, Madison, Wisconsin, contributed this
version of the RACC code system for computing radioactivity-related
parameters for fusion reactor systems, which they modified for
pulsed/intermittent activation analysis. CCC-388/RACC was
specifically developed to compute the radioactivity and radioactivity-related parameters (e.g., afterheat, biological hazard potential, etc.) due
to neutron activation within inertial fusion energy and magnetic fusion
energy reactor systems. It can also be utilized to compute the
radioactivity in fission, accelerator or any other neutron generating and
neutron source system. This new version designated RACC-PULSE is
based on CCC-388 and has the capability to model irradiation histories
of varying flux levels having varying pulse widths (on times) and dwell
periods (off times) and varying maintenance periods. This provides the
user with the flexibility of modeling most any complexity of irradiation
history beginning with simple steady state operating systems to
complex multi-flux level pulse/intermittent operating systems. The
solution method implemented is a matrix based method which relies on
the evaluation of the matrix exponential for the pulse period (on period),
dwell period (off time) and post shutdown periods. The code retains the
capability of modeling the standard slab, cylinder, sphere and torus
geometries in multidimensions as well as the point or zero-dimension
geometry for Monte Carlo code interfacing. It provides easy interfacing
with many of the standard multigroup, multidimensional neutron/photon
transport code systems currently employed by the fusion community
and implemented on the UNICOS Cray 2 System at NERSC. An
auxiliary code is provided to interface between the Los Alamos
National Laboratory CCC-547/DANTSYS transport codes for users
running on UNIX workstations. The FIDO formatted style of data input
RACC-PULSE runs on the CRAY 2 UNICOS computer and the DEC 5000 and HP 7000 series UNIX workstations. The code is memory intensive, hence workstations containing 32 MB of RAM or more are required for large problems. A Fortran 77 compiler is required. Included in the package are the Fortran source codes, makefiles, test case input and output, which is transmitted on either one CD-ROM or DC 6150 (150 MB), 4-mm DAT (8 GB), or 8-mm (2.3)GB cartridge tape. References: ANL/FPP/TM-122 (May 1979), UWFDM-980 (May 1995), UWFDM-977 (January 1995). Fortran 77; Cray 2, DEC 5000 and HP 7000 series workstations (C00639/ MNYWS/00).
OP SYS: all
|The Los Alamos National Laboratory developers have recommended a
modification to the MCNPDAT6 package, which consists of standard
neutron cross-sections derived from ENDF/B-VI, photon interaction,
and electron data libraries for use with CCC-200/MCNP4A. Two
nuclides were removed from distribution: Am-242 (ground state)
95242.60c and Np-238 93238.60c. These files appear in the ENDF60
library as am95242 and np93238. While the data files accurately reflect
the evaluations, LANL is concerned that the evaluations are too
incomplete to be used for most transport calculations. The
corresponding lines were removed from XSDIR, which was extensively
revised. Users who already have the package may access the updated
XSDIR, README, and Table 1 files from RSIC's web server under
software. Alternately the information can be transmitted on one 1.44
DS/HD 3.5-in. diskette. An Errata for LA-12891 was added to the
document to reflect changes to Table I "The MCNP ENDF60 Library."|
MCNPDAT6 is distributed on either CD-ROM, DC 6150 (150 MB), 4 mm DAT (8 GB), or 8 mm (2.3 GB) cartridge tapes in UNIX compressed tar format. It is alternately available on either CD-ROM or QIC-80 tape in self-extracting compressed DOS files for PC users. References: LA-12891 (Dec. 1994) and Errata (April 1996). Fortran 77; All Computers (D00181/ ALLCP/01).
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 National Research Council of Canada, Ottawa, Ontario, is sponsoring an OMEGA-BEAM Workshop, October 7-11, 1996. The OMEGA (Ottawa-Madison Electron Gamma Algorithm) project is a collaboration between investigators at the University of Wisconsin (UW) - Madison, and the National Research Council of Canada (NRCC) - Ottawa, to develop procedures and software for radiation therapy treatment planning using the Monte Carlo technique. The package consists of a code to simulate the heads of linear accelerators, called BEAM, software to characterize the output of BEAM, and software to transport the simulated beams through a phantom specified by a computed tomography dataset.
The course will include didactic instruction and hands-on workshops. The participants will receive all educational materials and software included in the package.
Additional information may be obtained from:
Dr. D.W.O. Rogers
Ionizing Radiation Standards
NRC, Ottawa, On., Canada K1A 0R6
Tel: 613-993-2715, fax: 613-952-9865
Your attention is directed to the following events of interest.
ANS Annual Meeting, June 16-20, 1996, Reno, Nevada. Contact: ANS, Meetings Dept. 555 North Kensington Ave., La Grange Park, IL 60525 (fax 708-352-6464).
12th Topical Meeting on the Technology of Fusion, June 16-20, 1996, Reno, Nevada. Contact: ANS, Meetings Dept. 555 North Kensington Ave., La Grange Park, IL 60525 (fax 708-352-6464).
Topical Meeting on DOE Spent Nuclear Fuel and Fissile Material Management, June 16-20, 1996, Reno, Nevada. Contact: ANS, Meetings Dept. 555 North Kensington Ave., La Grange Park, IL 60525 (fax 708-352-6464).
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 firstname.lastname@example.org).
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 email@example.com).
Air Sampling for Radioactive Materials, June 24-28, 1996, 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: 423-576-3576; fax: 423-576-9383; E-mail: MCLAINA@ORAU.GOV).
Meeting on Burnup Credit Criticality Safety Benchmarks, June 25-27, 1996, Paris, France. Contact: Dr. Enrico Sartori, OECD/NEA Data Bank, 12 boulevard des Iles, F-92130 Issy-les-Moulineaux, France (phone 33-1-4524-1072; fax 33-1-4524-1110; e-mail firstname.lastname@example.org).
Controlled Fusion and Plasma Physics, June 24-28, 1996, Kiev, Ukraine. Contact: Dr. I. Goutych, Scientific Secretary, 23rd EPS CFPP, Bogolyubov Institute for Theoretical Physics, 252143, Kiev, Ukraine (phone 380-44-266-5362; fax 380-44-266-5998; email email@example.com).
SCALE Training Course, July 1-5, 1996, Stuttgart, Germany. Contact: Dr. Enrico Sartori, OECD/NEA Data Bank, 12 boulevard des Iles, F-92130 Issy-les-Moulineaux, France (phone 33-1-4524-1072; fax 33-1-4524-1110; e-mail 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).
Computational Methods in Reactor Analysis and Shielding, Aug. 12-16, 1996, 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 423-974-2525; fax 423-974-0668).
Nuclear Criticality Safety, Aug. 12-16, 1996, 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 423-974-2525; fax 423-974-0668).
Monte Carlo Analysis, Aug. 12-16, 1996, 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 423-974-2525; fax 423-974-0668).
Spectrum'96: Nuclear and Hazardous Waste Management International Topical, August 18-23, 1996, Seattle, Washington., Contact: Cheryl Thornhill at 509/375-2532 (web page at http://www.hanford.gov/ans/s96home.html).
Safe Use of Radionuclides, Aug. 19-23, 1996, 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: 423-576-3576; fax: 423-576-9383; E-mail: MCLAINA@ORAU.GOV).
Radiological Surveys in Support of Decommissioning, Aug. 26-30, 1996, 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: 423-576-3576; fax: 423-576-9383; E-mail: MCLAINA@ORAU.GOV).
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).
Environmental Monitoring, Sept. 9-13, 1996, 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: 423-576-3576; fax: 423-576-9383; E-mail: MCLAINA@ORAU.GOV).
International Conference on Physics of Reactors, "Breakthrough of Nuclear Energy by Reactor Physics," PHYSOR '96, Sept. 16-20, 1996, Mito, Japan. Contact: Dr. Keichiro Tsuchihashi, Dep. Dir., Dept of Reactor Engg., JAERI, Tokai-Mura, Naka-Gun, Ibaraki-ken 319-11 Japan (phone 81-292-82-6120; fax 81-292-82-6122; email firstname.lastname@example.org).
Applied Health Physics, Sept. 16-Oct. 18, 1996, 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: 423-576-3576; fax: 423-576-9383; E-mail: MCLAINA@ORAU.GOV).
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).
3rd Topical Meeting on Industrial Radiation and Radioisotope Measurements and Applications, IRRMA '96, Oct. 6-9, 1996, Raleigh, North Carolina. Contact: William L. Dunn, Quantum Research Services, Inc., Suite W, 5410 Apex Highway, Durham, NC 27713-9434 (phone 919-544-4952; fax 919-544-2918; email email@example.com).
OMEGA - BEAM Workshop: Monte Carlo Treatment Planning, Oct. 7-11, 1996, Ottawa, On., Canada, Contact: Dr. D.W.O. Rogers, Ionizing Radiation Standards, NRC, Ottawa, Ontario, Canada K1A 0R6 (phone 613-993-2715, fax: 613-952-9865, email: firstname.lastname@example.org).
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).
Specialists' Meeting on "In-Core Instrumentation and Reactor Core Assessment," Oct. 14-17, 1996, Mito, Japan. Contact: Dr. Pierre Nagel, OECD/NEA Data Bank, 12 blvd. des Iles, F-92130 Issy-les-Moulineaux, France (phone 33-1-4524-1082; fax 33-1-4524-1110; email email@example.com).
96 NEE: International Symposium on Nuclear Energy and the Environment, Oct. 14-18, 1996, Beijing, sponsored by the Chinese Society of Radiation Protection, Chinese Nuclear Society, and the Chinese Society of Environmental Sciences. Contact: Prof. Leng Reiping, 96 NEE, P.O. Box 2102-14, Beijing 100822, People's Republic of China (phone 0086-10-8510370; fax 0086-10-8539375; email ZHUZM@BEPC2.IHEP.AC.CN).
International Conference on Radiation and Health, Ben Gurion University of the Negev, Nov. 3-7, 1996, Beer Sheva, Israel. Contact: International Conference on Radiation and Health, Ortra Ltd, 2 Kaufman Street, Textile Center, POB 50432, Tel Aviv 61500, Israel. (Phone: 972-3-5177888, fax: 972-3-5174433, E-mail: firstname.lastname@example.org).
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).
7th International Symposium on Radiation Physics (ISRP-7), Feb. 24-28, 1997, Jaipur, India. Contact: Dr. Bikash C. Sinha, Director, Variable Energy Cyclotron Centre, 1/AF Bidhan Nagar, Calcutta 700064, India (phone 91-33-37-0032; fax 91-33-34-6871).
ISFNT-4: 4th International Symposium on Fusion Nuclear Technology, Apr. 6-11, 1997, Tokyo, Japan. Contact: Prof. Satoru Tanaka, Dept. of Quantum Eng. & Systems Science, Univ. of Tokyo, Hongo, Bunkyo-ku, Tokyo 113, Japan (phone 81-3-3812-2111 ext. 6968; fax 81-3-5800-6860 or 81-3-3818-3455; email email@example.com; url http://hooker.gen.u-tokyo.ac.jp/isfnt4.html).
6th Topical Meeting on Emergency Preparedness and Response, April 22-25, 1997, San Francisco, sponsored by the American Nuclear Society. Contact: Dr. Thomas Sullivan, LLNL Mail Code L-103, P.O. Box 808, Livermore, CA 94550 (phone 510-422-1838, fax 510-423-5167, e-mail firstname.lastname@example.org).
International Conference on "Nuclear Data," May 19-23, 1997, Trieste, Italy. Contact: Dr. Gianni Reffo, E.N.E.A.-Centro Ricerche, Energia "E. Clementel", Centro Dati Nucleari V. Martiri di Monte Sole 4, I-40129 Bologna, Italy (phone 39-51-60-98-522; fax 39-51-60-98-785; email email@example.com).
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).
International Conference on "Future Nuclear Systems," Global '97, Oct. 5-10, 1997, Yokohama, Japan. Contact: Dr. Takehiko Mukaiyama, JAERI, Tokai-mura, Ibaraki-ken 319-11, Japan (phone 81-29-282-5325; fax 81-29-282-6181; email firstname.lastname@example.org).
Joint International Conference on "Mathematical Methods and Supercomputing in Nuclear Applications," Oct. 6-10, 1997, Saratoga Springs, New York. Contact: Dr. Richard Mendelson, KAPL, E6-216, P.O. Box 1072, Schenectady, NY 12301 USA (phone 518-395-7046; fax 518-395-4422; email email@example.com).
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.
Health Phys., 69, 187-201 . . . A Proposed Blood Circulation Model for Reference Man. . . . Leggett, R.W.; Williams, L.R. . . . August 1995 . . . Oak Ridge National Laboratory, Oak Ridge, TN; Indiana University South Bend, South Bend, IN.
Health Phys., 69, 210-218 . . . Reduced Integral Solutions for Gamma Absorbed Dose from Gaussian Plume. . . . Gorshkov, V.E.; Karmazin, I.P.; Tarasov, V.I. . . . August 1995 . . . Nuclear Safety Institute, Moscow, Russia.
Health Phys., 69, 243-256 . . . A Sensitivity Study of the SCK-CEN Biosphere Model for Performance Assessment of Near-Surface Repositories. . . . Zeevaert, Th.; Volckaert, G.; Vandecasteele, C. . . . August 1995 . . . SCK-CEN, Mol, Belgium.
Health Phys., 69, 257-260 . . . Significant Digits: Foundations, Myths and Utilization. . . . Chambless, D.A.; Broadway, J.A. . . . August 1995 . . . Auburn University, Montgomery, AL; Moscow State University, Moscow, Russia.
Health Phys., 69, 261-264 . . . Occupational Exposure in Pediatric Cardiac Catheterization. . . . Li, L.B.; Kai, M.; Takano, K.; Ikeda, S.; Matsuura, M.; Kusama, T. . . . August 1995 . . . University of Tokyo, Tokyo, Japan; Hygiene and Antiepidemic Station of Shandong Province, China; Nihon University Itabashi Hospital, Tokyo, Japan.
Health Phys., 69, 265-268 . . . Estimates of Thyroid Equivalent Dose in Lithuania Following the Chernobyl Accident. . . . Nedveckaite, T.; Filistowicz, W. . . . August 1995 . . . Institute of Physics, Vilnius, Lithuania.
Nucl. Sci. Eng., 122, 287-308 . . . Concurrent Source Iteration in the Solution of Three-Dimensional, Multigroup Discrete Ordinates Neutron Transport Equations. . . . Dorr, M.R.; Still, C.H. . . . March 1996 . . . Lawrence Livermore National Laboratory, Livermore, CA.
Nucl. Sci. Eng., 122, 309-325 . . . The Simplified P2 Approximation. . . . Tomasevic, D.I.; Larsen, E.W. . . . March 1996 . . . University of Michigan, Ann Arbor, MI.
Nucl. Sci. Eng., 122, 326-343 . . . Efficient Monte Carlo Simulation of 16-O Neutron Activation and 16-N Decay Gamma-Ray Detection in a Flowing Fluid for On-Line Oxygen Analysis or Flow Rate Measurement. . . . Gardner, R.P.; Barrett, C.L.; Haq, W. Peplow, D.E. . . . March 1996 . . . North Carolina State University, Raleigh, NC.
Nucl. Sci. Eng., 122, 374-383 . . . Cross-Section Calculations for Neutron-Induces Reactions Up to 50 MeV. . . . Yamamuro, N. . . . March 1996.
Nucl. Technol., 114, 1-11 . . . Validation of MCNP for RBMK Criticality Calculations. . . . Behrens, D.; Meyer, S.; Ehrenstein, D.; Donderer, R.; Schumacher, O.; Davydova, G.; Krayushk . . . April 1996 . . . Kerntechnik und Energie an der Universitat Bremen, Bremen, Germany; Kollert, & Donderer, Bremen, Germany; Kurchatov Institute, Moscow, Russia.
Nucl. Technol., 114, 23-50 . . . Fission Product Releases at Severe Light Water Reactor Accident Conditions: ORNL/CEA Measurements Versus Calculations. . . . Andre, B.; Ducros, G.; Leveque, J.P.; Osborne, M.F.; Lorenz, R.A.; Maro, D . . . April 1996 . . . Commissariat a l'Energie Atomique, Grenoble Cedex 9, France; Oak Ridge National Laboratory, Oak Ridge, TN; Commissariat a l'Energie Atomique, Fontenay aux Roses, France.
Nucl. Technol., 114, 77-83 . . . Protection from Radioaerosols and Volatile Radionuclides. . . . Mikheev, N.B.; Kulyukhin, S.A.; Kamenskaya, A.N.; Rumer, I.A. . . . April 1996 . . . Russian Academy of Sciences, Institute of Physical Chemistry; Moscow, Russia . . .This paper is from "New Trends in Nuclear System Thermohydraulics," an international conference that took place in Pisa, Italy, May 30-June 2, 1994.
BNL-63006 . . . The U.S. Nuclear Reaction Data Network. . . . Bhat, M.R., ed. . . . April 1996 . . . Brookhaven National Laboratory, Upton, Long Island, NY . . . Summary of the First Meeting held at the Colorado Schools of Mines, Golden, Colorado, March 13 & 14, 1996.
CNIC-01016; CNDC-0017; INDC(CPR)-036/L . . . Communication of Nuclear Data Progress No. 14 (1995). . . . . . . December 1995 . . . China Nuclear Data Center, Beijing, China.
INDC(BLR)-003 . . . Evaluation of Neutron Data for Curium-245. . . . Maslov, V.M.; Sukhovitskij, E.Sh.; Porodzinskij, Y.V.; Klepatskij, A.B.; Morogovskij, G.B. . . . February 1996 . . . Radiation Physics & Chemistry Problems Institute, Minsk-sosny, Belarus.
INDC(NDS)-342 . . . Activation Cross Sections for the Generation of Long-Lived Radionuclides of Importance in Fusion Reactor Technology. . . . Pashchenko, A.B., ed. . . . February 1996 . . . IAEA Nuclear Data Section, Vienna, Austria . . .Presented at the Third and Final Research Coordination Meeting, St. Petersburg, Russia, June 19-23, 1995.
INDC(NDS)-347 . . . Neutron Metrology File NMF-90. . . . Kocherov, N.P. . . . January 1996 . . . IAEA Nuclear Data Section, Vienna, Austria . . . An integrated database for performing neutron spectrum adjustment calculations.
INDC(NDS)-351 . . . IAEA Consultants' Meeting on Benchmark Validation of FENDL-1, Karlsruhe, Germany 17 to 19 October 1995. . . . Pashchenko, A.B., ed. . . . January 1996 . . . IAEA Nuclear Data Section, Vienna, Austria.
INDC(PAK)-012 . . . Hauser-Feshbach Calculations of Neutron-Induced Reaction Cross Sections for 52-Cr in 6-20 MeV Neutron Energy Range. . . . Gul, K. . . . October 1995 . . . Pakistan Institute of Nuclear Science & Technology, Islamabad.
Health Phys., 69, 243-256 BIOSHPERE; DOSE; SITE; AQUIFER A Sensitivity Study of the SCK-CEN Biosphere Model for Performance Assessment of Near-Surface Repositories. . . . Zeevaert, Th.; Volckaert, G.; Vandecasteele, C. . . . 03/96 . . . . . . SCK-CEN, Mol. Belgium. Nucl. Sci. Eng., 122, 374-383 SINCROS-II Cross-Section Calculations for Neutron-Induced Reactions Up to 50 MeV. . . . Yamamuro, N. . . .08/95. NUREG/CP-0142-V2, 1574-1585 GEYSER/TONUS GEYSER/TONUS: A Coupled Multi-D Lumped Parameter Code for Reactor Thermal Hydraulics Analysis in Case of Severe Accidents. . . .Petit, M.; Durin, M.; Gauvain, J. . . . 09/95 . . . Commissariat a l'Energie Atomique, Gif-sur-Yvette, France ; Nuclear Regulatory Commission, Washington, D.C. . . . OSTI; NTIS; INIS; GPO.