Radiation Safety Information Computational Center
|Oak Ridge National Laboratory|
Post Office Box 2008
Oak Ridge, Tennessee 37831-6362
Lockheed Martin Energy Research Corp.
for the U.S. Department of Energy
under contract DE-AC05-96OR22464
Phone No. 423-574-6176
|No. 393||September 1997|
Quality isn't something that can be argued into an article or promised into it. It must be put
there. If it isn't put there, the finest sales talk in the world won't act as a
substitute.--C. G. Campbell
CHANGES TO THE COMPUTER CODE COLLECTION
Three changes were made to the computer code collection during the month. One new code system was packaged and added to the collection and two existing code packages were corrected or replaced with newly frozen versions. One change resulted from a foreign contribution.
Oak Ridge National Laboratory modified this package for standardized analysis for licensing evaluation with a correction to one KENO-VI subroutine and replacement of the KENO-VI and CSAS6 test cases to correspond to changes in some default input values in the August 1997 KENO-VI modifications. Users may get these updates from the "Download" page on the SCALE Web site at http://www.cad.ornl.gov/cad_nea/text/scale-home.html. References: NUREG/CR-0200, Rev. 5 (ORNL/NUREG/CSD-2/R5), Vols. I, II, and III (March 1997), 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/03) and PC486 (C00545/PC486/04).
Oak Ridge National Laboratory, Oak Ridge, Tennessee, contributed a newly frozen version of this code system for the radiological asessment for consequence analysis. RASCAL, Version 2.2, estimates reactor source term, atmospheric transport and doses resulting from radiological emergencies and can be used to assist in making protective action decisions. RASCAL 2.1 was modified to create RASCAL 2.2 to allow better analysis of radiological materials accidents. Other updates were made to improve ease of use. Corrections to all errors found were made. RASCAL 2.2 includes a "close-in" straight-line Gaussian plume model that computes doses at distances from 25 to 800 meters. Modifications to the calculations include the addition of some isotopes, the ability to enter isotopic source terms in mass units, and a simple model of the toxicity of UF6. The reactor core release fractions have been updated to match those defined by the final NUREG-1465 report.
The recommended minimum configuration is a 386 PC and an EGA (or better) graphics adapter. MS-DOS 5.0 or higher is recommended; it also runs under Windows95. Microsoft compilers were used to compile the Fortran (Version 5) and C (Version 7) sources. Compiling the C source also requires Vermont Creative Software's Vermont Views libraries, used only for data input. The package is transmitted on 3 DS/HD 3.5-in. (1.44 MB) diskettes which include source files, executables, data, help files, and batch jobs in DOS files. References: NUREG/CR-5247 Vol. 1, Rev. 2, Supp. 1., and NUREG/CR-5247 (ORNL-6820) Vol. 1, Rev. 2 (December 1994). Fortran 77, C; PC 386 (C00553/PC386/03).
Lawrence Livermore National Laboratory, Livermore, California, and the International Atomic Energy Agency, Vienna, Austria, contributed a newly frozen version of the pre-processing code system for data in ENDF/B format, designated PREPRO-96. The ENDF/B pre-processing codes are designed to be a modular set of computer codes, each of which reads evaluated nuclear data in the ENDF/B format, processes the data and writes it in the ENDF/B format. Each code performs one or more independent operations on the data. These codes are designed to operate on virtually any type of computer with the included capability of optimization on any given computer. Although these codes can process datasets in any ENDF/B format, e.g. ENDF/B-IV, V or VI, there are some problems processing the ENDF/B-IV, Rev. 4. data.
The Lahey Fortran F77L3-EM/32 v5.1 compiler was used to create the PC executables included in the package. The package is distributed on 5 DS/HD 3.5" (1.44 MB) diskettes written in self-extracting compressed DOS files. The diskettes contain Fortran 77 source files, executables for PC, sample input and output, and an information file. Reference: IAEA-NDS-39, Rev. 9 (1996). Fortran 77 on IBM PC and compatibles (P00351/MNYCP/01) with portability to DEC VAX, IBM RS/6000, and other platforms.
CHANGES TO THE DATA LIBRARY COLLECTION
Two new data libraries were added to the collection. One was added through the efforts of an international team.
Oak Ridge National Laboratory, Oak Ridge, Tennessee, and the OCDE/OECD NEA Data Bank, Paris, France, contributed a new data package called SINBAD version 97 (Shielding Integral Benchmark Archive and Database). Prompted by the closures of experimental facilities throughout the world, the effort to preserve benchmark information in formats acceptable to the international community began in 1992-93. These benchmarks are a part of a recommended set from the Cross Section Evaluation Working Group (CSEWG) and the Nuclear Energy Agency Nuclear Science Committee (NEANSC) sanctioned for use as quality assurance in computational shielding verification and cross-section library production.
SINBAD is an active and growing radiation benchmark catalogue that provides the most accurate and complete electronic data available from bulk shielding experiments. The initial set of benchmark documents is mainly fission shielding with a single fusion shielding benchmark. Work on follow-up versions of SINBAD will provide more on fission, fusion, and accelerator shielding, as well as criticality safety.
The full benchmark information includes the source of radiation, its energy, angle, and strength; the materials tested, their compositions, tolerances, temperatures, and physical arrangement; and the detectors, their locations, data results, resolution limits, response curves and unfolding code references. Statistical error analyses of the measurements are included. Often a benchmark is accompanied by a computation to help lend validity to the data.
This archive of benchmark experiments is distributed in two desktop publishing formats, Adobe Acrobat 3.0 PDF and Microsoft Word 8.0 for Windows. The highly graphical and tabular nature of the benchmark data makes storage of isolated ASCII text apart from the representative figures most unfitting. These two file formats were chosen based on the universal availability of the software and its ability to display the contents in a complete and clear manner.
The 1-2-page abstracts, which completely specify the major components of each benchmark, are available on the RSICC WEB site at http://www-rsicc.ornl.gov/BENCHMARKS.html and at the OECD/NEA WEB site at http://www.nea.fr/html/dbprog. A user may check the updates to SINBAD and benchmarks being prepared for release at the above WEB sites. References: Abstracts (1997). PC 486 (D00191/PC486/00).
Lawrence Livermore National Laboratory, Livermore, California, contributed a new data library distributed as POINT97. The reference evaluated data includes cross sections represented in the form of a combination of resonance parameters and/or tabulated energy dependent cross sections, nominally at 0 Kelvin temperature. For use in applications, the ENDF/B-VI, Release 4, data were processed into the form of temperature dependent cross sections at eight temperatures between 0 and 2100 Kelvin, in steps of 300 Kelvin. At each temperature the cross sections are tabulated and linearly interpolable in energy. The POINT97 library contains data for 321 evaluations.
The PREPRO97 code system was used to process the ENDF/B data. Listed below are the steps which were used to process the data in the order in which the codes were run.
The data files, which were written on a PC, are in ENDF-B6 ASCII (character) format. The data are approximately 1 gigabyte in size and are distributed on two CD-ROM disks written in DOS format. Reference: UCRL-ID-127776 (July 4, 1997). Many computers (D00192/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 firstname.lastname@example.org.
The SCALE Training Course has been expanded to two consecutive courses that will separately cover the SCALE criticality codes and the SCALE shielding and source-term codes. The criticality course will focus on KENO V.a and the associated criticality analysis sequences in CSAS. It also will include a brief introduction to KENO-VI. The shielding and source-terms course will emphasize SAS2/ORIGEN-ARP (depletion/source-term generation) and SAS4/MORSE-SGC (3-D Monte Carlo neutron/gamma shielding). It will also cover SAS1/XSDRNPM (1-D neutron/gamma shielding) and QADS/QAD-CGGP (3-D point kernel gamma shielding). Each course will be conducted at Oak Ridge National Laboratory (ORNL) in Oak Ridge, Tennessee. Attendees will gain hands-on experience in problem sessions each afternoon.
The SCALE Criticality Course will be offered October 28 - 31 (Tuesday - Friday) and the SCALE Shielding and Source Term Course will be offered the following week on November 3 - 6 (Monday - Thursday). The courses are scheduled so that users may attend both courses if they choose. The expanded format allows time to more adequately cover each SCALE sequence. It also gives users the opportunity to select the course that best suits their professional needs and interests. This format was offered last fall and was very popular with the attendees. The registration fees are $1,200 for one course or $2,000 for both courses.
The number of registrants for each course is limited to 24. Registrations will be accepted on a first-come basis. Hotel rooms are available at the Garden Plaza Hotel (423-481-2468). Additional information can be obtained by fax (423-576-3513), e-mail (email@example.com), or on the web at http://www.cad.ornl.gov/cad_nea/text/trcourse.html.
1st Meeting of the Brazilian Society of Nuclear Biosciences
The first scientific meeting of the Brazilian Society of Nuclear Biosciences will be held in Rio de Janeiro, Brazil, on November 18-20, 1997. Exchange of information on different topics in the nuclear biosciences will permit the integration of national and international scientists with students and professionals in these areas. Topics to be covered include radiopharmacy, nuclear medicine, radiation protection, medical physics, education in nuclear biosciences, quality control, radiobiology, photobiology, and toxicology, and in-vivo and in-vitro methods in diagnosis, therapy, and research. Scientists wishing to submit an abstract should do so by September 10, 1997. Contact: Secretariat, Departmento de Biofisica e Biometria, Instituto de Biologia, Universidade do Estado do Rio de Janeiro, Av. 28 de setembro 87 - Vila Isabel, CEP:20551-030 - Rio de Janeiro, Brazil (phone 5521-587-6507, fax 5521-254-3532).
Technologies for the New Century
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 (firstname.lastname@example.org) and the Technical Chairman is D. T. Ingersoll (email@example.com). Information about the conference can be found at http://wwwrsicc.ornl.gov/RPS98/rps98.htm.
1998 Symposium on Radiation Measurements and Applications
This symposium is the ninth in a series emphasizing sources and applications of ionizing
radiation. The conference will be held on May 12-14, 1998, at the University of Michigan, Ann
Arbor. The symposium will include innovations in radiation sources, detectors and detection
systems, data acquisition and data analysis methods, radiation spectroscopy, particle-induced
X-ray emission and radiation-induced fluorescence, analytical standards, elemental analysis,
industrial radiography and tomography, and new and unique applications of radiation. The scope
includes applications in energy and environmental technology, geosciences, materials research,
non-destructive evaluation and testing, medical and biological research, radiological assessment,
and nonproliferation technology. Papers accepted for publication will appear in a special issue of
Nuclear Instruments and Methods in Physics Research. For further information, contact:
Symposium Secretary, 3034 Phoenix Memorial Laboratory, The University of Michigan, Ann Arbor, MI 48109-2100 U.S.A. (email: firstname.lastname@example.org)
Symposium Topics include
Practical MCNP for the HP, Medical Physicist and Rad Engineer
MCNP made easy! The Los Alamos MCNP code is a general and powerful Monte Carlo transport code for photons, neutrons, and electrons. It is now supported on a variety of platforms and can run on everything from a laptop to a workstation.
This 4.5-day course is aimed at the health physicist, medical physicist or rad engineer with little or no experience with Monte Carlo techniques. The course will be offered on the following dates:
May 18-22, 1998 (registration deadline: 5/8/98)
August 10-14, 1998 (registration deadline: 7/31/98)
The focus is almost entirely on the application of MCNP to solve a variety of practical problems in radiation protection, radiation shielding, and dosimetry. The intent is to "jump start" the student toward using MCNP productively. Extensive practice sessions are conducted on a Windows-based personal computer platform.
Topics will include:
Students will be provided with a comprehensive class manual and a diskette containing all of the practice problems. This course has been granted 32 Continuing Education Credits by the AAHP. The course is offered by the Health Physics Measurements Group at the Los Alamos National Laboratory.
For further information, please contact Dick Olsher, 505-667-3364, e-mail: email@example.com. The course will be held at the University of New Mexico-Los Alamos Campus. Registration is $1500 per person.
Make checks payable to the University of California (checks must be in U.S. dollars on a U.S. bank) and mail together with your address, phone and fax numbers to:Group ESH-4 MCNP Class/Paulette Sanchez Mail Stop G761 Los Alamos National Laboratory Los Alamos, NM 87545
Inquiries regarding registration and class space availability should be made to Paulette Sanchez (phone 505-665-6068, fax: 505-665-6071).
The 5th Intl. Workshop will be organized in Spring/Summer 1998. The 3rd and 4th International
Training Courses/Workshops on "Methodologies for Particle Transport Simulation and Their
Application to Reactor Dosimetry/Shielding" were held at the Pennsylvania State University
(May 19-23, 1997), and at the University of Stuttgart (June 9-13, 1997), respectively. The 3rd
workshop was organized by the Penn State Transport Theory Group (PSTTG), and the 4th
workshop by the OECD/NEA Data Bank; both the 3rd and 4th workshops were co-sponsored by
RSICC and in collaboration with the IAEA Nuclear Data Section. Each workshop had nine
participants representing Belgium, Czech Republic, France, Germany, Italy, Malaysia, Sweden,
and the United States. These one-week workshops provided in-depth discussions on transport
theory methods and their application, on effective use of computer codes (DORT/TORT, MCNP,
and others) and nuclear data libraries for complex real-life modeling and calculations. To be
included on the mailing list and receive additional information, please send an email message to
firstname.lastname@example.org or email@example.com with your name, title/position,
company, address, phone/fax/email, or contact Prof. Haghighat or Dr. Petrovic at the following address.
Penn State University
Nuclear Engineering Department
231 Sackett Building
University Park, PA 16802
(Prof. Haghighat's phone, 814-865-0039; fax, 814-865-8499: Dr. Petrovic's numbers 814-865-0045; fax, 814-865-8499).
1998 IEEE Nuclear and Space Radiation Effects Conference
The 1998 IEEE International Conference on Nuclear and Space Radiation Effects will be held July 20-24 in Newport Beach, California. The Conference features a technical program of eight to ten sessions of contributed papers describing the latest observations in radiation effects, an up-to-date Short Course on radiation effects offered on July 20, a Radiation Effects Data Workshop, and an Industrial Exhibit. The technical program includes oral and poster sessions. To allow maximum participation by attendees, no parallel sessions will be scheduled.
Papers describing nuclear and space radiation effects on electronic and photonic materials, devices, circuits, sensors, and systems, as well as semiconductor processing technology and techniques for producing radiation-tolerant (hardened) devices and integrated circuits, will be presented at this meeting of engineers, scientists, and managers. International participation is strongly encouraged.
We are soliciting papers describing significant new findings in the following or related areas:
Papers in the areas of "Commercial Space Systems & Environments" and "Radiation Effects in Emerging Technologies" are especially encouraged.
Summaries (12 copies) must be received by February 4, 1998. Address them to: Lloyd W. Massengill. IEEE/NSREC Technical Chairman, Vanderbilt University, Department of Electrical and Computer Engineering, Room 215 - Jacobs Hall, 400 24th Avenue South, Nashville, TN 37212. Further information may obtained at http://members.iquest.net/~nsrec/call98.htm.
The 1999 Conference on Radionuclide Metrology and its Application organized by the Czech Metrological Institute under the auspices of the International Committee for Radionuclide Metrology (ICRM) will be held in Prague, capital of the Czech Republic, June 7-11, 1999. It will be an opportunity for scientists to present original works and to learn about new developments in metrology of radionuclides. Topics to be covered include:
Contact person: Pavel Dryák, Czech Metrological Institute, Radiova 1, CZ 102 00 Prague, Czech Republic (phone: +420 2 67008244, fax: +420 2 67008466, email: firstname.lastname@example.org).
Your attention is directed to the following events of interest.
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: email@example.com).
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: firstname.lastname@example.org; url; http://www.rpi.edu/~wittej/ansmnc.html).
Regulatory Medical X-Ray Physics, Oct. 20-24, 1997, 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).
Introduction to Medical Dosimetry, Nov. 3-7, 1997, 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).
Nuclear Applications of Accelerator Technology, Nov. 16-20, 1997, Albuquerque, New Mexico, sponsored by the Accelerator Applications Technical Group of the American Nuclear Society. Contact: Dr. L. Warren Funk, AccAPP '97 Tech. Prog. Comm., Westinghouse Savannah River Co., Savannah River Site, 703-45A, Aiken, SC 29808, USA (phone 803-725-2797; fax 803-725-8727; email email@example.com).
International Conference and Exhibition "Plant Life Management and Plant Life Extension in Nuclear Facilities," Dec. 8-10, 1997, Prague, Czech Republic, organized by Nuclear Engineering International. Contact: Alan Wagstaff, Events Manager, Nuclear Engineering International, Wilmington Publishing, Wilmington House, Church Hill, Wilmington, Dartford, Kent, DA2 7EF, UK (phone 44-1322-277788, fax 44-1322-273748).
X-Ray Mammography, Basic Physics and Quality Assurance, Jan. 12-13, 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).
Medical Radiation Safety Physics, Jan. 14, 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).
Diagnostic Medical Physics, Jan. 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).
Radiation Oncology Physics, Jan. 16, 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).
Nuclear Medicine Physics, Jan. 17, 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).
Radiation Safety Officer's Course, Jan. 19-23, 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).
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: firstname.lastname@example.org).
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).
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).
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).
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).
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: email@example.com).
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: firstname.lastname@example.org).
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: email@example.com).
AUGUST 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.
Radiation Shielding Literature
Health Phys., 72, 513-518 . . . Early Dose Assessment Following Severe Radiation Accidents. . . . Goans, R.E.; Holloway, E.C.; Berger, M.E.; Ricks, R.C. . . . April 1997 . . . Oak Ridge Institute for Science and Education, Oak Ridge, TN.
Health Phys., 72, 524-529 . . . Neutron Sources in the Varian Clinac 2100C/2300C Medical Accelerator Calculated by the EGS4 Code. . . . Mao, X.S.; Kase, K.R.; Liu, J.C.; Nelson, W.R.; Kleck, J.H., Johnsen, S. . . . April 1997 . . . Stanford Linear Accelerator Center, Stanford, CA; Varian Associates, Inc., Palo Alto, CA.
Health Phys., 72, 530-543 . . . Neutron RBEs for Cytopenia and Repopulation of Stroma and Hematopoietic Stem Cells: Mathematical Models of Marrow Cell Kinetics. . . . Jones, T.D.; Morris, M.D.; Young, R.W.; Kehlet, R.A. . . . April 1997 . . . Oak Ridge National Laboratory, Oak Ridge, TN; Defense Nuclear Agency, Washington, DC.
Health Phys., 72, 550-557 . . . Loss of Lifetime Due to Radiation Exposure - Averaging Problems. . . . Raicevic, J.J.; Merkle, M.; Ehrhardt, J.; Ninkovic, M.M. . . . April 1997 . . . Institute for Nuclear Sciences "Vinca," Belgrade, Yugoslavia; Electrical Engineering, Belgrade, Yugoslavia; Institut fur Neutronemphysik und Reaktortechnik, Karlsruhe, Germany.
Health Phys., 72, 558-567 . . . Radiation Doses to Critical Groups Since the Early 1950'S Due to Discharges of Liquid Radioactive Waste From Sellafield. . . . Hunt, G.J. . . . April 1997 . . . Fisheries Laboratory, Lowestoft, Suffolk, England.
Health Phys., 72, 568-573 . . . A Computerized Implementation of a Non-Linear Equation to Predict Barrier Shielding Requirements. . . . Chamberlain, A.C.; Strydom, W.J. . . . April 1997 . . . Department of Medical Physics, Medunsa, South Africa.
Health Phys., 72, 574-578 . . . Monte Carlo Simulation of Depth-Dose Distributions in TLD-100 Under 90Sr-90Y Irradiation. . . . Rodriguez-Villafuerte, M.; Gamboa-deBuen, I.; Brandan, M.E. . . . April 1997 . . . Instituto de Fisica, Mexico.
Health Phys., 72, 579-593 . . . Reevaluation of the Committed Dose Equivalent from 232Th and Its Radioactivity Progeny. . . . Lee, D.; Skrable, D.W.; French, C.S. . . . April 1997 . . . Korea Institute of Nuclear Safety, Taejon, Korea; University of Massachusetts, Lowell, MA.
Health Phys., 72, 594-600 . . . Premature Chromosome Condensation Assay for Biodosimetry: Studies with Fission-Neutrons. . . . Prasanna, P.G.S.; Kolanko, C.J.; Gerstenberg, H.M.; Blakely, W.F. . . . April 1997 . . . Armed Forces Radiobiology Research Institute, Bethesda, MD.
Nucl. Technol., 119, 105-111 . . . Two-Group, Flux-Coupled Xenon Oscillation Model with an Equation System of Axial Difference Parameters. . . . Jae Seung Song; Nam Zin Cho . . . April 1997 . . . Korea Advanced Institute of Science and Technology, Taejon, Korea.
Nucl. Technol., 119, 123-140 . . . Advanced Plutonium Fuel Assembly: An Advanced Concept for Using Plutonium in Pressurized Water Reactors. . . . Puill, A.; Bergeron, J. . . . August 1997 . . . Commissariat a l'Energie Atomique, Gif sur Yvette, France.
Nucl. Technol., 119, 141-148 . . . Some Specific Aspects of Homogeneous Americium - and Neptunium-Based Fuels Transmutation Through the Outcomes of the Superfact Experiment in Phenix Fast Reactor . . . Prunier, C.; Boussard, F.; Koch, L.; Coquerelle, M. . . . August 1997 . . . Commissariat a l'Energie Atomique, Saint-Paul-lez-Durance, Cedex, France; European Institute for Transuranium Elements, Karlsruhe, Germany.
Nucl. Technol., 119, 194-200 . . . Melcor Self-Initialization Algorithm for Pressurized Water Reactors and Its Importance in Accident Analysis. . . . Chun-Sheng Chien; Shih-Jen Wang; Te-Chuan Wang . . . August 1997 . . . Institute of Nuclear Energy Research, Taoyuan, Taiwan.
Nucl. Technol., 119, 201-210 . . . Effect of Operating Cycle and Fuel Burnup on Isotopic Composition and Decay Characteristics of Irradiated MTR-Type Low-Enriched Uranium Fuel. . . . Khan, L.A.; Ahmad, N. . . . August 1997 . . . Pakistan Atomic Energy Commission; Islamabad, Pakistan; Centre for Nuclear Studies, Islamabad, Pakistan.
UCRL-ID-127776 . . . A Temperature Dependent ENDF/B-VI, Release 4, Cross Section Library. . . July 1997 . . . Lawrence Livermore National Laboratory, Livermore, CA.
INDC(UKR)-003 . . . Selected Articles Translated From Jadernye Konstanty (Nuclear Constants) Volumes 3-4, 1994. . . June 1997 . . . IAEA Nuclear Data Section, Wagramerstrasse, Vienna, Austria. . . Translated by the IAEA.
ANL/NDM-139 [ENDF-358] . . . The Simultaneous Evaluation of the Standards and Other Cross Sections of Importance for Technology. . . . Poenitz, W.P.; Aumeier, S.E. . . . September 1997 . . . Argonne National Laboratory, Argonne, IL.
Computer Codes Literature
Nucl. Sci. Eng., 126, 239-244 ASYNT
The ASYNT Adjoint Synthesis Method for Neutron Irradiation Assessment of VVER/Pressurized Water Reactor Pressure Vessel. . .Belousov, S.I.; Ilieva, K.D. . .06/97. . .Bulgarian Academy of Sciences, Sofia, Bulgaria.
Nucl. Technol., 119, 158-180 CORFLOW
CORFLOW: A Code for the Numerical Simulation of Free-Surface Flow. . .Wittmaack, R. . .08/97. . .Siemens AG, Erlangen, Germany.