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
BitNet: PDC@ORNLSTC Internet: PDC@ORNL.GOV
376 March 1996
The SCALE staff at ORNL will be offering several training courses in 1996. The courses will be taught by the staff of the ORNL Computational Physics and Engineering Division, who are responsible for the development and maintenance of the SCALE code system. The courses emphasize hands-on experience solving practical problems on PCs or Unix workstations in small workgroups. No prior experience in the use of SCALE is required to attend any of these courses.
|Date||Title||Description||Location||May 21 - 23
||In-depth introduction to new
KENO-VI code for complex
||ORNL||July 1 - 5
||SCALE Criticality &
||Overview of CSAS/KENO V.a,
|Stuttgart, Germany||Oct. 15 - 18
||SCALE Criticality Course
||In-depth introduction to
(May be combined with the following Shielding Course)
|ORNL||Oct. 21 - 24
||SCALE Shielding Course
||In-depth introduction to SAS1,
SAS2/ORIGEN-S, SAS4/MORSE, |
Classes are limited to 24 participants and are subject to cancellation if minimum enrollment is not obtained. Course fees range from $1200 - $2000. Course fees are refundable up to one month before each class. For further information, contact Steve Bowman,
Three changes were made to the computer collection during the month. Two existing code packages were updated to improve performance, and an existing code package was replaced with a newly frozen version.
OP SYS: UNIX, DOS
Language: Fortran 77, C
Computers: PC, workstation
Format: DOS, tar
| Oak Ridge National Laboratory, Oak Ridge, Tennessee,
updated the PC version of this modular code system for performing
standardized computer analyses for licensing evaluation for UNIX
workstations and personal computers. Several source files and
executables in the package were updated with modifications which
allow them to run under both Windows95 and WindowsNT Vers. 3.51
for workstation. All modules now run under either DOS 6, Windows
3.1, Windows95, or WindowsNT except for the GIF related graphics
processors which do not run under WindowsNT or Windows 3.1. PC
users who have already received the package may contact RSIC to get
the updated files which are available on three 1.44 DS/HD 3.5-in.
diskettes in self-extracting compressed DOS files. No modifications
were made to the Unix version. 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 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 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. Executables included in the initial 4.3 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. The executables added in this update were linked under Windows95. Included in both packages are documentation files written in either WordPerfect 5.1 or 6.1 format on CD-ROM.
Workstation version: includes source codes, binary data libraries, makefiles, scripts, and sample problem input and output, transmitted in a UNIX compressed tar file on either cartridge tape or CD-ROM, plus OFFSCALE, ORIGNATE, and README in DOS format. Thermal codes (HTAS1, HEATING 7, OCULAR) are included in the UNIX package but are NOT included in the PC package.
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. ORIGEN-ARP is distributed only with the PC version. 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/PC486/01).
OP SYS: DOS
Language: Fortran 77
Computers: PC 386
| Oak Ridge National Laboratory contributed two updated PC
versions of this nuclear reactor analysis code system called CITATION-PC and CITALDI-PC. CITATION 2.0 is designed to solve problems
using the finite difference representation of neutron diffusion theory
treating up to three space dimensions with arbitrary group-to-group
scattering. The x-y-z, theta-r-z, hexagonal z, and triagonal z geometries
may be treated. Depletion problems may be solved and fuel managed
for multi-cycle analysis. Extensive first order perturbation results may
be obtained given microscopic data and nuclide concentrations.
Statistics problems may be solved and perturbation results obtained with
microscopic data. This version of CITATION was released by ORNL as
CITATION - Rev. 2, Supplement 3 in July 1972 and ran on
mainframes. It was frist ported to PC by AECL in October 1988.
CITATION-PC in this release incorporated minor changes includng the
removal of overlay statements introduced in 1988. CITALDI-PC is a
new modified version with list-directed input.|
The codes run on personal computers equipped with an 80386 processor or better. The executables were created with the Lahey Fortran V5.1 and 5.2 compilers under DOS 6.22. They can be run in a DOS window of Windows95. At least 578 kB RAM must be available to run the executables included in the package. The package which includes source, executables, and test cases is transmitted on two 1.44 DS/HD 3.5-in. diskettes in self-extracting compressed DOS files. No cross sections are included. References: Informal notes (1996) and ORNL-TM-2496, Rev. 2 (July 1971). Fortran; PC 386 (C00643/PC386/00).
OP SYS: AIX
Computers: IBM RISC 6000
| Oak Ridge National Laboratory contributed a newly frozen version
K1 of the SAMMY code system for multilevel R-matrix fits to neutron
data using Bayes' equations. This version differs from the previous
version (H1) primarily in that the input/output protocols for the
temporary files were modified with concomitant modifications in the
array-storage system. Users should notice this only via the resultant
increase in execution speed. Improvements include the incorporation of
self-shielding and multiple-scattering corrections in the calculation of
capture yields. Other additions include the abilities to fit differential
elastic angular distributions, to calculate Maxwellian (stellar) averages
for capture cross sections, and to reconstruct point-wise cross sections
on an automatically generated energy grid. |
The system runs on the IBM RS/6000 and has been ported to DEC Alpha computers under both Open/VMS and OSF1 operating systems. Virtually no changes were required in the FORTRAN. SAMMY-K1 is transmitted in compressed tar format on either a CD-ROM or cartridge tape. References: ORNL/TM-9179 (Aug. 1984), /R1 (July 1985), /R2 (June 1989), and Rev. 3 (Draft Feb. 1996).
One change was made to the data library collection during the month. A new data library was packaged and added to the collection.
OP SYS: Any
|ORNL has contributed a revised multigroup cross-section library based
on ENDF/B-VI Release 3 for LWR shielding and reactor pressure
vessel dosimetry applications. This new broad group library (47n,20g),
which is designated BUGLE-96, represents an improvement over the
BUGLE-93 library released in February 1994 and replaces that data.
The cross-section processing methodology is the same as that used for
producing BUGLE-93 and is consistent with ANSI/ANS 6.1.2. As an
added feature cross-section sets having upscatter data for four thermal
neutron groups are included in the BUGLE-96 package. The
upscattering data should improve the appication of this library to the
calculation of more accurate thermal fluences, although more computer
time will be required. The incorporation of feedback from users has
resulted in a data library that addresses a wider spectrum of user needs.|
The new package consists of four sets of data. BUGLE-96 is a complete replacement for all files previously contained in DLC-175/BUGLE-93. Above the thermal region, BUGLE-96T contains the same cross section data as BUGLE-96 with the thermal upscattering cross sections retained. SAILOR-96 contains the same cross sections as BUGLE-96 with the ANISN identifiers arranged to be plug compatible with the DLC-76/SAILOR data package. SAILOR-96T contains the same cross sections as BUGLE-96T with the ANISN identifiers arranged to be plug compatible with DLC-76/SAILOR. The BCBN Fortran program is included to read the formatted ANISN records and write them as unformatted records. The package is available in compressed Unix tar files on either CD-ROM, DC 6150 (150 MB), 4-mm DAT (8GB), or 8-mm (2.3)GB cartridge tapes. Reference: NUREG/ CR-6214 (January 1995) and ANS Topical Meeting presentation (April 21-25, 1996). Fortran 77; All Computers (D00185/ALLCP/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 2nd International ARS'97 will be held June 1-4, 1997, in Orlando, Florida. The conference is sponsored by the Nuclear Reactor Safety Division of the American Nuclear Society (ANS) with several co-sponsors (ANS, KNS, AESJ, U.S. Department of Energy , IAEA) with pending co-sponsorship by ENS & OECD/NEA and is hosted by the Oak Ridge-Knoxville, Tenn., USA section of the ANS.
The conference will be an embedded topical meeting in conjunction with the summer annual ANS conference of 1997. ARS'97 has the objective to bring together worldwide experts to discuss recent findings and experiences related to enhancing safety, and regulatory compliance for timely certification, licensing and operation of next generation power and nonpower nuclear facilities. Papers are solicited in the following areas covering design, R&D needs, analytical methods and criteria, economics, and key safety and licensing issues:
Dr. Rusi P. Taleyarkhan
The Department of Nuclear Engineering at the University of Tennessee-Knoxville is offering three five-day short courses of interest to radiation transport specialists during Tennessee Industries Week (TIW-31), August 12-16, 1996.
Computational Methods in Reactor Analysis and Shielding -- Engineers, scientists, and technical managers who wish to increase their knowledge and understanding of the computational methods and computer codes currently used in nuclear reactor analysis and shielding will be interested in this intensive one-week short course. A good understanding of the models and associated numerical methods is essential for the successful use of the codes in designing new systems or improving the performance and safety of existing systems.
Areas to be covered include multidimensional diffusion theory methods and perturbation theory methods for applications in reactor statics, space-dependent kinetics, and fuel depletion; transport theory methods including the discrete ordinates method, integral transport theory, and the Monte Carlo method; and cross section generation and processing utilizing the AMPX and SCALE systems developed at the Oak Ridge National Laboratory.
Special emphasis in the course is placed on the Monte Carlo method because of its widespread use and importance for nuclear system analysis brought about primarily by the increased availability of high performance workstations. The course ends at noon on Friday.
Monte Carlo Analysis -- Monte Carlo is often the method of choice to solve complex problems in radiation shield design. The transport analyst must often choose between Monte Carlo and deterministic methods like discrete ordinates; or the nature of the design problem may dictate that he perform a coupled
(Monte Carlo/discrete ordinates) calculation. Therefore, to use Monte Carlo and other transport methods effectively, the analyst must understand the theoretical and computational fundamentals. Rather than use an existing program, it is sometimes advantageous to create a new special-purpose Monte Carlo program. The procedures that are involved in preparing a user-written Monte Carlo program will be described in terms of the classical and conceptually simple straight-ahead, one-speed, slab transmission problem.
Many advanced topics will be included that will permit optimum use of existing computer codes such as MORSE and MCNP. Special attention will be given to the understanding of the adjoint calculation. New topics involving the biased adjoint Monte Carlo calculation will be presented.
In addition, a generalized albedo option for the MORSE code will be described. This version employs albedos having a spatially-dependent point-of-emergence and permits an adjoint analysis when using the albedo option. Advantages and disadvantages of the adjoint mode versus the forward mode of analysis will be described. The full range of variance reduction techniques will be studied for both forward and adjoint calculations.
The Monte Carlo method offers the expectation that the true solution to the problem as modeled can be achieved. However, this may lead to a false sense of credibility - in particular when calculations are performed by relatively inexperienced users (the majority of people who use the Monte Carlo method do so only occasionally). Monte Carlo calculations are subject to major errors and/or misinterpretations because currently used statistical measures may be insufficient. Other methods for statistically characterizing Monte Carlo methods will be described. Some of these methods have been incorporated into an experimental version of the MORSE code. The modifications will be described along with descriptions of problems which are subject to undersampling.
The relationship of the Monte Carlo method to the other transport methods such as discrete ordinates will be described, including comparisons of computational advantages and disadvantages. The MORSE and MCNP computer codes will be described as required to illustrate the general features of large Monte Carlo computer programs. This course ends at noon on Friday.
Nuclear Criticality Safety -- Engineers, scientists, and technical managers who wish to increase their knowledge and understanding of nuclear criticality safety will be interested in this intensive one-week short course. The topics covered in the course are based primarily on the experience of the six instructors which totals over 130 years of nuclear criticality safety related experience. Such a wealth of experience needs to be shared with the criticality safety community including both new professionals in the field as well as experienced professionals.
The course topics include illustrative applications using the SCALE system developed at the Oak Ridge National Laboratory with emphasis on the Monte Carlo code KENO Va, standards, regulations, review of accidents, hand calculation methods, subcritical limits, code validation techniques, emergency response, process upsets and recovery actions, and transient excursion modeling. The course ends at noon on Friday.
The registration fee is $1195 per person for each course. The deadline for registration in these three courses is July 31, 1996. For additional information contact T. W. Kerlin, Head of the Dept. of Nuclear Engineering, University of Tennessee, Knoxville, TN 37996 (phone 423-974-2525).
Your attention is directed to the following events of interest.
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).
11th KAIF/KNS Annual Conference, Apr. 11-12, 1996, Seoul, Korea. Contact: KAIF (phone 82-2-785-2570; fax 82-2-785-3975).
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.
Applied Health Physics, April 15-May 17, 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).
2nd North-West Europe Conference on Nuclear Physics, Apr. 16-19, 1996, Amsterdam, The Netherlands. Contact: G. van der Stoenhoven (phone 31-20-592-2142; fax 31-20-592-2165; email firstname.lastname@example.org).
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 email@example.com).
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).
9th International Symposium on Reactor Dosimetry, Apr. 22-26, 1996, Prague, Czech Republic. Contact: K. Dach (fax 42-2-612-10325).
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).
6th International Radiopharmaceutical Dosimetry Symposium, May 7-10, 1996, Gatlinburg, Tennessee. Contact: Audrey T.S.-Stelson, Program Committee, Radiopharmaceutical Dosimetry Symposium, Radiation Internal Dose Information Center, EHSG, Oak Ridge Institute for Science and Education, P.O. Box 117, Oak Ridge, TN 37831-0117 (phone 423-576-3450; fax 423-576-8673).
Training Course on "The Use of MCNP in Radiation Protection and Dosimetry," May 13-16, 1996, Bologna, Italy. Contact: Dr. Gianfranco Gualdrini, ENEA/AMB-IRP, Via dei Colli 16, I-40136 Bologna, Italy (phone: 39-51-609-8350; fax: 39-51-609-8348; e-mail: firstname.lastname@example.org).
Radiation Safety Principles, May 13-16, 1996, Raleigh, North Carolina, a short course offered by North Carolina State University. Contact: Joni Tanner, North Carolina State University, Box 7401, Raleigh, NC 27695-7401 (phone 919-515-8171; fax 919-515-7614).
Symposium on Acceptability of Risk from Radiation -- Application to Manned Space Flight, May 29, 1996, Arlington, Virginia, sponsored by the National Council on Radiation Protection and Measurements (NCRP). Contact: Laura Atwell, NCRP (301-657-2652).
2nd International Conference on Accelerator-Driven Transmutation Technologies and Applications, June 3-7, 1996, Kalmar, Sweden. Contact: Mr. Inger Ericson, Dept. for Radiation Sciences, Uppsala University, Box 535, S-751 21 Uppsala, Sweden (phone 46-18-183848, fax 46-18-183833; email email@example.com).
ENS Class 1 Topical Meeting on Research Facilities for the Future of Nuclear Energy, June 4-7, 1996, Brussels, Belgium. Contact: Mr. Jean-Marie Baugnet, CEN-SCK, Boeretang 200, B-2400 Mol, Belgium (phone 32-14-332412; fax 32-14-320513), or Mr. Hamid Ait Abderrahim, CEN-SCK, Boeretang 200, B-2400 Mol, Belgium (phone 32-14-332277; fax 32-14-321529; email firstname.lastname@example.org).
5th International Conference on Applications of Nuclear Techniques,--Neutrons in Research and Industry, June 9-15, 1996, Crete, Greece. Contact: George Vourvopoulos, Dept. of Physics, Western Kentucky University, Bowling Green, KY 42101 (phone 502-745-5277; fax 502-745-5062; email email@example.com) or Themis Paradellis, INP Demokritos, GR-15310, Aghia Paraskevi, Greece (phone 1-6518770; fax 1-6511215; email firstname.lastname@example.org)
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).
Environmental Monitoring, June 10-14, 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).
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. 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 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).
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 email@example.com).
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 firstname.lastname@example.org).
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 email@example.com).
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 firstname.lastname@example.org).
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 email@example.com).
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 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).
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.
Nucl. Technol., 113, 190-203 . . . A Set of Integrated Environmental Transport and Diffusion Models for Calculating Hazardous Releases. . . . Pepper, D.W.; Marino, J.A. . . . February 1996 . . . University of Nevada-Las Vegas, Las Vegas, NV; Applied Graphic Solutions, Moorpark, CA.
Nucl. Technol., 113, 204-221 . . . On the French Project Developed in the 1980s for the Production of 99Mo from the Fission of 235U. . . . Bourges, J.; Madic, C.; Koehly, G.; Nguyen, T.H.; Baltes, D.; Landesman, C.; Simon, A. . . . February 1996 . . . Commissariat a l'Energie Atomique, Fontenay-aux-Roses, Cedex, France.
Nucl. Technol., 113, 316-326 . . . Sensitivity of the Radionuclide Release from a Repository to the Variability of Materials and Other Properties. . . . Romero, L.; Moreno, L.; Neretnieks, I. . . . March 1996 . . . Royal Institute of Technology, Stockholm, Sweden.
Health Phys., 3, 394-395 . . . Sensible Radiation Protection. . . . Rossi, H.H. . . . March 1996.
Health Phys., 70, 318-335 . . . A Dynamic Model for Evaluating Radionuclide Distribution in Forests from Nuclear Accidents. . . . Schell, W.R.; Linkov, I.; Myttenaere, C.; Morel, B. . . . March 1996 . . .University of Pittsburgh, Pittsburgh, PA; Universite Catholique de Louvain, Louvain-la-neuve, Belgium; Carnegie Mellon University, Pittsburgh, PA.
Health Phys., 70, 336-345 . . . An Approach to Evaluating Bias and Uncertainty in Estimates of External Dose Obtained from Personal Dosimeters. . . . Gilbert, E.S.; Fix, J.J.; Baumgartner, W.V. . . . March 1996 . . . Pacific Northwest Laboratory, Richland, WA.
Health Phys., 70, 388-393 . . . Ten Principles and Ten Commandments of Radiation Protection. . . . Strom, D.J. . . . March 1996 . . . Pacific Northwest National Laboratory, Richland, WA . . . . . . Presented at the 40th Annual Meeting of the Health Physics Society, Boston, MA, 1995.
Health Phys., 70, 207-214 . . . Giant Dipole Resonance Neutron Yields Produced By Electrons as a Function of Target Material and Thickness. . . . Xiaotian Mao; Kase, K.R.; Nelson, W.R. . . . February 1996 . . . Stanford Linear Accelerator Center, Stanford University, Stanford, CA.
Health Phys., 70, 227-237 . . . Analysis of Models Assessing the Radionuclide Migration from Catchments to Water Bodies. . . . Monte, L. . . . February 1996 . . . ENEA Casaccia, Roma, Italy.
E3-95-282 . . . Monte Carlo Simulation of Spectral Filters for Ultracold Neutrons. . . . Muzychka, A.Y.; Pokotilovski, Y.N. . . . 1995.
E3-95-251 . . . Monte Carlo Calculation of the Slow Neutron Background in the Neutron-Neutron Scattering Experiment at the Pulse Reactor BIGR. . . . Budnik, A.D.; Ososkov, G.A.; Pokotilovski, Y.N.; Rogov, A.D. . . . 1995.
NCRP REPORT No. 122 . . . Use of Personal Monitors to Estimate Effective Dose Equivalent and Effective Dose to Workers for External Exposure to Low-Let Radiation. . . . . . . December 1995 . . . National Council on Radiation Protection and Measurements, Bethesda, MD.
NCRP REPORT No. 121 . . . Principles and Application of Collective Dose in Radiation Protection. . . . . . . November 1995 . . . National Council on Radiation Protection and Measurements, Bethesda, MD.
DESY D3-82 . . . Neutron Dosimetry at High Energy Accelerators. . . . Dinter, H.; Racky, B.; Tesch, K. . . . January 1996 . . . Deutsches Elektronen-Synchrotron DESY, Hamburg, Germany. . . . . . . to be published.
INDC(BLR)-002 . . . Evaluation of Neutron Data for Curium-243. . . . Maslov, V.M.; Sukhovitskji, E.S.; Porodzinskij, Y.V.; Klepatskij, A.B.; Morogovskij, G.B. . . . December 1995 . . . Radiation Physics & Chemistry Problems Institute, Belarus, CIA.
INDC(NDS)-324 . . . The Nuclear Data Centers Network. . . . Lemmel, H.D., ed. . . . August 1995 . . . IAEA Nuclear Data Section, Vienna, Austria.
INDC(NDS)-328 . . . Development of an International Nuclear Decay Data and Cross-Section Database. . . . Lemmel, H.D., ed. . . . December 1994 . . . IAEA Nuclear Data Section, Vienna, Austria . . . . . . Summary Report of an IAEA Specialists Meeting, Vienna, 24-28 October 1994.
INDC(NDS)-329 . . .
Papers Presented at the IAEA Specialists' Meeting on the Development of an International Nuclear Decay Data and Cross-Section Database. . . . Lemmel, H.D., ed. . . . December 1994 . . . IAEA Nuclear Data Section, Vienna, Austria . . . . . . Vienna, 24-28 October 1994.
INDC(NDS)-340 . . . Activation Cross Sections for the Generation of Long-Lived Radionuclides of Importance in Fusion Reactor Technology. . . . . . . November 1995 . . . IAEA Nuclear Data Section, Vienna, Austria . . . . . . Summary Report of the Third IAEA Research Coordination Meeting organized by the IAEA in co-operation with the V. G. Khlopin Radium Institute, St. Pete.
INDC(CCP)-389 . . . Neutron Radiative Capture Cross-Sections for the 232Th and 197Au Nuclei in the 0.37-1 MeV Region. . . . . . . December 1994 . . . Institute of Physics and Power Engineering, Obninsk, Kaluga Region, Russia . . . . . . Translated from Jadernye Konstanty 1993/1 p. 13-16.
INDC(CCP)-390 . . . Neutron Radiative Capture Cross-Sections for Even Isotopes of Neodymium in the Energy Range from 0.5 to 2.2. MeV. . . . Trofimov, Y.N. . . . December 1994 . . . V.G. Khlopin Radium Institute, St. Petersburg, Russia. . . . . . . Translated form Jadernye Konstanty 1993/1 p.17-21.
INDC(CCP)-391 . . . Evaluation of Thermal Neutron Cross-Sections and Resonance Integrals of Protactinium, Americium, Curium, and Berkelium Isotopes. . . . Belanova, T.S. . . . December 1994 . . . Institute of Physics and Power Engineering, Obninsk, Kaluga Region, Russia . . . . . . Translated from Jadernye Konstanty 1993/1 p. 22-42.
INDC(CCP)-392 . . . Compilation of Leakage Neutron Spectrum Measurements for Spherical Assemblies with T(d,n) and 252Cf Neutron Sources. . . . Simakov, S.P. . . . December 1994 . . . Institute of Physics and Power Engineering, Obninsk, Kaluga Region, Russia . . . . . . Translated from Jadernye Konstanty 1993/1 p. 43-51.
INDC(CCP)-393 . . . Evaluation of Photonuclear Reaction Cross-Sections Using the Reduction Method for Large Systematic Uncertainties. . . . Varlamov, V.V.; Efimkin, N.G.; Ishkhanov, B.S.; Sapunenko, V.V. . . . December 1994 . . . Scientific Research Institute for Nuclear Physics, Moscow State University, Moscow, Russia . . . . . . Translated form Jadernye Konstanty 1993/1 p. 52-69.
INDC(CCP)-395 . . . The Russian Nuclear Data Research Programme. . . . . . . 1995 . . . Institute of Physics and Power Engineering, Obninsk, Kaluga Region, Russia . . . . . . Atomic Energy Ministry of the Russian Federation.
INDC(CCP)-399 . . . Selected Articles Translated from Jadernye Konstanty (Nuclear Constants) Volume 2, 1993 and Volumes 1 and 2, 1994. . . . . . . December 1995 . . . IAEA Nuclear Data Section, Vienna, Austria . . . . . . Translated by the IAEA.
ORNL/NRC/LTR-96/2 . . . Review of the Potential Use of Monte Carlo Techniques for Pressure Vessel Fluence Analysis. . . . Remec, I. . . . January 1996 . . . Oak Ridge National Laboratory, Oak Ridge, TN.
CDTN, 434-438 MICRAS
Use of MICRAS Code on the Evaluation of the Maximum Radionuclides Concentrations Due to Transport/Migration of Decay Chain in Groundwaters.. . . .Aquino-Branco, O.E.. . . .1995. . . .Library of Comissao Nacional de Energia Nuclear, Brazil. . . .Centro de Desenvolvimento da Technologia Nuclear (CDTN), Brazil. . . . (In Portuguese).
HYGODG 14, 296-301 RETRAN02
Modification of RETRAN02 and Its Conversion to CDC NOS/VE System.. . . .Gao Zuying; Gao Cheng; Chen Xinming; Zhang Zouyi; He Junxiao. . . .12/94. . . .Qinghua University, Beijing, China. . . . (In Chinese).
YODIEX, 1, 32-36 GEOCHEMICAL
Geochemical Modelling Code: Case Studies.. . . .Shi Weijun; Zhou Wenbin; Jin Limin. . . .1995. . . .East China Geological Inst., Fuzhou, China. . . . (In Chinese).
BNL-NUREG-49018; CONF-940518-1 MELCOR
Independent Assessment of MELCOR as a Severe Accident Thermal-Hydraulic/Source Term Analysis Tool.. . . .Madni, I.K.; Eltawila, F.. . . .1994. . . .OSTI; NTIS; INIS; GPO. . . .Brookhaven National Laboratory, Upton, NY. . . . International Conference on Nuclear Systems Thermal Hydraulics, Pisa, Italy 30 May - 2 June 1994.
NUREG/CR-6107; SAND-93-2042 MELCOR 1.8.2
Summary of MELCOR 1.8.2 Calculations for Three LOCA Sequences (AG, S2D, and S3D) at the Surry Plant.. . . .Kmetyk, L.; Smith, L.. . . .1994. . . .OSTI; NTIS; INIS; GPO. . . .Sandia National Labs., Albuquerque, NM; Nuclear Regulatory Commission, Washington, DC.
SAND-93-1899 MELCOR 1.8.2
MELCOR 1.8.2 Assessment: Surry PWR TMLB' (with a DCH Study).. . . .Kmetyk, L.N.; Cole, R.K.; Smith, R.C.; Summers, R.M.; Thompson, S.L.. . . .02/94. . . .OSTI; NTIS; INIS; GPO. . . .Sandia National Labs., Albuquerque, NM.
Air Ingression Calculations for Selected Plant Transients Using MELCOR.. . . .Kmetyk, L.N.. . . .01/94. . . .OSTI; NTIS; INIS; GPO. . . .Sandia National Labs., Albuquerque, NM.