- Progress reports of national programs
- Fuel development
- Fuel testing and evaluation
- Measurements and calculations for converted reactors
- Safety tests and evaluations
- Core conversion studies
- Production of fission Mo-99 from LEU
- Licensing requirements
- HEU and LEU fuel cycle
- Spent fuel transportation and storage
- Utilization of converted (LEU) reactors
- Fission Reactor Shielding
- Accelerator and Target Shielding
- Fusion Reactor Shielding
- Aircraft and Spacecraft Shielding
- Radioactive Waste
- Radiation Protection & Safety
- Fuel Cycle Facility Shielding
- Transportation and Storage of Radioactive Materials
- Decontamination and Decommissioning
- Impact of Radiation and Radioactivity to Environment
- Radiation Applications in Medical and Industrial Uses
- Shielding Calculation--Monte Carlo Methods, Deterministic Methods, Point Kernel and Other Analytical Methods
- Shielding Experiment--Benchmark Experiments, Integral and Mockup Experiments
- Shielding Design
- Methods Verification and Validation
- Visualization and User Interface
- Source Term Evaluation
- Skyshine and and Streaming
- Nuclear Data for Shielding
- Field Characterization
- Radiation Dosimetry
- Radiation Detection and Measurement
- Shielding Materials and Irradiation Effects
- Activation and Induced Radioactivity
- Exposure Evaluation and Protection
Radiation Safety Information
Computational Center
 |
Oak Ridge National Laboratory |
| No. 400 |
April 1998 |
I would not waste the springtime of my youth in idle dalliance; I would plant rich seeds to blossom in my manhood, and bear fruit when I am old.--Hillhouse | |
Electronic Documentation
Since the dawn of history, man has felt the need to instruct and share knowledge through language. Communication by spoken word was augmented by cave drawings, which was followed by drawings and symbols on more portable stone tablets. The key word here is portable. The timely dissemination of information is crucial to science and technology, and what, short of telepathy, could be more portable or timely than the internet. RSICC has committed to providing the documentation for code packages and data libraries in our collection via the internet. Most of the documentation is available in pdf format; a few are available as postscript or text files. If you're not sure a code system or data library meets your requirements and the abstract (available at http://www-rsicc.ornl.gov/ABSTRACTS.html) doesn't provide enough information, you are free to examine the code/data library documentation which can be found at http://www-rsicc.ornl.gov/DOCUMENTS.html. Most of our code and data library contributors now include the documentation with the electronic media they provide and it will be included in the code or data library package.CHANGES TO THE COMPUTER CODE COLLECTION
Five changes or additions were made to the computer code collection during the month. One new code system was packaged and added to the collection, two code systems were replaced with newly frozen versions, a PC version was added to an existing package, and an existing code package was corrected.
Oak Ridge National Laboratory contributed a personal computer version
of this code system to calculate space radiation doses at arbitrary points
inside a space vehicle by performing a numerical angular integration of
dose attenuation kernels about the dose points. In SIGMA-II the kernels
are curve-fit functions constructed from input data. The geometry of the
vehicle, equipment and supplies, and man models are described by
quadric surfaces. Simultaneous dose calculations for multiple vehicle trajectories, each involving
several radiation sources, may be performed for each specified dose point. The calculation may
be a parametric study of dose as a function of shield thickness or an analysis of the dose received
through designated outer sectors of the vehicle.
The PC version was converted from the CDC 6600 release of October 1974. The only changes
made to the code were those required to create an executable using the Lahey F77/L3-EM32
Version 5.2 compiler. The package, which includes Fortran source, executable, and test cases, is
transmitted on one diskette. References: DAC-60878 (November 1967), DAC Memo
A3-830-BBFO-121 (April 1971). Fortran77; PC 486 (C00118/PC486/00).
The Oak Ridge Institute for Science and Education (ORISE), Oak Ridge,
Tennessee, contributed a newly frozen version of this code system to
calculate internal dose estimates by the MIRD technique. MIRDOSE 3.1
allows the user to choose from 28 source organs and calculates the
radiation-absorbed dose to 28 target organs, plus the effective dose and
effective dose equivalent for ten phantoms representing adults, children,
and pregnant women. Several corrections and enhancements to MIRDOSE 3.0 were made in
preparing version 3.1. In the following models, the noted bugs were fixed.
1) There was a bug in the ICRP 30 GI tract model and the dynamic bladder model features that caused radioactive decay to be excluded whenever a setup file including these features was brought in from the disk.
2) The dynamic bladder model did not trap the event in which a radionuclide was not chosen before the dynamic bladder model was invoked, but the program crashed and no harm was done.
3) In the (unlikely) event that only the cortical bone was chosen as a source organ (and not the marrow or trabecular bone), the bone model was not invoked, and no beta component was calculated. So the resultant doses reflected only the photon dose.
Other changes are listed in the information file.
The program is interactive and produces results for most problems on modern PC's in a matter of
seconds. MIRDOSE 3.1 is compiled in Visual Basic, which was used to create the executable
included in this package. The program must be run under the Windows operating system, version
3.1 or higher. The package is transmitted on two diskettes written in DOS format which contain
the executable, data files, and documentation. Reference: ORISE Unpublished Report (December
21, 1994). BASIC; PC 386 (C00528/PC386/01)
Oak Ridge National Laboratory, Oak Ridge, Tennessee, contributed a
correction to this one-, two- and three-dimensional discrete ordinates
neutron/photon transport code system. This correction to DOORS3.2
impacts TORT users who write internal boundary flux files to be used
with TORSET and who then run TORSET and write a sequential file.
DOORS 3.2 includes the most recent versions of CCC-543/TORT-DORT, CCC-254/ANISN-ORNL, CCC-628/GBANISN and CCC-351/FALSTF. It also includes the ISOPLOT code from PSR-155/DOGS and various utility programs previously included in the TORT-DORT package: GIP, ALC, RTFLUM, BNDRYS, GRTUNCL, VISA, TORSED and TORSET. ISOPLOT was modified to use the Sandia National Laboratory RSCORS graphical system. Sandia National Laboratory's CMP system for code maintenance is used to build the Fortran source files for the target computer. Both RSCORS and CMP are distributed with the system.
TORT calculates the flux or fluence of particles due to particles incident upon the system from extraneous sources or generated internally as a result of interaction with the system in two- or three-dimensional geometric systems, and DORT is used in one- or two-dimensional geometric systems. The principle application is to the deep-penetration transport of neutrons and photons. Certain reactor eigenvalue problems can also be solved.
DOORS 3.2 was tested on Cray and workstations running Unix and on PC running Red Hat
Linux. Users of either DOORS3.0, 3.1, or 3.2 may install the updates only file, which may be
downloaded via anonymous ftp (ftp://infosrv1.ctd.ornl.gov/pub/rsic/doors/). The entire package
is transmitted as a UNIX tar file written on either CD, QIC-150 (150 MB), 4-mm DAT (8 GB),
or 8-mm (2.3 GB) cartridge tapes. The tar file contains the Fortran and C source files, test cases,
implementation instructions, procedures, description of sample problem cases, and much of the
referenced documentation. References: ORNL/TM-13221 Draft, ORNL/TM-11778 (March
1992), K-1693 (March 1967), NAA-SR-10951 (March 1966), ORNL/TM-12675 (Jan. 1996),
ORNL/TM-8362 (September 1982), ORNL/TM-12246 (January 1993), ORNL/TM-12359
(August 1993), ORNL/TM-4015 (December 1972), SAND85-0825 (April 8, 1991),
SAND99-XXXX (October 19, 1991). Fortran and C; Cray Unicos, IBM AIX, Sun, DEC OSF/1,
SGI and Hewlett Packard (C00650/MFMWS/03).
Argonne National Laboratory, Argonne, Illinois, contributed the VIM
code system, which solves the steady-state neutron or photon transport
problem in any detailed three-dimensional geometry using either
continuous energy-dependent ENDF nuclear data or multigroup cross
sections. Neutron transport is carried out in a criticality mode, or in a
fixed source mode (optionally incorporating subcritical multiplication).
Photon transport is simulated in the fixed source mode. The geometry options are infinite
medium, combinatorial geometry, and hexagonal or rectangular lattices of combinatorial
geometry unit cells, and rectangular lattices of cells of assembled plates. Boundary conditions
include vacuum, specular and white reflection, and periodic boundaries for reactor cell
calculations. VIM uses standard Monte Carlo methods for particle tracking with several optional
variance-reduction techniques.
VIM 3.6 runs on IBM and Sun workstations. At RSICC the system was successfully tested on
IBM RS/6000 model 590 under AIX 4.2 with XLF77 version 3.2.2 and on Sun Sparc 20 running
SUNOS 5.6 (Solaris 2.6) with f77 version 4.2. The package is transmitted on either a CD or tape
cartridge as a compressed tar file which contains installation instructions, the User's Guide,
Fortran source, and test cases. References: Argonne National Laboratory Report (Unpublished).
Fortran 77; Sun, IBM RS/6000 (C00658/MNYWS/00).
Los Alamos National Laboratory, Los Alamos, New Mexico, contributed
a newly frozen version, designated Version gn9cp0, of this
pre-equilibrium, statistical nuclear-model code system for calculation of
cross sections and emission spectra. In this 1998 release improvements
were made in the accuracy of the exciton model and other calculations,
and provision was made for including energy-dependent renormalization
of the reaction cross section and energy-dependent exciton model parameterization (for data
evaluation purposes). The GNXS code is included to analyze decay chains, retrieve cross sections
and spectra, and make various ENDF-6 formatted files from GNASH output. GNASH provides a
flexible method by which reaction and level cross sections, isomer ratios, and emission spectra
(neutron, gamma-ray, and charged-particle) resulting from particle- and photon-induced reactions
can be calculated. The new release runs on Sun Ultra and Sun Sparcstations. The package is
transmitted on one diskette, which contains the source code, data libraries, sample problem input
and output in a GNU compressed tar file. Reference: Los Alamos National Laboratory report to
be published. Fortran 77; Sun (P00125/SUN05/00).
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 raf@ornl.gov.
The Second International Topical Meeting on Nuclear Applications of Accelerator Technology (AccApp'98) is sponsored by the Accelerator Applications Technical Group of the American Nuclear Society (ANS), and is hosted by the Oak Ridge-Knoxville, Tennessee, USA Section of the ANS. It will be held in Gatlinburg, Tennessee, during the week of September 20-23, 1998, at the Park Vista Hotel & Conference Center.
AccApp'98 will provide a forum for discussion of the uses of particle accelerator technology for nuclear applications. It will focus on production of neutrons and other particles, utilization of these particles for scientific or industrial purposes, production or destruction of radionuclides significant to energy, medicine, defense, or other endeavors, as well as imaging and diagnostics.
Papers are solicited in the following areas: applications, design, R&D needs, analytical methods,
tools and databases, economics, safety and licensing. The Call For Papers with all relevant
information and points of contact is located at http://www.engr.utk.edu/org/ans/AccApp98.
21st RERTR, Call For Papers
The 21st International Meeting on Reduced Enrichment for Research and Test Reactors (RERTR) will be held October 18-23, 1998, in São Paulo, Brazil. Information will be exchanged on the progress of national and international programs to develop low enriched fuels for research and test reactors and to convert the reactors to such fuels. This meeting is organized by the Institute of Research and Development Directorate of the Brazilian Nuclear Energy Commission (CNEN) (IPEN) in cooperation with the International Atomic Energy Agency, Argonne National Laboratory, the Brazilian Nuclear Energy Commission, the Brazilian Association for Nuclear Energy (ABEN), and other sectors of the Brazilian nuclear energy industry. Topics to be covered during the meeting are:The language of the meeting will be English with no simultaneous translation provided. Those
who wish to present a paper at the meeting should send an abstract of the paper, as soon as
possible, but not later than August 1, 1998. Further information about the meeting is available
from Dr. José Rubens Maiorino, Chairman 1998-RERTR Meeting, Comissão Nacional de
Energia Nuclear, Instituto de Pesquisas Energéticas e Nucleares, Diretoria de Reatores, Travessa
R 400 - Cidade Universitária- CEP: 05508-900, São Paulo - SP - Brazil (phone (55-11)
816-9111, fax (55-11) 816-9432, email: rertr98@net.ipen.br), or please visit the webpage at url
http://www.ipen.br/r/rertr/rertr.html).
Abstracts of 400 words should be sent by the end of January 1999. Notification of acceptance
will be made by the end of March 1999. A full paper should to be sent to Program Secretary by
the end of July 1999. Manuscripts for both abstracts and papers should be sent via Web or as an
electronic file with attached text files. The proceedings will be distributed on CD at the
conference. Detailed information about the conference may be obtained from Yujiro Ikeda, Japan
Atomic Energy Research Institute, Tokai Research Establishment, Neutron Science Research
Center, Spallation Neutronics Laboratory, Tokai-mura, Naka-gun, Ibaraki-ken 319-11 Japan
(phone 81-29-282-6074, fax 81-29-282-5709, email keda@fnshp.tokai.jaeri.go.jp) or from the
web page at http://icrs9.tokai.jaeri.go.jp.
Calendar
Your attention is directed to the following events of interest.
May 1998
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).
Computational Methods in Reactor Analysis and Shielding, May 18-22, 1998, Knoxville,
Tennessee, a short course offered by the University of Tennessee-Knoxville. Contact: Lydia
Salmon, Dept. of Nuclear Engineering, University of Tennessee, Knoxville, TN 37996 (phone
423-974-2525; email lsalmon@utk.edu).
Nuclear Criticality Safety, May 18-22, 1998, Knoxville, Tennessee, a short course offered by the
University of Tennessee-Knoxville. Contact: Lydia Salmon, Dept. of Nuclear Engineering,
University of Tennessee, Knoxville, TN 37996 (phone 423-974-2525; email lsalmon@utk.edu).
Monte Carlo Analysis, May 18-22, 1998, Knoxville, Tennessee, a short course offered by the
University of Tennessee-Knoxville. Contact: Lydia Salmon, Dept. of Nuclear Engineering,
University of Tennessee, Knoxville, TN 37996 (phone 423-974-2525; email lsalmon@utk.edu).
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).
Practical MCNP for the HP, May 18-22, 1998, University of New Mexico-Los Alamos Campus.
Contact Dick Olsher, 505-667-3364, e-mail: dick@lanl.gov.
SAMO 98: Second International Symposium on Sensitivity Analysis of Model Output, May
19-22, 1998, University of Venice, Dorsoduro 3825, 30123 Venezia, Italy. Contact: Mrs. Dorit
Schlittenhardt, Public Relations and Publications Unit - JRC Ispra Site, TP 020, 21020 Ispra
(VA) Italy (phone 39 332 789370, fax: 39 332 785409, email dorit.schlittenhardt@jrc.org, web
http://www.jrc.org/isis/sa/events/samo98/).
Methodologies For Particle Transport Simulation and Their Application to Reactor Dosimetry/
Shielding, May 25-29, 1998, SCK/CEN, Mol, Belgium. Contact: Prof. Ali Haghighat, Penn State
University, Nucl. Eng. Dept., 231 Sackett Building, University Park, PA 16802 (phone
814-865-0039, fax 814-865-8499, email: http://haghigha@transport.nuce.psu.edu/).
June 1998
Radiation Safety Officer, June 8-12, Las Vegas, Nevada, a Technical Short Course offering of
Nevada Technical Associates. Contact: Nevada Technical Associates, Inc., P.O. Box 90748,
Henderson, NV 89009 (phone 702-564-2798; fax 702-558-7672).
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: broadway@strudel.aum.edu).
ICENES '98, Emerging Nuclear Energy Systems, June 28-July 2, 1998, Tel-Aviv, Israel. Contact:
Conference Secretariat, Dan Knassim Ltd., P.O. Box 1931, Ramat Gan 52118, Israel (phone
972-3-6133340, fax 972-3-6133341, email congress@mail.inter.net.il, web
http://icenes98.simplenet.com/).
July 1998
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: hpsburkmgt@aol.com).
September 1998
AccApp'98, Sept. 20-23, 1998, Gatlinburg, Tennessee, sponsored by the Oak Ridge-Knoxville,
TN, USA Section of the ANS. Contact: Dr. John Haines, Chairman, AccApp '98 Technical
Program Committee, Oak Ridge National Laboratory, Oak Ridge, TN 37831-8071, USA (phone
423-574-0966, fax: 423-576-7926, email: hainesjr@ornl.gov, or
http://www.engr.utk.edu/org/ans/AccApp98).
Training Course on the Use of MCNP in Radiation Protection and Dosimetry, Sept. 28-1 Oct.
1998, at the Imperial College of Science, Technology and Medicine, London. Contact: Robert
Alan Price, Imperial College of Science, Technology and Medicine, T. H. Huxley School of the
Environment, Earth Sciences and Engineering, Applied Modelling and Computation Group,
Centre for Environmental Technology, Room 405, Royal School of Mines Building, Prince
Consort Rd, London SW7 2BP, UK (phone 44 171 594 9323, fax 44 171 594 9341, url
http://wrench.et.ic.ac.uk/courses/).
November 1998
Radiation Safety Officer, Nov. 2-6, 1998, Las Vegas, Nevada, a Technical Short Course offering
of Nevada Technical Associates. Contact: Nevada Technical Associates, Inc., P.O. Box 90748,
Henderson, NV 89009 (phone 702-564-2798; fax 702-558-7672).
April 1999
First Latin American Symposium on Nuclear Tracks and Radiation, April 5-9, 1999, Caracas,
Venezuela, Institute for Advanced Studies, Convention Centre. Contact: Professor Laszlo Sajo,
Universidad Simon Bolivar, FE-1, Apdo 89000, Caracas, Venezuela, (phone 58-2- 906- 3590,
FAX 58- 2 -906-3712, email: lsajo@fis.usb.ve)
June 1999
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: pdryak@cmi.cz).