Radiation Safety Information Computational Center

Oak Ridge National Laboratory
Post Office Box 2008 Oak Ridge, Tennessee 37831-6362
managed by Lockheed Martin Energy Research Corp.
for the U.S. Department of Energy
Phone No. 423-574-6176
FAX 423-574-6182
WWW: http://epicws.epm.ornl.gov

No. 384 November 1996

The very essence of all power to influence lies in getting the other person to participate. The mind that can do that has a powerful leverage on his human world.---
Harry A. Overstreet

Please file this ......

Paper will always be with us which makes it necessary to file and retrieve documents in a timely and efficient manner. With the great increase in electronic correspondence it has become necessary to remind our clients that we need essential information included with any correspondence (fax or email) that may not include your company letterhead. The following are some examples of our dilemma. The following email addresses, as email addresses tend to be, are rather cryptic and require additional detective work to find where they belong.

From: Erin Rogozinski <erin@sq.com>
From: "Wang,Steve" <SWANG@cerner.com>
From: "WM Symposia, Inc." <wmsym@basix.com>
From: Adam Bradbury <adam@sanstone.demon.co.uk>
From: BURROWS@bnlnd2.dne.bnl.gov
From: Ralph Kenning <rkenning@atl.mindspring.com>
From: Enfir <enfir@iprj.uerj.br>
From: Gianni Reffo <reffo@nudace.arcoveggio.enea.it>

The following example is an improvement, but it could be better:

Adam Bradbury
Stonewell Consultants Ltd
(01524) 811260  (Is it a phone number or mail code?)

The following examples are excellent and most mail systems will allow the user to append a "signature" to outgoing mail. Please do our staff a kindness and include the information in your email message that would ordinarily appear on your company letterhead if you had to write a letter to communicate.

Stephen E. Binney
Professor of Nuclear Engineering
116 Radiation Center
Oregon State University
Corvallis, OR 97331-5902

Phone: (541)737-7068
Fax: (541)737-0480
Internet: binneys@ccmail.orst.edu

Insoo Jun, Ph.D.
Hughes Space and Communications
Building S25, M/S C372
P.O. Box 92919
Los Angeles, CA 90009

If we do not have all the information we need your request could be delayed. Please include all means of contacting you; phone, fax, and email if it is available.

Two changes were made to the computer code collection during the month. One code system was packaged and added to the collection and an existing code package was replaced with a newly frozen version.

CCC-636/ISO-PC 2.1

Language: Fortran 77
Computers: PC
Format: DOS

Westinghouse Hanford Company, Richland, Washington, contributed a newly frozen version of this kernel integration shielding code system for simple arrangements of source and shields. ISO-PC calculates dose rates from the decay of radionuclides at the exterior of simple geometric shapes. The dose rates from X-rays, gammas, and bremsstrahlung radiation are computed. ISO-PC is a revision of the CCC-079/ISOSHLD-II program and corrects all known errors in ISOSHLD-II. Both the Radio-Isotope Buildup and Decay (RIBD) program and the non-uniform source parameter, SSV1, were removed. Version 2.1 contains several changes and improvements:

three new geometries were added for hollow cylinders,maximum number of shield regions increased from 5 to 6,the DELR parameter is now computed internally,several nuclides were added to the library,the definition of ICONC was expanded to include mass concentrations, andnew NAMELIST variables were added to allow input in SI units with standard prefix multipliers.

The Lahey Computer Systems F77L-EM/32 Version 5.01 compiler was used to create the executable included in the package which runs on IBM and compatible personal computers under DOS version 3 or higher. References: Informal documentation (1996), WHC-SD-WM-UM-030 (1995), BNWL-236 (1966) and BNWL-236-SUP1 (1967). Fortran; IBM PC (C00636/IBMPC/01).


Language: Fortran 77, Assembler
Computers: PC
Format: DOS

Oak Ridge National Laboratory, Tennessee, contributed the FASTPLOT library of routines which can be used to interface with the Microsoft Fortran Graphics library (GRAPHICS.LIB) for personal computers. The FASTPLOT routines simplify the development of graphics applications and add capabilities such as histograms, splines, symbols, and error bars. FASTPLOT also includes routines to create menus. The FASTPLOT library must be linked with a user's Fortran program which can call any FASTPLOT routines. The user must also link with the MS GRAPHICS.LIB. The system is compatible with Microsoft v5.1. The package is transmitted on one DS/HD 3.5-in. (1.44MB) diskette in DOS format. References: ORNL/TM-12373 (1994). Fortran and Assembler; IBM PC (P00354/IBMPC/00).


In serving a specialized area of scientific endeavor, it seems important that we note significant events or changes in the activities of people concerned with radiation protection, transport, and shielding in the nuclear industry. We, therefore, continue to carry personal items as they are brought to our attention.

Nina Kalach from the Institute for Nuclear Research (INR), Kiev, Ukraine, has completed an assignment at RSICC as an IAEA Fellow. The primary purpose of her assignment was on-the-job training on nuclear data processing procedures using the latest available technology in RSICC. The initial two-month assignment was extended to facilitate a guided research project to generate a multigroup neutron data library to be used for the calculation of neutron fluence in the pressure vessel of VVER reactors.

NJOY94.10 was used to generate a 103-group neutron data library based on the latest release of ENDF/B-VI reference evaluated data for the 31 nuclides requested by INR. Several computer codes were implemented on RSICC workstation computers to establish the calculational system for production, checking and testing of processed multigroup nuclear data. The resulting groupwise data were converted to AMPX master format whereby simple physics tests were performed using the SMILER/RADE sequence. It is anticipated that this 103-group data library in ANISN format for the calculation of neutron fluence in the pressure vessel of VVER reactors will become part of the RSICC data library collection for distribution to the radiation transport community.

The RSICC staff enjoyed working with Nina who also helped us better understand the operation of the former USSR code GRUCON. We hope Nina's experiences at ORNL will help her future professional endeavors.

John H. Hubbell, retired, received the Doctor Honoris Causa awarded by the National University of Cordoba, Argentina, in April 1996. Dr. Hubbell traveled to Cordoba in October to receive the award. He was appointed "visiting professor" during his visit and gave several lectures on radiation physics topics to graduate physics students. Though officially retired from the National Institute of Standards in 1988, Dr. Hubbell continues work on photon cross section evaluation and compilation. He is presently in collaboration with Stephen M. Seltzer on "Tables of X-Ray Mass Attenuation Coefficients and Mass Energy-Absorption Coefficients 1 keV to 20 MeV for Elements Z = 1 to 92 and 48 Additional Substances of Dosimetric Interest." He currently serves as president of the International Radiation Physics Society and editor-in-chief of Radiation Physics and Chemistry.

Conferences, Cources, Symposia


The following literature cited has been ordered for review, and that selected as suitable will be placed in the RSICC Information Storage and Retrieval Information System (SARIS). This early announcement is made as a service to the shielding community. Copies of the literature are not distributed by 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.

RSICC 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.

Radiation Shielding Literature

Nucl. Technol., 111, 305-318 . . . Confinement of the Radiological Source Term During Beyond-Design-Basis Events in Future Pressurized Water Reactors. . . . Kessler, G.; Kuczera, B.; Ehrhardt, J.; Henneges, G.; Scholtyssek, W.; Hans-Werner, W. . . . September 1995 . . . Forschungszentrum Karlsruhe GmbH, Karlsruhe, Germany.

Nucl. Technol., 116, 146-159 . . . A Formal Approach for Quantitative Treatment of Modeling Uncertainties in Safety Analysis. . . . Kwang-Il Ahn; Young-Ho Jin . . . November 1996 . . . Korea Atomic Energy Research Institute, Taejon, Korea.

Nucl. Technol., 116, 173-179 . . . Core Performance of Fast Reactors for Actinide Recycling Using Metal, Nitride, and Oxide Fuels. . . . Yokoo, T.; Sasahara, A.; Inoue, T.; Kang, J.; Suzuki, A. . . . November 1996 . . . Central Research Institute of Electric Power Industry, Tokyo, Japan; University of Tokyo, Tokyo, Japan.

Nucl. Technol., 116, 257-260 . . . Exposure Buildup Factors of UO2 Using the Monte Carlo Method. . . . Bozkurt, A.; Tsoulfanidis, N. . . . November 1996 . . . University of Missouri-Rolla, Rolla, MO.

Dissertation . . . Development of a Continuous Energy Version of the Monte Carlo Code KENO V.a. . . . Dunn, M.E. . . . December 1996 . . . . . . . . . A Dissertation Presented for the Doctor of Philosophy Degree, University of Tennessee, Knoxville.

CRCPD Publication 96-4 . . . 28th Annual National Conference on Radiation Control. . . . . . . October 1996.

KEK Proceedings 96-4 . . . Radiation Detectors and Their Uses. . . . Miyajima, M.; Sasaki, S.; Iguchi, T.; Nakazawa, M.; eds. . . . July 1996 . . . National Laboratory for High Energy Physics, Ibaraki-ken, Japan . . . . . . Proceedings of the 10th Workshop on Radiation Detectors and Their Users, January 23-25, 1996, KEK, Tsukuba, Ibaraki, Japan.

LA-12808 . . . Nuclear Criticality Safety Guide. . . . Pruvost, N.L.; Paxton, H.C., eds. . . . September 1996 . . . Los Alamos National Laboratory, Los Alamos, NM.

ORNL/TM-13313 . . . Assessment of the Available 233U Cross-Section Evaluations in the Calculation of Critical Benchmark Experiments. . . . Leal, L.C.; Wright, R.Q. . . . October 1996 . . . Oak Ridge National Laboratory, Oak Ridge, TN.

Computer Codes Literature

DOE/RW/00134-T25. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . RIP
Repository Integration Program: RIP Performance Assessment and Strategy Evaluation Model Theory Manual and User's Guide. . . . No authors listed. . . . 11/95 . . . Golder Associates, Inc.; Redmond, WA . . . OSTI; NTIS; GPO; INIS (mf only).

IAEA-TECDOC-882 . . . . . . . . . . . . . . . . . . . . . . . .LMFBR
Verification and Validation Analyses of LMFBR Core Mock-Up Seismic Experiments by Finds Code. . . . Itoh, K.; Satoh, T.; Aizawa, I. . . . 05/96 . . . Mitsubishi Heavy Industries, Yohomama, Japan . . . INIS (mf only) . . . Proceedings of a final research co-ordination meeting. 30 May - 2 June 1995, Bologna Italy.

INFO-0624. . . . . . . . . . . . . . . . .MODTURC-CLAS; PHOENICS
A Review of Computer Codes MODTURC-CLAS and PHOENICS. . . . No authors listed. . . . 01/96 . . . Rowan Williams Davies and Irwin, Inc., Guelph, ON, Canada; Atomic Energy Control Board, Ottawa, ON, Canada . . . INIS (mf only).

INFO-0625. . . . . . . . . . . . . . . . . . . . . GOTHIC

Review of the GOTHIC Code and Trial Application. . . . Lacroix, M.; Galanis, N.; Millette, J. . . . 01/96 . . . Marcel Lacroix Enr., Sherbrooke, PQ, Canada; Atomic Energy Control Board, Ottawa, ON, Canada . . . INIS (mf only).

JAERI-Data/Code-95-015. . . . . . . . . . . . . . . . . . . . SRAC95
SRAC95: General Purpose Neutronics Code System. . . . Okumura, K.; Tsuchihashi, K.; Kaneko, K. . . . 03/96 . . . Japan Atomic Energy Research Inst., Tokai, Ibaraki, Japan; Tokai Research Establishment, Kaneko, Kunio, Japan . . . INIS (mf only) . . . In Japanese.

Nucl. Sci. Eng., 123, 86-95. . . . . . . . . . . . . . . . . FLEXBURN
The FLEXBURN Neutron Transport Code Developed by the Sn Method with Transmission Probabilities in Arbitrary Square Meshes for Light Water Reactor Fuel Assemblies. . . . Kameyama, T.; Matsumura, T.; Sasaki, M. . . . 10/96 . . . Central Research Inst. Electric Power Industry, Tokyo, Japan; Japan Research Institute, Ltd., Tokyo, Japan.