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
under contract DE-AC05-96OR22464

Phone No. 423-574-6176
FAX 423-574-6182

Internet: PDC@ORNL.GOV
WWW: http://www-rsicc.ornl.gov/rsic.html

No. 405 September 1998
If ever this free people, if this Government itself is ever utterly demoralized, it will come from this incessant human wriggle and struggle for office, which is but a way to live without work.--Abraham Lincoln


Four changes or additions were made to the computer code collection during the month. One existing code system was replaced with a newly frozen version, one code system was extended with an additional hardware version, and two code systems were enhanced with software updates.

Oak Ridge National Laboratory, Oak Ridge, Tennessee, contributed additional files to allow the IBM RS/6000 version of ASOP to run on personal computers under the Linux operating system. ASOP is a shield optimization calculational system based on the one-dimensional discrete ordinates transport code system ANISN (CCC-254). It has been used to design optimum shields for space applications of SNAP zirconium-hydride-uranium-fueled reactors and uranium-oxide fueled thermionic reactors and to design beam stops for the ORELA facility at ORNL. A Fortran 77 compiler is required to compile and run the code on either IBM RS/6000 under AIX or on personal computers running Linux. The PC version was tested with Red Hat Linux using the g77 compiler. The package is transmitted on one DS/HD Unix-formatted diskette in a GNU compressed tar file which includes Fortran source, test case input and output, and makefiles for running under both AIX and Linux. Reference: CTC-INF-941 (September 1969). IBM RS/6000 or Linux PC; Fortran 77 (C00126/IRISC/00).

ORNL contributed a newly frozen version of the Standardized Computer Analyses for Licensing Evaluation modular code system. Many enhancements and corrections were made to SCALE in the three years since the release of SCALE-4.3. SCALE-4.4 is compatible with the year 2000. The SCALE system was developed for the Nuclear Regulatory Commission to satisfy a need for a standardized method of analysis for the evaluation of nuclear fuel facility and package designs. In its present form, the system can 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/decay calculation. User-specified surface detectors were added to SAS4/MORSE to improve its computational flexibility and efficiency. The KENO-VI input requirements for HOLEs were simplified and made more consistent with KENO V.a. Additionally, the speed and stability of KENO-VI was significantly improved. A large number of changes were made to the SAS2H depletion module. A significant effort was made to minimize the programming differences between the PC and Unix workstation versions. Both versions contain the same modules. The heat transfer modules HTAS1, HEATING, and the HEATING auxiliary codes are now available in the PC version for the first time. More details are available in the "Notes to Recipients" which is available in the SCALE4.4 document in PDF format under Electronic Documents on RSICC's www site: http://www-rsicc.ornl.gov/DOCALPH.html.

The PC version recognizes MS-DOS, Windows 95, Windows 98, and Windows NT operating systems. Executables included in the PC package were created using the Lahey F90 Fortran compiler version 4.00e in a DOS window of Windows NT 4.0. Makefiles, source files, batch files, data libraries, and test cases are included in the PC package which is transmitted in DOS self-extracting compressed files.

The Unix version of SCALE-4.4 runs on IBM RS/6000, DEC, SUN, and HP workstations and requires a minimum of 550 MB to create executables and run test cases. Fortran 90, Fortran 77 and C compilers are required to install the Unix version, which is transmitted in a GNU compressed tar file that includes source codes, BCD and binary data libraries, makefiles, scripts, and sample problem input and output. Makefile flags are included to allow the source codes to compile on DEC Alpha OSF/1, SUN/Solaris, SUN/Sun OS4, HP/HP-UX9, HP/HP-UX10, and SGI/IRIX workstations. SCALE4.4 was tested on the following Unix systems:

IBM RS/6000 AIX 4.2.1 using XLF90

SUN under SunOS 5.6 using f77 4.2, Fortran 90 1.2 and c 4.2

DEC/Alpha 4.0B using Fortran 90 V4.1 compiler

HPUX 10.20 using Fortran 90 and Fortran 77 compilers.

Both Unix and PC versions are included on one CD. NUREG/CR-0200 is included on the CD-ROM in electronic (PDF) form;it is not distributed in hardcopy form. References: README (September 1998), NUREG/CR-6182, Vol. 1 (ORNL/TM-12663/V1) (November 1994), NUREG/CR-0200, Rev. 6 (ORNL/ NUREG/CSD-2/R6), Vols. I, II, and III (September 1998) DRAFT. Fortran 90, C (C00545/MNYCP/00).

Oak Ridge National Laboratory updated the Sun version of this Monte Carlo code system for the design and analysis of calorimeter systems, Spallation Neutron Source (SNS) target systems, etc., with a replacement for the MORSE module. CALOR95 was designed to assist experimentalists in evaluating and analyzing different types of calorimeter systems used in many high-energy physics experiments to determine the energy and direction of incident hadrons, leptons, and photons. This code package contains HETC95, SPECT95, EGS4, MORSE, and other support programs. The MORSE version in earlier releases of CALOR95 did not yield the correct energy balance because absorbed gamma-ray energies were underestimated. This correction was made to the IBM RS/6000 version in June 1998. Now the Sun and IBM RS/6000 versions are functionally equivalent.

CALOR95 runs on IBM RS/6000 computers with the XLF Fortran 77 compiler or on Sun Sparc workstations under Solaris 2.6 with the Fortran 4.2 compiler. It is transmitted on one CD-ROM in compressed Unix tar format. References ORNL/TM-11185 (unpublished report) and SDC-92-00257 (May 1992). Fortran 77; IBM RS/6000 (C00610/IRISC/02); SUN (C00610/SUN05/02).

Oak Ridge National Laboratory, Oak Ridge, Tennessee, contributed a minor correction to this multidimensional, finite-difference heat conduction analysis code system. HEATING can solve steady-state and/or transient heat conduction problems in one-, two-, or three-dimensional Cartesian, cylindrical, or spherical coordinates. Both HEATING 7.2i and HEATING7.3 are distributed in this package. The correction was made to the HEATING 7.3 Windows95/NT user interface to correct problems with restart cases. In the previous version a restart case would run, but the .prt and .pst files were not saved back to the directory containing the input file.

HEATING7.2i runs on several Unix systems including IBM RS/6000, Sun, DEC, DEC Alpha, HP and Cray. Fortran 77 and C compilers are required. For the PC version, a Fortran compiler and DOS extender software are needed to create new executables or to compile and load user-supplied subroutines. The Microway NDP Fortran 386 4.2.1 compiler was used to create 7.2i executables included in package. HEATING 7.3 is written in Fortran 77 but includes some Fortran 90 features. HEATING 7.3 PC executables were created using Microsoft Powerstation v4.0. Visual Basic 4.0 was used to create the graphical front end for the program. Windows95 or WindowsNT is required to use the GUI version of HEATING 7.3, though a non-gui version is included in the package that may be run in a DOS window of Windows95 or WindowsNT. HEATING7.3 for Unix was tested only on IBM RS/6000 and requires the XLF 3.2 compiler.

One CD-ROM, readable on both PC and Unix computers, includes the referenced document, source code, PC executables, script files, and sample cases. References: ORNL/TM-12262 (February 1993). HEATING 7.2i: Fortran 77 and C; UNIX Workstation or Mainframe: Fortran 77; 386 or 486 PC; HEATING 7.3: Fortran 90 486PC and IBM RS/6000 (P00199/MNYCP/02).


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 First Latin American Symposium on Nuclear Tracks

The First Latin American Symposium on Nuclear Tracks will be held April 5-9, 1999, in Caracas, Venezuela. The symposium will be devoted to review of the present knowledge of nuclear track science and technology and its applications in physics, health, environmental studies, earth sciences and industry. Participants are encouraged to submit one-page abstracts, even if they might be seen as preliminary results. The list of suggested topics are:

  1. Basic Physical Processes Related to Track Formation
  2. Track Observation and Measurement Methodology
  3. Environmental Radiation and Radon Studies
  4. Radiation Dosimetry
  5. Nuclear Physics
  6. Geoscience
  7. Medical Physics and Radiobiology
  8. Archeology
  9. Industry
  10. New Trends in Nuclear Tracks Science and Technology

Abstracts with the complementary registration page can be sent in three ways by the February 15, 1999 deadline:

1. By FAX to one the following numbers:

(+58-2) 906-3155 (Laboratorio de Física Nuclear, USB)
(+58-2) 906-3888 (Laboratorio de Física Nuclear, USB)
(+58-2) 605-2188 (Escuela de Física, Facultad de Ciencias, UCV)

2. By E-mail to one of the following addresses:


3. Send the abstract either by FAX or E-mail and then proceed with the electronic registration.

Details may be found on the internet at http://fisica.ciens.ucv.ve/~rmartin/1lasont/1lasont.html.

Tenth International Symposium on Reactor Dosimetry

The Tenth International Symposium on Reactor Dosimetry will be held September 12-17, 1999, in Osaka, Japan. This Symposium is held about every three years to provide a forum for the interchange of state-of-the-art techniques, databases and standardization of radiation metrology. The Symposium will be of value to those involved in reactor dosimetry, including researchers, manufacturers and representatives from industry, utilities and regulatory agencies. The Symposium is jointly sponsored by the Atomic Energy Society of Japan (AESJ), the American Society for Testing and Materials (ASTM) and the European Working Group on Reactor Dosimetry (EWGRD). It is organized by ASTM Committee E10 on Nuclear Technology and Applications and EWGRD.

The Symposium theme is dosimetry for the assessment of irradiated reactor materials and reactor experiments, featuring radiation metrology techniques, databases and standardization. Inquiries and requests to be added to the mailing list should be sent to one of the following:

North and South America, East and Southeast Asia:

Dr. David W. Vehar
ASTM Program Secretary
Sandia National Laboratories, MS-1136
P.O. Box 5800, Albuquerque, NM 87185-1136, USA

Phone: 505-845-3414, fax: 505-844-0798
email: dwvehar@sandia.gov

Europe, Africa, Asia (other), and Australia:

Dr. Hamid Ait Abderrahim
EWGRD Programme Secretary
Boeretang 200, B-2400 Mol, BELGIUM

Phone: 32-14-332277, fax: 32-14-321529
email: haitabde@sckcen.be

"Half a Century of Radiation Shielding Research and Its Evolution into the Next Era" is the theme for the 9th International Conference on Radiation Shielding to be held October 17-22, 1999, in Tsukuba, Japan. It is sponsored and organized by the Japan Atomic Energy Research Institute and co-sponsored by the OECD-Nuclear Energy Agency-Nuclear Science Committee (NEA-NSC), Atomic Energy Society of Japan (AESJ), and the Radiation Safety Information Computational Center (RSICC). Participants in the conference explore the scientific, technological and engineering issues associated with radiation shielding in broad nuclear energy systems, accelerator facilities, space and general environments. 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 ikeda@fnshp.tokai. jaeri.go.jp) or from the web page at http://icrs9.tokai.jaeri.go.jp.


Your attention is directed to the following events of interest.

October 1998

5th International Conference on Recycling, Conditioning, and Disposal (RECOD '98), Oct. 25-28, 1998, Nice, France, sponsored by the French Nuclear Energy Society and the European Nuclear Society. Contact: SFEN-RECOD '98, 69-73, rue Dutot, 75015 Paris, France (phone 33-01-4419-6220, email sfen@wanadoo.fr).

International Nuclear Congress (ENC '98) and World Congress, Oct. 25-28, 1998, Nice, France, sponsored by the European Nuclear Society and others. Contact: ENC '98 Secretariat, European Nuclear Society, Belpstrasse 23, P.O. Box 5032, CH-3001 Berne, Switzerland (phone 41-31-320-6111, fax 41-31-382-4466, url http://www.acv.ch/enc98).

26th Water Reactor Safety Information Meeting, Oct. 26-28, 1998, Bethesda, Maryland, sponsored by the U.S. Nuclear Regulatory Commission. Contact: Susan Montelcome (phone 516-344-7235, fax 516-344-3957, email smontele@bnl.gov).

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).

15th International Conference on the Application of Accelerators in Research and Industry, Nov. 4-7, 1998, Denton, Texas, sponsored by the University of North Texas. Contact: Barbie Stippec (phone 940-565-3252, fax 940-565-2227, email stippec@unt.edu, url http://www.phy.unt.edu/accercon/).

SWR-1000: A Reactor Concept for the Future, Nov. 5, 1998, Königswinter, Germany, sponsored by Informum GmbH. Contact: Inforum Conference Office, Heussallii10, D 53113 Bonn, Germany (phone 49-0-228-507-223, fax 49-0-228-507-262, email inforum_gmbh@compuserve.com).

International Symposium on Storage of Spent Fuel from Power Reactors, Nov. 9-13, 1998, Vienna, sponsored by the IAEA and OECD Nuclear Energy Agency. Contact: IAEA, Wagramerstrasse 5, P.O. Box 100, A-1400 Vienna, Austria (phone 43-1-20600, fax 43-1-20607, email official.mail@iaea.org).

19th Low-Level Radioactive Waste Management Conference, Nov. 10-12, 1998, Salt Lake City, Utah, sponsored by the U.S. Department of Energy and the University of Utah. Contact: Donna Lake (phone 208-526-0234, fax 208-526-9165, email lrd@inel.gov).

TapRoot® Incident/Accident Investigation System User's Conference, Nov. 11-13, 1998, Dallas, Texas, sponsored by System Improvements, Inc. Contact: Katrina Kidd, System Improvements, Inc., Suite 301, 238 South Peters Rd., Knoxville, TN 37923-5224 (phone 423-539-2139, fax 423-539-4335, email taproot@taproot.com, url http://www.taproot.com).

ANS Winter Meeting, Nov. 15-19, 1998, Washington, D.C. Contact: James O'Hanlon, Sr. Vice President-Nuclear, Virginia Power, 5000 Dominion Blvd., Glen Allen, VA 23060 (phone 804-273-3551, fax 804-273-3759).

Meeting of the Americas: Nuclear Science, Technology, and Applications, Nov. 15-19, 1998, Washington, D. C. sponsored by the ANS, the Canadian Nuclear Society, ANS Latin American Section, the Brazilian Nuclear Energy Association, the Nuclear Technology Association of Argentina, and Soc. Nuclear Mexicana. Contact: Donald Hoffman (phone 301-984-4400, fax 301-984-7600).

International Symposium on Evolutionary Water-Cooled Reactors, Nov. 30-Dec. 4, 1998, Seoul, Republic of Korea, sponsored by the IAEA. Contact: IAEA, Wagramerstrasse 5, P.O. Box 100, A-1400 Vienna, Austria (phone 43-1-20600, fax x43-1-20607, email official.mail@iaea.org).

December 1998

Nuclear Decom '98, Dec. 2-3, 1998, London, sponsored by the Inst. of Mechanical Engineers. Contact: Alison Hamlett (phone 44-0171-304-6864, fax 44-0171-222-9881, email a_hamlett@imeche.org.uk).

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).

September 1999

Tenth International Symposium on Reactor Dosimetry, Sept. 12-17, 1999, in Osaka, Japan. Contact: Dr. David W. Vehar (505-845-3414, fax 505-844-0798, email: dwvehar@sandia.gov) or Dr. Hamid Ait Abderrahim (32-14-332277, fax 32- 14-321529, email haitabde@sckcen.be).

October 1999

Half a Century of Radiation Shielding Research and Its Evolution into the Next Era (ICRS-9), Oct. 17-22, 1999, Tsukuba, Japan, sponsored and organized by the Japan Atomic Energy Research Institute. Contact: 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 ikeda@fnshp.tokai.jaeri.go.jp, url http://icrs9.tokai.jaeri.go.jp.


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/SARIS.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.


Health Phys., 75, 77-85 . . . Effects of Intake Function Shape on Internal Dose Estimations. . . . Manuca, D.; Kearfott, K.J. . . . July 1998 . . . University of Michigan, Ann Arbor, MI.

Health Phys., 75, 197-204 . . . The Characterization of a Commercial Mosfet Dosimeter System for Use in Diagnostic X Ray. . . . Bower, M.W.; Hintenlang, D.E. . . . August 1998 . . . University of Florida, Gainsville, FL.

Health Phys., 75, 93-196 . . . Radiation Shielding Implications of Computed Tomography Scatter Exposure to the Floor. . . . Langer, S.G.; Gray, J.E. . . . August 1998 . . . Mayo Clinic and Foundation, Rochester, MN; University of Washington Medical Center, Seattle, WA.

Health Phys., 75, 170-178 . . . Effective Dose Equivalent and Effective Dose for Photon Exposures from Point and Disk Sources on the Floor. . . . Kim, C.H.; Reece, W.D.; Poston, J.W., Sr. . . . August 1998 . . . Texas A&M University, College Station, TX.

Health Phys., 75, 165-169 . . . Monte Carlo Determination of Gamma-Ray Dose Rate with the Geant System. . . . August 1998 . . . J. Stefan Institute and University of Ljubljana, Ljubljana, Slovenia.

Health Phys., 75, 130-135 . . . Dose and Cost Considerations for Relocation After Nuclear Accidents. . . . Qu, J.; Ehrhardt, J. . . . August 1998 . . . Tsinghua University, Beijing, P.R. China; Institut f. Neutronenphysik und Reaktortechnik, Karlsruhe, Germany.

Nucl. Technol., 122, 1-18 . . . Description of Critical Experiments in Spherical Geometry Containing UO2F2 Solution. . . . Pitts, M.; Rahnema, F.; Williamson, T. G.; Trumble, F. . . . April 1998 . . . Georgia Institute of Technology, Atlanta, GA; Westinghouse Savannah River Company, Aiken, SC.

Nucl. Technol., 122, 43-51 . . . Neutronic and Burnup Characteristics of an Actinide-Reduced Plutonium Fuel with Tungsten. . . . Chang, G.S. . . . April 1998 . . . Idaho National Engineering and Environmental Laboratory, Idaho Falls, ID.

Nucl. Technol., 122, 72-82 . . . Radioactive Contamination Around a Boiling Water Reactor Main Turbine System and Procedures for Minimizing the Contaminated Area. . . . Otoha, K-I.; Uchida, S. . . . April 1998 . . . Japan Atomic Power Company, Tokyo, Japan; Hitachi, Ltd., Ibaraki, Japan.

Nucl. Technol., 122, 93-103 . . . Simulation of Radionuclide Release from a Repository to the Biosphere: Using a Model-Coupling Concept. . . . Gylling, B.; Moreno, L.; Neretnieks, I. . . . April 1998 . . . Royal Institute of Technology, Stockholm, Sweden.

Health Phys., 122, 104-124 . . . Evaluation of Kalman Filters and Genetic Algorithms for Delayed-Neutron Nondestructive Assay Data Analyses. . . . Aumeier, S.E.; Forsmann, J.H. . . . April 1998 . . . Argonne National Laboratory, Idaho Falls, ID.

Nucl. Technol., 123, 184-192 . . . Radionuclide Mass Transfer Rates from a Pinhole in a Waste Container for an Inventory-Limited and Constant Concentration Source. . . . LeNeveu, D.M. . . . August 1998 . . . Atomic Energy of Canada Limited, Manitoba, Canada.

Nucl. Technol., 123, 320-324 . . . Evaluation of Moderator Assemblies for Use in an Accelerator-Based Neutron Source for Boron Neutron Capture Therapy. . . . Woollard, J.E.; Blue, T.E.; Gupta, N.; Gahbauer, R.A. . . . September 1998 . . . Ohio State University, Columbus, OH.

Nucl. Technol., 123, 259-267 . . . Comparison Between MCNP and Critical Experiments - A Determination of Bias Values to be Utilized in Licensing Calculations for High-Level Radioactive Waste Disposal. . . . Wright, K.D.; Tulenko, J.S.; Dugan, E.T. . . . September 1998 . . . University of Florida, Gainesville, FL.

N-REP-03416.4-0217 . . . Review of Operational Aspects of VARSKIN MOD 2. . . . Davis, S. . . . August 1997 . . . Ontario Hydro Nuclear, Ontario, Canada.

ORNL/M-6576 . . . Introduction to the Theory and Analysis of Resolved (and Unresolved) Neutron Resonances via SAMMY. . . . ; Larson, N.M. . . . July 1998 . . . Oak Ridge National Laboratory, Oak Ridge, TN.

Prot.181/IRP . . . Use of MCNP in Radiation Protection and Dosimetry. . . . 1998 . . . ENEA, Bologna, Italy.