March 1997

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

No. 388 March 1997

No one has learned the meaning of life until he has surrendered his ego to the service of his fellow man---Beran Wolfe

The Ecstasy of the Web and the Agony of Email

Last month this editor was challenged to perform an experiment. Assignment: notify subscribers with email when the current newsletter is posted to the web and ask for a response. The message was sent to 1625 subscribers. Of that number 908 replied; 315 were refused; and 402 yielded no response, which I interpret to mean that someone somewhere received the message. I spent approximately 13 days abusing my carpel tunnel to evaluate, investigate, and respond to all those messages.

The purpose was twofold. First, to let our regular readers know that the newsletter is available at our web site. Second, to check the accuracy of the email list. The registration form, which we periodically ask you to complete, is our primary source of information. Since the form is often completed by hand and faxed, the email address can be misinterpreted.

I don't expect to repeat this process again, so those with access to the web may wish to check occasionally for the most current issue. Several of you suggested that the newsletter be sent as an attachment. That won't happen for several reasons that make it impractical. It would tie up our local email server; not every email system can or is set up to receive attachments; and many users could not read the software version that would be attached.

At some point in the future, those with access to the world-wide web will be asked to drop their subscription for a hard copy of the newsletter. This will result in a considerable savings in reproduction and postal expenses. Our subscribers will benefit in several ways. New and revised codes and data libraries announced are linked to the abstracts, and I will include the uniform resource locator (url) for conferences and seminars if it is provided by the author.

I thank all those who took the time to respond.

Alice F. Rice


Two new codes systems were added to the code collection and an existing code package was modified.


OP SYS: Unix Language: C, Fortran 77 Computers: Cray, WS Format: tar

Los Alamos National Laboratory contributed modifications to DANTSYS to correct a problem of overfilling a string (SITOP). The changes to subroutines PERR and TOLCM are available on diskette, via email or through the www. The RSICC master has been updated with these recommended changes. DANTSYS is a one-, two-, and three-dimensional, multigroup, discrete-ordinates transport code system, which includes five major codes: ONEDANT, TWODANT, TWOHEX, THREEDANT, and TWODANT-GQ.

DANTSYS runs on the following platforms: CRAY-YMP, Sun SparcStation IPX, IBM RS/6000, HP, and Silicon Graphics under Unix-based operating systems. A Fortran 77 compiler, a C-language preprocessor (cpp), a C-compiler, and GMAKE (GnuMake from Free Software Foundation) are required to install the package which is distributed on 1 CD, DC 6150 (150 MB) cartridge, 4-mm or 8-mm tape in compressed tar format. Reference: LA-12969-M (June 1995). Fortran 77 and C; Cray and workstations (C00547/MFMWS/01).

CCC-648/GENII-S 1.485

OP SYS: DOS Language: Fortran 77, Basic Computers: PC Format: DOS

Sandia National Laboratory, Albuquerque, New Mexico, contributed this environmental radiation dosimetry code system. GENII-S is the result of implementing CCC-601/GENII from Pacific Northwest Laboratory in the Sensitivity and UNcertainty analysis Shell (SUNS) to provide the capability to perform sensitivity and uncertainty analysis in one calculation, eliminating manual interfaces between the GENII code results and sensitivity and uncertainty analysis codes. The GENII portion of the GENII-S package contains the program developed to incorporate the internal dosimetry models recommended by the International Commission on Radiological Protection (ICRP) into the environmental pathway analysis models used at Hanford. GENII is a coupled system of seven programs and the associated data libraries that comprise the Hanford Dosimetry System (Generation II) to estimate potential radiation doses to individuals or populations from both routine and accidental releases of radionuclides to air or water and residual contamination from spills or decontamination operations. The programs in GENII-S analyze environmental contamination resulting from both far-field and near-field scenarios. The system can calculate annual dose, committed dose, and accumulated dose from acute and chronic releases from ground or elevated sources to air or water and from initial contamination of soil or surfaces and can evaluate exposure pathways including direct exposure via water, soil, air, inhalation and ingestion pathways. The original data released with the CCC-601/GENII package and the alternate data contributed by HEDL, which is intended to improve the treatment of decay chains for calculation of doses from contaminated soil allowed to decay for hundreds of years, are included.

Lahey F77L-EM/32 Vers. 5.01 and Microsoft QuickBASIC 4.0 were used to create the executables included in the package. GENII-S runs on Intel PC's under MS DOS 6.0 or in a DOS window of the Windows95 operating system. One DS/HD 3.5-in., 1.44MB diskette is required for transmittal. Reference: SAND91-0561 UC-721 (April 1993). Fortran 77 and Basic; IBM PC (C00648/IBMPC/00).


OP SYS: many Language: Fortran 77, C Computers: many Format: Unix, DOS

Los Alamos National Laboratory, Los Alamos, New Mexico, contributed the MCNP4B code system which replaces CCC-200/MCNP4A. This is a general-purpose, continuous-energy, generalized geometry, time-dependent, coupled neutron-photon-electron Monte Carlo transport code system. In addition to hundreds of minor features and numerous corrections, major MCNP4B code enhancements include:

MCNP treats an arbitrary three-dimensional configuration of materials in geometric cells bounded by first- and second-degree surfaces and some special fourth-degree surfaces. Pointwise continuous-energy cross section data are used, although multigroup data may also be used. Fixed-source adjoint calculations may be made with the multigroup data option. For neutrons, all reactions in a particular cross-section evaluation are accounted for. Both free gas and S(, ) thermal treatments are used. Criticality sources as well as fixed and surface sources are available. For photons, the code takes account of incoherent and coherent scattering with and without electron binding effects, the possibility of fluorescent emission following photoelectric absorption, and absorption in pair production with local emission of annihilation radiation. A very general source and tally structure is available. The tallies have extensive statistical analysis of convergence. Rapid convergence is enabled by a wide variety of variance reduction methods. Energy ranges are 0-60 MeV for neutrons (data generally only available up to 20 MeV) and 1 keV - 1 GeV for photons and electrons.

MCNP4B includes a test library of cross sections for running the sample problems, but all cross sections are included in the new DLC-189/MCNPXS code package, which is distributed with the code and requires a separate software license. MCNP4B is operable on Cray computers under UNICOS using CFT77, IBM RS/6000 under AIX 3.2.5 and AIX 4.2, SunSparc under SOLARIS 2.4 using F77 4.0, DEC Alpha under Digital Unix V3.2, HP with HP F77 9.16, SGI under IRIX 4.0.2, VAX computers under VMS 5.9 and all computers in general with at least 150 megabytes of hard disk. Executable files for the PC version are provided for running on 32MB memory on either a Pentium or 80486 computer with a coprocessor. The PC executables included in the package were created with the Lahey Fortran F77L3-EM/32 version 5.2 compiler. They run in a DOS window of either Windows95 or WindowsNT 4.0. Compilation of MCNP under Unix requires both Fortran 77 and ANSI C standard compilers. PVM is required for multiprocessing on a cluster of workstations. Scripts are provided for installation on both PC and Unix systems. Included are the referenced documents and the source codes, test problems, executables, and installation scripts available in either compressed Unix or DOS files on cartridge tape or CD-ROM. The code and cross sections are not available via ftp. References: LA-12625-M (1997), LA-13181 (August 1996), and LA-13138 (April 1996). Fortran 77 and C; Unix workstations, Intel-based PC, Cray, and VAX (C00660/ALLCP/00).


One new data library was added to the collection during the month.


OP SYS: many Language: Computers: many Format: ASCII

Los Alamos National Laboratory, Los Alamos, New Mexico, contributed the new MCNPXS standard neutron, photon, and electron data libraries for use with MCNP4B. This release includes all of the X-TM supported neutron data libraries, the photon libraries MCPLIB1 and MCPLIB02, the electron library EL1, an updated XSDIR file, and an information file README. This release completely replaces previous RSICC releases DLC-105 and DLC-181, as well as the cross sections previously included with CCC-200/MCNP4A, and will be updated as new libraries become available.

Currently the neutron data library ENDF60 (based on ENDF/B-VI, up through and including release 2) is the default library for continuous-energy neutron transport. Additionally, the libraries MCPLIB02 and EL1, are the default libraries for photon and electron transport..

A wide variety of continuous-energy, discrete, multigroup, thermal and dosimetry neutron data libraries are available in this release. The continuous-energy neutron data libraries available include: ENDF601, RMCCS1, RMCCSA1, ENDF5U1, ENDF5P1, NEWXS1, ENDF5MT1, MISC5XS1, ENDL851, KIDMAN1, and 100XS1. The discrete neutron data libraries include: NEWXSD1, DRMCCS1, DRE51. The multigroup neutron data library is MGXSNP1, and the thermal S(, ) libraries are TMCCS1 and THERXS1. The neutron dosimetry libraries are 531DOS1, 532DOS1, and LLLDOS1. The photon transport libraries are MCPLIB1 and MCPLIB02, and the electron library is EL1. The photon and electron data libraries contain data for elements having Z<95.

The data library ENDF5MT1 contains data previously available in the library EPRIXS, along with the U600K data library. The data library MISC5XS contains corrected data for ENDF/B-V based Zr and the libraries previously known as IRNAT, MISCXS, ARKRC, TM169, GDT2GP, and T2DDC. None of these data libraries have been previously distributed through RSICC. All data libraries and files are in ASCII mode and can be used with MCNP4B on all computer platforms supported by the code. The package is distributed in either compressed Unix or DOS files on CD-ROM or cartridge tape. References: Informal papers (Jan. 1997), LA-12891 (1994), LANL memorandum X-6:HGH-93-77 (revised 1996), X-6:RCL-87-225 (1987), and XTM:95-259 LA-UR-96- 24 (1995). All Computers; D00189/ALLCP/00.


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.

This literature is on order. It is not in our system. Please order from NTIS or other available source as indicated.

Radiation Shielding Literature

Health Phys., 72, 351-360 . . . Proposed Model for Estimating Dose to Inhabitants of 60Co Contaminated Buildings. . . . Carlarelli, J. II; Elliott, L.; Hornung, R.; Chang, W.P. . . . March 1997 . . . National Institute for Occupational Safety and Health, Cincinnati, Ohio; National Yang Ming University Medical School, Shih-pai, Taipei, Taiwan.

Health Phys., 72, 361-367 . . . Dose Equivalents to Neutron Theory Facility Staff Due to Induced Activation. . . . Yudelev, M.; Maughan, R.L.; Jordan, L.E.; Saxena, R. . . . March 1997 . . . Gershenson Radiation Oncology Center, Detroit, MI; St. Francis Hospital, Evanston, IL

Health Phys., 72, 368-383 . . . A Statistical Analysis of the Internal Organ Weights of Normal Japanese People. . . . Ogiu, N.; Nakamura, Y.; Ijiri, I.; Hiraiwa, K.; Ogiu, T. . . . March 1997 . . . National Institute of Radiological Sciences, Chiba, Japan; Kagawa Medical School, Kagawa, Japan; Fukushima Medical College, Fukushima, Japan.

Health Phys., 72, 443-449 . . . A Modified Bottle Manikin Phantom for In Vivo Neutron Activation Analysis. . . . Yasumura, S.; Ma, R.; Weber, D.A.; Dilmanian, F.A.; Zhao, M.; LoMonte, A.F.; Moore, R.I.; Sk . . . March 1997 . . . Brookhaven National Laboratory, Upton, NY; University of California, Davis Med. Center, Sacramento, CA; St. Luke's Roosevelt Hospital Center, New York, NY.

Health Phys., 72, 465-470 . . . Examination of the Effect of Counting Geometry on 125I Monitoring Using MCNP. . . . Kramer, G.H.; Yiu, S. . . . March 1997 . . . Human Monitoring Laboratory, Ontario, Canada.

INDC(NDS)-358 . . . Improvement of Measurements, Theoretical Computations and Evaluations of Neutron Induced Helium Production Cross Sections. . . . Pashchenko, A.B., ed. . . . December 1996 . . . IAEA Nuclear Data Section, Vienna, Austria. . . . Status Report prepared at the final CRP Meeting in Sendai, Japan 25-29 September 1995.

UCRL-ID-126455 . . . TART96: A Coupled Neutron-Photon 3-D, Combinatorial Geometry Monte Carlo Transport Code. . . . Cullen, D.E. . . . November 1996 . . . Lawrence Livermore National Laboratory, Livermore, CA.

Nucl. Sci. Eng., 123, 319-327 . . . A Three-Dimensional Time-Dependent Unstructured Tetrahedral-Mesh SPN Method. . . . Morel, J.E.; McGhee, J.M.; Larsen, E.W. . . . July 1996 . . . University of California, Los Alamos National Laboratory, Los Alamos, NM; University of Michigan, Ann Arbor, MI.

Nucl. Sci. Eng., 123, 328-342 . . . Asymptotic Derivation of the Multigroup P1 and Simplified PN Equations with Anisotropic Scattering. . . . Larsen, E.W.; Morel, J.E.; McGhee, J.M. . . . July 1996 . . . University of Michigan, Ann Arbor, MI; Los Alamos National Laboratory, Los Alamos, NM.

Nucl. Sci. Eng., 123, 343-357 . . . Asymptotic Derivation of the Fermi Pencil-Beam Approximation. . . . Borgers, C.; Larsen, E.W. . . . July 1996 . . . Tufts University, Medford, MA; University of Michigan, Ann Arbor, MI.

Nucl. Sci. Eng., 123, 358-368 . . . Application of the Bn Theory to Unit Cell Calculations. . . . Roy, R. . . . July 1996 . . . Ecole Polytechnique de Montreal, Quebec, Canada.

Nucl. Sci. Eng., 123, 369-380 . . . Variational Nodal Transport Perturbation Theory. . . . Laurin-Kovitz, K.F.; Lewis, E.E. . . . July 1996 . . . Northwestern University, Evanston, IL

Nucl. Sci. Eng., 123, 381-391 . . . Solution of Mathematical Adjoint Equation for a Higher Order Nodal Expansion Method. . . . Kim, T.K.; Kim, C.H. . . . July 1996 . . . Seoul National University, Seoul, Korea.

Nucl. Sci. Eng., 123, 392-402 . . . Collision Probability Calculation and Multigroup Flux Solvers Using PVM. . . . Qaddouri, A.; Roy, R.; Mayrand, M.; Goulard, B. . . . July 1996 . . . Ecole Polytechnique de Montreal, Quebec, Canada; Universite de Montreal, Quebec, Canada.

Nucl. Sci. Eng., 123, 403-414 . . . An Incomplete Domain Decomposition Preconditioning Method for Nonlinear Nodal Kinetics Calculations. . . . Joo, H.G.; Downar, T.J. . . . July 1996 . . . Purdue University, Wet Lafayette, IL.

Nucl. Sci. Eng., 123, 435-442 . . . Kalman Filter Application for Distributed Parameter Estimation in Reactor Systems. . . . Martin, R.P.; Edwards, R.M. . . . July 1996 . . . Pennsylvania State University, University Park, PA.

Nucl. Sci. Eng., 123, 443-454 . . . Flow Modeling in Heterogeneous Media in the Context of Geologic Nuclear Waste Repositories. . . . Sagar, B. . . . July 1996 . . . Center for Nuclear Waste Regulatory Analyses, San Antonio, TX

Book . . . CINDA96, Supplement to CINDA95 (1988-1996). . . . 1996 . . . International Atomic Energy Agency, Vienna, Austria.

Nucl. Technol, 117, 281-292 . . . Development of a Three-Dimensional Core Dynamics Analysis Program for Commercial Boiling Water Reactors. . . . Bessho, Y.; Yoshimoto, Y.; Yokomizo, O.; Yamashita, R.; Ishikawa, M.; Toba, A. . . . March 1997 . . . Hitachi Works, Hitachi, Ltd., Ibaraki-ken, Japan; Hitahi Engineering Co., Ibaraki-ken, Japan; Tokyo Electric Power Co., Tokyo, Japan; Toden Software, Inc., Tokyo, Japan.

Nucl. Technol., 117, 293-398 . . . Transmutation of Technetium and Iodine-Irradiation Tests in the Frame of the EFTTRA Cooperation. . . . Konings, R.J.M.; Franken, W.M.P.; Contrad, R.R.; Gueugnon, J-F.; Spirlet, J-C. . . . March 1997 . . . ECN, Petten, The Netherlands; European Commission Joint Research Center, Petten, The Netherlands; European Commission Joint Research Center, Karlsruhe, Germany.

Nucl. Technol., 117, 306-315 . . . Local Analysis Technique for the Advanced Neutron Source Reactor Fuel Defect Studies. . . . Giles, G.E. . . . March 1997 . . . Oak Ridge National Laboratory, Oak Ridge, TN.

Nucl. Technol., 117, 316-328 . . . Transport of Weapons-Grade Plutonium and Boron Through Fractured Geologic Media. . . . Ahn, J. . . . March 1997 . . . University of California-Berkeley, Berkeley, CA.

Nucl. Technol., 117, 329-339 . . . Development of an Integrated Transuranic Waste Management System for a Large Research Facility: NUCEF. . . . Mineo, H.; Matsumura, T.; Takeshita, I.; Nishizawa, I.; Sugikawa, S.; Tsujino, T. . . . March 1997 . . . Japan Atomic Energy Research Institute, Ibaraki, Japan; Nuclear Material Control Center, Ibaraki, Japan.

Nucl. Sci. Eng., 125, 249-256 . . . Comparison of LAHET Code System Calculations with Experimental Results for Protons of Energies Less Than 50 MeV Incident on Copper and Iron. . . . Eaton, S.L.; Beard, C.A.; Adams, M.L. . . . March 1997 . . . Los Alamos National Laboratory, Los Alamos, NM; Texas A&M University, College Station, TX.

Nucl. Sci. Eng., 125, 257-283 . . . A Transport Synthetic Acceleration Method for Transport Iterations. . . . Ramone, G.L.; Adams, M.L.; Nowak, P.F. . . . March 1997 . . . Texas A&M University, College Station, TX; Lawrence Livermore National Laboratory, Livermore, CA.

Nucl. Sci. Eng., 125, 284-299 . . . Error Analysis of the Nodal Expansion Method for Solving the Neutron Diffusion Equation. . . . Penland, R.C.; Azmy, Y.Y.; Turinsky, P.J. . . . March 1997 . . . North Carolina State University, Raleigh, NC; Oak Ridge National Laboratory, Oak Ridge, TN.

Nucl. Sci. Eng., 125, 300-313 . . . Parallel Processing of Two-Dimensional Sn Transport Calculations. . . . Uematsu, M. . . . March 1997 . . . Toshiba Corp., Yokohama, Japan.

Nucl. Sci. Eng., 125, 314-323 . . . Generalized Rayleigh Quotients for Eigenvalue Estimates of Neutron Balance Equations. . . . Gheorghiu, H.N.M.; Rahnema, F. . . . March 1997 . . . Georgia Institute of Technology, Atlanta, GA.

Nucl. Sci. Eng., 125, 362-370 . . . Thermal Breeding of Tritium: A Comparative Study of the Li + C and 3He + C Systems. . . . Gupta, S. Ahmed, F.; Garg, S. . . . March 1997 . . . University of Delhi, Delhi, India; Indira Gandhi National Open University, Delhi, India

Nucl. Sci. Eng., 125, 371-375 . . . Systematics of Isomeric Cross-Section Ratios for (n,2n), (n,p), (n,a) Reactions at 14.5 MeV. . . . Xiaolong Huang; Dunjiu Cai . . . March 1997 . . . China Institute of Atomic Energy, Beijing, China.

Nucl. Sci. Eng., 125, 376-379 . . . Corrigendum . . . . . . March 1997 . . . Corrected versions of Tables II, III, and IV and Figs. 1-4 of "Analysis of Nuclear Power Transmutation Potential at Equilibrium," Nucl. Sci. Eng. 124.