Oak Ridge National Laboratory
Post Office Box 2008 Oak Ridge, Tennessee 37831-6362
managed by Lockheed Martin Energy Systems
for the U.S. Department of Energy
Phone No. 615-574-6176
BitNet: PDC@ORNLSTC Internet: PDC@ORNL.GOV
No. 366 May 1995
CHANGES TO THE COMPUTER CODE COLLECTION
OP SYS: Windows
Oak Ridge Institute for Science and Education contributed a newly frozen version of this code system for calculating internal dose estimates by the Medical Internal Radiation Dose (MIRD) scheme. MIRDOSE3 is a significant update from MIRDOSE2 in four aspects: (1) three models for the pregnant female have become available, (2) a new bone and marrow model is included, (3) the ability to calculate dose estimates for small, unit density spheres (e.g. tumors) is provided, and (4) a significant improvement in the Windows user interface. MIRDOSE3 allows the user to choose from 28 source organs and calculate 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.
The code is compiled in Visual Basic and must be run under the Windows operating system, version 3.0, or higher on a 386 or higher processor. The executable, datafiles and documentation are transmitted on two DS/HD 3.5-in. (1.44 MB) diskettes written in DOS format. The BASIC source files are not included in the package. Reference: ORISE Unpublished Report (Dec. 1994). BASIC; PC 386 (C00528/PC386/01).
OP SYS: DOS, Windows
Language: Fortran 77, C
Oak Ridge National Laboratory contributed a newly frozen version of this code system for use during response to radiological emergencies. The system supplements assessments based on plant conditions and quick estimates based on hand-calculational methods. The model was developed to allow consideration of the dominant aspects of source term, transport, dose, and consequences. The model is a DOS application that can be run under Windows with results displayed as text or graphics. Three new source term calculations have been added: (1) a source term based on the reactor containment monitor reading, (2) a source term for a spent fuel pool accident, and (3) an isotopic concentration source term. The tabular output of ST-DOSE and FM-DOSE have been changed to include EPA PAGs. Field Measurements to Dose calculations now consider the effect of delay for re-entry on first-year and second-year dose, incorporate a variable resuspension rate, and compute a factor used to estimate first-year dose from R/hr measurements on the ground.
The recommended minimum configuration for RASCAL2.1 is a 386 processor and EGA graphics adapter. Microsoft Fortran (Version 5) and C (Version 7) compilers were used to create the executable included in the package which is transmitted on 2 DS/HD 3.5-in. (1.44 MB) diskettes in compressed DOS files. References: NUREG/CR-5247; ORNL-6820 (Dec. 1994). Fortran 77 and C; PC 386 (C00553/PC386/02).
OP SYS: DOS
Language: BASIC, C, Fortran 77
Oak Ridge National Laboratory contributed this code system to calculate specific effective energies for any of 54 source regions and 32 target regions in the human body for ages from newborn to adult male and adult female for any of 825 radionuclides in the ICRP Publication 38 collection or 242 radionuclides in the Medical Internal Radiation Dose Committee (MIRD) collection. Sources and targets from the new ICRP respiratory tract model (ICRP Publication 66, 1994) are included in this package designated SEECAL, Version 2.0. The specific effective energies are computed from equations given in ICRP Publication 56, Part 1 (1089), and ICRP Publication 60 (1991), and from databases of nuclear decay data, absorbed fractions, and region masses. The data in the DLC-172/NUCDECAY package are required by SEECAL and will be sent with SEECAL when requested. Users who have already received NUCDECAY from RSIC need not request the update announced later in this newsletter.
SEECAL consists of database and computational programs, with some input selected from menus. The menuing and other user-interface routines were written in Microsoft BASIC Professional Development System (Ver. 7.1) or Microsoft C (Ver. 6), and all computational programs were written in Microsoft Fortran (Ver. 5.1). The entire source for SEECAL is not included, but a program fragment in Fortran is provided for reading the SEE output files. References: Addendum (March 1995) and ORNL/TM-12351 (1993). BASIC, C, Fortran; IBM PC (C00620/IBMPC/00).
OP SYS: CTSS, UNICOS, UNIX
Language: Fortran 77
Format: tar, DOS
Los Alamos National Laboratory, Los Alamos, New Mexico, contributed a new update to correct a problem in the output PENDF tape from HEATR for NJOY 91.118, in which the values of the heating cross section come out much too low at high energies for Fe-56. This was traced to up103. The error will occur for any material using File 6, but it will only occur if IPRINT=0. Therefore, it does not affect the test problem output. The new ident 119 has been added to RSIC's package and is available upon request to users of NJOY 91.118.
NJOY91 produces pointwise and multigroup cross sections from ENDF/B evaluated nuclear data, including ENDF/B-VI. NJOY91 works with neutrons, photons, and charged particles and produces libraries for a wide variety of particle transport and reactor analysis codes. This is the last in the NJOY-91 series. It uses the same module structure as the earlier versions and its graphics options depend on DISSPLA. The 91.119 release is basically configured for UNIX. The test problem input files are UNIX shell scripts, and the test problem results are from runs on a Cray Y-MP/8-64 running UNICOS. The code runs on Cray/UNICOS, Cray/CTSS, IBM, VAX/VMS, and Sun workstations. The package is transmitted on either 1 DC 6150 (150 MB) cartridge or 8-mm tape in tar format. References: Informal document (November 1994), LA- 12057-MS (April 1991), LANL Memo T-2-L-10991 (June 1987), LA-9303-M (ENDF-324), Vol. I (May 1982), Vol. II (May 1982), Vol. III (October 1987), Vol. IV (December 1985), and LA-UR 89-2057 (June 1989). Fortran 77; Cray (CTSS & UNICOS), VAX/VMS, SUN/UNIX; (P00171/MFMWS/04).
Language: Fortran 77
Computers: IBM 3033, IBM RS/6000
Oak Ridge National Laboratory contributed a new hardware version of this code system for PWR pressure vessel surveillance dosimetry analysis. LEPRICON prepares input to and processes results from the discrete ordinates codes CCC-484/DORT and CCC-254/ANISN-ORNL to determine best estimates with uncertainties of group fluences in pressure vessels of pressurized water reactors. The new release runs on IBM RS/6000 and is functionally equivalent to the IBM 3033 release of 1990. The system was ported using the XLF 2.3 compiler, and sample cases were also executed using the XLF 3.2 compiler under AIX 3.2.5. The package is transmitted on either DC 6150 (150 MB), 4 mm DAT (8 GB), or 8 mm (2.3 GB) cartridge tapes in tar format. References: EPRI Research Project 1399-1 Interim Reports (Sept 1984, March 1985, Oct 1985, and Dec. 1985.) Fortran IV; IBM 3033 (P00277/I3033/01) and Fortran 77; IBM RS/6000 (P00277/IRISC/00).
OP SYS: CTSS, UNICOS, UNIX
Language: Fortran 77
Format: tar, DOS
Los Alamos National Laboratory, Los Alamos, New Mexico, contributed a new code system for producing pointwise and multigroup cross sections from ENDF/B evaluated nuclear data, including ENDF/B-VI. The new code designated NJOY94, is an interim release on the way to NJOY95. NJOY91 accumulated a large number of changes which was becoming a burden for the maintenance. In NJOY94 additional capabilities were introduced such as LEAPR for computing thermal scattering law data, PURR (a new version of the unresolved resonance probability table method including temperature correlations), an improved ACER which includes consistency checks and a QA program, and a graphics system that no longer needs the proprietary DISSPLA software.
The NJOY 94 release is basically configured for UNIX. The test problem input files are UNIX shell scripts, and the test problem results are from runs on a Cray Y-MP/8-64 running UNICOS. The code runs on Cray/UNICOS, Cray/CTSS, IBM, VAX/VMS, and Sun workstations. The package is transmitted on either 1 DC 6150 (150 MB) cartridge or 8-mm tape in tar format. References: LA-12740-M (Oct. 1994). Fortran 77; Cray (CTSS & UNICOS), VAX/VMS, SUN/UNIX; IBM/AIX (P00355/MFMWS/00).
OP SYS: DOS
Language: Fortran 77, BASIC
Oak Ridge National Laboratory changed the DEXRAX utility code and install program to make them easier to use. The nuclear decay data for radiation dosimetry calculations were not changed. Users who have already received NUCDECAY from RSIC need not request this update. The unabridged data used in preparing International Commission on Radiological Protection (ICRP) Publication 38 and a monograph of the Medical Internal Radiation Dose (MIRD) Committee of the Society of Nuclear Medicine are distributed in this package. A more complete description of the data libraries and utility codes included in this packaged are given in the December 1994 newsletter. The executables and most of the source codes are provided. The Microsoft Fortran 5.1 compiler was used to compile the CHAINS code and the READDEC portion of the DEXRAX code. The full source for DEXRAX is not provided as that implementation must be linked with two special libraries. The source code is provided for a QBASIC version of the utility RADSUM. This version of RADSUM does not include plotting of the beta spectra or computations of the gamma constant. Other utilities were written in Microsoft BASIC Professional Development System. The package is distributed on two DS/HD 3.5-in. (1.44 MB) diskettes written in compressed DOS files. References: ORNL/TM-12350 (December 1993), Health Phys. 67(4):338-345 (1994). Fortran 77 and BASIC; PC 386 (D00172/PC386/01).
In serving a specialized area of scientific endeavor, it seems important that we note significant 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.
John H. Hubbell has been awarded the 1995 Outstanding Alumnus Award from the University of Michigan College of Engineering, Department of Nuclear Engineering. Hubbell received his B.S.E. in Engineering Physics from that institution in 1949. Most of his career has been with the National Institute of Standards and Technology. He has established a strong international reputation as an authority on quantitative data on radiation interactions. He developed the primary data base that defines photon interaction cross sections covering the energy range from soft x-rays to energetic gamma rays. He was instrumental in the founding of the International Radiation Physics Society and is now serving as its president.
Visitors during the month included Pedro Vaz, of the computer program service at the Nuclear Energy Agency Data Bank in Paris, France.
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.
September 1, 1995, is the deadline for receipt of papers from those wishing to participate in the Hardened Electronics and Radiation Technology (HEART) Conference. The conference will be held at the Naval Training Center, Orlando, Florida, March 18-21, 1996. This is a classified conference sponsored by the U.S. Department of Defense and the Department of Energy to provide a forum specifically for research and development of a classified or sensitive nature. Of particular interest are experimental and analytical observations that are both new and significant to the design and test or the economics of hardened systems. Technical papers, either classified up to the level of Secret Restricted Data or unclassified but restricted by export control (ITAR), are invited exclusively for consideration in the conference program. No CNWDI will be presented. All those in attendance will have security clearances certified by DOD and DOE officials to be appropriate for receipt of this information.
Information for submission of papers may be obtained from Logicon/RDA, ATTN: 1996 HEART Conference, Mr. Ed. Quinn, 2100 Washington Blvd., Arlington, VA 22204-5706. (phone 703-486-3500 ext. 2235; fax 703-920-4710).
Group XTM at Los Alamos National Laboratory is offering two MCNP classes during the summer. Electron/Photon Calculations with MCNP will be held July 18-21, and Variance Reduction Techniques with MCNP will be held August 15-17. Both classes will be held at Los Alamos National Laboratory. Enrollment is limited so it is advisable to get your registration in early. A brief description of the classes follows.
Electron/Photon Calculations is an introductory class with particular emphasis on the use of MCNP for coupled electron-photon transport problems. The course will include interactive computer sessions. Time will also be available to discuss individual questions and problems with MCNP experts, or to pursue in more detail topics mentioned in the talks. Topics to be covered include: Installation and execution of MCNP, and multitasking; Basic and advanced geometry; Source definition; Data and material specification; Tally specification; Pulse-height tallies, energy, and charge deposition; Statistical analysis and variance reduction; Plotting of geometry, tallies, particle tracks, and data; Aspects of electron-photon transport: Condensed-history Monte Carlo, Stopping powers and straggling, Bremsstrahlung, Dose and dose enhancement, Multigroup electron transport. Some knowledge of UNIX is required. An MCNP manual will be provided for use in the classroom.
Variance Reduction Techniques with MCNP will be on the level of the Los Alamos report "A Sample Problem for Variance Reduction in MCNP" (LA-10363-MS). The course is appropriate for novice and mid-level variance reduction practictioners. Prospective students should be capable of adding cells to a simple existing MCNP input file supplied by the instructor. The course will be in two parts. First, the instructor will lead the class through an MCNP variance reduction example. The problem will be analyzed by the class as a whole with guidance from the instructor. The variance reduction methods will then be tested on the computer. Second, the instructor will supply a difficult variance reduction problem and let each student apply his choice of variance reduction techniques to his own MCNP run of the supplied problem. The course will be an overview of most variance reduction techniques in MCNP and not an in-depth consideration of any. In fact, the techniques will only be described in the context of one or two conceptually simple, but demanding, transport problems, with enough theory presented to describe the general flavor of the techniques. The course will assume a general familiarity with Monte Carlo transport terms such as particle weight, roulette, score, bias, etc. Before coming to the course students not familiar with such terms should read: MCNP Chapter 2 Section VII. Subsection A pages 2-112 through 2-117. Specific techniques to be covered are: 1)Energy and Time Cutoffs; 2)Geometry Splitting/Russian Roulette; 3)Energy Splitting/Roulette; 4)Implicit Capture and Weight Cutoff; 5)Forced Collisions; 6)DXTRAN; 7)Weight Windows; 8)Weight Window Generator; 9)The Exponential Transform; 10)Source Biasing.
Address all correspondence regarding either of these classes to Judith Briesmeister, Group XTM MS B226, Los Alamos, NM USA 87545 (email firstname.lastname@example.org , phone: 505-667-7277, FAX: 505-665-5538).
Your attention is directed to the following events of interest.
Transport Methodologies and Uncertainty Estimation for PWR Vessel Fluence and BWR Shield/Shroud Dose Calculations, June 19-23, 1995, a workshop sponsored by Penn State Nuclear Engineering Department and GPU Nuclear Corp. Contact: Prof. Ali Haghighat, Penn State University, Nuclear Engg. Dept., 231 Sackett Bldg., University Park, PA 16802 (phone 814-865-0039, fax 814-865-8499, email: email@example.com, WWW: http://gracie.psu.edu/~haghigha/annc.html).
7th International Symposium on Nuclear Reactor Surveillance and Diagnostics, June 19-23, 1995, Avignon, France. Contact: OECD Nuclear Energy Agency, Conference Section, Le Seine St. Germain, 12, blvd. Des Iles, F-92130 Issy-les-Moulineaux, France, (fax 33-1-45241110).
ANS Workshop on An Update on Nuclear Decommissioning, Decontamination, and Restoration Technology, June 25-26, 1995, Philadelphia, Pennsylvania. Contact: ANS Meetings Dept., 555 N. Kensington Ave., La Grange Park, IL 60525 (phone 708-579-8258).
ANS Annual Meeting, June 25-29, 1995, Philadelphia, Pennsylvania. Contact: Dickinson M. Smith, PECO Energy Company, MC 63C-3, 965 Chesterbrook Blvd., Wayne, PA 19087-5681 (phone 215-640-6600) or ANS Meetings Dept., 555 N. Kensington Ave., La Grange Park, IL 60525 (phone 708-579-8258).
Environmental Monitoring, June 26-30, 1995, 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 615-576-3576 or 615-241-4888; fax 615-576-9383).
Conference on Radiation Protection and Medicine, June 28-30, 1995, Montpellier, France. Contact: European Commission, DG X11/F6, Mr. H. Schibilla, 200 rue de la Loi, Building Arts 3/58, B-1049, Brussels, Belgium (fax 32-2-2966256).
International Low-Level Waste Conference & Exhibit Show '95, July 10-12, 1995, Orlando, Florida. Contact: Paul Williams (phone 216-723-0915).
Health Physics Society Summer School on Reactor Health Physics, July 16-21, 1995, Beverly, Massachusetts. Contact: Health Physics Society, 1313 Dolly Madison Blvd., Suite 402, McLean, VA 22101 (phone: 703-790-1745; fax: 703-790-2672).
1995 Radiation Effects Data Workshop, July 17, 1995, Middleton, Wisconsin. Contact: D. G. Platteter (phone 812- 854-1808).
International Symposium on Physics and Detectors at LHC, July 19-21, 1995, Dubna, Russian Federation. Contact: Joint Inst. for Nuclear Research, T. Donskova, 141980, Dubna, Moscow Region, Russian Federation (fax: 007-095-975-2381; email: firstname.lastname@example.org).
32nd Annual IEEE International Nuclear and Space Radiation Effects Conference, July 21-27, 1995, Madison, Wisconsin. Contact: United Technologies, Microelectronics Center, 1575 Garden of the Gods Road, Colorado Springs, CO 80907 (fax 719-594-8187).
HPS-AAPM Joint Annual Meeting, July 23-27, 1995, Boston, Massachusetts. Contact: HPS (phone 703-790-1745).
Joint Annual Meeting of the Health Physics Society and the American Association of Physicists in Medicine to Celebrate the X-Ray Centennial, July 23-27, 1995, Boston, Massachusetts. Contact: Health Physics Society, ATTN: Richard J. Burke, Jr., Suite 130, 8000 Westpark Drive, McLean, VA 22102 (phone 703-790-1745; fax 703-790-9063) or American Association of Physicists in Medicine, ATTN: Salvatore Trofi, Jr., One Physics Ellipse, College Park, MD 20740-3846 (phone 301-209-3350; fax 301-209-0862).
3rd Annual Conference on the Recycle and Reuse of Radioactive Scrap Metal, July 31-Aug. 3, 1995, Knoxville, Tennessee. Contact: Tad McGalliard, University of Tennessee, EERC Center, 327 South Stadium Hall, Knoxville, TN 37996-0710 (phone 615-974-4251).
10th Brazilian Meeting on Reactor Physics and Thermal Hydraulics (X ENFIR) and the 3rd Brazilian Meeting on Nuclear Applications (III ENAN), Aug. 7-11, 1995, Rio de Janeiro, Brazil. Contact: Wilma S. Bastos, IEN, C.P. 68550, CEP-21945.970, RJ, Brazil (fax 55-21-5902692: email IENRCB@BRLNCC.BITNET).
Environmental Remediation Conference: Committed To Results, Aug. 13-18, 1995, Denver, Colorado. Contact: Environmental Resources Specialist, Inc., P.O. Box 440112, Aurora, CO 80044 (phone 303-690-4245).
Computational Methods in Reactor Analysis and Shielding, Aug. 14-18, 1995, 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 615-974-2525 (fax 615-974-0668).
Nuclear Criticality Safety, Aug. 14-18, 1995, 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 615-974-2525 (fax 615-974-0668).
Safe Use of Radionuclides, August 21-25, 1995, 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 615-576-3576 or 615-241-4888; fax 615-576-9383).
Symposium on Tomography in Nuclear Medicine: Present Status and Future Prospects, Aug. 21-25, 1995, Vienna, Austria. Contact: IAEA (phone 43-1-2360-1310; fax 43-1-234564).
International Nuclear Physics Conference, Aug. 21-26, 1995, Beijing, China. Contact: INPC '95 (phone 86-1-935- 7787; fax 86-1-935-7008).
5th Workshop on Heavy Charged Particles in Biology and Medicine, Aug. 23-25, 1995, Darmstadt, Germany. Contact: GSI Biophysik, Herr G. Kraft, Planckstr. 12, D-64291, Darmstadt, Germany (fax 49-6151-3592106).
10th International Congress of Radiation Research, Aug. 27-Sept. 1, 1995, Würzburg, Germany. Contact: Congress Secretariat (phone 49-89-3187-2669; fax 49-89-3187-3362).
Seminar on Requirements for the Safe Management of Radioactive Waste, Aug. 28-Sept. 1, 1995, Vienna, Austria. Contact: IAEA (43-1-2360-1310; fax 43-1-234564).
5th International Conference on Radioactive Waste Management and Environmental Remediation, Sept. 3-9, 1995, Berlin, Germany. Contact: ASME Headquarters, Ms. L. Friedman, 345 East 47th St., New York, NY 10017-2392 (fax 212-705-7856) or Battelle Pacific Northwest Laboratory, MSIN K1-19, SC Slate, P.O. Box 999, Richland, WA 99352 (fax 509-375-5963).
VOLGA-95, Sept. 4-8, 1995, in Volga, Russia. Contact: Prof. V. Khromov, Department Head, Chairman of Organizing Committee, Prof. V. Naumov, Program Chairman, or Dr. L. Goncharov, Scientific Secretary at the Moscow Engineering Physics Institute, Kashirskoe Shosse 31, Moscow, 115409, Russia (phone +7-095-323-9242; fax +7-095-324-7026; email email@example.com).
4th European Space Power Conference, Sept. 4-8, 1995, Poitiers, France. Contact: ESTEC, Power and Energy Conversion Div., Ms. J. Sanchez-Michielsen, P.O. Box 299, NL-2200, AG Noordwijk, Netherlands, or ESA Publications Division, T. D. Guyenne, NL-2200, AG Noordwijk, Netherlands (fax 31-1719-85433).
International Conference on Evaluation of Emerging Nuclear Fuel Cycle Systems (GLOBAL'95), Sept. 11-14, 1995, Palais des Congres, Versailles, France. Contact: Massimo Salvatores, CE/CADARACHE, DRN, Bat. 707, F-13108 ST. Paul-lez Durance Cedex, France (phone +33 42 25 33 65; fax: +33 42 25 41 42; internet : firstname.lastname@example.org)
Environmental Monitoring, Sept. 11-15, 1995, 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 615-576-3576 or 615-241-4888; fax 615-576-9383).
Fifth International Conference on Nuclear Criticality Safety (ICNC'95), Sept. 17-22, 1995, Albuquerque, New Mexico. Contact: R. Douglas O'Dell, ESH-6, MS F691, P.O. Box 1663, Los Alamos National Laboratory, Los Alamos, NM 87545 (phone 505-667-4614; fax 505-665-4970; email email@example.com).
Applied Health Physics, Sept. 18-Oct. 20, 1995, 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 615-576-3576 or 615-241-4888; fax 615-576-9383).
7th International Conference on Fusion Reactor Materials, Sept. 25-29, 1995, Obninsk, Russian Federation. Contact: Inst. of Physics and Power Engineering, Prof. V. M. Chernov, 249020, Obninsk, Kaluga Region, Russian Federation (fax 007-095-230-2326).
16th Symposium on Fusion Engineering, Sept. 30-Oct. 4, 1995, Urbana, Illinois. Contact: Cella Elliott, Conference Secretary, Fusion Studies Lab., University of Illinois, Urbana, IL 61801 (phone 217-333-2772; fax 217-333-2906; email firstname.lastname@example.org).
3rd International Workshop on Dosimetry for Radiation Processing, Oct. 1-6, 1995, Québec, Canada. Contact: John D. Rickey, Far West Technology, Inc., 330 D S. Kellogg, Goleta, CA 93117 USA (phone 805-964-3615; fax 805-964-3162).
International Conference on Radiation Dose Management, Oct. 3-5, 1995, Windermere, United Kingdom. Contact: European Nuclear Society, Belpstrasse 23, CH-3007, Bern, Switzerland.
International Symposium on Nuclear Energy, Oct. 20-21, 1995, Bucharest, Romania. Contact: C. Briatianu, Univ. Politechnicadin Bucuresti, Facultateade Inginerie Mecanica, Splaiul Independentei Nr. 313, Sector 6, 77206, Bucharest, Romania (phone 40-1-6314010/224).
Annual Meeting of the Society for Industrial and Applied Mathematics, Oct. 23-26, 1995, Charlotte, North Carolina. Contact: Soc. for Indus. and App. Math., 3600 University City Sciences Center, Philadelphia, PA 19104-2688 (fax 215-386-7999, email email@example.com).
International High-Level Radioactive Waste Management, Nov. 11, 1995, Las Vegas, Nevada. Contact: Allen G. Croff, ANS, 555 N. Kensington Ave., La Grange Park, IL 60525.
Environment Safety and Health Conference, Nov. 13-17, 1995, Denver, Colorado. Contact: Eleanor Crampton, U.S. Department of Energy, EH-51, 270CC Washington, DC 20875-0963 (301-903-3732).
ANS International Topical Meeting on Managing Plant Life, Nov. 28-30, 1995, Nice, France. Contact: Dr. S. Charbonneau, Tour Fiat, Cedex 16, F-92024, Paris, France.
11th International Conference on Packaging and Transportation of Radioactive Materials, Dec. 3-8, 1995, Las Vegas, Nevada. Contact: Laura Dechter, Social & Scientific Systems, Inc., 7101 Wisconsin Ave., Bethesda, MD 20814-4805 (phone 301-986-4870; fax 301-913-0351).
96th Annual Meeting of the American College of Nuclear Physicians, Jan. 14-18, 1996, San Juan, Puerto Rico. Contact: American College of Nuclear Physicians, Mr. H. Johnson, Suite 700, 1101 Connecticut Ave., NW, Washington, DC 20036.
3rd ASME/JSME International Conference on Nuclear Engineering, Mar. 10-13, 1996, New Orleans, Louisiana. Contact: ASME Meetings Dept., P.O. Box 2900, 22 Law Drive, Fairfield, NJ 07007-2900 USA (fax: 201-882-1717 or 201-882-5155; email: firstname.lastname@example.org).
1996 HEART Conference, Mar. 1821, 1996, Orlando, Florida. Contact: William A. Seidler, JAYCOR, Suite 110, 4970 Corporate Drive, Huntsvill, AL 35805 (phone 205-837-9100).
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. NRC, Office of NRR, 12H5, Washington, DC 20555 (phone 301-504-3075).
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.
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).
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).
The following literature cited has been ordered for review, and that selected as suitable will be placed in the RSIC 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 RSIC. 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.
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.
App. Math. Computation, 69, 255-262 . . . A Note on the Epstein-Hubbell Generalized Elliptic-Type Integral. . . . Srivastava, R. . . . 1995 . . . University of Victoria, British Columbia, Canada.
Health Phys., 68; 723-730 . . . Shielding Design and Dose Assessment for Accelerator Based Neutron Capture Therapy. . . . Howard, W.B.; Yanch, J.C. . . . May 1995 . . . Massachusetts Institute of Technology, Cambridge, MA.
Health Phys., 68, 627-631 . . . Application of the HSEF to Assessing Radiation Risks in the Practice of Radiation Protection. . . . Bond, V.P.; Varma, M.; Feinendegen, L.E.; Wuu, C.S.; Zaider, M. . . . May 1995 . . . Brookhaven National Laboratory, Upton, NY; Department of Energy, Washington, DC; Institute for Medicine, Nuclear Research Center, Julich, Germany; Columbia University, New York, N.Y.
Nucl. Instrum. Meth. Phys. Res., 340, 283-292 . . . Simulation of the Reconfigurable-Stack Test Calorimeter Experiments with CALOR89. . . . Job, P.K.; Price, L.E.; Proudfoot, J.; Handler, T.; Gabriel, T.A. . . . February 1994 . . . Argonne National Laboratory, Argonne, IL; University of Tennessee, Knoxville, TN; Oak Ridge National Laboratory, Oak Ridge, TN.
Nucl. Instrum. Meth. Phys., Res., 340, 371-378 . . . Neutron Detection Using GSO Scintillator. . . . Reeder, P.L. . . . February 1994 . . . Pacific Northwest Laboratory, Richland, WA.
Nucl. Instrum. Meth. Phys., Res., 349, 506-514 . . . Systematic Study of Neutron Production Cross Sections for Heavy Ions by Intranuclear Cascade-Evaporation Calculations. . . . Shin, K.; Miyahara, K.; Uwamino, Y. . . . 1994 . . . Kyoto University, Kyoto, Japan; University of Tokyo, Tokyo, Japan.
J. Radioanal. Nucl. Chem., Letters 199, 57-63 . . . A Short Contribution to the Hubbell Expression for the Radiation Field from a Class of Disk-Shaped Sources. . . . Timus, D.M. . . . July 1994 . . . Institute of Atomic Physics, Bucharest, Romania.
Nucl. Sci. Technol. 31, 590-595 . . . Activity Characterization of Thin Samples Moving in Front Disk-Shaped Isotropically Emitting Sources. . . . Timus, D.M.; Hubbell, J.H.; Kalla, S.L. . . . June 1994 . . . Institute of Atomic Physics, Bucharest, Romania; National Institute of Standards and Technology, Gaithersburg, MD; Facultad de Ingineria, Universidad del Zulia, Maracaibo, Venezuela.
Nucl. Technol., 110, 1-21 . . . Feasibility Assessment of Burnup Credit in the Criticality Analysis of Shipping Casks with Boiling Water Reactor Spent Fuel. . . . Broadhead, B.L. . . . April 1995 . . . Oak Ridge National Laboratory, Oak Ridge, TN.
Nucl. Technol., 110, 22-31 . . . Evaluation of Burnup Credit for Fuel Storage Analysis - Experience in Spain. . . . Conde, J.M.; Recio, M. . . . April 1995 . . . Consejo de Seguridad Nuclear Justo Dorado, Madrid, Spain.
Nucl. Technol., 110, 33-39 . . . Burnup Credit Experiences with the GA-4 Cask. . . . Boshoven, J.K. . . . April 1995 . . . General Atomics, San Diego, CA.
Nucl. Technol., 110, 40-52 . . . Study on the Criticality Safety Evaluation Method for Burnup Credit in JAERI. . . . Naito, Y.; Takano, M.; Kurosawa, M.; Suzaki, T. . . . April 1995 . . . Japan Atomic Energy Research Institute, Ibaraki, Japan.
Nucl. Technol., 110, 53-70 . . . Validation of SCALE-4 for Burnup Credit Applications. . . . Bowman, S.M.; DeHart, M.D.; Parks, C.V. . . . April 1995 . . . Oak Ridge National Laboratory, Oak Ridge, TN.
Nucl. Technol., 110, 71-85 . . . Three-Dimensional PDQ Validation for Calculating Core Parameters of a Uranium-Aluminide-Fueled Test Reactor. . . . Kim, S.S.; Judd, J.L. . . . April 1995 . . . Idaho National Engineering Laboratory, EG&G Idaho, Inc.; Idaho Falls, ID.
Nucl. Technol., 110, 93-105 . . . A Comparison of Two Versions of a Proposed Test Reactor Using the MCNP Neutronics Code. . . . Jahshan, S.N.; Terry, W.K. . . . April 1995 . . . Idaho National Engineering Laboratory, Idaho Falls, ID.
Nucl. Technol., 110, 115-131 . . . Preliminary Investigation of Actinide and Xenon Reactivity Effects in Accelerator Transmutation of Waste High-Flux Systems. . . . Olson, K.R.; Henderson, D.L.; Woosley, M.L., Jr.; Sailor, W.C. . . . April 1995 . . . University of Wisconsin-Madison, Madison, WI; University of Virginia, Charlottesville, VA; Los Alamos National Laboratory, Los Alamos, NM.
Nucl. Technol., 110, 168-180 . . . Monte Carlo Calculations for Recriticality During the Reflood Phase of a Severe Accident in a Boiling Water Reactor. . . . Mosteller, R.D.; Rahn, F.J. . . . May 1995 . . . Los Alamos National Laboratory, Los Alamos, NM; Electric Power Research Institute, Palo Alto, CA.
Nucl. Technol., 110, 181-197 . . . Modeling Fission Product Vapor Transport in the Falcon Facility. . . . Shepherd, I.M.; Drossinos, Y.; Benson, C.G. . . . May 1995 . . . Joint Research Center, Ispra, Italy; AEA Technology, Winfrith, Dorchester, England.
Nucl. Technol., 110, 198-219 . . . Application of Nonlinear Nodal Diffusion Generalized Perturbation Theory to Nuclear Fuel Reload Optimization. . . . Maldonado, G.I.; Turinsky, P.J. . . . May 1995 . . . North Carolina State University, Raleigh, NC.
Nucl. Technol., 110, 228-237 . . . Artificial Neural Networks Optimization Method for Radioactive Source Localization. . . . Wacholder, E. Elias, E.; Merlis, Y. . . . May 1995 . . . Israel Institute of Technology, Haifa, Israel.
INDC(NDS)-316 . . . FENDL Neutronics Benchmark: Specifications for the Calculational Neutronics and Shielding Benchmark. . . . Sawan, M.E. . . . December 1994 . . . IAEA Nuclear Data Section, Wagramerstrasse, Vienna.
INDC(NDS)-318 . . . FENDL Activation Benchmark: Specifications for the Calculational Activation Benchmark. . . . Sawan, M.E. . . . December 1994 . . . University of Wisconsin, Madison, WI.
JAERI-Research 95-017 . . . Bulk Shielding Experiment on a Large SS316/Water Assembly Bombarded by D-T Neutrons, Volume I: Experiment. . . . Konno, C.; Maekawa, F.; Oyama, Y.; Ikeda, Y.; Uno, Y.; Verzilov, Y.; Wada, M.; Maekawa, H. . . . March 1995 . . . Japan Atomic Energy Research Institute, Ibaraki-ken, Japan.
JAERI-Research 95-018 . . . Bulk Shielding Experiment on a Large SS316/Water Assembly Bombarded by D-T Neutrons, Volume II: Analysis. . . . Maekawa, F.; Konno, C.; Wada, M.; Oyama, Y.; Ikeda, Y.; Uno, Y.; Verzilov, Y.; Maekawa, H. . . . March 1995 . . . Japan Atomic Energy Research Institute, Ibaraki-ken, Japan.
KEK Proceedings 94-8 . . . Proceedings of the Fourth EGS4 Users' Meeting in Japan. . . . Hirayama, H., ed.; Namito, Y., ed.; Ban, S., ed. . . . November 1994 . . . National Laboratory for High Energy Physics, Ibaraki-ken, Japan . . . . . . July 25-27, 1994, KEK, Tsukuba, Japan.
KEK Preprint 94-154 . . . Validity of the Concept of Absorbed Dose as a Physical Quantity. . . . Tada, J.; Katoh, K. . . . December 1994 . . . National Laboratory for High Energy Physics, Ibaraki-ken, Japan . . . . . . Submitted to J. Phys. Soc. Jpn..
NISTIR 5632 . . . 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. . . . Hubbell, J.H.; Seltzer, S.M. . . . May 1995 . . . National Institute of Standards and Technology, Gaithersburg, MD.
ORNL/TM-12294/V1 . . . Scale-4 Analysis of Pressurized Water Reactor Critical Configurations: Volume 1- Summary. . . . DeHart, M.D. . . . March 1995 . . . Oak Ridge National Laboratory, Oak Ridge, TN.
ORNL/TM-12294/V2 . . . Scale-4 Analysis of Pressurized Water Reactor Critical Configurations: Volume 2- Sequoyah Unit 2 Cycle 3. . . . Bowman, S.M.; Hermann, O.W.; Brady, M.C. . . . March 1995 . . . Oak Ridge National Laboratory, Oak Ridge, TN; Sandia National Laboratories, Las Vegas, NV.
ORNL/TM-12294/V3 . . . Scale-4 Analysis of Pressurized Water Reactor Critical Configurations: Volume 3- Surry Unit 1 Cycle 2. . . . Bowman, S.M.; Hermann, O.W. . . . March 1995 . . . Oak Ridge National Laboratory, Oak Ridge, TN.
ORNL/TM-12294/V4 . . . Scale-4 Analysis of Pressurized Water Reactor Critical Configurations: Volume 4- Three Mile Island Unit 1 Cycle 5. . . . DeHart, M.D. . . . March 1995 . . . Oak Ridge National Laboratory, Oak Ridge, TN.
ORNL/TM-12667 . . . Validation of the Scale System for PWR Spent Fuel Isotopic Composition Analyses. . . . Hermann, O.W.; Bowman, S.M.; Brady, M.C.; Parks, C.V. . . . March 1995 . . . Oak Ridge National Laboratory, Oak Ridge, TN; Sandia National Laboratories, Las Vegas, NV.
Y/DD-631 . . . Additional Critical Experiments for Computer Code Validation Base. . . . Elliott, E.P.; Tollefson, D.A.; Vornehm, R.G. . . . April 1994 . . . Oak Ridge Y-12 Plant, Oak Ridge, TN.
KEK Proceedings 94-8 EGS4
Proceedings of the Fourth EGS4 Users' Meeting in Japan. . . . Hirayama, H., ed.; Namito, Y., ed.; Ban, S., ed. . . . November 1994 . . . National Laboratory for High Energy Physics, Ibaraki-ken, Japan.
A New MCNP Trademark Test Set. . . . Brockhoff, R.C.; Hendricks, J.S. . . . 09/94 . . . USDOE, Washington, DC; Los Alamos National Laboratory, Los Alamos, NM . . . INIS (mf only); OSTI; NTIS; GPO.
Nucl. Instrum. Meth. A340, 379-383 LISA
LISA - A Powerful Program Package for Listmode and Spectral Data Analysis. . . . Oberstedt, A.; Hambsch, F.-J. . . . 1994 . . . CEC-JRC Inst. for Ref. Materials and Measurements, Geel, Belgium.
The HET Mini-Manual. . . . Eccleston, R.S.; Osborn, R. . . . November 1994 . . . British Library Doc. Supply Ctr., Boston Spa, Wetherby, West Yorks Rutherford Appleton Lab., Chilton, United Kingdom.
THERMAL: A Routine Designed to Calculate Neutron Thermal Scattering. . . . Cullen, D.E. . . . 02/95 . . . Lawrence Livermore National Laboratory, Livermore, CA.