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. 367 June 1995
Advanced Neutron Source Shielding
Fusion Reactor Shielding
Point Kernel Techniques & Applications
Space Reactor Shielding
Transport Theory Analysis
Advancements in Discrete Ordinates Methods
Applications of Discrete Ordinates Methods
Advancements in Monte Carlo Methods
Applications of Monte Carlo Methods
Comparison of D.O. and M.C. Methods
Benchmark Experiments & Integral Tests
Cross Section Libraries and Data Uncertainties
Graphical User Interfaces
Non-Traditional Geometries for Transport Applications
PC Applications/Computer Visualization
Radiation Dosimetry and Material Damage
Radiation Detection and Measurement
Reactor Cavity Gamma Dosimetry
Pressure Vessel Dosimetry
Material Damage Correlations
Radioactive Waste Issues
Low-Level Waste Packaging & Site Design Issues
High-Level Waste Packaging & Site Design Issues
Interim Spent Fuel Storage & Transport Casks
Site Characterization and Decommissioning
Health Physics/Medical Issues
ALARA Program Developments
Environmental Monitoring for Public Perception
Implications of 10CFR20 on Worker Perceptions
Computational Methods for Medical Applications
Radiation Epidemiology and Health Effects
Radiation Protection Standards for Medical Applications
Component Activation Analysis
Argonne National Laboratory contributed a newly frozen version of this code system to calculate site-specific residual radioactive material guidelines and radiation dose and excess cancer risk to an on-site resident. Version 5.60 major improvements include an enhanced plotting program, user interface, the use of Federal Guidance Reports (FGR) 11 and 12 for internal and external dose conversion factors (DLC-167/FGR-DOSE), and a new external dose model. External dose is calculated for any size, depth, and shape of contaminated soil based on values listed in FGR 12.
The Lahey F77L/EM32 and Microsoft Quick BASIC Version 7.1 software packages were used to create the executable included in the package. Note that the source files are not included. The package is distributed on one DS/HD 3.5-in. (1.44 MB) diskette in self-extracting compressed DOS files. Reference: ANL/EAD/LD-2 (Sept. 1993) and ANL/EAIS-8 (April 1993). Fortran 77 and BASIC; PC 386 or 486 (C00552/PC386/02).
Oak Ridge National Laboratory contributed this U.S. Army radiological bioassay and dosimetry software package. RBD computes the quantity of a radionuclide taken into the body by inhalation, ingestion, or uptake from a wound based on measurements of the retained activity in the body or its appearance in excreta; i.e., bioassay measurements. RBD evaluates both acute and chronic intakes. The package includes database programs for management of the bioassay data and the estimated intakes and radiation doses. Graphical inspection of the data and the computed response are available in the interactive mode. Estimates of intake are derived by convolution of biological response functions in the manner outlined in Publication 54 of the International Commission on Radiological Protection. Dose estimates are derived from the estimated intake using dose coefficients from Federal Guidance Report 11 (DLC-167/FGR-DOSE). Only the initial activity at the wound site is evaluated; i.e., no dose estimates are provided.
RBD was designed for use on a PC running DOS. The package consists of database and computational programs interconnected by a menuing program. The database programs were developed using Clipper. The menu program and other user interface routines were written in MS BASIC using the MS PDS v7.1. All computational programs were written using MS Fortran v5.1. Note that source files are not included in this distribution. RBD is transmitted on one DS/HD 3.5-in. (1.44 MB) diskette in DOS compressed files. Reference: ORNL/TM-11858 (1993). Fortran, BASIC, Clipper; IBM PC (C00632/IBMPC/00).
The Centre de Radioprotection et Sûreté in Algeria contributed a code system for the analysis of materials test reactor (MTR) cores. RETRAC uses a set of coupled neutron point-kinetics equations and thermal-hydraulic conservation laws to simulate nuclear reactor core behavior under transient or accident conditions. The reactor core is represented by a single equivalent unit cell composed of three regions: fuel, clad, and moderator (coolant). The numerical resolution is performed using the Range-Kutta-Gill method. The externally inserted reactivity is specified in the input data file, whereas Doppler, fuel, clad, and water temperature reactivity feedbacks are calculated by the code itself. The code is written in Fortran 77 and runs on Vax computers under VMS. Reference: CRS report (Sept 1993). Fortran 77; Vax (C00635/D0VAX/00).
The Nuclear Research Institute, e near Prague, Czech Republic, contributed a new code package. FEDGROUP-R processes evaluated nuclear data from files in ENDF/B format to prepare group cross sections for reactor physics calculations. In particular, data for ABBN and WIMS group libraries can be generated. This release is based on FEDGROUP-2 and FEDGROUP-3 (PSR-123). There are some completely new modules included, in particular, the module for calculating cross sections in the resonance region, including calculation of self-shielded quantities. In the calculation of cross sections in the resonance region in general the methods described for LINEAR and RECENT codes (PSR-351/PREPRO-94) have been applied. Generally, data from ENDF/B-IV, V, or VI can be processed with the following limitations: 1) Only Breit-Wigner resonance formalism is included and 2) MF=6 files are not processed.
FEDGROUP-R has run on EC1040, DEC VAX, and IBM PC or compatible computers with a math coprocessor. Executables created with Microsoft Fortran v5.1 under MS-DOS 6.2 are included in the package. Reference: UJV 9683R (1992). Fortran; EC 1040, VAX, IBM PC (P00349/MNYCP/00).
Oak Ridge National Laboratory updated the retrieval program in this data library of dose coefficients for both intakes and external exposures to radionuclides from Federal Guidance Reports 11 and 12. Dose coefficients for radionuclide intake (dose per unit activity inhaled or ingested) in FGR 11 were abstracted from the ICRP and the ORNL dosimetric data files assembled during the preparation of Publication 30 of the ICRP. The dose coefficients for external exposure (dose per unit radionuclide concentration) in FGR 12 are based on new calculations of the radiation field for nuclides distributed in the environment. The data retrieval programs READEM and CHAIN were compiled and linked using MS Fortran 5.0. In this update minor modifications were made to standardize the programs READEM and CHAIN. READEM was revised to correct an end-of-file error which occurred when trying to read inhalation data for Md-258, the last nuclide in the index file. Notes were added on modifications necessary for use with the Lahey F77L/EM-32 compiler. READEM illustrates the manner in which the dose coefficient files might be accessed by other software. The package is transmitted on one DS/HD 5.25-in. (1.2 MB) diskette in self-extracting compressed DOS files. References: EPA 402-R-93-081 (Sept. 1993) and EPA-520/1-88-020 (Sept. 1988). Fortran; All Computers (D00167/ALLCP/01).
Introduction to MCNP will be held for people who have never used MCNP or have very limited experience with the code. Instruction will include interactive computer sessions. Time will 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: Basic and advanced geometry; Source definitions; Tallies; Data; Variance reduction; Statistical analysis; Criticality; Plotting of geometry, tallies, and particle tracks; and Neutron/photon/electron physics. Participants are expected to have little or no experience with MCNP. Some knowledge of UNIX is required. A manual will be provided for use while in the classroom.
Criticality Calculations with MCNP will feature advanced MCNP geometries using the new MCNP criticality primer. Setting up complex geometries easily, with emphasis on setting up accurate problem representations, and the new MCNP4A criticality features will be presented. An interactive hands-on computer experience is provided using progressively more advanced example problems.
One Day Tutorial for Novice Users will be held Monday, Oct. 16, for participants who have very limited or no experience with MCNP to get them up to speed for the following four days. If you have no UNIX experience, you are also encouraged to attend. The Monday class includes interactive computer sessions. If you do not attend the Monday class, you are expected to have some familiarity with MCNP. Some knowledge of UNIX is required because we will be using UNIX-based workstations. A manual will be provided for use while in the classroom. Time will be available to discuss individual questions and problems with MCNP experts or to pursue in more detail topics mentioned in the talks.
Address all correspondence regarding this class to Judith Briesmeister, email@example.com or contact by telephone 505-667-7277 or fax 505-665-5538.
Registration forms and other information are included in the back of this Newsletter. Because the class is being held at ORNL, the number of registrants will be limited to 24. Registrations will be accepted on a first-come basis and must include the full registration fee of $1,200. No FAX or e-mail registrations will be accepted. The increase in the registration fee reflects the transition to a full cost-recovery basis. Prior courses have been substantially underwritten by the DOE Transportation and Packaging Safety Division.
The course content will be similar to the course held in April, with some modifications based on feedback from that course. This course will cover the criticality, depletion, and shielding codes in SCALE. The heat transfer codes will not be included. If you are not interested or able to attend, but know someone who is, please pass this announcement to them. To obtain a registration form or more information, use fax (615-576-3513) or e-mail (firstname.lastname@example.org).
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).
3rd European Symposium on Radiations and Their Effects on Components and Systems, Sept. 18-22, 1995, Arcachon, France. Contact Europa Organisation, 40 Blvd. de Recollets, F-31405, Toulouse Cedex, France (fax 33-61 32 6600).
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).
ANS Winter Meeting, Oct. 30-Nov. 2, 1995, San Francisco. Contact: ANS, 555 N. Kensington Ae., La Grange Park, IL 60545
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).
29th Midyear Topical Meeting of the Health Physics Society: Naturally Occuring and Accelerator Produced Radioactive Material--Regulation and Risk Assessment, Jan 7-10, 1996, Scottsdale, Arizona. Contact: HPS Secretariat, Suite 402, 1313 Dolley Madison Blvd., McLean, VA 22101.
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.
Radiation Protection and Shielding Division Topical Meeting on Advancements and Applications in Radiation Protection and Shielding, Apr. 21-25, 1996, Falmouth, Massachusetts. Contact Keith Spinney, Yankee Atomic Electric Company, 580 Mail St., Boston, MA 01740-1398 (phone 508-779-6711 x 2039; fax 508-779-6730; email email@example.com).
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.
Nucl. Technol., 110, 321-356 . . . Parametric Systems Studies of the Aqueous-Based (Slurry) Blanket Concept for Accelerator Transmutation of Waste. . . . Beard, C.A.; Davidson, J.W.; Krakowski, R.A.; Battat, M.E. . . . June 1995 . . . Los Alamos National Laboratory, Los Alamos, New Mexico.
Nucl. Technol. 110, 369-395 . . . Preliminary Analysis of the Induced Structural Radioactivity Inventory of the Base-Case Aqueous Accelerator Transmutation of Waste Reactor Concept. . . . Bezdecny, J.A.; Vance, K.M.; Henderson, D.L. . . . June 1995 . . . University of Wisconsin-Madison, Madison, Wisconsin.
Nucl. Technol., 110, 422-435 . . . Application of High-Frame-Rate Neutron Radiography with a Steady Thermal Neutron Beam to Two-Phase Flow Measurements in a Metallic Rectangular Duct. . . . Hibiki, T.; Mishima, K.; Matsubayashi, M. . . . June 1995 . . . Kyoto University Research Reactor Institute, Kumatori-cho, Sennan-gun, Osaka, Japan; Japan Atomic Energy Research Institute tokai Research Establishment, Tokai-mura, Naka-gun, Ibaraki, Japan.
JAERI-Data/Code 94-003 . . . Attenuation Data of Point Isotropic Neutron Sources Up to 400MeV in Water, Ordinary Concrete and Iron. . . . Tanaka, S. . . . August 1994 . . . Japan Atomic Energy Research Institute, Ibaraki-ken, Japan.
JAERI-Data/Code 94-012 . . . Benchmark Problems for Intermediate and High Energy Accelerator Shielding. . . . Nakashima, H.; Sakamoto, Y.; Tanaka, S.; Hasegawa, A.; Fukahori, T.; Nishida, T.; Sasamoto, N.; Tanaka, S.; Nakamura, T.; Shin, K.; Hirayama, H.; Ban, . . . September 1994 . . . Japan Atomic Energy Research Institute, Ibaraki-ken, Japan.
JAERI-Data/Code 95-006 . . . A New Library of Neutron Group Constants for BERMUDA Based on JENDL-3.2 Nuclear Data File. . . . Nakashima, H.; Hasegawa, A.; Suzuki, T. . . . June 1995 . . . Japan Atomic Energy Research Institute, Ibaraki-ken, Japan.
INDC(NDS)-312 . . . Improved Evaluations and Integral Data Testing for FENDL. . . . Ganesan, S. . . . December 1994 . . . IAEA Nuclear Data Section, Vienna, Austria . . . . . . Summary Report of the IAEA Advisory Group Meeting organized by the IAEA in co-operation with the Max-Planck-Institut fur Plasmaphysik and held at the Max-Planck-Institut fur Plasmaphysik, Garching near Munich, Germany, 12-16 September 1994.
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.
J. Phys. Chem. Ref. Data, Vol. 23, 339-364 . . . A Review, Bibliography, and Tabulation of K, L, and Higher Atomic Shell X-Ray Fluorescence Yields. . . . Hubbell, J.H.; Trehan, P.N.; Singh, N.; Chand, B.; Mehta, D.; Garg, M.L.; Garg, R.R.; Singh, S.; Puri, S. . . . 1994 . . . National Institute of Standards and Technology, Gaithersburg, MD; Panjab University, Chandigarh, India.
Applied Math. Computation 61: 157-161 . . . On the Epstein-Hubbell Generalized Elliptic-Type Integral. . . . Todorov, P.G.; Hubbell, J.H. . . . 1994 . . . Paissii Hilendarski University, Plovdiv, Bulgaria; National Institute of Standards and Technology, Gaithersburg, MD.
Radiat. Phys. Chem. 43, 497-502 . . . Algorithms for the Approximation of the Generalized Hubbell Rectangular Source Integrals. . . . Galue, L.; Kalla, S.L.; Leubner, C. . . . 1994 . . . Universidad del Zulia, Maracaibo, Venezuela; Universitat Innsbruck, Innsbruck, Austria.
DESY D3-81 . . . Studies on the Neutron Field Behind the Shielding of Proton Accelerators, Part II: Iron Shielding. . . . Dinter, H.; Tesch, K.; Dworak, D. . . . April 1995 . . . Deutsches Elektronen-Synchrotron DESY, Hamburg, Germany; Institute of Nuclear Physics, Krakow, Poland.
DESY D3-80 . . . Studies on the Neutron Field Behind Shielding of Proton Accelerators, Part I: Concrete Shielding. . . . Dinter, H.; Tesch, K.; Dworak, D. . . . April 1995 . . . Deutsches Elektronen- Synchrotron DESY, Hamburg, Germany; Institute of Nuclear Physics, Krakow, Poland.
E3-94-437 . . . Recent Development of Radioanalytical Methods at the IBR-2 Pulsed Fast Reactor. . . . Nazarov, V.M.; Peresedov, V.F. . . . 1994 . . . . . . . . . Accepted by Organizing Committee of the Third International Conference on Methods and Applications of Radioanalytical Chemistry, Hawaii, April 10-16,.
E3-94-445 . . . The Dynamic Method for Time-of-Flight Measurement of Thermal Neutron Spectra from Pulsed Sources. . . . Pepyolyshev, Yu.N.; Chuklyaev, S.V.; Tulaev, A.B.; Bobrakov, V.F. . . . 1994 . . . RDIMT, Moscow, Russia . . . . . . Submitted to Nuclear Instruments and Methods A.
ORNL/CSD/TM-266 . . . Actinide Nuclear Data for Reactor Physics Calculations. . . . Brady, M.C.; Wright, R.Q.; England, T.R. . . . July 1991 . . . Oak Ridge National Laboratory, Oak Ridge, TN; Los Alamos National Laboratory, Los Alamos, NM.
NISTIR 5437 . . . Bibliography of Photon Total Cross Section (Attenuation Coefficient) Measurements 10 eV to 14.5 GeV, 1907-1993. . . . Hubbell, J.H. . . . May 1994 . . . National Institute of Standards and Technology, Gaithersburg, MD.
HDGOE6 v.15(1) 7-11 In Chinese RELAP4/MOD7Modified RELAP4/MOD7 Code and Large Break Loss of Water Accident Analysis. . . . Luo Bangqi . . . 02/94 . . . Beijing Inst. of Nuclear Engineering, Beijing, China.
IAEA-SM-333/90P 547-550 FRAM; MGA; TRIFIDComparison of Three Gamma Ray Isotopic Determination Codes: FRAM, MGA and TRIFID. . . . Cremers, T.L.; Malcolm, J.E.; Bonner, C.A. . . . 1994 . . . Los Alamos National Laboratory, Los Alamos, New Mexico.
JINR-E-2-94-352 CEM92MPhysics of the CEM92M Code. . . . Mashnik, S.G. . . . 1994 . . . Joint Inst. for Nuclear Research, Dubna, Russia Federation . . . INIS (mf only).
KEK Preprint 94-137 DAQBENCHPerformance Evaluation Tool of DAQ Computer DAQBENCH. . . . Yasu, Y.; Tajima, Y. . . . 11/94 . . . Tokyo Institute of Technology, Meguro, Tokyo, Japan.
NUREG/CR-5535 V. 6; EGG-2596 V.6 RELAP5/MOD3RELAP5/MOD3 Code Manual. Volume 6: Validation of Numerical Techniques in RELAP5/MOD3. . . . Shieh, A.S.; Ransom, V.H.; Krishnamurthy, R. . . . 10/94 . . . EG&G Idaho, Inc., Idaho Falls, ID; Nuclear Regulatory Commission, Washington, DC . . . INIS (mf only); OSTI; NTIS (Doc. only); ESTSC.