Post Office Box 2008
Oak Ridge, Tennessee 37831-6362
Lockheed Martin Energy Research Corp.
for the U.S. Department of Energy
under contract DE-AC05-96OR22464
Phone No. 423-574-6176
The 1998 ANS Radiation Protection and Shielding Division Topical Conference, held in Nashville, Tennessee, on April 19-23, was a rousing success with over 170 attendees from 16 different countries. The meeting got off to an excellent start with provocative and stimulating presentations by Theodore Rockwell and Alan Waltar. Rockwell addressed the issues associated with the debate on low level radiation and presented the attendees with some tough challenges and responsibilities for our technical community. (The text of his presentation follows.) In his usual enthusiastic style, Waltar reviewed the current and projected needs for nuclear energy and nuclear technologies for a wide range of applications. Both talks gave definitive reasons why we should be optimistic about the future for our field.
The technical program of approximately 125 presentations covered a wide range of traditional and emerging topics, including: Monte Carlo and discrete ordinates methods, reactor pressure vessel dosimetry, nuclear data, benchmark experiments, etc. The most rapidly growing area appears to be methods and analyses for nuclear medicine applications, since the number of sessions for this topic increased from one in 1996 to three at this meeting. Building on this interest, Dr. Gary Smith presented the banquet talk on the topic of current and developing technologies for nuclear medical imaging. The conference was followed by a two-day workshop, also well attended, covering the DORT and TORT discrete ordinates radiation transport codes.
In addition to the technical program, there was a lot of fun and good food. A highlight was the dinner cruise on the General Jackson river boat. All in all, the meeting reinforced the merits of the RPS&S policy of bi-annual topical meetings. The next topical conference is scheduled for September 2000, in Spokane, Washington.
The conference proceedings are available for $50/2-volume-set plus $10 shipping & handling. Contact Bryan Broadhead by phone at 423-576-4476 or by email at firstname.lastname@example.org promptly since the supply is limited.
D. T. Ingersoll
Two changes or additions were made to the computer code collection during the month. One new code system was packaged and added to the collection, and one code system was replaced with a newly frozen version.
Oak Ridge National Laboratory contributed a newly frozen version of this code system for simulating atomic collisions in crystalline targets using the binary collision approximation. The new release is designated Marlowe 14c and includes several corrections and enhancements. The algorithm for locating the next collision point in a trajectory was modified to correct an error which could occur when the first proposed site was vacant. A change was made to EVENT to correct an error which occurred when atoms experiencing non-local inelastic energy losses were followed to very low kinetic energies. Two key words were redefined and another was added to the MPP glossary. More information on these and other changes is included in Section 1.11 in the Marlowe User's Guide.
The system executes on IBM MVS, VAX VMS, Data General, MS-DOS and a variety of Unix systems (AIX, DG/UX, EP/IX, HP-UX, IRIX, DEC Unix, SunOS, Ultrix, and Unicos). This new MARLOWE14c also runs on Linux on an Intel PC. A limited version of the code runs on PCs under Windows using the Lahey Fortran 90 compiler. Source, scripts, test problems, and documentation files are included. No executables are included in this package, which is transmitted either on one DS/HD 3.5-in. (1.44MB) diskette in self-extracting compressed DOS files or on one diskette in a compressed tar file. References: Unpublished report (Sept. 1997), Phys. Rev. B 40, (1989), Nucl. Instrum. Methods in Phys. Res. B 48 (1990), and Nucl. Instrum. Methods in Phys. Res. B 67 (1992). Fortran 77 and C or Assembler; many computers (P00137/MNYCP/04).
Los Alamos National Laboratory, Los Alamos, New Mexico, contributed a new version of the NJOY Nuclear Data Processing System, a modular computer code for converting evaluated nuclear data in the ENDF format into libraries useful for application calculations. Because the Evaluated Nuclear Data File (ENDF) format is used worldwide (e.g., ENDF/B-VI in the US, JEF-2.2 in Europe, JENDL-3.2 in Japan, BROND-2.2 in Russia), NJOY gives its users access to a wide variety of up-to-date nuclear data. NJOY provides comprehensive capabilities for processing evaluated data, and it can serve applications ranging from continuous-energy Monte Carlo (MCNP), through deterministic transport codes (DANT, ANISN, DORT), to reactor lattice codes (WIMS, EPRI). NJOY handles a wide variety of nuclear effects, including resonances, Doppler broadening, heating (KERMA), radiation damage, thermal scattering (even cold moderators), gas production, neutrons and charged particles, photoatomic interactions, self shielding, probability tables, photon production, and high-energy interactions (to 150 MeV). Output can include printed listings, special library files for applications, and postscript graphics (plus color).
NJOY97 is a cleaned up version of NJOY 94.105 that features compatibility with a wider variety of compilers and machines, explicit double precisioning for 32-bit systems, a larger test-problem suite, a new revision control system, and some changes to the user input. This version was tested on a Cray YMP with both static and stack-based memory allocation with a Fortran-90 compiler, on a Sun Ultra in 32-bit mode using f90, on a Sun Ultra in 64-bit mode (-dbl) using f77, on a Pentium 90 using Linux g77 (32 bits with stack-based memory allocation), on an IBM RS/6000 using f77 (with f90 libraries available), and on Windows NT and Windows 95 using the Lahey LF90 Version 4 compiler. LF90 was used to create the PC executable included in the package. The Linux installation was run on Intel PC under RedHat Linux 5.0 with the EGCS package replacing the standard gcc compiler package. The package is transmitted on CD-ROM in Unix and DOS formats. References: LA-12740-M (Oct. 1994) and LA-12639-MS (1994). Fortran 77; Cray (UNICOS), SUN/UNIX; IBM/AIX.
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 email@example.com.
CINDER'90 is a radionuclide inventory program developed primarily for accelerator-driven radiation environments. The code uses medium- energy reaction-product production probabilities and lower-energy particle fluxes from transport codes (HETC, LCS, MCNPX) with a library of transmutation data to calculate temporal inventories of nuclides and their decay, absorption, fission, and hazard properties.
The imminent release of CINDER'90 and its data libraries is scheduled for late July 1998. No-fee classes, limited to sixteen users each, will be offered -- June 30July 1 and again July 1415 -- introducing the code, libraries, and applications. Those interested in attending can contact Bill Wilson at: firstname.lastname@example.org, voice 505-667-7749, fax: 505-667-9671, or W. B. Wilson, Nuclear Theory and Applications Group (T-2), Theoretical Division, Los Alamos National Laboratory, PO Box 1663, MS:B243, Los Alamos, NM 87545. A release package is now being accumulated for the class and for RSICC distribution.
Immediately following SARE-4/SATIF-4, the American Nuclear Society will hold a topical meeting, Accelerator Applications 1998 (AccApp'98) (see following announcement), organized by the ANS Accelerator Application Technical Working Group. This meeting will be held in Gatlinburg, Tennessee, from Sept. 20-23, 1998. The current development of the Spallation Neutron Source (SNS) at Oak Ridge makes Tennessee an ideal location for this series of meetings. SARE now has three highly successful workshops to its credit.
Proceedings from previous workshops are routinely used by the community involved in physics development and applications of radiation transport codes for accelerators. With the advent of new, high-powered spallation sources, high-intensity beams for hadron and muon colliders and other facilities, the need for validated simulation codes is critical. In the US, we will soon come under close scrutiny by agencies such as the Nuclear Regulatory Commission, whose standards of proof are much higher than anything most of us have ever encountered. It is vital that long-standing issues in accelerator radiation transport be solved quickly, to the highest degree of accuracy possible. As with the previous workshops, SARE-4 will cover most aspects of the simulation of accelerator-generated radiation fields in hadron and electron machines. Specific uses of our tools include, but are not limited to:
The SARE workshops support these activities through detailed discussions of the latest developments in radiation transport codes including Monte-Carlo, deterministic and analytic methods, as well as benchmarking and validation procedures. In addition to physics and code discussions, new results on applications of radiation transport codes and methods to accelerator facilities is highly encouraged. If you are confused as to where to submit your paper, SARE-4 or SATIF-4, keep in mind that presentations at SATIF are generally followups to specific assigned topics from the previous specialist's meeting. SARE is a conference format, for the presentation and discussion of new results. We look forward to your participation in SARE-4, and please pass this announcement along to others who might be interested. If you plan to attend SARE-4, please provide the information below and return it to Bernadette Kirk at email@example.com. Look for further information on our Web site: http://www-rsicc.ornl.gov/sare/sare. html.
I AM INTERESTED IN ATTENDING THE SARE-4 WORKSHOP:
The Second International Topical Meeting on Nuclear Applications of Accelerator Technology (AccApp'98) is sponsored by the Accelerator Applications Technical Group of the American Nuclear Society (ANS), and is hosted by the Oak Ridge-Knoxville, Tennessee, Section of the ANS. It will be held in Gatlinburg, Tennessee, during the week of September 20-23, 1998, at the Park Vista Hotel & Conference Center.
AccApp'98 will provide a forum for discussion of the uses of particle accelerator technology for nuclear applications. It will focus on production of neutrons and other particles, utilization of these particles for scientific or industrial purposes, production or destruction of radionuclides significant to energy, medicine, defense, or other endeavors, as well as imaging and diagnostics.
Papers are solicited in the following areas: applications, design, R&D needs, analytical methods, tools and databases, economics, safety and licensing. The Call For Papers with all relevant information and points of contact is located at http://www.engr.utk.edu/org/ans/AccApp98.
The language of the meeting will be English with no simultaneous translation provided. Those who wish to present a paper at the meeting should send an abstract of the paper, as soon as possible, but not later than August 1, 1998. Further information about the meeting is available from Dr. José Rubens Maiorino, Chairman 1998-RERTR Meeting, Comissão Nacional de Energia Nuclear, Instituto de Pesquisas Energéticas e Nucleares, Diretoria de Reatores, Travessa R 400 - Cidade Universitária- CEP: 05508-900, São Paulo - SP - Brazil (phone (55-11) 816-9111, fax (55-11) 816-9432, email: firstname.lastname@example.org), or please visit the webpage at url http://www.ipen.br/r/rertr/rertr.html).
Abstracts of 400 words should be sent by the end of January 1999. Notification of acceptance will be made by the end of March 1999. A full paper should to be sent to Program Secretary by the end of July 1999. Manuscripts for both abstracts and papers should be sent via Web or as an electronic file with attached text files. The proceedings will be distributed on CD at the conference. 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 email@example.com) or from the web page at http://icrs9.tokai.jaeri.go.jp.
Your attention is directed to the following events of interest.
Radiation Oncology Resident's Review in Radiation Oncology Physics and Radiation Biology, May 11-15, 1998, a continuing education course offered by the University of Texas at San Antonio. Contact: The University of Texas Health Science Center at San Antonio, Continuing Medical Education, 7703 Floyd Curl Dr., San Antonio, TX 78284-7980 (phone 210-567-4491; fax 210-567-6964).
Physicist's Review in Radiation Oncology Physics, May 11-15, 1998, a continuing education course offered by the University of Texas at San Antonio. Contact: The University of Texas Health Science Center at San Antonio, Continuing Medical Education, 7703 Floyd Curl Dr., San Antonio, TX 78284-7980 (phone 210-567-4491; fax 210-567-6964).
Computational Methods in Reactor Analysis and Shielding, May 18-22, 1998, Knoxville, Tennessee, a short course offered by the University of Tennessee-Knoxville. Contact: Lydia Salmon, Dept. of Nuclear Engineering, University of Tennessee, Knoxville, TN 37996 (phone 423-974-2525; email firstname.lastname@example.org).
Nuclear Criticality Safety, May 18-22, 1998, Knoxville, Tennessee, a short course offered by the University of Tennessee-Knoxville. Contact: Lydia Salmon, Dept. of Nuclear Engineering, University of Tennessee, Knoxville, TN 37996 (phone 423-974-2525; email email@example.com).
Monte Carlo Analysis, May 18-22, 1998, Knoxville, Tennessee, a short course offered by the University of Tennessee-Knoxville. Contact: Lydia Salmon, Dept. of Nuclear Engineering, University of Tennessee, Knoxville, TN 37996 (phone 423-974-2525; email firstname.lastname@example.org).
Radiation Safety Officer's Course, May 18-22, 1998, a continuing education course offered by the University of Texas at San Antonio. Contact: The University of Texas Health Science Center at San Antonio, Continuing Medical Education, 7703 Floyd Curl Dr., San Antonio, TX 78284-7980 (phone 210-567-4491; fax 210-567-6964).
Practical MCNP for the HP, May 18-22, 1998, University of New Mexico-Los Alamos Campus. Contact Dick Olsher, 505-667-3364, e-mail: email@example.com.
SAMO 98: Second International Symposium on Sensitivity Analysis of Model Output, May 19-22, 1998, University of Venice, Dorsoduro 3825, 30123 Venezia, Italy. Contact: Mrs. Dorit Schlittenhardt, Public Relations and Publications Unit - JRC Ispra Site, TP 020, 21020 Ispra (VA) Italy (phone 39 332 789370, fax: 39 332 785409, email firstname.lastname@example.org, web http://www.jrc.org/isis/sa/events/samo98/).
Methodologies For Particle Transport Simulation and Their Application to Reactor Dosimetry/ Shielding, May 25-29, 1998, SCK/CEN, Mol, Belgium. Contact: Prof. Ali Haghighat, Penn State University, Nucl. Eng. Dept., 231 Sackett Building, University Park, PA 16802 (phone 814-865-0039, fax 814-865-8499, email: http://email@example.com/).
Radiation Safety Officer, June 8-12, 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).
3rd International Meeting of Physicists in the Inca Region, June 15-20, 1998, Cusco, Peru. Contact: Jon Broadway, Internatl. Corps on Environment (ICE), Auburn University, 75 Technacenter Drive, Montgomery, AL 36117-6035 (phone: 334-242-2777; fax: 334-242-2755; email: firstname.lastname@example.org).
ICENES '98, Emerging Nuclear Energy Systems, June 28-July 2, 1998, Tel-Aviv, Israel. Contact: Conference Secretariat, Dan Knassim Ltd., P.O. Box 1931, Ramat Gan 52118, Israel (phone 972-3-6133340, fax 972-3-6133341, email email@example.com, web http://icenes98.simplenet.com/).
CINDER'90 June 30 - July 1, and again July 1415, 1998, Los Alamos National Laboratory. Contact: W. B. Wilson, Nuclear Theory and Applications Group (T-2), Theoretical Division, Los Alamos National Laboratory, PO Box 1663, MS:B243, Los Alamos, NM 87545 (phone 505-667-7749, fax: 505-667-9671, or firstname.lastname@example.org).
Health Physics Society Annual Meeting, July 12-16, 1998, Minneapolis, Minnesota. Contact: Health Physics Society, Suite 402, 1313 Dolley Madison Blvd., McLean, VA 22101-3926 (phone 703-790-1745; fax 703-790-2672; email: email@example.com).
The 1998 IEEE International Conference on Nuclear and Space Radiation Effects, July 20-24, Newport Beach, California. Contact: James R. Schwank, Sandia National Laboratories, P.O Box 5800, MS 1083, Albuquerque, NM 87185-1083 (phone 505-844-8376, fax: 505-844-2991, email firstname.lastname@example.org).
AccApp'98, Sept. 20-23, 1998, Gatlinburg, Tennessee, sponsored by the Oak Ridge-Knoxville, TN, USA Section of the ANS. Contact: Dr. John Haines, Chairman, AccApp '98 Technical Program Committee, Oak Ridge National Laboratory, Oak Ridge, TN 37831-8071, USA (phone 423-574-0966, fax 423-576-7926, email: email@example.com, or url http://www.engr.utk.edu/org/ans/AccApp98)
Training Course on the Use of MCNP in Radiation Protection and Dosimetry, Sept. 28-1 Oct. 1998, at the Imperial College of Science, Technology and Medicine, London. Contact: Robert Alan Price, Imperial College of Science, Technology and Medicine, T. H. Huxley School of the Environment, Earth Sciences and Engineering, Applied Modelling and Computation Group, Centre for Environmental Technology, Room 405, Royal School of Mines Building, Prince Consort Rd, London SW7 2BP, UK (phone 44 171 594 9323, fax 44 171 594 9341, url http://wrench.et.ic.ac.uk/courses/).
4th Annual Workshop on Monte Carlo Simulation of Radiotherapy Treatment Sources using the OMEGA/BEAM Code System, Oct. 5-8, 1998, Ottawa, Canada. Contact: Blake Walters, Ionizing Radiation Standards, National Research Council of Canada, Ottawa, Canada, K1A 0R6. (phone 613-993-2715; fax 613-952-9865; e-mail firstname.lastname@example.org; url: www.irs.inms.nrc.ca/inms/irs/BEAM/ beamhome.html)
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).
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: email@example.com)
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: firstname.lastname@example.org).
APRIL ACCESSION OF LITERATURE
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/rsic.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.
Nucl. Sci. Eng., 127, 105-129 . . . R-Matrix Analysis of the 240Pu Neutron Cross Sections in the Thermal to 5700-eV Energy Range. . . . Bouland, O.; Derrien, H.; Larson, N.M.; Leal, L.C. . . . October 1997 . . . Commissariat a l'Energie Atomique, St. Paul-lez-Durance, France; Organization for Economic Cooperation and Development, NEADB, Issy-les-Moulineaux, France; Oak Ridge National Laboratory, Oak Ridge, TN.
Nucl. Sci. Eng., 127, 130-138 . . . Partial-Wave Analysis with the Optical Model for the Resolved and Unresolved Resonance Regions of 56Fe. . . . Kawano, T.; Frohner, F.H. . . . October 1997 . . . Kyushu University, Kasuga, Japan; Forschungszentrum Karlsruhe, Karlsruhe, Germany.
Nucl. Sci. Eng., 127, 139-153 . . . A Composite Nodal Finite Element for Hexagons. . . . Hennart, J.P.; Mund, E.H.; Del valle, E. . . . October 1997 . . . Universidad Nacional Autonoma de Mexico, Mexico D.F., Mexico; Universite Libre de Bruxelles, Bruxelles, Belgium; Universite Catholique de Louvain, Louvain-la-Neuve, Belgium; Instituto Politecnico Nacional, Mexico D.F., Mexico.
Nucl. Sci. Eng., 127, 154-168 . . . Variational Nodal Transport Methods with Heterogeneous Nodes. . . . Fanning, T.H.; Palmiotti, G. . . . October 1997 . . . University of Wisconsin, Madison, WI; Argonne National Laboratory, Argonne, IL.
Nucl. Sci. Eng., 127, 169-181 . . . Discrete Ordinates Methods in xy Geometry with Spatially Varying Angular Discretization. . . . Bal, G.; Warin, X. . . . October 1997 . . . Electricite de France, Clamart Cedex, France.
Nucl. Sci. Eng., 127, 182-198 . . . A Non-Gaussian Treatment of Radiation Pencil Beams. . . . Pomraning, G.C. . . . October 1997 . . . University of California, Los Angeles, Los Angeles, CA.
Nucl. Sci. Eng., 127, 230-237 . . . Neutron Skyshine Calculations with the Integral Line-beam Method. . . . Gui, A.A.; Shultis, K.; Faw, R.E. . . . October 1997 . . . Kansas State University, Manhattan, KS.
Nucl. Sci. Eng., 128, 1-16 . . . Two-Dimensional Geometrical Corner Singularities in Neutron Diffusion - Part I: Analysis. . . . Cacuci, D.G. . . . January 1998 . . . Forschungszentrum Karlsruhe, Karlsruhe, Germany.
Nucl. Sci. Eng., 128, 17-26 . . . Two-Dimensional Geometrical Corner Singularities in Neutron Diffusion - Part II: Application to the SNR-300 Benchmark. . . . Cacuci, D.G.; Kiefhaber, E.; Stehle, B. . . . January 1998 . . . Forschungszentrum Karlsruhe, Karlsruhe, Germany.
Nucl. Sci. Eng., 128, 27-46 . . . The Time-Dependent Simplified P2 Equations: Asympototic Analyses and Numerical Experiments. . . . Shin, U.; Miller, W.F. Jr. . . . January 1998 . . . Los Alamos National Laboratory, Los Alamos, NM.
Nucl. Sci. Eng., 128, 47-60 . . . Measured and Calculated Differential and Total Yield Cross-Section Data of 58Ni(n,xa) and 63Cu(n,xp) in the Neutron Energy Range from 2.0 to 15.6 MeV. . . . Tsabaris, C.; Papadopoulos, C. . . . January 1998 . . . National Technical University, Athens, Greece.
Nucl. Sci. Eng., 128, 61-69 . . . Neutron Total Cross-Section Measurements and Resonance Parameter Analysis of Holmium, Thulium, and Erbium from 0.001 to 20 eV. . . . Danon, Y.; Werner, C.J.; Youk, G.; Block, R.C. Slovacek, R.E.; Francis, N.C.; Burke, J.A.; D . . . January 1998 . . . Rensselaer Polytechnic Institute, Troy, NY; Lockheed Martin Corp., Schenectady, NY.
Nucl. Sci. Eng., 128, 70-75 . . . Transmutation of Technitium in the Petten High Flux Reactor: A Comparison of Measurements and Calculations. . . . Konings, R.J.M.; Kloosterman, J.L.; Hendriks, J.A.; Gruppelaar, H. . . . January 1998 . . . Netherlands Energy Research Foundation ECN, Petten, The Netherlands.
Nucl. Sci. Eng., 128, 76-87 . . . Calculation of Point-Kinetics Parameters in the MOBY-DICK System. . . . Svarny, J.; Krysl, V.; Mikolas, P.; Vlachovsky, K. . . . January 1998 . . . SKODA Nuclear Machinery Ltd., Plzen, Czech Republic.
Nucl. Sci. Eng., 128, 88-91 . . . The Scalar Flux and Current for Small Critical One-Dimensional Systems. . . . Pomraning, G.C. . . . January 1998 . . . University of California, Los Angeles, CA.
Nucl. Sci. Eng., 128, 196-208 . . . Automated Variance Reduction of Monte Carlo Shielding Calculations Using the Discrete Ordinates Adjoint Function. . . . Wagner, J.C.; Haghighat, A. . . . Feburary 1998 . . . Pennsylvania State University, University Park, PA.
Nucl. Sci. Eng., 128, 209-223 . . . On the Equivalence of Boundary and Boundary Condition Perturbations in Transport Theory and Its Diffusion Approximation. . . . Rahnema, F.; Ravetto, P. . . . February 1998 . . . Georgia Institute of Technology, Atlanta, GA.; Politecnico di Torino, Torino, Italy.
Nucl. Sci. Eng., 128, 270-277 . . . Measurements of Absolute Delayed Neutron Yield and Group Constants in the Fast Fission of 235U and 237Np. . . . Loaiza, D.J.; Brunson, G.; Sanchez, R.; Butterfield, K. . . . March 1998 . . . Los Alamos National Laboratory, Los Alamos, NM.
Nucl. Sci. Eng., 128, 278-296 . . . A Nonlinear Corner-Balance Spatial Discretization for Transport on Arbitrary Grids. . . . Castrianni, C.L.; Adams, M.L. . . . March 1998 . . . Texas A&M University, College Station, TX.
Nucl. Sci. Eng., 128, 297-311 . . . Development of a Numerical Experiment Technique to Solve Inverse Gamma-Ray Transport Problems with Application to Nondestructive Assay of Nuclear Waste Barrels. . . . Chang, C.J.; Anghaie, S. . . . March 1998 . . . University of Florida, Gainesville, FL.
Nucl. Sci. Eng., 128, 312-320 . . . An Sn Algorithm for the Massively Parallel CM-200 Computer. . . . Baker, R.S.; Koch, K.R. . . . March 1998 . . . Los Alamos National Laboratory, Los Alamos, NM.
Nucl. Sci. Eng.,1 28, 321-238 . . . Neutron Cross-Section Probability Tables in TRIPOLI-3 Monte Carlo Transport Code. . . . Zheng, S.H.; Vergnaud, T.; Nimal, J.C. . . . March 1998 . . . CEA - DRN/DMT/SERMA/LEPP, Gif-sur-Yvette, Cedex, France.
Nucl. Technol., 121, 14-23 . . . Study on the Permeability of Engineered Barriers for the Enhancement of a Radioactive Waste Repository System. . . . Tashiro, S.; Fujiwara, A.; Senoo, M . . . January 1998 . . . Radioactive Waste Management Center, Tokyo, Japan.
Nucl. Technol., 121, 24-39 . . . Integrated Radionuclide Transport Model for a High-level Waste Repository in Water-Saturated Geologic Formations. . . . Ahn, J. . . . January 1998 . . . University of California, Berkeley, Berkeley, CA.
Nucl. Technol., 121, 40-51 . . . Stability of Natural Circulation Boiling Water Reactors: Part I - Description Stability Model and Theoretical Analysis in Terms of Dimensionless Groups. . . . Van Bragt, D.D.B.; Van Der Hagen, T.H.J.J. . . . January 1998 . . . Delft University of Technology Interfaculty Reactor Institute, JB Delft, The Netherlands.
Nucl. Technol., 121, 52-62 . . . Stability of Natural Circulation Boiling Water Reactors: Part II - Parametric Study of Coupled Neutronic-Thermohydraulic Stability. . . . Van Bragt, D.D.B.; Van Der Hagen, T.H.J.J. . . . January 1998 . . . Delft University of Technology, JB Delft, The Netherlands.
Nucl. Technol., 121, 101-113 . . . Fifteen Years of Research and Development on Direct Disposal in Germany: An Overview. . . . Closs, K.D.; Papp, R. . . . February 1998 . . . Forschungszentrum Karlsruhe, Karlsruhe, Germany.
Nucl. Technol., 121, 114-119 . . . An Assessment of the Results of the Direct Disposal Project by the Federal Ministry for the Environment, Nature Conservation, and Nuclear Safety. . . . Bloser, M.; Beuth, T. . . . February 1998 . . . Bundesministerium fur Umwelt, Naturschutz, und Reaktorsicherheit, Bonn, Germany; Gesellschaft fur Anlagen - und Reaktorsicherheit, Koln, Germany.
Nucl. Technol., 121, 120-127 . . . Evaluation of Direct Disposal from the Point of View of One Utility and Perspectives for Waste Management. . . . Heni, W. . . . February 1998 . . . Gemeinschaftskernkraftwerk Neckar Im Steinbruch, Neckarwestheim, Germany.
Nucl. Technol., 121, 148-161 . . . Conceptual Design and Demonstration Tests for Disposal of Spent Fuel in a Salt Repository. . . . Engelmann, H.J. . . . February 1998 . . . Deutsche Gesellschaft zum bau und Betrieb von Endlagern fur Abfallstoffe, Peine, Germany.
Nucl. Technol., 121, 162-167 . . . International Nuclear Material Safeguards for the Direct Final Disposal of Spent-Fuel Assemblies. . . . Richter, B. . . . February 1998 . . . Forschungszentrum Julich, Julich, Germany.
Nucl. Technol., 121, 168-173 . . . Retrievability of Spent Nuclear Fuel After Final Disposal in a Salt Dome. . . . Biurrun, E.A. . . . February 1998 . . . Deutsche Gesellschaft zum Bau und Betrieb von Endlagern fur Abfallstoffe, Peine, Germany.
Nucl. Technol., 121, 174-188 . . . Long-Term Stability of Spent Nuclear Fuel Waste Packages in Gorleben Salt Repository Environments. . . . Grambow, B.; Loida, A.; Smailos, E. . . . February 1998 . . . Forschungszentrum Karlsruhe, Karlsruhe, Germany.
Nucl. Technol., 121, 189-198 . . . Special Safety Aspects of Drift Disposal - The Thermal Simulation of the Drift Storage Experiment. . . . Heusermann, S.; Schneefuss, J.U.; Pudewills, A. . . . February 1998 . . . Gesellschaft f. Anlagen - & Reaktorsicherheit Fachbereich Endlagersicherheitsforschung, Braunschweig, Germany; Fed. Inst. for Geosciences & Natural Resources, Hannover, Germany; Forschungsbergwerk Asse, Wolfenbuttel, Germany; Forschungszentrum Karlsruhe technik & Umwelt Inst. f. Nukleare Entsorgungstechnik, Karlsruhe, Germany.
Nucl. Technol., 121, 199-211 . . . Evaluation of Repository Concepts for the Disposal of Spent Fuel on the Basis of Geotechnical Safety Indicators and Exploration Data. . . . Langer, M.; Wallner, M. . . . February 1998 . . . Bundesanstalt fur Geowissenschaften und Rohstoffe, Hannover, Germany.
Nucl. Technol., 121, 212-220 . . . A Comparison of Long-Term Safety Aspects - Concepts for Disposal of Spent Fuel and Wastes from Reprocessing. . . . Storck, R.; Buhmann, D. . . . February 1998 . . . Gesellschaft fur Anlagen und Reaktorsicherheit, Braunschweig, Germany.
Nucl. Technol., 121, 229-236 . . . Overview of Electric Power Research Institute Nuclear Safety Analysis Activities. . . . Agee, L.J. . . . March 1998 . . . Electric Power Research Institute, Palo Alto, CA.
Rad. Prot. Dos. 70, vol. 1-4 (1997) Neutron Dosimetry. . . . March 1997 . . . from Radiation Protection Publications Catalogue; Proceedings of the Eighth Symposium on Neutron Dosimetry, Paris, France, November 13-17, 1995.
Rad. Prot. Dos. 72, vol. 3-4 (1997) Non-Ionising Radiation. . . . Dennis, J.A., ed.; Stather, J.W., ed. . . . October 1997 . . . from Radiation Protection Publications Catalogue.
Rad. Prot. Dos. 75, vol. 1-4 (1998) Radionuclides in the Oceans, Distributions, Models and Impacts. . . . Hung, G.J., ed.; Kershaw, P.J., ed.; Swift, D.J., ed. . . . March 1998 . . . from Radiation Protection Publications Catalogue; Proceedings of Part 2 of an International Symposium, Norwich/Lowestoft, England, April 7-11, 1997.
JNMM, 26, 13-16 . . . Future Perspectives on Nuclear Issues. . . . Domenici, P.V. . . . Winter 1998 . . . American Nuclear Society, Albuquerque, NM.
OECD Proceedings . . . SATIF-3 Shielding Aspects of Accelerators, Targets and Irradiation Facilities. . . . 1998 . . . Proceedings of the Third Specialists Meeting, Tohoku University, Sendai, Japan 12-13 May 1997.
KEK Preprint 97-15 . . . Comparison Between Soil Benchmark Experiment and MARS Calculation. . . . Suzuki, T.; Numajiri, M. Ban, S.; Kanda, Y.; et al. . . . May 1997 . . . High Energy Accelerator Research Organization (KEK), Ibaraki-ken, Japan.
KEK Preprint 97-16 . . . Shielding Design of Decay Volume and Target Station for Neutrino Oscillation Experiment Using MARS. . . . Suzuki, T.; Numajiri, M.; Ban, S.; Kanda, Y.; et al. . . . May 1997 . . . High Energy Accelerator Research Organization (KEK), Ibaraki-ken, Japan.
KEK Preprint 97-29 . . . Inter-Comparison of the Medium-Energy Neutron Attenuation in Iron and Concrete. . . . Hirayama, H.; et al. . . . May 1997 . . . High Energy Accelerator Research Organization (KEK), Ibaraki-ken, Japan.
KEK Preprint 97-61 . . . Calculation of Radiation Fields Inside Iron Beam Dump Irradiated by 24 GeV/c Proton. . . . Nakao, N. . . . June 1997 . . . High Energy Accelerator Research Organization (KEK), Ibaraki-ken, Japan.
KEK Preprint 97-79 . . . Comparison of Line Beam Response Function for Gamma-Ray Skyshine Analysis Based on Single Scattering Method with the Monte Carlo Calculations. . . . Harima, Y.; Hirayama, H.; Sakamoto, Y.; Kurosawa, N.; Nemoto, M. . . . June 1997 . . . High Energy Accelerator Research Organization (KEK), Ibaraki-ken, Japan.
LA-13439-C . . . Proceedings of the Nuclear Criticality Technology Safety Workshop. . . .April 1998 . . . Los Alamos National Laboratory, Los Alamos, NM.
ORNL/TM-13170/V4 . . . Characteristics of Spent Fuel from Plutonium Disposition Reactors Vol. 4: Westinghouse Pressurized-Water-Reactor Fuel Cycle Without Integral Absorber. . . . Murphy, B.D. . . . April 1998 . . . Oak Ridge National Laboratory, Oak Ridge, TN.
ORNL/TM-13221 . . . The TORT Three-Dimensional Discrete Ordinates Neutron/Photon Transport Code (TORT Version 3). . . . Rhoades, W.A.; Simpson, D.B. . . . October 1997 . . . Oak Ridge National Laboratory, Oak Ridge, TN.
Handbook . . . Radionuclide and Radiation Protection Data Handbook (1998). . . . Delacroix, D.; Guerre, J.P.; Leblanc, P.; Hickman, C. . . . 1998 . . . from Radiation Protection Publications Catalogue.
Book . . . The Physics of Radiation Protection. . . . Dorschel, B.; Schuricht, V.; Steuer, J. . . . February 1996 . . . from Radiation Protection Publications Catalogue.
Book . . . Thermoluminescence Dosimetry Materials: Properties and Uses. . . . McKeever, S.W.S.; Moscovitch, M.; Townsend, P.D. . . . December 1995 . . . from Radiation Protection Publications Catalogue.
Book . . . Nuclear Criticality Safety Theory and Practice. . . .1996 . . . American Nuclear Society, La Grange Park, IL.
Book . . . Guide to Radiation and Radioactivity Levels Around High Energy Particle Accelerators. . . . Sullivan, A.H. . . . November 1992 . . . from Radiation Protection Publications Catalogue.
Book . . . A History of Accelerator Radiation Protection - Personal and Professional Memoirs. . . . Patterson, H.W., ed.; Thomas, R.H., ed. . . . June 1994 . . . from Radiation Protection Publications Catalogue.
Book . . . Retrospective Dosimetry Physical and Biological Aspects. . . . Sugahara, T., ed.; Zhang, L., ed.; Wang, J., ed.; Aoyama, T., ed.; Zhang, J., ed. . . . July 1998 . . . from Radiation Protection Publications Catalogue; Proceedings of an International Workshop, Tianjin, China, October 14-17, 1997.