| Radiation Safety Information Computational Center | |
 |
Oak Ridge National Laboratory Post Office Box 2008 Oak Ridge, Tennessee 37831-6362 Managed by Lockheed Martin Energy Research Corp. for the U.S. Department of Energy under contract DE-AC05-96OR22464 Phone No. 423-574-6176 Internet: PDC@ORNL.GOV |
| No. 407 | November 1998 |
| Never regard study as a duty, but as the enviable opportunity to learn to know the liberating influence of beauty in the realm of the spirit for your own personal joy and to the profit of the community to which your later work belongs.--Albert Einstein | |
Two changes or additions were made to the computer code collection during the month. One existing code system was updated and one code system was replaced with a newly frozen version.
Argonne National Laboratory, Argonne, Illinois, contributed an update to the VIM code system with the addition of ASCII data libraries and a convenient means to convert them to binary on a target machine. The original distribution included binary sequential data libraries for use with the code system on IBM or Sun workstations. VIM solves the steady-state neutron or photon transport problem in any detailed three-dimensional geometry using either continuous energy-dependent ENDF nuclear data or multigroup cross sections. Neutron transport is carried out in a criticality mode, or in a fixed source mode (optionally incorporating subcritical multiplication). Photon transport is simulated in the fixed source mode. VIM uses standard Monte Carlo methods for particle tracking with several optional variance-reduction techniques.
VIM 3.6 runs on IBM and Sun workstations. At RSICC the system was successfully tested on IBM RS/6000 model 590 under AIX 4.2 with XLF77 version 3.2.2 and on Sun Sparc 20 running SUNOS 5.6 (Solaris 2.6) with f77 version 4.2. The package is transmitted on either a CD or tape cartridge as a compressed tar file which contains installation instructions, the User's Guide, Fortran and C source, and test cases. References: Argonne National Laboratory Report (Unpublished). Fortran 77; Sun, IBM RS/6000 (C00658/MNYWS/01).
Battelle Pacific Northwest National Laboratory, Richland, Washington, contributed a
newly frozen version of this visual editor for creating input files for the Los Alamos
MCNP4 program. The new MCNP-VISED26f release was upgraded to call slightly
modified Fortran subroutines from the initiation and plot modules of MCNP4B. It
runs on additional computing platforms and includes numerous bug fixes. Up to 10
dynamic cross section views of the geometry can be utilized to create surfaces and
build the geometry. MCNP input files created by VISED can be read by either
CCC-200/MCNP4A or CCC-660/MCNP4B.
This menu-driven graphical interface is based on C-language routines that interface with the screen and call Fortran subroutines which initialize the input data and prepare the information for the geometry plots. These Fortran routines in turn call slightly modified Fortran subroutines from the initiation and plot modules of MCNP version 4B. The Fortran subroutines constantly check the evolving input data being received from the C routines and generate the information for dynamically plotting the geometry in user-selected cross-section views. The widgets are created in Motif, and the graphics are created using Xlib routines. VISED runs on HP, SGI, and Sun workstations, or PCs running Red Hat Linux with at least 30 Mbytes of memory. MCNP-VISED will not run on other systems. Fortran and ANSI-C compilers with access to the Xlib and Motif libraries are required to build executables. The package is transmitted on either CD or tape cartridge in a compressed Unix tar file. Reference: unpublished Battelle Pacific Northwest National Laboratory report (October 1997). HP, SGI, Sun, and Linux-based PC; Fortran 77 and C (P00358/MNYCP/00).
CONFERENCES, COURSES, SYMPOSIA
RSICC attempts to keep its users/contributors advised of conferences, courses, and symposia in the field of radiation protection, transport, and shielding through this section of the newsletter. Should you be involved in the planning/organization of such events, feel free to send your announcements and calls for papers via email to raf@ornl.gov. Please include the announcement in its native format as an attachment to the message. If the meeting is on a website, please include the url.
The First Latin American Symposium on Nuclear Tracks will be held April 5-9, 1999, in Caracas, Venezuela. The symposium will be devoted to the review of present knowledge of nuclear track science and technology and its applications in physics, health, environmental studies, earth sciences and industry. Participants are encouraged to submit one-page abstracts, even if they might be seen as preliminary results. The list of suggested topics are:
Abstracts with the complementary registration page can be sent in three ways by February 15, 1999:
1. By fax to one the following numbers:
(+58-2) 906-3155 (Laboratorio de Física Nuclear, USB)
(+58-2) 906-3888 (Laboratorio de Física Nuclear, USB)
(+58-2) 605-2188 (Escuela de Física, Facultad de Ciencias, UCV)
2. By email to one of the following addresses:
rmartin@fisica.ciens.ucv.ve
lsajo@usb.ve
asajo@usb.ve
fgutt@pion.ivic.ve
3. Send the abstract either by fax or email and then proceed with the electronic registration.
Details may be found on the internet at http://fisica.ciens.ucv.ve/~rmartin/1lasont/1lasont.html.
The National Council on Radiation Protection and Measurements (NCRP) has released the program for the 1999 Annual Meeting. The meeting will be held April 7-8, 1999, in Arlington, Virginia. In keeping with its mission to formulate and disseminate information, guidance and recommendations on radiation protection and measurements which represent the consensus of leading scientific thinking, the theme of the meeting is Radiation Protection in Medicine: Contemporary Issues. A summary of the program topics is available in the October issue of the RSICC Newsletter. No registration fee is required, but those wishing to attend should register in advance with the NCRP office (Suite 800, 7910 Woodmont Ave., Bethesda, MD 20814-3095, phone 301-657-2652) or at the meeting reception desk. Additional information about the organization and meeting is available at the following web site: http://www.ncrp.com/.
The Third International Conference on Isotopes (3ICI) follows successful meetings in Beijing (1995) and Sydney (1997). 3ICI will be held in the Renaissance Hotel in Vancouver, Canada, September 6-10, 1999. 3ICI will be hosted by TRIUMF, Canada's national accelerator facility and a major center for isotope production and applications in research and medicine. The conference is being organized in conjunction with the Canadian Chapter meeting of the International Isotope Society.
The scientific program will consist of plenary and parallel oral sessions in conjunction with poster presentations. Topics will include the following:
Persons interested in presenting an oral or poster paper should prepare a one page abstract in accord with the instructions on the web page: http://www.triumf.ca/3ici/. Further information is available from Ms. Elly M. Driessen, TRIUMF, 4004 Wesbrook Mall, Vancouver, B.C., Canada V6T 2A3 (phone 604-222-7352, fax 604-222-1074, email ici@triumf.ca).
We have received several requests from SCALE users for organising the next SCALE training course in Europe. As you may know already, from 20-24 September 1999 the "International Conference on Nuclear Criticality Safety (ICNC'99)" will take place in Versailles, France; http://www.ipsn.fr/icnc99/. We have found it therefore convenient to organise this training course the week before that conference. This will facilitate both attendance in the criticality safety training course and be part of the last major event in criticality safety of this decade (sorry but I shall not use the term millennium).
We plan to hold this training course in the premises of the French National Institute for Nuclear Science and Techniques (INSTN) located about 6 miles from Versailles. The course will be given by the authors and code managers from the ORNL (http://www.cad.ornl.gov/scale).
The technical programme of the workshop has been designed by Steve Bowman, SCALE Project Leader, Computational Physics & Engineering Division, Oak Ridge National Laboratory (phone +1 423-574-5263, fax+1 423-576-3513, email st5@ornl.gov. An attendance certificate will be delivered at the end of the course. This course is organised in co-operation with the Radiation Safety Information Computational Center (RSICC). Should you be interested in participating, please return the form by 31 December 1998. More precise information, including the exact participation fee, location, transportation and accommodation possibilities will be provided later.
Best regards
Enrico Sartori
OECD NEA Data Bank
12 Bd des Iles
92130 Issy-les-Moulineaux
France
Tel.+33 1 45 24 10 72; Fax +33 1 45 24 11 10; www http://www.nea.fr; e-mail sartori@nea.fr
The SCALE KENO VI Criticality Course focuses on KENO VI and the associated criticality analysis sequences in CSAS. This version of KENO can handle triangular pitch fuel such as that required for VVER lattices. A registration form is included at the back of this newsletter. The number of registrants for each course is limited. Registrations will be accepted on a first-come basis.
| SCALE KENO VI Criticality Course Agenda | |
| Monday | Tuesday |
| Introduction to CSAS6 Resonance Self-Shielding Standard Composition Library Material Information Processor Library (MIPLIB) Input Unit Cell Geometry - Lattice Cell / Multiregion Problem Session 1 |
Review of Problem Session 1 KENO-VI Parameters KENO-VI Geometry KENO-VI Plot Data Problem Session 2 |
| Wednesday | Thursday |
| Review of Problem Session 2 KENO-VI Output - How to Read It Geometry Modification Data (Chords/Rotate/Translate) Media/Holes Media/Arrays Problem Session 3 |
Review of Problem Session 3 Start Data Bias Data Boundary Data Mixing Table Problem Session 4 |
| Friday | |
| Review of Problem Session 4 Monte Carlo Uncertainties Code and Data Validation Issues Conclusion / Questions and Answers |
|
The Tenth International Symposium on Reactor Dosimetry will be held September 12-17, 1999, in Osaka, Japan. About every three years this symposium provides a forum for the interchange of state-of-the-art techniques, databases and standardization of radiation metrology. The Symposium will be of value to those involved in reactor dosimetry, including researchers, manufacturers and representatives from industry, utilities and regulatory agencies. The Symposium is jointly sponsored by the Atomic Energy Society of Japan (AESJ), the American Society for Testing and Materials (ASTM) and the European Working Group on Reactor Dosimetry (EWGRD). It is organized by ASTM Committee E10 on Nuclear Technology and Applications and EWGRD.
The Symposium theme is dosimetry for the assessment of irradiated reactor materials and reactor experiments, featuring radiation metrology techniques, databases and standardization. Inquiries and requests to be added to the mailing list should be sent to one of the following:
North & South America, East & Southeast Asia:
Dr. David W. Vehar
ASTM Program Secretary
Sandia National Laboratories, MS-1136
P.O. Box 5800, Albuquerque, NM 87185-1136, USA
Phone: 505-845-3414, fax: 505-844-0798
email: dwvehar@sandia.gov
Europe, Africa, Asia (other), and Australia:
Dr. Hamid Ait Abderrahim
EWGRD Programme Secretary
SCK/CEN
Boeretang 200, B-2400 Mol, BELGIUM
Phone: 32-14-332277, fax: 32-14-321529
email: haitabde@sckcen.be
"Half a Century of Radiation Shielding Research and Its Evolution into the Next Era" is the theme for the 9th International Conference on Radiation Shielding to be held October 17-22, 1999, in Tsukuba, Japan. It is sponsored and organized by the Japan Atomic Energy Research Institute and co-sponsored by the OECD-Nuclear Energy Agency-Nuclear Science Committee (NEA-NSC), Atomic Energy Society of Japan (AESJ), and the Radiation Safety Information Computational Center (RSICC). Participants in the conference explore the scientific, technological and engineering issues associated with radiation shielding in broad nuclear energy systems, accelerator facilities, space and general environments. Detailed information about the conference may be obtained from Yujiro Ikeda, Japan Atomic Energy Research Institute, Tokai Research Establishment, Neutron Science Research Center, Spallation Neutronics Laboratory, Tokai-mura, Naka-gun, Ibaraki-ken 319-11 Japan (phone 81-29-282-6074, fax 81-29-282-5709, email ikeda@fnshp.tokai. jaeri.go.jp) or from the web page at http://icrs9.tokai.jaeri.go.jp.
The Department of Nuclear Engineering at the University of Tennessee-Knoxville is offering three five-day short courses of interest to radiation transport specialists during Tennessee Industries Week (TIW-34), August 16-20, 1999.
Computational Methods in Reactor Analysis and Shielding Engineers, scientists, and technical managers who wish to increase their knowledge and understanding of the computational methods and computer codes currently used in nuclear reactor analysis and shielding will be interested in this intensive one-week short course. A good understanding of the neutronic models and associated numerical methods employed in the codes is essential for the successful use of the codes in designing new systems or improving the performance and safety of existing systems.
Areas to be covered include multidimensional diffusion theory methods and perturbation theory methods for applications in reactor statics, space dependent kinetics, and fuel depletion; transport theory methods including the discrete ordinates method, integral transport theory, and the Monte Carlo method; and cross section generation and processing utilizing the AMPX and SCALE systems developed at the oak Ridge National Laboratory.
Special emphasis in the course is placed on the Monte Carlo method because of its widespread use and importance for nuclear system analysis brought about primarily by the increased availability of high performance workstations. The course ends at noon on Friday.
Monte Carlo Analysis is designed specifically for the practicing engineer engaged in shield design and does not presume any prior knowledge of Monte Carlo methods. However, some understanding of radiation transport physics is desirable. A wide range of topics will be presented that will lead to a good understanding of the basics of Monte Carlo analysis and the specialized applications of Monte Carlo methods to practical shielding problems. Many advanced topics will be included that will promote the best use of existing computer code systems. Special attention will be paid to the understanding and Monte Carlo implementation of the adjoint analysis. Advantages and disadvantages of the adjoint mode versus the forward mode of analysis will be described including several practical applications of the adjoint mode of Monte Carlo analysis. Variance reduction techniques will be developed in a comprehensive fashion for both forward and adjoint calculations. The versatile computer code system, MORSE, will be described to illustrate the general features of Monte Carlo computer programs. The relationships of the Monte Carlo methods to other methods of solving radiation transport problems, such as discrete ordinates, will be described, as well as computational advantages and disadvantages of Monte Carlo versus the other methods. This course will cover, in depth, the theory and mathematics a user must have in order to understand and use the Monte Carlo method effectively to solve difficult problems in radiation transport.
Nuclear Criticality Safety Engineers, scientists, and technical managers who wish to increase their knowledge and understanding of nuclear criticality safety will be interested in this intensive one-week short course. The topics covered in the course are based primarily on the experience of the six instructors which totals over 130 years of nuclear criticality safety related experience. Such a wealth of experience needs to be shared with the criticality safety community including both new professionals in the field as well as experienced professionals.
The course topics include illustrative applications using the SCALE system developed at the Oak Ridge National Laboratory with emphasis on the Monte Carlo code KENO Va, standards, regulations, review of accidents, hand calculation methods, subcritical limits, code validation techniques, emergency response, process upsets and recovery actions, and transient excursion modeling. The course ends at noon on Friday.
The registration fee is $1195 per person for each course. The deadline for registration in these three courses is August 2, 1999. For additional information contact Lydia Salmon, Dept. of Nuclear Engineering, University of Tennessee, Knoxville, TN 37996 (phone 423-974-2525; email lutne@utk.edu). If you have access to the internet, you may also register via the website at http://www.engr.utk.edu/dept/nuclear/TIW.html.
Calendar
Your attention is directed to the following events of interest.
November 1998
International Symposium on Evolutionary Water-Cooled Reactors, Nov. 30-Dec. 4, 1998, Seoul, Republic of Korea, sponsored by the IAEA. Contact: IAEA, Wagramerstrasse 5, P.O. Box 100, A-1400 Vienna, Austria (phone 43-1-20600, fax x43-1-20607, email official.mail@iaea.org).
December 1998
Nuclear Decom '98, Dec. 2-3, 1998, London, sponsored by the Inst. of Mechanical Engineers. Contact: Alison Hamlett ( phone 44-0171-304-6864, fax 44-0171-222-9881, email a_hamlett@imeche.org.uk).
1998 Meeting of the National Organization of Test, Research, and Training Reactors, Dec. 13-16, 1998, Cambridge, Massachusetts. Contact: John Bernard, Massachusetts Inst. of Technology Nuclear Research Lab (phone 617-253-4202, fax 217-253-7300, email jbernard@mit.edu).
March 1999
1999 Hardened Electronics and Radiation Technology (HEART), March 8-12, 1999, Monterey, California. Contact: Ralph Nadell, Palisades Institute, Suite 1006, 201 Varick St., New York, NY 10014 (phone 212-620-3341, fax 212-620-3379).
April 1999
First Latin American Symposium on Nuclear Tracks and Radiation, April 5-9, 1999, Caracas, Venezuela, Institute for Advanced Studies, Convention Centre. Contact: Professor Laszlo Sajo, Universidad Simon Bolivar, FE-1, Apdo 89000, Caracas, Venezuela, (phone 58-2-906- 3590, fax 58-2-906-3712, email lsajo@fis.usb.ve).
35th Annual Meeting of the National Council on Radiation Protection and Measurements, Apr. 7-8, 1999, Arlington, Virginia. Contact: NCRP, Suite 800, 7910 Woodmont Ave., Bethesda, MD 20814-3095 (phone 301-657-2652, fax 301-907-8768, email ncrp@ncrp.com).
June 1999
Conference on Radionuclide Metrology and its Application, June 7-11, 1999, Prague. Contact: Pavel Dryák, Czech Metrological Institute, Radiova 1, CZ 102 00 Prague, Czech Republic (phone 420-2-67008244, fax 420-2-67008466, email pdryak@cmi.cz).
August 1999
Computational Methods in Reactor Analysis and Shielding, Aug. 16-20, 1999, 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 423-974-2525 (fax 423-974-0668).
Nuclear Criticality Safety, Aug. 16-20, 1999, 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 423-974-2525 (fax 423-974-0668).
Monte Carlo Analysis, Aug. 16-20, 1999, 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 423-974-2525 (fax 423-974-0668).
September 1999
Tenth International Symposium on Reactor Dosimetry, Sept. 12-17, 1999, in Osaka, Japan. Contact: Dr. David W. Vehar (505-845-3414, fax 505-844-0798, email: dwvehar@sandia.gov) or Dr. Hamid Ait Abderrahim (32-14-332277, fax 32- 14-321529, email haitabde@sckcen.be).
SCALE Criticality Course (KENO V.a), Sept. 13-17, 1999, INSTN, Saclay, France. Contact: Enrico SARTORI, OECD/NEA Data Bank, Le Seine-Saint Germain, 12 boulevard des Iles, F- 92130 Issy-les-Moulineaux, FRANCE (Tel+33 (0)1 45 24 10 72; Fax+33 (0)1 45 24 11 10; E-mail sartori@nea.fr).
October 1999
Half a Century of Radiation Shielding Research and Its Evolution into the Next Era (ICRS-9), Oct. 17-22, 1999, Tsukuba, Japan, sponsored and organized by the Japan Atomic Energy Research Institute. Contact: Yujiro Ikeda, Japan Atomic Energy Research Institute, Tokai Research Establishment, Neutron Science Research Center, Spallation Neutronics Laboratory, Tokai-mura, Naka-gun, Ibaraki-ken 319-11 Japan (phone 81-29-282-6074, fax 81-29-282-5709, email ikeda@fnshp.tokai.jaeri.go.jp, url http://icrs9.tokai.jaeri.go.jp).
OCTOBER 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/SARIS.html). This early announcement is made as a service to the shielding community. Copies of the literature are not distributed by RSICC. They may generally be obtained from the author or from a documentation center such as the National Technical Information Service (NTIS), Department of Commerce, Springfield, Virginia 22161. For literature listed as available from INIS contact INIS Clearinghouse, International Atomic Energy Agency, P.O. Box 100, A-1400 Vienna.
Radiation Shielding Literature
Health Phys., 75, 367-374 . . . Informing the Public About Radiation - The Messenger and the Message: 1997 G. William Morgan Lecture. . . . Lakey, J. . . . October 1998 .
Health Phys., 75, 398-404 . . . Self-Absorption of Tritium Betas in Metal Tritide Particles. . . . Kropf, R.F.; Wang, Y.; Cheng, Y.S. . . . October 1998 . . . Lovelace Respiratory Research Institute, Albuquerque, NM.
Health Phys., 75, 405-409 . . . Measurement of Neutrons Produced in an Intermediate Energy Heavy Ion Reaction Using an Activation Technique. . . . Guisheng, L.; Jing, W.; Yansen, Z.; Wenjian, L.; Tianmei, Z.; Youwu, S.; Zongqiang, L. . . . October 1998 . . . The Chinese Academy of Sciences, Lanzhou, The People's Republic of China.
Health Phys., 75, 492-499 . . . Radiation Dosimetry for Extremity Radiographs. . . . Huda, W.; Gkanatsios, N.A. . . . November 1998 . . . University Hospital, Syracuse, NY; University of Florida, Gainesville, FL.
Nucl. Sci. Eng., 130, 1-17 . . . The Pencil Beam Problem for Screened Rutherford Scattering. . . . Pomraning, G.C.; Prinja, A.K. . . . September 1998 . . . University of California, Los Angeles, CA; University of New Mexico, Albuquerque, NM.
Nucl. Sci. Eng., 130, 18-46 . . . Characteristic Methods in Thick Diffusive Problems. . . . Adams, M.L.; Wareing, T.A.; Walters, W.F. . . . September 1998 . . . Texas A&M University, College Station, TX; Los Alamos National Laboratory, Los Alamos, NM.
Nucl. Sci. Eng., 130, 47-59 . . . Stabilization Techniques for the Nonlinear Analytic Nodal Method. . . . Joo, H.G.; Jiang, G.; Downar, T.J. . . . September 1998 . . . Purdue University, West Lafayette, IN.
Nucl. Sci. Eng., 130, 60-69 . . . A PN Solution to the Multigroup Slowing-Down Problem - I: Basic Formulation. . . . Caldeira, A.D.; Dias, A.F.; Garcia, R.D.M. . . . September 1998 . . . Centro Tecnico Aeroespacial, Sao Jose dos Campos, SP, Brazil.
Nucl. Sci. Eng., 130, 70-78 . . . A PN Solution to the Multigroup Slowing-Down Problem - II: The Degenerate Case. . . . Caldeira, A.D.; Dias, A.F.; Garcia, R.D.M. . . . September 1998 . . . Centro Tecnico Aeroespacial, Sao Jose dos Campos, SP, Brazil.
Nucl. Sci. Eng., 130, 79-84 . . . On the Equivalence Between the Discrete Ordinates and the Spherical Harmonics Methods in Radiative Transfer. . . . Barichello, L.B.; Siewert, C.E. . . . September 1998 . . . Universidade Federal do Rio Grande do Sul, Porto Alegre, RS, Brazil; North Carolina State University, Raleigh, NC.
Nucl. Sci. Eng., 130, 85-97 . . . The Stochastic Behavior of the Eigenvalue Due to Spatial Perturbation in the Fuel Distribution of the One-Speed Slab Reactor. . . . Jahshan, S.N. . . . September 1998 .
Nucl. Sci. Eng., 130, 98-112 . . . Higher Order Generalized Perturbation Theory for Boiling Water Reactor In-Core Fuel Management Optimization. . . . Moore, B.R.; Turinsky, P.J. . . . September 1998 . . . North Carolina State University, Raleigh, NC.
Nucl. Sci. Eng., 130, 141-152 . . . Passive Neutron Assay of Plutonium Materials: Monte Carlo Procedures to Simulate Generation of Neutron Pulse Trains and the Application of the Neutron Coincidence Counting Method . . . Dodaro, A.; Frazzoli, F.V.; Remetti, R. . . . September 1998 . . . University of Rome "La Sapienza", Rome, Italy.
Nucl. Sci. Eng., 130, 153-163 . . . The Central Void Reactivity in the Oak Ridge National Laboratory Enriched Uranium (93.2) Metal Sphere. . . . Mihalczo, J.T.; Lynn, J.J.; Taylor, J.R. . . . September 1998 . . . Oak Ridge National Laboratory, Oak Ridge, TN.
KEK Preprint 97-159 . . . Measurements of High-Energy Photonuclear Reaction Yields in the 2.5-GeV Electron Beam Stop. . . . Sato, T.; Shin, K.; Ban, S.; Namito, Y.; Nakamura, H.; Hirayama, H. . . . October 1997 . . . Kyoto University, Kyoto, Japan; High Energy Accelerator Research Organization, Ibaraki, Japan.
KEK Preprint 97-237 . . . Improvements of Low-Energy Photon Transport in EGS4. . . . Namito, Y.; Hirayama, H.; Ban, S. . . . December 1997 . . . KEK, Tsukuba, Japan.
KEK Preprint 97-251 . . . Shielding Experiment at 800 MeV Proton Accelerator Facility. . . . Nakao, N.; Shibata, T.; Ohkubo, T.; Sato, S.; Uwamino, Y.; Sakamoto, Y.; Perry, D.R. . . . January 1998 . . . High Energy Accelerator Research Organization, Toko, Japan; The Institute of Physical and Chemical Research, Saitama, Japan,; Japan Atomic Energy Research Institute, Ibaraki, Japan; Rutherford Appleton Laboratory, Oxon, UK.
ANL/NDM-146 . . . Non-Destructive Assay of EBR-II Blanket Elements Using Resonance Transmission Analysis. . . . Klann, R.T.; Poenitz, W.P. . . . August 1998 . . . Argonne National Laboratory, Argonne, IL.
CINDA98 . . . CINDA98; Supplement to CINDA97 (1988-1998). . . 1998 .
LA-UR-98-4186 . . . A Closed ThUOX Fuel Cycle for LWRs with ADTT (ATW) Backend for the 21st Century. . . . Beller, D.E.; Sailor, W.C.; Venneri, F. . . . October 1998 . . . Los Alamos National Laboratory, Los Alamos, NM.
ORNL/TM-13687 . . . Prediction of the Isotopic Compositon of UO2 Fuel from a BWR: Analysis of the DU1 Sample from the Dodewaard Reactor. . . . Murphy, B.D. . . . October 1998 . . . Oak Ridge National Laboratory, Oak Ridge, TN.