Radiation Safety Information Computational Center
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No. 429 November 2000
"We cannot advance without new experiments in living, but no wise man tries every day what he has proved wrong the day before" - James Truslow Adams

NRC Codes Made Available

Three U.S. Nuclear Regulatory Commission (NRC) software packages which were transferred from the Energy Science and Technology Software Center, Oak Ridge, Tennessee, to RSICC were incorporated into the RSICC computer software collection. Please browse the computer abstracts available at RSICC's www site for more information on these packages.



Two new packages were added to the computer software collection during the month, one being a foreign contribution. One update and one newly frozen package were also added.

CCC-640/DCHAIN 1.3

A new PC executable was added to the DCHAIN package, which calculates time-dependent daughter populations in radioactive decay and nuclear reaction chains. DCHAIN was developed at Idaho National Engineering Laboratory, Idaho Falls, Idaho. A user reported an apparent year 2000 related problem when running the distributed executable on a personal computer. A new executable was created at RSICC using Microsoft C++ v6.0 under Windows 98 on a Pentium III. This executable eliminates the problem and was added to the package.

An ANSI C compiler is required on all systems except for PC. An executable file created with Microsoft C++ v6.0 under Windows 98 on a Pentium III is supplied for use on personal computers. The program can run on most platforms that support ANSI C. The package is transmitted on one DS/HD diskette written in DOS format, which contains source files, sample data and their related output files, and a PC executable. Reference: EGG-NRP-11289 (May 1994). ANSI C; Many computers IBM RS/6000, VAX, PC (C00640MNYCP01).


Institute Jozef Stefan, Ljubljana, Slovenia, through the OECD NEA Data Bank, Issy-les-Moulineaux, France, contributed SUSD3D to calculate sensitivity coefficients and standard deviation in the calculated detector responses or design parameters of interest due to input cross sections and their uncertainties. One-, two- and three-dimensional transport problems can be studied. Several types of uncertainties can be considered, i.e. those due to (1) neutron/gamma multi-group cross sections, (2) energy-dependent response functions, (3) secondary angular distribution (SAD) or secondary energy distribution (SED) uncertainties. SUSD3D development is based on SUSD (CCC-501) and includes several modifications and extensions:

- Three-dimensional analysis is possible.
- Flux moment files are used to evaluate the sensitivity profiles instead of angular flux files, subsequently reducing the computer space requirements.
- Processing codes were updated to the ENDF-6 format.
- Process of SAD covariance matrices was programmed.
- Complete SAD covariance matrices can be taken into account in SUSD3D to calculate the variance.

First-order perturbation theory is used to obtain sensitivity coefficients. They are derived from the direct and adjoint flux moments (or angular fluxes) calculated by the DORT, TORT, ONEDANT, TWODANT, and THREEDANT discrete ordinates. The sensitivity profiles are folded with the cross section covariance matrices to determine the variance and standard deviation in an integral response of interest. 

SUSD3D runs on Unix workstations and on personal computers under Linux. It was tested at RSICC on a SUN UltraSparc 60 under SunOS 5.6 using F77 Version 5 and Fortran 90 Version 2 and on a 450 MHz Pentium III running Redhat Linux Version 6.1 with g77. The package is transmitted in Unix format on CD and includes documentation, source code, and test problems. Reference: Proc. PHYSOR-2000, Pittsburgh, PA (May 2000). Fortran 77; PC, VAX, Unix Workstations (C00695MNYCP00).


Oak Ridge National Laboratory, Oak Ridge, Tennessee, contributed this Monte Carlo N-particle transport code system with digital signal processing, which is a modification of the Los Alamos National Laboratory's Monte Carlo code MCNP4a. The DSP version is used to simulate a variety of subcritical measurements and was developed to simulate frequency analysis measurements, correlation (Rossi-) measurements, pulsed neutron measurements, Feynman variance measurements, and multiplicity measurements. MCNP-DSP is recommended only for experienced MCNP users working with subcritical measurements. CCC-700/MCNP4C is recommended for general purpose calculations.

MCNP-DSP performs calculations very similarly to MCNP and uses the same generalized geometric capabilities of MCNP. It is used to obtain the time-dependent response of detectors that are modeled in the simulation geometry. The detectors represent actual detectors used in measurements. These time-dependent detector responses are used to compute a variety of quantities such as frequency analysis signatures, correlation signatures, multiplicity signatures, etc., between detectors or sources and detectors. A variety of source and detector options are available. However, unlike standard MCNP, the source and detector options are limited to those described in the manual because these options are specified in the MCNP-DSP extra data file.

MCNP-DSP is operable on SUN and DEC Unix workstations and on personal computers that have at least 8 MB memory with an 80486 processor. Both Fortran 77 and ANSI C compilers are needed to install MCNP-DSP on Unix. Compilation of the PC version requires Lahey Fortran F77L-EM/32 V5.2; an executable created with this compiler is included for PC users. DLC-189/MCNPXS, which includes standard cross sections based on ENDF/B-V and ENDF/B-VI, is distributed with the MCNP-DSP package as a convenience to users. The package is transmitted on CD in both DOS and UNIX formats. Reference: ORNL/TM-13334 R2 (October 2000). Fortran 77 and C: SUN and DEC UNIX workstations; Fortran 77 MS-DOS PCs (C00699MNYCP00).

PSR-450/KENO3D 2.00

Oak Ridge National Laboratory, Oak Ridge, Tennessee, contributed a newly frozen version of this visualization tool that can now be used with KENO-VI. KENO3D is a powerful state-of-the-art visualization tool that enables KENO-V.a and KENO-VI users to interactively display their three-dimensional geometry models. The KENO Monte Carlo criticality programs are distributed within the CCC-545/SCALE4.4a package and are not included in this distribution. Familiarity with KENO V.a and KENO-VI is assumed.

KENO3D has the look and feel of a typical PC Windows application. Toolbar buttons are included for all major menu options. A setup dialog allows the user to specify which toolbars should be displayed. An extensive online help system is included in this package to aid the user. The file, KENO3D.chm, is a compiled html file that is viewable while running KENO3D or using Internet Explorer 5.0. KENO3D provides an interface to ACIS® 3D Toolkit. To install and use KENO3D, you must have the following:

  • Windows 95/98/NT PC,
  • a VGA monitor,
  • a Pentium or later processor,
  • at least 32 Megabytes RAM (128-512 Megabytes RAM is recommended), and
  • 30 Megabytes of free disk space is recommended.
KENO3D provides an interface to ACIS® 3D Toolkit. ACIS® is a registered trademark of Spatial Technology Inc. ACIS® is the sole property of Spatial Technology Inc. and is protected by copyright under the laws of the United States. The software is CONFIDENTIAL, PROPRIETARY, and a TRADE SECRET, not to be disclosed without written authorization from Spatial Technology Inc. Any duplication or disclosure of the ACIS® software by other than Spatial Technology Inc. or their assigned licensees and customers is strictly forbidden by law. Copyright© 1989-1998 by Spatial Technology Inc. and Three-Space Ltd. All rights reserved.

Internet Explorer 5 or later is required to use the KENO3D help files. Microsoft C++ Version 6.0 was used to create the executable included in the package. Due to the proprietary nature of the ACIS® software, source code is not available, and each user will be charged a royalty fee. The required ACIS® software is bundled into the executable. The package is transmitted on one CD-ROM which includes the documentation files, executables, and test case input written in DOS format. Reference: README.html (September 2000). Microsoft Visual C++; Pentium (P00450PC58602).


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 finchsy@ornl.gov with "conferences" in the subject line. 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.

Every attempt is made to ensure that the links provided in the Conference and Calendar sections of this newsletter are correct and live. However, the very nature of the web creates the possibility that the links may become unavailable. In that case, please call or mail the contact provided.

MCNP™ Workshops for the Year 2001

The following is the 2001 schedule for Monte Carlo N-Particle Transport Code Workshops. These classes are taught by the team who develops and maintains MCNP.

27 Feb-2 March Advanced Class Los Alamos National Laboratory
2-6 April Level to be decided Imperial College, London, UK
5-8 June Introductory Class Los Alamos National Laboratory

Introductory classes are for people who have little or no experience with MCNP. The classes survey the features of MCNP so the beginning user will be exposed to the capabilities of the program, and will have hands-on experience at running the code to solve rudimentary problems. Course topics include Basic Geometry, Source Definitions, Output (Tallies) Specification and Interpretation, Advanced Geometry (repeated structures specification), Variance Reduction Techniques, Statistical Analysis, Criticality, Plotting of Geometry, Tallies, and Particle Tracks, and Neutron/Photon/Electron Physics.

Advanced classes are for people with MCNP experience who want to extend their knowledge and gain depth of understanding. Most areas of MCNP operation will be discussed in detail, with emphasis on Advanced Geometry, Advanced Variance Reduction Techniques, and other Advanced features of the program. Time will be available to discuss approaches to specific problems of interest to students. 

NOTE: While MCNP supports a number of platforms, class computers are usually Unix machines. Experience with Unix will be helpful to the student but is not essential.

Costs for Domestic U.S. Classes: Cost for the class is $1,800. There is a $300 discount if payment is received by the close of registration/early payment deadline for each class. Radiation Safety Information Computational Center (RSICC) provides the code and data package and documentation for a reduced fee of $310 to all who complete the class and free to students employed by sponsors that fund RSICC.

The class fee includes a notebook with all class viewgraphs (over 300) and handouts. Dinner the first evening is included as part of your registration fee and snacks and refreshments are provided during class breaks. Lodging will be available for roughly $75 per night. Information will be sent by follow-up letter or email when we receive your registration information.

All classes provide interactive computer learning. Time will be available to discuss individual questions and problems with MCNP experts. To register for the LANL classes via the Internet, go to http://www.solutionsbyhqc.com/mcnpform.html. For registration information on the European classes, contact Enrico Sartori, OECD/NEA at sartori@nea.fr.


Your attention is directed to the following events of interest.

December 2000

Fifth Annual Nuclear Congress, Dec. 6-7, 2000, London, England, sponsored by the British Nuclear Energy Society and the British Nuclear Industry Forum. Contact: Sue Frye, ICE Conferences, 1-7 Great George St., London, SW1P 3AA U.K. (tel + 44 20 7665 2315, fax + 44 20 7233 1743, email frye_s@ice.org.uk, url www.bnes.com). 

18th Nuclear Particle Physics Conference, Dec. 10-15, 2000, Adelaide, Australia, sponsored by the Australian Institute of Nuclear Science and Engineering. Contact: Irene Parker, AINSE, PMB 1, Menai NSW 2234 Australia (tel + 02 9717 3436, fax +02 9717 9268, email ainse@ansto.gov.au, url www.ainse.edu.au).

Americas Nuclear Energy Symposium (ANES), Dec. 11-13, 2000, Miami, FL, sponsored by the Department of Energy's Office of Nuclear Energy, Science, and Technology and Florida International University's Hemispheric Center for Environmental Technology. Contact: Ana Ferreira, (tel 305-348-1818, email nuclear@eng.fiu.edu, url http://www.nes2000.org/)

International Conference of National Regulatory Authorities with Competence in the Safety of Radiation Sources and the Security of Radioactive Materials, Dec. 11-15, 2000, Buenos Aires, Argentina, sponsored by the International Atomic Energy Agency. Contact: IAEA, IAEA-CN-84, Vienna International Centre, P.O. Box 100, Wagramerstrasse 5, A-1400 Vienna, Austria; (tel +43 1 2600, fax +43 1 26007, email official.mail@iaea.org; url www.iaea.org/worldatom/).

Symposium Science with Radioactive Beams (PACIFICHEM 2000), Dec. 14-19, 2000, Honolulu, Hawaii, sponsored by the American Chemical Society and others. Contact: Congress Secretariat, ACS, (tel 800-227-5558, fax 202-872-6128, email pacifichem@acs.org, url www.acs.org.) 

February 2001

2001 International ALARA Symposium, Feb. 4-7, 2001, Anaheim, CA, sponsored by the North American Technical Center and others. Contact: David Miller, NATC, (tel 217-935-8881, ext. 3880, fax 217-935-4632, email david_ miller@illinova.com).

Introduction Course to MCBEND Radiation Transport Software, Feb. 6-9, 2001, Winfrith, United Kingdom, sponsored by AEA Technology, Winfrith, UK. Contact: Simon Aplin (tel + 44 (0) 1305 203634, fax +44 (0) 1305 202746, email simon.aplin@aeat.co.uk url www.aeat.co.uk/answers).

Space Technology and Applications International Forum (STAIF-2001), Feb. 11-15, 2001, Albuquerque, NM, sponsored by the Institute for Space and Nuclear Power Studies at the University of New Mexico. Contact: ISNPS-UNM, (tel 505-277-0446, fax 505-277-2814, email isnps@unm.edu, url www-chne.unm.edu/isnps).

Fire and Safety 2001: Fire Protection and Prevention in Nuclear Facilities, Feb. 12-14, 2001, London, England, sponsored by Nuclear Engineering International. Contact: Julie Rossiter, Wilmington Publishing, Ltd., Wilmington House, Church Hill, Wilmington, Dartford, Kent, DA2 7EF, U.K. (tel +44 1322 394706, fax +44 1322 276 743, email conferences@wilmington.co.uk). 

21st Century Biodosimetry: Quantifying the Past and Predicting the Future, Feb. 22, 2001, Arlington, VA, sponsored by the National Council on Radiation Protection and Measurements. Contact: William M. Beckner (tel 301-657-2652, fax 301-907-8768, url www.ncrp.com). 

Waste Management 2001 Symposium, Feb. 25-Mar. 1, 2001, Tucson, AZ, sponsored by WM Symposia, Inc. Contact: LOI, Inc. (tel 520-292-5652, fax 520-292-9080, email info@laser-options.com, url www.wmsym.org). 

Fourth Urals Seminar on Radiation Damage Physics, Feb. 25-Mar. 3, 2001, Snezhinsk, Russia, sponsored by the Institute of Metal Physics. Contact: C.M. Elliott, foreign secretary (tel 217-244-7725, fax 217-244-4293, email cmelliot@uiuc.edu, url www.physics.uiuc.edu/Research/ Workshops/4th_Urals/).

April 2001

Implications for Radiation Measurement Science, Atmospheric and Biospheric Processes, and Health Effects from Worldwide Fallout, Apr. 4-5, 2001, Arlington, VA, sponsored by the National Council on Radiation Protection and Measurements. Contact: William M. Beckner (tel 301-657-2652, fax 301-907-8768, url www.ncrp.com). 

Radiation Transport Calculations using the EGS Monte Carlo System, Apr. 30 - May 3, 2001, Ottawa, Canada. Contact: Blake Walters, Ionizing Radiation Standards, National Research Council of Canada, Ottawa, Canada, K1A 0R6. (tel (613) 993-2715, fax (613) 952-9865, e-mail bwalters@irs.phy.nrc.ca, url www.irs.inms.nrc.ca/inms/irs/papers/egsnrc/brochure.html).

May 2001

The ANSWERS Software Service Reactor Physics, Radiation Shielding and Nuclear Criticality Annual Seminar, May 15-17, 2001, Bournemouth, Dorset, United Kingdom, sponsored by the AEA Technology. Contact: Simon Aplin (tel + 44 (0) 1305 203634, fax +44 (0) 1305 202746, email simon.aplin@aeat.co.uk url www.aeat.co.uk/answers).

June 2001

ANS Annual Meeting, June 17-21, 2001, Milwaukee, WI, more details later.


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., 79, 341-357 . . . Internal Exposure from the Ingestion of Foods Contaminated by 137Cs After the Chernobyl Accident - Report 2. Ingestion Doses of the Rural Population of Ukraine . . . Likhtarev, I.A.; Kovgan, L.N.; Vavilov, S.E.; Perevoznikov, O.N.; Litvinets, L.N.; Anspaugh, . . . October 2000 . . . Radiation Protection Institute, Kyiv, Ukraine; University of Utah, Salt Lake City, UT; GSF-National Research Center for Environment and Health, Neuherberg, Germany.

Health Phys., 79, 358-364 . . . Accelerator Mass Spectrometry of 63Ni at the Munich Tandem Laboratory for Estimating Fast Neutron Fluences from the Hiroshima Atomic Bomb. . . . Ruhm, W.; Knie, K.; Rugel, G.; Marchetti, A.A.; Faestermann, T.; Wallner, C.; McAninch, J.E. . . . October 2000 . . . University of Munich, Munich, Germany; Technical University of Munich, Garching, Germany; Lawrence Livermore National Laboratory, Livermore, CA; University of Utah, Salt Lake City, UT.

Health Phys., 79, 402-406 . . . Using Measured 30-150 kVp Polychromatic Tungsten X-Ray Spectra to Determine Ion Chamber Calibration Factors, Nx(GyC-1). . . . Mercier, J.R.; Kopp, D.T.; McDavid, W.D.; Dove, S.B.; Lancaster, J.L.; and Tucker, D.M. . . . October 2000 . . . University of Texas Health Science Center at San Antonio, San Antonio, TX; Storage Technology Corporation, Louisville, CO. 

Health Phys., 79, 407-411 . . . On the Application of a Radiation Weighting Factor for Alpha Particles in Protection of Non-Human Biota. . . . Kocher, D.C.; Trabalka, J.R. . . . October 2000 . . . Oak Ridge National Laboratory, Oak Ridge, TN.

Health Phys., 79, 412-418 . . . The LNT-Controversy and the Concept of "Controllable Dose." . . . Kellerer, A.M.; Nekolla, E.A. . . . October 2000 . . . Radiobiological Institute of the University of Munich, Munich, Germany; Institute for Radiation Biology of the GSF-National Research Center for Environment and Health, Neuherberg, Germany.

Nucl. Energy, 36, 237 . . . Editoral . . . Williams, M.M.R. . . . April 2000.

Nucl. Eng. Design, 201, 155-175 . . . Design of Advanced Integral-Type Marine Reactor, MRX. . . . Kusunoki, T.; Odano, N.; Yoritsune, T.; Ishida, T.; Hoshi, T.; Sako, K. . . . October 2000 . . . Japan Atomic Energy Research Institute, Ibaraki-ken, Japan; Research Organization for Information Science and Technology, Ibraki-ken, Japan.

Nucl. Eng. Design, 201, 227-238 . . . Procedure to Prevent Temperature Rise of Primary Upper Shielding in High Temperature Engineering Test Reactor (HTTR). . . . Tachibana, Y.; Hontani, K.; Takeda, T.; Saikusa, A.; Shinozaki, M.; Isozaki, M.; Iyoku, T.Kunitomi, K. . . . October 2000 . . . Japan Atomic Energy Research Institute, Ibaraki-ken, Japan.

Nucl. Eng. Design, 201, 259-271 . . . The Development of Passive Design Features for the Korean Next Generation Reactor. . . . Cho, S.J.; Kim, B.S.; Kang, M.G.; Kim, H.G. . . . October 2000 . . . Korea Electric Power Research Institute, Taejon, South Korea.

Nucl. Eng. Design, 201, 289-306 . . .An Approach to the Assessment of High-Level Radioactive Waste Containment. I: Waste Package Degradation. . . . Cragnolino, G.A.; Mohanty, S.; Dunn, D.S.; Sridhar, N.; Ahn, T.M. . . . October 2000 . . . Southwest Research Institute, San Antonio, TX; US Nuclear Regulatory Commission, Washington, DC.

Nucl. Eng. Design, 201, 307-325 . . . An Approach to the Assessment of High-Level Radioactive Waste Containment - II: Radionuclide Releases from an Engineered Barrier System. . . . Mohanty, S.; Codell, R.B.; Ahn, T.M.; Cragnolino, G.A. . . . October 2000 . . . Southwest Research Institute, San Antonio, TX; US Nuclear Regulatory Commission, Washington, DC.

Nucl. Eng. Design, 201, 327-334 . . . Non-Proliferation Attributes of Molten Salt Reactors. . . . Gat, U.; Engel, J.R. . . . October 2000 . . . Oak Ridge National Laboratory, Oak Ridge, TN.

Nucl. Sci. Eng., 136, 151-177 . . . Development of Nonfertile and Evolutionary Mixed-Oxide Nuclear Fuels for Use in Existing Water Reactors. . . .Eaton, S.; Beard, C.; Ramsey, K.; Buksa, J.; Chidester, K. . . . October 2000 . . . Los Alamos National Laboratory, Los Alamos, NM; University of Texas at Austin, Austin, TX.

Nucl. Sci. Eng., 136, 178-201 . . . Split-Cell, Linear Characteristic Transport Method for Unstructured Tetrahedral Meshes. . . . Mathews, K.A.; Miller, R.L.; Brennan, C.R. . . . October 2000 . . . Air Force Institute of Technology, Wright-Patterson AFB, OH.

Nucl. Sci. Eng., 136, 202-226 . . . Acceleration of Multidimensional Discrete Ordinates Methods Via Adjacent-Cell Preconditioners. . . . Azmy, Y.Y. . . . October 2000 . . . Oak Ridge National Laboratory, Oak Ridge, TN.

Nucl. Sci. Eng., 136, 265-271 . . . Calculations for the Excitation Functions of Reactions Induced in 63Cu by Neutrons in the 1- to 20-MeV Energy Range. . . . Gul, K. . . . October 2000 . . . Pakistan Institute of Nuclear Science and Technology, Islamabad, Pakistan.

Nucl. Sci. Eng., 136, 272-281 . . . Definition of Subcriticality Using the Importance Function for the Production of Fission Neutrons. . . . Kobayashi, K.; Nishihara, K. . . . October 2000 . . . Kyoto University, Kyoto, Japan.

Nucl. Sci. Eng., 136, 282-293 . . . Uniform Gauss-Weight Quadratures for Discrete Ordinate Transport Calculations. . . . Carew, J.F.; Hu, K.; Zamonsky, G. . . . October 2000 . . . Brookhaven National Laboratory, Upton, NY.

Nucl. Sci. Eng., 136, 294-304 . . . Hybrid Skyshine Calculations for Complex Neutron and Gamma-Ray Sources. . . . Shultis, J.K. . . . October 2000 . . . Kansas State University, Manhattan, KS.

Nucl. Sci. Eng., 136, 305-319 . . . A Quantitative Analysis of the Feynman- and Rossi-Alpha Formulas with Multiple Emission Sources. . . . Kuang, Z.F.; Pazsit, I. . . . October 2000 . . . Chalmers University of Technology, Goteborg, Sweden.

Nucl. Technol., 132, 3-14 . . . Thermal-Hydraulic Design of the Accelerator Production of Tritium Tungsten Neutron Source. . . . Pasamehmetoglu, K.O.; Willcutt, G.J.; Elson, J.S.; Siebe, D.A. . . . October 2000 . . . Los Alamos National Laboratory, Los Alamos, NM.

Nucl. Technol., 132, 15-29 . . . Disposition of Nuclear Waste Using Subcritical Accelerator-Driven Systems: Technology Choices and Implementation Scenarios. . . . Venneri, F.; Williamson, M.A.; Li, N.; Houts, M.G.; Morley, R.A.; Beller, D.E.; Sailor, W. . . . October 2000 . . . Los Alamos National Laboratory, Los Alamos, NM.

Nucl. Technol., 132, 30-48 . . . Nuclear Simulation and Radiation Physics Investigations of the Target Station of the European Spallation Neutron Source. . . . Filges, D.; Neef, R-D.; Schaal, H. . . . October 2000 . . . Forschungszentrum Juelich, GmbH, Institut fuer Kernphysik, Juelich, Germany.

Nucl. Technol., 132, 49-60 . . . Target Systems Overview for the Spallation Neutron Source. . . . Gabriel, T.A.; Barnes, J.M.; Charlton, L.A.; DiStefano, J.; Farrell, K.; Haines, J.; Johnson, J.O.; Mansur, L.K.; Pawel, S.J.; Siman-Tov, M.; Taleyarkhan, R.; Wendel, M.W. . . . October 2000 . . . Oak Ridge, National Laboratory, Oak Ridge, TN; Lockheed Martin Energy Systems, Inc., Oak Ridge, TN.

Nucl. Technol., 132, 61-65 . . . Intensity and Spectra of a White Light Neutron Source Produced by a 70-MeV Proton Accelerator. . . . Shen, Q.B. . . . October 2000 . . . China Institute of Atomic Energy, Beijing, China.

Nucl. Technol., 132, 66-93 . . . Once-Through Thermal-Spectrum Accelerator-Driven Light Water Reactor Waste Destruction Without Reprocessing. . . . Bowman, C.D. . . . October 2000 . . . The ADNA Corporation, Los Alamos, NM.

Nucl. Technol., 132, 94-102 . . . Neutronic Design Studies for the Spallation Neutron Source. . . . Charlton, L.A.; Barnes, J.M.; Johnson, J.O., Gabriel, T.A. . . . October 2000 . . . Oak Ridge National Laboratory, Oak Ridge, TN.

Nucl. Technol., 132, 103-114 . . . The Accelerator Production of Tritium Materials Test Program. . . . Maloy, S.A.; Sommer, W.F.; James, M.R.; Romero, T.J.; Lopez, M.R.; Zimmermann, E.; Ledbetter, J.M. . . . October 2000 . . . Los Alamos National Laboratory, Los Alamos, NM.

Nucl. Technol., 132, 115-127 . . . Target/Blanket Design for the Accelerator Production of Tritium Plant. . . . Cappiello, M.W.; Lisowski, P.W. . . . October 2000 . . . Los Alamos National Laboratory, Los Alamos, NM.

Nucl. Technol., 132, 128-151 . . . Benchmark Calculations for Standard and Dupic Candu Fuel Lattices Compared with the MCNP-4B Code. . . . Roh, G.; Choi, H. . . . October 2000 . . . Korea Atomic Energy Research Institute, Taejon, Korea.

Nucl. Technol., 132, 152-166 . . . Mitigation Measures Following a Loss-of-Residual-Heat-Removal Event During Shutdown. . . . Seul, K.W.; Bang, Y.S., Kim, H.J. . . . October 2000 . . . Korea Institute of Nuclear Safety, Taejon, Korea.

Nucl. Technol., 132, 167-178 . . . Analysis of an Advanced Test Reactor Small-Break Loss-of-Coolant Accident with an Engineered Safety Feature to Automatically Trip the Primary Coolant Pumps. . . . Polkinghorne, S.T.; Davis, C.F.; McCracken, R.T. . . . October 2000 . . . Idaho National Engineering and Environmental Laboratory, Idaho Falls, ID.

Prog. Nucl. Energy, 36, 323-365 . . . Angular Distribution Due to an Isotropic Point Source and Spherically Symmetrical Eigensolutions of the Transport Equation (MT-112). . . . Davison, B. . . . April 2000 . . . Issued January 31, 1945.

NUREG/CR-6683; ORNL/TM-2000/230 . . . A Critical Review of the Practice of Equating the Reactivity of Spent Fuel to Fresh Fuel in Burnup Credit Criticality Safety Analyses for PWR Spent Fuel Pool Storage . . . Wagner, J.C.; Parks, C.V. . . . September 2000 . . . Oak Ridge National Laboratory, Oak Ridge, TN.