Idaho National Engineering and Environmental Laboratory, Idaho Falls, Idaho, contributed a newly frozen version of this radiological safety analysis code system. RSAC-6 calculates the consequences of the release of radionuclides to the atmosphere. A user can generate a fission product inventory; decay and ingrow the inventory during transport through processes, facilities, and the environment; model the downwind dispersion of the activity; and calculate doses to downwind individuals. Doses are calculated through the inhalation, immersion, ground surface and ingestion pathways. New to RSAC-6 are the ability to calculate inhalation from release to a room, inhalation from resuspension of activities, and a new model for dry deposition. Doses can now be calculated as close as 10 meters from the release point. Internal doses (inhalation and ingestion) are calculated using the ICRP-30 model with dose conversion factors from Federal Guidance Report No. 11 (EPA 1988). External factors are calculated from Federal Guidance Report No. 12 (EPA 1993). This is a significant move from the previous factors that were used in RSAC5. A unique capability is the ability to model Class F fumigation conditions, the meteorological condition that causes the highest ground level concentrations from an elevated release. Dose calculations may be made for either acute or chronic releases. RSAC has been subjected to extensive independent verification and validation for use in performing safety-related dose calculations to support safety analysis reports. RSAC is an excellent tool to evaluate accident conditions in emergency response scenarios.
RSAC-6 runs on Pentium computers under Windows
operating systems. It was tested at RSICC on a Pentium 4 running Windows2000.
The source files are not included in this distribution. RSAC was validated
for the Windows 95, 98, NT and 2000 platforms. The transmittal CD contains
RSAC-6 and RSAC+ executable files plus test cases and documentation written
in self-extracting compressed Windows format. Reference: INEEL/EXT-01-00540
(2001). Fortran 77; Pentium (C00125/PC386/02).
The Safety Research Institute, Kalpakkam, Tamilnadu, India, contributed a newly frozen version of this code system for neutron and gamma-ray shielding calculations by the point kernel method. GUI2QAD is an aid in preparation of input for the included QAD-CGPIC program, which is based on CCC-493/QAD-CGGP and PICTURE. Provision is available to interactively input the geometry and view the same in three dimensions with arbitrary rotations along x,y,z axis. The salient features of the new package are:
a) Handles off-centered multiple identical
The code QAD-CGPIC incorporates both QAD-CGGP
and PICTURE and has a provision to select either ANS-6.4.3 1990 GP buildup
factor compilation or Capo's buildup factors. The code runs on Pentium-III
computers under Windows operating systems. The graphical user interface
is coded in Visual Basic 6. The QAD-CGPIC executable was created with the
Lahey F77L3-EM/32 V5.2 compiler. The package is transmitted on one CD in
a self-extracting, compressed Windows file. References: Informal user manual
(June 2001) and CCC-493 documentation. Visual Basic 6 and Fortran 77; Pentium-III
The Bucharest University, Faculty of Physics,
Bucharest Magurele, Romania, through NEA Data Bank, Issy-les-Moulineaux,
France, contributed this newly frozen version of this code system designated
SCAT-2B. SCAT-2 was designed as a fast, easy-to-use program to calculate
total cross sections, elastic scattering cross sections and their angular
distributions, and transmission coefficients from the optical model of
a spherical nucleus. SCAT-2B extends the incident particles to include
heavy ions. SCAT-2B runs on workstations and Pentium computers. The SCAT-2B
source code was written in Fortran 77 and was tested at RSICC on an IBM
RS/6000 Model 270 running AIX 4.3.3 with xlf Fortran 7.1 and on a Pentium
4 in a DOS window of Windows2000 with the Digital Visual Fortran 6.0 compiler.
The DVF executable was added to the package. This release was also tested
at the NEA Data Bank under Linux with the g77 compiler. The SCAT distribution
CD includes both the new SCAT-2B release and the previous release SCAT-2.
The package is transmitted on one CD in self-extracting compressed Windows
files which include Fortran source, PC executables, and sample case input
and output. References: CEA-N-2227 (October 1981) and NEANDC-152'A', INDC(NEA)4
(October 3, 1983). Fortran 77; Pentium and IBM RS/6000 (SCAT-2B P00294/MNYCP/02).
Fortran 77; IBM PC, VAX, and IBM mainframe (SCAT-2 P00294/MNYCP/01).
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.
Organizer: Hamilton Quality Consulting
MCNPX is the LANL all-particle, all-energy
(eV-GeV) Monte Carlo transport code based on MCNP4C2, LAHET, CEM, etc.
MCNPX has been developed for the past six years, particularly for the high-energy
accelerator community, and has now become an accepted tool for a broad
range of applications by nuclear engineers, physicists, and scientists.
All workshops are hands-on and will include a distribution of MCNPX 2.3
(subject to participant export approval), LA150 (150 MeV) cross-section
data, and a notebook of viewgraphs. More information on course topics and
fees can be found at the registration website.
There is no fee to participate in the meeting.
Advance registration is requested, for planning purposes. Everyone, including
COSYMA users, are invited to present a paper. Please visit the website
to find out about IMUG, register for the meeting or request notification
of web updates. The website will be updated as additional information becomes
EC-Sponsored Training Course on Radioecological Assessment and Decision-Making Techniques for the Management of Contaminated Freshwater Ecosystems, Jan. 29-Feb. 2, 2002, Madrid, Spain. Sponsored by Polytechnic University of Madrid. Contact: Prof. Alfredo Lorente (tel +34 91 336 3113, then dial ext. 104, fax +34 91 336 3002, email email@example.com).
Hardened Electronics and Radiation Technology (HEART) Conference, Mar. 11-15, 2002, Monterey, CA. Contact: Thomas Stringer, chair (tel 719-599-1719, fax 719-599-1991).
Thirty-Eighth Annual Meeting of the National Council on Radiation Protection and Measurements, Apr. 10-12, 2002, Arlington, VA. Contact: William M. Beckner (tel 301-657-2652, fax 301-907-8768, url www.ncrp.com).
Back to the Future of Nuclear Technology, 2002 ANS Student Conference, Apr. 10-13, 2002, University Park, PA. Contact: Frank Buschman (tel 814-865-6351, email firstname.lastname@example.org, url www.clubs.psu.edu/ANS).
12th Biennial RPSD Topical Meeting, Apr. 14-17, 2002, Santa Fe, NM. Hosted by the ANS Trinity Section and cosponsored by the Health Physics Society, L'Organisation de cooperation et de developpement/L'Agence pour l'energie nucleaire (OECD/AEN, and RSICC. Contact: (email rpsd2002@lanl. gov, url www.lanl.gov/RPSD2002/).
International Youth Nuclear Congress 2002, Apr. 16-20, 2002, Taejon, Korea. Contact: Alexandre Tsiboulia or Han Seong Son (email email@example.com, firstname.lastname@example.org, url http://www.iync.org).
Seventh International Radiopharmaceutical Dosimetry Symposium, Apr. 17-19, 2002, Nashville, TN. Contact: Michael Stabin (email email@example.com, url http://www.doseinfo-radar.com/symphome.html).
Symposium on Radiation Measurements and Applications, May 21-23, 2002, Ann Arbor, MI. Contact: General Chair David K. Wehe (tel 734-764-6215, email firstname.lastname@example.org, url http://rma -symposium.engin.umich.edu/).
Topical Meeting: Industrial Radiation and Radioisotope Measurement Applications IRRMA-V A Class IV Topical, June 9-14, 2002, Bologna, Italy, co-sponsored by the American Nuclear Society. Contact: Prof. Jorge Fernandez (Chair) (e-mail: email@example.com)
Fourth Meeting of the International MACCS Users Group (IMUG) September 6, 2002, in the Principality of Monaco (url www.bnl.gov/est/IMUG2002).
PHYSOR 2002, Oct. 7-10, 2002, Seoul,
Korea, sponsored by the American Nuclear Society and hosted by the Korean
Nuclear Society. Contact: Prof. Nam Zin Cho (tel +82-42-869-3819, fax +82-42-869-5859,
First Asian and Oceanic Congress for Radiation Protection (AOCRP-1), Oct. 20-24, 2002, Seoul, Korea, sponsored by the Korean Association for Radiation Protection (KARP). Contact: Dr. Myung-Jae Song (tel +82-42-870-0202, fax +82-42-870-0269, email firstname.lastname@example.org; url www.aocrp-1.com).
International Conference on Supercomputing
in Nuclear Applications, SNA 2003, September 22-24, 2003, Paris, France.
Organizers: CEA, SFANS, co-organizer: OECD/NEA. (email
Ann. Nucl. Energy, 28, 1799-1807 . . . Groundwater Contaminant Transport in Presence of Colloids II: Sensitivity and Uncertainty Analysis on Literature Case Studies. . . . Marseguerra, M.; Patelli, E.; Zio, E. . . . December 2001 . . . Polytechnic of Milan, Italy.
Ann. Nucl. Energy, 28, 1809-1824 . . . The Greuling-Goertzel and Wigner Approximations in the Theory of Neutron Slowing Down. . . . Larsen, E.W.; Ahrens, C. . . . December 2001 . . . University of Michigan, Ann Arbor, MI.
Ann. Nucl. Energy, 28, 1825-1850 . . . Temperature Distribution in Nuclear Fuel Rod and Variation of the Neutronic Performance Parameters in (D-T) Driven Hybrid Reactor System. . . . Yapici, H.; Ipek, O.; Özceyhan, V. . . . December 2001 . . . Erciyes Üniversitesi Mühendislik-Mimarlik Fakültesi, Kayseri, Turkey; Süleyman Demirel Üniversitesi Mühendislik-Mimarlik Fakültesi, Isparta, Turkey.
Ann. Nucl. Energy, 28, 1851-1880 . . . Discretizing the Diffusion Equation on Unstructured Polygonal Meshes in Two Dimensions. . . . Palmer, T.S. . . . December 2001 . . . Oregon State University, Corvallis, OR.
Ann. Nucl. Energy, 29, 109-136 . . . Application of Preconditioned GMRES to the Numerical Solution on the Neutron Transport Equation. . . . Patton, B.W.; Holloway, J.P. . . . January 2002 . . . University of Michigan, Ann Arbor, MI.
Ann. Nucl. Energy, 29, 137-145 . . . Monotonicity Properties of keff with Shape Change and with Nesting. . . . Arzhanov, V. . . . January 2002 . . . Chalmers University of Technology, Göteborg, Sweden; Keldysh Institute of Applied Mathematics, Moscow, Russia.
Ann. Nucl. Energy, 29, 147-168 . . . Simultaneous and Multi-Criteria Optimization of TS Requirements and Maintenance at NPPs. . . . Martorell, S.; Sánchez, A.; Carlos, S.; Serradell, V. . . . January 2002 . . . Polytechnical University of Valencia, Spain.
Ann. Nucl. Energy, 29, 169-192 . . . A Unified Theory of Zero Power and Power Reactor Noise Via Backward Master Equations. . . . Pázsit, I.; Kuang, Z.F.; Prinja, A.K. . . . January 2002 . . . Chalmers University of Technology, Göteborg, Sweden; China Institute of Atomic Energy, Beijing, China; University of New Mexico, Albuquerque, NM.
Ann. Nucl. Energy, 29, 193-213 . . . Critical Conditions in an Infinitely Reflected, Multiplying Slab Using Two-Group, Integral Transport Theory. . . . Williams, M.M.R. . . . January 2002. . . no address given.
Ann. Nucl. Energy, 29, 215-234 . . . Modal Influence of the Detector Location for the Noise Calculation of the ADS. . . . Rugama, Y.; Muñoz-Cobo, J.L.; Valentine, T.E. . . . February 2002 . . . Universidad Politécnica de Valencia, Spain; Oak Ridge National Laboratory, Oak Ridge, TN.
Ann. Nucl. Energy, 29, 255-269 . . . Validation of Coupled Neutron Kinetic/Thermal-Hydraulic Codes. Part 2: Analysis of a VVER-440 Transient (Loviisa-1) . . . Hämäläinen, A. et al. . . . February 2002 . . . VTT Energy, VTT, Finland; FZR Forschungszentrum Rossendorf, Dresden, Germany; GRS, Garching, Germany; Kurchatov Institute, Moscow, Russia; NRI Nuclear Research Institute, Rez, Czech Republic; AEKI-KFKI Atomic Energy Research Institute, Budapest, Hungary.
Ann. Nucl. Energy, 29, 271-286 . . . Modeling and Parametric Studies of the Effect of Inhomogeneity on Fission Gas Release in LWR MOX Fuel. . . . Koo, Y-H.; Lee, B-H.; Cheon, J-S,; Sohn, D-S. . . . February 2002 . . . Korea Atomic Energy Research Institute, Daejon, South Korea.
Ann. Nucl. Energy, 29, 287-302 . . . Investigation of the Flattened Fissile Fuel Enrichment Possibility with a (D,T) Driven Hybrid Blanket Cooled by Flibe (Li2BeF4). . . . Akansu, S.O.; Ünalan, S. . . . February 2002 . . . Erciyes Üniversitesi Mühendislik Fakültesi, Kayseri, Turkey.
Ann. Nucl. Energy, 29, 303-321 . . . A Subchannel Analysis Code MATRA-LMR for Wire Wrapped LMR Subassembly. . . . Kim, W-S.; Kim, Y-G.; Kim, Y-J. . . . February 2002 . . . Korea Atomic Energy Research Institute, Taejon, Korea.
Health Phys., 77, 505-511 . . . A Brief History of Nuclear Criticality Accidents in Russia. . . . Vargo, G.J. . . . November 1999 . . . Pacific Northwest National Laboratory, Richland, WA.
Health Phys., 77, 536-540 . . . Improved Estimates of Effective Dose Equivalent Using Two Optimal Anisotropic Responding Dosimeters. . . . Han, H.J.; Reece, W.D.; Kim, C.H. . . . November 1999 . . . Texas A&M University, College Station, TX.
Health Phys., 77, 571-578 . . . Mass Attenuation Coefficients of Clear-Pb for Photons from 125I, 103Pd, 99mTc, 192Ir, 137Cs, and 60Co. . . . Rivard, M.J.; Waid, D.S.; Wierzbicki, J.G. . . . November 1999 . . . Tufts University School of Medicine, Boston, MA; Hackley Hospital, Muskegon, MI; St. Mary's Medical Center, Saginaw, MI.
Health Phys., 77, 588-594 . . . Radiation Safety System of the B-Factory at the Stanford Linear Accelerator Center. . . . Liu, J.C. et al. . . . November 1999 . . . Stanford Linear Accelerator Center, Stanford, CA.
J. Nucl. Mater., 298, 211-224 . . . Microstructural Characterization of Irradiation-Induced Cu-Enriched Clusters in Reactor Pressure Vessel Steels. . . . Carter, R.G. et al. . . . October 2001 . . . EPRI, Charlotte, NC; Central Research Institute of Electric Power Industry, Tokyo, Japan; AEA Technology, Oxon, UK; ATI Consulting, Pinehurst, NC.
J. Nucl. Mater., 298, 225-230 . . . Deuterium in Re-Deposited Silicon-Doped Carbon Layers and Its Removal by Heating in Air. . . . Balden, M.; Mayer, M. . . . October 2001 . . . Max-Planck-Institut fur Plasmaphyusik, Garching, Germany.
J. Nucl. Mater., 298, 231-238 . . . Accumulation of Radioactive Corrosion Products on Steel Surfaces of VVER-Type Nuclear Reactors. II. 60Co. . . . Varga, K. et al. . . . October 2001 . . . University of Veszprém, Hungary; University of Pretoria, South Africa; Paks NPP Co., Ltd., Paks, Hungary.
J. Nucl. Mater., 298, 239-247 . . . In Situ Raman Spectroscopic Investigation of Zirconium-Niobium Alloy Corrosion Under Hydrothermal Conditions. . . . Maslar, J.E.; Hurst, W.S.; Bowers, Jr., W.J.; Hendricks, J.H. . . . October 2001 . . . National Institute of Standards and Technology, Gaithersburg, MD.
J. Nucl. Mater., 298, 248-254 . . . Mechanical Properties of Pure Tantalum After 800 MeV Proton Irradiation. . . . Chen, J. et al. . . . October 2001 . . . Projekt ESS, Julich, Germany; University of Ancona, Italy; Rutherford Appleton Laboratory, Chilton, UK.
J. Nucl. Mater., 298, 255-268 . . . Thermochemical and Thermophysical Properties of Curium and Its Oxides. . . . Konings, R.J.M. . . . October 2001 . . . Joint Research Center, Karlsruhe, Germany.
J. Nucl. Mater., 298, 269-279 . . . Strain Hardening and Plastic Instability Properties of Austenitic Stainless Steels After Proton and Neutron Irradiation. . . . Byun, T.S.; Farrell, K.; Lee, E.H.; Hunn, J.D.; Mansur, L.K. . . . October 2001 . . . Oak Ridge National Laboratory, Oak Ridge TN.
J. Nucl. Mater., 298, 280-290 . . . Use of UO2 Films for Electrochemical Studies. . . . Miserque, F.; Gouder, T.; Wegen, D.H.; Bottomley, P.D.W. . . . October 2001 . . . JRC, Institute for Transuranium Elements, Karlsruhe, Germany; Facultés Universitaires Notre-Dame de la Paix, Belgium, Germany.
J. Nucl. Mater., 298, 291-296 . . . Dissolution of Oxygen-Enriched Zircaloy-2. . . . Oskarsson, M.; Ahlberg, E.; Pettersson, K. . . . October 2001 . . . Royal Institute of Technology, Stockholm, Sweden; Göteborg University, Göteborg, Sweden.
J. Nucl. Mater., 298, 297-308 . . . In Situ Characterization of Zircaloy-4 Oxidation at 500 C in Dry Air. . . . Vermoyal, J.J.; Sessemond, L.; Hammou, A.; Frichet, A. . . . October 2001 . . . Laboratory of Electrochemistry and Physical-Chemistry of Materials and Interfaces, St. Martin d'Hères, France; Framatome Nuclear Fuel, Lyon, France.
J. Nucl. Mater., 298, 309-315 . . . Activation of Stainless Steel with High Energy Neutrons. . . . Grégoire, O.; Ladrière, J. . . . October 2001 . . . Université Catholique de Louvain, Louvain-la-Neuve, Belgium.
J. Nucl. Mater., 298, 316-320 . . . Structural and Thermal Investigations on Cerium Oxalate and Derived Oxide Powders for the Preparation of (Th,Ce)O2 Pellets. . . . Alta, Y.; Tel, H. . . . October 2001 . . . Ege University, Bornova-Izmir, Turkey.
Nucl. Sci. Eng., 138, 205-232 . . . Inherent and Passive Safety Sodium-Cooled Fast Reactor Core Design with Minor Actinide and Fission Product Incineration. . . . Kuraishi, H.; Sawada, T.; Ninokata, H.; Endo, H. . . . July 2001 . . . Tokyo Institute of Technology, Tokyo, Japan; Toshiba Corp., Yokohama, Japan.
Nucl. Sci. Eng., 138, 233-255 . . . Improved Gamma-Heating Calculational Methods for Fast Reactors and Their Validation for Plutonium-Burning Configurations. . . . Lüthi, A.; Chawla, R.; Rimpault, G. . . . July 2001 . . . Swiss Federal Institute of Technology, Lausanne, Switzerland; Commissariat á l'Energie Atomique, St. Paul-Lez-Durance, France.
Nucl. Sci. Eng., 138, 256-268 . . . Discontinuous Finite Element SN Methods on Three-Dimensional Unstructured Grids. . . . Wareing, T.A.; McGhee, J.M.; Morel, J.E.; Pautz, S.D. . . . July 2001 . . . Los Alamos National Laboratory, Los Alamos, NM.
Nucl. Sci. Eng., 138, 269-278 . . . Fast Tree Multigrid Transport Application for the Simplified P3 Approximation. . . . Kotiluoto, P. . . . July 2001 . . . VTT Chemical Technology, VTT, Finland.
Nucl. Sci. Eng., 138, 279-294 . . . Sensitivity Analysis of Nuclide Importance to One-Group Neutron Cross Sections. . . . Sekimoto, H.; Nemoto, A.; Yoshimura, Y. . . . July 2001 . . . Tokyo Institute of Technology, Tokyo, Japan.
Nucl. Sci. Eng., 138, 295-304 . . . Homogeneous 242mAm-Fueled Reactor for Neutron Capture Therapy. . . . Ronen, Y.; Aboudy, M.; Regev, D. . . . July 2001 . . . Ben-Gurion University, Beer-Sheva, Israel.
Nucl. Sci. Eng., 138, 315-321 . . . Importance of Delayed Neutrons on the Coupled Neutronic-Thermohydraulic Stability of a Natural Circulation Heavy Water-Moderated Boiling Light Water-Cooled Reactor . . . Nayak, A.K.; Aritomi, M.; Raj, V.V. . . . July 2001 . . . Bhabha Atomic Research Centre, Mumabi, India; Tokyo Institute of Technology, Tokyo, Japan.
Nucl. Sci. Eng., 139, 111-117 . . . High-Resolution Transmission Measurements of 233U Using a Cooled Sample at the Temperature T=11K. . . . Guber, K.H. et al. . . . October 2001 . . . Oak Ridge National Laboratory, Oak Ridge, TN.
Nucl. Sci. Eng., 139, 118-137 . . . Conceptual Design of a Fluidized Bed Nuclear Reactor. . . . Kloosterman, J.L. et al. . . . October 2001 . . . Delft University of Technology, JB Delft, Netherlands.
Nucl. Sci. Eng., 139, 138-155 . . . Conceptual Neutronic Design of a Lead-Bismuth-Cooled Actinide Burning Reactor. . . . Hejzlar, P.; Driscoll, M.J.; Kazimi, M.S. . . . October 2001 . . . Massachusetts Institute of Technology, Cambridge, MA.
Nucl. Sci. Eng., 139, 185-208 . . . Analytic Radiation Transport Systems and Monte Carlo Benchmarks. . . . Cramer, S.N. . . . October 2001 . . . Oak Ridge National Laboratory, Oak Ridge, TN.
Nucl. Sci. Eng., 139, 209-220 . . . Measurement of Neutron and Gamma-Ray Absorbed Doses Under Criticality Accident Conditions at TRACY Using Tissue-Equivalent Dosimeters. . . . Sono, H.; Yanagisawa, H.; Ohno, A.; Kojima, T.; Soramasu, N. . . . October 2001 . . . JAERI, Ibaraki, Japan; JAERI, Gumma, Japan; Matsushita Industrial Equipment Co., Ltd., Osaka, Japan.
Nucl. Technol., 134, 221-230 . . . Startup Thermal Considerations for Supercritical-Pressure Light Water-Cooled Reactors. . . . Nakatsuka, T.; Oka, Y.; Koshizuka, S. . . . June 2001 . . . University of Tokyo, Ibaraki, Japan.
Nucl. Technol., 134, 231-240 . . . Distribution Behavior of U(VI), Pu(IV), Am(III), and Zr(IV) with N,N-Dihexyl Octanamide Under Uranium-Loading Conditions. . . . Manchanda, V.K. et al. . . . June 2001 . . . Bhabha Atomic Research Center, Mumbai and Tarapur, India.
Nucl. Technol., 134, 241-262 . . . Geomechanical and Thermal Effects on Moisture Flow at the Proposed Yucca Mountain Nuclear Waste Repository. . . . Ofoebgbu, G.I. et al. . . . June 2001 . . . Southwest Research Institute, San Antonio, TX.
Nucl. Technol., 134, 263-277 . . . A Description of the Ceramic Waste Form Production Process from the Demonstration Phase of the Electrometallurgical Treatment of EBR-II Spent Fuel. . . . Simpson, M.F. et al. . . . June 2001 . . . Argonne National Laboratory-West, Idaho Falls, ID.
Nucl. Technol., 134, 278-293 . . . Optimization of Beam-Shaping Assemblies for BNCS Using the High-Energy Neutron Sources D-D and D-T. . . . Verbeke, J.M.; Chen, A.S.; Vujic, J.L.; Leung, K-N. . . . June 2001 . . . University of Berkeley, Berkeley, CA; Lawrence Berkeley National Laboratory, Berkeley, CA.
Nucl. Technol., 136, 63-75 . . . The Shielding Effect of Iron Louvers for Neutrons and Gamma Rays. . . . Mio, K.; Kurashige, T.; Kosako, T. . . . October 2001 . . . Ishikawajima-Harima Heavy Industries Co., Ltd., Yokohama, Japan; University of Tokyo, Japan.
Nucl. Technol., 136, 76-88 . . . Induced Radioactivity and Waste Classification of Reactor Zone Components of the Chernobyl Nuclear Power Plant Unit 1 After Final Shutdown. . . . Bylkin, B.K. et al. . . . October 2001 . . . Kurchatov Institute, Moscow, Russia; Chernobyl Nuclear Power Plant, Slavutych, Ukraine; Slavutych Division of the International Chernobyl Center, Slavutych, Ukraine.
Nucl. Technol., 136, 89-98 . . . Development of the Process for the Recovery and Conversion of 233UF6 Chemisorbed in NaF Traps from the Molten Salt Reactor Remediation Project. . . . Del Cul, G.D.; Icenhour, A.S.; Simmons, D.W. . . . October 2001 . . . Oak Ridge National Laboratory, Oak Ridge, TN.
Nucl. Technol., 136, 99-129 . . . Unfavorable Conditions for Nuclear Criticality Following Disposal of Transuranic Waste at the Waste Isolation Pilot Plant. . . . Rechard, R.P.; Sanchez, L.C.; Trellue, H.R.; Stockman, C.T. . . . October 2001 . . . Sandia National Laboratories, Albuquerque, NM.
Nucl. Technol., 136 130-140 . . . 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 St . . . Wagner, J.C.; Parks, C.V. . . . October 2001 . . . Oak Ridge National Laboratory, Oak Ridge, TN.