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Current papers in nuclear energy
Ann. Nucl. Energy, Vol. 24, No. 11, pp. 917-920, 1997
Pergamon PII: S0306-4549(97)00001-7
© 1997 Elsevier Science Ltd. All rights reserved Printed in Great Britain 0306-4549/97 $17.00 + 0.00
CURRENT PAPERS IN NUCLEAR ENERGY A selected list of references from the following journals:
Nuclear Science and Engineering Nuclear Technology Nuclear Engineering and Design Journal of Nuclear Science and Technology Journal of Nuclear Materials REACTOR PHYSICS A Monte Carlo model for gamma ray Klein - Nishina scattering probabilities to finite detectors. Li D. et al J. Nucl. Sci. & Technol. 33, 736 (1996) (Institute of Applied Physics and Computational Mathematics, P.O.Box 8009, Beijing 100088, Peoples Republic of China) Epithermal neutron beam up grade with a fission plate converter at the Brookhaven Medical Research Reactor. Liu H.B. et al Nucl. Technol. 116, 373 (1996) (Brookhaven National Laboratory, Medical Department, Upton, New York 11973) Exposure buildup factors of UO2 using the Monte Carlo method. Bozkurt A. and Tsoulfanidir N. Nucl. Technol. 116, 257 (1996) (University of Missouri - Rolla, 221 Fulton Hall, Rolla, Mo 65401, U.S.A.) Boundary condition perturbations in transport theory. Rahnema F. Nucl. Sci. & Eng. 124 (2) 320 (1996) (Georgia Institute of Technology, Nuclear Engineering and Health Physics Programs, Atlanta, Georgia 30332-0405, U.S.A.) A modified P3-1ike approximation to the transport equation. Su B. and Pomraning G.C. Nucl. Sci. & Eng. 124 (2) 309 (1996) (University of California, Los Angleles, School of Engineering and Applied Science, Los Angeles, California 90095-1597, U.S.A.) Optimization of nonanalog Monte Carlo games using differential operator sampling. *Sarkar P.K. and Rief H. Nucl. Sci. & Eng. 124 (2) 291 (1996) (CEC, Ispra Establishment, 1-21020 Ispra (Va), Italy) The 59Co (n, X, a) reaction from 5 to 50 MeV. Grimes S.M. et al Nucl. Sci. & Eng. 124 (2) 271 (1996) (Ohio University, Athens, Ohio 45701, U.S.A.) Analysis of nuclear power transmission potential at equilibrium. Salvatores M. et al. Nucl. Sci. & Eng. 124 (2) 280 (1996) (CEA, Nuclear Reactor Directorate, Cadarache, France) Effects of the photon cross sections and energy-absorption coefficients of air to the gamma-ray point isotTopic exposure buildup factors. Hirayarna H. Nucl. Sci. & Eng. 124 (2) 258 (1996) (National Laboratory for High Energy Physics, 1 - 10ho, Tsukuba-shi, Ibaraki 305, Japan) Transmission through shields of quasi-monoenergetic neutrons generated by 43- and 68MeV protens - 1: concrete shielding experiment and calculation for practical application. Nakao N. Nucl. Sci. & Eng. 124 (2) 228 (1996) 917
918
Current Papers in Nuclear Energy (Tohoku University, Cyclotron and Radioisotope Centre, Aramaki, Akobo-ku, Sendai 980, Japan Fission cross-section measurements of the odd-odd isotopes 232pa 238Np, and 236Np. Danon Y. et al Nucl. Sci. & Eng. 124 (3) 482 (1996) (Rensselaer Polytechnic Institute, Department of Nuclear Engineering and Engineering Physics, Troy, New York 12180, U.S.A.) Technical Note. Statistical model calculations of the 232U fission cross section. Maslov V.M. and Kikuchi Y. Nucl. Sci. & Eng. 124 (3) 492 (1996) (Japan Atomic Energy Research Institute, Tokai-mura, Nuka-gun, Ibartaki-ken, 319-11, Japan) Systematic evaluation of neutron shielding effects for materials. Ueki K. et al Nucl. Sci. & Eng. 124 (3) 455 (1996) (Ship Research Institute, 6-38-1 Shinkawa, Mitaka, Tokyo 181, Japan) Thermalization of neutrons in graphite: status and error analysis. Difilippo F.C. et al Nucl. Sci. & Eng. 124 (3) 465 (1996) (Oak Ridge National Laboratory, P.O.Box 2008, Building 6025, Oak Ridge, Tenn 37831-6363, U.S.A.) The derivation and proper use of stewart's formula for thermal neutron self-shielding in scattering media. Blaauw M. Nucl. Sci. & Eng. 124 (3) 431 (1996) (Delft University of Technology, Mekelweg 15, 2629 JB Delft, The Netherlands) Wavelet Theory for solution of the neutron diffusion equation. Cho N.Z. and Park C.J. Nucl. Sci. & Eng. 124 (3) 417 (1996) (Department of Nuclear Engineering, 373-1 Kusong-dong, Yusong-gu, Taejon Korea 305-701) Higher order Fokker-Planck operators. Pomraning G.C. Nucl. Sci. & Eng. 124 (3) 390 (1996) (University of California, Los Angeles, School of Engineering and Applied Science, Los Angeles, California 90095-1597, U.S.A.) Forward-adjoint Monte Carlo coupling with no statistical error propagation. Cramer S.N. Nucl. Sci. & Eng. 124 (3) 398 (1996) (Oak Ridge National Laboratory, P.O.Box 2008, Oak Ridge, Tenn 37831-6362, U.S.A.) A hybrid multigroup/continuous-energy Monte Carlo method for solving the BoltzrnannFokker-Planck equation. Morel J.E. et al Nucl. Sci. & Eng. 124 (3) 369 (1996) (Los Alamos National University, Los Alamos, New Mexico, 87545, U.S.A.) Technical Note. A Semiempirical method to calculate continuum gamma-ray spectra and multiplicities from neutron-induced reactions. Fan S. and Zhao Z. Nucl. Sci. & Eng. 124 (2) 349 (1996) (Chinese Nuclear Data Centre, Institute of Atomic Energy, P.O.Box 274 (41), Beijing 102413, China) Design concept of fast spectrum pulse reactor with packed core of coated dilute fuel particles. Obara T. and Sekimoto H. J.Nucl. Sci. & Technol. 33 (7) 547 (1996) (Research Laboratory for Nuclear Reactors, Tokyo Institute of Technoloigy, 0-okayama Meguro-ku, Tokyo 152, Japan)
Current Papers in Nuclear Energy SAFETY Reliability of systems subject to common cause hazards assumed to obey an exponential power model. EI-Damcese, M.A. Nucl. Engng & Des. 167 85 (1996) (Mathematics Department, Tanta University, Tanta, Egypt) Probabilistic fire analysis capabilities, applications and weak points. Fernandez P. Nucl. Engng & Des. 167 77 (1996) (Safety Department, Reliability Section, A I E, Magallanes 3, 28015 Madrid, Spain) Identifying organizational deficiences through root-cause analysis. Tuli R.W. et al Nucl. Technol. 116, 334 (1996) (S A I C, 1309 Continental Drive, Abingdon MD 21009, U.S.A) L W R aerosol containment experiment LA4 simulated by Jericho to Aerosols-B2 codes. Passalacque R. et al Nucl. Technol. 116, 283 (1996) (E N E A, C R E, Cassacia via Auguillarese 301, 00060 Rome, Italy) Modelling of thermophosetic deposition of aerosols in nuclear reactor containments. Fernandes A. and Loyalka S.K. Nucl. Technol. 116, 270 (1996) (University of Missouri-Columbia, Nuclear Engineering Progam, Columbia, MO 65211, U.S.A.) Failure dependent test repair and shutdown strategies: reducing the impact of common cause failures. Uryasev S.P. et al Nucl. Technol. 116, 245 (1996) (Brookhaven National Laboratory, Building 130, Upton, N.Y. 11973-5000, U.S.A.) DYNAMICS AND CONTROL Package flowmodels by neural network representation. Matsuoka H. et al J. Nucl. Sci. & Technol. 33, 675 (1996) (Science & Technology Agency, Chiyoda-ku, Tokyo 100, Japan) Analytic initialization of non equilibrium iodine and xenon distributions for core transient simulation. Song J.S. et al Nucl. Technol. 116, 137 (1996) (K A I S T, Taejon, 305-701, Korea) Neural network-based fault detections in a pressurized water reactor pressurizer. Marseguerra M. et al Nucl. Sci. & Eng. 124 (2) 339 (1996) (Polytechnic of Milan, Department of Nuclear Engineering, via Ponzio 34/3, 20133, Milano, Italy) Quantitive method to measure void fraction of two-phase flow using electronic imaging with neutrons. Mishima K. and Hibiki T. Nucl. Sci. & Eng. 124 (2) 327 (1996) (Kyoto University, Research Reactor Institute, Kumatori-cho, Sennan-gun, Osaka 590-04, Japan) MATERIALS Helium production by 9.85- MeV neutrons in elemental iron, nickel and copper and in 56Fe and 58,60,61Ni. Haight R.C. et al Nucl. Sci. & Eng. 124 (2) 219 (1996) (Los Alamos National Laborator, Los Alarnos, New Mexico, 87545, U.S.A.) Solibility of nickel fcrrite in high-temperature pure or oxygeneratcd water. Hanzawa Y. et al Nucl. Sci. & Eng. 124 (2) 211 (1996) (The University of Tokyo, Department of Quantum Engineering and Systems Science, 73-1 Hongo, Bunkyo-ku, Tokyo 113, Japan)
919
920
Current Papers in Nuclear Energy Kinetics of dissolution of uranium metal foil by Alkaline hydrogen peroxide. Dong D. and Vandegrift G.F. Nucl. Sci. & Eng. 124 (3) 73 (1996) (Argonne National Laboratory, Chemical Technology Division, 9700 South Cass Av. Argonne, IU 60439, U.S.A.) NUCLEARFUEL Development of a coated fuel particle failure model under high burnup irradiation. Sawa K. et al J.Nucl. Sci. & Technol. 33, 712 (1996) (Department of H T T R Project, J A E R I, Ibaraki-ken, 311-13, Japan) Core performance of fast reactors for actinide recycling using metal, nitride and oxide fuels. Yokoo T. et al Nucl. Technol. 116, 173 (1996) (Central Research Institute of Electric Powert, Komae, Tokyo, Japan) Mass spectrometric measurements of fission product effusion from irradiated light water reactor fuel. Capone F. et al Nucl. Sci. & Eng. 124 (3) 436 (1996) (European Commission, Joint Research Centre, European Institute for Transuranium Elements, Karlsruhe, Germany) NUCLEAR WASTE Efficient modelling of reactive transport phenomena by a multispecies random walk coupled to chemical equilibrium. Pfingsten W. Nucl. Technol. 116, 208 (1996) (P S I CH-5232 Villigen-PSI, Switzerland) Treatment of simulated high-level radioactive waste with formic acid. Hsu, C.L. et al Nucl. Technol. 116, 196 (1996)
(Westinghouse Savannah River Co., Aiken, S. Carolina, 29808, U.S.A.) HEAT TRANSFER AND FLUID DYNAMICS An experimental investigation of natural convection heat transfer within horizontal spent fuel assemblies. Caraan, R.E. et al Nucl. Technol. 116, 306 (1996) (University of Texas at Austin, College of Engineering, ECJ 10.388, Austin, Texas 78712, U.S.A.) Development and assessment of US nuclear regulatory commission thermal-hydraulic system computer codes. Shotkin L.M. Nucl. TechnoL 116, 231 (1996) (US NRC, Mailstop T-10 E37, Washington DC 20555, U.S.A) STRUCTURAL MECHANICS Measurement of the yield and tensil strength of neutron-irradiated and post-irradiation recovered vessel steels. Valiente A. et al Nucl. Engng & Des. 167, 11 (1996) (Materials Science Dept. Polytechnic University of Madrid, 28040 Madrid, Spain)
Pergamon PII: S0306-4549(97)00001-7
© 1997 Elsevier Science Ltd. All rights reserved Printed in Great Britain 0306-4549/97 $17.00 + 0.00
CURRENT PAPERS IN NUCLEAR ENERGY A selected list of references from the following journals:
Nuclear Science and Engineering Nuclear Technology Nuclear Engineering and Design Journal of Nuclear Science and Technology Journal of Nuclear Materials REACTOR PHYSICS A Monte Carlo model for gamma ray Klein - Nishina scattering probabilities to finite detectors. Li D. et al J. Nucl. Sci. & Technol. 33, 736 (1996) (Institute of Applied Physics and Computational Mathematics, P.O.Box 8009, Beijing 100088, Peoples Republic of China) Epithermal neutron beam up grade with a fission plate converter at the Brookhaven Medical Research Reactor. Liu H.B. et al Nucl. Technol. 116, 373 (1996) (Brookhaven National Laboratory, Medical Department, Upton, New York 11973) Exposure buildup factors of UO2 using the Monte Carlo method. Bozkurt A. and Tsoulfanidir N. Nucl. Technol. 116, 257 (1996) (University of Missouri - Rolla, 221 Fulton Hall, Rolla, Mo 65401, U.S.A.) Boundary condition perturbations in transport theory. Rahnema F. Nucl. Sci. & Eng. 124 (2) 320 (1996) (Georgia Institute of Technology, Nuclear Engineering and Health Physics Programs, Atlanta, Georgia 30332-0405, U.S.A.) A modified P3-1ike approximation to the transport equation. Su B. and Pomraning G.C. Nucl. Sci. & Eng. 124 (2) 309 (1996) (University of California, Los Angleles, School of Engineering and Applied Science, Los Angeles, California 90095-1597, U.S.A.) Optimization of nonanalog Monte Carlo games using differential operator sampling. *Sarkar P.K. and Rief H. Nucl. Sci. & Eng. 124 (2) 291 (1996) (CEC, Ispra Establishment, 1-21020 Ispra (Va), Italy) The 59Co (n, X, a) reaction from 5 to 50 MeV. Grimes S.M. et al Nucl. Sci. & Eng. 124 (2) 271 (1996) (Ohio University, Athens, Ohio 45701, U.S.A.) Analysis of nuclear power transmission potential at equilibrium. Salvatores M. et al. Nucl. Sci. & Eng. 124 (2) 280 (1996) (CEA, Nuclear Reactor Directorate, Cadarache, France) Effects of the photon cross sections and energy-absorption coefficients of air to the gamma-ray point isotTopic exposure buildup factors. Hirayarna H. Nucl. Sci. & Eng. 124 (2) 258 (1996) (National Laboratory for High Energy Physics, 1 - 10ho, Tsukuba-shi, Ibaraki 305, Japan) Transmission through shields of quasi-monoenergetic neutrons generated by 43- and 68MeV protens - 1: concrete shielding experiment and calculation for practical application. Nakao N. Nucl. Sci. & Eng. 124 (2) 228 (1996) 917
918
Current Papers in Nuclear Energy (Tohoku University, Cyclotron and Radioisotope Centre, Aramaki, Akobo-ku, Sendai 980, Japan Fission cross-section measurements of the odd-odd isotopes 232pa 238Np, and 236Np. Danon Y. et al Nucl. Sci. & Eng. 124 (3) 482 (1996) (Rensselaer Polytechnic Institute, Department of Nuclear Engineering and Engineering Physics, Troy, New York 12180, U.S.A.) Technical Note. Statistical model calculations of the 232U fission cross section. Maslov V.M. and Kikuchi Y. Nucl. Sci. & Eng. 124 (3) 492 (1996) (Japan Atomic Energy Research Institute, Tokai-mura, Nuka-gun, Ibartaki-ken, 319-11, Japan) Systematic evaluation of neutron shielding effects for materials. Ueki K. et al Nucl. Sci. & Eng. 124 (3) 455 (1996) (Ship Research Institute, 6-38-1 Shinkawa, Mitaka, Tokyo 181, Japan) Thermalization of neutrons in graphite: status and error analysis. Difilippo F.C. et al Nucl. Sci. & Eng. 124 (3) 465 (1996) (Oak Ridge National Laboratory, P.O.Box 2008, Building 6025, Oak Ridge, Tenn 37831-6363, U.S.A.) The derivation and proper use of stewart's formula for thermal neutron self-shielding in scattering media. Blaauw M. Nucl. Sci. & Eng. 124 (3) 431 (1996) (Delft University of Technology, Mekelweg 15, 2629 JB Delft, The Netherlands) Wavelet Theory for solution of the neutron diffusion equation. Cho N.Z. and Park C.J. Nucl. Sci. & Eng. 124 (3) 417 (1996) (Department of Nuclear Engineering, 373-1 Kusong-dong, Yusong-gu, Taejon Korea 305-701) Higher order Fokker-Planck operators. Pomraning G.C. Nucl. Sci. & Eng. 124 (3) 390 (1996) (University of California, Los Angeles, School of Engineering and Applied Science, Los Angeles, California 90095-1597, U.S.A.) Forward-adjoint Monte Carlo coupling with no statistical error propagation. Cramer S.N. Nucl. Sci. & Eng. 124 (3) 398 (1996) (Oak Ridge National Laboratory, P.O.Box 2008, Oak Ridge, Tenn 37831-6362, U.S.A.) A hybrid multigroup/continuous-energy Monte Carlo method for solving the BoltzrnannFokker-Planck equation. Morel J.E. et al Nucl. Sci. & Eng. 124 (3) 369 (1996) (Los Alamos National University, Los Alamos, New Mexico, 87545, U.S.A.) Technical Note. A Semiempirical method to calculate continuum gamma-ray spectra and multiplicities from neutron-induced reactions. Fan S. and Zhao Z. Nucl. Sci. & Eng. 124 (2) 349 (1996) (Chinese Nuclear Data Centre, Institute of Atomic Energy, P.O.Box 274 (41), Beijing 102413, China) Design concept of fast spectrum pulse reactor with packed core of coated dilute fuel particles. Obara T. and Sekimoto H. J.Nucl. Sci. & Technol. 33 (7) 547 (1996) (Research Laboratory for Nuclear Reactors, Tokyo Institute of Technoloigy, 0-okayama Meguro-ku, Tokyo 152, Japan)
Current Papers in Nuclear Energy SAFETY Reliability of systems subject to common cause hazards assumed to obey an exponential power model. EI-Damcese, M.A. Nucl. Engng & Des. 167 85 (1996) (Mathematics Department, Tanta University, Tanta, Egypt) Probabilistic fire analysis capabilities, applications and weak points. Fernandez P. Nucl. Engng & Des. 167 77 (1996) (Safety Department, Reliability Section, A I E, Magallanes 3, 28015 Madrid, Spain) Identifying organizational deficiences through root-cause analysis. Tuli R.W. et al Nucl. Technol. 116, 334 (1996) (S A I C, 1309 Continental Drive, Abingdon MD 21009, U.S.A) L W R aerosol containment experiment LA4 simulated by Jericho to Aerosols-B2 codes. Passalacque R. et al Nucl. Technol. 116, 283 (1996) (E N E A, C R E, Cassacia via Auguillarese 301, 00060 Rome, Italy) Modelling of thermophosetic deposition of aerosols in nuclear reactor containments. Fernandes A. and Loyalka S.K. Nucl. Technol. 116, 270 (1996) (University of Missouri-Columbia, Nuclear Engineering Progam, Columbia, MO 65211, U.S.A.) Failure dependent test repair and shutdown strategies: reducing the impact of common cause failures. Uryasev S.P. et al Nucl. Technol. 116, 245 (1996) (Brookhaven National Laboratory, Building 130, Upton, N.Y. 11973-5000, U.S.A.) DYNAMICS AND CONTROL Package flowmodels by neural network representation. Matsuoka H. et al J. Nucl. Sci. & Technol. 33, 675 (1996) (Science & Technology Agency, Chiyoda-ku, Tokyo 100, Japan) Analytic initialization of non equilibrium iodine and xenon distributions for core transient simulation. Song J.S. et al Nucl. Technol. 116, 137 (1996) (K A I S T, Taejon, 305-701, Korea) Neural network-based fault detections in a pressurized water reactor pressurizer. Marseguerra M. et al Nucl. Sci. & Eng. 124 (2) 339 (1996) (Polytechnic of Milan, Department of Nuclear Engineering, via Ponzio 34/3, 20133, Milano, Italy) Quantitive method to measure void fraction of two-phase flow using electronic imaging with neutrons. Mishima K. and Hibiki T. Nucl. Sci. & Eng. 124 (2) 327 (1996) (Kyoto University, Research Reactor Institute, Kumatori-cho, Sennan-gun, Osaka 590-04, Japan) MATERIALS Helium production by 9.85- MeV neutrons in elemental iron, nickel and copper and in 56Fe and 58,60,61Ni. Haight R.C. et al Nucl. Sci. & Eng. 124 (2) 219 (1996) (Los Alamos National Laborator, Los Alarnos, New Mexico, 87545, U.S.A.) Solibility of nickel fcrrite in high-temperature pure or oxygeneratcd water. Hanzawa Y. et al Nucl. Sci. & Eng. 124 (2) 211 (1996) (The University of Tokyo, Department of Quantum Engineering and Systems Science, 73-1 Hongo, Bunkyo-ku, Tokyo 113, Japan)
919
920
Current Papers in Nuclear Energy Kinetics of dissolution of uranium metal foil by Alkaline hydrogen peroxide. Dong D. and Vandegrift G.F. Nucl. Sci. & Eng. 124 (3) 73 (1996) (Argonne National Laboratory, Chemical Technology Division, 9700 South Cass Av. Argonne, IU 60439, U.S.A.) NUCLEARFUEL Development of a coated fuel particle failure model under high burnup irradiation. Sawa K. et al J.Nucl. Sci. & Technol. 33, 712 (1996) (Department of H T T R Project, J A E R I, Ibaraki-ken, 311-13, Japan) Core performance of fast reactors for actinide recycling using metal, nitride and oxide fuels. Yokoo T. et al Nucl. Technol. 116, 173 (1996) (Central Research Institute of Electric Powert, Komae, Tokyo, Japan) Mass spectrometric measurements of fission product effusion from irradiated light water reactor fuel. Capone F. et al Nucl. Sci. & Eng. 124 (3) 436 (1996) (European Commission, Joint Research Centre, European Institute for Transuranium Elements, Karlsruhe, Germany) NUCLEAR WASTE Efficient modelling of reactive transport phenomena by a multispecies random walk coupled to chemical equilibrium. Pfingsten W. Nucl. Technol. 116, 208 (1996) (P S I CH-5232 Villigen-PSI, Switzerland) Treatment of simulated high-level radioactive waste with formic acid. Hsu, C.L. et al Nucl. Technol. 116, 196 (1996)
(Westinghouse Savannah River Co., Aiken, S. Carolina, 29808, U.S.A.) HEAT TRANSFER AND FLUID DYNAMICS An experimental investigation of natural convection heat transfer within horizontal spent fuel assemblies. Caraan, R.E. et al Nucl. Technol. 116, 306 (1996) (University of Texas at Austin, College of Engineering, ECJ 10.388, Austin, Texas 78712, U.S.A.) Development and assessment of US nuclear regulatory commission thermal-hydraulic system computer codes. Shotkin L.M. Nucl. TechnoL 116, 231 (1996) (US NRC, Mailstop T-10 E37, Washington DC 20555, U.S.A) STRUCTURAL MECHANICS Measurement of the yield and tensil strength of neutron-irradiated and post-irradiation recovered vessel steels. Valiente A. et al Nucl. Engng & Des. 167, 11 (1996) (Materials Science Dept. Polytechnic University of Madrid, 28040 Madrid, Spain)