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Current papers in nuclear energy. US$24.00
Ann.nucl.Energy,Vol.9, pp. 283to 286,1982 PergamonPressLtd.Printedin GreatBritain
CURRENT PAPERS IN NUCLEAR ENERGY
REACTOR PHYSICS
Average//-ray energies of short-lived fission products. Aleklett K. Nucl. Sci. Engng 80, 74 (1982). Heterogeneous poisoning of the critical HTGR test facility (The Studsvik Science Research Lab., 5-61182 Nyk6ping, KAHTGR Drfike V. et al. Nucl. Technol. 55, 549 (1981). Sweden). (Institut fur Reaktorentwicklung der KernforNuclear excitation by T rays from 6°Co. Watanabe X. Nucl. schungsanlage, Julich, Federal Republic of Germany). Sci. Engna 80, 92 (1982). A posteriori evaluation of the coarse mesh calculation results (National Defence Academy, Department of Maths & in boiling water reactor dynamics. Havranek M. and Physics, Yokosuka, Japan). Elzmann J. Nucl. Technol. 55, 569 (1981). Unfolding methods with the prior knowledge and integral (Pfaffenwaldring 31, 7000 Stuttgart 80, Federal Republic of data of neutron spectrum. Sekimota H. Nucl. Sci. Engng 80, Germany). 101 (1982). A design study of the neutron irradiation facility for boron (Tokyo Institute of Technical Research, Laboratory for neutron capture therapy. Oka Y. et al. Nucl. Technol. 55, 642 Nuclear Reactors, O-Okayoma Meguro-ku, Tokyo, (1981). Japan). (University of Tokyo, Faculty of Engineering,Tokai-mura, New singular integral equations in experimental neutron Japan). rethermalization. Haidar N. H. S. Nucl. Sei. Engne 80, 113 Measurements and calculations of the fuel temperature (1982). coefficient of reactivity for the Hinckley Point 'B' AGR. (NCSR, Nuclear Research Center, Lebanero University, Richard A. and Telford R. Nucl. Teehnol. 56, 33 (1982). Hadath, Beirut, Lebanon). (CEGB, Berkeley Nuclear Labs, Berkeley Gloueestershire, Geometrical splitting in Monte Carlo. Erperin T. Nucl. Sci. U.K.). Enon0 80, 139 (1982). Gamma spectrometry of TRIGA fuel elements. Bock H. and (Ben Gurion University of the Negev, Department of Hammer J. A T K E 39, 202 (1981). Nuclear Engineering, Beer Sheva, Israel). (Atominstitut der Osterreichischen Universitate, Continuous energy adjoint Monte Carlo theory of coupled Schuttelstr 115, 1020 Vienna, Austria). continuum]discrete radiation transport. Halbleib J. A. Sr. Monte Carlo parametric importance sampling with particle Nucl. Sci. Engng 80, 162 (1982). tracks scaling. Ragheb M. M. H. A T K E 39, 198 (1981). (Sandia National Labs, Albuquerque, NM 87185, U.S.A. (Nuclear Engineering Program, University of Illinois, Lattice parameters of mixed oxides in S m - U ~ ) system. Urbana, Champagne, Illinois, U.S.A.). Tagawa H. J. nucl. Sci. Technol. 18, 811 (1981). The nodal integration method--a diverse solver for neutron (Institute of Environmental Science and Technology, diffusion problems. Fischer H. Dieter and Finnermann H. Yokahama National University, Yokahama, Japan). A T K E 39, 229 (1981). Spark counting of tracks directly introduced by fast neutrons (KUAG, Abt R513, Hammerbacherstrasse 12+ 14, 8520 in cellulose nitrate detector. Sawamura T. J. nucl. Enon0 Erlangen, Federal Republic of Germany). Tectmol. 18, 766 (1981). The effect of a moderator in the central region of a hollow fuel (Department of Nuclear Engineering, Hokkaido element as a function of the neutron spectrum composition. University, Kita 13, Kita-ku, Sappora 060, Japan). Demetrakopoulos N. and Leorudon D. A T K E 39, 237 Zero variance biasingschemes for Monte Carlo calculationsof (1981). neutron and radiation transport problems. Bwivedi S. R. (Nuclear EngineeringLab., National Technical University, Nucl. Sci. Enon0 80, 172 (1982). Patission 42, Athens 147, Greece). (Bhabha Atomic Research Centre, Theoretical Reactor Monte Carlo position dependent angular source biassing. Physics Section, 5th Floor Central Complex, Bombay Ragheb M. M. H. A T K E 39, 241 (1981). 400 085, India). (Nuclear Engineering Program, University of Illinois, Hermite approximation of the neutron transport equation. Urbana, Champagne, Illinois, U.S.A.). Brandt D. Nucl. Sci. Enong 79, 333 (1981). A new Monte Carlo method of T-ray transport calculations. (Swiss Federal Institute of Technology, Department of Jalyam A. A. S. and Razani A. A T K E 39, 249 (1981). Nuclear Engineering, 8092 Zurich, Switzerland). (School of Engineering, Shiraz University, Shiraz, Iran). Practical adjoint Monte Carlo technique for fixed-souree and Benchmark y-ray skyshine experiment. Shultis J. K. Nucl. Sci. eigenfunctinns neutron transport problems. J. E. Enono 79, 404 (1981). Googenboom Nuel. Sci. Enona 79, 357 (1981). (Kansas State University, Manhattan, KS 66506, U.S.A.). (Delft University of Technology, Department of Applied Physics, Delft, Netherlands). Adjoint T-ray estimation to the surface of a cylinder--analysis of a remote reproeessing facility. Cramer S. N. Nucl. Sci. Neutron-introduced fission cross section of 2*°pu in the Engno 79, 417 (1981). energy range from 10 keY to 10 MeV. Budtz C. and (ORNL, P.O. Box X, Oak Ridge, TN 37830, U.S.A.). Jorgensen C. Nucl. Sci. Enong 79, 281 (1981). 283
284
Current Papers in Nuclear Energy
(Commi.~sionof the European CommunitiesJoint Research Centre, Central Bureau for Nuclear Measurements, 2440
G~I, Belgium). Multi-leveleffect in 23sU and 232Th effective neutron capture resonance integrals. Tellier H. Nucl. Sci. Enono 79, 393 (1981). (Centre d'Etudes Nucleaires de Saclay, 91190 Gif-surYvette, France). Neutron resonance parameters of 79Br and s 1Br. Ohkuba M. J. nucl. Sci. Technol. lg, 745 (1981). (JAERI, Tokai-mura, Naka-gun, Ibaraki-ken 319-11, Japan). MATERIALS Effects of texture and surface condition on the iodine stress corrosion cracking of Zircaloy 2. Syrett B. C. et al. Nucl. Technol. 55, 628 (1981). (Stanford Research Institute, Menlo Park, California, U.S.A.). A critical survey on the appfication of plastic fracture mechanics to nuclear pressure vessels and piping. Kanninen M. F. etal. Nucl. Enong Des. 67, 27 (1981). (Battelle Columbus Labs, 505 King Ave, Columbus, Ohio, U.S.A.). In-reactor deformation of zirconium alloy tubes. Ibrahim E. F. J. nucl. Mater. 101, 1 (1981). (AECL, Chalk River Nuclear Labs, Chalk River, Ontario, Canada). The oxidation behaviour ofuraninm in air. Bennette M. J. and Price J. B. J. nucl. Mater. 101, 44 (1981). (AERE, Materials Development Division, Harwell, Oxon, U.K.). The contribution of the intrinsic anisotropy of point defect diffusion rates to irradiation growth of zirconium. Ball C. J. J. nucl. Mater. 101, 147 (1981). (AAEC Research Establishment, Lucas Heights, Private Mail Bag, Sutherland, N.S.W. 2232, Australia). Lattice parameter change in irradiated (Th,U)O2. Akabori M. and Shiba K. J. nucl. Mater. 101, 184 (1981). (JAERI, Thorium Fuel Laboratories, Tokai-mura, Nakagun, Ibaraki-ken 319-11, Japan). A model for bubble diffusion in uranium dioxide. Nixon W. and Macinnes D. A. J. nuci. Mater. 101, 192 (1981). (UKAEA, SRD, Wigshaw Lane, Culcheth, Warrington, Cheshire, U.K.). Leaching of radionuclides from a cement composite incorporating evaporator concentrates generated at a pressurized water reactor nuclear power plant. Matsuzuru H. NucL Sci. Enong 80, 14 (1982). (JAERI, Tokai-mura, Naka-gun, lbaraki-ken 319-11, Japan). Ductility loss of Zireaioy cladding by inner-surface oxidation during high temperature transient. Furuta T. J. nucl. Sci. Technoi. lg, 802 (1981). (JAERI, Division of Reactor Safety, Tokal-mura, Nakagun, lbaraki-ken 319-11, Japan). Effect of iodine on fatigue properties of Zircaloy-2 fuel cladding under cyclic tensile stress. Nakatsuka M. J. nucl. Sci. Technol. 18, 785 (1981). (Nippon Nuclear Fuel Dept Co. Ltd, Oarai-Machi, NaritaMachi, lbaraki-ken 311-13, Japan).
FUEL CYCLES Fuel cycle extension by part-length control rod removal at Rancho Seco. Ake T. N. et al. Nucl. Technoi..~ 583 (1981). (Babcock & Wilcox Co., Nuclear Power Generating Division, P.O. Box 1260, Lynchburg, Virginia, U.S.A.). The role of 23Spu in nuclear fuel cycles. Massey J. V. and Schneider A. Nuci. Technol. 56, 55 (1982). (Georgia Institute of Technology, School of Nuclear Engineering, Atlanta, GA 30332, U.S.A.). Optimization of fuel cycle strategies with constraints on uranium availability Sflvennoinen P. et al. Nuci. Technoi. 56, 72 (1982). (Technical Research Centre of Finland, P.O. Box 169, SF00181 Helsinki 18, Finland). Fuel cycle cost considerations of increased discharge burnups. Scherperecl L. R. and Frank F. J. Nuci. Technol. 56,106 (1982). (Westinghouse Nuclear Commercial Operation, Fuel and Field Services Evaluations, P.O. Box 355, Pittsburgh, Pennsylvania, U.S.A.). Some energetics considerations of fission product transmutation with protons. Oyedele J. A. and Harms A. A. A T K E 39, 175 (1981). (Department of Engineering Physics, McMaster University, Hamilton, Ontario, Canada L85 4M1). Application of neutron count moment analysis method to passive assay. Shenhav N. Nuci. Sci. En0no gO, 61 (1982). (Technion Israel Institute of Technology, Department of Nuclear Engineering, Haifa, Israel). Optimization of radioactive waste management system by application of multiobjective nuclear programming. Shimizo X. J. nucl. Sci. Technol. 18, 773 (1981). (Research Reactor Institute, Kyoto University, Kamatoricho, Sennan gun, Osaka 590-04, Japan).
SAFETY Spectral effects in the extrapolation of pressure vessel surveillance capsule measurements. Carew J. F. etal. Nucl. Technol. 55, 565 (1981). (BNL, Upton, Long Island, NY 11973, U.S.A.). Analysisof manual depressurization of a boiling water reactor under transient conditions. Bamlad F. Nucl. Technoi. 55, 579 (1981). (Boston Edison Co., Boston, Massachusetts, U.S.A.). Fuel motion in experiments simulating liquid-metal fast breeder reactor loss of coolant accident. Simms R. et al. Nucl. Technoi. 55, 595 (1981). (ANL, 9700 South Cass Ave., Argonne, IL 60439, U.S.A.). The critical safety functions and plant operation. Corcoran W. R. etal. Nucl. Technol. ~ 690(1981). (Combustion Engineering Inc., 1000 Prospect Hill Rd, Windsor, Connecticut, U.S.A.). Instrument fault detection in a pressurized water reactor pressurizer. Clark R. N. etal. Nucl. Technol. 56, 23 (1982). (University of Washington, Electrical Engineering Dept, Seattle, Washington, U.S.A.). Analyzing the rod drop accident in a BWR. Chang H. and Diamond D. J. Nuci. Technol. 56, 40 (1982). (BNL, Upton, Long Island, NY 11973, U.S.A.).
Current Papers in Nuclear Energy The influence of speciation on the geospheric migration of radionudideL Hodermaun J. NucL Tedmol. $~, 102 (1982). (Swiss Federal Institute for Reactor Research, 5303 W~reniingen,Switzerland). An asessment o f d a u 9 accidents for PWR dry-containment systeme. Theofanons T. G. and Saito M. Nuci. Engn0 Des. 66, 301 (1981). (School of Nuclear Engineering. Purdue University, W. Layfayette, Indiana, U.S.A.). An assessment of the application of active control to reduce the seismic response of nuclear power plants. Wolf J. P. and Madden P. A. Nucl. E ~ Des. 66, 383 (1981). (EIectrowatt Engineering Services Lid, 8022 Zurich, Switzerland). Analytical investigation of a one-dimensional model for a PWR core. BennerJ. and SchumannU. Nucl. E n g ~ Des. 66, 413 (1981). (KFK, Institut fur Reactorentwicklung, Postfach 3640, 7500 Karlsruhe, Federal Republic of Germany). Prediction of decay heat removal capabilities for LMFBRs and comparison with experiment. Agrawal A. K. et al. Nucl. Enono Des. 66, 437 (1981). (BNL, Upton, Long Island, NY 11973, U.S.A.). Physics of the reactor meltdown accident. Cohen B. L. Nucl. Sd. Engn0 80, 47 (1982). (University of Pittsburgh, Department of Physics and Astronomy, Pittsburgh, PA 15260, U.S.A.). On a leak detection method for OWL- 1 loop by arc modeling using dewpoint signals. Ogoma R. J. nucl. Sci. Technol. 18, 757 (1981). (JAERI, Division of Reactor Engineering,Tokal Research Establishment, Tokai-mura, Naka-gun, Ibaraki-ken 31911, Japan). HEAT TRANSFER AND FLUID DYNAMICS Thermal response of a flat plate of finite thickness immersed in a fluid with oscillatingtemperature. Poindexter A. M. Nucl. Technol. ~ 656 (1981). (Westinghouse Electric Corp., Advanced Reactors Division, P.O. Box 158, Madison, Pennsylvania, U.S.A.). OptimiTation of a variable flow allocation scheme in heterogeneous liquid-metalfast breeder reactors. Tzanos C. P. Nucl. Technol. 55, 662 (1981). (Science Application Inc., 1211 W 22rid Street, Oak Brook, Illinois, U.S.A.). Influence of partial blockage of a BWR bundle on heat transfer. Brand B. et ai. Nucl. Technol. 56, 128 (1982). (KUAG, Abt R513, Hammerbacherstrasse 12+14, 8520 Erlangen, Federal Republic of Germany). Downflow post-critical heat flux heat transfer to low pressure water. Robershotte P. and Gritiith P. Nucl. Technol..56,134 (1982). (Department of Mechanical Engineering, MIT, 77 Massachusetts. Ave., Cambridge, Massachusetts, U.S.A.). Some boiling experiments in a 19-pin bundle under loss-offlow conditions. Kikuchi Y. and Haga K. Nucl. Engng Des. 66, 557 (1981). (Oaral Engineering Centre, Power Reactor and Nuclear Fuel Development Corp., Oaral, Japan). Void fraction distribution in low flow rate sub-cooled boiling. Edelman Z. and Elias E. Nuci. Enono Des. 66, 395 (1981).
285
(Technion Israel Institute of Technology, Department of Nuclear Engineering Haifa, Israel). Temperature distribution in cladded configurations of complicated boundary shape. Laura P. A. A. et al. Nucl. EnOr~ Des. 67, 75 (198). (Institute of Applied Mechanics, 8111 Puerto Beigrano Naval Base, Argentina). Heat transfer analysis in internally-cooled fuel elements by means of a conformal mapping approach. SanchezSarmuento G. et al. Nucl. Enono Des. 67, 101 (1981). (Centro Atomico Bariloche, 8400 Bariloche, Argentina). Effect of debris bed pressure/particle size and distribution on degraded nuclear reactor core coolability. Squarer D. Nucl. Sci. Engng 80, 2 (1982). (Westinghouse Electric Corp., Research & Development Center, Pittsburgh, PA 15235, U.S.A.). On fundamentalcontinuityequation for material transport in fractured media and retention factor for a system of joints. Mubhopadhyay N. C. Nucl. Sci. EngnO 80, 26 (1982). (Federal Institute for Reactor Research, 5303 Wfirenlingen, Switzerland). Coordinate transformation method for thermohydraulics in irregular three-dimensional geometries. Peckover R. S. Nucl. Sci. EnonO 88, 32 (1982). (UKAEA, Culham Lab., Abingdon, Oxon OX14 3DB, U.K.). NUCLEAR FUEL Economic impact of nuclear core limitations. Franklin D. G. Nucl. Technol. 5~, 607 (1981). (EPRI, 3412 Hillview Ave., P.O. Box 10412, Palo Alto, California, U.S.A.). Uranium isotope separation by cation exchange chromatography using uranous sulfal complexes. Sakuma Y. J. nuel. Sci. Technoi. 18, 793 (1981). (Research Lab. for Nuclear Reactors, Tokyo Institute of Technology, Ookayama, Meguroku, Tokyo 152, Japan).
FUSION Kinetic studies of the tritium release process in neutronirradiated Li20 and LiOH. Kudo H. and Okuno K. J. nucl. Mater. 101, 38 (1981). (JAERI, Tokal-Mura, Naka-gun, Ibaraki-ken, Japan). Model for particle transport in high density plasmas. Coppi B. and Sharky N. Nucl. Fusion 21, 1262 (1981). (MIT, Cambridge, Massachusetts, U.S.A.). Tokamak MHD stability. Kerner W. et al. Nucl. Fusion 21, 1383 (1981). (Max-Planck Institut fur Plasma Physik, EURATOM, Garching, Federal Republic of Germany). Fast-ion thermalizationinnon-circularTokamaks with largebanana width effects. Hively L. M. et al. Nucl. Fusion 21, 1421 (1981). (Fusion Studies Lab., Nuclear Engineering Program, University of Illinois, Champagne, Illinois, U.S.A.). Ignition critical profiles for small fusion targets. Kirkpatrick R. C. Nuci. Fusion 21, 1457 (1981). (Univendty of California, Los Alamos National Lab., Los Alamos, NM 87545, U.S.A.).
286
Current Papers in Nuclear Energy
Electrical characteristics of an ideal Tokamak limiter. Motley R. W. NucL Fusion 21, 1541 (1981). (Plasma Physics Lab., Princeton University, Princeton, New Jersey, U.S.A.). Injection of intense pulsed-ion beam into Tokamaks. Manheimer W. M. and Winsor N. K. Nucl. Fusion 21,1559 (1981). (Naval Research Lab., Washington, DC, U.S.A.). Thermonuclear detonation waves (I). Winterberg F. A T K E 39, 181 (1981). (Desert Research Institute, University of Nevada Systems, Reno, Nevada, U.S.A.). Kinetics and energetics of moon-catalyzed deuterium-tritium fusion. Lie S. G. Nucl. Sci. Engng 80, 124 (1982). (McMaster University, Hamilton, Ontario, Canada L8S 4M1).
Multigroup tra~fer matrices for charged particle and neutron-introduced reaction Part I: the general two-body interation. Perkins S. T. NucL Sci. Enong 80, 130 (1982). (University of California, Lawrence Livermore National Lab., P.O. Box 808, Livermore, CA 94550, U.S.A.). Fokker-Planck calculations using standard discrete ordinates transport codes. Morel J. E. Nucl. Sci. Engng 79, 340 (1981). (Sandia National Labs, Theoretical Division 4231, Albuquerque, NM 87185, U.S.A.). Forced and free convective magn©ton-hydrodynamic flow between vertical conducting walls. Singh M. NucL Sci. Engng 79, 374 (1981). (Simon Fraser University, Department of Maths, Burnaby, British Columbia, Canada).
CURRENT PAPERS IN NUCLEAR ENERGY
REACTOR PHYSICS
Average//-ray energies of short-lived fission products. Aleklett K. Nucl. Sci. Engng 80, 74 (1982). Heterogeneous poisoning of the critical HTGR test facility (The Studsvik Science Research Lab., 5-61182 Nyk6ping, KAHTGR Drfike V. et al. Nucl. Technol. 55, 549 (1981). Sweden). (Institut fur Reaktorentwicklung der KernforNuclear excitation by T rays from 6°Co. Watanabe X. Nucl. schungsanlage, Julich, Federal Republic of Germany). Sci. Engna 80, 92 (1982). A posteriori evaluation of the coarse mesh calculation results (National Defence Academy, Department of Maths & in boiling water reactor dynamics. Havranek M. and Physics, Yokosuka, Japan). Elzmann J. Nucl. Technol. 55, 569 (1981). Unfolding methods with the prior knowledge and integral (Pfaffenwaldring 31, 7000 Stuttgart 80, Federal Republic of data of neutron spectrum. Sekimota H. Nucl. Sci. Engng 80, Germany). 101 (1982). A design study of the neutron irradiation facility for boron (Tokyo Institute of Technical Research, Laboratory for neutron capture therapy. Oka Y. et al. Nucl. Technol. 55, 642 Nuclear Reactors, O-Okayoma Meguro-ku, Tokyo, (1981). Japan). (University of Tokyo, Faculty of Engineering,Tokai-mura, New singular integral equations in experimental neutron Japan). rethermalization. Haidar N. H. S. Nucl. Sei. Engne 80, 113 Measurements and calculations of the fuel temperature (1982). coefficient of reactivity for the Hinckley Point 'B' AGR. (NCSR, Nuclear Research Center, Lebanero University, Richard A. and Telford R. Nucl. Teehnol. 56, 33 (1982). Hadath, Beirut, Lebanon). (CEGB, Berkeley Nuclear Labs, Berkeley Gloueestershire, Geometrical splitting in Monte Carlo. Erperin T. Nucl. Sci. U.K.). Enon0 80, 139 (1982). Gamma spectrometry of TRIGA fuel elements. Bock H. and (Ben Gurion University of the Negev, Department of Hammer J. A T K E 39, 202 (1981). Nuclear Engineering, Beer Sheva, Israel). (Atominstitut der Osterreichischen Universitate, Continuous energy adjoint Monte Carlo theory of coupled Schuttelstr 115, 1020 Vienna, Austria). continuum]discrete radiation transport. Halbleib J. A. Sr. Monte Carlo parametric importance sampling with particle Nucl. Sci. Engng 80, 162 (1982). tracks scaling. Ragheb M. M. H. A T K E 39, 198 (1981). (Sandia National Labs, Albuquerque, NM 87185, U.S.A. (Nuclear Engineering Program, University of Illinois, Lattice parameters of mixed oxides in S m - U ~ ) system. Urbana, Champagne, Illinois, U.S.A.). Tagawa H. J. nucl. Sci. Technol. 18, 811 (1981). The nodal integration method--a diverse solver for neutron (Institute of Environmental Science and Technology, diffusion problems. Fischer H. Dieter and Finnermann H. Yokahama National University, Yokahama, Japan). A T K E 39, 229 (1981). Spark counting of tracks directly introduced by fast neutrons (KUAG, Abt R513, Hammerbacherstrasse 12+ 14, 8520 in cellulose nitrate detector. Sawamura T. J. nucl. Enon0 Erlangen, Federal Republic of Germany). Tectmol. 18, 766 (1981). The effect of a moderator in the central region of a hollow fuel (Department of Nuclear Engineering, Hokkaido element as a function of the neutron spectrum composition. University, Kita 13, Kita-ku, Sappora 060, Japan). Demetrakopoulos N. and Leorudon D. A T K E 39, 237 Zero variance biasingschemes for Monte Carlo calculationsof (1981). neutron and radiation transport problems. Bwivedi S. R. (Nuclear EngineeringLab., National Technical University, Nucl. Sci. Enon0 80, 172 (1982). Patission 42, Athens 147, Greece). (Bhabha Atomic Research Centre, Theoretical Reactor Monte Carlo position dependent angular source biassing. Physics Section, 5th Floor Central Complex, Bombay Ragheb M. M. H. A T K E 39, 241 (1981). 400 085, India). (Nuclear Engineering Program, University of Illinois, Hermite approximation of the neutron transport equation. Urbana, Champagne, Illinois, U.S.A.). Brandt D. Nucl. Sci. Enong 79, 333 (1981). A new Monte Carlo method of T-ray transport calculations. (Swiss Federal Institute of Technology, Department of Jalyam A. A. S. and Razani A. A T K E 39, 249 (1981). Nuclear Engineering, 8092 Zurich, Switzerland). (School of Engineering, Shiraz University, Shiraz, Iran). Practical adjoint Monte Carlo technique for fixed-souree and Benchmark y-ray skyshine experiment. Shultis J. K. Nucl. Sci. eigenfunctinns neutron transport problems. J. E. Enono 79, 404 (1981). Googenboom Nuel. Sci. Enona 79, 357 (1981). (Kansas State University, Manhattan, KS 66506, U.S.A.). (Delft University of Technology, Department of Applied Physics, Delft, Netherlands). Adjoint T-ray estimation to the surface of a cylinder--analysis of a remote reproeessing facility. Cramer S. N. Nucl. Sci. Neutron-introduced fission cross section of 2*°pu in the Engno 79, 417 (1981). energy range from 10 keY to 10 MeV. Budtz C. and (ORNL, P.O. Box X, Oak Ridge, TN 37830, U.S.A.). Jorgensen C. Nucl. Sci. Enong 79, 281 (1981). 283
284
Current Papers in Nuclear Energy
(Commi.~sionof the European CommunitiesJoint Research Centre, Central Bureau for Nuclear Measurements, 2440
G~I, Belgium). Multi-leveleffect in 23sU and 232Th effective neutron capture resonance integrals. Tellier H. Nucl. Sci. Enono 79, 393 (1981). (Centre d'Etudes Nucleaires de Saclay, 91190 Gif-surYvette, France). Neutron resonance parameters of 79Br and s 1Br. Ohkuba M. J. nucl. Sci. Technol. lg, 745 (1981). (JAERI, Tokai-mura, Naka-gun, Ibaraki-ken 319-11, Japan). MATERIALS Effects of texture and surface condition on the iodine stress corrosion cracking of Zircaloy 2. Syrett B. C. et al. Nucl. Technol. 55, 628 (1981). (Stanford Research Institute, Menlo Park, California, U.S.A.). A critical survey on the appfication of plastic fracture mechanics to nuclear pressure vessels and piping. Kanninen M. F. etal. Nucl. Enong Des. 67, 27 (1981). (Battelle Columbus Labs, 505 King Ave, Columbus, Ohio, U.S.A.). In-reactor deformation of zirconium alloy tubes. Ibrahim E. F. J. nucl. Mater. 101, 1 (1981). (AECL, Chalk River Nuclear Labs, Chalk River, Ontario, Canada). The oxidation behaviour ofuraninm in air. Bennette M. J. and Price J. B. J. nucl. Mater. 101, 44 (1981). (AERE, Materials Development Division, Harwell, Oxon, U.K.). The contribution of the intrinsic anisotropy of point defect diffusion rates to irradiation growth of zirconium. Ball C. J. J. nucl. Mater. 101, 147 (1981). (AAEC Research Establishment, Lucas Heights, Private Mail Bag, Sutherland, N.S.W. 2232, Australia). Lattice parameter change in irradiated (Th,U)O2. Akabori M. and Shiba K. J. nucl. Mater. 101, 184 (1981). (JAERI, Thorium Fuel Laboratories, Tokai-mura, Nakagun, Ibaraki-ken 319-11, Japan). A model for bubble diffusion in uranium dioxide. Nixon W. and Macinnes D. A. J. nuci. Mater. 101, 192 (1981). (UKAEA, SRD, Wigshaw Lane, Culcheth, Warrington, Cheshire, U.K.). Leaching of radionuclides from a cement composite incorporating evaporator concentrates generated at a pressurized water reactor nuclear power plant. Matsuzuru H. NucL Sci. Enong 80, 14 (1982). (JAERI, Tokai-mura, Naka-gun, lbaraki-ken 319-11, Japan). Ductility loss of Zireaioy cladding by inner-surface oxidation during high temperature transient. Furuta T. J. nucl. Sci. Technoi. lg, 802 (1981). (JAERI, Division of Reactor Safety, Tokal-mura, Nakagun, lbaraki-ken 319-11, Japan). Effect of iodine on fatigue properties of Zircaloy-2 fuel cladding under cyclic tensile stress. Nakatsuka M. J. nucl. Sci. Technol. 18, 785 (1981). (Nippon Nuclear Fuel Dept Co. Ltd, Oarai-Machi, NaritaMachi, lbaraki-ken 311-13, Japan).
FUEL CYCLES Fuel cycle extension by part-length control rod removal at Rancho Seco. Ake T. N. et al. Nucl. Technoi..~ 583 (1981). (Babcock & Wilcox Co., Nuclear Power Generating Division, P.O. Box 1260, Lynchburg, Virginia, U.S.A.). The role of 23Spu in nuclear fuel cycles. Massey J. V. and Schneider A. Nuci. Technol. 56, 55 (1982). (Georgia Institute of Technology, School of Nuclear Engineering, Atlanta, GA 30332, U.S.A.). Optimization of fuel cycle strategies with constraints on uranium availability Sflvennoinen P. et al. Nuci. Technoi. 56, 72 (1982). (Technical Research Centre of Finland, P.O. Box 169, SF00181 Helsinki 18, Finland). Fuel cycle cost considerations of increased discharge burnups. Scherperecl L. R. and Frank F. J. Nuci. Technol. 56,106 (1982). (Westinghouse Nuclear Commercial Operation, Fuel and Field Services Evaluations, P.O. Box 355, Pittsburgh, Pennsylvania, U.S.A.). Some energetics considerations of fission product transmutation with protons. Oyedele J. A. and Harms A. A. A T K E 39, 175 (1981). (Department of Engineering Physics, McMaster University, Hamilton, Ontario, Canada L85 4M1). Application of neutron count moment analysis method to passive assay. Shenhav N. Nuci. Sci. En0no gO, 61 (1982). (Technion Israel Institute of Technology, Department of Nuclear Engineering, Haifa, Israel). Optimization of radioactive waste management system by application of multiobjective nuclear programming. Shimizo X. J. nucl. Sci. Technol. 18, 773 (1981). (Research Reactor Institute, Kyoto University, Kamatoricho, Sennan gun, Osaka 590-04, Japan).
SAFETY Spectral effects in the extrapolation of pressure vessel surveillance capsule measurements. Carew J. F. etal. Nucl. Technol. 55, 565 (1981). (BNL, Upton, Long Island, NY 11973, U.S.A.). Analysisof manual depressurization of a boiling water reactor under transient conditions. Bamlad F. Nucl. Technoi. 55, 579 (1981). (Boston Edison Co., Boston, Massachusetts, U.S.A.). Fuel motion in experiments simulating liquid-metal fast breeder reactor loss of coolant accident. Simms R. et al. Nucl. Technoi. 55, 595 (1981). (ANL, 9700 South Cass Ave., Argonne, IL 60439, U.S.A.). The critical safety functions and plant operation. Corcoran W. R. etal. Nucl. Technol. ~ 690(1981). (Combustion Engineering Inc., 1000 Prospect Hill Rd, Windsor, Connecticut, U.S.A.). Instrument fault detection in a pressurized water reactor pressurizer. Clark R. N. etal. Nucl. Technol. 56, 23 (1982). (University of Washington, Electrical Engineering Dept, Seattle, Washington, U.S.A.). Analyzing the rod drop accident in a BWR. Chang H. and Diamond D. J. Nuci. Technol. 56, 40 (1982). (BNL, Upton, Long Island, NY 11973, U.S.A.).
Current Papers in Nuclear Energy The influence of speciation on the geospheric migration of radionudideL Hodermaun J. NucL Tedmol. $~, 102 (1982). (Swiss Federal Institute for Reactor Research, 5303 W~reniingen,Switzerland). An asessment o f d a u 9 accidents for PWR dry-containment systeme. Theofanons T. G. and Saito M. Nuci. Engn0 Des. 66, 301 (1981). (School of Nuclear Engineering. Purdue University, W. Layfayette, Indiana, U.S.A.). An assessment of the application of active control to reduce the seismic response of nuclear power plants. Wolf J. P. and Madden P. A. Nucl. E ~ Des. 66, 383 (1981). (EIectrowatt Engineering Services Lid, 8022 Zurich, Switzerland). Analytical investigation of a one-dimensional model for a PWR core. BennerJ. and SchumannU. Nucl. E n g ~ Des. 66, 413 (1981). (KFK, Institut fur Reactorentwicklung, Postfach 3640, 7500 Karlsruhe, Federal Republic of Germany). Prediction of decay heat removal capabilities for LMFBRs and comparison with experiment. Agrawal A. K. et al. Nucl. Enono Des. 66, 437 (1981). (BNL, Upton, Long Island, NY 11973, U.S.A.). Physics of the reactor meltdown accident. Cohen B. L. Nucl. Sd. Engn0 80, 47 (1982). (University of Pittsburgh, Department of Physics and Astronomy, Pittsburgh, PA 15260, U.S.A.). On a leak detection method for OWL- 1 loop by arc modeling using dewpoint signals. Ogoma R. J. nucl. Sci. Technol. 18, 757 (1981). (JAERI, Division of Reactor Engineering,Tokal Research Establishment, Tokai-mura, Naka-gun, Ibaraki-ken 31911, Japan). HEAT TRANSFER AND FLUID DYNAMICS Thermal response of a flat plate of finite thickness immersed in a fluid with oscillatingtemperature. Poindexter A. M. Nucl. Technol. ~ 656 (1981). (Westinghouse Electric Corp., Advanced Reactors Division, P.O. Box 158, Madison, Pennsylvania, U.S.A.). OptimiTation of a variable flow allocation scheme in heterogeneous liquid-metalfast breeder reactors. Tzanos C. P. Nucl. Technol. 55, 662 (1981). (Science Application Inc., 1211 W 22rid Street, Oak Brook, Illinois, U.S.A.). Influence of partial blockage of a BWR bundle on heat transfer. Brand B. et ai. Nucl. Technol. 56, 128 (1982). (KUAG, Abt R513, Hammerbacherstrasse 12+14, 8520 Erlangen, Federal Republic of Germany). Downflow post-critical heat flux heat transfer to low pressure water. Robershotte P. and Gritiith P. Nucl. Technol..56,134 (1982). (Department of Mechanical Engineering, MIT, 77 Massachusetts. Ave., Cambridge, Massachusetts, U.S.A.). Some boiling experiments in a 19-pin bundle under loss-offlow conditions. Kikuchi Y. and Haga K. Nucl. Engng Des. 66, 557 (1981). (Oaral Engineering Centre, Power Reactor and Nuclear Fuel Development Corp., Oaral, Japan). Void fraction distribution in low flow rate sub-cooled boiling. Edelman Z. and Elias E. Nuci. Enono Des. 66, 395 (1981).
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(Technion Israel Institute of Technology, Department of Nuclear Engineering Haifa, Israel). Temperature distribution in cladded configurations of complicated boundary shape. Laura P. A. A. et al. Nucl. EnOr~ Des. 67, 75 (198). (Institute of Applied Mechanics, 8111 Puerto Beigrano Naval Base, Argentina). Heat transfer analysis in internally-cooled fuel elements by means of a conformal mapping approach. SanchezSarmuento G. et al. Nucl. Enono Des. 67, 101 (1981). (Centro Atomico Bariloche, 8400 Bariloche, Argentina). Effect of debris bed pressure/particle size and distribution on degraded nuclear reactor core coolability. Squarer D. Nucl. Sci. Engng 80, 2 (1982). (Westinghouse Electric Corp., Research & Development Center, Pittsburgh, PA 15235, U.S.A.). On fundamentalcontinuityequation for material transport in fractured media and retention factor for a system of joints. Mubhopadhyay N. C. Nucl. Sci. EngnO 80, 26 (1982). (Federal Institute for Reactor Research, 5303 Wfirenlingen, Switzerland). Coordinate transformation method for thermohydraulics in irregular three-dimensional geometries. Peckover R. S. Nucl. Sci. EnonO 88, 32 (1982). (UKAEA, Culham Lab., Abingdon, Oxon OX14 3DB, U.K.). NUCLEAR FUEL Economic impact of nuclear core limitations. Franklin D. G. Nucl. Technol. 5~, 607 (1981). (EPRI, 3412 Hillview Ave., P.O. Box 10412, Palo Alto, California, U.S.A.). Uranium isotope separation by cation exchange chromatography using uranous sulfal complexes. Sakuma Y. J. nuel. Sci. Technoi. 18, 793 (1981). (Research Lab. for Nuclear Reactors, Tokyo Institute of Technology, Ookayama, Meguroku, Tokyo 152, Japan).
FUSION Kinetic studies of the tritium release process in neutronirradiated Li20 and LiOH. Kudo H. and Okuno K. J. nucl. Mater. 101, 38 (1981). (JAERI, Tokal-Mura, Naka-gun, Ibaraki-ken, Japan). Model for particle transport in high density plasmas. Coppi B. and Sharky N. Nucl. Fusion 21, 1262 (1981). (MIT, Cambridge, Massachusetts, U.S.A.). Tokamak MHD stability. Kerner W. et al. Nucl. Fusion 21, 1383 (1981). (Max-Planck Institut fur Plasma Physik, EURATOM, Garching, Federal Republic of Germany). Fast-ion thermalizationinnon-circularTokamaks with largebanana width effects. Hively L. M. et al. Nucl. Fusion 21, 1421 (1981). (Fusion Studies Lab., Nuclear Engineering Program, University of Illinois, Champagne, Illinois, U.S.A.). Ignition critical profiles for small fusion targets. Kirkpatrick R. C. Nuci. Fusion 21, 1457 (1981). (Univendty of California, Los Alamos National Lab., Los Alamos, NM 87545, U.S.A.).
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Current Papers in Nuclear Energy
Electrical characteristics of an ideal Tokamak limiter. Motley R. W. NucL Fusion 21, 1541 (1981). (Plasma Physics Lab., Princeton University, Princeton, New Jersey, U.S.A.). Injection of intense pulsed-ion beam into Tokamaks. Manheimer W. M. and Winsor N. K. Nucl. Fusion 21,1559 (1981). (Naval Research Lab., Washington, DC, U.S.A.). Thermonuclear detonation waves (I). Winterberg F. A T K E 39, 181 (1981). (Desert Research Institute, University of Nevada Systems, Reno, Nevada, U.S.A.). Kinetics and energetics of moon-catalyzed deuterium-tritium fusion. Lie S. G. Nucl. Sci. Engng 80, 124 (1982). (McMaster University, Hamilton, Ontario, Canada L8S 4M1).
Multigroup tra~fer matrices for charged particle and neutron-introduced reaction Part I: the general two-body interation. Perkins S. T. NucL Sci. Enong 80, 130 (1982). (University of California, Lawrence Livermore National Lab., P.O. Box 808, Livermore, CA 94550, U.S.A.). Fokker-Planck calculations using standard discrete ordinates transport codes. Morel J. E. Nucl. Sci. Engng 79, 340 (1981). (Sandia National Labs, Theoretical Division 4231, Albuquerque, NM 87185, U.S.A.). Forced and free convective magn©ton-hydrodynamic flow between vertical conducting walls. Singh M. NucL Sci. Engng 79, 374 (1981). (Simon Fraser University, Department of Maths, Burnaby, British Columbia, Canada).