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Current papers in nuclear energy
C U R R E N T PAPERS IN N U C L E A R E N E R G Y
REACTOR PHYSICS
Comparison of various types of SSNTD for neutron dosimetry. Sayed A. M. A T K E 39, 27 (1981). (Physics Dept, College of Science, Basrah University, Basrah, Iraq). Sedimentological measurements in the river Ghezel uzan using the radioactive sources 137Cs and 133Ba. Panahandeh I. H. A T K E 39, 20 (1981). (University of Nuclear Science and Technology, Tehran University, Tehran, Iran). Analysis of 14 MeV (n, p) cross section with pre-equilibrium model and effective Q-values. Kumabe I. J. nucl. Sci. Technol. 18, 563 (1981). (Department of Nuclear Engineering, Faculty of Engineering, Kyushu University, Hakozaki, Higashi-ku, Fukuoka-shi 812, Japan). A new mixed method with finite difference and finite element method for neutron diffusion calculation. Naito Y. J. nucl. Sci. Technol. 18, 571 (1981). (JAERI, Tokai-mura, Naka-gun, Ibaraki-ken 319-11, Japan). Analysis of neutron and secondary ~-ray transport in air-overground geometry by PALLAS-2DCX-FC code. Takeuchi K. J. nucl. Sci. Technol. 18, 581 (1981). (Tokai Branch, Ship Research Institute, Tokai-mura, Ibaraki-ken, Japan). The effects on reactivity coefficient of spectral shifts introduced by Doppler broadening. Alapour N. Nucl. Sci. Engn9 79, 278 (1981). (Georgia Institute of Technology, School of Nuclear Engineering, Atlanta, GA 30332, U.S.A.). Gold neutron capture cross section from 100 to 2000 keV. Mackun R. L. Nucl. Sci. Enon9 79, 265 (1981). (ORNL, P.O. Box X, Building 6010, Oak Ridge, TN 37830, U.S.A.). Three-dimensional neutron streaming calculations using the Monte Carlo coupling technique. Ueki K. Nucl. Sci. En#n# 79, 253 (1981). (Nuclear Ship Division, Ship Research Institute, 6-38-1 Shinkawa, Mitaka, Tokyo 181, Japan). Cross section for the 25Mg (~,n) 12sSi reaction for Ea < 4.8 MeV. Van der Zwan L. Nucl. Sci. Engng 79, 197 (1981). (National Research Council of Canada, Division of Physics, Ottawa, Ontario K 1A OS 1, Canada). Neutron capture cross section of 237Np. Eston L. W. Nucl. Sci. Enong 79, 184 (1981). (ORNL, P.O. Box X, Building 6010, Oak Ridge, TN 37830,
U.S.A.). Neutron capture and total cross section of E32Thfrom 0.006 to 18 eV. Little R. C. Nucl. Sci. Engno 79, 175 (1981). (Rensselaer Polytechnic Institute, Gaerttner Linoc Lab., Troy, NY 12181, U.S.A.). Mass distribution in the reactor-neutron induced fission of 232Th. Erten H. N. Nucl. Sci. En.qn.q 79, 167 (1981). 227
(Eidgenoessiches Institut fur Reaktorforschung, 5305 Wiirenlingen, Switzerland). Neutron production by medium-energy ( ~ 1.5 GeV) protons in thick uranium targets. Alsmiller R. G. Nucl. Sci. Enono 79, 162(1981). (ORNL, P.O. Box X, Oak Ridge, TN 37830, U.S.A.). Phenomenological model for particle production from the collisions of nucleons and pions with fissile elements at medium energies. Alsmiller R. S. Nucl. Sci. Enon O 79, 147 (1981). (ORNL, P.O. Box X, Building 6025, Oak Ridge, TN 37830, U.S.A.). A Monte Carlo calculation of the neutron and gamma sensitivities of self-powered detectors. Pytel K. A T K E 39, 31 (1981). (Reactor Operation Dept, Institute of Nuclear Research, 05-400 Swierk, Otwock, Poland). Neutron analysis of fast hybrid thermionic reactors. Sahin S. A T K E 39, 41 (1981). (Swiss Federal Institute of Technology, 1700 Lausanne, Switzerland). CONTROL AND DYNAMICS
New method of startup planning for boiling water reactors. Bessho Y. J. nucl. Sci. Technol. 18, 697 (1981). (Energy Research Lab., Hitachi Ltd, Moriyama-Cho, Hitachi-shi, Ibaraki-ken 317, Japan). Sink frequency analogy for cross-spectral density and neutron wave propagation in multi-region multiplying systems. Nagy M. E. et al. A T K E 39, 45 (1981). (Nuclear Engineering Dept, University of Alexandria, Alexandria, Egypt). NUCLEAR FUEL
Preliminary comparison of Samura code predictions with experimental fuel pin data. Samiei M. Nucl. Engng Des. 66, 61 (1981). (Nuclear Power Section, Imperial College, London SW7 2BX, U.K.). Fretting and wear of stainless and ferritic steels in LMFBR steam generators. Lewis M. W. J. and Campbell C. S. Nucl. Technol. 55, 460 (I 981). (UKAEA, National Centre of Tribology, Risley, Warrington, Cheshire, U.K.). Migration of gas liquid inclusions in single crystals of potassium and sodium chlorides. Olander D. R. Nucl. Sci. Engng 79, 212 (1981). (Lawrence Berkeley Lab., Materials and Molecular Research Division, Berkeley, California, U.S.A.), Non-destructive assay of fuel rods with any number of fissile isotopes. Swan M. E. et al. A T K E 39, 48 (1981). (Nuclear Engineering Dept, University of Alexandria, Alexandria, Egypt).
228
Current Papers in Nuclear Energy FUEL
CYCLES
Specification of limiting sizes ofPuO 2 microheterogeneities in pellets of mixed oxide fuels. Sanchez Sarmiento G. Nucl. Enang Des. 65, 423 (1981). (Centro Atomico Bariloche, Bariloche, Argentina). Adjoint sensitivity analysis in nuclear reactor fuel behaviour modelling. Christensen R. A. et al. Nucl. Engng Des. 66, 125 (1981). (Entropy Lid, South Great Road, Lincoln, Massachusetts, U.S.A.). SAFETY
Eddy current inspection of a 17-year-old nuclear steam generator. Van Drunen G. and Cecco V. S. Nucl. Technol. 55, 362 (1981). (AECL, Chalk River, Ontario, Canada). Seismic analysis of the pile foundation of a reactor building of the NPP ANGRA 2. WolfJ. P. et al. Nucl. Engn# Des. 65, 329 (1981). (Electrowatt Engineering Services Ltd, 8022 Zurich, Switzerland). Design of a steel liner against rupture. Moon Y. I. Nucl. Engng Des. 65, 431 (1981). (Department of Mechanical Engineering, Bucknell University, Lewisburg, PA 17837, U.S.A.). Occurrence rates of fuses in nuclear power plants. Hockenbury R. W. et al. Nucl. En#ng Des. 66, 233 (1981). (Rensselaer Polytechnic Institute, Troy, NY 12181, U.S.A.). Molten fuel-coolant interaction during a reactivity initiated accident experiment. E1-Genk M. S. et aL Nucl. Engng Des. 66, 247 (1981). (EG & G Idaho Inc., P.O. Box 1625, Idaho Falls, ID 83415, U.S.A.). An analysis of containment failure by a steam explosion in a LWR. Corradnu M. L. et al. N ucl. Engng Des. 66, 287 (1981). (Sandia Nuclear Labs, Albuquerque, NM 87185, U.S.A.). Analysis of contour map of natural radiation in Japan. Fukitaka K. J. nucl. Sci. Technol. 18, 727 (1981). (Environmental Health Division, National Institute of Radiological Sciences, Anagaura, Chiba-shi 260, Japan). Upper plenum bump during reflood in PWR loss of coolant accident. Sudo Y. J. nucl. Sci. Technol. 18, 487 (1981). (JAERI, Tokai-mura, Naka-gun, Ibaraki-ken 319-11, Japan). Seismic response of high temperature gas-cooled reactor core with block-type fuel. Ikushima T. J. nucl. Sci. Technol. 18, 514 (1981). (JAERI, Tokai-mura, Naka-gun, Ibaraki-ken 319-11, Japan). Determination of heat capacity of simulated radioactive waste glasses by drop calorimetry. Saito S. J. nucl. Sci. Technol. 18, 540 (1981). (Department of Nuclear Engineering, Faculty of Engineering, Kyushu University, Hakozaki, Higashi-ku, Fukuoka-shi 812, Japan). Radiological measurements at nuclear power plants during start-up. Martin D. A T K E 39, 1 (1981). (EEC, Joint Research Centre, Ispra Establishment, 1-21020 Ispra, Varese, Italy).
HEAT TRANSFER AND FLUID
DYNAMICS
Materials performance in nuclear PWR steam generators. Green S. J. and Paine J. P. N. Nucl. Technol. 55, 10 (1981). (EPRI, 3412 Hillview Ave., P.O. Box 10412, Palo Alto, California, U.S.A.). Materials performance in CANDU steam generators. Taylor G. F. and Dantovich D. P. Nucl. Technol. 55, 50 (1981). (AECL, Chalk River, Ontario, Canada). Steam generator materials performance in HTGCR. Chafey J. E. and Roberts D. I. NucL Technol. 55, 37 (1981). (GAC, P.O. Box 81608, San Diego, CA 92138, U.S.A.). LMFBR steam generators--U.S. Design. Stone C. C. et al. Nucl. Technol. 55, 60 (1981). (ANL, 9700 South Cass Ave., Argonne, IL 60439, U.S.A.). The design and construction of boilers for AGCR in the U.K. Cameron P. J. and Waiters J. Nucl. Technol. 55, 151 (I 981). (National Nuclear Corp. Warrington Road, Risley, Warrington, Cheshire, U.K.). Fabrication technology for LMFBR steam generators. Spalaris C. N. et al. Nucl. Technol. 55, 243 (1981). (GEC, 175 Curtner Ave., San Jose, California, U.S.A.). Some aspects of materials development for sodium heated steam generators. Roy P. and Spalarin C. N. Nucl. Technol. 55, 259 (1981). (GEC, 175 Curtner Ave., San Jose, California, U.S.A.). Steam generator tubing development for FBR. Sessions C. E. and Uber C. F. Nucl. Technol. 55, 280 (1981). (Westinghouse Electric Corp., 6001 S. West Shore Blvd, Tampa, Florida, U.S.A.). Effect on decarbonization on structural and mechanical properties of ferritic steels. Tavassoli A. A. et al. Nucl. Technol. 55, 302 (1981). (CEA, Saclay, France). Flow induced vibration and wear of steam generator tubes. Connors H. J. Nucl. Technol. 55, 311 (1981). (Westinghouse Electric Corp., 1310 Beulah Road, Pittsburgh, PA 15235, U.S.A.). Materials model boiler tests for B and W once through steam generators. Emanuelson R. H. et al. Nucl. Technol. 55, 422 (1981). (Babcock & Wilcox Co., 1562 Beeson Street, Alliance, Ohio, U.S.A.). Heat transfer coefficients under LOCA conditions in containment buildings. Carbajo J. J. Nucl. Engng Des. 65, 369 (1981). (Babcock & Wilcox Co., P.O. Box 1260, Lynchburg, Ohio, U.S.A.). A quasi-transient heat conduction model of heat transfer in fuel-coolant interaction in LMFBRs. Rao R. B. et al. Nucl. Engng Des. 66, 1 (1981). (Reactor Research Centre, Kalpakkam 603 102, Tamil Nadu, India). A method for determining rewetting velocity under generalized boiling conditions. Bonakdar H. and McAssey E. V. Nucl. Engng Des. 66, 7 (1981). (Department of Mechanical Engineering, Villanova University, Villanova, PA 19085, U.S.A.). Dynamic testing of U.S.-built nuclear power plant buildings. Srinivasan M. G. et al. Nucl. Engng Des. 66, 97 (1981). (Components Technology Division, ANL, 9700 South Cass Ave., Argonne, IL 60439, U.S.A.).
Current Papers in Nuclear Energy Thermodynamic transients in nuclear steam turbines. Murty L. G. K. and Kale D. D. Nucl. Enon 0 Des. 66, 117 (1981). (Reactor Analysis and Studies Section, Bhabha Research Centre, Bombay 400085, India). A one-dimensional computation method for predicting the asymptotic heat transfer behaviour of sodium saturated fuel particle bed. Schwalm T. N. D. Nucl. Enon 0 Des. 66, 131 (1981). (EEC, Joint Research Centre, Ispra Establishment, 1-21020 lspra, Varese, Italy). Modelling the formation of local blockages at the grids of LMFBR sub-assemblies. Anderson R. Nucl. En#no Des. 66, 203 (1981). (Dounreay Nuclear Power Development Establishment, UKAEA, Dounreay, Scotland). Effects of presence of impurities on non-equilibrium MHD power generation incorporating fossil fuel-fired heat exchanger. Yoshikawa I. C. d. nucl. Sci. Technol. 18, 73 (1981). (Institute of Atomic Energy, Kyoto University, Gokanosho, Uji-shi, Kyoto, Japan). Pool boiling heat transfer in liquid nitrogen. Kida M. J. nucl. Sci. Technol. 18, 501 (1981). (Yoshida, Sakyo-ku, Kyoto 600, Japan). Analysis of temperature fluctuations in liquid-metal systems. Meek C. C. Nucl. Sci. Engno 79, 202 (1981). (ANL, 9700 South Cass Ave., Argonne, IL 60439, U.S.A.).
MATERIALS Chemical thermohydraulics of steam generators. Cohen P. Nuel. Technol. 55, 105 (1981). (3024 Beechwood Blvd, Pittsburgh, Pennsylvania, U.S.A.). Effects of copper and nickel compounds on the corrosion of PWR steam generator materials. White E. L. and Berry W. E. Nucl. Technol. 55, 135 (1981). (Battelle Columbus Labs, 505 King Ave., Columbus, Ohio, U.S.A.). Corrosion of aUoy 600 by cationic resin beads. Kendig M. W. and lsaacs H. S. Nucl. Technol. 55, 191 (1981). (BNL, Upton, New York, U.S.A.). SNR 300 experience in steam generators. Knaap M. H. et al. Nucl. Technol. 55, 218 (1981). (B. V. Neratoom, The Hague, Netherlands). Water chemistry of breeder reactor steam generators. Simpson J. L. et al. Nucl. Technol. 55, 339 (1981). (GEC, 175 Curtner Ave., San Jose, California, U.S.A.). A stress corrosion cracking evaluation of inconel 690. Airey G. P. et al. Nucl. Technol. 55, 456 (1981). (Westinghouse Research & Development Center, 1310 Beulah Road, Pittsburgh, PA 15235, U.S.A.). The corrosion of etched Magnox S°AL in dry steam at 105 Pa pressure in the temperature range 373-573 K. Friskney C. A. J. nucl. Mater. 99, 165 (1981). (CEGB, Berkeley Nuclear Labs, Berkeley, Gloucestershire, U.K.). Microstructure ofpolycrystalline SC containing excess Si after neutron and ion irradiation. Harrison S. D. and Corelli J. C. J. nucl. Mater. 99, 203 (1981). (Department of Nuclear Engineering, Rensselaer Polytechnic Institute, Troy, NY 12181, U.S.A.).
229
Iodine stress corrosion crackingofzercaloy:laboratory data, a phenomenological model. Miller A. K. et al. J. nucl. Mater. 99, 254 (1981). (Department of Materials Science and Engineering, Stanford University, Stanford, CA 94305, U.S.A.). A fission-nentron source for the study of defect production in metal. Klabunde C. E. J. nucl. Mater. 99, 294 (1981). (Solid State Division, ORNL, Oak Ridge, TN 37830, U.S.A.). Some recollections of metallurgy at Los Alamos 1943-1945. Smith C. S. J. nucl. Mater. 100, 3 (1981). (31 Madison Street, Cambridge, Massachusetts, U.S.A.). History of nuclear materials: memoirs and surveys. J. nucl. Mater. 100, 267 (1981). Specialist volume. Neutron induced autoradiography to determine the range of fission fragments in tissue and the plutonium burden of mouse liver. Wilson D. J. and Bentley K. W. Radiat. Effects 56, 187 (1981). (AAEC Research Establishment, Private Mail Bag, Lucas Heights, Sutherland, N.S.W. 2232, Australia). Zircaloy-4 cladding embrittlement due to inner surface oxidation under simulated loss-of-coolant condition. Vetsuka H. J. nucl. Sci. Technol. 18, 705 (1981). (Division of Reactor Safety, JAERI, Tokai-mura, Nakagun, Ibaraki-ken 319-11, Japan). High temp. reformation behaviour of gradually pressurized Zircaloy-4 tubes. J. nucl. Sci. Technol. 18, 617 (1981). (JAERI, Tokai-mura, Naka-gun, Ibaraki-ken 319-11, Japan). Compatibility of Eu203 and (Eu, Gd) 203 with type 316 stainless steel. Maruyama T. Nucl. Sci. Technol. 18, 608 (1981). (Research Lab. for Nuclear Reactors, Tokyo Institute of Technology, Ohakayama, Tokyo). Theory of the spatial distribution of defects in radiation cascades in crystals: I and II. Orlov A. N. and Trushin Y. V. Radiat. Effects 56, 193 (1981). (Academy of Sciences of U.S.S.R., 194021 Leningrad, I.LS,S.R.).
FUSION Neo-classical transport of impurities in Tokamak plasmas. Hirshman S. P. and Sigmar D. J. Nucl. Fusion 21, 1079 (1981). (ORNL, Oak Ridge, TN 37830, U.S.A.). Stabilization of ballooning modes by energetic particles in Tokamaks. Tsang K. T. and Sigmar D. J. Nucl. Fusion 21, 1227 (1981). (ORNL, Oak Ridge, TN 37830, U.S.A.). Stability of EBT in guiding centre fluid theory. Miller R. L. Nucl. Fusion 21, 1249 (1981). (GAC, San Diego, CA 92138, U.S.A.). Toroidal plasma rotation in the PLT Tokarnak. Suckewer S. et al. Nucl. Fusion 21, 1301 (1981). (Plasma Physics Lab., Princeton University, Princeton, NJ 08540, U.S.A.). High density cascade effects. Thompson D. A. Radiat. Effects 56, 105 (1981). (Department of Engineering Physics, McMaster University, Hamilton, Ontario, Canada).
230
Current Papers in Nuclear Energy
Range measurements and track kinetics in dielectric nuclear track detectors (DNTDs). Aframian A. A T K E 39, 23 ( 1981). (Alio, P.O. Box 3327, Tehran, Iran). Mathematical simulation procedure of multicomponent separating cascade. Kinoshita M. J. nucl. Sci. Technol. 18, 718 (1981). (JAERI, Division of Thermonuclear Fusion Research, Tokai-mura, Naka-gun, Ibaraki-ken 319-11, Japan). Effects of Toroidal field ripple on the loss of energetic injected ions and Toroidal coil configuration in a Tokamak reactor. Tone T. J. nucl. Sci. Technol. 18, 684 (1981). (JAERI, Tokai-mura, Naka-gun, Ibaraki-ken 319-11, Japan). Energetics of beam driven D-cycle plasmas. Schoepf K. F. J. nucl. Sci. Technol. 18, 653 (1981). (McMaster University, Hamilton, Ontario, Canada). Dynamical instability of non-equilibrium MHD generator with fully ionized seed plasma. Tanaka D. and Hattori Y. J. nucl. Sci. Technol. 19, 477 (1981). (Institute of Atomic Energy, Kyoto University, Gokanosho, Uji-shi, Kyoto, Japan). Computer analysis on steady state separation characteristics of hydrogen isotope separation system by cryogenic
distillation. Kinoshita M. J. nucl. Sci. Technol. 18, 525 (1981). (JAERI, Division of Thermonuclear Fusion Research, Tokai-mura, Naka-gun, Ibaraki-kcn 319-11, Japan). Parameter setting method for control system of cryogenic distillation column. Kinoshita M. J. nucl. Sci. TechnoL 19, 595 (1981). (JAERI, Division of Thermonuclear Fusion Research, Tokai-mura, Naka-gun, Ibaraki-ken 319-11, Japan). An accurate numerical method to solve the linear FokkerPlanck equation characterizing charged particle transport in spherical plasmas. Tran T. M. Nucl. Sci. Engn 0 79, 269 (1981). (Laboratoire de Genie Atomique, Swiss Federal Institute of Technology, 1700, Lausanne, Switzerland). Electronic stopping power formula for intermediate energies. Sugiyama H. Radiat. Effects 56, 205 (1981). (Electrotechnical Lab., 1-1-4 Umezono, Saka-mura, Ibaraki-ken, Japan). Stable thermonuclear pinch. Winterberg F. A T K E 39, 133 (1981). (Desert Research Institute, University of Nevada System, Reno, Nevada, U.S.A.).
REACTOR PHYSICS
Comparison of various types of SSNTD for neutron dosimetry. Sayed A. M. A T K E 39, 27 (1981). (Physics Dept, College of Science, Basrah University, Basrah, Iraq). Sedimentological measurements in the river Ghezel uzan using the radioactive sources 137Cs and 133Ba. Panahandeh I. H. A T K E 39, 20 (1981). (University of Nuclear Science and Technology, Tehran University, Tehran, Iran). Analysis of 14 MeV (n, p) cross section with pre-equilibrium model and effective Q-values. Kumabe I. J. nucl. Sci. Technol. 18, 563 (1981). (Department of Nuclear Engineering, Faculty of Engineering, Kyushu University, Hakozaki, Higashi-ku, Fukuoka-shi 812, Japan). A new mixed method with finite difference and finite element method for neutron diffusion calculation. Naito Y. J. nucl. Sci. Technol. 18, 571 (1981). (JAERI, Tokai-mura, Naka-gun, Ibaraki-ken 319-11, Japan). Analysis of neutron and secondary ~-ray transport in air-overground geometry by PALLAS-2DCX-FC code. Takeuchi K. J. nucl. Sci. Technol. 18, 581 (1981). (Tokai Branch, Ship Research Institute, Tokai-mura, Ibaraki-ken, Japan). The effects on reactivity coefficient of spectral shifts introduced by Doppler broadening. Alapour N. Nucl. Sci. Engn9 79, 278 (1981). (Georgia Institute of Technology, School of Nuclear Engineering, Atlanta, GA 30332, U.S.A.). Gold neutron capture cross section from 100 to 2000 keV. Mackun R. L. Nucl. Sci. Enon9 79, 265 (1981). (ORNL, P.O. Box X, Building 6010, Oak Ridge, TN 37830, U.S.A.). Three-dimensional neutron streaming calculations using the Monte Carlo coupling technique. Ueki K. Nucl. Sci. En#n# 79, 253 (1981). (Nuclear Ship Division, Ship Research Institute, 6-38-1 Shinkawa, Mitaka, Tokyo 181, Japan). Cross section for the 25Mg (~,n) 12sSi reaction for Ea < 4.8 MeV. Van der Zwan L. Nucl. Sci. Engng 79, 197 (1981). (National Research Council of Canada, Division of Physics, Ottawa, Ontario K 1A OS 1, Canada). Neutron capture cross section of 237Np. Eston L. W. Nucl. Sci. Enong 79, 184 (1981). (ORNL, P.O. Box X, Building 6010, Oak Ridge, TN 37830,
U.S.A.). Neutron capture and total cross section of E32Thfrom 0.006 to 18 eV. Little R. C. Nucl. Sci. Engno 79, 175 (1981). (Rensselaer Polytechnic Institute, Gaerttner Linoc Lab., Troy, NY 12181, U.S.A.). Mass distribution in the reactor-neutron induced fission of 232Th. Erten H. N. Nucl. Sci. En.qn.q 79, 167 (1981). 227
(Eidgenoessiches Institut fur Reaktorforschung, 5305 Wiirenlingen, Switzerland). Neutron production by medium-energy ( ~ 1.5 GeV) protons in thick uranium targets. Alsmiller R. G. Nucl. Sci. Enono 79, 162(1981). (ORNL, P.O. Box X, Oak Ridge, TN 37830, U.S.A.). Phenomenological model for particle production from the collisions of nucleons and pions with fissile elements at medium energies. Alsmiller R. S. Nucl. Sci. Enon O 79, 147 (1981). (ORNL, P.O. Box X, Building 6025, Oak Ridge, TN 37830, U.S.A.). A Monte Carlo calculation of the neutron and gamma sensitivities of self-powered detectors. Pytel K. A T K E 39, 31 (1981). (Reactor Operation Dept, Institute of Nuclear Research, 05-400 Swierk, Otwock, Poland). Neutron analysis of fast hybrid thermionic reactors. Sahin S. A T K E 39, 41 (1981). (Swiss Federal Institute of Technology, 1700 Lausanne, Switzerland). CONTROL AND DYNAMICS
New method of startup planning for boiling water reactors. Bessho Y. J. nucl. Sci. Technol. 18, 697 (1981). (Energy Research Lab., Hitachi Ltd, Moriyama-Cho, Hitachi-shi, Ibaraki-ken 317, Japan). Sink frequency analogy for cross-spectral density and neutron wave propagation in multi-region multiplying systems. Nagy M. E. et al. A T K E 39, 45 (1981). (Nuclear Engineering Dept, University of Alexandria, Alexandria, Egypt). NUCLEAR FUEL
Preliminary comparison of Samura code predictions with experimental fuel pin data. Samiei M. Nucl. Engng Des. 66, 61 (1981). (Nuclear Power Section, Imperial College, London SW7 2BX, U.K.). Fretting and wear of stainless and ferritic steels in LMFBR steam generators. Lewis M. W. J. and Campbell C. S. Nucl. Technol. 55, 460 (I 981). (UKAEA, National Centre of Tribology, Risley, Warrington, Cheshire, U.K.). Migration of gas liquid inclusions in single crystals of potassium and sodium chlorides. Olander D. R. Nucl. Sci. Engng 79, 212 (1981). (Lawrence Berkeley Lab., Materials and Molecular Research Division, Berkeley, California, U.S.A.), Non-destructive assay of fuel rods with any number of fissile isotopes. Swan M. E. et al. A T K E 39, 48 (1981). (Nuclear Engineering Dept, University of Alexandria, Alexandria, Egypt).
228
Current Papers in Nuclear Energy FUEL
CYCLES
Specification of limiting sizes ofPuO 2 microheterogeneities in pellets of mixed oxide fuels. Sanchez Sarmiento G. Nucl. Enang Des. 65, 423 (1981). (Centro Atomico Bariloche, Bariloche, Argentina). Adjoint sensitivity analysis in nuclear reactor fuel behaviour modelling. Christensen R. A. et al. Nucl. Engng Des. 66, 125 (1981). (Entropy Lid, South Great Road, Lincoln, Massachusetts, U.S.A.). SAFETY
Eddy current inspection of a 17-year-old nuclear steam generator. Van Drunen G. and Cecco V. S. Nucl. Technol. 55, 362 (1981). (AECL, Chalk River, Ontario, Canada). Seismic analysis of the pile foundation of a reactor building of the NPP ANGRA 2. WolfJ. P. et al. Nucl. Engn# Des. 65, 329 (1981). (Electrowatt Engineering Services Ltd, 8022 Zurich, Switzerland). Design of a steel liner against rupture. Moon Y. I. Nucl. Engng Des. 65, 431 (1981). (Department of Mechanical Engineering, Bucknell University, Lewisburg, PA 17837, U.S.A.). Occurrence rates of fuses in nuclear power plants. Hockenbury R. W. et al. Nucl. En#ng Des. 66, 233 (1981). (Rensselaer Polytechnic Institute, Troy, NY 12181, U.S.A.). Molten fuel-coolant interaction during a reactivity initiated accident experiment. E1-Genk M. S. et aL Nucl. Engng Des. 66, 247 (1981). (EG & G Idaho Inc., P.O. Box 1625, Idaho Falls, ID 83415, U.S.A.). An analysis of containment failure by a steam explosion in a LWR. Corradnu M. L. et al. N ucl. Engng Des. 66, 287 (1981). (Sandia Nuclear Labs, Albuquerque, NM 87185, U.S.A.). Analysis of contour map of natural radiation in Japan. Fukitaka K. J. nucl. Sci. Technol. 18, 727 (1981). (Environmental Health Division, National Institute of Radiological Sciences, Anagaura, Chiba-shi 260, Japan). Upper plenum bump during reflood in PWR loss of coolant accident. Sudo Y. J. nucl. Sci. Technol. 18, 487 (1981). (JAERI, Tokai-mura, Naka-gun, Ibaraki-ken 319-11, Japan). Seismic response of high temperature gas-cooled reactor core with block-type fuel. Ikushima T. J. nucl. Sci. Technol. 18, 514 (1981). (JAERI, Tokai-mura, Naka-gun, Ibaraki-ken 319-11, Japan). Determination of heat capacity of simulated radioactive waste glasses by drop calorimetry. Saito S. J. nucl. Sci. Technol. 18, 540 (1981). (Department of Nuclear Engineering, Faculty of Engineering, Kyushu University, Hakozaki, Higashi-ku, Fukuoka-shi 812, Japan). Radiological measurements at nuclear power plants during start-up. Martin D. A T K E 39, 1 (1981). (EEC, Joint Research Centre, Ispra Establishment, 1-21020 Ispra, Varese, Italy).
HEAT TRANSFER AND FLUID
DYNAMICS
Materials performance in nuclear PWR steam generators. Green S. J. and Paine J. P. N. Nucl. Technol. 55, 10 (1981). (EPRI, 3412 Hillview Ave., P.O. Box 10412, Palo Alto, California, U.S.A.). Materials performance in CANDU steam generators. Taylor G. F. and Dantovich D. P. Nucl. Technol. 55, 50 (1981). (AECL, Chalk River, Ontario, Canada). Steam generator materials performance in HTGCR. Chafey J. E. and Roberts D. I. NucL Technol. 55, 37 (1981). (GAC, P.O. Box 81608, San Diego, CA 92138, U.S.A.). LMFBR steam generators--U.S. Design. Stone C. C. et al. Nucl. Technol. 55, 60 (1981). (ANL, 9700 South Cass Ave., Argonne, IL 60439, U.S.A.). The design and construction of boilers for AGCR in the U.K. Cameron P. J. and Waiters J. Nucl. Technol. 55, 151 (I 981). (National Nuclear Corp. Warrington Road, Risley, Warrington, Cheshire, U.K.). Fabrication technology for LMFBR steam generators. Spalaris C. N. et al. Nucl. Technol. 55, 243 (1981). (GEC, 175 Curtner Ave., San Jose, California, U.S.A.). Some aspects of materials development for sodium heated steam generators. Roy P. and Spalarin C. N. Nucl. Technol. 55, 259 (1981). (GEC, 175 Curtner Ave., San Jose, California, U.S.A.). Steam generator tubing development for FBR. Sessions C. E. and Uber C. F. Nucl. Technol. 55, 280 (1981). (Westinghouse Electric Corp., 6001 S. West Shore Blvd, Tampa, Florida, U.S.A.). Effect on decarbonization on structural and mechanical properties of ferritic steels. Tavassoli A. A. et al. Nucl. Technol. 55, 302 (1981). (CEA, Saclay, France). Flow induced vibration and wear of steam generator tubes. Connors H. J. Nucl. Technol. 55, 311 (1981). (Westinghouse Electric Corp., 1310 Beulah Road, Pittsburgh, PA 15235, U.S.A.). Materials model boiler tests for B and W once through steam generators. Emanuelson R. H. et al. Nucl. Technol. 55, 422 (1981). (Babcock & Wilcox Co., 1562 Beeson Street, Alliance, Ohio, U.S.A.). Heat transfer coefficients under LOCA conditions in containment buildings. Carbajo J. J. Nucl. Engng Des. 65, 369 (1981). (Babcock & Wilcox Co., P.O. Box 1260, Lynchburg, Ohio, U.S.A.). A quasi-transient heat conduction model of heat transfer in fuel-coolant interaction in LMFBRs. Rao R. B. et al. Nucl. Engng Des. 66, 1 (1981). (Reactor Research Centre, Kalpakkam 603 102, Tamil Nadu, India). A method for determining rewetting velocity under generalized boiling conditions. Bonakdar H. and McAssey E. V. Nucl. Engng Des. 66, 7 (1981). (Department of Mechanical Engineering, Villanova University, Villanova, PA 19085, U.S.A.). Dynamic testing of U.S.-built nuclear power plant buildings. Srinivasan M. G. et al. Nucl. Engng Des. 66, 97 (1981). (Components Technology Division, ANL, 9700 South Cass Ave., Argonne, IL 60439, U.S.A.).
Current Papers in Nuclear Energy Thermodynamic transients in nuclear steam turbines. Murty L. G. K. and Kale D. D. Nucl. Enon 0 Des. 66, 117 (1981). (Reactor Analysis and Studies Section, Bhabha Research Centre, Bombay 400085, India). A one-dimensional computation method for predicting the asymptotic heat transfer behaviour of sodium saturated fuel particle bed. Schwalm T. N. D. Nucl. Enon 0 Des. 66, 131 (1981). (EEC, Joint Research Centre, Ispra Establishment, 1-21020 lspra, Varese, Italy). Modelling the formation of local blockages at the grids of LMFBR sub-assemblies. Anderson R. Nucl. En#no Des. 66, 203 (1981). (Dounreay Nuclear Power Development Establishment, UKAEA, Dounreay, Scotland). Effects of presence of impurities on non-equilibrium MHD power generation incorporating fossil fuel-fired heat exchanger. Yoshikawa I. C. d. nucl. Sci. Technol. 18, 73 (1981). (Institute of Atomic Energy, Kyoto University, Gokanosho, Uji-shi, Kyoto, Japan). Pool boiling heat transfer in liquid nitrogen. Kida M. J. nucl. Sci. Technol. 18, 501 (1981). (Yoshida, Sakyo-ku, Kyoto 600, Japan). Analysis of temperature fluctuations in liquid-metal systems. Meek C. C. Nucl. Sci. Engno 79, 202 (1981). (ANL, 9700 South Cass Ave., Argonne, IL 60439, U.S.A.).
MATERIALS Chemical thermohydraulics of steam generators. Cohen P. Nuel. Technol. 55, 105 (1981). (3024 Beechwood Blvd, Pittsburgh, Pennsylvania, U.S.A.). Effects of copper and nickel compounds on the corrosion of PWR steam generator materials. White E. L. and Berry W. E. Nucl. Technol. 55, 135 (1981). (Battelle Columbus Labs, 505 King Ave., Columbus, Ohio, U.S.A.). Corrosion of aUoy 600 by cationic resin beads. Kendig M. W. and lsaacs H. S. Nucl. Technol. 55, 191 (1981). (BNL, Upton, New York, U.S.A.). SNR 300 experience in steam generators. Knaap M. H. et al. Nucl. Technol. 55, 218 (1981). (B. V. Neratoom, The Hague, Netherlands). Water chemistry of breeder reactor steam generators. Simpson J. L. et al. Nucl. Technol. 55, 339 (1981). (GEC, 175 Curtner Ave., San Jose, California, U.S.A.). A stress corrosion cracking evaluation of inconel 690. Airey G. P. et al. Nucl. Technol. 55, 456 (1981). (Westinghouse Research & Development Center, 1310 Beulah Road, Pittsburgh, PA 15235, U.S.A.). The corrosion of etched Magnox S°AL in dry steam at 105 Pa pressure in the temperature range 373-573 K. Friskney C. A. J. nucl. Mater. 99, 165 (1981). (CEGB, Berkeley Nuclear Labs, Berkeley, Gloucestershire, U.K.). Microstructure ofpolycrystalline SC containing excess Si after neutron and ion irradiation. Harrison S. D. and Corelli J. C. J. nucl. Mater. 99, 203 (1981). (Department of Nuclear Engineering, Rensselaer Polytechnic Institute, Troy, NY 12181, U.S.A.).
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Iodine stress corrosion crackingofzercaloy:laboratory data, a phenomenological model. Miller A. K. et al. J. nucl. Mater. 99, 254 (1981). (Department of Materials Science and Engineering, Stanford University, Stanford, CA 94305, U.S.A.). A fission-nentron source for the study of defect production in metal. Klabunde C. E. J. nucl. Mater. 99, 294 (1981). (Solid State Division, ORNL, Oak Ridge, TN 37830, U.S.A.). Some recollections of metallurgy at Los Alamos 1943-1945. Smith C. S. J. nucl. Mater. 100, 3 (1981). (31 Madison Street, Cambridge, Massachusetts, U.S.A.). History of nuclear materials: memoirs and surveys. J. nucl. Mater. 100, 267 (1981). Specialist volume. Neutron induced autoradiography to determine the range of fission fragments in tissue and the plutonium burden of mouse liver. Wilson D. J. and Bentley K. W. Radiat. Effects 56, 187 (1981). (AAEC Research Establishment, Private Mail Bag, Lucas Heights, Sutherland, N.S.W. 2232, Australia). Zircaloy-4 cladding embrittlement due to inner surface oxidation under simulated loss-of-coolant condition. Vetsuka H. J. nucl. Sci. Technol. 18, 705 (1981). (Division of Reactor Safety, JAERI, Tokai-mura, Nakagun, Ibaraki-ken 319-11, Japan). High temp. reformation behaviour of gradually pressurized Zircaloy-4 tubes. J. nucl. Sci. Technol. 18, 617 (1981). (JAERI, Tokai-mura, Naka-gun, Ibaraki-ken 319-11, Japan). Compatibility of Eu203 and (Eu, Gd) 203 with type 316 stainless steel. Maruyama T. Nucl. Sci. Technol. 18, 608 (1981). (Research Lab. for Nuclear Reactors, Tokyo Institute of Technology, Ohakayama, Tokyo). Theory of the spatial distribution of defects in radiation cascades in crystals: I and II. Orlov A. N. and Trushin Y. V. Radiat. Effects 56, 193 (1981). (Academy of Sciences of U.S.S.R., 194021 Leningrad, I.LS,S.R.).
FUSION Neo-classical transport of impurities in Tokamak plasmas. Hirshman S. P. and Sigmar D. J. Nucl. Fusion 21, 1079 (1981). (ORNL, Oak Ridge, TN 37830, U.S.A.). Stabilization of ballooning modes by energetic particles in Tokamaks. Tsang K. T. and Sigmar D. J. Nucl. Fusion 21, 1227 (1981). (ORNL, Oak Ridge, TN 37830, U.S.A.). Stability of EBT in guiding centre fluid theory. Miller R. L. Nucl. Fusion 21, 1249 (1981). (GAC, San Diego, CA 92138, U.S.A.). Toroidal plasma rotation in the PLT Tokarnak. Suckewer S. et al. Nucl. Fusion 21, 1301 (1981). (Plasma Physics Lab., Princeton University, Princeton, NJ 08540, U.S.A.). High density cascade effects. Thompson D. A. Radiat. Effects 56, 105 (1981). (Department of Engineering Physics, McMaster University, Hamilton, Ontario, Canada).
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Current Papers in Nuclear Energy
Range measurements and track kinetics in dielectric nuclear track detectors (DNTDs). Aframian A. A T K E 39, 23 ( 1981). (Alio, P.O. Box 3327, Tehran, Iran). Mathematical simulation procedure of multicomponent separating cascade. Kinoshita M. J. nucl. Sci. Technol. 18, 718 (1981). (JAERI, Division of Thermonuclear Fusion Research, Tokai-mura, Naka-gun, Ibaraki-ken 319-11, Japan). Effects of Toroidal field ripple on the loss of energetic injected ions and Toroidal coil configuration in a Tokamak reactor. Tone T. J. nucl. Sci. Technol. 18, 684 (1981). (JAERI, Tokai-mura, Naka-gun, Ibaraki-ken 319-11, Japan). Energetics of beam driven D-cycle plasmas. Schoepf K. F. J. nucl. Sci. Technol. 18, 653 (1981). (McMaster University, Hamilton, Ontario, Canada). Dynamical instability of non-equilibrium MHD generator with fully ionized seed plasma. Tanaka D. and Hattori Y. J. nucl. Sci. Technol. 19, 477 (1981). (Institute of Atomic Energy, Kyoto University, Gokanosho, Uji-shi, Kyoto, Japan). Computer analysis on steady state separation characteristics of hydrogen isotope separation system by cryogenic
distillation. Kinoshita M. J. nucl. Sci. Technol. 18, 525 (1981). (JAERI, Division of Thermonuclear Fusion Research, Tokai-mura, Naka-gun, Ibaraki-kcn 319-11, Japan). Parameter setting method for control system of cryogenic distillation column. Kinoshita M. J. nucl. Sci. TechnoL 19, 595 (1981). (JAERI, Division of Thermonuclear Fusion Research, Tokai-mura, Naka-gun, Ibaraki-ken 319-11, Japan). An accurate numerical method to solve the linear FokkerPlanck equation characterizing charged particle transport in spherical plasmas. Tran T. M. Nucl. Sci. Engn 0 79, 269 (1981). (Laboratoire de Genie Atomique, Swiss Federal Institute of Technology, 1700, Lausanne, Switzerland). Electronic stopping power formula for intermediate energies. Sugiyama H. Radiat. Effects 56, 205 (1981). (Electrotechnical Lab., 1-1-4 Umezono, Saka-mura, Ibaraki-ken, Japan). Stable thermonuclear pinch. Winterberg F. A T K E 39, 133 (1981). (Desert Research Institute, University of Nevada System, Reno, Nevada, U.S.A.).