Annals of Nuclear Energy 1998: Vol 25 Index & Table of Contents

13 Pages·1998·2.4 MB·English

annals of
NUCLEAR ENERGY
Volume 25
List of Contents and Author Index
Executive Editors
M.M.R. Williams
University of London, U.K.
L. E. Weaver
Florida Institute of Technology, Melbourne, U.S.A.
Associate Editor
A. K. Prinja
University of New Mexico, Albuquerque, U.S.A.
ANNALS OF NUCLEAR ENERGY
EXECUTIVE EDITORS
L. E. WEAVER M. M. R. WILLIAMS
President, Florida Institute of Technology, University of London,
150 W. University Boulevard, Melbourne, London, U.K.
FL 32901-6988, U.S.A.
ASSOCIATE EDITOR
A. K. PRINJA
Department of Chemical and Nuclear Engineering, University of New Mexico,
Albuquerque, NM 87131, U.S.A.
ADVISORY EDITORS
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R. A. BONALUMI, North York, Canada D. OKRENT, Los Angeles, U.S.A.
F. R. FARMER, Warrington, U.K. A. E. PARSHAKOV, Kiev, Ukraine
H. FENECH, Santa Barbara, U.S.A. A. M. Perry, Oak Ridge, U.S.A.
W. FRANKOWSKI, Warsaw, Poland H. Ruer, /spra, Italy
B. D. GANAPOL, Tucson, U.S.A. W. ROTHENSTEIN, Haifa, Israel
A. GANDINI, Rome, Italy D. C. SAHNI, Bombay, India
W. HAFELE, Karlsruhe, Germany A. SCHNEIDER, Atlanta, U.S.A.
R. A. KARAM, Atlanta, U.S.A. B. I. SPINRAD, Seattle, U.S.A.
A. KLEIN, Corvallis, U.S.A. R. J. J. STAMM’LER, Gaithersburg, U.S.A.
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J. MiLDA, Tokai, Japan R. E. UnRIG, Knoxville, U.S.A.
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PII: S0306-4549(98)00060-7
LIST OF CONTENTS
NUMBER 1-3
M. Goswami and F. Ahmed l A quantitative structural analysis of the low
temperature phase of lithium-7
K. Hashimoto, S. Yamada, 13 Feynman-a correlation analysis by prompt-
Y. Hasegawa and T. Horiguchi photon detection
Y. Kasugai, H. Yamamoto, 23 Measurement of (n, p) cross sections for short-
K. Kawade and T. lida lived products by 13.4-14.9 MeV neutrons
D. Ginestar, G. Verdu, V. Vidal, High order backward discretization of the
R. Bru, J. Marin and neutron diffusion equation
J. L. Muiioz-Cobo
M. A. Feltus and U. Shoop 65 TRAC-BF1 three-dimensional BWR vessel
thermal-hydraulic and ANSYS stress analyses
for BWR core shroud cracking
T. G. Apostolov, G. Alekova 83 Comparative analysis of WWER-1000 bench-
and K. N. Ivanov mark calculations and improvements in
hexagonal-Z diffusion methodology
G. S. Chen and D. Y. Yang 97 Comparison of preconditioned generalized
conjugate gradient methods to _ two-
dimensional neutron and photon transport
equation
M. Chang and J. D. Lewins 117 Using life cycle revenue loss and Monte
Carlo simulation as a prior and direct assess-
ment of consequences of un-wished events
S. Q. B. Leite
129 Revised interface-current relations for the
unit-cell transport problem in cylindrical and
spherical geometries
Y. Yamane, T. Misawa, 141 Formulation of data synthesis technique for
S. Shiroya and H. Unesaki Feynman-a method
M. Yavuz 149 Methods for computing Sy eigenvalues and
eigenvectors of slab geometry transport
problems
Vi Volume contents
Technical Notes
K. Devan, V. Gopalakrishnan, 161 Preparation of multigroup lumped fission
P. Mohanakrishnan and product cross-sections from ENDF/B-VI for
M. S. Sridharan FBRs
M. Goswami, F. Ahmed 18] A simulation study for thermal breeding of
and S. Gupta tritium at low temperatures in a D-T fusion
reactor blanket
NUMBER 4-5
K. Kobayashi 189 A relation of the coupling coefficient to the
eigenvalue separation in the coupled reactors
theory
E. J. M. Wallerbos and 203 Experimental investigation of the count-loss
J. E. Hoogenboom effect due to the time interval between
counting-gates in the Feynman-a method
W. Rothenstein and R. Dagan 209 Ideal gas scattering kernel for energy
dependent cross-sections
T. Seino and H. Sekimoto 223 A study on the criticality search of transura-
nium recycling BWR core by adjusting
supplied fuel composition in equilibrium state
J. A. Perrotta, L. A. A. Terremoto 237 Experience on wet storage spent fuel sipping
and C. A. Zeituni at IEA-R1 Brazilian research reactor
J. L. Delcoux, P. E. Labeau and 259 Approximate zero-variance Monte Carlo esti-
J. Devooght mation of Markovian unreliability
M. Rosselet, T. Williams and 285 Subcriticality measurements using an epi-
R. Chawla thermal Pulsed—Neutron—Source technique in
pebble-bed HTR configurations
295 Experimental investigation of tube length
effect on nucleate pool boiling heat transfer
305 Small break LOCA analysis for optimization
of safety injection system of Korean standard
nuclear power plant
Volume contents Vil
Technical Note
M. S. Abdel Krim and 317 Variational approach to the Milne problem
A. R. Degheidy with specular and diffuse reflecting boundary
327 Book Review
329 Corrigendum
NUMBER 6
A. M. Mirza, N. M. Mirza 331 Simulation of corrosion product activity in
and I. Mir pressurized water reactors under flow rate
transients
B. Ozgener 347 A boundary integral equation for boundary
element applications in multigroup neutron
diffusion theory
S. Gupta, S. Garg 359 Enhancing tritium breeding characteristics
and F. Ahmed of a fusion reactor blanket
W. M. Ratemi and A. E. Eshabo 377 New form of. the inhour equation and its
universal abc-values for different reactor
types
A. Racz and I. Pazsit 387 Diagnostics of detector tube impacting with
wavelet techniques
Technical Note
K. R. Prasad and V. Balagi 401 Estimating gamma fields with an ion chamber
operating below saturation
NUMBER 7
J. K. Lee and B. S. Han 409 Modelling of core protection and monitoring
system for PWR nuclear power plant simulator
Y. Kasugai, Y. Ikeda, 421 Systematics for (n, a) excitation functions in
H. Yamamoto and K. Kawade the neutron energy between 13.3 and 16.0 MeV
Vill Volume contents
A. Hotta, H. Takeuchi 437 Three dimensional evaluation of two-phase
and S. Takeda flow in BWR _ fuel bundles based on
compressible two fluid-one pressure and k
and ¢ turbulence models
M. Antononopoulos-Domis 465 System indentification during a transient via
and T. Tambouratzis wavelet multiresolution analysis followed
by spectral techniques
NUMBER 8
L. Ruby, M. Becker and E. Elias 481 A new method of benchmarking diffusion
codes
K. Dobashi, A. Kimura, 487 Conceptual design of a high temperature
Y. Oka and S. Koshizuka power reactor cooled and moderated by
supercritical light water
V. G. Zimin and H. Ninokata 507 Nodal neutron kinetics model based on
nonlinear iteration procedure for LWR
analysis
C. Yildiz 529 Variation of the critical slab thickness with
the degree of strongly anisotropic scattering
in One-speed neutron transport theory
H. Konno and S. Kanemoto 54! Effect of multiplicative noise on decay ratio
Ser Gi Hong and Nam Zin Cho 547 CRX: A code for rectangular and hexagonal
lattices based on the method of characteristics
B. P. Dubey, V. Jagannathan 567 Quick and reliable estimation of power
and S. K. Kataria distribution in a PHWR by ANN
NUMBER 9
R. A. Bonalumi 581 Integration of differential equations by the
pseudo-linear (PL) approximation
T. Yamamoto, K. Sakurai 599 Numerical validation of a modified neutron
and Y. Naito source multiplication method using a
calculated eigenvalue
Volume contents ix
A. Ikonomopoulos and A. Endou 609 Empirical process modeling in fast breeder
reactors
A. Mizutani and H. Sekimoto 623 Cell geometry effects on nuclear characteristics
in equilibrium state
K. Hashimoto, H. Ohsaki, 639 Variance-to-mean method generalized by
T. Horiguchi, Y. Yamane linear difference filter technique
and S. Shiroya
T. Takeda, H. Nakabayashi 653 Interpretation of transmutation rates of minor
and N. Hirokawa actinides in thermal and fast reactors
I. Pazsit and Y. Yamane 667 The variance-to-mean ratio in subcritical
systems driven by a spallation source
S. I. Lee and H. C. No 677 Improvement of direct contact condensation
model of RELAPS/MOD3.1 for passive high-
pressure injection system
689 Book Review
693 Announcement
NUMBER 10
G. Horhoianu, D. R. Moscalu 695 Investigation of fuel rod behaviour under
and I. A. Popescu extended | burnup conditions with ROFEM
fuel performance code
H. Yamagata and K. Kanda 709 Bayesian analysis of public views on the
safety of nuclear developments
K. Ishitani, Y. Yamane, 721 Measurement of eigenvalue separation by
A. Uritani, T. Iguchi using position sensitive proportional counter
and S. Shiroya
E. J. M. Wallerbos and 733 The forgotten effect of the finite measurement
J. E. Hoogenboom time on various noise analysis techniques
A. Trkov 747 Analysis of the Rowlands uranium oxide
pin-cell benchmark with an updated WIMS-D
library
xX Volume contents
M.-H. Chun, N.-I. Tak 753 Development of a computer code to estimate
and S.-K. Lee the fuel rod failure using primary coolant
activities of operating PWRs
Technical Notes
P. E. Labeau 765 Multicomponent systems with _ time-
dependent transition rates. A note on the
representation and number of system states
W. I. Ko, J. W. Choi, C. H. Kang, 77) Nuclear fuel cycle cost analysis using a
J. S. Lee and K. J. Lee probabilistic simulation technique
791 Book Review
NUMBER 11
H. Sekimoto 793 Trade-off between neutron excess and long-
and K. Kanai term toxicity reduction by employing LLFP
incineration
K. Behringer 801 Concerning the neutron level and the neutron
RMS value in a linear feedback model of point
reactor kinetics with one group of delayed
neutrons and driven by the random reactivity
noise: application of the Runge-Kutta method
to solve a system of stochastic ordinary
differential equations
J. Koclas 821 Comparisons\of the different approximations
leading to mesh centered finite differences
starting from the analytic nodal method
V. Gopalakrishnan 839 Self-shielding and energy dependence of
and S. Ganesan dilution cross-section in the resolved resonance
region
D. A. de Andrade 859 Thermal hydrodynamical analysis of a
and J. L. F. Bastos countercurrent gas centrifuge
Technical Notes
K. Behringer 889 Detrending of non-stationary noise data by
spline techniques
Volume contents xi
K. Naguib, M. L. Michaiel 893 Feasibility study of U-235, Pu-239 and
and H. N. Morcos Pu-240 content determination in an irradiated
fuel by neutron transmission analysis
903 Book Review
NUMBER 12
J. Navarro-Esbri, G. Verdi 907 Reactor noise analysis based on the singular
D. Ginestar and J. L. Muitioz-Cobo value decomposition (SVD)
Y. S. Choi, S. H. Lee 923 Development of the public attitude model
and B. W. Lee toward nuclear power in Korea
C. Pereira 937 Non-proliferating reprocessed nuclear fuels
and E. M. Leite in pressurised water reactors: fuel cycle
options
J. O. Kim 963 A new uncertainty arising in_ reactor
and J. K. Kim pressure vessel fluence calculation
Technical Notes
Y. Ronen 983 Applying the 2Z-N correlation to predict
the fissility of *48Bk
H. Konno 987 Decay ratio for third order Brownian
and S. Kanemoto oscillators
995 Book Review
NUMBER 13
S. H. Ghyym 997 Overview of in-vessel retention concept
involving level of passivity: with application
to evolutionary pressurized water reactor
design
A. Mizutani 1011 Core performance of equilibrium fast reactors
and H. Sekimoto for different coolant materials and fuel types
J. Y. Cho 1021 Higher order polynomial expansion nodal
and C. H. Kim method for hexagonal core neutronics
analysis
xil Volume contents
V. Hristea 1033 Local Galerkin’s schemes qualitative analysis
and M. Pavelescu for 1D transport equation solving
M. O. Allagi, J. D. Lewins 1055 Variationally processed Monte Carlo transport
and G. T. Parks theory
B. P. Dubey, D. S. Pilkhwal 1069 Reliable prediction of complex thermal
and P. K. Vijayan hydraulic parameters by ANN
I. Pazsit, J. Karlsson 1079 Some developments in core-barrel vibration
and N. S. Garis diagnostics
NUMBER 14
B. Morillon 1095 On the use of Monte Carlo perturbation
in neutron transport problems
B. H. Rho 1119 Development and validation of atmospheric
and K. J. Lee dispersion: computer program using tritiim
air concentrations in the environment around
heavy water reactor power plants
H. Saygin, A. Sigman 1133 A comparison between the results of
and T. Biike perturbation theory and trigap for the
reactivity worth calculations of fuel elements
W. K. Matthes 1141 Calculation of radiation effects in solids by
direct numerical solution of the adjoint
transport equation
T.-H. Chun, D.-H. Hwang, Assessment of a tube-based bundle CHF
W. P. Baek and S. H. Chang prediction method using a subchannel code
H. Yoshioka, I. Pazsit, Analysis of temporal and spatial decay of
H. Otake and K. Nishina pulsed neutrons in single- and multiple-core
systems
Announcement
NUMBER 15
P. F. Frutuoso e Melo, 1191 Sensitivity analysis on the accident rate of a
A. C. M. Alvim and F. C. Silva plant equipped with a single protective channel
by generalized perturbation methods