Annals of Nuclear Energy 2000: Vol 27 Table of Contents

11 Pages·2000·1.4 MB·English

LIST OF CONTENTS
NUMBER |
H. Choi A fast-running fuel management program
for a CANDU reactor
J.S. Cassell and M.M.R. Williams The infinite medium Green’s function in
space and angle for the integro-differential
form of the neutron transport equation with
isotropic scattering
B. Morillon 21 Resonance parameters perturbation with
Doppler broadening in Monte Carlo neutron
transport problems
J.K.-H. Karlsson, I. Pazsit 3 An analytically solvable, axially non-homo-
geneous reactor model
II. Reactor kinetic approximations
Long-term control of excess reactivity by
burnable poison in reflector regions
A. Gandini, M. Salvatores and Balance of power in ADS operation and safety
I. Slessarev
Technical notes
Y. Ronen, M. Aboudy and A nuclear engine design with *47"Am as a
D. Regev nuclear fuel
K. Ryu and H. Sekimoto 3 Basic study of concentrically zoned fast
reactor using natural uranium highly efficiently
without fuel reprocessing
NUMBER 2
W.D. Sharp and E.J. Allen 99 Stochastic neutron transport equations for
rod and plane geometries
Il
IV Volume contents
H. Song, Y.-I. Kim, 117 Evaluation of core nuclear analysis code
T.-K. Kim, Y.-I. Kim system for LMR using measured physics
and S.-J. Kim parameters of BFS-73-1 critical assembly
H. Roushdy Derivation of modified approximate analytical
formulae for calculating the direct and adjoint
flux weighted resonance integrals using a
variable neutron spectrum
M.M.R. Williams The effect of random geometry on the
criticality of a multiplying system
D.L. Aldama and A. Trkov Analysis of the burnup credit benchmark
with an updated WIMS-D library
A.O. Goltsev, V.D. Davidenko, Computational problems in the calculation of
V.F. Tsibulsky and A.A. Lekomtsev temperature effects for heterogeneous nuclear
reactor unit cells
Book reviews
NUMBER 3
K.M. Leigh and R.T. Ackroyd 187 Obituary: Cedric Euan Iliffe O.B.E., E.R.D.,
M.A., C.Eng., F.I-Mech.E.
M. Pitts, F. Rahnema, 191 Experiments of water-moderated plutonium
T.G. Williamson, F. Trumble metal arrays: part I — description
and R.E. Rothe
M. Pitts, F. Rahnema, Experiments of water-moderated plutonium
T.G. Williamson and F. Trumble metal arrays: part II — analysis
M.M.R. Williams Neutron density fluctuations due _ to
randomly distributed sources in finite media
C.J. Jeong and H. Choi Xenon transient analysis for direct use of
spent pressurized water reactor fuel in CANDU
reactors (DUPIC)
Volume contents
NUMBER 4
H. Yapici, O. Ipek, V. Ozceyhan, 279 Analysis of the rejuvenation performance of
A. Erigen hybrid blankets by using uranium fuels (UN,
UC, UOs>, U;3Si,) and different coolants for
various volume fraction
Y.S. Choi, J.S. Kim and Public’s perception and judgment on nuclear
B.W. Lee power
S.R. Malkawi and N. Ahmad Prediction and measurement of neutron
energy spectrum in a material test research
reactor
G.S. Srinivasan, O.P. Singh Leak noise detection and characterisation
and R. Prabhakar using statistical features
C.H. Pyeon, Y. Yamane, Application of modified explicit higher order
T. Misawa and S. Shiroya perturbation (MHP) method to PWR core
analysis
O.M. Zamonsky, G.C. Buscaglia A posteriori error estimation for the one-
and Y.Y. Azmy dimensional arbitrarily high order transport-
nodal method
NUMBER 5
M.L. Buzano, S.E. Corno and 371 Kinetics of two phase fuel reflected reactors
F. Mattioda
V.G. Toshinsky, H. Sekimoto and A method to improve multiobjective genetic
G.I. Toshinsky algorithm optimization of a self-fuel-provid-
ing LMFBR by niche induction among
nondominated solutions
D.C. Sahni and A. Sharma Computation of higher spherical harmonics
moments of the angular flux for neutron
transport problems in spherical geometry
S.J. Kim, N.Z. Cho and Y.J. Kim A pan-shape transuranic burner core with a
low sodium void worth
C. Pereira, E.M. Leite and Waste analysis generated by alternative
E.F. Faria reprocessing fuels from pressurised water
reactors
Volume contents
NUMBER 6
S.T. Khericha 465 Development of one-energy group, two-
dimensional, frequency dependent detector
adjoint function based on the nodal method
M.O. Allagi and Variational processing of stochastic simula-
J.D. Lewins tion in neutron transport: the three-dimen-
sional system
N. Morishima Cold and thermal neutron scattering cross
sections of liquid H, and D, at temperatures
between melting and boiling points
M.M.R. Williams The effect of random geometry on the criti-
cality of a multiplying system II: Extension
to resonance absorption
Technical note
N. Ashoub and H.G. Saleh Neutronic evaluation of two proposed fuel
lattice pitches for ET-RR-1 reactor
NUMBER 7
A.K. Popov, Yu. N. Pepelyshevy and 563 The model of the IBR-2 pulsed reactor of
E.A. Bondarchenko periodic operation for investigations of
transitional processes
Y.S. Choi, S.H. Lee and Expert judgment for nuclear energy
B.W. Lee
A. Novelli The AMEBA PWR, a new concept in the
technology of nuclear reactor safety
M.O. Allagi and J.D. Lewins Higher-order variational _ perturbation
expressions in fixed source problems using
Monte Carlo trial functions
T. Miura, M. Baba, M. Ibaraki, Measurement of neutron inelastic scattering
T. Sanami, T. Win, Y. Hirasawa and cross-section for the first level of 7°8U in
N. Hirakawa hundreds of keV range
Volume contents Vil
M. Marseguerra and E. Zio 639 Monte Carlo biasing in reliability calculations
with deterministic repair times
F. Adorjan, T. Czibok, S. Kiss, Core asymmetry evaluation using static
K. Krinizs and J. Vegh measurements and neutron noise analysis
NUMBER 8
W.J. Park, M.H. Han and K.J. Lee 659 Analysis of the distributional effects of
radioactive materials on external gamma
exposure
R.C. Raichura 3 A working model for particle deposition in
turbulent flow
A.S. Ivanov and D.A. Ivanov Some peculiar features for kinetics of fission
gas release from nuclear fuel on fast heating
up
D. Yu and W.S. Park 3. Combination and evaluation of expert
opinions characterized in terms of fuzzy
probabilities
T.H.J.J. van der Hagen, R. Zboray Questioning the use of the decay ratio in
and W.J.M. de Kruijf BWR stability monitoring
H. van Dam 33 Long-term control of excess reactivity by
burnable particles
Technical note
A.M. El-Messiry ETRR-2 control rod withdrawal accident
Book review
NUMBER 9
M. Caner and E.T. Dugan 759 ThO,-UO, annular pins for high burnup
fuels
M.A. Feltus and W.S. Miller Three-dimensional coupled kinetics/thermal-
hydraulic benchmark TRIGA experiments
Vill Volume contents
K. Hashimoto, H. Ikeda and 791 Numerical instability of time-discretized
T. Takeda one-point kinetic equations
M.M.R. Williams Probabilistic methods in heterogeneous neu-
tronic systems
C.K. Jo, N.Z. Cho and Y.H. Kim Graphite-filled mixed-oxide fuel design for
fully loaded PWR cores
C. Yildiz Variation of the albedo and the transmission
factor with forward and backward scattering
in neutron transport theory—the Fx method
Technical note
N. Ashoub and E. Amin Detailed evaluation of ET-RR-2 neutronic
design: approach to criticality
NUMBER 10
S.Y. Kim and J.K. Kim 855 A reactivity hold-down strategy for soluble
boron free operation by introducing Pu-238
added fuel
L. Ali Khan, N. Ahmad, M.S. Zafar Reactor physics calculations and_ their
and A. Ahmad experimental validation for conversion and
upgrading of a typical swimming pool type
research reactor .
C.-J. Jeong and H. Choi Instability analysis on xenon spatial oscillation
ina CANDU-6 reactor with DUPIC fuel
J.S. Cassell and M.M.R. Williams Analytic solution of algebraic equations
associated with the source-sink method of
reactor lattices
J.H. Moon, C.S. Kang and A pattern-matching model for operator
J.H. Whang cognitive behaviors during accident conditions
at a nuclear power plant
Technical note
F. Yousefpour and M.B. Ghofrani Improvement of the axial power distribution
control capabilities in VVER-1000 reactors
Volume contents
NUMBER I]
R. Koohi-Fayegh, M.H. Abad, 959 Neutron spectrum measurements from 1-16
S. Green and M.C. Scott MeV in beryllium assemblies with a central
D-—T neutron source
D.K. Mohapatra and Moderator temperature effect on reactivity in
P. Mohanakrishnan light water moderated experimental reactors
J. Solis-Rodarte, TRAC-BF1/NEM stability methodology for
M. Cecenias-Falcon, K.N. Ivanov, BWR core wide and regional stability analysis
A.J. Baratta and R.M. Edwards
G. Vladuca, M. Sin and Neutron cross-sections of 7°5U in the energy
C.C. Negoita range 0.01—5.5 MeV
K.H. Bae, H.S. Lim, Design options for the safety injection
J.H. Song, S.K. Sim and system of Korean next generation reactor
J.K. Park
V. Gopalakrishnan Temperature dependence of unshielded cross-
sections in multigroup cross-section sets
A. Yamamoto and Effect of core calculation models on opti-
T. Kimoto mum cycle length analyses of pressurized
water reactors
NUMBER 12
H. Fu, J. Solis-Rodarte and 1051 TRAC-BF1I/NEM Modeling and results of
K.N. Ivanov OECD/NEA BWR core transient benchmarks
W. Hwang, B.-O. Lee and Recent improvements in modelling fission
Y.J. Kim gas release and rod deformation on metallic
fuel in LMR
W.T. Hwang, M.H. Han and A methodology for determining optimal
G. Cho durations for the use of contaminated crops
as fodder following a nuclear accident using
a dynamic food-chain model
J.L. Muiioz-Cobo, R.B. Perez, A stochastic transport theory of neutron and
T.E. Valentine, Y. Rugama and photon coupled fields: neutron and photon
J.T. Mihalezo counting statistics in nuclear assemblies
Xx Volume contents
V. Gressier, D.G. Naberejnev and 1115 The impact of the harmonic crystal model on
C. Mounier the neutron resonance parameters of 7*’Np
K. Ishitani and Y. Yamane 1131 Estimation of fuel concentration distribution
and subcriticality by using “‘pattern matching”
method
Technical note
K. Ryu and H. Sekimoto A possibility of highly efficient uranium
utilization with a pebble bed fast reactor
NUMBER 13
A. Gandini, M. Salvatores and 1147 Coupling of reactor power with accelerator
I. Slessarev current in ADS systems
R. Sanchez On the singular structure of the uncollided
and first-collided components of the Green’s
function
G. Vladuca and A. Tudora High accuracy average prompt fission neu-
tron multiplicity description in the improved
Los Alamos model
Y. Kitamura, T. Misawa, General formulae for the Feynman-o
H. Unesaki and S. Shiroya method with the bunching technique
R.D.M. Garcia An analysis of the source-function integra-
tion technique for postprocessing Py angular
fluxes
C.H. Pyeon, Y. Yamane, Higher order perturbation calculation with
T. Misawa and S. Shiroya higher mode eigenfunctions in homogeneous
system
Technical note
H. Yapici, S.O. Akansu Neutronic analysis of a moderated (D, T)
and V. Ozceyhan fusion driven hybrid blanket
Volume contents
NUMBER 14
S.B. Degweker 1245 Some variants of the Feynman alpha method
in critical and accelerator driven sub critical
systems
H.-J. Cho, K. Kobayashi, Measurement of neutron total cross-sections
S. Yamamoto, Y. Fujita, Y. Lee, of Dy and Hf in the energy region from
G. Kim, I.S. Ko, M.-H. Cho, 0.002 to 100 keV
W. Namkung and S.K. Ko
W.-J. Cho, J.-O. Lee Influence of temperature elevation on the
and C.-H. Kang sealing performance of a potential buffer
material for a high-level radioactive waste
repository
N. Zavaljevski and A. Shapiro A Markov chain Monte Carlo inverse
procedure for radioactive contaminant
transport in fractured rock: 1. Forward
model
N. Zavaljevski and A. Shapiro A Markov chain Monte Carlo inverse
procedure for radioactive contaminant
transport in fractured rock: 2. Inverse model
Technical notes
D.N. Ziabletsev and K.N. Ivanov Improved verification methodology for
TRAC-PFI/NEM using NEA/OECD core
transient benchmarks
A.H. El-Kateb, R.A.M. Rizk Determination of atomic cross-sections and
and A.M. Abdul-Kader effective atomic numbers for some alloys
NUMBER 15
J.L. Munoz-Cobo, O. Rosello, 1345 Coupling of density wave oscillations in
R. Miro, A. Escriva, D. Ginestar parallel channels with high order modal
and G. Verda kinetics: application to BWR out of phase
oscillations
J.-S. Cheong An analytical prediction on the pump-
induced pressure pulsation in a pressurized
water reactor
XII Volume contents
I. Pazsit and V. Arzhanov 1385 Linear reactor kinetics and neutron noise in
systems with fluctuating boundaries
W.I. Ko, H.D. Kim, M.S. Yang, Electrical circuit model for quantifying the
H.S. Park and K.J. Lee proliferation resistance of nuclear fuel cycles
Technical note
A.M. El-Messiry Reactivity accidents analysis during natural
core cooling operation of ETRR-2
NUMBER 16
S. Perov, E. Altstadt 144] Vibration analysis of the pressure vessel
and M. Werner internals of WWER-1000 type reactors with
consideration of fluid—structure interaction
J.H. Kim and P.H. Seong A methodology for the quantitative evalua-
tion of NPP fault diagnostic systems’
dynamic aspects
M.A. Atalay Milne problem for linearly anisotropic scat-
tering and a specularly reflecting boundary
H. van Dam Self-stabilizing criticality waves
F. Mattioda, P. Ravetto Effective delayed neutron fraction for fluid-
and G. Ritter fuel systems
M.M.R. Williams Book reviews
NUMBER 17
1535 Memories of Ivan Kuscer 1918—2000
P.E. Labeau 1543 A variational principle in probabilistic
dynamics
M. Marseguerra and E. Zio System unavailability calculations in biased
Monte Carlo simulation: a possible pitfall