Annals of Nuclear Energy 2003: Vol 30 Table of Contents

10 Pages·2003·2.3 MB·English

LIST OF CONTENTS
NUMBER I
G.J. Wu and R. Roy l A new characteristics algorithm for 3D transport
calculations
M.M.R. Williams 17 The probability density function of the multi-
plication factor due to small, random displace-
ments of fissile spheres
A. Erdogan and M. Gegkinli A PWR reload optimisation code (YCore) using
artificial neural networks and genetic algorithms
G.C. Bakos Heat generation and corresponding energy saving
in nuclear reactor shielding facilities due to y-rays
energy variation
M. Boroushaki, M.B. Ghofrani, C. Lucas An intelligent nuclear reactor core controller for
and M.J. Yazdanpanah load following operations, using recurrent neural
networks and fuzzy systems
G.I. Balogun Automating some analysis and design calcula-
tions of miniature neutron source reactors at
CERT (1)
A. Kereszturi, Gy. Hegyi, Cs. Marazcy, Development and validation of the three-dimen-
I. Panka, M. Telbisz, I. Trosztel and sional dynamic code—KIKO3D
Cs. Hegediis
Technical notes
S. Mark and Y. Ronen Some aspects of °Li as a nuclear fuel for aneu-
tronic fusion
Deng Li, Xie Zhongsheng and Li Shu Monte Carlo transport and burnup calculation
NUMBER 2
S. Carlos, D. Ginestar, S. Martorell and Parameter estimation in thermalhydraulic models
V. Serradell using the multidirectional search method
H. Yapici and M. Ubeyli Power flattening in Prometheus breeder reactor
using nuclear fuel and waste actinide
A. El-Sayed Abdo, M.A. El-Sarraf and Utilization of ilmenite/epoxy composite for
F.A. Gaber neutrons and gamma rays attenuation
N.K. Todorova and K.N. Ivanov Investigation of spatial coupling aspects for
coupled code application in PWR safety analysis
II]
IV Volume contents
R.S. Modak and A. Gupta A simple scheme for the direct evaluation of time-
eigenvalues of neutron transport equation
S.B. Degweker Reactor noise in accelerator driven systems
Technical note
S. Sahin, $. Yalgin, H.M. Sahin and Neutronic investigation of a hybrid version of the
M. Ubeyli ARIES-RS fusion reactor
NUMBER 3
R.M. Cotta, M.J. Ungs and 261 Contaminant transport in finite fractured porous
M.D. Mikhailov medium: integral transforms and lumped-differential
formulations
C. Hellwig, U. Kasemeyer, Interpretation of experimental results from
G. Ledergerber, B.-H. Lee, Y.-W. Lee moderate-power in-pile testing of a Pu—Er—Zr—
and R. Chawla oxide inert matrix fuel
M. Constantin, D. Gugiu and Void reactivity and pin power calculation for a
V. Balaceanu CANDU cell using the SEU-43 fuel bundle
E. Nichita and F. Rahnema A heterogeneous finite element method in diffusion
theory
G.Th. Analytis Implementation of the renormalization group
(RNG) k-e turbulence model in GOTHIC/6.lb:
solution methods and assessment
NUMBER 4
389 Editorial
A. El-Sayed Abdo, M.A.M. Ali and 391 Influence of magnetite and boron carbide on
M.R. Ismail radiation attenuation of cement—fiber/composite
C. Liao and Z. Xie The coupled kinetic and thermal-hydraulic three
dimensional code system NLSANMT/COBRA-
IV for PWR core transient analysis
H. Yapici Study on transmutation of minor actinides dis-
charged from high burn-up PWR-MOX spent
fuel in the force-free helical reactor
S.M. Basha, R.K. Singh, R. Patnaik, Predictions of ultimate load capacity for pre-
S. Ramanujam, H.S. Kushwaha and stressed concrete containment vessel model with
V. Venkat Raj BARC finite element code ULCA
M. Marseguerra, E. Zio, E. Patelli, Modeling the effects of the engineered barriers of
F. Giacobbo, P. Risoluti, G. Ventura and a radioactive waste repository by Monte Carlo
G. Mingrone simulation
Volume contents
Technical notes
T. Obara, T. Miura, Y. Fujita, Y. Ando 497 Preliminary study of the removal of polonium
and H. Sekimoto contamination by neutron-irradiated lead-bis-
muth eutectic
G. Joseph and S. Chandrasekaran Criticality safety of fuel pins in a post irradiation
examination cell
Corrigendum
NUMBER 5
M.M.R. Williams 513 The flat flux problem in one-speed neutron transport
theory
W.J.M. de Kruijf and 549 On the average chord length in reactor physics
J.L. Kloosterman
C.M.N.A. Pereira and 555 Coarse-grained parallel genetic algorithm applied
C.M.F. Lapa to a nuclear reactor core design optimization
problem
G.J. Wu and R. Roy Acceleration techniques for trajectory-based
deterministic 3D transport solvers
E. Valero and I.E. Parra Reactor pressure analysis at the initial stage of a
loss of coolant accident
E.F. Faria and C. Pereira Nuclear fuel loading pattern optimisation using a
neural network
Technical note
T. Hazama Practical correction of dead time effect in variance-
to-mean ratio measurement
NUMBER 6
633 Determination of the optimal plutonium fraction
in transuranium discharged from pressured water
reactor (PWR) spent fuel for a flat fission power
generation in the force-free helical reactor
(FFHR) along the transmutation period
Y.P. Mahlers Numerical study of optimal equilibrium cycles for
pressurized water reactors
S. Sahin, $. Yalgin, H.M. Sahin and Neutronics analysis of HYLIFE-II blanket for
M. Ubeyli fissile fuel breeding in an inertial fusion energy
reactor
VI Volume contents
M. Andreani, F. Putz, T.V. Dury, 685 On the application of field codes to the analysis of
C. Gjerloev and B.L. Smith gas mixing in large volumes: case studies using
CFX and GOTHIC
M.E. Montesinos, J.L. Munoz-Cobo Hilbert-Huang analysis of BWR neutron detector
and C. Perez signals: application to DR calculation and to
corrupted signal analysis
Technical notes
A.D. Caldeira The WIMSD library in the ENDF/B format
H. Arab-Alibeik and S. Setayeshi An adaptive-cost-function optimal controller
design for a PWR nuclear reactor
NUMBER 7
J. Navarro-Esbri, D. Ginestar and 755 BWR stability monitoring using adaptive methods
G. Verdu
A. Lombardi Costa and C. Pereira 775 A neutronic evaluation of the Americium and
Neptunium co-insertion in UO) fuel
D. Pankratov, S. Ignatiev, D. Ridikas 785 Estimation of 7!°Po losses from the solid 7°°Bi
and A. Letourneau target irradiated in a thermal neutron flux
T.K. Thiyagarajan, S. Ganesan, 793 Generation of handbook of multi-group cross
V. Jagannathan and R. Karthikeyan sections of WIMS-D libraries by using the
XnWlup?2.0 software
T. Takeda, Y. Tachibana, T. Iyoku and Heat removal performance of auxiliary cooling
S. Takenaka system for the high temperature engineering test
reactor during scrams
N.M. Mirza, M. Rafique, M.J. Hyder Computer simulation of corrosion product activity
and S.M. Mirza in primary coolants of a typical PWR under flow
rate transients and linearly accelerating corrosion
A.C.F. Guimaraes A new methodology for the study of FAC pheno-
menon based on a fuzzy rule system
Technical notes
J.S. Cassell and M.M.R. Williams A note on the behaviour of a two group minimum
critical mass problem as the slowing down length
tends to zero
M. Segev and G. Raitses The use of flux ratios to homogenize squared
absorber cells
NUMBER 8
R. Sayareh, M. Ghannadi Maragheh and 883 Theoretical calculations for the production of
M. Shamsaie °°Mo using natural uranium in Iran
Volume contents Vil
Y. Kitamura, H. Yamauchi and 897 Derivation of variance-to-mean formula for periodic
Y. Yamane and pulsed neutron source
F. Jatuff, P. Grimm, R. van Geemert, 911 Validation of axial pin power distributions in a
M. Murphy, R. Seiler, R. Brogli, 10x10 BWR assembly across an enrichment
F. Giust, R. Jacot-Guillarmod, boundary under full-density water moderation
T. Williams, S. Helmersson and conditions
R. Chawla
Technical notes
G. Espinosa-Paredes and Scope and limitations of the structural and
J. Alvarez-Ramirez dynamic analysis of a thermal—hydraulic model
M.M.R. Williams The effect of random geometry on the criticality of
a multiplying system V: influence of the reflector
Correspondence
L.E. Weaver Nuclear power holds new promise in the United
States
NUMBER 9
M. Marseguerra and E. Zio 953 Model-free fuzzy tracking control of a nuclear
reactor
S. Pelloni 983 Sensitivities of the proton beam current resulting
from variations in the source term for a Pb—Bi
cooled accelerator driven system with a Pb-—Bi
target
I.A. Reyhancan Measurements and statistical model calculations
of activation cross sections for !?F(n,p)!?O reac-
tion between 13.6 and 14.9 MeV neutron energies
J.S. Cassell and M.M.R. Williams An integral equation arising in neutron transport
theory
NUMBER 10
H.-G. Willschiitz, E. Altstadt, 1033 Simulation of creep tests with French or German
B.R. Sehgal and F.-P. Weiss RPV-steel and investigation of a RPV-support
against failure
C. Notari Neutronic optimization of PHWR fuel
M.M.R. Williams Some further considerations on Goertzel’s minimum
critical mass problem
G. Ilas and F. Rahnema A Monte Carlo based nodal diffusion model for
criticality analysis of spent fuel storage lattices
Vill Volume contents
Technical notes
Y. Ronen The 2Z-—N correlation related to the total delayed
neutron yield of 77Am
A.E. Aboanber and Y.M. Hamada Power series solution (PWS) of nuclear reactor
dynamics with Newtonian temperature feedback
NUMBER 11
G. Kim, R. Machrafi, H. Ahmed, D. Son, 1123 Measurement of neutron total cross-section of Dy
V. Skoy, Y.S. Lee, M.-H. Cho, H. Kang, at Pohang Neutron Facility
LS. Ko, W. Namkung, J.H. Chang and
K.J. Yoo
A.O. Goltsev, V.D. Davidenko, The influence of a non-uniform radial tempera-
V.F. Tsibulsky and A.A. Lekomtsev ture distribution in the fuel on the results of
calculation of transients
V.M. Maslov, Yu.V. Porodzinskij, Evaluation of resolved and unresolved resonance
N.A. Tetereva, M. Baba and range of 232-U
A. Hasegawa
K. Devan, G. Pandikumar, M. Alagan, Effects of cross section sets and quadrature orders
V. Gopalakrishnan and on neutron fluxes and on secondary *4Na activa-
P. Mohanakrishnan tion rate of a pool type 500 MWe FBR
Y.S. Kim, S.H. Jeon and C.H. Jung Fluorination reaction of uranium dioxide in
CF,/O,/N> r.f. plasma
J. Lewins Book review
NUMBER 12
J.L. Francois, C. Martin-del-Campo, 1213 A practical optimization procedure for radial
R. Francois and L.B. Morales BWR fuel lattice design using tabu search with a
multiobjective function
M.C. Song and K.J. Lee The evaluation of radioactive corrosion product
at PWR as change of primary coolant chemistry
for long-term fuel cycle
M.O. Giménez, M.A. Schlamp and Sensitivity analysis of the aerosols transport
F.R.A. Lima equation
F. Watanabe and H. Konno Space-dependency analysis of amplitude and
decay ratio based on Forsmark noise data: new
approach to contraction of space-dependent
information on reactor stability
S.A. El-Wakil, A.R. Degheidy and Time-dependent neutron transport in a semi-
M. Sallah infinite random medium
Volume contents IX
T.Y. Song and N.I. Tak 1297 Optimal design of HYPER target system based
on the thermal and structural analysis of Pb—Bi
spallation target and beam window
NUMBER 13
M. Ishii, X. Sun and S. Kim 1309 Modeling strategy of the source and sink terms in
the two-group interfacial area transport equation
J.S. Cassell and M.M.R. Williams 1333 An application of the Wiener-Hopf method to
the one-speed flat-flux problem in a half-space
S. Mittag, P.T. Petkov and 1347 Discontinuity factors for non-multiplying
U. Grundmann material in two-dimensional hexagonal reactor
geometry
A.C. de A. Mol, A.S. Martinez and A neural model for transient identification in
R. Schirru dynamic processes with ‘“‘don’t know” response
Letters to the Editor
A. Gandini On the correct physical approach for ADS analysis
J.D. Lewins On Gandini’s defence of generalised perturbation
theory
NUMBER 14
A. Mazzolo, B. Roesslinger and 1391 On the properties of the chord length distribution,
C.M. Diop from integral geometry to reactor physics
A.J. Arul, C.S. Kumar, S. Marimuthu 1401 The power law character of off-site power failures
and O.P. Singh
A. Yamamoto and S. Shiroya 1409 Study on neutronics design of accelerator driven
subcritical reactor as future neutron source, part
1: static characteristics
A. Yamamoto and S. Shiroya Study on neutronics design of accelerator driven
subcritical reactor as future neutron source, part
2: kinetic characteristics
M. Marseguerra, E. Zio and Model parameters estimation and sensitivity by
L. Podofillini genetic algorithms
W.T. Hwang, E.H. Kim, K.S. Suh, Influence of predictive contamination to agri-
H.J. Jeong, M.H. Han and C.W. Lee cultural products due to dry and wet processes
during an accidental release of radionuclides
T.L. Teng, Y.A. Chu, F.A. Chang, The dynamic analysis of nuclear waste cask under
H.S. Chin and M.C. Lee impact loading
X Volume contents
Technical note
H.-R. Kim, S.-K. Kim, B.-K. Seo, 1487 The preliminary 3D dynamic simulation on the
K.-W. Lee and J.-H. Park RSR dismantling process of the KRR-1&2
NUMBER 15
H. van Dam 1495 Flux distributions in stable criticality waves
W. Ambrosini and J.C. Ferreri 1505 Prediction of stability of one-dimensional natural
circulation with a low diffusion numerical scheme
I.A. Reyhancan, M. Bostan, 1539 Measurements ofi someric cross sections for (n,2n)
A. Durusoy, A. Elmali, A. Baykal reaction on !4°Ce, '47Nd and !*4Sm_ isotopes
and Y. Ozbir around 14 MeV
J. Kwon, S.C. Kwon and J.-H. Hong Prediction of radiation hardening in _ reactor
pressure vessel steel based on a theoretical model
G.-C. Lee and S.H. Chang Radial basis function networks applied to DNBR
calculation in digital core protection systems
R. Plukiene and D. Ridikas Modelling of HTRs with Monte Carlo: from a
homogeneous to an exact heterogeneous core
with microparticles
Technical notes
1.B. Plecas Effect of curing time on the fraction of Cs!?’ from
cement matrix
M. Zaker Effective delayed neutron fraction and prompt
neutron lifetime of Tehran research reactor
M.M.R. Williams Book review and announcement
S. Pelloni Erratum
NUMBER 16
X. Sun, M. Ishii and Joseph M. Kelly 1601 Modified two-fluid model for the two-group
interfacial area transport equation
D. Ene 1623 Safety studies related to the spent fuel storage of
the Romanian VVR-S reactor
R. Sanchez 1645 The Moments Method for the one-group transport
and diffusion equations
C.M.N.A. Pereira and C.M.F. Lapa 1665 Parallel island genetic algorithm applied to a
nuclear power plant auxiliary feedwater system
surveillance tests policy optimization
Volume contents
Technical notes
I.S. Kim, S.W. Cheon and M.C. Kim Nuclear equipment parts classification: a functional
modeling approach
I. Slessarev and P. Bokov On potential of thermo-nuclear fusion as a
candidate for external neutron source in hybrid
systems (applied to the ““WISE” concept)
M.C. Thorne Book review
S.B. Degweker Corrigendum
NUMBER 17
A SPECIAL ISSUE IN HONOUR OF
PROFESSOR HUGO VAN DAM ON THE OCCASION
OF HIS RETIREMENT
T.H.J.J. van der Hagen 1703 Editorial: In honour of Professor Hugo van Dam
on the occasion of his retirement
M.M.R. Williams 1707 An application of the ‘end-point’ method to the
minimum critical mass problem in two group
transport theory
F. Jatuff, A. Liithi, M. Murphy, Measurement and interpretation of delayed
T. Williams and R. Chawla photoneutron effects in multizone criticals with
partial DO moderation
I. Pazsit Hugo van Dam and the dynamic adjoint function
S. Seker, E. Tiirkcan, E. Ayaz and Artificial neural networks for dynamic monitoring
B. Barutc¢u of simulated-operating parameters of high
temperature gas cooled engineering test reactor
(HTTR)
D. Lathouwers Iterative computation of time-eigenvalues of the
neutron transport equation
J.L. Kloosterman Application of boron and gadolinium burnable
poison particles in UO and PUQO) fuels in HTRs
NUMBER 18
M. Bostan, E. Giiltekin and 1821 Cross-section measurements for the ®’Mo (n,p)
I.A. Reyhancan °7™NIb reaction at the neutron energies from 13.6
to 14.9 MeV
A. Dall’Osso Introducing the migration mode method for
the solution of the space and energy dependent
diffusion equation
XII Volume contents
H. Sakane, Y. Kasugai, M. Shibata, 1847 Measurements of the (n, np+d) activation cross
H. Takeuchi and K. Kawade sections with 13.4-14.9 MeV neutrons using a
fusion neutronics source/JAERI
Y. Okano and A. Yamaguchi Numerical simulation of a free-falling liquid
sodium droplet combustion
E. Fort, G. Rimpault, J-C. Bosq, Improved performances of the fast reactor
B. Camous, V. Zammit, E. Dupont, calculational system ERANOS-ERALIBI due to
R. Jacqmin, P. Smith, D. Biron and improved a priori nuclear data and consideration
D. Verrier of additional specific integral data
Technical notes
I. Plecas Immobilization of '*7Cs and ®°Co in concrete
matrix
M. Adib, N. Habib, A. Ashry and On the use of silicon as thermal neutron filter
M. Fathalla
D. Vande Putte Book review
J.S. Cassell and M.M.R. Williams Erratum