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Number 1

Table of Contents

Power Reactor and Critical Experiment Heterogeneity Effects Assessment for Bias Factors Definition
M. Salvatores, M. Carta, R. Soule
Nuclear Science and Engineering | Volume 100 | Number 1 | September 1988 | Pages 1-15
Technical Paper | doi.org/10.13182/NSE88-A29009
An Approach to the Prediction of Cladding Azimuthal Temperature in a Light Water Reactor Four-Cusp Channel
Enrico Lorenzini, Marco Spiga, Mauro A. Corticelli
Nuclear Science and Engineering | Volume 100 | Number 1 | September 1988 | Pages 16-20
Technical Paper | doi.org/10.13182/NSE88-A29010
Preservation of Natural Circulation Similarity Criteria in Mathematical Models
T. K. Larson, R. A. Dimenna
Nuclear Science and Engineering | Volume 100 | Number 1 | September 1988 | Pages 21-32
Technical Paper | doi.org/10.13182/NSE88-A29011
Interpolation of Gamma-Ray Buildup Factors for Point Isotropic Source with Respect to Atomic Number
Yukio Sakamoto, Shun-ichi Tanaka, Yoshiko Harima
Nuclear Science and Engineering | Volume 100 | Number 1 | September 1988 | Pages 33-42
Technical Paper | doi.org/10.13182/NSE88-A29012
Spectrum-Averaged Cross-Section Measurement of ¹⁰³Rh(n, n′)^103mRh in the ²⁵²Cf Fission Neutron Spectrum
G.P. Lamaze, F. J. Schima, C. M. Eisenhauer, V. Spiegel
Nuclear Science and Engineering | Volume 100 | Number 1 | September 1988 | Pages 43-47
Technical Paper | doi.org/10.13182/NSE88-A29013
Neutron Scattering Cross Sections Up to 2.4 MeV for the Ground and First Two Excited States of ²³²Th
G. C. Goswami, J. J. Egan, G. H. R. Kegel, A. Mittler, E. Sheldon
Nuclear Science and Engineering | Volume 100 | Number 1 | September 1988 | Pages 48-60
Technical Paper | doi.org/10.13182/NSE88-A29014
Approximation of Precompound Effects in Hauser-Feshbach Codes for Calculating Double Differential (n, xn) Cross Sections
C. Y. Fu
Nuclear Science and Engineering | Volume 100 | Number 1 | September 1988 | Pages 61-76
Technical Paper | doi.org/10.13182/NSE88-A29015
Calculation of Recoil Spectra Resulting from Nuclear Reactions with Multiple Particle Emission
Mario Uhl
Nuclear Science and Engineering | Volume 100 | Number 1 | September 1988 | Pages 77-82
Technical Note | doi.org/10.13182/NSE88-A29016
A Model of Reactor Kinetics
A. Stanley Thompson, Bruce R. Thompson
Nuclear Science and Engineering | Volume 100 | Number 1 | September 1988 | Pages 83-88
Technical Note | doi.org/10.13182/NSE88-A29017

Number 2

Table of Contents
Comments on “An Assessment of Steam-Explosion-Induced Containment Failure. Parts I-IV” (Marshall Berman)
Response to “Comments on ’ An Assessment of Steam-Explosion-Induced Containment Failure. Parts I-IV’” by M. Berman (T. G. Theofanous)
Comments on “An Assessment of Steam-Explosion-Induced Containment Failure. Parts I-IV’ (Billy W. Marshall, Jr.)
Response to “Comments on ‘An Assessment of Steam-Explosion-lnduced Containment Failure. Parts I-IV’” by B. W. Marshall, Jr. (T. G. Theofanous)
Comments on “An Assessment of Steam-Explosion-Induced Containment Failure. Parts I-IV” (M. L. Corradini)
Response to “Comments on ‘An Assessment of Steam-Explosion-Induced Containment Failure. Parts I-IV’” by M. L. Corradini (T. G. Theofanous)

Theoretical and Numerical Examination of a Two-Phase Flow in a Diverging Nozzle
M. Wadle
Nuclear Science and Engineering | Volume 100 | Number 2 | October 1988 | Pages 89-104
Technical Paper | doi.org/10.13182/NSE88-A29019
Sensitivity/Uncertainty Analysis for Free-in-Air Tissue Kerma Due to Initial Radiation at Hiroshima and Nagasaki
R. A. Lillie, B. L. Broadhead, J. V. Pace III, D. G. Cacuci
Nuclear Science and Engineering | Volume 100 | Number 2 | October 1988 | Pages 105-124
Technical Paper | doi.org/10.13182/NSE88-A29020
Applications of the Generalized Bias Operators in Reactor Theory
Y. Navon (Fahima), Y. Ronen
Nuclear Science and Engineering | Volume 100 | Number 2 | October 1988 | Pages 125-141
Technical Paper | doi.org/10.13182/NSE88-A29021
Boundary Treatment of the Diffusion Synthetic Acceleration Method for Fixed-Source Discrete-Ordinates Problems in x-y Geometry
Dimitris Valougeorgis
Nuclear Science and Engineering | Volume 100 | Number 2 | October 1988 | Pages 142-148
Technical Paper | doi.org/10.13182/NSE88-A29022

Number 3

Table of Contents

Boundary Projection Acceleration: A New Approach to Synthetic Acceleration of Transport Calculations
Marvin L. Adams, William R. Martin
Nuclear Science and Engineering | Volume 100 | Number 3 | November 1988 | Pages 177-189
Technical Paper | doi.org/10.13182/NSE100-177
Comparison of Three Approximations to the Linear-Linear Nodal Transport Method in Weighted Diamond-Difference Form
Y. Y. Azmy
Nuclear Science and Engineering | Volume 100 | Number 3 | November 1988 | Pages 190-200
Technical Paper | doi.org/10.13182/NSE88-5
SMART Scattering Matrices for Single Collision Electron Monte Carlo Calculations
W. L. Filippone, S. Woolf
Nuclear Science and Engineering | Volume 100 | Number 3 | November 1988 | Pages 201-208
Technical Paper | doi.org/10.13182/NSE88-A29032
The S_N/Monte Carlo Response Matrix Hybrid Method
W. L. Filippone, R. E. Alcouffe
Nuclear Science and Engineering | Volume 100 | Number 3 | November 1988 | Pages 209-217
Technical Paper | doi.org/10.13182/NSE88-A29033
Mixed and Mixed-Hybrid Elements for the Diffusion Equation
F. Coulomb, C. Fedon-Magnaud
Nuclear Science and Engineering | Volume 100 | Number 3 | November 1988 | Pages 218-225
Technical Paper | doi.org/10.13182/NSE88-A29034
Parallel Multigrid Algorithms Implemented on Memory-Coupled Multiprocessors
H. Finnemann, J. Volkert
Nuclear Science and Engineering | Volume 100 | Number 3 | November 1988 | Pages 226-236
Technical Paper | doi.org/10.13182/NSE88-A29035
On the Application of Runge-Kutta Methods to Transport Calculations
Paul Nelson, James Jeffery
Nuclear Science and Engineering | Volume 100 | Number 3 | November 1988 | Pages 237-247
Technical Paper | doi.org/10.13182/NSE88-A29036
The Intelligent Random Number Technique in MCNP
Thomas E. Booth
Nuclear Science and Engineering | Volume 100 | Number 3 | November 1988 | Pages 248-254
Technical Paper | doi.org/10.13182/NSE88-A29037
Neutronics Methods for Thermal Radiative Transfer
Edward W. Larsen
Nuclear Science and Engineering | Volume 100 | Number 3 | November 1988 | Pages 255-259
Technical Paper | doi.org/10.13182/NSE88-A29038
Two-Dimensional Calculation of Neutron Flux and Power Distribution in the Fuel Assembly of a Light Water Reactor
Zhao Chunlei, Xie Zhongsheng, Yin Banghua
Nuclear Science and Engineering | Volume 100 | Number 3 | November 1988 | Pages 260-268
Technical Paper | doi.org/10.13182/NSE88-A29039
Control Rod Heterogeneity Effects in Liquid-Metal Fast Breeder Reactors: Method Developments and Experimental Validation
M. Carta, G. Granget, G.Palmiotti, M. Salvatores ,R. Soule
Nuclear Science and Engineering | Volume 100 | Number 3 | November 1988 | Pages 269-276
Technical Paper | doi.org/10.13182/NSE88-A29040
Core Design Aspects of SNR-2
Udo K. Wehmann
Nuclear Science and Engineering | Volume 100 | Number 3 | November 1988 | Pages 277-282
Technical Paper | doi.org/10.13182/NSE88-A29041
Status of Axial Heterogeneous Liquid-Metal Fast Breeder Reactor Core Design Studies and Research and Development
Hiroshi Nakagawa , Tatsutoshi Inagaki, Hirotaka Yoshimi , Keisho Shirakata, Yoshio Watari, Masao Suzuki, Kotaro Inoue, Takanobu Kamei
Nuclear Science and Engineering | Volume 100 | Number 3 | November 1988 | Pages 283-295
Technical Paper | doi.org/10.13182/NSE88-A29042
Physics Methods for Calculating Light Water Reactor Increased Performances
Cl. Vandenberg , A. Charlier
Nuclear Science and Engineering | Volume 100 | Number 3 | November 1988 | Pages 296-304
Technical Paper | doi.org/10.13182/NSE88-A29043
Validation of the Pressurized Water Reactor Core Analysis System SEANAP-86 with Measurements in Tests and Operation
C.Ahnert, J. M. Aragonés , A. Crespo, A. Labay, J. R. León, A. I. Alvarez
Nuclear Science and Engineering | Volume 100 | Number 3 | November 1988 | Pages 305-313
Technical Paper | doi.org/10.13182/NSE88-A29044
Validation of Neutronic Codes for Distorted Core Configurations with the SNEAK-12 Critical Assemblies
Georg Henneges
Nuclear Science and Engineering | Volume 100 | Number 3 | November 1988 | Pages 314-323
Technical Paper | doi.org/10.13182/NSE88-A29045
Testing and Applications of the QPANDA Nodal Model
K. S. Smith, K. R. Rempe
Nuclear Science and Engineering | Volume 100 | Number 3 | November 1988 | Pages 324-331
Technical Paper | doi.org/10.13182/NSE88-A29046
ILLICO-HO: A Self-Consistent Higher Order Coarse-Mesh Nodal Method
Abderrafi M. Ougouag , Hrabri L. Rajic
Nuclear Science and Engineering | Volume 100 | Number 3 | November 1988 | Pages 332-341
Technical Paper | doi.org/10.13182/NSE100-332
CASMO-3: New Features, Benchmarking, and Advanced Applications
Malte Edenius, Ake Ahlin
Nuclear Science and Engineering | Volume 100 | Number 3 | November 1988 | Pages 342-351
Technical Paper | doi.org/10.13182/NSE88-A29048
APOLLO II: A User-Oriented, Portable, Modular Code for Multigroup Transport Assembly Calculations
Richard Sanchez, Jacques Mondot, arko Stankovski, Antoine Cossic, Igor Zmijarevic
Nuclear Science and Engineering | Volume 100 | Number 3 | November 1988 | Pages 352-362
Technical Paper | doi.org/10.13182/NSE88-3
The DIT Nuclear Fuel Assembly Physics Design Code
Alf Jonsson
Nuclear Science and Engineering | Volume 100 | Number 3 | November 1988 | Pages 363-374
Technical Paper | doi.org/10.13182/NSE88-A29050

Number 4

Table of Contents
Liquid-Metal-Cooled Reactor Thermal-Hydraulic Calculations in the United States (F. E. Dunn, D. J. Malloy, D. Mohr)

Review of European Thermal-Hydraulic Calculational Methods for Thermal Reactors
M. A. Porracchia, M. M. Reocreux, M. C. Rousseau
Nuclear Science and Engineering | Volume 100 | Number 4 | December 1988 | Pages 375-379
Technical Paper | doi.org/10.13182/NSE88-A23569
An Implicit Method to Speed Up WCOBRA/TRAC
K. Takeuchi, M. Y. Young
Nuclear Science and Engineering | Volume 100 | Number 4 | December 1988 | Pages 380-384
Technical Paper | doi.org/10.13182/NSE88-A23570
The ARTEC Code: An Algorithm for Solving Thermal-Hydraulic Equations in Complex Geometries
R. D. Lonsdale
Nuclear Science and Engineering | Volume 100 | Number 4 | December 1988 | Pages 385-392
Technical Paper | doi.org/10.13182/NSE88-A23571
A Chaotic Attractor in a Periodically Forced Two-Phase Flow System
Rizwan-uddin, J. J. Doming
Nuclear Science and Engineering | Volume 100 | Number 4 | December 1988 | Pages 393-404
Technical Paper | doi.org/10.13182/NSE88-A23572
Parallel Algorithms for Fluid Dynamics Problems
J. S. B. Gajjar
Nuclear Science and Engineering | Volume 100 | Number 4 | December 1988 | Pages 405-413
Technical Paper | doi.org/10.13182/NSE88-A23573
A Time-Dependent Nodal-Integral Method for the Investigation of Bifurcation and Nonlinear Phenomena in Fluid Flow and Natural Convection
G. L. Wilson, R. A. Rydin, Y. Y. Azmy
Nuclear Science and Engineering | Volume 100 | Number 4 | December 1988 | Pages 414-425
Technical Paper | doi.org/10.13182/NSE88-A23574
Development of an Expert System for the Design Synthesis and Reliability Assessment
Bok Ki Min, Soon Heung Chang
Nuclear Science and Engineering | Volume 100 | Number 4 | December 1988 | Pages 426-434
Technical Paper | doi.org/10.13182/NSE88-A23575
Expert Systems for the Analysis of Transients on Nuclear Reactors: SEXTANT, A General-Purpose Physical Analyzer
N. Barbet, M. Dumas, G. Mihelich, Y. Souchet, J. B. Thomas
Nuclear Science and Engineering | Volume 100 | Number 4 | December 1988 | Pages 435-439
Technical Paper | doi.org/10.13182/NSE88-A23576
The Potential for Expert System Support in Solving the Pressurized Water Reactor Fuel Shuffling Problem
B. M. Rothleder, G. R. Poetschat, W. S. Faught, W. J. Eich
Nuclear Science and Engineering | Volume 100 | Number 4 | December 1988 | Pages 440-450
Technical Paper | doi.org/10.13182/NSE88-A23577
Analysis of a Delayed Return to Full Power Using a Three-Dimensional Simulator
A. Charlier, M. Doucet, C. Vandenberg, W. de Roovere, J. Bens
Nuclear Science and Engineering | Volume 100 | Number 4 | December 1988 | Pages 451-457
Technical Paper | doi.org/10.13182/NSE88-A23578
Multidimensional Effects in Optimal Control Analysis for Nuclear Reactors
Gregory D. Wyss, Roy A. Axford
Nuclear Science and Engineering | Volume 100 | Number 4 | December 1988 | Pages 458-466
Technical Paper | doi.org/10.13182/NSE88-A23579
Neutron Spectral Analysis of the Caorso Boiling Water Reactor Cavity and Sacrificial Shield Penetrations and Comparison with the Irradiation Experiment Results
P. Barbucci, G. Mariotti, N. Cerullo, P. Riscossa⁺ A. Cesana, M. Terrani, G. Sandrelli
Nuclear Science and Engineering | Volume 100 | Number 4 | December 1988 | Pages 467-478
Technical Paper | doi.org/10.13182/NSE88-A23580
Intercomparison of Reaction Rate and Gamma Scan Measurements and Calculation Analyses in a Pressurized Water Reactor
B. M. Rothleder
Nuclear Science and Engineering | Volume 100 | Number 4 | December 1988 | Pages 479-489
Technical Paper | doi.org/10.13182/NSE88-A23581
The Superphénix-2 Project
J. P. Marcon, H. Sztark
Nuclear Science and Engineering | Volume 100 | Number 4 | December 1988 | Pages 490-495
Technical Paper | doi.org/10.13182/NSE88-A23582
Experimental Study of the Large-Scale Axially Heterogeneous Liquid-Metal Fast Breeder Reactor at the Fast Critical Assembly —Power Distribution Measurements and Their Analyses
Susumu Iijima, Makoto Ōbu, Tamotsu Hayase, Akio Ohno, Tatsuo Nemoto, Shigeaki Okajima
Nuclear Science and Engineering | Volume 100 | Number 4 | December 1988 | Pages 496-506
Technical Paper | doi.org/10.13182/NSE88-A23583
The Integral Fast Reactor Concept: Physics of Operation and Safety
D. C. Wade, Y. I. Chang
Nuclear Science and Engineering | Volume 100 | Number 4 | December 1988 | Pages 507-524
Technical Paper | doi.org/10.13182/NSE88-2
Analyses of Reactor Physics Experiments in the Kyoto University Critical Assembly
Seiji Shiroya, Keiji Kanda, Keichiro Tsuchihashi
Nuclear Science and Engineering | Volume 100 | Number 4 | December 1988 | Pages 525-537
Technical Paper | doi.org/10.13182/NSE88-7
Analysis of Large Liquid-Metal Fast Breeder Reactor Critical Experiments by Improved Methods
Toshikazu Takeda, Hironobu Unesaki, Tamotsu Sekiya, Keisho Shirakata
Nuclear Science and Engineering | Volume 100 | Number 4 | December 1988 | Pages 538-548
Technical Paper | doi.org/10.13182/NSE88-A23586
Results and Implications of the Experimental Breeder Reactor II Inherent Safety Demonstration Tests
H. P. Planchon, G. H. Golden, J. I. Sackett, D. Mohr, L. K. Chang, E. E. Feldman, P. R. Betten
Nuclear Science and Engineering | Volume 100 | Number 4 | December 1988 | Pages 549-557
Technical Paper | doi.org/10.13182/NSE100-549