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Number 1

Table of Contents
Comments on “An Assessment of Steam-Explosion-Induced Containment Failure. Parts I–IV” (J. Hopenfeld)
Response to “Comments on ‘An Assessment of Steam-Explosion-Induced Containment Failure. Parts I–IV’” (T.G. Theofanous)
Comments on Fuel-Coolant Premixing Modeling (D. F. Fletcher, A. Thyagaraja)
Response to “Comments on Fuel-Coolant Premixing Modeling” (T. G. Theofanous, W. H. Amarasooriya)
Response to “Comments on Fuel-Coolant Premixing Modeling” (Michael L. Corradini)
Response to “Comments on Fuel-Coolant Premixing Modeling” (T. G. Theofanous)
Comments on the Fuel-Coolant Premixing Debate (M. F. Young)
Response to “Comments on the Fuel-Coolant Premixing Debate” (T. G. Theofanous)

Angular Fokker-Planck Decomposition and Representation Techniques
Mark Landesman, J. E. Morel
Nuclear Science and Engineering | Volume 103 | Number 1 | September 1989 | Pages 1-11
Technical Paper | doi.org/10.13182/NSE89-A23655
Advanced Methods Comparisons of Reaction Rates in the Purdue Fast Breeder Blanket Facility
R. N. Hill, K. O. Ott
Nuclear Science and Engineering | Volume 103 | Number 1 | September 1989 | Pages 12-24
Technical Paper | doi.org/10.13182/NSE89-A23656
Directional Effects in Transitional Resonance Spectra and Group Constants
R. N. Hill, K. O. Ott, J. D. Rhodes
Nuclear Science and Engineering | Volume 103 | Number 1 | September 1989 | Pages 25-36
Technical Paper | doi.org/10.13182/NSE89-A23657
The Interaction of Fast Neutrons with Beryllium
M. Sugimoto, P. T. Guenther, J. E. Lynn, A. B. Smith, J. F. Whalen
Nuclear Science and Engineering | Volume 103 | Number 1 | September 1989 | Pages 37-45
Technical Paper | doi.org/10.13182/NSE89-A23658
Experiment and Analysis of Neutron Spectra in a Concrete Assembly Bombarded by 14-MeV Neutrons
Koji Oishi, Yujiro Ikeda, Hiroshi Maekawa, Tomoo Nakamura
Nuclear Science and Engineering | Volume 103 | Number 1 | September 1989 | Pages 46-58
Technical Paper | doi.org/10.13182/NSE89-A23659
On the Liner Failure Potential in MARK-1 Boiling Water Reactors
M. S. Kazimi
Nuclear Science and Engineering | Volume 103 | Number 1 | September 1989 | Pages 59-69
Technical Paper | doi.org/10.13182/NSE89-A23660
Yassin A. Hassan
Post Critical Heat Transfer Predictions Using a Modified RELAP5/MOD2 Computer Code
Nuclear Science and Engineering | Volume 103 | Number 1 | September 1989 | Pages 70-80
Technical Paper | doi.org/10.13182/NSE89-A23661
Probabilistic Methods for Evaluating Operational Transient Margins and Uncertainties
R. S. May, J. M. Sorensen, R. E. Engel
Nuclear Science and Engineering | Volume 103 | Number 1 | September 1989 | Pages 81-93
Technical Paper | doi.org/10.13182/NSE89-A23662
On the Numerical Solution of the Point Reactor Kinetics Equations by Generalized Runge-Kutta Methods
J. Sánchez
Nuclear Science and Engineering | Volume 103 | Number 1 | September 1989 | Pages 94-99
Technical Note | doi.org/10.13182/NSE89-A23663

Number 2

Table of Contents

A New Resonance Region Evaluation of Neutron Cross Sections for ²³⁵U
G. de Saussure, L. C. Leal, R. B. Perez, N. M. Larson, M. S. Moore
Nuclear Science and Engineering | Volume 103 | Number 2 | October 1989 | Pages 109-118
Technical Paper | doi.org/10.13182/NSE89-A28500
Evaluation of the Unresolved Resonance Range of ²³⁸U
F.H. Fröhner
Nuclear Science and Engineering | Volume 103 | Number 2 | October 1989 | Pages 119-128
Technical Paper | doi.org/10.13182/NSE89-A28501
Delayed Neutron Data and Group Parameters for 43 Fissioning Systems
M. C. Brady, T. R. England
Nuclear Science and Engineering | Volume 103 | Number 2 | October 1989 | Pages 129-149
Technical Paper | doi.org/10.13182/NSE103-129
Analysis and Results of a Hydrogen-Moderated Isotope Production Assembly in the Fast Flux Test Facility
D. W. Wootan, J. A. Rawlins, L. L. Carter, H. R. Brager, R. E. Schenter
Nuclear Science and Engineering | Volume 103 | Number 2 | October 1989 | Pages 150-156
Technical Paper | doi.org/10.13182/NSE89-A28503
Prediction Uncertainty Evaluation Methods of Core Performance Parameters in Large Liquid-Metal Fast Breeder Reactors
Toshikazu Takeda, Akira Yoshimura, Takanobu Kamei, Keisho Shirakata
Nuclear Science and Engineering | Volume 103 | Number 2 | October 1989 | Pages 157-165
Technical Paper | doi.org/10.13182/NSE89-1
A Study of High-Burnup and Long-Operating Cycle Core Concepts for Large Liquid-Metal Fast Breeder Reactors
Yoshio Watari
Nuclear Science and Engineering | Volume 103 | Number 2 | October 1989 | Pages 166-181
Technical Paper | doi.org/10.13182/NSE89-A28505
Trends Versus Reactor Size of Passive Reactivity Shutdown and Control Performance
David C. Wade, Edward K. Fujita
Nuclear Science and Engineering | Volume 103 | Number 2 | October 1989 | Pages 182-195
Technical Paper | doi.org/10.13182/NSE89-6
Critical Experiment Tests of Bowing and Expansion Reactivity Calculations for Liquid-Metal-Cooled Fast Reactors
R. W. Schaefer
Nuclear Science and Engineering | Volume 103 | Number 2 | October 1989 | Pages 196-209
Technical Paper | doi.org/10.13182/NSE89-5
An Analysis of Gamma-Ray Energy Deposition in a Heterogeneous Liquid-Metal Fast Breeder Reactor
Masatoshi Kawashima, Tadashi Yoshida, Tsugio Yokoyama, Toshihisa Yamamoto
Nuclear Science and Engineering | Volume 103 | Number 2 | October 1989 | Pages 210-218
Technical Note | doi.org/10.13182/NSE89-A28508

Number 3

Table of Contents

Experiments and Analysis for an Axially Heterogeneous Liquid-Metal Reactor Assembly at the Zero-Power Physics Reactor
S. B. Brumbach, P. J. Collins
Nuclear Science and Engineering | Volume 103 | Number 3 | November 1989 | Pages 219-236
Technical Paper | doi.org/10.13182/NSE89-2
Compact Nuclear Power Source Critical Experiments and Analysis
Gordon E. Hansen, Ronald G. Palmer
Nuclear Science and Engineering | Volume 103 | Number 3 | November 1989 | Pages 237-246
Technical Paper | doi.org/10.13182/NSE89-A23674
Analysis of PROTEUS Phase II Experiments Performed Using the AARE Modular System and JEF-Based Libraries
S. Pelloni, J. Stepanek, P. Vontobel
Nuclear Science and Engineering | Volume 103 | Number 3 | November 1989 | Pages 247-253
Technical Paper | doi.org/10.13182/NSE89-A23675
A Simple Calculation of Control Assembly Effectiveness in a Liquid-Metal Fast Breeder Reactor by a Transport-Diffusion Equivalence Method
P. Benoist, M. Carta, G. Palmiotti, M. Salvatores, J. Tullett
Nuclear Science and Engineering | Volume 103 | Number 3 | November 1989 | Pages 254-264
Technical Paper | doi.org/10.13182/NSE89-A23676
Monte Carlo Calculations of the Neutron Environment Produced by the White Sands Missile Range Fast Burst Reactor
T. M. Flanders, M. H. Sparks
Nuclear Science and Engineering | Volume 103 | Number 3 | November 1989 | Pages 265-275
Technical Paper | doi.org/10.13182/NSE89-A23677
Flux-Adjoint Weighted Few-Group Cross Sections Used for Reactor Transient Analysis
Myung H. Kim, A. F. Henry
Nuclear Science and Engineering | Volume 103 | Number 3 | November 1989 | Pages 276-282
Technical Paper | doi.org/10.13182/NSE89-A23678
The Physical Basis for the Void Reactivity Effect and Its Dependence on Absorber Rod Configuration in the RBMK-1000
P. S. W. Chan, A. R. Dastur
Nuclear Science and Engineering | Volume 103 | Number 3 | November 1989 | Pages 283-288
Technical Paper | doi.org/10.13182/NSE89-A23679
The Sensitivity of Positive Scram Reactivity to Neutronic Decoupling in the RBMK-1000
P. S. W. Chan, A. R. Dastur
Nuclear Science and Engineering | Volume 103 | Number 3 | November 1989 | Pages 289-293
Technical Paper | doi.org/10.13182/NSE89-A23680
Multifrequency Binary Sequence Testing at the Fast Flux Test Facility
R. A. Harris, Yau Ming Chien, D. A. Clark, W. M. Ritter, R. A. Bennett, R. B. Rothrock, Jr., R. A. Sevenich
Nuclear Science and Engineering | Volume 103 | Number 3 | November 1989 | Pages 294-301
Technical Paper | doi.org/10.13182/NSE89-A23681
The TINTE Modular Code System for Computational Simulation of Transient Processes in the Primary Circuit of a Pebble-Bed High-Temperature Gas-Cooled Reactor
H. Gerwin, W. Scherer, E. Teuchert
Nuclear Science and Engineering | Volume 103 | Number 3 | November 1989 | Pages 302-312
Technical Paper | doi.org/10.13182/NSE89-A23682
TU Electric Reactor Model Verification: Power Reactor Benchmark
C. E. Willingham, M. R. Killgore
Nuclear Science and Engineering | Volume 103 | Number 3 | November 1989 | Pages 313-319
Technical Paper | doi.org/10.13182/NSE89-A23683

Number 4

Table of Contents

The Optimum Fuel and Power Distribution for a Pressurized Water Reactor Burnup Cycle
J. A. Stillman, Y. A. Chao, T. J. Downar
Nuclear Science and Engineering | Volume 103 | Number 4 | December 1989 | Pages 321-333
Technical Paper | doi.org/10.13182/NSE89-A23685
SIMULATE-3 Pin Power Reconstruction: Methodology and Benchmarking
K. R. Rempe, K. S. Smith, A. F. Henry
Nuclear Science and Engineering | Volume 103 | Number 4 | December 1989 | Pages 334-342
Technical Paper | doi.org/10.13182/NSE89-A23686
A Nodal Expansion Method with Spatially Coupled Effects Incorporated into the Transverse Leakage Approximation
Moon H. Chang, Kap S. Moon, Jae M. Noh, Si H. Kim
Nuclear Science and Engineering | Volume 103 | Number 4 | December 1989 | Pages 343-350
Technical Paper | doi.org/10.13182/NSE89-A23687
Neutronic Analysis Code for Fuel Assembly Using a Vectorized Monte Carlo Method
Yuuichi Morimoto, Hiromi Maruyama, Kazuya Ishii, Motoo Aoyama
Nuclear Science and Engineering | Volume 103 | Number 4 | December 1989 | Pages 351-358
Technical Paper | doi.org/10.13182/NSE89-A23688
Environment-Insensitive Equivalent Diffusion Theory Group Constants for Pressurized Water Reactor Radial Reflector Regions
E. Z. Müller
Nuclear Science and Engineering | Volume 103 | Number 4 | December 1989 | Pages 359-376
Technical Paper | doi.org/10.13182/NSE89-A23689
Three-Dimensional Nodal Diffusion and Transport Theory Methods for Hexagonal-z Geometry
M. R. Wagner
Nuclear Science and Engineering | Volume 103 | Number 4 | December 1989 | Pages 377-391
Technical Paper | doi.org/10.13182/NSE89-A23690
ILLICO: A Nodal Neutron Diffusion Method for Modern Computer Architectures
Hrabri L. Rajic, Abderrafi M. Ougouag
Nuclear Science and Engineering | Volume 103 | Number 4 | December 1989 | Pages 392-408
Technical Paper | doi.org/10.13182/NSE89-A23691
A Spatial Kinetics Computational Method for Large Fast Reactors
J. K. Fletcher
Nuclear Science and Engineering | Volume 103 | Number 4 | December 1989 | Pages 409-414
Technical Paper | doi.org/10.13182/NSE89-A23692
Theory and Performance of the Fast-Running Multidimensional Pressurized Water Reactor Kinetics Code, SPNOVA-K
Y. A. Chao, P. Huang
Nuclear Science and Engineering | Volume 103 | Number 4 | December 1989 | Pages 415-419
Technical Paper | doi.org/10.13182/NSE89-A23693
Verification of the SIMULATE-3 Pin Power Distribution Calculation
A. S. DiGiovine, J. P. Gorski, M. A. Tremblay
Nuclear Science and Engineering | Volume 103 | Number 4 | December 1989 | Pages 420-426
Technical Note | doi.org/10.13182/NSE89-A23694