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Volume 103

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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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.doi.org/10.13182/NSE89-A23694