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Volume 111

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Number 1

Table of Contents

Canada Deuterium Uranium Reactor Design Optimization Using Three-Dimensional Generalized Perturbation Theory

D. Rozon, M. Beaudet

Nuclear Science and Engineering / Volume 111 / Number 1 / May 1992 / Pages 1-20

Technical Paper / dx.doi.org/10.13182/NSE92-A23919

Reconstruction of Pin Power and Burnup Characteristics from Nodal Calculations in Hexagonal-Z Geometry

W. S. Yang, P. J. Finck, H. Khalil

Nuclear Science and Engineering / Volume 111 / Number 1 / May 1992 / Pages 21-33

Technical Paper / dx.doi.org/10.13182/NSE92-A23920

A Spectral Nodal Method for One-Group X,Y-Geometry Discrete Ordinates Problems

Ricardo C. De Barros, Edward W. Larsen

Nuclear Science and Engineering / Volume 111 / Number 1 / May 1992 / Pages 34-45

Technical Paper / dx.doi.org/10.13182/NSE92-A23921

A Massively Parallel Discrete Ordinates Response Matrix Method for Neutron Transport

U. R. Hanebutte, E. E. Lewis

Nuclear Science and Engineering / Volume 111 / Number 1 / May 1992 / Pages 46-56

Technical Paper / dx.doi.org/10.13182/NSE92-A23922

An Iterative Algorithm for Solving the Multidimensional Neutron Diffusion Nodal Method Equations on Parallel Computers

Bernadette L. Kirk, Yousry Y. Azmy

Nuclear Science and Engineering / Volume 111 / Number 1 / May 1992 / Pages 57-65

Technical Paper / dx.doi.org/10.13182/NSE92-A23923

Estimation of Neutron Flux and Xenon Distributions via Observer-Based Control Theory

Young Ho Park, Nam Zin Cho

Nuclear Science and Engineering / Volume 111 / Number 1 / May 1992 / Pages 66-81

Technical Paper / dx.doi.org/10.13182/NSE92-A23924

Ex-Vessel Releases of Radionuclides During Molten Core/Concrete Interactions in Severe Light Water Reactor Accidents

Min Lee, Jan Sea Wu

Nuclear Science and Engineering / Volume 111 / Number 1 / May 1992 / Pages 82-101

Technical Paper / dx.doi.org/10.13182/NSE92-A23925

Time-Dependent Monte Carlo Calculations of the Oak Ridge Electron Linear Accelerator Target Neutron Spectrum

S. N. Cramer, F. G. Perey

Nuclear Science and Engineering / Volume 111 / Number 1 / May 1992 / Pages 102-111

Technical Paper / dx.doi.org/10.13182/NSE92-A23926

Number 2

Table of Contents

An Extension of the Rigorous Pole Representation of Cross Sections for Reactor Applications

Richard N. Hwang

Nuclear Science and Engineering / Volume 111 / Number 2 / June 1992 / Pages 113-131

Technical Paper / dx.doi.org/10.13182/NSE92-A23928

The Interaction of 1- to 20-MeV Neutrons with ²³⁸U

A. C. Merchant, P. E. Hodgson, H. R. Schelin

Nuclear Science and Engineering / Volume 111 / Number 2 / June 1992 / Pages 132-144

Technical Paper / dx.doi.org/10.13182/NSE92-A23929

Diffusion Synthetic Acceleration of Discontinuous Finite Element Transport Iterations

Marvin L. Adams, William R. Martin

Nuclear Science and Engineering / Volume 111 / Number 2 / June 1992 / Pages 145-167

Technical Paper / dx.doi.org/10.13182/NSE92-A23930

Three-Dimensional Variational Nodal Transport Methods for Cartesian, Triangular, and Hexagonal Criticality Calculations

C. B. Carrico, E. E. Lewis, G. Palmiotti

Nuclear Science and Engineering / Volume 111 / Number 2 / June 1992 / Pages 168-179

Technical Paper / dx.doi.org/10.13182/NSE92-1

Domain Decomposition of a Two-Dimensional S_n Method

Ronald Mattis, Alireza Haghighat

Nuclear Science and Engineering / Volume 111 / Number 2 / June 1992 / Pages 180-196

Technical Paper / dx.doi.org/10.13182/NSE92-A23932

Influence of Delayed Neutron Spectra on Fast Reactor Criticality

Edgar Kiefhaber

Nuclear Science and Engineering / Volume 111 / Number 2 / June 1992 / Pages 197-204

Technical Note / dx.doi.org/10.13182/NSE92-A23933

Sensitivity Theory for the Closed Nuclear Fuel Cycle

H. B. Choi, T. J. Downar

Nuclear Science and Engineering / Volume 111 / Number 2 / June 1992 / Pages 205-213

Technical Note / dx.doi.org/10.13182/NSE92-A23934

Number 3

Table of Contents
A Program for Calculating Complex Reactions of a Medium-Heavy Nucleus with Charged Particles(Chonghai Cai, Qingbiao Shen)

A Comparison of Models for Particle Transport Through Stochastic Mixtures

F.Malvagi, G. C. Pomraning

Nuclear Science and Engineering / Volume 111 / Number 3 / July 1992 / Pages 215-228

Technical Paper / dx.doi.org/10.13182/NSE92-A23936

Probabilistic Reactor Dynamics —I: The Theory of Continuous Event Trees

J. Devooght, C. Smidts

Nuclear Science and Engineering / Volume 111 / Number 3 / July 1992 / Pages 229-240

Technical Paper / dx.doi.org/10.13182/NSE92-A23937

Probabilistic Reactor Dynamics —II: A Monte Carlo Study of a Fast Reactor Transient

C. Smidts, J. Devooght

Nuclear Science and Engineering / Volume 111 / Number 3 / July 1992 / Pages 241-256

Technical Paper / dx.doi.org/10.13182/NSE92-A23938

Analysis of Cluster Geometries Using the DP1 Approximation of the J_± Technique

G. Marleau, A. Hebert

Nuclear Science and Engineering / Volume 111 / Number 3 / July 1992 / Pages 257-270

Technical Paper / dx.doi.org/10.13182/NSE92-A23939

Applied Resonance Equivalence

M. Segev

Nuclear Science and Engineering / Volume 111 / Number 3 / July 1992 / Pages 271-278

Technical Paper / dx.doi.org/10.13182/NSE91-51

Stability Improvement of the Alternating Direction Implicit Method for Two-Dimensional Space-Time Reactor Kinetics Applications

Gen-Shun Chen, John M. Christenson, Dow-Yung Yang

Nuclear Science and Engineering / Volume 111 / Number 3 / July 1992 / Pages 279-293

Technical Paper / dx.doi.org/10.13182/NSE92-A23941

Gain-Scheduled Nonlinear Control of U-Tube Steam Generator Water Level

Sunil K. Menon, Alexander G. Parlos

Nuclear Science and Engineering / Volume 111 / Number 3 / July 1992 / Pages 294-308

Technical Paper / dx.doi.org/10.13182/NSE92-A23942

Small-Angle Scattering Cross Sections of 14.8-MeV Neutrons for Iron, Nickel, and Chromium

Huiquan Qi, Hongbin Chen, Yingtang Chen, Qiankun Chen, Zhenpeng Chen, Zemin Chen

Nuclear Science and Engineering / Volume 111 / Number 3 / July 1992 / Pages 309-313

Technical Paper / dx.doi.org/10.13182/NSE92-A23943

Cross-Section Measurement for ¹⁰⁹Ag(n,2n)^,108mAg Reaction

Yongchang Wang, Junqian Yuan, Jingkang Yang, Huamin Wang, Yongqing Shui, Zhongliang Ren

Nuclear Science and Engineering / Volume 111 / Number 3 / July 1992 / Pages 314-316

Technical Paper / dx.doi.org/10.13182/NSE92-A23944

Number 4

Table of Contents
Improved Techniques of Analog and Digital Dynamic Compensation for Delayed Self-Powered Neutron Detectors(Dietrich Hoppe, Rainer Maletti)

Analytical Method for Processing Neutron Multigroup Transfer Cross Sections

R. Ofek, M. Segev

Nuclear Science and Engineering / Volume 111 / Number 4 / August 1992 / Pages 319-344

Technical Paper / dx.doi.org/10.13182/NSE92-A15482

Contributon Slowing-Down Theory

Mark L. Williams, Harish Manohara

Nuclear Science and Engineering / Volume 111 / Number 4 / August 1992 / Pages 345-367

Technical Paper / dx.doi.org/10.13182/NSE92-A15483

Product Yields of ²³⁵U, ²³⁸U, ²³⁷Np, and ²³⁹Pu by Photofission Reactions with 20-, 30-, and 60-MeV Bremsstrahlung

Takeshi Kase, Akira Yamadera, Takashi Nakamura, Seiichi Shibata, Ichiro Fujiwara

Nuclear Science and Engineering / Volume 111 / Number 4 / August 1992 / Pages 368-378

Technical Paper / dx.doi.org/10.13182/NSE92-A15484

Fission Fragment Transport Effects on Heat Transfer in Fissioning Gases

Yoichi Watanabe, Jacob Appelbaum

Nuclear Science and Engineering / Volume 111 / Number 4 / August 1992 / Pages 379-390

Technical Paper / dx.doi.org/10.13182/NSE92-A15485

Measurement of Neutron Activation Cross Sections of Energy up to 40 MeV Using Semimonoenergetic p-Be Neutrons

Yoshitomo Uwamino, Hiroshi Sugita, Yuhri Kondo, Takashi Nakamura

Nuclear Science and Engineering / Volume 111 / Number 4 / August 1992 / Pages 391-403

Technical Paper / dx.doi.org/10.13182/NSE111-391

Evaluation of the Unresolved Resonance Range of ²³⁸U 4-+n, Part II: Differential Data Tests

F. H. Fröhner

Nuclear Science and Engineering / Volume 111 / Number 4 / August 1992 / Pages 404-414

Technical Paper / dx.doi.org/10.13182/NSE92-A15487

High-Resolution Fission Cross-Section Measurements of ²³⁵U and ²³⁹Pu

L. W. Weston, J. H. Todd

Nuclear Science and Engineering / Volume 111 / Number 4 / August 1992 / Pages 415-421

Technical Paper / dx.doi.org/10.13182/NSE92-A15488

Six-Group Decomposition of Composite Delayed Neutron Spectra from ²³⁵U Fission

M. F. Villani, G. P. Couchell, M. H. Haghighi, D. J. Pullen, W. A. Schier

Nuclear Science and Engineering / Volume 111 / Number 4 / August 1992 / Pages 422-432

Technical Paper / dx.doi.org/10.13182/NSE92-A15489