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Volume 104

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Number 1

A Split-Matrix Method for the Numerical Solution of Two-Phase Flow Equations

Peter Romstedt

Nuclear Science and Engineering / Volume 104 / Number 1 / January 1990 / Pages 1-9

Technical Paper / dx.doi.org/10.13182/NSE90-A23696

Fast Three-Dimensional Core Model for Digital Control in Boiling Water Reactors

O. Lupas, D. Beraha

Nuclear Science and Engineering / Volume 104 / Number 1 / January 1990 / Pages 10-25

Technical Paper / dx.doi.org/10.13182/NSE90-A23697

Optimized Two-Dimensional S_n Transport (BISTRO)

G. Palmiotti, J. M. Rieunier, C. Gho, M. Salvatores

Nuclear Science and Engineering / Volume 104 / Number 1 / January 1990 / Pages 26-33

Technical Paper / dx.doi.org/10.13182/NSE90-1

Thermal Disadvantage Factor: An Efficient Calculation

K. M.-S. Abdullah, S. K. Loyalka

Nuclear Science and Engineering / Volume 104 / Number 1 / January 1990 / Pages 34-39

Technical Paper / dx.doi.org/10.13182/NSE90-A23699

Energy Dependence of Neutron Self-Shielding Factors in an Isolated Resonance

Maria Do Carmo Lopes, Jorge Molina Avila

Nuclear Science and Engineering / Volume 104 / Number 1 / January 1990 / Pages 40-45

Technical Paper / dx.doi.org/10.13182/NSE90-A23700

Iron and Cadmium Capture Gamma-Ray Photofission Measurements

T. G. Williamson, G. P. Lamaze, D. M. Gilliam, C. M. Eisenhauer

Nuclear Science and Engineering / Volume 104 / Number 1 / January 1990 / Pages 46-52

Technical Paper / dx.doi.org/10.13182/NSE90-A23701

Measurement of Prompt Neutron Decay Constant and Large Subcriticality by the Feynman-α Method

Tsuyoshi Misawa, Seiji Shiroya, Keiji Kanda

Nuclear Science and Engineering / Volume 104 / Number 1 / January 1990 / Pages 53-65

Technical Paper / dx.doi.org/10.13182/NSE104-53

Feasibility and Incentives for Burnup Credit in Spent-Fuel Transport Casks

Thomas L. Sanders, R. Michael Westfall

Nuclear Science and Engineering / Volume 104 / Number 1 / January 1990 / Pages 66-77

Technical Paper / dx.doi.org/10.13182/NSE90-A23703

Global Optimization and Sensitivity Analysis

Dan G. Cacuci

Nuclear Science and Engineering / Volume 104 / Number 1 / January 1990 / Pages 78-88

Technical Paper / dx.doi.org/10.13182/NSE90-A23704

Number 2

Table of Contents
Comments on “The Effect of Random Material Density on Reactor Criticality”(E. G. Sakhnovsky)
Additional Comments on “The Effect of Random Material Density on Reactor Criticality”(M. M. R. Williams)

A Synthetically Accelerated Weighted Diamond Scheme for Charged-Particle Transport Calculations

J. J. Honrubia, J. E. Morel

Nuclear Science and Engineering / Volume 104 / Number 2 / February 1990 / Pages 91-111

Technical Paper / dx.doi.org/10.13182/NSE90-A23707

A Fundamental Derivation of the Nodal Diffusion Equation and Its Variation

Hoju Moon, Samuel H. Levine

Nuclear Science and Engineering / Volume 104 / Number 2 / February 1990 / Pages 112-122

Technical Paper / dx.doi.org/10.13182/NSE90-A23708

Harmonic Analysis of Stochastic Descriptors and the Interpretation of ²⁵²Cf Neutron Source Experiments

Felix C. Difilippo

Nuclear Science and Engineering / Volume 104 / Number 2 / February 1990 / Pages 123-134

Technical Paper / dx.doi.org/10.13182/NSE90-A23709

Interpretation of Noise Coherence Function Measurements in Liquid-Metal Fast Breeder Reactor Critical Assemblies

Toshio Sanda

Nuclear Science and Engineering / Volume 104 / Number 2 / February 1990 / Pages 135-144

Technical Paper / dx.doi.org/10.13182/NSE90-A23710

A Method for Projecting Integral Measured Quantities

D. K. Wehe, J. Schmidt

Nuclear Science and Engineering / Volume 104 / Number 2 / February 1990 / Pages 145-152

Technical Paper / dx.doi.org/10.13182/NSE90-A23711

Parity Simulation of Single-Phase Thermal Hydraulics

Eduardo V. Depiante, John E. Meyer

Nuclear Science and Engineering / Volume 104 / Number 2 / February 1990 / Pages 153-168

Technical Paper / dx.doi.org/10.13182/NSE90-A23712

Two-Phase Thermal-Hydraulic Analysis Using Parity Simulation

Eduardo V. Depiante, John E. Meyer

Nuclear Science and Engineering / Volume 104 / Number 2 / February 1990 / Pages 169-182

Technical Paper / dx.doi.org/10.13182/NSE90-A23713

Some Findings in Neutron Multiplication Factor Monitoring

Pedro A. Landeyro, Tadeusz Zoltowski

Nuclear Science and Engineering / Volume 104 / Number 2 / February 1990 / Pages 183-187

Technical Note / dx.doi.org/10.13182/NSE90-A23714

Effective Cross Sections and Sources in Moving Material

B. R. Wienke, T. R. Hill

Nuclear Science and Engineering / Volume 104 / Number 2 / February 1990 / Pages 188-196

Technical Note / dx.doi.org/10.13182/NSE90-A23715

Number 3

Table of Contents

A Numerical Method for One-Group Slab-Geometry Discrete Ordinates Problems with No Spatial Truncation Error

Ricardo C. De Barros, Edward W. Larsen

Nuclear Science and Engineering / Volume 104 / Number 3 / March 1990 / Pages 199-208

Technical Paper / dx.doi.org/10.13182/NSE90-A23719

Analytic Reductions for Transmission and Leakage Probabilities in Finite Tubes and Hexahedra

G. Marleau, R. Roy, A. Hébert

Nuclear Science and Engineering / Volume 104 / Number 3 / March 1990 / Pages 209-216

Technical Paper / dx.doi.org/10.13182/NSE90-A23720

Influence of Water Density Change on the Criticality in Special Fuel Lattices

János Gadó, István Vidovszky

Nuclear Science and Engineering / Volume 104 / Number 3 / March 1990 / Pages 217-221

Technical Paper / dx.doi.org/10.13182/NSE90-A23721

A Diffusion Iterative Model for Simulation of Reactivity Devices in Pressurized Heavy Water Reactors

V. Jagannathan, R. P. Jain, Vinod Kumar, H. C. Gupta, P. D. Krishnani

Nuclear Science and Engineering / Volume 104 / Number 3 / March 1990 / Pages 222-238

Technical Paper / dx.doi.org/10.13182/NSE90-A23722

Neutron Energy Spectra in Lithium: Measurements and Calculations

R. Ofek, A. Tsechanski, A. Goldfeld, G. Shani, A. E. Profio, J. J. Wagschal

Nuclear Science and Engineering / Volume 104 / Number 3 / March 1990 / Pages 239-257

Technical Paper / dx.doi.org/10.13182/NSE90-A23723

Neutron Absorption Cross Section of ²³⁶U

R. L. Macklin, C. W. Alexander

Nuclear Science and Engineering / Volume 104 / Number 3 / March 1990 / Pages 258-270

Technical Paper / dx.doi.org/10.13182/NSE90-A23724

Activation Cross Sections of Neutron Threshold Reactions on Some Zirconium Isotopes in the 5.4- to 10.6-MeV Energy Range

M. Ibn Majah, S. M. Qaim

Nuclear Science and Engineering / Volume 104 / Number 3 / March 1990 / Pages 271-276

Technical Paper / dx.doi.org/10.13182/NSE90-A23725

Fast Neutron Capture Cross Sections of Europium

Xiang Zhengyu, Xu Haishan, Li Yexiang, Mu Yunshan, Wang Shiming, Liu Jianfeng

Nuclear Science and Engineering / Volume 104 / Number 3 / March 1990 / Pages 277-279

Technical Paper / dx.doi.org/10.13182/NSE90-A23726

Systematics and Parameterization of Continuum Angular Distributions for Application to Reactions Induced by 14-MeV Neutrons

Isao Kumabe, Yukinobu Watanabe, Yoshimitsu Nohtomi, Mitsuru Hanada

Nuclear Science and Engineering / Volume 104 / Number 3 / March 1990 / Pages 280-287

Technical Paper / dx.doi.org/10.13182/NSE90-A23727

On the Calculation of Steam Explosion Conversion Ratios from Experimental Data

Y. M. Farawila, S. I. Abdel-Khalik

Nuclear Science and Engineering / Volume 104 / Number 3 / March 1990 / Pages 288-295

Technical Note / dx.doi.org/10.13182/NSE90-A23728

Studies on the Higher Order Spatial Difference Schemes at the Interface of Two Media

V. Sundararaman

Nuclear Science and Engineering / Volume 104 / Number 3 / March 1990 / Pages 296-299

Technical Note / dx.doi.org/10.13182/NSE90-A23729

Number 4

Table of Contents
Experiment and Analysis of Neutron Spectra in a Concrete Assembly Bombarded by 14-MeV Neutrons(K. Oishi, Y. Ikeda, H. Maekawa, T. Nakamura)

A Neutron Multiplicity Counter for Plutonium Assay

N. Dytlewski, N. Ensslin, J. W. Boldeman

Nuclear Science and Engineering / Volume 104 / Number 4 / April 1990 / Pages 301-313

Technical Paper / dx.doi.org/10.13182/NSE90-A23731

Dynamic Subcriticality Measurements Using the ²⁵²Cf-Source-Driven Noise Analysis Method

J. T. Mihalczo, E. D. Blakeman, G. E. Ragan, E. B. Johnson, Y. Hachiya

Nuclear Science and Engineering / Volume 104 / Number 4 / April 1990 / Pages 314-338

Technical Paper / dx.doi.org/10.13182/NSE90-A23732

Neutron Yields from Stopping- and Near-Stopping-Length Targets for 256-MeV Protons

M. M. Meier, C. A. Goulding, G. L. Morgan, J. L. Ullmann

Nuclear Science and Engineering / Volume 104 / Number 4 / April 1990 / Pages 339-363

Technical Paper / dx.doi.org/10.13182/NSE90-A23733

A Novel Fusion Power Concept Based on Molten-Salt Technology: PACER Revisited

Charles J. Call, Ralph W. Moir

Nuclear Science and Engineering / Volume 104 / Number 4 / April 1990 / Pages 364-373

Technical Paper / dx.doi.org/10.13182/NSE90-A23734

A Quasi-Deterministic Approximation of the Monte Carlo Importance Function

Thomas E. Booth

Nuclear Science and Engineering / Volume 104 / Number 4 / April 1990 / Pages 374-384

Technical Paper / dx.doi.org/10.13182/NSE90-A23735

The Coarse Space-Energy Mesh Rebalancing Method for Neutron Diffusion Calculations in Fast Reactors

Yasuyoshi Kato, Hiroshi Urushihara

Nuclear Science and Engineering / Volume 104 / Number 4 / April 1990 / Pages 385-395

Technical Paper / dx.doi.org/10.13182/NSE90-A23736

An Analytic Method for Analyzing Prompt-Critical Reactivity Transients

J. F. Carew

Nuclear Science and Engineering / Volume 104 / Number 4 / April 1990 / Pages 396-401

Technical Paper / dx.doi.org/10.13182/NSE90-A23737

Spatial Mesh Effects on Three-Dimensional x-y-z Neutron Diffusion Calculations in Fast Breeder Reactors

Yasuyoshi Kato

Nuclear Science and Engineering / Volume 104 / Number 4 / April 1990 / Pages 402-411

Technical Note / dx.doi.org/10.13182/NSE90-A23738