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Volume 83

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Number 1

Table of Contents
Nuclear Energy(Hugh F. Henry)
Introduction to Metallurgical Thermodynamics(David O. Welch)
Approximations to Neutron Escape Probability and Dancoff Correction(Y. A. Chao, M. B. Yarbrough, A. S. Martinez)

Gravity-Driven Flow and Heat Transfer in a Spent Nuclear Fuel Storage Pool

Rodney R. Gay

Nuclear Science and Engineering / Volume 83 / Number 1 / January 1983 / Pages 1-12

Technical Paper / dx.doi.org/10.13182/NSE83-A17984

Neutron Emission Cross Sections at 25.7 MeV: ⁵¹V, ⁵⁶Fe, ⁶⁵Cu, ⁹³Nb, and ²⁰⁹Bi

A. Marcinkowski, R. W. Finlay, G. Randers-Pehrson, C. E. Brient, R. Kurup, S. Mellema, A. Meigooni, R. Tailor

Nuclear Science and Engineering / Volume 83 / Number 1 / January 1983 / Pages 13-21

Technical Paper / dx.doi.org/10.13182/NSE83-13

Measurement of the ²⁴¹Am Neutron Fission Cross Section

J. W. T. Dabbs, C. H. Johnson, C. E. Bemis, Jr.

Nuclear Science and Engineering / Volume 83 / Number 1 / January 1983 / Pages 22-36

Technical Paper / dx.doi.org/10.13182/NSE83-A17986

Correction of Multigroup Cross Sections for Resolved Resonance Interference in Mixed Absorbers

M. L. Williams

Nuclear Science and Engineering / Volume 83 / Number 1 / January 1983 / Pages 37-49

Technical Paper / dx.doi.org/10.13182/NSE83-2

Critical Experiments on Gadolinium Poisoned Cluster-Type Fuel Assemblies in Heavy Water Lattices

Toshio Wakabayashi, Isao Minatsuki

Nuclear Science and Engineering / Volume 83 / Number 1 / January 1983 / Pages 50-62

Technical Paper / dx.doi.org/10.13182/NSE83-A17988

Inverse Problem Calculations for Multigroup Diffusion Theory

R. Sanchez, N. J. McCormick

Nuclear Science and Engineering / Volume 83 / Number 1 / January 1983 / Pages 63-71

Technical Paper / dx.doi.org/10.13182/NSE83-A17989

Perturbation Theory in the Diffusion Approximation

G. C. Pomraning

Nuclear Science and Engineering / Volume 83 / Number 1 / January 1983 / Pages 72-74

Technical Paper / dx.doi.org/10.13182/NSE83-A17990

Ordinary and Generalized Eigenvectors of Low-Order S_n-Diamond-Difference Transport Operators

W. L. Filippone, R. Conversano

Nuclear Science and Engineering / Volume 83 / Number 1 / January 1983 / Pages 75-89

Technical Paper / dx.doi.org/10.13182/NSE83-A17991

On Numerical Solutions of Transport Problems in the Diffusion Limit

Edward W. Larsen

Nuclear Science and Engineering / Volume 83 / Number 1 / January 1983 / Pages 90-99

Technical Paper / dx.doi.org/10.13182/NSE83-A17992

Solving the Uncommon Nuclear Reactor Core Neutronics Problems

D. R. Vondy, T. B. Fowler

Nuclear Science and Engineering / Volume 83 / Number 1 / January 1983 / Pages 100-111

Technical Paper / dx.doi.org/10.13182/NSE83-A17993

Adjoint Sensitivity Analysis of Extremum-Type Responses in Reactor Safety

D. G. Cacuci, P. J. Maudlin, C. V. Parks

Nuclear Science and Engineering / Volume 83 / Number 1 / January 1983 / Pages 112-135

Technical Paper / dx.doi.org/10.13182/NSE83-A17994

Optimal Control for Xenon Spatial Oscillations in Load Follow of a Nuclear Reactor

Nam Zin Cho, Lawrence M. Grossman

Nuclear Science and Engineering / Volume 83 / Number 1 / January 1983 / Pages 136-148

Technical Paper / dx.doi.org/10.13182/NSE83-A17995

The Influence of Energy Group Structure and Nonlinearities on the Calculation of Xenon-Induced Flux Oscillations

J. D. Teachman, R. J. Onega

Nuclear Science and Engineering / Volume 83 / Number 1 / January 1983 / Pages 149-161

Technical Paper / dx.doi.org/10.13182/NSE83-A17996

Estimates of Neutron-Induced Radionuclide Populations

George Patrick Lasche

Nuclear Science and Engineering / Volume 83 / Number 1 / January 1983 / Pages 162-173

Technical Paper / dx.doi.org/10.13182/NSE83-A17997

Resolved Resonance Parameters for ²³⁸U from 4 to 6 keV

D. K. Olsen, P. S. Meszaros

Nuclear Science and Engineering / Volume 83 / Number 1 / January 1983 / Pages 174-181

Technical Note / dx.doi.org/10.13182/NSE83-A17998

Number 2

Table of Contents
:Unjustified Interpretation of Flux Anomaly at the Transient Reactor Test Facility(A. DeVolpi)
Response to “Unjustified Interpretation of Flux Anomaly at the Transient Reactor Test Facility”(Alex H. Lumpkin, George J. Bertzins)
Fast Neutron Activation of 48.6-min 111mCd in Natural Cadmium(Donald L. Smith, James W. Meadows)

A Class of Zero-Variance Biasing Schemes for Monte Carlo Reaction Rate Estimators

H. C. Gupta

Nuclear Science and Engineering / Volume 83 / Number 2 / February 1983 / Pages 187-197

Technical Paper / dx.doi.org/10.13182/NSE83-A18212

A Handy Method for Approximate Optimization of Splitting in Monte Carlo

Iván Lux

Nuclear Science and Engineering / Volume 83 / Number 2 / February 1983 / Pages 198-205

Technical Paper / dx.doi.org/10.13182/NSE83-A18213

Equivalence Resonance Integrals for Lattices of Annular Absorber Rods

M. Segev, S. Carmona

Nuclear Science and Engineering / Volume 83 / Number 2 / February 1983 / Pages 206-213

Technical Paper / dx.doi.org/10.13182/NSE83-A18214

Double Heterogeneity Effect of Fuel Pin and Subassembly in a Fast Power Reactor

Masayuki Nakagawa, Hideaki Inoue

Nuclear Science and Engineering / Volume 83 / Number 2 / February 1983 / Pages 214-228

Technical Paper / dx.doi.org/10.13182/NSE83-A18215

Angular Distribution Measurements for the Reaction ⁶Li(n,t)⁴He

H.-H. Knitter, C. Budtz-Jørgensen, D. L. Smith, D. Marletta

Nuclear Science and Engineering / Volume 83 / Number 2 / February 1983 / Pages 229-241

Technical Paper / dx.doi.org/10.13182/NSE83-A18216

Treatment of Scattering Anisotropy of Neutrons Through the Boltzmann-Fokker-Planck Equation

M. Caro, J. Ligou

Nuclear Science and Engineering / Volume 83 / Number 2 / February 1983 / Pages 242-252

Technical Paper / dx.doi.org/10.13182/NSE83-A18217

Natural Convection Heat Transfer in a Confined-Flow Geometry

M. K. Exeter, N. Hay, J. J. Webster, T. A. Dullforce

Nuclear Science and Engineering / Volume 83 / Number 2 / February 1983 / Pages 253-266

Technical Paper / dx.doi.org/10.13182/NSE83-A18218

On Combining Data for Estimating the Frequency of Low-Probability Events with Application to Sodium Valve Failure Rates

H. F. Martz, M. C. Bryson

Nuclear Science and Engineering / Volume 83 / Number 2 / February 1983 / Pages 267-280

Technical Paper / dx.doi.org/10.13182/NSE83-A18219

Use of the Explicit High-Order Perturbation Formulation

G. Palmiotti

Nuclear Science and Engineering / Volume 83 / Number 2 / February 1983 / Pages 281-294

Technical Note / dx.doi.org/10.13182/NSE83-A18220

A Simple Model for Calculation of Fast Neutron Induced Gamma-Ray Spectra

B. Basarragtscha, D. Hermsdorf, D. Seeliger

Nuclear Science and Engineering / Volume 83 / Number 2 / February 1983 / Pages 294-299

Technical Note / dx.doi.org/10.13182/NSE83-A18221

An Approximation of Gamma-Ray Buildup Factors by Modified Geometrical Progression

Y. Harima

Nuclear Science and Engineering / Volume 83 / Number 2 / February 1983 / Pages 299-309

Technical Note / dx.doi.org/10.13182/NSE83-A18222

Neutron Capture in the 1.15-keV Resonance of Iron

R. L. Macklin

Nuclear Science and Engineering / Volume 83 / Number 2 / February 1983 / Pages 309-311

Technical Note / dx.doi.org/10.13182/NSE83-A18223

Optical Model Parameters for Neutron Cross Sections for Medium Mass Nuclei in the 4- to 20-MeV Energy Range and Iron in the 4- to 100-MeV Energy Range

S. Pearlstein

Nuclear Science and Engineering / Volume 83 / Number 2 / February 1983 / Pages 312-315

Technical Note / dx.doi.org/10.13182/NSE83-A18224

Number 3

Table of Contents
A Defense of Benoist's Corrected Diffusion Coefficient(R. P. Hughes)
Response to “A Defense of Benoist's Corrected Diffusion Coefficient”(J. V. Muralidhar Rao, S. M. Lee)

Solid Spot Thermal Conductance of Zircaloy-2/Uranium Dioxide Interfaces

C. V. Madhusudana, L. S. Fletcher

Nuclear Science and Engineering / Volume 83 / Number 3 / March 1983 / Pages 327-332

Technical Paper / dx.doi.org/10.13182/NSE83-A17566

Experimental Study of Neutron Streaming Through Steel-Walled Annular Ducts in Reactor Shields

Toshimasa Miura, Nobuo Sasamoto

Nuclear Science and Engineering / Volume 83 / Number 3 / March 1983 / Pages 333-349

Technical Paper / dx.doi.org/10.13182/NSE83-A17567

On the Development of the Finite Element Method for Fast Reactor Kinetics with Material Motion

Emerson Paul Chivington, William E. Kastenberg

Nuclear Science and Engineering / Volume 83 / Number 3 / March 1983 / Pages 350-365

Technical Paper / dx.doi.org/10.13182/NSE83-A17568

Time-Dependent One-Dimensional Transport Calculations Using the Streaming Ray Method

W. L. Filippone, B. D. Ganapol

Nuclear Science and Engineering / Volume 83 / Number 3 / March 1983 / Pages 366-373

Technical Paper / dx.doi.org/10.13182/NSE83-A17569

On the Relation Between Decay Constants and Critical Parameters in Monoenergetic Neutron Transport

E. B. Dahl, V. Protopopescu, N. G. Sjöstrand

Nuclear Science and Engineering / Volume 83 / Number 3 / March 1983 / Pages 374-379

Technical Paper / dx.doi.org/10.13182/NSE83-A17570

An Assessment of Existing Klein-Nishina Monte Carlo Sampling Methods

R. N. Blomquist, E. M. Gelbard

Nuclear Science and Engineering / Volume 83 / Number 3 / March 1983 / Pages 380-384

Technical Paper / dx.doi.org/10.13182/NSE83-A17571

High-Temperature Isotopic Exchange Between Water Vapor and Hydrogen Gas in an Alumina-Supported Platinum Catalyst Bed

Yamato Asakura, Makoto Kikuchi, Hideo Yusa, Shinpei Matsuda

Nuclear Science and Engineering / Volume 83 / Number 3 / March 1983 / Pages 385-388

Technical Note / dx.doi.org/10.13182/NSE83-A17572

Sensitivity Analysis for a Specific Fusion Reactor Shielding Experiment Containing Tungsten

R. G. Alsmiller, Jr., R. T. Santoro, R. L. Childs, J. M. Barnes, J. L. Lucius

Nuclear Science and Engineering / Volume 83 / Number 3 / March 1983 / Pages 389-393

Technical Note / dx.doi.org/10.13182/NSE83-A17573

A Simple Approximation of the Fermi Function in Nuclear Beta Decay

G. K. Schenter, P. Vogel

Nuclear Science and Engineering / Volume 83 / Number 3 / March 1983 / Pages 393-396

Technical Note / dx.doi.org/10.13182/NSE83-A17574

Coupled-Channel Optical-Model Calculations for Evaluating Neutron Cross Sections of Odd-Mass Actinides

Ch. Lagrange, O. Bersillon, D. G. Madland

Nuclear Science and Engineering / Volume 83 / Number 3 / March 1983 / Pages 396-401

Technical Note / dx.doi.org/10.13182/NSE83-A17575

Calculated Gamma-Ray Spectra for keV Neutron Capture in ²⁴⁰Pu, ²⁴²Pu, and ²³⁸U

G. Reffo, F. Fabbri, K. Wisshak, F. Käppeler

Nuclear Science and Engineering / Volume 83 / Number 3 / March 1983 / Pages 401-407

Technical Note / dx.doi.org/10.13182/NSE83-A17576

Number 4

Table of Contents
Comment on “Asymptotic Equivalence of Neutron Diffusion and Transport in Time-Independent Reactor Systems”(Edward W. Larsen)
Response to “Comment on ‘Asymptotic Equivalence of Neutron Diffusion and Transport in Time-Independent Reactor Systems’”(Mieczyslaw Borysiewicz, Januss Mika, Giampiero Spiga)

Solution of the Multigroup Diffusion Equation for Two-Dimensional Triangular Regions by Finite Fourier Transformation

Takeshi Yokoo and Keisuke Kobayashi

Nuclear Science and Engineering / Volume 83 / Number 4 / April 1983 / Pages 415-426

Technical Paper / dx.doi.org/10.13182/NSE83-A18646

The Use of Neutronic Fluctuations to Locate a Vibrating Control Rod in a Pressurized Water Reactor Model

S. J. Lee, R. W. Albrecht

Nuclear Science and Engineering / Volume 83 / Number 4 / April 1983 / Pages 427-443

Technical Paper / dx.doi.org/10.13182/NSE83-A18647

Neutron Production from Thick Targets of Carbon, Iron, Copper, and Lead by 30- and 52-MeV Protons

Takashi Nakamura, Masahiko Fujii, Kazuo Shin

Nuclear Science and Engineering / Volume 83 / Number 4 / April 1983 / Pages 444-458

Technical Paper / dx.doi.org/10.13182/NSE83-A18648

Particle-Size Distribution in Capacitor Discharge Vaporization of Uranium Dioxide

K. Chen, C. A. Erdman, M. F. Kennedy, A. B. Reynolds

Nuclear Science and Engineering / Volume 83 / Number 4 / April 1983 / Pages 459-472

Technical Paper / dx.doi.org/10.13182/NSE83-A18649

Feed Cycles for the Industrial Production of Heavy Water Through Multiphoton Dissociation of Fluoroform

Jacob Bigeleisen, Willis B. Hammond, Sam Tuccio

Nuclear Science and Engineering / Volume 83 / Number 4 / April 1983 / Pages 473-481

Technical Paper / dx.doi.org/10.13182/NSE83-A18650

Nonuniqueness of Boundary Conditions in the Spherical Harmonic Method—A Reprise

Raphael Aronson

Nuclear Science and Engineering / Volume 83 / Number 4 / April 1983 / Pages 482-483

Technical Note / dx.doi.org/10.13182/NSE83-A18651

Kinetics of Driven Multiplying Media

D. R. Wyman, A. A. Harms

Nuclear Science and Engineering / Volume 83 / Number 4 / April 1983 / Pages 483-487

Technical Note / dx.doi.org/10.13182/NSE83-A18652

Extended Model of Geometrical Surface Splitting in Monte Carlo

A. Dubi, D. J. Dudziak

Nuclear Science and Engineering / Volume 83 / Number 4 / April 1983 / Pages 487-497

Technical Note / dx.doi.org/10.13182/NSE83-A18653

Comparison of Experimental and Calculated Spectrum-Averaged Neutron Cross Sections for the IAEA International Reactor Dosimetry File (IRDF-82)

D. E. Cullen, N. P. Kocherov, P. M. McLaughlin

Nuclear Science and Engineering / Volume 83 / Number 4 / April 1983 / Pages 497-504

Technical Note / dx.doi.org/10.13182/NSE83-A18654

Ga(n;n,n′)Ga Cross-Section Measurement at 3.23 and 4.03 MeV

H. C. Meng, W. C. Tung, J. P. Chien

Nuclear Science and Engineering / Volume 83 / Number 4 / April 1983 / Pages 504-507

Technical Note / dx.doi.org/10.13182/NSE83-A18655

Shielding Calculations for Neutrons from Enhanced Radiation Weapons by Monte Carlo Theory

Gerald Kamelander

Nuclear Science and Engineering / Volume 83 / Number 4 / April 1983 / Pages 507-513

Technical Note / dx.doi.org/10.13182/NSE83-A18656

Angular Quadrature Sets for the Streaming Ray Method in x-y Geometry

Roland England, W. L. Filippone

Nuclear Science and Engineering / Volume 83 / Number 4 / April 1983 / Pages 513-521

Technical Note / dx.doi.org/10.13182/NSE83-A18657