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Volume 50

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Number 1

Table of Contents
A Program for Calculating Thermal Neutron Scattering Kernels(A. G. Gibbs, C. W. Lindenmeier)
Nuclear Radiation Physics(Newton Underwood)
Education and Research in the Nuclear Fuel Cycle(C. E. Stevenson)

Two-Group Critical Problems for Slabs and Spheres in Neutron-Transport Theory

J. T. Kriese, C. E. Siewert, Y. Yener

Nuclear Science and Engineering / Volume 50 / Number 1 / January 1973 / Pages 3-9

Technical Paper / dx.doi.org/10.13182/NSE73-A22582

Neutron Transport for a Slab with a Degenerate Scattering Kernel

H. A. Larson, N. J. McCormick

Nuclear Science and Engineering / Volume 50 / Number 1 / January 1973 / Pages 10-19

Technical Paper / dx.doi.org/10.13182/NSE73-A22583

Improved Moment Method Calculations of Gamma-Ray Transport: Application to Point Isotropic Sources in Water

L. V. Spencer, G. L. Simmons

Nuclear Science and Engineering / Volume 50 / Number 1 / January 1973 / Pages 20-31

Technical Paper / dx.doi.org/10.13182/NSE73-A22584

Moments Method Calculation of Buildup Factors for Point Isotropic Monoenergetic Gamma-Ray Sources at Depths Greater than 20 Mean-Free-Paths

E. E. Morris

Nuclear Science and Engineering / Volume 50 / Number 1 / January 1973 / Pages 32-37

Technical Paper / dx.doi.org/10.13182/NSE73-A22585

A Pulsed Neutron Experiment with Beryllium by the Use of a Gamma-Ray Flash from an Electron Linear Accelerator

Otohiko Aizawa, Hiroyuki Kadotani, Keiji Kanda, Yoshiaki Fujita

Nuclear Science and Engineering / Volume 50 / Number 1 / January 1973 / Pages 38-45

Technical Paper / dx.doi.org/10.13182/NSE73-A22586

On the Use of Maximum Principle in Optimal Xenon Shutdown Problems

Seppo Salo

Nuclear Science and Engineering / Volume 50 / Number 1 / January 1973 / Pages 46-52

Technical Paper / dx.doi.org/10.13182/NSE73-A22587

Analysis of the Coolant Behavior Following Fuel Failure and Molten Fuel-Sodium Interaction in a Fast Nuclear Reactor

A. W. Cronenberg, H. K. Fauske, D. T. Eggen

Nuclear Science and Engineering / Volume 50 / Number 1 / January 1973 / Pages 53-62

Technical Paper / dx.doi.org/10.13182/NSE73-A22588

Sensitivity Analysis of Ideal Centrifuge Cascade for Producing Slightly Enriched Uranium

Toshio Kawai, Kotaro Inoue, Hiroshi Motoda, Tomofumi Kobayashi, Takashi Kiguchi

Nuclear Science and Engineering / Volume 50 / Number 1 / January 1973 / Pages 63-72

Technical Paper / dx.doi.org/10.13182/NSE73-A22589

Monte Carlo Confidence Limits for Iterated-Source Calculations

D. B. MacMillan

Nuclear Science and Engineering / Volume 50 / Number 1 / January 1973 / Pages 73-75

Technical Note / dx.doi.org/10.13182/NSE73-A22590

Studies in Spectral Neutron Flux Synthesis

Harold Greenspan

Nuclear Science and Engineering / Volume 50 / Number 1 / January 1973 / Pages 75-78

Technical Note / dx.doi.org/10.13182/NSE73-A22591

The Effective Cross Section for the ¹⁶O(d, n)¹⁷ F Reaction for Fission Neutrons Moderated by Heavy Water

H. S. Pruys, B. D. Ganapol

Nuclear Science and Engineering / Volume 50 / Number 1 / January 1973 / Pages 79-80

Technical Note / dx.doi.org/10.13182/NSE73-A22592

Revised Delayed-Neutron Yield Data

A. E. Evans, M. M. Thorpe, M. S. Krick

Nuclear Science and Engineering / Volume 50 / Number 1 / January 1973 / Pages 80-82

Technical Note / dx.doi.org/10.13182/NSE73-A22593

Merit Index for Gas-Cooled Reactor Heat Transfer

G. Melese-d’Hospital

Nuclear Science and Engineering / Volume 50 / Number 1 / January 1973 / Pages 83-85

Technical Note / dx.doi.org/10.13182/NSE73-A22594

Thermal Characterization of Restructured Fuel

Aaron J. Friedland

Nuclear Science and Engineering / Volume 50 / Number 1 / January 1973 / Pages 85-87

Technical Note / dx.doi.org/10.13182/NSE73-A22595

Number 2

Table of Contents
Tranzit(K. D. Lathrop, F. W. Brinkley)
Twotran Sphere(K. D. Lathrop, F. W. Brinkley)
Thermal-Neutron Diffusion at the Ice-Water Phase Transition(S. P. Tewari)
Nuclear Energy Conversion(E. Richard Cohen)
Direct Conversion of Nuclear Radiation Energy(Ned Rasor)
Measurement of Low-Level Radioactivity, ICRU-22(James E. McLaughlin)

Mixed Sorption Models and Isotherms of the Cesium-Rubidium-Graphite System at High Temperatures

M. J. Haire, L. R. Zumwalt

Nuclear Science and Engineering / Volume 50 / Number 2 / February 1973 / Pages 91-97

Technical Paper / dx.doi.org/10.13182/NSE73-A23232

The Neutron-Induced Gamma-Ray Reactions in Sodium-23 in the Energy Range 4.85 ≤ E_n ≤ 7.5 MeV

J. K. Dickens

Nuclear Science and Engineering / Volume 50 / Number 2 / February 1973 / Pages 98-107

Technical Paper / dx.doi.org/10.13182/NSE73-A23233

The Energy Spectrum of Prompt Neutrons from the Fission of Uranium-235 by 0.40-MeV Neutrons

M. M. Islam, H. -H. Knitter

Nuclear Science and Engineering / Volume 50 / Number 2 / February 1973 / Pages 108-114

Technical Paper / dx.doi.org/10.13182/NSE73-A23234

Critical Experiments with Homogeneous Mixtures of Plutonium and Uranium Oxides Containing 8,15, and 30 wt% Plutonium

S. R. Bierman, E. D. Clayton, L. E. Hansen

Nuclear Science and Engineering / Volume 50 / Number 2 / February 1973 / Pages 115-126

Technical Paper / dx.doi.org/10.13182/NSE73-2

Criticality of Plutonium Nitrate Solutions Containing Borated Raschig Rings

R. C. Lloyd, S. R. Bierman, E. D. Clayton

Nuclear Science and Engineering / Volume 50 / Number 2 / February 1973 / Pages 127-134

Technical Paper / dx.doi.org/10.13182/NSE73-A23236

Improved Integral Transport Theory by Means of Space Polynomial Approximations

J. Ligou

Nuclear Science and Engineering / Volume 50 / Number 2 / February 1973 / Pages 135-146

Technical Paper / dx.doi.org/10.13182/NSE73-A23237

Higher Flux Mode Effects in Xenon Spatial Oscillations

R. A. Rydin

Nuclear Science and Engineering / Volume 50 / Number 2 / February 1973 / Pages 147-152

Technical Paper / dx.doi.org/10.13182/NSE73-A23238

Optimal Fuel Enrichment Distribution in Fast Reactors

P. Goldschmidt

Nuclear Science and Engineering / Volume 50 / Number 2 / February 1973 / Pages 153-163

Technical Paper / dx.doi.org/10.13182/NSE73-A23239

An Integral Formulation of the Neutron Scattering Moments for Monatomic Gases

Nicholas H. Kuehn III, Raymond L. Murray

Nuclear Science and Engineering / Volume 50 / Number 2 / February 1973 / Pages 164-169

Technical Note / dx.doi.org/10.13182/NSE73-A23240

Neutron Multiplicity Distributions in the Spontaneous Fission of ²⁴⁴Cm, ²⁴⁸Cm, and ²⁵²Cf

R. W. Stoughton, J. Halperin, C. E. Bemis, H. W. Schmitt

Nuclear Science and Engineering / Volume 50 / Number 2 / February 1973 / Pages 169-171

Technical Note / dx.doi.org/10.13182/NSE73-A23241

Average Neutron Cross Sections in the Unresolved Resonance Range

Mendel Beer

Nuclear Science and Engineering / Volume 50 / Number 2 / February 1973 / Pages 171-173

Technical Note / dx.doi.org/10.13182/NSE73-A23242

Effect of Delayed-Neutron Mode on the Determination of the Prompt-Neutron Decay Constant in Pulsed-Neutron Measurements

Yoshihiko Kaneko, Shuzi Ohkubo, Fujiyoshi Akino

Nuclear Science and Engineering / Volume 50 / Number 2 / February 1973 / Pages 173-176

Technical Note / dx.doi.org/10.13182/NSE73-A23243

Correlating the Ratio of the Peak-to-Average Power in a Reactor with Quadrant Power Distributions

M. M. Levine

Nuclear Science and Engineering / Volume 50 / Number 2 / February 1973 / Pages 176-179

Technical Note / dx.doi.org/10.13182/NSE73-A23244

Number 3

Table of Contents
3DP A Three-Dimensional Perturbation Code(R. W. Hardie, W. W. Little, Jr.)
Advances in Nuclear Science and Technology, Vol. 6(Melvin Tobias)
Neutron Activation Analysis(W. S. Lyon)
Shock Waves in Collisionless Plasmas(Robert A. Gross)

Numerical Methods of High Order Accuracy for One-Dimensional Diffusion Equation

J. P. Hennart

Nuclear Science and Engineering / Volume 50 / Number 3 / March 1973 / Pages 185-199

Technical Paper / dx.doi.org/10.13182/NSE73-A28971

The Neutron Diffusion Coefficient as a Second-Order Tensor—Theory and Calculations

V. C. Boffi, T. Trombetti

Nuclear Science and Engineering / Volume 50 / Number 3 / March 1973 / Pages 200-207

Technical Paper / dx.doi.org/10.13182/NSE73-A28972

Delayed Neutron Data for Fast Reactor Analysis

J. E. Cahalan, K. O. Ott

Nuclear Science and Engineering / Volume 50 / Number 3 / March 1973 / Pages 208-215

Technical Paper / dx.doi.org/10.13182/NSE73-A28973

On the Applicability of Sjöstrand’s Area Method for Reactivity Measurement by the Pulsed-Neutron Technique

Jan B. Dragt

Nuclear Science and Engineering / Volume 50 / Number 3 / March 1973 / Pages 216-219

Technical Paper / dx.doi.org/10.13182/NSE73-A28974

A Bilinear Formulation for Spatial Cross-Section Averaging

Masaoki Komata, Richard B. Nicholson, Earl M. Page

Nuclear Science and Engineering / Volume 50 / Number 3 / March 1973 / Pages 220-228

Technical Paper / dx.doi.org/10.13182/NSE73-A28975

A Study of Several Methods for Analysis of Critical Assembly Heterogeneity

R. G. Palmer, J. P. Plummer, R. B. Nicholson

Nuclear Science and Engineering / Volume 50 / Number 3 / March 1973 / Pages 229-242

Technical Paper / dx.doi.org/10.13182/NSE73-A28976

The Total Neutron Cross Sections of Uranium-238 from 0.8 to 30 MeV

S. H. Hayes, P. Stoler, J. M. Clement, C. A. Goulding

Nuclear Science and Engineering / Volume 50 / Number 3 / March 1973 / Pages 243-247

Technical Paper / dx.doi.org/10.13182/NSE73-A28977

Measurement of Bremsstrahlung Spectra Produced in Iron and Tungsten Targets by 15-MeV Electrons with Activation Detectors

Hideo Hirayama, Takashi Nakamura

Nuclear Science and Engineering / Volume 50 / Number 3 / March 1973 / Pages 248-256

Technical Paper / dx.doi.org/10.13182/NSE73-A28978

The Californium-252 Fission Neutron Spectrum from 0.5 to 13 MeV

L. Green, J. A. Mitchell, N. M. Steen

Nuclear Science and Engineering / Volume 50 / Number 3 / March 1973 / Pages 257-272

Technical Paper / dx.doi.org/10.13182/NSE73-A28979

A Study of Fission-Fragment-Induced Nucleation of Bubbles in Superheated Water

L. W. Deitrich, T. J. Connolly

Nuclear Science and Engineering / Volume 50 / Number 3 / March 1973 / Pages 273-282

Technical Paper / dx.doi.org/10.13182/NSE73-A28980

Thermal Contact Conductance in Reactor Fuel Elements

Gary Jacobs, Neil Todreas

Nuclear Science and Engineering / Volume 50 / Number 3 / March 1973 / Pages 283-290

Technical Note / dx.doi.org/10.13182/NSE73-A28981

Errors in Perturbation Calculations

C. W. J. McCallien

Nuclear Science and Engineering / Volume 50 / Number 3 / March 1973 / Pages 290-293

Technical Note / dx.doi.org/10.13182/NSE73-A28982

Second-Order Boltzmann Equation from Invariant Imbedding Theory

Zbigniew Weiss

Nuclear Science and Engineering / Volume 50 / Number 3 / March 1973 / Pages 294-297

Technical Note / dx.doi.org/10.13182/NSE73-A28983

Computational Experimentation on the Finite Element Method in Bare Slab Criticality Calculations

Juhani Pitkäranta, Pekka Silvennoinen

Nuclear Science and Engineering / Volume 50 / Number 3 / March 1973 / Pages 297-300

Technical Note / dx.doi.org/10.13182/NSE73-A28984

Variational Estimates of the Detector Response Change in a Fixed Source System Due to Cross-Section Perturbations

T. J. Hoffman

Nuclear Science and Engineering / Volume 50 / Number 3 / March 1973 / Pages 300-302

Technical Note / dx.doi.org/10.13182/NSE73-A28985

In-Core Neutron Flux Distribution Measurement by a Circulating Fluid Activation Method

Masaaki Fujii

Nuclear Science and Engineering / Volume 50 / Number 3 / March 1973 / Pages 302-306

Technical Note / dx.doi.org/10.13182/NSE73-A28986

Number 4

Table of Contents
XLACS A Program to Produce Weighted Multigroup Neutron Cross Sections from ENDF/B(N. M. Greene, J. L. Lucius, J. E. White, R. Q. Wright, C. W. Craven, Jr., M. L. Tobias)
An Introduction to On-Line Computers(Melvin Tobias)
Dissociation in Heavy Particle Collisions(Gordon H. Dunn)
Nuclear Power Plant Systems and Equipment(M. J. Larocco)

Neutron-Induced Gamma-Ray Production in Iron for the Energy Range 0.8 ≤ E_n ≤ 20 MeV

J. K. Dickens, G. L. Morgan, F. G. Perey

Nuclear Science and Engineering / Volume 50 / Number 4 / April 1973 / Pages 311-336

Technical Paper / dx.doi.org/10.13182/NSE73-A26567

Neutron Thermalization in Various H₂O-D₂O Mixtures in the Temperature Range 253 to 4°K

G. S. Gangwani, S. P. Tewari, L. S. Kothari

Nuclear Science and Engineering / Volume 50 / Number 4 / April 1973 / Pages 337-344

Technical Paper / dx.doi.org/10.13182/NSE73-A26568

Adjustment of Multigroup Neutron Cross Sections by a Correlation Method

M. Salvatores

Nuclear Science and Engineering / Volume 50 / Number 4 / April 1973 / Pages 345-353

Technical Paper / dx.doi.org/10.13182/NSE73-A26569

A Many-Resonance Approximation for the Neutron Energy Spectrum

M. Segev

Nuclear Science and Engineering / Volume 50 / Number 4 / April 1973 / Pages 354-363

Technical Paper / dx.doi.org/10.13182/NSE73-A26570

Thermal-Neutron Capture Cross Sections and Capture Resonance Integrals of Americium-241

R. M. Harbour, K. W. MacMurdo, F. J. McCrosson

Nuclear Science and Engineering / Volume 50 / Number 4 / April 1973 / Pages 364-369

Technical Paper / dx.doi.org/10.13182/NSE73-A26571

Stability of Nuclear Reactors with Changes in Eigenvalue

Dong H. Nguyen

Nuclear Science and Engineering / Volume 50 / Number 4 / April 1973 / Pages 370-381

Technical Paper / dx.doi.org/10.13182/NSE73-A26572

Two-Phase Mixing for Annular Flow in Simulated Rod Bundle Geometries

Kuldip Singh, C. C. St. Pierre

Nuclear Science and Engineering / Volume 50 / Number 4 / April 1973 / Pages 382-387

Technical Note / dx.doi.org/10.13182/NSE73-A26573

Extrapolated Endpoint for the Uniform Source Half-Space Problem

W. P. Petrick, C. T. McDaniel, A. Leonard

Nuclear Science and Engineering / Volume 50 / Number 4 / April 1973 / Pages 388-390

Technical Note / dx.doi.org/10.13182/NSE73-A26574

Interpolation of Tabular Secondary Neutron and Photon Energy Distributions

Richard J. Doyas, Sterrett T. Perkins

Nuclear Science and Engineering / Volume 50 / Number 4 / April 1973 / Pages 390-392

Technical Note / dx.doi.org/10.13182/NSE73-A26575

The (n, γn’) Reaction in Calculations of Fast Reactor Neutron Spectra

M. P. Fricke, J. M. Neill

Nuclear Science and Engineering / Volume 50 / Number 4 / April 1973 / Pages 392-397

Technical Note / dx.doi.org/10.13182/NSE73-A26576

Effect of the ²³⁸U(n, γn’) Reaction in Fast-Neutron Spectrum Critical Assemblies

Harry H. Hummel, Weston M. Stacey, Jr.

Nuclear Science and Engineering / Volume 50 / Number 4 / April 1973 / Pages 397-398

Technical Note / dx.doi.org/10.13182/NSE73-A26577

Exact Time-Dependent Second Spatial Moment of the One-Speed Neutron Transport Model

C. S. Barnett

Nuclear Science and Engineering / Volume 50 / Number 4 / April 1973 / Pages 398-401

Technical Note / dx.doi.org/10.13182/NSE73-A26578