Home / Publications / Journals / Nuclear Science and Engineering / Volume 36

Volume 36

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Number 1

Table of Contents
ATHENA(D. Spielberg)
Nuclear Matter and Nuclear Reactions(William E. Kiker)
The Constructive Uses of Nuclear Explosives(Paul Kruger)
Determination of Reactor Kinetic Parameters by Photon Observation(Wayne K. Lehto, John M. Carpenter)

Neutron Diffusion Lengths of Graphite-Absorber Mixtures Between 200 and 2000°K

W. W. Clendenin

Nuclear Science and Engineering / Volume 36 / Number 1 / April 1969 / Pages 1-14

Technical Paper / dx.doi.org/10.13182/NSE69-A18852

Measurement of Neutron Flux Spectra by a Multiple Foil Activation Iterative Method and Comparison with Reactor Physics Calculations and Spectrometer Measurements

W. N. McElroy, S. Berg, T. B. Crockett, R. J. Tuttle

Nuclear Science and Engineering / Volume 36 / Number 1 / April 1969 / Pages 15-27

Technical Paper / dx.doi.org/10.13182/NSE69-A18853

A Space-Dependent Reactor-Noise Formulation Utilizing Modal Expansions

R. A. Danofsky

Nuclear Science and Engineering / Volume 36 / Number 1 / April 1969 / Pages 28-38

Technical Paper / dx.doi.org/10.13182/NSE69-A18854

The Bimodal Decay of Two Pulsed-Neutron-Coupled Cores of an Organic-Moderated and -Reflected System

U. Farinelli, N. Pacilio

Nuclear Science and Engineering / Volume 36 / Number 1 / April 1969 / Pages 39-46

Technical Paper / dx.doi.org/10.13182/NSE69-A18855

Resonance Integral and Doppler Coefficients in Nonuniform Cylindrical Reactor Fuel Rods

J. J. Van Binnebeek

Nuclear Science and Engineering / Volume 36 / Number 1 / April 1969 / Pages 47-58

Technical Paper / dx.doi.org/10.13182/NSE69-A18856

Resonance Moderation of Neutrons in Weakly Absorbing Mixtures

M. Segev

Nuclear Science and Engineering / Volume 36 / Number 1 / April 1969 / Pages 59-66

Technical Paper / dx.doi.org/10.13182/NSE69-A18857

Application of Statistical Theory and Multilevel Formalism to Doppler Effect Analysis—I

R. N. Hwang

Nuclear Science and Engineering / Volume 36 / Number 1 / April 1969 / Pages 67-81

Technical Paper / dx.doi.org/10.13182/NSE69-A18858

Application of Statistical Theory and Multilevel Formalism to Doppler Effect Analysis—II

R. N. Hwang

Nuclear Science and Engineering / Volume 36 / Number 1 / April 1969 / Pages 82-96

Technical Paper / dx.doi.org/10.13182/NSE69-A18859

Comparison of Modal and Iterative Approaches to Space and Space-Time Nonlinear Problems

Louis M. Shotkin

Nuclear Science and Engineering / Volume 36 / Number 1 / April 1969 / Pages 97-104

Technical Paper / dx.doi.org/10.13182/NSE69-A18860

Multiple Scattering in Double Differential Measurements as a Function of Neutron Path Length

E. L. Slaggie

Nuclear Science and Engineering / Volume 36 / Number 1 / April 1969 / Pages 105-107

Technical Note / dx.doi.org/10.13182/NSE69-A18861

Iteration and Intermediate Resonance Neutron Absorption in Multinuclide Systems

F. de Kruijf

Nuclear Science and Engineering / Volume 36 / Number 1 / April 1969 / Pages 107-109

Technical Note / dx.doi.org/10.13182/NSE69-A18862

Implications of Recent Fission-Averaged Cross-Section Measurements

W. N. McElroy

Nuclear Science and Engineering / Volume 36 / Number 1 / April 1969 / Pages 109-113

Technical Note / dx.doi.org/10.13182/NSE69-A18863

On the Step-Response Method of Determining the Zero-Power Reactor Transfer Function

D. M. Chapin

Nuclear Science and Engineering / Volume 36 / Number 1 / April 1969 / Pages 113-114

Technical Note / dx.doi.org/10.13182/NSE69-A18864

Discrepancy Between Measured and Calculated Reactivity Coefficients in Dilute Plutonium Fueled Fast Criticals

W. W. Little, Jr., R. W. Hardie

Nuclear Science and Engineering / Volume 36 / Number 1 / April 1969 / Pages 115-116

Technical Note / dx.doi.org/10.13182/NSE69-A18865

An Evaluation of Homogeneous and Heterogeneous Methods of Analysis in a Reflected Subcritical Assembly

M. R. Haroon

Nuclear Science and Engineering / Volume 36 / Number 1 / April 1969 / Pages 116-122

Technical Note / dx.doi.org/10.13182/NSE69-A18866

A Method for Calculating Space-Dependent Reactor Source Transfer Functions with Feedback

D. N. Bridges, J. D. Clement, J. P. Renier

Nuclear Science and Engineering / Volume 36 / Number 1 / April 1969 / Pages 122-125

Technical Note / dx.doi.org/10.13182/NSE69-A18867

Reactivity Rate-Constrained Time-Optimal Neutron Kinetics

S. F. Moon, R. R. Mohler

Nuclear Science and Engineering / Volume 36 / Number 1 / April 1969 / Pages 125-128

Technical Note / dx.doi.org/10.13182/NSE69-A18868

Number 2

Table of Contents
Moderator Studies for a Repetitively Pulsed Test Facility (RPTF)(R. G. Fluharty, F. B. Simpson, G. J. Russell, J. H. Menzel)
TWOTRAN (x, y)(K. D. Lathrop)
GAKIT(R. Froehlich, S. R. Johnson, M. H. Merrill)

Time-Energy-Dependent Neutron Transport in an Infinite Medium in the Framework of Age-Dependent Branching Processes

P. Wälti

Nuclear Science and Engineering / Volume 36 / Number 2 / May 1969 / Pages 133-142

Technical Paper / dx.doi.org/10.13182/NSE69-A19713

Experimental Neutron Kinetic Studies in a ²³⁸U Sphere

Tsahi Gozani

Nuclear Science and Engineering / Volume 36 / Number 2 / May 1969 / Pages 143-158

Technical Paper / dx.doi.org/10.13182/NSE69-A19714

The Loss-of-Coolant Accident Analysis in Pressurized Water Reactors

Amir N. Nahavandi

Nuclear Science and Engineering / Volume 36 / Number 2 / May 1969 / Pages 159-188

Technical Paper / dx.doi.org/10.13182/NSE69-A19715

A Unified Nuclear Model for the Generation of Nuclear Data

K. J. Yost, P. H. Pitkanen, C. Y. Fu

Nuclear Science and Engineering / Volume 36 / Number 2 / May 1969 / Pages 189-201

Technical Paper / dx.doi.org/10.13182/NSE69-A19716

The Measurement of Absolute Delayed-Neutron Yields from 3.1- and 14.9-MeV Fission

Christopher F. Masters, M. M. Thorpe, Darryl B. Smith

Nuclear Science and Engineering / Volume 36 / Number 2 / May 1969 / Pages 202-208

Technical Paper / dx.doi.org/10.13182/NSE69-A19717

An Accurate Determination of the Cadmium Ratio of Neutron Capture Rates in ²³⁸U in Slightly Enriched Uranium

Ç. Ertek, A. Yalçin, Y. İnel

Nuclear Science and Engineering / Volume 36 / Number 2 / May 1969 / Pages 209-219

Technical Paper / dx.doi.org/10.13182/NSE69-A19718

The Application of a Gamma-Ray Cascade Model to the Calculation of Neutron Energy-Dependent Capture Gamma-Ray Production Cross Sections

K. J. Yost, S. M. Kremer

Nuclear Science and Engineering / Volume 36 / Number 2 / May 1969 / Pages 220-231

Technical Paper / dx.doi.org/10.13182/NSE69-A19719

Measurements of Nonfission Heating in a High Neutron Flux Reactor

R. M. Carroll, R. B. Perez, O. Sisman

Nuclear Science and Engineering / Volume 36 / Number 2 / May 1969 / Pages 232-237

Technical Paper / dx.doi.org/10.13182/NSE69-A19720

Experimental Studies on Gamma-Ray Dose Rates from a ⁶⁰Co Cylindrical Source with Shell-Shaped Shields

Yoshihiko Kanemori, Yutaka Furuta

Nuclear Science and Engineering / Volume 36 / Number 2 / May 1969 / Pages 238-245

Technical Paper / dx.doi.org/10.13182/NSE69-A19721

A Semiempirical Formula for Albedo of Alternating Layers

Takashi Nakamura, Tomonori Hyodo

Nuclear Science and Engineering / Volume 36 / Number 2 / May 1969 / Pages 246-250

Technical Paper / dx.doi.org/10.13182/NSE69-A19722

High-Energy (<400-MeV) Neutron Transport Using the Method of Discrete Ordinates

R. G. Alsmiller, Jr., F. R. Mynatt, J. Barish, W. W. Engle, Jr.

Nuclear Science and Engineering / Volume 36 / Number 2 / May 1969 / Pages 251-255

Technical Note / dx.doi.org/10.13182/NSE69-A19723

Number 3

Table of Contents
Noah(G. S. Lellouche)
On Rafalski's Solution to the Albedo Problem(G. C. Pomraning)
Peter Kapitsa, on Life and Science(Don M. Yost)
Theory of Turbulent Plasma(Albert Simon)
Nuclear Chemistry(Richard L. Hahn, Curtis E. Bemis, Jr.)
Radiation Chemistry(C. J. Hochanadel)
Fabrication of Thorium Fuel Elements(David H. Gurinsky)

Calculation of Temperature Distributions in Fuel Rods with Varying Conductivity and Asymmetric Flux Distribution

D. G. Andrews, M. Dixmier

Nuclear Science and Engineering / Volume 36 / Number 3 / June 1969 / Pages 259-267

Technical Paper / dx.doi.org/10.13182/NSE69-A18722

The Computation of the Equilibrium Vapor Composition Over UO_{2 + x}

M. H. Fontana, R. E. Bailey

Nuclear Science and Engineering / Volume 36 / Number 3 / June 1969 / Pages 268-274

Technical Paper / dx.doi.org/10.13182/NSE69-A18723

Elastic and Inelastic Scattering of Fast Neutrons from ¹⁰B, ¹¹B, Natural Ge, and ⁹³NB

John C. Hopkins, D. M. Drake

Nuclear Science and Engineering / Volume 36 / Number 3 / June 1969 / Pages 275-279

Technical Paper / dx.doi.org/10.13182/NSE69-A18724

The ¹⁴N(n, xγ) Reaction for 5.8 ≤ E_n ≤ 8.6 MeV

J. K. Dickens, F. G. Perey

Nuclear Science and Engineering / Volume 36 / Number 3 / June 1969 / Pages 280-290

Technical Paper / dx.doi.org/10.13182/NSE69-A18725

Calculation of the Neutron and Proton Spectra from Thick Targets Bombarded by 450-MeV Protons and Comparison with Experiment

R. G. Alsmiller, Jr., J. W. Wachter, H. S. Moran

Nuclear Science and Engineering / Volume 36 / Number 3 / June 1969 / Pages 291-294

Technical Paper / dx.doi.org/10.13182/NSE69-A18726

A Numerical Treatment of the Attenuation of Neutrons by Air Ducts in Shields

Ricardo Artigas, H. E. Hungerford

Nuclear Science and Engineering / Volume 36 / Number 3 / June 1969 / Pages 295-303

Technical Paper / dx.doi.org/10.13182/NSE69-A18727

Advantages of Using a Combination Electromagnetic and Material Shield

R. D. Shelton, H. E. Stern, J. W. Watts

Nuclear Science and Engineering / Volume 36 / Number 3 / June 1969 / Pages 304-308

Technical Paper / dx.doi.org/10.13182/NSE69-A18728

Neutron Flux and Importance Distribution by Collision Method, Starting from a Generalized Source

G. Bitelli, M. Salvatores

Nuclear Science and Engineering / Volume 36 / Number 3 / June 1969 / Pages 309-314

Technical Paper / dx.doi.org/10.13182/NSE69-A18729

Discrete Energy Representation of Thermal-Neutron Spectra in Uranium-Plutonium Lattices

B. Fredin, T. Boševski, M. Mataušek

Nuclear Science and Engineering / Volume 36 / Number 3 / June 1969 / Pages 315-325

Technical Paper / dx.doi.org/10.13182/NSE69-A18730

Neutron Diffusion in Aluminum-Water Lattices: Measurements of Anisotropy in the Continuous Eigenvalue Region

Philip F. Palmedo, John F. Conant

Nuclear Science and Engineering / Volume 36 / Number 3 / June 1969 / Pages 326-335

Technical Paper / dx.doi.org/10.13182/NSE69-A18731

A Detailed Method for Calculating the Low Energy Multigroup Cross Sections and the Doppler Coefficient in a Fast Reactor

C. R. Adkins, T. E. Murley, M. W. Dyos

Nuclear Science and Engineering / Volume 36 / Number 3 / June 1969 / Pages 336-350

Technical Paper / dx.doi.org/10.13182/NSE69-A18732

Neutron Rethermalization Near a Temperature Discontinuity Between Terphenyl and Light Water

A. Rastas, J. Saastamoinen

Nuclear Science and Engineering / Volume 36 / Number 3 / June 1969 / Pages 351-360

Technical Paper / dx.doi.org/10.13182/NSE69-A18733

On Transient Digital Control of a Linear Model of the Halden Boiling Water Reactor

W. Ciechanowicz, K. O. Solberg

Nuclear Science and Engineering / Volume 36 / Number 3 / June 1969 / Pages 361-371

Technical Paper / dx.doi.org/10.13182/NSE69-A18734

A Three-Dimensional Analysis of Xenon-Induced Oscillations in Boiling Water Cooled Reactors

Wataru Shinoda, Susumu Mitake

Nuclear Science and Engineering / Volume 36 / Number 3 / June 1969 / Pages 372-388

Technical Paper / dx.doi.org/10.13182/NSE69-A18735

Stochastic Kinetic Theory for a Space- and Energy-Dependent Zero Power Nuclear Reactor Model

Weston M. Stacey, Jr.

Nuclear Science and Engineering / Volume 36 / Number 3 / June 1969 / Pages 389-401

Technical Paper / dx.doi.org/10.13182/NSE69-A18736

Accuracy of the Quasistatic Treatment of Spatial Reactor Kinetics

K. O. Ott, D. A. Meneley

Nuclear Science and Engineering / Volume 36 / Number 3 / June 1969 / Pages 402-411

Technical Paper / dx.doi.org/10.13182/NSE36-402

Analytical and Experimental Investigations of the Kinetic Behavior of a Uranium-Dioxide-Fueled Pressurized-Water Reactor

J. E. Houghtaling, J. E. Grund

Nuclear Science and Engineering / Volume 36 / Number 3 / June 1969 / Pages 412-426

Technical Paper / dx.doi.org/10.13182/NSE69-A18738

Pressure Pulse Propagation in an Annular Flowing Two-Phase System

C. W. Garrard, Jr., R. S. Wick

Nuclear Science and Engineering / Volume 36 / Number 3 / June 1969 / Pages 427-429

Technical Note / dx.doi.org/10.13182/NSE69-A18739

A Systematic Comparison of Different Hydrodynamics Models

Rainer Grumbach

Nuclear Science and Engineering / Volume 36 / Number 3 / June 1969 / Pages 429-433

Technical Note / dx.doi.org/10.13182/NSE69-A18740

Monatomic Gas Cross Section Expansion Coefficients

W. W. Clendenin

Nuclear Science and Engineering / Volume 36 / Number 3 / June 1969 / Pages 433-434

Technical Note / dx.doi.org/10.13182/NSE69-A18741

Selected Fission Cross Sections for ²³⁶U

William G. Davey

Nuclear Science and Engineering / Volume 36 / Number 3 / June 1969 / Pages 434-435

Technical Note / dx.doi.org/10.13182/NSE69-A18742

Space-Angle Synthesis

Harry S. Zwibel, Bradley Bowes

Nuclear Science and Engineering / Volume 36 / Number 3 / June 1969 / Pages 435-438

Technical Note / dx.doi.org/10.13182/NSE69-A18743

Source Convergence in Monte Carlo Calculations

L. L. Carter, N. J. McCormick

Nuclear Science and Engineering / Volume 36 / Number 3 / June 1969 / Pages 438-441

Technical Note / dx.doi.org/10.13182/NSE69-1

Single Rod Fine Distribution of the Fast Fission Ratio

V. Aiello, G. Maracci, F. Rustichelli

Nuclear Science and Engineering / Volume 36 / Number 3 / June 1969 / Pages 441-444

Technical Note / dx.doi.org/10.13182/NSE69-A18745

An Anomaly Arising in the Collapsed-Group Flux Synthesis Approximation

C. H. Adams, W. M. Stacey, Jr.

Nuclear Science and Engineering / Volume 36 / Number 3 / June 1969 / Pages 444-447

Technical Note / dx.doi.org/10.13182/NSE69-A18746

On the Milne-Problem Extrapolation Distance

G. R. Bond, C. E. Siewert

Nuclear Science and Engineering / Volume 36 / Number 3 / June 1969 / Page 447

Technical Note / dx.doi.org/10.13182/NSE69-A18747

Application of the j_N Method to Neutron Transport in Slabs and Spheres

H. Kschwendt

Nuclear Science and Engineering / Volume 36 / Number 3 / June 1969 / Pages 447-450

Technical Note / dx.doi.org/10.13182/NSE69-A18748

Equivalence of Integral Transform and Spatial Spherical Harmonics Methods

J. Mika, R. Stankiewicz

Nuclear Science and Engineering / Volume 36 / Number 3 / June 1969 / Pages 450-453

Technical Note / dx.doi.org/10.13182/NSE69-A18749

Collisional Importance and Adjoint Problems in Neutron Transport

Paul Nelson, Jr.

Nuclear Science and Engineering / Volume 36 / Number 3 / June 1969 / Pages 453-455

Technical Note / dx.doi.org/10.13182/NSE69-A18750