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Volume 53

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Number 1

Measurements of the ⁵⁹Ni(n,α) Cross Section for Thermal Neutrons

H. M. Eiland and G. J. Kirouac

Nuclear Science and Engineering / Volume 53 / Number 1 / January 1974 / Pages 1-8

Technical Paper / dx.doi.org/10.13182/NSE74-A23326

Measurement and Calculation of Integral Heavy-Element Cross-Section Ratios in the Fast Breeder Reactor EBR-II

N. D. Dudey, D. Meneghetti, R. R. Heinrich, R. H. Rempert

Nuclear Science and Engineering / Volume 53 / Number 1 / January 1974 / Pages 9-26

Technical Paper / dx.doi.org/10.13182/NSE74-A23327

Measurement of Steady-State, Space-Dependent, Thermal-Neutron Spectra in Beryllium Assemblies with Strong Transverse Leakage

J. A. Lake, J. M. Kallfelz

Nuclear Science and Engineering / Volume 53 / Number 1 / January 1974 / Pages 27-46

Technical Paper / dx.doi.org/10.13182/NSE74-A23328

Measurements of Equilibrium and Time-Dependent Energy Spectra of Beta Rays from Californium-252 Fission Fragments

R. A. Knief, B. W. Wehring, M. E. Wyman

Nuclear Science and Engineering / Volume 53 / Number 1 / January 1974 / Pages 47-60

Technical Paper / dx.doi.org/10.13182/NSE74-A23329

Model for Calculating Prompt-Response Self-Powered Neutron Detectors

W. Jaschik, L W. Seifritz

Nuclear Science and Engineering / Volume 53 / Number 1 / January 1974 / Pages 61-78

Technical Paper / dx.doi.org/10.13182/NSE74-A23330

A Criticality Study of Fissile-Metal and Fissile-Solution Combinations

D. C. Hunt, Robert E. Rothe

Nuclear Science and Engineering / Volume 53 / Number 1 / January 1974 / Pages 79-92

Technical Paper / dx.doi.org/10.13182/NSE74-A23331

Numerical Solution of the Linear Integral Boltzmann Equation

Dermott E. Cullen

Nuclear Science and Engineering / Volume 53 / Number 1 / January 1974 / Pages 93-106

Technical Paper / dx.doi.org/10.13182/NSE74-A23332

The Permeability Minimum and the Viscosity of Gases at Low Pressure

E. Creutz

Nuclear Science and Engineering / Volume 53 / Number 1 / January 1974 / Pages 107-109

Technical Paper / dx.doi.org/10.13182/NSE74-A23333

Calculated and Measured Dose Buildup Factors for Gamma Rays Penetrating Multilayered Slabs

Gail de P. Burke and Harold L. Beck

Nuclear Science and Engineering / Volume 53 / Number 1 / January 1974 / Pages 109-112

Technical Paper / dx.doi.org/10.13182/NSE74-A23334

Modified One-Mode Method for Fast-Reactor Diffusion Calculations

Takashi Kiguchi

Nuclear Science and Engineering / Volume 53 / Number 1 / January 1974 / Pages 112-120

Technical Paper / dx.doi.org/10.13182/NSE74-A23335

Number 2

Table of Contents

The Continued Fraction Approximation: A Time-Dependent Transport Method

William A. Yingling, Charles J. Bridgman

Nuclear Science and Engineering / Volume 53 / Number 2 / February 1974 / Pages 123-136

Technical Paper / dx.doi.org/10.13182/NSE74-A23338

Exact Time-Dependent Spatial and Legendre Moments for the Monoenergetic Transport Equation

E. H. Canfield

Nuclear Science and Engineering / Volume 53 / Number 2 / February 1974 / Pages 137-140

Technical Paper / dx.doi.org/10.13182/NSE74-A23339

An Analytical Estimate of the Error in Conventional Point-Kinetics Reactivity Due to Spatial Effects

George E. Apostolakis

Nuclear Science and Engineering / Volume 53 / Number 2 / February 1974 / Pages 141-152

Technical Paper / dx.doi.org/10.13182/NSE74-A23340

Neutron Slowing Down via Inelastic Scattering in Heavy Moderators—I. Steady State

Michael J. Lineberry, Noel Corngold

Nuclear Science and Engineering / Volume 53 / Number 2 / February 1974 / Pages 153-161

Technical Paper / dx.doi.org/10.13182/NSE74-A23341

Gamma-Ray Heating Measurements in Zero-Power Fast Reactors with Thermoluminescent Dosimeters

G. G. Simons, T. J. Yule

Nuclear Science and Engineering / Volume 53 / Number 2 / February 1974 / Pages 162-175

Technical Paper / dx.doi.org/10.13182/NSE74-A23342

Analyses and Measurements of Gamma-Ray Heating in the Demonstration Benchmark Plutonium-Fueled Critical Assembly

G. G. Simons, A. P. Olson

Nuclear Science and Engineering / Volume 53 / Number 2 / February 1974 / Pages 176-196

Technical Paper / dx.doi.org/10.13182/NSE74-A23343

Moments Method Calculations of Neutron Distributions in Concrete

G. L. Simmons, C. Eisenhauer

Nuclear Science and Engineering / Volume 53 / Number 2 / February 1974 / Pages 197-219

Technical Paper / dx.doi.org/10.13182/NSE74-A23344

Early Time Air Fireball Model for Near Surface Energy Release

G. C. Pomraning

Nuclear Science and Engineering / Volume 53 / Number 2 / February 1974 / Pages 220-225

Technical Paper / dx.doi.org/10.13182/NSE74-A23345

An Algorithm for the Energy Deposition by Fast Electrons

Tatsuo Tabata, Rinsuke Ito

Nuclear Science and Engineering / Volume 53 / Number 2 / February 1974 / Pages 226-239

Technical Paper / dx.doi.org/10.13182/NSE74-A23346

Pool Boiling in Subcooled Sodium at Atmospheric Pressure

M. M. K. Farahat, Donald T. Eggen, Donn R. Armstrong

Nuclear Science and Engineering / Volume 53 / Number 2 / February 1974 / Pages 240-254

Technical Note / dx.doi.org/10.13182/NSE74-A23347

A New Form of the B_N Transport Equations

J. Ligou, J. Stepanek

Nuclear Science and Engineering / Volume 53 / Number 2 / February 1974 / Pages 255-256

Technical Note / dx.doi.org/10.13182/NSE74-A23348

Angle Selection Techniques for Gamma Photons in Monte Carlo Calculations on Parallel Computers

G. P. Cavanaugh, A. B. Chilton

Nuclear Science and Engineering / Volume 53 / Number 2 / February 1974 / Pages 256-261

Technical Note / dx.doi.org/10.13182/NSE74-A23349

Deposition of Energy in U, UC, and UO₂ Fuels

K. B. Winterbon

Nuclear Science and Engineering / Volume 53 / Number 2 / February 1974 / Pages 261-262

Technical Note / dx.doi.org/10.13182/NSE74-A23350

Number 3

Table of Contents
TWOTRAN-II(K. D. Lathrop, F. W. Brinkley)
TRIPLET(W. H. Reed, T. R. Hill, F. W. Brinkley, K. D. Lathrop)
A Direct Calculation of the Time-Dependent Spatial Moments of the One-Speed Neutron Transport Model(B. D. Ganapol)
Annual Review of Nuclear Science, Volume 22(E. P. Wigner)
Fundamental Interactions and the Nucleus(W. T. Pinkston)

On the Effects of Heat Transfer upon Collapsing Bubbles

Terry Mitchell, Frederick G. Hammitt

Nuclear Science and Engineering / Volume 53 / Number 3 / March 1974 / Pages 263-276

Technical Paper / dx.doi.org/10.13182/NSE74-A23352

Neutron-Induced Gamma-Ray Production in Calcium in the Energy Range 0.7 ≤ E_n ≤ 20 MeV

J. K. Dickens, T. A. Love, G. L. Morgan

Nuclear Science and Engineering / Volume 53 / Number 3 / March 1974 / Pages 277-284

Technical Paper / dx.doi.org/10.13182/NSE74-A23353

Transport Analysis of Measured Neutron Leakage Spectra from Spheres as Tests of Evaluated High-Energy Cross Sections

Donald Bogart, Donald F. Shook, Daniel Fieno

Nuclear Science and Engineering / Volume 53 / Number 3 / March 1974 / Pages 285-303

Technical Paper / dx.doi.org/10.13182/NSE74-A23354

Cross-Section Sensitivity of Breeding Ratio in a Fusion-Reactor Blanket

D. E. Bartine, R. G. Alsmiller, Jr., E. M. Oblow, F. R. Mynatt

Nuclear Science and Engineering / Volume 53 / Number 3 / March 1974 / Pages 304-318

Technical Paper / dx.doi.org/10.13182/NSE74-A23355

Transmutation of Massive Loadings of Cesium-137 in the Blanket of a Controlled Thermonuclear Reactor

B. F. Gore, B. R. Leonard, Jr.

Nuclear Science and Engineering / Volume 53 / Number 3 / March 1974 / Pages 319-323

Technical Note / dx.doi.org/10.13182/NSE74-A23356

Calculated Secondary-Particle Spectra from Alpha-Particle- and Carbon-Induced Nuclear Reactions

T. A. Gabriel, R. T. Santoro, H. W. Bertini, N. M. Larson

Nuclear Science and Engineering / Volume 53 / Number 3 / March 1974 / Pages 323-325

Technical Note / dx.doi.org/10.13182/NSE74-A23357

The Effective Half-Life of Californium-252

V. Spiegel

Nuclear Science and Engineering / Volume 53 / Number 3 / March 1974 / Pages 326-327

Technical Note / dx.doi.org/10.13182/NSE74-A23358

An Iterated Sequential Transport Approximation for Anisotropic Spectral Moments

D. C. Gibbs, M. Becker, B. K. Malaviya

Nuclear Science and Engineering / Volume 53 / Number 3 / March 1974 / Pages 327-329

Technical Note / dx.doi.org/10.13182/NSE74-A23359

Transport Equation in an Accelerated Material, Legendre Moments, and a Diffusion Approximation

B. R. Wienke

Nuclear Science and Engineering / Volume 53 / Number 3 / March 1974 / Pages 329-332

Technical Note / dx.doi.org/10.13182/NSE74-A23360

Forward-Adjoint Coupling as a Means of Solving Three-Dimensional Deep-Penetration Transport Problems

C. O. Slater, J. C. Robinson

Nuclear Science and Engineering / Volume 53 / Number 3 / March 1974 / Pages 332-337

Technical Note / dx.doi.org/10.13182/NSE74-A23361

Few-Group Methods for Fast-Reactor Transients

William B. Terney, R. Srivenkatesan

Nuclear Science and Engineering / Volume 53 / Number 3 / March 1974 / Pages 337-347

Technical Note / dx.doi.org/10.13182/NSE74-A23362

Number 4

Table of Contents
Scattering Theory(Paul F. Zweifel)
The Invariant Imbedding Theory of Nuclear Transport(G. C. Pomraning)
Environmental Radioactivity(Karl Z. Morgan)
Measurement of the ⁵⁹Ni(n,α) Cross Section for Thermal Neutrons(H. M. Eiland, G. J. Kirouac)

Solution of Standard Diamond Difference Equations for Discrete-Ordinate Neutron Transport Equations Equivalent to the P_L Approximation in x-y Geometry

Jungchung Jung, Nobuo Ohtani, Keisuke Kobayashi, Hiroshi Nishihara

Nuclear Science and Engineering / Volume 53 / Number 4 / April 1974 / Pages 355-369

Technical Paper / dx.doi.org/10.13182/NSE74-A23369

Relative and Absolute Measurements of the Fast-Neutron Fission Cross Section of Uranium-235

W. P. Poenitz

Nuclear Science and Engineering / Volume 53 / Number 4 / April 1974 / Pages 370-392

Technical Paper / dx.doi.org/10.13182/NSE74-A23370

The Use of Californium-252 as a Randomly Pulsed Neutron Source for Prompt-Neutron Decay Measurements

J. T. Mihalczo

Nuclear Science and Engineering / Volume 53 / Number 4 / April 1974 / Pages 393-414

Technical Paper / dx.doi.org/10.13182/NSE74-5

A Study of the 2.8-keV Neutron Resonance of Sodium and an Analysis of the Total Neutron Cross Section up to 50 keV

Janet Seltzer, W. K. Firk

Nuclear Science and Engineering / Volume 53 / Number 4 / April 1974 / Pages 415-419

Technical Paper / dx.doi.org/10.13182/NSE74-A23372

Fine Neutron-Spectrum Effects on Spatial Calculations for Fast-Reactor Design

R. Corcuera, A. Khairallah

Nuclear Science and Engineering / Volume 53 / Number 4 / April 1974 / Pages 420-435

Technical Paper / dx.doi.org/10.13182/NSE74-A23373

A Method of Computing Fission-Product Decay Heat in a Reactor with Time-Dependent Flux

F. W. Barclay, K. W. Dormuth

Nuclear Science and Engineering / Volume 53 / Number 4 / April 1974 / Pages 436-439

Technical Paper / dx.doi.org/10.13182/NSE74-A23374

SINOD—A Nonlinear Lumped-Parameter Model for Steady-State, Transient, and Stability Analysis of Two-Phase Flow in Natural Circulation Boiling-Water Loops

M. R. Mataušek

Nuclear Science and Engineering / Volume 53 / Number 4 / April 1974 / Pages 440-457

Technical Paper / dx.doi.org/10.13182/NSE74-A23375

Radiation-Induced Boiling in Superheated Water and Organic Liquids

C. R. Bell, N. P. Oberle, W. Rohsenow, N. Todreas, C. Tso

Nuclear Science and Engineering / Volume 53 / Number 4 / April 1974 / Pages 458-465

Technical Paper / dx.doi.org/10.13182/NSE74-A23376

Equations of Motion of a Liquid-Submerged Sonic Gas Jet Relative to Fission-Gas-Jet Impingement in Subassemblies of the Liquid Metal Fast Breeder Reactor

T. C. Chawla

Nuclear Science and Engineering / Volume 53 / Number 4 / April 1974 / Pages 466-474

Technical Paper / dx.doi.org/10.13182/NSE74-A23377

Reciprocity Relations in Response Matrix Theory

Sten-Örjan Lindahl

Nuclear Science and Engineering / Volume 53 / Number 4 / April 1974 / Pages 475-478

Technical Note / dx.doi.org/10.13182/NSE74-A23378

The Effect of Local Flux Distortions on the Doppler Effect of Small Fissile Samples

P. H. Kier, M. Salvatores

Nuclear Science and Engineering / Volume 53 / Number 4 / April 1974 / Pages 479-482

Technical Note / dx.doi.org/10.13182/NSE74-A23379

Relationships Between Experimental and Theoretical Parameters in Unresolved Resonance Theory

M. Gyulassy, S. T. Perkins

Nuclear Science and Engineering / Volume 53 / Number 4 / April 1974 / Pages 482-486

Technical Note / dx.doi.org/10.13182/NSE74-A23380

An Assessment of Proposed (n, γn<’) Data Based on Measured and Calculated Neutron Spectra in Uranium Depleted in Uranium-235

Martin Becker, Narinder N. Kaushal

Nuclear Science and Engineering / Volume 53 / Number 4 / April 1974 / Pages 487-488

Technical Note / dx.doi.org/10.13182/NSE74-A23381