ANS / Publications / Journals / Nuclear Science and Engineering

The Matching of Dense Plasma Focus Devices with Fission Reactors

A. A. Harms, M. Heindler

Nuclear Science and Engineering / Volume 66 / Number 1 / April 1978 / Pages 1-8

Technical Paper / dx.doi.org/10.13182/NSE78-A15182

Optimum Supervision Intervals and Order of Supervision in Nuclear Reactor Protective Systems

J. M. Kontoleon

Nuclear Science and Engineering / Volume 66 / Number 1 / April 1978 / Pages 9-13

Technical Paper / dx.doi.org/10.13182/NSE78-A15183

Probabilistic Accident Analysis with Deterministic Codes Using Stochastically Variable Parameters

P. B. Abramson, H. H. Hummel, E. M. Gelbard, P. A. Pizzica, J. J. Sienicki

Nuclear Science and Engineering / Volume 66 / Number 1 / April 1978 / Pages 14-23

Technical Paper / dx.doi.org/10.13182/NSE78-A15184

Angular Distribution of Fission Fragments from Fast Fission of Uranium-235

S. T. Hsue, G. F. Knoll, J. Meadows

Nuclear Science and Engineering / Volume 66 / Number 1 / April 1978 / Pages 24-28

Technical Paper / dx.doi.org/10.13182/NSE78-A15185

Determination of Reactivity from Power Spectral Density Measurements with Californium-252

J. T. Mihalczo, V. K. Paré, G. L. Ragan, M. V. Mathis, G. C. Tillett

Nuclear Science and Engineering / Volume 66 / Number 1 / April 1978 / Pages 29-59

Technical Paper / dx.doi.org/10.13182/NSE78-A15186

A Monte Carlo Perturbation Source Method for Reactivity Calculations

T. J. Hoffman, L. M. Petrie, N. F. Landers

Nuclear Science and Engineering / Volume 66 / Number 1 / April 1978 / Pages 60-66

Technical Paper / dx.doi.org/10.13182/NSE78-A15187

Calculation of the Reactivity due to Bubble Collapse with the Probability Table Method

T. J. Hoffman, L. M. Petrie

Nuclear Science and Engineering / Volume 66 / Number 1 / April 1978 / Pages 67-74

Technical Paper / dx.doi.org/10.13182/NSE78-A15188

Gamma-Ray Production Cross Sections of Neutron-Induced Reactions in Oxygen

C. Nordborg, L. Nilsson, H. Condé, L. G. Strömberg

Nuclear Science and Engineering / Volume 66 / Number 1 / April 1978 / Pages 75-83

Technical Paper / dx.doi.org/10.13182/NSE78-A15189

Finite Element Analysis for Turbulent Flows of Incompressible Fluids in Fuel Rod Bundles

W. Slagter

Nuclear Science and Engineering / Volume 66 / Number 1 / April 1978 / Pages 84-92

Technical Paper / dx.doi.org/10.13182/NSE78-A15190

Characteristics, Stability, and Short-Wavelength Phenomena in Two-Phase Flow Equation Systems

John D. Ramshaw, John A. Trapp

Nuclear Science and Engineering / Volume 66 / Number 1 / April 1978 / Pages 93-102

Technical Paper / dx.doi.org/10.13182/NSE78-A15191

Experimental Investigation of Gas Evolution as the Mechanism for Free-Contact Fragmentation

G. Shiralker, W. Rohsenow, A. Sonin, N. Todreas

Nuclear Science and Engineering / Volume 66 / Number 1 / April 1978 / Pages 103-109

Technical Paper / dx.doi.org/10.13182/NSE78-A15192

The Oxidation and Degradation of Short-Chain Aliphatic Compounds by Hyperazeotropic Nitric Acid

Walter E. Clark, W. B. Howerton, B. M. Benjamin, W. H. Baldwin

Nuclear Science and Engineering / Volume 66 / Number 1 / April 1978 / Pages 110-117

Technical Paper / dx.doi.org/10.13182/NSE78-A15193

A Semi-Analytic Solution to the Transport Equation in Spherical Geometry

A. Dubi, Y. S. Horowitz

Nuclear Science and Engineering / Volume 66 / Number 1 / April 1978 / Pages 118-121

Technical Note / dx.doi.org/10.13182/NSE78-A15194

General Formulation of Track-Length-Type Estimators

I. Lux

Nuclear Science and Engineering / Volume 66 / Number 1 / April 1978 / Pages 121-124

Technical Note / dx.doi.org/10.13182/NSE78-A15195

Applications of the Upper Bound Estimation Method in Reactor Theory

Yigal Ronen, Dror Regev

Nuclear Science and Engineering / Volume 66 / Number 1 / April 1978 / Pages 124-127

Technical Note / dx.doi.org/10.13182/NSE78-A15196

Thermal Westcott g-Factor Measurement for Thorium-232

L. Green

Nuclear Science and Engineering / Volume 66 / Number 1 / April 1978 / Pages 127-134

Technical Note / dx.doi.org/10.13182/NSE78-A15197

A Multigroup Formalism for Evaluation of Continuous Slowing Down Theory Parameters

Ansar Parvez, Martin Becker

Nuclear Science and Engineering / Volume 66 / Number 1 / April 1978 / Pages 134-140

Technical Note / dx.doi.org/10.13182/NSE78-A15198

Modeling the Effect of Fission Product Capture on Reactor Decay Power

B. I. Spinrad, A. Tripathi

Nuclear Science and Engineering / Volume 66 / Number 1 / April 1978 / Pages 140-141

Technical Note / dx.doi.org/10.13182/NSE78-A15199

Note on ²³⁸U + n Resolved Resonance Energies

D. K. Olsen, G. de Saussure, R. B. Perez, F. C. Difilippo, and R. W. Ingle

Nuclear Science and Engineering / Volume 66 / Number 1 / April 1978 / Pages 141-144

Technical Note / dx.doi.org/10.13182/NSE78-A15200

Critical Impurity Concentrations for Ignition of Catalyzed-Deuterium Fusion Plasmas

R. V. Jensen, D. L. Jassby, D. E. Post

Nuclear Science and Engineering / Volume 66 / Number 1 / April 1978 / Pages 144-146

Technical Note / dx.doi.org/10.13182/NSE78-A15201

An Experimental Study of the Molten Glass/Water Thermal Interaction Under Free and Forced Conditions

V. H. Arakeri, I. Catton, and W. E. Kastenberg

Nuclear Science and Engineering / Volume 66 / Number 2 / May 1978 / Pages 153-166

Technical Paper / dx.doi.org/10.13182/NSE78-A27197

Fissile Fuel Doubling Time Characteristics for Reactor Lifetime Fuel Logistics

M. Heindler and A. A. Harms

Nuclear Science and Engineering / Volume 66 / Number 2 / May 1978 / Pages 167-187

Technical Paper / dx.doi.org/10.13182/NSE78-A27198

Cross Sections for the ¹¹B(α, p)¹⁴C Reaction in the Alpha-Particle Energy Range from 4.4 to 6.7 MeV

Wen-Sou Hou, Chia-Shou Lin, Ming Wen, Hsiao-Hua Hsu, and Jen-Chang Chou

Nuclear Science and Engineering / Volume 66 / Number 2 / May 1978 / Pages 188-192

Technical Paper / dx.doi.org/10.13182/NSE78-A27199

Spectral Fine-Structure Effects in the Reactivity-Reaction-Rate Method for Determining Capture-to-Fission Ratios

E. Greenspan, Y. Karni

Nuclear Science and Engineering / Volume 66 / Number 2 / May 1978 / Pages 193-204

Technical Paper / dx.doi.org/10.13182/NSE78-A27200

Measurement of the Fission Cross Sections of Uranium-233 and Plutonium-239 Relative to Uranium-235 from 1 keV to 30 MeV

G. W. Carlson and J. W. Behrens

Nuclear Science and Engineering / Volume 66 / Number 2 / May 1978 / Pages 205-216

Technical Paper / dx.doi.org/10.13182/NSE78-1

Neutron Capture Probabilities for Thick Samples at Resonance Energies

Makio Ohkubo

Nuclear Science and Engineering / Volume 66 / Number 2 / May 1978 / Pages 217-228

Technical Paper / dx.doi.org/10.13182/NSE78-A27202

The Importance Factor of a Source in Reactor Kinetics

J. Ligou

Nuclear Science and Engineering / Volume 66 / Number 2 / May 1978 / Pages 229-234

Technical Paper / dx.doi.org/10.13182/NSE78-A27203

Polynomial Approach to Reactor Kinetics Equations

Kueng Yeh

Nuclear Science and Engineering / Volume 66 / Number 2 / May 1978 / Pages 235-242

Technical Paper / dx.doi.org/10.13182/NSE78-A27204

Cross-Section Sensitivity Analysis of ²³⁵U and ²³⁸U Fission Rates Measured in a Graphite-Reflected Lithium Assembly

Yasushi Seki and Hiroshi Maekawa

Nuclear Science and Engineering / Volume 66 / Number 2 / May 1978 / Pages 243-251

Technical Note / dx.doi.org/10.13182/NSE78-A27205

Extension of the Width Fluctuation Correction to Reactions Involving Continuum Level Excitations

G. Reffo and F. Fabbri

Nuclear Science and Engineering / Volume 66 / Number 2 / May 1978 / Pages 251-254

Technical Note / dx.doi.org/10.13182/NSE78-A27206

On Approximations to the Neutron Escape Probability from an Absorbing Body

Yung-An Chao, Aquilino Senra Martinez

Nuclear Science and Engineering / Volume 66 / Number 2 / May 1978 / Pages 254-258

Technical Note / dx.doi.org/10.13182/NSE66-254

Remark on the Efficiency of Track-Length Estimators in Reaction Rate Estimations

I. Lux

Nuclear Science and Engineering / Volume 66 / Number 2 / May 1978 / Pages 258-264

Technical Note / dx.doi.org/10.13182/NSE78-A27208

Determination of Void Fraction Profile in a Boiling Water Reactor Channel Using Neutron Noise Analysis

M. Ashraf Atta, D. N. Fry, J. E. Mott, and W. T. King

Nuclear Science and Engineering / Volume 66 / Number 2 / May 1978 / Pages 264-268

Technical Note / dx.doi.org/10.13182/NSE78-A27209

Higher Order Prompt-Jump Approximation in Reactor Kinetics

Tomasz Błeński, Adam Gadomski, Janusz Mika

Nuclear Science and Engineering / Volume 66 / Number 3 / June 1978 / Pages 277-283

Technical Paper / dx.doi.org/10.13182/NSE78-A27212

Analysis of the Eigenvalue Equations in k, λ, γ, and α Applied to Some Fast- and Thermal-Neutron Systems

Guillermo Velarde, Carolina Ahnert, José M. Aragonés

Nuclear Science and Engineering / Volume 66 / Number 3 / June 1978 / Pages 284-294

Technical Paper / dx.doi.org/10.13182/NSE78-A27213

Polynomial Solutions to the Tensorial Differential Equations for Monoenergetic Neutrons in Slab and Sphere Geometries

P. Landini, G. Spiga, F. Premuda

Nuclear Science and Engineering / Volume 66 / Number 3 / June 1978 / Pages 295-306

Technical Paper / dx.doi.org/10.13182/NSE78-A27214

Application of Sensitivity and Uncertainty Methodology to Fast Reactor Integral Experiment Analysis

C. R. Weisbin, E. M. Oblow, J. H. Marable, R. W. Peelle, J. L. Lucius

Nuclear Science and Engineering / Volume 66 / Number 3 / June 1978 / Pages 307-333

Technical Paper / dx.doi.org/10.13182/NSE78-3

Calculation of Nuclear Level Densities for ⁵⁶Fe, ⁵⁹Co, ⁶⁰Ni, ⁶¹Cu, ⁶²Ni, ⁶³Cu, and ⁶⁵Cu

G. P. Ford

Nuclear Science and Engineering / Volume 66 / Number 3 / June 1978 / Pages 334-348

Technical Paper / dx.doi.org/10.13182/NSE78-A27216

Precise Measurement of the Capture Width of the 6.67-eV Neutron Resonance of Uranium-238

P. Staveloz, F. Poortmans, L. Mewissen, E. Cornelis

Nuclear Science and Engineering / Volume 66 / Number 3 / June 1978 / Pages 349-353

Technical Paper / dx.doi.org/10.13182/NSE78-A27217

Measurement and Calculation of Californium-252 Fission Neutron-Induced Gamma Fields in Iron

S. H. Jiang, H. Werle

Nuclear Science and Engineering / Volume 66 / Number 3 / June 1978 / Pages 354-362

Technical Paper / dx.doi.org/10.13182/NSE78-A27218

Neutron Capture Cross-Section Ratios of ²⁴⁰Pu, ²⁴²Pu, ²³⁸U, and ¹⁹⁷Au in the Energy Range from 10 to 90 keV

K. Wisshak, F. Käppeler

Nuclear Science and Engineering / Volume 66 / Number 3 / June 1978 / Pages 363-377

Technical Paper / dx.doi.org/10.13182/NSE78-A27219

Characteristics and Stability Analyses of Transient One-Dimensional Two-Phase Flow Equations and Their Finite Difference Approximations

Robert W. Lyczkowski, Dimitri Gidaspow, Charles W. Solbrig, E. D. Hughes

Nuclear Science and Engineering / Volume 66 / Number 3 / June 1978 / Pages 378-396

Technical Paper / dx.doi.org/10.13182/NSE78-4

Effects of Internal Circulation Velocity and Noncondensable Gas on Vapor Condensation from a Rising Bubble

M. N. Özişik, T. S. Kress

Nuclear Science and Engineering / Volume 66 / Number 3 / June 1978 / Pages 397-405

Technical Paper / dx.doi.org/10.13182/NSE78-A27221

Self-Diffusion Processes in Nuclear Carbonitrides UC_xN_{1 − x} and (U, Pu)C_0.8N_0.2

H. Matsui, M. H. Bradbury, Hj. Matzke

Nuclear Science and Engineering / Volume 66 / Number 3 / June 1978 / Pages 406-414

Technical Paper / dx.doi.org/10.13182/NSE78-A27222

Fast Power Excursions in Pebble-Bed Reactors—Methods and Results

K. Friedrich, E. Inführ, U. Weicht

Nuclear Science and Engineering / Volume 66 / Number 3 / June 1978 / Pages 415-421

Technical Note / dx.doi.org/10.13182/NSE78-A27223

A General Correlation for Independent Fission Product Yield Uncertainties

B. I. Spinrad, C. H. Wu

Nuclear Science and Engineering / Volume 66 / Number 3 / June 1978 / Pages 421-424

Technical Note / dx.doi.org/10.13182/NSE78-A27224

Evaluation of the Neutron Flux-Depression Factor via the Integral Transform Method

V. C. Boffi, V. G. Molinari, G. Spiga

Nuclear Science and Engineering / Volume 66 / Number 3 / June 1978 / Pages 424-428

Technical Note / dx.doi.org/10.13182/NSE78-A27225

Transport of Neutron and Secondary Gamma Radiations Through a Liquid Air Sphere Surrounding a 14-MeV Neutron Source

G. S. Sidhu, W. E. Farley, L. F. Hansen, T. Komoto, B. Pohl, C. Wong

Nuclear Science and Engineering / Volume 66 / Number 3 / June 1978 / Pages 428-433

Technical Note / dx.doi.org/10.13182/NSE78-A27226

Measurements of the Neutron-Induced Fission Cross Sections of ²⁴⁰Pu, ²⁴²Pu, and ²⁴⁴Pu Relative to ²³⁵U from 0.1 to 30 MeV

J. W. Behrens, R. S. Newbury, J. W. Magana

Nuclear Science and Engineering / Volume 66 / Number 3 / June 1978 / Pages 433-441

Technical Note / dx.doi.org/10.13182/NSE78-A27227

⁶Li + ⁶Li ⇒ 3⁴He Cross Sections and Thermonuclear Fusion Parameters

E. Norbeck

Nuclear Science and Engineering / Volume 66 / Number 3 / June 1978 / Pages 441-444

Technical Note / dx.doi.org/10.13182/NSE78-A27228