ANS / Publications / Journals / Nuclear Science and Engineering

Iterative and Direct Approaches to the Critical Dominant Eigenfunction in Three-Dimensional Neutron Transport

F. Premuda, G. Spiga

Nuclear Science and Engineering / Volume 63 / Number 1 / May 1977 / Pages 1-8

Technical Paper / dx.doi.org/10.13182/NSE77-A26998

Monte Carlo Treatment of Fundamental-Mode Neutron Leakage in the Presence of Voids

Ely M. Gelbard, Richard Lell

Nuclear Science and Engineering / Volume 63 / Number 1 / May 1977 / Pages 9-23

Technical Paper / dx.doi.org/10.13182/NSE77-A26999

Neutron Wave Propagation Across a Temperature Discontinuity

Ashok Kumar, N. K. Saxena, L. S. Kothari

Nuclear Science and Engineering / Volume 63 / Number 1 / May 1977 / Pages 24-30

Technical Paper / dx.doi.org/10.13182/NSE77-A27000

Neutron Kinetics of Highly Compressed Fissionable Pellets

J. Ligou

Nuclear Science and Engineering / Volume 63 / Number 1 / May 1977 / Pages 31-40

Technical Paper / dx.doi.org/10.13182/NSE77-A27001

Origin of Protons in Californium-252 Fission

John A. Adams, R. R. Roy

Nuclear Science and Engineering / Volume 63 / Number 1 / May 1977 / Pages 41-47

Technical Paper / dx.doi.org/10.13182/NSE77-A27002

Neutron and Gamma Radiation from a Nitrogen Sphere Surrounding a D-T Neutron Source

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

Nuclear Science and Engineering / Volume 63 / Number 1 / May 1977 / Pages 48-54

Technical Paper / dx.doi.org/10.13182/NSE77-A27003

A Comparison of the Gamma-Ray Spectra from 2.8-keV Neutron Capture and Thermal-Neutron Capture in Sodium-23

W. M. Wilson, H. E. Jackson, G. E. Thomas

Nuclear Science and Engineering / Volume 63 / Number 1 / May 1977 / Pages 55-62

Technical Paper / dx.doi.org/10.13182/NSE77-A27004

Structure-Fluid Interaction Between a Vibrating Wall and Flow in a Channel

R. A. Bajura, A. H. Mace, Jr.

Nuclear Science and Engineering / Volume 63 / Number 1 / May 1977 / Pages 63-74

Technical Paper / dx.doi.org/10.13182/NSE77-A27005

Steady-State Natural Circulation Performance of the Experimental Breeder Reactor II Primary Heat Transport Circuit

Ralph M. Singer, Jerry L. Gillette, Gerald H. Golden, Dale Mohr, Wayne K. Lehto, Charles C. Price, John I. Sackett

Nuclear Science and Engineering / Volume 63 / Number 1 / May 1977 / Pages 75-82

Technical Paper / dx.doi.org/10.13182/NSE77-A27006

The Effect of Niobium Additions on the Corrosion Behavior of Zircaloy-4

G. P. Sabol, S. G. McDonald

Nuclear Science and Engineering / Volume 63 / Number 1 / May 1977 / Pages 83-90

Technical Paper / dx.doi.org/10.13182/NSE77-A27007

Selection of Angular Quadrature for Anisotropic Transport Computations

Wayne J. Mikols, J. Kenneth Shultis

Nuclear Science and Engineering / Volume 63 / Number 1 / May 1977 / Pages 91-95

Technical Note / dx.doi.org/10.13182/NSE77-A27008

On the Inverse Problem for Multigroup Neutron Transport Theory

C. E. Siewert, M. N. Özişik, Y. Yener

Nuclear Science and Engineering / Volume 63 / Number 1 / May 1977 / Pages 95-96

Technical Note / dx.doi.org/10.13182/NSE77-A27009

Rapid Method of Calculating the Fluence and Spectrum of Neutrons from a Critical Assembly and the Resulting Dose

Joseph Bessis

Nuclear Science and Engineering / Volume 63 / Number 1 / May 1977 / Pages 96-101

Technical Note / dx.doi.org/10.13182/NSE77-A27010

Neutron-Induced Gamma-Ray Production in Lead-208 for Incident-Neutron Energies Between 4.9 and 8.0 MeV and in Bismuth-209 for an Incident-Neutron Energy of 5.4 MeV

J. K. Dickens

Nuclear Science and Engineering / Volume 63 / Number 1 / May 1977 / Pages 101-109

Technical Note / dx.doi.org/10.13182/NSE77-A27011

Natural Convection in Porous Media with Heat Generation

H. C. Hardee, R. H. Nilson

Nuclear Science and Engineering / Volume 63 / Number 2 / June 1977 / Pages 119-132

Technical Paper / dx.doi.org/10.13182/NSE77-A27015

Release of Adsorbed Krypton and Xenon from Spilled Charcoal

Dwight W. Underhill

Nuclear Science and Engineering / Volume 63 / Number 2 / June 1977 / Pages 133-142

Technical Paper / dx.doi.org/10.13182/NSE77-A27016

Neutron Capture Cross Section of Plutonium-240

L. W. Weston, J. H. Todd

Nuclear Science and Engineering / Volume 63 / Number 2 / June 1977 / Pages 143-148

Technical Paper / dx.doi.org/10.13182/NSE77-A27017

A Measurement of the Fission Cross Section of Plutonium-241 from 8 eV to 70 keV

G. W. Carlson, J. W. Behrens, J. B. Czirr

Nuclear Science and Engineering / Volume 63 / Number 2 / June 1977 / Pages 149-152

Technical Paper / dx.doi.org/10.13182/NSE77-A27018

Measurement of the Uranium-238 Subthreshold Fission Cross Section for Incident Neutron Energies Between 0.6 and 100 keV

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

Nuclear Science and Engineering / Volume 63 / Number 2 / June 1977 / Pages 153-166

Technical Paper / dx.doi.org/10.13182/NSE77-A27019

Solution of the Finite Element Diffusion and P₁ Equations by Iteration

E. T. Tomlinson, J. C. Robinson

Nuclear Science and Engineering / Volume 63 / Number 2 / June 1977 / Pages 167-178

Technical Paper / dx.doi.org/10.13182/NSE77-A27020

Exponential Supplementary Equations for S_N Methods: The One-Dimensional Case

P. Barbucci, F. Di Pasquantonio

Nuclear Science and Engineering / Volume 63 / Number 2 / June 1977 / Pages 179-187

Technical Paper / dx.doi.org/10.13182/NSE77-A27021

Laminar Heat Transfer Data with a Step-Varying Wall Heat Flux

Otto I. Reisman, Robert O. Parker

Nuclear Science and Engineering / Volume 63 / Number 2 / June 1977 / Pages 188-191

Technical Note / dx.doi.org/10.13182/NSE77-A27022

The Trapping Efficiency of Molten Lithium for 20-keV Tritium Ions

Albert K. Fischer, David V. Steidl, Charles E. Brient, Fred A. Cafasso, Carl E. Johnson

Nuclear Science and Engineering / Volume 63 / Number 2 / June 1977 / Pages 191-193

Technical Note / dx.doi.org/10.13182/NSE77-A27023

High-Resolution Gamma-Ray Spectrum from Concrete

S. K. Gupta

Nuclear Science and Engineering / Volume 63 / Number 2 / June 1977 / Pages 193-197

Technical Note / dx.doi.org/10.13182/NSE77-A27024

Cross Section for the Production of Beryllium-7 from Lithium-6, Lithium-6 Interactions

Lawrence Ruby, Robert V. Pyle, Yue-Chau Wong

Nuclear Science and Engineering / Volume 63 / Number 2 / June 1977 / Pages 197-198

Technical Note / dx.doi.org/10.13182/NSE77-A27025

Fission Cross Section of Berkelium-249 Between 0.7 and 3.0 MeV

M. G. Silbert

Nuclear Science and Engineering / Volume 63 / Number 2 / June 1977 / Pages 198-200

Technical Note / dx.doi.org/10.13182/NSE77-A27026

Hydrogen and Helium Production Cross Sections for 15-MeV Neutrons on Types 316 and 304 Stainless Steel

R. C. Haight, S. M. Grimes, J. D. Anderson

Nuclear Science and Engineering / Volume 63 / Number 2 / June 1977 / Pages 200-204

Technical Note / dx.doi.org/10.13182/NSE77-A27027

Accurate Approximations to Average Beta-Particle Energies and Spectra

M. G. Stamatelatos, T. R. England

Nuclear Science and Engineering / Volume 63 / Number 2 / June 1977 / Pages 204-208

Technical Note / dx.doi.org/10.13182/NSE77-A27028

Monte Carlo Calculations of Cadmium Cutoff Energies and an Ansatz Formula

S. Fiarman, R. Sher

Nuclear Science and Engineering / Volume 63 / Number 2 / June 1977 / Pages 208-212

Technical Note / dx.doi.org/10.13182/NSE77-A27029

Wigner-Type Continuous Slowing Down Theory for the Fast-Neutron Spectrum

Yasunori Yamamura, Tamotsu Sekiya

Nuclear Science and Engineering / Volume 63 / Number 2 / June 1977 / Pages 213-217

Technical Note / dx.doi.org/10.13182/NSE77-A27030

Discrete Neutron Decay Constants Above the Corngold Limit for Infinite Slabs

N. G. Sjöstrand

Nuclear Science and Engineering / Volume 63 / Number 2 / June 1977 / Pages 217-218

Technical Note / dx.doi.org/10.13182/NSE77-A27031

A Comparison of Constrained Finite Elements and Response Matrices as One-Dimensional Transport Approximations

L. L. Briggs, E. E. Lewis

Nuclear Science and Engineering / Volume 63 / Number 3 / July 1977 / Pages 225-235

Technical Paper / dx.doi.org/10.13182/NSE77-A27035

Elastic Neutron Scattering from Distributed Fusion Neutrons, Deuterium, Tritium, and Lithium, and Multigroup Rate Coefficients

B. R. Wienke, R. E. Seamon

Nuclear Science and Engineering / Volume 63 / Number 3 / July 1977 / Pages 236-241

Technical Paper / dx.doi.org/10.13182/NSE77-A27036

Calculated Neutron Capture Cross Sections to the Americium Ground and Isomeric States

F. M. Mann, R. E. Schenter

Nuclear Science and Engineering / Volume 63 / Number 3 / July 1977 / Pages 242-249

Technical Paper / dx.doi.org/10.13182/NSE77-A27037

Measurements of the Neutron-Induced Fission Cross Sections of ²³⁴U, ²³⁶U, and ²³⁸U Relative to ²³⁵U from 0.1 to 30 MeV

J. W. Behrens, G. W. Carlson

Nuclear Science and Engineering / Volume 63 / Number 3 / July 1977 / Pages 250-267

Technical Paper / dx.doi.org/10.13182/NSE77-2

Measurement of the ⁵⁸Ni(n, p)⁵⁸Co Cross Section with H(n, n)p as a Standard

Mien-Win Wu, Jen-Chang Chou

Nuclear Science and Engineering / Volume 63 / Number 3 / July 1977 / Pages 268-275

Technical Paper / dx.doi.org/10.13182/NSE77-A27039

Uncertainties in Fission Product Decay-Heat Calculations

F. Schmittroth, R. E. Schenter

Nuclear Science and Engineering / Volume 63 / Number 3 / July 1977 / Pages 276-291

Technical Paper / dx.doi.org/10.13182/NSE77-A27040

Thermal-Neutron Behavior in Cluster-Type Plutonium Fuel Lattices

T. Wakabayashi, Y. Hachiya

Nuclear Science and Engineering / Volume 63 / Number 3 / July 1977 / Pages 292-305

Technical Paper / dx.doi.org/10.13182/NSE77-A27041

Theoretical Investigation of the Local and Global Components of the Neutron-Noise Field in a Boiling Water Reactor

K. Behringer, G. Kosály, Lj. Kostić

Nuclear Science and Engineering / Volume 63 / Number 3 / July 1977 / Pages 306-318

Technical Paper / dx.doi.org/10.13182/NSE77-A27042

Effects of Fast-Neutron Irradiation and High-Intensity Magnetic Fields upon Cavitation Thresholds and Nuclei Spectra in Water

E. Yilmaz, F. G. Hammitt

Nuclear Science and Engineering / Volume 63 / Number 3 / July 1977 / Pages 319-329

Technical Paper / dx.doi.org/10.13182/NSE77-A27043

Determination of the Probing Distance in Pulsed-Neutron Uranium Logging Experiments

James H. Renken

Nuclear Science and Engineering / Volume 63 / Number 3 / July 1977 / Pages 330-335

Technical Paper / dx.doi.org/10.13182/NSE77-A27044

A Parametric Analysis of the Spallation Breeder

A. A. Harms, C. W. Gordon

Nuclear Science and Engineering / Volume 63 / Number 3 / July 1977 / Pages 336-341

Technical Note / dx.doi.org/10.13182/NSE77-A27045

The Tritium Production in a Controlled Thermonuclear Reactor Blanket Model with a Graphite Reflector

R. Herzing, L. Kuijpers, P. Cloth, D. Filges, R. Hecker, N. Kirch

Nuclear Science and Engineering / Volume 63 / Number 3 / July 1977 / Pages 341-343

Technical Note / dx.doi.org/10.13182/NSE77-A27046

Thermonuclear Reaction Rate Parameters for d + ⁶Li Reactions

A. J. Elwyn, J. E. Monahan, F. J. D. Serduke

Nuclear Science and Engineering / Volume 63 / Number 3 / July 1977 / Pages 343-346

Technical Note / dx.doi.org/10.13182/NSE77-A27047

A Perturbation Analysis of Changes in Prompt Fission Neutron Uranium-Logging Signals Produced by Trace Neutron-Absorbing Rock Constituents

James H. Renken

Nuclear Science and Engineering / Volume 63 / Number 3 / July 1977 / Pages 347-349

Technical Note / dx.doi.org/10.13182/NSE77-A27048

Solidification of a Sphere with Internal Heat Generation and Convective Cooling at the Surface

Vijay K. Dhir, Kin Wong, W. E. Kastenberg

Nuclear Science and Engineering / Volume 63 / Number 3 / July 1977 / Pages 350-356

Technical Note / dx.doi.org/10.13182/NSE77-A27049

Nonequilibrium Critical Discharge of Saturated and Subcooled Liquid Freon-11

Michael R. Prisco, Robert E. Henry, Michael N. Hutcherson, John L. Linehan

Nuclear Science and Engineering / Volume 63 / Number 4 / August 1977 / Pages 365-375

Technical Paper / dx.doi.org/10.13182/NSE77-A27054

Estimation of Nuclear Decay Heat for Short-Lived Fission Products

Tadashi Yoshida

Nuclear Science and Engineering / Volume 63 / Number 4 / August 1977 / Pages 376-390

Technical Paper / dx.doi.org/10.13182/NSE77-A27055

Neutron Thermalization Spectrum in a Partially Hydrogenated Terphenyl: Evaluation of Scattering Kernels for Organic Reactor Coolant

H. Alan Robitaille, John S. Hewitt

Nuclear Science and Engineering / Volume 63 / Number 4 / August 1977 / Pages 391-400

Technical Paper / dx.doi.org/10.13182/NSE77-A27056

Double-Differential Beryllium Neutron Cross Sections at Incident Neutron Energies of 5.9, 10.1, and 14.2 MeV

D. M. Drake, G. F. Auchampaugh, E. D. Arthur, C. E. Ragan, P. G. Young

Nuclear Science and Engineering / Volume 63 / Number 4 / August 1977 / Pages 401-412

Technical Paper / dx.doi.org/10.13182/NSE77-A27057

Thermal-Neutron Capture and Fission Cross Sections and Resonance Integrals for Curium-243

C. E. Bemis, Jr., J. H. Oliver, R. Eby, J. Halperin

Nuclear Science and Engineering / Volume 63 / Number 4 / August 1977 / Pages 413-417

Technical Paper / dx.doi.org/10.13182/NSE77-A27058

High-Resolution Fast-Neutron Gamma-Ray Production Cross Sections for Iron up to 2100 keV

W. E. Kinney, F. G. Perey

Nuclear Science and Engineering / Volume 63 / Number 4 / August 1977 / Pages 418-429

Technical Paper / dx.doi.org/10.13182/NSE77-A27059

A Reconciliation of Measurements of for Neutron-Induced Fission of Uranium-235

J. W. Boldeman, J. Fréhaut, R. L. Walsh

Nuclear Science and Engineering / Volume 63 / Number 4 / August 1977 / Pages 430-436

Technical Paper / dx.doi.org/10.13182/NSE77-A27060

Coarse-Mesh Flux-Expansion Method for the Analysis of Space-Time Effects in Large Light Water Reactor Cores

S. Langenbuch, W. Maurer, W. Werner

Nuclear Science and Engineering / Volume 63 / Number 4 / August 1977 / Pages 437-456

Technical Paper / dx.doi.org/10.13182/NSE77-A27061

Some Basic Properties of the Response Matrix Equations

Zbigniew Weiss

Nuclear Science and Engineering / Volume 63 / Number 4 / August 1977 / Pages 457-492

Technical Paper / dx.doi.org/10.13182/NSE77-A27062

Measurements of Energy Spectra and Doses in Liquid Air of Neutrons from a Californium-252 Source

K. Clausen, U. Roose, P. Schneider-Kühnle, F. W. Buchholz, L. Schänzler, S. Stüker, G. Tumbrägel, M. Weinert

Nuclear Science and Engineering / Volume 63 / Number 4 / August 1977 / Pages 493-500

Technical Note / dx.doi.org/10.13182/NSE77-A27063

Space- and Angle-Dependent Steady-State Thermal-Neutron Spectra Inside Small Beryllium Assemblies: II

Suresh Garg, Feroz Ahmed, L. S. Kothari

Nuclear Science and Engineering / Volume 63 / Number 4 / August 1977 / Pages 500-504

Technical Note / dx.doi.org/10.13182/NSE77-A27064

Distribution of Fission Yields for Fission Spectrum Neutron-Induced Fission of Uranium-238

D. C. Harris, J. N. Beck, W. L. Raines, J. T. Harvey, K. G. W. Inn, J. L. Meason, H. L. Wright

Nuclear Science and Engineering / Volume 63 / Number 4 / August 1977 / Pages 504-507

Technical Note / dx.doi.org/10.13182/NSE77-A27065

Two-Half-Space Milne Problem in Two-Group Neutron Transport Theory

Yuji Ishiguro, José Rubens Maiorino

Nuclear Science and Engineering / Volume 63 / Number 4 / August 1977 / Pages 507-509

Technical Note / dx.doi.org/10.13182/NSE77-A27066

Upper-Bound Estimation of Bilinear Functionals in Reactor Theory

Yigal Ronen, Ehud Greenspan

Nuclear Science and Engineering / Volume 63 / Number 4 / August 1977 / Pages 509-513

Technical Note / dx.doi.org/10.13182/NSE77-A27067