ANS / Publications / Journals / Nuclear Science and Engineering

Rate of Liquid Entrainment at the Gas-Liquid Interface of a Liquid Submerged Sonic Gas Jet

T. C. Chawla

Nuclear Science and Engineering / Volume 56 / Number 1 / January 1975 / Pages 1-6

Technical Paper / dx.doi.org/10.13182/NSE75-A26616

A Computational Technique to Assess Procedures for Failed-Fuel Identification

N. J. McCormick

Nuclear Science and Engineering / Volume 56 / Number 1 / January 1975 / Pages 7-15

Technical Paper / dx.doi.org/10.13182/NSE75-A26617

Joint Probability Distribution of Neutron Counts in Reactor Noise Analysis

M. Marseguerra

Nuclear Science and Engineering / Volume 56 / Number 1 / January 1975 / Pages 16-26

Technical Paper / dx.doi.org/10.13182/NSE75-A26618

Total Neutron Cross Section of Carbon from 1 keV to 15 MeV

H. T. Heaton, II, J. L. Menke, R. A. Schrack, R. B. Schwartz

Nuclear Science and Engineering / Volume 56 / Number 1 / January 1975 / Pages 27-36

Technical Paper / dx.doi.org/10.13182/NSE75-A26619

Delayed-Neutron Data for Reactor-Physics Analysis

R. J. Tuttle

Nuclear Science and Engineering / Volume 56 / Number 1 / January 1975 / Pages 37-71

Technical Paper / dx.doi.org/10.13182/NSE75-A26620

A Theory of Resonance-Group Self-Shielding

M. Segev

Nuclear Science and Engineering / Volume 56 / Number 1 / January 1975 / Pages 72-82

Technical Paper / dx.doi.org/10.13182/NSE75-A26621

Thermonuclear Microfission

F. Winterberg

Nuclear Science and Engineering / Volume 56 / Number 1 / January 1975 / Pages 83-84

Technical Note / dx.doi.org/10.13182/NSE75-A26622

Compact Tables of Functions for Use in Shielding Calculations

K. Shure, O. J. Wallace

Nuclear Science and Engineering / Volume 56 / Number 1 / January 1975 / Pages 84-94

Technical Note / dx.doi.org/10.13182/NSE75-A26623

A New Measurement of the ¹⁰B(n, α)⁷Li Branching Ratio

G. P. Lamaze, A. D. Carlson, M. M. Meier

Nuclear Science and Engineering / Volume 56 / Number 1 / January 1975 / Pages 94-96

Technical Note / dx.doi.org/10.13182/NSE75-A26624

Calculated Nickel-58 Reaction Cross Sections Around 14-MeV Neutron Energy

B. S. Wadhwa, R. K. Mohindra

Nuclear Science and Engineering / Volume 56 / Number 1 / January 1975 / Pages 96-98

Technical Note / dx.doi.org/10.13182/NSE75-A26625

Measured Thermal-Neutron Cross Section for the ⁵⁹Ni(n, α)⁵⁶Fe Reaction

R. D. Werner, D. C. Santry

Nuclear Science and Engineering / Volume 56 / Number 1 / January 1975 / Pages 98-100

Technical Note / dx.doi.org/10.13182/NSE75-A26626

A Generalized Source-Multiplication Method for Determining Reactivity

Ehud Greenspan

Nuclear Science and Engineering / Volume 56 / Number 1 / January 1975 / Pages 100-103

Technical Note / dx.doi.org/10.13182/NSE75-A26627

A Source-Multiplication Reactivity

Ehud Greenspan

Nuclear Science and Engineering / Volume 56 / Number 1 / January 1975 / Pages 103-106

Technical Note / dx.doi.org/10.13182/NSE75-A26628

An Improved Series Representation of Doppler-Broadened Resonance Absorption

Arthur Ginsberg, Martin Becker

Nuclear Science and Engineering / Volume 56 / Number 1 / January 1975 / Pages 106-107

Technical Note / dx.doi.org/10.13182/NSE75-A26629

A Generalized Perturbation Theory and Variational Principle for Multiple Ratios of Linear and Bilinear Functionals

Ehud Greenspan

Nuclear Science and Engineering / Volume 56 / Number 1 / January 1975 / Pages 107-112

Technical Note / dx.doi.org/10.13182/NSE75-A26630

Characteristics of Uncertainties in Sensitivity Studies of Fast-Reactor Parameters

R. N. Hwang

Nuclear Science and Engineering / Volume 56 / Number 2 / February 1975 / Pages 119-130

Technical Paper / dx.doi.org/10.13182/NSE75-A26651

A Higher Order Relationship Between Static Power Tilts and Eigenvalue Separation in Nuclear Reactors

W. D. Beckner, R. A. Rydin

Nuclear Science and Engineering / Volume 56 / Number 2 / February 1975 / Pages 131-141

Technical Paper / dx.doi.org/10.13182/NSE75-A26652

Application of Artificial Intelligence Techniques to Digital Computer Control of Nuclear Reactors

ames L. Macdonald, Billy V. Koen

Nuclear Science and Engineering / Volume 56 / Number 2 / February 1975 / Pages 142-151

Technical Paper / dx.doi.org/10.13182/NSE75-A26653

Computational Models for the Study of Azimuthally Dependent Disassembly of Liquid-Metal Fast Breeder Reactors

Paul B. Bleiweis, William E. Kastenberg, David Okrent

Nuclear Science and Engineering / Volume 56 / Number 2 / February 1975 / Pages 152-170

Technical Paper / dx.doi.org/10.13182/NSE75-A26654

Tabulation and Empirical Representation of Infinite-Medium Gamma-Ray Buildup Factors for Monoenergetic, Point Isotropic Sources in Water, Aluminum, and Concrete

E. E. MORRIS, A. B. CHILTON, A. F VETTER

Nuclear Science and Engineering / Volume 56 / Number 2 / February 1975 / Pages 171-178

Technical Paper / dx.doi.org/10.13182/NSE75-A26655

Experimental Determination of Photofission Neutron Multiplicities for Eight Isotopes in the Mass Range 232 ≤ A ≤ 239

J. T. Caldwell and E. J. Dowdy

Nuclear Science and Engineering / Volume 56 / Number 2 / February 1975 / Pages 179-187

Technical Paper / dx.doi.org/10.13182/NSE75-A26656

A Thermal Analysis of Hot Spots on Fast-Reactor Fuel Cladding Due to Deposition of Low-Conductivity Materials

M. Ishii, T. C. Chawla

Nuclear Science and Engineering / Volume 56 / Number 2 / February 1975 / Pages 188-195

Technical Paper / dx.doi.org/10.13182/NSE75-A26657

Atmospheric Stability Inside Containments with a Heated Layer of Liquid on the Floor

Joh. F. van de Vate, A. Plomp

Nuclear Science and Engineering / Volume 56 / Number 2 / February 1975 / Pages 196-200

Technical Paper / dx.doi.org/10.13182/NSE75-A26658

Partial Wave Expansion of the Induced Collision Kernel

B. R. Wienke

Nuclear Science and Engineering / Volume 56 / Number 2 / February 1975 / Pages 201-202

Technical Note / dx.doi.org/10.13182/NSE75-A26659

Practical Preprocessed Nuclear Data Files for Fast Reactor Calculations

Y. Gur, S. Yiftah

Nuclear Science and Engineering / Volume 56 / Number 2 / February 1975 / Pages 202-210

Technical Note / dx.doi.org/10.13182/NSE75-A26660

Subcritical Reactivity as Determined from Reactor Noise

Hsiao-Kang Wang, Lawrence Ruby

Nuclear Science and Engineering / Volume 56 / Number 2 / February 1975 / Pages 211-212

Technical Note / dx.doi.org/10.13182/NSE75-A26661

Reactivity from Power Spectral Density Measurements with Californium-252

V. K. Paré, J. T. Mihalczo

Nuclear Science and Engineering / Volume 56 / Number 2 / February 1975 / Pages 213-218

Technical Note / dx.doi.org/10.13182/NSE75-A26662

Direct Sampling from the Klein-Nishina Distribution for Photon Energies Above 1.4 MeV

László Koblinger

Nuclear Science and Engineering / Volume 56 / Number 2 / February 1975 / Pages 218-219

Technical Note / dx.doi.org/10.13182/NSE75-A26663

Additional Few-Group and Multigroup Calculations of Neutron Penetration

K. Shure

Nuclear Science and Engineering / Volume 56 / Number 2 / February 1975 / Pages 219-224

Technical Note / dx.doi.org/10.13182/NSE75-A26664

An In-Pile Study of Thermal Interactions Between . High-Energy Molten UO₂ Fuel and Liquid Sodium

S. M. Zivi, M. Epstein, R. W. Wright, J. J. Barghusen, D. H. Cho, F. J. Testa, G. T. Goldfuss, R. W. Mouring

Nuclear Science and Engineering / Volume 56 / Number 3 / March 1975 / Pages 229-240

Technical Paper / dx.doi.org/10.13182/NSE75-A26737

Measured and Calculated Rates of Decay Heat in Irradiated ²³⁵U, ²³³U, 239Pu, and ²³²Th

S. B. Gunst, D. E. Conway, J. C. Connor

Nuclear Science and Engineering / Volume 56 / Number 3 / March 1975 / Pages 241-262

Technical Paper / dx.doi.org/10.13182/NSE75-A26738

Point Isotropic Gamma-Ray Buildup Factors in Concrete

C. M. Eisenhauer, G. L. Simmons

Nuclear Science and Engineering / Volume 56 / Number 3 / March 1975 / Pages 263-270

Technical Paper / dx.doi.org/10.13182/NSE75-A26739

Neutron Importance and Fission Density in Uranium-235-Enriched Uranium and Plutonium Metal Spheres

J. T. Mihalczo

Nuclear Science and Engineering / Volume 56 / Number 3 / March 1975 / Pages 271-290

Technical Paper / dx.doi.org/10.13182/NSE75-3

Response Matrices in Space-Time Reactor Dynamics

J. M. Sicilian

Nuclear Science and Engineering / Volume 56 / Number 3 / March 1975 / Pages 291-300

Technical Paper / dx.doi.org/10.13182/NSE75-2

Laser-Induced Thermonuclear Micro-Explosions Using Fissionable Triggers

W. Seifritz, J. Ligou

Nuclear Science and Engineering / Volume 56 / Number 3 / March 1975 / Pages 301-303

Technical Note / dx.doi.org/10.13182/NSE75-A26742

The EBR-I Incident: A Reexamination

Gerald S. Lellouche

Nuclear Science and Engineering / Volume 56 / Number 3 / March 1975 / Pages 303-307

Technical Note / dx.doi.org/10.13182/NSE75-A26743

An Assessment of ENDF/B-III Data for Uranium-238 Based on Integral Spectrum Measurements

Martin Becker, Narinder N. Kaushal

Nuclear Science and Engineering / Volume 56 / Number 3 / March 1975 / Pages 307-309

Technical Note / dx.doi.org/10.13182/NSE75-A26744

Diregionally Discontinuous Harmonic Solutions of the Neutron Transport Equation in Spherical Geometry

A. A. Harms, E. A. Attia

Nuclear Science and Engineering / Volume 56 / Number 3 / March 1975 / Pages 310-317

Technical Note / dx.doi.org/10.13182/NSE75-A26745

A Numerical Method for Solving Integral Equations of Neutron Transport

S. K. Loyalka

Nuclear Science and Engineering / Volume 56 / Number 3 / March 1975 / Pages 317-319

Technical Note / dx.doi.org/10.13182/NSE75-2

A Generalized Diffusion Theory for Calculating the Neutron Transport Scalar Flux

Raymond E. Alcouffe

Nuclear Science and Engineering / Volume 56 / Number 4 / April 1975 / Pages 321-339

Technical Paper / dx.doi.org/10.13182/NSE75-A26680

Variational Functionals Which Admit Discontinuous Trial Functions

Paul Nelson, Jr.

Nuclear Science and Engineering / Volume 56 / Number 4 / April 1975 / Pages 340-353

Technical Paper / dx.doi.org/10.13182/NSE75-A26681

Nonlinear Oscillations in a Reactor with Two Temperature Coefficients

James P. Keener, Donald S. Cohen

Nuclear Science and Engineering / Volume 56 / Number 4 / April 1975 / Pages 354-359

Technical Paper / dx.doi.org/10.13182/NSE75-A26682

Calculational Methods for Nuclear Heating-Part I: Theoretical and Computational Algorithms

M. A. Abdou, C. W. Maynard

Nuclear Science and Engineering / Volume 56 / Number 4 / April 1975 / Pages 360-380

Technical Paper / dx.doi.org/10.13182/NSE75-A26683

Calculational Methods for Nuclear Heating—Part II: Applications to Fusion-Reactor Blankets and Shields

M. A. Abdou, C. W. Maynard

Nuclear Science and Engineering / Volume 56 / Number 4 / April 1975 / Pages 381-398

Technical Paper / dx.doi.org/10.13182/NSE75-A26684

Removal of Iodide from LiF-BeF₂ Melts by HF-H₂ Sparging—An Application to Iodine Removal from Molten Salt Breeder Reactor Fuel

C. F. Baes, Jr., R. P. Wichner, C. E. Bamberger, B. F. Freasier

Nuclear Science and Engineering / Volume 56 / Number 4 / April 1975 / Pages 399-410

Technical Paper / dx.doi.org/10.13182/NSE75-A26685

Transmission Probability Method of Integral Neutron Transport Calculation for Two-Dimensional Rectangular Cells

Hans Häggblom, Åke Ahlin, Takashi Nakamura

Nuclear Science and Engineering / Volume 56 / Number 4 / April 1975 / Pages 411-422

Technical Note / dx.doi.org/10.13182/NSE75-A26686

Zero-Power Noise Analysis in a Reactor with Two Weakly Coupled Asymmetrical Fission Zones

Eckart Viehl

Nuclear Science and Engineering / Volume 56 / Number 4 / April 1975 / Pages 422-427

Technical Note / dx.doi.org/10.13182/NSE75-A26687

A Benchmark Experiment of Neutron Propagation in Iron Used to Test ENDF/B Cross-Section Data

M. Martini, G. Palmiotti, M. Salvatores

Nuclear Science and Engineering / Volume 56 / Number 4 / April 1975 / Pages 427-430

Technical Note / dx.doi.org/10.13182/NSE75-A26688

Power Reactor Calculations with the Finite Element Program FEM 2D

F. A. R. Schmidt, H. P. Franke

Nuclear Science and Engineering / Volume 56 / Number 4 / April 1975 / Pages 431-433

Technical Note / dx.doi.org/10.13182/NSE75-A26689