ANS / Publications / Journals / Nuclear Science and Engineering

Integral Transport Theory Formalism for Diffusion Coefficient Calculations in Wigner-Seitz Cells

Pierre Benoist

Nuclear Science and Engineering / Volume 77 / Number 1 / January 1981 / Pages 1-12

Technical Paper / dx.doi.org/10.13182/NSE81-A21334

Interface and Source Problems by a Transport Theoretic P_N Approximation

K. Ganguly, A. Sengupta

Nuclear Science and Engineering / Volume 77 / Number 1 / January 1981 / Pages 13-19

Technical Paper / dx.doi.org/10.13182/NSE81-A21335

Elastic Nuclear Plus Interference Cross Sections for Light-Charged Particles

Sterrett T. Perkins, Dermott E. Cullen

Nuclear Science and Engineering / Volume 77 / Number 1 / January 1981 / Pages 20-39

Technical Paper / dx.doi.org/10.13182/NSE81-A21336

Progress in Integral Data and Their Accuracy: Average Neutron Cross Sections in the Californium-252 Benchmark Field

W. Mannhart

Nuclear Science and Engineering / Volume 77 / Number 1 / January 1981 / Pages 40-50

Technical Paper / dx.doi.org/10.13182/NSE81-A21337

Measurements of the Fast Neutron Emission Spectrum of Californium-252 by Means of Proton-Recoil Spectrometers

H. Jasicek, F. Bensch

Nuclear Science and Engineering / Volume 77 / Number 1 / January 1981 / Pages 51-57

Technical Paper / dx.doi.org/10.13182/NSE81-A21338

Determination of the Capture Width of the 27.7-keV s-Wave Neutron Resonance in Iron-56

K. Wisshak, F. Käppeler

Nuclear Science and Engineering / Volume 77 / Number 1 / January 1981 / Pages 58-70

Technical Paper / dx.doi.org/10.13182/NSE81-A21339

Computational Benchmark for Neutron Penetration in Iron

J. S. Hendricks, L. L. Carter

Nuclear Science and Engineering / Volume 77 / Number 1 / January 1981 / Pages 71-83

Technical Paper / dx.doi.org/10.13182/NSE81-A21340

A Study of the Penetration of a Hot Liquid Pool into a Vertical Solid Surface

Rouyentan Farhadieh

Nuclear Science and Engineering / Volume 77 / Number 1 / January 1981 / Pages 84-91

Technical Paper / dx.doi.org/10.13182/NSE81-A21341

On the Two-Dimensional Analysis of Fluid Flow and Heat Transfer in Rod Bundles with Arbitrary Arrangement

Sun Wong, Kawei Chen

Nuclear Science and Engineering / Volume 77 / Number 1 / January 1981 / Pages 92-106

Technical Paper / dx.doi.org/10.13182/NSE81-A21342

Neutron Utilization Parameter for Complex Coupled Systems

Charles R. Marotta

Nuclear Science and Engineering / Volume 77 / Number 1 / January 1981 / Pages 107-109

Technical Note / dx.doi.org/10.13182/NSE81-A21343

Fast-Neutron Total and Elastic- and Nonelastic-Scattering Cross Sections of Elemental Nickel

A. B. Smith, P. T. Guenther, J. F. Whalen

Nuclear Science and Engineering / Volume 77 / Number 1 / January 1981 / Pages 110-113

Technical Note / dx.doi.org/10.13182/NSE81-A21344

Particle Transport Calculations with the Method of Streaming Rays

W. L. Filippone, S. Woolf, R. J. Lavigne

Nuclear Science and Engineering / Volume 77 / Number 2 / February 1981 / Pages 119-136

Technical Paper / dx.doi.org/10.13182/NSE81-A21346

A Method for Calculating Power Distributions in Boiling Water Reactors Using In-Core Detector Readings

Sadao Uchikawa, Hiroshi Motoda

Nuclear Science and Engineering / Volume 77 / Number 2 / February 1981 / Pages 137-145

Technical Paper / dx.doi.org/10.13182/NSE81-A21347

Yields of Short-Lived Fission Products Produced by Thermal-Neutron Fission of Plutonium-239

J. K. Dickens, J. W. McConnell, K. J. Northcutt

Nuclear Science and Engineering / Volume 77 / Number 2 / February 1981 / Pages 146-152

Technical Paper / dx.doi.org/10.13182/NSE81-A21348

High-Order Flux Perturbations

A. Dubi, Donald J. Dudziak

Nuclear Science and Engineering / Volume 77 / Number 2 / February 1981 / Pages 153-156

Technical Paper / dx.doi.org/10.13182/NSE81-A21349

The Distribution of Thermal Neutron Cross Sections

Yu. V. Petrov, A. I. Shlyakhter

Nuclear Science and Engineering / Volume 77 / Number 2 / February 1981 / Pages 157-167

Technical Paper / dx.doi.org/10.13182/NSE81-A21350

A Systematic Study on the Neutron Skyshine from Nuclear Facilities—Part I. Monte Carlo Analysis of Neutron Propagation in Air-over-Ground Environment from a Monoenergetic Source

Takashi Nakamura, Toshiso Kosako

Nuclear Science and Engineering / Volume 77 / Number 2 / February 1981 / Pages 168-181

Technical Paper / dx.doi.org/10.13182/NSE81-A21351

A Systematic Study on the Neutron Skyshine from Nuclear Facilities—Part II. Experimental Approach to the Behavior of Environmental Neutrons Around an Electron Synchrotron

Takashi Nakamura, Toshiso Kosako, Katsumi Hayashi, Shuichi Ban, Kazuaki Katoh

Nuclear Science and Engineering / Volume 77 / Number 2 / February 1981 / Pages 182-191

Technical Paper / dx.doi.org/10.13182/NSE81-A21352

Nonlinear Transient Analysis of Light Water Reactor Steam Generators Using an Implicit Eulerian Method

Mark W. Crump, John C. Lee

Nuclear Science and Engineering / Volume 77 / Number 2 / February 1981 / Pages 192-210

Technical Paper / dx.doi.org/10.13182/NSE81-A21353

The Solubility of Nickel Ferrite in Aqueous Boric Acid Solution

Y. L. Sandler, R. H. Kunig

Nuclear Science and Engineering / Volume 77 / Number 2 / February 1981 / Pages 211-218

Technical Paper / dx.doi.org/10.13182/NSE81-A21354

Rigorous Homogenized Diffusion Theory Parameters for Neutrons

Riccardo A. Bonalumi

Nuclear Science and Engineering / Volume 77 / Number 2 / February 1981 / Pages 219-229

Technical Note / dx.doi.org/10.13182/NSE81-A21355

An Equivalence Relation for a Lattice of Annular Absorbers

M. Segev

Nuclear Science and Engineering / Volume 77 / Number 2 / February 1981 / Pages 229-235

Technical Note / dx.doi.org/10.13182/NSE81-A21356

Reactor Fuel Burnup Calculation for a Square Lattice Cell

Y. Y. Chang, S. K. Loyalka

Nuclear Science and Engineering / Volume 77 / Number 2 / February 1981 / Pages 235-250

Technical Note / dx.doi.org/10.13182/NSE81-A21357

The Effect of Self-Shielding of the Iron Inelastic Scattering Cross Section on Neutron Spectra

Hideki Takano, Kunio Kaneko

Nuclear Science and Engineering / Volume 77 / Number 2 / February 1981 / Pages 250-256

Technical Note / dx.doi.org/10.13182/NSE81-A21358

Cross Sections for ¹⁹F(n,p)¹⁹O and ¹⁹F(n,α)¹⁶N from Threshold to 9 MeV

Donald L. Smith, James W. Meadows, James F. Whalen

Nuclear Science and Engineering / Volume 77 / Number 2 / February 1981 / Pages 256-262

Technical Note / dx.doi.org/10.13182/NSE81-A21359

Decay Schemes for Radionuclides of Potential Importance in the Nuclear Fuel Cycle

D. C. Kocher

Nuclear Science and Engineering / Volume 77 / Number 2 / February 1981 / Pages 263-265

Technical Note / dx.doi.org/10.13182/NSE81-A21360

A Model of Countercurrent Steam-Water Flow in Large Horizontal Pipes

Bart J. Daly, Francis H. Harlow

Nuclear Science and Engineering / Volume 77 / Number 3 / March 1981 / Pages 273-284

Technical Paper / dx.doi.org/10.13182/NSE81-A19838

Sensitivity of Light Water Reactor Fuel Cycle Parameters and Costs to Uncertainties in Thermal Nuclear Data and Methods

J. M. Ryskamp, D. R. Harris, M. Becker

Nuclear Science and Engineering / Volume 77 / Number 3 / March 1981 / Pages 285-296

Technical Paper / dx.doi.org/10.13182/NSE81-A19839

Event Sequences and Consequence Spectrum: A Methodology for Probabilistic Transient Analysis

A. Amendola, G. Reina

Nuclear Science and Engineering / Volume 77 / Number 3 / March 1981 / Pages 297-315

Technical Paper / dx.doi.org/10.13182/NSE81-A19840

Generalized Perturbation Theory for Nonlinear Systems from the Importance Conservation Principle

A. Gandini

Nuclear Science and Engineering / Volume 77 / Number 3 / March 1981 / Pages 316-343

Technical Paper / dx.doi.org/10.13182/NSE81-A19841

A Stability Analysis for Nuclear Reactor Systems

Trine-Yie Dawn

Nuclear Science and Engineering / Volume 77 / Number 3 / March 1981 / Pages 344-351

Technical Note / dx.doi.org/10.13182/NSE81-A19842

Using Orthogonal Functions with a Finite Element Method for Approximating Even-Parity Neutron Flux in Slab Geometry

B. A. Splawski, A. K. Ziver, J. Galliara

Nuclear Science and Engineering / Volume 77 / Number 3 / March 1981 / Pages 351-354

Technical Note / dx.doi.org/10.13182/NSE81-A19843

Stability Analysis for Integro-Differential Coupled-Core Reactor Models

M. Podowski

Nuclear Science and Engineering / Volume 77 / Number 3 / March 1981 / Pages 354-359

Technical Note / dx.doi.org/10.13182/NSE81-A19844

Effectiveness of an Adaptive Acceleration Method for Inner Iterations in Some Neutron Diffusion Codes

Toichiro Fujimura, Yasushi Matsui

Nuclear Science and Engineering / Volume 77 / Number 3 / March 1981 / Pages 360-367

Technical Note / dx.doi.org/10.13182/NSE81-A19845

A Semianalytic Method for the Solution of the Neutron Transport Equation in Plane and Spherical Geometries

J. K. Fletcher

Nuclear Science and Engineering / Volume 77 / Number 3 / March 1981 / Pages 367-372

Technical Note / dx.doi.org/10.13182/NSE81-A19846

Treatment of Anisotropic Scattering in Numerical Neutron Transport Theory

H. Brockmann

Nuclear Science and Engineering / Volume 77 / Number 4 / April 1981 / Pages 377-414

Technical Paper / dx.doi.org/10.13182/NSE81-3

Boundary Perturbation Theory

Edward W. Larsen, G. C. Pomraning

Nuclear Science and Engineering / Volume 77 / Number 4 / April 1981 / Pages 415-425

Technical Paper / dx.doi.org/10.13182/NSE81-A18954

Determination and Application of Generalized Bias Operators Using an Inverse Perturbation Approach

Y. Ronen, D. G. Cacuci, J. J. Wagschal

Nuclear Science and Engineering / Volume 77 / Number 4 / April 1981 / Pages 426-437

Technical Paper / dx.doi.org/10.13182/NSE81-A18955

On Linear Extrapolation Distances, Extrapolated Endpoints, and Eigenvalues

F. Rahnema, G. C. Pomraning

Nuclear Science and Engineering / Volume 77 / Number 4 / April 1981 / Pages 438-443

Technical Paper / dx.doi.org/10.13182/NSE81-A18956

Measurement of the Neutron-Induced Fission Cross Sections of Americium-241 and Americium-243 Relative to Uranium-235 from 0.2 to 30 MeV

J. W. Behrens, J. C. Browne

Nuclear Science and Engineering / Volume 77 / Number 4 / April 1981 / Pages 444-453

Technical Paper / dx.doi.org/10.13182/NSE81-A18957

Fission Neutron Multiplicity for the ^242mAm(n,f) Reaction

R. E. Howe, J. C. Browne, R. J. Dougan, R. J. Dupzyk, J. H. Landrum

Nuclear Science and Engineering / Volume 77 / Number 4 / April 1981 / Pages 454-462

Technical Paper / dx.doi.org/10.13182/NSE81-A18958

The Ratio of D-T to D-D Reactions as a Measure of the Fuel Density-Radius Product in Initially Tritium-Free Inertial Confinement Fusion Targets

T. E. Blue, D. B. Harris

Nuclear Science and Engineering / Volume 77 / Number 4 / April 1981 / Pages 463-469

Technical Paper / dx.doi.org/10.13182/NSE81-A18959

Film Boiling and Vapor Explosions from Small Spheres

Chunkuan Shih, M. M. El-Wakil

Nuclear Science and Engineering / Volume 77 / Number 4 / April 1981 / Pages 470-479

Technical Paper / dx.doi.org/10.13182/NSE81-A18960

Stability Monitoring of Boiling Water Reactors by Time Series Analysis of Neutron Noise

B. R. Upadhyaya, M. Kitamura

Nuclear Science and Engineering / Volume 77 / Number 4 / April 1981 / Pages 480-492

Technical Paper / dx.doi.org/10.13182/NSE81-A18961

Application of Computed Tomography Techniques to Pinhole Images of Nuclear-Reactor Test Fuel Rods

G. J. Berzins, G. C. McKinnon, R. H. T. Bates, A. H. Lumpkin

Nuclear Science and Engineering / Volume 77 / Number 4 / April 1981 / Pages 493-495

Technical Note / dx.doi.org/10.13182/NSE81-A18962

Deposition of Cobalt-60 on the Stainless-Steel Surface Used for the Primary Cooling System of a Boiling Water Reactor

Shunsuke Uchida, Masao Kitamura, Yasunori Matsushima, Koichi Yonezawa, Katsumi Ohsumi, Minoru Miki

Nuclear Science and Engineering / Volume 77 / Number 4 / April 1981 / Pages 496-501

Technical Note / dx.doi.org/10.13182/NSE81-A18963