ANS / Publications / Journals / Nuclear Science and Engineering

Analysis of Measured Total Pressures from Irradiated Solid and Liquid (U,Pu)-Mixed Oxide

W. Breitung

Nuclear Science and Engineering / Volume 108 / Number 1 / May 1991 / Pages 1-15

Technical Paper / dx.doi.org/10.13182/NSE91-A23804

Forward and Adjoint Methods and Applications for Deterministic Electron-Photon Transport

C. R. Drumm, W. C. Fan, J. H. Renken

Nuclear Science and Engineering / Volume 108 / Number 1 / May 1991 / Pages 16-49

Technical Paper / dx.doi.org/10.13182/NSE91-A23805

On the Slowing Down and Transport of Neutrons in an Infinite Medium

Dan G. Cacuci

Nuclear Science and Engineering / Volume 108 / Number 1 / May 1991 / Pages 50-68

Technical Paper / dx.doi.org/10.13182/NSE91-A23806

Temperature Jump: Rigid-Sphere Gas with Arbitrary Gas/Surface Interaction

S. K. Loyalka

Nuclear Science and Engineering / Volume 108 / Number 1 / May 1991 / Pages 69-73

Technical Paper / dx.doi.org/10.13182/NSE91-A23807

Derivatives for the Equations of State of Multicomponent Mixtures for Universal Multicomponent Flow Models

N. I. Kolev

Nuclear Science and Engineering / Volume 108 / Number 1 / May 1991 / Pages 74-87

Technical Paper / dx.doi.org/10.13182/NSE91-A23808

Vapor Explosions in a Stratified Geometry

K. H. Bang, M. L. Corradini

Nuclear Science and Engineering / Volume 108 / Number 1 / May 1991 / Pages 88-108

Technical Paper / dx.doi.org/10.13182/NSE91-A23809

Calculation of Fission Neutron Spectra for Spontaneous Fission of ²⁴⁰Pu, ²³⁸Pu and ²⁴²Pu

R. L. Walsh, G. Chircu, D. G. Madland

Nuclear Science and Engineering / Volume 108 / Number 1 / May 1991 / Pages 109-115

Technical Paper / dx.doi.org/10.13182/NSE91-A23810

Calculations of the Production Cross Sections of High-Spin Isomeric States in Hafnium

M. B. Chadwick, P. G. Young

Nuclear Science and Engineering / Volume 108 / Number 2 / June 1991 / Pages 117-125

Technical Paper / dx.doi.org/10.13182/NSE91-A23812

Time-Independent Neutronic Analysis of the Chernobyl Accident

P. A. Landeyro, A. Buccafurni

Nuclear Science and Engineering / Volume 108 / Number 2 / June 1991 / Pages 126-149

Technical Paper / dx.doi.org/10.13182/NSE91-A23813

Reactivity Due to Deformation of a Thin Plate in a Critical Reactor

M. L. Williams

Nuclear Science and Engineering / Volume 108 / Number 2 / June 1991 / Pages 150-171

Technical Paper / dx.doi.org/10.13182/NSE91-A23814

Lower Head Creep-Rupture Sensitivity Studies

Sudip S. Dosanjh, Martin Pilch

Nuclear Science and Engineering / Volume 108 / Number 2 / June 1991 / Pages 172-183

Technical Paper / dx.doi.org/10.13182/NSE91-A23815

Decay of Buoyancy-Driven Stratified Layers with Applications to Pressurized Thermal Shock: Reactor Predictions

K. Iyer, T. G. Theofanous

Nuclear Science and Engineering / Volume 108 / Number 2 / June 1991 / Pages 184-197

Technical Paper / dx.doi.org/10.13182/NSE91-A23816

Flooding-Limited Thermal Mixing: The Case of High Froude Number Injection

K. Iyer, T. G. Theofanous

Nuclear Science and Engineering / Volume 108 / Number 2 / June 1991 / Pages 198-207

Technical Note / dx.doi.org/10.13182/NSE91-A23817

Probabilities for Lattice Integral Transport

M. Segev, J. Stepanek

Nuclear Science and Engineering / Volume 108 / Number 2 / June 1991 / Pages 208-213

Technical Note / dx.doi.org/10.13182/NSE91-A23818

Surface Current Double-Heterogeneous Multilayer Multicell Methodology

J. Stepanek , M. Segev

Nuclear Science and Engineering / Volume 108 / Number 3 / July 1991 / Pages 215-229

Technical Paper / dx.doi.org/10.13182/NSE91-A23820

Generalization of the Stamm’ler Method for the Self-Shielding of Resonant Isotopes in Arbitrary Geometries

A. Hébert , G. Marleau

Nuclear Science and Engineering / Volume 108 / Number 3 / July 1991 / Pages 230-239

Technical Paper / dx.doi.org/10.13182/NSE90-57

A Monte Carlo Direction Biasing Approach in the Laboratory System for Isotropic Neutron Center-of-Mass Scattering Including Hydrogen

R. P. Gardner, M. Mickael, M. Oraby, K. Verghese

Nuclear Science and Engineering / Volume 108 / Number 3 / July 1991 / Pages 240-246

Technical Paper / dx.doi.org/10.13182/NSE91-A23822

An Analysis of the Finite Differenced, Even-Parity, Discrete Ordinates Equations in Slab Geometry

Warren F. Miller, Jr.

Nuclear Science and Engineering / Volume 108 / Number 3 / July 1991 / Pages 247-266

Technical Paper / dx.doi.org/10.13182/NSE91-A23823

Angular Parallelization of a Curvilinear S_n Transport Theory Method

Alireza Haghighat

Nuclear Science and Engineering / Volume 108 / Number 3 / July 1991 / Pages 267-277

Technical Paper / dx.doi.org/10.13182/NSE91-A23824

Richardson Extrapolation Applied to Difference Methods for Numerically Solving the Neutron Transport Equation in Spherical Geometry

W. E. Abbott, E. J. Allen

Nuclear Science and Engineering / Volume 108 / Number 3 / July 1991 / Pages 278-288

Technical Note / dx.doi.org/10.13182/NSE91-A23825

Cross-Section Measurements of (n,p) and (n,np + pn + d) Reactions for Some Titanium, Chromium, Iron, Cobalt, Nickel, and Zinc Isotopes Around 14 MeV

M. Viennot, M. Berrada, G. Paic, S. Joly

Nuclear Science and Engineering / Volume 108 / Number 3 / July 1991 / Pages 289-301

Technical Note / dx.doi.org/10.13182/NSE87-157

Fast Neutron Radiative Capture Cross Sections of Natural Niobium and Molybdenum

Yunshan Mu, Haishan Xu, Zhengyu Xiang, Yexiang Li, Shiming Wang, Jianfeng Liu

Nuclear Science and Engineering / Volume 108 / Number 3 / July 1991 / Pages 302-307

Technical Note / dx.doi.org/10.13182/NSE91-A23827

Neutron Absorber Effect on Coolant Void Reactivity in a Pressure-Tube-Type Heavy Water Reactor

Yasuki Kowata , Nobuo Fukumura

Nuclear Science and Engineering / Volume 108 / Number 3 / July 1991 / Pages 308-318

Technical Note / dx.doi.org/10.13182/NSE91-A23828

Thermal Neutron Steady-State Spectra in Light Water Reactor Fuel Assemblies Poisoned with Various Non-l/v Absorbers of Different Concentrations

K. Swaminathan, Satish Chandra, R. C. Jha, S. P. Tewari

Nuclear Science and Engineering / Volume 108 / Number 3 / July 1991 / Pages 319-323

Technical Note / dx.doi.org/10.13182/NSE91-A23829

The Effect of Random Material Density on Reactor Criticality

G. C. Pomraning

Nuclear Science and Engineering / Volume 108 / Number 4 / August 1991 / Pages 325-330

Technical Paper / dx.doi.org/10.13182/NSE91-A23831

Noise Analysis Method for Monitoring the Moderator Temperature Coefficient of Pressurized Water Reactors: I. Theory

J. R. Thomas, Jr., J. D. Herr, D. S. Wood

Nuclear Science and Engineering / Volume 108 / Number 4 / August 1991 / Pages 331-340

Technical Paper / dx.doi.org/10.13182/NSE90-42

Noise Analysis Method for Monitoring the Moderator Temperature Coefficient of Pressurized Water Reactors: II. Experimental

J. D. Herr, J. R. Thomas, Jr.

Nuclear Science and Engineering / Volume 108 / Number 4 / August 1991 / Pages 341-346

Technical Paper / dx.doi.org/10.13182/NSE90-43

Feedback Theory for Linear Reactivity Transients in a Point Reactor

Takeo Nishigori

Nuclear Science and Engineering / Volume 108 / Number 4 / August 1991 / Pages 347-354

Technical Paper / dx.doi.org/10.13182/NSE91-A23834

Generalized Contributon Response Theory

M. L. Williams

Nuclear Science and Engineering / Volume 108 / Number 4 / August 1991 / Pages 355-383

Technical Paper / dx.doi.org/10.13182/NSE90-33

The Maximum Entropy Method for Reconstruction of the Pointwise Neutron Flux Distribution in Nodal Methods

Woo Sik Jung, Nam Zin Cho

Nuclear Science and Engineering / Volume 108 / Number 4 / August 1991 / Pages 384-395

Technical Paper / dx.doi.org/10.13182/NSE91-A23836

A New Critical Heat Flux Correlation for Boiling Liquid Metals

H. M. Kottowski, C. Savatteri, W. Hufschmidt

Nuclear Science and Engineering / Volume 108 / Number 4 / August 1991 / Pages 396-413

Technical Paper / dx.doi.org/10.13182/NSE91-A23837

Effective Atomic Numbers for Total Gamma-Ray Interaction and Incoherent Scattering in Some Alloys at 662 keV

Ashok Madiyal, I. Vasudeva Rao, N. Lingappa, K. Siddappa

Nuclear Science and Engineering / Volume 108 / Number 4 / August 1991 / Pages 414-418

Technical Paper / dx.doi.org/10.13182/NSE91-A23838