ANS / Publications / Journals / Nuclear Science and Engineering

An R Matrix Analysis of the ²³⁵U Neutron-Induced Cross Sections up to 500 eV

L. C. Leal, G. de Saussure, R. B. Perez

Nuclear Science and Engineering / Volume 109 / Number 1 / September 1991 / Pages 1-17

Technical Paper / dx.doi.org/10.13182/NSE91-A23840

Pairing Corrections and Spin Cutoff Factors in Exciton Level Densities for Two Kinds of Fermions

C. Y. Fu

Nuclear Science and Engineering / Volume 109 / Number 1 / September 1991 / Pages 18-25

Technical Paper / dx.doi.org/10.13182/NSE91-A23841

Modeling of Fission Product Release and Transport for Severe Fuel Damage Analyses

K. Y. Suh, R. J. Hammersley

Nuclear Science and Engineering / Volume 109 / Number 1 / September 1991 / Pages 26-38

Technical Paper / dx.doi.org/10.13182/NSE91-A23842

High-Temperature Hydrogen Combustion in Reactor Safety Applications

Douglas W. Stamps, Marshall Berman

Nuclear Science and Engineering / Volume 109 / Number 1 / September 1991 / Pages 39-48

Technical Paper / dx.doi.org/10.13182/NSE91-A23843

The P_N Theory as an Asymptotic Limit of Transport Theory in Planar Geometry —I: Analysis

Edward W. Larsen, G. C. Pomraning

Nuclear Science and Engineering / Volume 109 / Number 1 / September 1991 / Pages 49-75

Technical Paper / dx.doi.org/10.13182/NSE91-A23844

The P_N Theory as an Asymptotic Limit of Transport Theory in Planar Geometry —II: Numerical Results

Robert P. Rulko, Edward W. Larsen, G. C. Pomraning

Nuclear Science and Engineering / Volume 109 / Number 1 / September 1991 / Pages 76-85

Technical Note / dx.doi.org/10.13182/NSE91-A23845

Effects of Changing the Random Number Stride in Monte Carlo Calculations

John S. Hendricks

Nuclear Science and Engineering / Volume 109 / Number 1 / September 1991 / Pages 86-91

Technical Note / dx.doi.org/10.13182/NSE91-A23846

Analysis of Beta-Ray Data Important to Decay Heat Predictions

J. K. Dickens

Nuclear Science and Engineering / Volume 109 / Number 1 / September 1991 / Pages 92-102

Technical Note / dx.doi.org/10.13182/NSE91-A23847

Application of Knowledge-Based Methods to In-Core Fuel Management

A. Galperin, Y. Kimhy

Nuclear Science and Engineering / Volume 109 / Number 1 / September 1991 / Pages 103-110

Technical Note / dx.doi.org/10.13182/NSE91-A23848

Measurement of the ¹⁰B(n, α_o)/¹⁰B(n,αγ) Ratio Versus Neutron Energy

L. W. Weston, J. H. Todd

Nuclear Science and Engineering / Volume 109 / Number 2 / October 1991 / Pages 113-119

Technical Paper / dx.doi.org/10.13182/NSE91-A28510

Prompt Fission Neutron Spectra and Fragment Characteristics for Spontaneous Fission of Even-Numbered Plutonium Isotopes

H. Märten, A. Ruben, D. Seeliger

Nuclear Science and Engineering / Volume 109 / Number 2 / October 1991 / Pages 120-127

Technical Paper / dx.doi.org/10.13182/NSE91-A28511

Calculation of Activation Cross Sections for Molybdenum Isotopes

Nobuhiro Yamamuro

Nuclear Science and Engineering / Volume 109 / Number 2 / October 1991 / Pages 128-141

Technical Paper / dx.doi.org/10.13182/NSE91-A28512

Comparisons of Global Phenomenological and Microscopic Optical Potentials for Nuclear Data Predictions

Chonghai Cai, Qingbiao Shen, Yizhong Zhuo

Nuclear Science and Engineering / Volume 109 / Number 2 / October 1991 / Pages 142-149

Technical Paper / dx.doi.org/10.13182/NSE91-A28513

Monte Carlo Next-Event Estimates from Thermal Collisions

John S. Hendricks, Richard E. Prael

Nuclear Science and Engineering / Volume 109 / Number 2 / October 1991 / Pages 150-157

Technical Paper / dx.doi.org/10.13182/NSE91-A28514

Axial Dependence of Partial Void Reactivity in a Light Water-Cooled, Heavy Water-Moderated, Pressure-Tube Reactor

Nagafumi Aihara, Nobuo Fukumura, Hiroyuki Kadotani, Yuuki Hachiya

Nuclear Science and Engineering / Volume 109 / Number 2 / October 1991 / Pages 158-170

Technical Paper / dx.doi.org/10.13182/NSE91-A28515

Model Reference Adaptive Control with Selective State Variable Weighting Applied to a Space Nuclear Power System

John D. Metzger, Mohamed S. El-Genk,Alexander G. Parlos

Nuclear Science and Engineering / Volume 109 / Number 2 / October 1991 / Pages 171-187

Technical Paper / dx.doi.org/10.13182/NSE91-A28516

Reconstructive Inverse Dynamics Control and Application to Xenon-Induced Power Oscillations in Pressurized Water Reactors

R. C. Berkan, B. R. Upadhyaya, L. H. Tsoukalas, R. A. Kisner

Nuclear Science and Engineering / Volume 109 / Number 2 / October 1991 / Pages 188-199

Technical Paper / dx.doi.org/10.13182/NSE91-A28517

Improved Pressurized Water Reactor Radial Reflector Modeling in Nodal Analysis

E. Z. Müller

Nuclear Science and Engineering / Volume 109 / Number 2 / October 1991 / Pages 200-214

Technical Note / dx.doi.org/10.13182/NSE91-A28518

Absolute Measurements of the ¹⁹⁷Au(n, γ)¹⁹⁸Au Cross Section for Fast Neutrons

Shigeyasu Sakamoto, Eiping Quang, Glenn F. Knoll

Nuclear Science and Engineering / Volume 109 / Number 2 / October 1991 / Pages 215-220

Technical Note / dx.doi.org/10.13182/NSE91-A28519

Evaluation of Liquid-Metal Reactor Design Options for Reduction of Sodium Void Worth

H. S. Khalil, R. N. Hill

Nuclear Science and Engineering / Volume 109 / Number 3 / November 1991 / Pages 221-266

Technical Paper / dx.doi.org/10.13182/NSE91-A23851

A Neutron Source Imaging Detector for Nuclear Arms Treaty Verification

W. C. Sailor, R. C. Byrd, A. Gavron, R. Hammock, Y. Yariv

Nuclear Science and Engineering / Volume 109 / Number 3 / November 1991 / Pages 267-277

Technical Paper / dx.doi.org/10.13182/NSE91-A23852

Uncertainty in the Burnup Reactivity Swing of Liquid-Metal Fast Reactors

T. J. Downar, H. Khalil

Nuclear Science and Engineering / Volume 109 / Number 3 / November 1991 / Pages 278-296

Technical Paper / dx.doi.org/10.13182/NSE91-A23853

An Experimental and Theoretical Study of Neutron Leakage and Transport in a Fast Neutron Moderator and Flight-Path Arrangement

V. Drüke, H. Schaal

Nuclear Science and Engineering / Volume 109 / Number 3 / November 1991 / Pages 297-303

Technical Paper / dx.doi.org/10.13182/NSE91-A23854

Some Useful Results for Surface Separation and Optimum Splitting for Simple Cases Based on the Direct Statistical Approach

N. Gurvitz, A. Dubi

Nuclear Science and Engineering / Volume 109 / Number 3 / November 1991 / Pages 304-318

Technical Paper / dx.doi.org/10.13182/NSE91-A23855

Measurement of the ¹⁹F(n,2n)¹⁸F Cross Section from 18 to 27 MeV

C. L. Hartmann, P. M. DeLuca, Jr.

Nuclear Science and Engineering / Volume 109 / Number 3 / November 1991 / Pages 319-323

Technical Note / dx.doi.org/10.13182/NSE91-A23856

Monitoring Pressurized Water Reactor Transients Using Reactor Coolant Pumps

James P. Adams, Glenn E. McCreery, Jong H. Kim

Nuclear Science and Engineering / Volume 109 / Number 4 / December 1991 / Pages 325-340

Technical Paper / dx.doi.org/10.13182/NSE91-A23858

Fission Cross-Section Measurements of ²⁴⁷Cm, ²⁵⁴Es, and ²⁵⁰Cf from 0.1 eV to 80 keV

Y. Danon, R. E. Slovacek, R. C. Block, R. W. Lougheed, R. W. Hoff, M. S. Moore

Nuclear Science and Engineering / Volume 109 / Number 4 / December 1991 / Pages 341-349

Technical Paper / dx.doi.org/10.13182/NSE91-A23859

Cross Sections for Formation of Fission Products in the ²³⁸U(p, f) Reaction at Proton Energies Between 12 and 30 MeV

E. Karttunen, M. Brenner, V. A. Rubchená, S. A. Egorov, V. B. Funschtein, V. A. Jakovlev, Yu. A. Selitskiy

Nuclear Science and Engineering / Volume 109 / Number 4 / December 1991 / Pages 350-359

Technical Paper / dx.doi.org/10.13182/NSE91-A23860

A Consistent Technique for the Global Homogenization of a Pressurized Water Reactor Assembly

Alain Hébert, Pierre Benoist

Nuclear Science and Engineering / Volume 109 / Number 4 / December 1991 / Pages 360-372

Technical Paper / dx.doi.org/10.13182/NSE109-360

Mitigation of Singularity Problems in Gamma-Ray Transport in Spherical Systems

K. V. Subbaiah, A. Natarajan, D. V. Gopinath, K. Takeuchi

Nuclear Science and Engineering / Volume 109 / Number 4 / December 1991 / Pages 373-379

Technical Paper / dx.doi.org/10.13182/NSE91-A23862

Transmission of Intermediate-Energy Neutrons and Associated Gamma Rays Through Iron, Lead, Graphite, and Concrete Shields

Kazuo Shin, Yoshiaki Ishii, Kagetomo Miyahara, Yoshitomo Uwamino, Hideyuki Sakai, Sigeo Numata

Nuclear Science and Engineering / Volume 109 / Number 4 / December 1991 / Pages 380-390

Technical Paper / dx.doi.org/10.13182/NSE91-A23863

Calculated Energy and Angular Dependence of Particle Fluxes at the Exit of the Advanced Neutron Source Radial and Tangential Beam Tubes

M. Hayashi, T. Nishigori, R. G. Alsmiller, Jr., R. A. Lillie

Nuclear Science and Engineering / Volume 109 / Number 4 / December 1991 / Pages 391-400

Technical Paper / dx.doi.org/10.13182/NSE91-A23864

Heating-Induced Damping of Density Perturbations in Nuclear-Reactor-Pumped Lasers

J. R. Torczynski

Nuclear Science and Engineering / Volume 109 / Number 4 / December 1991 / Pages 401-410

Technical Paper / dx.doi.org/10.13182/NSE91-A23865

Antiproton-Boosted Microfission

R. A. Lewis, R. Newton, G. A. Smith, R. J. Kanzleiter

Nuclear Science and Engineering / Volume 109 / Number 4 / December 1991 / Pages 411-415

Technical Paper / dx.doi.org/10.13182/NSE91-A23866

Approximate Estimators for Fluence at a Point in Monte Carlo Center-of-Mass Neutron Transport

Esam M. A. Hussein

Nuclear Science and Engineering / Volume 109 / Number 4 / December 1991 / Pages 416-422

Technical Note / dx.doi.org/10.13182/NSE91-A23867