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Volume 99

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Number 1

Neutron-Induced Fission Cross Section of 243Am in the Energy Range from 1 eV to 10 MeV

H-H. Knitter, C. Budtz-Jørgensen

Nuclear Science and Engineering / Volume 99 / Number 1 / May 1988 / Pages 1-12

Technical Paper / dx.doi.org/10.13182/NSE88-A23540

Correlation of the Signals from Detectors in the Presence of a Stochastic Neutron Field

Felix C. Difilippo

Nuclear Science and Engineering / Volume 99 / Number 1 / May 1988 / Pages 28-35

Technical Paper / dx.doi.org/10.13182/NSE88-A23542

A Vectorized Source Algorithm for the Light Water Reactor Coarse-Mesh Nodal Code SIMULATE-E

Charles A. Wemple, Ilhan Dilber, Thomas J. Downar

Nuclear Science and Engineering / Volume 99 / Number 1 / May 1988 / Pages 36-40

Technical Paper / dx.doi.org/10.13182/NSE88-A23543

Fertile-to-Fissile and Fission Measurements for Depleted Uranium and Thorium Bombarded by 800-MeV Protons

J. S. Gilmore, G. J. Russell, H. Robinson, R. E. Prael

Nuclear Science and Engineering / Volume 99 / Number 1 / May 1988 / Pages 41-52

Technical Paper / dx.doi.org/10.13182/NSE88-A23544

Sensitivity Analysis of Two-Phase Flow Problems

N. Toomarian, E. Wacholder, S. Kaizerman

Nuclear Science and Engineering / Volume 99 / Number 1 / May 1988 / Pages 53-81

Technical Paper / dx.doi.org/10.13182/NSE88-A23545

Radon in Air Calibration Procedure: A Primary Method

H.F. Lucas, F. Markun

Nuclear Science and Engineering / Volume 99 / Number 1 / May 1988 / Pages 82-87

Technical Note / dx.doi.org/10.13182/NSE88-A23546

Number 2

Stability Analysis of Synthetic Acceleration Methods with Anisotropic Scattering

Dimitris Valougeorgis, Michael Williams, Edward W. Larsen

Nuclear Science and Engineering / Volume 99 / Number 2 / June 1988 / Pages 91-98

Technical Paper / dx.doi.org/10.13182/NSE88-A23549

Nodal Synthesis—Consistent Nodal Approach for Global Reactor Analysis

Jerzy Mackiewicz

Nuclear Science and Engineering / Volume 99 / Number 2 / June 1988 / Pages 99-108

Technical Paper / dx.doi.org/10.13182/NSE88-A23550

Numerical Improvements of the Exact Kernel Method in Transport Theory

Jacques Ligou, Patrick Miazza

Nuclear Science and Engineering / Volume 99 / Number 2 / June 1988 / Pages 109-117

Technical Paper / dx.doi.org/10.13182/NSE88-A23551

On Choice of Trial Functions in Integro-Differential Variational Principles of Transport Theory

S. K. Loyalka, J. W. Cipolla, Jr.

Nuclear Science and Engineering / Volume 99 / Number 2 / June 1988 / Pages 118-122

Technical Paper / dx.doi.org/10.13182/NSE88-A23552

Application of Richardson Extrapolation to Numerical Solution of the Neutron Transport Equation

E. J. Allen

Nuclear Science and Engineering / Volume 99 / Number 2 / June 1988 / Pages 123-132

Technical Paper / dx.doi.org/10.13182/NSE88-A23553

Neutron Capture by 79Br, 81Br, and 75As

Richard L. Macklin

Nuclear Science and Engineering / Volume 99 / Number 2 / June 1988 / Pages 133-144

Technical Paper / dx.doi.org/10.13182/NSE88-A23554

Effects of Incoherent and Coherent Scattering on the Exposure Buildup Factors of Low-Energy Gamma Rays

H. Hirayama, D. K. Trubey

Nuclear Science and Engineering / Volume 99 / Number 2 / June 1988 / Pages 145-156

Technical Paper / dx.doi.org/10.13182/NSE88-A23555

Integral Check on Nuclear Data of 232Th with Neutron Spectra in a Thoria Pile and from a Thorium Slab

Katsuhei Kobayashi, Itsuro Kimura, Takamasa Mori

Nuclear Science and Engineering / Volume 99 / Number 2 / June 1988 / Pages 157-171

Technical Paper / dx.doi.org/10.13182/NSE88-A23556

The Accuracy of Processed Nuclear Data

Dermott E. Cullen

Nuclear Science and Engineering / Volume 99 / Number 2 / June 1988 / Pages 172-181

Technical Note / dx.doi.org/10.13182/NSE88-A23557

Number 3

Generalized Control System Modeling for Liquid-Metal Reactors

R. B. Vilim, T. Y. C. Wei, F. E. Dunn

Nuclear Science and Engineering / Volume 99 / Number 3 / July 1988 / Pages 183-196

Technical Paper / dx.doi.org/10.13182/NSE88-4

A Rigorous Solution to the Classical Space-Dependent Neutron Slowing Down Transport Problem

V. C. Boffi, W. L. Dunn, G. Spiga

Nuclear Science and Engineering / Volume 99 / Number 3 / July 1988 / Pages 197-207

Technical Paper / dx.doi.org/10.13182/NSE88-A28993

Combined Monte Carlo Narrow Resonance-Intermediate Resonance Method for Testing Resonance Integral Calculations in Complex Geometries

I. J. Chen, E. M. Gelbard

Nuclear Science and Engineering / Volume 99 / Number 3 / July 1988 / Pages 208-231

Technical Paper / dx.doi.org/10.13182/NSE88-A28994

The Theory and Application of SMART Electron Scattering Matrices

W. L. Filippone

Nuclear Science and Engineering / Volume 99 / Number 3 / July 1988 / Pages 232-250

Technical Paper / dx.doi.org/10.13182/NSE88-A28995

An Improved Method for Estimating Particle Scattering Probabilities to Finite Detectors for Monte Carlo Simulation

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

Nuclear Science and Engineering / Volume 99 / Number 3 / July 1988 / Pages 251-266

Technical Paper / dx.doi.org/10.13182/NSE88-A28996

Measurement of the Neutron-Induced Fission Cross Sections of 242Cm and 238Pu

Badrul Alam, Robert C. Block

Nuclear Science and Engineering / Volume 99 / Number 3 / July 1988 / Pages 267-277

Technical Paper / dx.doi.org/10.13182/NSE88-A28997

Potential Applications of 242mAm as a Nuclear Fuel

Yigal Ronen, Melvin J. Leibson

Nuclear Science and Engineering / Volume 99 / Number 3 / July 1988 / Pages 278-284

Technical Paper / dx.doi.org/10.13182/NSE88-A28998

Charged-Particle Transport in One Dimension

John W. Wilson, Lawrence W. Townsend, Barry Ganapol, Sang Y. Chun, Warren W. Buck

Nuclear Science and Engineering / Volume 99 / Number 3 / July 1988 / Pages 285-287

Technical Note / dx.doi.org/10.13182/NSE88-A28999

Number 4

Nonuniform Steam Generator U-Tube Flow Distribution During Natural Circulation Tests in ROSA-IV Large Scale Test Facility

Y. Kukita, H. Nakamura, K. Tasaka, C. Chauliac

Nuclear Science and Engineering / Volume 99 / Number 4 / August 1988 / Pages 289-298

Technical Paper / dx.doi.org/10.13182/NSE99-289

Study on Coolant Void Reactivity of Pressure-Tube-Type Heavy Water Lattice by the Substitution Method

Yasuki Kowata, Nobuo Fukumura

Nuclear Science and Engineering / Volume 99 / Number 4 / August 1988 / Pages 299-312

Technical Paper / dx.doi.org/10.13182/NSE88-A23560

On the Neutron Noise Diagnostics of Pressurized Water Reactor Control Rod Vibrations. III. Application at a Power Plant

I. Pázsit, O. Glöckler+

Nuclear Science and Engineering / Volume 99 / Number 4 / August 1988 / Pages 313-328

Technical Paper / dx.doi.org/10.13182/NSE88-A23561

Monte Carlo Shielding Analyses Using an Automated Biasing Procedure

J. S. Tang, T. J. Hoffman

Nuclear Science and Engineering / Volume 99 / Number 4 / August 1988 / Pages 329-342

Technical Paper / dx.doi.org/10.13182/NSE88-A23562

Application of a Heuristic Search Method for Generation of Fuel Reload Configurations

A. Galperin, E. Nissan

Nuclear Science and Engineering / Volume 99 / Number 4 / August 1988 / Pages 343-352

Technical Paper / dx.doi.org/10.13182/NSE88-A23563

Generalized Perturbation Theory for Constant Power Core Depletion

Won Sik Yang, Thomas J. Downar

Nuclear Science and Engineering / Volume 99 / Number 4 / August 1988 / Pages 353-366

Technical Paper / dx.doi.org/10.13182/NSE99-353

Systematics of Excitation Function for (n, Charged-Particle) Reactions

Zhao Zhixiang, Zhou Delin

Nuclear Science and Engineering / Volume 99 / Number 4 / August 1988 / Pages 367-374

Technical Paper / dx.doi.org/10.13182/NSE88-A23565

Evaluation of p for 239Pu: Impact for Applications of the Fluctuations at Low Energy

E. Fort, J. Fréhaut, H. Tellier, P. Long

Nuclear Science and Engineering / Volume 99 / Number 4 / August 1988 / Pages 375-389

Technical Paper / dx.doi.org/10.13182/NSE88-A23566

The Radiolytic Gas Production Rate in Boiling Water Reactors

Chien C. Lin

Nuclear Science and Engineering / Volume 99 / Number 4 / August 1988 / Pages 390-393

Technical Note / dx.doi.org/10.13182/NSE88-A23567