ANS / Publications / Journals / Nuclear Science and Engineering

Neutronic Design of a Fission Converter-Based Epithermal Neutron Beam for Neutron Capture Therapy

W. S. Kiger III, S. Sakamoto, O. K. Harling

Nuclear Science and Engineering / Volume 131 / Number 1 / January 1999 / Pages 1-22

Technical Paper / dx.doi.org/10.13182/NSE99-A2015

Nonlinear Analysis of a Natural Circulation Boiling Water Reactor

D. D. B. van Bragt, Rizwan-uddin, T. H. J. J. van der Hagen

Nuclear Science and Engineering / Volume 131 / Number 1 / January 1999 / Pages 23-44

Technical Paper / dx.doi.org/10.13182/NSE99-A2016

Design of a Spent-Fuel Assay Device Using a Lead Spectrometer

Yong-Deok Lee, Naeem M. Abdurrahman, Robert C. Block, Donald R. Harris, Rudy E. Slovacek

Nuclear Science and Engineering / Volume 131 / Number 1 / January 1999 / Pages 45-61

Technical Paper / dx.doi.org/10.13182/NSE97-100

Composition Adjustment on Direct Use of Spent Pressurized Water Reactor Fuel in CANDU

Hangbok Choi, Jongwon Choi, Myung S. Yang

Nuclear Science and Engineering / Volume 131 / Number 1 / January 1999 / Pages 62-77

Technical Paper / dx.doi.org/10.13182/NSE99-A2018

Cascade-Exciton Model Analysis of Nucleon-Induced Fission Cross Sections of Lead and Bismuth at 45- to 500-MeV Energies

A. V. Prokofiev, S. G. Mashnik, A. J. Sierk

Nuclear Science and Engineering / Volume 131 / Number 1 / January 1999 / Pages 78-95

Technical Paper / dx.doi.org/10.13182/NSE99-A2019

Experimental Determination of the Resonance Integral for ²³⁷Np in a Heavy Water Solution

Yu. E. Titarenko, O. V. Shvedov, M. M. Igumnov, E. I. Karpikhin, V. F. Batyaev, V. I. Volk, A. Yu. Vakhrushin, S. V. Shepelkov, A. V. Lopatkin, S. G. Mashnik, T. A. Gabriel

Nuclear Science and Engineering / Volume 131 / Number 1 / January 1999 / Pages 96-106

Technical Paper / dx.doi.org/10.13182/NSE99-A2020

Estimation of Energy Dependence of the Optical Potential Parameters for ²⁰⁹Bi

Toshihiko Kawano

Nuclear Science and Engineering / Volume 131 / Number 1 / January 1999 / Pages 107-115

Technical Paper / dx.doi.org/10.13182/NSE99-A2021

Numerical Evaluation of a Screened Rutherford Pencil Beam Solution

G. C. Pomraning, Anil K. Prinja

Nuclear Science and Engineering / Volume 131 / Number 1 / January 1999 / Pages 116-122

Technical Paper / dx.doi.org/10.13182/NSE99-A2022

In-Rod Effective Cross Sections of Resonance Absorbers Evaluated with Routine Cell Codes

M. Segev, G. Raitses, J. M. Paratte

Nuclear Science and Engineering / Volume 131 / Number 1 / January 1999 / Pages 123-131

Technical Paper / dx.doi.org/10.13182/NSE99-A2023

Direction Cosines and Polarization Vectors for Monte Carlo Photon Scattering

Douglas E. Peplow

Nuclear Science and Engineering / Volume 131 / Number 1 / January 1999 / Pages 132-136

Technical Note / dx.doi.org/10.13182/NSE99-A2024

Dimensionally Adaptive Neutron Kinetics for Multidimensional Reactor Safety Transients - I: New Features of RELAP5/PANBOX

C. J. Jackson, D. G. Cacuci, H. B. Finnemann

Nuclear Science and Engineering / Volume 131 / Number 2 / February 1999 / Pages 143-163

Technical Paper / dx.doi.org/10.13182/NSE99-A2025

Dimensionally Adaptive Neutron Kinetics for Multidimensional Reactor Safety Transients - II: Dimensionally Adaptive Switching Algorithms

C. J. Jackson, D. G. Cacuci, H. B. Finnemann

Nuclear Science and Engineering / Volume 131 / Number 2 / February 1999 / Pages 164-186

Technical Paper / dx.doi.org/10.13182/NSE99-A2026

Spatial Neutronic Decoupling of Large Fast Breeder Reactor Cores: Application to Nuclear Core Design Method

Keisho Shirakata, Toshio Sanda, Fumiaki Nakashima

Nuclear Science and Engineering / Volume 131 / Number 2 / February 1999 / Pages 187-198

Technical Paper / dx.doi.org/10.13182/NSE99-A2027

Uniform Positive-Weight Quadratures for Discrete Ordinate Transport Calculations

John F. Carew, Gabriel Zamonsky

Nuclear Science and Engineering / Volume 131 / Number 2 / February 1999 / Pages 199-207

Technical Paper / dx.doi.org/10.13182/NSE97-83

Status of Six-Group Delayed Neutron Data and Relationships Between Delayed Neutron Parameters from the Macroscopic and Microscopic Approaches

T. A. Parish, W. S. Charlton, N. Shinohara, M. Andoh, M. C. Brady, S. Raman

Nuclear Science and Engineering / Volume 131 / Number 2 / February 1999 / Pages 208-221

Technical Paper / dx.doi.org/10.13182/NSE99-A2029

The Influence of Crystalline Binding on Resonant Absorption and Reaction Rates

Dimitri G. Naberejnev, Claude Mounier, Richard Sanchez

Nuclear Science and Engineering / Volume 131 / Number 2 / February 1999 / Pages 222-229

Technical Paper / dx.doi.org/10.13182/NSE99-A2030

R-Matrix Analysis of ²³⁵U Neutron Transmission and Cross-Section Measurements in the 0- to 2.25-keV Energy Range

L. C. Leal, H. Derrien, N. M. Larson, R. Q. Wright

Nuclear Science and Engineering / Volume 131 / Number 2 / February 1999 / Pages 230-253

Technical Paper / dx.doi.org/10.13182/NSE99-A2031

Integral Data Analysis for Resonance Parameter Determination

N. M. Larson, L. C. Leal, H. Derrien

Nuclear Science and Engineering / Volume 131 / Number 2 / February 1999 / Pages 254-266

Technical Paper / dx.doi.org/10.13182/NSE99-A2032

The Effect of Low-Energy Neutrons on Activation Cross-Section Measurement

Xiaolong Huang, Weixiang Yu, Xiaogang Han, Wenrong Zhao, Hanlin Lu, Jinxiang Chen, Zhaomin Shi, Gouyou Tang, Guohui Zhang

Nuclear Science and Engineering / Volume 131 / Number 2 / February 1999 / Pages 267-274

Technical Paper / dx.doi.org/10.13182/NSE99-A2033

Design of a Subcritical Assembly for Conducting Neutron Activation Analyses in the Field

Mark S. Jarzemba, James Weldy, English Pearcy

Nuclear Science and Engineering / Volume 131 / Number 2 / February 1999 / Pages 275-281

Technical Paper / dx.doi.org/10.13182/NSE131-275

Testing of Multigroup Neutron Cross-Section Libraries on Neutron Transmission Through the VVER-440 Vessel

K. Ilieva, S. Belousov, T. Apostolov

Nuclear Science and Engineering / Volume 131 / Number 2 / February 1999 / Pages 282-285

Technical Paper / dx.doi.org/10.13182/NSE99-A2035

On the Existence of Multiple Harmonics in Neutronic Spectra of Regional Oscillations in the Ringhals-1 Boiling Water Reactor

G. Th. Analytis, J. K.-H. Karlsson {ti}Spatial Neutronic Decoupling of Large Fast Breeder Reactor Cores: Application to Nuclear Core Design Method

Nuclear Science and Engineering / Volume 131 / Number 2 / February 1999 / Pages 286-292

Technical Note / dx.doi.org/10.13182/NSE99-A2036

Cross-Section Evaluations to 150 MeV for Accelerator-Driven Systems and Implementation in MCNPX

M. B. Chadwick, P. G. Young, S. Chiba, S. C. Frankle, G. M. Hale, H. G. Hughes, A. J. Koning, R. C. Little, R. E. MacFarlane, R. E. Prael, L. S. Waters

Nuclear Science and Engineering / Volume 131 / Number 3 / March 1999 / Pages 293-328

Technical Paper / dx.doi.org/10.13182/NSE98-48

PRODIAG: A Process-Independent Transient Diagnostic System - I: Theoretical Concepts

Jaques Reifman, Thomas Y. C. Wei

Nuclear Science and Engineering / Volume 131 / Number 3 / March 1999 / Pages 329-347

Technical Paper / dx.doi.org/10.13182/NSE99-A2038

PRODIAG: A Process-Independent Transient Diagnostic System - II: Validation Tests

Jaques Reifman, Thomas Y. C. Wei

Nuclear Science and Engineering / Volume 131 / Number 3 / March 1999 / Pages 348-369

Technical Paper / dx.doi.org/10.13182/NSE99-A2039

Calculating Flux Perturbations with a Davidson Algorithm

Chung-Hsing Hu, Wen-Wei Lin, Yen-Wan Hsueh Liu

Nuclear Science and Engineering / Volume 131 / Number 3 / March 1999 / Pages 370-386

Technical Paper / dx.doi.org/10.13182/NSE99-A2040

The Intermediate Resonance Parameters in the Multigroup Formalism

A. Sanchez, A. dos Santos

Nuclear Science and Engineering / Volume 131 / Number 3 / March 1999 / Pages 387-400

Technical Paper / dx.doi.org/10.13182/NSE99-A2041

A Multiband Method with Resonance Interference Effect

Toshikazu Takeda, Yuichiro Kanayama

Nuclear Science and Engineering / Volume 131 / Number 3 / March 1999 / Pages 401-410

Technical Paper / dx.doi.org/10.13182/NSE99-A2042

Low-Flow Critical Heat Flux in Heated Microchannels

G. M. Roach, Jr., S. I. Abdel-Khalik, S. M. Ghiaasiaan, M. F. Dowling, S. M. Jeter

Nuclear Science and Engineering / Volume 131 / Number 3 / March 1999 / Pages 411-425

Technical Paper / dx.doi.org/10.13182/NSE99-A2043

Measurement of Safety Injection Fluid Transport in a Scaled Reactor Test

T. D. Radcliff, J. R. Parsons, W. S. Johnson, A. E. Ruggles

Nuclear Science and Engineering / Volume 131 / Number 3 / March 1999 / Pages 426-438

Technical Paper / dx.doi.org/10.13182/NSE99-A2044