American Nuclear Society

/Create an Account

Home

Home / Publications / Journals / Nuclear Science and Engineering / Volume 123 / Number 1

Volume 123

Number 1

Table of Contents

Calculation and Evaluation of Cross Sections and Kerma Factors for Neutrons up to 100 MeV on ¹⁶O and ¹⁴N

M. B. Chadwick, P. G. Young

Nuclear Science and Engineering / Volume 123 / Number 1 / May 1996 / Pages 1-16

Technical Paper / dx.doi.org/10.13182/NSE96-A24209

Calculation and Evaluation of Cross Sections and Kerma Factors for Neutrons up to 100 MeV on Carbon

M. B. Chadwick, L. J. Cox, P. G. Young, A.S. Meigooni

Nuclear Science and Engineering / Volume 123 / Number 1 / May 1996 / Pages 17-37

Technical Paper / dx.doi.org/10.13182/NSE96-A24210

The Even-Parity and Simplified Even-Parity Transport Equations in Two-Dimensional x-y Geometry

Taewan Noh, Warren F. Miller, Jr., Jim E. Morel

Nuclear Science and Engineering / Volume 123 / Number 1 / May 1996 / Pages 38-56

Technical Paper / dx.doi.org/10.13182/NSE96-A24211

A Locally Exact Numerical Scheme with Nonoscillation Properties for Stationary Transport Equations with Absorption and Source Terms

Katsuhiro Sakai

Nuclear Science and Engineering / Volume 123 / Number 1 / May 1996 / Pages 57-67

Technical Paper / dx.doi.org/10.13182/NSE96-A24212

Singular Perturbation Solutions of the Neutron Transport Equation

David C. Losey, John C. Lee, William R. Martin, Thomas C. Adamson, Jr.

Nuclear Science and Engineering / Volume 123 / Number 1 / May 1996 / Pages 68-85

Technical Paper / dx.doi.org/10.13182/NSE96-A24213

The FLEXBURN Neutron Transport Code Developed by the S_n Method with Transmission Probabilities in Arbitrary Square Meshes for Light Water Reactor Fuel Assemblies

Takanori Kameyama, Tetsuo Matsumura, Makoto Sasak

Nuclear Science and Engineering / Volume 123 / Number 1 / May 1996 / Pages 86-95

Technical Paper / dx.doi.org/10.13182/NSE96-A24214

Continuous Energy Monte Carlo Calculations of Randomly Distributed Spherical Fuels in High-Temperature Gas-Cooled Reactors Based on a Statistical Geometry Model

Isao Murata, Takamasa Mori, Masayuki Nakagawa

Nuclear Science and Engineering / Volume 123 / Number 1 / May 1996 / Pages 96-109

Technical Paper / dx.doi.org/10.13182/NSE96-A24215

The Two-Region Milne Problem

B.D. Ganapol, G. C. Pomraning

Nuclear Science and Engineering / Volume 123 / Number 1 / May 1996 / Pages 110-120

Technical Paper / dx.doi.org/10.13182/NSE96-A24216

The Effective Fuel Temperature to be Used for Calculating Resonance Absorption in a ²³⁸UO₂ Lump with a Nonuniform Temperature Profile

W. J. M. de Kruijf, A. J. Janssen

Nuclear Science and Engineering / Volume 123 / Number 1 / May 1996 / Pages 121-135

Technical Paper / dx.doi.org/10.13182/NSE94-108

The Effect of Gas Injection Configuration on Two-Phase Countercurrent Flow Limitation in Short Vertical Channels

S. M. Ghiaasiaan, J. D. Bohner, S. I. Abdel-Khalik

Nuclear Science and Engineering / Volume 123 / Number 1 / May 1996 / Pages 136-146

Technical Paper / dx.doi.org/10.13182/NSE96-A24218

Home|Contact Us|Invoice Payment|Nuclear Links

Privacy Policy|Terms of Use