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Volume 107

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Nuclear Science and Engineering / Volume 107 / Number 2

February 1991

Table of Contents

Nuclear Science and Engineering / Volume 107 / Number 1

January 1991

Table of Contents

Nuclear Science and Engineering / Volume 107 / Number 3

March 1991

Table of Contents

Nuclear Science and Engineering / Volume 107 / Number 4

April 1991

Reaction Cross Sections on Carbon for Neutron Energies from 11.5 to 19 MeV

B. Antolković, G. Dietze, H. Klein

Nuclear Science and Engineering / Volume 107 / Number 1 / Pages 1-21

January 1991

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Determination of Neutron-Induced Alpha-Particle Cross Sections on Carbon Using the Response of a Liquid Scintillation Detector

H. J. Brede, G. Dietze, H. Klein, H. Schölermann

Nuclear Science and Engineering / Volume 107 / Number 1 / Pages 22-34

January 1991

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252Cf-Source-Driven Noise Measurements of Subcriticality for a Slab Tank of Aqueous Pu-U Nitrate

J. T. Mihalczo, E. D. Blakeman, G. E. Ragan, R. C. Kryter, H. Seino, R. C. Robinson

Nuclear Science and Engineering / Volume 107 / Number 1 / Pages 35-57

January 1991

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Comparison of Vectorization Methods Used in a Monte Carlo Code

Masayuki Nakagawa, Takamasa Mori, Makoto Sasaki

Nuclear Science and Engineering / Volume 107 / Number 1 / Pages 58-66

January 1991

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Study of Slab Transmission and Reflection

C. M. Eisenhauer

Nuclear Science and Engineering / Volume 107 / Number 1 / Pages 67-81

January 1991

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Physics of the Conceptual Design of Intense Steady Neutron Sources

Felix C. Difilippo

Nuclear Science and Engineering / Volume 107 / Number 1 / Pages 82-98

January 1991

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Preparation, Conduct, and Experimental Results of the AVR Loss-of-Coolant Accident Simulation Test

K. Krüger, A. Bergerfurth, S. Burger, P. Pohl, M. Wimmers, J. C. Cleveland

Nuclear Science and Engineering / Volume 107 / Number 2 / Pages 99-113

February 1991

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Monte Carlo Calculation of Delayed Gamma Dose Rate in Complex Geometry Using the Concept of Effective Delayed Gamma Production Cross Section

S. L. Liew, L. P. Ku

Nuclear Science and Engineering / Volume 107 / Number 2 / Pages 114-130

February 1991

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Use of Qualitative and Quantitative Models in the Supervision of Power Plant Operations

Alex Galperin, Jean-Michel Evrard

Nuclear Science and Engineering / Volume 107 / Number 2 / Pages 131-141

February 1991

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KNOWBOT: An Adaptive Data Base Interface

A. Sharif Heger, Billy V. Koen

Nuclear Science and Engineering / Volume 107 / Number 2 / Pages 142-157

February 1991

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Adaptive Predictive Control of a Boiling Water Reactor

Chaung Lin, Shyurng-Rern Chang

Nuclear Science and Engineering / Volume 107 / Number 2 / Pages 158-172

February 1991

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A Mechanism for Out-of-Phase Power Instabilities in Boiling Water Reactors

José March-Leuba, E. D. Blakeman

Nuclear Science and Engineering / Volume 107 / Number 2 / Pages 173-179

February 1991

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Monte Carlo Analysis of a Neutron Streaming Experiment

S. N. Cramer, T. Y. Lee

Nuclear Science and Engineering / Volume 107 / Number 2 / Pages 180-187

February 1991

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A Model for Neutron Scattering Off Heavy Isotopes That Accounts for Thermal Agitation Effects

Mohamed Ouisloumen, Richard Sanchez

Nuclear Science and Engineering / Volume 107 / Number 3 / Pages 189-200

March 1991

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An Integral Sn Method for Large-Memory Supercomputers

S. P. Monahan, W. L. Filippone

Nuclear Science and Engineering / Volume 107 / Number 3 / Pages 201-216

March 1991

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Synthetic Acceleration Methods for Linear Transport Problems with Highly Anisotropic Scattering

Kassem M. Khattab, Edward W. Larsen

Nuclear Science and Engineering / Volume 107 / Number 3 / Pages 217-227

March 1991

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