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Volume 107 / Number 2

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Nuclear Science and Engineering / Volume 107 / Number 2

February 1991

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

Format:

Price:$30.00

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

Format:

Price:$30.00

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

Format:

Price:$30.00

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

Format:

Price:$30.00

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

Format:

Price:$30.00

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

Format:

Price:$30.00

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

Format:

Price:$30.00
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