Neutron Flux Analysis for Power Reactor Instrumentation Design
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Authors
Baldwin, George T.
Issue Date
1975
Type
Thesis
Language
en_US
Keywords
Alternative Title
Abstract
This Senior Individualized Project has been a first step theoretical analysis in an ongoing design engineering project conducted at the Nuclear Energy Division of the General Electric Company. A proposed "neutron window," a solid zirconium enclosure
for the in-core instrumentation for the boiling water reactor, was simulated, using two-group diffusion theory applied to three materials in a two-dimensional
mixed geometry. The analysis involved development of a computer routine, using relaxation methods, on the H-6000 time-share facility. The "neutron window" feature was found to induce a low and flattened thermal neutron flux distribution in
the instrument location, thus providing for improved measurement accuracy and increased detector life expectancy.
Description
iv, 58 p.
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License
U.S. copyright laws protect this material. Commercial use or distribution of this material is not permitted without prior written permission of the copyright holder. All rights reserved.