Journal of the Atomic Energy Society of Japan / Atomic Energy Society of Japan
Online ISSN : 2186-5256
Print ISSN : 0004-7120
ISSN-L : 0004-7120
Safety Evaluation of Post Incident Devices of Light Water Power Reactor
Hideo FUJIE
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1966 Volume 8 Issue 11 Pages 609-613

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Abstract

In order to evaluated the effectiveness of post incident safety devices for light water power reactors, experiments were performed on the cooling efficiency of spray, the flow rate of saturated water from a pressure vessel, the heat transfer of a container wall surface, and the cooling efficiency of container spray, and the following results were obtained:
(1) Measurements of the temperature changes caused on heated rods (model fuel assembly) by spray cooling contributed to the formulation of a proposed theory to explain the temperature changes.
(2) The relationships existing between dry-out heat out-put and spray flow rate for stationary core spray cooling were obtained.
(3) The flow rate of saturated water from a model pressure vessel was measured and compared with Moody's theoretical results.
(4) The heat transfer coefficient of a container wall surface was measured with an apparatus installed in a model container and the variation of heat transfer with time and with inner-pressure of the container was determined.
(5) The relationship between cooling efficiency of container spray and inner-pressure of the container was obtained from experiments with a model container.

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