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
Development of Thermalhydraulic Analysis Models for ATR
Yoshitaka HAYAMIZUSatoru SUGAWARAHiroyasu MOCHIZUKI
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1989 Volume 31 Issue 12 Pages 1343-1354

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Abstract
Analytical models for the ATR are characterized for thermal hydraulics in a pressure tube, a steam drum and a water drum, based on the configuration features of the primary cooling system. PNC constructed the experimental facilities in 1970, simulating pressure tubes and fuel bundles in full scale to develop a thermal hydraulic code system. Typical models are explained for the thermal hydraulic analyses of the ATR under normal, operational transient and LOCA conditions.
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© by the Atomic Energy Society of Japan
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