Effects of coolant flow on light water reactor fuel behaviors during reactivity initiated accident.

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概要

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• This paper describes the in-pile experimental results to study the influences of coolant flow on fuel behaviors under reactivity initiated accident (RIA) conditions performed in the Nuclear Safety Research Reactor (NSRR), A single PWR type test fuel rod was irradiated by a large neutron pulse in the NSRR to simulate a prompt power excursion of RIA's. The effects of coolant flow were studied at a coolant flow velocity of 0.31.8 m/s and a coolant temperature of 2090°C under the atmospheric pressure. It was found that the cooling conditions had considerable influences on fuel thermal behaviors under prompt heat-up. The increase of coolant flow velocity and subcooling enhanced heat transfer coefficient at cladding surface during film boiling, which resulted in large decrease of maximum cladding temperature and film boiling duration, and consequently in the increase of fuel failure threshold energy. The data tendencies are summarized and the influences of coolant flow are discussed with some computer analyses.

• 一般社団法人 日本原子力学会の論文

著者

• FUJISHIRO Toshio

  Division of Reactor Safety, Japan Atomic Energy Research Institute

関連論文

• Measurement and evaluation on pulsing characteristics and experimental capability of NSRR.
• Effects of coolant flow on light water reactor fuel behaviors during reactivity initiated accident.

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