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JAEA Reports

A Method for Evaluating the Linear Heat Rate of the Fuel Rod in BOCA/OSF-1

Kawamura, Hiroshi; ; ; ;

JAERI-M 85-211, 50 Pages, 1985/12


no abstracts in English

Oral presentation

Development of fuel transient test facility in JMTR

Kimura, Nobuaki; Matsui, Yoshinori; Tobita, Masahiro*; Nakamura, Jinichi; Yamaura, Takayuki

no journal, , 

Power transient tests for the fuels of light water reactors were to be carried out in the Japan Materials Testing Reactor (JMTR) using capsule-type irradiation test facilities, and the integrity of the fuels had been to be investigated by the tests. Prior to the irradiation tests of the fuels, evaluation of thermal-hydraulic behavior in the capsule using ACE-3D code were carried out. And more, the out-pile test facility, which had an electric heater pin instead of a test fuel pin, was designed and fabricated to simulate the capsules used in the power transient tests. Using this facility, necessary tests for the realization of the irradiation tests and the planning of the test methods were carried out. From these analytical and experimental results, it was confirmed that the power ramping tests for 10$$times$$10 BWR fuel are able to achieve linear heat rate of 600W/cm in JMTR.

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