Center for Nuclear Technology Assessment - BATAN
Email: igndjoko@batan.go.id
ABSTRACT
PRIMARY SYSTEM DEPRESSURIZATION ACCIDENT ANALYSIS IN THE HTTR. The behavior of the HTTR (High Temperature Testing Reactor) during depressurization accident caused by a primary pipe rupture was analyzed in a safety analysis of HTTR. The analysis was performed using TAC-NC computer code which is a thermal hydraulics code used to calculate thermal transient, including natural circulation. This paper describes analytical model, analytical condition and analytical results during the depressurization accident. The analytical results proved that thermal transient behavior during depressurization accident is slower than that of the PWR (Pressurized Water Reactor) for the similar accident. It also proved that the maximum fuel temperature does not exceed the normal operation temperature 1495 C, and the maximum pressure vessel temperature would remain below its limit of 550 C.
Keywords : Primary System, Accident Analysis, HTTR, Thermal Transient.
Published : Proceeding "Seminar dan Lokakarya ke-3 Teknologi dan Aplikasi Reaktor Temperatur Tinggi", Jakarta, 3-4 Juni 1996, ISSN No. : 0854-8803
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