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Second Thermal and Fluids Engineering  Conference

ISSN: 2379-1748
ISBN: 978-1-56700-430-4

Experimental Study For The Reflood Behavior of Nuclear Reactor In Medium And High Pressure Conditions Using 3×3 Heater Bundle

Jong-Rok Kim
Korea Atomic Energy Research Institute, Daedeok-Daero 989 Beon-Gil 111, Yuseong-Gu, Daejeon, KOREA

Jong-Kuk Park
Korea Atomic Energy Research Institute Daedeok-daero 989-111, Yuseong-gu, Daejeon, 305-353, Republic of Korea

Seok Cho
Korea Atomic Energy Research Institute Daedeok-daero 989-111, Yuseong-gu, Daejeon, 305-353, Republic of Korea

Young-Jung Youn
Korea Atomic Energy Research Institute Daedeok-daero 989-111, Yuseong-gu, Daejeon, 305-353, Republic of Korea

Hae Seob Choi
Korea Atomic Energy Research Institute Daedeok-daero 989-111, Yuseong-gu, Daejeon, 305-353, Republic of Korea

SeungHyun Hong
Korea Atomic Energy Research Institute, Daedeok- Daero 989-111, Yuseong-gu, Daejeon, 305-353, Republic of Korea

Sang-Ki Moon
Korea Atomic Energy Research Institute Daedeok-daero 989-111, Yuseong-gu, Daejeon, 305-353, Republic of Korea

Abstract

For a loss-of-coolant accident (LOCA) conditions in a pressurized-water reactor (PWR), the coolant level decreases and then fuel core is uncovered. The cladding temperature of uncovered fuel increases until the reflood phase, which is a process to refill coolant into the core, and the cladding ballooning can be made at high temperature position. The ballooned claddings block a coolant flow path in the fuel assembly and this flow blockage is one of the major concerns associated with the coolability of partially blocked regions. Several experimental programs had been devoted to perform the coolability after ballooned cladding. However, the previous experimental programs did not consider the ballooned cladding in medium and high pressure conditions. So, the coolability in partially blocked core in medium and high pressure conditions is one of the unresolved thermal-hydraulic safety issues. In the present experimental program at Korea Atomic Energy Research Institute, the reflood tests will be performed to investigate the effects of clad ballooning on the coolability of partially blocked rod bundle in medium and high pressure conditions. The first phase of this experimental program is the reflood test using intact rod bundle, which has 3×3 array intact heater rods, for reference conditions. And the second phase is the reflood test using nine partially ballooned heater rods. In the present research, the first phase experiments had been performed and analyzed. The peak cladding temperatures, quenching temperatures and quenching times were analyzed for various conditions.

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