본문 바로가기
KERD
논문KCI 등재

코어캐처 노심용융물 차단설비 적용을 위한 MCCI 해석적 연구

Analytical Study on Molten Corium-Concrete Interaction for Melt Barrier Application on Core Catcher

2

조회

0

다운로드

0

인용

0

참고문헌

키워드

주제분류기계공학

초록

MCCI, one of the ex-vessel phenomena during a severe accident, is generally caused by mutual reactions between molten core and reactor building basemat concrete, but occurs between sacrificial materials made by concrete and corium in APR nuclear power plant with PECS applied. In this paper, MCCI analysis was performed to design and apply a device to block the core melt at the junction connected to the ICI cavity sump from the core catcher installed in the reactor cavity of the APR. Unlike the sacrificial material, which has a cooling effect by inducing erosion of the ex-vessel core melt, the device is composed of concrete applied as a barrier to protect the ICI cavity sump. The decent thickness of the barrier wall of the device was calculated.

Abstract

MCCI, one of the ex-vessel phenomena during a severe accident, is generally caused by mutual reactions between molten core and reactor building basemat concrete, but occurs between sacrificial materials made by concrete and corium in APR nuclear power plant with PECS applied. In this paper, MCCI analysis was performed to design and apply a device to block the core melt at the junction connected to the ICI cavity sump from the core catcher installed in the reactor cavity of the APR. Unlike the sacrificial material, which has a cooling effect by inducing erosion of the ex-vessel core melt, the device is composed of concrete applied as a barrier to protect the ICI cavity sump. The decent thickness of the barrier wall of the device was calculated.

참고문헌 (6)

  1. "Advanced Power Reactors in Korea" (2017)[URL]
  2. Kim, M. S., "Development of Core Catcher for EU-APR1400", The Spring and Autumn Conference of KSME, pp.2485~2489 (2011)
  3. USNRC, "SECY-93-087, Policy, Technical, and Licensing Issues Pertaining to Evolutionary and Advanced Light-Water Reactor(ALWR) Designs", ~ (1993)
  4. OECD MCCI Project Final Report, "M. T. Farmer", ANL, ~ (2006)
  5. EPRI, "Modular Accident Analysis Program for LWR Power Plants-Computer Code Manual", ~ (2013)
  6. An, S. M., "Ablation characterics of special concrete due to an impinging zirconium-dioxide melt jet", NED, 284(1), pp.10~18 (2015)

관련 논문AI추천

Development of ex-vessel corium coolability analysis program(COCCA) with simplified models validated against FARO experiments정석규, 정재훈한국원자력학회 · Nuclear Engineering and Technology2025 · 제57권 제5호Analysis on the discharge characteristics and spreading behavior of an ex-vessel core melt in the SMART김상호, 김성일, 김환열, 박래준, 이병희, 정재훈, 함재현한국원자력학회 · Nuclear Engineering and Technology2022 · 제54권 제12호Experimental study on natural circulation cooling system for core catcher with downward-facing heating channel강준영, 강창완, 김진혁, 이병희, 정석규, 홍성호한국원자력학회 · Nuclear Engineering and Technology2025 · 제57권 제12호Transient heat transfer and crust evolution during debris bed melting process in the hypothetical severe accident of HPR1000Gao Jinchen, Li Gen, Lv Chao, Wang Jinshi, Yan Junjie한국원자력학회 · Nuclear Engineering and Technology2023 · 제55권 제8호Assessment of the core-catcher in the VVER-1000 reactor containment under various severe accidentsFaghihi Farshad, Rabiee Ataollah, Salari Farhad한국원자력학회 · Nuclear Engineering and Technology2023 · 제55권 제1호Numerical simulation on in-vessel molten corium behavior with external vessel cooling using smoothed particle hydrodynamics김윤재, 김응수, 박소현, 이연건, 이태훈, 임국희한국원자력학회 · Nuclear Engineering and Technology2024 · 제56권 제10호

이 간행물의 다른 논문 (43건)