Thermal Hydraulic and Mechanical Aspects of In-Vessel Retention of Core Debris
Creators
- 1. Department of Nuclear Engineering, Seoul National University, 56-1 Shinrim-dong, Gwanak-gu, Seoul, 151-742 (Korea, Republic of)
Description
Several advanced water reactor designs incorporate provisions to manage the escaped core debris outside the reactor vessel. This type of ex-vessel management approach involves a difficult task of core debris cooling, direct containment heating and steam explosion control inside the containment building. If one can secure the integrity of the lower head by maintaining coolability within the reactor, core meltdown accidents will be arrested within the vessel at a significant advantage over the ex-vessel measures. This paper examines potential options for in-vessel retention for large PWRs as functions of time spent for the wetting of the external wall of the lower head. Several important options were evaluated utilizing detailed thermohydraulic and mechanical analysis models that have been developed and benchmarked against experimental data. Results elucidate that the risk of lower head failure by either creep rupture or quench fracture increases rapidly with the amount of time spent till external wall wetting. To expedite rapid wetting of the lower head without installation of major pumping systems and large inventory of cooling water, gap structures have been proposed inside and outside the reactor vessel lower head. The external gap structure, designated as COASISO, is shown to be an effective tool for in-vessel retention of core melt for both new and operating reactors during a hypothetical severe accident. (authors)
Files
44026320.pdf
Files
(444.2 kB)
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Additional details
Publishing Information
- Imprint Title
- Proceedings of the Workshop on in-vessel core debris retention and coolability
- Imprint Pagination
- 409 p.
- Journal Page Range
- p. 399-404
- Report number
- NEA-CSNI-R--1998-18
Conference
- Title
- Workshop on in-vessel core debris retention and coolability
- Dates
- 3-6 Mar 1998
- Place
- Garching (Germany)
INIS
- Country of Publication
- Nuclear Energy Agency of the OECD (NEA)
- Country of Input or Organization
- Nuclear Energy Agency of the OECD (NEA)
- INIS RN
- 44026320
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- ACCIDENT MANAGEMENT; COMPARATIVE EVALUATIONS; CONTAINMENT SYSTEMS; CORE CATCHERS; CORE FLOODING SYSTEMS; CORIUM; CREEP; FRACTURE MECHANICS; PWR TYPE REACTORS; REACTOR ACCIDENTS; REACTOR COOLING SYSTEMS; REACTOR CORES; REACTOR SAFETY; REACTOR VESSELS; RUPTURES; SYSTEM FAILURE ANALYSIS; THERMAL HYDRAULICS
- Descriptors DEC
- ACCIDENTS; CONTAINERS; CONTAINMENT; COOLING SYSTEMS; ECCS; ENERGY SYSTEMS; ENGINEERED SAFETY SYSTEMS; ENRICHED URANIUM REACTORS; EVALUATION; FAILURES; FLUID MECHANICS; HYDRAULICS; MANAGEMENT; MECHANICAL PROPERTIES; MECHANICS; POWER REACTORS; REACTOR COMPONENTS; REACTOR PROTECTION SYSTEMS; REACTORS; SAFETY; SYSTEMS ANALYSIS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- 9 refs.