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Advanced in-vessel retention design for next generation risk management

Abstract

In the TMI-2 accident, approximately twenty (20) tons of molten core material drained into the lower plenum. Early advanced light water reactor (LWR) designs assumed a lower head failure and incorporated various measures for ex-vessel accident mitigation. However,one of the major findings from the TMI-2 Vessel Investigation Project was that one part of the reactor lower head wall estimated to have attained a temperature of 1100 deg C for about 30 minutes has seemingly experienced a comparatively rapid cooldown with no major threat to the vessel integrity. In this regard, recent empirical and analytical studies have shifted interests to such in-vessel retention designs or strategies as reactor cavity flooding, in-vessel flooding and engineered gap cooling of the vessel. Accurate thermohydrodynamic and creep deformation modeling and rupture prediction are the key to the success in developing practically useful in-vessel accident/risk management strategies. As an advanced in-vessel design concept, this work presents the COrium Attack Syndrome Immunization Structures (COASIS) that are being developed as prospective in-vessel retention devices for a next-generation LWR in concert with existing ex-vessel management measures. Both the engineered gap structures in-vessel (COASISI) and ex-vessel (COASISO) are demonstrated to maintain effective heat transfer geometry during molten core debris attack  More>>
Authors:
Suh, Kune Y; Hwang, Il Soon [1] 
  1. Seoul National University, Seoul (Korea, Republic of)
Publication Date:
Dec 31, 1997
Product Type:
Conference
Report Number:
ETDE/KR-99732628; CONF-9710296-
Reference Number:
SCA: 220900; 210200; PA: KR-99:000326; EDB-99:035286; SN: 99002059953
Resource Relation:
Conference: Korean Nuclear Society autumn meeting, Taegu (Korea, Republic of), 24-25 Oct 1997; Other Information: PBD: 1997; Related Information: Is Part Of Proceedings of the korean nuclear society autumn meeting vol I, October 24-25, 1997 Taegu, Korea; PB: 797 p.
Subject:
22 NUCLEAR REACTOR TECHNOLOGY; 21 NUCLEAR POWER REACTORS AND ASSOCIATED PLANTS; MELTDOWN; REACTOR CORES; REACTOR VESSELS; PWR TYPE REACTORS; CAVITIES; CORE FLOODING SYSTEMS; REACTOR PROTECTION SYSTEMS; COOLING; REACTOR COOLING SYSTEMS; CREEP; RUPTURES; CORIUM; MANAGEMENT
OSTI ID:
324171
Research Organizations:
Korean Nuclear Society, Taejon (Korea, Republic of)
Country of Origin:
Korea, Republic of
Language:
English
Other Identifying Numbers:
Other: ON: DE99732628; TRN: KR9900326
Availability:
OSTI as DE99732628
Submitting Site:
KR
Size:
pp. 713-718
Announcement Date:

Citation Formats

Suh, Kune Y, and Hwang, Il Soon. Advanced in-vessel retention design for next generation risk management. Korea, Republic of: N. p., 1997. Web.
Suh, Kune Y, & Hwang, Il Soon. Advanced in-vessel retention design for next generation risk management. Korea, Republic of.
Suh, Kune Y, and Hwang, Il Soon. 1997. "Advanced in-vessel retention design for next generation risk management." Korea, Republic of.
@misc{etde_324171,
title = {Advanced in-vessel retention design for next generation risk management}
author = {Suh, Kune Y, and Hwang, Il Soon}
abstractNote = {In the TMI-2 accident, approximately twenty (20) tons of molten core material drained into the lower plenum. Early advanced light water reactor (LWR) designs assumed a lower head failure and incorporated various measures for ex-vessel accident mitigation. However,one of the major findings from the TMI-2 Vessel Investigation Project was that one part of the reactor lower head wall estimated to have attained a temperature of 1100 deg C for about 30 minutes has seemingly experienced a comparatively rapid cooldown with no major threat to the vessel integrity. In this regard, recent empirical and analytical studies have shifted interests to such in-vessel retention designs or strategies as reactor cavity flooding, in-vessel flooding and engineered gap cooling of the vessel. Accurate thermohydrodynamic and creep deformation modeling and rupture prediction are the key to the success in developing practically useful in-vessel accident/risk management strategies. As an advanced in-vessel design concept, this work presents the COrium Attack Syndrome Immunization Structures (COASIS) that are being developed as prospective in-vessel retention devices for a next-generation LWR in concert with existing ex-vessel management measures. Both the engineered gap structures in-vessel (COASISI) and ex-vessel (COASISO) are demonstrated to maintain effective heat transfer geometry during molten core debris attack when applied to the Korean Standard Nuclear Power Plant (KSNPP) reactor. The likelihood of lower head creep rupture during a severe accident is found to be significantly suppressed by the COASIS options. 15 refs., 5 figs., 1 tab. (Author)}
place = {Korea, Republic of}
year = {1997}
month = {Dec}
}