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Development of severe accident analysis code - Development of a finite element code for lower head failure analysis

Abstract

The study concerns the development of analysis models and computer codes for lower head failure analysis when a severe accident occurs in a nuclear reactor system. Although the lower head failure modes consists of several failure modes, the study this year was focused on the global rupture with the collapse pressure and mode by limit analysis and elastic deformation. The behavior of molten core causes elevation of temperature in the reactor vessel wall and deterioration of load-carrying capacity of a reactor vessel. The behavior of molten core and the heat transfer modes were, therefore, postulated in several types and the temperature distributions according to the assumed heat flux modes were calculated. The collapse pressure of a nuclear reactor lower head decreases rapidly with elevation of temperature as time passes. The calculation shows the safety of a nuclear reactor is enhanced with the lager collapse pressure when the hot spot is located far from the pole. 42 refs., 2 tabs., 31 figs. (author)
Authors:
Huh, Hoon; Lee, Choong Ho; Choi, Tae Hoon; Kim, Hyun Sup; Kim, Se Ho; Kang, Woo Jong; Seo, Chong Kwan [1] 
  1. Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)
Publication Date:
Aug 01, 1995
Product Type:
Technical Report
Report Number:
KAERI-CM-051/94
Reference Number:
SCA: 210200; 220200; PA: KR-97:000749; EDB-98:023914; NTS-98:003981; SN: 98001897025
Resource Relation:
Other Information: PBD: Aug 1995
Subject:
21 NUCLEAR POWER REACTORS AND ASSOCIATED PLANTS; 22 NUCLEAR REACTOR TECHNOLOGY; SYSTEM FAILURE ANALYSIS; REACTOR VESSELS; REACTOR ACCIDENTS; FAILURES; RUPTURES; DEFORMATION; MOLTEN SALTS; MELTDOWN; HEAT FLUX; HEAT TRANSFER
OSTI ID:
574510
Research Organizations:
Korea Advanced Energy Research Inst., Daeduk-Danji (Korea, Republic of). Korea Nuclear Safety Center
Country of Origin:
Korea, Republic of
Language:
Korean
Other Identifying Numbers:
Other: ON: DE98724922; TRN: KR9700749
Availability:
OSTI as DE98724922
Submitting Site:
KR
Size:
87 p.
Announcement Date:
Mar 24, 1998

Citation Formats

Huh, Hoon, Lee, Choong Ho, Choi, Tae Hoon, Kim, Hyun Sup, Kim, Se Ho, Kang, Woo Jong, and Seo, Chong Kwan. Development of severe accident analysis code - Development of a finite element code for lower head failure analysis. Korea, Republic of: N. p., 1995. Web.
Huh, Hoon, Lee, Choong Ho, Choi, Tae Hoon, Kim, Hyun Sup, Kim, Se Ho, Kang, Woo Jong, & Seo, Chong Kwan. Development of severe accident analysis code - Development of a finite element code for lower head failure analysis. Korea, Republic of.
Huh, Hoon, Lee, Choong Ho, Choi, Tae Hoon, Kim, Hyun Sup, Kim, Se Ho, Kang, Woo Jong, and Seo, Chong Kwan. 1995. "Development of severe accident analysis code - Development of a finite element code for lower head failure analysis." Korea, Republic of.
@misc{etde_574510,
title = {Development of severe accident analysis code - Development of a finite element code for lower head failure analysis}
author = {Huh, Hoon, Lee, Choong Ho, Choi, Tae Hoon, Kim, Hyun Sup, Kim, Se Ho, Kang, Woo Jong, and Seo, Chong Kwan}
abstractNote = {The study concerns the development of analysis models and computer codes for lower head failure analysis when a severe accident occurs in a nuclear reactor system. Although the lower head failure modes consists of several failure modes, the study this year was focused on the global rupture with the collapse pressure and mode by limit analysis and elastic deformation. The behavior of molten core causes elevation of temperature in the reactor vessel wall and deterioration of load-carrying capacity of a reactor vessel. The behavior of molten core and the heat transfer modes were, therefore, postulated in several types and the temperature distributions according to the assumed heat flux modes were calculated. The collapse pressure of a nuclear reactor lower head decreases rapidly with elevation of temperature as time passes. The calculation shows the safety of a nuclear reactor is enhanced with the lager collapse pressure when the hot spot is located far from the pole. 42 refs., 2 tabs., 31 figs. (author)}
place = {Korea, Republic of}
year = {1995}
month = {Aug}
}