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Research on the improvement of nuclear safety -A study on the establishment of severe accident experimental facility-

Abstract

For the first phase (1992-1995) of the current research program under nuclear reactor safety enhancement project, the primary objective was placed on the development of an improved cavity design and on the improvement of theoretical models of the separate effects for major severe accident phenomena occurring in the reactor cavity. Also, during the fourth year of this project, small-scale experiments were performed to visualize the fundamental phenomena of boiling in narrow spaces that may exist between the debris crust and the reactor vessel lower head in preparation for the large-scale in-vessel cooling experiment planned for the second phase of the project (1996-2001). Separate effect tests have been performed during the first phase spanning the high pressure melt ejection (HPME) resulting in the direct containment heating (DCH), crust formation during cooling of the high temperature melt, fuel coolant interaction (FCI) in the process of injecting coolant onto the reactor cavity, and the molten core concrete interaction (MCCI). Some research programs were subcontracted with universities. Steam condensation on the containment inner wall was investigated by the POSTECH, while the experimental technique for the simultaneous measurement of particle size and velocity was developed by the KAIST. The second phase experimental projects center about  More>>
Publication Date:
Jul 01, 1995
Product Type:
Technical Report
Report Number:
KAERI/RR-1636/95
Reference Number:
SCA: 210200; PA: AIX-28:018913; EDB-97:025383; NTS-97:007452; SN: 97001736187
Resource Relation:
Other Information: PBD: Jul 1995
Subject:
21 NUCLEAR POWER REACTORS AND ASSOCIATED PLANTS; REACTOR ACCIDENTS; COMPUTER CODES; REACTOR CORES; CONCRETES; CONTAINMENT BUILDINGS; COOLANTS; CORIUM
OSTI ID:
429998
Research Organizations:
Korea Atomic Energy Research Inst., Daeduk (Korea, Republic of)
Country of Origin:
Korea, Republic of
Language:
Korean
Other Identifying Numbers:
Other: ON: DE97614508; TRN: KR9600243018913
Availability:
INIS; OSTI as DE97614508
Submitting Site:
KRN
Size:
415 p.
Announcement Date:
Feb 24, 1997

Citation Formats

Seo, Kune Yull, Ryu, Keon Joong, Park, Chang Kyu, Sim, Seok Ku, Kim, Sang Baek, Nho, Ki Mann, Bang, Kwang Hyun, Park, Rae Jun, Lee, Seong Jae, Kang, Kyung Ho, Jo, Young Ro, Hong, Sung Wan, Jeong, Moon Ki, Park, Chun Kyung, Cheon, Se Young, Kim, In Sik, Moon, Sang Ki, Kim, Jong Hwan, Kim, Seong Ho, Sin, Ki Yeol, and Cho, Jae Sun. Research on the improvement of nuclear safety -A study on the establishment of severe accident experimental facility-. Korea, Republic of: N. p., 1995. Web.
Seo, Kune Yull, Ryu, Keon Joong, Park, Chang Kyu, Sim, Seok Ku, Kim, Sang Baek, Nho, Ki Mann, Bang, Kwang Hyun, Park, Rae Jun, Lee, Seong Jae, Kang, Kyung Ho, Jo, Young Ro, Hong, Sung Wan, Jeong, Moon Ki, Park, Chun Kyung, Cheon, Se Young, Kim, In Sik, Moon, Sang Ki, Kim, Jong Hwan, Kim, Seong Ho, Sin, Ki Yeol, & Cho, Jae Sun. Research on the improvement of nuclear safety -A study on the establishment of severe accident experimental facility-. Korea, Republic of.
Seo, Kune Yull, Ryu, Keon Joong, Park, Chang Kyu, Sim, Seok Ku, Kim, Sang Baek, Nho, Ki Mann, Bang, Kwang Hyun, Park, Rae Jun, Lee, Seong Jae, Kang, Kyung Ho, Jo, Young Ro, Hong, Sung Wan, Jeong, Moon Ki, Park, Chun Kyung, Cheon, Se Young, Kim, In Sik, Moon, Sang Ki, Kim, Jong Hwan, Kim, Seong Ho, Sin, Ki Yeol, and Cho, Jae Sun. 1995. "Research on the improvement of nuclear safety -A study on the establishment of severe accident experimental facility-." Korea, Republic of.
@misc{etde_429998,
title = {Research on the improvement of nuclear safety -A study on the establishment of severe accident experimental facility-}
author = {Seo, Kune Yull, Ryu, Keon Joong, Park, Chang Kyu, Sim, Seok Ku, Kim, Sang Baek, Nho, Ki Mann, Bang, Kwang Hyun, Park, Rae Jun, Lee, Seong Jae, Kang, Kyung Ho, Jo, Young Ro, Hong, Sung Wan, Jeong, Moon Ki, Park, Chun Kyung, Cheon, Se Young, Kim, In Sik, Moon, Sang Ki, Kim, Jong Hwan, Kim, Seong Ho, Sin, Ki Yeol, and Cho, Jae Sun}
abstractNote = {For the first phase (1992-1995) of the current research program under nuclear reactor safety enhancement project, the primary objective was placed on the development of an improved cavity design and on the improvement of theoretical models of the separate effects for major severe accident phenomena occurring in the reactor cavity. Also, during the fourth year of this project, small-scale experiments were performed to visualize the fundamental phenomena of boiling in narrow spaces that may exist between the debris crust and the reactor vessel lower head in preparation for the large-scale in-vessel cooling experiment planned for the second phase of the project (1996-2001). Separate effect tests have been performed during the first phase spanning the high pressure melt ejection (HPME) resulting in the direct containment heating (DCH), crust formation during cooling of the high temperature melt, fuel coolant interaction (FCI) in the process of injecting coolant onto the reactor cavity, and the molten core concrete interaction (MCCI). Some research programs were subcontracted with universities. Steam condensation on the containment inner wall was investigated by the POSTECH, while the experimental technique for the simultaneous measurement of particle size and velocity was developed by the KAIST. The second phase experimental projects center about the in-vessel accident management tests SONATA-IV (Simulation of Naturally Arrested Thermal Attack in Vessel) and ex-vessel accident management tests TOCATA-XV (Tests on Cavity Arrested Thermal Attack ex Vessel). In preparation for the second phase in-vessel experimental program, one of our research staff has participated in the PHEBUS-FP program in CEA Cadarache, France. Small-scale scoping tests were performed for the study of in-vessel cooling of debris in the lower head. (Abstract Truncated)}
place = {Korea, Republic of}
year = {1995}
month = {Jul}
}