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The analysis of thermal-hydraulic models in MELCOR code

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Abstract

The objective of the present work is to verify the prediction and analysis capability of MELCOR code about the progression of severe accidents in light water reactor and also to evaluate appropriateness of thermal-hydraulic models used in MELCOR code. Comparing the results of experiment and calculation with MELCOR code is carried out to achieve the above objective. Specially, the comparison between the CORA-13 experiment and the MELCOR code calculation was performed.
Authors:
Kim, M H; Hur, C; Kim, D K; Cho, H J [1] 
  1. POhang Univ., of Science and TECHnology, Pohang (Korea, Republic of)
Publication Date:
Jul 15, 1996
Product Type:
Technical Report
Report Number:
KINS/HR-153
Resource Relation:
Other Information: 20 refs, 192 figs, 6 tabs
Subject:
22 GENERAL STUDIES OF NUCLEAR REACTORS; ACCIDENTS; COMPUTER CALCULATIONS; FORECASTING; INTERSTITIAL HYDROGEN GENERATION; M CODES; PWR TYPE REACTORS; SENSITIVITY; SIMULATION; THERMAL HYDRAULICS
OSTI ID:
20775520
Research Organizations:
Korea Institute of Nuclear Safety, Taejon (Korea, Republic of)
Country of Origin:
Korea, Republic of
Language:
Korean
Other Identifying Numbers:
TRN: KR0601464079125
Availability:
Available from INIS in electronic form; Also available from KINS
Submitting Site:
KRN
Size:
284 pages
Announcement Date:
Oct 16, 2006

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Citation Formats

Kim, M H, Hur, C, Kim, D K, and Cho, H J. The analysis of thermal-hydraulic models in MELCOR code. Korea, Republic of: N. p., 1996. Web.
Kim, M H, Hur, C, Kim, D K, & Cho, H J. The analysis of thermal-hydraulic models in MELCOR code. Korea, Republic of.
Kim, M H, Hur, C, Kim, D K, and Cho, H J. 1996. "The analysis of thermal-hydraulic models in MELCOR code." Korea, Republic of.
@misc{etde_20775520,
title = {The analysis of thermal-hydraulic models in MELCOR code}
 author = {Kim, M H, Hur, C, Kim, D K, and Cho, H J}
 abstractNote = {The objective of the present work is to verify the prediction and analysis capability of MELCOR code about the progression of severe accidents in light water reactor and also to evaluate appropriateness of thermal-hydraulic models used in MELCOR code. Comparing the results of experiment and calculation with MELCOR code is carried out to achieve the above objective. Specially, the comparison between the CORA-13 experiment and the MELCOR code calculation was performed.}
 place = {Korea, Republic of}
 year = {1996}
 month = {Jul}
 }