Published October 2013 | Version v1
Miscellaneous

SBLOCA Analysis Using Modified MAAP4 Code through Semi-empirical CHF Correlation Application

  • 1. Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)
  • 2. Seoul National Univ., Seoul (Korea, Republic of)

Description

The molten core configuration and thermal load analyses for the determined accident sequences and break areas of a cold leg in APR1400 PSA were performed using the MAAP4 code. As the break size increased, the starting time at which the molten core was relocated to the lower head and the reactor vessel failure time decreased while the debris crust thickness increased for the accident sequences 17, 22, and 23 in the SBLOCA event tree. The angular heat flux generally increased as the break size was increased. However, if the decay heat and ratio of total upward-facing heat transfer to decay heat from the debris are simultaneously greater than those for the other cases, the thermal load of the metal layer could be greater regardless of the break sizes. Furthermore, the difference between the average temperature of the metal layer and the temperature of the internal reactor vessel is also one of the uncertainties for a sideward heat flux from metal layer. Therefore, the sideward-facing heat flux from the metal layer could depend on the ratio of total upward-facing heat transfer to the decay heat, as well as the temperature difference between the average temperatures of the metal layer and inner vessel wall temperature

Part of:
Proceedings of the KNS Fall meeting

Additional details

Publishing Information

Publisher
KNS
Imprint Place
Daejeon (Korea, Republic of)
Imprint Title
Proceedings of the KNS Fall meeting
Imprint Pagination
[1 CD-ROM]
Journal Page Range
[2 p.]

Conference

Title
2013 Fall meeting of the KNS
Dates
23-25 Oct 2013
Place
Kyungju (Korea, Republic of)

INIS

Country of Publication
Korea, Republic of
Country of Input or Organization
Korea, Republic of
INIS RN
45082397
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference, Non-conventional Literature
Descriptors DEI
AFTER-HEAT; CORRELATIONS; CRITICAL HEAT FLUX; LOSS OF COOLANT; M CODES; PRESSURE VESSELS; REACTOR VESSELS; USES
Descriptors DEC
ACCIDENTS; COMPUTER CODES; CONTAINERS; HEAT FLUX; REACTOR ACCIDENTS

Optional Information

Notes
8 refs, 5 figs