Published 2004 | Version v1
Miscellaneous Metadata-only

Comparison of the PLCS malfunction event analyses by using the CESEC III and MEDUSA codes

Creators

  • 1. Korea Power Engineering Company, Taejon (Korea, Republic of)

Description

The MEDUSA is a code developed by Korea Power Engineering Company (KOPEC) for non-LOCA and LOCA analysis, providing two-fluid, three-field representation of two-phase flow. In this paper, as an effort to verify the MEDUSA code, comparative simulation for Pressurizer Level Control System (PLCS) malfunction with loss of off-site power is performed for UCN 3 and 4 plants. The results by the MEDUSA are compared with those calculated by the CESEC-III, a licensing analysis code used for Korean Standard Nuclear Power Plant (KSNP)

Part of:
Proceedings of the KNS autumn meeting

Additional details

Publishing Information

Publisher
KNS
Imprint Place
Taejon (Korea, Republic of)
Imprint Title
Proceedings of the KNS autumn meeting
Imprint Pagination
1466 p.
Journal Page Range
p. 443-444

Conference

Title
2004 autumn meeting of the KNS
Dates
28-29 Oct 2004
Place
Yongpyong (Korea, Republic of)

INIS

Country of Publication
Korea, Republic of
Country of Input or Organization
Korea, Republic of
INIS RN
36102365
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference, Non-conventional Literature
Descriptors DEI
C CODES; COMPUTERIZED SIMULATION; LOSS OF COOLANT; M CODES; PRESSURIZERS; STEAM GENERATORS; TWO-PHASE FLOW; ULCHIN-3 REACTOR; ULCHIN-4 REACTOR
Descriptors DEC
ACCIDENTS; BOILERS; COMPUTER CODES; ENRICHED URANIUM REACTORS; FLUID FLOW; POWER REACTORS; PWR TYPE REACTORS; REACTOR ACCIDENTS; REACTORS; SIMULATION; THERMAL REACTORS; VAPOR GENERATORS; WATER COOLED REACTORS; WATER MODERATED REACTORS

Optional Information

Notes
2 refs, 3 figs