Published 2004 | Version v1
Miscellaneous Metadata-only

CEA withdrawal from low power accident analysis using RETRAN

Creators

  • 1. Korea Electric Power Research Institute, Taejon (Korea, Republic of)
  • 2. Atomie Creative Technology, Taejon (Korea, Republic of)

Description

Korea Electric Power Research Institute is developing the design basis accident safety analysis methodology for Korea Standard Nuclear Power Plants. In the methodology, RETRAN-3D is used to estimated the system analysis during transients and core thermal-hydraulic sub-channel analysis codes, CETOP/TORC, are used to evaluate corresponding departure from nuclear boiling ratio (DNBR). In this study, the CEA(Control Element Assembly) withdrawal from low power accident of Ulchin Units 3 and 4 is analyzed to confirm the feasibility of the methodology and the results are compared with those of FSAR Ch.15

Part of:
Proceedings of the KNS spring meeting

Additional details

Publishing Information

Publisher
KNS
Imprint Place
Taejon (Korea, Republic of)
Imprint Title
Proceedings of the KNS spring meeting
Imprint Pagination
[CD-ROM]
Journal Page Range
[9 p.]

Conference

Title
2004 spring meeting of the KNS
Dates
27-28 May 2004
Place
Gyeongju (Korea, Republic of)

INIS

Country of Publication
Korea, Republic of
Country of Input or Organization
Korea, Republic of
INIS RN
35100429
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference, Non-conventional Literature
Descriptors DEI
C CODES; CONTROL ELEMENTS; DESIGN; FEASIBILITY STUDIES; HYDRAULICS; SAFETY ANALYSIS; THERMAL ANALYSIS; TRANSIENTS; ULCHIN-3 REACTOR; ULCHIN-4 REACTOR
Descriptors DEC
COMPUTER CODES; ENRICHED URANIUM REACTORS; FLUID MECHANICS; MECHANICS; POWER REACTORS; PWR TYPE REACTORS; REACTOR COMPONENTS; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS

Optional Information

Notes
6 refs, 8 figs, 2 tabs