Published October 2013 | Version v1
Miscellaneous

Analysis on the Direct Vessel Injection Line Break Accident at APR+ Standard Design

  • 1. TUEV Rheinland Korea Ltd., Seoul (Korea, Republic of)
  • 2. Korea Institute of Nuclear Safety, Daejeon (Korea, Republic of)

Description

APR+ (Advanced Power Reactor +) is the newest design variation of APR1400. The main characteristics of APR+, compared with APR1400, are passive safety systems and dedicated systems for severe accident mitigation. APR+ is under review for standard design certification. In this study, thermal hydraulic analysis on the Direct Vessel Injection (DVI) line break accident postulated in APR+ design was performed. Comparisons of the major parameters which can represent the overall accident behavior during DVI line break accident, several discrepancies between this study and reference data were found and such discrepancies include actuation timing of SIPs and SITs, and also include parameter behaviors of break flow rate and PCT at the accident initiation. These differences were mainly from the different thermal hydraulic models in simulation codes. The behavioral differences for break flow as well as peak cladding temperatures will be examined further as a next step for this study

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
45082376
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference, Non-conventional Literature
Descriptors DEI
COMPUTERIZED SIMULATION; DESIGN; FLOW RATE; PWR TYPE REACTORS; REACTOR ACCIDENTS; THERMAL HYDRAULICS
Descriptors DEC
ACCIDENTS; ENRICHED URANIUM REACTORS; FLUID MECHANICS; HYDRAULICS; MECHANICS; POWER REACTORS; REACTORS; SIMULATION; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS

Optional Information

Notes
1 ref, 5 figs, 1 tab