Published April 2008 | Version v1
Miscellaneous

Experimental activities on a LBLOCA Reflood Phase in the ATLAS Facility

  • 1. Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

Description

KAERI recently constructed a new thermal-hydraulic integral test facility for advanced pressurized water reactors (PWRs) - ATLAS. The ATLAS facility has the following characteristics: 1/2-height and length, 1/288-volume, and a full pressure simulation of APR1400, maintaining a geometrical similarity with APR1400 including 2(hot legs) x 4(cold legs) reactor coolant loops, a direct vessel injection (DVI) for an emergency core cooling water, integrated annular downcomer, etc., incorporation of specific design characteristics of OPR1000 such as cold leg injection and low-pressure safety injection pumps, maximum 8% of a scaled nominal core power. The ATLAS will mainly be used to simulate various accident and transient scenarios for evolutionary PWRs, OPR1000 and APR1400: the simulation capability of broad scenarios including the reflood phase of a large-break loss-of-coolant accident (LOCA), small-break LOCA scenarios including DVI line breaks, a steam generator tube rupture, a main steam line break, a feed line break, a mid-loop operation, etc. The ATLAS was used to simulate the LBLOCA reflood phase of the APR1400 in 2007. Three kinds of the LBLOCA reflood tests were performed, e. g. parametric effect test for the LBLOCA late reflood phase, the LBLOCA reflood tests and a separate effect test(SET) for lower reflooding rate

Part of:
Proceedings of the 23rd KAIF/KNS Annual Conference

Additional details

Publishing Information

Publisher
KAIF-KNS
Imprint Place
Seoul (Korea, Republic of)
Imprint Title
Proceedings of the 23rd KAIF/KNS Annual Conference
Imprint Pagination
567 p.
Journal Page Range
p. 437-450

Conference

Title
23. KAIF/KNS Annual Conference
Dates
16-18 Apr 2008
Place
Seoul (Korea, Republic of)

INIS

Country of Publication
Korea, Republic of
Country of Input or Organization
Korea, Republic of
INIS RN
44066792
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference, Non-conventional Literature
Descriptors DEI
COMPUTERIZED SIMULATION; LOSS OF COOLANT; MAINTENANCE; PWR TYPE REACTORS; SAFETY INJECTION; STEAM LINES; TEST FACILITIES; THERMAL HYDRAULICS
Descriptors DEC
ACCIDENTS; ENRICHED URANIUM REACTORS; FLUID MECHANICS; HYDRAULICS; MECHANICS; PIPELINES; POWER REACTORS; REACTOR ACCIDENTS; REACTORS; SIMULATION; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS

Optional Information

Notes
Imprint:15 refs, 10 figs, 9 tabs