Published October 2011 | Version v1
Miscellaneous

A SBLOCA Test of Shutdown Cooling System for SMART with the VISTA-ITL

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

Description

The VISTA-ITL for a thermal-hydraulic integral effect test is a modified version of an existing VISTA facility to have the simulation capability of Small-Break Loss Of Coolant Accident (SBLOCA) for the System integrated Modular Advanced ReacTor (SMART) design. The VISTA-ITL has been designed following the three level scaling methodology of Ishii and Kataoka which consists of integral scaling, boundary flow scaling, and local phenomena scaling. The VISTA-ITL is a 1/2.77- height, 1/1310-volume scaled test facility based on the design features of SMART. The major components of reactor pressure vessel, steam generator, PRHRS and secondary system are preserved, but some changes are given to the simulate the SBLOCA behavior of the SMART design: the steam pressurizer, the safety injection system, the steam generator bypass, the hot leg, the cold leg, the PRHRS makeup tank, the break simulator and the break measuring system were revised. In order to perform the safety analysis and performance analysis of a SMART, SBLOCA test of the Shutdown Cooling System (SCS) line break was performed by the Korea Atomic Energy Research Institute (KAERI) using the Experimental Verification of by Integral Simulation of Transients and Accidents (VISTA) Integral Test Loop (ITL). In this paper, test results of the SCS line-break have been summarized with major parameter and experimental results obtained from the SBLOCA test

Part of:
Proceedings of Korean Nuclear Society, Daejeon (KR)

Additional details

Publishing Information

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

Conference

Title
2011 autumn meeting of the KNS
Dates
26-28 Oct 2011
Place
Kyoungju (Korea, Republic of)

INIS

Country of Publication
Korea, Republic of
Country of Input or Organization
Korea, Republic of
INIS RN
43045505
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference, Non-conventional Literature
Descriptors DEI
COMPUTERIZED SIMULATION; COOLING SYSTEMS; DESIGN; LOSS OF COOLANT; PWR TYPE REACTORS; SAFETY INJECTION; SHUTDOWN; THERMAL HYDRAULICS; VERIFICATION
Descriptors DEC
ACCIDENTS; ENERGY SYSTEMS; ENRICHED URANIUM REACTORS; FLUID MECHANICS; HYDRAULICS; MECHANICS; POWER REACTORS; REACTOR ACCIDENTS; REACTORS; SIMULATION; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS

Optional Information

Notes
2 refs, 1 fig, 3 tabs