Published October 2011 | Version v1
Miscellaneous

An Integral Effect Test of Complete Loss of RCS Flowrate for SMART with the VISTA-ITL

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

Description

A thermal-hydraulic integral effect test facility, VISTA-ITL, for the SMART design has been constructed by the Korea Atomic Energy Research Institute (KAERI). The VISTA-ITL is a revised version of an existing VISTA facility to have the simulation capability of small-break loss of coolant accident (SBLOCA), passive residual heat removal system (PRHRS) performance tests, and complete loss of RCS (Reactor Coolant System) flowrate (CLOF), etc. It is newly equipped with the steam pressurizer, the safety injection system, the steam generator bypass, the pump discharge line, the dowcomer, the PRHRS makeup tank, the break simulator and the break measuring system, etc. The VISTA-ITL is a 1/2.77-height, 1/1310-volume scaled test facility based on the design features of SMART. The reference scale ratios of length (1/2.77) and area (1/472.9) are based on the elevation difference between the core and steam generator centers and the core flow area, respectively. According to the scaling law, the reduced height scaling results in time-reducing results in the model as the time scale ratio is 1/1.664. A CLOF test was successfully performed by using the VISTA-ITL facility recently and its major results have been discussed

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
43045472
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference, Non-conventional Literature
Descriptors DEI
COMPUTERIZED SIMULATION; DESIGN; FLOW RATE; LOSS OF COOLANT; PWR TYPE REACTORS; TEST FACILITIES; THERMAL HYDRAULICS
Descriptors DEC
ACCIDENTS; ENRICHED URANIUM REACTORS; FLUID MECHANICS; HYDRAULICS; MECHANICS; POWER REACTORS; REACTOR ACCIDENTS; REACTORS; SIMULATION; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS

Optional Information

Notes
5 refs, 1 fig, 3 tabs