Published 2011 | Version v1
Miscellaneous Metadata-only

An integral effect test program for the SMART design: VISTA-ITL

Creators

  • 1. Thermal Hydraulics Safety Research Division, Koreat Atomic Energy Research Institute - KAERI, 1045 Daedeok-daero, Yuseong-gu, Daejeon 305-353 (Korea, Republic of)

Description

A thermal-hydraulic integral effect test program for the SMART (System-integrated Modular Advanced Reactor) design has been introduced, it is called VISTA-ITL. The VISTA-ITL is a small-scale integral effect test facility for the SMART design and it has the following characteristics: 1/2.77-height, 1/1310-volume and full pressure and temperature simulation of the SMART design. The VISTA-ITL will be used extensively to assess the safety and performance of the SMART design and to validate various thermal-hydraulic analysis codes such as the MARS and TASS/SMR. As a typical scenario of SBLOCA (Small-Break Loss of Coolant Accident) the safety injection line break accident has been analyzed with the MARS-KS code, to assess a thermal-hydraulic similarity between the SMART design and the VISTA-ITL facility. The present similarity analysis ascertained the thermal-hydraulic similarity between the SMART design and the VISTA-ITL facility and provided a good insight into the unique features of the VISTA-ITL and the thermal-hydraulic characteristics of the SMART design as well. (authors)

Part of:
Proceedings of ICAPP 2011

Additional details

Identifiers

URL
http://www.iaea.org/INIS/contacts/;

Publishing Information

Imprint Title
Proceedings of ICAPP 2011
Imprint Pagination
2851 p.
Journal Page Range
p. 1828-1836
Report number
INIS-FR--13-0283

Conference

Title
The Power of Innovation
Acronym
ICAPP 2011 - Performance and Flexibility
Dates
2-5 May 2011
Place
Nice (France)

INIS

Country of Publication
France
Country of Input or Organization
France
INIS RN
44092996
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
LOSS OF COOLANT; REACTOR ACCIDENT SIMULATION; REACTOR SAFETY; REACTOR SAFETY EXPERIMENTS; SPECIFICATIONS; TESTING
Descriptors DEC
ACCIDENTS; REACTOR ACCIDENTS; SAFETY; SIMULATION

Optional Information

Notes
8 refs.; Available from the INIS Liaison Officer for France, see the 'INIS contacts' section of the INIS website for current contact and E-mail addresses: http://www.iaea.org/INIS/contacts/