Design of the VISTA-ITL Test Facility for an Integral Type Reactor of SMART and a Post-Test Simulation of a SBLOCA Test

To validate the performance and safety of an integral type reactor of SMART, a thermal-hydraulic integral effect test facility, VISTA-ITL, is introduced with a discussion of its scientific design characteristics. The VISTA-ITL was used extensively to assess the safety and performance of the SMART de...

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Main Authors: Hyun-Sik Park, Byung-Yeon Min, Youn-Gyu Jung, Yong-Cheol Shin, Yung-Joo Ko, Sung-Jae Yi
Format: Article
Language:English
Published: Wiley 2014-01-01
Series:Science and Technology of Nuclear Installations
Online Access:http://dx.doi.org/10.1155/2014/840109
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author Hyun-Sik Park
Byung-Yeon Min
Youn-Gyu Jung
Yong-Cheol Shin
Yung-Joo Ko
Sung-Jae Yi
author_facet Hyun-Sik Park
Byung-Yeon Min
Youn-Gyu Jung
Yong-Cheol Shin
Yung-Joo Ko
Sung-Jae Yi
author_sort Hyun-Sik Park
collection DOAJ
description To validate the performance and safety of an integral type reactor of SMART, a thermal-hydraulic integral effect test facility, VISTA-ITL, is introduced with a discussion of its scientific design characteristics. The VISTA-ITL was used extensively to assess the safety and performance of the SMART design, especially for its passive safety system such as a passive residual heat removal system, and to validate various thermal-hydraulic analysis codes. The VISTA-ITL program includes several tests on the SBLOCA, CLOF, and PRHRS performances to support a verification of the SMART design and contribute to the SMART design licensing by providing proper test data for validating the system analysis codes. A typical scenario of SBLOCA was analyzed using the MARS-KS code to assess the thermal-hydraulic similarity between the SMART design and the VISTA-ITL facility, and a posttest simulation on a SBLOCA test for the shutdown cooling system line break has been performed with the MARS-KS code to assess its simulation capability for the SBLOCA scenario of the SMART design. The SBLOCA scenario in the SMART design was well reproduced using the VISTA-ITL facility, and the measured thermal-hydraulic data were properly simulated with the MARS-KS code.
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institution Kabale University
issn 1687-6075
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language English
publishDate 2014-01-01
publisher Wiley
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series Science and Technology of Nuclear Installations
spelling doaj-art-deba0368bbbb46da977dff4b82e89d752025-02-03T01:07:29ZengWileyScience and Technology of Nuclear Installations1687-60751687-60832014-01-01201410.1155/2014/840109840109Design of the VISTA-ITL Test Facility for an Integral Type Reactor of SMART and a Post-Test Simulation of a SBLOCA TestHyun-Sik Park0Byung-Yeon Min1Youn-Gyu Jung2Yong-Cheol Shin3Yung-Joo Ko4Sung-Jae Yi5Thermal Hydraulics Safety Research Division, Korea Atomic Energy Research Institute, 989-111 Daedeokdaero, Yuseong, Daejeon 305-353, Republic of KoreaThermal Hydraulics Safety Research Division, Korea Atomic Energy Research Institute, 989-111 Daedeokdaero, Yuseong, Daejeon 305-353, Republic of KoreaThermal Hydraulics Safety Research Division, Korea Atomic Energy Research Institute, 989-111 Daedeokdaero, Yuseong, Daejeon 305-353, Republic of KoreaThermal Hydraulics Safety Research Division, Korea Atomic Energy Research Institute, 989-111 Daedeokdaero, Yuseong, Daejeon 305-353, Republic of KoreaThermal Hydraulics Safety Research Division, Korea Atomic Energy Research Institute, 989-111 Daedeokdaero, Yuseong, Daejeon 305-353, Republic of KoreaThermal Hydraulics Safety Research Division, Korea Atomic Energy Research Institute, 989-111 Daedeokdaero, Yuseong, Daejeon 305-353, Republic of KoreaTo validate the performance and safety of an integral type reactor of SMART, a thermal-hydraulic integral effect test facility, VISTA-ITL, is introduced with a discussion of its scientific design characteristics. The VISTA-ITL was used extensively to assess the safety and performance of the SMART design, especially for its passive safety system such as a passive residual heat removal system, and to validate various thermal-hydraulic analysis codes. The VISTA-ITL program includes several tests on the SBLOCA, CLOF, and PRHRS performances to support a verification of the SMART design and contribute to the SMART design licensing by providing proper test data for validating the system analysis codes. A typical scenario of SBLOCA was analyzed using the MARS-KS code to assess the thermal-hydraulic similarity between the SMART design and the VISTA-ITL facility, and a posttest simulation on a SBLOCA test for the shutdown cooling system line break has been performed with the MARS-KS code to assess its simulation capability for the SBLOCA scenario of the SMART design. The SBLOCA scenario in the SMART design was well reproduced using the VISTA-ITL facility, and the measured thermal-hydraulic data were properly simulated with the MARS-KS code.http://dx.doi.org/10.1155/2014/840109
spellingShingle Hyun-Sik Park
Byung-Yeon Min
Youn-Gyu Jung
Yong-Cheol Shin
Yung-Joo Ko
Sung-Jae Yi
Design of the VISTA-ITL Test Facility for an Integral Type Reactor of SMART and a Post-Test Simulation of a SBLOCA Test
Science and Technology of Nuclear Installations
title Design of the VISTA-ITL Test Facility for an Integral Type Reactor of SMART and a Post-Test Simulation of a SBLOCA Test
title_full Design of the VISTA-ITL Test Facility for an Integral Type Reactor of SMART and a Post-Test Simulation of a SBLOCA Test
title_fullStr Design of the VISTA-ITL Test Facility for an Integral Type Reactor of SMART and a Post-Test Simulation of a SBLOCA Test
title_full_unstemmed Design of the VISTA-ITL Test Facility for an Integral Type Reactor of SMART and a Post-Test Simulation of a SBLOCA Test
title_short Design of the VISTA-ITL Test Facility for an Integral Type Reactor of SMART and a Post-Test Simulation of a SBLOCA Test
title_sort design of the vista itl test facility for an integral type reactor of smart and a post test simulation of a sbloca test
url http://dx.doi.org/10.1155/2014/840109
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