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

Author:

Park Hyun-Sik1,Min Byung-Yeon1,Jung Youn-Gyu1,Shin Yong-Cheol1,Ko Yung-Joo1,Yi Sung-Jae1

Affiliation:

1. Thermal Hydraulics Safety Research Division, Korea Atomic Energy Research Institute, 989-111 Daedeokdaero, Yuseong, Daejeon 305-353, Republic of Korea

Abstract

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.

Funder

National Research Foundation of Korea

Publisher

Hindawi Limited

Subject

Nuclear Energy and Engineering

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2. References;Handbook on Thermal Hydraulics in Water-Cooled Nuclear Reactors;2024

3. References;Handbook on Thermal Hydraulics in Water-Cooled Nuclear Reactors;2024

4. Thermal-Hydraulic Research Supporting the Development of SMART;Nuclear Technology;2023-07-17

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