Code Validation of a SBLOCA test in SMART Integral Test Loop

Journal Article · Wed Jun 15 04:00:00 EDT 2016 · Transactions of the American Nuclear Society

OSTI ID:22992018

Jeon, Byong Guk; Bae, Hwang; Ryu, Sung-Uk; Kim, Yeon-Sik; Yi, Sung-Jae; Park, Hyun-Sik ^[1]; Cho, Yeon-Sik ^[2]

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1. Korea Atomic Energy Research Institute, Thermal Hydraulics Safety Research Division, 989-111 Daedeokdaero, Yuseong-gu, Daejeon (Korea, Republic of)
2. System Engineering and Technology Co., Venture Town 302, 105, Sinildong-ro, Daedeok-gu, Daejeon (Korea, Republic of)

Integrated small modular reactors (iSMRs) are favored because of their unique characteristics, such as enhanced safety without any large break loss of coolant accidents (LBLOCAs), low initial construction costs, and multi-use of desalination and electricity generation. Many iSMRs have been developed thus far. In Korea, an iSMR called SMART was developed after a thorough validation of the components and systems, and finally received its design certificate in 2012 for the first time in the world. To ensure the performance of its safety systems, an integral test loop, SMART-ITL, is constructed. It contains the primary system, secondary system, passive safety systems, and an auxiliary system. The passive safety systems include a passive residual heat removal system (PRHRS), passive injection system with a core makeup tank (CMT) and a safety injection tank (SIT), and an automatic depressurization system (ADS). The height is preserved while the diameter is scaled down to 1:7. A series of SBLOCA tests have been performed with 4 trains of PRHRS, 1 train of CMT and SIT, and ADS. In parallel with the experiments, simulation of a representative test has been conducted to track the underlying thermal hydraulics. SMART-ITL is an integral test loop for SMART and a series of SBLOCA tests for confirming the performance of passive safety systems have been conducted. In this paper, a system code simulation on a SBLOCA test using SMART-ITL is presented. The reactor vessel water level, break flow rate, and CMT and SIT water levels are predicted well. (authors)

• OSTI ID: 22992018
• Journal Information: Transactions of the American Nuclear Society, Journal Name: Transactions of the American Nuclear Society Journal Issue: 1 Vol. 114; ISSN 0003-018X
• Country of Publication: United States
• Language: English

Related Subjects

42 ENGINEERING
97 MATHEMATICS AND COMPUTING
AFTER-HEAT REMOVAL
AUXILIARY SYSTEMS
DEPRESSURIZATION SYSTEMS
DESALINATION
FLOW RATE
LBLOCA
PERFORMANCE
POWER GENERATION
REACTOR VESSELS
RHR SYSTEMS
SAFETY INJECTION
SBLOCA
SIMULATION
SMALL MODULAR REACTORS
TANKS
THERMAL HYDRAULICS