Comparison of three small-break loss-of-coolant accident tests with different break locations using the system-integrated modular advanced reactor-integral test loop facility to estimate the safety of the smart design
- 1. Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)
- 2. Dept. of Precision Mechanical Engineering, Kyungpook National University, Sangju (Korea, Republic of)
Description
Three small-break loss-of-coolant accident (SBLOCA) tests with safety injection pumps were carried out using the integral-effect test loop for SMART (System-integrated Modular Advanced ReacTor), i.e., the SMART-ITL facility. The types of break are a safety injection system line break, shutdown cooling system line break, and pressurizer safety valve line break. The thermal–hydraulic phenomena show a traditional behavior to decrease the temperature and pressure whereas the local phenomena are slightly different during the early stage of the transient after a break simulation. A safety injection using a high-pressure pump effectively cools down and recovers the inventory of a reactor coolant system. The global trends show reproducible results for an SBLOCA scenario with three different break locations. It was confirmed that the safety injection system is robustly safe enough to protect from a core uncovery
Additional details
Publishing Information
- Journal Title
- Nuclear Engineering and Technology
- Journal Volume
- 49
- Journal Issue
- 5
- Series
- 23 refs, 11 figs, 4 tabs
- Journal Page Range
- p. 968-978
- ISSN
- 1738-5733
INIS
- Country of Publication
- Korea, Republic of
- Country of Input or Organization
- Korea, Republic of
- INIS RN
- 48082176
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- COMPUTERIZED SIMULATION; COOLING SYSTEMS; DESIGN; EFFICIENCY; LOSS OF COOLANT; PUMPS; REACTOR SHUTDOWN; RELIEF VALVES; SAFETY; SAFETY INJECTION; THERMAL HYDRAULICS
- Descriptors DEC
- ACCIDENTS; CONTROL EQUIPMENT; ENERGY SYSTEMS; EQUIPMENT; FLOW REGULATORS; FLUID MECHANICS; HYDRAULICS; MECHANICS; REACTOR ACCIDENTS; REACTOR LIFE CYCLE; SHUTDOWN; SIMULATION; VALVES