https://orcid.org/0000-0002-2167-7761
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Abstract
The thermal-hydraulic research supporting the development of an integral type of reactor named System-integrated Modular Advanced ReacTor (SMART) is discussed. First, the SMART development program is introduced. The Standard Design Approval (SDA) for SMART was certificated in 2012 based on extensive technical validation activities during 2009 to 2012, and a set of passive safety systems (PSSs) was designed and validated for SMART during 2013 to 2015 after the Fukushima Daiichi accident. During 2016 to 2018, the Kingdom of Saudi Arabia and Korea conducted a 3-year project of Pre-Project Engineering (PPE), and now, the Standard Design Approval (SDA) for SMART100 is being processed from 2019. Second, the SMART validation test program and related test facilities are introduced. A set of integral effect tests (IETs) was performed using VISTA-ITL, and several separate effect tests (SETs) using the facilities of SWAT, SCOP, and FTHEL were performed for SMART SDA. Counterpart tests for SMART SDA were performed with the newly constructed SMART-ITL facility, and various validation tests for SMART PSSs were also performed. In addition, dozens of validation tests for SMART PPE were performed to produce IET data for design-basis-accident scenarios and PSSs. Additional SETs for SMART PPE and SMART100 SDA were performed using the facilities of SISTA-1, SISTA-2, and FINCLS. Third, the major test results are discussed for phenomena expected to occur in an integral type of reactor such as the SMART design. They include core cooling behaviors in the reactor coolant system and safety injection behaviors in the passive safety injection system and counterpart test results of a small-break loss-of-coolant accident between VISTA-ITL and SMART-ITL. Fourth, the major analysis results for SMART are discussed. Several sets of code analysis were performed for selected IET cases with the MARS-KS and TASS/SMR-S codes to validate their models and the codes themselves. They include simulation of a SMART safety injection system line break test with the MARS-KS code, validation of the TASS/SMR-S code for natural circulation tests, and validation of the MARS-KS and TASS/SMR-S codes based on a pressurizer safety valve line break test.
Acronyms
| AC: | = | alternating current |
| ADS: | = | automatic depressurization system |
| ADV: | = | automatic depressurization valve |
| CHF: | = | critical heat flux |
| CLOF: | = | complete loss of RCS flow rate |
| CMT: | = | core makeup tank |
| CPRSS: | = | containment pressure and radioactivity suppression system |
| DBA: | = | design-basis accident |
| ECC: | = | emergency core coolant |
| ECCS: | = | emergency core cooling system |
| ECT: | = | emergency cooldown tank |
| ELSMOR: | = | European Licencing of Small MOdular Reactors |
| FINCLS: | = | Facility to Investigate Natural Circulation in SMART (a SET facility for NC in SMART) |
| FMHA: | = | flow mixing head assembly |
| FTHEL: | = | Freon Thermal Hydraulic Experimental Loop (a SET facility for Freon CHF test) |
| IET: | = | integral effect test |
| IPWR: | = | integral pressurized water reactor |
| IRWST: | = | in-containment refueling water storage tank |
| K.A.CARE: | = | King Abdullah City for Atomic and Renewable Energy |
| KAERI: | = | Korea Atomic Energy Research Institute |
| KHNP: | = | Korea Hydro & Nuclear Power Company |
| KINS: | = | Korea Institute of Nuclear Safety |
| KSA: | = | Kingdom of Saudi Arabia |
| LCA: | = | low containment area |
| LOOP: | = | loss of off-site power |
| MARS-KS: | = | Multi-dimensional Analysis of Reactor Safety–KINS Standard (a best-estimate, multidimensional, thermal-hydraulic code |
| MSLB: | = | main steam line break |
| MT: | = | makeup tank |
| NC: | = | natural circulation |
| NPP: | = | nuclear power plant |
| NSSC: | = | Nuclear Safety and Security Commission |
| OM: | = | operation and maintenance |
| OSU-MASLWR: | = | Oregon State University–Multi-Application Small Light Water Reactor (facility) |
| PAFS: | = | passive auxiliary feedwater system |
| PIRT: | = | Phenomena Identification and Ranking Table |
| PPE: | = | Pre-Project Engineering |
| PRHRS: | = | passive residual heat removal system |
| PSIS: | = | passive safety injection system |
| PSS: | = | passive safety system |
| PSV: | = | pressurizer safety valve |
| PZR: | = | pressurizer |
| RCP: | = | reactor coolant pump |
| RCS: | = | reactor coolant system |
| RPV: | = | reactor pressure vessel |
| RRT: | = | radioactive material removal tank |
| RV: | = | reactor vessel |
| RVA: | = | reactor vessel assembly |
| SBLOCA: | = | small break loss-of-coolant accident |
| SCOP: | = | SMART COre flow & Pressure test facility (a SET facility for flow and pressure distributions) |
| SDA: | = | Standard Design Approval |
| SET: | = | separate effect test |
| SG: | = | steam generator |
| SIS: | = | safety injection system |
| SISTA: | = | A SET facility for SMART CPRSS |
| SIT: | = | safety injection tank |
| SMART: | = | System-integrated Modular Advanced ReacTor |
| SMART-ITL: | = | SMART–Integral Test Loop (a large-scale IET Loop for SMART, FESTA) |
| SMR: | = | small modular reactor |
| SP: | = | system performance |
| SPNC: | = | single-phase natural circulation |
| SR: | = | safety related |
| SRDBE: | = | safety-related design-basis events |
| SWAT: | = | SMART ECC Water Asymmetric Two-phase choking test facility (a SET facility for ECC behavior in SMART) |
| TASS/SMR: | = | Transient And Setpoint Simulation/SMR (code) |
| TLOF: | = | total loss of reactor coolant flow |
| TPNC: | = | two-phase natural circulation |
| UCA: | = | upper containment area |
| UDC: | = | upper downcomer |
| VISTA: | = | Verification by Integral Simulation of Transients and Accidents |
| VISTA-ITL: | = | Verification by Integral Simulation of Transients and Accidents–Integral Test Loop (a small-scale integral test loop for SMART) |
Disclosure Statement
No potential conflict of interest was reported by the author(s).