Thermal-Hydraulic Validation Tests for SMART Pre-Project Engineering
Creators
- 1. Korea Atomic Energy Research Institutde, Daejeon (Korea, Republic of)
Description
To satisfy the domestic and international needs for nuclear safety improvement after the Fukushima accident, a couple of passive safety systems (PSSs) of passive safety injection system (PSIS) and automatic depressurization system (ADS) were newly developed. The SMART also adopts a new PCCS (Passive Containment Cooling System) concept of CPRSS (Containment Pressure and Radioactivity Suppression System). In addition the thermal power of SMART increased from 330 to 365 MWt and some geometrical changes were given during the SMART PPE project. Therefore, there are strong needs both to understand the thermal-hydraulic phenomena expected to occur during the operation, transient and accident scenarios and to validate its performance for the SMART design. In this paper, the validation test activities will be summarized. They include integral effect tests of DBA (Design Basis Accident), SP (System Performance) and OP (Operation and Maintenance) using the SMART-ITL facility, which is an Integral Test Loop for the SMART design (SMART-ITL, or FESTA). Also the separate effect test facility of SISTA were commissioned to investigate the thermal-hydraulic phenomena in the SMART CPRSS (Containment Pressure and Radioactivity Suppression System). In this paper, the validation test activities for the SMART PPE are summarized. They include integral effect tests of DBA (Design Basis Accident), SP (System Performance) and OP (Operation and Maintenance) and performance tests of SG using the SMART-ITL facility.
Additional details
Publishing Information
- Publisher
- KNS
- Imprint Place
- Daejeon (Korea, Republic of)
- Imprint Title
- Proceedings of the KNS 2017 Fall Meeting
- Imprint Pagination
- [1 CD-ROM]
- Journal Page Range
- [3 p.]
Conference
- Title
- 2017 Fall Meeting of the KNS
- Dates
- 25-27 Oct 2017
- Place
- Kyungju (Korea, Republic of)
INIS
- Country of Publication
- Korea, Republic of
- Country of Input or Organization
- Korea, Republic of
- INIS RN
- 49079018
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- DEPRESSURIZATION; DESIGN; FEASIBILITY STUDIES; PWR TYPE REACTORS; RHR SYSTEMS; SAFETY ANALYSIS; THERMAL HYDRAULICS; VALIDATION
- Descriptors DEC
- COOLING SYSTEMS; ENERGY SYSTEMS; ENRICHED URANIUM REACTORS; FLUID MECHANICS; HYDRAULICS; MECHANICS; POWER REACTORS; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REACTORS; TESTING; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- 5 refs, 2 figs, 1 tabs