Performance validation of advanced safety features of APR+ - 15264
Creators
- 1. Korea Atomic Energy Research Institute, Daejeon, Korea Daedeok-daero 989-111, Yuseong-Gu, Daejeon 305-353 (Korea, Republic of)
Description
This paper briefly introduces performance validation tests of advanced safety features of the Advanced Power Reactor plus (APR+). The main improvement on the safety systems of the APR+ are the advanced Direct Vessel Injection Plus (DVI+), Control Element Driving Mechanism (CEDM), and Passive Auxiliary Feedwater System (PAFS). The DVI+ test was performed using the 1/5-scale air-water test facility, full scale duct vibration test facility, and full scale ECC injection test facility. The CEDM test was performed using the full scale single CEDM test facility. The scram test, air cooling test, endurance test, etc. were performed for a design and performance validation of the CEDM of the APR+. The PAFS separate effect test was performed using a single full scale heat exchange tube to measure the steam condensation rate and temperature distribution. The ATLAS-PAFS integral effect test was also performed to validate the system cooling performance of the PAFS. The following design verification tests were also performed: -1) full scale 3-fuel assembly cross flow test to quantify the axial and cross flowrates in the core, -2) 1/5- scale core and reactor flow distribution test, and -3) 1/5-scale core simulator test to develop and calibrate core simulators. Through these tests, the performance of the advanced safety features of the APR+ was validated. (authors)
Additional details
Publishing Information
- Publisher
- Societe Francaise d'Energie Nucleaire - SFEN
- Imprint Place
- Paris (France)
- Imprint Title
- ICAPP 2015 Proceedings
- Imprint Pagination
- 3390 p.
- Journal Page Range
- p. 2274-2278
Conference
- Title
- Nuclear Innovations for a low-carbon future
- Acronym
- ICAPP 2015
- Dates
- 3-6 May 2015
- Place
- Nice (France)
INIS
- Country of Publication
- France
- Country of Input or Organization
- France
- INIS RN
- 49005023
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- CONTROL ROD DRIVES; PERFORMANCE TESTING; PWR TYPE REACTORS; REACTOR PROTECTION SYSTEMS; REACTOR SAFETY; SAFETY INJECTION
- Descriptors DEC
- ENGINEERED SAFETY SYSTEMS; ENRICHED URANIUM REACTORS; POWER REACTORS; REACTOR COMPONENTS; REACTORS; SAFETY; TESTING; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- 14 refs.; This record replaces 48095418