Preliminary Design of KALIMER-600 PDRC Performance Test Facility
Creators
- 1. Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)
Description
The PDRC (Passive Decay Heat Removal Circuit) is the only safety-grade decay heat removal system in KALIMER-600. The core decay heat after a reactor trip is removed by natural circulation of the PDRC loop and the reactor vessel inside. The PDRC comprises of two independent loops, and each loop is equipped with a DHX (sodium-sodium Decay Heat eXchanger), an AHX (sodium-Air Heat eXchanger), and the pipes connecting the DHX and the AHX. For a verification of the passive decay heat removal concept and an assessment of the system performance, the PDRC performance test was planned for. In the test, the natural circulation cool-down capability after a reactor trip will be investigated for the conservative accident condition such as a station blackout. This paper briefly introduces the preliminary design parameters of the major components which were produced as a first step to assess the appropriateness of the test facility
Additional details
Publishing Information
- Publisher
- KNS
- Imprint Place
- Daejeon (Korea, Republic of)
- Imprint Title
- Proceedings of the KNS autumn meeting
- Imprint Pagination
- [1 CD-ROM]
- Journal Page Range
- [2 p.]
Conference
- Title
- 2008 autumn meeting of the KNS
- Dates
- 30-31 Oct 2008
- Place
- Pyongchang (Korea, Republic of)
INIS
- Country of Publication
- Korea, Republic of
- Country of Input or Organization
- Korea, Republic of
- INIS RN
- 40066523
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- AFTER-HEAT REMOVAL; DESIGN; LIQUID METAL COOLED REACTORS; NATURAL CONVECTION; PERFORMANCE; REACTOR VESSELS; TEST FACILITIES
- Descriptors DEC
- CONTAINERS; CONVECTION; ENERGY TRANSFER; HEAT TRANSFER; MASS TRANSFER; REACTORS; REMOVAL
Optional Information
- Notes
- 2 refs, 2 figs, 2 tabs