PCM Heat Transfer Experiment with PureTemp58X
Creators
- 1. Korea Advanced Institute of Science and Technology, Daejeon (Korea, Republic of)
Description
The Passive Containment Cooling Systems (PCCSs) were designed to be installed inside the containment and transfer the released heat to the water pool outside the containment. However, the PCCS of AP1000 cannot be applied to the Korean PWRs directly. The penetration adds the risk of radioactive material release by introducing another potential pass way. In order to simplify the PCCS design and eliminate the risk of radioactive material release, the KAIST research team proposed a new PCCS concept, a condenser using a phase change material (PCM) as shown in Fig. 1. The PCM acts as the final heat sink and absorbs the heat. The heat is transferred through the copper thermal conductor. As a simple system, this condenser does not need to penetrate the containment wall for installation. Thus, it has the potential applicability for operating PWRs and can work with other PCCSs to improve the cooling efficiency. The main target nuclear reactor is the APR1400 but it also can be applicable to many other designs. This study aims to see the heat transfer performance of a certain PCM with a given heat transfer structure. PCCS using PCM can be applied to existing nuclear power plants without containment penetration. The Steam to PCM Heat Transfer Experiment setup is planned to test the performance of the PCM in accident conditions. Various PCMs will be tested in different pressure and temperature conditions to secure database and find the optimum material or combination for future application.
Additional details
Identifiers
- URL
- https://www.kns.org;
Publishing Information
- Publisher
- KNS
- Imprint Place
- Daejeon (Korea, Republic of)
- Imprint Title
- Proceedings of the KNS 2018 Fall Meeting
- Imprint Pagination
- vp.
- Journal Page Range
- [3 p.]
Conference
- Title
- 2018 Fall Meeting of the KNS
- Dates
- 24-26 Oct 2018
- Place
- Yeosu (Korea, Republic of)
INIS
- Country of Publication
- Korea, Republic of
- Country of Input or Organization
- Korea, Republic of
- INIS RN
- 50060370
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- CONTAINMENT SYSTEMS; COOLING SYSTEMS; DESIGN; HEAT EXCHANGERS; HEAT TRANSFER; NUCLEAR POWER PLANTS; PWR TYPE REACTORS; RADIOACTIVE MATERIALS; THERMOSYPHONS; USES
- Descriptors DEC
- CONTAINMENT; ENERGY SYSTEMS; ENERGY TRANSFER; ENGINEERED SAFETY SYSTEMS; ENRICHED URANIUM REACTORS; MATERIALS; NUCLEAR FACILITIES; POWER PLANTS; POWER REACTORS; REACTORS; THERMAL POWER PLANTS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- 4 refs, 6 figs