Applicability of Two-fluid Model in Predicting Onset of Flow Instability in a Narrow Rectangular Cooling Channel under Low Pressure
Creators
- 1. Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)
Description
Plate-type fuel assemblies have been widely used in the research reactors to enhance power density. This type fuel assembly consists of a number of fuel plates, supporting plates, cooling channels between the fuel plates, common inlet and outlet plenums. The cooling channels are completely isolated from each other so that the cross flow between the channels does not occur. Hence, if onset of flow instability (OFI) takes place in any one of cooling channels during the flow blockage accident in a plate-type fuel assembly, it can develop CHF and cause OFI in an adjacent cooling channel. This phenomenon is called flow instability propagation, one of the greatest concerns in safety analysis of research reactors. Therefore, it is necessary to precisely assess the two-phase flow instability in a narrow rectangular cooling channel and its propagation caused by the flow blockage in order to improve the safety of a research reactor. In the present work, CFD analysis was performed to assess the capability of the CFD code in predicting OFI in a narrow rectangular cooling channel under low pressure. It is found that the CFD code with the models implemented in this study can predict the tendency of two-phase pressure drop that the pressure drop increases after the initiation of OFI although the mass flow rate decreases. These results show that it is possible to predict OFI under low pressure in a narrow rectangular channel using a commercial CFD code with the models implemented in this study.
Additional details
Publishing Information
- Publisher
- KNS
- Imprint Place
- Daejeon (Korea, Republic of)
- Imprint Title
- Proceedings of the KNS 2017 Spring Meeting
- Imprint Pagination
- [1 CD-ROM]
- Journal Page Range
- [3 p.]
Conference
- Title
- 2017 Spring Meeting of the KNS
- Dates
- 17-19 May 2017
- Place
- Jeju (Korea, Republic of)
INIS
- Country of Publication
- Korea, Republic of
- Country of Input or Organization
- Korea, Republic of
- INIS RN
- 49050385
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- C CODES; COOLING; CRITICAL HEAT FLUX; FLOW RATE; FORECASTING; FUEL ASSEMBLIES; PRESSURE DROP; RESEARCH REACTORS; USES
- Descriptors DEC
- COMPUTER CODES; HEAT FLUX; REACTORS; RESEARCH AND TEST REACTORS
Optional Information
- Notes
- 4 refs, 6 figs, 3 tabs