Estimation for side flow holes of an end-plug in a dual-cooled annular fuel
Creators
- 1. Korea Atomic Energy Research Inst., Daejeon (Korea, Republic of)
Description
A dual-cooled annular fuel for a PWR has been introduced for a significant increase in reactor power. KAERI has been developing a dual-cooled annular fuel for a power uprate of 20% in an optimized PWR in Korea, an OPR1000. Several thermal-hydraulic issues exist for the application of dual-cooled annular fuel. One of the key issues is the hypothetical event of inner channel blockage because the inner channel is an isolated flow channel without coolant mixing between the neighboring flow channels. A conceptual design used to complement the entrance blockage of an inner channel was suggested by KAERI. A long lower end plug for the annular fuel is invented to provide flow holes by perforating the side surface of the end plug body. Experiments and a numerical analysis were performed to investigate the bypass flow through the side holes of the lower end plug to complement the entrance blockage of an inner channel. In this study, An experiment with a single annular rod within a round tube is performed to measure the form loss coefficient of the side holes in the long lower end plug, and a numerical study was performed to estimate the parametric sensitivity of the geometric effect. (author)
Additional details
Identifiers
Publishing Information
- Imprint Title
- Proceedings of 8th Japan-Korea symposium on nuclear thermal hydraulics and safety (NTHAS8)
- Imprint Pagination
- 888 p.
- Journal Page Range
- 6 p.
Conference
- Title
- 8. Japan-Korea symposium on nuclear thermal hydraulics and safety
- Acronym
- NTHAS8
- Dates
- 9-12 Dec 2012
- Place
- Beppu, Oita (Japan)
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 46074212
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- ANNULAR FUEL ELEMENTS; BENCH-SCALE EXPERIMENTS; BYPASSES; C CODES; CLOSURES; DUALITY; FLOW BLOCKAGE; FLOW RATE; FLUID FLOW; HOLES; NUMERICAL ANALYSIS; PRESSURE DROP; PWR TYPE REACTORS
- Descriptors DEC
- COMPUTER CODES; ENRICHED URANIUM REACTORS; FUEL ELEMENTS; MATHEMATICS; POWER REACTORS; REACTOR COMPONENTS; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- 13 refs., 14 figs.