Experimental study of pressure drops through LOCA-generated debris deposited on a fuel assembly
Creators
- 1. KHNP Central Research Institute, 1312-70 Yuseong-daero, Yuseong-gu, Daejeon 305-343 (Korea, Republic of)
- 2. Department of Nuclear Engineering, Seoul National University, Seoul 151-742 (Korea, Republic of)
Description
Highlights: • In-vessel downstream effect tests were performed in the presence of LOCA-generated debris. • Available driving heads under each LOCA scenario were verified using experimental data. • Fibrous debris was prepared to satisfy the length distribution obtained from the bypass test. • Limiting test conditions were identified through sensitivity studies. - Abstract: Under post loss-of-coolant accident (LOCA) conditions, it is postulated that debris can be generated and transported to the containment sump strainer. Some of the debris may pass through the strainer and could challenge the long-term core cooling capability of the plant. To address this safety issue, in-vessel downstream effect tests for the advanced power reactor (APR) 1400 were performed. Fibrous debris is the most crucial material in terms of causing pressure drops, and was prepared in this study to satisfy the fiber length distribution obtained through a strainer bypass test. Sensitivity studies on pressure drops through LOCA-generated debris deposited on a fuel assembly were performed to evaluate the effects of water chemistry and fiber length distribution. The pressure drops with debris laden pure water were substantially less than those with debris laden ordinary tap water. The experiment with fiber length distribution suggested by WCAP-16793 showed lower pressure drops than those with the APR1400 specific fiber length distribution. All the experimental results showed that the pressure drops in the mock-up fuel assembly were less than the available driving head at each LOCA scenario
Availability note (English)
Available from http://dx.doi.org/10.1016/j.nucengdes.2015.04.009Additional details
Identifiers
- DOI
- 10.1016/j.nucengdes.2015.04.009;
- PII
- S0029-5493(15)00134-X;
Publishing Information
- Journal Title
- Nuclear Engineering and Design
- Journal Volume
- 289
- Journal Page Range
- p. 49-59
- ISSN
- 0029-5493
- CODEN
- NEDEAU
INIS
- Country of Publication
- Netherlands
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 47016399
- Subject category
- S42: ENGINEERING; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- ALUMINIUM OXIDES; CONTAINERS; FIBERS; FUEL ASSEMBLIES; LENGTH; LOSS OF COOLANT; NOZZLES; PRESSURE DROP; PWR TYPE REACTORS; REACTOR ACCIDENT SIMULATION; REACTOR COOLING SYSTEMS; SAFETY INJECTION; SENSITIVITY ANALYSIS; SILICON CARBIDES; STEAM GENERATORS; THERMOCOUPLES; WATER CHEMISTRY
- Descriptors DEC
- ACCIDENTS; ALUMINIUM COMPOUNDS; BOILERS; CARBIDES; CARBON COMPOUNDS; CHALCOGENIDES; CHEMISTRY; COOLING SYSTEMS; DIMENSIONS; ENERGY SYSTEMS; ENRICHED URANIUM REACTORS; MEASURING INSTRUMENTS; OXIDES; OXYGEN COMPOUNDS; POWER REACTORS; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTORS; SILICON COMPOUNDS; SIMULATION; THERMAL REACTORS; VAPOR GENERATORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Copyright
- Copyright (c) 2015 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.