Sensitivity Study of Fiber Length Effect on Pressure Drops in the Mockup PLUS7 Fuel Assembly
- 1. KHNP Central Research Institute, Daejeon (Korea, Republic of)
Description
There has been a concern that following a loss-of-coolant accident (LOCA), particulates, fibrous material and chemical precipitate could be ingested into the emergency core cooling system (ECCS) and flow into the reactor coolant system (RCS). This phenomenon could be harmful for a long term core cooling (LTCC) when the debris accumulates on the core inlets and blocks the flow of cooling water. The in-vessel downstream effect tests for the APR1400 have been performed to address this generic safety issue (GSI) 191. In this study, we performed sensitivity tests using a fiber grinder for 10 seconds and 8 seconds. When the fiber is gridded for shorter time, the fiber length is increased. In this study, sensitivity study of fiber length effect on pressure drops has been performed using a mockup PLUS7 FA. Particulate-to-fiber mass ratio of 1:1 was chosen, because the condition caused most limiting results. The fiber gridded for 8 seconds was used, and the result showed higher differential pressure than the condition of 10 seconds gridded. Because, both cases meet the fiber length distribution in the test protocol developed by the PWROG, the tests should be run using the fiber grinded for 8 seconds which gives more limiting results. However, all the test results meet the acceptance head loss (91.8 kPa) of the APR1400 with a sufficient margin
Additional details
Publishing Information
- Publisher
- KNS
- Imprint Place
- Daejeon (Korea, Republic of)
- Imprint Title
- Proceedings of the KNS Fall meeting
- Imprint Pagination
- [1 CD-ROM]
- Journal Page Range
- [2 p.]
Conference
- Title
- 2013 Fall meeting of the KNS
- Dates
- 23-25 Oct 2013
- Place
- Kyungju (Korea, Republic of)
INIS
- Country of Publication
- Korea, Republic of
- Country of Input or Organization
- Korea, Republic of
- INIS RN
- 45082354
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- FUEL ASSEMBLIES; LOSS OF COOLANT; MOCKUP; PRESSURE DROP; PWR TYPE REACTORS; SAFETY; SENSITIVITY ANALYSIS
- Descriptors DEC
- ACCIDENTS; ENRICHED URANIUM REACTORS; POWER REACTORS; REACTOR ACCIDENTS; REACTORS; STRUCTURAL MODELS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- 4 refs, 5 figs, 2 tabs