Published October 2013 | Version v1
Miscellaneous

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

Part of:
Proceedings of the KNS Fall meeting

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