Published May 2015 | Version v1
Miscellaneous

Evaluation for the Impact of Debris Settling on the In-vessel Downstream Effect Tests of the APR1400 Design

  • 1. KHNP Central Research Institute, Daejeon (Korea, Republic of)

Description

Four tests were run to evaluate hot-leg break conditions with a four safety injection (SI) flow rate varying particle to fiber (P/F) ratios of 0.5, 1, 2, and 10. Seven tests were run to evaluate cold-leg (CL) break conditions with a core boil-off rate at 700 seconds after a LOCA with varying P/F ratios of 1, 10, 20, 30, 40, 50, and 60. The phenomenon of debris settling was observed at the inlet of test column when simulating cold-leg beak. In this paper, the applicability of the test results was evaluated by providing pressure drops through debris bed in which condition debris settling did not occur under the same P/F mass ratio. The impact of debris settling on the validity of testing that has been conducted to address in-vessel downstream effects of the APR1400 was evaluated in this study. The test results that have been conducted with some debris settling are valid with a margin of approximately 52.3% under the cold-leg break condition

Part of:
Proceedings of the KNS 2015 Spring Meeting

Additional details

Publishing Information

Publisher
KNS
Imprint Place
Daejeon (Korea, Republic of)
Imprint Title
Proceedings of the KNS 2015 spring meeting
Imprint Pagination
[1 CD-ROM]
Journal Page Range
[2 p.]

Conference

Title
2015 spring meeting of the KNS
Dates
6-8 May 2015
Place
Jeju (Korea, Republic of)

INIS

Country of Publication
Korea, Republic of
Country of Input or Organization
Korea, Republic of
INIS RN
47023319
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference, Non-conventional Literature
Descriptors DEI
DESIGN; FISSION PRODUCTS; LOSS OF COOLANT; PWR TYPE REACTORS; SAFETY INJECTION; VALIDATION
Descriptors DEC
ACCIDENTS; ENRICHED URANIUM REACTORS; ISOTOPES; MATERIALS; POWER REACTORS; RADIOACTIVE MATERIALS; REACTOR ACCIDENTS; REACTORS; TESTING; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS

Optional Information

Notes
3 refs, 5 figs, 1 tab