Published October 2008 | Version v1
Miscellaneous

ECC Bypass in the ATLAS Separate Effect Test for a Low Reflooding Rate

  • 1. Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

Description

KAERI (Korea Atomic Energy Research Institute) has recently started the operation of the ATLAS (Advanced Thermal-Hydraulic Test Loop for Accident Simulation), which is a thermal-hydraulic integral effect test facility for evolutionary pressurized water reactors. As the first phase of the ATLAS program, a series of large break loss of coolant accident (LBLOCA) reflood tests have been performed to resolve the safety issues related with thermal-hydraulic phenomena during the LBLOCA late reflood period in the APR1400. After completion of the integral LBLOCA reflood tests, separate effect test named as LB-CL-15 was performed to help validate the RELAP5 reflood models for a core quench phenomenon under a low flow rate ECC injection condition. A separate effect test data peculiar to the APR1400 could be obtained, which has the DVI injection, reverse heat transfer from steam generators and steam binding effect, etc. In this paper, among the typical thermal-hydraulic phenomena during the LBLOCA reflood period, the emergency core cooling (ECC) bypass is focused and a fraction of the direct ECC bypass in the LB-CL-15 test is evaluated

Part of:
Proceedings of the KNS autumn meeting

Additional details

Publishing Information

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

Conference

Title
2008 autumn meeting of the KNS
Dates
30-31 Oct 2008
Place
Pyongchang (Korea, Republic of)

INIS

Country of Publication
Korea, Republic of
Country of Input or Organization
Korea, Republic of
INIS RN
40066721
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference, Non-conventional Literature
Descriptors DEI
BYPASSES; COMPUTERIZED SIMULATION; FLOW RATE; HEAT TRANSFER; LOSS OF COOLANT; PWR TYPE REACTORS; STEAM GENERATORS; THERMAL HYDRAULICS
Descriptors DEC
ACCIDENTS; BOILERS; ENERGY TRANSFER; ENRICHED URANIUM REACTORS; FLUID MECHANICS; HYDRAULICS; MECHANICS; POWER REACTORS; REACTOR ACCIDENTS; REACTORS; SIMULATION; THERMAL REACTORS; VAPOR GENERATORS; WATER COOLED REACTORS; WATER MODERATED REACTORS

Optional Information

Notes
4 refs, 3 figs