Published 2005 | Version v1
Miscellaneous

Development of LOCA Response Strategy during Shutdown Operation in Kori 3 and 4 and Ygn 1 and 2 Units

  • 1. Korea Electric Power Research Institute, Daejeon (Korea, Republic of)

Description

The abnormal transients and accidents during shutdown operation modes of pressurized water reactor, in contrast with those during full power operation modes, have been recently issued due to their potential risk for leading to a severe abnormal condition because the various safety-related systems and equipments may be unavailable. The NRC issued Loss of Reactor Coolant Inventory and Potential Loss of Emergency Mitigation Functions While in a Shutdown Condition, on January 12, 1995, to alert addressees to an incident at the Wolf Creek plant involving the loss of reactor coolant inventory while the reactor was in a hot shutdown condition. Considering those situations, abnormal response mitigation strategies in shutdown operation modes have been developed by evaluating the plant specific thermal hydraulic behavior following LOCA. The objectives of this study are: (1) to verify the effectiveness of abnormal operating procedure (AOP) and emergency core cooling system (ECCS) on reactor safety at shutdown operation, developing the operation strategy at the condition and abnormal operation guideline in the light water reactors; (2) to enhance understanding of the thermal-hydraulic phenomena during abnormal and accident conditions. In this paper, some accident scenarios are analyzed to develop the abnormal operating strategy following LOCA in shutdown operation modes for Kori 3 and 4 and Ygn 1and 2 units. This study shows the adequacy of operator action time to mitigate the LOCA, the thermal hydraulic behavior, reactor inventory distribution and possibility of cold overpressurization after SBLOCA during shutdown operation modes using computer code RELAP5 /MOD3.2

Part of:
Proceedings of the KNS spring meeting

Additional details

Publishing Information

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

Conference

Title
2005 spring meeting of the KNS
Dates
26-27 May 2005
Place
Jeju (Korea, Republic of)

INIS

Country of Publication
Korea, Republic of
Country of Input or Organization
Korea, Republic of
INIS RN
37041952
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference, Non-conventional Literature
Descriptors DEI
KORI-3 REACTOR; LOSS OF COOLANT; R CODES; REACTOR OPERATION; REACTOR SAFETY; REACTOR SHUTDOWN; THERMAL HYDRAULICS; TRANSIENTS; YONGGWANG-1 REACTOR
Descriptors DEC
ACCIDENTS; COMPUTER CODES; ENRICHED URANIUM REACTORS; FLUID MECHANICS; HYDRAULICS; MECHANICS; OPERATION; POWER REACTORS; PWR TYPE REACTORS; REACTOR ACCIDENTS; REACTORS; SAFETY; SHUTDOWN; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS

Optional Information

Notes
6 refs