Published 1988 | Version v1
Miscellaneous

Current methods in qualification of CANDU heat transport pumps for operation under loss-of-coolant accident conditions

Creators

  • 1. Atomic Energy of Canada Ltd., Sheridan Park, ON (Canada). CANDU Operations

Description

The Heat Transport (HT) pumps in a CANDU reactor circulate heavy water coolant through the reactor core under all normal operating conditions. For a Loss-of-Coolant-Accident (LOCA) in the heat transport system, depressurization of the system occurs. It is desirable to establish that the HT pumps will continue to operate under two-phase flow conditions resulting from a LOCA for a short duration. Evaluating the operational behaviour of large centrifugal pumps under two-phase flow conditions is complex. Various techniques have been used with different degrees of reliability and associated costs. This paper presents the current methods used for evaluating the post-LOCA operational capability of CANDU HT pumps. Conclusions from the recent research studies suggest the possibility of using the LOCA test data generated by Ontario Hydro for qualification of future CANDU HT pumps. A methodology for such a cost-effective approach is also presented

Part of:
Proceedings of the Canadian Nuclear Society ninth annual conference, 1988

Additional details

Publishing Information

Imprint Title
Proceedings of the Canadian Nuclear Society ninth annual conference, 1988
Imprint Pagination
488 p.
Journal Page Range
p. 411-416.
Report number
INIS-mf--12827

Conference

Title
Canadian Nuclear Society 9. annual conference.
Dates
13-15 Jun 1988.
Place
Winnipeg, MB (Canada).

Optional Information