Current methods in qualification of CANDU heat transport pumps for operation under loss-of-coolant accident conditions
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
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).
INIS
- Country of Publication
- Canada
- Country of Input or Organization
- Canada
- INIS RN
- 22047618
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- CANDU TYPE REACTORS; LOSS OF COOLANT; PRIMARY COOLANT CIRCUITS; PUMPS; SAFETY ANALYSIS; TWO-PHASE FLOW
- Descriptors DEC
- ACCIDENTS; COOLING SYSTEMS; EQUIPMENT; FLUID FLOW; HEAVY WATER MODERATED REACTORS; POWER REACTORS; PRESSURE TUBE REACTORS; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REACTORS; THERMAL REACTORS