Neutron Overpower (NOP) system coverage during Bruce NGS A channel turn-around
Description
In the CANDU safety analysis process, a series of design basis accident are analyzed to confirm safety system effectiveness. Among all the postulated accidents, the Large Break Loss of Coolant (LBLOCA) sets the most demanding requirements on the speed and the reactivity depth of the shutdown reactivity devices. In such an accident, coolant discharge out of the fuel channels lead to a reactivity increase and power increase which is turned around by the shutdown systems action within seconds. In March 1993, the issue of fuel string relocation introducing additional positive reactivity for reactors fuelled against flow during a LBLOCA was identified. The combined reactivity effect could lead to power pulses much higher than would rise due to coolant voiding alone. To maintain adequate safety margins in the event of such postulated accident, the eight units of Bruce NGS A and B were derated to 60% full power
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30020416.pdf
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Additional details
Publishing Information
- Imprint Title
- CNS proceedings of the 1997 CNA/CNS annual conference on powering Canada's future. Vol. 1, 2
- Imprint Pagination
- [1122 p.]
- Journal Page Range
- v. 1 [2 p.]
- ISSN
- 0227-1907
- Report number
- INIS-CA--0070
Conference
- Title
- Powering Canada's future
- Dates
- 8-11 Jun 1997
- Place
- Toronto, Ontario (Canada)
INIS
- Country of Publication
- Canada
- Country of Input or Organization
- Canada
- INIS RN
- 30020416
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BRUCE SITE; DESIGN BASIS ACCIDENTS; FUEL CHANNELS; LOSS OF COOLANT; REACTOR SHUTDOWN; SAFETY ANALYSIS
- Descriptors DEC
- ACCIDENTS; REACTOR ACCIDENTS; REACTOR CHANNELS; REACTOR COMPONENTS; REACTOR SITES; SHUTDOWN
Optional Information
- Notes
- 1 ref.