Avoidance of reactor trip on high PHT system pressure for 220 MWe Indian PHWRs with addition of pressuriser
- 1. Reactor Safety Div., Bhabha Atomic Research Centre, Mumbai (India)
- 2. Reactor Process Group, Nuclear Power Corporation of India Limited, Mumbai (India)
Description
Full text: As reported from 220 MWe PHWRs operating units, most of the plant outages are attributed to disturbances like single PCP trip, turbine trip etc., which result in tripping of reactor on high PHT system pressure. To avoid these unwanted plant outages the PHT pressure control system capacity needs to be enhanced or increase the PHT inventory in the form of pressuriser. To minimize the capital cost in D2O holdup no pressuriser is provided in the existing units of Indian PHWRs. Since in the primary side the coolant remains in incompressible liquid phase, a small rise in the PHT temperature (swell in the PHT volume) results in pressure surges of larger magnitude. To arrest this pressure rise without jeopardizing the safety limits, different mitigation schemes are being studied to increase the plant availability during such incidents. The various mitigation schemes are like full opening of bleed valves, enhanced cooling from the secondary side through CSDVs/ASDVs under certain conditions. In this respect, incorporation of a pressuriser is being analysed using an in house computer code developed for plant transient studies. Promising results have been obtained with the help of added pressurizer of 10-meter cube, which results in an increase in the net compressibility of the PHT system. The pressuriser rides over the PHT system in a passive manner and provides a steam cushion. This helps in mitigating sudden swell and the steam bleed valves help in taking care of sustained swells. The integrated code incorporates the mathematical models of the thermal hydraulics system of the primary and secondary heat transport systems along with associated control system modules. The fluid models are based on the unsteady state, one dimensional conservation equations of mass, momentum, energy and equation of state of fluid. In the present paper, parametric responses for different transients obtained with addition of the pressuriser will be compared with the responses obtained with the present existing configuration of the plant
Additional details
Publishing Information
- Publisher
- Bhabha Atomic Research Centre
- Imprint Place
- Mumbai (India)
- Imprint Title
- First national conference on nuclear reactor technology
- Imprint Pagination
- 421 p.
- Journal Page Range
- p. 345
Conference
- Title
- 1. nuclear reactor safety
- Acronym
- NRT-1
- Dates
- 25-27 Nov 2002
- Place
- Mumbai (India)
INIS
- Country of Publication
- India
- Country of Input or Organization
- India
- INIS RN
- 34011423
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- OUTAGES; PHWR TYPE REACTORS; PRESSURE DEPENDENCE; PRIMARY COOLANT CIRCUITS; REACTOR OPERATION; SCRAM; TRANSIENTS
- Descriptors DEC
- COOLING SYSTEMS; ENERGY SYSTEMS; HEAVY WATER COOLED REACTORS; HEAVY WATER MODERATED REACTORS; OPERATION; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REACTOR SHUTDOWN; REACTORS; SHUTDOWN