Role of pressuriser in enhancing pressure control system capability in primary system of 500 MWe PHWR
- 1. Nuclear Power Corporation, Bhabha Atomic Research Centre, Mumbai (India)
Description
The primary heat transport system of a pressurized heavy water reactor (PHWR) extracts and transports the heat produced in the fuel (located inside coolant channel assemblies) to the steam generators where steam is generated to run the turbo-generator. The heat transport medium (primary coolant) is heavy water which is kept in a pressurized liquid state with the help of a pressure control system. Feed and bleed circuits with associated equipment of PHT main system have traditionally constituted the pressure control system. However, for large size reactors of 500 MWe capacity, a surge tank known as pressurizer was incorporated due to the presence of relatively large inventory in PHT main circuit. The pressurizer acts as a cushion for pressure variations resulting from various transients. This significantly reduces the onerous demand on feed and bleed system, thereby reducing reactor outages on system pressure excursions. The paper describes in detail the pressure control system of 500 MWe PHWR involving pressuriser and feed and bleed system including their functions and instrumentation. The results of mathematical modelling/analysis undertaken to establish the response adequacy of pressure control system, to postulated plant transients vis-a-vis the role of pressurizer are presented. (author)
Additional details
Publishing Information
- Publisher
- Bhabha Atomic Research Centre.
- Imprint Place
- Mumbai (India)
- Imprint Title
- Advances in chemical engineering in nuclear and process industries
- Imprint Pagination
- 628 p.
- Journal Page Range
- p. 187-199.
Conference
- Title
- advances in chemical engineering in nuclear and process industries.
- Acronym
- ACE-94
- Dates
- 9-11 Jun 1994.
- Place
- Mumbai (India).
INIS
- Country of Publication
- India
- Country of Input or Organization
- India
- INIS RN
- 29018150
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- FLOWSHEETS; PARAMETRIC ANALYSIS; PHWR TYPE REACTORS; POWER RANGE 100-1000 MW; PRESSURE CONTROL; PRESSURE DEPENDENCE; PRESSURIZERS; PRIMARY COOLANT CIRCUITS; REACTOR CONTROL SYSTEMS; STEAM GENERATORS; TRANSIENTS
- Descriptors DEC
- BOILERS; CONTROL; CONTROL SYSTEMS; COOLING SYSTEMS; DIAGRAMS; HEAVY WATER COOLED REACTORS; HEAVY WATER MODERATED REACTORS; INFORMATION; MEGAWATT POWER RANGE; POWER RANGE; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REACTORS; VAPOR GENERATORS
Optional Information
- Notes
- 10 figs.