Role of system characteristics in evolution of pump hydraulic design
- 1. Nuclear Power Corporation of India Ltd., Bombay (India). 500 MWe PHWR Group
Description
Primary heat transport (PHT) main circuit provides the means for transferring the heat produced in the fuel by circulating heavy water in the main circuit loop by primary coolant pumps (PCPs). The procurement specification of PCPs for 500 MWe pressurised heavy water reactor (PHWR) was prepared based upon the first order hydraulic analysis of the primary heat transport system and accordingly duty point was fixed. With this specification the manufacturer carried out model testing to arrive at optimum size of the impeller followed by determination of pump characteristics curves using full scale impeller during type testing. The duty point thus obtained was higher than specified necessitating the trimming of impeller. However, in order to make use of available higher duty point from system considerations, the duty point was redefined for production of subsequent pumps within specified tolerances governed by manufacturing limitations. PHT main system sizing (piping and feeders) was carried out based upon pump (delivering maximum flow) characteristics curve. Pressure profiles of PHT system at various operating modes were drawn and corresponding power drawn by motor was calculated. The interfacing of reactor coolant main system with hydraulic characteristics of PCP plays a significant role in establishing the requisite capability and capacity of PHT system in performing its intended functions. Therefore the paper traces the evolution of design parameters for PCP and subsequent generation of pressure profiles commensurate with the changes made in power profile including their impact on feeder sizing. The paper also highlights the scope of interaction between process designer and pump manufacturer in formulating a mutually acceptable and efficient hydraulic performance for PCP. (author). 3 refs., 8 figs., 3 tabs
Additional details
Publishing Information
- Publisher
- Bhabha Atomic Research Centre.
- Imprint Place
- Bombay (India)
- Imprint Title
- Pumping equipment in nuclear industry and thermal power plants: Proceedings of national symposium
- Imprint Pagination
- [265 p.].
- Journal Page Range
- p. II.2-1-II.2-9.
Conference
- Title
- national symposium on pumping equipment in nuclear industry and thermal power plants.
- Acronym
- NSPE-94
- Dates
- 24-25 Feb 1994.
- Place
- Bombay (India).
INIS
- Country of Publication
- India
- Country of Input or Organization
- India
- INIS RN
- 26041650
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S42: ENGINEERING;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- DESIGN; HEAT TRANSFER; HYDRAULICS; OPERATION; PHWR TYPE REACTORS; PRIMARY COOLANT CIRCUITS; PUMPS; SPECIFICATIONS; TESTING
- Descriptors DEC
- COOLING SYSTEMS; ENERGY TRANSFER; EQUIPMENT; HEAVY WATER COOLED REACTORS; HEAVY WATER MODERATED REACTORS; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REACTORS