Fault-tolerant digital feedwater control in nuclear power plants
Description
Nuclear plants, such as PWRs and CANDU-PHWRs (Pressurized Heavy-Water Reactors) have experienced both controllability and reliability problems with analog controls for steam generator level. This has been a major operability problem on the KANUPP PHWR, and is the limiting factor in the maneuverability of the Pickering A 4 x 540 MW PHWR units in Canada. In the United States, the Nuclear Regulatory Commission (NRC) and the Institute for Nuclear Plant Operation (INPO) have focussed their attention on feedwater control because the operability problems during startup and low power operation on most PWRs have caused a large number of scrams. Prompted by the INPO and NRC interest and by the good operating experience CANDU-PHWRs with Digital Feedwater Control Systems (DFCS), EPRI launched a pair of demonstration DFCS projects for U.S. LWRs; one BWR - Monticello and one for a PWR - Sequoyah. Since then a number of U.S. plants have initiated programs to retrofit digital feedwater control. This paper addresses the identified issues of importance to LWR utilities looking to retrofit a DFCS. Examples of approaches in design are drawn from the dFCS for Philadelphia Electric Co.'s Peach Bottom Atomic Power State and from CANDU-PHWRs such as Pt. Lepreau, both designed by AECL
Additional details
Publishing Information
- Publisher
- University of Tennessee at Knoxville.
- Imprint Place
- Knoxville, TN (United States)
- Imprint Title
- Proceedings of the 7th power plant dynamics, control and testing symposium
- Imprint Pagination
- vp.
- Journal Page Range
- p. 73.01-73.21.
Conference
- Title
- 7. power plant dynamics, control and testing symposium.
- Dates
- 15-17 May 1989.
- Place
- Knoxville, TN (United States).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 23036607
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- COMPUTERIZED CONTROL SYSTEMS; CONTROL EQUIPMENT; DIGITAL SYSTEMS; EPRI; FEEDWATER; NUCLEAR POWER PLANTS; OPTIMIZATION; PHWR TYPE REACTORS; PWR TYPE REACTORS; REACTOR COOLING SYSTEMS; REACTOR OPERATION; RELIABILITY; STEAM GENERATORS; US NRC
- Descriptors DEC
- BOILERS; CONTROL SYSTEMS; COOLING SYSTEMS; ENRICHED URANIUM REACTORS; EQUIPMENT; HEAVY WATER COOLED REACTORS; HEAVY WATER MODERATED REACTORS; HYDROGEN COMPOUNDS; NATIONAL ORGANIZATIONS; NUCLEAR FACILITIES; ON-LINE CONTROL SYSTEMS; ON-LINE SYSTEMS; OPERATION; OXYGEN COMPOUNDS; POWER PLANTS; POWER REACTORS; REACTOR COMPONENTS; REACTORS; THERMAL POWER PLANTS; THERMAL REACTORS; US ORGANIZATIONS; VAPOR GENERATORS; WATER; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Secondary number(s)
- CONF-890555--.