Best estimate analysis of Monticello plant transients using DYNODE-B
Creators
- 1. Northern States Power Co., Minneapolis, MN (USA)
- 2. Utility Associates International, Inc., Rockville, MD (USA)
Description
The DYNODE-B code has been used to simulate operational transients which have occurred at the Monticello Nuclear Generation Plant in Monticello, Minnesota. For the case of a complete isolation of all main steam lines during full power operation, DYNODE-B has been used to help identify the cause of an unexpected response in system pressure which delayed the opening of the safety/relief valves until much later than had previously been expected. It is shown that the DYNODE-B model of a BWR system can be used to realistically model the response of such a system to transient conditions. The use of DYNODE-B to support plant operations by analyzing unexpected system responses and evaluating their possible causes is also demonstrated. These calculations provide documentation in support of the use of DYNODE-B for best- estimate analysis
Additional details
Publishing Information
- Publisher
- American Nuclear Society.
- Imprint Place
- La Grange Park, IL (USA)
- ISBN
- 0-89448-136-3
- Imprint Title
- Anticipated and abnormal transients in nuclear power plants
- Imprint Pagination
- vp.
- Journal Page Range
- p. VII-34-VII-39.
Conference
- Title
- Topical meeting on anticipated and abnormal transients in nuclear power plants.
- Dates
- 12-15 Apr 1987.
- Place
- Atlanta, GA (USA).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 22077570
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S99: GENERAL AND MISCELLANEOUS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BWR TYPE REACTORS; D CODES; FEEDWATER; MODIFICATIONS; MONTICELLO REACTOR; PUMPS; REACTOR OPERATION; SIMULATION; TRANSIENTS
- Descriptors DEC
- COMPUTER CODES; ENRICHED URANIUM REACTORS; EQUIPMENT; HYDROGEN COMPOUNDS; OPERATION; OXYGEN COMPOUNDS; POWER REACTORS; REACTORS; THERMAL REACTORS; WATER; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Secondary number(s)
- CONF-870418--.