Results of CP and L analysis of Brunswick unit 1 startup tests using RETRAN
Description
RETRAN models for the two-unit BWR/4 Brunswick Steam Electric Power Plant have been under development by Carolina Power and Light Company (CP and L) since 1981 with the ultimate objective of obtaining Nuclear Regulatory Commission (NRC) approval to perform reload cycle transient licensing analyses. While attainment of this goal remains several years in the future, these models have been useful in the evaluation of operational occurrences and in the conduct of design reviews of vendor analyses. Qualification of the Brunswick Unit 1 model against five initial cycle startup tests has been completed. These test include a turbine trip, a single feed pump trip, a level setpoint change, and single and double recirculation pump trips. A description of the interface code PETRA and the methods used to generate and collapse the PRESTO three-dimensional neutronics parameters for use with one-dimensional RETRAN models is presented. This is followed by comparisons of calculated and measured values of key parameters for each of the five initial startup tests used to qualify the Brunswick Unit 1 RETRAN model
Additional details
Publishing Information
- Imprint Title
- Proceedings: Fifth International RETRAN conference
- Journal Page Range
- p. 13.1-13.16.
- Report number
- EPRI-NP--5781-SR
Conference
- Title
- 5. international RETRAN meeting.
- Dates
- 9-11 Nov 1987.
- Place
- Boston, MA (USA).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 20030197
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- BWR TYPE REACTORS; COMPUTERIZED SIMULATION; HEAT TRANSFER; HYDRAULICS; LOSS OF COOLANT; P CODES; R CODES; REACTOR ACCIDENTS; REACTOR SAFETY; SYSTEMS ANALYSIS; TEMPERATURE GRADIENTS; THERMODYNAMICS; TRANSIENTS
- Descriptors DEC
- ACCIDENTS; COMPUTER CODES; ENERGY TRANSFER; ENRICHED URANIUM REACTORS; POWER REACTORS; REACTORS; SAFETY; SIMULATION; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS