RETRAN-02 comparison of natural circulation flow rates at Babcock and Wilcox 177-FA plants
Description
A very important aspect of nuclear steam supply system (NSSS) model development is the process of comparing the computer model results against actual plant responses. Good comparisons will qualify the computer model for specific engineering analyses. Flow rates and decay heat power levels were obtained from planned and unplanned natural circulation events that occurred at Arkansas Nuclear One, Crystal River, Davis-Besse, and Oconee nuclear power plants. A oneloop RETRAN model of the Oconee NSSS is used to attain a spectrum of steady-state equilibrium conditions at different power levels of 25, 50, 75, and 100 MW. The benchmark comparisons are respectable. The comparisons also illustrate the ability of the Babcock and Wilcox raised-loop plant to induce a greater natural circulation flow rate
Additional details
Publishing Information
- Journal Title
- Nucl. Technol.
- Journal Volume
- 70
- Journal Issue
- 1
- Series
- Nucl. Technol.
- Journal Page Range
- 120-123
- ISSN
- 0029-5450
- CODEN
- NUTYB
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 17069553
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- ARKANSAS-1 REACTOR; COMPARATIVE EVALUATIONS; COMPUTERIZED SIMULATION; CRYSTAL RIVER-3 REACTOR; CRYSTAL RIVER-4 REACTOR; DAVIS BESSE-1 REACTOR; DAVIS BESSE-2 REACTOR; DAVIS BESSE-3 REACTOR; FLOW RATE; HEAT TRANSFER; HYDRAULICS; LOSS OF FLOW; OCONEE-1 REACTOR; OCONEE-2 REACTOR; OCONEE-3 REACTOR; PRIMARY COOLANT CIRCUITS; PWR TYPE REACTORS; R CODES; REACTOR SAFETY
- Descriptors DEC
- ACCIDENTS; COMPUTER CODES; COOLING SYSTEMS; ENERGY TRANSFER; ENRICHED URANIUM REACTORS; EVALUATION; POWER REACTORS; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REACTORS; SAFETY; SIMULATION; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS