RETRAN's improved small break modeling capability
- 1. Electric Power Research Inst., Inc., Palo Alto, CA (USA)
- 2. Energy, Inc., Idaho Falls, ID (USA)
Description
The RETRAN-02 computer code has been used extensively to analyze both operational transients and small break loss-of-coolant accidents (SBLOCA). While the results of these analyses are generally in good agreement with data, the explicit solution method sometimes requires small time-steps for portions of the small break calculations. The RETRAN-03 code, now under development, is incorporating additional models to extend the capability of RETRAN-02 and improve the code efficiency for SBLOCA's. Included in these models is a stable, implicit solution method which has provided a significant reduction in CPU requirements while maintaining satisfactory analyses results. The new models for RETRAN-03 and results of small break analyses using RETRAN-03 are briefly discussed in this paper. (orig.)
Additional details
Publishing Information
- Journal Title
- Nuclear Engineering and Design
- Journal Volume
- 102
- Journal Issue
- 2
- Series
- Nucl. Eng. Des.
- Journal Page Range
- 191-198
- ISSN
- 0029-5493
- CODEN
- NEDEA
INIS
- Country of Publication
- Netherlands
- Country of Input or Organization
- Netherlands
- INIS RN
- 20030246
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- BWR TYPE REACTORS; COMPUTER CALCULATIONS; LOSS OF COOLANT; R CODES; SIMULATION; THERMAL SHOCK; TIME DEPENDENCE; VERIFICATION
- Descriptors DEC
- ACCIDENTS; COMPUTER CODES; ENRICHED URANIUM REACTORS; POWER REACTORS; REACTOR ACCIDENTS; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS