Abstract
The conservatism of the current safety analysis was assessed by comparing the predicted results with cylindrical core test facility (CCTF) test results performed at Japan Atomic Energy Research Institute (JAERI). The WREM code was selected for the assessment. The overall conservatism of the WREM code on the peak clad temperature prediction was confirmed against CCTF EM test which simulated the typical initial and boundary conditions in the safety evaluation analysis. The WREM code predicted the reasonable core boundary conditions and the conservatism of the code came mainly from the core calculation. The conservatism of the WREM code against CCTF data could be attributed to the following three points: 1. (i) no horizontal mixing assumption between subchannels at each elevation, 2. (ii) no modeling on heat transfer enhancement caused by the radial core power profile, 3. (iii) usage of conservative heat transfer correlations in the code.
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