THREE DIMENSIONAL NUCLEAR THERMAL-HYDRAULIC CHARACTERISTIC ANALYSIS OF JPDR CORE (in Japanese)
Nuclear thermal-hydraulic characteristics of JPDR core have been calculated by the three dimensional nuclear thermal-hydraulic code 'FLARE'. The calculation results with a set of nuclear constants adopted by us are consistent with the measurement results in the JPDR core. The FLARE model proves its accuracies. Many calculation results under the various reactor operation conditions are shown and it becomes clear that the design values of JPDR core, adopted by General Electric Co, have sufficient margin. Concrete and useful informations on flux distributions in the core are also reported as a function of the reactor power and rod patterns. In the appendix, the experimental investigation on the validity of the FLARE model from the general viewpoint are reported. Readers are referred also to the appendix for the input data used in this report.
- Research Organization:
- Japan Atomic Energy Research Inst., Tokai. Tokai Research Establishment (Japan)
- NSA Number:
- NSA-22-039777
- OSTI ID:
- 4493631
- Report Number(s):
- JAERI-1159
- Country of Publication:
- Japan
- Language:
- Japanese
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