According to characteristics of TOPAZ-II reactor, a transient analytic method combined a nuclear reactor six-group point-kinetics model, a reactor core thermal-hydraulic model, a thermionic fuel element (TFE) performance model is established. Afterwards, establishment and debugging of this transient analytic code are completed. Verification results are reasonable agreement with reported American and Russian data. The code is original with the author.
Volume Subject Area:
Thermal Hydraulics
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