In order to carry out power transient tests for PWR fuel element in China Advanced research Reactor (carr), the research and conceptual design of 3he pressure control loop were completed.
为使中国先进研究堆(CARR)具备开展压水堆燃料瞬态试验的能力，本工作对氦- 3回路进行研究与初步设计。
Calculating water radionuclide content in a loop under normal operating conditions, as well as that in a loop corresponding to the damage rate of equivalent fuel element.
计算正常工况下一回路水核素含量，以及与当量燃料元件破损率相对应的一回路水核素含量。
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