在中子输运计算中，准确的裂变中子源是保证计算结果可靠性的前提和基础。

For the neutron transportation calculation, accurate fission neutron source is the prerequisite and fundament ensuring that the calculation results are reliable.

youdao

因此，在中子输运计算中，必须考虑组件燃耗对堆芯的裂变中子源参数的影响。

So the impact of fuel assemblies burn-up on core fission neutron source parameters shall be considered in the neutron transportation calculation.

youdao

本文讨论了在混合堆和快堆的多群中子输运计算中，考虑共振自屏效应的重要性及其考虑方法。

This paper discussed the importance as well as the method of considering the resonance self-shielding effect in hybrid blanket and fast reactor neutron multigroup calculations.

youdao