本文采用相空间有限元方法求解了柱形临界多群中子输运问题。

The phase-space finite element method is applied to the multigroup neutron transport equation in cylindrical critical systems.

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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.

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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.

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