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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研究了弱中子源驱动下，裂变系统中子裂变链统计涨落问题的数值计算方法。

A numerical method of the statistics fluctuation problem of fission chains is studied for fission system driven by a weak neutron source.

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