So the impact of fuel assemblies burn-up on core fission neutron source parameters shall be considered in the neutron transportation calculation.
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。
For the neutron transportation calculation, accurate fission neutron source is the prerequisite and fundament ensuring that the calculation results are reliable.
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。
A numerical method of the statistics fluctuation problem of fission chains is studied for fission system driven by a weak neutron source.
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。
The numerical method of the statistics fluctuation problem of fission chain is studied for a fission system driven by a weak neutron source.
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。
The numerical method of the statistics fluctuation problem of fission chain is studied for a fission system driven by a weak neutron source.
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。
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