【摘 要】
：
通常在用 Nordheim-Fuchs 模型计算铀氢锆堆芯脉冲参数时,必须考虑燃料热容随温度的线性关系,但采用一平均瞬发温度系数值.本文将瞬发温度系数与燃料温度的关系用一多项式表
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通常在用 Nordheim-Fuchs 模型计算铀氢锆堆芯脉冲参数时,必须考虑燃料热容随温度的线性关系,但采用一平均瞬发温度系数值.本文将瞬发温度系数与燃料温度的关系用一多项式表示,数值结果表明,这种处理改善了计算精度.
In general, when using the Nordheim-Fuchs model to calculate the uranium-zirconium-zirconium core pulse parameters, the linear relationship of the heat capacity of the fuel with the temperature must be considered, but an average instantaneous temperature coefficient value is used. The relationship between the instantaneous temperature coefficient and the fuel temperature A polynomial indicates that the numerical results show that this processing improves the calculation accuracy.
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