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采用一阶广义微扰理论,开发燃耗计算中核素的核子密度对反应截面的灵敏度分析程序。分析各核素的反应截面对244Cm在50 GW·d/t时核子密度的灵敏度系数,235U和239Pu的裂变截面和238U、240Pu、241Pu、242Pu以及243Am的俘获截面具有较大的灵敏度系数;243Am俘获截面的灵敏度系数在热中子区和共振区明显大于快中子区,因此243Am俘获截面精度的改善应该优先考虑热中子区和共振区。
A first-order generalized perturbation theory is used to develop a sensitivity analysis program for the nuclear cross section of the radionuclide in the fuel burn calculation. The sensitivity of 244Cm for nuclear density, the 235U and 239Pu fission cross sections and the 238U, 240Pu, 241Pu, 242Pu and 243Am capture cross sections for each of the nuclides were analyzed. The sensitivity coefficient was 243Am The sensitivity coefficient of the capture cross section is significantly greater in the neutron and resonance regions than in the neutron region, so improving the accuracy of the 243Am capture cross section should give priority to the thermal neutron region and the resonance region.