Method for obtaining sensitivity coefficients of effective multiplication factor to section under different burnups
A technology of fuel consumption and cross-section, which is applied in the measurement of nuclear data and the safety and economic fields of nuclear reactors. It can solve the problems that the sensitivity coefficient cannot be calculated accurately and effectively, and achieve the effect of high-efficiency sensitivity coefficient
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[0114] The method of the present invention will be described in detail below in conjunction with the accompanying drawings and specific embodiments.
[0115] Such as figure 1 As shown, a method of obtaining the sensitivity coefficient of the effective multiplication factor to the cross-section under different burnups in the present invention comprises the following steps:
[0116] Step 1: Carry out forward burnup calculation, and calculate the effective self-screening cross-section, middle angular flux density, neutron conjugate angular flux density and nucleon density of each nuclide at each burnup point, as figure 2 As shown, the forward fuel consumption calculation specifically includes the following contents:
[0117] 1) Read the multi-group micro-section and burnup chain information of each nuclide. The multi-group micro-section adopts the 69-group energy group structure of WIMSD, and the burnup chain of each nuclide also adopts the burnup chain in the WIMSD burnup libr...
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