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REACTOR FUEL NONDESTRUCTIVE BURNUP EVALUATION METHOD AND APPARATUS THEREFOR

机译:反应器燃料非破坏性燃耗评估方法及装置

摘要

PROBLEM TO BE SOLVED: To non-destructively evaluate burnup after the irradiation in a reactor of an atomic fuel containing plutonium before loading into the reactor.SOLUTION: Burnup BUis determined from a gamma-ray intensity C7 of cesium 137 (S12), an initial pultonium enrichment degree εis determined from a ratio (C4/C7) of gamma-ray intensities C4 and C7 of cesium 134 and Bu(S13), and a composition ratio fof fissile pultonium and a composition ratio Pof Pu 242 are determined from a ratio (Φ/C4) of neutron flux Φ and C4, BUand ε(S14). Then, a neutron effective multiplication factor (k) is determined (S16), and a neutron emission rate S is determined from an expression Φ=S×P/(1-k) (S17). By using a coefficient α and a coefficient β as functions of the initial pultonium enrichment degree ε, the composition ratio fof the initial fissile pultonium and the composition ratio Pof the initial Pu 242, burnup BUis determined from an expression S=α×BU(S18).
机译:解决的问题:无损评估反应堆中辐照的含containing原子燃料在辐照后的燃耗,然后再装入反应堆中。解决方案:燃耗BU由铯137的伽马射线强度C7(S12)确定富集度ε由铯134和Bu(S13)的γ射线强度C4和C7之比(C4 / C7)确定,裂变pu的组成比fpu和组成比Pof Pu 242由比值(中子通量Φ和C4,BU和ε(S14)。然后,确定中子有效倍增系数(k)(S16),并根据表达式Φ= S×P /(1-k)确定中子发射率S(S17)。通过使用系数α和系数β作为初始富集度ε,初始易裂变的组成比f和初始Pu 242的组成比P的函数,燃耗BU由表达式S =α×BU(S18 )。

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