Expected Value of Finite Fission Chain Lengths of Pulse Reactors
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Graphical Abstract
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Abstract
The average neutron population necessary for sponsoring a persistent fission chain in a multiplying system, is discussed. In the point reactor model, the probability function (n, t0, t) of a source neutron at time t0 leading to n neutrons at time t is dealt with. The nonlinear partial differential equation for the probability generating function G(z; t0, t) is derived. By solving the equation, we have obtained an approximate analytic solution for a slightly prompt supercritical system. For the pulse reactor GodivaⅡ, the mean value of finite fission chain lengths is estimated in this work and shows that the estimated value is reasonable for the experimental analysis.
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