Author/Authors :
Williams، نويسنده , , M.M.R، نويسنده ,
Abstract :
A method has been developed for calculating the probability distribution of the
multiplication factor in a reactor in which the fuel elements are randomly distributed across
the core. The method is also applicable to waste storage drums in which lumps of fissile
waste material are stored in a background matrix. The procedure is based upon the
Feinberg-Galanin-Horning method of heterogeneous reactors, in which the fuel element or
fissile lump is replaced by a point, line or plane sink of thermal neutrons and a similar
source of fast neutrons. The fuel element positions are chosen to lie randomly in the core
and for each realisation a criticality calculation is carried out. Thus a large number of values
of keff is obtained and reduced to a probability distribution P(keff). We observe that keff lies
in the range kefJ,min, keff.max), where the very small value keff.min arises when all elements lie
on the reactor boundary, and the value of kefJ,max when all elements are fortuitously in the
position of minimum critical mass. A further simulation is carried out in which the fuel
elements are notionally at a fixed position in a regular lattice but are allowed to vary
randomly about the position by 10% of the lattice pitch. In this case, the distribution in keff
is found to be highly symmetrical about the critical value of keff = I and the distribution
appears to be Gaussian. The methods developed will also be useful for safety assessments
arising in the storage of fissile material and general problems in radioactive waste disposal.
An analytical method has been developed for calculating P(keff ) for N randomly distributed
plates and illustrated for the case of a reactor containing one plate. The agreement between
the simulation and the analytical method is excellent. It also seems likely that P(keff)
becomes Gaussian-like as the number of plates increases.