MATRIX EXPONENTIAL METHODS FOR PARALLEL COMPUTING OF ISOTOPIC DEPLETION AND SPECIES TRANSPORT FOR MOLTEN SALT REACTOR ANALYSIS

Matrix exponential methods have long been utilized for isotopic depletion in nuclear fuel calculations. In this paper we discuss the development of such addition to species transport liquid fueled molten salt reactors (MSRs). Conventional work with fixed assemblies which fission products and fissile material do not throughout core. Liquid a much different way, allowing primary reactor loop. Because this, product must be taken into account. The set partial differential equations that apply are discretized systems first order ordinary (ODEs). exact solution ODEs is herein being estimated using matrix method known as Chebychev Rational Approximation Method (CRAM).