Application of code systems to fast reactor calculations

Application of code systems to fast reactor calculations 

The traditional way to calculate the physical characteristics of a fast reactor is to carry out the following steps (1) preparation of the effective cross sections for regions of the reactor (2) a three-dimensional calculation to obtain k-eff, and real and adjoint fluxes (3) edit the results of the previous steps to estimate the power and reaction rate distributions, neutron kinetics parameters, control rod effectiveness, etc., and (4) a bumup analysis, calculating the variation of the isotopic composition with time, and then recalculating the results obtained in the previous steps for particular bumup states. This scheme has been implemented, for example, in the TRIGEX code [4.49]. This code calculates k-eff, few group real and adjoint fluxes, power spatial distribution, dose factor and reaction rates distributions, breeding parameters, bumup effects, and kinetics parameters (effective delayed neutron Auction, etc.). 

Monte Carlo calculations on a unified cross section data base, so as to have an opportunity to work with different codes in a unified way, several modular code schemes have been developed. 

The development of computer technology has made it possible to create more powerful visualisation systems for input/output data, and new computer architectures can have an influence on the development of algorithms. The efficiency of calculations can be improved if special computers are used with  

An example of a fast reactor calculation, made for a reactor with a sodium plenum above the core instead of a breeding blanket, is the international intercomparison Sodium Void Benchmark, [4.20]. The list of cross section data sets and reactor codes, used in the benchmark calculations is given in Table 4.2 (taken from [4.20]). 

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