Determination of equilibrium fuel composition for fast reactor in closed fuel cycle

Abstract

Abstract. Technique of evaluation of multiplying and reactivity characteristics of fast reactor operating in the mode of multiple refueling is presented. We describe the calculation model of the vertical section of the reactor. Calculation validations of the possibility of correct application of methods and models are given. Results on the isotopic composition, mass feed, and changes in the reactivity of the reactor in closed fuel cycle are obtained. Recommendations for choosing perspective fuel compositions for further research are proposed.

Stellarator–mirror fusion–fission hybrid – a fast route to clean and safe nuclear energy

“…2012; Ternovykha et al. 2017; Moiseenko & Chernitskiy 2019). In cyclic reprocessing, after the burning sequence, fuel is unloaded from the reactor, fission products are removed, the corresponding amount of depleted uranium is added and finally new fuel is made from this mixture.…”

“…The project Integral Fast Reactor (Chang 1989) is of special interest, in particular because of its closing for safety reasons (see https://en.wikipedia.org/wiki/ Integral_fast_reactor). Some different approaches with multiple-recycle fuel cycles for fast reactors, which could provide radically higher aggregate combustion percentages, should be mentioned here (Orlov et al 2005;Moiseenko et al 2012;Ternovykha et al 2017;Moiseenko & Chernitskiy 2019). In cyclic reprocessing, after the burning sequence, fuel is unloaded from the reactor, fission products are removed, the corresponding amount of depleted uranium is added and finally new fuel is made from this mixture.…”

Modeling of Analytical-Experimental Benchmark on Irradiation of Nitride Fuel in BN-600 Reactor in the SCALE6 code

“…The purpose of this work is to conduct a detailed calculation analysis in the SCALE6 code [1] of the experiment with irradiated nitride fuel for verification of codes and libraries of constants used in the substantiation of projects of reactors with liquid-metal coolant with MNUP fuel. The possibility of using the SCALE6 code for the calculation of fast neutron reactors was analyzed in [2,3]. codes has been completed.…”