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MODELING OF THE PU-238 PRODUCTION PROCESS IN A VVER-440 REACTOR USING DIFFERENT STARTING MATERIALS AND THEIR ARRANGEMENT STRUCTURES

237Np, 238Pu, irradiation device, lattice pitch, Serpent2, ppm (parts per million), radioisotope thermoelectric generators (RTGs), VVER-440 reactor.

Authors

The paper investigates the feasibility of producing high-purity Pu-238 in a VVER-440 thermal reactor by irradiating the actinide Neptunium-237 (Np-237) from spent nuclear fuel. The study uses Serpent2 Monte Carlo simulations to model neutron interactions and optimize key configurations, including lattice height and moderation environment. The goal is to produce approximately 3 kilograms of high-purity plutonium annually, with an isotopic specification of no less than 80% 238Pu and not exceeding 2 ppm of 236Pu