Springer Online Journal Archives 1860-2000
Energy, Environment Protection, Nuclear Power Engineering
Abstract The paper describes the method of calculating fuel burn-up in nuclear reactors, taking into account the capture and multiplication of neutrons while slowing down. In the calculations, account is taken of the burn-up of U235 and the build-up and burn-up of Np239, Pu239, Pu240, Pu241 and of the fission fragments.
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