Abstract

As an excellent material for candidate coolant of the molten salt reactor, the activation of 2LiF-BeF2 is an important issue and should be concerned. In this paper, the activation of 2LiF-BeF2 has been analyzed based on a specific Molten Salt Reactor. And combined approaches, Monte Carlo method for neutron transport and extension of the Euler for inventory calculation, have been adopted. The short life nuclides for shielding design, the long-life nuclides for occupational radiation exposure management and 3H, 14C production for environment protection have been studied.

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