A concept on calculating radiolysis rate with MCNP code

Radiolysis is a dissociation process of medium passed by ionizing radiation such as α, β, γ and neutron. Radiolysis process in nuclear reactors or other nuclear facilities should get attention, as its product may affect safety and accelerate component degradation. Therefore, a concept has to be available to calculate radiolysis rate, in such that we can estimate how much and what species are produced. This paper elaborates a calculation concept using MCNP code. F6 tally is provided by MCNP to calculate energy deposition in the medium transferred by radiation. By combining the experimental data of g-value, i.e. number of molecules produced by radiation due to transfer of unit energy, the dissociation of medium can be calculated. Compared to the deterministic method, this method is more flexible since the users can define the problem easily such as type of radiation, the choice on radiation energy spectrum, source geometry, medium geometry, and material, etc. This paper is aimed at formulating calculation concept of radiolysis rate with MCNP and by combining experimental data of g-value. (author)