Analysis and Research of Release Behavior on Fission Product of Dispersion Fuel

In order to obtain the release characteristics of fission products from dispersion fuel to coolant in the primary loop, the release behavior of fission products from dispersion fuel has been studied, a fission product source term calculation code for dispersion fuel is developed, and the influence of fission product source term is analyzed. The results indicate that the nuclide spectra of fission products after uranium contamination and blistering damage are different; and the release of fission products is proportional to the square of the blister equivalent diameter; and for the dispersion fuel, the proportion of release through recoil in blistering damage is fairly low; and there is a difference in the order of magnitude of fission product release between the dispersion fuel and the ceramic fuel under the same fracture condition. The code developed in this paper can be used to analyze the fission product source term of dispersion fuel, and lay the foundation for the engineering design of follow-up projects.