²⁵²Cf is a high-intensity isotope neutron source in great demand for scientific research and device development. Currently, it is produced only in high-flux reactors in the United States and Russia, which rely on imports in China for a long time.

This study aims to analyze key factors of ²⁵²Cf production by irradiation based on the preliminary design scheme of a high-flux fast reactor.

Firstly, an irradiation target design was implemented, and the fission deposition energies and energy spectra were calculated for three irradiated target designs using different zirconium hydride and Eu₂O₃ absorbers. Then, burnup calculations for heavy and light curium targets were performed using a burnup calculation program STEP, which was developed by China Institute of Atomic Energy. The experimental values for ²⁵²Cf produced by irradiation in the United States were then compared. Finally, the calculation results were analyzed using the energy spectrum and cross-section.

Comparison results between simulation and experiment indicate that ²⁴⁵Cm is the key nuclide affecting the production of ²⁵²Cf. Utilizing the hard-energy spectral characteristics of high-flux fast reactors can effectively reduce the fission loss of the target and increase the production of ²⁵²Cf.

The calculations and analysis in this study can provide theoretical and technical support for the high-flux fast neutron research reactor irradiation production of ²⁵²Cf.