NSUF 19-CINR-16583: Neutron Radiation Effect on Diffusion between Zr (and Zircaloy) and Cr for Accurate Lifetime Prediction of ATF
One of the very promising accident-tolerant fuel (ATF) claddings consists of Zircaloy coated with chromium (Cr). The diffusion coefficients – both impurity (dilute) diffusion coefficients and interdiffusion coefficients – between Zr (and Zircaloy) and Cr are essential for understanding the behavior of ATF under operating and accident conditions and for accurate ATF lifetime prediction. The objectives of this proposed project are: (1) to perform systematic diffusion studies of the Zr–(Cr, Nb, Ta, Mo) (and Zircaloy–Cr) as well as the Cr–(Nb, Ta, Mo) binary systems across the entire composition range and at multiple temperatures from 300 °C to 1200 °C to establish a reliable diffusion (mobility) database for the Zr–(Cr, Nb, Ta, Mo) and Cr–(Nb, Mo, Ta) binary systems; (2) to perform neutron radiation experiments at the temperature and neutron flux conditions close to the ATF operating conditions for extended durations at TREAT using the MARCH specimen holder such that the neutron-accelerated diffusion coefficients can be carefully evaluated; and (3) to subtract the regular diffusion contributions from the neutron-accelerated diffusion coefficients so that the neutron radiation effect on diffusion can be accurately evaluated. The systematic data from this proposed study will allow accurate prediction of the interdiffusion behavior of Cr, Mo and Ta and Zr (Zircaloy) and thus the lifetime of the Cr coated Zircaloy with Nb, Mo and Ta interlayered ATF.
Допълнителна информация
| Поле | Стойност |
|---|---|
| Abstract | One of the very promising accident-tolerant fuel (ATF) claddings consists of Zircaloy coated with chromium (Cr). The diffusion coefficients – both impurity (dilute) diffusion coefficients and interdiffusion coefficients – between Zr (and Zircaloy) and Cr are essential for understanding the behavior of ATF under operating and accident conditions and for accurate ATF lifetime prediction. The objectives of this proposed project are: (1) to perform systematic diffusion studies of the Zr–(Cr, Nb, Ta, Mo) (and Zircaloy–Cr) as well as the Cr–(Nb, Ta, Mo) binary systems across the entire composition range and at multiple temperatures from 300 °C to 1200 °C to establish a reliable diffusion (mobility) database for the Zr–(Cr, Nb, Ta, Mo) and Cr–(Nb, Mo, Ta) binary systems; (2) to perform neutron radiation experiments at the temperature and neutron flux conditions close to the ATF operating conditions for extended durations at TREAT using the MARCH specimen holder such that the neutron-accelerated diffusion coefficients can be carefully evaluated; and (3) to subtract the regular diffusion contributions from the neutron-accelerated diffusion coefficients so that the neutron radiation effect on diffusion can be accurately evaluated. The systematic data from this proposed study will allow accurate prediction of the interdiffusion behavior of Cr, Mo and Ta and Zr (Zircaloy) and thus the lifetime of the Cr coated Zircaloy with Nb, Mo and Ta interlayered ATF. |
| Award Announced Date | 2019-12-13T00:00:00 |
| Awarded Institution | None |
| Facility | None |
| Facility Tech Lead | |
| Irradiation Facility | None |
| PI | Ji-Cheng Zhao |
| PI Email | [email protected] |
| Project Type | CINR |
| RTE Number | 3035 |