| Autor: |
Belonogov, M. N., Volkov, I. A., Modestov, D. G., Rykovanov, G. N., Simonenko, V. A., Khmelnitsky, D. V. |
| Předmět: |
|
| Zdroj: |
Atomic Energy; Aug2022, Vol. 132 Issue 4, p202-207, 6p |
| Abstrakt: |
As an alternative approach to the transmutation of Np, Am, and Cm in fast power reactors, the use of a specialized facility is considered, which includes a molten-salt burner reactor and module for fuel reprocessing and fabrication. Based on the requirements for the consumer properties of the installation, a comparative analysis of transmutation for LiF–NaF–KF and LiF–BeF2 salts was performed. Calculations of the transmutation characteristics were performed for model systems. The computational results show the advantages of a reactor based on the LiF–NaF–KF salt on account of the higher solubility of actinide fluorides. For a given transmutation capacity, a burner reactor based on LiF–NaF–KF consumes several-fold less power-grade plutonium, right up to its absence in the equilibrium regime, as well as lower thermal power and lower production of fission products. Of note is a particular aspect of the molten-salt incinerator reactor that is associated with the accumulation of even-numbered plutonium isotopes during its operation whereby the plutonium extracted from the facility is actually converted into long-lived radioactive waste. [ABSTRACT FROM AUTHOR] |
| Databáze: |
Complementary Index |
| Externí odkaz: |
|
Full text from SpringerLink