Analysis of the Possibility of Using Fuel Based on Reclaimed Uranium in VVÉR Reactors |
| |
| Authors: | V N Proselkov S S Aleshin S G Popov V D Sidorenko P D Slavyagin A L Tataurov O V Milovanov E N Mikheev Yu A Anan'ev Yu N Pytkin Yu V Pimenov |
| |
| Affiliation: | (1) Russian Science Center Kurchatov Institute, Russia;(2) Federal State Unitary Enterprise, A. A. Bochvar All-Russia Scientific-Research Institute of Standardization in Machine Engineering, Russia;(3) Special Design Office Gidropress, Federal State Unitary Enterprise, Russia;(4) Russia;(5) Open Joint-Stock Company Tvél, Russiaf |
| |
| Abstract: | A current problem is to show that reclaimed uranium can be, in principle, brought into the VVÉR fuel cycle. The possibility of using fuel based on reprocessed uranium in VVÉR is analyzed. The requirements for the initial isotopic composition of test batches of fuel pellets with 4% effective enrichment are determined, the compensation coefficient is calculated, the requirements for monitoring the isotopic composition are determined, and the technlogy for fabricating fuel pellets from relaimed fuel is determined. It is shown that the basic neutron-physical characteristics satisfy the restrictions adopted in the VVÉR-440 and -1000 designs. The effect of radiation on the public and the environment as a result of switching to fuel fabricated from reclaimed uranium is the same as for the standard oxide fuel. |
| |
| Keywords: | |
| 本文献已被 SpringerLink 等数据库收录！ |
|
