2017 Fiscal Year Final Research Report
Development of the treatment to volume-reduce of the high radioactive zirconium waste using the metal solvent
| Project/Area Number |
15K06521
|
|---|
| Research Category |
Grant-in-Aid for Scientific Research (C)
|
| Allocation Type | Multi-year Fund |
|---|
| Section | 一般 |
|---|
| Research Field |
Metal making/Resorce production engineering
|
|---|
| Research Institution | Waseda University (2017)
Iwate University (2015-2016) |
|---|
Principal Investigator |
|
|---|
| Project Period (FY) |
2015-04-01 – 2018-03-31
|
| Keywords | ジルカロイ / 状態図 / 塩化揮発 / 酸化精製 |
|---|
| Outline of Final Research Achievements |
A fundamental study was undertaken for the treatment of refractory zirconium base alloy wastes in nuclear power plants. Firstly, based on the experimentally determined activities, heat contents, and liquidus and solidus temperatures, thermodynamic optimization was made for the Cu-Zr binary system to evaluate the thermodynamic properties and phase diagram of this system. Secondly, by using the evaluated data, heat and mass balances were calculated to look for the optimum conditions in the following three processes to treat the zirconium base alloy wastes： (a) melting of the cladding hulls by alloying with the minimum quantity of molten copper, (b) recovery of zirconium from the wastes by selective chlorination of the molten Cu-Zr base alloy, and (c) elimination of radioactive elements in the zircalloy by selective oxidation of the molten Cu alloy.
|
| Free Research Field |
金属生産工学
|
