Low temperature chemical processing of graphite-clad nuclear fuels
Patent
·
OSTI ID:1399896
A reduced-temperature method for treatment of a fuel element is described. The method includes molten salt treatment of a fuel element with a nitrate salt. The nitrate salt can oxidize the outer graphite matrix of a fuel element. The method can also include reduced temperature degradation of the carbide layer of a fuel element and low temperature solubilization of the fuel in a kernel of a fuel element.
- Research Organization:
- Savannah River Site (SRS), Aiken, SC (United States)
- Sponsoring Organization:
- USDOE
- DOE Contract Number:
- AC09-08SR22470
- Assignee:
- Savannah River Nuclear Solutions, LLC
- Patent Number(s):
- 9,793,019
- Application Number:
- 14/226,458
- OSTI ID:
- 1399896
- Country of Publication:
- United States
- Language:
- English
Block-type HTGR spent fuel processing: CEA investigation program and initial results
|
journal | March 2006 |
Similar Records
Method for disposing of radioactive graphite and silicon carbide in graphite fuel elements
High Temperature Gas-cooled Reactor (HTGR) Graphite Pebble Fuel: Review of Technologies for Reprocessing
High Temperature Gas-cooled Reactor (HTGR) Graphite Pebble Fuel: Review of Technologies for Reprocessing
Patent
·
Tue Sep 12 00:00:00 EDT 1995
·
OSTI ID:131949
High Temperature Gas-cooled Reactor (HTGR) Graphite Pebble Fuel: Review of Technologies for Reprocessing
Technical Report
·
Tue Sep 08 00:00:00 EDT 2015
·
OSTI ID:1214176
High Temperature Gas-cooled Reactor (HTGR) Graphite Pebble Fuel: Review of Technologies for Reprocessing
Technical Report
·
Tue Sep 01 00:00:00 EDT 2015
·
OSTI ID:1214192