Laboratory tests using chlorine trifluoride in support of deposit removal at MSRE [electronic resource]
Experimental trials were conducted to investigate some unresolved issues regarding the use of chlorine trifluoride (ClF₃ for removal of uranium-bearing deposits in the Molten Salt Reactor Experiment (MSRE) off-gas system. The safety and effectiveness of operation of the fixed-bed trapping system for...
Saved in:
| Online Access: |
Online Access |
|---|---|
| Corporate Author: | |
| Format: | Government Document Electronic eBook |
| Language: | English |
| Published: |
Washington, D.C. : Oak Ridge, Tenn. :
United States. Dept. of Energy ; distributed by the Office of Scientific and Technical Information, U.S. Dept. of Energy,
1997.
|
| Subjects: |
| Summary: | Experimental trials were conducted to investigate some unresolved issues regarding the use of chlorine trifluoride (ClF₃ for removal of uranium-bearing deposits in the Molten Salt Reactor Experiment (MSRE) off-gas system. The safety and effectiveness of operation of the fixed-bed trapping system for removal of reactive gases were the primary focus. The chief uncertainty concerns the fate of chlorine in the system and the potential for forming explosive chlorine oxides (primarily chlorine dioxide) in the trapping operation. Tests at the MSRE Reactive Gas Removal System reference conditions and at conditions of low ClF₃ flow showed that only very minor quantities of reactive halogen oxides were produced before column breakthrough. Somewhat larger quantities accompanied breakthrough. A separation test that exposed irradiated MSRE simulant salt to ClF₃ confirmed the expectation that the salt is basically inert for brief exposures to ClF₃ at room temperature. |
|---|---|
| Item Description: | Published through the Information Bridge: DOE Scientific and Technical Information. 04/01/1997. "ORNL/TM--13403" "DE98007044" Rudolph, J.C.; Williams, D.F.; Simmons, D.W.; Del Cul, G.D.; Toth, L.M.; Loghry, S.L. |
| Physical Description: | 50 p. |