This report describes the application of a vapor transportation model to fission product release data obtained for uranium/aluminum alloy fuel during early Oak Ridge fuel melt experiments. The Oak Ridge data validates the vapor transpiration model and suggests that iodine and cesium are released from the molten fuel surface in elemental form while tellurium and ruthenium are released as oxides. Cesium iodide is postulated to form in the vapor phase outside of the fuel matrix. Kinetic data indicates that cesium iodide can form from Cs atoms and diatomic iodine in the vapor phase. Temperatures lower than those capable of melting fuel are necessary in order to maintain a sufficient I2 concentration. At temperatures near the fuel melting point,...
During a hypothetical severe nuclear accident involving a pressurised water reactor, it is of primar...
The objective of this work was to examine the chemical reactions taking place on primary circuit sur...
International audienceIn case of severe accident in a water-cooled nuclear reactor, the amount of ga...
This report presents a scoping study of cesium, iodine, and tellurium behavior during a cold leg man...
Experiments in the controlled melting of irradiated fuel speciman, particularly of the APPR, STR, an...
Three tests have provided additional data on fission product release under LWR accident conditions i...
The chemistry of cesium and iodine is of main importance to quantify the radioactive release in case...
AbstractThe chemistry of cesium and iodine is of main importance to quantify the radioactive release...
The instant release of fission products from high burn-up UO2 fuels and one MOX fuel was investigate...
The chemical form and rate of release of volatile fission products (i.e., Xe, Kr, Cs, Te, I...) effu...
Approximately 50% of the fission product cesium was released from the overheated UO/sub 2/ fuel in t...
Qualitative and quantitative determination of the release of low-volatile fission products and core ...
The melt-dilute treatment technology is being developed to facilitate the ultimate disposition of hi...
Five melt refining demonstration experiments were conducted with highly irradiated EBR-II prototype ...
Fission product migration and end-of-life distributions were examined in the F-1 (X094) series of se...
During a hypothetical severe nuclear accident involving a pressurised water reactor, it is of primar...
The objective of this work was to examine the chemical reactions taking place on primary circuit sur...
International audienceIn case of severe accident in a water-cooled nuclear reactor, the amount of ga...
This report presents a scoping study of cesium, iodine, and tellurium behavior during a cold leg man...
Experiments in the controlled melting of irradiated fuel speciman, particularly of the APPR, STR, an...
Three tests have provided additional data on fission product release under LWR accident conditions i...
The chemistry of cesium and iodine is of main importance to quantify the radioactive release in case...
AbstractThe chemistry of cesium and iodine is of main importance to quantify the radioactive release...
The instant release of fission products from high burn-up UO2 fuels and one MOX fuel was investigate...
The chemical form and rate of release of volatile fission products (i.e., Xe, Kr, Cs, Te, I...) effu...
Approximately 50% of the fission product cesium was released from the overheated UO/sub 2/ fuel in t...
Qualitative and quantitative determination of the release of low-volatile fission products and core ...
The melt-dilute treatment technology is being developed to facilitate the ultimate disposition of hi...
Five melt refining demonstration experiments were conducted with highly irradiated EBR-II prototype ...
Fission product migration and end-of-life distributions were examined in the F-1 (X094) series of se...
During a hypothetical severe nuclear accident involving a pressurised water reactor, it is of primar...
The objective of this work was to examine the chemical reactions taking place on primary circuit sur...
International audienceIn case of severe accident in a water-cooled nuclear reactor, the amount of ga...