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An attempt is being made to develop a method for reporting radiation damage exposure which will be consistent and applicable for different reactor environments. A model has been proposed for this purpose and calculations of relative damage rates have been performed. The experimental work described in this report is an attempt to verify the model. Progress from January through July, 1962, is reported.
The approach is to perform series of irradiations on one type of steel in several reactor locations which have different fast spectra. The spectra are calculated and then verified by foil dosimetry. For each location a curve is developed of the shift in the brittle-ductile transition temperature as a function of integrated reactor power. The test of the model will be the extent of agreement obtained between the several curves.
Long-term exploratory irradiations have been performed in the Experimental Breeder Reactor I (EBR-I) and in two locations in CP-5. The facilities and spectra are described. Shifts as great as 270 F were observed. The series of shorter irradiations in EBR-I was performed, but the testing and analysis could not be completed in time for this report. Capsules for the next CP-S irradiations are now being prepared.
Dosimetry forms a major aspect of this work. Results of nickel-58 monitor foils in the EBR-I irradiation are reported, but work on sulfur, iron-54, copper-63 and some fission monitors is not complete.
The appendices contain details of cross-sectional data, specimens, irradiation facilities and locations, and irradiation history.
Rossin, A. D.
Argonne National Laboratory, Argonne, Ill.