Dissolution of Zirconium Reactor Fuels in Titanium Equipment (open access)

Dissolution of Zirconium Reactor Fuels in Titanium Equipment

Continuous dissolution of Zircaloy-2 in a titanium dissolver appears practical using as a dissolvent refluxing 3 M HNO/sub 2/-l.2 M HF--0.4 M HBF/sub 4/-0.6 M Cr(III)-0.4 M Cr(VI)--0.46 M Zr. Dissolution and corrosion rates were 10 mg/cm/sub 2/-min and 0.0 mil/mo in short term tests, respectively. A stable product solution containing 0.36 M Zr was obtained after addition of aluminum nitrate to complex fluoride ion. Another reagent investigated for use in continuous dissolution was 16 M HNO/sub 3/-2.6 M F-0.025 M HBF/sub 4/-1.4 M Zr with short term titanium corrosion rates of 0.0 mil/mo. However, Zircaloy-2 dissolution rates were only 3 mg/cm/sup 2/-min in the latter reagent. (auth)
Date: October 11, 1961
Creator: Gens, T.A.
Object Type: Report
System: The UNT Digital Library
Cesium-137 as an index of the nuclear materials content of coating waste (open access)

Cesium-137 as an index of the nuclear materials content of coating waste

An experimental program was carried out to evaluate the validity of using the cesium-137 content of coating waste as an indirect measure of the uranium and/or plutonium content. A small number of large volume samples and a large number of normal (small volume) samples of Redox and Purex coating waste were used for the investigations. The distribution of cesium, uranium, and plutonium throughout the two-phase system was determined. a comparison of uranium by direct assay and uranium by cesium-137 was obtained for both Redox and Purex samples. A plant test was carried out to determine the extent of cesium migration and the extent to which product materials are transferred from the dissolver to underground storage in coating waste. Sampling for cesium-137 was found to be markedly more consistent than for product materials. In general, the cesium-137 content was found to be a more sensitive measure of the relative product content of coating waste than the uranium content as measured by direct assay. To date al the evidence indicates that the cesium-137 content of coating waste is a valid measure of the product content. However, more ``back-up`` data and a ``routine use`` evaluation are needed before the method can be considered …
Date: October 11, 1961
Creator: Schneider, R. A.
Object Type: Report
System: The UNT Digital Library
Texas Attorney General Opinion: WW-1164 (open access)

Texas Attorney General Opinion: WW-1164

Document issued by the Office of the Attorney General of Texas in Austin, Texas, providing an interpretation of Texas law. It provides the opinion of the Texas Attorney General, Will Wilson, regarding a legal question submitted for clarification: Effect of House Bill No. 829, 57th Leg., R.S., amending Sec. 9 of Article 734a, Vernon's Penal Code, as to a student enrolled in an approved barber school, whose schooling was interrupted and who later re-enrolls to complete his course.
Date: October 11, 1961
Creator: Texas. Attorney-General's Office.
Object Type: Text
System: The Portal to Texas History