Standard method of test for atom percent fission in uranium fuel - radiochemical method

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OSTI ID:6921868

The determination of the U at. % fission that has occurred in U fuel from an analysis of the /sup 137/Cs ratio to U ratio after irradiation is described. The method is applicable to high-density, clad U fuels (metal, alloys, or ceramic compounds) in which no separation of U and Cs has occurred. The fuels are best aged for several months after irradiation in order to reduce the 13-day /sup 136/Cs activity. The fuel is dissolved and diluted to produce a solution containing a final concentration of U of 100 to 1000 mg U/l. The /sup 137/Cs concentration is determined by ASTM method E 320, for Radiochemical Determination of Cesium-137 in Nuclear Fuel Solutions, and the U concentration is determined by ASTM method E 267, for Determination of Uranium and Plutonium Concentrations and Isotopic Abundances, ASTM method E 318, for Colorimetric Determination of Uranium by Controlled-Potential Coulometry. Calculations are given for correcting the /sup 137/Cs concentration for decay during and after irradiation. The accuracy of this method is limited, not only by the experimental errors with which the fission yield and the half-life of /sup 137/Cs are known.

• OSTI ID: 6921868
• Report Number(s): ASTM-E-219
• Country of Publication: United States
• Language: English

Related Subjects

38 RADIATION CHEMISTRY, RADIOCHEMISTRY, AND NUCLEAR CHEMISTRY
400700* -- Radiochemistry & Nuclear Chemistry
ACTINIDE ALLOYS
ACTINIDES
ALLOYS
CERMETS
CHEMICAL ANALYSIS
COMPOSITE MATERIALS
ELEMENTS
ENERGY SOURCES
FISSION
FISSION YIELD
FUELS
IRRADIATION
MATERIALS
METALS
NUCLEAR FUELS
NUCLEAR REACTION YIELD
NUCLEAR REACTIONS
QUANTITATIVE CHEMICAL ANALYSIS
RADIOCHEMICAL ANALYSIS
REACTOR MATERIALS
STANDARDS
URANIUM
URANIUM ALLOYS
URANIUM BASE ALLOYS
YIELDS