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ASTM C1769-15 PDF Download

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Standard Practice for Analysis of Spent Nuclear Fuel to Determine Selected Isotopes and Estimate Fuel Burnup
standard by ASTM International, 06/01/2015

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1.1 A sample of spent nuclear fuel is analyzed to determine the quantity and atomic ratios of uranium and plutonium isotopes, neodymium isotopes, and selected gamma-emitting nuclides (137Cs, 134Cs, 154Eu, 106Ru, and 241Am). Fuel burnup is calculated from the 148Nd-to-fuel ratio as described in this method, which uses an effective 148Nd fission yield calculated from the fission yields of 148Nd for each of the fissioning isotopes weighted according to their contribution to fission as obtained from this method. The burnup value determined in this way requires that values be assumed for certain reactor-dependent properties called for in the calculations (1, 2).2

Product Details

Published:
06/01/2015
Number of Pages:
7
File Size:
1 file , 150 KB