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Measurement of 135I Yield Ratios and Fission-Product Cross Sections in the Advanced Reactivity Measurement Facilities

R. G. Nisle, I. E. Stepan

Nuclear Science and Engineering / Volume 31 / Number 2 / February 1968 / Pages 241-246

Technical Paper / dx.doi.org/10.13182/NSE68-A18236

The yields of 135I in the fission of 233U, 239Pu, and 241pu relative to that of 235U have been measured by an integral method using the Advanced Reactivity Measurement Facilities (ARMF I and II). The xenon reactivity transient was measured following irradiation of the fissile isotope in the Materials Testing Reactor (MTR) for periods from to 2½ to 16 days. The use of the two ARMF reactors permits the calculation of the absorption cross sections of both simple absorbers and fissile atoms. The 135I yield ratios, relative to 235U, were found to be 0.825 ± 0.072 for 233U, 1.006 ± 0.067 for 239Pu, and 1.221 ± 0.089 for 241Pu. The uncertainties quoted are confidence intervals at the 90% confidence level.