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Division Spotlight
Materials Science & Technology
The objectives of MSTD are: promote the advancement of materials science in Nuclear Science Technology; support the multidisciplines which constitute it; encourage research by providing a forum for the presentation, exchange, and documentation of relevant information; promote the interaction and communication among its members; and recognize and reward its members for significant contributions to the field of materials science in nuclear technology.
Meeting Spotlight
International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025)
April 27–30, 2025
Denver, CO|The Westin Denver Downtown
Standards Program
The Standards Committee is responsible for the development and maintenance of voluntary consensus standards that address the design, analysis, and operation of components, systems, and facilities related to the application of nuclear science and technology. Find out What’s New, check out the Standards Store, or Get Involved today!
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Latest News
DTE Energy studying uprate at Fermi-2, considers Fermi-3’s prospects
DTE Energy, the owner of Fermi nuclear power plant in Michigan, is considering an extended uprate for Unit 2 that would increase its 1,100-MW generation capacity by 150 MW.
R. G. Nisle, I. E. Stepan
Nuclear Science and Engineering | Volume 31 | Number 2 | February 1968 | Pages 241-246
Technical Paper | doi.org/10.13182/NSE68-A18236
Articles are hosted by Taylor and Francis Online.
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.