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Division Spotlight
Accelerator Applications
The division was organized to promote the advancement of knowledge of the use of particle accelerator technologies for nuclear and other applications. It focuses on production of neutrons and other particles, utilization of these particles for scientific or industrial purposes, such as the production or destruction of radionuclides significant to energy, medicine, defense or other endeavors, as well as imaging and diagnostics.
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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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.
W. C. Redman, M. M. Bretscher
Nuclear Science and Engineering | Volume 27 | Number 1 | January 1967 | Pages 34-44
Technical Paper | doi.org/10.13182/NSE67-A18040
Articles are hosted by Taylor and Francis Online.
An experimental method for the determination of the spectral average of the capture-to-fission ratio ᾱ for materials inserted in a low-flux reactor is described. The procedure involves a comparison of reactor response to oscillated samples of a fissile material, an absorber, and a spontaneous fission neutron source, plus an experimental determination of fission rate for the fissile material and capture rate for the absorber. In addition, it is necessary that the neutron source be calibrated. These experimental results, combined with a knowledge of the number of neutrons per fission for the fissile material, yield a value of the quantity 1 + ᾱ. This method has been tested in Hi-C Core 10, a critical assembly of 3%-enriched-U02 fuel pins, moderated and reflected by light water, in a lattice spacing which yields a H-to-238U atom ratio of 2:91. The oscillator and absolute counting data yield a value of 0.217 for the central capture-to-fission ratio of 235U, with a standard deviation of ± 0.015. This agrees well with values derived from a combination of measured 235U fission cadmium ratios and calculated thermal and epithermal values for a.
