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Division Spotlight
Nuclear Installations Safety
Devoted specifically to the safety of nuclear installations and the health and safety of the public, this division seeks a better understanding of the role of safety in the design, construction and operation of nuclear installation facilities. The division also promotes engineering and scientific technology advancement associated with the safety of such facilities.
Meeting Spotlight
ANS Student Conference 2025
April 3–5, 2025
Albuquerque, NM|The University of New Mexico
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
Penn State and Westinghouse make eVinci microreactor plan official
Penn State and Westinghouse Electric Company are working together to site a new research reactor on Penn State’s University Park, Pa., campus: Westinghouse’s eVinci, a HALEU TRISO-fueled sodium heat-pipe reactor. Penn State has announced that it submitted a letter of intent to host and operate an eVinci reactor to the Nuclear Regulatory Commission on February 28 and plans to engage with the NRC on specific siting decisions. Penn State already boasts the Breazeale reactor, which began operating in 1955 as the first licensed research reactor at a university in the United States. At 70, the Breazeale reactor is still in operation.
Robert E. Uhrig
Nuclear Science and Engineering | Volume 6 | Number 6 | December 1959 | Pages 530-532
doi.org/10.13182/NSE59-A15514
Articles are hosted by Taylor and Francis Online.
An alternate method of measuring material buckling in a subcritical assembly is presented. The fundamental mode of the neutron flux is isolated by using the orthogonality introduced when the equation for the neutron flux is a subcritical assembly is multiplied by [cos πx/a cos πy/b dx dy] and integrated over the cross-sectional area of the assembly. The resulting double integral is evaluated by measuring the neutron flux at grid points and then employing tabular integration. After neutron flux measurements have been taken on two levels, the inverse relaxation length and material buckling can be evaluated. The precision of these determinations are obtained by using the method of propagation of precision indices.
