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Division Spotlight
Fusion Energy
This division promotes the development and timely introduction of fusion energy as a sustainable energy source with favorable economic, environmental, and safety attributes. The division cooperates with other organizations on common issues of multidisciplinary fusion science and technology, conducts professional meetings, and disseminates technical information in support of these goals. Members focus on the assessment and resolution of critical developmental issues for practical fusion energy applications.
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.
H. D. Brown
Nuclear Science and Engineering | Volume 2 | Number 5 | September 1957 | Pages 687-693
Technical Paper | doi.org/10.13182/NSE57-A25436
Articles are hosted by Taylor and Francis Online.
The solution of the equations describing the reactor state is obtained by numerical integration of the differential equations on an IBM-650. The general description includes the dependence of lattice constants and absorption cross sections upon the temperatures of various components and accommodates the effects of manipulations of the geometric buckling and of the total absorption cross section. The reactor kinetic equations are put into difference form suitable for numerical solution. Measures are described for eliminating divergences introduced by the numerical treatment of the coupling among temperature coefficients, delayed neutrons, and flux.
