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Division Spotlight
Thermal Hydraulics
The division provides a forum for focused technical dialogue on thermal hydraulic technology in the nuclear industry. Specifically, this will include heat transfer and fluid mechanics involved in the utilization of nuclear energy. It is intended to attract the highest quality of theoretical and experimental work to ANS, including research on basic phenomena and application to nuclear system design.
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
Argonne’s METL gears up to test more sodium fast reactor components
Argonne National Laboratory has successfully swapped out an aging cold trap in the sodium test loop called METL (Mechanisms Engineering Test Loop), the Department of Energy announced April 23. The upgrade is the first of its kind in the United States in more than 30 years, according to the DOE, and will help test components and operations for the sodium-cooled fast reactors being developed now.
A. F. Debosscher
Nuclear Science and Engineering | Volume 69 | Number 3 | March 1979 | Pages 354-362
Technical Paper | doi.org/10.13182/NSE79-A19952
Articles are hosted by Taylor and Francis Online.
In the present paper, an exact first-order statistical analysis is given of the power and temperature fluctuations in a nuclear power reactor with temperature feedback, which is perturbed by Gaussian white reactivity noise. Using a new technique, the time-independent Fokker-Planck equation for the two-dimensional power-temperature Markov process is solved in terms of a two-dimensional first-order characteristic function. This characteristic function gives a complete first-order statistical description of the investigated stochastic process and allows for the calculation of the marginal and the combined probability density functions of reactor power and temperature. In addition, a general expression for the moments is derived. Since the underlying reactor model has been extensively used in approximate linearized analyses, a comparison can be made of the exact results obtained in this paper with the earlier results, and the validity of the linear approximation can be delimited in terms of two dimensionless system parameters.