ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
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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
TerraPower begins U.K. regulatory approval process
Seattle-based TerraPower signaled its interest this week in building its Natrium small modular reactor in the United Kingdom, the company announced.
TerraPower sent a letter to the U.K.’s Department for Energy Security and Net Zero, formally establishing its intention to enter the U.K. generic design assessment (GDA) process. This is TerraPower’s first step in deployment of its Natrium technology—a 345-MW sodium fast reactor coupled with a molten salt energy storage unit—on the international stage.
W. W. Hudritsch
Nuclear Technology | Volume 18 | Number 1 | April 1973 | Pages 25-28
Technical Paper | Instrument | doi.org/10.13182/NT73-A16104
Articles are hosted by Taylor and Francis Online.
Self-powered neutron detectors are suitable for continuous flux measurements and were used to monitor some of Gulf General Atomic’s irradiation experiments in the Engineering Test Reactor in connection with the development of fuel for high temperature gas-cooled reactors. For the purpose of detector current data reduction, the special case of a rhodium detector is analyzed and explicit solutions for the neutron flux and neutron fluence are developed. The solutions describe the time-dependence of flux and fluence for detector irradiation times ≳1 h. Independent variables are the detector current and its time derivative, both of which are functions of time. Constants appearing in the equations are the neutron flux, the corresponding electrical current and its time derivative at the time of calibration, the decay constant of 104Rh (4.36 min), and the effective cross section for 103Rh(n,γ)104Rh reactions .
