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Division Spotlight
Human Factors, Instrumentation & Controls
Improving task performance, system reliability, system and personnel safety, efficiency, and effectiveness are the division's main objectives. Its major areas of interest include task design, procedures, training, instrument and control layout and placement, stress control, anthropometrics, psychological input, and motivation.
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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Nuclear Science and Engineering
May 2025
Nuclear Technology
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Latest News
Judge temporarily blocks DOE’s move to slash university research funding
A group of universities led by the American Association of Universities (AAU) acted swiftly to oppose a policy action by the Department of Energy that would cut the funds it pays to universities for the indirect costs of research under DOE grants. The group filed suit Monday, April 14, challenging a what it termed a “flagrantly unlawful action” that could “devastate scientific research at America’s universities.”
By Wednesday, the U.S. District Court judge hearing the case issued a temporary restraining order effective nationwide, preventing the DOE from implementing the policy or terminating any existing grants.
Zheng-Ming Zhang, Min-Zhi Wang, Shu-Yan He
Nuclear Technology | Volume 135 | Number 2 | August 2001 | Pages 85-91
Technical Paper | Fission Reactors | doi.org/10.13182/NT01-A3207
Articles are hosted by Taylor and Francis Online.
The HTR-10, which now is under construction, is the first high-temperature gas-cooled reactor developed in China. The primary loop boundary components of the HTR-10 are peculiarly arranged as the reactor pressure vessel stands side by side with the steam-generator pressure vessel, and a hot-gas duct vessel connects them. This arrangement can diminish the thermal loads on the pressure vessels but can cause some new problems under seismic conditions. The design features of the support system of the HTR-10 primary loop boundary components are introduced. The procedure of seismic analysis of the support system is emphasized. Based on equivalent-static and dynamic calculations, the safety features of the support system under seismic conditions are demonstrated.