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
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
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
INL’s new innovation incubator could link start-ups with an industry sponsor
Idaho National Laboratory is looking for a sponsor to invest $5 million–$10 million in a privately funded innovation incubator to support seed-stage start-ups working in nuclear energy, integrated energy systems, cybersecurity, or advanced materials. For their investment, the sponsor gets access to what INL calls “a turnkey source of cutting-edge American innovation.” Not only are technologies supported by the program “substantially de-risked” by going through technical review and development at a national laboratory, but the arrangement “adds credibility, goodwill, and visibility to the private sector sponsor’s investments,” according to INL.
Thomas K. Larson, Keith G. Condie, Steven T. Polkinghorne, Brent J. Buescher
Nuclear Technology | Volume 93 | Number 2 | February 1991 | Pages 174-194
Technical Paper | Fission Reactor | doi.org/10.13182/NT91-A34504
Articles are hosted by Taylor and Francis Online.
An unheated, integral thermal-hydraulic facility scaled to the Advanced Test Reactor (ATR) at the Idaho National Engineering Laboratory was designed, constructed, and operated to gather simulated large-break loss-of-coolant accident (LOCA) data for use in assessing codes used in ATR analysis. Eighteen experiments were performed in the facility to establish a data base consisting of qualitative and quantitative information for assessment purposes. The effects of initial liquid temperature, break location, and use of safety injection are examined. The results obtained offer significant insights about thermal-hydraulic processes in a complex loop during subatmospheric pressure operating conditions similar to those expected during a hypothetical LOCA in the ATR.