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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.
Bo-Young Han, Hee-Sung Shin, Ho-Dong Kim
Nuclear Technology | Volume 182 | Number 3 | June 2013 | Pages 369-377
Technical Note | Fuel Cycle and Management | doi.org/10.13182/NT13-A16986
Articles are hosted by Taylor and Francis Online.
Pyrochemical processing (pyroprocessing) was developed to recover plutonium that is inherently comingled with minor actinides, uranium, and fission products and has been studied with the aim of recovering actinide elements from spent nuclear fuel. Although a significant amount of attention has been given to pyroprocessing technology as a future fuel recycling system, safeguards approaches are challengeable because of a lack of international experience with safeguarding pyroprocessing facilities beyond those at a pilot scale. Safeguards have primarily depended on nuclear material accountancy with the measurement uncertainties inherent in nuclear material flow. When the weakness of nuclear material accountancy is addressed, the quantity of material unaccounted for (MUF) is generally regarded as an important measure of the safeguardability of a facility. Statistically, the observed MUF is a random variable that is an estimate of the true MUF because the observed MUF is affected by measurement errors. The MUF uncertainty can be calculated by properly combining the random error and systematic error of the nuclear material accounting measurement. Therefore, in this study, a conceptual design for estimation of the uncertainty of MUF that can occur in a reference pyroprocessing facility (REPF) is developed, where REPF is a model used to optimize the safeguardability of a future pyroprocessing facility.