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Division Spotlight
Fuel Cycle & Waste Management
Devoted to all aspects of the nuclear fuel cycle including waste management, worldwide. Division specific areas of interest and involvement include uranium conversion and enrichment; fuel fabrication, management (in-core and ex-core) and recycle; transportation; safeguards; high-level, low-level and mixed waste management and disposal; public policy and program management; decontamination and decommissioning environmental restoration; and excess weapons materials disposition.
Meeting Spotlight
ANS Student Conference 2025
April 3–5, 2025
Albuquerque, NM|The University of New Mexico
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
NEA panel on AI hosted at World Governments Summit
A panel on the potential of artificial intelligence to accelerate small modular reactors was held at the World Governments Summit (WGS) in February in Dubai, United Arab Emirates. The OECD Nuclear Energy Agency cohosted the event, which attracted leaders from developers, IT companies, regulators, and other experts.
Shiang-Huei Jiang
Nuclear Science and Engineering | Volume 75 | Number 1 | July 1980 | Pages 16-29
Technical Paper | doi.org/10.13182/NSE80-1
Articles are hosted by Taylor and Francis Online.
A one-dimensional gamma-ray transport code BIGGI 4T has been used to calculate gamma-ray attenuation in single layer and multiple layers of lead and water slabs from a plane monodirectional source. It has been found that boundary effect of finite medium is appreciable only in water within two mean-free-paths (mfp) of the boundary. Transmission buildup factors for multilayer slabs are not sensitive to the sequence of the alternate layers for the 3-MeV source. The conventional rule of thumb, that when the outermost layer exceeds 2 or 3 mfp, the buildup factor of the outermost material generally recommended, has been shown to be a bad approximation when based on the total number of mean-free-paths along the line of sight through all materials. Energy absorption buildup factor at the interface between layers was investigated in more detail. Transmission buildup factors obtained in the present study have been compared with those calculated by other empirical formulas. The applied range of various empirical formulas has been discussed. It has been found that semiempirical formulas devised by Kalos give data agreeing, in general and on the average, with the present results to within 5%.