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Division Spotlight
Materials Science & Technology
The objectives of MSTD are: promote the advancement of materials science in Nuclear Science Technology; support the multidisciplines which constitute it; encourage research by providing a forum for the presentation, exchange, and documentation of relevant information; promote the interaction and communication among its members; and recognize and reward its members for significant contributions to the field of materials science in nuclear technology.
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.
Hermann Würz
Nuclear Technology | Volume 95 | Number 2 | August 1991 | Pages 193-206
Technical Paper | Nuclear Fuel Cycle | doi.org/10.13182/NT91-A34556
Articles are hosted by Taylor and Francis Online.
A method for nondestructive assay of spent light water reactor fuel assemblies based on a combination of active and passive neutron counting is presented. After geometrical optimization, the Fuel Assembly Monitoring System (FAMOS) is a rather simple system. It allows the burnup, initial enrichment, type of fuel (uranium or mixed oxide), and criticality of the spent-fuel assembly to be determined. The results of a characterization program with emphasis on boiling water reactor (BWR) fuel assemblies are discussed. Burnup-dependent neutron emission data for spent BWR fuel are now available. The effect of steam void on plutonium and curium buildup is demonstrated. Because of this effect, the axial measurement position is of importance for an accurate assay. If the measurement is done at the upper part of the BWR fuel assembly, the error in burnup remains below ±2 GWd/tonne U, and the initial enrichment can be determined with an accuracy of ±15%. This still allows a clear distinction between the different enrichment regions used for BWR fuel assemblies.