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Nuclear Criticality Safety
NCSD provides communication among nuclear criticality safety professionals through the development of standards, the evolution of training methods and materials, the presentation of technical data and procedures, and the creation of specialty publications. In these ways, the division furthers the exchange of technical information on nuclear criticality safety with the ultimate goal of promoting the safe handling of fissionable materials outside reactors.
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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
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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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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.
Yoshiyuki Asaoka, Kunihiko Okano, Tomoaki Yoshida, Ken Tomabechi, Yuichi Ogawa, Naoto Sekimura, Yuzo Fukai, Akiyoshi Hatayama, Nobuyuki Inoue, Akira Kohyama, Sei-Ichiro Yamazaki, Seiji Mori
Fusion Science and Technology | Volume 34 | Number 3 | November 1998 | Pages 863-867
Fusion Blanket and Shield Technology (Poster Session) | doi.org/10.13182/FST98-A11963720
Articles are hosted by Taylor and Francis Online.
The possibility of developing a cost competitive fusion power plant with a water-cooled blanket concept, which has much experience in nuclear power plants, was examined. The new blanket design is based on using reduced activation ferritic steel components and an advanced super-heated steam cycle which is used to realize high thermal efficiency. The high value of thermal efficiency is very effective in reducing the cost of electricity.
The allowable temperature range of the structure material, reduced activation ferritic steel, is assumed to be 350K to 900K based on expectations from the material research and development program. A mixture of lithium oxide pebbles and beryllium pebbles is installed in the breeding zone for high tritium breeding ratio and high thermal conductivity. Mixture ratio of beryllium and lithium-6 enrichment were optimized from the viewpoint of temperature distribution in the breeding zone, achievable tritium breeding ratio and its reduction due to burn up. The reference blanket system has a local tritium breeding ratio of 1.37. The arrangement of cooling channels in the breeding zones and flow rate and inlet temperature of the coolant were also optimized to keep the temperatures of structure materials, breeding materials and coolant in the allowable range. The first wall is cooled by pressurized water at about 570 K. The coolant out of the first wall is led to the breeding zone and starts to boil. The steam is super-heated up to 750 K in the blanket. This high temperature raises the thermal efficiency of the turbine to 41 %.