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Division Spotlight
Robotics & Remote Systems
The Mission of the Robotics and Remote Systems Division is to promote the development and application of immersive simulation, robotics, and remote systems for hazardous environments for the purpose of reducing hazardous exposure to individuals, reducing environmental hazards and reducing the cost of performing work.
Meeting Spotlight
Conference on Nuclear Training and Education: A Biennial International Forum (CONTE 2025)
February 3–6, 2025
Amelia Island, FL|Omni Amelia Island Resort
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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Fusion Science and Technology
Latest News
Christmas Night
Twas the night before Christmas when all through the houseNo electrons were flowing through even my mouse.
All devices were plugged in by the chimney with careWith the hope that St. Nikola Tesla would share.
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 %.