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WIPP: Lessons in transportation safety
As part of a future consent-based approach by the federal government to site new deep geologic repositories for nuclear waste, local communities and states that are considering hosting such facilities are sure to have many questions. Currently, the Waste Isolation Pilot Plant in New Mexico is the only example of such a repository in operation, and it offers the opportunity for state and local officials to visit and judge for themselves the risks and benefits of hosting a similar facility. But its history can also provide lessons for these officials, particularly the political process leading up to the opening of WIPP, the safety of WIPP operations and transportation of waste from generator facilities to the site, and the economic impacts the project has had on the local area of Carlsbad, as well as the rest of the state of New Mexico.
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 %.