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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
Utility Working Conference and Vendor Technology Expo (UWC 2024)
August 4–7, 2024
Marco Island, FL|JW Marriott Marco Island
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
Taking shape: Fusion energy ecosystems built with public-private partnerships
It’s possible to describe fusion in simple terms: heat and squeeze small atoms to get abundant clean energy. But there’s nothing simple about getting fusion ready for the grid.
Private developers, national lab and university researchers, suppliers, and end users working toward that goal are developing a range of complex technologies to reach fusion temperatures and pressures, confounded by science and technology gaps linked to plasma behavior; materials, diagnostics, and electronics for extreme environments; fuel cycle sustainability; and economics.
Chikara Konno, Satoshi Sato, Kentaro Ochiai, Masayuki Wada, Seiki Ohnishi, Kosuke Takakura, Hiromasa Iida
Nuclear Technology | Volume 168 | Number 3 | December 2009 | Pages 743-746
Heavy Ion Transport | Special Issue on the 11th International Conference on Radiation Shielding and the 15th Topical Meeting of the Radiation Protection and Shielding Division (PART 3) / Radiation Protection | doi.org/10.13182/NT09-A9299
Articles are hosted by Taylor and Francis Online.
The three-dimensional Sn code Attila of Transpire, Inc., can use computer-aided-design data as direct geometrical input and can deal with assemblies of complicated geometry without much effort. The International Thermonuclear Experimental Reactor (ITER) organization plans to adopt this code as one of the standard codes for nuclear analyses. However, validation of calculations with this code has not been carried out in detail so far. Thus, we validate this code through analyses of some bulk experiments and streaming experiments with deuterium-tritium neutrons at the Japan Atomic Energy Agency Fusion Neutronics Source. Analyses with the Sn code system DOORS and Monte Carlo code MCNP4C were also carried out for comparison. The agreement between the Attila and DOORS calculations is very good for the bulk experiments. For the streaming experiments Attila requires special treatment (biased angular quadrature sets or last collided source calculation) as well as DOORS in order to obtain similar results as those with MCNP, though Attila consumes much more time than DOORS.