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Division Spotlight
Nuclear Installations Safety
Devoted specifically to the safety of nuclear installations and the health and safety of the public, this division seeks a better understanding of the role of safety in the design, construction and operation of nuclear installation facilities. The division also promotes engineering and scientific technology advancement associated with the safety of such facilities.
Meeting Spotlight
2027 ANS Winter Conference and Expo
October 31–November 4, 2027
Washington, DC|The Westin Washington, DC 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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Nuclear Technology
Fusion Science and Technology
November 2024
Latest News
Siting of Canadian repository gets support of tribal nation
Canada’s Nuclear Waste Management Organization (NWMO) announced that Wabigoon Lake Ojibway Nation has indicated its willingness to support moving forward to the next phase of the site selection process to host a deep geological repository for Canada’s spent nuclear fuel.
Dong-Jun Kim, Seong Dae Park, Dong Won Lee, Mu-Young Ahn
Fusion Science and Technology | Volume 72 | Number 4 | November 2017 | Pages 760-765
Technical Note | doi.org/10.1080/15361055.2017.1350487
Articles are hosted by Taylor and Francis Online.
After Conceptual Design (CD) Approval, Helium Cooled Ceramic Reflector (HCCR) Test Blanket Module (TBM) design is being updated for the preparation of the preliminary design phase, in which the manufacturability is the main concern based on the TBM-set model of CD phase. The major design parameters at the preliminary design phase were introduced. According to these parameters, the design of the main components such as first wall (FW), side wall (SW), and the breeding zone (BZ) was updated through the thermal-hydraulic analysis with ANSYS CFX v14.5. Also, the detailed design was performed on the back manifold (BM), TBM-shield, and the connecting supports. The internal channels for the He coolant and purge gas are designed in BM, in which the characteristics of the He channel were analyzed to meet the requirements of the temperature. The design concept of the connecting supports was described. The design of the TBM-shield is updated in order to simplify production and assembly.