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Young Members Group
The Young Members Group works to encourage and enable all young professional members to be actively involved in the efforts and endeavors of the Society at all levels (Professional Divisions, ANS Governance, Local Sections, etc.) as they transition from the role of a student to the role of a professional. It sponsors non-technical workshops and meetings that provide professional development and networking opportunities for young professionals, collaborates with other Divisions and Groups in developing technical and non-technical content for topical and national meetings, encourages its members to participate in the activities of the Groups and Divisions that are closely related to their professional interests as well as in their local sections, introduces young members to the rules and governance structure of the Society, and nominates young professionals for awards and leadership opportunities available to members.
2021 ANS Winter Meeting and Technology Expo
November 30–December 3, 2021
Washington, DC|Washington Hilton
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Nuclear Science and Engineering
Fusion Science and Technology
Hanford completes wastewater basin work to support tank waste treatment
Record-breaking heat and the vast size of the job did not stop the Department of Energy’s Office of River Protection and its tank operations contractor, Washington River Protection Solutions (WRPS), from completing a construction project critical to the Hanford Site’s Direct-Feed Low-Activity Waste program for treating radioactive tank waste.
S. C. Xiao, Jing Zhao, X. Heng, X. Y. Sheng, Z. Zhou, Y. Yang
Fusion Science and Technology | Volume 68 | Number 3 | October 2015 | Pages 566-572
Technical Paper | Proceedings of TOFE-2014 | dx.doi.org/10.13182/FST14-907
Articles are hosted by Taylor and Francis Online.
In this paper, an innovative natural uranium-thorium fuel fusion-fission hybrid reactor (FFHR) design aiming at closed thorium-uranium fuel cycle, and which could operate with high energy gain, fast 233U breeding rate and tritium self-sufficiency, is presented. The reactor consists of two main modules, i.e. natural uranium module and thorium module, which are placed alternately in the blanket’s toroidal direction. Uranium module plays the role of energy generation and neutron multiplication at the initial stage. Excess neutrons are then used to drive the thorium module to breed 233U. After the 233U inventory reaches a certain level, the uranium module is then replaced by new thorium fuel module. The system is transition to the all thorium fueled operating mode. With appropriately selected thorium fuel to water volumetric ratio, the system could then be started by the limited bred 233U. The blanket could reach thorium-uranium closed fuel cycle with high energy gain and tritium self-sufficiency. The system could burn up about 90 tonnes 232Th at the end of 60 years operating.