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Nuclear Criticality Safety
NCSD provides communication among nuclear criticality safety professionals through the development of standards, the evolution of training methods and materials, the presentation of technical data and procedures, and the creation of specialty publications. In these ways, the division furthers the exchange of technical information on nuclear criticality safety with the ultimate goal of promoting the safe handling of fissionable materials outside reactors.
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ANS Student Conference 2025
April 3–5, 2025
Albuquerque, NM|The University of New Mexico
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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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Latest News
First astatine-labeled compound shipped in the U.S.
The Department of Energy’s National Isotope Development Center (NIDC) on March 31 announced the successful long-distance shipment in the United States of a biologically active compound labeled with the medical radioisotope astatine-211 (At-211). Because previous shipments have included only the “bare” isotope, the NIDC has described the development as “unleashing medical innovation.”
Maosheng Li, Rong Liu, Xueming Shi, Weiwei Yi, Yaosong Shen, Xianjue Peng
Fusion Science and Technology | Volume 61 | Number 1 | January 2012 | Pages 195-199
Fusion-Fission Hybrids and Transmutation | Proceedings of the Fifteenth International Conference on Emerging Nuclear Energy Systems | doi.org/10.13182/FST12-1T2
Articles are hosted by Taylor and Francis Online.
The project, conceptual design of the fusion-fission hybrid energy reactors (FFHER) and related verifying experiments, was started in the framework of the National Magnetic Confinement Fusion Science Program of China in May 2010.Based on the current or slightly extrapolated ITER fusion science and technology and the well developed fission technology, fusion-driven sub-critical systems design was performed. We put forward the main concept of FFHER blanket with uranium alloy as fuel and water as coolant. The uranium can be natural uranium, LWR spent fuel or depleted uranium. FFHER can increase the utilization rate of uranium in a comparatively simple way to sustain the development of nuclear energy.We study the interaction among the fusion neutron and fuel to achieve larger energy multiplication and tritium sustainable, verify the creditability of physical design by the integral neutron experiments. With the combination research of this program and the following thermal hydraulic design, alloy fuel manufacture and nuclear fuel cycle programs provide the science and technology foundation for the future development of FFHER in China.
