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Division Spotlight
Mathematics & Computation
Division members promote the advancement of mathematical and computational methods for solving problems arising in all disciplines encompassed by the Society. They place particular emphasis on numerical techniques for efficient computer applications to aid in the dissemination, integration, and proper use of computer codes, including preparation of computational benchmark and development of standards for computing practices, and to encourage the development on new computer codes and broaden their use.
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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Jul 2024
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Nuclear Science and Engineering
August 2024
Nuclear Technology
Fusion Science and Technology
Latest News
ARPA-E announces $40 million to develop transmutation technologies for UNF
The Department of Energy’s Advanced Research Projects Agency–Energy (ARPA-E) announced $40 million in funding to develop cutting-edge technologies to enable the transmutation of used nuclear fuel into less-radioactive substances. According to ARPA-E, the new initiative addresses one of the agency’s core goals as outlined by Congress: to provide transformative solutions to improve the management, cleanup, and disposal of radioactive waste and spent nuclear fuel.
Chang An Chen, Xin Zhou, Zhanlei Wang, Bo Wang, Lingbo Liu, Xin Xiang, Yong Yao, Jiangfeng Song
Fusion Science and Technology | Volume 73 | Number 1 | January 2018 | Pages 34-42
Technical Note | doi.org/10.1080/15361055.2017.1368333
Articles are hosted by Taylor and Francis Online.
The Chinese (CN) Helium Cooled Ceramic Breeding (HCCB) Test Blanket Module (TBM) (CN HCCB TBM) set with its ancillary systems will demonstrate the feasibility of in-pile tritium production/breeding in ITER for fuel self-sufficiency and high-grade fusion energy conversion to heat and extraction for a future magnetic confined fusion reactor. Tritium release in some major components of the recently designed TBM systems through permeation and natural leakage was estimated with simple diffusion/permeation and leak rate calculation models. Results showed that because of the tritium permeation barrier coating for tritium confinement in some tritium containments, total tritium release to the environment by permeation in the CN HCCB TBM and ancillary systems will be kept well below 2 Ci/full-power day. However, tritium release through natural leakage from components can be neglected compared with permeation. Equipped with ITER tritium safety guarantee facilities like the tritium monitoring and detritiation systems, tritium release from CN TBM system–caused radiological safety issues will be well controlled.