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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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International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025)
April 27–30, 2025
Denver, CO|The Westin Denver 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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Latest News
Judge temporarily blocks DOE’s move to slash university research funding
A group of universities led by the American Association of Universities (AAU) acted swiftly to oppose a policy action by the Department of Energy that would cut the funds it pays to universities for the indirect costs of research under DOE grants. The group filed suit Monday, April 14, challenging a what it termed a “flagrantly unlawful action” that could “devastate scientific research at America’s universities.”
By Wednesday, the U.S. District Court judge hearing the case issued a temporary restraining order effective nationwide, preventing the DOE from implementing the policy or terminating any existing grants.
H.Yoshida, M.Taniguchi, K.Yokoyama, Y.Hirohata, M.Akiba, T.Hino
Fusion Science and Technology | Volume 41 | Number 3 | May 2002 | Pages 943-947
Material Interaction and Permeation | Proceedings of the Sixth International Conference on Tritium Science and Technology Tsukuba, Japan November 12-16, 2001 | doi.org/10.13182/FST02-A22724
Articles are hosted by Taylor and Francis Online.
Tritium retention of carbon dust co-deposited with fuel hydrogen is large, and then it is required to evaluate the tritium inventory as a safety issue of ITER. Several species of co-deposited carbon dust were prepared by D2 arc discharge with carbon electrodes. The dependence of D2 gas pressure on the retained deuterium amount of the co-deposited dust was investigated. The structure and the surface morphology were also examined. The retained deuterium amount increased with the discharge gas pressure. The deuterium concentrations of the co-deposited carbon dust samples prepared at 1.3 Pa and 6.8 Pa were 0.12 and 0.3 in the atomic ratio, D/C, respectively. No clear dependence of the substrate temperature on retained deuterium amount was observed, perhaps due to the coarse temperature control. In the environment of gas pressure in ITER, approximately 1 Pa, the tritium concentration is estimated approximately T/C ≈ 0.06, which is several times smaller than the value estimated so far, T/C ≈ 0.2.