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Division Spotlight
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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Nuclear Energy Conference & Expo (NECX)
September 8–11, 2025
Atlanta, GA|Atlanta Marriott Marquis
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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Fusion Science and Technology
Latest News
DOE opens pilot program to authorize test reactors outside national labs
Details of the plan to test new reactor concepts under the Department of Energy’s authority but outside national laboratory boundaries—first outlined in one of the four executive orders on nuclear energy released on May 23—were just released in a request for applications issued by the DOE.
F. Bachelet, E. Bourgeois, R. Collier, E. Fleury, O. Legaie, B. Reneaume, M. Theobald
Fusion Science and Technology | Volume 60 | Number 3 | October 2011 | Pages 889-892
ICF | Proceedings of the Ninth International Conference on Tritium Science and Technology | doi.org/10.13182/FST11-A12560
Articles are hosted by Taylor and Francis Online.
As part of the French Inertial Confinement Fusion (ICF) program, CEA has developped Cryogenic Target Assemblies (CTAs) for the Laser MegaJoule (LMJ). These targets are filled by permeation with high pressure deuterium-tritium gas mixture. The evolution of the materials physical properties, particularly organic ones (PI and CHx), which compose the target is unknown in these hard conditions. The polyimide and CHx membranes permeation was studied in this context. The hydrogen and helium permeation parameters are unaltered for polyimide membrane after tritium ageing in the 20 K-300 K temperature range:KHe = 3.10-14 exp(-16040/RT) mol.m-1.s-1.Pa-1KH2 = 2.10-14 exp(-16950/RT) mol.m-1.s-1.Pa-1First results for the CHx hydrogen permeation parameters without ageing tritium have been obtained:KH2 = 7.10-13 exp(-10550/RT) mol.m-1.s-1.Pa-1New CHx permeation results after tritium ageing are shortly waited.