ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
Explore the many uses for nuclear science and its impact on energy, the environment, healthcare, food, and more.
Division Spotlight
Fuel Cycle & Waste Management
Devoted to all aspects of the nuclear fuel cycle including waste management, worldwide. Division specific areas of interest and involvement include uranium conversion and enrichment; fuel fabrication, management (in-core and ex-core) and recycle; transportation; safeguards; high-level, low-level and mixed waste management and disposal; public policy and program management; decontamination and decommissioning environmental restoration; and excess weapons materials disposition.
Meeting Spotlight
Conference on Nuclear Training and Education: A Biennial International Forum (CONTE 2025)
February 3–6, 2025
Amelia Island, FL|Omni Amelia Island Resort
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
Christmas Night
Twas the night before Christmas when all through the houseNo electrons were flowing through even my mouse.
All devices were plugged in by the chimney with careWith the hope that St. Nikola Tesla would share.
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.