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
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
Conference on Nuclear Training and Education: A Biennial International Forum (CONTE 2023)
February 6–9, 2023
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!
Latest Magazine Issues
Jan 2023
Jul 2022
Latest Journal Issues
Nuclear Science and Engineering
February 2023
Nuclear Technology
Fusion Science and Technology
January 2023
Latest News
Framatome, Ultra Safe partner to manufacture TRISO and FCM fuel
Framatome and Ultra Safe Nuclear announced on January 26 that they intend to form a joint venture to manufacture commercial quantities of tristructural isotropic (TRISO) particles and Ultra Safe’s proprietary fully ceramic microencapsulated (FCM) fuel.
The companies have signed a nonbinding agreement to integrate their resources to bring commercially viable, fourth-generation nuclear fuel to market for Ultra Safe’s micro-modular reactor (MMR) and other advanced reactor designs.
B. W. N. Fitzpatrick, J. W. Davis, A. A. Haasz
Fusion Science and Technology | Volume 73 | Number 4 | May 2018 | Pages 552-558
Technical Note | doi.org/10.1080/15361055.2017.1404346
Articles are hosted by Taylor and Francis Online.
If both carbon and tungsten were to be part of the plasma-facing armor in a future fusion reactor, it is inevitable that carbon co-deposits containing tungsten impurities will form. This work examines the effectiveness of thermo-oxidation in removing hydrogen from W-containing carbon co-deposits. Amorphous deuterated hydrocarbon (a-C:D) films were created with a CD4/Ar direct-current glow discharge and doped with W sputtered from a W mesh in front of the specimen. The W concentration in the specimens ranged from 0 to 35 at. % W/(W + C). The films were oxidized at 350°C, in 2 Torr pure O2 for time increments totaling 8 h. The D content of the films was measured before and at various stages of the oxidation exposure using laser thermal desorption spectroscopy. Essentially all deuterium was removed from films containing very little or no W doping [<0.1% W/(W + C)]. For films with more W [few percent W/(W + C)], oxidation was less effective at removing D. For two specimens with 2.4% and 35% W/(W + C), oxidation was completely ineffective at removing D.