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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.
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2024 ANS Annual Conference
June 16–19, 2024
Las Vegas, NV|Mandalay Bay Resort and Casino
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
College students help develop waste-measuring device at Hanford
A partnership between Washington River Protection Solutions (WRPS) and Washington State University has resulted in the development of a device to measure radioactive and chemical tank waste at the Hanford Site. WRPS is the contractor at Hanford for the Department of Energy’s Office of Environmental Management.
Zhanlei Wang, Kaigui Zhu, Wei Wang, Yongchu Rao, Xiaoqiu Ye, Yakun Guo, Jing Yan, Chang An Chen
Fusion Science and Technology | Volume 76 | Number 2 | February 2020 | Pages 102-109
Technical Paper | doi.org/10.1080/15361055.2019.1693192
Articles are hosted by Taylor and Francis Online.
Hydrogen isotope behavior in tungsten coated on reduced activation ferritic/martensitic (RAFM) steels such as China low activation martensitic (CLAM) steel has attracted more attention in the fusion engineering research community. This paper is mainly devoted to the investigation of the effect of tungsten coating on deuterium permeation and retention behavior in RAFM steels. The permeability and diffusion coefficients of CLAM, W-CLAM, and W were determined by gas-driven permeation (GDP) tests followed by thermal desorption spectroscopy to measure deuterium retention. It was found that the observed deuterium permeability and diffusivity of the composite W-CLAM specimen was reduced to about ~60% of the pure CLAM steel, whereas deuterium retention increased, evidently owing to the W coating on the surface that caused the slower release of D into the environment and increased of the effective surface area. In addition, a key finding was that the lath martensite–coarsened and more precipitate phase was found, which may be due to the migration of lath interface during the GDP test.