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Radiation Protection & Shielding
The Radiation Protection and Shielding Division is developing and promoting radiation protection and shielding aspects of nuclear science and technology — including interaction of nuclear radiation with materials and biological systems, instruments and techniques for the measurement of nuclear radiation fields, and radiation shield design and evaluation.
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ANS Student Conference 2025
April 3–5, 2025
Albuquerque, NM|The University of New Mexico
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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
Norway’s Halden reactor takes first step toward decommissioning
The government of Norway has granted the transfer of the Halden research reactor from the Institute for Energy Technology (IFE) to the state agency Norwegian Nuclear Decommissioning (NND). The 25-MWt Halden boiling water reactor operated from 1958 to 2018 and was used in the research of nuclear fuel, reactor internals, plant procedures and monitoring, and human factors.
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.