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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.
Meeting Spotlight
International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025)
April 27–30, 2025
Denver, CO|The Westin Denver Downtown
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
Argonne’s METL gears up to test more sodium fast reactor components
Argonne National Laboratory has successfully swapped out an aging cold trap in the sodium test loop called METL (Mechanisms Engineering Test Loop), the Department of Energy announced April 23. The upgrade is the first of its kind in the United States in more than 30 years, according to the DOE, and will help test components and operations for the sodium-cooled fast reactors being developed now.
Shu-Huan Liu, Aqil Hussain, Da Li, Xiaoqiang Guo, Zhuo-Qi Li, Olarewaju Mubashiru Lawal, Jiangkun Yang, Wei Chen
Nuclear Science and Engineering | Volume 191 | Number 1 | July 2018 | Pages 98-103
Technical Paper | doi.org/10.1080/00295639.2018.1450004
Articles are hosted by Taylor and Francis Online.
For evaluating the SiGe heterojunction bipolar transistors (HBTs) performance during and after gamma-ray irradiation, the characteristics of the direct current (dc) gain of the test samples changed with increasing irradiation dose, and collector current injection levels during 60Co gamma irradiation were measured and analyzed. The experimental results of the typical dc and alternating current (ac) electronic parameters before and after irradiation revealed that the base current Ib, the collector current IC, the dc current gain, and the maximum oscillation frequency fmax exhibited degradation. While other electronic parameters including the cut-off frequency fT, the ac current gain |H21|, and output capacitance CBC did not exhibit any significant change compared with those of pre-irradiation. The degradation mechanisms of the typical dc and ac parameters measured in this work were primarily analyzed. The tested results of SiGe HBTs offered some reference data for evaluating the behavior of the test type of device operated in an ionizing radiation environment.