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Division Spotlight
Operations & Power
Members focus on the dissemination of knowledge and information in the area of power reactors with particular application to the production of electric power and process heat. The division sponsors meetings on the coverage of applied nuclear science and engineering as related to power plants, non-power reactors, and other nuclear facilities. It encourages and assists with the dissemination of knowledge pertinent to the safe and efficient operation of nuclear facilities through professional staff development, information exchange, and supporting the generation of viable solutions to current issues.
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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Nuclear Technology
Fusion Science and Technology
May 2025
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.
Haifei Deng, Desheng Cheng, Weihua Wang, Kaiping Li, Bo Shi, Jinhong Yang
Fusion Science and Technology | Volume 72 | Number 2 | August 2017 | Pages 188-198
Technical Note | doi.org/10.1080/15361055.2017.1320495
Articles are hosted by Taylor and Francis Online.
The Helium (He) gas Cooled Ceramic Breeder (HCCB) test blanket module (TBM) is the primary option of the Chinese TBM program. In order to enhance the cooling ability of the first wall (FW) of the HCCB TBM and reduce the circulation power, a binary mixtures gas of He gas and additive CO2 deserves to be another option for the coolant of the blanket, based on high temperature gas-cooled reactors which are a generation-IV fission reactor concept, when it is reported that forced convective heat transfer can be enhanced by means of binary mixing with unreactive gas (e.g., CO2, molecular weight 44). This technique can significantly enhance the plant’s overall efficiency and reduce the cost of electricity. In order to evaluate the cooling performance of the He/CO2 binary mixtures gas and its circulation power in the FW of the HCCB TBM, a three-dimensional computational fluid dynamics (CFD) numerical simulation, combined experimental research method is applied. The results reveal that under the condition of the cooling requirements of the FW (e. g., maximum temperature, radial temperature gradient) similar to the pure He gas, the flow velocity and circulation power of the He/CO2 binary mixtures gas (mole fraction 0.4) are reduced by 70% and 87%, respectively. It implies that the thermal efficiency of a He-cooled blanket system can be fairly enhanced by means of this technique. In the near future experiment plan, it should be tested to validate the correlative cooling scheme of the HCCB TBM, in which the pure He gas and He/CO2 binary mixtures gas are used as coolant, respectively, at our High-Pressure Helium-Cooled Loop facility. The CFD numerical results will be selected as the reference for the experiments. A new approach may be provided for cooling the high heat flux components of a fusion reactor.