ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
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Division Spotlight
Thermal Hydraulics
The division provides a forum for focused technical dialogue on thermal hydraulic technology in the nuclear industry. Specifically, this will include heat transfer and fluid mechanics involved in the utilization of nuclear energy. It is intended to attract the highest quality of theoretical and experimental work to ANS, including research on basic phenomena and application to nuclear system design.
Meeting Spotlight
2025 ANS Annual Conference
June 15–18, 2025
Chicago, IL|Chicago Marriott 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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Jun 2025
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Nuclear Science and Engineering
August 2025
Nuclear Technology
July 2025
Fusion Science and Technology
Latest News
Hanford proposes “decoupled” approach to remediating former chem lab
Working with the Environmental Protection Agency, the Department of Energy has revised its planned approach to remediating contaminated soil underneath the Chemical Materials Engineering Laboratory (commonly known as the 324 Building) at the Hanford Site in Washington state. The soil, which has been designated the 300-296 waste site, became contaminated as the result of a spill of highly radioactive material in the mid-1980s.
Siyu Yi, Zhouyu Liu, Kunpeng Wang, Wei Shen, Tiejun Zu, Liangzhi Cao, Hongchun Wu
Nuclear Science and Engineering | Volume 199 | Number 1 | April 2025 | Pages S73-S92
Research Article | doi.org/10.1080/00295639.2023.2296239
Articles are hosted by Taylor and Francis Online.
Fully ceramic microencapsulated fuels is a promising potential fuel for pressurized water reactors because of its inherent safety, but double heterogeneity (DH) brings challenges to the neutronic calculation. In this paper, the Hébert model is applied to the global-local resonance method to solve DH, in which the Dancoff factor obtained by the neutron current method is used to transform the coupled fuel pins in the reactor into multiple independent one-dimensional equivalent cylindrical fuel pins. Then, the Hébert model and the hyperfine group method are used to perform the resonance self-shielding calculation in these independent pins. The Sanchez-Pomraning method coupled with the Method of Characteristics (Sanchez-MOC) method is introduced to the two-dimensional/one-dimensional transport module to realize the subsequent whole-core DH transport calculations. The proposed method has been implemented in the high-fidelity neutronics code NECP-X and tested with a set of cases. The results show good agreement with the Monte Carlo reference values for the reactivity and self-shielding cross sections.