ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
Explore the many uses for nuclear science and its impact on energy, the environment, healthcare, food, and more.
Isotopes & Radiation
Members are devoted to applying nuclear science and engineering technologies involving isotopes, radiation applications, and associated equipment in scientific research, development, and industrial processes. Their interests lie primarily in education, industrial uses, biology, medicine, and health physics. Division committees include Analytical Applications of Isotopes and Radiation, Biology and Medicine, Radiation Applications, Radiation Sources and Detection, and Thermal Power Sources.
2024 ANS Annual Conference
June 16–19, 2024
Las Vegas, NV|Mandalay Bay Resort and Casino
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 Science and Engineering
Fusion Science and Technology
Study indicates pilot facility could significantly reduce waste volumes
Waste disposal start-up Deep Isolation and fusion tech company SHINE Technologies have announced the completion of a collaborative study assessing the costs of disposing of radioactive byproducts from a pilot spent nuclear fuel recycling facility.
Qian Zhang, Liang Liang, Qiang Zhao, Zhijian Zhang, Hongchun Wu, Liangzhi Cao
Nuclear Science and Engineering | Volume 194 | Number 3 | March 2020 | Pages 232-247
Technical Note | doi.org/10.1080/00295639.2019.1664146
Articles are hosted by Taylor and Francis Online.
The Embedded Self-Shielding Method (ESSM) coupled with the heterogeneous Resonance Integral tables and the Enhanced Neutron Current Method (ENCM) with equivalent Dancoff factor are reviewed and reformulated to a unified framework by incorporating the ultra-fine-group slowing-down calculation on two-dimensional square pin cell problems. The comparison between the two approaches on the resonance self-shielding calculation of irregular fuel lattices shows that the reformulated ESSM approach will bring errors to the cross-section prediction of fuel pins in the irregular lattice, especially when the moderator density is low. Also, the reformulated ENCM approach is more stable for different configurations. Further numerical tests show that the scalar flux calculated by the ESSM approach is affected by the global neutron balance across the fuel lattice and ESSM is more sensitive to the error brought by the enforced equivalence.