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Aerospace Nuclear Science & Technology
Organized to promote the advancement of knowledge in the use of nuclear science and technologies in the aerospace application. Specialized nuclear-based technologies and applications are needed to advance the state-of-the-art in aerospace design, engineering and operations to explore planetary bodies in our solar system and beyond, plus enhance the safety of air travel, especially high speed air travel. Areas of interest will include but are not limited to the creation of nuclear-based power and propulsion systems, multifunctional materials to protect humans and electronic components from atmospheric, space, and nuclear power system radiation, human factor strategies for the safety and reliable operation of nuclear power and propulsion plants by non-specialized personnel and more.
Meeting Spotlight
2024 ANS Annual Conference
June 16–19, 2024
Las Vegas, NV|Mandalay Bay Resort and Casino
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
NRC updating GEIS rule for new nuclear technology
The Nuclear Regulatory Agency is issuing a proposed generic environmental impact statement (GEIS) for use in reviewing applications for new nuclear reactors.
In an April 17 memo, NRC secretary Carrie Safford wrote that the commission approved NRC staff’s recommendation to publish in the Federal Register a proposed rule amending 10 CFR Part 51, “Environmental Protection Regulations for Domestic Licensing and Related Regulatory Functions.”
Cheol Ho Pyeon, Kota Morioka
Nuclear Science and Engineering | Volume 196 | Number 10 | October 2022 | Pages 1147-1160
Technical Paper | doi.org/10.1080/00295639.2022.2070385
Articles are hosted by Taylor and Francis Online.
Nuclear data–induced uncertainty of criticality is successfully analyzed by combining the eigenvalue calculations, the uncertainty, and the reduction of uncertainty with the use of the KENO-VI code, the TSUNAMI-3D and the TSURFER modules of the SCAL6.2.4 code system, respectively. The comparative study of conventional and revised S(α, β) applications is also conducted by KENO-VI. Notably, the KENO-VI analyses reveal the difference between the experimental and numerical results of criticality and the neutron spectrum dependence of criticality on the H/U ratio in the solid-moderated and solid-reflected cores at the Kyoto University Critical Assembly (KUCA). The difference is identified as the leading cause of uncertainty in the 235U fission spectrum (χ value) through the combined use of the uncertainty and the cross-section adjustment by TSUNAMI-3D and TSURFER, respectively, especially that the highly enriched uranium (HEU) fuel is loaded into the KUCA cores. Also, the neutron spectrum dependence of criticality is attributable to the uncertainty induced by the cross-section data of 235U capture, 27Al elastic scattering, and inelastic scattering reactions in the HEU fuel plate and to the 1H capture reactions in the polyethylene moderator through the TSUNAMI-3D analyses.