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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
ANS Student Conference 2025
April 3–5, 2025
Albuquerque, NM|The University of New Mexico
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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April 2025
Latest News
Nuclear News 40 Under 40 discuss the future of nuclear
Seven members of the inaugural Nuclear News 40 Under 40 came together on March 4 to discuss the current state of nuclear energy and what the future might hold for science, industry, and the public in terms of nuclear development.
To hear more insights from this talented group of young professionals, watch the “40 Under 40 Roundtable: Perspectives from Nuclear’s Rising Stars” on the ANS website.
Lingrui Li, Zijia Zhao, Yanyun Ma, Zhe Ma, Jiang Lai, Yunliang Zhu
Fusion Science and Technology | Volume 78 | Number 6 | August 2022 | Pages 475-489
Technical Paper | doi.org/10.1080/15361055.2022.2049121
Articles are hosted by Taylor and Francis Online.
With the development of magnetic confinement fusion (MCF), it has become feasible for fusion energy to solve the future energy crisis. High-energy neutrons are produced during the fusion reaction. Neutron shielding and the tritium breeding ratio in MCF require a neutron source of high precision. In traditional methods, the neutron source is supposed to be isotropic. However, the double-differential cross sections for nuclear fusion given in the ENDF/B-VI database make it possible to calculate the neutron direction distribution in deuterium-tritium (D-T) plasma. In this study, a Maxwellian reactivity rate database is obtained by extracting double-differential cross-section data from the ENDF/B-VI database and then revising it. Monte Carlo and discrete ordinate methods are used to simulate transportation and fusion in D-T plasma and obtain the angular distribution of the neutron generation rate. The results of a preliminary numerical simulation in a simple model tell us that the difference between anisotropy and isotropy can reach an average of 4.6%. A temperature-corrected double-differential cross-section database and a numerical simulation method are developed to calculate the angular distribution of the neutron generation rate.