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Division Spotlight
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.
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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Fusion Science and Technology
Latest News
Norway’s Halden reactor takes first step toward decommissioning
The government of Norway has granted the transfer of the Halden research reactor from the Institute for Energy Technology (IFE) to the state agency Norwegian Nuclear Decommissioning (NND). The 25-MWt Halden boiling water reactor operated from 1958 to 2018 and was used in the research of nuclear fuel, reactor internals, plant procedures and monitoring, and human factors.
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.