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Division Spotlight
Materials Science & Technology
The objectives of MSTD are: promote the advancement of materials science in Nuclear Science Technology; support the multidisciplines which constitute it; encourage research by providing a forum for the presentation, exchange, and documentation of relevant information; promote the interaction and communication among its members; and recognize and reward its members for significant contributions to the field of materials science in nuclear technology.
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
G7 pledges support for nuclear at Italy meeting
The Group of Seven (G7) recommitted its support for nuclear energy in the countries that opt to use it at a Ministerial Meeting on Climate in Italy last month.
In a statement following the April meeting, the group committed to support multilateral efforts to strengthen the resilience of nuclear supply chains, referencing the goal set by 25 countries during last year’s COP28 climate conference in Dubai to triple global nuclear generating capacity by 2050.
Catherine Romano, Ram Venkataraman, David Glasgow, Ben Roach
Nuclear Technology | Volume 208 | Number 11 | November 2022 | Pages 1696-1703
Technical Paper | doi.org/10.1080/00295450.2022.2070353
Articles are hosted by Taylor and Francis Online.
The cross sections of 237Np and 238Np are important for accurate modeling and simulation of 238Pu in the High Flux Isotope Reactor (HFIR) at Oak Ridge National Laboratory (ORNL). Uncertainties in these cross sections can impact the ability to predict and optimize the target design and loading for 238Pu production targets. The effective capture cross section of 237Np in the location of pneumatic tube 1 in HFIR was measured as a first step in the measurement of the 238Np capture and fission cross sections. This paper describes the flux measurements, 237Np experiments, and data analysis of the 237Np capture cross section in HFIR.