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Reactor Physics
The division's objectives are to promote the advancement of knowledge and understanding of the fundamental physical phenomena characterizing nuclear reactors and other nuclear systems. The division encourages research and disseminates information through meetings and publications. Areas of technical interest include nuclear data, particle interactions and transport, reactor and nuclear systems analysis, methods, design, validation and operating experience and standards. The Wigner Award heads the awards program.
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2024 ANS Annual Conference
June 16–19, 2024
Las Vegas, NV|Mandalay Bay Resort and Casino
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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.
Colby Jensen, Austin Fleming
Nuclear Technology | Volume 205 | Number 10 | October 2019 | Pages 1354-1368
Technical Paper | doi.org/10.1080/00295450.2019.1627123
Articles are hosted by Taylor and Francis Online.
A fuel safety research program centered on in-pile transient testing experiments is being developed to support assessment and qualification of advanced nuclear fuel systems using the recently restarted Transient Reactor Test (TREAT) facility at the Idaho National Laboratory. While resumption of transient testing at TREAT is crucial to enable these programs, full recovery and cutting-edge transient testing capability also require a well-coordinated and innovative instrumentation development and qualification program to support near-term and future objectives. This paper summarizes the experimental approach of transient testing to focus on measuring the response of nuclear fuel to off-normal (or power-cooling mismatch) conditions for modern and advanced reactor environments requiring capabilities extending over wide measurement and environment conditions. It also highlights unique attributes of transient testing of importance to in-pile instruments including relatively low total neutron fluence, high gamma heating, and the need for a well-defined and possibly short time response. Historical approaches to instrumentation for transient testing are also reviewed to provide context to the modern instrument strategy. The paper details the instrumentation needs of modern transient testing. It also summarizes several ongoing research and development (R&D) activities that support the development of state-of-the-art and advanced measurement technologies that will provide a baseline capability for light water reactor and sodium-cooled fast reactor (SFR) experiment objectives. This R&D will extend to other advanced reactor needs and advanced sensing technology opportunities. Examples of specific sensors planned for near-term deployment with ongoing development include prompt response self-powered neutron detectors, miniature fission chambers, optical fiber–coupled infrared pyrometers, cladding surface thermocouples, electrical impedance–based boiling detectors, and linear variable differential transformer–based sensors for fuel elongation and pressure measurement.