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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.
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ANS Student Conference 2025
April 3–5, 2025
Albuquerque, NM|The University of New Mexico
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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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RP3C Community of Practice’s fifth anniversary
In February, the Community of Practice (CoP) webinar series, hosted by the American Nuclear Society Standards Board’s Risk-informed, Performance-based Principles and Policies Committee (RP3C), celebrated its fifth anniversary. Like so many online events, these CoPs brought people together at a time when interacting with others became challenging in early 2020. Since the kickoff CoP, which highlighted the impact that systems engineering has on the design of NuScale’s small modular reactor, the last Friday of most months has featured a new speaker leading a discussion on the use of risk-informed, performance-based (RIPB) thinking in the nuclear industry. Providing a venue to convene for people within ANS and those who found their way online by another route, CoPs are an opportunity for the community to receive answers to their burning questions about the subject at hand. With 50–100 active online participants most months, the conversation is always lively, and knowledge flows freely.
D. D. Lanning
Nuclear Technology | Volume 56 | Number 3 | March 1982 | Pages 565-574
Technical Paper | Nuclear Fuel | doi.org/10.13182/NT82-A32915
Articles are hosted by Taylor and Francis Online.
Thermally induced cracking of the UO2 fuel pellets undoubtedly results in some reduction of the effective fuel thermal conductivity, relative to that for solid UO2. This effect may be approximated by appropriately chosen “crack factors” that reduce the solid-UO2 thermal conductivity. We demonstrate that the assumption of reduced fuel conductivity always results in a reduction of the fuel stored energy that is inferred from fuel centerline temperature data. This reduction occurs whether the crack factors are introduced as simple constants or as functions of radial position within the fuel pellet. If fuel performance computer codes remain “tuned” to the current body of centerline temperature data, those codes will predict lower fuel stored energy when fuel cracking is taken into account regardless of the modeling assumptions invoked. Accounting for fuel cracking should lead to a reduction in calculated peak cladding temperatures obtained in some loss-of-coolant accident simulations.