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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
2022 ANS Annual Meeting
June 12–16, 2022
Anaheim, CA|Anaheim Hilton
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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Nuclear Science and Engineering
June 2022
Nuclear Technology
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Latest News
A passionate call to save Diablo Canyon
In a recent opinion piece for the San Luis Obispo Tribune, Heather Hoff describes her conversion from nuclear energy skeptic to advocate and lays out the case for keeping the Diablo Canyon nuclear power plant open beyond its planned closure in 2025.
Hoff, who is an operations procedure writer at Diablo Canyon, tells how she spent years "excessively and sometimes annoyingly" investigating her concerns about the safety of nuclear after she was first hired at Diablo Canyon. She adds that she almost quit her job after the Fukushima accident until realizing that many concerns about that event were triggered by "fear of nuclear, rather than nuclear itself.”
Hangbok Choi
Nuclear Technology | Volume 204 | Number 3 | December 2018 | Pages 283-298
Technical Paper | dx.doi.org/10.1080/00295450.2018.1484646
Articles are hosted by Taylor and Francis Online.
The performance of uranium-plutonium mixed carbide fuel was analyzed based on experimental data produced from the Japan Research Reactor No. 2, the Japan Materials Testing Reactor, and the Fast Flux Test Facility irradiation tests during 1983 to 1992. The analysis includes a review of earlier fuel irradiation test results, material property data, and physics models, and a simulation by a finite element method fuel performance code FEMAXI-6GA to predict the historic results. The simulation results were compared to the measured fission gas release, fuel swelling, and dimensional change of the cladding. The simulation results are reasonably consistent with the measurement. However, a few differences between the simulations and measurements were encountered, which are attributed to the lack of detailed experimental conditions, characteristics of fuel materials, material property data, and physics models. Based on sensitivity analyses of the results to experimental conditions and material property data, it is recommended to develop an experimental plan for the systematic measurements of thermal conductivity, including the effect of porosity, impurities, and stoichiometry, fission gas diffusion, and irradiation-induced swelling and densification, supplemented by advanced modeling and simulation techniques to support advanced fuel development in a cost-effective way.
