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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
Nuclear Energy Conference & Expo (NECX)
September 8–11, 2025
Atlanta, GA|Atlanta Marriott Marquis
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
Supreme Court rules against Texas in interim storage case
The Supreme Court voted 6–3 against Texas and a group of landowners today in a case involving the Nuclear Regulatory Commission’s licensing of a consolidated interim storage facility for spent nuclear fuel, reversing a decision by the 5th Circuit Court of Appeals to grant the state and landowners Fasken Land and Minerals (Fasken) standing to challenge the license.
E. Duncombe, C. M. Friedrich, W. H. Guilinger
Nuclear Technology | Volume 12 | Number 2 | October 1971 | Pages 194-208
Technical Paper | Fuel | doi.org/10.13182/NT71-A31027
Articles are hosted by Taylor and Francis Online.
The prediction and analysis of fuel rod performance in the CYGRO-3 model is an extended version of the earlier models CYGRO-1 and CYGRO-2 arising from the LWBR development program. The model assumes that circumferential and axial variations in conditions are small compared with radial variations. Fuel and clad are considered as a set of interacting concentric ring elements. Time-dependent values of temperatures, stresses, and deformations (elastic and creep effects) are calculated as the response to a history of coolant water conditions and of rod power and neutron flux. Provision is made to calculate effects of swelling due to pore growth and of thermally induced pore migration in the fuel. An approximation to fuel property changes as a result of cracking are introduced via changes in the elastic relationships. Frictional interaction between fuel and clad when the latter is in the collapsed condition is provided. Forces introduced by fuel rod supports are included. A first-order calculation of straightening moments introduced by circumferential variation in power can also be performed.
