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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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International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025)
April 27–30, 2025
Denver, CO|The Westin Denver Downtown
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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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Argonne’s METL gears up to test more sodium fast reactor components
Argonne National Laboratory has successfully swapped out an aging cold trap in the sodium test loop called METL (Mechanisms Engineering Test Loop), the Department of Energy announced April 23. The upgrade is the first of its kind in the United States in more than 30 years, according to the DOE, and will help test components and operations for the sodium-cooled fast reactors being developed now.
J. E. Till, H. R. Meyer, L. E. Morse, W. D. Bond, E. S. Bomar, V. J. Tennery
Nuclear Technology | Volume 48 | Number 1 | April 1980 | Pages 54-62
Technical Paper | Fuel | doi.org/10.13182/NT80-A32447
Articles are hosted by Taylor and Francis Online.
The radiological dose associated with the use of (Th,U) carbide fuel in the core and thorium carbide in the blankets of a fast breeder reactor (FBR) has been investigated. Analysis of the estimated dose due to reprocessing spent (Th,U) carbide fuel allows a direct comparison between the radiological consequences of the use of this fuel versus other candidates such as (U,Pu) oxide or carbide. This study employed methodologies similar to those used in previous assessments of advanced FBR fuels. Results are calculated in terms of the potential dose commitment to a maximally exposed individual and to the general population living within 80 km of the operating plant. Tritium is found to be the principal contributor to dose commitment to total body for both the individual and the general population. Also contributing significantly to the dose are 14C, 137Cs, and 232U. Maximum individual dose is 3.1 mrem (total body), while dose to total body for the population is found to be 39 man-rem per 50 GW(electric)-yr. A parametric analysis was conducted to determine the effect on dose of varying the 232U content from 10 to 5000 ppm. The study showed that at 5000 ppm 232U/U and with no additional modification in the effluent treatment system, dose to the total body of a maximally exposed individual is increased by a factor of 1.4, from 2.8 to 4.0 mrem. Another analysis was conducted to determine the effect of increasing the reprocessing plant confinement factor for 3H from 1 to 100. This exercise was prompted by recent experimental data suggesting that greater quantities of 3H may be produced in FBRs than were previously anticipated. It was found that a confinement factor of 100 for 3H reduces the dose to total body (for individuals and populations) by a factor of ∼3. It is concluded that reprocessing of (Th,U) carbide fuel for FBRs should meet applicable standards in terms of radiological impact during routine operations. In this context, little difference is seen to exist between the (Th,U) carbide fuels and earlier results for (U,Pu) oxide and carbide fuels,
