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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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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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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.
John F. Carew, Kai Hu
Nuclear Science and Engineering | Volume 140 | Number 1 | January 2002 | Pages 70-85
Technical Paper | doi.org/10.13182/NSE02-A2245
Articles are hosted by Taylor and Francis Online.
Pressure vessel surveillance and benchmark dosimetry measurements are used to determine the effects of the plant-specific as-built core/internals/vessel materials and geometry on the vessel fluence. In several recent applications, uncertainties in these measurements and their interpretation have prevented the use of the dosimetry measurements in the benchmarking of the vessel fluence calculations. In this analysis, the uncertainties having a significant effect on the measurement-to-calculation comparisons used in the benchmarking are identified and evaluated, and the effect of these uncertainties on the >1-MeV vessel fluence derived from the measurements is determined.The vessel >1-MeV fluence is determined by a weighted sum of the response from a set of 63Cu, 46Ti, 58Ni, 54Fe, 238U, and 237Np fast neutron dosimeters located on the outer wall of the thermal shield, vessel inner wall and/or in the cavity outside the vessel. The uncertainty estimates assume a well-maintained and calibrated measurement system and the use of state-of-the-art methods for interpreting the measurements. In the case where the effects of the individual uncertainties on the fluence are correlated, the specific correlation is calculated and properly included in the fluence uncertainty estimate.The uncertainty in the >1-MeV fluence inferred from dosimeters located on the outer wall of the thermal shield or on the inner wall of the vessel ranges from 11 to 15% (1) depending on the specific type of fast neutron dosimeter. The uncertainty in the >1-MeV fluence inferred from dosimeters located in the cavity is significantly higher, due to the uncertainty in the iron cross section and the resulting uncertainty in the extrapolation to the vessel inner wall, and ranges from 19 to 23% depending on the type of dosimeter. These vessel fluence uncertainties are substantially larger than the uncertainty in the measured dosimeter reaction rates of 6 to 8% from which the fluence was derived.