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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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2025 ANS Annual Conference
June 15–18, 2025
Chicago, IL|Chicago Marriott Downtown
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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Zaporizhzhia ‘extremely fragile’ relying on single off-site power line, IAEA warns
Europe’s largest nuclear power plant has just one remaining power line for essential nuclear safety and security functions, compared with its original 10 functional lines before the military conflict with Russia, warned Rafael Mariano Grossi, director general of the International Atomic Energy Agency.
M. E. Dunn, B. Basoglu, C. L. Bentley, C. Haught, M. J. Plaster, A. D. Wilkinson, T. Yamamoto, H. L. Dodds
Nuclear Technology | Volume 111 | Number 2 | August 1995 | Pages 183-196
Technical Paper | Nuclear Criticality Safety Special / Fission Reactor | doi.org/10.13182/NT95-A35129
Articles are hosted by Taylor and Francis Online.
The multigroup Monte Carlo code KENO V.a and the 238- and 44-energy-group ENDF/B-V cross-section libraries were validated for 233U systems. Fifty-one critical experiments involving 233UO2(NO3)2, 233UO2F2, or 233U metal were selected for the validation. The H/233U ratios for the experiments range from 0 to 1986. Each experiment was modeled with KENO V.a, and the effective multiplication factor keff was calculated for each system using the 44- and 238-group ENDF/B-V, the 27- and 218-group ENDF/B-IV, and the 16-group Hansen-Roach cross-section libraries. The mean calculated keff for all experiments using the 44- and 238-group libraries is 1.0090 ± 0.0021 and 1.0064 ± 0.0020, respectively. For comparison, the mean calculated keff using the 27-, 218-, and 16-group libraries is 1.0142 ± 0.0038, 1.0125 ± 0.0038, and 0.9991 ± 0.0019, respectively. In general, an improvement exists in the agreement between the calculated keff’s and the experimental results (i.e., keff= 1.0) obtained with the newer ENDF/B-V libraries relative to ENDF/B-IV.
