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Division Spotlight
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
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
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
TerraPower begins U.K. regulatory approval process
Seattle-based TerraPower signaled its interest this week in building its Natrium small modular reactor in the United Kingdom, the company announced.
TerraPower sent a letter to the U.K.’s Department for Energy Security and Net Zero, formally establishing its intention to enter the U.K. generic design assessment (GDA) process. This is TerraPower’s first step in deployment of its Natrium technology—a 345-MW sodium fast reactor coupled with a molten salt energy storage unit—on the international stage.
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.
