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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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Smarter waste strategies: Helping deliver on the promise of advanced nuclear
At COP28, held in Dubai in 2023, a clear consensus emerged: Nuclear energy must be a cornerstone of the global clean energy transition. With electricity demand projected to soar as we decarbonize not just power but also industry, transport, and heat, the case for new nuclear is compelling. More than 20 countries committed to tripling global nuclear capacity by 2050. In the United States alone, the Department of Energy forecasts that the country’s current nuclear capacity could more than triple, adding 200 GW of new nuclear to the existing 95 GW by mid-century.
Mahmoud Z. Youssef, Anil Kumar, Mohamed A. Abdou, Chikara Konno, Fujio Maekawa, Yujiro Ikeda
Fusion Science and Technology | Volume 34 | Number 3 | November 1998 | Pages 953-963
Neutronics Experiments and Analysis (Poster Session) | doi.org/10.13182/FST98-A11963736
Articles are hosted by Taylor and Francis Online.
As part of a collaboration with Japan, the U.S. participated in several fusion integral experiments that simulate the design features of the shielding blanket of the International Thermonuclear Experimental Reactor, ITER. The purpose of these efforts is to resolve the critical issues associated with the neutronics R&D tasks of ITER, among which is the adequacy of the newly developed FENDL-1 database. For that purpose, JAERI has constructed a cylindrical test assembly of dimension 1.2 D × 1.2 L m and made of front multi-layers of SS316 and water with an embedded smaller zone consists of multi-layers of super conducting magnet (SCM) stimulant and SS316. Measured parameters, covering the neutron energy range from 14 MeV down to thermal energy, were taken inside the SS316 and the SCM layers at 9 locations up to a depth of 91.4 cm. In one experiment (Assembly#l), a 1.27 cm B4C + 3.8 cm Pb layer was added in front of the SCM multi-layer zone. This layer is not included in Assembly#2. As in previous experiments, the 14 MeV source is housed inside a source reflector can (20 cm-thick) and located at a distance of 30 cm from the assembly. The U.S. analysis reported here was performed with 175n-42g FENDL/MG-1.0 (multigroup) as well as ENDF/B-VI data using the DORT 2-D code. Analysis was also performed with the Monte Carlo (MC) continuous energy data, FENDL/MC-1.0. The calculated parameters were compared to the following measured data: (a) neutron spectrum below 2 MeV, (b) foil activation rates such as Nb-93(n,2n)Nb-93m, Al-27(n,α)Na-24, In-115(n,n)In-115m, Au-197(n, γ)Au-198, and B-10(n,α)Li-7, (c) fission rate U-235(n,f) and U-238(n,f). (d) gamma-ray spectrum, and (e) gamma-ray heating rate.
