Results 11 to 20 of about 935 (164)
Nuclear Materials and Energy, 2021 The small punch test is evaluated as a screening procedure for irradiation embrittlement of reactor pressure vessel steels. In particular, the correlation between ductile-to-brittle transition temperatures obtained from this small specimen test technique
E. Altstadt, F. Bergner, M. Houska
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Energies, 2022 This study discusses the potential corrosion of boiler materials in chemical-looping combustion (CLC) of biomass. The CLC of biomass has the potential to negative CO2 emission in heat and power production.
Jan-Erik Eriksson +4 more
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Current state and prospect on the development of advanced nuclear fuel system materials: A review
Materials Reports: Energy, 2021 The intricate balance between reactor economics and safety necessitates the emergence of new and advanced nuclear systems and, very importantly, advanced materials, which can overcome current shortcomings and bring about more economic nuclear systems ...
Di Yun +7 more
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Materials Research Express, 2023 The core problem of low energy consumption anaerobic fermentation reactor is that the reactor can make reasonable and effective use of energy from two aspects of quantity and quality, so as to ensure the anaerobic fermentation performance of the reactor ...
Kun Wang, Chun Fu, Xu Chen
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Research Progress on Ferritic/Martensitic Steels for Integrated Fast Reactor Fuel Cladding [PDF]
TeshugangThe integrated fast reactors use metallic fuel， with fuel cladding operating at temperatures ranging from 350 ℃ to 630 ℃ and a service lifespan exceeding 50 000 hours.
Feng Wei +7 more
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EPJ Nuclear Sciences & Technologies, 2022 The goal of the ORIENT-NM action is to produce a single European strategic vision on research and innovation concerning nuclear materials in the EU, serving all reactor generations and nuclear systems.
Malerba Lorenzo +3 more
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Machine learning predictions of irradiation embrittlement in reactor pressure vessel steels
npj Computational Materials, 2022 Irradiation increases the yield stress and embrittles light water reactor (LWR) pressure vessel steels. In this study, we demonstrate some of the potential benefits and risks of using machine learning models to predict irradiation hardening extrapolated ...
Yu-chen Liu +20 more
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Selection criteria for fusion reactor structures
Journal of Thermal Engineering, 2019 Fusion energy is the ultimate energy to cover Mankind’s energy needs forever. However, taming the fusion energy is the greatest technological challenge the humanity is facing.
Sümer ŞAHİN
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Alloying of steel and graphite by hydrogen in nuclear reactor [PDF]
IOP Conference Series: Materials Science and Engineering, 2017 In traditional power engineering hydrogen may be one of the first primary source of equipment damage. This problem has high actuality for both nuclear and thermonuclear power engineering. Study of radiation-hydrogen embrittlement of the steel raises the question concerning the unknown source of hydrogen in reactors.
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γ→α’ Martensitic Transformation in the Reactor Steels Under Irradiation and Deformation
Medžiagotyra, 2014 Complex studies of the 12Cr18Ni10Ti and Cr15Mn14 reactor steels in the initial, deformed states, and after irradiation with the and WC+ heavy ions were conducted.
Darya ALONTSEVA +3 more
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