Results 31 to 40 of about 248 (163)
Improving Accident Tolerance of Nuclear Fuel with Coated Mo-alloy Cladding
Nuclear Engineering and Technology, 2016 In severe loss of coolant accidents (LOCA), similar to those experienced at Fukushima Daiichi and Three Mile Island Unit 1, the zirconium alloy fuel cladding materials are rapidly heated due to nuclear decay heating and rapid exothermic oxidation of ...
Bo Cheng, Young-Jin Kim, Peter Chou
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He jishu, 2021 BackgroundLarge-grained UO2 pellet and coated zirconium cladding are the most practical fuel pellet and cladding material scheme for accident tolerant fuel (ATF) solutions, which are expected to be commercially available in the next few years.
YOU Yan, GONG Xin, LI Cong
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Thermo, 2021 Since the nuclear accident at Fukushima Daiichi Nuclear Power Station in 2011, a considerable number of studies have been conducted to develop accident tolerant fuel (ATF) claddings for safety enhancement of light water reactors. Among many potential ATF
Hai V. Pham +2 more
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Design Rules for Carboborothermic Reduction Synthesis of High Uranium Density UB4–UBC Composites
Journal of the American Ceramic Society, Volume 109, Issue 5, May 2026.ABSTRACT Uranium borides are promising candidate fuel forms for use in advanced nuclear reactors due to their high thermal conductivity and potential for dual use as both fuel and burnable absorber. In this work, uranium tetraboride (UB4${\rm UB}_4$) and uranium monoboroncarbide (UBC) composite were synthesized by using industrially scalable ...
Riley Moeykens +4 more
wiley +1 more source
International Journal of Energy Research, Volume 2026, Issue 1, 2026.A numerical framework leveraging finite element analysis is established to examine the thermomechanical behavior and burst safety of a novel accident‐tolerant fuel (ATF) cladding design. This design incorporates a thin niobium (Nb) liner positioned between two layers of silicon carbide ceramic matrix composites (SiC‐CMC).
Jabir Ubaid +4 more
wiley +1 more source
Frontiers in Energy Research, 2021 FCM fuel which microencapsulated TRISO particles in SiC matrix is a promising ATF (accident tolerant fuel) candidate fuel designed to replace the traditional pellet-cladding fuel rod. In order to predict the in-pile behavior of FCM fuel accurately and to
Tang Changbing +4 more
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Low‐Activation Compositionally Complex Alloys for Advanced Nuclear Applications—A Review
Advanced Engineering Materials, Volume 27, Issue 17, September 2025.Low‐activation compositionally complex alloys (LACCAs) are advanced metallic materials primarily composed of low‐activation elements, offering advantages such as rapid compliance with operational standards and safe recyclability. This review highlights their potential for extreme high‐temperature irradiation environments as structural materials for ...
Yangfan Wang +8 more
wiley +1 more source
Energy Science &Engineering, Volume 13, Issue 2, Page 728-741, February 2025.A computational framework is developed to evaluate the thermo‐mechanical performance of APR1400 fuel rods with FeCrAl claddings under normal and LOCA conditions. Results show that reducing the pellet‐cladding gap enhances heat conduction and burst safety, while an 80% strength enhancement in FeCrAl claddings improves burst safety by up to 80%.
Jabir Ubaid +4 more
wiley +1 more source
Alexandria Engineering JournalAfter the Fukushima-Daiichi event, there has been notable progress in developing accident-tolerant fuel (ATF) cladding designs to improve light-water reactor (LWR) safety features. In this regard, the Zirconium alloy (Zircaloy) has significant advantages
Ghadeer Hegab Mohamed +5 more
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Frontiers in Energy Research, 2021 Fully ceramic microencapsulated fuel (FCM) is employed in the supercritical CO2 (S-CO2)-cooled reactor as accident tolerant fuel (ATF). Although the fuel and the assembly substrate contain SiC, the assembly cannot be sufficiently moderated due to the ...
Di Lu +4 more
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