Results 61 to 70 of about 1,923 (185)

Creep performance of fuel cladding

, 2016
The understanding of the creep behavior of nuclear fuel claddings is essential to predict safely and reliably the thermal performance and mechanical integrity of fuel rods. Fuel cladding tubes experience a range of changing conditions during their reactor life, further complicating the analysis.
Tulkki, Ville, Ikonen, Timo, Moilanen, Pekka, Rantala, Juhani, Huotilainen, Santtu, Ehrnstén, Ulla, Pohja, Rami   +7 more
openaire   +4 more sources

In Situ Preparation of Ti2Ni/NiTi Dual‐Phase Alloy With High Wear Resistance and Damping Performance by Additive Manufacturing

Rare Metals, Volume 45, Issue 8, August 2026.
ABSTRACT Many metallic components are frequently subjected to coupled environments of friction and vibration, stemming from interfacial contact and relative motion between mating parts or external stimuli. Consequently, it is imperative for these components to exhibit a synergy of high wear resistance and superior damping properties.
Ze Pu, Jingjing Mao, Long Cui, Dong Du, Changyong Chen, Hao Jiang, Liying Sun, Xiebin Wang, Zibin Chen, Kangcheung Chan, Baohua Chang, Ming Li, Chengrui Zhang   +12 more
wiley   +1 more source

EXTRUSION CLADDING OF URANIUM FUEL PLATES [PDF]

, 1958
Two methods for extrusion cladding were investigated and evaluated. In the coaxial method, the component parts of the extrusion assembly are concentric, and the fuel plate moves in the same direction as the hydraulicpress ram. In the right-angle method, the fuel-plate metion is perpendicular to that of the ram.
Fiorentino, R. J., Drennen, D. C., Slunder, C. J., Hall, A. M.   +3 more
openaire   +2 more sources

Reconfigurable Nonlinear Activation Using Low‐Loss Ge3Sb2Te15 for Photonic Neural Networks

Nanophotonics, Volume 15, Issue 14, 27 July 2026.
Composition‐engineered, low‐loss Ge3Sb2Te15 is identified from high‐throughput GST spreads and integrated with silicon microring resonators. Multistate optical programming produces tunable resonance responses and diverse fixed‐wavelength optical nonlinear activation functions, connecting phase‐change material discovery with programmable nanophotonic ...
Yida Dong, Zhuoxuan Zhu, Yifan Zhu, Lichong Zhao, Lei Lei, Zihan Geng, Yida Li, X.‐D. Xiang, Heshan Yu, Mei Shen   +9 more
wiley   +1 more source

POST CRITICAL HEAT TRANSFER AND FUEL CLADDING OXIDATION

Acta Polytechnica CTU Proceedings, 2016
The knowledge of heat transfer coefficient in the post critical heat flux region in nuclear reactor safety is very important. Although the nuclear reactors normally operate at conditions where critical heat flux (CHF) is not reached, accidents where ...
Vojtěch Caha, Jakub Krejčí
doaj   +1 more source

Effect of fuel chips on cladding stress in zircaloy clad oxide fuel rods (LWBR development program) [PDF]

, 1978
Zircaloy clad oxide fuel rods are subjected to a variety of core power transients. One of these, an up-power transient, can place a severe burden on the fuel rod cladding that would potentially lead to rupture if not properly allowed for during the fuel rod design and plant operation.
openaire   +2 more sources

Study on Fuel Rod Melting and Molten Material Migration in Core Channels Based on Particle Method

Science and Technology of Nuclear Installations
During nuclear reactor accidents where cooling fails, fuel rod melting and subsequent molten material flow through core channels critically determine disaster progression.
Yulu Wang, Tian Luan, Wanqian Du
doaj   +1 more source

High-fidelity numerical investigation on structural integrity of SFR fuel cladding during design basis events

Nuclear Engineering and Technology
A high-fidelity numerical analysis methodology was proposed for evaluating the fuel rod cladding integrity of a Prototype Gen IV Sodium Fast Reactor (PGSFR) during normal operation and Design basis events (DBEs).
Seo-Yoon Choi, Hyung-Kyu Kim, Min-Seop Song, Jae-Ho Jeong   +3 more
doaj   +1 more source

The effect of Laves phase on heavy-ion radiation response of Nb-containing FeCrAl alloy for accident-tolerant fuel cladding. [PDF]

Fundam Res, 2022
Xu H, Si S, Li Y, Liu X, Li W, Jiang C, Zhao S, Wang H, Xiao X.   +8 more
europepmc   +1 more source

Experimental Study on CHF Limit of Cr-coated Fuel Cladding under High Temperature and High Pressure Flow Condition

Yuanzineng kexue jishu
Nuclear fuel cladding is the first safety barrier of the reactor. For additional safety of the fuel assemblies under accident conditions, accident tolerant fuel (ATF) cladding material has been widely noted.
FAN Guanhua, FANG Qifei, YAO Xi, PENG Zhenxun, GUO Ming, CHEN Senyang, LYU Lulu, ZHANG Ge, SU Qianhua, LU Donghua
doaj   +1 more source