Results 71 to 80 of about 1,923 (185)

HYDROGEN CHARGING OF FUEL CLADDING METHODOLOGY

open access: yesActa Polytechnica CTU Proceedings, 2016
Hydrogen content is a very important parameter for mechanical properties of fuel cladding, especially after LOCA transients. Therefore, it is necessary to take into account the amount of hydrogen absorbed in the fuel cladding during normal operation (before a hypothetical LOCA). The required value of hydrogen content is possible to reach by a long-term
Jakub Krejčí   +4 more
openaire   +3 more sources

Numerical Simulation of Multi-field Coupled Corrosion Behavior of Core Cladding in Lead-bismuth Fast Reactor

open access: yesYuanzineng kexue jishu
Corrosion of structural materials in lead-bismuth fast reactors due to liquid lead-bismuth eutectic (LBE) is a significant issue that hinders their development.
JIA Zheng, LIU Li, BAO Ruiqi, LUO Haotian, YUAN Junjie, GU Hanyang
doaj   +1 more source

Compatibility of SNAP fuel and clad materials [PDF]

open access: yes, 1960
Samples capsules containing buttons of materials of interest for SNAP fuel elements were held at temperatures up to 1600°F , in hydrogen, under a 20-tsi load for 200+ hours.
openaire   +2 more sources

Raman Characteristics Analysis of Fuel-cladding Chemical Interaction Layer for Intact and Leak PWR Fuel Rods

open access: yesYuanzineng kexue jishu, 2023
Zirconium alloys have long been used as cladding materials for pressurized water reactors (PWR) due to excellent corrosion resistance and low thermal neutron capture cross-section.
WANG Huacai;CHENG Huanlin;SONG Wulin;GUO Lina;TANG Qi;GUO Yifan;YANG Qifa
doaj  

Experimental Study on Interaction between Ce-Nd Alloy and Stainless Steel

open access: yesYuanzineng kexue jishu
In integrated fast reactor, metal fuel is used for its advantages in fuel reprocessing and recycling. However, under high temperature and irradiation, complex mechanical and chemical interactions between the fuel and cladding significantly limit fuel ...
RUAN Zhangshun, ZHANG Ruiying, WANG Yuhui, TU Menghe, FU Xiaogang, LONG Bin
doaj   +1 more source

Full-core fuel analysis of a soluble boron-free SMR: Pellet-cladding interaction issue and enhancing fuel safety through loading pattern design

open access: yesNuclear Engineering and Technology
The full-core fuel behavior of the Soluble Boron-Free (SBF) Small Modular Reactor (SMR) was analyzed and compared with conventional pressurized water reactors (PWRs) and Soluble Boron-Using (SBU) SMRs to evaluate unique pellet-cladding interaction (PCI ...
Chansoo Lee   +5 more
doaj   +1 more source

Module Development and Verification for Fuel-pin Cladding Failure of Sodium-cooled Fast Reactor Based on System Code FRTAC

open access: yesYuanzineng kexue jishu
The inherent safety of reactor is emphasized in the design of sodium-cooled fast reactors (SFRs), and the performance analysis of oxide fuel plays a critical role in the safety assessment of SFRs, as fuel swelling and cladding failure are key phenomena ...
LEI Yi1, ZHANG Bin1, 2, , WU Zongyun3, YANG Wenqiang1, FENG Siqi1
doaj   +1 more source

Review of Recent Advances in Cold-Sprayed Coatings for Accident-Tolerant Fuel Cladding. [PDF]

open access: yesMaterials (Basel)
Mou Y   +10 more
europepmc   +1 more source

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