Results 81 to 90 of about 5,476 (206)

Influence of helium ion irradiation on the mechanical properties of high-entropy (Hf,Ta,Ti,V,Zr)-nitride, -carbide and -diboride thin films: A comparative study

Materials & Design
In this study, high-entropy (Hf, Ta, Ti, V, Zr)- nitride, -carbide, and -diboride thin films were synthesized via magnetron sputtering and implanted with helium ions using a helium ion microscope. All films exhibited a stable single-phase structure, with
T. Astecker, P. Hosemann, M. Balooch, A.N. Lee, M.L. Crespillo, K. Hattar, M.O. Liedke, A. Wagner, P. Polcik, A. Kirnbauer, P.H. Mayrhofer   +10 more
doaj   +1 more source

Radiation resistivity of Ti-5331 alloy with different microstructures

Journal of Materials Research and Technology
Titanium alloys have promising potential for applications in marine nuclear power systems owing to their exceptional mechanical and corrosion properties.
Zhen Wu, Yunmei Shi, Xudong An, Qianqian Wang, Te Zhu, Qigui Yang, Eryang Lu, Kenichiro Mizohata, Mingpan Wan, Peng Zhang, Baoyi Wang, Xingzhong Cao   +11 more
doaj   +1 more source

Irradiation hardening and void swelling behaviors of F82H IEA by using dual-ion irradiation

, 2023
The irradiation hardening behavior and the void swelling behavior of the Japanese reduced activation ferritic/martensitic steel, i.e. F82H IEA heat, were investigated by using single- and dual-ion irradiation experiments in this study.
Ando Masami, Hamaguchi Dai, Nozawa Takashi, Watanabe Yoshiyuki   +3 more
core   +1 more source

Multiple Approaches to Quantifying the Effective Porosity of Lacustrine Shale Oil Reservoirs in Bohai Bay Basin, East China

Geofluids, 2020
An effective porosity is defined as the ratio of volume of interconnected pore space to total volume of a porous sample. It controls the magnitude of fluid flow and is a key parameter in the assessment of recoverable resources.
Binyu Ma, Qinhong Hu, Shengyu Yang, Na Yin, Hongguo Qiao, Tao Zhang, Mianmo Meng   +6 more
doaj   +1 more source

Theoretical investigations on helium trapping in the Zr/Ti2AlC interface

, 2017
MAX phases have been suggested to be applicable in the next generation nuclear reactors for their advantages in thermal/mechanical properties at high temperatures and radiation damage resistance.
Huang, Qing, Zha, Xian-Hu, Zhang, Ruifeng, Shiyu Du, Luo, Kan, Ruifeng Zhang, Qing Huang, Lin, Cheng-Te, Kan Luo, Cheng-Te Lin, Du, Shiyu, Xian-Hu Zha   +11 more
core   +1 more source

On the uncertainties in helium generation predictions for fission and fusion alloys

JPhys Energy
With ongoing advances in fusion and advanced fission reactors, quantifying irradiation effects in materials is critical. Transmutation-induced helium in cladding and structural materials can drive swelling and embrittlement, thereby reducing these ...
Alexander J Birmingham, Justin A Hamil, Stephen Taller, Kevin G Field   +3 more
doaj   +1 more source

Dynamic behavior of helium in nanocrystalline tungsten film by thermal desorption and internal friction

Nuclear Materials and Energy
Tungsten (W) has been considered a primary candidate for plasma-facing materials due to its superior properties. However, significant challenges remain due to helium-induced (He-induced) irradiation damage, particularly the formation of He clusters and ...
Banglei Zhao, Hao Feng, Le Wang, Ting Hao, Xuebang Wu   +4 more
doaj   +1 more source

Mechanism of swelling suppression in phosphorous-modified Fe-Ni-Cr alloys [PDF]

, 1986
Five simple alloys were ion irradiated at 948/sup 0/K in an experiment designed to investigate the mechanism of swelling suppression associated with phosphorous additions.
Mansur, L.K., Lee, E.H.
core  

Applications of the theory of cavity growth to dual-ion swelling experiments [PDF]

, 1980
The rate theory of cavity growth is applied to study the effects of helium gas on cavity swelling. The variation of swelling with temperature is emphasized: (1) expressions are derived showing that the primary effect of the helium is in pressurizing ...
Mansur, L.K., Hayns, M.R.
core  

Helium swelling behavior for neutron multipliers after irradiation with He ions at high temperatures

Nuclear Materials and Energy
Beryllides as beryllium intermetallic compounds are the advanced multiplier materials as candidate materials for fusion demonstration power plant (DEMO) due to having good properties such as low swelling rate and stable chemical properties.Under DEMO ...
Yutaka Sugimoto, Mitsutaka Miyamoto, Jae-Hwan Kim, Taehyun Hwang, Masaru Nakamichi   +4 more
doaj   +1 more source