Results 1 to 10 of about 1,250 (204)

Linear complexions enable unprecedented ductility retention in neutron irradiated ferritic steel [PDF]

Nature Communications
Herein, the operando formation of Si-enriched linear complexions during neutron irradiation enables Grade 91 ferritic steel to overcome the strength–ductility tradeoff, one of the most critical life-limiting challenges facing nuclear structural alloys ...
Arya Chatterjee, Soumita Mondal, Yu Lu, Yaqiao Wu, Janelle P. Wharry   +4 more
doaj   +2 more sources

Fundamental Mechanisms for Irradiation-Hardening and Embrittlement: A Review

Metals, 2019
It has long been recognized that exposure to irradiation environments could dramatically degrade the mechanical properties of nuclear structural materials, i.e., irradiation-hardening and embrittlement.
Xiazi Xiao
exaly   +3 more sources

A study of predicting irradiation-induced transition temperature shift for RPV steels with XGBoost modeling

Nuclear Engineering and Technology, 2021
The prediction of irradiation-induced transition temperature shift for RPV steels is an important method for long term operation of nuclear power plant.
Chaoliang Xu, Xiangbing Liu, Hongke Wang, Yuanfei Li, Wenqing Jia, Wangjie Qian, Qiwei Quan, Huajian Zhang, Fei Xue   +8 more
doaj   +1 more source

Influence analysis of alloy elements on irradiation embrittlement of RPV steel based on deep neural network

International Journal of Advanced Nuclear Reactor Design and Technology, 2023
Reactor pressure vessel (RPV) is the most important core equipment in PWR. Its service life determines the service life of nuclear power plant and directly affects the economy and safety of nuclear power plant. Because RPV is serviced at high temperature,
Bai Bing, Xu Han, Lixia Jia, Xinfu He, Changyi Zhang, Wen Yang   +5 more
doaj   +1 more source

Direct Observation of Cu Clusters and Dislocation Loops by Cs-Corrected STEM in Fe-0.6wt%Cu Alloy Irradiated in BR2

Metals, 2022
The neutron irradiation of Fe-based fusion and fission reactor materials leads to an increase in ductile-to-brittle transition temperature with a decrease in upper shelf energy. It is well known that Cu content has a strong influence on the embrittlement
Hideo Watanabe, Tomonari Tanaka, Takuya Turu, Yasuhiro Kamada   +3 more
doaj   +1 more source

The development of prediction model on irradiation embitterment for low Cu RPV steels

Heliyon, 2023
The development of prediction model on irradiation embitterment (PMIE) of reactor pressure vessel (RPV) is an important method for nuclear reactor long term operation.
Chaoliang Xu, Xiangbing Liu, Yuanfei Li, Wenqing Jia, Qiwei Quan, Wangjie Qian, Jian Yin, Xiao Jin   +7 more
doaj   +1 more source

Swelling and He-Embrittlement of Austenitic Stainless Steels and Ni-Alloys in Nuclear Reactors

Metals, 2022
Rate theory models have been developed for the swelling and He-embrittlement of austenitic stainless steels and Ni-alloys in nuclear reactors. The models illustrate how microstructure evolution during irradiation affects the rate of change of mechanical ...
Malcolm Griffiths, Steven Xu, Juan Eduardo Ramos Nervi   +2 more
doaj   +1 more source

Investigation on effect of neutron irradiation on welding residual stresses in core shroud of pressurized water reactor

Nuclear Engineering and Technology, 2023
This paper presents the results of investigating the change in welding residual stresses of the core shroud, which is one of subcomponents in reactor vessel internals, performing finite element analysis.
Jong-Sung Kim, Young-Chan Kim, Wan Yoo
doaj   +1 more source

Multicriteria Analytical Model for Mechanical Integrity Prognostics of Reactor Pressure Vessels Manufactured from Forged and Rolled Steels

Mathematics, 2022
The aim of this work is to present a new analytical model to evaluate jointly the mechanical integrity and the fitness-for-service of nuclear reactor pressure-vessels steels.
Alvaro Rodríguez-Prieto, Manuel Callejas, Ernesto Primera, Guglielmo Lomonaco, Ana María Camacho   +4 more
doaj   +1 more source

Interpretation of Nondestructive Magnetic Measurements on Irradiated Reactor Steel Material

Applied Sciences, 2021
Neutron irradiation-generated embrittlement of nuclear pressure vessel steel was inspected by a nondestructive magnetic method, called magnetic adaptive testing (MAT).
Gábor Vértesy, Antal Gasparics, Ildikó Szenthe, Inge Uytdenhouwen   +3 more
doaj   +1 more source