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author:

Lai, Huan Sheng (Lai, Huan Sheng.) [1] | Wang, Rongcheng (Wang, Rongcheng.) [2] | Zhong, Yuntao (Zhong, Yuntao.) [3] | Du, Peinan (Du, Peinan.) [4] | Guo, Jinquan (Guo, Jinquan.) [5] | Huang, Qifei (Huang, Qifei.) [6]

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EI

Abstract:

The manufacturing process of nuclear fuel cladding tubes endows them with anisotropic material properties. In this study, a small punch testing (SPT) method was established to investigate the circumferential tensile behavior of nuclear fuel cladding tubes. The specimen of the proposed SPT method was bended and stretched in a single stress state under a punching force. The proposed SPT method was then used to analyze the circumferential tensile behavior of a FeCrAl fuel cladding tube. Finite element simulation results indicated that the SPT method established herein determined ultimate tensile stress with higher accuracy than standard SPT because the plastic strain in the proposed method under maximum force is considerably smaller than that in standard SPT. Moreover, the proposed method can more accurately determine yield stress compared with standard SPT, as reflected by the elastic stage in the load–displacement curve that was a straight line. The test results indicated that the proposed SPT can be used to accurately determine the circumferential yield stress and ultimate tensile stress of nuclear fuel cladding tubes. © 2023 Elsevier B.V.

Keyword:

Aluminum alloys Cladding (coating) Iron alloys Tensile stress Tensile testing Ternary alloys Tubes (components) Yield stress

Community:

  • [ 1 ] [Lai, Huan Sheng]Sino-French Institute of Nuclear Engineering and Technology, Sun Yat-sen University, Zhuhai; 519082, China
  • [ 2 ] [Wang, Rongcheng]Sino-French Institute of Nuclear Engineering and Technology, Sun Yat-sen University, Zhuhai; 519082, China
  • [ 3 ] [Zhong, Yuntao]Science and Technology on Reactor Fuel and Materials Laboratory, Nuclear Power Institute of China, Sichuan, Chengdu; 610213, China
  • [ 4 ] [Du, Peinan]Science and Technology on Reactor Fuel and Materials Laboratory, Nuclear Power Institute of China, Sichuan, Chengdu; 610213, China
  • [ 5 ] [Guo, Jinquan]School of Mechanical Engineering and Automation, Fuzhou University, Fuzhou; 350108, China
  • [ 6 ] [Huang, Qifei]School of Chemical Engineering, Fuzhou University, Fuzhou; 350108, China

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Source :

Journal of Nuclear Materials

ISSN: 0022-3115

Year: 2023

Volume: 583

2 . 8

JCR@2023

2 . 8 0 0

JCR@2023

ESI HC Threshold:35

JCR Journal Grade:1

CAS Journal Grade:1

Cited Count:

WoS CC Cited Count:

SCOPUS Cited Count: 1

ESI Highly Cited Papers on the List: 0 Unfold All

WanFang Cited Count:

Chinese Cited Count:

30 Days PV: 0

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