Improved irradiation resistance of Cr-Fe alloy for Cr-coated Zircaloy application in accident tolerant fuel

被引：9
作者：
Cui, L. J. [1 ]
Du, Y. F. [2 ]
Yang, H. L. [3 ]
Jovellana, J. A. K. [4 ]
Shi, Q. Q. [1 ]
Kano, S. [1 ]
Abe, H. [1 ,4 ]
机构：
[1] Univ Tokyo, Nucl Profess Sch, 2-22 Shirakata Shirane, Tokai, Ibaraki 3191188, Japan
[2] Tohoku Univ, Inst Mat Res, Oarai, Ibaraki 3111313, Japan
[3] Shanghai Jiao Tong Univ, Sch Nucl Sci & Engn, Shanghai 200240, Peoples R China
[4] Univ Tokyo, Dept Nucl Engn & Management, 7-3-1 Hongo Bunkyo, Tokyo 1138656, Japan
来源：
SCRIPTA MATERIALIA | 2023年 / 229卷
关键词：
ATF; Cr Coating; Hardness; Irradiation; Void swelling; HIGH FLUENCE IRRADIATION; PRECIPITATION; DISLOCATION; UNIVERSITY; EVOLUTION; FACILITY; SYSTEM; STEELS; PHASE;
D O I：
10.1016/j.scriptamat.2023.115344
中图分类号：
TB3 [工程材料学];
学科分类号：
0805 ; 080502 ;
摘要：
Cr coating onto Zircaloy for the application of accident tolerance fuel claddings became a popular topic in the nuclear material field since the Fukushima-Daiichi accident in 2011. However, in the Cr coating layer the solute element effect on the potential performance improvement is still unknown, especially under irradiation. The irradiation effect in Cr-7Fe was studied after irradiation by 2.8 MeV Fe2} to 20 dpa at 550 degrees C. The nano-indentation results show that doping of Fe not only can strengthen the material but also can significantly reduce the irradiation-induced hardness compared with pure Cr. The microstructure analyses show that solute element Fe can retain the diffusion of defects and reduce void swelling. In addition, the APT results indicate that no detrimental Fe-rich cluster formed in irradiated Cr-7Fe. From the aspects of irradiation-induced hardening, void-swelling, and clustering, a great improvement in irradiation resistance was achieved in Cr-7Fe alloy compared with pure Cr.
引用
收藏
页数：7
相关论文
共 47 条
  • [1] Irradiation creep and growth of zirconium alloys: A critical review
    Adamson, Ronald B.
    Coleman, Christopher E.
    Griffiths, Malcolm
    [J]. JOURNAL OF NUCLEAR MATERIALS, 2019, 521 : 167 - 244
  • [2] On the use of SRIM for calculating vacancy production: Quick calculation and full-cascade options
    Agarwal, S.
    Lin, Y.
    Li, C.
    Stoller, R. E.
    Zinkle, S. J.
    [J]. NUCLEAR INSTRUMENTS & METHODS IN PHYSICS RESEARCH SECTION B-BEAM INTERACTIONS WITH MATERIALS AND ATOMS, 2021, 503 : 11 - 29
  • [3] THERMO-CALC & DICTRA, computational tools for materials science
    Andersson, JO
    Helander, T
    Höglund, LH
    Shi, PF
    Sundman, B
    [J]. CALPHAD-COMPUTER COUPLING OF PHASE DIAGRAMS AND THERMOCHEMISTRY, 2002, 26 (02): : 273 - 312
  • [4] Bryk V.V., 1995, MICROSTRUCTURE INVES
  • [5] Cui L.J., 2022, TEM CHARACTERIZATION, V569, DOI [10.1016/j.jnucmat.2022.153920, DOI 10.1016/J.JNUCMAT.2022.153920]
  • [6] Characterization of dislocation loops in hydrogen-ion irradiated vanadium
    Cui Li-Juan
    Gao Jin
    Du Yu-Feng
    Zhang Gao-Wei
    Zhang Lei
    Long Yi
    Yang Shan-Wu
    Zhan Qian
    Wan Fa-Rong
    [J]. ACTA PHYSICA SINICA, 2016, 65 (06)
  • [7] Quantitative APT analysis of solid transmutants in ferritic-martensitic steels after irradiation in SINQ targets: Experimental validation of neutronic calculations
    Cui, Lijuan
    Li, Jinyang
    Gerstl, Stephan
    Pouchon, Manuel
    Dai, Yong
    [J]. NUCLEAR INSTRUMENTS & METHODS IN PHYSICS RESEARCH SECTION B-BEAM INTERACTIONS WITH MATERIALS AND ATOMS, 2021, 502 (502) : 1 - 9
  • [8] Doyle PJ, 2020, J NUCL MATER, V536
  • [9] Formation of Vacancy-Type Dislocation Loops in Hydrogen-Ion-Implanted Fe-Cr Alloy
    Du, Yu-Feng
    Cui, Li-Juan
    Han, Wen-Tuo
    Wan, Fa-Rong
    [J]. ACTA METALLURGICA SINICA-ENGLISH LETTERS, 2019, 32 (05) : 566 - 572
  • [10] Anomalous heat-releasing phenomenon from bubbles in aluminum induced by electron beam irradiation
    Du Yu-Feng
    Cui Li-Juan
    Li Jin-Sheng
    Li Ran-Ran
    Wan Fa-Rong
    [J]. ACTA PHYSICA SINICA, 2018, 67 (21)
12345