The effects of fusion reactor thermal transients on the microstructure of Eurofer-97 steel

被引:12
|
作者
Kumar, D. [1 ]
Hargreaves, J. [1 ]
Bharj, A. [1 ]
Scorror, A. [1 ]
Harding, L. M. [1 ]
Dominguez-Andrade, H. [1 ]
Holmes, R. [2 ]
Burrows, R. [2 ]
Dawson, H. [3 ]
Warren, A. D. [1 ]
Flewitt, P. E. J. [1 ]
Martin, T. L. [1 ]
机构
[1] Univ Bristol, HH Wills Phys Lab, Tyndall Ave, Bristol BS8 1TL, Avon, England
[2] Natl Nucl Lab, Chadwick House,Birchwood Pk, Warrington WA3 6AE, Cheshire, England
[3] UKAEA, Culham Sci Ctr, Culham Ctr Fus Energy, Abingdon OX14 3DB, Oxon, England
基金
英国工程与自然科学研究理事会;
关键词
Fusion; Martensite; Microstructure; Thermal effects; Modelling; ACTIVATION MARTENSITIC STEEL; PLASMA-FACING COMPONENTS; DEMO; BLANKET; DESIGN; IRRADIATION; BEHAVIOR; ITER;
D O I
10.1016/j.jnucmat.2021.153084
中图分类号
T [工业技术];
学科分类号
08 ;
摘要
Plasma-wall interactions in a commercial-scale fusion power station may exert high transient thermal loads on plasma-facing surfaces, repeatedly subjecting underlying structural materials to high temperatures for short durations. Specimens of the reduced activation ferritic-martensitic steel Eurofer-97 were continuously aged at constant temperature in the range of 550 degrees C to 950 degrees C for up to 168 hours in a furnace to investigate the microstructural effects of short-term high temperature exposure. A CO2 laser was also used to repeatedly heat another specimen from 400 degrees C to 850 degrees C a total of 1,480 times over a period of 41 hours to explore transient heating effects. Microstructural changes were studied via scanning electron and focused ion beam microscopy and include (i) the coarsening of Cr-rich secondary phase precipitates when continuously heated above 750 degrees C, (ii) an increase in average grain size above 800 degrees C and (iii) the evolution of a new lath martensite microstructure above 850 degrees C. Conversely, transient heating via a laser was found to result in the decomposition of the as-received lath martensite structure into ferrite and Cr-rich carbide precipitates, accompanied by a significant increase in average grain size from 0.1-2 mu m to 5-40 mu m. Experimental analysis was supported by thermodynamic simulation of the equilibrium phase behaviour of Eurofer-97 in MatCalc and thermal finite element modelling of plasma-wall interaction heating on the water-cooled lithium-lead tritium breeding blanket concept in Comsol Multiphysics. Simulated thermal transients were found to significantly alter the microstructure of Eurofer-97 and the implications of this are discussed. (C) 2021 The Author(s). Published by Elsevier B.V.
引用
收藏
页数:14
相关论文
共 50 条
  • [31] Investigation of the residual strain and deformation mechanisms in laser-welded Eurofer97 steel for fusion reactors
    Zhu, Bin
    Leung, Nathanael
    Wang, Yiqiang
    Zhang, Hannah
    Dluhos, Jiri
    Pirling, Thilo
    Gorley, Michael
    Whiting, Mark J.
    Sui, Tan
    MATERIALS SCIENCE AND ENGINEERING A-STRUCTURAL MATERIALS PROPERTIES MICROSTRUCTURE AND PROCESSING, 2023, 877
  • [32] The microstructure and tensile properties of ferritic/martensitic steels T91, Eurofer-97 and F82H irradiated up to 20 dpa in STIP-III
    Tong, Z.
    Dai, Y.
    JOURNAL OF NUCLEAR MATERIALS, 2010, 398 (1-3) : 43 - 48
  • [33] Annealing effects on microstructure and coercive field of ferritic-martensitic ODS Eurofer steel
    Renzetti, R. A.
    Sandim, H. R. Z.
    Sandim, M. J. R.
    Santos, A. D.
    Moeslang, A.
    Raabe, D.
    MATERIALS SCIENCE AND ENGINEERING A-STRUCTURAL MATERIALS PROPERTIES MICROSTRUCTURE AND PROCESSING, 2011, 528 (03): : 1442 - 1447
  • [34] Metallurgical properties of reduced activation martensitic steel Eurofer'97 in the as-received condition and after thermal ageing
    Fernández, P
    Lancha, AM
    Lapeña, J
    Serrano, M
    Hernández-Mayoral, M
    JOURNAL OF NUCLEAR MATERIALS, 2002, 307 (1 SUPPL.) : 495 - 499
  • [35] Distribution of Tritium in the Near Surface of Candidate Structural Materials for Fusion Reactors. Type 304L Stainless Steel, Inconel, Hastelloy, Eurofer-97, Oxide Dispersion-Strengthened Alloy 14YWT
    O'Callaghan, James
    Shmayda, Walter T.
    Smith, Henry
    Sharpe, Matthew
    McWilliam, Lyn
    Almond, Philippa
    Canavan, Rhiann
    Eedy, Nathan
    Karajgikar, Gowri
    Kennedy, David
    Gardner, Hazel
    Sanni, Fatimah
    Shackleford, Alec
    Steventon, Callum
    Ruby, Josh
    Mahafa, Tshepo
    Hoelzer, David T.
    Heinola, Kalle
    Hollingsworth, Anthony
    IEEE TRANSACTIONS ON PLASMA SCIENCE, 2024, : 1 - 0
  • [36] Microstructure evolution and hardness of hot dip aluminized coating on pure iron and EUROFER 97 steel: Effect of substrate chemistry and heat treatment
    Kishore, Kaushal
    Chhangani, Sumit
    Prasad, M. J. N., V
    Bhanumurthy, K.
    SURFACE & COATINGS TECHNOLOGY, 2021, 409
  • [37] In-Situ synchrotron investigation of elastic and tensile properties of oxide dispersion strengthened EUROFER97 steel for advanced fusion reactors
    Sparks, Tay
    Kuksenko, Viacheslav
    Gorley, Michael
    Hoffmann, Jan
    Chiu, Yu-Lung
    Connolley, Thomas
    Rieth, Michael
    Wang, Yiqiang
    Cai, Biao
    ACTA MATERIALIA, 2024, 271
  • [38] Effects of heavy-ion irradiation on solute segregation to dislocations in oxide-dispersion-strengthened Eurofer 97 steel
    Williams, Ceri A.
    Hyde, Jonathan M.
    Smith, George D. W.
    Marquis, Emmanuelle A.
    JOURNAL OF NUCLEAR MATERIALS, 2011, 412 (01) : 100 - 105
  • [39] Atom probe study of radiation induced precipitates in Eurofer97 Ferritic-Martensitic steel irradiated in BOR-60 reactor
    Rogozhkin S.V.
    Nikitin A.A.
    Aleev A.A.
    Germanov A.B.
    Zaluzhnyi A.G.
    Inorganic Materials: Applied Research, 1600, Maik Nauka Publishing / Springer SBM (04): : 112 - 118
  • [40] Effects of thermal aging on microstructure and hardness of stainless steel weld-overlay claddings of nuclear reactor pressure vessels
    Takeuchi, T.
    Kakubo, Y.
    Matsukawa, Y.
    Nozawa, Y.
    Toyama, T.
    Nagai, Y.
    Nishiyama, Y.
    Katsuyama, J.
    Yamaguchi, Y.
    Onizawa, K.
    Suzuki, M.
    JOURNAL OF NUCLEAR MATERIALS, 2014, 452 (1-3) : 235 - 240