High heat flux test results for a thermal break DEMO divertor target and subsequent design and manufacture development

被引:11
|
作者
Lukenskas, Adomas [1 ]
Barrett, T. R. [1 ]
Fursdon, M. [1 ]
Domptail, F. [1 ]
Schoofs, F. [1 ]
Greuner, H. [2 ]
Dose, G. [3 ]
Roccella, S. [4 ]
Visca, E. [4 ]
Gallay, F. [5 ]
Richou, M. [5 ]
You, J-H [2 ]
机构
[1] CCFE, Culham Sci Ctr, Abingdon OX14 3DB, Oxon, England
[2] Max Planck Inst Plasma Phys, Boltzmann Str 2, D-85748 Garching, Germany
[3] Univ Roma Tor Vergata, Dipartimento Ingn Ind, Via Politecn 1, I-00133 Rome, Italy
[4] ENEA Frascati, Fus & Technol Nucl Safety, Via E Fermi 45, I-00044 Frascati, Italy
[5] CEA, IRFM, F-13108 St Paul Les Durance, France
关键词
CuCrZr; Divertor target; Thermal break; High heat flux; Brazing;
D O I
10.1016/j.fusengdes.2019.03.010
中图分类号
TL [原子能技术]; O571 [原子核物理学];
学科分类号
0827 ; 082701 ;
摘要
This paper focuses on the development of the water-cooled divertor target concept known as Thermal Break, which was carried out in two phases. In Phase 1, six small scale mock-ups were fabricated and subjected to high heat flux (HHF) testing of up to 25 MW/m(2) and thermal cycling of up to 500 cycles at 20 MW/m(2). All six mockups survived the campaign and maintained 20 MW/m(2) heat exhaust capability. Detailed examination of mockups was carried out to understand the damage mechanisms. One mock-up, which was tested beyond its design intent at 500 cycles, shows signs of progressive damage. Potential damage modes were identified and influenced subsequent Phase 2 mock-up design. Although there are signs of tungsten surface cracking, the predominant damage mode is not by "deep cracking" but substantial permanent deformation in the interlayer features. Therefore, in Phase 2 the manufacturing procedure was updated, the interlayer grooves were given stressre-lieving radii which have significantly reduced the interlayer plastic strain range. Interlayer design parameters were selected following the use of response surface-based design search and optimization. Mock-ups of the Phase 2 design have been manufactured and HHF testing is planned within 2018.
引用
收藏
页码:1657 / 1660
页数:4
相关论文
共 50 条
  • [31] Qualification of high heat flux components: application to target elements of W7-X divertor
    Missirlian, M.
    Durocher, A.
    Grosman, A.
    Schlosser, J.
    Boscary, J.
    Escourbiac, F.
    Cismondi, F.
    PHYSICA SCRIPTA, 2007, T128 : 182 - 188
  • [32] Comparison between FEM and high heat flux thermal fatigue testing results of ITER divertor plasma facing mock-ups
    Crescenzi, F.
    Roccella, S.
    Visca, E.
    Moriani, A.
    FUSION ENGINEERING AND DESIGN, 2014, 89 (7-8) : 985 - 990
  • [33] High heat flux test of CVD-tungsten coated Cu heat sink divertor mock-up
    Sato, K
    Nakamura, K
    Suzuki, S
    Araki, M
    Dairaku, M
    Yokoyama, K
    Akiba, M
    FUSION TECHNOLOGY, 1996, 30 (03): : 769 - 773
  • [34] Materials development for new high heat-flux component mock-ups for DEMO
    Coenen, J. W.
    Mao, Y.
    Sistla, S.
    Mueller, A., V
    Pintsuk, G.
    Wirtz, M.
    Riesch, J.
    Hoeschen, T.
    Terra, A.
    You, J-H
    Greuner, H.
    Kreter, A.
    Broeckmann, Ch
    Neu, R.
    Linsmeier, Ch
    FUSION ENGINEERING AND DESIGN, 2019, 146 : 1431 - 1436
  • [35] Ultrasonic analysis of tungsten monoblock divertor mock-ups after high heat flux test
    Dose, Giacomo
    Roccella, Selanna
    Richou, Marianne
    Gallay, Franklin
    Visca, Eliseo
    Greuner, Henri
    Romanelli, Francesco
    Hunger, Katja
    Barrett, Tom
    You, Jeong-Ha
    FUSION ENGINEERING AND DESIGN, 2019, 146 : 870 - 873
  • [36] First thermal fatigue studies of tungsten armor for DEMO and ITER at the OLMAT High Heat Flux facility
    Alegre, D.
    Tafalla, D.
    De Castro, A.
    Gonzalez, M.
    Manchon, J. G.
    Tabares, F. L.
    Hernandez, T.
    Wirtz, M.
    Coenen, J. W.
    Mao, Y.
    Oyarzabal, E.
    NUCLEAR MATERIALS AND ENERGY, 2024, 38
  • [37] Results and consequences of high heat flux testing as quality assessment of the Wendelstein 7-X divertor
    Greuner, Henri
    Toussaint, Udo V.
    Boeswirth, Bernd
    Boscary, Jean
    Peacock, Alan
    FUSION ENGINEERING AND DESIGN, 2013, 88 (6-8) : 581 - 584
  • [38] 3D thermal elasto plastic analysis of ITER divertor high heat flux elements
    Bykov, VA
    Komarov, VM
    Mazul, IV
    Borovkov, AI
    Semenov, AS
    PLASMA DEVICES AND OPERATIONS, 1998, 6 (1-3): : 55 - 63
  • [39] Design and development of LN2 cooled cryopump for application in high heat flux test facility
    Mukherjee, S. S.
    Gupta, V
    Panchal, P.
    Mishra, J. S.
    Nayak, P.
    Agarwal, J.
    Agravat, H.
    Dewasi, A.
    Dutta, R.
    Desai, A. B.
    Verma, S. K.
    Swamy, R.
    Mokariya, P.
    Patel, N.
    Patel, T.
    Belsare, S. M.
    Khirwadkar, S. S.
    Gangradey, R.
    FUSION ENGINEERING AND DESIGN, 2022, 184
  • [40] Design and performance of vacuum system for high heat flux test facility
    Kidambi, Rajamannar Swamy
    Mokaria, Prakash
    Khirwadkar, Samir
    Belsare, Sunil
    Khan, M. S.
    Patel, Tushar
    Krishnan, Deepu S.
    10TH ASIA PLASMA AND FUSION ASSOCIATION CONFERENCE (APFA), 2017, 823