Stress relaxation testing of pre-compression ring mock-up for the ITER magnet system

被引:7
|
作者
Rossi, R. [1 ]
Annino, C. [1 ]
Baker, W. [3 ]
Bettinali, L. [1 ]
Knaster, J. [4 ]
Lo Bue, A. [1 ]
Mazzone, G. [4 ]
Nardi, C. [1 ]
Pizzuto, A. [1 ]
Semeraro, L. [2 ]
机构
[1] EURATOM, ENEA Fus, CR Frascati, I-00044 Frascati, Italy
[2] Fus Energy, Barcelona 08019, Spain
[3] EFDA CSU, D-85748 Garching, Germany
[4] ITER Cadarache, F-13108 St Paul Les Durance, France
关键词
Composite; Epoxy; Fibreglass; ITER; Pre-compression rings;
D O I
10.1016/j.fusengdes.2008.12.024
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
The ITER pre-compression ring system is based on two sets of 3 rings made in fibreglass-epoxy composite and is located on top and bottom of the inner straight leg region. These rings will provide a radial force of about 70 MN/coil (35 MN at the top and 35 MN at the bottom) under cryogenic conditions, pulling the TF coils into contact, reducing the gap between the poloidal shear keys and their keyways during operation and also reducing the toroidal tension in the four Outer intercoil structures bands. The paper describes the stress relaxation test performed in ENEA Frascati laboratories on a reduced scale glass fibre-epoxy composite ring. The ring was manufactured with a diameter of 1 m (1/5 of the real scale one) by winding S2 glass fibres then impregnated with epoxy. The volumetric glass content was of 69% and no significant presence of defects was verified by an X-ray survey. The test has been carried out following as close as possible the ASTM standard E 328-86. The ring has been inserted into a dedicated hydraulic testing machine consisting of 18 radial pulling actuators and then loaded up to a ring membrane hoop stress of 800 MPa. The deformation has been maintained constant during the test by inserting a solid steel disk in the machine centre restraining the machine radial motion. Average hoop stress has been daily monitored measuring the force required to lift the ring just free of the constraints during the test period. The ring performed 125 testing days showing no significant stress relaxation and a small reduction of the ring stiffness that appeared mainly in the first days of the test. (C) 2009 Published by Elsevier B.V.
引用
收藏
页码:1649 / 1652
页数:4
相关论文
共 40 条
  • [21] Implementation on a mock-up of the automatic feedback controlled matching options of the full ITER ICRH system
    Grine, D.
    Vervier, M.
    Messiaen, A.
    Dumortier, P.
    FUSION ENGINEERING AND DESIGN, 2011, 86 (6-8) : 978 - 981
  • [22] Tests of load resilient matching procedure for the ITER ICRH system on a mock-up and layout proposal
    Dumortier, P.
    Lamalle, P.
    Leroy, N.
    Messiaen, A.
    Vervier, M.
    FUSION ENGINEERING AND DESIGN, 2007, 82 (5-14) : 758 - 764
  • [23] Extensive characterisation of advanced manufacturing solutions for the ITER Central Solenoid pre-compression system
    Langeslag, S. A. E.
    Sgobba, S.
    Libeyre, P.
    Marcinek, D. J.
    Zhang, Z.
    FUSION ENGINEERING AND DESIGN, 2015, 98-99 : 2015 - 2019
  • [24] FABRICATION AND INTEGRITY TESTING OF A KOREAN ITER TBM FW MOCK-UP IN PREPARATION FOR HIGH HEAT FLUX TEST
    Yoon, Jae Sung
    Kim, Suk Kwon
    Lee, Eo Hwak
    Cho, Seungyon
    Lee, Dong Won
    FUSION SCIENCE AND TECHNOLOGY, 2013, 64 (03) : 657 - 661
  • [25] Study of the ITER ICRH system with external matching by means of a mock-up loaded by a variable water load
    Messiaen, A
    Vervier, M
    Dumortier, P
    Lamalle, P
    Louche, F
    Radio Frequency Power in Plasmas, 2005, 787 : 198 - 201
  • [26] Study of the ITER ICRH system with external matching by means of a mock-up loaded by a variable water load
    Messiaen, A.
    Vervier, M.
    Dumortier, P.
    Latnalle, P.
    Louche, R.
    NUCLEAR FUSION, 2006, 46 (07) : S514 - S539
  • [27] Thermo-hydraulic testing and integrity of ITER Test Blanket Module (TBM) First Wall mock-up in JAEA
    Ezato, K.
    Seki, Y.
    Tanigawa, H.
    Hirose, T.
    Tsuru, D.
    Nishi, H.
    Dairaku, M.
    Yokoyama, K.
    Suzuki, S.
    Enoeda, M.
    FUSION ENGINEERING AND DESIGN, 2010, 85 (7-9) : 1255 - 1260
  • [28] Thermal fatigue testing of a diffusion-bonded beryllium divertor mock-up under ITER-relevant conditions
    Youchison, DL
    Guiniatouline, RN
    Watson, RD
    McDonald, JM
    Walsh, DS
    Beloturov, VI
    Mazul, IV
    Zakharov, AP
    Mills, BE
    Boehme, DR
    Savenko, VI
    FUSION TECHNOLOGY, 1996, 29 (04): : 599 - 614
  • [29] Fatigue behavior testing and evaluation of ITER In-vessel mock-up coil under combined thermal and electromagnetic loads
    Jin, H.
    Wu, Y.
    Qin, J. G.
    Vostner, A.
    Laquiere, J.
    Yu, M.
    Jin, J.
    Tao, B. W.
    Han, H. X.
    Han, Q. Y.
    FUSION ENGINEERING AND DESIGN, 2021, 167 (167)
  • [30] Study of the load resilient external matching circuit for the ITER ICRH/FWCD system by means of its mock-up
    Messiaen, A.
    Dumortier, P.
    Lamalle, P. U.
    Vervier, M.
    RADIO FREQUENCY POWER IN PLASMAS, 2007, 933 : 163 - +