The TBM-CA configuration management approach for the ITER test blanket module - application to the HCLL TBS

被引:1
|
作者
Jourd'Heuil, L. [1 ]
Panayotov, D. [2 ]
Salavy, J. -F. [3 ]
Storto, C. [4 ]
Colombo, M. [4 ]
Sardain, P. [1 ]
机构
[1] CEA, IRFM, F-13108 St Paul Les Durance, France
[2] KIT, D-76344 Eggenstein Leopoldshafen, Germany
[3] CEA, DEN, DM2S, F-91191 Gif Sur Yvette, France
[4] LGM, F-13858 Aix En Provence 3, France
关键词
TBM; TBS; Configuration Management; Change Management; Nonconformance Management; Organization;
D O I
10.1016/j.fusengdes.2011.03.101
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 European Test Blanket Modules (EU-TBM) are first prototypes of a fusion reactor breeding blanket. They will be tested in dedicated equatorial ports n degrees 16 of ITER. Technical developments are performed by a Consortium of European Associates (TBM-CA) and supported within the framework of F4E agency. Designing a complex nuclear system like TBM for ITER necessitates an organizational structure inside the consortium to manage in permanence the coherence between requirements (F4E technical and management specifications) and the TBM development through their life time. At the present stage, evolutionary nature of the design from the different teams is important. Highest priority is assigned to the Management support and Design Integration Team (MDIT) to perform an efficient control of the Configuration Management (CM). The TBM-CA CM comprises 4 main processes: a) identifying configuration of a product characteristics, including its interfaces (Configuration identification), b) controlling the evolution from agreed baseline (Configuration Control), c) creating the knowledge database in order to manage the information all along the lifecycle of the items (Configuration status accounting) and d) verifying the current configuration status of the items (Audits). CM is then a powerful tool to link the requirements for engineering, safety, quality assurance and test & acceptance activities. The application of the CM approach is illustrated through the case of TBM-HCLL (Helium Cooled Lithium Lead). The result shows that the proposed methodology and tools are suitable and provide quality solution for the items with a complex configuration such as TBM HCLL (C) 2011 Elsevier B.V. All rights reserved.
引用
收藏
页码:2317 / 2321
页数:5
相关论文
共 12 条
  • [1] Preliminary RAMI assessment for HCPB and HCLL ITER test blanket module ancillary systems
    Dongiovanni, Danilo Nicola
    Aiello, Antonio
    Ghidersa, Bradut-Eugen
    Pinna, Tonio
    Ricapito, Italo
    FUSION ENGINEERING AND DESIGN, 2019, 146 : 1685 - 1689
  • [2] Current status of technology development for fabrication of Indian Test Blanket Module (TBM) of ITER
    Jayakumar, T.
    Kumar, E. Rajendra
    FUSION ENGINEERING AND DESIGN, 2014, 89 (7-8) : 1562 - 1567
  • [3] The HCLL Test Blanket Module system: Present reference design, system integration in ITER and R&D needs
    Salavy, J. -F.
    Aiello, G.
    David, O.
    Gabriel, F.
    Giancarli, L.
    Girard, C.
    Jonqueres, N.
    Laffont, G.
    Madeleine, S.
    Poitevin, Y.
    Rampal, G.
    Ricapito, I.
    Splichal, K.
    FUSION ENGINEERING AND DESIGN, 2008, 83 (7-9) : 1157 - 1162
  • [4] Construction of a test platform for Test Blanket Module (TBM) systems integration and maintenance in ITER Port Cell #16
    Vala, Ladislav
    Reungoat, Mathieu
    Vician, Martin
    Poitevin, Yves
    Ricapito, Italo
    Zmitko, Milan
    Panayotov, Dobromir
    FUSION ENGINEERING AND DESIGN, 2015, 96-97 : 365 - 368
  • [5] Engineering studies for integration of the test blanket module (TBM) systems inside an ITER equatorial port plug
    Madeleine, S.
    Saille, A.
    Martins, J. -R
    Salavy, J. -F.
    Jonqueres, N.
    Rampal, G.
    Bede, O.
    Neuberger, H.
    Boccaccini, L.
    Doceul, L.
    FUSION ENGINEERING AND DESIGN, 2009, 84 (7-11) : 1233 - 1237
  • [6] 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
  • [7] Activation analysis and waste management of China ITER helium cooled solid breeder test blanket module
    Han, J. R.
    Chen, Y. X.
    Han, R.
    Feng, K. M.
    Forrest, R. A.
    FUSION ENGINEERING AND DESIGN, 2010, 85 (05) : 761 - 765
  • [8] Preliminary Analysis of Three ULOFAs Based on the Dual-Functional Lithium Lead Test Blanket Module Configuration in ITER
    Ni, Weifeng
    Qiu, Suizheng
    Su, Guanghui
    Tian, Wenxi
    PROCEEDINGS OF THE 18TH INTERNATIONAL CONFERENCE ON NUCLEAR ENGINEERING 2010, VOL 6, 2011, : 553 - 557
  • [9] Optimization of electron beam butt welding of 32 mm CLF-1 steel T-joints of Test Blanket Module (TBM) in ITER
    Shi, Yilei
    Zhang, Guoyu
    Liao, Hongbin
    Wang, Xiaoyu
    Wu, Shikai
    FUSION ENGINEERING AND DESIGN, 2020, 161
  • [10] Thermal-hydraulic system study of the Helium cooled pebble bed (HCPB) test blanket module (TBM) for ITER using system code RELAP5
    Jin, XZ
    Meyder, R
    PLASMA SCIENCE & TECHNOLOGY, 2005, 7 (02) : 2753 - 2757