The radiation analyses of ITER lower ports

被引:0
|
作者
Petrizzi, L. [1 ]
Brolatti, G. [1 ]
Martin, A. [2 ]
Loughlin, M. [2 ]
Moro, F. [1 ]
Villari, R. [1 ]
机构
[1] Assoc EURATOM ENEA Fus, I-00044 Rome, Italy
[2] ITER Org, Cadarache, F-13108 St Paul Les Durance, France
关键词
ITER; Lower ports; Neutronics; Radiation streaming;
D O I
10.1016/j.fusengdes.2010.01.024
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 Vacuum Vessel has upper, equatorial, and lower ports used for equipment installation, diagnostics, heating and current drive systems, cryo-vacuum pumping, and access inside the vessel for maintenance. At the level of the divertor, the nine lower ports for remote handling, cryo-vacuum pumping and diagnostic are inclined downwards and toroidally located each every 40 degrees. The cryopump port has additionally a branch to allocate a second cryopump. The ports, as openings in the Vacuum Vessel, permit radiation streaming out of the vessel which affects the heating in the components in the outer regions of the machine inside and outside the ports. Safety concerns are also raised with respect to the dose after shutdown at the cryostat behind the ports: in such zones the radiation dose level must be kept below the regulatory limit to allow personnel access for maintenance purposes. Neutronic analyses have been required to qualify the ITER project related to the lower ports. A 3-D model was used to take into account full details of the ports and the lower machine surroundings. MCNP version 5 1.40 has been used with the FENDL 2.1 nuclear data library. The ITER 40 degrees model distributed by the ITER Organization was developed in the lower part to include the relevant details. The results of a first analysis, focused on cryopump system only, were recently published. In this paper more complete data on the cryopump port and analysis for the remote handling port and the diagnostic rack are presented; the results of both analyses give a complete map of the radiation loads in the outer divertor ports. Nuclear heating, dpa, tritium production, and dose rates after shutdown are provided and the implications for the design are discussed. (C) 2010 Elsevier B.V. All rights reserved.
引用
收藏
页码:1085 / 1089
页数:5
相关论文
共 50 条
  • [31] Computational Challenges of Fusion Neutronics for ITER Ports
    Serikov, A.
    Fischer, U.
    Pitcher, C. S.
    Suarez, A.
    Weinhorst, B.
    [J]. SNA + MC 2013 - JOINT INTERNATIONAL CONFERENCE ON SUPERCOMPUTING IN NUCLEAR APPLICATIONS + MONTE CARLO, 2014,
  • [32] Shutdown dose rate mitigation in the ITER upper ports
    Kolsek, Aljaz
    Juarez, Rafael
    Lopez, Antonio
    Pedroche, Gabriel
    Serikov, Arkady
    Pampin, Raul
    Bertalot, Luciano
    Udintsev, Victor
    Guirao, Julio
    Sanz, Javier
    [J]. FUSION ENGINEERING AND DESIGN, 2018, 136 : 228 - 232
  • [33] Qualification of Boron Carbide Ceramics for Use in ITER Ports
    Shoshin, Andrey
    Burdakov, Alexander
    Ivantsivskiy, Maxim
    Polosatkin, Sergey
    Klimenko, Maria
    Semenov, Alexey
    Taskaev, Sergey
    Kasatov, Dmitrii
    Shchudlo, Ivan
    Makarov, Alexander
    Davydov, Nikolay
    [J]. IEEE TRANSACTIONS ON PLASMA SCIENCE, 2020, 48 (06) : 1474 - 1478
  • [34] Assessment of occupational radiation exposure (ORE) for hands-on assistance to the remote handling at ITER ports and waste treatment
    Di Pace, L.
    Pinna, T.
    [J]. FUSION ENGINEERING AND DESIGN, 2007, 82 (15-24) : 2758 - 2764
  • [35] Nuclear Analysis for the Upper Ports in the NB Cell in ITER
    Flammini, Davide
    Pak, Sunil
    Colangeli, Andrea
    Fonnesu, Nicola
    Mballa, Frederik Sorel Mballa
    Mariano, Giovanni
    Moro, Fabio
    Polunovskiy, Eduard
    Villari, Rosaria
    [J]. IEEE TRANSACTIONS ON PLASMA SCIENCE, 2022, 50 (11) : 4551 - 4556
  • [36] Monte Carlo radiation shielding and activation analyses for the Diagnostic Equatorial Port Plug in ITER
    Serikov, A.
    Fischer, U.
    Leichtle, D.
    Pitcher, C. S.
    [J]. FUSION ENGINEERING AND DESIGN, 2012, 87 (5-6) : 690 - 694
  • [37] ITER Safety Analyses with ISAS
    W. Gulden
    S. Nisan
    M.-T. Porfiri
    I. Toumi
    T. Boubée de Gramont
    [J]. Journal of Fusion Energy, 1997, 16 : 75 - 83
  • [38] ITER safety analyses with ISAS
    NET Team, Garching, Germany
    [J]. J Fusion Energy, 1-2 (75-83):
  • [39] ITER safety analyses with ISAS
    Gulden, W
    Nisan, S
    Porfiri, MT
    Toumi, I
    deGramont, TB
    [J]. JOURNAL OF FUSION ENERGY, 1997, 16 (1-2) : 75 - 82
  • [40] Shielding conceptual designs of ITER TCP ports to protect electronics
    Martinez-Albertos, P.
    Pedroche, G.
    Dremel, M.
    Pearce, R.
    Loughlin, M.
    Le Tonqueze, Y.
    Sanz, J.
    Juarez, R.
    [J]. FUSION ENGINEERING AND DESIGN, 2022, 176