Progress in engineering design of Indian LLCB TBM set for testing in ITER

被引：40

作者：

Chaudhuri, Paritosh ^{[1
]}

Ranjithkumar, S. ^{[1
]}

Sharma, Deepak ^{[1
]}

Danani, Chandan ^{[1
]}

Swami, H. L. ^{[1
]}

Bhattacharya, R. ^{[1
]}

Patel, Anita ^{[1
]}

Kumar, E. Rajendra ^{[1
]}

Vyas, K. N. ^{[2
]}

机构：

[1] Inst Plasma Res, Gandhinagar 382428, Gujarat, India

[2] Bhabha Atom Res Ctr, Bombay 85, Maharashtra, India

来源：

FUSION ENGINEERING AND DESIGN | 2014年 / 89卷 / 7-8期

关键词：

ITER; TBM; LLCB; Thermal-hydraulics; First wall; Shield block;

D O I：

10.1016/j.fusengdes.2014.02.001

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 Indian Lead-Lithium Ceramic Breeder (LLCB) Test Blanket Module (TBM) is the Indian DEMO relevant blanket module, as a part of the TBM program in ITER. The LLCB TBM will be tested from the first phase of ITER operation in one-half of an ITER port no. 2. LLCB TBM-set consists of LLCB TBM module and shield block, which are attached with the help of attachment systems. This LLCB TBM set is inserted in a water-cooled stainless steel frame called 'TBM frame', which also provides the separation between the neighboring TBM-sets (Chinese TBM set) in port no. 2. In LLCB TBM, high-pressure helium gas is used to cool the first wall (FW) structure and lead-lithium eutectic (Pb-Li) flowing separately around the ceramic breeder (CB) pebble bed to cool the TBM internals which are heated due to the volumetric neutron heating during plasma operation. Low-pressure helium is purged inside the CB zones to extract the bred tritium. Thermal-structural analyses have been performed independently on LLCB TBM and shield block for TBM set using ANSYS. This paper will also describe the performance analysis of individual components of LLCB TBM set and their different configurations to optimize their performances. (C) 2014 Elsevier B.V. All rights reserved.

引用

页码：1362 / 1369

页数：8

共 50 条

[41] Progress of Design and Development for the ITER Radial Neutron Camera [J].

Esposito, B. ;

Marocco, D. ;

Gandolfo, G. ;

Belli, F. ;

Bertalot, L. ;

Blocki, J. ;

Bocian, D. ;

Brolatti, G. ;

Cecconello, M. ;

Centioli, C. ;

Pereira, R. C. ;

Conroy, S. ;

Crescenzi, F. ;

Cruz, N. ;

de Bilbao, L. ;

Domenicone, A. ;

Ducasse, Q. ;

Di Mambro, G. ;

Dongiovanni, D. ;

Eletxigerra, I ;

Etxeita, B. ;

Fernandez, A. ;

Ficker, O. ;

Gallina, P. ;

Giacomin, T. ;

Ginoulhiac, G. ;

Godlewski, J. ;

Hjalmarsson, A. ;

Imrisek, M. ;

Kantor, R. ;

Kasprzak, K. ;

Kotula, J. ;

Krasilnikov, V ;

Lewandowska, M. ;

Maffucci, A. ;

Marotta, U. ;

Marzullo, D. ;

Mazzitelli, G. ;

Mazzone, G. ;

Miklaszewski, R. ;

Mikszuta-Michalik, K. ;

Maciocha, W. ;

Magagnino, S. ;

Misano, M. ;

Mlynar, J. ;

Monti, C. ;

Moro, F. ;

Ortwein, R. ;

Passeri, M. ;

Pinna, T. .

JOURNAL OF FUSION ENERGY, 2022, 41 (02)

[42] Design progress on ITER port plug test facility [J].

Levesy, B. ;

Beaumont, B. ;

Bruno, L. ;

Cerisier, T. ;

Cordier, J. J. ;

Dammann, A. ;

Giancarli, L. ;

Henderson, M. ;

Romannikov, A. ;

Rumyantsev, Y. ;

Udintsev, V. S. .

FUSION ENGINEERING AND DESIGN, 2012, 87 (7-8) :1060-1064

[43] Design progress for the ITER torus and neutral beam cryopumps [J].

Day, Chr. ;

Haas, H. ;

Hanke, St. ;

Hauer, V. ;

Luo, X. ;

Scannapiego, M. ;

Simon, R. ;

Strobel, H. ;

Fellin, F. ;

Laesser, R. ;

Masiello, A. ;

Papastergiou, St. ;

Dremel, M. ;

Mayaux, Chr. ;

Pearce, R. .

FUSION ENGINEERING AND DESIGN, 2011, 86 (9-11) :2188-2191

[44] Progress in Design, Analysis, and Manufacturing Studies of the ITER Feeders [J].

Gung, Chen-yu ;

Ilin, Yuri ;

Dolgetta, Nello ;

Chen, Yonghua ;

Bauer, Pierre ;

Jong, Cornelis ;

Sahu, Ananta ;

Devred, Arnaud ;

Mitchell, Neil ;

Lu, Kun ;

Cheng, Yong ;

Wang, Zhongwei ;

Song, Yuntao ;

Huang, Xionyi ;

Bi, Yangfan ;

Zhou, TingZhi ;

Shen, Guang ;

Ding, Kaizhong .

IEEE TRANSACTIONS ON APPLIED SUPERCONDUCTIVITY, 2012, 22 (03)

[45] Seismic analysis for conceptual design of HCCR TBM-set [J].

Lee, Dong Won ;

Park, Seong Dae ;

Jin, Hyung Gon ;

Lee, Eo Hwak ;

Kim, Suk-Kwon ;

Yoon, Jae Sung ;

Shin, Kyu In ;

Cho, Seungyon .

FUSION ENGINEERING AND DESIGN, 2016, 109 :232-236

[46] Thermo-hydraulic testing and integrity of ITER Test Blanket Module (TBM) First Wall mock-up in JAEA [J].

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

[47] Cryogenic Engineering Design of the ITER Superconducting Magnet Feeders [J].

Sahu, A. K. ;

Gung, C. Y. ;

Lu, K. ;

Bauer, P. ;

Devred, A. ;

Song, Y. ;

Bi, Y. ;

Ilin, I. ;

Rodriguez-Mateos, F. ;

Dolgetta, N. ;

Mitchell, N. .

IEEE TRANSACTIONS ON APPLIED SUPERCONDUCTIVITY, 2012, 22 (03)

[48] Engineering design of the neutral particle analyser system on ITER [J].

Afanasiev, VI ;

Kislyakov, AI ;

Kozlovski, SS ;

Kuzmin, EG ;

Ljublin, BV ;

Petrov, MP ;

Petrov, SY .

PLASMA DEVICES AND OPERATIONS, 2004, 12 (03) :209-215

[49] Engineering analyses of ITER divertor diagnostic rack design [J].

Modestov, Victor S. ;

Nemov, Alexander S. ;

Borovkov, Aleksey I. ;

Buslakov, Igor V. ;

Lukin, Aleksey V. ;

Kochergin, Mikhail M. ;

Mukhin, Eugene E. ;

Litvinov, Andrey E. ;

Koval, Alexandr N. ;

Andrew, Philip .

FUSION ENGINEERING AND DESIGN, 2013, 88 (9-10) :2038-2042

[50] Progress in Design Integration and Configuration Control of the ITER machine Baseline [J].

Kuehn, I. ;

Cordier, J-J. ;

Chiocchio, S. ;

Levesy, B. ;

Manfreo, B. ;

Reich, J. ;

Rigoni, G. .

2009 23RD IEEE/NPSS SYMPOSIUM ON FUSION ENGINEERING, 2009, :154-157

← 1 2 3 4 5 →