Engineering of diagnostic equatorial port plugs for ITER

被引:3
|
作者
Phillips, G. [1 ]
Krivchenkov, Y. [1 ]
Davis, S. [1 ]
Riddle, K. [1 ]
Parsons, P. [1 ]
Thompson, V. [1 ]
Pampin, R. [1 ]
Balshaw, N. [1 ]
机构
[1] UKAEA, Culham Sci Ctr, Abingdon OX14 3DB, Oxon, England
基金
英国工程与自然科学研究理事会;
关键词
Port plug thermal analysis; Electromagnetic analysis; Neutronics analysis;
D O I
10.1016/j.fusengdes.2009.01.105
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
Within the ITER vacuum vessel, there are a significant number of diagnostics, measuring items such as plasma density, temperature and impurities: and providing a visible image of the ITER plasma. Since reliable diagnostic measurements are critical to the successful operation of ITER, robust structural design of the diagnostic supports, or Port Plugs, is also essential. The port plugs are substantial steel structures, mounted in both the equatorial and upper ports on the vacuum vessel. They not only support the diagnostics, but also provide functions of baking, cooling, and neutron shielding. Significant progress has been made in the mechanical design of the port plugs, culminating in the proposal of a new Conceptual design, which uses the lid of the port plug as a structural member. This allows the Port Plug's mass to be more efficiently distributed, providing additional space for diagnostics, and better neutron shielding. A critical aspect of the design has been to provide a suitable interface between the lid and body of the structure which will support all of the structural loads which may be applied to the port plug. The lid also allows easy access to the diagnostic components when maintenance is required. Analyses have been carried out in support of the proposed changes. Structural analysis indicates that the wall thickness of the port plug could be reduced from 130mm to 40mm. Thermal analysis has demonstrated that the cooling and baking requirement for the port plug structure is less challenging than originally thought, and hence could be carried out in a simpler fashion. Neutronics analysis has led to a better understanding of the impact of different shielding materials and cavities through the contents of the port plug, and show that it may be possible to reduce the shielding thickness from 2000mm to 1000 min. Further electromagnetic analysis has been carried out demonstrating that modelling the effect of plasma movement will not affect the resultant loads by more than 20%, and that the originally defined port plug loads were probably conservative. (C) 2009 Elsevier B.V. All rights reserved.
引用
收藏
页码:1510 / 1514
页数:5
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