Analysis of an ex-vessel break in the ITER divertor cooling loop

被引:6
|
作者
Paci, S.
Porfiri, M. T.
机构
[1] Univ Pisa, I-56100 Pisa, Italy
[2] ENEA Nucl Fus Technol, I-00044 Rome, Italy
关键词
ECART code; fusion reactors safety; ITER; LOCA;
D O I
10.1016/j.fusengdes.2005.12.004
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
In the present work the integrated ECART code, developed for severe accident analysis in LWRs, is applied on the analysis of a large ex-vessel break in the divertor cooling loop of the international thermonuclear experimental reactor (ITER). A comparison of the ECART results with those obtained by Studsvik Nuclear AB (S), utilizing the MELCOR code, was also performed in the general framework of the quality assurance program for the ITER accident analyses. This comparison gives a good agreement in the results, both for thermal-hydraulics and the environmental radioactive releases. Mainly these analyses, from the point of view of the ITER safety, confirm that the accidental overpressure inside the vacuum vessel and the Tokamak cooling water system (TWCS) Vault is always well below the design limits and that the radioactive releases are adequately confined below the ITER guidelines. (c) 2006 Elsevier B.V. All rights reserved.
引用
收藏
页码:2115 / 2126
页数:12
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