Neutronic analyses for the equatorial diagnostic port plug #12 in ITER

被引:1
|
作者
Flammini, D. [1 ]
Chaudhary, A. [2 ]
Colangeli, A. [1 ]
Fonnesu, N. [1 ]
Guirao, J. [2 ]
Gupta, K.
Kalwale, S. [2 ]
Mariano, G. [1 ]
Moro, F. [1 ]
Previti, A. [1 ]
Quatrevaux, M. [2 ]
Shigin, P. [2 ]
Udintsev, V. S. [2 ]
Villari, R. [1 ]
机构
[1] ENEA, FSN Dept, Via E Fermi 45, I-00044 Frascati, Rome, Italy
[2] ITER Org, Route Vinon Verdon, St Paul Les Durance, France
关键词
ITER; Neutronics; Equatorial port; Monte Carlo;
D O I
10.1016/j.fusengdes.2023.113639
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 standard modular Equatorial Port Plug (EPP) in ITER is at its final stage of design. It serves as common platforms for different diagnostics systems which are integrated together in three cassettes called Diagnostic Shielding Module (DSM). The equatorial port #12 will host an EPP with six diagnostics: the Visible-Infrared Camera and the H-alpha Monitor integrated in DSM #1, the Glow Discharge Wall Conditioning, the Radial X-rays Camera and the Hard X-rays Monitor, installed in DSM #2 and the Core Thomson Scattering in DSM #3. The EPP should not only serve as a diagnostic port, but also it has to provide the necessary shielding to allow for maintenance in port interspace and in port cell. This work is devoted to nuclear analyses performed to assess the nuclear loads and the shielding performance of the system. A very detailed neutronic model of EPP #12 has been developed and integrated in a 40 degrees ITER sector MCNP model (C-model). The implemented model has been used to evaluate the neutron and gamma flux distributions, nuclear heating, radiation induced damage, tritium and helium concentration at the ITER end of life in the port plug area.
引用
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页数:6
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