Nuclear analysis of the ITER Cryopump Ports

被引：6

作者：

Moro, Fabio ^{[1
]}

Villari, Rosaria ^{[1
]}

Flammini, Davide ^{[1
]}

Antipenkov, Alexander ^{[2
]}

Dremel, Matthias ^{[2
]}

Levesy, Bruno ^{[2
]}

Loughlin, Michael ^{[2
]}

Juarez, Rafael ^{[3
]}

Perez, Lucia ^{[3
]}

Petrizzi, Luigino ^{[4
]}

机构：

[1] ENEA, Fus Tech Unit, Nucl Technol Lab, I-00044 Rome, Italy

[2] ITER Org, F-13115 St Paul Les Durance, France

[3] UNED, Energet Engn Dept, Madrid, Spain

[4] Commiss European Communities, DG Res & Innovat G5, B-1049 Brussels, Belgium

来源：

FUSION ENGINEERING AND DESIGN | 2015年 / 98-99卷

关键词：

ITER; Cryopump; Neutronics; Design; Analysis;

D O I：

10.1016/j.fusengdes.2015.06.077

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 machine will be equipped with 6 torus Cryopumps (TCP) that are positioned in their housings (TCPH) and integrated into the cryostat walls at B1 level in the port cells. A comprehensive nuclear analysis of the Cryopump Ports #4 and #12 has been carried out by means of the MCNP-5 Monte Carlo code in a full 3-D geometry, providing guidelines for the design of the embedded components. Radiation transport calculations have been performed in order to determine the radiation field inside the Lower Ports, up the Port Cell: 3-D neutrons and gamma maps have been provided in order to evaluate the shielding effectiveness of the TCPHs. Nuclear heating induced by neutron and photons have been estimated on the TCP and TCPH to assess the nuclear loads during plasma operations. The shutdown dose rate in the maintenance area of the Lower Ports has been assessed with the Advanced D1S method to verify the design limits. (C) 2015 Elsevier B.V. All rights reserved.

引用

页码：1561 / 1565

页数：5

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