High heat flux thermal–hydraulic analysis of ITER divertor and blanket systems-Reference-Cited by-同舟云学术

High heat flux thermal–hydraulic analysis of ITER divertor and blanket systems

Published:1998-09 Issue: Volume:39-40 Page:323-331
ISSN:0920-3796
Container-title:Fusion Engineering and Design
language:en
Short-container-title:Fusion Engineering and Design

Author:

Raffray A.R,Chiocchio S,Ioki K,Krassovski D,Kubik D,Tivey R

Publisher

Elsevier BV

Subject

Mechanical Engineering,General Materials Science,Nuclear Energy and Engineering,Civil and Structural Engineering

Reference10 articles.

1. K. Ioki, et al., ITER first wall/shield blanket, Proc. Fusion Eng. Des. 39-40 (1998) 585–592.

2. G. Janeschitz, et al., Divertor development for ITER, Fusion Eng. Des. 39-40 (1998) 173–187.

3. Proc. ITER Thermal Hydraulic Technical Meeting, JET, Abingdon, UK, September, 1996.

4. A.R. Raffray, R. Jakeman, Critical heat flux analysis of divertor vertical target, ITER Memo, G16MD 70 96-10-31 W 0.1, Garching, Germany, 31 October, 1996.

5. J. Schlosser, F. Escourbiac, Manufacture and Testing of Permanent Components: Optimisation of cooling system, final report (short version), ITER Task T222.4, Note P/CO 96/08, DSM/DRFC/STID, Association EURATOM-CEA, Cadarache, France, 30 September, 1996.

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