Evaluation of helium cooling for fusion divertors-Reference-Cited by-同舟云学术

Evaluation of helium cooling for fusion divertors

Published:1994-08 Issue:1-3 Volume:25 Page:263-271
ISSN:0920-3796
Container-title:Fusion Engineering and Design
language:en
Short-container-title:Fusion Engineering and Design

Author:

Baxi C.B.

Publisher

Elsevier BV

Subject

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

Reference11 articles.

1. ITER Concept Definition,1989

2. J. Haines, BPX divertor design and R&D program, 14th Symp. on Fusion Engineering, San Diego, Ca.

3. J. Schlosser et al., Development of high heat flux components for continuous operation in tokamaks, 14th Symp. on Fusion Engineering, San Diego, CA.

4. US position paper for safety and environment activities related to ITER;Piet;ITER/US/93/TE/ SE-2,1993

5. Design and analysis of helium-cooled divertor module for fusion reactors;Baxi,1993

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1. Optimal design of divertor heat sink with different geometric configurations of sectorial extended surfaces;Fusion Engineering and Design;2015-11

2. An experimental and numerical study of flow and heat transfer in helium cooled divertor finger mock-up with sectorial extended surface;Applied Thermal Engineering;2015-05

3. COMPARISON OF COOLING SCHEMES FOR HIGH HEAT FLUX COMPONENTS COOLING IN FUSION REACTORS;Acta Polytechnica;2015-04-30

4. Numerical studies on helium cooled divertor finger mock up with sectorial extended surfaces;Fusion Engineering and Design;2014-11

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