Estimate of Cross Flow in High Temperature Gas-Cooled Reactor Fuel Blocks-Reference-Cited by-同舟云学术

Estimate of Cross Flow in High Temperature Gas-Cooled Reactor Fuel Blocks

Published:1982-02 Issue:2 Volume:56 Page:392-400
ISSN:0029-5450
Container-title:Nuclear Technology
language:en
Short-container-title:Nuclear Technology

Author:

Groehn H. G.¹

Affiliation:

1. Kernforschungsanlage Jülich GmbH, Institut für Reaktorbauelemente, Postfach 1913 D-5170 Jülich, Federal Republic of Germany

Publisher

Informa UK Limited

Subject

Condensed Matter Physics,Nuclear Energy and Engineering,Nuclear and High Energy Physics

Link

https://www.tandfonline.com/doi/pdf/10.13182/NT82-A32866

Reference1 articles.

1. H. G. GROEHN, “Störung der Kühlmittelverteilung in blockförmigen Brennelementen durch Bypass-Strömungen,” JüL-1185, Kernforschungsanlage Jülich (Apr. 1975).

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