Modeling of Carbide Fuel Rods-Reference-Cited by-同舟云学术

Modeling of Carbide Fuel Rods

Published:1982-06 Issue:3 Volume:57 Page:343-371
ISSN:0029-5450
Container-title:Nuclear Technology
language:en
Short-container-title:Nuclear Technology

Author:

Preusser Timm¹

Affiliation:

1. Institute of Reactor Technology, Technical University Darmstadt, D-6100 Darmstadt, West 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-A26303

Reference48 articles.

1. URANUS — A computer programme for the thermal and mechanical analysis of the fuel rods in a nuclear reactor

2. Zum Wärmedurchgang im Bereich zwischen Hülle und Brennstoff eines Brennstabes

3. T. PREUSSER, “Analysis of the Carbide Fuel Experiment GOCAR-4 Using the URANUS Fuel Rod Code,” RTDA-58-81, Institute of Reactor Technology, Technical University of Darmstadt (1981).

4. The structure of fuel element codes

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