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An Advanced Method for Transient Temperature Calculation in Fuel Element Structural Analysis

  • Published:1983-03 Issue:3 Volume:60 Page:406-419
  • ISSN:0029-5450
  • Container-title:Nuclear Technology
  • language:en
  • Short-container-title:Nuclear Technology

Author:

Lassmann K.1,Preusser Timm2

Affiliation:

1. Kernforschungszentrum Karlsruhe GmbH Institut für Reaktorentwicklung, Postfach 3640 D-7500 Karlsruhe, Federal Republic of Germany

2. Institut für Reaktortechnik Technische Hochschule Darmstadt, Petersenstrasse 30 D-6100 Darmstadt, Federal Republic of Germany

Publisher

Informa UK Limited

Subject

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

Reference26 articles.

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

2. The structure of fuel element codes

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

4. J. R. OCKENDON and W. R. HODGKINS, Eds. “Moving Boundary Problems in Heat Flow and Diffusion,”Oxford University Press, Oxford (1975).

Cited by 8 articles. 订阅此论文施引文献 订阅此论文施引文献，注册后可以免费订阅5篇论文的施引文献，订阅后可以查看论文全部施引文献

1. A review of fuel performance modelling;Journal of Nuclear Materials;2019-04

2. TRANSURANUS: a fuel rod analysis code ready for use;Journal of Nuclear Materials;1992-06

3. TRANSURANUS: a fuel rod analysis code ready for use;Nuclear Materials for Fission Reactors;1992

4. The coupling algorithm between fuel pin and coolant channel in the european accident code EAC-2;Nuclear Engineering and Design;1989-05

5. Modelling of fuel rod behaviour and recent advances of the transuranus code;Nuclear Engineering and Design;1988-03
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