ELESIM: A Computer Code for Predicting the Performance of Nuclear Fuel Elements-Reference-Cited by-同舟云学术

ELESIM: A Computer Code for Predicting the Performance of Nuclear Fuel Elements

Published:1979-08 Issue:3 Volume:44 Page:445-450
ISSN:0029-5450
Container-title:Nuclear Technology
language:en
Short-container-title:Nuclear Technology

Author:

Notley M. J. F.¹

Affiliation:

1. Atomic Energy of Canada Limited Chalk River Nuclear Laboratories, Fuel Materials Branch Chalk River, Ontario, KOJ IJO, Canada

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/NT79-A32279

Reference20 articles.

1. A Computer Program to Predict the Performance of UO2Fuel Elements Irradiated at High Power Outputs to a Burnup of 10 000 MWd/MTu

2. A. M. ROSS and R. L. STOUTE, “Heat Transfer Coefficient Between UO2and Zircaloy-2,” AECL-1552, Atomic Energy of Canada Limited (1962).

3. The thermal conductance of uranium dioxide/stainless steel interfaces

4. F. R. CAMPBELL, L. R. BOURQUE, R. DESHAIES, and M. J. F. NOTLEY, “In-Reactor Measurements of the Fuel-to-Sheath Heat Transfer Between UO2and Stainless Steel,” AECL-5400, Atomic Energy of Canada Limited (1977).

5. Thermal Contact Conductance in Reactor Fuel Elements

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