A transient heat conduction model for reactor fuel elements
- 31 December 1971
- journal article
- Published by Elsevier in Nuclear Engineering and Design
- Vol. 15, 33-40
- https://doi.org/10.1016/0029-5493(71)90053-7
Abstract
No abstract availableKeywords
This publication has 7 references indexed in Scilit:
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- Heat-transfer analysis in loss-of-coolant accidentsNuclear Engineering and Design, 1968
- Heat transfer in water-cooled nuclear reactorsNuclear Engineering and Design, 1967
- Time dependent coolant temperature after a step increase in powerNuclear Engineering and Design, 1967
- Simplified Calculation on Thermal Transient of a UO2 Fuel RodNuclear Science and Engineering, 1961