Implications of the EBR-II inherent safety demonstration test
- 1 April 1987
- journal article
- Published by Elsevier in Nuclear Engineering and Design
- Vol. 101 (1) , 75-90
- https://doi.org/10.1016/0029-5493(87)90152-x
Abstract
No abstract availableKeywords
This publication has 6 references indexed in Scilit:
- Whole-core damage analysis of EBR-II driver fuel elements following SHRT programNuclear Engineering and Design, 1987
- Loss-of-primary-flow-without-scram tests: Pretest predictions and preliminary resultsNuclear Engineering and Design, 1987
- Modification of EBR-II plant to conduct loss-of-flow-without-scram testsNuclear Engineering and Design, 1987
- Evolution of thermal-hydraulics testing in EBR-IINuclear Engineering and Design, 1987
- EBR-II unprotected loss-of-heat-sink predictions and preliminary test resultsNuclear Engineering and Design, 1987
- The experimental breeder reactor II inherent shutdown and heat removal tests — results and analysisNuclear Engineering and Design, 1986