Published July 1970
| Version v1
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Correlation of rod bundle critical heat flux for water in the pressure range 150 to 725 PSIA
Description
no abstract available
Availability note (English)
MF available from INIS under the Report Number.Files
2004726.pdf
Files
(3.8 MB)
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Additional details
Publishing Information
- Imprint Pagination
- 75 p.
- Report number
- IN--1412
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 2004726
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Descriptors DEI
- FLUID FLOW; FUEL ELEMENTS; HEAT TRANSFER; HIGH TEMPERATURE; PRESSURE; REACTOR SAFETY; RODS; TESTING; CRITICAL HEAT FLUX; WATER COOLED REACTORS