Published 1978
| Version v1
Report
Restricted
Rod bundle critical heat flux at low pressure
Description
A study of critical heat flux (CHF) in a close-packed bundle of electrically heated rods which simulated the closely spaced nuclear fuel rods of the Power Burst Facility (PBF) was performed. The study examined the effects that close rod spacing and rod bowing would have on CHF at low, near-atmospheric, pressure conditions similar to PBF conditions. The PBF nuclear reactor, which is used in the Nuclear Regulatory Thermal Fuels Behavior Program, has an open vessel and a driver core with forced upward flow through the close-packed rods. The core design power is 40 MW. An effort was undertaken to design a reload core with a steady state power level of 50 MW
Availability note (English)
MF available from INIS under the Report Number; Available from NTIS., PC A02/MF A01.
Files
Restricted
The record is publicly accessible, but files are restricted to users with access.
Additional details
Publishing Information
- Imprint Pagination
- 13 p.
- Report number
- CONF-781022--21
Conference
- Title
- Meeting on nuclear power reactor safety.
- Dates
- 16 - 19 Oct 1978.
- Place
- Brussels, Belgium.
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 10449752
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- CRITICAL HEAT FLUX; FUEL ELEMENT CLUSTERS; PBF REACTOR; SIMULATION
- Descriptors DEC
- FUEL ASSEMBLIES; HEAT FLUX; PULSED REACTORS; REACTORS; TANK TYPE REACTORS