Reactor vessel model flow tests for 205-fuel assembly core
Description
The results of adiabatic hydraulic tests performed on the BW 205-fuel assembly PWR vessel model are reported. The data presented include the following, all of which has been extrapolated to prototype operating conditions (W/sub s/ = 150.5 x 106 lb/h and T/sub avg/ = 600.6F): (1) core inlet flow distributions acquired during each allowable combination of pumps, and (2) reactor vessel incremental pressure drops. A development program was completed to create an optimum core inlet flow profile by determining a proper hole pattern for the core inlet flat plate flow distributor. Subsequently, final arrangement data were acquired that demonstrated the acceptability of the core inlet flow distribution; following statistical treatment, the resultant minimum flow factor measured within the core is 0.99. In addition, the unrecoverable reactor vessel pressure drop was measured and has been compared with the calculated unrecoverable loss. Agreement is very good; calculated drops are conservative by approximately 5 percent
Availability note (English)
MF available from INIS under the Report Number.
Files
Additional details
Additional titles
- Augmented title (English)
- PWR
Publishing Information
- Imprint Pagination
- 25 p.
- Report number
- BAW--10025
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 8299700
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- FLUID FLOW; FUEL ASSEMBLIES; PRESSURE DROP; PRIMARY COOLANT CIRCUITS; PWR TYPE REACTORS; REACTOR CORES; REACTOR VESSELS
- Descriptors DEC
- CONTAINERS; COOLING SYSTEMS; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- Babcock and Wilcox, Lynchburg, VA.