Internal fluid flow management analysis for Clinch River Breeder Reactor Plant sodium pumps
Description
The Clinch River Breeder Reactor Plant (CRBRP) sodium pumps are currently being designed and the prototype unit is being fabricated. In the design of these large-scale pumps for elevated temperature Liquid Metal Fast Breeder Reactor (LMFBR) service, one major design consideration is the response of the critical parts to severe thermal transients. A detailed internal fluid flow distribution analysis has been performed using a computer code HAFMAT, which solves a network of fluid flow paths. The results of the analytical approach are then compared to the test data obtained on a half-scale pump model which was tested in water. The details are presented of pump internal hydraulic analysis, and test and evaluation of the half-scale model test results
Availability note (English)
MF available from INIS under the Report Number; Available from NTIS., PC A03/MF A01.
Files
Additional details
Publishing Information
- Imprint Pagination
- 27 p.
- Report number
- CRBRP-GEFR-SP--139
Conference
- Title
- ASME meeting.
- Dates
- 10 - 15 Dec 1978.
- Place
- San Francisco, CA, USA.
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 11500286
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- CLINCH RIVER BREEDER REACTOR; COMPUTER CALCULATIONS; FLUID FLOW; HYDRAULICS; MOCKUP; PRIMARY COOLANT CIRCUITS; PUMPS; SPATIAL DISTRIBUTION; THERMAL STRESSES
- Descriptors DEC
- BREEDER REACTORS; COOLING SYSTEMS; DISTRIBUTION; EPITHERMAL REACTORS; FAST REACTORS; FBR TYPE REACTORS; LIQUID METAL COOLED REACTORS; POWER REACTORS; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REACTORS; SODIUM COOLED REACTORS; STRESSES; STRUCTURAL MODELS
Optional Information
- Secondary number(s)
- CONF-781202--41.