Published December 1978 | Version v1
Report Restricted

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

Restricted

The record is publicly accessible, but files are restricted to users with access.

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.

Optional Information

Secondary number(s)
CONF-781202--41.