Clinch River Breeder Reactor Prototype Sodium Pump. Final report. Prototype Pump Sodium Test Program

Technical Report · Tue Nov 15 04:00:00 EST 1983

DOI:https://doi.org/10.2172/707434· OSTI ID:707434

Frisby, W L

This document reports the results of qualification testing the Clinch River Breeder Reactor Plant Prototype Sodium Pump, Drive System and Flow Controller at the Energy Technology Engineering Center`s Sodium Pump Test Facility. The document describes the test articles, describes the test planning documents, the test facilities, the data acquisition system, and presents the test results with observations/conclusions. Pump performance testing included hydraulic performance in sodium at pony motor and main motor speeds, cavitation testing, gaseous cellular convection testing, fluid thermal transients tests and endurance testing. Shaft seal heat exchanger performance with the sodium fluid as high as 1100{sup 0}F was validated. Pump assembly procedures were verified. Drive speed control servo testing was accomplished using the pump and hydraulic test loop as a load. Sinusoid, step, and ramp responses of the Drive System were tested; Drive gain margin and phase margin were determined for both closed loop and open loop conditions. The sodium flow servo loop, consisting of a flow controller, the drive and speed control system, the pump and hydraulic loop with a Permanent Magnet flowmeter were tested for sinusoidal, step and ramp responses. Test article performance against test program objectives and specification requirements is presented.

• Research Organization: General Electric Co., Sunnyvale, CA (United States). Advanced Reactor Systems Dept.
• DOE Contract Number: AM03-76SF00893
• OSTI ID: 707434
• Report Number(s): CRBRP-GEFR--00688; ON: TI85027869
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
CLINCH RIVER BREEDER REACTOR
PERFORMANCE TESTING
PUMPS
REACTOR COOLING SYSTEMS
SODIUM
TEST FACILITIES