THERMAL CYCLING AND LEAKAGE TESTS OF 2-IN. VALVES FOR SODIUM SERVICE
Technical Report
·
OSTI ID:4117006
Tests were performed to determine the effect of thermal cycling on the across-the-seat leakage characteristics of valves considered for use in the auxiliary coolant system of the Hallam Nuclear Power Facility. Twelve 2-in. valves were thermally cycled in a sodium loop between 300 and 650 deg F and periodically tested for across-the-seat sodium leakage. Five different valve types, representing eight manufacturers, were sodium-leak tested at pressure difierentials of 10 to 30 psi, and temperatures of 395 to 685 deg F. Five bellows- seal globe valves had a leakage pattern which indicated a maximum leakage rate at a pressure differential of 20 psi. The torque-tube valve had considerable leakage in some tests caused by inconsistent valve closing. A freeze-seat valve, a solenoid valve, and four flexibleseat valves had no leakage. The flexible-seat valves were particularly easy to open and close. No valve-stem sodium leakage was observed for any of the valves tested. (auth)
- Research Organization:
- Atomics International. Div. of North American Aviation, Inc., Canoga Park, Calif.
- DOE Contract Number:
- AT(11-1)-GEN-8
- NSA Number:
- NSA-15-007445
- OSTI ID:
- 4117006
- Report Number(s):
- NAA-SR-5275
- Country of Publication:
- United States
- Language:
- English
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