The effects of load-sensitive behavior on the operability margins of motor-operated gate valves
Description
Testing of motor-operated gate valves at various loads has produced a phenomenon we call load-sensitive behavior. This phenomenon has a significant effect on the accuracy of the methods used (and proposed) in the nuclear industry for determining that these valves can perform their design basis function. A valve subjected to tests with low flow and pressure loadings may achieve a stem thrust (at seating) analytically determined to be adequate for design basis flows and pressures, but this is no guarantee that the valve will achieve the same stem thrust when actually subjected to those design basis loads. This is because the friction at the interface between the stem and the stem nut is higher in tests with higher flow and pressure loadings, and this loss to friction is outside the control of the motor-operator's torque switch. This paper identifies a tentative method for determining, a stable, useful value for the stem/stem-nut coefficient of friction, one that can possibly be extrapolated and used in calculations to accurately estimate the design basis thrust requirements of these valves
Availability note (English)
MF available from INIS under the Report Number; OSTI as DE93013680; NTIS; INIS; US Govt. Printing Office Dep.
Files
Additional details
Publishing Information
- Imprint Pagination
- 11 p.
- Report number
- EGG-M--92476
Conference
- Title
- 12. biennial conference of the International Association on Structural Mechanics in Reactor Technology (SMIRT 12).
- Dates
- 16-20 Aug 1993.
- Place
- Stuttgart (Germany).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 24069986
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS; S42: ENGINEERING;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BEARINGS; DYNAMIC LOADS; FRICTION; GEARS; HYDRAULICS; OPERATION; REACTOR COOLING SYSTEMS; TESTING; VALVES
- Descriptors DEC
- CONTROL EQUIPMENT; COOLING SYSTEMS; EQUIPMENT; FLOW REGULATORS; MACHINE PARTS; REACTOR COMPONENTS
Optional Information
- Contract/Grant/Project number
- Contract AC07-76ID01570
- Funding organization
- Nuclear Regulatory Commission, Washington, DC (United States).
- Secondary number(s)
- CONF-930803--11.