Stem thrust prediction model for W-K-M double wedge parallel expanding gate valves
Creators
- 1. Kalsi Engineering Inc., Sugar Land, TX (United States)
- 2. Electric Power Research Institute, Palo Alto, CA (United States)
Description
An analytical model for determining the required valve stem thrust during opening and closing strokes of W-K-M parallel expanding gate valves was developed as part of the EPRI Motor-Operated Valve Performance Prediction Methodology (EPRI MOV PPM) Program. The model was validated against measured stem thrust data obtained from in-situ testing of three W-K-M valves. Model predictions show favorable, bounding agreement with the measured data for valves with Stellite 6 hardfacing on the disks and seat rings for water flow in the preferred flow direction (gate downstream). The maximum required thrust to open and to close the valve (excluding wedging and unwedging forces) occurs at a slightly open position and not at the fully closed position. In the nonpreferred flow direction, the model shows that premature wedging can occur during ΔP closure strokes even when the coefficients of friction at different sliding surfaces are within the typical range. This paper summarizes the model description and comparison against test data
Files
Additional details
Publishing Information
- Imprint Title
- Proceedings of the 4th NRC/ASME symposium on valve and pump testing
- Imprint Pagination
- 719 p.
- Journal Page Range
- p. 1B.93-1B.113.
- Report number
- NUREG/CP--0152
Conference
- Title
- 4. NRC/ASME symposium on valve and pump testing in nuclear power plants.
- Dates
- 15-18 Jul 1996.
- Place
- Washington, DC (United States).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 28013962
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- COMPUTERIZED SIMULATION; NUCLEAR POWER PLANTS; PERFORMANCE TESTING; VALVES
- Descriptors DEC
- CONTROL EQUIPMENT; EQUIPMENT; FLOW REGULATORS; NUCLEAR FACILITIES; POWER PLANTS; SIMULATION; TESTING; THERMAL POWER PLANTS
Optional Information
- Secondary number(s)
- CONF-9607103--.