Published 1996 | Version v1
Report Restricted

Stem thrust prediction model for W-K-M double wedge parallel expanding gate valves

  • 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

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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--.