Development of a swing check valve model for a low velocity pipe flow prediction
- 1. Korea Atomic Energy Research Institute, P.O. Box 105, Yusung 305-606, Taejeon (Korea, Republic of)
Description
A swing check valve is commonly used to prevent a reverse flow in the pipe lines of a nuclear power plant. The flow resistance by the swing check valve varies with the location of the swing disk in the velocity range lower than the required minimum velocity for a full opening of the swing disk, thereby the fluid flow is significantly affected by the dynamic motion of the swing disk. Such a phenomenon is very important to analyze safety issues, one of which is the gravity feed following a loss of the residual heat removal (RHR) which occurs during a mid-loop operation. This paper focused on the development of a new check valve model to enhance the capability of the thermal-hydraulic system code. A new angular momentum equation for the disk of a swing check valve is proposed. The proposed model is implemented into the MARS code and verified through a comparison of the simulation results with the experimental data. In particular, the results of the simulation for the gravity feed line are comparably consistent with the real test data performed in a nuclear power plant
Additional details
Identifiers
- DOI
- 10.1016/j.nucengdes.2005.12.004;
- PII
- S0029-5493(05)00436-X;
Publishing Information
- Journal Title
- Nuclear Engineering and Design
- Journal Volume
- 236
- Journal Issue
- 10
- Journal Page Range
- p. 1051-1060
- ISSN
- 0029-5493
- CODEN
- NEDEAU
INIS
- Country of Publication
- Netherlands
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 37062311
- Subject category
- S42: ENGINEERING; S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Descriptors DEI
- AFTER-HEAT REMOVAL; ANGULAR MOMENTUM; EQUATIONS; FLUID FLOW; FORECASTING; NUCLEAR POWER PLANTS; OPENINGS; REACTOR OPERATION; REACTOR SAFETY; RHR SYSTEMS; SIMULATION; THERMAL HYDRAULICS; VALVES; VELOCITY
- Descriptors DEC
- CONTROL EQUIPMENT; COOLING SYSTEMS; ENERGY SYSTEMS; EQUIPMENT; FLOW REGULATORS; FLUID MECHANICS; HYDRAULICS; MECHANICS; NUCLEAR FACILITIES; OPERATION; POWER PLANTS; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REMOVAL; SAFETY; THERMAL POWER PLANTS
Optional Information
- Copyright
- Copyright (c) 2006 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.