Representation of Measured Ejector Characteristics by Simple Eulerian Bond Graph Models

H. M. Paynter

doi:10.1115/1.3140732

Representation of Measured Ejector Characteristics by Simple Eulerian Bond Graph Models

Journal of Dynamic Systems Measurement and Control ◽

10.1115/1.3140732 ◽

1985 ◽

Vol 107 (4) ◽

pp. 258-261 ◽

Cited By ~ 1

Author(s):

H. M. Paynter

Keyword(s):

Power Plants ◽

Bond Graph ◽

Nuclear Industry ◽

Graph Models ◽

Design Data ◽

Fluidic Devices ◽

Jet Pumps ◽

Fixed Constant ◽

And Control ◽

Support Facility

Ejectors (or jet pumps) are highly reliable pure fluidic devices very commonly used in power plants, propulsion systems, petrochemical processes and other thermofluid systems. However, little off-design data has been available in a form suitable for dynamic simulation and control system design. Fortunately, concerns of the nuclear industry have recently led the Idaho National Engineering Laboratory (INEL) to obtain, from their LOFT Test Support facility, ejector test data sufficiently extensive to formulate a complete model accurately describing all flow conditions. Thus an elementary fixed-constant bond graph structure will approximate complete ejector characteristics, while a model only slightly more complex fits all INEL data within experimental scatter.

Download Full-text

The Development of a Generic Qualified Digital Platform

18th International Conference on Nuclear Engineering: Volume 1 ◽

10.1115/icone18-29396 ◽

2010 ◽

Author(s):

Victor S. S. Shyu ◽

Ming-Huei Chen

Keyword(s):

Nuclear Power ◽

Power Plants ◽

Systems Design ◽

Nuclear Industry ◽

Regulatory Body ◽

Short Term ◽

Digital Platform ◽

And Control ◽

Nuclear Instrumentation

The nuclear industry and research institutes in Taiwan are conducting a joint effort project to establish a self-reliant nuclear Instrumentation and Control (I&C) system design and fabrication capabilities in Taiwan. The purposes of this project, as called Taiwan’s Nuclear I&C System (TaiNICS), are planned to support digital upgrade of the existing nuclear power plants and the new nuclear installations in Taiwan. The project will be a long term pursuit of several task branches, including establishment of a generic qualified digital platform, qualification and certification processes, nuclear I&C systems design, safety analyses for software common cause failure, licensing, and collaboration. The short term goal of this project is to submit the License Topical Report (LTR) of a generic digital platform for the review of Taiwan’s regulatory body in 2013.

Download Full-text