NDLI: Development of ultrasonic waveguide sensor for liquid level measurement in loop system

Content Provider	IET Digital Library
Author	Dhayalan, R. Saravanan, S. Manivannan, S. Rao, B. Purna Chandra
Abstract	This Letter presents an ultrasonic waveguide sensor for measuring fluctuations in a liquid level using leaky longitudinal wave L(0,2) in a coolant loop system. A 20% cold-worked D9 fuel pin clad tube of 1000 mm long, 6.6 mm outer diameter and 0.45 mm wall thickness was used as a waveguide on which the L(0,2) mode was transmitted/received along the axial direction at 500 kHz. When the waveguide got introduced into a coolant loop and partially immersed in a non-viscous liquid (water/liquid sodium), the amplitude of L(0,2) mode got reduced due to leakage. The rate of leakage depends on the characteristics of the waveguide and the embedding liquid medium. By utilising this physical property of L(0,2) mode, it is possible to predict the variations in liquid level during dynamic conditions. Experimental measurements were carried out on a mock-up test loop in which water was used as embedding liquid and two artificial notches were made on the waveguide at different depths were used as reference levels. The time-amplitude signals were monitored and the reflected energies from the bottom end of the waveguide and the notches were used as the threshold and reference amplitudes respectively for identification of water level.
Starting Page	1120
Ending Page	1122
Page Count	3
ISSN	00135194
Volume Number	56
e-ISSN	1350911X
Issue Number	Issue 21, Oct (2020)
Alternate Webpage(s)	https://digital-library.theiet.org/content/journals/el/56/21
Alternate Webpage(s)	https://digital-library.theiet.org/content/journals/10.1049/el.2020.1678
Journal	Electronics Letters
Publisher Date	2020-09-01
Access Restriction	Open
Rights Holder	© The Institution of Engineering and Technology
Subject Keyword	Cold-worked D9 Fuel Pin Clad Tube Coolant Loop System Fast Reactors Fission Reactor Coolants Fission Reactor Fuel Claddings Fission Reactor Fuel Element Fission Reactor Instrumentation Frequency 500.0 KHz Instrumentation And Experiments with Fission Reactors Liquid Level Measurement Liquid Metal Fast Breeder Reactors Mock-up Test Loop Nonviscous Liquid Nuclear Reactors Size 0.45 Mm Size 1000.0 Mm Size 6.6 Mm Ultrasonic Waveguide Sensor Water Level
Content Type	Text
Resource Type	Article
Subject	Electrical and Electronic Engineering

Sl.	Authority	Responsibilities	Communication Details
1	Ministry of Education (GoI), Department of Higher Education	Sanctioning Authority	https://www.education.gov.in/ict-initiatives
2	Indian Institute of Technology Kharagpur	Host Institute of the Project: The host institute of the project is responsible for providing infrastructure support and hosting the project	https://www.iitkgp.ac.in
3	National Digital Library of India Office, Indian Institute of Technology Kharagpur	The administrative and infrastructural headquarters of the project	Dr. B. Sutradhar bsutra@ndl.gov.in
4	Project PI / Joint PI	Principal Investigator and Joint Principal Investigators of the project	Dr. B. Sutradhar bsutra@ndl.gov.in Prof. Saswat Chakrabarti will be added soon
5	Website/Portal (Helpdesk)	Queries regarding NDLI and its services	support@ndl.gov.in
6	Contents and Copyright Issues	Queries related to content curation and copyright issues	content@ndl.gov.in
7	National Digital Library of India Club (NDLI Club)	Queries related to NDLI Club formation, support, user awareness program, seminar/symposium, collaboration, social media, promotion, and outreach	clubsupport@ndl.gov.in
8	Digital Preservation Centre (DPC)	Assistance with digitizing and archiving copyright-free printed books	dpc@ndl.gov.in
9	IDR Setup or Support	Queries related to establishment and support of Institutional Digital Repository (IDR) and IDR workshops	idr@ndl.gov.in

Liquid Metal Fuel Reactor: Four-Inch Utility Test Loop: Design, Construction, Operation, and Experimental Results

Conceptual Design of an In-Pile Package Loop for Fast Reactor Fuel Testing

Liquid Metal Fuel Reactor Experiment: The Economic Comparison of a Large-Scale LMFR Breeder & Burner

Transient Temperature Simulation of Reactor Primary Loop

Ultrasonic Imaging in Hot Liquid Sodium Using a Plate-Type Ultrasonic Waveguide Sensor

The Application of the Combined Fission Matrix Theory in Fast Reactors

Design of a delayed neutron detection system for the ASTRID Sodium-cooled fast reactor

Comparisons of Reduced Moderation Small Modular Reactors With Heavy Water Coolant

Irradiation Testing of Fuel for Core B of the Enrico Fermi Fast Breeder Reactor

Development of ultrasonic waveguide sensor for liquid level measurement in loop system

Similar Documents

Liquid Metal Fuel Reactor: Four-Inch Utility Test Loop: Design, Construction, Operation, and Experimental Results

Conceptual Design of an In-Pile Package Loop for Fast Reactor Fuel Testing

Liquid Metal Fuel Reactor Experiment: The Economic Comparison of a Large-Scale LMFR Breeder & Burner

Transient Temperature Simulation of Reactor Primary Loop

Ultrasonic Imaging in Hot Liquid Sodium Using a Plate-Type Ultrasonic Waveguide Sensor

The Application of the Combined Fission Matrix Theory in Fast Reactors

Design of a delayed neutron detection system for the ASTRID Sodium-cooled fast reactor

Comparisons of Reduced Moderation Small Modular Reactors With Heavy Water Coolant

Irradiation Testing of Fuel for Core B of the Enrico Fermi Fast Breeder Reactor

Development of ultrasonic waveguide sensor for liquid level measurement in loop system