Experimental and numerical validation of an ultrasonic visualization system for nuclear reactor application
Creators
- 1. von Karman Institute for Fluid Dynamics (Belgium)
- 2. Belgian Nuclear Research Center (Belgium)
Description
This paper deals with the design of ultrasonic imaging systems for the next generation of nuclear reactors cooled by liquid metal. Indeed, a generation IV research nuclear reactor is being developed by the Belgian Nuclear Research Center (SCK-CEN) in the frame of the MYRRHA project (for Multipurpose hYbrid Research Reactor for High-tech Applications). This sub-critical/critical reactor is cooled by Lead-Bismuth Eutectic (LBE). The opacity of this liquid metal requires the development of an ultrasonic visualization system for internal inspection and object detection. But due to the peculiar conditions met in the core of the reactor, velocity as well as temperature gradients are expected and are likely to affect directly the ultrasonic propagation. The objective of this work is to validate the ultrasonic imaging strategy by tests performed in a dedicated test rig and by numerical simulations using a ray-tracing method. The experimental investigations have been performed on a specific water facility reproducing conditions similar to those encountered in the core of the MYRRHA reactor. These conditions include the propagation over large distance, and the presence of temperature and velocity gradients. In the MYRRHA reactor application, the distance to be travelled by the acoustic waves of the visualization system is about 5 m, including a reflection. The acoustic absorption, the scattering losses, the beam divergence and the transmitted energy during reflection have been determined as a function of the travelled distance. The experimental values are compared with the literature for validation. The presence of temperature and velocity gradients in the core of the reactor is due to the coolant circulation. These gradients are about 5 K over 0.1 m and 1 m/s over 0.2 m, respectively, and are reproduced in the facility for investigating their influence on the propagation of ultrasounds. The experimental data are used for improving and validating a ray-tracing algorithm. This algorithm is then applied to the full scale application for validating the ultrasonic visualization system for nuclear reactor application. (authors)
Additional details
Publishing Information
- Imprint Pagination
- 1 p.
- Report number
- ANIMMA--2015-IO-341
Conference
- Title
- 4. International Conference on Advancements in Nuclear Instrumentation Measurement Methods and their Applications
- Acronym
- ANIMMA 2015
- Dates
- 20-24 Apr 2015
- Place
- Lisboa (Portugal)
INIS
- Country of Publication
- United States
- Country of Input or Organization
- France
- INIS RN
- 47102329
- Subject category
- S46: INSTRUMENTATION RELATED TO NUCLEAR SCIENCE AND TECHNOLOGY; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- ALGORITHMS; COMPARATIVE EVALUATIONS; COMPUTERIZED SIMULATION; DETECTION; EUTECTICS; INSPECTION; LIQUID METAL COOLED REACTORS; MYRRHA FACILITY; OPACITY; REACTOR COOLING SYSTEMS; REACTOR CORES; REFLECTION; SOUND WAVES; TEMPERATURE GRADIENTS; ULTRASONIC TESTING; VALIDATION; WAVE PROPAGATION
- Descriptors DEC
- ACCELERATOR-DRIVEN SUBCRITICAL SYSTEMS; ACOUSTIC TESTING; COOLING SYSTEMS; ENERGY SYSTEMS; EPITHERMAL REACTORS; EVALUATION; EXPERIMENTAL REACTORS; FAST REACTORS; MATERIALS TESTING; MATHEMATICAL LOGIC; NONDESTRUCTIVE TESTING; OPTICAL PROPERTIES; PHYSICAL PROPERTIES; REACTOR COMPONENTS; REACTORS; RESEARCH AND TEST REACTORS; RESEARCH REACTORS; SIMULATION; SUBCRITICAL ASSEMBLIES; TESTING