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Updated: Jul 13, 2025

Laser-heating and Radiance Spectrometry for the Study of Nuclear Materials in Conditions Simulating a Nuclear Power Plant Accident
Published on: December 14, 2017
A laser-based system to heat nuclear fuel pellets at high temperature
C Cifuentes Quintal1,2, M Reymond1,2, F Fiorito1
1CEA, DES, IRESNE, DEC, Cadarache, F-13108 Saint-Paul-Lez-Durance, France.
Laser heating offers a novel method for nuclear fuel research, enabling controlled annealing of uranium dioxide (UO2) pellets up to 1500°C. This technique provides precise temperature control for studying material properties and microstructure evolution.
Area of Science:
- Nuclear Engineering
- Materials Science
- Thermal Analysis
Background:
- Annealing tests are crucial for understanding nuclear fuel behavior.
- Conventional heating methods face limitations in control and speed.
- Investigating thermophysical properties, microstructure, and gas release requires precise thermal treatment.
Purpose of the Study:
- To introduce a laser-heating technique as an alternative to conventional annealing for nuclear fuel research.
- To demonstrate controlled and isothermal heating of uranium dioxide (UO2) fuel pellets.
- To explore the potential for rapid heating rates and high temperatures in nuclear fuel analysis.
Main Methods:
- Development of an indirect laser-heating system using a two-compartment tungsten crucible.
- Utilizing a laser susceptor for efficient and homogeneous heating of the nuclear fuel sample.
- Employing two 500 W lasers to achieve target temperatures and heating rates.
Main Results:
- Successfully heated UO2 samples to 1500°C with a maximum heating rate of 30°C/s.
- Demonstrated the feasibility of isothermal and controlled heating using the proposed laser system.
- The system showed scalability for higher heating rates and temperatures with increased laser power.
Conclusions:
- The laser-heating method provides a viable and controllable alternative for nuclear fuel annealing studies.
- This technique can be adapted for various sample geometries and materials beyond UO2.
- The system's scalability suggests potential for advanced nuclear fuel performance research.
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