HIGH TEMPERATURE ANNEALING OF IRRADIATED NUCLEAR GRADE GRAPHITE
Conference
·
OSTI ID:1484477
- Idaho National Laboratory
Previous work has shown that the properties of nuclear grade graphite are substantially affected by neutron irradiation. Understanding the details of how these changes occur and exactly what the damage consists of will enable prediction of the property changes as a function variables like dose, temperature, composition, micro and macrostructure. Other work has shown these atomic level changes or damage can be healed or annealed out by raising the irradiated graphite above its irradiation temperature. Experiments were carried out at the Idaho National Laboratory to investigate how the properties of irradiated graphite recover. By showing property recovery as a function of annealing temperature or energy, insight is provided into the type of damage that occurred during neutron irradiation. The data presented here shows recovery of thermal diffusivity, coefficient of thermal expansion, Young’s modulus and electrical resistivity between annealing temperatures of 500°C and 2380°C. Graphite grades NBG-18, IG-110 and PCEA are considered in both stressed and unstressed irradiation conditions.
- Research Organization:
- Idaho National Laboratory (INL), Idaho Falls, ID (United States)
- Sponsoring Organization:
- Advanced Reactor Technologies
- DOE Contract Number:
- AC07-05ID14517
- OSTI ID:
- 1484477
- Report Number(s):
- INL/CON-18-45742-Rev000
- Country of Publication:
- United States
- Language:
- English
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