Published October 2019
| Version v1
Miscellaneous
Comparison of the oxidation behavior between pyrolytic carbon and nuclear-grade graphite at temperatures between 700-1000 Celsius degrees
Creators
- 1. IPN, Centro de Investigacion y de Estudios Avanzados, Unidad Saltillo, Av. Industria Metalurgica No. 1062, Zona Industrial, 25900 Ramos Arizpe, Coahuila (Mexico)
Description
The TRISO coated fuel particle (tri structural isotropic) has an uranium oxide kernel coated with three layers of pyrolytic carbon (PyC) and one of silicon carbide (SiC). Although originally designed for the high temperature reactor (HTR), this fuel is currently being considered as an accident tolerant fuel for the light water reactor (LWR). For this reason, it is very important to understand the stability of these coatings under oxidation conditions. In this work, we compare the oxidation behavior of different coatings of PyC and nuclear grade graphite in air at temperatures of 700 to 1000 Celsius degrees. (Author)
Availability note (English)
Available from the Instituto Nacional de Investigaciones Nucleares. Centro de Informacion y Documentacion, 52750 Ocoyoacac, Estado de Mexico (MX), E-mail: mclaudia.gonzalez@inin.gob.mxAdditional details
Publishing Information
- Publisher
- Sociedad Nuclear Mexicana
- Imprint Place
- Ciudad de Mexico (Mexico)
- Imprint Pagination
- 5 p.
Conference
- Title
- peaceful applications of nuclear energy for the Mexico benefit
- Original Conference Title
- 30. Congreso Anual de la SNM: aplicaciones pacificas de la energia nuclear en beneficio de Mexico
- Acronym
- 30. SNM Annual Congress
- Dates
- 4-7 Aug 2019
- Place
- Monterrey, Nuevo Leon (Mexico)
INIS
- Country of Publication
- Mexico
- Country of Input or Organization
- Mexico
- INIS RN
- 51005332
- Subject category
- S36: MATERIALS SCIENCE;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- ACCIDENT-TOLERANT NUCLEAR FUELS; AIR; COATED FUEL PARTICLES; COATINGS; COMPARATIVE EVALUATIONS; GRAPHITE; KERNELS; LAYERS; OXIDATION; PYROLYTIC CARBON; SILICON CARBIDES; STABILITY; TEMPERATURE RANGE 0400-1000 K; URANIUM OXIDES; WATER COOLED REACTORS; WATER MODERATED REACTORS
- Descriptors DEC
- ACTINIDE COMPOUNDS; CARBIDES; CARBON; CARBON COMPOUNDS; CHALCOGENIDES; CHEMICAL REACTIONS; ELEMENTS; ENERGY SOURCES; EVALUATION; FLUIDS; FUEL PARTICLES; FUELS; GASES; MATERIALS; MINERALS; NONMETALS; NUCLEAR FUELS; OXIDES; OXYGEN COMPOUNDS; REACTOR MATERIALS; REACTORS; SILICON COMPOUNDS; TEMPERATURE RANGE; URANIUM COMPOUNDS