Published October 1993
| Version v1
Miscellaneous
Performance under irradiation of material test reactor dispersion fuels
Creators
- 1. Coordenadoria para Projetos Especiais (COPESP), Sao Paulo, SP (Brazil)
- 2. Instituto de Pesquisas Energeticas e Nucleares (IPEN), Sao Paulo, SP (Brazil)
Description
The U3 O8-Al, U Alx-Al and U3 Si2-Al dispersion fuels of Material Test Reactors (MTR) are analyzed in terms of their irradiation performance. The analysis focuses fuel pre- and post-irradiation micro-structural aspects, matrix-particle chemical reactions, and the most relevant phenomena for the fuel irradiation performance. (author)
Additional details
Additional titles
- Original title (Portuguese)
- Desempenho sob irradiacao de combustiveis a dispersao de MTR
Publishing Information
- Imprint Title
- Proceedings of the 9. Brazilian Meeting on Reactor Physics and Thermal Hydraulics
- Imprint Pagination
- 559 p.
- Journal Page Range
- p. 481-486.
Conference
- Title
- 9. Brazilian Meeting on Reactor Physics and Thermal Hydraulics.
- Dates
- 25-29 Oct 1993.
- Place
- Caxambu, MG (Brazil).
INIS
- Country of Publication
- Brazil
- Country of Input or Organization
- Brazil
- INIS RN
- 25010657
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- DISPERSION NUCLEAR FUELS; FABRICATION; FUEL DISPERSION REACTORS; FUEL ELEMENTS; FUEL INTEGRITY; IEAR-1 REACTOR; IRRADIATION REACTORS; MATERIALS TESTING REACTORS; NUCLEAR FUELS; PHYSICAL RADIATION EFFECTS; POOL TYPE REACTORS; POST-IRRADIATION EXAMINATION; REACTOR SAFETY; RESEARCH AND TEST REACTORS; RESEARCH REACTORS; SPENT FUEL ELEMENTS
- Descriptors DEC
- ENERGY SOURCES; ENRICHED URANIUM REACTORS; FUELS; HOMOGENEOUS REACTORS; MATERIALS; RADIATION EFFECTS; REACTOR COMPONENTS; REACTOR MATERIALS; REACTORS; SAFETY; SOLID FUELS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- Imprint:Anais do 9. Encontro Nacional de Fisica de Reatores e Termo-Hidraulica.