Published November 1973
| Version v1
Journal article
Measurement and significance of the oxygen threshold for oxide fuel--sodium reactions
Creators
Description
no abstract available
Additional details
Additional titles
- Augmented title (English)
- Mixed PuO_2--UO_2 fuels
Publishing Information
- Journal Title
- Trans. Amer. Nucl. Soc.
- Journal Volume
- 17
- Series
- Trans. Amer. Nucl. Soc.
- Journal Page Range
- 198-199
Conference
- Title
- Joint meeting of the American Nuclear Society and the Atomic Industrial Forum and Nuclear Energy Exhibition.
- Dates
- 11 Nov 1973.
- Place
- San Francisco, California, USA.
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 5109332
- Subject category
- S37: INORGANIC, ORGANIC, PHYSICAL AND ANALYTICAL CHEMISTRY; S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Resource subtype / Literary indicator
- Conference, No Abstract
- Descriptors DEI
- ACTIVATION ENERGY; CHEMICAL REACTIONS; CORROSION; HIGH TEMPERATURE; LIQUID METALS; NUCLEAR FUELS; OXYGEN; PLUTONIUM OXIDES; REACTION KINETICS; SODIUM; URANIUM DIOXIDE; VACANCIES; VERY HIGH TEMPERATURE
- Descriptors DEC
- ACTINIDE COMPOUNDS; ALKALI METALS; CHALCOGENIDES; CRYSTAL DEFECTS; CRYSTAL STRUCTURE; ELEMENTS; ENERGY; ENERGY SOURCES; FLUIDS; FUELS; KINETICS; LIQUIDS; METALS; NONMETALS; OXIDES; OXYGEN COMPOUNDS; PLUTONIUM COMPOUNDS; POINT DEFECTS; REACTOR MATERIALS; TRANSURANIUM COMPOUNDS; URANIUM COMPOUNDS; URANIUM OXIDES
Optional Information
- Notes
- See CONF-731101-- Published in summary form only.