Published June 1998 | Version v1
Journal article Metadata-only

Uranium dioxide thermal conductivity

Creators

Description

Aimed to reveal the reasons for disagreement between the data obtained by different investigators on uranium dioxide thermal conductivity temperature dependence under reactor and out-of-pile conditions the heat transfer mechanisms and the influence of oxygen content, fuel pellet porosity and irradiation on thermal conductivity of reactor fuel are considered. The recommendations on calculations of thermal conductivity and temperatures in cylindrical fuel elements in the temperature range of 713-3120 K are presented

Additional details

Additional titles

Original title (Russian)
Теплопроводност' диоксида урана

Publishing Information

Journal Title
Atomnaya Tekhnika za Rubezhom
Journal Issue
no.6
Journal Page Range
p. 3-11
ISSN
0320-9326
CODEN
ATRUA8

INIS

Country of Publication
Russian Federation
Country of Input or Organization
Russian Federation
INIS RN
30055511
Subject category
S36: MATERIALS SCIENCE; S36: MATERIALS SCIENCE;
Descriptors DEI
CHEMICAL COMPOSITION; FUEL PELLETS; IMPURITIES; NUMERICAL SOLUTION; POROSITY; SOLID FUELS; TEMPERATURE DEPENDENCE; TEMPERATURE RANGE 1000-4000 K; THERMAL CONDUCTIVITY; URANIUM DIOXIDE
Descriptors DEC
ACTINIDE COMPOUNDS; CHALCOGENIDES; FUELS; OXIDES; OXYGEN COMPOUNDS; PHYSICAL PROPERTIES; TEMPERATURE RANGE; THERMODYNAMIC PROPERTIES; URANIUM COMPOUNDS; URANIUM OXIDES

Optional Information

Notes
34 refs., 4 figs., 2 tabs.