Fuel modelling: gap conductivity, gas bubble swelling and fission gas release
Description
Irradiation of instrumented Zircaloy- and stainless steel-clad UO/sub 2/ elements has enabled one to examine the effects of filling-gas composition and pressure, fuel-to-sheath interfacial pressure and fuel-to-sheath gap, on the fuel-to-sheath heat-transfer coefficient. The experiments confirm the applicability of current models for gas-phase conductivity. The heat-transfer coefficient varied significantly during periods following a change in filling-gas pressure; this effect is attributed to the corresponding change in volume of fission gas bubbles within the fuel. A model for fission gas behavior is proposed, based on the accumulation of gas in grain boundary bubbles by diffusion or grain boundary sweeping and release when the bubbles interlink. Predicted results agree reasonably well with experimental data. 18 refs
Additional details
Publishing Information
- Publisher
- American Nuclear Society.
- Imprint Place
- Chicago, IL
- Imprint Title
- Water reactor fuel performance, ans topical meeting, 1977
- Journal Page Range
- p. 114-122.
Conference
- Title
- ANS topical meeting on water reactor fuel performance.
- Dates
- 9 - 11 May 1981.
- Place
- St Charles, IL, USA.
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 12642134
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- FISSION PRODUCT RELEASE; FISSION PRODUCTS; FUEL ELEMENTS; HEAT TRANSFER; MATHEMATICAL MODELS; STAINLESS STEELS; SWELLING; ZIRCALOY
- Descriptors DEC
- ALLOYS; CARBON ADDITIONS; CHROMIUM ALLOYS; CORROSION RESISTANT ALLOYS; DEFORMATION; ENERGY TRANSFER; IRON ALLOYS; IRON BASE ALLOYS; ISOTOPES; RADIOACTIVE MATERIALS; REACTOR COMPONENTS; STEELS; TIN ALLOYS; TRANSITION ELEMENT ALLOYS; ZIRCONIUM ALLOYS; ZIRCONIUM BASE ALLOYS