Modelling of thermal mechanical behaviour of high burn-Up VVER fuel at power transients with special emphasis on the impact of fission gas induced swelling of fuel pellets
- 1. Institute of Inorganic Materials (VNIINM), Federal State Unitary Enterprise, Moscow (Russian Federation)
Description
This paper is devoted to the modelling of unsteady state mechanical and thermo-physical behaviour of high burn-up VVER fuel at a power ramp. The contribution of the processes related to the kinetics of fission gas to the consequences of pellet-clad mechanical interaction is analysed by the example of integral VVER-440 rod 9 from the R7 experimental series, with a pellet burn-up in the active part at around 60 MWd/kgU. This fuel rod incurred ramp testing with a ramp value ΔW1 ∼ 250 W/cm in the MIR research reactor. The experimentally revealed residual deformation of the clad by 30-40 microns in the 'hottest' portion of the rod, reaching a maximum linear power of up to 430 W/cm, is numerically justified on the basis of accounting for the unsteady state swelling and additional degradation of fuel thermal conductivity due to temperature-induced formation and development of gaseous porosity within the grains and on the grain boundaries. The good prediction capability of the START-3 code, coupled with the advanced model of fission gas related processes, with regard to the important mechanical (residual deformation of clad, pellet-clad gap size, central hole filling), thermal physical (fission gas release) and micro-structural (profiles of intra-granular concentration of the retained fission gas and fuel porosity across a pellet) consequences of the R7 test is shown. (authors)
Additional details
Publishing Information
- Publisher
- Organisation for Economic Co-Operation and Development - Nuclear Energy Agency
- Imprint Place
- Paris (France)
- ISBN
- 92-64-01157-9
- Imprint Title
- Pellet-clad Interaction in Water Reactor Fuels
- Imprint Pagination
- 548 p.
- Journal Page Range
- p. 477-494
Conference
- Title
- Pellet-clad Interaction in Water Reactor Fuels
- Acronym
- Seminar
- Dates
- 9-11 Mar 2004
- Place
- Aix-en-Provence (France)
INIS
- Country of Publication
- France
- Country of Input or Organization
- Nuclear Energy Agency of the OECD (NEA)
- INIS RN
- 37021761
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BURNUP; FUEL PELLETS; FUEL RODS; FUEL-CLADDING INTERACTIONS; MICROSTRUCTURE; PARAMETRIC ANALYSIS; SIMULATION; SWELLING; WWER TYPE REACTORS
- Descriptors DEC
- DEFORMATION; ENRICHED URANIUM REACTORS; FUEL ELEMENTS; PELLETS; POWER REACTORS; PWR TYPE REACTORS; REACTOR COMPONENTS; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- 9 refs.