Published April 1993 | Version v1
Report

FGR model improvement for high burnup fuel analysis

  • 1. Nuclear Fuel Industries Ltd, Osaka (Japan)

Description

NFI has developed and has been utilizing FPAC code (Fuel Performance Analysis Code) to analyze fuel behavior. Two main models in FPAC were revised in 1988 to expand the capability of the code based on the available high burnup fuel data at that time. Fission gas release from pellets (FGR) is modelled in FPAC based on diffusion theory. Diffusion constant in the model consists of three terms: K1, K2 and K3. K1 models the gas channels through grain boundaries and was revised to be more sensitive to fuel temperature. K2 models FGR enhancement by burnup increase and was adjusted to be less sensitive to burnup. K3 models the gas channels through open porosities. As a total, these constants were adjusted to minimize the error of code prediction. A new pellet relocation model was introduced into the code to predict the fuel temperature and clad deformation accurately. FGR is sensitive to fuel temperature and the code prediction is closely related to these models. 7 refs, 8 figs, 3 tabs

Part of:
Fission gas release and fuel rod chemistry related to extended burnup

Additional details

Publishing Information

Imprint Title
Fission gas release and fuel rod chemistry related to extended burnup
Imprint Pagination
235 p.
Journal Page Range
p. 176-182.
ISSN
1011-4289
Report number
IAEA-TECDOC--697

Conference

Title
Technical committee meeting on fission gas release and fuel rod chemistry related to extended burnup.
Dates
28 Apr - 1 May 1992.
Place
Pembroke, ON (Canada).

INIS

Country of Publication
International Atomic Energy Agency (IAEA)
Country of Input or Organization
International Atomic Energy Agency (IAEA)
INIS RN
24050759
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
BURNUP; DEFORMATION; ERRORS; FISSION PRODUCT RELEASE; FUEL ASSEMBLIES; FUEL CANS; FUEL RODS; GRAIN BOUNDARIES; MODIFICATIONS; N CODES; POST-IRRADIATION EXAMINATION; PRESSURE GRADIENTS; PWR TYPE REACTORS; TEMPERATURE DISTRIBUTION
Descriptors DEC
COMPUTER CODES; CRYSTAL STRUCTURE; ENRICHED URANIUM REACTORS; FUEL ELEMENTS; MICROSTRUCTURE; POWER REACTORS; REACTOR COMPONENTS; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS

Optional Information