Published March 1984 | Version v1
Journal article Metadata-only

A model for the thermal-mechanical behavior of mixed-carbide Sphere-Pac fuel pins

Creators

  • 1. Texas A and M University, Department of Nuclear Engineering, College Station, Texas

Description

The major components of a numerical model (SPECKLE-III) for the irradiation behavior of mixed-carbide Sphere-Pac fuel are described. Based on user-supplied power and outer cladding temperature history, radial profiles for the pin temperature, restructuring, fission gas behavior, and stress distribution are calculated at several axial locations as a function of irradiation time. Finite difference and finite element methods are used to solve the quasi-steady, axisymmetric governing equations. Axial slip at the fuel cladding interface is also modeled. The effects of temperature and restructuring on the fuel thermal and mechanical properties are included. Representative results are presented for a Sphere-Pac fuel irradiation experiment

Additional details

Publishing Information

Journal Title
Nucl. Sci. Eng.
Journal Volume
86
Journal Issue
3
Series
Nucl. Sci. Eng.
Journal Page Range
253-266
ISSN
0029-5639

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
16046258
Subject category
S22: GENERAL STUDIES OF NUCLEAR REACTORS;
Descriptors DEI
FINITE DIFFERENCE METHOD; FINITE ELEMENT METHOD; FUEL PINS; FUEL-CLADDING INTERACTIONS; MATHEMATICAL MODELS; MECHANICAL PROPERTIES; MIXED CARBIDE FUELS; PHYSICAL RADIATION EFFECTS; SLIP; STRESSES; TEMPERATURE DEPENDENCE; THERMODYNAMIC PROPERTIES; TIME DEPENDENCE
Descriptors DEC
ENERGY SOURCES; FUEL ELEMENTS; FUELS; ITERATIVE METHODS; MATERIALS; NUCLEAR FUELS; NUMERICAL SOLUTION; PHYSICAL PROPERTIES; RADIATION EFFECTS; REACTOR COMPONENTS; REACTOR MATERIALS; SOLID FUELS