About: Burnup is a research topic. Over the lifetime, 5172 publications have been published within this topic receiving 38691 citations. The topic is also known as: Fuel utilization.
TL;DR: FRAPCON-3 as mentioned in this paper is a FORTRAN IV computer code that calculates the steady-state response of light water reactor fuel rods during long-term burnup, including the temperature, pressure, and deformation of a fuel rod as functions of time-dependent fuel rod power and coolant boundary conditions.
Abstract: FRAPCON-3 is a FORTRAN IV computer code that calculates the steady-state response of light water reactor fuel rods during long-term burnup. The code calculates the temperature, pressure, and deformation of a fuel rod as functions of time-dependent fuel rod power and coolant boundary conditions. The phenomena modeled by the code include (1) heat conduction through the fuel and cladding, (2) cladding elastic and plastic deformation, (3) fuel-cladding mechanical interaction, (4) fission gas release, (5) fuel rod internal gas pressure, (6) heat transfer between fuel and cladding, (7) cladding oxidation, and (8) heat transfer from cladding to coolant. The code contains necessary material properties, water properties, and heat-transfer correlations. The codes` integral predictions of mechanical behavior have not been assessed against a data base, e.g., cladding strain or failure data. Therefore, it is recommended that the code not be used for analyses of cladding stress or strain. FRAPCON-3 is programmed for use on both mainframe computers and UNIX-based workstations such as DEC 5000 or SUN Sparcstation 10. It is also programmed for personal computers with FORTRAN compiler software and at least 8 to 10 megabytes of random access memory (RAM). The FRAPCON-3 code is designed to generate initial conditions for transient fuel rod analysis by the FRAPTRAN computer code (formerly named FRAP-T6).
TL;DR: In this article, the thermal conductivity of irradiated UO2 fuel is discussed considering the effects of burnup (dissolved and precipitated solid fission products), porosity and fission gas bubbles, deviation from stoichiometry and radiation damage based on single-effect results previously published on SIMFUEL (simulated extended burnup UO 2 fuel) and on radiation damage measurements.