Post DNB Heat Transfer Experiments for PWR Fuel Assemblies

Dnb Tests for Us-apwr Fuel

Cfd Methodology and Validation for Single-phase Flow in Pwr Fuel Assemblies

This paper presents the CFD modeling methodology and validation for steady-state, normal operation in a PWR fuel assembly. This work is part of a program that is developing a CFD methodology for modeling and predicting single-phase and two-phase flow conditions downstream of structural grids that have mixing devices. The purpose of the mixing devices (mixing vanes in this case) is to increase t...

2d Natural Convection and Radiation Heat Transfer Simulations of a Pwr Fuel Assembly within a Constant Temperature Support Structure

Two-dimensional simulations of steady natural convection and radiation heat transfer for a 14x14 pressurized water reactor (PWR) spent nuclear fuel assembly within a square basket tube of a typical transport package were conducted using a commercial computational fluid dynamics package. The assembly is composed of 176 heat generating fuel rods and 5 larger guide tubes. The maximum cladding temp...

Fission Gas Release Comparison for PWR Duplex Fuel Pellets

Current research has identified Duplex pellets as an effective strategy for decreasing the centerline temperature of the fuel. However, before this design can be widely utilized several areas, including fission gas release, need to be better characterized. Therefore, this paper seeks to ascertain the relative difference in fission gas release between a standard solid UO2 reference design and a ...

Nanofluids for Heat Transfer Enhancement – A Review

A nanofluid is a dilute liquid suspension of particles with at least one critical dimension smaller than ~100 nm. Research works so far suggest that nanofluids offer excellent heat transfer enhancement over conventional base fluids. The enhancement depends on several factors such as particle shape, particle size distribution, volume fraction of nanoparticles, temperature, pH, and thermal conduc...