文档介绍：Design and Analysis of Nuclear Steam Generator
Components Using CFX-5
M. H. Hu
Westinghouse pany
Madison, PA
Abstract
A nuclear power plant “U-Tube” steam generator is a boiling heat exchanger with shell and tubes. Feed
water enters the generator as subcooled water and goes through a series ponents to distribute into
tube bundle. In the tube bundle, the subcooled water boils, leaves the bundle as a mixture of steam and
water, and rises through moisture separation devices. Saturated water returns to a water pool where the
feed water enters and mixes with the saturated water. Steam continues rising up and leaves the steam
generator. ponent has its unique fluid conditions ranging from single phase to two-phase flow
plus corrosion particles and solute. Modules of CFD analysis for ponents are being developed
using the CFX-5 program. This paper presents four modules: (1) the lower tube bundle, (2) the sludge
collector in the water pool, (3) the steam flow through the last stage of moisture separation, and (4) the feed
water distribution ring. This paper presents results of the CFX-5 CFD analysis for these modules. The
paper demonstrates the CFX-5 role and its usefulness in the design and analysis of the nuclear steam
generator. The continued module development will cover ponents, in particular, in the tube
bundle where boiling takes place. For example, it is planned to evaluate steam and water flow through the
restricted passage of the tube support plate so that particulate deposition and solute precipitation in the
restricted passage can be examined and prevented.
Introduction
As ponent of pressurized water reactor (PWR) power plant, a steam generator is a boiling heat
exchanger that uses the reactor coolant as heat source to bring water into steam. Figure 1 illustrates a
nuclear steam generator that consists of thousands of U-shaped tubes through which the reactor coolant
passes and transfer heat to water outside the