Published September 2008 | Version v1
Journal article

The modeling of graphite oxidation behavior for HTGR fuel coolant channels under normal operating conditions

  • 1. Institute of Nuclear and New Energy Technology, Tsinghua University, Beijing 100084 (China)
  • 2. CEA-CADARACHE-Nuclear Technology Department, Saint-Paul-Lez-Durance 13108 (France)

Description

The oxidation of graphite in normal operating conditions is a very important factor when evaluating the service time of the graphite structural material in a high temperature gas-cooled reactor (HTGR). This paper deals with the modeling of graphite oxidation by steam in the helium channel of a fuel block. The FEM software COMSOL is used: the turbulent flow of the coolant is simulated by using the k-ε model and the chemical reaction is expressed by the Langmuir-Hinshelwood equation. Calculations were carried out for steam pressures around 1 Pa and for different temperature distributions. The influence of burn-off and the diffusion in graphite porosities were both considered in the oxidation. Results show that oxidation mainly occurred on the graphite surface at the bottom of the core because of the higher temperature. The thickness of graphite with a burn-off higher than 8% was about 1 mm at the core base. Less than 15% of steam was consumed in the coolant channel of the fuel assemblies. Calculations also showed that the mean gasification rate in one channel for the second service time was larger than the first service time

Availability note (English)

Available from http://dx.doi.org/10.1016/j.nucengdes.2008.02.022

Additional details

Identifiers

DOI
10.1016/j.nucengdes.2008.02.022;
PII
S0029-5493(08)00156-8;

Publishing Information

Journal Title
Nuclear Engineering and Design
Journal Volume
238
Journal Issue
9
Journal Page Range
p. 2230-2238
ISSN
0029-5493
CODEN
NEDEAU

Optional Information

Copyright
Copyright (c) 2008 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.