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.2008.02.022Additional 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
INIS
- Country of Publication
- Netherlands
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 40005624
- Subject category
- S42: ENGINEERING;
- Descriptors DEI
- COMPUTER CODES; COOLANTS; DIFFUSION; EQUATIONS; FUEL ASSEMBLIES; GRAPHITE; HELIUM; HTGR TYPE REACTORS; NUCLEAR FUELS; OXIDATION; POROSITY; SIMULATION; STEAM; SURFACES; TEMPERATURE DISTRIBUTION; THICKNESS; TURBULENT FLOW
- Descriptors DEC
- CARBON; CHEMICAL REACTIONS; DIMENSIONS; ELEMENTS; ENERGY SOURCES; FLUID FLOW; FLUIDS; FUELS; GAS COOLED REACTORS; GASES; GRAPHITE MODERATED REACTORS; MATERIALS; MINERALS; NONMETALS; RARE GASES; REACTOR MATERIALS; REACTORS
Optional Information
- Copyright
- Copyright (c) 2008 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.