Graphite is widely used as a major internal structural material in high temperature gas-cooled reactors (HTRs). In order to evaluate service lives of graphite components, both the fast neutrons and temperature distributions inside the reactor core are required as input data for the irradiation-induced stress analysis. Since the fast neutron distributions may vary along the vertical direction due to the movement of the control rods, the corresponding location of the maximum neutron fluence changes with different in-core temperature levels. In this paper, the effect of the in-core temperature on both the stresses of graphite components due to irradiation and the corresponding life evaluations are studied numerically. The associated constitutive law for the simulation of irradiated graphite covering properties, dimensional changes and creep is briefly reviewed. A FORTRAN code based on user subroutines of MSC.MARC is developed in INET in order to perform three-dimensional finite element analysis of irradiated behavior of the graphite components for the HTRs. A side reflector graphite model is established and analyzed under a prescribed fast neutron distribution and several temperature levels. The results of irradiation-induced stresses and failure probability of the side reflector are obtained and the impact of temperature levels is discussed.
Skip Nav Destination
17th International Conference on Nuclear Engineering
July 12–16, 2009
Brussels, Belgium
Conference Sponsors:
- Nuclear Engineering Division
ISBN:
978-0-7918-4354-3
PROCEEDINGS PAPER
Effect of In-Core Temperature on the Life Evaluation of Graphite Component Available to Purchase
Xiang Fang,
Xiang Fang
Tsinghua University, Beijing, China
Search for other works by this author on:
Haitao Wang
Haitao Wang
Tsinghua University, Beijing, China
Search for other works by this author on:
Xiang Fang
Tsinghua University, Beijing, China
Suyuan Yu
Tsinghua University, Beijing, China
Haitao Wang
Tsinghua University, Beijing, China
Paper No:
ICONE17-75828, pp. 657-660; 4 pages
Published Online:
February 25, 2010
Citation
Fang, X, Yu, S, & Wang, H. "Effect of In-Core Temperature on the Life Evaluation of Graphite Component." Proceedings of the 17th International Conference on Nuclear Engineering. Volume 4: Codes, Standards, Licensing and Regulatory Issues; Student Paper Competition. Brussels, Belgium. July 12–16, 2009. pp. 657-660. ASME. https://doi.org/10.1115/ICONE17-75828
Download citation file:
11
Views
Related Proceedings Papers
Related Articles
Lifetime Analysis of Fusion Reactor First Wall Components
J. Pressure Vessel Technol (May,1983)
Thermal Predictions of the AGR-3/4 Experiment With Time-Varying Gas Gaps
ASME J of Nuclear Rad Sci (October,2015)
Related Chapters
A Study of Irradiation-Induced Growth of Modified and Advanced Zr-Nb System Alloys after Irradiation in the VVER-1000 Reactor Core at Temelin NPP
Zirconium in the Nuclear Industry: 20th International Symposium
Long.Term Reactivity Change and Control: On.Power Refuelling
Fundamentals of CANDU Reactor Physics
Analysis of Components: Strain- and Deformation-Controlled Limits
Design & Analysis of ASME Boiler and Pressure Vessel Components in the Creep Range