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Improved Understanding of the Irradiation Creep Behaviour of Nuclear Graphite
Closed for proposals
Project Type
Project Code
I31019CRP
1645Approved Date
Status
Start Date
Expected End Date
Completed Date
1 November 2016Description
Member States have shown interest in High Temperature Gas-Cooled Reactors (HTGRs), using graphite as a moderator. If successfully demonstrated, HTGRs will achieve higher thermal efficiencies (45%- 48%) than current evolutionary LWRs and HWRs (34-36%), and thereby promise improved economics.
This CRP promotes international collaboration among IAEA Member States for the development of Gas-Cooled Reactors in the areas of graphite behaviour under irradiation.
The CRP has been planned on the advice and with the support of the IAEA Nuclear Energy Department’s Technical Working Group on Gas-Cooled Reactors (TWG-GCR). The CRP will be conducted by IAEA’s Nuclear Power Technology Development Section, in cooperation with the Division of Physical and Chemical Sciences, Nuclear Data Section.
Coordination has been agreed with the OECD-NEA, which also provides the Technical Secretariat services to the Generation-IV International Forum (GIF).
Objectives
The overall objective of this project is to enhance the prospects for demonstration of modular HTGR power generation technology by facilitating the exchange of relevant technical information and co-ordinating co-operative technology development among Member States.
Specific objectives
To support the design of structural graphite components for use in the construction of HTGR cores through the development of an improved understanding of the irradiation induced creep of graphite.