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          Improved Understanding of the Irradiation Creep Behaviour of Nuclear Graphite

          Closed for proposals

          Project Type

          Coordinated Research Project

          Project Code

          I31019

          CRP

          1645

          Approved Date

          27 April 2009

          Status

          Active - Ongoing

          Start Date

          6 November 2009

          Expected End Date

          31 May 2016

          Completed Date

          1 November 2016

          Description

          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 objective of the CRP is to Support the Operation and Design of graphite cores by:-
          Improving the prediction of stresses within graphite parts
          Improving the Prediction of deformation of graphite parts
          Specifically, the work will focus on the phenomenon of irradiation induced creep in graphite.

          Specific objectives

          Based on the mechanisms of irradiation damage to graphite, propose a model for irradiation creep (modified dimensional change) that is consistent with the data.”

          Perform lab-scale scientific/mechanistic experiments to elaborate data already collected

          To collate historical data on all available creep models and perform an assessment of their performance and their short-coming.

          To support the design of structural graphite components for use in the construction of HTGR cores and to justified continued operation for the existing AGR cores through the development of an improved understanding of the irradiation induced creep of graphite.

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