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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

          2009/04/27

          Project Status

          Closed

          Start Date

          2009/11/06

          Expected End Date

          2016/05/31

          Completed Date

          2016/11/01

          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 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.

          Impact

          Graphite serves as the moderator, reflector, and structural material in HTGRs. Its mechanical and thermal properties under irradiation directly affect the core's geometry, reactivity, and safety margins. Its dimensional changes, thermal conductivity degradation, and irradiation creep have to be well understood to ensure long-term performance. As new HTGR designs move toward deployment, regulators require robust experimental data and validated models of graphite behaviour under irradiation to support safety cases.
          The information produced in the CRP on irradiation creep in nuclear graphite provides a robust foundation for applying creep models and data to new HTGR designs.

          Relevance

          The work conducted in the CRP is highly relevant to the development and deployment of new HTGR designs. The work conducted included assembling an extensive database of irradiation creep data across a wide range of graphite grades, temperatures, and fluences. This data might enable reactor designers to identify subsets of data most relevant to their specific HTGR systems, facilitating targeted model validation and application.

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