Submitted by Mi.Varokky@iaea.org on
Project Code
F11014
1750
Status
Project Author
INTERNATIONAL ATOMIC ENERGY AGENCY
Approved Date
Start Date
Expected End Date
Completed Date
CRP Closed Date
Description

To enhance the future role of nuclear energy systems, several innovative reactor designs have been proposed (e.g. Generation IV, INPRO, ADS or ITER). These new systems would enhance sustainability and reduce radioactive wastes in the nuclear fuel cycle, further enhance reactor safety, improve economics for electricity production and new applications such as the supply of process heat and/or hydrogen production, and increase proliferation resistance. The operating regimes for the structural materials in these innovative new reactor concepts extend to higher temperatures and irradiation doses than in existing power reactors and the design life will be extended to at least 60 years. In addition, some new coolants provide potentially more aggressive environment. In order to achieve these objectives, durable and expensive works, as well as intensive information exchange, are needed to develop and qualify new materials for key structural components. Therefore, international efforts should be concentrated on testing new materials.  Several recently developed structural materials have very promising characteristics, especially for application in primary components of innovative nuclear reactors. Among these are reduced activation ferritic-martensitic steels and vanadium alloys, oxide dispersion strengthened (ODS) steels, and silicon-carbide composites (SiC). Special attention should be given to materials for the nuclear fuel cladding and the reactor vessel since they act as the main barriers to release of fission products. For these and other innovative materials, continued activities related to research, development and qualification are urgently needed, hence coordinated research efforts of candidate materials should be initiated. These efforts should combine studies of their long-term stability and microstructural behaviour. Today there is clear evidence of high interest from many Member States, and various research groups would like to directly contribute to planned Round-Robin exercise in order to fully characterise and test recently developed ODS class of steels for fission and fusion applications.

Objectives

Application of nuclear techniques for characterisation and analysis of materials for nuclear technologies, supporting emerging advanced design as well as nuclear fuel cycle technologies for advanced and innovative reactors. The objective of the project 1.4.3.2 (NAPC), 1.2.4.1 (NEFW) and 1.1.5.3 (NENP) under which the CRP is being proposed is:To increase the capacity of Member States to utilize frontline nuclear techniques and key nuclear facilities to support their research and development needs;To harmonize and qualify experimental techniques and methods;To establish international consensus in the developmental efforts on advanced nuclear fuel cycle technologies.

Specific objectives

To investigate and fully characterize the material properties in the framework of coordinated research (test matrix);

To bring together scientists and engineers in order to share knowledge and enhance the capacity building in the application of nuclear techniques for investigation and characterisation of materials and components relevant to innovative reactor systems.

To formulate recommendations for harmonized characterization of materials (including testing methodology) and proposal for further improvement of fabrication and processing;

To create a material database of qualified tests (mechanical tests and microstructure characterisation);

To fabricate and distribute the agreed samples of supplied ODS materials for Round-Robin testing;

Impact

A large network of institutions was assembled with a complex set of mutually dependent tests. While many results have been published, the aim of producing a comprehensive database of properties of ODS steels within a three-to-four-year CRP were probably too ambitious. The lack of documentation internally and externally means the CRP "died" when the POs who ran it when it was "live" left.

Relevance

The CRP was extremely relevant to the development of oxide-dispersed strengthened mechanical alloys which have promising applications in fast reactors and fusion systems.

CRP PO1 Section
PHY - Physics Section
CRP PO1 Division
NAPC - Division of Physical and Chemical Sciences
CRP PO2 Section
NFCM - Nuclear Fuel Cycle and Materials Section
CRP PO2 Division
NEFW - Division of Nuclear Fuel Cycle and Waste Technology
CRP Open for proposals
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