Radiation effects and differential damage in binary carbide hybrids

Lead Research Organisation: University of Liverpool
Department Name: Mech, Materials & Aerospace Engineering

Abstract

Recent innovations in material science has led to a range of new materials being identified as being usable within nuclear reactor cores, these range from SiC based ceramics, to novel alloys such as FeCrAl, and to hybrids with both metallic and ceramic properties. One specific area that is become more timely is the potential use of binary carbides such as SiC-SiC which is a system based on two distinct SiC phases. This proposal takes this work as a concept, modifying it to use SiC and TiC, two carbides with different material properties, but which together may have advantageous properties when used within a nuclear core.

This proposal examines the effects of damage on the interfaces between the TiC and SiC, for example the impact of differential expansion due to induced damage, or the potential for fission gas bubble formation at the interfaces. These are just two of the potential issues that face such systems and which are part of this work.

The project utilises the unique facilities at Argonne National Laboratory (IVEM-TANDEM), and at Oak Ridge National Laboratory (LAMDA), in concert with the ATR-NSUF programme providing access.

Planned Impact

The direct impact form this work will be three fold, firstly the classical output of results, such as via publications and conferences, in a new and novel area of nuclear materials research, highlighting that such work is key to developing new nuclear materials. An equally important impact will be the use of this work in developing a further research programme, where the results form this programme can be used to identify the key areas for research. This provides the programme with a strong base from which to work from, and which can be used to communicate with the nuclear industry the areas that need address. Finally a third impact is the strengthening of a strong international collaboration between the UK and US is also vital going forward in the development of nuclear materials, with the presentation of this work at the annual user meeting at Idaho National Laboratory.

Publications

10 25 50
 
Description It was discovered that it is possible to design a self-supporting matrix of TiC and SiC which retains structural integrity, whilst being irradiated with ions inducing damage. This leads to these materials have potential in applications where the material is expected to be impacts by damaging induced radiation, eg a nuclear reactor core.
Exploitation Route These results maybe of interest to those working in fields where structural integrity after irradiation is a key factor in their use.
Sectors Chemicals

Energy

 
Description Oak Ridge National Laboratory 
Organisation Oak Ridge National Laboratory
Country United States 
Sector Public 
PI Contribution Free flowing discussion of ideas and data for analysis, the development of new research ideas leading to collaborative proposals.
Collaborator Contribution Provision of information, and access to facilities for examination of damaged material.
Impact Joint editorship of a special issue of Journal of Nuclear Materials
Start Year 2014
 
Description Novel Materials and Damage - The Impacts of Radiation 
Form Of Engagement Activity A talk or presentation
Part Of Official Scheme? No
Geographic Reach International
Primary Audience Professional Practitioners
Results and Impact An invited conference talk at the Spring MRS Conference in Phoenix, AZ in 2018. The talk gave an overview of the projects to an international audience which has led to new collaborations being developed further.
Year(s) Of Engagement Activity 2018
 
Description Radiation Damage and Materials - Clearing up Unclear Processes 
Form Of Engagement Activity A talk or presentation
Part Of Official Scheme? No
Geographic Reach International
Primary Audience Professional Practitioners
Results and Impact Invited talk at workshop on nuclear materials development, working both with academic and industrial partners. The talk in turn has led onto new collaborative research being initiated and continued.
Year(s) Of Engagement Activity 2018
 
Description Radiation Damage in Ceramics - The View from Microscopy 
Form Of Engagement Activity A talk or presentation
Part Of Official Scheme? No
Geographic Reach International
Primary Audience Professional Practitioners
Results and Impact Invited talk at a conference highlighting the work undertaken within the research group
Year(s) Of Engagement Activity 2019
 
Description Radiation Effects in Binary Carbides 
Form Of Engagement Activity A talk or presentation
Part Of Official Scheme? No
Geographic Reach International
Primary Audience Professional Practitioners
Results and Impact Invited talk at International conference, leading to further collaborative links with international partners
Year(s) Of Engagement Activity 2018