NEA International Workshop on

    Structural Materials for Innovative Nuclear Systems

    11-14 July 2016, Manchester, UK
    Hosted by University of Manchester


    The Nuclear Energy Agency (NEA) is organising the Fourth International Workshop on Structural Materials for Innovative Nuclear Systems (SMINS-4) in cooperation with IAEA and, with the support of the EERA Joint Programme on Nuclear Materials (JPNM) and the FP7/MatISSE project. The workshop will be held in Manchester, UK from 11 to 14 July 2016, hosted by the University of Manchester.


    Materials research is a field of growing relevance for innovative nuclear systems, such as Generation IV reactors, critical and sub-critical transmutation systems and fusion devices. For these different systems, structural materials are selected or developed taking into account the specificities of their foreseen operational environment. However, material development projects require both cross-cutting research programmes and advanced experimental/simulation facilities so as to characterise and evaluate the performance of the selected materials.

    This purpose of this workshop is to stimulate an exchange of information on current materials research programmes for different innovative nuclear systems with a view to identifying and developing potential synergies.


    The workshop will cover fundamental studies, modelling and experiments on innovative structural materials including cladding materials for the range of advanced nuclear systems such as thermal/fast systems, sub-critical systems, as well as fusion systems.

    Five topics are suggested:

    1. Fundamental studies
    2. Metal Alloys
    3. Ceramic and Ceramic Composites
    4. Advanced Materials and Processing/Joining
    5. Ion vs. neutron irradiation

    Fundamental studies should focus on the identification of mechanisms driving the response of materials under the conditions expected in innovative nuclear systems. These mechanisms may act at the atomic or at higher scale and the application of multiscale approaches, together with related problems of scale bridging or numerical methods, are of special interest. Moreover irradiation experiments and subsequent characterisation of materials with analytical techniques are included in the session if aimed at better understanding the acting mechanisms or drawing physics-based correlations.

    Metal Alloys, Ceramic and Ceramic Composites includes in- and out-of-core applications taking into account the scope of: data availability and gaps (considering also licensing issues); experimental and modelling needs for specific components or degradation modes; link between R&D, standardisation and experimental protocols; coolant effects and mechanical properties. Discussions on code development and implementation plans are also of interest. Application of SiC composites to LWR systems is of interest as an advanced concept.

    Advanced materials may include nano-grained materials, grain boundary engineered materials, nano-precipitation-strengthened materials and micro-laminates, processing and joining among other topics. Processing and Joining will focus on novel and advanced methods for the production and joining of materials for innovative nuclear systems.

    The "Ions vs. neutron irradiation" topic will focus on specific irradiation comparisons including mechanical properties and microstructural effects caused by ion or neutron irradiation. Comparative irradiation studies on a common material are also welcome.

    Please note that fuel-cladding interaction will not be covered in this edition of the workshop.


    Plenary lectures and technical sessions will be organised according to the five topics listed above.

    A workshop discussion session on ion vs. neutron irradiation will be organised.

    A poster session covering all technical subjects will be held.

    Download the preliminary programme.

    Registration and abstract submission

    Abstracts submission is now closed. Participants planning to attend the meeting are first invited to complete the registration form. Note: you will need to login into your NEA account or pre-register if have do not already have an account.

    Full papers based on accepted abstracts and invited talks must reach the by 15 May 2016.

    Important dates

    14 July 2015

    Start of registrations and abstract submissions

    15 November 2015

    Abstract submissions now closed

    March 2016

    Notification to authors

    15 May 2016

    Close of registration

    1 August 2016

    Full paper submissions


    No registration fee will be charged. If you decide not to attend following your registration, please send a cancellation note to the .

    Working language

    The working language will be English.




    • Development and characterization of diffusion-bonded Fe- and Ni-base alloys for the application in the advanced high temperature reactor systems-C. Jang (KAIST, Korea)
    • Development of Advanced Ferritic Steels for Fast Reactor Applications-S. Maloy (LANL, USA)
    • The importance of the steel microstructure in the dissolution corrosion behaviour of 316L austenitic stainless steels in static LBE-K. Lambrinou (SCK-CEN, Belgium)
    • Testing and assessment methodologies for determining 1515-Ti fuel cladding material properties- K-F. Nilsson (JRC-Petten, EC)
    • Phase Stability in an Ion Irradiated Haynes 230 at High Temperatures-O. Anderoglu (LANL, USA)
    • Corrosion resistance of 316H and Super304 austenitic steels in supercritical water-L. Nádherný (Rez, Czech Rep.)
    • A Swelling Model for Fast-Reactor Cladding Materials-A. Courcelle (CEA, France)


    • ODS steels R&D for application to advanced nuclear systems-A. Kimura (Kyoto, Japan)
    • Influence of the plastic deformation on the recrystallization of Ferritic ODS alloys-B. Hary (CEA, France)
    • Report on creep and LCF-Data on ODS-Materials for GEN IV-Reactors-A. Hobt (Uni. Stuttgart, Germany)
    • Microstructural and mechanical behavior of ODS bars and tubes-E. Oñorbe (CIEMAT, Spain)
    • Radiation Resistance of Several Novel Structural Materials Systems-S. Zinkle (Uni. Tennessee, USA)
    • MAX phase-based materials for advanced nuclear systems-T. Lapauw (KU Leuven, Belgium)
    • Ion irradiation-induced structural transitions and amorphisation tolerance in Mn+1AXn phases-Y. Wang (Peking Uni., China)
    • Mo-alloys for Advanced Reactor System Applications-B. Cheng (EPRI, USA)


    • Mo-alloys for Advanced Reactor System Applications-B. Cheng (EPRI, USA)
    • TMSR materials development: Carbide dispersed Strengthening Nickel based alloys-H. Huang (CAS, China)



    • Joining of Silicon Carbide Assemblies for Application in High Temperature Power Engineering-W. Lippmann (Uni. Dresden, Germany)
    • In-service enhancement of nuclear nanoceramics-F. Garcia-Ferré (Istituto Italiano di Tecnologia, Italy)
    • In situ observation of mechanical damage in a GFR SiC-SiCfibre ceramic composite-J. Marrow (Uni. Oxford, UK)
    • Characterising the mechanical properties of SiC fibre-SiCCVI composites-N. Robheck (Uni. Manchester, UK)


    • Ab initio trained neural-network driven kinetic Monte Carlo simulations of microstructure evolution of irradiated iron alloys-L. Messina (KTH, Sweden)
    • Multi-scale simulation of the experimental response of ion-irradiated zirconium carbide: role of interstitial clustering-J-P. Crocombette  (CEA, France)
    • Microstructural similarities and differences between neutron, ion and electron irradiation of Fe-Cr-C. Pareige (CNRS, France)
    • Investigation into neutron and ion irradiated tungsten-R. Abernethy (Uni. Oxford, UK)
    • Use of self-ion irradiation to forecast the void swelling behavior of candidate ferritic-martensitic alloys and their ODS variants at very high doses-F. Garner (Texas A&M Uni., USA)

    SESSION VII: Discussion on Ion vs. Neutron Irradiation-Chair: L. Malerba

    • Accelerated Irradiation for Emulation of Radiation Damage in Reactor-G. Was (Uni. Michigan, USA)
    • How credible is ion simulation of neutron-induced changes in mechanical properties or dimensional stability of reactor structural alloys?-F. Garner (Texas A&M Uni., USA)
    • Use of electron irradiation to study radiation damage. Do electrons simulate neutrons?-J. Henry (CEA, France)
    • Roles and limitations of ion irradiation studies for understanding neutron irradiation behaviour-S. Zinkle


    Poster Session I: Metal Alloys and Novel Pathways

    • Crack initiation in heavy liquid metals (F. Di Gabriele)
    • Role of purification systems in the solubility of alloying elements in heavy liquid metals (M. Dellabianca)
    • Study of the oxidation of austenitic alloys in supercritical water in comparison with liquid water and steam (A. Sáez-Maderuelo)
    • Creep-to-rupture test of T91 steel in air and liquid lead bismuth eutectic at 500°C (R. Hernandez)
    • Microstructural characterisation of alloy 800 H irradiated with neutrons to 1.4 dpa at 500°C and 800°C (J. Gan)
    • Preliminary results of the study on the influence of oxygen concentration and temperature on the corrosion behaviour of 316L austenitic stainless steel in static LBE (O. Klok)
    • The effect of steel cold working and surface finish on the dissolution behaviour of austenitic stainless steels in contact with static LBE (E. Charalampopoulou)
    • Corrosion behaviour of Fe-Cr-Al-based alloys exposed to oxygen-containing molten lead, supercritical water and steam (A. Jianu)
    • Low-cycle fatigue, creep-fatigue and relaxation-fatigue tests on P91 (C. Cristalli)
    • Grain boundary damage mechanisms in strained AGR claddings under irradiation (C. Barcellini)
    • Development of high-temperature test facilities for material investigations in hot liquid metal flows (A. Onea)
    • Assessment of ODS ferritic alloys with different composition Nano-mechanical design for advanced nuclear energy system (Z. Zhou)
    • Compatibility of ODS steels with Pb alloys – Influence of surface melting using pulsed electron beams on localised corrosion (A. Weisenburger)
    • Submicron sized sintered ODS steels prepared by high efficient attritor milling (B.Z. Haroune Rachid)
    • Advances in modelling new exotic materials under extreme conditions (S. Cuesta-López)
    • Neutronics of MAX phase materials (C. Grove)
    • Improving modelling of complex geometries in novel materials using 3D imaging  (Ll. M. Evans)
    • Assessment of the 475ºC-embrittlement of ODS alloys by small punch tests (M. Serrano)
    • Stabilisation of Zrn+1AlCn MAX phases by partial substitutions in the quaternary systems (Zr,M´)n+1AlCn and Zrn+1(Al, A´)Cn (E. Zapata Solvas)
    • Current status of advanced radiation resistant ODS steel (ARROS) development (T. Kyu Kim)
    • Evaluation of high-temperature mechanical property of diffusion-bonded ferritic/martensitic ODS steel (S. Hong)
    • Effects of titanium and niobium on void swelling of 15Cr/15Ni austenitic steels irradiated under ion irradiation (Y. de Carlan)


    Poster Session II: Fundamentals and Ceramics and Ions vs Neutrons

    • Advanced ceramic coatings as tritium permeation barriers for fusion systems (D. Iadicicco)
    • Impact of irradiation by low energy He, Kr and Xe ions on the structure and mechanical properties of the TiMoN coating (S. Kislitsin)
    • Radiation-tolerant nanoceramic coatings for lead fast reactors (F. García Ferré)
    • An approach to improve the retention of the fission product Ag in fuel particles for High-temperature-Reactors (H. Liu)
    • Modulation of He agglomeration in metal nitrides by swift heavy ions (A. Janse van Vuuren)
    • Description of hydrogen transport through a metal wall and prediction of embrittlement risk (D. Gaude-Fugarolas)
    • Examining thermo-mechanical coupling based multi-physics in nuclear materials using a combination of electron microscopy and spectroscopy (V. Tomar)
    • Object kinetic Monte Carlo study on the comparison between ion and neutron irradiation in ferritic/martensitic steels (M. Chiapetto)
    • Effects of high-energy Fe ion irradiation on deuterium permeation and retention of RAFM steels (G.-N. Luo)
    • Nanoindentation on ion-irradiated Fe-Cr alloys with Ni, Si and P additions (C. Heintze)
    • A snapshot of the microstructural evolution of alloy 800 H under heavy ion irradiation (E.R Anderson)
    • A new approach to emulate reactor neutron irradiation by medium-mass ions with tens of MeV (Y. Fang)
    • Primary damage induced in zirconium alloys (A. Adrych-Brunning)


    Venue, hotels, transport


    The workshop will be held at the University of Manchester. The meeting will be held in the Harwood Room, the entrance is from Altrincham Street. This is a few minutes walk from Piccadilly station or car parking is available in the multi-story car park on Charles Street. 

    The link to the campus map shows the location of the Harwood Room.


    The following hotels are all adjacent to the campus and only a few minutes walk from the meeting venue.

    Macdonald Manchester Hotel & Spa 
    London Road, Manchester, M1 2PG
    Tel.: +44 (0)344 879 9088
    International tel.: +44 (0)161 272 3200

    IBIS Hotel Manchester Centre Princess Street 
    Charles Street/Princess Street, M1 7DG MANCHESTER
    Tel.: +44 (0)161 272 5000

    The Pendulum Hotel 
    Weston Building, Sackville Street (ex. Days City) Manchester, United Kingdom
    Tel.: +44 (0)161 955 8000


    Travel by air

    If you plan to travel by air to the University of Manchester, the nearest airport is Manchester Airport. Manchester Airport is one of the largest and busiest in the country. It is located about 10 miles (16 km) south of the city centre, about 30 minutes from the university.

    The airport has a number of transport links to the city:

    Train – The airport's two terminals are linked directly to the city centre by a fast, frequent 24-hour train link to both Piccadilly and Oxford Road stations.
    Taxi – A taxi from the airport to the university will cost approximately GBP 20.
    Bus – Local buses also run to the Oxford Road and Sackville Street areas of the campus.

    Most major airlines fly to and from Manchester.

    Workshop officials, committees and contact

    Scientific and Organising Committee

    Chair and co-chair: Grace BURKE (University of Manchester, UK) and James MARROW (University of Oxford, UK)

    Thierry Auger (CNRS, France) Lorenzo MALERBA (SCK-CEN, Belgium)
    Fanny BALBAUD (CEA, France) Stuart MALOY (LANL, USA)
    Jeremy BUSBY(ORNL, USA) Simone MASSARA (NEA)
    Céline CABET (CEA, France)                        Pär OLSSON (KTH, Sweden)
    Rachid CHAOUADI (SCKCEN, Belgium) Ji-Yeon PARK (KAERI, Korea)
    Jean-Pierre CHEVALIER (CNRS, France) Manuel Alexandre POUCHON (PSI, Switzerland) 
    Jian Gan(INL, USA) Marta SERRANO (CIEMAT, Spain)
    Stéphanie CORNET (NEA) Mychailo TOLOCZKO (PNL, USA)
    Yong DAI (PSI, Switzerland)         François WILLAIME (CEA, France)
    Alessandro GESSI (ENEA, Italy)  

    Local Organising Committee

    Jane DEAKIN and Grace BURKE (University of Manchester, UK)

    All correspondence with regard to the meeting should be addressed to the workshop Secretariat:

    Dr Stéphanie CORNET
    OECD Nuclear Energy Agency
    46 Quai Le Gallo
    92100 Boulogne Billancourt,

    Dr Jane Deakin
    Materials Performance Centre
    Room A11, The Mill
    The University of Manchester
    Manchester M13 9PL
    United Kingdom


    The conference will be held in cooperation with the IAEA. IAEA travel grants will be provided on the basis of paper selection for applicants from countries eligible to receive technical assistance under the IAEA's Technical Cooperation Programme. The grant application form can be downloaded here.