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Coupled Neutronic Thermal Hydraulic Transient Analysis of the by 0vb89c4


									   Introduction to Work
        Package 4
Safety and Performance for a
 New Generation of Reactor

                        Tony Goddard
            Applied Modelling and Computation Group

                 Earth Science and Engineering

                    Imperial College London
                       Initial Aims and Objectives

•   PhD and PDRA training in systems modelling with respect to Gen IV
•   Research into modelling fault and severe accident transient behaviour of VHTR
    and GFR systems
•   Link materials performance and detailed heat transfer processes into safety
    performance research
•   Develop the ability to predict the dynamical behaviour of fission products
•   To form an overview of hydrogen production using nuclear heat from advanced
    reactors and comment on design implications
•   To work closely with UK industry and international bodies
•   Identify gaps in knowledge to supplement the UK contribution to the international
                                  Investigators and Projects
                        ‘Strong cross cutting (CC) with other WPs’
•   Chris Pain and Tony Goddard (Imperial, CC with WP1) Coupled 3D
    asymmetric neutronics/thermal hydraulics for Gen IV fault studies

        Multi-scale physics and fluids modelling … of 3D whole core spatially coupled transients
    using the FETCH code ….. with a primary research focus on … the physics and engineering

    of …selected fault and severe accident sequences for for VHTR and GFR models. Incl first
    exploration of uncertainty.   (part PDRA and 3 PhD)

•   Dominique Laurence and Mark Cotton (Manchester, CC with WP1) Heat
    transfer in advanced ceramic structures

        A PhD student will exploit the database … of advanced RANS models .. focus on
    optimising fuel/coolant exchanges for novel VHTR-GFR (gas-cooled) ceramic-prismatic cells
    in future reactor designs… explore a variety of innovative designs, such as spiral ribs, or

    twisted hexagonal rods    (1 PhD)
                                 Investigators and Projects

•   Robin Grimes (Imperial, CC with WP3) Radiation damage simulations in
    fuel                       … develop the ability to predict the dynamical evolution of fission
    products in fuel and waste forms subject to displacement damage. …will employ
    conventional molecular dynamics and a new multi-time scale simulation approach….
    underpinning …..reactor safety case models for the release of volatile fission products (in

    particular gas atoms) from fuel. (1 PhD)

•   Barry Marsden (Manchester, CC with WP2) Graphite issues for Generation
    IV              To obtain a core life to ~40years as required under Generation IV aims new
    longer lasting graphite needs to be developed for VHTR technology .. This will involve the
    development of mechanistic models that may be used to predict the irradiation behaviour of
    new novel graphitic material from knowledge of the unirradiated microstructure. (1 PhD)
                                 Investigators and Projects

•   Mike Fitzpatrick and Lyndon Edwards (OU, CC WP2) Review of candidate
    metallic materials.
    … a very good understanding of the behaviour of the materials (static and dynamic) is
    required over the entire scale range from atomic, through micro-structure, to large scale
    structures.. the OU will review international work, identify gaps in knowledge (-)

•   Ray Allen (Sheffield) Design implications of hydrogen production

    A Generation IV reactor, such as the VHTR, is considered an essential element of the
    international drive to harness nuclear heat for the zero emission production of hydrogen….,

    the Sheffield team will consider in detail the thermodynamic limitations of the available
    cycles and the extent to which these impact on the reactor design, particularly in so far as it
    places limits on the upper temperature for process use. (2 PDRA)
                     Features of activity since October 2005

•   Held two WP meetings (hosted Barry) in Manchester – Spring 2006 and


•   Meetings useful for new ideas – eg KNOO cfd benchmarking activity

•   Good forum for PhD students – supplemented by:
    –      six young people attended Stuttgart Raphael VHTR course
    –      Three attended FJ/OH course last year and two to attend 2007

•   GenIV systems excellent for originality and research training

•       UK becoming ‘inactive’ GIF member has hit stakeholders

•   Nonetheless – wider spin-offs for stakeholders from KNOO
                 Examples of wider UK industry spin-offs

•   Increases pool of people familiar with gas

    reactor issues – eg graphite materials

    issues, whole circuit modelling – MACE

    code – and coolant channel flows

•   ‘virtual’ reactor – KNOO WP4 3D coupled

    nuclear/T/H/structural modelling provides

    supportive platform for collaboration with

    SULTAN/MOD reactor research
                             Relations with EC etc

•   The commission now has robust frameworks for indirect action

    programmes for all six GenIV systems under FP7

•   We have ensured that senior figures in the Commission and EURATOM

    are aware of KNOO – they want closer contacts

•   Need for a UK ‘legal entity’ which could bring KNOO within GIF – better

    international contacts for our training and research?

•   Only current formal route to GIF is participation in FP6/FP7 indirect action

    programmes – several KNOO groups have these links
                           For our student audience
                        What are the GenIV systems?

•   Compared with Gen III, (~2015), Gen IV systems (~2040) enhanced

    sustainability (including full actinide recycling) and enhanced

    competitiveness (eg cogeneration of heat and power for process heat,

    syn-fuels and hydrogen)
                           For our student audience
                            GenIV thermal systems

•   VHTR – mainly possible co-generation,

    maybe electricity production with high

    efficiency, no actinide management, once

    through cycle

•   SCWR – Supercritical water-cooled

    reactor – mainly electricity production

    with high efficiency, maybe cogeration,

    actinide management with ‘fast’ version.
                          For our student audience
                       GenIV fast systems – and MSR

•   GFR – Mainly electricity production with

    high efficiency/actinide management

•   SFR – as for GFR

•   LFR - as for GFR

•   MSR- Molten salt reactor – full actinide

    management; electricity production – also

    MSR research links with advanced

    reprocessing technology

•   WP 4 off to a good start with good inter-university

    relations and links between WPs

•   Exciting new research areas emerging

•   Gen IV clearly a major research activity in Europe

    and we need to find better ways to interact with

    this and with GIF

•   Spin-offs to current UK industry interests

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