TAILIEUCHUNG - Quantifying water in spent fuel assemblies with neutrons: A simulation-based approach

A simulation-based study concerning three non-destructive approaches by which water in spent nuclear fuel assemblies might be quantified with neutrons is described. Three fuel types have been considered: thirty-six spent Advanced Gas-cooled Reactor (AGR) fuel pins contained in a stainless-steel can; a prototype fast reactor (PFR) spent fuel assembly and a light water reactor (LWR) spent fuel assembly – with the PFR and LWR assemblies containing mixed oxide fuels. | Progress in Nuclear Energy 145 2022 104110 Contents lists available at ScienceDirect Progress in Nuclear Energy journal homepage locate pnucene Quantifying water in spent fuel assemblies with neutrons A simulation-based approach C. Binnersley a . Ashley b P. Chard c A. Lansdell b G. O Brien b P. Shaughnessy d M. J. Joyce e f a Mirion Technologies Canberra UK Ltd. Birchwood Park Warrington UK b NSG Environmental Ltd. Scientia House Western Avenue Matrix Park Buckshaw Village Chorley UK c Mirion Technologies Canberra UK Ltd. Lower Dunbeath House Forss Business amp Technology Park Forss Thurso UK d Orano Projects Ltd. Hitching Court Abingdon Business Park Abingdon UK e Department of Engineering Lancaster University Lancaster UK f Hybrid Instruments Ltd. Gordon Manley Building Bailrigg UK A R T I C L E I N F O A B S T R A C T Keywords A simulation-based study concerning three non-destructive approaches by which water in spent nuclear fuel Spent nuclear fuel assemblies might be quantified with neutrons is described. Three fuel types have been considered thirty-six Water ingress spent Advanced Gas-cooled Reactor AGR fuel pins contained in a stainless-steel can a prototype fast reactor Detection PFR spent fuel assembly and a light water reactor LWR spent fuel assembly with the PFR and LWR as Neutrons MCNP semblies containing mixed oxide fuels. The three approaches are investigated with MCNP5 based on neutron interrogation fast neutron detection of the perturbed fast neutron flux and two approaches based on the MeV γ-ray photon emission resulting from the 1H n γ 2H capture reaction stimulated with moderated and unmoderated neutrons. For each of these approaches the following perspectives have been considered neutron transmission the influence of radiation emitted by the associated spent fuel inventory and the dependencies on water quantity and location. The moderated γ-ray assay technique is observed to return the most significant distinction .

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• Nuclear energy
• Spent nuclear fuel
• Water ingress
• Non destructive approaches
• Advanced Gas cooled Reactor
• Prototype fast reactor
• Nuclear engineering and technology
• Integral nuclear data validation
• Experimental spent nuclear fuel compositions
• Economic Co operation and Development
• Nuclear Energy Agency
• Nuclear Criticality Safety
• Expanded spent fuel isotopic compositions
• Mitigation of high energy arcing faults
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• Heterogeneous global model
• Nuclear fuel cycle
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