In this paper, an analysis of the Integral Inherently Safe LWR design (I2S-LWR), a reactor concept developed by an international collaboration led by the Georgia Institute of Technology, within a US DOE Nuclear Energy University Program (NEUP) Integrated Research Project (IRP) is considered. | Reactor physics modelling of accident tolerant fuel for LWRs using ANSWERS codes EPJ Nuclear Sci. Technol. 2 14 2016 Nuclear Sciences . Lindley et al. published by EDP Sciences 2016 amp Technologies DOI epjn 2016012 Available online at http REGULAR ARTICLE Reactor physics modelling of accident tolerant fuel for LWRs using ANSWERS codes Benjamin A. Lindley1 Dan Kotlyar2 Geoffrey T. Parks2 John N. Lillington1 and Bojan Petrovic3 1 Amec Foster Wheeler Dorchester UK 2 Department of Engineering University of Cambridge Cambridge UK 3 Georgia Institute of Technology Georgia USA Received 10 September 2015 Received in final form 5 February 2016 Accepted 15 February 2016 Published online 25 March 2016 Abstract. The majority of nuclear reactors operating in the world today and similarly the majority of near-term new build reactors will be LWRs. These currently accommodate traditional Zr clad UO2 PuO2 fuel designs which have an excellent performance record for normal operation. However the events at Fukushima culminated in significant hydrogen production and hydrogen explosions resulting from high temperature Zr steam interaction following core uncovering for an extended period. These events have resulted in increased emphasis towards developing more accident tolerant fuels ATFs -clad systems particularly for current and near-term build LWRs. R amp D programmes are underway in the US and elsewhere to develop ATFs and the UK is engaging in these international programmes. Candidate advanced fuel materials include uranium nitride UN and uranium silicide U3Si2 . Candidate cladding materials include advanced stainless steel FeCrAl and silicon carbide. The UK has a long history in industrial fuel manufacture and fabrication for a wide range of reactor systems including LWRs. This is supported by a national infrastructure to perform experimental and theoretical R amp D in fuel performance fuel transient behaviour and reactor physics. In this paper an analysis
