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Laboratory Fellows


Glyn has a BSc in Theoretical Physics from the University of Newcastle-Upon-Tyne. His early career (1994-2005) was with British Nuclear Fuels plc (BNFL), where he was involved in fuel design and licensing. This included a two-year secondment to the Institute for Energy Technology (IFE) in Norway. During his time at IFE, Glyn worked on the operation and analysis of nuclear fuel behaviour experiments in the Halden Boiling Water Reactor (HBWR) under the auspices of the OECD Halden Reactor Project.

Since 2005, Glyn's work has focused on research and development associated with fuel performance – that is, the thermo-mechanical and thermo-chemical behaviour of nuclear fuel, both in-reactor and during subsequent storage and disposal. 

Key Areas of Expertise

Glyn's primary expertise is in Light Water Reactor (LWR) fuel performance and LWR core thermal-hydraulics, in particular in the context of design and licensing of LWR fuel. Glyn also has experience in advanced gas-cooled reactor (AGR) and fast reactor fuel performance. 

Key Achievements

Glyn was fuel performance technical lead for licensing of BNFL mixed oxide (MOX) fuel in Cycles 32 and 33 of the Beznau-1 reactor in Switzerland. He was also the core thermal-hydraulics technical lead for licensing of three reloads of BNFL fuel for the UK’s Sizewell B reactor, and for design and licensing of Lead Test Assemblies (LTAs) for the Loviisa reactor in Finland.

Glyn successfully completed NNL's Technical Excellence Development Programme (TEDP) in 2012, and was the Individual of the Year for Commitment to Quality at the 2015 NNL Impact Awards.

Key Positions Held

Glyn is the chair of the Nuclear Energy Agency (NEA) Expert Group on Reactor Fuel Performance (EGRFP), and is the UK representative on the International Atomic Energy Agency (IAEA) Technical Working Group on Fuel Performance and Technology (TWGFPT). Glyn is also the UK fuels and materials representative on the Halden Programme Group (HPG): the technical steering group for the fuels and materials irradiation programme of the OECD Halden Reactor Project.

Key Publications

Glyn has authored around 20 external publications and more than 80 technical reports. External publications include the following:

  • D Shepherd, G D Rossiter, I D Palmer, G Marsh and M Fountain, “Technology readiness level (TRL) assessment of advanced nuclear fuels”, TopFuel 2015, Zurich, Switzerland, September 2015
  • G Rossiter, “Understanding and modelling fuel behaviour under irradiation”, in I Crossland (Ed.), “Nuclear fuel cycle science and engineering”, Woodhead Publishing, 2012
  • G Rossiter and M Mignanelli, “The characteristics of spent AGR fuel: what can we learn from spent LWR fuel?”, IChemE nuclear fuel cycle conference, Manchester, UK, April 2012
  • G Rossiter, “Development of the ENIGMA fuel performance code for whole core analysis and dry storage assessments”, Nuclear Engineering and Technology, Vol. 43 No. 6, December 2011
  • T Tverberg, W Wiesenack, S K Yagnik and G Rossiter, “Behavior of homogeneous and heterogeneous MOX fuel”, 2010 LWR Fuel Performance/TopFuel/WRFPM, Orlando, Florida, September 2010
  • A Alapour, R M Joyce, A S DiGiovine, S Tarves, N Patino, A Worrall, R Gregg and G Rossiter, “Robust PCI monitoring during PWR operation at Southern Nuclear”, 2010 LWR Fuel Performance/TopFuel/WRFPM, Orlando, Florida, September 2010
  • A Worrall, T J Abram, R W H Gregg, K W Hesketh, I D Palmer, G D Rossiter and G M Thomas, “Plutonium utilization options in future UK PWRs using MOX and inert matrix fuels”, Global-2007, Idaho, USA, September 2007
  • R Weston, I D Palmer, J M Wright, G D Rossiter, R C Corcoran, T C Gilmour, C T Walker and S Bremier, “Progress on SBR MOX fuel development”, TopFuel, Stockholm, Sweden, May 2001
  • R Chawla, C Hellwig, F Jatuff, U Kasemeyer, G Ledergerber, B-H Lee and G Rossiter, “First experimental results from neutronics and in-pile testing of a Pu-Er-Zr oxide inert matrix fuel”, TopFuel, Stockholm, Sweden, May 2001
  • G D Rossiter, P M A Cook and R Weston, “Isotopic modelling using the ENIGMA-B fuel performance code”, IAEA technical committee meeting on nuclear fuel behaviour modelling at high burnup and its experimental support, Windermere, UK, June 2000
  • I D Palmer, G D Rossiter and R J White, “Development and validation of the ENIGMA code for MOX fuel performance modelling”, IAEA symposium on MOX fuel cycle technologies for medium and long term deployment, Vienna, Austria, May 1999