The use of gadolinium as a burnable poison within U3Si2 fuel pellets
Turner, J., Buckley, J., Phillips, G., Abram, T.J.
Published in Journal of nuclear materials (01.10.2018)
Published in Journal of nuclear materials (01.10.2018)
Get full text
Journal Article
Development of high-temperature-steam resistant UN via the addition of UB2
Pritchard, M.J., Buckley, J., Abram, T.J., Turner, J.
Published in Journal of nuclear materials (01.01.2025)
Published in Journal of nuclear materials (01.01.2025)
Get full text
Journal Article
The oxidation of uranium diboride in flowing air atmospheres
Mistarihi, Q., Martini, F., Buckley, J., Middleburgh, S.C., Abram, T.J., Turner, J.
Published in Journal of nuclear materials (01.07.2023)
Published in Journal of nuclear materials (01.07.2023)
Get full text
Journal Article
UN-UB 2 Composite fuel material; improved water tolerance with integral burnable absorber
Turner, J., Buckley, J., Worth, R.N., Salata-Barnett, M., Schmidt, M.J.J., Abram, T.J.
Published in Journal of nuclear materials (01.02.2022)
Published in Journal of nuclear materials (01.02.2022)
Get full text
Journal Article
Oxidation of U3Si2: The role of exothermic energy
Worth, R.N., Goddard, D.T., Buckley, J., Harrison, R.W., Liu, H., Paul, J.I., Abram, T.J.
Published in Journal of nuclear materials (01.09.2022)
Published in Journal of nuclear materials (01.09.2022)
Get full text
Journal Article
UN-UB2 Composite fuel material; improved water tolerance with integral burnable absorber
Turner, J., Buckley, J., Worth, R.N., Salata-Barnett, M., Schmidt, M.J.J., Abram, T.J.
Published in Journal of nuclear materials (01.02.2022)
Published in Journal of nuclear materials (01.02.2022)
Get full text
Journal Article
Small modular high temperature reactor optimisation – Part 1: A comparison between beryllium oxide and nuclear graphite in a small scale high temperature reactor
Atkinson, S., Abram, T.J., Litskevich, D., Merk, B.
Published in Progress in nuclear energy (New series) (01.03.2019)
Published in Progress in nuclear energy (New series) (01.03.2019)
Get full text
Journal Article
Prismatic core high temperature reactor fuel modelling incorporating fuel rotation
Atkinson, S., Whittle, K.R., Dean, J.S., Abram, T.J.
Published in Nuclear engineering and design (01.05.2018)
Published in Nuclear engineering and design (01.05.2018)
Get full text
Journal Article
Thermal conductivity mapping of pyrolytic carbon and silicon carbide coatings on simulated fuel particles by time-domain thermoreflectance
López-Honorato, E., Chiritescu, C., Xiao, P., Cahill, David G., Marsh, G., Abram, T.J.
Published in Journal of nuclear materials (15.08.2008)
Published in Journal of nuclear materials (15.08.2008)
Get full text
Journal Article
Structure and mechanical properties of pyrolytic carbon produced by fluidized bed chemical vapor deposition
López-Honorato, E., Meadows, P.J., Xiao, P., Marsh, G., Abram, T.J.
Published in Nuclear engineering and design (01.11.2008)
Published in Nuclear engineering and design (01.11.2008)
Get full text
Journal Article
Conference Proceeding
Meeting Europe's energy needs through next generation nuclear energy systems: an industrial view of the role of EC co-sponsored research
Ion, S.E., Bull, A.J., Ivens, R., Abram, T.J.
Published in Nuclear engineering and design (01.02.2005)
Published in Nuclear engineering and design (01.02.2005)
Get full text
Journal Article
Conference Proceeding