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Number of items: 8.
Article
CHEN, Tzu-Yu, MADDRELL, Ewan R., HYATT, Neil C., GANDY, Amy S., STENNETT, Martin C. and HRILJAC, Joseph A.
(2017).
Transformation of Cs-IONSIV® into a ceramic wasteform by hot isostatic pressing.
Journal of Nuclear Materials, 498, 33 - 43.
[Article]
CONNELLY, A.J., HAND, R.J., BINGHAM, Paul and HYATT, N.C.
(2011).
Mechanical properties of nuclear waste glasses.
Journal of Nuclear Materials, 408 (2), 188-193.
[Article]
HYATT, N.C., SCHWARZ, R.R., BINGHAM, Paul, STENNETT, M.C., CORKHILL, C.L., HEATH, P.G., HAND, R.J., JAMES, M., PEARSON, A. and MORGAN, S.
(2014).
Thermal treatment of simulant plutonium contaminated materials from the Sellafield site by vitrification in a blast-furnace slag.
Journal of Nuclear Materials, 444 (1-3), 186-199.
[Article]
KYAW, Si, SUN, W and BECKER, A.A
(2015).
Effects of compositions of filler, binder and porosity on elastic and fracture properties of nuclear graphite.
Journal of Nuclear Materials, 457, 42-47.
[Article]
MCGANN, O.J., BINGHAM, Paul, HAND, R.J., GANDY, A.S., KAVČIČ, M., ŽITNIK, M., BUČAR, K., EDGE, R. and HYATT, N.C.
(2012).
The effects of γ-radiation on model vitreous wasteforms intended for the disposal of intermediate and high level radioactive wastes in the United Kingdom.
Journal of Nuclear Materials, 429 (1-3), 353-367.
[Article]
RAUTIYAL, Prince, GUPTA, Gaurav, EDGE, Ruth, LEAY, Laura, DAUBNEY, Aaron, PATEL, Maulik, JONES, Alan and BINGHAM, Paul
(2020).
Gamma irradiation-induced defects in borosilicate glasses for high-level radioactive waste immobilisation.
Journal of Nuclear Materials.
[Article]
RIGBY, Jessica, DIXON, Derek, CUTFORTH, Derek, MARCIAL, Jose, KLOUZEK, Jaroslav, POKORNY, Richard, KRUGER, Albert, SCRIMSHIRE, Alex, BELL, Anthony and BINGHAM, Paul
(2022).
Melting behaviour of simulated radioactive waste as functions of different redox iron-bearing raw materials.
Journal of Nuclear Materials, 569: 153946.
[Article]
UTTON, C. A., HAND, R. J., BINGHAM, P. A., HYATT, N. C., SWANTON, S. W. and WILLIAMS, S. J.
(2013).
Dissolution of vitrified wastes in a high-pH calcium-rich solution.
Journal of Nuclear Materials, 435 (1-3), 112-122.
[Article]