Concepedia

Modelling of thermal conductivity and melting behaviour of minor actinide-MOX fuels and assessment against experimental and molecular dynamics data

A. Magni, L. Luzzi, D. Pizzocri, A. Schubert, P. Van Uffelen, Alessandro Del Nevo

Journal of Nuclear Materials · 2021 · 19 citations · 50 references

Open access

References

50

Thermophysical properties of uranium dioxide

J.K. Fink · Journal of Nuclear Materials · 2000 · 707 citations

Materials Science, Inorganic Chemistry, Engineering +7

Generation IV nuclear reactors: Current status and future prospects

Giorgio Locatelli, Mauro Mancini, Nicola Todeschini · Energy Policy · 2013 · 478 citations

Advanced Nuclear Reactors, Engineering, Reactor Design +7

Nuclear fuels – Present and future

D.R. Olander · Journal of Nuclear Materials · 2009 · 239 citations

Fuel Cycle, Nuclear Fuels, Chemical Engineering +10

TRANSURANUS: a fuel rod analysis code ready for use

Journal of Nuclear Materials · 1992 · 214 citations

Fuel Injection, Engineering, Fuel Science +1

MYRRHA – A multi-purpose fast spectrum research reactor

Hamid Aı̈t Abderrahim, P. Baeten, Didier De Bruyn et al. · Energy Conversion and Management · 2012 · 206 citations

Engineering, Nuclear Physics, Nuclear Reactors +4