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Interpretation of high-burnup fuel annealing tests

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Interpretation of high-burnup fuel annealing tests

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Development of the control assembly pattern and dynamic analysis of the generation IV large gas-cooled fast reactor (GFR)

Experimental validation of reaction rate distributions for a SVEA-96+ BWR assembly with hafnium control blades

Determination of within-rod caesium and europium isotopic distributions in high burnup fuel rods through computerised gamma-ray emission tomography

Void reactivity coefficient benchmark results for a 10x10 BWR assembly in the full 0-100% void fraction range

Modelling of fission gas behaviour in high burnup nuclear fuel

Development and application of an advanced fuel model for the safety analysis of the generation IV gas-cooled fast reactor

Nondestructive determination of fresh and spent nuclear fuel rod density distributions through computerised gamma-ray transmission tomography

Characterisation of high-burnup LWR fuel rods through gamma tomography

Investigations of238U captures to total fissions in a westinghouse SVEA-96+ assembly

Development and benchmarking of a 2D transient thermal model for GFR plate-type fuel