Author: Blaine, Deborah
Similar Items: Next generation high temperature gas reactors : a failure methodology for the design of nuclear graphite components
- Purifying coal for the production of nuclear graphite
- Low temperature thermal properties of HTR nuclear fuel composite graphite
- Properties of graphitic composites
- Experimental measurement of graphite wear in helium at elevated temperatures and the discrete element modelling of graphite dust production inside the Pebble Bed Modular Reactor
- A study of some aspects of the formation and performance of atomic vapour in a graphite atom reservoir for atomic fluorescence spectrometry
- Characterisation of expandable graphite and its flame retardant abilities in flame retardant systems for polyethylene