The first generation of UK research and production reactors were graphite moderated and operated at low temperatures, below 150 °C. The graphite in these reactors now contains a significant amount of stored (Wigner) energy that may be relatively easily released by heating the graphite above the irradiation temperature. This exothermic behaviour has lead to a number of decommissioning issues which are related to characterization of graphite samples, long term "safe-storage", reactor core dismantling, graphite waste packaging and the final disposal of this irradiated graphite waste. The release of stored energy can be modelled using kinetic models linked to classical kinetic analysis theory. These models rely on Differential Scanning Calorime...
Presented at the NuMat 2014 Conference, 27–30 October 2014, Clearwater, Florida, USA.International a...
Waste graphite containing fragments of nuclear fuel and fission products is produced mainly as a res...
Graphite expands linearly with irradiation at temperatures below 250 deg C and develops stored energ...
Stored energy release rates have been determined for neutron irradiated graphite samples machined fr...
Data, which finding during thermal differential analysis of sampled irradiated graphite are presente...
The rate of annealing due to primary neutron-carbon atom collisions transferring 3 to 25 ev to the r...
International audienceGraphite was used as a moderator in the French-designed first generation nucle...
A natural graphite recommended for use in nuclear applications was analyzed using thermogravimetric ...
The European Project on ‘Treatment and Disposal of Irradiated Graphite and other Carbonaceous Waste ...
Dismantling of old reactors and the management of radioactive graphite wastes are becoming increasin...
A kinetic study was conducted to provide information on oxidation of reactor graphites in the temper...
Graphite reacts with such gases as CO{sub 2}, O{sub 2}, or water vapor to form gaseous oxides of car...
The Finnish FiR 1 TRIGA Mark II reactor is facing shut-down after more than 50 years of operation. T...
International audienceImpurities in nuclear graphite can become neutron-activated during operation, ...
Abstract. Graphite is used as a moderator material in a number of nuclear reactor designs, such as M...
Presented at the NuMat 2014 Conference, 27–30 October 2014, Clearwater, Florida, USA.International a...
Waste graphite containing fragments of nuclear fuel and fission products is produced mainly as a res...
Graphite expands linearly with irradiation at temperatures below 250 deg C and develops stored energ...
Stored energy release rates have been determined for neutron irradiated graphite samples machined fr...
Data, which finding during thermal differential analysis of sampled irradiated graphite are presente...
The rate of annealing due to primary neutron-carbon atom collisions transferring 3 to 25 ev to the r...
International audienceGraphite was used as a moderator in the French-designed first generation nucle...
A natural graphite recommended for use in nuclear applications was analyzed using thermogravimetric ...
The European Project on ‘Treatment and Disposal of Irradiated Graphite and other Carbonaceous Waste ...
Dismantling of old reactors and the management of radioactive graphite wastes are becoming increasin...
A kinetic study was conducted to provide information on oxidation of reactor graphites in the temper...
Graphite reacts with such gases as CO{sub 2}, O{sub 2}, or water vapor to form gaseous oxides of car...
The Finnish FiR 1 TRIGA Mark II reactor is facing shut-down after more than 50 years of operation. T...
International audienceImpurities in nuclear graphite can become neutron-activated during operation, ...
Abstract. Graphite is used as a moderator material in a number of nuclear reactor designs, such as M...
Presented at the NuMat 2014 Conference, 27–30 October 2014, Clearwater, Florida, USA.International a...
Waste graphite containing fragments of nuclear fuel and fission products is produced mainly as a res...
Graphite expands linearly with irradiation at temperatures below 250 deg C and develops stored energ...