Stored energy release rates have been determined for neutron irradiated graphite samples machined from an early air-cooled nuclear reactor (British Experimental Pile Zero or BEPO). The rate of release of stored energy was measured for both isothermal and linear rise heating rate differential scanning calorimetry experiments. The rate of release data were analysed using a thermal kinetics, independent parallel reactions model. The effect of annealing on the graphite crystalline structure was evaluated by investigating changes to X-ray diffraction spectra. A correlation between the calculated crystallite size and stored energy release is presented. A method for calculating the kinetic parameters for the annealing reaction is proposed and test...
COMPARISON Of IRRADIATION DAMAGE IN ARTIFICIAL AND NATURAL GRAPHITE AT DIFFERENTIRRADIATION TEMPERAT...
Design da ta for irradiated graphite are usually presented as families of isothermal curves showing ...
Irradiation effects at 500 deg C in experiemtal graphites with varied density, crystallinity, surfac...
The first generation of UK research and production reactors were graphite moderated and operated at ...
The rate of annealing due to primary neutron-carbon atom collisions transferring 3 to 25 ev to the r...
Data, which finding during thermal differential analysis of sampled irradiated graphite are presente...
Graphite expands linearly with irradiation at temperatures below 250 deg C and develops stored energ...
The present sthtus, past annealing procedures and experiences, future annealing procedures, annealin...
Changes in Raman spectra of polished and ion-irradiated Gilsocarbon and Highly Orientated Pyrolytic ...
A natural graphite recommended for use in nuclear applications was analyzed using thermogravimetric ...
tThe properties of graphite samples from the thermal column of a material testing reactor and from t...
This thesis investigates graphites used in nuclear materials engineering applications – so called nu...
A kinetic study was conducted to provide information on oxidation of reactor graphites in the temper...
Graphite has historically been used as a moderator material in nuclear reactor designs dating back t...
Property changes in polycrystalline graphite resulting from reactor irradiations at temperatures up ...
COMPARISON Of IRRADIATION DAMAGE IN ARTIFICIAL AND NATURAL GRAPHITE AT DIFFERENTIRRADIATION TEMPERAT...
Design da ta for irradiated graphite are usually presented as families of isothermal curves showing ...
Irradiation effects at 500 deg C in experiemtal graphites with varied density, crystallinity, surfac...
The first generation of UK research and production reactors were graphite moderated and operated at ...
The rate of annealing due to primary neutron-carbon atom collisions transferring 3 to 25 ev to the r...
Data, which finding during thermal differential analysis of sampled irradiated graphite are presente...
Graphite expands linearly with irradiation at temperatures below 250 deg C and develops stored energ...
The present sthtus, past annealing procedures and experiences, future annealing procedures, annealin...
Changes in Raman spectra of polished and ion-irradiated Gilsocarbon and Highly Orientated Pyrolytic ...
A natural graphite recommended for use in nuclear applications was analyzed using thermogravimetric ...
tThe properties of graphite samples from the thermal column of a material testing reactor and from t...
This thesis investigates graphites used in nuclear materials engineering applications – so called nu...
A kinetic study was conducted to provide information on oxidation of reactor graphites in the temper...
Graphite has historically been used as a moderator material in nuclear reactor designs dating back t...
Property changes in polycrystalline graphite resulting from reactor irradiations at temperatures up ...
COMPARISON Of IRRADIATION DAMAGE IN ARTIFICIAL AND NATURAL GRAPHITE AT DIFFERENTIRRADIATION TEMPERAT...
Design da ta for irradiated graphite are usually presented as families of isothermal curves showing ...
Irradiation effects at 500 deg C in experiemtal graphites with varied density, crystallinity, surfac...