The changes in dimensions and lattice parameters produced by irradiation in two reactors with very different dose rate have been studied over the temperature range 400-700ยฐC. In this range it is found that the activation energy associated with the equivalent temperature concept is not constant. It i
Energy released at high temperature by irradiated graphite
โ Scribed by J Rappeneau; J.L Taupin; J Grehier
- Publisher
- Elsevier Science
- Year
- 1966
- Tongue
- English
- Weight
- 895 KB
- Volume
- 4
- Category
- Article
- ISSN
- 0008-6223
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โฆ Synopsis
The energy H stored by graphite under the effect of neutron radiation can be released by thermal annealing. It is possible to determine by differential thermal analysis the differential enthalpy dH/dO (cal/g/'C) as a function of the annealing temperature 8. Integration of the spectrum obtained gives the overall quantity of energv H(8). To determine the form of the energy spectrum at high temperature, a differential thermal analysis apparatus operating up to 1800ยฐC was built. The tests were carried out under vacuum in a graphite resistance furnace and the temperature was measured as a function of time by means of WRe&WRep8% and graphite/boronated graphite thermocouples. The description of the apparatus is followed by an examination of graphites irradiated in the reactors BR.2 (C.E.N. Belgium) and H.F.R. (Petten, Holland) at doses between 1000 and 4000 MWJ/T and at temperatures between 70ยฐC and 250ยฐC. The energy spectra obtained show, for all the samples studied, the presence of a healing peak at temperatures of the order of 1200 to 15OO'C. This peak was also found in the case of thermal healing of other physical properties of irradiated graphites.
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The linear dimensional changes of anisotropic and near-isotropic graphites were measured after irradiation in the range 300 to 1500ยฐC to 3.3 x 102r n/cm" (E > 0.18 MeV). The presence of a nongraphitizing impregnant coke in an anisotropic needle-coke graphite increased its volume contraction, reduced
The paper presents the results of graphite irradiations carried out in the Dounreay Fast Reactor; the use of this reactor for graphite irradiations is advantageous for several reasons. The total neutron flux is very high, practically all the neutrons have energies capable of producing damage in grap