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AbstractAbstract
[en] The main purposes of this thesis are: - to point out the spectral effects on the radiation embrittlement of the pressure-vessel steels (A 508-Class 3). - to discern among the damage models proposed, using as gauge of exposure, the one that gives the best approach of the spectral effects observed between different irradiation locations. A simulated vessel-wall environment (called ''special location'') was constructed in the ''Melusine'' reactor of ''Centre d'Etudes Nucleaires de Grenoble'' that provided for measurements of steel embrittlement increase on Charpy-V notch samples and neutron flux detector activations as well as two other additionnal standard locations. Neutron spectra for these locations were calculated using Discrete Ordinate Transport Codes (ANISN and DOT 3.5.). Six campaigns of measurements of neutron spectrum by multiple foils activations were performed. Good agreement with results obtained from the calculations and the measurements were observed. The measured increases in steel transition temperature from the experimental locations revealed an important spectrum effect between the standard and special locations. If the data are expressed in (phi.t) > 1 MeV, this effect is about 50%. None of the tested damage models (displacement zones, Lindhard model, ...) does represent the observed effects
[fr]
Les buts principaux de cette these sont: - d'etudier les effets du spectre neutronique sur la fragilisation des aciers de cuves de reacteurs nucleaires, - de choisir parmi les modeles de dommages existants celui qui rend le mieux compte des phenomenes observes. Un emplacement special a spectre neutronique voisin de celui regnant dans les cuves de pression a ete construit dans le reacteur Melusine (8MW) du Centre d'Etudes Nucleaires de Grenoble. Des irradiations d'acier ont eu lieu dans cet emplacement ainsi que dans deux autres emplacements standard. Les spectres neutroniques ont ete calcules par le systeme de codes de transport ANISN - DOT 3,5. Six campagnes de mesures par detecteurs a seuil ont ete faites. Un bon accord experience-calcul a ete trouve. L'accroissement de la temperature de transition des echantillons d'acier mesure dans les emplacements standard et dans l'emplacement special, montre un effet de spectre important. Les doses neutroniques etant exprimees en fluences de neutrons d'energie superieure a 1 MeV, l'effet de spectre est de l'ordre de 50%. Aucun modele de dommage teste (zones de deplacement, modele de Lindhard, etc.) ne rend compte des effets de spectre observesOriginal Title
Influence du spectre des neutrons sur la fragilisation des aciers de cuves de reacteurs
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Jan 1979; 165 p
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