Das hier vorgeschlagene Modell zur Beschreibung der durch Neutronenbestrahlung erzielten Änderungen der Materialeigenschaften des Graphits basiert auf drei Sättigungsprozessen, die mit der Überführung von Kohlenstoffatomen oder Gruppen von Kohlenstoffatomen aus einer anfänglich bestehenden Konfiguration in eine energetisch oder statistisch begünstigte Anordnung innerhalb der atomaren Struktur verknüpft ist. Der Einfluß der Prozesse ist durch Produkte von jeweils drei Faktoren dargestellt. Der erste Faktor enthält den exponentiell abklingenden Einfluß der Bestrahlungsdosis, der zweite vorwiegend die Temperaturabhängigkeit entsprechend dem Popularisierungszustand eines damit verknüpften Energiezustàndes und der dritte Faktor vermittelt die Ko...
A model data set covering the temperature range 300 - 800 °C and irradiation dose range 0 - 4$\cdot$...
Preliminary results of a broad irradiation program on graphite are reported. Within this program gra...
National audienceEn tant que matériau utilisé comme modérateur dans les premières centrales nucléair...
SIGLELD:3106.076(CEGB-RD/B/N--4979) / BLDSC - British Library Document Supply CentreGBUnited Kingdo
National audienceDans le cœur des réacteurs de type Uranium Naturel Graphite Gaz (UNGG), du graphite...
In the present report a method is introduced by which it has become possible to analyze data for irr...
The default theory of radiation damage in graphite invokes Frenkel pair formation as the principal c...
Dans le but de mettre en évidence des phénomènes dus à des défauts relativement simples, l'étude par...
A detailed scientific investigation is carried out into the effects of ion irradiation on graphite ...
International audienceEtant un excellent modérateur neutronique, le graphite est utilisé comme matér...
COMPARISON Of IRRADIATION DAMAGE IN ARTIFICIAL AND NATURAL GRAPHITE AT DIFFERENTIRRADIATION TEMPERAT...
Detailed knowledge regarding the nature of and mechanisms causing neutron irradiation damage in grap...
Design da ta for irradiated graphite are usually presented as families of isothermal curves showing ...
The default theory of radiation damage in graphite invokes Frenkel pair formation as the principal c...
International audienceDue to its excellent moderator and reflector qualities, graphite was used in C...
A model data set covering the temperature range 300 - 800 °C and irradiation dose range 0 - 4$\cdot$...
Preliminary results of a broad irradiation program on graphite are reported. Within this program gra...
National audienceEn tant que matériau utilisé comme modérateur dans les premières centrales nucléair...
SIGLELD:3106.076(CEGB-RD/B/N--4979) / BLDSC - British Library Document Supply CentreGBUnited Kingdo
National audienceDans le cœur des réacteurs de type Uranium Naturel Graphite Gaz (UNGG), du graphite...
In the present report a method is introduced by which it has become possible to analyze data for irr...
The default theory of radiation damage in graphite invokes Frenkel pair formation as the principal c...
Dans le but de mettre en évidence des phénomènes dus à des défauts relativement simples, l'étude par...
A detailed scientific investigation is carried out into the effects of ion irradiation on graphite ...
International audienceEtant un excellent modérateur neutronique, le graphite est utilisé comme matér...
COMPARISON Of IRRADIATION DAMAGE IN ARTIFICIAL AND NATURAL GRAPHITE AT DIFFERENTIRRADIATION TEMPERAT...
Detailed knowledge regarding the nature of and mechanisms causing neutron irradiation damage in grap...
Design da ta for irradiated graphite are usually presented as families of isothermal curves showing ...
The default theory of radiation damage in graphite invokes Frenkel pair formation as the principal c...
International audienceDue to its excellent moderator and reflector qualities, graphite was used in C...
A model data set covering the temperature range 300 - 800 °C and irradiation dose range 0 - 4$\cdot$...
Preliminary results of a broad irradiation program on graphite are reported. Within this program gra...
National audienceEn tant que matériau utilisé comme modérateur dans les premières centrales nucléair...