Dose, dose rate and irradiation temperature effects in β-irradiated simplified nuclear waste glasses by EPR spectroscopy

2001 ◽  
Vol 283 (1-3) ◽  
pp. 179-185 ◽  
Author(s):  
B. Boizot ◽  
G. Petite ◽  
D. Ghaleb ◽  
G. Calas

Author(s):  
A. Alessi ◽  
I. Reghioua ◽  
S. Girard ◽  
S. Agnello ◽  
D. Di Francesca ◽  
...  


1992 ◽  
Vol 195 (1-2) ◽  
pp. 173-178 ◽  
Author(s):  
S.A. Fabritsiev ◽  
V.V. Rybin ◽  
V.A. Kasakov ◽  
A.S. Pokrovskii ◽  
V.R. Barabash


2017 ◽  
Vol 52 (18) ◽  
pp. 10697-10708 ◽  
Author(s):  
A. Alessi ◽  
S. Agnello ◽  
S. Girard ◽  
D. Di Francesca ◽  
I. Reghioua ◽  
...  


1989 ◽  
Vol 4 (1-4) ◽  
pp. 205-209 ◽  
Author(s):  
A. Claverie ◽  
A. Roumili ◽  
N. Gessinn ◽  
J. Beauvillain


1988 ◽  
Vol 128 ◽  
Author(s):  
J. Koike ◽  
P. R. Okamoto ◽  
L. E. Rehn ◽  
M. Meshii

ABSTRACTCuTi was irradiated with 1-MeV electrons and Kr+ ions simultaneously at temperatures from 10 to 423 K. Retardation of Kr+-induced amorphization was observed with simultaneous electron irradiation at 295 and 423 K. The retardation effect increased with increasing irradiation temperature and relative electron-to-Kr dose rate. In contrast, simultaneous irradiation below 100 K showed an additive effect of electron- and Kr+-induced amorphization. The results can be explained by the mobility point defects introduced by electron irradiation interacting with Kr+-induced displacement cascades.



Author(s):  
Ken-ichi Ebihara ◽  
Masatake Yamaguchi ◽  
Yutaka Nishiyama ◽  
Kunio Onizawa ◽  
Hiroshi Matsuzawa

The experimental results on neutron-irradiated reactor pressure vessel (RPV) steels have revealed grain boundary segregation of phosphorous (P) due to neutron irradiation, which may lead to intergranular fracture. Because of the lack of experimental database, however, the dependence of the segregation on variables such as dose, dose-rate, and temperature is not clear. Here, we incorporate the parameters determined by first-principles calculations into the rate theory model which was developed for bcc lattice on the basis of the fcc lattice model proposed by Murphy and Perks [1], and apply it to the simulation of irradiation-induced P segregation in bcc iron. We evaluate the grain boundary P coverage and discuss its dependence on dose-rate and irradiation temperature by comparing our results with previously reported results and experimental data. As results, we find that dose-rate does not affect the grain boundary P coverage within the range of our simulation condition and that the dependence on irradiation temperature differs remarkably from the previous results.



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