E-LIB Suche - Ergebnisse für: Alimov, V. Kh.

1

Deuterium retention in reduced activation ferritic/martensi..:

Alimov, V.Kh. ; Roth, J. ; Sugiyama, K....
Nuclear Materials and Energy. 35 (2023) - p. 101430 , 2023

2

Selective Sputtering of Eurofer Steel by Deuterium Plasma:

Golubeva, A. V. ; Khripunov, B. I. ; Alimov, V. Kh....
Journal of Surface Investigation: X-ray, Synchrotron and Neutron Techniques. 16 (2022) 4 - p. 469-479 , 2022

Link: https://doi.org/10.1134/..

3

Tritium retention in displacement-damaged tungsten exposed ..:

Alimov, V.Kh. ; Torikai, Y. ; Hatano, Y..
Fusion Engineering and Design. 162 (2021) - p. 112100 , 2021

Link: https://doi.org/10.1016/..

4

Deuterium release from deuterium plasma-exposed neutron-irr..:

Alimov, V.Kh. ; Hatano, Y. ; Kuwabara, T....
Nuclear Fusion. 60 (2020) 9 - p. 096025 , 2020

Link: https://doi.org/10.1088/..

5

Analysis of mixed-material layers deposited on the toroidal..:

Alimov, V.Kh. ; Yajima, M. ; Masuzaki, S..
Fusion Engineering and Design. 147 (2019) - p. 111228 , 2019

Link: https://doi.org/10.1016/..

6

Deuterium and helium retention in W with and without He-ind..:

Ogorodnikova, O.V. ; Klimov, K.S. ; Poskakalov, А.G....
Journal of Nuclear Materials. 515 (2019) - p. 150-159 , 2019

Link: https://doi.org/10.1016/..

7

Surface modification and deuterium retention in reduced-act..:

Alimov, V. Kh ; Ogorodnikova, O.V. ; Hatano, Y....
Journal of Nuclear Materials. 502 (2018) - p. 1-8 , 2018

Link: https://doi.org/10.1016/..

8

Surface morphology of F82H steel exposed to low-energy D pl..:

Alimov, V. Kh. ; Hatano, Y. ; Yoshida, N....
Journal of Nuclear Materials. 510 (2018) - p. 366-372 , 2018

Link: https://doi.org/10.1016/..

9

Deuterium absorption in reduced activation ferritic/martens..:

Alimov, V.Kh ; Hatano, Y. ; Sugiyama, K....
Journal of Nuclear Materials. 507 (2018) - p. 54-58 , 2018

Link: https://doi.org/10.1016/..

10

Surface modification and sputtering erosion of iron and cop..:

Alimov, V.Kh. ; Hatano, Y. ; Balden, M....
Nuclear Materials and Energy. 13 (2017) - p. 81-89 , 2017

Link: https://doi.org/10.1016/..

11

Deuterium retention in W and W-Re alloy irradiated with hig..:

Hatano, Y. ; Ami, K. ; Alimov, V.Kh....
Nuclear Materials and Energy. 9 (2016) - p. 93-97 , 2016

Link: https://doi.org/10.1016/..

12

Surface modification and sputtering erosion of reduced acti..:

Alimov, V.Kh. ; Hatano, Y. ; Yoshida, N....
Nuclear Materials and Energy. 7 (2016) - p. 25-32 , 2016

Link: https://doi.org/10.1016/..

13

Tritium Trapping on the Plasma Irradiated Tungsten Surface:

Torikai, Y. ; Alimov, V. Kh. ; Isobe, K....
Fusion Science and Technology. 67 (2015) 3 - p. 619-622 , 2015

Link: https://doi.org/10.13182..

14

Tritium Retention in Reduced-Activation Ferritic/Martensiti..:

Hatano, Y. ; Alimov, V. Kh. ; Spitsyn, A. V....
Fusion Science and Technology. 67 (2015) 2 - p. 361-364 , 2015

Link: https://doi.org/10.13182..

15

Erosion study of Fe–W binary mixed layer prepared as model ..:

Sugiyama, K. ; Roth, J. ; Alimov, V.Kh....
Journal of Nuclear Materials. 463 (2015) - p. 272-275 , 2015

Link: https://doi.org/10.1016/..