Zobrazeno 1 - 10
of 51
pro vyhledávání: '"Gamma flux"'
Publikováno v:
Journal of Nuclear Engineering, Vol 4, Iss 1, Pp 213-227 (2023)
The SM-MSR (small modular molten salt reactor) has a good prospect for development with regards to combining the superiority of the molten salt reactor and modularization technologies, showing the advantages of safety, reliability, low economic cost
Externí odkaz:
https://doaj.org/article/8f670cb03ed6474faabd8331532ae2ef
Determination of defect depth in industrial radiography imaging using MCNP code and SuperMC software
Publikováno v:
Nuclear Engineering and Technology, Vol 52, Iss 7, Pp 1597-1601 (2020)
Background: Non-destructive evaluation of defects in metals or composites specimens is a regular method in radiographic imaging. The maintenance examination of metallic structures is a relatively difficult effort that requires robust techniques for u
Externí odkaz:
https://doaj.org/article/df70bbe08b0e44388671969589828fa8
Publikováno v:
EPJ Web of Conferences, Vol 225, p 04029 (2020)
The neutron field of various irradiation positions of the TRIGA Mark II reactor of the Jožef Stefan Institute has been thoroughly characterized by neutron activation dosimetry and miniature fission chambers techniques. In order to have a fully valid
Externí odkaz:
https://doaj.org/article/2a9fb6ddc2794480b36e0ce35347b16c
Publikováno v:
EPJ Web of Conferences, Vol 225, p 04030 (2020)
The CNESTEN (National Center for Energy Sciences and Nuclear Technology, Morocco) operates a TRIGA Mark II reactor, which can reach a thermal maximum power at steady state of 2 MW. In reactors devoted to research and experiments, it is mandatory to c
Externí odkaz:
https://doaj.org/article/09558a95d535439682c6cc2a99c40c96
Akademický článek
Tento výsledek nelze pro nepřihlášené uživatele zobrazit.
K zobrazení výsledku je třeba se přihlásit.
K zobrazení výsledku je třeba se přihlásit.
Determination of defect depth in industrial radiography imaging using MCNP code and SuperMC software
Publikováno v:
Nuclear Engineering and Technology, Vol 52, Iss 7, Pp 1597-1601 (2020)
Background Non-destructive evaluation of defects in metals or composites specimens is a regular method in radiographic imaging. The maintenance examination of metallic structures is a relatively difficult effort that requires robust techniques for us
Publikováno v:
EPJ Web of Conferences
EPJ Web of Conferences, 2020, 225, pp.04029. ⟨10.1051/epjconf/202022504029⟩
EPJ Web of Conferences, Vol 225, p 04029 (2020)
IEEE Transactions on Nuclear Science
IEEE Transactions on Nuclear Science, Institute of Electrical and Electronics Engineers, 2020, 67 (4), pp.559-567. ⟨10.1109/TNS.2020.2974968⟩
IEEE Transactions on Nuclear Science, 2020, 67 (4), pp.559-567. ⟨10.1109/TNS.2020.2974968⟩
EPJ Web of Conferences, 2020, 225, pp.04029. ⟨10.1051/epjconf/202022504029⟩
EPJ Web of Conferences, Vol 225, p 04029 (2020)
IEEE Transactions on Nuclear Science
IEEE Transactions on Nuclear Science, Institute of Electrical and Electronics Engineers, 2020, 67 (4), pp.559-567. ⟨10.1109/TNS.2020.2974968⟩
IEEE Transactions on Nuclear Science, 2020, 67 (4), pp.559-567. ⟨10.1109/TNS.2020.2974968⟩
International audience; The neutron field of various irradiation positions of the TRIGA Mark II reactor of the Jožef Stefan Institute (JSI) has been thoroughly characterized by neutron activation dosimetry and miniature fission chambers techniques.
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::66ed2598f713c58c5469348923c5c996
https://cea.hal.science/cea-02524722/file/epjconf_animma2019_04029.pdf
https://cea.hal.science/cea-02524722/file/epjconf_animma2019_04029.pdf
Akademický článek
Tento výsledek nelze pro nepřihlášené uživatele zobrazit.
K zobrazení výsledku je třeba se přihlásit.
K zobrazení výsledku je třeba se přihlásit.
Introduction A neutron irradiation facility based on four 241Am–Be sources, activity of 1.11·1011 Bq each (yield ~7.0 ·106 n s-1), consisting in four source-channels and an irradiation channel placed in a tank filled with light water both as mode
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=od______3658::d98044c648479f8dd92ead2f590daf78
http://hdl.handle.net/10447/359523
http://hdl.handle.net/10447/359523
Publikováno v:
IEEE Transactions on Nuclear Science
IEEE Transactions on Nuclear Science, Institute of Electrical and Electronics Engineers, 2018, 65 (9), pp.2490-2493. ⟨10.1109/TNS.2018.2827393⟩
IEEE Transactions on Nuclear Science, 2018, 65 (9), pp.2490-2493. ⟨10.1109/TNS.2018.2827393⟩
IEEE Transactions on Nuclear Science, Institute of Electrical and Electronics Engineers, 2018, 65 (9), pp.2490-2493. ⟨10.1109/TNS.2018.2827393⟩
IEEE Transactions on Nuclear Science, 2018, 65 (9), pp.2490-2493. ⟨10.1109/TNS.2018.2827393⟩
In this paper, test measurements of a fibered optically stimulated luminescent dosimeter (OSLD) system performed during a dedicated experimental phase in EOLE zero-power reactor are presented. The measurement setup consists of an OSLD crystal connect
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::6f05d66df4d2c0b34a10271ca4d34bfe
https://hal-cea.archives-ouvertes.fr/cea-01917204
https://hal-cea.archives-ouvertes.fr/cea-01917204