Zobrazeno 1 - 10
of 41
pro vyhledávání: '"J.J. Laidler"'
Publikováno v:
ECS Proceedings Volumes. :713-720
We are developing a two-step electrochemical process for purifying and separating metals called ion replacement electrorefining. In each step, metal cations formed by oxidation at an electrode replace other metal cations that are reduced at another e
The void nucleation behavior of an alloy is related to the development of the initial microstructure during irradiation. There is some concern that the void nucleation and swelling behavior of fast reactor steels may be controlled by the presence of
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::0f117e18e3678a8189966a47d6a239c2
https://doi.org/10.1520/stp33705s
https://doi.org/10.1520/stp33705s
Publikováno v:
Fusion Technology. 20:605-609
This report summarizes highlights of the technical progress made in the Integral Fast Reactor (IFR) Program in FY 1992. Technical accomplishments are presented in the following areas of the IFR technology development activities: (1) metal fuel perfor
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::820d2450c7d03ce75329bb6185468a54
https://doi.org/10.2172/10181235
https://doi.org/10.2172/10181235
Publikováno v:
Journal of Nuclear Materials. :504-514
In order to avoid the artifacts which result because void swelling and precipitate stability are not accelerated to the same degree during radiation damage simulation experiments, a series of electron irradiation experiments were performed on commerc
Publikováno v:
Journal of Nuclear Materials. 54:313-324
The formation of irradiation-induced dislocation loops was studied in four Ni-base γ/γ' alloys, severely overaged so that the influence of individual γ/γ' interfaces could be investigated. The alloys, Ni-14.07% Al, Ni-12.68% Si, Ni-18% Cr-7% Al a
Autor:
J.J. Laidler
Progress is reported in six chapters: swelling and creep, analytical studies (of irradiation effects), coolant compatibility (sodium), and status of EBR-II irradiation tests (one table). Materials studied include HT-9, 330 ss, Inconel 706, A-286, Nim
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::e8e62505d9384d550be8b30d88785e86
https://doi.org/10.2172/709477
https://doi.org/10.2172/709477