Zobrazeno 1 - 10
of 111
pro vyhledávání: '"M. Atzmon"'
Autor:
H. H. T IAN, M. ATZMON
Publikováno v:
Philosophical Magazine A. 79:1769-1786
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::7f681785e1a4cae31feea2afb36c53f4
https://doi.org/10.1080/014186199251698
https://doi.org/10.1080/014186199251698
Publikováno v:
Applied Physics Letters. 73:1805-1807
Low-energy ball milling of amorphous Fe78B13Si9 has been performed at temperatures between 25 and 250 °C. Primary crystallization is observed after milling at elevated temperatures, but not after annealing at the same temperatures. Although milling
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::963076669e855a10d04d6e189b3cbf94
https://doi.org/10.1063/1.122288
https://doi.org/10.1063/1.122288
OAK B188 A Novel Approach to Materials Development for Advanced Reactor Systems - Quarterly Progress Report: Year 2; Quarter 1. There are three major goals for year two of the program. First, to build on the successful initial experiments on proton i
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::35a1ffbf7d0e3ea4420916c91c13174e
https://doi.org/10.2172/770633
https://doi.org/10.2172/770633
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OAK B188 A Novel Approach to Materials Development for Advanced Reactor Systems. Annual Report for Year 1 Year one of this project had three major goals. First, to specify, order and install a new high current ion source for more rapid and stable pro
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::1be7c87f809cdedb87a53c742ab01ab7
https://doi.org/10.2172/766526
https://doi.org/10.2172/766526
OAK B188 Isolation of Microstructure in Proton-Irradiated Steels. Topical Report. Component degradation by irradiation is a primary concern in both current reactor systems as well as advanced designs and concepts where the demand for higher efficienc
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::33c7bddbb439365d6209d817c1785438
https://doi.org/10.2172/766528
https://doi.org/10.2172/766528
OAK B188 A Novel Approach to Material Development for Advanced Reactor Systems. Year one of this project had three major goals. First, to specify, order and install a new high current ion source for more rapid and stable proton irradiation. Second, t
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::4db26a3058612ae6840d701377212452
https://doi.org/10.2172/761592
https://doi.org/10.2172/761592
Publikováno v:
Journal of ASTM International. 1:11316
In studies of radiation effects on materials for reactor applications, it is desirable to identify irradiation methods that induce microstructural effects similar to those of neutrons, but at reduced time and expense. In the present study, 2 MeV prot
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::f339a742832c6fa2cd637b3f3768835f
https://doi.org/10.1520/jai11316
https://doi.org/10.1520/jai11316
Publikováno v:
Proceedings, annual meeting, Electron Microscopy Society of America. 52:962-963
Irradiation-assisted stress corrosion cracking (IASCC) of stainless steels has been attributed in part to radiation-induced segregation (RIS) of both major alloying and impurity elements at grain boundaries. There are phenomenological similarities ob
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::98a053325a312ce2e59b7da5806f7f2b
https://doi.org/10.1017/s0424820100172541
https://doi.org/10.1017/s0424820100172541