Zobrazeno 1 - 6
of 6
pro vyhledávání: '"E. V. Mader"'
Autor:
E. A. Pfeif, Z. Jones, A. N. Lasseigne, K. Koenig, K. Krzywosz, E. V. Mader, S. Yagnik, B. Mishra, D. L. Olson, Donald O. Thompson, Dale E. Chimenti
Publikováno v:
AIP Conference Proceedings.
Submerged eddy current testing of zircaloy‐4 fuel cladding has been developed as a method of characterizing the hydrogen evolution within zircaloy‐4 fuel cladding in spent fuel pools. The parameters associated with storage in spent fuel pools mus
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::04c9fb777632bd70c64d97e980852ff0
https://doi.org/10.1063/1.3592067
https://doi.org/10.1063/1.3592067
Autor:
S. Valizadeh, G. Ledergerber, S. Abolhassani, D. Jädernäs, M. Dahlbäck, E. V. Mader, G. Zhou, J. Wright, L. Hallstadius
Publikováno v:
Scopus-Elsevier
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::af2b6420ad8f1960a886dbeb8fe4df99
https://doi.org/10.1520/stp49379s
https://doi.org/10.1520/stp49379s
Autor:
E. A. Pfeif, A. N. Lasseigne, K. Krzywosz, E. V. Mader, B. Mishra, D. L. Olson, Donald O. Thompson, Dale E. Chimenti
Publikováno v:
AIP Conference Proceedings.
Assessment of hydrogen uptake of underwater nuclear fuel clad and component materials will enable improved monitoring of fuel health. Zirconium alloys are used in nuclear reactors as fuel cladding, fuel channels, guide tubes and spacer grids, and are
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::bdf415b1ae352df626c18e3e4106902b
https://doi.org/10.1063/1.3362220
https://doi.org/10.1063/1.3362220
Autor:
M Christensen, W Wolf, C Freeman, E Wimmer, R B Adamson, L Hallstadius, P E Cantonwine, E V Mader
Publikováno v:
Journal of Physics: Condensed Matter; 1/21/2015, Vol. 27 Issue 2, p1-1, 1p