Zobrazeno 1 - 10
of 20
pro vyhledávání: '"Mitch Meyer"'
Autor:
DENNIS D. KEISER, JR., JAN-FONG JUE, BRANDON D. MILLER, JIAN GAN, ADAM B. ROBINSON, PAVEL MEDVEDEV, JAMES MADDEN, DAN WACHS, MITCH MEYER
Publikováno v:
Nuclear Engineering and Technology, Vol 46, Iss 2, Pp 147-158 (2014)
In order to investigate how the microstructure of fuel/matrix-interaction (FMI) layers change during irradiation, different U–7Mo dispersion fuel plates have been irradiated to high fission density and then characterized using scanning electron mic
Externí odkaz:
https://doaj.org/article/9284bb955d304f868a8b545f83402a3f
Autor:
Jian Gan, Dennis D. Keiser, Hakan Ozaltun, James W. Madden, J.F. Jue, Adam B. Robinson, Mitch Meyer, Glenn A. Moore, Brandon D. Miller
Publikováno v:
Journal of Nuclear Materials. 492:195-203
Monolithic U-10Mo alloy fuel plates with Al-6061 cladding are being developed for use in research and test reactors as low enrichment fuel ( 1 μm) are distributed evenly in U-Mo and interlink of these bubbles is evident. The average size of subdivid
Autor:
James W. Madden, Jan-Fong Jue, M. Ross Finlay, Mitch Meyer, Jian Gan, Dennis D. Keiser, Adam B. Robinson, Glenn A. Moore, Brandon D. Miller, Pavel Medvedev
Publikováno v:
Journal of Nuclear Materials. 488:100-122
The Material Management and Minimization (M3) Reactor Conversion Program, in the past called the Reduced Enrichment for Research and Test Reactor (RERTR) Program, is developing low-enriched uranium (LEU) fuels for application in research and test rea
Publikováno v:
Journal of Nuclear Materials. 544:152703
Understanding swelling behavior in monolithic, uranium-molybdenum, plate-type fuel is necessary to qualify the fuel for reactor use and for the conversion of high performance research reactors from highly enriched to low-enriched uranium. Multiple me
Autor:
Gordon A. Alanko, K. Urso, Brian J. Jaques, Darryl P. Butt, Peng Xu, B. Tyburska-Päschel, Kumar Sridharan, Mitch Meyer
Publikováno v:
Nuclear Technology. 196:100-110
The corrosion resistance of cerium silicide, a surrogate of uranium silicide, is investigated to gain insight into the reaction of uranium silicide with water. As-received and proton-irradiated Ce3...
Autor:
Edward J. Lahoda, Gordon A. Alanko, Darryl P. Butt, Brian J. Jaques, Joseph R. Croteau, Jennifer K. Watkins, Peng Xu, Mitch Meyer, Beata Tyburska-Püschel
Publikováno v:
Journal of Nuclear Materials. 466:745-754
The design and development of an economical, accident tolerant fuel (ATF) for use in the current light water reactor (LWR) fleet is highly desirable for the future of nuclear power. Uranium mononitride has been identified as an alternative fuel with
Autor:
Dennis D. Keiser, Daniel M. Wachs, Adam B. Robinson, Mitch Meyer, Brandon D. Miller, Jian Gan
Publikováno v:
Journal of Nuclear Materials. 464:1-5
To investigate the thermal stability of the fission gas bubble superlattice, a key microstructural feature in both irradiated U–7Mo dispersion and U–10Mo monolithic fuel plates, a focused ion beam-transmission electron microscopy (FIB-TEM) sample
Autor:
Brandon D. Miller, Dennis D. Keiser, James W. Madden, Adam B. Robinson, Pavel Medvedev, Mitch Meyer, Jan-Fong Jue, Curtis R. Clark, Daniel M. Wachs, Jian Gan
Publikováno v:
Metallurgical and Materials Transactions E. 2:173-189
Low-enrichment (235U
Autor:
Kemal O. Pasamehmetoglu, Rekha S Pillai, Zachary Tudor, Michael Hagood, Anita K. Gianotto, David Schoonen, Sean O'Kelly, John Wagner, Ronald A. Crone, Kelly J. Beierschmitt, Steven Hartenstein, Mitch Meyer
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::e523c2aca8a95c14d1c59a93ee11ec11
https://doi.org/10.2172/1485430
https://doi.org/10.2172/1485430
Autor:
James W. Madden, Dennis D. Keiser, Pavel Medvedev, Mitch Meyer, Jian Gan, Jan-Fong Jue, Brandon D. Miller, Daniel M. Wachs, Adam B. Robinson
Publikováno v:
Nuclear Engineering and Technology, Vol 46, Iss 2, Pp 147-158 (2014)
In order to investigate how the microstructure of fuel/matrix-interaction (FMI) layers change during irradiation, different U?7Mo dispersion fuel plates have been irradiated to high fission density and then characterized using scanning electron micro