Zobrazeno 1 - 10
of 33
pro vyhledávání: '"B. R. Betzler"'
Publikováno v:
Nuclear Science and Engineering. 196:1572-1580
Publikováno v:
Nuclear Technology. 208:1433-1452
Autor:
B. R. Betzler, B. J. Ade, P. K. Jain, A. J. Wysocki, P. C. Chesser, W. M. Kirkland, M. S. Cetiner, A. Bergeron, F. Heidet, K. A. Terrani
Publikováno v:
Nuclear Science and Engineering. 196:1399-1424
Publikováno v:
Nuclear Science and Engineering. 196:1476-1495
Autor:
S. N. P. Vegendla, Florent Heidet, B. R. Betzler, A. Bergeron, Brian J Ade, Kurt A. Terrani, S. Mohanty, Alberto Talamo
Publikováno v:
Nuclear Science and Engineering. 196:1464-1475
Autor:
Margulis, M., Blaise, P., Bae, J. W.1 baej@ornl.gov, Betzler, B. R.1 betzlerbr@ornl.gov, Chandler, D.1 chandlerd@ornl.gov, Ilas, G.1 ilasg@ornl.gov
Publikováno v:
EPJ Web of Conferences. 2021, Vol. 247, p1-9. 9p.
Autor:
B. R. Betzler, Briana Hiscox, Emilian L. Popov, Cory D. Hauck, Rick Archibald, Vladimir Sobes, Kurt A. Terrani
Publikováno v:
Scientific Reports
Scientific Reports, Vol 11, Iss 1, Pp 1-9 (2021)
Scientific Reports, Vol 11, Iss 1, Pp 1-9 (2021)
The authors developed an artificial intelligence (AI)-based algorithm for the design and optimization of a nuclear reactor core based on a flexible geometry and demonstrated a 3× improvement in the selected performance metric: temperature peaking fa
Autor:
M. Scott Greenwood, B. R. Betzler
Publikováno v:
Nuclear Science and Engineering. 193:417-430
Fluid-fueled nuclear reactors, such as molten salt reactors (MSRs), have recently gained significant interest. These advanced reactors represent a potential revolutionary shift in the implementatio...
Publikováno v:
EPJ Web of Conferences, Vol 247, p 08016 (2021)
The mission of the Neutron Sciences Directorate (NScD) at the U.S. Department of Energy’s Oak Ridge National Laboratory (ORNL) is the undertaking of high-impact research into the structure and properties of materials across the spectrum of biology,
Publikováno v:
EPJ Web of Conferences, Vol 247, p 08017 (2021)
Engineering design studies are underway to assess the feasibility of converting the High Flux Isotope Reactor (HFIR) to operate with low-enriched uranium silicide dispersion (LEU3Si2-Al) fuel. These studies are supported by the U.S. Department of Ene