Zobrazeno 1 - 10
of 76
pro vyhledávání: '"Douglas L. Porter"'
Autor:
Andrei V. Gribok, Fidelma G. Di Lemma, Jake Fay, Douglas L. Porter, Kyle M. Paaren, Luca Capriotti
Publikováno v:
Energies, Vol 17, Iss 9, p 1990 (2024)
Approximately 130,000 metal fuel pins were irradiated in the Experimental Breeder Reactor II (EBR-II) during its 30 years of operation to develop and characterize existing and prospective fuels. For many of the metal fuel irradiation experiments, neu
Externí odkaz:
https://doaj.org/article/db6a491dc60140b4b017a0bfa3237756
Autor:
Jacob A. Hirschhorn, Jeffrey J. Powers, Ian Greenquist, Ryan T. Sweet, Jianwei Hu, Douglas L. Porter, Douglas C. Crawford
Publikováno v:
Nuclear Science and Engineering. 196:123-147
Publikováno v:
Journal of Nuclear Materials. 519:205-216
The irradiation-induced void swelling of HT9 stainless steel has been observed many times, but there are little data available to quantify the amount of swelling expected as a function of neutron exposure and temperature. This is further complicated
Publikováno v:
Energies, Vol 14, Iss 515, p 515 (2021)
Energies; Volume 14; Issue 2; Pages: 515
Energies; Volume 14; Issue 2; Pages: 515
BISON finite element method fuel performance simulations were conducted using an existing automated process that couples the Fuels Irradiation & Physics Database (FIPD) and the Integral Fast Reactor Materials Information System database by writing in
Autor:
Steven L. Hayes, Douglas L. Porter, Jason M. Harp, Heather J.M. Chichester, Luca Capriotti, Pavel Medvedev
Publikováno v:
Journal of Nuclear Materials. 509:454-464
Irradiation experiments on metallic fuel alloys containing rare earth additions to simulate potential carry-over from pyro-metallurgical reprocessing and minor actinide additions were performed in the Idaho National Laboratory Advanced Test Reactor.
Autor:
Douglas L. Porter, Kyle M. Paaren, Nancy J. Lybeck, Andrei V. Gribok, Scott Middlemas, Micah Gale
Publikováno v:
Journal of Nuclear Materials. 557:153250
Approximately 130,000 metal fuel pins were irradiated in the Experimental Breeder Reactor II (EBR-II) during its 30 years of operation to develop and characterize existing and prospective fuels. For many of the metal fuel irradiation experiments, neu
Publikováno v:
Journal of Nuclear Materials. 557:153304
A slow-ramp (0.1%/s), extended overpower (∼32%) transient was conducted in the Experimental Breeder Reactor-II (EBR-II) on 19 metallic alloy fuel elements, including both binary (U-Zr) and ternary (U-Pu-Zr) fuel designs. The elements were clad in e
Publikováno v:
Nuclear Engineering and Design. 382:111393
Using the BISON fuel performance code, simulations were conducted using an automated process to read initial and operating conditions from the Fuels Irradiation and Physics Database (FIPD) and Integral Fast Reactor materials information system (IMIS)