Zobrazeno 1 - 10
of 24
pro vyhledávání: '"Karen E. Wright"'
Publikováno v:
Journal of Nuclear Materials. 559
Two tristructural isotropic (TRISO)-coated nuclear fuel particles were examined by electron probe microanalysis (EPMA) as part of the Advanced Gas Reactor program. The compacts’ average irradiation temperatures ranged from approximately 1260 to 129
Publikováno v:
MRS Advances, 6(47-48)
Two irradiated AGR-2 TRISO particles were chosen to demonstrate a recently developed mass balance technique in which EPMA-generated concentration data were used to determine fission product mass on a layer-by-layer basis in TRISO particles. EPMA-calc
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::83354cef43d21087961429210f38d6ce
https://doi.org/10.1557/s43580-021-00166-2
https://doi.org/10.1557/s43580-021-00166-2
Autor:
Casey McKinney, Alexander Winston, Karen E. Wright, Assel Aitkaliyeva, Jason M. Harp, Riley Parrish
Publikováno v:
Journal of Nuclear Materials. 524:67-79
This work utilizes electron microscopy-based techniques to examine the radial behavior of solid fission products in plutonium (Pu) bearing mixed oxide (MOX) fuel irradiated to a burnup of 13.7% fissions per initial metal atom (FIMA). Metallic precipi
Publikováno v:
Transactions of the American Nuclear Society - Volume 121.
Autor:
Alexander Winston, Luca Capriotti, Daniel M. Wachs, Fidelma Di Lemma, Colby Jensen, Karen E. Wright, Adam X. Zabriskie
Publikováno v:
Journal of Nuclear Materials. 544:152711
The influence of a reactor overpower transient on irradiated metallic fuel performance was investigated in this work. Such transient studies support safety and performance optimization of future sodium fast reactors. A ternary metallic fuel alloy (U-
Autor:
Tiankai Yao, Jason M. Harp, Qingsheng Cai, Michael T. Benson, James A. King, Karen E. Wright, Ayman I. Hawari, Kevin R. Tolman, Yi Xie
Publikováno v:
Journal of Nuclear Materials. 544:152727
Palladium is being investigated as a fuel additive to bind with and potentially immobilize lanthanide fission products. A primary cause of fuel-cladding chemical interaction (FCCI) is the lanthanide fission products migrating to the fuel periphery an
Publikováno v:
Microscopy and Microanalysis. 26:874-874
Fission product distribution in irradiated safety-tested and non-safety-tested AGR-2 TRISO particles
Autor:
Karen E. Wright, I. J. van Rooyen
Publikováno v:
IOP Conference Series: Materials Science and Engineering. 891:012024
Two similarly-irradiated TRISO nuclear fuel particles, one safety-tested and one not-safety-tested, were examined by electron probe microanalysis (EPMA) as part of the advanced gas reactor (AGR) fuel development and qualification programme. The prima
Publikováno v:
Journal of Nuclear Materials. 526:151745
Electron microprobe examinations were performed to characterize the chemical features of a full cross section of irradiated nuclear fuel from the FUTURIX-FTA experiment. This experiment investigated the nuclear fuel performance of a candidate fuel al
Publikováno v:
Microscopy and Microanalysis. 25:1612-1613