Nathan Almirall
Nathan Almirall
PHD Graduate Student Researcher
在 ucsb.edu 的电子邮件经过验证
标题
引用次数
引用次数
年份
Structural characterization of nanoscale intermetallic precipitates in highly neutron irradiated reactor pressure vessel steels
DJ Sprouster, J Sinsheimer, E Dooryhee, SK Ghose, P Wells, T Stan, ...
Scripta Materialia 113, 18-22, 2016
572016
Thermodynamic and kinetic modeling of Mn-Ni-Si precipitates in low-Cu reactor pressure vessel steels
H Ke, P Wells, PD Edmondson, N Almirall, L Barnard, GR Odette, ...
Acta Materialia 138, 10-26, 2017
532017
Stability of nanosized oxides in ferrite under extremely high dose self ion irradiations
E Aydogan, N Almirall, GR Odette, SA Maloy, O Anderoglu, L Shao, ...
Journal of Nuclear Materials 486, 86-95, 2017
402017
Thermodynamics and kinetics of core-shell versus appendage co-precipitation morphologies: An example in the Fe-Cu-Mn-Ni-Si system
S Shu, PB Wells, N Almirall, GR Odette, DD Morgan
Acta Materialia 157, 298-306, 2018
362018
Dose rate dependence of Cr precipitation in an ion-irradiated Fe18Cr alloy
ER Reese, N Almirall, T Yamamoto, S Tumey, GR Odette, EA Marquis
Scripta Materialia 146, 213-217, 2018
322018
Precipitation and hardening in irradiated low alloy steels with a wide range of Ni and Mn compositions
N Almirall, PB Wells, T Yamamoto, K Wilford, T Williams, N Riddle, ...
Acta Materialia 179, 119-128, 2019
302019
Precipitation in Fe-Cu and Fe-Cu-Mn model alloys under irradiation: Dose rate effects
S Shu, N Almirall, PB Wells, T Yamamoto, GR Odette, DD Morgan
Acta Materialia 157, 72-82, 2018
252018
On the elevated temperature thermal stability of nanoscale Mn-Ni-Si precipitates formed at lower temperature in highly irradiated reactor pressure vessel steels
N Almirall, PB Wells, H Ke, P Edmondson, D Morgan, T Yamamoto, ...
Scientific reports 9 (1), 1-12, 2019
172019
Infrastructure development for radioactive materials at the NSLS-II
DJ Sprouster, R Weidner, SK Ghose, E Dooryhee, TJ Novakowski, T Stan, ...
Nuclear Instruments and Methods in Physics Research Section A: Accelerators …, 2018
112018
The mechanistic implications of the high temperature, long time thermal stability of nanoscale Mn-Ni-Si precipitates in irradiated reactor pressure vessel steels
N Almirall, PB Wells, S Pal, PD Edmondson, T Yamamoto, K Murakami, ...
Scripta Materialia 181, 134-139, 2020
102020
The effect of composition variations on the response of steels subjected to high fluence neutron irradiation
BM Jenkins, JO Douglas, N Almirall, N Riddle, PAJ Bagot, JM Hyde, ...
Materialia 11, 100717, 2020
82020
On the use of charged particles to characterize precipitation in irradiated reactor pressure vessel steels with a wide range of compositions
N Almirall, PB Wells, T Yamamoto, K Yabuuchi, A Kimura, GR Odette
Journal of Nuclear Materials 536, 152173, 2020
62020
Effects of ATR-2 Irradiation to High Fluence on Nine RPV Surveillance Materials
RK Nanstad, GR Odette, N Almirall, JP Robertson, WL Server, ...
ORNL/TM-2017/172, April, 2017
42017
Precipitation in reactor pressure vessel steels under ion and neutron irradiation: On the role of segregated network dislocations
GR Odette, N Almirall, PB Wells, T Yamamoto
Acta Materialia 212, 116922, 2021
32021
Atom probe characterisation of segregation driven Cu and Mn–Ni–Si co-precipitation in neutron irradiated T91 tempered-martensitic steel
TP Davis, MA Auger, N Almirall, P Hosemann, GR Odette, PAJ Bagot, ...
Materialia 14, 100946, 2020
32020
On developing a mechanistic model and supporting database to predict high fluence-low flux extended life RPV embrittlement: status, challenges and opportunities
PB Wells, N Almirall, T Yamamoto, GR Odette
Transactions 111 (1), 451-453, 2014
22014
Some useful mechanical property correlations for nuclear reactor pressure vessel steels
RK Nanstad, WL Server, MA Sokolov, GR Odette, N Almirall
Pressure Vessels and Piping Conference 51685, V06BT06A019, 2018
12018
On the Dose Rate Dependence of Cr Clustering in Ion-Irradiated Fe-18Cr Alloys
ER Anderson, GR Odette, N Almirall, S Tumey, EA Marquis
Microscopy and Microanalysis 23 (S1), 690-691, 2017
12017
Embrittlement of Reactor Pressure Vessel Steels Under Extended Service Conditions: The Status and Implications of the UCSB ATR-2 Experiment [PowerPoint presentation]
GR Odette, P Wells, N Almirall, T Yamamoto, RK Nanstad, MA Sokolov, ...
Nuclear Power Plant Life Management. Proceedings of an International …, 2021
2021
On the Role of Mn-Ni-Si Precipitation in Irradiated Reactor Pressure Vessel Steels: Implications to Life Extension and Advanced Damage Tolerant Alloys
NT Almirall
University of California, Santa Barbara, 2021
2021
系统目前无法执行此操作,请稍后再试。
文章 1–20