Irradiation damage concurrent challenges with RAFM and ODS steels for fusion reactor first-wall/blanket: a review
Reduced activation ferritic martensitic (RAFM) and oxide dispersion strengthened (ODS)
steels are the most promising candidates for fusion first-wall/blanket (FW/B) structures. The …
steels are the most promising candidates for fusion first-wall/blanket (FW/B) structures. The …
Corrosion of 316H stainless steel in flowing FLiNaK salt
Type 316H stainless steel samples were exposed to flowing FLiNaK salt for 1000 h in a
monometallic thermal convection loop (TCL) with a maximum temperature of 650° C and a …
monometallic thermal convection loop (TCL) with a maximum temperature of 650° C and a …
Recent Progress on Creep Properties of ODS FeCrAl Alloys for Advanced Reactors
H Jia, Y Wang, Y Wang, L Han, Y Zhang, Z Zhou - Materials, 2023 - mdpi.com
In order to meet the growing energy demand, more environmentally friendly and efficient
GEN-IV reactors have emerged. Additionally, nuclear structural materials need larger more …
GEN-IV reactors have emerged. Additionally, nuclear structural materials need larger more …
Evaluation of the interaction between SiC, pre-oxidized FeCrAlMo with aluminized and pre-oxidized Fe-8Cr-2W in flowing PbLi
Dissimilar materials interactions are a major concern when liquid metals are used as a
working fluid. To simulate a dual-coolant PbLi blanket, chemical vapor deposited (CVD) SiC …
working fluid. To simulate a dual-coolant PbLi blanket, chemical vapor deposited (CVD) SiC …
[HTML][HTML] Chemical and structural durability of α-Al2O3 and γ-LiAlO2 layers formed on ODS FeCrAl alloys in liquid lithium lead stirred flow
The protection performance of an α-Al 2 O 3 layer formed on oxide dispersion-strengthened
(ODS) FeCrAl alloys in liquid LiPb flow was investigated by means of the corrosion tests …
(ODS) FeCrAl alloys in liquid LiPb flow was investigated by means of the corrosion tests …
The Tritium Extraction eXperiment (TEX): A forced convection fusion blanket PbLi loop
A forced convection PbLi loop has been designed and constructed to test tritium extraction
from molten PbLi. This Tritium Extraction eXperiment (TEX) is designed to operate at …
from molten PbLi. This Tritium Extraction eXperiment (TEX) is designed to operate at …
Corrosion-resistant materials for liquid LiPb fusion blanket in elevated temperature operation
The corrosion tests of CVD-SiC, FeCrAl alloy (APMT, Fe-22Cr-5Al) and ODS FeCrAlZr alloy
(NF12, Fe-11.6 Cr-6.2 Al) were performed in liquid LiPb up to 1173 K for 250 h. High-purity …
(NF12, Fe-11.6 Cr-6.2 Al) were performed in liquid LiPb up to 1173 K for 250 h. High-purity …
[HTML][HTML] Growth of α-Al2O3 layer involving abnormal oxides in FeCrAl alloy tube fabricated by WEDM process and electrical insulating performance in fusion reactor …
The tubular specimens of FeCrAl alloy APMT (Fe-22Cr-5Al-3Mo) were fabricated by a wire
electrical discharge machining (WEDM) process. The oxidation characteristics of the …
electrical discharge machining (WEDM) process. The oxidation characteristics of the …
Exploring Material Solutions for Supercritical CO2 Applications above 800 °C
BA Pint, JR Keiser - Oxidation of Metals, 2022 - Springer
There has been recent interest in exploring revolutionary supercritical CO2 (sCO2) power
cycles, and this exploratory investigation was seeking materials with CO2 compatibility at up …
cycles, and this exploratory investigation was seeking materials with CO2 compatibility at up …
Prediction of PbLi fluid flow and temperature field in a thermal convection loop for qualification of fusion materials
Two modeling tools, a thermohydraulics code and a computational model in COMSOL
Multiphysics, have been developed, tested and then applied to the analysis of fluid flow and …
Multiphysics, have been developed, tested and then applied to the analysis of fluid flow and …