Chen et al., 2013 - Google Patents
Irradiation creep of candidate materials for advanced nuclear plantsChen et al., 2013
- Document ID
- 8887473821132606401
- Author
- Chen J
- Jung P
- Hoffelner W
- Publication year
- Publication venue
- Journal of nuclear materials
External Links
Snippet
In the present paper, irradiation creep results of an intermetallic TiAl alloy and two ferritic oxide dispersion strengthened (ODS) steels are summarized. In situ irradiation creep measurements were performed using homogeneous implantation with α-and p-particles to …
- 239000000463 material 0 title abstract description 22
Classifications
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C3/00—Reactor fuel elements and their assemblies; Selection of substances for use as reactor fuel elements
- G21C3/02—Fuel elements
Similar Documents
| Publication | Publication Date | Title |
|---|---|---|
| Chen et al. | Dislocation loops and bubbles in oxide dispersion strengthened ferritic steel after helium implantation under stress | |
| Naeem et al. | Temperature-dependent hardening contributions in CrFeCoNi high-entropy alloy | |
| Chen et al. | Irradiation creep of candidate materials for advanced nuclear plants | |
| Alsabbagh et al. | Microstructure and mechanical behavior of neutron irradiated ultrafine grained ferritic steel | |
| Mo et al. | High temperature aging and corrosion study on alloy 617 and alloy 230 | |
| Shen et al. | Proton irradiation effects on the precipitate in a Zr–1.6 Sn–0.6 Nb–0.2 Fe–0.1 Cr alloy | |
| Maloy et al. | Characterization and comparative analysis of the tensile properties of five tempered martensitic steels and an oxide dispersion strengthened ferritic alloy irradiated at≈ 295 C to≈ 6.5 dpa | |
| Jiang et al. | Bubbles and precipitates formation and effects on the hardening of irradiated vanadium alloys | |
| Onimus et al. | Experimental analysis of slip systems activation in neutron-irradiated zirconium alloys and comparison with polycrystalline model simulations | |
| Chen et al. | Deuterium transport and retention properties of representative fusion blanket structural materials | |
| Lin et al. | In situ synchrotron tensile investigations on 14YWT, MA957, and 9-Cr ODS alloys | |
| Oksiuta et al. | Microstructural changes upon annealing in ODS-strengthened ultrafine grained ferritic steel | |
| Liu et al. | Deuterium permeation behavior in a FeCrAl-based alloy containing Mo, Nb and Ta elements for LWR cladding application | |
| Park et al. | High-energy synchrotron x-ray techniques for studying irradiated materials | |
| Brown et al. | Elastic properties of rolled uranium–10 wt.% molybdenum nuclear fuel foils | |
| Chen et al. | Irradiation creep and microstructural changes of ODS steels of different Cr-contents during helium implantation under stress | |
| Miao et al. | Load-partitioning in an oxide dispersion-strengthened 310 steel at elevated temperatures | |
| Kumar et al. | Evolution of microstructure and crystallographic texture during cold rolling of liquid phase sintered tungsten heavy alloy | |
| Kerber et al. | In Situ Synchrotron X‐Ray Diffraction during High‐Pressure Torsion Deformation of Ni and NiTi | |
| Chen et al. | Irradiation creep of oxide dispersion strengthened (ODS) steels for advanced nuclear applications | |
| Likhanskii et al. | Method of elastic energy minimization for evaluation of transition parameters in oxidation kinetics of Zr alloys | |
| Cha et al. | The effect of hydrogen and oxygen contents on hydride reorientations of zirconium alloy cladding tubes | |
| Rogozhkin et al. | The influence of Fe-ion irradiation on the microstructure of reduced activation ferritic-martensitic steel Eurofer 97 | |
| Chen et al. | Irradiation creep and precipitation in a ferritic ODS steel under helium implantation | |
| Chakravartty et al. | Superplasticity in. beta.-zirconium; A study using a processing map |