Microstructure of HIPed and SPSed 9Cr-ODS steel and its effect on helium bubble formation

Lu, Chenyang; Lu, Zheng; Xie, Rui; Liu, Chunming; Wang, Lumin

doi:10.1016/j.jnucmat.2016.03.010

Cited by 40 publications

(7 citation statements)

References 36 publications

Supporting

Mentioning

Contrasting

Order By: Relevance

“…Introducing high-densities of defect sinks, such as secondary phase or grain boundaries, is a popular way for reducing residual defects in irradiated materials. The success of this approach has been demonstrated in oxide-dispersion-strengthened steels567, nano-layered8 and nano-grained polycrystalline alloys9. However, the nanostructures in the above materials are often unstable at elevated temperatures and in extreme radiation environments1011.…”

mentioning

confidence: 99%

Enhancing radiation tolerance by controlling defect mobility and migration pathways in multicomponent single-phase alloys

et al. 2016

Self Cite

View full text Add to dashboard Cite

A grand challenge in material science is to understand the correlation between intrinsic properties and defect dynamics. Radiation tolerant materials are in great demand for safe operation and advancement of nuclear and aerospace systems. Unlike traditional approaches that rely on microstructural and nanoscale features to mitigate radiation damage, this study demonstrates enhancement of radiation tolerance with the suppression of void formation by two orders magnitude at elevated temperatures in equiatomic single-phase concentrated solid solution alloys, and more importantly, reveals its controlling mechanism through a detailed analysis of the depth distribution of defect clusters and an atomistic computer simulation. The enhanced swelling resistance is attributed to the tailored interstitial defect cluster motion in the alloys from a long-range one-dimensional mode to a short-range three-dimensional mode, which leads to enhanced point defect recombination. The results suggest design criteria for next generation radiation tolerant structural alloys.

show abstract

mentioning

confidence: 99%

Enhancing radiation tolerance by controlling defect mobility and migration pathways in multicomponent single-phase alloys

et al. 2016

Self Cite

View full text Add to dashboard Cite

show abstract

“…A category of reduced activation ferritic/martensitic (F/M) steels, nanostructured oxide dispersion strengthened (ODS) steels are considered as promising candidate materials for first wall/blanket applications in fusion reactor because of their promising swelling resistance under irradiation and excellent high-temperature mechanical properties24. Atom probe tomography (APT) and transmission electron microscopy (TEM) revealed that ultra-high density nano-oxides were dispersed homogenously in the steel matrix and at the grain boundaries24567. In theory, the interface between matrix and nano-oxide particles can act as efficient trapping sites for point defects and helium atoms to enhance defect recombination and disperse helium atoms, thus minimizing helium embrittlement and suppressing void swelling4.…”

mentioning

confidence: 99%

Enhanced Radiation-tolerant Oxide Dispersion Strengthened Steel and its Microstructure Evolution under Helium-implantation and Heavy-ion Irradiation

Wang

et al. 2017

Sci Rep

Self Cite

View full text Add to dashboard Cite

The world eagerly needs cleanly-generated electricity in the future. Fusion reactor is one of the most ideal energy resources to defeat the environmental degradation caused by the consumption of traditional fossil energy. To meet the design requirements of fusion reactor, the development of the structural materials which can sustain the elevated temperature, high helium concentration and extreme radiation environments is the biggest challenge for the entire material society. Oxide dispersion strengthened steel is one of the most popular candidate materials for the first wall/blanket applications in fusion reactor. In this paper, we evaluate the radiation tolerance of a 9Cr ODS steel developed in China. Compared with Ferritic/Martensitic steel, this ODS steel demonstrated a significantly higher swelling resistance under ion irradiation at 460 °C to 188 displacements per atom. The role of oxides and grain boundaries on void swelling has been explored. The results indicated that the distribution of higher density and finer size of nano oxides will lead a better swelling resistance for ODS alloy. The original pyrochlore-structured Y2Ti2O7 particles dissolved gradually while fine Y-Ti-O nano clusters reprecipitated in the matrix during irradiation. The enhanced radiation tolerance is attributed to the reduced oxide size and the increased oxide density.

show abstract

“…For that to happen the molten metal drops have to inflow into the liquid-alloy close to the convection cell axis around Stokes lines area with the amplitudes from 0.046 to 0.162. In this case, similar to the numerical calculations given in [7][8][9], convective flows capture zirconium dioxide particles and distribute them within the cell volume and at the same time they simultaneously homogenize them.…”

Section: Zro 2 Particles Size and Their Homogenization Condition In Omentioning

confidence: 64%

“…Study of properties of ODS steels ductility was performed for 9Cr-ODS steel with equal nominal content produced by means of hot isostatic pressing (HIP, steel was named COS-1) and spark plasma sintering (SPS, steel was named COS-2) [9]. The results had shown bimodal grain size distribution in COS-2 and more uniform grain size distribution in COS-1 steel samples, which indicates that COS-2 steel samples had higher metal ductility.…”

Section: Literature Review and Problem Statementmentioning

confidence: 99%

See 1 more Smart Citation

Investigation of the oxide phase convective homogenization while vacuum-arc with hollow cathode remelting of steel

Andreeva

Borts

Kostikov

et al. 2016

EEJET

View full text Add to dashboard Cite

Досліджено процес гомогенізації порошку діоксиду цирконію при вакуумно-дуговому виготовленні реакторних сталей. Процес гомогенізації запропоновано здійснювати в конвективному осередку з неплоским профілем дна і змішаними межами, який формується при переплаві сталі, з застосуванням катоду з поперечним перерізом типу «hollow fish-bone». Аналізується вплив форми катоду, розміру легуючих частинок, масопереносу в конвективному осередку на рівномірність розподілу діоксиду цирконію в розплаві сталі Ключові слова: реакторна сталь, порошок оксиду, порожнистий катод, вакуумно-дуговий переплав, конвективний осередок, змішані граничні умови, масоперенос, гомогенізація Исследован процесс гомогенизации порошка диоксида циркония при вакуумно-дуговом изготовлении реакторных сталей. Процесс гомогенизации предложено осуществлять в конвективной ячейке с неплоским профилем дна и смешанными пределами, который формируется при переплаве стали, с применением катода с поперечным сечением типа «hollow fishbone». Анализируется влияние формы катода, размера легирующих частиц, массопереноса в конвективной ячейке на равномерность распределения диоксида циркония в расплаве сталиКлючевые слова: реакторная сталь, порошок оксида, полый катод, вакуумно-дуговой переплав, конвективная ячейка, смешанные граничные условия, массоперенос, гомогенизация UDC 621.384.6:620.198

show abstract

Microstructure of HIPed and SPSed 9Cr-ODS steel and its effect on helium bubble formation

Cited by 40 publications

References 36 publications

Enhancing radiation tolerance by controlling defect mobility and migration pathways in multicomponent single-phase alloys

Enhancing radiation tolerance by controlling defect mobility and migration pathways in multicomponent single-phase alloys

Enhanced Radiation-tolerant Oxide Dispersion Strengthened Steel and its Microstructure Evolution under Helium-implantation and Heavy-ion Irradiation

Investigation of the oxide phase convective homogenization while vacuum-arc with hollow cathode remelting of steel

Contact Info

Product

Resources

About