Swelling of austenitic stainless steels under fast neutron irradiation at elevated temperatures

Lauritzen, T.; Withop, A.; Wolff, U.

doi:10.1016/0029-5493(69)90063-6

Cited by 20 publications

(3 citation statements)

References 2 publications

Supporting

Mentioning

Contrasting

Order By: Relevance

“…To demonstrate unambiguously the nature of a dislocation loop, (1) the Burgers vector, (2) the loop plane and (3) the inside-outside behavior in ±g must be fully analyzed. For a pure edge loop, such as a Frank loop, (1) and (3) will be sufficient because the Burgers vector is perpendicular to the loop plane.…”

Section: Resultsmentioning

confidence: 99%

See 1 more Smart Citation

Drastic influence of micro-alloying on Frank loop nature in Ni and Ni-based model alloys

Décamps

Frączkiewicz

et al. 2020

Materials Research Letters

View full text Add to dashboard Cite

Nickel and its alloys are f.c.c. model materials to investigate the elementary mechanisms of radiation damage and solute effects. This paper focuses on the drastic influence of micro-alloying (0.4 wt.% Ti or Cr) on the nature of defects after ion irradiation. Ultra-high purity materials are used to avoid impurity effects. For the first time, (i) large stable intrinsic Frank loops are identified in nickel while in alloys extrinsic Frank loops are observed; (ii) an eradication mechanism of intrinsic Frank loops is clearly identified; (iii) the morphology of Frank loops is shown to be characteristic of their nature. IMPACT STATEMENT For the first time, a drastic influence of micro-alloying on the defect nature is shown in irradiated Ni systems. Minor addition of solutes modifies significantly elementary mechanisms of radiation damage.

show abstract

Section: Resultsmentioning

confidence: 99%

“…Advanced austenitic steels are candidate materials for current and future nuclear systems. Their main limitation is their macroscopic volume extension under irradiation, so-called void swelling [1,2]. Empirically, the fine-tuning of major elements (Ni, Cr) and the addition of some minor solutes (Ti, etc.)…”

Section: Introductionmentioning

confidence: 99%

Drastic influence of micro-alloying on Frank loop nature in Ni and Ni-based model alloys

Décamps

Frączkiewicz

et al. 2020

Materials Research Letters

View full text Add to dashboard Cite

show abstract

“…The helium atoms act as a vacancy trap forming helium-vacancy complexes (helium bubbles) [3,4]. Experimental studies on helium implanted samples of austenitic steels [5][6][7][8][9][10][11][12][13] revealed the existence of small, mainly spherical, bubbles with diameters ranging from less than a nanometer [7] to more than a hundred of nanometers [6]. The helium bubbles number density in the steel matrix varies from 10 20 m -3 to 10 24 m -3 .…”

Section: Introductionmentioning

confidence: 99%

Molecular dynamics modeling of helium bubbles in austenitic steels

Jelea

2018

Nuclear Instruments and Methods in Physics Research Section B:

View full text Add to dashboard Cite

The austenitic steel devices from pressurized water reactors are continuously subjected to neutron irradiation that produces crystalline point defects and helium atoms in the steel matrix. These species evolve into large defects such as dislocation loops and helium filled bubbles. This paper analyzes, through molecular dynamics simulations with recently developed interatomic potentials, the impact of the helium/steel interface on the helium behavior in nanosize bubbles trapped in an austenitic steel matrix. It is shown that the repulsive helium-steel interactions induce higher pressures in the bubble compared to bulk helium at the same temperature and average density. A new equation of state for helium is proposed in order to take into account these interface effects.

show abstract

Irradiation-produced defects in austenitic stainless steel

Brager¹,

Straalsund²,

Holmes³

et al. 1971

Metall Trans

View full text Add to dashboard Cite

The microstructure of annealed AISI Type 304 and Type 316 stainless steels has been characterized by transmission electron microscopy as a function of fast reactor irradiation at fluence levels from 4 x 1021 to 7 x 1022 n/cm2 (E > 0.1 MeV) and at irradiation temperatures from 370 to 700°C. Several irradiation produced defect types were found: voids, Frank faulted loops, perfect loops, dislocation networks, and precipitates. Void number density obeys a power law relationship to fluence. wherein the exponent increases with increasing temperature and has a mean value near unity; The void size is nearly •independent of fluence and increases with increasing temperature. The upper limit irradiation temperature for void formation is about 650 to 700°C. The density and size of Frank faulted loops followed.trends similar to those found for voids to temperatures of ~ssooc where unfaulted loops, perfect loops, and dislocation networks coexist. These experimental results do not confirm predictions of recently advanced models of void formation. The major deficiency of these models appears• to be the nucleation rate. Accordingly, empirical nucleation rates were used to formulate a diffusion controlled void growth model. This model was found to closely describe experimentally determined void growth kinetics .

show abstract

Swelling of austenitic stainless steels under fast neutron irradiation at elevated temperatures

Cited by 20 publications

References 2 publications

Drastic influence of micro-alloying on Frank loop nature in Ni and Ni-based model alloys

Drastic influence of micro-alloying on Frank loop nature in Ni and Ni-based model alloys

Molecular dynamics modeling of helium bubbles in austenitic steels

Irradiation-produced defects in austenitic stainless steel

Contact Info

Product

Resources

About