2004
DOI: 10.1016/j.jnucmat.2004.04.127
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Control of phosphorus inter-granular segregation in ferritic steels

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Cited by 10 publications
(10 citation statements)
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“…For undersized solutes, the binding energy is positive and the solutes migrate in the same direction as the self-interstitial. On the basis of the earlier models [10,12], the misorientation and stress effects are included. The maximum segregation, C j m , of undersized atoms induced by irradiation at grain boundary in ternary alloys can be expressed by…”
Section: Ris For Undersized Atomsmentioning
confidence: 99%
See 1 more Smart Citation
“…For undersized solutes, the binding energy is positive and the solutes migrate in the same direction as the self-interstitial. On the basis of the earlier models [10,12], the misorientation and stress effects are included. The maximum segregation, C j m , of undersized atoms induced by irradiation at grain boundary in ternary alloys can be expressed by…”
Section: Ris For Undersized Atomsmentioning
confidence: 99%
“…chromium in austenitic steels, is believed to contribute to the irradiation-assisted stress corrosion cracking (IASCC) [2]. It has been found that radiation-induced Cr depletion in austenitic steels and radiation-induced P enrichment in ferritic steels can be suppressed by oversized atom additions [3][4][5][6][7][8][9][10]. Ti, V, Nb, Ta, Zr, Hf and Pt were added to austenitic steels [3][4][5][6][7][8][9] and Hf to ferritic steel [10] to study the influence of oversized solute additions on radiation-induced segregation (RIS).…”
Section: Introductionmentioning
confidence: 99%
“…Thus, it is reasonable to expect that there is a high impurity grain boundary segregation of elements, such as P, in the high Cr ferritic steels subjected to high neutron fluence irradiation. Experimental results [4][5][6] verified that irradiation induced intergranular segregation of impurity atoms, like P and Si, occurs in several high Cr ferritic steels. However, so far, few investigations of intergranular impurity segregation on the DBTT in high Cr ferritic steels have been carried out.…”
Section: Introductionmentioning
confidence: 67%
“…A solute drag model has been applied successfully to predict the radiation-induced impurity segregation in 9Cr ferritic steel [4]. The maximum neutron irradiation-induced intergranular maximum impurity segregation in ferritic steels is given by [3],…”
Section: Radiation-induced Impurity Segregationmentioning
confidence: 99%
“…An especially important problem is the segregation of P atoms to the grain boundaries of the steel, which is thought to be a major cause of embrittlement. [1][2][3][4] This can lead to a serious reduction in the lifetime of NPVs. It is therefore very important to be able to understand the mechanisms by which this segregation takes place, both to predict the mechanical properties of the NPVs as a function of time and to give pointers towards measures that could be taken to reduce the embrittlement problem.…”
Section: Introductionmentioning
confidence: 99%