The role of niobium carbide in radiation induced segregation behaviour of type 347 austenitic stainless steel

Resistance to He2+ irradiation damage in metallic glass Fe80Si7.43B12.57

“…DPA [22] can be obtained from the vacancy and phonon distribution calculated by SRIM. The expression of DPA can be derived from NRT equation [23][24][25][26],…”

The effect of sodium hydroxide on niobium carbide precipitates in thermally sensitised 20Cr-25Ni-Nb austenitic stainless steel

“…However, if this were to be the case, then NbC interfaces would show a similar microchemistry to a RIS sensitised grain boundary for instance: Cr depletion and Ni enrichment. The pitting corrosion Ahmedabadi et al [15] witnessed around NbC clusters, said to be from an excess of defects, would differ from that exhibited in thermally sensitised 20Cr-25Ni-Nb as the material was proton irradiated through the RIS sensitisation mechanism.…”

“…Ahmedabadi et al [15] did not observe corrosion around NbC precipitates following a double loop electrochemical potentiokinetic reactivation (DL-EPR) test for sensitisation on a proton irradiated Nb-stabilised AISI 347 (EN 1.4550, UNS S34700) austenitic stainless steel. They did, however, observe the presence of pits at large clusters of smaller sized NbC precipitates (~300 nm), indicating that the NbC precipitates create strained regions within the matrix; pointing to past work on oversized elements limiting Cr depletion (from RIS) [16] and other works on thermal sensitisation [17].…”

“…Proton irradiation of 20Cr-25Ni-Nb stainless steel has also been conducted by Alshater et al [18], though in the published work such voids were not observed at either the Bragg peak, the NbC precipitates nor the NbC-matrix interface. Ahmedabadi et al [15] suggest another reason for the pitting around NbC clusters may be due to Cr depletion at the precipitate-precipitate interface. However, if this were to be the case, then NbC interfaces would show a similar microchemistry to a RIS sensitised grain boundary for instance: Cr depletion and Ni enrichment.…”

Ar12+Induced Irradiation Damage in Bulk Metallic Glass (Cu47Zr45Al8)98.5Y1.5

“…where 𝐸 d is the displacement energy, 𝑑𝐸 𝑑𝑥 is the linear energy transfer per ion to target by nuclear processes, 𝜑 t is the fluence per unit area and 𝜌 is the atomic density, ( 𝑑𝐸 𝑑𝑥 ) nuclear is obtained from SRIM2013 by summing up phonon and binding energy profiles. [24] Figure 1 shows the incident depth-dependent curve for the DPA arising from the 3 MeV Ar ion irradiation of metallic glass at a fluence of 1 × 10 16 ions/cm 2 . As can be seen from Fig.…”