A SANS investigation of the irradiation-enhanced α–α′ phases separation in 7–12 Cr martensitic steels

Implications of ab initio energetics on the thermodynamics of Fe–Cr alloys

“…In Fig. 3 we have added the experimental results of Kuwano and Hamaguchi, 5 and those of Mathon et al 8 The discrepancy between the SSOL solvus and the solvus implied in the ab initio results is obvious, as is the agreement between the experimental results and our prediction. The most striking difference is the fact that the solvus line, if extrapolated to zero temperature, does not cross the x axis at x = 0, as explicitly assumed in the CALPHAD treatment.…”

“…Kuwano and Hamaguchi 5 reported neutron irradiation results showing precipitation of Cr in the postirradiation annealing for x Cr ജ 10% at 800 K. Sagaradze et al 6 reported electron irradiation results at the same temperature showing similar behavior. Inversion of the sign of short range order was recently confirmed by Shabashov et al 7 Finally, Mathon et al 8 studied steels with 7 -10 wt % Cr under neutron irradiation and again confirmed the separation into ␣ and ␣Ј. From the experimental point of view it seems clear then that both the binary alloy and the steel have ordering for low Cr content and segregation above it, a somehow interesting behavior.…”

Neutron analyses for nuclear materials: Texture, residual stresses and small angle scattering

“…S(q,R) is the interference term between precipitates, which is not negligible for a precipitated fraction larger than 1%; a formulation which is commonly used in solid system, is the structure factor for a liquid-like arrangement of hard spheres, calculated analytically by Ashcroft and Lekner [9] from the Percus-Yevick equation. Moreover, generally, the particles sizes are not mono-disperse, so the SANS intensity includes a size distribution function h(R).…”

“…Reactor) [9,10] Martensitic steels with 7-12 wt% Cr are candidates for the internal structures of future generation nuclear reactors or spallation sources, because of their remarkable mechanical properties and resistance to swelling; but they suffer from radiation hardening and embrittlement below 400 • C, even at moderate doses. In order to promote their use, it is necessary to understand the evolution of their microstructure and its relationship with the degradation of mechanical properties during irradiation.…”

Assessment of a new fabrication route for Fe–9Cr–1W ODS cladding tubes

“…For ferromagnetic materials, the neutron scattering cross-section is composed of a nuclear contribution and a magnetic one. Measurements were made at room temperature under a saturate magnetic field of 1.7 Tesla perpendicular to the incident neutron beam direction [10][11].…”