Microchemical evolution of irradiated additive-manufactured HT9

Xiu, Pengyuan; Massey, Caleb; Green, T.M. Kelsy; Taller, Stephen; Isheim, Dieter; Field, Kevin G.

doi:10.1016/j.jnucmat.2021.153410

Cited by 5 publications

(2 citation statements)

References 90 publications

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“…ORNL published a series of papers on the additively manufactured HT9, but all the work they did was on the blown powder technique. The characterization showed that the as-built structure essentially consisted of a martensitic matrix with δ-ferrite present in the reheat zones between each pass during the sample fabrication process [19]- [21]. The martensitic matrix consisted of an ultrafine dispersion of carbides and carbonitrides.…”

Section: Ht9mentioning

confidence: 99%

Evaluation of LPBF Steels for Nuclear Applications

Mantri¹,

Zhang²

2023

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Section: Ht9mentioning

confidence: 99%

Evaluation of LPBF Steels for Nuclear Applications

Mantri¹,

Zhang²

2023

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“…), MnNi-rich precipitates (MNP), and P segregation on grain boundaries [ 12 , 13 ]. Recently published papers [ 14 , 15 ] also described Cu- and Ni/Si/Mn-rich clusters in irradiated reactor steels and they are often being located near line dislocations. Structural defects such as vacancies or dislocations probably can suppress the formation of large Ni/Si/Mn-rich and Cu-rich clusters by reducing the diffusion process under irradiation.…”

Section: Introductionmentioning

confidence: 99%

Positron Annihilation Study of RPV Steels Radiation Loaded by Hydrogen Ion Implantation

et al. 2022

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Specimens of 15Kh2MFAA steel used for reactor pressure vessels V-213 (VVER-440 reactor) were studied by positron annihilation techniques in terms of their radiation resistance and structural recovery after thermal treatment. The radiation load was simulated by experimental implantation of 500keV H+ ions. The maximum radiation damage of 1 DPA was obtained across a region of 3 µm. Radiation-induced defects were investigated by coincidence Doppler broadening spectroscopy and positron lifetime spectroscopy using a conventional positron source as well as a slow positron beam. All techniques registered an accumulation of small open-volume defects (mostly mono- and di-vacancies) due to the irradiation, with an increase of the defect volume ΔVD ≈ 2.88 × 10−8 cm−3. Finally, the irradiated specimens were gradually annealed at temperatures from 200 to 550 °C and analyzed in detail. The best defect recovery was found at a temperature between 450 and 475 °C, but the final defect concentration of about ΔCD = 0.34 ppm was still higher than in the as-received specimens.

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