Evaluation of radiation shielding potentials of Ni-based alloys, Inconel-617 and Incoloy-800HT, candidates for high temperature applications especially for nuclear reactors, by EpiXS and Phy-X/PSD codes
Öz
Anahtar Kelimeler
Kaynakça
- [1] Archana M., Rao C.J., Ningshen S., Philip J., “High-Temperature Air and Steam Oxidation and Oxide Layer Characteristics of Alloy 617”, J Mater Engineer Performance, 30: 931–943, (2021).
- [2] Rahman M.S., Ding J., Beheshti A., Zhang X., Polycarpou A.A., “Elevated temperature tribology of Ni alloys under helium environment for nuclear reactor applications”, Tribology Inter, 123: 372–384, (2018).
- [3] Us H., “Oxıdatıon behavıor of very hıgh temperature reactor (vhtr) candıdate materıals: 316l staınless steel, Alloy 617, and incoloy 800-h”, A Dissertation presented to the Faculty of the Graduate School at the University of Missouri, (2016).
- [4] Kumar S.A., Sathıya P., “Effects of heat ınput on the mechanıcal and metallurgıcal characterıstıcs of tıg welded ıncoloy 800HT joınts”, Arch Metall Mater, 62(3): 1673-1679, (2017).
- [5] http://www.specialmetals.com. (accessed 15 July 2021)
- [6] Alım B., “A comprehensive study on radiation shielding characteristics of Tin Silver, Manganin R, Hastelloy B, Hastelloy X and Dilver P alloys”, Appl Phys A, 126: 262, (2020).
- [7] Singh V.P., Badiger N.M., “Gamma ray and neutron shielding properties of some alloy materials”, Annl Nucl Energy, 64: 301-310, (2014).
- [8] Wang K., Hu J., Tianyou C., Tang J., Zhai Y., Feng Y., Zhao Z., Fan H., Wang K., “Radiation shielding properties of flexible liquid metal-GaIn alloy”, Progress in Nucl Energy, 135:103696 (2021).
Ayrıntılar
Birincil Dil
İngilizce
Konular
Mühendislik
Bölüm
Araştırma Makalesi
Yayımlanma Tarihi
5 Temmuz 2023
Gönderilme Tarihi
4 Ekim 2021
Kabul Tarihi
7 Şubat 2022
Yayımlandığı Sayı
Yıl 2023 Cilt: 26 Sayı: 2
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