Zobrazeno 1 - 10
of 27
pro vyhledávání: '"Byeong Seo Kong"'
Autor:
Chaewon Jeong, Ji Ho Shin, Byeong Seo Kong, Junjie Chen, Qian Xiao, Changheui Jang, Yun-Jae Kim
Publikováno v:
Nuclear Engineering and Technology, Vol 56, Iss 6, Pp 2131-2140 (2024)
The chloride-induced stress corrosion cracking (CISCC) is one of the major integrity concerns in dry storage canisters made of austenitic stainless steels (ASSs). In this study, an advanced duplex stainless steel (DSS) with a composition of Fe–19Cr
Externí odkaz:
https://doaj.org/article/4cc17309f06847ddb9a5592d065f9718
Publikováno v:
Nuclear Engineering and Technology, Vol 55, Iss 8, Pp 2823-2834 (2023)
Austenitic stainless steel welds (ASSWs) of nuclear components undergo aging-related degradations caused by high temperature and neutron radiation. Since irradiation leads to the change of material characteristics, relevant quantification is importan
Externí odkaz:
https://doaj.org/article/a42c1206ab904cd9926071b259fafcdf
Publikováno v:
Journal of Materials Research and Technology, Vol 23, Iss , Pp 4990-5003 (2023)
The deformation behavior of δ-ferrite in an aged austenitic stainless-steel weld was investigated to obtain insights on the contribution of aging-induced nanofeatures, such as spinodal decomposition and G-phase precipitation, to aging embrittlement.
Externí odkaz:
https://doaj.org/article/7c9321870bb449bc9d1dc231599e6ad3
Publikováno v:
Nuclear Engineering and Technology, Vol 55, Iss 2, Pp 555-565 (2023)
Despite many advantages as structural materials, austenitic stainless steels (SSs) have been avoided in many next generation nuclear systems due to poor void swelling resistance. In this paper, we report the results of heavy ion irradiation to the re
Externí odkaz:
https://doaj.org/article/dd6762da0bfb4c7caa1c82c13efd07ee
Publikováno v:
Materials, Vol 15, Iss 17, p 5836 (2022)
The tensile deformation behavior of double-forged (DF-W) and recrystallized (RX-W) commercial-grade tungsten was investigated at 700 °C. With increasing strain rate, the dominant dynamic recrystallization (DRX) mechanism changes from continuous dyna
Externí odkaz:
https://doaj.org/article/ee4027c8b0e943fa86ab8ed0560d7a06
Publikováno v:
Materials, Vol 13, Iss 1, p 244 (2020)
The evaluation of fracture toughness of pure tungsten is essential for the structural integrity analysis in a fusion reactor. Therefore, the accurate quantification of fracture toughness of tungsten alloys is needed. However, due to the inherent brit
Externí odkaz:
https://doaj.org/article/ff73075638e54f0a8b63ca014d238d43
Publikováno v:
Volume 4B: Materials and Fabrication.
Reactor vessel internals (RVIs) consist of austenitic stainless steels (ASSs) which have excellent material properties. Meanwhile, the high radiation environment of a reactor can cause the degradation of components. Since changed material properties
Autor:
Ho Jung Lee, Jiho Shin, Dongchan Jang, Ye-eun Na, Changheui Jang, Gokul Obulan Subramanian, Jun-Seog Yang, Junjie Chen, Byeong Seo Kong
Publikováno v:
Scripta Materialia. 186:236-241
Nanopillar compression tests were applied on δ-ferrites in austenitic stainless steel welds to measure the thermal ageing activation energy caused by spinodal decomposition. Welds of an austenitic stainless steel were thermally aged at 343, 375, and
Autor:
Kyung Mo Kim, Jongbeom Kim, Kyung-Young Jhang, Sung Sik Kang, Byeong Seo Kong, Changheui Jang, Jin Gyum Kim
Publikováno v:
Nuclear Engineering and Technology, Vol 52, Iss 3, Pp 621-625 (2020)
Cast austenitic stainless steel (CASS) is used for fabricating different components of the primary reactor coolant system of pressurized water reactors. However, the thermal embrittlement of CASS resulting from long-term operation causes structural s
Publikováno v:
International Journal of Pressure Vessels and Piping. 198:104679