• Title/Summary/Keyword: Energy safety

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Analysis of Hydrogen Accident in Korea (국내 수소사고사례 분석)

  • Jo, Young-Do;Tak, Song-Su;Choi, Kyoung-Suhk;Lee, Jong Rark;Park, Kyo-Shik
    • Transactions of the Korean hydrogen and new energy society
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    • v.15 no.1
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    • pp.82-87
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    • 2004

  • Hydrogen is considered to be the most important future energy carrier in many applications reducing greenhouse gas emissions significantly. To be applicable as energy carrier the safety issues associated with hydrogen applications needs to be investigated and fully understood. In order to analyze the risks associated with hydrogen applications, accidents associated with hydrogen in Korea from 1963 to 2002 have been analysed in this work. From analysis of accidents, we propose the necessity of research on hydrogen releases, dispersion in air, and explosion due to high hazardous of hydrogen.

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Moderating effect of regulatory focus on public acceptance of nuclear energy

  • He, Yanling;Li, Yazhou;Xia, Dongqin;Zhang, Tingting;Wang, Yongliang;Hu, Li;Gu, Jibao;Wu, Yican
    • Nuclear Engineering and Technology
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    • v.51 no.8
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    • pp.2034-2041
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    • 2019

  • Public acceptance has become the most critical question for sustainable development of nuclear energy in recent decades. Many researches concentrated on risk and benefit perception, which were deemed as the most influential factors of Public Acceptance of Nuclear Energy (PANE). But few researches focused on psychological factors including regulatory focus. Therefore, this paper aimed to explore the moderating effect of regulatory focus on PANE based on Regulatory Focus Theory in order to find ways to increase/decrease PANE. An Internet-based survey had been carried out in China nationwide. The results indicated that trust in government was positively related to PANE and this relationship was mediated by risk and benefit perception. In addition, the strength of the associations between risk and benefit perception and PANE were moderated by regulatory focus, consisting of prevention focus and promotion focus. Prevention focus strengthened the negative relationship between risk perception and PANE, while promotion focus weakened. Moreover, promotion focus weakened the positive relationship between benefit perception and PANE, but no significant moderating effect of prevention focus was founded on the relationship between benefit perception and PANE. Some policy implications were also proposed on the basis of above-mentioned findings.

  • https://doi.org/10.1016/j.net.2019.06.002 인용 PDF KSCI

Flow-accelerated corrosion assessment for SA106 and SA335 pipes with elbows and welds

  • Kim, Dong-Jin;Kim, Sung-Woo;Lee, Jong Yeon;Kim, Kyung Mo;Oh, Se Beom;Lee, Gyeong Geun;Kim, Jongbeom;Hwang, Seong-Sik;Choi, Min Jae;Lim, Yun Soo;Cho, Sung Hwan;Kim, Hong Pyo
    • Nuclear Engineering and Technology
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    • v.53 no.9
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    • pp.3003-3011
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    • 2021

  • A FAC (flow-accelerated corrosion) test was performed for a straight pipe composed of the SA335 Gr P22 and SA106 Gr B (SA106-SA335-SA106) types of steel with welds as a function of the flow rate in the range of 7-12 m/s at 150 ℃ and with DO < 5 ppb at pH levels ranging from 7 to 9.5 up to a cumulative test time of 7200 h using the FAC demonstration test facility. Afterward, the experimental pipe was examined destructively to investigate opposite effects as well as entrance effects. In addition, the FAC rate obtained using a pipe specimen with a 50 mm inner diameter was compared with the rate obtained from a rotating cylindrical electrode. The effects of the complicated fluid flows at the elbow and orifice of the pipeline were also evaluated using another test section designed to examine the independent effects of the orifice and the elbow depending on the distance and the combined effects on orifice and elbow. The tests were performed under the following conditions: 130-150 ℃, DO < 5 ppb, pH 7 and a flow rate of 3 m/s. The FAC rate was determined using the thickness change obtained from commercial room-temperature ultrasonic testing (UT).

  • https://doi.org/10.1016/j.net.2021.03.026 인용 PDF KSCI

Overall System Description and Safety Characteristics of Prototype Gen IV Sodium Cooled Fast Reactor in Korea

  • Yoo, Jaewoon;Chang, Jinwook;Lim, Jae-Yong;Cheon, Jin-Sik;Lee, Tae-Ho;Kim, Sung Kyun;Lee, Kwi Lim;Joo, Hyung-Kook
    • Nuclear Engineering and Technology
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    • v.48 no.5
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    • pp.1059-1070
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    • 2016

  • The Prototype Gen IV sodium cooled fast reactor (PGSFR) has been developed for the last 4 years, fulfilling the technology demonstration of the burning capability of transuranic elements included in light water reactor spent nuclear fuel. The PGSFR design has been focused on the robustness of safety systems by enhancing inherent safety characteristics of metal fuel and strengthening passive safety features using natural circulation and thermal expansion. The preliminary safety information document as a major outcome of the first design phase of PGSFR development was issued at the end of 2015. The project entered the second design phase at the beginning of 2016. This paper summarizes the overall structures, systems, and components of nuclear steam supply system and safety characteristics of the PGSFR. The research and development activities to demonstrate the safety performance are also briefly introduced in the paper.

  • https://doi.org/10.1016/j.net.2016.08.004 인용 PDF KSCI