{"status":"ok","message-type":"work","message-version":"1.0.0","message":{"indexed":{"date-parts":[[2025,11,7]],"date-time":"2025-11-07T09:37:35Z","timestamp":1762508255603,"version":"3.37.3"},"reference-count":61,"publisher":"Institute of Electrical and Electronics Engineers (IEEE)","license":[{"start":{"date-parts":[[2020,1,1]],"date-time":"2020-01-01T00:00:00Z","timestamp":1577836800000},"content-version":"vor","delay-in-days":0,"URL":"https:\/\/creativecommons.org\/licenses\/by\/4.0\/legalcode"}],"funder":[{"DOI":"10.13039\/501100003725","name":"Nuclear Research & Development Program of the National Research Foundation of Korea grant","doi-asserted-by":"publisher","id":[{"id":"10.13039\/501100003725","id-type":"DOI","asserted-by":"publisher"}]},{"DOI":"10.13039\/501100003621","name":"Korean government, Ministry of Science, ICT & Future Planning","doi-asserted-by":"publisher","award":["2017M2A8A4015291"],"award-info":[{"award-number":["2017M2A8A4015291"]}],"id":[{"id":"10.13039\/501100003621","id-type":"DOI","asserted-by":"publisher"}]}],"content-domain":{"domain":[],"crossmark-restriction":false},"short-container-title":["IEEE Access"],"published-print":{"date-parts":[[2020]]},"DOI":"10.1109\/access.2020.3021741","type":"journal-article","created":{"date-parts":[[2020,9,4]],"date-time":"2020-09-04T21:01:40Z","timestamp":1599253300000},"page":"166034-166046","source":"Crossref","is-referenced-by-count":21,"title":["Operational Vulnerability Identification Procedure for Nuclear Facilities Using STAMP\/STPA"],"prefix":"10.1109","volume":"8","author":[{"ORCID":"https:\/\/orcid.org\/0000-0002-9307-6156","authenticated-orcid":false,"given":"Sang Hun","family":"Lee","sequence":"first","affiliation":[]},{"given":"Sung-Min","family":"Shin","sequence":"additional","affiliation":[]},{"given":"Jeong Sik","family":"Hwang","sequence":"additional","affiliation":[]},{"ORCID":"https:\/\/orcid.org\/0000-0002-0250-1832","authenticated-orcid":false,"given":"Jinkyun","family":"Park","sequence":"additional","affiliation":[]}],"member":"263","reference":[{"key":"ref39","doi-asserted-by":"publisher","DOI":"10.1016\/j.ssci.2013.03.013"},{"key":"ref38","doi-asserted-by":"publisher","DOI":"10.1145\/2502524.2502545"},{"key":"ref33","doi-asserted-by":"publisher","DOI":"10.2514\/1.A32449"},{"key":"ref32","doi-asserted-by":"publisher","DOI":"10.1007\/s11219-017-9396-0"},{"key":"ref31","doi-asserted-by":"publisher","DOI":"10.1016\/j.ssci.2016.03.001"},{"key":"ref30","doi-asserted-by":"publisher","DOI":"10.1007\/978-1-84882-791-2"},{"article-title":"Hazard analysis methods for digital instrumentation and control systems","year":"2013","author":"gibson","key":"ref37"},{"key":"ref36","doi-asserted-by":"publisher","DOI":"10.1016\/j.jlp.2017.01.021"},{"article-title":"Applying system-theoretic accident model and processes (STAMP) to hazard analysis","year":"2012","author":"song","key":"ref35"},{"article-title":"A formal methods based quality evaluation techniques for safety-level I&C software","year":"2015","author":"yoo","key":"ref34"},{"key":"ref60","first-page":"929","article-title":"Introduction of human factors engineering program plan of a research reactor","author":"jang","year":"2011","journal-title":"Proceedings of the Korean Nuclear Society Autumn Meeting"},{"article-title":"Safety culture indicators in HANARO","year":"2007","author":"wo","key":"ref61"},{"journal-title":"International Atomic Energy Agency","article-title":"Operational limits and conditions and operating procedures for nuclear power plants","year":"2000","key":"ref28"},{"key":"ref27","first-page":"42622","article-title":"Use of probabilistic risk assessment methods in nuclear regulatory activities; final policy statement","volume":"60","year":"1995","journal-title":"Federal Register"},{"article-title":"HANARO technical administrative procedures manual: Manual preparation, revision and management","year":"2008","author":"woo","key":"ref29"},{"key":"ref2","doi-asserted-by":"publisher","DOI":"10.1016\/j.ress.2006.02.004"},{"journal-title":"International Nuclear Safety Advisory Group (INSAG)","article-title":"Management of operational safety in nuclear power plants","year":"1999","key":"ref1"},{"key":"ref20","doi-asserted-by":"publisher","DOI":"10.1016\/j.ress.2018.05.019"},{"key":"ref22","doi-asserted-by":"publisher","DOI":"10.1016\/j.ress.2017.08.003"},{"key":"ref21","doi-asserted-by":"publisher","DOI":"10.1016\/j.ress.2017.07.015"},{"key":"ref24","doi-asserted-by":"publisher","DOI":"10.1016\/j.proeng.2015.11.498"},{"key":"ref23","doi-asserted-by":"publisher","DOI":"10.1016\/j.ress.2019.03.038"},{"journal-title":"International Atomic Energy Agency","article-title":"Operational safety performance indicators for nuclear power plants","year":"2000","key":"ref26"},{"journal-title":"STPA Handbook","year":"2018","author":"leveson","key":"ref25"},{"article-title":"HANARO safety analysis report","year":"1996","author":"lee","key":"ref50"},{"article-title":"Basic design requirements for systems and facilities of HANARO cold neutron source","year":"2005","author":"jung","key":"ref51"},{"article-title":"Internal event level 1 PSA for HANARO research reactor in Korea","year":"2019","author":"lee","key":"ref59"},{"key":"ref58","doi-asserted-by":"publisher","DOI":"10.1201\/b22260"},{"article-title":"Operational process modelling and analysis for HANARO research reactor based on STAMP\/STPA","year":"2020","author":"lee","key":"ref57"},{"article-title":"HANARO operational procedure—Reactor startup and shutdown","year":"2019","author":"in","key":"ref56"},{"article-title":"HANARO operational procedure—CNS vacuum system","year":"2013","author":"kim","key":"ref55"},{"article-title":"HANARO operational procedure—CNS compression air system","year":"2013","author":"kim","key":"ref54"},{"article-title":"HANARO operational procedure—CNS cooling water system","year":"2013","author":"hwang","key":"ref53"},{"article-title":"HANARO operational procedure—CNS helium refrigeration system","year":"2013","author":"kim","key":"ref52"},{"journal-title":"Engineering A Safer World Systems Thinking Applied to Safety","year":"2011","author":"leveson","key":"ref10"},{"key":"ref11","doi-asserted-by":"publisher","DOI":"10.1016\/j.ssci.2010.02.004"},{"key":"ref40","doi-asserted-by":"publisher","DOI":"10.1007\/978-4-431-54898-0"},{"key":"ref12","doi-asserted-by":"publisher","DOI":"10.1016\/j.aap.2013.02.041"},{"journal-title":"FRAM the functional resonance analysis method modelling complex socio-technical systems","year":"2012","author":"hollnagel","key":"ref13"},{"key":"ref14","doi-asserted-by":"publisher","DOI":"10.1080\/00140139.2016.1232841"},{"key":"ref15","doi-asserted-by":"publisher","DOI":"10.1016\/S0925-7535(03)00047-X"},{"journal-title":"Human Factors Methods A Practical Guide for Engineering And Design","year":"2013","author":"stanton","key":"ref16"},{"key":"ref17","doi-asserted-by":"publisher","DOI":"10.1016\/j.ssci.2014.07.009"},{"key":"ref18","doi-asserted-by":"publisher","DOI":"10.1016\/j.ssci.2014.12.005"},{"key":"ref19","doi-asserted-by":"publisher","DOI":"10.1016\/j.ssci.2017.06.011"},{"article-title":"Modeling a digital feedwater control system using traditional probabilistic risk assessment methods","year":"2009","author":"chu","key":"ref4"},{"journal-title":"Digital Instrumentation and Control Systems in Nuclear Power Plants Safety and Reliability Issues","year":"1997","key":"ref3"},{"article-title":"Current state of reliability modeling methodologies for digital systems and their acceptance criteria for nuclear power plant assessments","year":"2006","author":"aldemir","key":"ref6"},{"journal-title":"Working Group on Risk Assessment","article-title":"Recommendations on assessing digital system reliability in probabilistic risk assessments of nuclear power plants","year":"2009","key":"ref5"},{"key":"ref8","doi-asserted-by":"publisher","DOI":"10.1016\/S0925-7535(97)00052-0"},{"article-title":"Dynamic reliability modeling of digital instrumentation and control systems for nuclear reactor probabilistic risk assessments","year":"2007","author":"aldemir","key":"ref7"},{"article-title":"Detail design of the hydrogen system and the gas blanketing system for the HANARO-CNS","year":"2007","author":"choi","key":"ref49"},{"journal-title":"Barriers and Accident Prevention","year":"2004","author":"hollnagel","key":"ref9"},{"article-title":"Development of cold neutron source facility","year":"2010","author":"woo","key":"ref46"},{"article-title":"Replacement of the HANARO control computer","year":"2015","author":"lee","key":"ref45"},{"article-title":"STPA software module: A eurostars funded project","year":"0","author":"brown","key":"ref48"},{"article-title":"Basic design of the cold neutron research facility in HANARO","year":"2005","author":"kim","key":"ref47"},{"key":"ref42","doi-asserted-by":"publisher","DOI":"10.1097\/PTS.0000000000000263"},{"article-title":"Extending and automating a systems-theoretic hazard analysis for requirements generation and analysis","year":"2013","author":"thomas","key":"ref41"},{"article-title":"Initiating event analysis for HANARO research reactor level 1 PSA","year":"2019","author":"lee","key":"ref44"},{"key":"ref43","doi-asserted-by":"publisher","DOI":"10.1016\/j.nucengdes.2007.10.022"}],"container-title":["IEEE Access"],"original-title":[],"link":[{"URL":"http:\/\/xplorestaging.ieee.org\/ielx7\/6287639\/8948470\/09186688.pdf?arnumber=9186688","content-type":"unspecified","content-version":"vor","intended-application":"similarity-checking"}],"deposited":{"date-parts":[[2021,12,17]],"date-time":"2021-12-17T19:55:42Z","timestamp":1639770942000},"score":1,"resource":{"primary":{"URL":"https:\/\/ieeexplore.ieee.org\/document\/9186688\/"}},"subtitle":[],"short-title":[],"issued":{"date-parts":[[2020]]},"references-count":61,"URL":"https:\/\/doi.org\/10.1109\/access.2020.3021741","relation":{},"ISSN":["2169-3536"],"issn-type":[{"type":"electronic","value":"2169-3536"}],"subject":[],"published":{"date-parts":[[2020]]}}}