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      KCI등재 SCIE SCOPUS

      Performance evaluation of Accident Tolerant Fuel under station blackout accident in PWR nuclear power plant by improved ISAA code

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      https://www.riss.kr/link?id=A108186298

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      다국어 초록 (Multilingual Abstract)

      The Accident Tolerant Fuel (ATF) is a new concept of fuel, which can not only withstand the consequences of the accident for a longer time, but also maintain or improve the performance under operating conditions. ISAA is a self-developed severe accide...

      The Accident Tolerant Fuel (ATF) is a new concept of fuel, which can not only withstand the consequences of the accident for a longer time, but also maintain or improve the performance under operating conditions. ISAA is a self-developed severe accident analysis code, which uses modular structures to simulate the development processes of severe accidents in nuclear plants. The basic version of ISAA is developed based on UO2eZr fuel. To study the potential safety gain of ATF cladding, an improved version of ISAA, referred to as ISAA-ATF, is introduced to analyze the station blackout accident of PWR using ATF cladding. The results show that ATF cladding enable the core to maintain a longer time compared to zirconium alloy cladding, thereby enhancing the accident mitigation capability. Meanwhile, the generation of hydrogen is significantly reduced and delayed, which proves that ATF can improve the safety characteristics of the nuclear reactor.

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      참고문헌 (Reference)

      1 Guoxin Du, "Station Black-Out Severe Accident Analysis of a Typical 1000MWe PWR" Xi'an Jiaotong University 2013

      2 Brad J. Merrill, "SiC modifications to melcor for severe accident analysis applications" 2013

      3 Jinyu Gao, "Research on advanced investment in nuclear fuel in the UK" 10 : 2015

      4 Xiaoli Wu, "Preliminary safety analysis of the PWR with accident-tolerant fuels during severe accident conditions" 80 : 1-13, 2015

      5 L. J. Ott, "Preliminary assessment of accident-tolerant fuels on LWR performance during normal operation and under DB and BDB accident conditions" 448 : 520-533, 2014

      6 B. S. Li, "Pellet Cladding Mechanical Interactions of Ceramic Claddings Fuels under Light Water Reactor Conditions" 2013

      7 Bo J€onsson, "Oxidation and creep limited lifetime of Kanthal APMT®, a dispersion strengthened FeCrAlMo alloy designed for strength and oxidation resistance at high temperatures" 79 : 29-39, 2013

      8 X. Wu, "Neutronics and fuel performance evaluation of accident tolerant FeCrAl cladding under normal operation conditions" 85 : 763-775, 2015

      9 K. A. Terrani, "Microencapsulated fuel technology for commercial light water and advanced reactor application" 427 : 209-224, 2012

      10 K. G. Field, "Mechanical properties of neutronirradiated model and commercial FeCrAl alloys" 489 : 118-128, 2017

      1 Guoxin Du, "Station Black-Out Severe Accident Analysis of a Typical 1000MWe PWR" Xi'an Jiaotong University 2013

      2 Brad J. Merrill, "SiC modifications to melcor for severe accident analysis applications" 2013

      3 Jinyu Gao, "Research on advanced investment in nuclear fuel in the UK" 10 : 2015

      4 Xiaoli Wu, "Preliminary safety analysis of the PWR with accident-tolerant fuels during severe accident conditions" 80 : 1-13, 2015

      5 L. J. Ott, "Preliminary assessment of accident-tolerant fuels on LWR performance during normal operation and under DB and BDB accident conditions" 448 : 520-533, 2014

      6 B. S. Li, "Pellet Cladding Mechanical Interactions of Ceramic Claddings Fuels under Light Water Reactor Conditions" 2013

      7 Bo J€onsson, "Oxidation and creep limited lifetime of Kanthal APMT®, a dispersion strengthened FeCrAlMo alloy designed for strength and oxidation resistance at high temperatures" 79 : 29-39, 2013

      8 X. Wu, "Neutronics and fuel performance evaluation of accident tolerant FeCrAl cladding under normal operation conditions" 85 : 763-775, 2015

      9 K. A. Terrani, "Microencapsulated fuel technology for commercial light water and advanced reactor application" 427 : 209-224, 2012

      10 K. G. Field, "Mechanical properties of neutronirradiated model and commercial FeCrAl alloys" 489 : 118-128, 2017

      11 L. L. Snead, "Handbook of SiC properties for fuel performance modeling" 371 (371): 329-377, 2007

      12 D. Kim, "Fabrication and measurement of hoop strength of SiC triplex tube for nuclear fuel cladding applications" 458 : 29-36, 2015

      13 D. Chandramouli, "Development of thermal models and analysis of UO2-BeO fuel during a loss of coolant accident" 2014

      14 Pengcheng Gao, "Development of mechanistic cladding rupture model for integrated severe accident code ISAA. Part I: module verification and application in CAP1400" 3 : 25-, 2021

      15 Wenchuan Xie, "China General Nuclear Power Group Takes the Lead the Accident Tolerant Fuel Major Technology"

      16 L. J. Ott, "Accident tolerant fuel/cladding: preliminary reactor DBDaccident simulations" 2013

      17 Bin Zhang, "A newly-developed suppression pool model based on ISAA code" 2020

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      유사연구자 (20) 활용도상위20명

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      학술지 이력

      학술지 이력
      연월일 이력구분 이력상세 등재구분
      2023 평가예정 해외DB학술지평가 신청대상 (해외등재 학술지 평가)
      2020-01-01 평가 등재학술지 유지 (해외등재 학술지 평가) KCI등재
      2014-01-01 평가 SCIE 등재 (등재유지) KCI등재
      2014-01-01 평가 SCOPUS 등재 (등재유지) KCI등재
      2011-01-01 평가 등재학술지 유지 (등재유지) KCI등재
      2009-01-01 평가 등재학술지 유지 (등재유지) KCI등재
      2007-01-01 평가 등재학술지 유지 (등재유지) KCI등재
      2006-07-31 학술지명변경 한글명 : Jorunal of the Korean Nuclear Society -> Nuclear Engineering and Technology
      외국어명 : 미등록 -> Nuclear Engineering and Technology
      KCI등재후보
      2004-01-01 평가 등재후보학술지 선정 (신규평가) KCI등재후보
      2003-01-01 평가 등재후보 1차 PASS (등재후보1차) KCI등재후보
      2002-01-01 평가 등재후보학술지 유지 (등재후보1차) KCI등재후보
      1999-01-01 평가 등재후보학술지 선정 (신규평가) KCI등재후보
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      학술지 인용정보

      학술지 인용정보
      기준연도 WOS-KCI 통합IF(2년) KCIF(2년) KCIF(3년)
      2016 1.04 0.17 0.77
      KCIF(4년) KCIF(5년) 중심성지수(3년) 즉시성지수
      0.63 0.56 0.343 0.11
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