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    Application of Level 3 Probabilistic Safety Analysis in UK HPR1000

    Source: Journal of Nuclear Engineering and Radiation Science:;2024:;volume( 010 ):;issue: 002::page 21702-1
    Author:
    Wang, Jinkai
    ,
    Wang, Qi
    DOI: 10.1115/1.4063874
    Publisher: The American Society of Mechanical Engineers (ASME)
    Abstract: A Level 3 probabilistic safety assessment (L3 PSA) is required in United Kingdom (UK) generic design assessment (GDA) to demonstrate that a new nuclear power plant is suitable to be built in UK. L3 PSA is used to assess the individual and societal risk and compare the results against the offsite radiation protection targets (RPTs) for fault and accident conditions. Its results can be used for risk evaluation and environmental impact assessment and provide useful information for alternative design features, rulemaking, and regulatory procedures. It takes into account atmospheric dispersion, demography, dosimetry, pathways to man, and plant/site characteristics. The radioactive source terms and their frequencies often are passed on from Level 1/2 PSA analyses. The framework for demonstrating the acceptability of the new plant design at GDA is presented for the assessments against RPTs 7, 8, and 9. There is little relevant good practice and mature standard for L3 PSAs that have recently been implemented worldwide. In this study, a pilot L3 PSA is performed for UK Hua-long Pressurized Water Reactor (UK HPR1000) to reflect the UK context and relevant good practices. It introduces the methodology and the processes to be followed to perform conditional consequence calculations for the faults and accident scenarios. All radiation sources are considered and analyzed. The radiological risks to a potential UK site are analyzed and compared against RPTs. A widely used code - PC COSYMA, is selected as a primary tool for the accident consequence calculations. The strengths and limitations of the code are identified based on the project situation, and either qualitative arguments or supplementary analyses are subsequently proposed to overcome the limitations. The final L3 PSA results are derived to support the demonstration that the offsite radiological risks for UK HPR1000 have been achieved as low as reasonably practicable (ALARP) and have met the UK regulatory expectation.
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      Application of Level 3 Probabilistic Safety Analysis in UK HPR1000

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    http://yetl.yabesh.ir/yetl1/handle/yetl/4295746
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    contributor authorWang, Jinkai
    contributor authorWang, Qi
    date accessioned2024-04-24T22:43:11Z
    date available2024-04-24T22:43:11Z
    date copyright1/29/2024 12:00:00 AM
    date issued2024
    identifier issn2332-8983
    identifier otherners_010_02_021702.pdf
    identifier urihttp://yetl.yabesh.ir/yetl1/handle/yetl/4295746
    description abstractA Level 3 probabilistic safety assessment (L3 PSA) is required in United Kingdom (UK) generic design assessment (GDA) to demonstrate that a new nuclear power plant is suitable to be built in UK. L3 PSA is used to assess the individual and societal risk and compare the results against the offsite radiation protection targets (RPTs) for fault and accident conditions. Its results can be used for risk evaluation and environmental impact assessment and provide useful information for alternative design features, rulemaking, and regulatory procedures. It takes into account atmospheric dispersion, demography, dosimetry, pathways to man, and plant/site characteristics. The radioactive source terms and their frequencies often are passed on from Level 1/2 PSA analyses. The framework for demonstrating the acceptability of the new plant design at GDA is presented for the assessments against RPTs 7, 8, and 9. There is little relevant good practice and mature standard for L3 PSAs that have recently been implemented worldwide. In this study, a pilot L3 PSA is performed for UK Hua-long Pressurized Water Reactor (UK HPR1000) to reflect the UK context and relevant good practices. It introduces the methodology and the processes to be followed to perform conditional consequence calculations for the faults and accident scenarios. All radiation sources are considered and analyzed. The radiological risks to a potential UK site are analyzed and compared against RPTs. A widely used code - PC COSYMA, is selected as a primary tool for the accident consequence calculations. The strengths and limitations of the code are identified based on the project situation, and either qualitative arguments or supplementary analyses are subsequently proposed to overcome the limitations. The final L3 PSA results are derived to support the demonstration that the offsite radiological risks for UK HPR1000 have been achieved as low as reasonably practicable (ALARP) and have met the UK regulatory expectation.
    publisherThe American Society of Mechanical Engineers (ASME)
    titleApplication of Level 3 Probabilistic Safety Analysis in UK HPR1000
    typeJournal Paper
    journal volume10
    journal issue2
    journal titleJournal of Nuclear Engineering and Radiation Science
    identifier doi10.1115/1.4063874
    journal fristpage21702-1
    journal lastpage21702-9
    page9
    treeJournal of Nuclear Engineering and Radiation Science:;2024:;volume( 010 ):;issue: 002
    contenttypeFulltext
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