F310 DAMAGE PROBABILITY OF THE STEAM GENERATOR HEAT EXCHANGE PIPELINES IN VVER NPP
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概要
- 論文の詳細を見る
Low operational reliability of steam generators (SG) of NPPs with VVER type reactors is one of main factors affecting stability and quality of the output electric energy. Unscheduled unit stoppage when detecting heat exchange tubes (HET) and other steam generator components defects, caused by their repairing or replacement of whole SG, Result in underproduction of electric energy and decreasing NPP capacity factor (CF). For these reasons the steam generator lifetime does not conform to the lifetime of NPP primary equipment. Therefore the enhancement of SG operational reliability attracts attention of experts from the countries operating PWR and VVER NPPs.
- 一般社団法人日本機械学会の論文
著者
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Belyakov O.
Electrogorsk Research And Engineering Center On Nuclear Plants Safety Of All-russian Research Instit
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Baranenko V.
Electrogorsk Research and Engineering Center on Nuclear Plants Safety of All-Russian Research Instit
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Oleynik S.
Electrogorsk Research and Engineering Center on Nuclear Plants Safety of All-Russian Research Instit
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Merkushev V.
Electrogorsk Research and Engineering Center on Nuclear Plants Safety of All-Russian Research Instit
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Kostyukov O.
Electrogorsk Research and Engineering Center on Nuclear Plants Safety of All-Russian Research Instit
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Kumov A.
Russian Research Institute of Atomic Machine-Building (VNIIAM)
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Baranenko V.
Electrogorsk Research And Engineering Center On Nuclear Plants Safety Of All-russian Research Instit
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Oleynik S.
Electrogorsk Research And Engineering Center On Nuclear Plants Safety Of All-russian Research Instit
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Kostyukov O.
Electrogorsk Research And Engineering Center On Nuclear Plants Safety Of All-russian Research Instit
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Merkushev V.
Electrogorsk Research And Engineering Center On Nuclear Plants Safety Of All-russian Research Instit