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- W117197130 abstract "The accurate estimation of fast (E {>=} 1 MeV) neutron vessel fluence is very important because it is a crucial factor for the reference nil-ductility temperature (NDT) shift ({Delta}RT{sub NDT}). Recently, there has been a growing interest in best-estimate vessel fluence in Korea as elsewhere due to the proposed life-extension programs of the nuclear power plants. In this paper we report the results of best-estimate evaluation of the vessel fluence at Ulchin nuclear unit 1 (Ulchin-1) in Korea. Ulchin-1 is a pressurized water reactor of the Framatome type rated at 2775 MW(thermal) and in operation since 1988. We used the LEPRICON code system. First, to validate LEPRICON, we have revisited a previous analysis of the VENUS-1 experiments using the ELXSIR library based on ENDF/B-V Mod 3, which has updated iron cross sections. Then, three surveillance tests performed at the plant were used in the LEPRICON analysis." @default.
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- W117197130 date "2000-06-04" @default.
- W117197130 modified "2023-09-24" @default.
- W117197130 title "Using the LEPRICON System To Evaluate Best-Estimate Vessel Fluence at Ulchin NPP Unit 1" @default.
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