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首页> 外文会议>International topical meeting on nuclear thermal hydraulics, operations and safety;NUTHOS-5 >First application of a complete best estimate loca methodology to the indian point unit 2 nuclear power plant
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First application of a complete best estimate loca methodology to the indian point unit 2 nuclear power plant

机译：完整的最佳估计局部定位方法首次应用于印度第2点机组核电站

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This paper present results of the first application of an approved best estimate methodology to the analysis of Large Break Loss of Coolant Accidents in order to quantify realistic LOCA safety margins for the Indian Point 2 Nuclear Plant. The methodology meets the requirements of the revised 10CFR50.46, issued by the NRC in 1988 and Regulatory Guide 1.157. The generic methodology was approved by the Advisory Committee on Reactor Safeguards (ACRS) and the United States Nuclear regulatory Commission (USNRC). The complete "Best Estimate" LOCA analysis methodology was developed under a joint Con Edison/EPRI/Westinghouse project and applied to Indian Point 2 to provide the basis for improvements in safety, reduction in fuel costs, an increase in availability and additional operating margins. A project has also been initiated to develop the methodology for a Small Break Best Estimate LOCA analysis and apply it to Indian Point 2.
机译：本文介绍了首次应用经过认可的最佳估计方法来分析冷却剂事故的重大突破损失，以便为印度第2点核电站定量逼真的LOCA安全裕度。该方法符合NRC于1988年发布的经修订的10CFR50.46和《法规指南1.157》的要求。通用方法学已得到反应堆保障咨询委员会（ACRS）和美国核监管委员会（USNRC）的批准。完整的“最佳估算” LOCA分析方法是在Con Edison / EPRI / Westinghouse联合项目下开发的，并应用于Indian Point 2，为改善安全性，降低燃料成本，增加可用性和增加运营利润提供了基础。还启动了一个项目，以开发用于“小间隔最佳估计值” LOCA分析的方法，并将其应用于印度点2。

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