Large break loca analysis for qinshan-2 nuclear power plant

机译：秦山二号核电站大破口分析

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Nuclear safety analyis becomes more important with the development of nuclear science and technology. Many nuclear safety analysis computer codes have been developed to assure the safety of nuclear power plants. Both of the reviewing codes and the best estimate codes have been well developed especially in the advanced countries, for example FLASH, RELAP4/MOD7, TRACPF1 and RELAP5/MOD3, etc.

机译：随着核科学技术的发展，核安全分析变得越来越重要。已经开发了许多核安全分析计算机代码以确保核电厂的安全。评审代码和最佳估计代码均已得到很好的开发，特别是在发达国家，例如FLASH，RELAP4 / MOD7，TRACPF1和RELAP5 / MOD3等。

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《International topical meeting on nuclear thermal hydraulics, operations and safety;NUTHOS-5》|1997年|p.O5-1-3 ^b 6|共1页
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Chen Xiaoxiang; Tang Gang; Wang Rongzhong;
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中图分类原子能技术;
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专利

1. Small Break LOCA Analysis for Optimization of Safety Injection System of Korean Standard Nuclear Power Plant [J] . N. H. Lee, K. H. Bae, S. J. Lee Annals of Nuclear Energy . 1998,第4a5期

机译：韩国标准核电站安全注入系统优化的小区间LOCA分析
2. Real-time estimation of break sizes during LOCA in nuclear power plants using NARX neural network [J] . Mahdi Saghafi, Mohammad B. Ghofrani Nuclear engineering and technology . 2019,第3期

机译：使用NARX神经网络实时估计核电厂LOCA期间的断裂尺寸
3. Uncertainty calculation in small break LOCA in the emergency core cooling system connected to the hot leg of Angra 2 nuclear power plant [J] . Eduardo Madeira Borges, Gaianê Sabundjian, Francesco DAuria, International Journal of Nuclear Energy Science and Technology . 2018,第2期

机译：连接到Angra 2核电厂热路段的应急堆芯冷却系统中小断裂LOCA的不确定度计算
4. Large break loca analysis for qinshan-2 nuclear power plant [C] . Chen Xiaoxiang, Tang Gang, Wang Rongzhong International topical meeting on nuclear thermal hydraulics, operations and safety . 1997

机译：秦山2核电站大型突破基因座分析
5. Case Study on the Development of Engineering Design Modification Projects for U.S. Nuclear Power Plants: A Knowledge Retention Tool in Support of the Longevity and Resilience of the Nuclear Power Industry [D] . Torres-Jiménez, Pamela M. 2018

机译：美国核电厂工程设计改造项目开发的案例研究：支持核电行业长寿和复原力的知识保留工具
6. Reanalysis of Epidemiological Investigation of Cancer Risk among People Residing near Nuclear Power Plants in South Korea [O] . Jeong-Min Kim, Myoung-Hee Kim, Young-Su Ju, 2018

机译：韩国核电厂附近居民癌症风险的流行病学调查再分析
7. Sensitivity Analyses of Failure Probability of Pipes in Nuclear Power Plants using PRO-LOCA [O] . Young Ki Cho, Sun Hye Kim, Jai Hak Park 2014

机译：使用Pro-Loca核电站管道失效概率的敏感性分析
8. Recirculation Suction Large Break LOCA Analysis of the Santa Maria De Garona Nuclear Power Plant Using TRAC-BFI (G1J1) [R] . Lopez, J V, Blanco, J, Crespo, J L, 1992

机译：使用TRaC-BFI（G1J1）对santa maria De Garona核电站进行再循环吸入大破口LOCa分析

Large break loca analysis for qinshan-2 nuclear power plant

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