REACTOR PRESSURE VESSEL AND REACTOR COOLANT CIRCUIT CAST DUPLEX STAINLESS STEEL COMPONENTS CONTRIBUTION OF THE EXPERTISES FOR LIFE MANAGEMENT STUDIES

机译：反应堆压力容器和反应堆冷却剂循环铸造双相不锈钢成分对生命管理研究专业知识的贡献

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The life management of French Nuclear Power Plants is a major stake from an economic and a technical point of view considering the aging management assessment of the key components of the plant.The actual life evaluation is the results of prediction of life assessment from important program of expertises for the 3-loop PWR and 4-loop PWR plants in operation.

机译：考虑到电厂关键部件的老化管理评估，从经济和技术角度来看，法国核电厂的寿命管理是一项重大工作。实际寿命评估是根据重要计划对寿命评估的预测结果。 3回路PWR和4回路PWR电厂的专业知识。

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来源
《ASME(American Society of Mechanical Engineers) Pressure Vessels and Piping Conference 2006 vol.7: Operations, Applications, and Components》|2006年|107-119|共13页
会议地点 Vancouver(CA)
作者
Georges Bezdikian;
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作者单位

EDF - GENERATION AND ENGINEERING Nuclear Generation Division Site CAP AMPERE - 1 Place Pleyel 93282 SAINT DENIS-FRANCE;

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原文格式 PDF
正文语种 eng
中图分类工业用热工设备;
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1. Thermodynamic modeling of G-phase and assessment of phase stabilities in reactor pressure vessel steels and cast duplex stainless steels [J] . Jacob Aurelie, Domain Christophe, Adjanor Gilles, Journal of Nuclear Materials: Materials Aspects of Fission and Fusion . 2020,第1期

机译：G相的热力学建模与反应堆压力容器钢中相稳定性评估及铸造双相不锈钢
2. Detailed CFX-5 study of the coolant mixing within the reactor pressure vessel of a VVER-1000 reactor during a non-symmetrical heat-up test [J] . Michael Boettcher Nuclear Engineering and Design . 2008,第3期

机译：在非对称加热测试中对VVER-1000反应堆压力容器内的冷却剂混合进行的详细CFX-5研究
3. Inelastic Cyclic Deformation Behaviors of Type 316H Stainless Steel for Reactor Pressure Vessel of Sodium-Cooled Fast Reactor at Elevated Temperatures [J] . Yoon Ji-Hyun, Kim Young-Chun, Hong Seokmin, Journal of Korean Institute of Metal and Materials . 2015,第10期

机译：高温下钠冷快堆反应堆压力容器用316H不锈钢的非弹性循环变形行为
4. REACTOR PRESSURE VESSEL AND REACTOR COOLANT CIRCUIT CAST DUPLEX STAINLESS STEEL COMPONENTS CONTRIBUTION OF THE EXPERTISES FOR LIFE MANAGEMENT STUDIES [C] . Georges Bezdikian, American Society of Mechanical Engineers(ASME) ASME Pressure Vessels and Piping Conference . 2007

机译：反应器压力容器和反应器冷却剂回路铸造双相不锈钢部件为终身管理研究的专业贡献
5. Understanding Load History Effects for Improved Defect Assessments in Reactor Pressure Vessel Steels [D] . Beswick, Jack P. 2018

机译：了解加载历史效果，以改善反应堆压力容器钢中的改进缺陷评估
6. Development of an automatedchemistry control system forsecondary coolant circuits inCANDU nuclear power reactors [O] . J. R. Dean, R. B. Stewart 1979

机译：开发自动化化学控制系统二次冷却液回路坎杜核电反应堆
7. DETAILED CFX-5 STUDY OF THE COOLANT MIXING WITHIN THE REACTOR PRESSURE VESSEL OF A VVER-1000 REACTOR DURING A NON-SYMMETRICAL HEAT-UP TEST [O] . Michael Böttcher 2010

机译：非对称加热试验中VVER-1000反应器内反应器压力容器内冷却剂混合的CFX-5详细研究
8. Long-Term Embrittlement of Cast Duplex Stainless Steels in LWR (Light Water Reactor) Systems. Semiannual Report October, 1987-March 1988. [R] . Chopra, O. K., Chung, H. M. 1990

机译：LWR（轻水反应堆）系统中铸造双相不锈钢的长期脆化。 1987年10月至1988年3月的半年度报告。

REACTOR PRESSURE VESSEL AND REACTOR COOLANT CIRCUIT CAST DUPLEX STAINLESS STEEL COMPONENTS CONTRIBUTION OF THE EXPERTISES FOR LIFE MANAGEMENT STUDIES

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