PRESSURE VESSEL AND PIPING CODES APPLICABLE TO THE PWR REACTOR PLANT

机译：适用于PWR反应器植物的压力容器和管道码

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J.F. Dobinsky; M.B. Andrew; T.R. Moffette;
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年度 1957
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专利

1. Development of probabilistic fracture mechanics analysis codes for reactor pressure vessels and piping considering welding residual stress [J] . Kunio Onizawa, Hiroyuki Nishikawa, Hiroto Itoh International Journal of Pressure Vessels and Piping . 2010,第1期

机译：考虑焊接残余应力的反应堆压力容器和管道的概率断裂力学分析代码的开发
2. A fracture mechanics analysis of the PWR nuclear power plant reactor pressure vessel beltline weld [J] . Young LJ. Journal of Nuclear Materials: Materials Aspects of Fission and Fusion . 2001,第2a3期

机译：压水堆核电站反应堆压力容器带线焊缝的断裂力学分析
3. MCNP Neutron Streaming Investigations from the Reactor Core to Regions Outside the Reactor Pressure Vessel for a Swiss PWR [J] . Ben Volmert, Elena Tamaseviciute, Manuel Pantelias, Transactions of the American nuclear society . 2013,第novapta2期

机译：瑞士压水堆从反应堆堆芯到反应堆压力容器以外区域的MCNP中子流研究
4. Assessment of the reactor pressure vessel integrity in PTS conditions. Thermal Hydraulic study of a safety injection in a three loop PWR plant with the finite element code N3S [C] . A.Martin, D.Alvarez, F.Ternon Morin, ASME pressure vessels and piping conference . 2000

机译：在PTS条件下评估反应堆压力容器的完整性。有限元代码为N3S的三回路压水堆安全注入热力水力研究
5. Finite Element Analysis of Composite Reactor Pressure Vessel [D] . Mhetre, Tejas Vasant. 2018

机译：复合反应堆压力容器的有限元分析
6. Occupational ALARA Planning for Reactor Pressure Vessel Dismantling at Kori Unit 1 [O] . Juyoul Kim, Batbuyan Tseren 2020

机译：Kori单元1的反应堆压力容器拆除职业Alara规划
7. Microstructure and Stress Corrosion Cracking of Dissimilar Metal Weld 16MND5/309L/308L/Z2CND18-12N Used for Connecting Reactor Pressure Vessel to Piping in Nuclear Power Plants [O] . Li G.F., Yuan Y.F., Lu X. 2015

机译：用于核反应堆压力容器与管道连接的异种金属焊缝16MND5 / 309L / 308L / Z2CND18-12N的组织和应力腐蚀开裂
8. PRESSURE VESSEL AND PIPING CODES APPLICABLE TO THE PWR REACTOR PLANT [R] . 1957

机译：适用于压水堆反应堆工厂的压力容器和管道代码

PRESSURE VESSEL AND PIPING CODES APPLICABLE TO THE PWR REACTOR PLANT

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