A severe accident code was applied for modeling of a typical pressurized water reactor (PWR) nuclear power plant, and the effects of RCS depressurization on the gas temperature of the relief tank cell in the containme...
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This paper first analyzes the feasibility of SA-508 Grade 3 Class 1 Steel as an alternative material for Supercritical Water-Cooled reactor (SCWR) reactor Pressure Vessel (RPV). This kind of steel is limited to be app...
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ISBN:
(纸本)9781119027942
This paper first analyzes the feasibility of SA-508 Grade 3 Class 1 Steel as an alternative material for Supercritical Water-Cooled reactor (SCWR) reactor Pressure Vessel (RPV). This kind of steel is limited to be applied in SCWR RPV due to its quenching property, though large forging could be accomplished by domestic manufacturers in forging aspect. Therefore, steels with higher strength and better quenching property are needed for SWCR RPV. The chemical component of SA-508 Gr.3 Cl.2 steel is similar to that of SA-508 Gr.3 Cl.1 steel, and more appropriate matching of strength and toughness could be achieved by the adjusting the elements contents, as well as proper control of tempering temperature and time. In light of the fact that Cl.2 steel has been successfully applied to steam generator, it could be an alternative material for SWCR RPV. SA-508 Gr.4N steel with high strength and good toughness is another alternative material for SCWR RPV. But large amount of research work before application is still needed for the lack of data on welding and irradiation etc.
Effects of main alloying elements, quenching and tempering temperatures and quenching cooling velocity on mechanical properties of Z12CN13 stainless steel were obtained by controlling the material composition and opti...
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ISBN:
(纸本)9781119027942
Effects of main alloying elements, quenching and tempering temperatures and quenching cooling velocity on mechanical properties of Z12CN13 stainless steel were obtained by controlling the material composition and optimizing the heat treatments. Evaluation of domestic forging Z12CN13 stainless steel for Hold-Down Spring of reactor had been completed, and all parameters met the requirement of design criteria national standard. The main alloying elements should be selected from upper limits to reach the technical standards of the strength and toughness properties. The strength, plasticity and toughness properties of domestic forging Z12CN13 stainless steel will decrease with increasing the quenching temperature. On the contrary, the strength decreases, plasticity and the toughness properties will increase with the increasing of tempering temperature. The tensile strength and impact toughness of materials are influenced obviously with the quenching cooling velocity. Improving the cooling velocity could meet the technical standards of the strength and toughness properties. The comprehensive mechanical properties and combination of strength and toughness is the best when the domestic forging Z12CN13 stainless steel is quenched at 985°C and then cooling fast and aged at 640°C.
The State Oriented Procedure (SOP) is developed to improve the existing emergency operation procedures, namely, the Event Oriented Procedure (EOP). It is developed based on the finite Nuclear Steam Supply system (NSSS...
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Metallic insulation is commonly used in reactor vessel because of its resistance to radiation and corrosion. Since the main mode of heat loss of reactor vessel is thermal radiation, the ability to prevent radiation he...
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In order to improve safety, economy and reliability of NPP(nuclear power plant) and to make the best of human, material and information resources in the NPP, a specific function model developing method for integrated ...
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