简介概要

Material Characterization of Ni Base Alloy for Very High Temperature Reactor

来源期刊:JOURNAL OF MATERIALS SCIENCE TECHNOLOG2013年第12期

论文作者:Dong-Jin Kim Gyeong-Geun Lee Dae Jong Kim Su Jin Jeong

文章页码:1184 - 1190

摘    要:The generation of highly efficient electricity and the production of massive hydrogen are possible using a very high temperature reactor (VHTR) among generation IV nuclear power plants.The structural material for an intermediate heat exchanger (IHX) among numerous components should be endurable at high temperature of up to 950 C during long-term operation.Impurities inevitably introduced in helium as a coolant facilitate the material degradation by corrosion at high temperature.In the present work,the surface reactions available under controlled impure helium at 950 C were investigated based on the thermodynamics and the corrosion tests were performed in a temperature range of 850e950 C during 10e250 h for commercial Alloy 617 as a candidate material for an IHX.Moreover,the mechanical property and microstructure for nickel-based alloys fabricated in laboratory were evaluated as a function of the processing parameters such as hot rolling and heat treatment conditions.From the reaction rate constant obtained from an impure helium control system for a material evaluation,it was predicted that the outer oxide layer thickness,internal oxide depth,and carbidedepleted zone depth reach about 116,600 and 1000 mm,respectively when Alloy 617 is exposed to an impure helium environment at 950 C for 20 years.For NieCreCoeMo alloy,subsequent annealing and a combination of cold working and subsequent annealing following solution annealing caused increases in the grain boundary carbide coverage and size.The angular distribution of the grain boundary as well as the carbide distribution was also changed leading to a consequent improvement of the mechanical property at950 C in air.

详情信息展示

Material Characterization of Ni Base Alloy for Very High Temperature Reactor

Dong-Jin Kim,Gyeong-Geun Lee,Dae Jong Kim,Su Jin Jeong

Nuclear Materials Division,Korea Atomic Energy Research Institute

摘 要:The generation of highly efficient electricity and the production of massive hydrogen are possible using a very high temperature reactor (VHTR) among generation IV nuclear power plants.The structural material for an intermediate heat exchanger (IHX) among numerous components should be endurable at high temperature of up to 950 C during long-term operation.Impurities inevitably introduced in helium as a coolant facilitate the material degradation by corrosion at high temperature.In the present work,the surface reactions available under controlled impure helium at 950 C were investigated based on the thermodynamics and the corrosion tests were performed in a temperature range of 850e950 C during 10e250 h for commercial Alloy 617 as a candidate material for an IHX.Moreover,the mechanical property and microstructure for nickel-based alloys fabricated in laboratory were evaluated as a function of the processing parameters such as hot rolling and heat treatment conditions.From the reaction rate constant obtained from an impure helium control system for a material evaluation,it was predicted that the outer oxide layer thickness,internal oxide depth,and carbidedepleted zone depth reach about 116,600 and 1000 mm,respectively when Alloy 617 is exposed to an impure helium environment at 950 C for 20 years.For NieCreCoeMo alloy,subsequent annealing and a combination of cold working and subsequent annealing following solution annealing caused increases in the grain boundary carbide coverage and size.The angular distribution of the grain boundary as well as the carbide distribution was also changed leading to a consequent improvement of the mechanical property at950 C in air.

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