The di-aromatics base oil and graphite powder,blended with the viscosity index improver,and the anti-oxidant and rheological additive,were used to prepare a kind of anti-seize thread lubricant.Its physical chemistry p...The di-aromatics base oil and graphite powder,blended with the viscosity index improver,and the anti-oxidant and rheological additive,were used to prepare a kind of anti-seize thread lubricant.Its physical chemistry properties,such as water resistance,thermal oxidation and aging properties,and tribological performance,were evaluated and compared with those of some commercial products.The results show that the overall performance of the anti-seize thread lubricant could meet the level of some commercial products,while its some properties such as thermal stability,anti-wear and anti-friction properties were better.The said anti-seize thread lubricant is more suitable for use under high temperature conditions.展开更多
Supercritical water reactor(SCWR)was proposed as a GenerationⅣconcept for building large capacity nuclear power plants.Comparing with the present GenerationⅡandⅢlight water reactors,SCWR possesses great advantages ...Supercritical water reactor(SCWR)was proposed as a GenerationⅣconcept for building large capacity nuclear power plants.Comparing with the present GenerationⅡandⅢlight water reactors,SCWR possesses great advantages of 10%higher efficiency,simpler system design,better sustainability,and so on.However,the selection of materials for fuel cladding and reactor internals of SCWR is facing a great challenge.Corrosion in supercritical steam is of the first important issue to be solved to meet the stringent requirement of the reactor internal components.Corrosion screening tests were conducted on candidate materials for nuclear fuel cladding and reactor internals of supercritical water reactor(SCWR)in static and re-circulating autoclave at the temperatures of 550,600 and 650℃,pressure of about 25 MPa,deaerated or saturated dissolved hydrogen(STP).Nickel base alloy type Hastelloy C276,austenitic stainless steels type 304NG,AL-6XN,HR3C.NF709 and SAVE 25,ferritic/martensitic(F/M)steel type P92,P122 and 410,and oxide dispersion strengthened steel MA 956,are tested.This paper presents corrosion rate,and focuses on the formation and breakdown of corrosion oxide film,and proposes the future trend for the development of SCWR internal structure materials.展开更多
基金The authors gratefully acknowledge the financial support from the National Science and Technology for Major Project of China(Project No.2019ZX06004002).
文摘The di-aromatics base oil and graphite powder,blended with the viscosity index improver,and the anti-oxidant and rheological additive,were used to prepare a kind of anti-seize thread lubricant.Its physical chemistry properties,such as water resistance,thermal oxidation and aging properties,and tribological performance,were evaluated and compared with those of some commercial products.The results show that the overall performance of the anti-seize thread lubricant could meet the level of some commercial products,while its some properties such as thermal stability,anti-wear and anti-friction properties were better.The said anti-seize thread lubricant is more suitable for use under high temperature conditions.
文摘Supercritical water reactor(SCWR)was proposed as a GenerationⅣconcept for building large capacity nuclear power plants.Comparing with the present GenerationⅡandⅢlight water reactors,SCWR possesses great advantages of 10%higher efficiency,simpler system design,better sustainability,and so on.However,the selection of materials for fuel cladding and reactor internals of SCWR is facing a great challenge.Corrosion in supercritical steam is of the first important issue to be solved to meet the stringent requirement of the reactor internal components.Corrosion screening tests were conducted on candidate materials for nuclear fuel cladding and reactor internals of supercritical water reactor(SCWR)in static and re-circulating autoclave at the temperatures of 550,600 and 650℃,pressure of about 25 MPa,deaerated or saturated dissolved hydrogen(STP).Nickel base alloy type Hastelloy C276,austenitic stainless steels type 304NG,AL-6XN,HR3C.NF709 and SAVE 25,ferritic/martensitic(F/M)steel type P92,P122 and 410,and oxide dispersion strengthened steel MA 956,are tested.This paper presents corrosion rate,and focuses on the formation and breakdown of corrosion oxide film,and proposes the future trend for the development of SCWR internal structure materials.
