Enhanced thermal transport and corrosion resistance by coating vertically-aligned graphene on zirconium alloy for nuclear reactor applications

2022 ◽  
pp. 152484
Author(s):  
Xiangyang Sun ◽  
Feng Gong ◽  
Menglong Hao ◽  
Lei Wu ◽  
Chunyu Yin ◽  
...  
Keyword(s):  
Corrosion Resistance ◽  
Thermal Transport ◽  
Zirconium Alloy ◽  
Nuclear Reactor ◽  
Vertically Aligned

JESSOP-SAVILLE ZIRCONIUM ALLOY

Alloy Digest ◽  
1965 ◽  
Vol 14 (3) ◽  
Keyword(s):  
Corrosion Resistance ◽  
Zirconium Alloy ◽  
Heat Treating ◽  
Pressurized Water Reactors ◽  
Neutron Absorption ◽  
High Melting Point ◽  
Absorption Properties ◽  
Pressurized Water ◽  
Excellent Corrosion Resistance ◽  
Water Reactors

Abstract JESSOP-SAVILLE ZIRCONIUM Alloy has a high melting point and possesses excellent corrosion resistance coupled with low neutron absorption properties. It is equivalent to ZIRCALOY 2. It is recommended for pressurized water reactors. This datasheet provides information on composition, physical properties, elasticity, and tensile properties as well as creep. It also includes information on corrosion resistance as well as forming, heat treating, machining, joining, and surface treatment. Filing Code: Zr-2. Producer or source: Jessop-Saville Ltd, Brightside Works.

Determination of the Hydrogen Concentration in Zr-2.5Nb Alloy by a Resonant Ultrasound Spectroscopy

2006 ◽  
Vol 321-323 ◽  
pp. 1576-1579
Author(s):  
Yong Moo Cheong ◽  
Young Suk Kim
Keyword(s):  
Hydrogen Concentration ◽  
Zirconium Alloy ◽  
Nuclear Reactor ◽  
Zirconium Alloys ◽  
Resonant Ultrasound Spectroscopy ◽  
Heavy Water Reactor ◽  
Resonant Ultrasound ◽  
Non Destructive

Zirconium alloys are used for many applications in nuclear components, such as the pressure tube material in a pressurized heavy water reactor, nuclear fuel cladding, etc. One of the problems during the operation of a nuclear reactor is the degradation of the zirconium alloys, which is due to an increase of the hydrogen content in the zirconium alloy. Therefore a non-destructive determination of the hydrogen concentration in zirconium alloy is one of the important issues that need to be addressed. The resonant ultrasound spectroscopy (RUS) technique is evaluated for a characterization of the hydrogen concentration in Zr-2.5Nb alloy. Referring to the terminal solid solubility for dissolution (TSSD) of Zr-2.5Nb alloy, the plot of the mechanical damping coefficient (Q-1) versus the temperature or the deviation of the resonant frequency for the temperature (df/dT) versus the temperature was correlated for the hydrogen concentration in Zr-2.5Nb alloy. It was found that the temperature at an abrupt change of the slope can be correlated with the hydrogen concentration of the Zr-2.5Nb alloy.

Thermal Transport in Actinide Oxide Fuels With Interstitial Defects

2019 ◽  
Author(s):  
Katherine Mitchell ◽  
Hunter Horner ◽  
Alex Resnick ◽  
Jungkyu Park ◽  
Eduardo B. Farfán ◽  
...  
Keyword(s):  
Point Defects ◽  
Thermal Transport ◽  
Nuclear Reactor ◽  
Nuclear Reactors ◽  
Reactor Operation ◽  
Oxygen Interstitial ◽  
Interstitial Defects ◽  
Actinide Oxides ◽  
Non Equilibrium Molecular Dynamics ◽  
Thermal Conductivities

Abstract Molecular displacement occurs in the oxide fuels of nuclear reactors during operation. This causes several types of point defects to be generated inside the oxide nuclear fuels. To improve the safety and efficiency of nuclear reactor operation, it is necessary to better understand the effects of point defects on the properties of the oxide fuels. In this study, we examine the effects of interstitial defects on thermal transport in two representative actinide oxides used in modern reactors (UO2, and PuO2). Reverse non-equilibrium molecular dynamics (RNEMD) is employed to approximate the thermal conductivities for the aforementioned fuels at several sample lengths and at defect concentrations of 0.1%, 1%, and 5%. The results show that alterations to the lattice structures of these fuels reduce their thermal conductivities significantly. For example, oxygen interstitial defects at concentrations even as low as 0.1% decreased thermal conductivity by 20% at 100 units for each fuel.

JESSOP JS625

Alloy Digest ◽  
1983 ◽  
Vol 32 (4) ◽  
Keyword(s):  
Corrosion Resistance ◽  
Fatigue Strength ◽  
Power Plant ◽  
Flue Gas ◽  
Heat Exchangers ◽  
Nuclear Reactor ◽  
Heat Treating ◽  
Steel Company ◽  
Aerospace Applications ◽  
Nickel Chromium

Abstract JESSOP JS625 is a nickel-chromium-molybdenum-columbium alloy that is well suited for applications where strength and corrosion resistance are required. It has superior strength and toughness at temperatures ranging from cryogenic to 2000 F; also, it has exceptional fatigue strength. It is outstanding in resistance to corrosion either general or localized (pitting/crevice), is virtually immune to chloride-ionstress-corrosion cracking, and is highly resistant to oxidation. Among its many uses are aerospace applications, heat exchangers, nuclear-reactor components and power-plant flue-gas scrubbers. This datasheet provides information on composition, physical properties, elasticity, and tensile properties. It also includes information on corrosion resistance as well as forming, heat treating, machining, and joining. Filing Code: Ni-285. Producer or source: Jessop Steel Company.

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