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Use of alloy 800H for applications i...

Virupaksha, Vinay.

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Use of alloy 800H for applications in hydrogen generation using nuclear power.

紀錄類型:	書目-電子資源 : Monograph/item
正題名/作者:	Use of alloy 800H for applications in hydrogen generation using nuclear power./
作者:	Virupaksha, Vinay.
面頁冊數:	133 p.
附註:	Source: Masters Abstracts International, Volume: 45-01, page: 0444.
Contained By:	Masters Abstracts International45-01.
標題:	Engineering, Mechanical. -
電子資源:	http://pqdd.sinica.edu.tw/twdaoapp/servlet/advanced?query=1438432
ISBN:	9780542892783

Use of alloy 800H for applications in hydrogen generation using nuclear power.
Virupaksha, Vinay.

Use of alloy 800H for applications in hydrogen generation using nuclear power. - 133 p.

Source: Masters Abstracts International, Volume: 45-01, page: 0444.

Thesis (M.S.)--University of Nevada, Las Vegas, 2006.

Alloy 800H, a candidate structural material for heat-exchangers to be used in nuclear hydrogen generation, was investigated for its high-temperature tensile properties and corrosion behavior. The tensile properties evaluated at different temperatures indicate that Alloy 800H was capable of maintaining high strength up to 600°C followed by its reduction in yield strength and ultimate tensile strength beyond this temperature. Further, the ductility was reduced at some critical temperatures, possibly due to the dynamic strain aging effect. Alloy 800H did not exhibit cracking in acidic aqueous solutions, both under constant-load and self-loaded conditions. Slight reductions in the true failure stress, percent elongation, percent reduction in area, and time-to-failure were observed when tested under a slow-strain-rate condition. The critical potentials became more active with increasing temperature determined by an electrochemical technique. The effect of anodic applied potential was more pronounced on the cracking susceptibility. Dimpled microstructures, characteristic of ductile failure, with some intergranular cracks were observed in the tested specimens. Typical austenitic grains with annealing twins and precipitates were observed in the microstructure.

ISBN: 9780542892783Subjects--Topical Terms:

783786
Engineering, Mechanical.

Use of alloy 800H for applications in hydrogen generation using nuclear power.
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502 $a Thesis (M.S.)--University of Nevada, Las Vegas, 2006.
520 $a Alloy 800H, a candidate structural material for heat-exchangers to be used in nuclear hydrogen generation, was investigated for its high-temperature tensile properties and corrosion behavior. The tensile properties evaluated at different temperatures indicate that Alloy 800H was capable of maintaining high strength up to 600°C followed by its reduction in yield strength and ultimate tensile strength beyond this temperature. Further, the ductility was reduced at some critical temperatures, possibly due to the dynamic strain aging effect. Alloy 800H did not exhibit cracking in acidic aqueous solutions, both under constant-load and self-loaded conditions. Slight reductions in the true failure stress, percent elongation, percent reduction in area, and time-to-failure were observed when tested under a slow-strain-rate condition. The critical potentials became more active with increasing temperature determined by an electrochemical technique. The effect of anodic applied potential was more pronounced on the cracking susceptibility. Dimpled microstructures, characteristic of ductile failure, with some intergranular cracks were observed in the tested specimens. Typical austenitic grains with annealing twins and precipitates were observed in the microstructure.
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