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|a (TOE)ost7315575
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|a (TOE)7315575
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|a TOE
|c TOE
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|a GDWR
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|a 21
|2 edbsc
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|a 36
|2 edbsc
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|a E 1.99:lmec-memo-70-5
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|a E 1.99:lmec-memo-70-5
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| 088 |
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|a lmec-memo-70-5
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| 245 |
0 |
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|a Examination of four-sodium-water reaction target tubes
|h [electronic resource]
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| 260 |
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|a Downey, Calif :
|b Rockwell International ;
|a Oak Ridge, Tenn. :
|b distributed by the Office of Scientific and Technical Information, U.S. Dept. of Energy,
|c 1970.
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| 300 |
|
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|a Pages: 67 :
|b digital, PDF file.
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| 336 |
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|a text
|b txt
|2 rdacontent.
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| 337 |
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|a computer
|b c
|2 rdamedia.
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| 338 |
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|a online resource
|b cr
|2 rdacarrier.
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| 500 |
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|a Published through the Information Bridge: DOE Scientific and Technical Information.
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| 500 |
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|a 06/26/1970.
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| 500 |
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|a "lmec-memo-70-5"
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| 500 |
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|a Lee, W.T.
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| 520 |
3 |
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|a Metallurgical examinations and evaluations were performed on a group of four target tubes from Atomic Power Development Associates (APDA) Rig 10. This group included two 2¹/₄ Cr--1 Mo ferritic steel tubes, one Type 304 SS, and one Incoloy 800 tube. These tubes had been exposed to small leaks of water in 600°F sodium. Metallographic data indicate that the material loss (wastage) was primarily due to impact (or erosion) of liquid particles. No evidence of corrosion was found in the wasted areas of any target tubes. Minor corrosion was observed on the outside diameter of the austenitic stainless-steel tubes only in areas away from impact; no corrosion was detected on the outside diameter of the ferritic steel tubes. Hardness measurements and microstructural analyses revealed that the maximum temperature may have reached 1600°F in the wasted areas. This localized temperature increase appeared to enhance the wastage process for all target tubes regardless of composition. Surface grain elongation and plastic deformation lines were observed in wasted areas, as well as in other areas. However, their cause(s) cannot be ascertained with respect to deformation due to water-jet impact, or deformation due to fabrication and handling, or both. Based on the volumetric measurements of the wastage zones produced, Incoloy 800 (tube No. 21) exhibited greater resistance to water-jet impact/erosion (penetration depth approximately 0.011 in. in 570 sec), while 2¹/₄ Cr--1 Mo ferritic steel displayed the least (depth of penetration 0.064 in. in 21 sec)
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| 536 |
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|b E(04-3)-0700.
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| 650 |
|
7 |
|a Corrosion.
|2 local.
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| 650 |
|
7 |
|a Heat Exchangers.
|2 local.
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| 650 |
|
7 |
|a Liquid Metal Cooled Reactors.
|2 local.
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| 650 |
|
7 |
|a Nickel Alloys.
|2 local.
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| 650 |
|
7 |
|a Simulation.
|2 local.
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| 650 |
|
7 |
|a Molten Metal-water Reactions.
|2 local.
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| 650 |
|
7 |
|a Lmfbr Type Reactors.
|2 local.
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| 650 |
|
7 |
|a Erosion.
|2 local.
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| 650 |
|
7 |
|a Water.
|2 local.
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| 650 |
|
7 |
|a Oxygen Compounds.
|2 local.
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| 650 |
|
7 |
|a Chromium Steels.
|2 local.
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| 650 |
|
7 |
|a Stainless Steel-304.
|2 local.
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| 650 |
|
7 |
|a Elements.
|2 local.
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| 650 |
|
7 |
|a Alloys.
|2 local.
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| 650 |
|
7 |
|a Leaks.
|2 local.
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| 650 |
|
7 |
|a Steels.
|2 local.
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| 650 |
|
7 |
|a Iron Base Alloys.
|2 local.
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| 650 |
|
7 |
|a Incoloy Alloys.
|2 local.
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| 650 |
|
7 |
|a Heat Resisting Alloys.
|2 local.
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| 650 |
|
7 |
|a Sodium.
|2 local.
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| 650 |
|
7 |
|a Alkali Metals.
|2 local.
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| 650 |
|
7 |
|a Breeder Reactors.
|2 local.
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| 650 |
|
7 |
|a Epithermal Reactors.
|2 local.
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| 650 |
|
7 |
|a Metals.
|2 local.
|
| 650 |
|
7 |
|a Reactors.
|2 local.
|
| 650 |
|
7 |
|a Corrosive Effects.
|2 local.
|
| 650 |
|
7 |
|a Stainless Steels.
|2 local.
|
| 650 |
|
7 |
|a Chromium-nickel Steels.
|2 local.
|
| 650 |
|
7 |
|a Incoloy 800.
|2 local.
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| 650 |
|
7 |
|a Chromium Alloys.
|2 local.
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| 650 |
|
7 |
|a Fbr Type Reactors.
|2 local.
|
| 650 |
|
7 |
|a Fast Reactors.
|2 local.
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| 650 |
|
7 |
|a Chemical Reactions.
|2 local.
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| 650 |
|
7 |
|a Tubes.
|2 local.
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| 650 |
|
7 |
|a Chromium-molybdenum Steels.
|2 local.
|
| 650 |
|
7 |
|a Iron Alloys.
|2 local.
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| 650 |
|
7 |
|a Hydrogen Compounds.
|2 local.
|
| 650 |
|
7 |
|a Corrosion Resistant Alloys.
|2 local.
|
| 650 |
|
7 |
|a Materials Science.
|2 edbsc.
|
| 650 |
|
7 |
|a Specific Nuclear Reactors And Associated Plants.
|2 edbsc.
|
| 710 |
2 |
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|a Liquid Metal Engineering Center (U.S.).
|4 res.
|
| 710 |
2 |
|
|a Rockwell International.
|4 res.
|
| 710 |
1 |
|
|a United States.
|b Department of Energy.
|b Office of Scientific and Technical Information.
|4 dst.
|
| 856 |
4 |
0 |
|u http://www.osti.gov/servlets/purl/7315575-EKjPgj/
|z Online Access
|
| 907 |
|
|
|a .b72814299
|b 03-07-23
|c 02-08-13
|
| 998 |
|
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|a web
|b 02-08-13
|c f
|d m
|e p
|f eng
|g cau
|h 0
|i 1
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| 956 |
|
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|a Information bridge
|
| 999 |
f |
f |
|i 8845913d-5f5c-5ec6-8b13-c67668b23f78
|s 2ace564a-8992-5a29-adfe-cf668a6894ff
|
| 952 |
f |
f |
|p Can circulate
|a University of Colorado Boulder
|b Online
|c Online
|d Online
|e E 1.99:lmec-memo-70-5
|h Superintendent of Documents classification
|i web
|n 1
|
