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|a (TOE)ost10121014
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|a (TOE)10121014
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|a TOE
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|a GDWR
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|a E 1.99:dun--921
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|a E 1.99:dun--921
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| 088 |
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|a dun--921
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| 245 |
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|a Abstract -- A description of low temperature hydriding of zircaloy at Hanford
|h [electronic resource]
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| 260 |
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|a Washington, D.C. :
|b United States. Dept. of Energy ;
|a Oak Ridge, Tenn. :
|b distributed by the Office of Scientific and Technical Information, U.S. Dept. of Energy,
|c 1966.
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| 300 |
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|a 2 p. :
|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 03/31/1966.
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| 500 |
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|a "dun--921"
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| 500 |
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|a "DE95007454"
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| 500 |
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|a Alexander, W.K.
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| 513 |
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|a Topical;
|b 03/01/1966.
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| 520 |
3 |
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|a The two K Reactors at the Hanford Plant of the Atomic Energy Commission were retubed in 1963 with ribless Zircaloy process tubes. These tubes, 1.81 inch OD x 0.037 inch wall, were made by tube reducing methods from extruded blooms and were installed without final pickling or autoclaving. These tubes are used with once-through filtered water with a maximum coolant temperature of approximately 110 C. After approximately two years̀ service, it was discovered that these tubes were absorbing hydrogen in a totally unexpected and alarming manner. It was found that the downstream few feet of these tubes had a layer of massive hydride platelets, several mils thick, on the inner surface, and that the hydrogen content of the tube wall beneath this layer had increased from the as-fabricated level of 5--15 ppm to 50--75 ppm. The portion of the tubes so affected was downstream of the fuel charge. Physical testing has indicated loss of ductility but no significant changes in strength, Cold burst tests resulted in a ductile failure mode with no tendency toward brittle fracture. A program to determine the basic mechanism responsible for this phenomenon as well as practical means for its elimination will be the subject of a companion paper.
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| 536 |
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|b AC06-76RL01830.
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| 650 |
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7 |
|a Mechanical Tests.
|2 local.
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| 650 |
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7 |
|a Hydridation.
|2 local.
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| 650 |
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7 |
|a Historical Aspects.
|2 local.
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| 650 |
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7 |
|a Hydrogen Embrittlement.
|2 local.
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| 650 |
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7 |
|a Hanford Production Reactors.
|2 local.
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| 650 |
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7 |
|a Fuel Channels.
|2 local.
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| 650 |
|
7 |
|a Mechanical Properties.
|2 local.
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| 650 |
|
7 |
|a Zircaloy.
|2 local.
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| 650 |
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7 |
|a General Studies Of Nuclear Reactors.
|2 edbsc.
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| 650 |
|
7 |
|a Specific Nuclear Reactors And Associated Plants.
|2 edbsc.
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| 710 |
2 |
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|a Douglas United Nuclear, Inc.
|4 res.
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| 710 |
1 |
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|a United States.
|b Department of Energy.
|4 spn.
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| 710 |
2 |
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|a Hanford Site (Wash.).
|4 res.
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| 710 |
1 |
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|a United States.
|b Department of Energy.
|b Office of Scientific and Technical Information.
|4 dst.
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| 856 |
4 |
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|u http://www.osti.gov/servlets/purl/10121014-htvrEQ/webviewable/
|z Online Access
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| 907 |
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|a .b72985161
|b 03-07-23
|c 02-08-13
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| 998 |
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|a web
|b 02-08-13
|c f
|d m
|e p
|f eng
|g dcu
|h 0
|i 1
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| 956 |
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|a Information bridge
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| 999 |
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|i 78075196-df6b-5546-89c5-92dd40612526
|s c01c6f95-5617-5339-90b3-60480790d150
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| 952 |
f |
f |
|p Can circulate
|a University of Colorado Boulder
|b Online
|c Online
|d Online
|e E 1.99:dun--921
|h Superintendent of Documents classification
|i web
|n 1
|
