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|a (TOE)ost6723753
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|a (TOE)6723753
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|a TOE
|c TOE
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|a GDWR
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|2 edbsc
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|a E 1.99:wsrc-ms-92-239
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|a E 1.99:wsrc-ms-92-239
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|a Failure of expansion joint tie rods -- Impact on bellows integrity
|h [electronic resource]
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| 260 |
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|a Washington, D.C. :
|b United States. Dept. of Defense ;
|a Oak Ridge, Tenn. :
|b distributed by the Office of Scientific and Technical Information, U.S. Dept. of Energy,
|c 1992.
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| 300 |
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|a Pages: (10 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 01/01/1992.
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| 500 |
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|a "wsrc-ms-92-239"
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| 500 |
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|a "DE93007453"
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| 500 |
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|a Miller, R.F.; Daugherty, W.L.
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| 520 |
3 |
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|a Expansion joints are used in piping systems to accomodate pipe deflections during service and to facilitate fitup. Often, tie rods are employed to limit the range of axial deflection. Additional restraint against excessive displacement can be provided by the surrounding pipe and associated supports. This paper presents a methodology that was employed to estimate the consequences of tie rod failure. Of particular interest is whether tie rod failure can lead to sufficient displacement as to cause bellows rupture.
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| 536 |
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|b AC09-89SR18035.
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| 650 |
|
7 |
|a Special Production Reactors.
|2 local.
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| 650 |
|
7 |
|a K Reactor.
|2 local.
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| 650 |
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|a Joints.
|2 local.
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| 650 |
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7 |
|a A Codes.
|2 local.
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| 650 |
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7 |
|a Cooling Systems.
|2 local.
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| 650 |
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7 |
|a Reactors.
|2 local.
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| 650 |
|
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|a Reliability.
|2 local.
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| 650 |
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7 |
|a Mechanical Structures.
|2 local.
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| 650 |
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7 |
|a Stresses.
|2 local.
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| 650 |
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7 |
|a Production Reactors.
|2 local.
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| 650 |
|
7 |
|a Pipes.
|2 local.
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| 650 |
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7 |
|a Expansion Joints.
|2 local.
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| 650 |
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|a Failures.
|2 local.
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| 650 |
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|a Bellows.
|2 local.
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| 650 |
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|a Heavy Water Moderated Reactors.
|2 local.
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| 650 |
|
7 |
|a Reactor Components.
|2 local.
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| 650 |
|
7 |
|a Thermal Stresses.
|2 local.
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| 650 |
|
7 |
|a Computer Codes.
|2 local.
|
| 650 |
|
7 |
|a Reactor Cooling Systems.
|2 local.
|
| 650 |
|
7 |
|a Specific Nuclear Reactors And Associated Plants.
|2 edbsc.
|
| 710 |
2 |
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|a Westinghouse Savannah River Company.
|4 res.
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| 710 |
1 |
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|a United States.
|b Department of Defense.
|4 spn.
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| 710 |
1 |
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|a United States.
|b Department of Energy.
|4 spn.
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| 710 |
1 |
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|a United States.
|b Department of Energy.
|b Savannah River Site.
|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.
|
| 856 |
4 |
0 |
|u http://www.osti.gov/servlets/purl/6723753-3pEDF9/
|z Online Access
|
| 907 |
|
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|a .b59705425
|b 03-06-23
|c 05-26-10
|
| 998 |
|
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|a web
|b 05-26-10
|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 ed5afbc8-e6e0-5391-b8ed-824a66ca7a6c
|s ce4b9214-e1cd-5297-b4fd-8124f9c9d35e
|
| 952 |
f |
f |
|p Can circulate
|a University of Colorado Boulder
|b Online
|c Online
|d Online
|e E 1.99:wsrc-ms-92-239
|h Superintendent of Documents classification
|i web
|n 1
|
