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|a (TOE)ost6775757
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|a (TOE)6775757
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|a TOE
|c TOE
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|a GDWR
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|a 22
|2 edbsc
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|a E 1.99:ornl/csd/tm-189
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|a E 1.99:ornl/csd/tm-189
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| 245 |
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|a SURE
|h [electronic resource] :
|b a system of computer codes for performing sensitivity/uncertainty analyses with the RELAP code. [PWR]
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| 260 |
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|a Oak Ridge, Tenn. :
|b Oak Ridge National Laboratory. ;
|a Oak Ridge, Tenn. :
|b distributed by the Office of Scientific and Technical Information, U.S. Dept. of Energy,
|c 1983.
|
| 300 |
|
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|a Pages: 60 :
|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 02/01/1983.
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| 500 |
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|a "ornl/csd/tm-189"
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| 500 |
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|a "DE83006633"
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| 500 |
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|a Bjerke, M.A.
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| 520 |
3 |
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|a A package of computer codes has been developed to perform a nonlinear uncertainty analysis on transient thermal-hydraulic systems which are modeled with the RELAP computer code. Using an uncertainty around the analyses of experiments in the PWR-BDHT Separate Effects Program at Oak Ridge National Laboratory. The use of FORTRAN programs running interactively on the PDP-10 computer has made the system very easy to use and provided great flexibility in the choice of processing paths. Several experiments simulating a loss-of-coolant accident in a nuclear reactor have been successfully analyzed. It has been shown that the system can be automated easily to further simplify its use and that the conversion of the entire system to a base code other than RELAP is possible.
|
| 536 |
|
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|b W-7405-ENG-26.
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| 650 |
|
7 |
|a Safety.
|2 local.
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| 650 |
|
7 |
|a Hydraulics.
|2 local.
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| 650 |
|
7 |
|a Water Moderated Reactors.
|2 local.
|
| 650 |
|
7 |
|a Water Cooled Reactors.
|2 local.
|
| 650 |
|
7 |
|a Reactors.
|2 local.
|
| 650 |
|
7 |
|a Reactor Safety.
|2 local.
|
| 650 |
|
7 |
|a R Codes.
|2 local.
|
| 650 |
|
7 |
|a Heat Transfer.
|2 local.
|
| 650 |
|
7 |
|a Energy Transfer.
|2 local.
|
| 650 |
|
7 |
|a Mechanics.
|2 local.
|
| 650 |
|
7 |
|a Loss Of Coolant.
|2 local.
|
| 650 |
|
7 |
|a Pwr Type Reactors.
|2 local.
|
| 650 |
|
7 |
|a Computer Codes.
|2 local.
|
| 650 |
|
7 |
|a Accidents.
|2 local.
|
| 650 |
|
7 |
|a Fluid Mechanics.
|2 local.
|
| 650 |
|
7 |
|a Reactor Accidents.
|2 local.
|
| 650 |
|
7 |
|a General Studies Of Nuclear Reactors.
|2 edbsc.
|
| 710 |
2 |
|
|a Oak Ridge National Laboratory.
|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/6775757-06X6ja/
|z Online Access
|
| 907 |
|
|
|a .b60022280
|b 03-06-23
|c 05-30-10
|
| 998 |
|
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|a web
|b 05-30-10
|c f
|d m
|e p
|f eng
|g tnu
|h 0
|i 1
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| 956 |
|
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|a Information bridge
|
| 999 |
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|i 89f3cd8d-16a1-5ea6-9f34-54997e542f35
|s c175fb06-4f5f-518a-adfb-56c75b65fb05
|
| 952 |
f |
f |
|p Can circulate
|a University of Colorado Boulder
|b Online
|c Online
|d Online
|e E 1.99:ornl/csd/tm-189
|h Superintendent of Documents classification
|i web
|n 1
|
