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|a (TOE)ost114652
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|a (TOE)114652
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|a TOE
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|a GDWR
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|a 22
|2 edbsc
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|a E 1.99:CONF-950914--7
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|a E 1.99:INEL--95/00381
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|a E 1.99:CONF-950914--7
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|a INEL--95/00381
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|a CONF-950914--7
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| 088 |
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|a DE96001617
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| 245 |
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|a Parameter uncertainty for ASP models
|h [electronic resource]
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| 260 |
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|a Idaho Falls, Idaho :
|b Idaho National Engineering and Environmental Laboratory ;
|a Oak Ridge, Tenn. :
|b distributed by the Office of Scientific and Technical Information, U.S. Dept. of Energy,
|c 1995.
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| 300 |
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|a 6 p.
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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 10/01/1995.
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| 500 |
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|a "INEL--95/00381"
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| 500 |
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|a "CONF-950914--7"
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| 500 |
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|a "DE96001617"
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| 500 |
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|a American Nuclear Society international topical conference on the safety of operating reactors, Seattle, WA (United States), 17-23 Sep 1995.
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| 500 |
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|a Smith, C.L.; Knudsen, J.K.
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| 500 |
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|a Lockheed Idaho Technologies Co., Idaho Falls, ID (United States)
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| 500 |
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|a Nuclear Regulatory Commission, Washington, DC (United States)
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| 520 |
3 |
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|a The steps involved to incorporate parameter uncertainty into the Nuclear Regulatory Commission (NRC) accident sequence precursor (ASP) models is covered in this paper. Three different uncertainty distributions (i.e., lognormal, beta, gamma) were evaluated to Determine the most appropriate distribution. From the evaluation, it was Determined that the lognormal distribution will be used for the ASP models uncertainty parameters. Selection of the uncertainty parameters for the basic events is also discussed. This paper covers the process of determining uncertainty parameters for the supercomponent basic events (i.e., basic events that are comprised of more than one component which can have more than one failure mode) that are utilized in the ASP models. Once this is completed, the ASP model is ready to be utilized to propagate parameter uncertainty for event assessments.
|
| 536 |
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|b AC07-94ID13223.
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| 650 |
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7 |
|a Nuclear Power Plants.
|2 local.
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| 650 |
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7 |
|a Accidents.
|2 local.
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| 650 |
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7 |
|a Reactor Components.
|2 local.
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| 650 |
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7 |
|a Failure Mode Analysis.
|2 local.
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| 650 |
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7 |
|a Data Covariances.
|2 local.
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| 650 |
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7 |
|a Precursor.
|2 local.
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| 650 |
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7 |
|a Reactor Safety.
|2 local.
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| 650 |
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7 |
|a Failures.
|2 local.
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| 650 |
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7 |
|a Distribution Functions.
|2 local.
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| 650 |
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7 |
|a S Codes.
|2 local.
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| 650 |
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7 |
|a A Codes.
|2 local.
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| 650 |
|
7 |
|a Nuclear Reactor Technology ;99 Mathematics, Computers, Information Science, Management, Law, Miscellaneous.
|2 edbsc.
|
| 710 |
2 |
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|a Idaho National Engineering and Environmental Laboratory.
|4 res.
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| 710 |
2 |
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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/114652-qCf4Sy/webviewable/
|z Online Access
|
| 907 |
|
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|a .b56636726
|b 03-06-23
|c 12-20-09
|
| 998 |
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|a web
|b 12-20-09
|c f
|d m
|e p
|f eng
|g idu
|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 b5bb2154-e081-5283-bc62-ef90f9be4732
|s 0b8af070-f40d-5e9c-8858-493217b750aa
|
| 952 |
f |
f |
|p Can circulate
|a University of Colorado Boulder
|b Online
|c Online
|d Online
|e E 1.99:CONF-950914--7
|h Superintendent of Documents classification
|i web
|n 1
|
