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|a (TOE)ost5745006
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|a E 1.99:conf-910435-79
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|a E 1.99:conf-910435-79
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|a A proposed Regulatory Guide basis for spent fuel decay heat
|h [electronic resource]
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| 260 |
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|a Las Vegas. Nev. :
|b U.S. Department of Energy Yucca Mountain Site Characterization Project ;
|a Oak Ridge, Tenn. :
|b distributed by the Office of Scientific and Technical Information, U.S. Dept. of Energy,
|c 1991.
|
| 300 |
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|a Pages: (9 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 01/01/1991.
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| 500 |
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|a "conf-910435-79"
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| 500 |
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|a "DE91012504"
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| 500 |
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|a 2. annual American Nuclear Society (ANS) international high level radioactive waste management conference, Las Vegas, NV (USA), 28 Apr - 3 May 1991.
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| 500 |
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|a Renier, J.P.; Parks, C.V.; Hermann, O.W.
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| 520 |
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|a A proposed revision to Regulatory Guide 3.54, Spent Fuel Heat Generation in an Independent Spent Fuel Storage Installation'' has been developed for the US Nuclear Regulatory Commission. The proposed revision includes a data base of decay heat rates calculated as a function of burnup, specific power, cooling time, initial fuel ²³⁵U enrichment and assembly type (i.e., PWR or BWR). Validation of the calculational method was done by comparison with existing measured decay heat rates. Procedures for proper use of the data base, adjustment formulae accounting for effects due to differences in operating history and initial enrichment, and a defensible safety factor were derived. 15 refs., 6 tabs.
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| 536 |
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|b AC05-84OR21400.
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| 650 |
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7 |
|a After-heat.
|2 local.
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| 650 |
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7 |
|a Point Beach-2 Reactor.
|2 local.
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| 650 |
|
7 |
|a Water Moderated Reactors.
|2 local.
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| 650 |
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7 |
|a Document Types.
|2 local.
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| 650 |
|
7 |
|a Nuclear Fuels.
|2 local.
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| 650 |
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7 |
|a O Codes.
|2 local.
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| 650 |
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7 |
|a Power Reactors.
|2 local.
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| 650 |
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7 |
|a Fuels.
|2 local.
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| 650 |
|
7 |
|a Regulatory Guides.
|2 local.
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| 650 |
|
7 |
|a Turkey Point-3 Reactor.
|2 local.
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| 650 |
|
7 |
|a Cooper Reactor.
|2 local.
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| 650 |
|
7 |
|a Computer Codes.
|2 local.
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| 650 |
|
7 |
|a Thermal Reactors.
|2 local.
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| 650 |
|
7 |
|a Energy Sources.
|2 local.
|
| 650 |
|
7 |
|a Storage.
|2 local.
|
| 650 |
|
7 |
|a Management.
|2 local.
|
| 650 |
|
7 |
|a Materials.
|2 local.
|
| 650 |
|
7 |
|a Computer Calculations.
|2 local.
|
| 650 |
|
7 |
|a Point Beach-1 Reactor.
|2 local.
|
| 650 |
|
7 |
|a Reactor Materials.
|2 local.
|
| 650 |
|
7 |
|a Water Cooled Reactors.
|2 local.
|
| 650 |
|
7 |
|a Bwr Type Reactors.
|2 local.
|
| 650 |
|
7 |
|a Reactors.
|2 local.
|
| 650 |
|
7 |
|a Enriched Uranium Reactors.
|2 local.
|
| 650 |
|
7 |
|a Data Base Management.
|2 local.
|
| 650 |
|
7 |
|a Spent Fuels.
|2 local.
|
| 650 |
|
7 |
|a Spent Fuel Storage.
|2 local.
|
| 650 |
|
7 |
|a Turkey Point-4 Reactor.
|2 local.
|
| 650 |
|
7 |
|a S Codes.
|2 local.
|
| 650 |
|
7 |
|a Pwr Type Reactors.
|2 local.
|
| 650 |
|
7 |
|a Management Of Radioactive And Non-radioactive Wastes From Nuclear Facilities.
|2 edbsc.
|
| 710 |
2 |
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|a Oak Ridge National Laboratory.
|4 res.
|
| 710 |
2 |
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|a U.S. Department of Energy Yucca Mountain Site Characterization Project.
|4 spn.
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| 710 |
2 |
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|a U.S. Nuclear Regulatory Commission.
|4 spn.
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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/5745006-2IYKXH/
|z Online Access
|
| 907 |
|
|
|a .b59876049
|b 03-06-23
|c 05-27-10
|
| 998 |
|
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|a web
|b 05-27-10
|c f
|d m
|e p
|f eng
|g nvu
|h 2
|i 1
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| 956 |
|
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|a Information bridge
|
| 999 |
f |
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|i 30f2377f-1930-5cfa-ad40-1a510874e93e
|s c0cd82c6-f7d2-5cf0-89e1-5c08969a3b0b
|
| 952 |
f |
f |
|p Can circulate
|a University of Colorado Boulder
|b Online
|c Online
|d Online
|e E 1.99:conf-910435-79
|h Superintendent of Documents classification
|i web
|n 1
|
