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|a (TOE)ost5054838
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|a (TOE)5054838
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|a TOE
|c TOE
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|a GDWR
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|a E 1.99: la-9716-ms
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|a E 1.99:nureg/cr-3224
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|a E 1.99: la-9716-ms
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|a nureg/cr-3224
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|a la-9716-ms
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| 245 |
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|a Assessment of CRBR core disruptive accident energetics
|h [electronic resource]
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| 260 |
|
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|a Los Alamos, N.M. :
|b Los Alamos National Laboratory ;
|a Oak Ridge, Tenn. :
|b distributed by the Office of Scientific and Technical Information, U.S. Dept. of Energy,
|c 1984.
|
| 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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|a Published through the Information Bridge: DOE Scientific and Technical Information.
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| 500 |
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|a 03/01/1984.
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| 500 |
|
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|a "nureg/cr-3224"
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| 500 |
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|a " la-9716-ms"
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| 500 |
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|a "DE84009164"
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| 500 |
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|a Theofanous, T.G.; Bell, C.R.
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| 520 |
3 |
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|a The results of an independent assessment of core disruptive accident energetics for the Clinch River Breeder Reactor are presented in this document. This assessment was performed for the Nuclear Regulatory Commission under the direction of the CRBR Program Office within the Office of Nuclear Reactor Regulation. It considered in detail the accident behavior for three accident initiators that are representative of three different classes of events; unprotected loss of flow, unprotected reactivity insertion, and protected loss of heat sink. The primary system's energetics accommodation capability was realistically, yet conservatively, determined in terms of core events. This accommodation capability was found to be equivalent to an isentropic work potential for expansion to one atmosphere of 2550 MJ or a ramp rate of about 200 $/s applied to a classical two-phase disassembly.
|
| 536 |
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|b W-7405-ENG-36.
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| 650 |
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7 |
|a Safety.
|2 local.
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| 650 |
|
7 |
|a Void Fraction.
|2 local.
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| 650 |
|
7 |
|a Hydraulics.
|2 local.
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| 650 |
|
7 |
|a Criticality.
|2 local.
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| 650 |
|
7 |
|a Reactor Safety.
|2 local.
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| 650 |
|
7 |
|a Liquid Metal Cooled Reactors.
|2 local.
|
| 650 |
|
7 |
|a Lmfbr Type Reactors.
|2 local.
|
| 650 |
|
7 |
|a Sodium Cooled Reactors.
|2 local.
|
| 650 |
|
7 |
|a Power Reactors.
|2 local.
|
| 650 |
|
7 |
|a Mechanics.
|2 local.
|
| 650 |
|
7 |
|a Clinch River Breeder Reactor.
|2 local.
|
| 650 |
|
7 |
|a Reactivity.
|2 local.
|
| 650 |
|
7 |
|a Pressure Gradients.
|2 local.
|
| 650 |
|
7 |
|a Fluid Mechanics.
|2 local.
|
| 650 |
|
7 |
|a Reactor Accidents.
|2 local.
|
| 650 |
|
7 |
|a Breeder Reactors.
|2 local.
|
| 650 |
|
7 |
|a Temperature Distribution.
|2 local.
|
| 650 |
|
7 |
|a Computer Calculations.
|2 local.
|
| 650 |
|
7 |
|a Epithermal Reactors.
|2 local.
|
| 650 |
|
7 |
|a Reactors.
|2 local.
|
| 650 |
|
7 |
|a Reactor Core Disruption.
|2 local.
|
| 650 |
|
7 |
|a Fbr Type Reactors.
|2 local.
|
| 650 |
|
7 |
|a Fast Reactors.
|2 local.
|
| 650 |
|
7 |
|a Temperature Gradients.
|2 local.
|
| 650 |
|
7 |
|a Accidents.
|2 local.
|
| 650 |
|
7 |
|a General Studies Of Nuclear Reactors.
|2 edbsc.
|
| 650 |
|
7 |
|a Specific Nuclear Reactors And Associated Plants.
|2 edbsc.
|
| 710 |
2 |
|
|a Los Alamos 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/5054838-06LkBl/
|z Online Access
|
| 907 |
|
|
|a .b73037163
|b 03-07-23
|c 02-11-13
|
| 998 |
|
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|a web
|b 02-11-13
|c f
|d m
|e p
|f eng
|g nmu
|h 0
|i 1
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| 956 |
|
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|a Information bridge
|
| 999 |
f |
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|i 5bd7ef38-034d-55c7-b00d-9a184c7228fa
|s a424aebb-cf04-5141-ac44-bc0ffcf714a6
|
| 952 |
f |
f |
|p Can circulate
|a University of Colorado Boulder
|b Online
|c Online
|d Online
|e E 1.99: la-9716-ms
|h Superintendent of Documents classification
|i web
|n 1
|
