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|a (TOE)ost5761557
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|a (TOE)5761557
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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 21
|2 edbsc
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|a E 1.99: conf-810606--110
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|a E 1.99:bnl-nureg--28999
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|a E 1.99: conf-810606--110
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|a conf-810606--110
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|a bnl-nureg--28999
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|a Effect of pressure and flow on the BWR rod drop accident
|h [electronic resource]
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| 260 |
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|a Washington, D.C. :
|b United States. Department of Energy. ;
|a Oak Ridge, Tenn. :
|b distributed by the Office of Scientific and Technical Information, U.S. Department of Energy,
|c 1981.
|
| 300 |
|
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|a Pages: 5 :
|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 SciTech Connect.
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| 500 |
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|a 01/01/1981.
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| 500 |
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|a "bnl-nureg--28999"
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| 500 |
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|a " conf-810606--110"
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| 500 |
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|a "TI85004758"
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| 500 |
|
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|a American Nuclear Society's annual meeting, Miami Beach, FL, USA, 7 Jun 1981.
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| 500 |
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|a Cheng, H. S.; Diamond, D. J.; Lu, M. S.
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| 520 |
3 |
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|a This paper has calculated the pressure rise and inlet flow variation during a rod drop accident. Results show that the effect of these parameters tends to increase the calculated peak fuel enthalpy. Nevertheless, it is clear that the moderator feedback still has a strong inherent mitigating effect on the transient, and the effect of pressure and flow on the RDA is, in this sense, of second order.
|
| 536 |
|
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|b AC02-76CH00016.
|
| 650 |
|
7 |
|a Bwr Type Reactors.
|2 local.
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| 650 |
|
7 |
|a Rod Drop Accidents.
|2 local.
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| 650 |
|
7 |
|a Feedback.
|2 local.
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| 650 |
|
7 |
|a Fluid Flow.
|2 local.
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| 650 |
|
7 |
|a Pressurizing.
|2 local.
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| 650 |
|
7 |
|a Accidents.
|2 local.
|
| 650 |
|
7 |
|a Reactivity.
|2 local.
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| 650 |
|
7 |
|a Reactivity Insertions.
|2 local.
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| 650 |
|
7 |
|a Reactor Accidents.
|2 local.
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| 650 |
|
7 |
|a Reactors.
|2 local.
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| 650 |
|
7 |
|a Water Cooled Reactors.
|2 local.
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| 650 |
|
7 |
|a Water Moderated Reactors.
|2 local.
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| 650 |
|
7 |
|a General Studies Of Nuclear Reactors.
|2 edbsc.
|
| 650 |
|
7 |
|a Specific Nuclear Reactors And Associated Plants.
|2 edbsc.
|
| 700 |
1 |
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|a Cheng, H. S.
|4 aut.
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| 700 |
1 |
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|a Diamond, D. J.
|4 aut.
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| 700 |
1 |
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|a Lu, M. S.
|4 aut.
|
| 710 |
2 |
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|a Brookhaven National Laboratory.
|4 res.
|
| 710 |
1 |
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|a United States.
|b Department of Energy.
|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.
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| 856 |
4 |
0 |
|u http://www.osti.gov/servlets/purl/5761557/
|z Online Access
|
| 907 |
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|a .b80948443
|b 03-08-23
|c 08-04-15
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| 998 |
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|a web
|b 08-04-15
|c f
|d m
|e p
|f eng
|g
|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 4308ef8e-065f-50cd-8404-5fbfe55a31f9
|s 7a5a5572-fa12-543f-8737-fef4e9966591
|
| 952 |
f |
f |
|p Can circulate
|a University of Colorado Boulder
|b Online
|c Online
|d Online
|e E 1.99: conf-810606--110
|h Superintendent of Documents classification
|i web
|n 1
|
