RELAP4/MOD6 analysis of forced- and gravity-feed reflood tests [electronic resource]
The RELAP4/MOD6 computer code is used for the analysis of the reactor core heat transfer during the reflooding phase of a postulated loss-of-coolant accident (LOCA) in a pressurized water reactor (PWR). The code requires the user to specify input parameters for the reflood heat transfer models. Resu...
Saved in:
| Online Access: |
Online Access |
|---|---|
| Format: | Government Document Electronic eBook |
| Language: | English |
| Published: |
Washington, D.C. : Oak Ridge, Tenn. :
United States. Department of Energy. ; distributed by the Office of Scientific and Technical Information, U.S. Department of Energy,
1980.
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| Subjects: |
MARC
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| 035 | |a (TOE)5164046 | ||
| 040 | |a TOE |c TOE | ||
| 049 | |a GDWR | ||
| 072 | 7 | |a 22 |2 edbsc | |
| 072 | 7 | |a 21 |2 edbsc | |
| 086 | 0 | |a E 1.99:conf-800723--2 | |
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| 245 | 0 | 0 | |a RELAP4/MOD6 analysis of forced- and gravity-feed reflood tests |h [electronic resource] |
| 260 | |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 1980. | ||
| 300 | |a Pages: 3 : |b digital, PDF file. | ||
| 336 | |a text |b txt |2 rdacontent. | ||
| 337 | |a computer |b c |2 rdamedia. | ||
| 338 | |a online resource |b cr |2 rdacarrier. | ||
| 500 | |a Published through SciTech Connect. | ||
| 500 | |a 01/01/1980. | ||
| 500 | |a "conf-800723--2" | ||
| 500 | |a 19. national heat transfer conference, Orlando, FL, USA, 27 Jul 1980. | ||
| 500 | |a Chen, T. H.; Fletcher, C. D. | ||
| 500 | |a EG and G Idaho, Inc., Idaho Falls (USA) | ||
| 520 | 3 | |a The RELAP4/MOD6 computer code is used for the analysis of the reactor core heat transfer during the reflooding phase of a postulated loss-of-coolant accident (LOCA) in a pressurized water reactor (PWR). The code requires the user to specify input parameters for the reflood heat transfer models. Results of previous comparisons of code calculations with experimental data have indicated no single selection of input parameters is adequate for a spectrum of tests and test facilities. This paper presents the development of revised quidelines and assesses the effect of those modifications on RELAP4/MOD6 data comparisons using previously analyzed reflood experiments. The paper also presents an assessment of the revised guidelines and the original guidelines against experimental data significantly different from previously analyzed tests. | |
| 536 | |b AC07-76ID01570. | ||
| 650 | 7 | |a Loss Of Coolant. |2 local. | |
| 650 | 7 | |a Heat Transfer. |2 local. | |
| 650 | 7 | |a Hydraulics. |2 local. | |
| 650 | 7 | |a Pwr Type Reactors. |2 local. | |
| 650 | 7 | |a Computer Calculations. |2 local. | |
| 650 | 7 | |a Reactor Safety. |2 local. | |
| 650 | 7 | |a Accidents. |2 local. | |
| 650 | 7 | |a Energy Transfer. |2 local. | |
| 650 | 7 | |a Fluid Mechanics. |2 local. | |
| 650 | 7 | |a Reactor Accidents. |2 local. | |
| 650 | 7 | |a Reactors. |2 local. | |
| 650 | 7 | |a Safety. |2 local. | |
| 650 | 7 | |a Mathematical Models. |2 local. | |
| 650 | 7 | |a Water Cooled Reactors. |2 local. | |
| 650 | 7 | |a Mechanics. |2 local. | |
| 650 | 7 | |a Water Moderated Reactors. |2 local. | |
| 650 | 7 | |a General Studies Of Nuclear Reactors. |2 edbsc. | |
| 650 | 7 | |a Specific Nuclear Reactors And Associated Plants. |2 edbsc. | |
| 710 | 1 | |a United States. |b Department of Energy. |4 spn. | |
| 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/5164046/ |z Online Access |
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| 952 | f | f | |p Can circulate |a University of Colorado Boulder |b Online |c Online |d Online |e E 1.99:conf-800723--2 |h Superintendent of Documents classification |i web |n 1 |