Thermal-hydraulic simulation of natural convection decay heat removal in the High Flux Isotope Reactor (HFIR) using RELAP5 and TEMPEST [electronic resource] : Part 2, Interpretation and validation of results.
The RELAP5/MOD2 code was used to predict the thermal-hydraulic behavior of the HFIR core during decay heat removal through boiling natural circulation. The low system pressure and low mass flux values associated with boiling natural circulation are far from conditions for which RELAP5 is well exerci...
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Online Access |
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| Format: | Government Document Electronic eBook |
| Language: | English |
| Published: |
Oak Ridge, Tenn. : Oak Ridge, Tenn. :
Oak Ridge National Laboratory. ; distributed by the Office of Scientific and Technical Information, U.S. Dept. of Energy,
1989.
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| Subjects: |
MARC
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| 086 | 0 | |a E 1.99:conf-890173-1 | |
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| 245 | 0 | 0 | |a Thermal-hydraulic simulation of natural convection decay heat removal in the High Flux Isotope Reactor (HFIR) using RELAP5 and TEMPEST |h [electronic resource] : |b Part 2, Interpretation and validation of results. |
| 260 | |a Oak Ridge, Tenn. : |b Oak Ridge National Laboratory. ; |a Oak Ridge, Tenn. : |b distributed by the Office of Scientific and Technical Information, U.S. Dept. of Energy, |c 1989. | ||
| 300 | |a Pages: 8 : |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 the Information Bridge: DOE Scientific and Technical Information. | ||
| 500 | |a 01/01/1989. | ||
| 500 | |a "conf-890173-1" | ||
| 500 | |a "DE89006415" | ||
| 500 | |a RELAPS users seminar, College Station, TX, USA, 31 Jan 1989. | ||
| 500 | |a Morris, D.G.; Ruggles, A.E. | ||
| 520 | 3 | |a The RELAP5/MOD2 code was used to predict the thermal-hydraulic behavior of the HFIR core during decay heat removal through boiling natural circulation. The low system pressure and low mass flux values associated with boiling natural circulation are far from conditions for which RELAP5 is well exercised. Therefore, some simple hand calculations are used herein to establish the physics of the results. The interpretation and validation effort is divided between the time average flow conditions and the time varying flow conditions. The time average flow conditions are evaluated using a lumped parameter model and heat balance. The Martinelli-Nelson correlations are used to model the two-phase pressure drop and void fraction vs flow quality relationship within the core region. Systems of parallel channels are susceptible to both density wave oscillations and pressure drop oscillations. Periodic variations in the mass flux and exit flow quality of individual core channels are predicted by RELAP5. These oscillations are consistent with those observed experimentally and are of the density wave type. The impact of the time varying flow properties on local wall superheat is bounded herein. The conditions necessary for Ledinegg flow excursions are identified. These conditions do not fall within the envelope of decay heat levels relevant to HFIR in boiling natural circulation. 14 refs., 5 figs., 1 tab. | |
| 536 | |b AC05-84OR21400. | ||
| 650 | 7 | |a Hydraulics. |2 local. | |
| 650 | 7 | |a Test Reactors. |2 local. | |
| 650 | 7 | |a Mass Transfer. |2 local. | |
| 650 | 7 | |a Water Moderated Reactors. |2 local. | |
| 650 | 7 | |a Computerized Simulation. |2 local. | |
| 650 | 7 | |a Hfir Reactor. |2 local. | |
| 650 | 7 | |a Isotope Production Reactors. |2 local. | |
| 650 | 7 | |a Fluid Flow. |2 local. | |
| 650 | 7 | |a Simulation. |2 local. | |
| 650 | 7 | |a Equations. |2 local. | |
| 650 | 7 | |a Research And Test Reactors. |2 local. | |
| 650 | 7 | |a After-heat Removal. |2 local. | |
| 650 | 7 | |a Energy Transfer. |2 local. | |
| 650 | 7 | |a Mechanics. |2 local. | |
| 650 | 7 | |a Computer Codes. |2 local. | |
| 650 | 7 | |a Thermal Reactors. |2 local. | |
| 650 | 7 | |a Fluid Mechanics. |2 local. | |
| 650 | 7 | |a Tank Type Reactors. |2 local. | |
| 650 | 7 | |a Water Cooled Reactors. |2 local. | |
| 650 | 7 | |a Reactors. |2 local. | |
| 650 | 7 | |a Enriched Uranium Reactors. |2 local. | |
| 650 | 7 | |a R Codes. |2 local. | |
| 650 | 7 | |a Irradiation Reactors. |2 local. | |
| 650 | 7 | |a Removal. |2 local. | |
| 650 | 7 | |a Heat Transfer. |2 local. | |
| 650 | 7 | |a Pressure Drop. |2 local. | |
| 650 | 7 | |a Research Reactors. |2 local. | |
| 650 | 7 | |a Specific Nuclear Reactors And Associated Plants. |2 edbsc. | |
| 710 | 2 | |a Oak Ridge 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/6422715-Ky2HSL/ |z Online Access |
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