Sensitivity Evaluation of the Daily Thermal Predictions of the AGR-1 Experiment in the Advanced Test Reactor [electronic resource]
A temperature sensitivity evaluation has been performed for the AGR-1 fuel experiment on an individual capsule. A series of cases were compared to a base case by varying different input parameters into the ABAQUS finite element thermal model. These input parameters were varied by ±10% to show the te...
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Online Access (via OSTI) |
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| Format: | Government Document Electronic eBook |
| Language: | English |
| Published: |
Washington, D.C. : Oak Ridge, Tenn. :
United States. Office of the Assistant Secretary for Nuclear Energy ; distributed by the Office of Scientific and Technical Information, U.S. Department of Energy,
2011.
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| Subjects: |
MARC
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| 245 | 0 | 0 | |a Sensitivity Evaluation of the Daily Thermal Predictions of the AGR-1 Experiment in the Advanced Test Reactor |h [electronic resource] |
| 260 | |a Washington, D.C. : |b United States. Office of the Assistant Secretary for Nuclear Energy ; |a Oak Ridge, Tenn. : |b distributed by the Office of Scientific and Technical Information, U.S. Department of Energy, |c 2011. | ||
| 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 05/01/2011. | ||
| 500 | |a "inl/con-10-20743" | ||
| 500 | |a ICAPP 2011 (International Congress on Advances in Nuclear Power Plants),Nice, France,05/02/2011,05/05/2011. | ||
| 500 | |a Grant Hawkes; James Sterbentz; John Maki. | ||
| 520 | 3 | |a A temperature sensitivity evaluation has been performed for the AGR-1 fuel experiment on an individual capsule. A series of cases were compared to a base case by varying different input parameters into the ABAQUS finite element thermal model. These input parameters were varied by ±10% to show the temperature sensitivity to each parameter. The most sensitive parameters are the outer control gap distance, heat rate in the fuel compacts, and neon gas fraction. Thermal conductivity of the compacts and graphite holder were in the middle of the list for sensitivity. The smallest effects were for the emissivities of the stainless steel, graphite, and thru tubes. Sensitivity calculations were also performed varying with fluence. These calculations showed a general temperature rise with an increase in fluence. This is a result of the thermal conductivity of the fuel compacts and graphite holder decreasing with fluence. | |
| 520 | 0 | |a Agr-1; Thermal Analysis; Thermal Sensitivity; Triso Fuel; Vhtr + Tdo. | |
| 536 | |b DE-AC07-05ID14517. | ||
| 650 | 7 | |a Evaluation. |2 local. | |
| 650 | 7 | |a Graphite. |2 local. | |
| 650 | 7 | |a Heat Rate. |2 local. | |
| 650 | 7 | |a Neon. |2 local. | |
| 650 | 7 | |a Nuclear Power Plants. |2 local. | |
| 650 | 7 | |a Sensitivity. |2 local. | |
| 650 | 7 | |a Test Reactors. |2 local. | |
| 650 | 7 | |a Stainless Steels. |2 local. | |
| 650 | 7 | |a Thermal Conductivity. |2 local. | |
| 650 | 7 | |a Nuclear Fuel Cycle And Fuel Materials. |2 edbsc. | |
| 710 | 2 | |a Idaho National Laboratory. |4 res. | |
| 710 | 1 | |a United States. |b Office of the Assistant Secretary for Nuclear 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/scitech/biblio/1023456 |z Online Access (via OSTI) |
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