Preliminary Design Study of Medium Sized Gas Cooled Fast Reactor with Natural Uranium as Fuel Cycle Input
In this study a feasibility design study of medium sized (1000 MWt) gas cooled fast reactors which can utilize natural uranium as fuel cycle input has been conducted. Gas Cooled Fast Reactor (GFR) is among six types of Generation IV Nuclear Power Plants. GFR with its hard neuron spectrum is superior...
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| Veröffentlicht in: | AIP conference proceedings 2010-06, Vol.1244 (1) |
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| creator | Meriyanti Su'ud, Zaki Rijal, K. Zuhair Ferhat, A. Sekimoto, H. |
| description | In this study a feasibility design study of medium sized (1000 MWt) gas cooled fast reactors which can utilize natural uranium as fuel cycle input has been conducted. Gas Cooled Fast Reactor (GFR) is among six types of Generation IV Nuclear Power Plants. GFR with its hard neuron spectrum is superior for closed fuel cycle, and its ability to be operated in high temperature (850° C) makes various options of utilizations become possible. To obtain the capability of consuming natural uranium as fuel cycle input, modified CANDLE burn‐up scheme[1–6] is adopted this GFR system by dividing the core into 10 parts of equal volume axially. Due to the limitation of thermal hydraulic aspects, the average power density of the proposed design is selected about 70 W/cc. As an optimization results, a design of 1000 MWt reactors which can be operated 10 years without refueling and fuel shuffling and just need natural uranium as fuel cycle input is discussed. The average discharge burn‐up is about 280 GWd/ton HM. Enough margin for criticality was obtained for this reactor. |
| doi_str_mv | 10.1063/1.4757158 |
| format | Article |
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Gas Cooled Fast Reactor (GFR) is among six types of Generation IV Nuclear Power Plants. GFR with its hard neuron spectrum is superior for closed fuel cycle, and its ability to be operated in high temperature (850° C) makes various options of utilizations become possible. To obtain the capability of consuming natural uranium as fuel cycle input, modified CANDLE burn‐up scheme[1–6] is adopted this GFR system by dividing the core into 10 parts of equal volume axially. Due to the limitation of thermal hydraulic aspects, the average power density of the proposed design is selected about 70 W/cc. As an optimization results, a design of 1000 MWt reactors which can be operated 10 years without refueling and fuel shuffling and just need natural uranium as fuel cycle input is discussed. The average discharge burn‐up is about 280 GWd/ton HM. 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Gas Cooled Fast Reactor (GFR) is among six types of Generation IV Nuclear Power Plants. GFR with its hard neuron spectrum is superior for closed fuel cycle, and its ability to be operated in high temperature (850° C) makes various options of utilizations become possible. To obtain the capability of consuming natural uranium as fuel cycle input, modified CANDLE burn‐up scheme[1–6] is adopted this GFR system by dividing the core into 10 parts of equal volume axially. Due to the limitation of thermal hydraulic aspects, the average power density of the proposed design is selected about 70 W/cc. As an optimization results, a design of 1000 MWt reactors which can be operated 10 years without refueling and fuel shuffling and just need natural uranium as fuel cycle input is discussed. The average discharge burn‐up is about 280 GWd/ton HM. Enough margin for criticality was obtained for this reactor.</abstract><cop>United States</cop><doi>10.1063/1.4757158</doi></addata></record> |
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| language | eng |
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| source | AIP Journals Complete |
| subjects | CRITICALITY DESIGN FAST REACTORS FUEL CYCLE GAS COOLED REACTORS MEGAWATT POWER RANGE NATURAL URANIUM NEUTRON SPECTRA NUCLEAR FUELS NUCLEAR POWER NUCLEAR POWER PLANTS OPTIMIZATION POWER DENSITY SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS THERMAL HYDRAULICS |
| title | Preliminary Design Study of Medium Sized Gas Cooled Fast Reactor with Natural Uranium as Fuel Cycle Input |
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