Preliminary Design Study of Medium Sized Gas Cooled Fast Reactor with Natural Uranium as Fuel Cycle Input
In this study a fesibility 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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| creator | Meriyanti Su’ud, Zaki Rijal, K. Zuhair Ferhat, A. Sekimoto, H. |
| description | In this study a fesibility 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 criticallity was obtained for this
reactor. |
| doi_str_mv | 10.1063/1.4757158 |
| format | Conference Proceeding |
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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 criticallity was obtained for this
reactor.</description><identifier>ISSN: 0094-243X</identifier><identifier>EISSN: 1551-7616</identifier><identifier>DOI: 10.1063/1.4757158</identifier><identifier>CODEN: APCPCS</identifier><language>eng</language><publisher>United States</publisher><subject>ACTINIDES ; BURNUP ; COOLANTS ; ELEMENTS ; ENERGY SOURCES ; EPITHERMAL REACTORS ; FAST REACTORS ; FISSION ; FUEL CYCLE ; FUELS ; GAS COOLED REACTORS ; MATERIALS ; METALS ; NATURAL URANIUM ; NUCLEAR FACILITIES ; NUCLEAR FUELS ; NUCLEAR POWER PLANTS ; NUCLEAR REACTIONS ; OPTIMIZATION ; POWER DENSITY ; POWER PLANTS ; REACTOR FUELING ; REACTOR MATERIALS ; REACTORS ; SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS ; SPECTRA ; THERMAL POWER PLANTS ; URANIUM</subject><ispartof>AIP Conference Proceedings, 2010, Vol.1244 (1), p.62-69</ispartof><rights>American Institute of Physics</rights><lds50>peer_reviewed</lds50><woscitedreferencessubscribed>false</woscitedreferencessubscribed></display><links><openurl>$$Topenurl_article</openurl><openurlfulltext>$$Topenurlfull_article</openurlfulltext><thumbnail>$$Tsyndetics_thumb_exl</thumbnail><linktohtml>$$Uhttps://pubs.aip.org/acp/article-lookup/doi/10.1063/1.4757158$$EHTML$$P50$$Gscitation$$H</linktohtml><link.rule.ids>230,309,310,314,776,780,785,786,790,881,4498,23909,23910,25118,27901,27902,76127</link.rule.ids><backlink>$$Uhttps://www.osti.gov/biblio/21410506$$D View this record in Osti.gov$$Hfree_for_read</backlink></links><search><contributor>Su’ud, Zaki</contributor><contributor>Waris, A.</contributor><creatorcontrib>Meriyanti</creatorcontrib><creatorcontrib>Su’ud, Zaki</creatorcontrib><creatorcontrib>Rijal, K.</creatorcontrib><creatorcontrib>Zuhair</creatorcontrib><creatorcontrib>Ferhat, A.</creatorcontrib><creatorcontrib>Sekimoto, H.</creatorcontrib><title>Preliminary Design Study of Medium Sized Gas Cooled Fast Reactor with Natural Uranium as Fuel Cycle Input</title><title>AIP Conference Proceedings</title><description>In this study a fesibility 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 criticallity was obtained for this
reactor.</description><subject>ACTINIDES</subject><subject>BURNUP</subject><subject>COOLANTS</subject><subject>ELEMENTS</subject><subject>ENERGY SOURCES</subject><subject>EPITHERMAL REACTORS</subject><subject>FAST REACTORS</subject><subject>FISSION</subject><subject>FUEL CYCLE</subject><subject>FUELS</subject><subject>GAS COOLED REACTORS</subject><subject>MATERIALS</subject><subject>METALS</subject><subject>NATURAL URANIUM</subject><subject>NUCLEAR FACILITIES</subject><subject>NUCLEAR FUELS</subject><subject>NUCLEAR POWER PLANTS</subject><subject>NUCLEAR REACTIONS</subject><subject>OPTIMIZATION</subject><subject>POWER DENSITY</subject><subject>POWER PLANTS</subject><subject>REACTOR FUELING</subject><subject>REACTOR MATERIALS</subject><subject>REACTORS</subject><subject>SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS</subject><subject>SPECTRA</subject><subject>THERMAL POWER PLANTS</subject><subject>URANIUM</subject><issn>0094-243X</issn><issn>1551-7616</issn><fulltext>true</fulltext><rsrctype>conference_proceeding</rsrctype><creationdate>2010</creationdate><recordtype>conference_proceeding</recordtype><recordid>eNp9kE9LwzAchoMoOKcHv0HAm9CZNP_ao1Q7B_MPzoG3kCapi3TNaFJlfno7NvDm7_L-Ds_7Hh4ALjGaYMTJDZ5QwQRm2REYYcZwIjjmx2CEUE6TlJL3U3AWwidCaS5ENgLupbONW7tWdVt4Z4P7aOEi9mYLfQ0frXH9Gi7cjzVwqgIsvG-Gt1QhwlerdPQd_HZxBZ9U7DvVwGWn2l1lYMveNrDY6sbCWbvp4zk4qVUT7MUhx2BZ3r8VD8n8eTorbueJTxmJiRUa5YRojrBKqagywjQlIlU0I7TOmBC0IqwS1IjccJ4PxzMiGEs5rkxuyBhc7Xd9iE4G7aLVK-3b1uooU0wxYoOoMbjeUztARedbuencerAgMZI7lRLLg8r_4C_f_YFyY2ryC6yecsU</recordid><startdate>20100622</startdate><enddate>20100622</enddate><creator>Meriyanti</creator><creator>Su’ud, Zaki</creator><creator>Rijal, K.</creator><creator>Zuhair</creator><creator>Ferhat, A.</creator><creator>Sekimoto, H.</creator><scope>OTOTI</scope></search><sort><creationdate>20100622</creationdate><title>Preliminary Design Study of Medium Sized Gas Cooled Fast Reactor with Natural Uranium as Fuel Cycle Input</title><author>Meriyanti ; Su’ud, Zaki ; Rijal, K. ; Zuhair ; Ferhat, A. ; Sekimoto, H.</author></sort><facets><frbrtype>5</frbrtype><frbrgroupid>cdi_FETCH-LOGICAL-o253t-e7c0933c601a247b835c4372a4834f85774b35b74d79d669999683755261bd9d3</frbrgroupid><rsrctype>conference_proceedings</rsrctype><prefilter>conference_proceedings</prefilter><language>eng</language><creationdate>2010</creationdate><topic>ACTINIDES</topic><topic>BURNUP</topic><topic>COOLANTS</topic><topic>ELEMENTS</topic><topic>ENERGY SOURCES</topic><topic>EPITHERMAL REACTORS</topic><topic>FAST REACTORS</topic><topic>FISSION</topic><topic>FUEL CYCLE</topic><topic>FUELS</topic><topic>GAS COOLED REACTORS</topic><topic>MATERIALS</topic><topic>METALS</topic><topic>NATURAL URANIUM</topic><topic>NUCLEAR FACILITIES</topic><topic>NUCLEAR FUELS</topic><topic>NUCLEAR POWER PLANTS</topic><topic>NUCLEAR REACTIONS</topic><topic>OPTIMIZATION</topic><topic>POWER DENSITY</topic><topic>POWER PLANTS</topic><topic>REACTOR FUELING</topic><topic>REACTOR MATERIALS</topic><topic>REACTORS</topic><topic>SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS</topic><topic>SPECTRA</topic><topic>THERMAL POWER PLANTS</topic><topic>URANIUM</topic><toplevel>peer_reviewed</toplevel><toplevel>online_resources</toplevel><creatorcontrib>Meriyanti</creatorcontrib><creatorcontrib>Su’ud, Zaki</creatorcontrib><creatorcontrib>Rijal, K.</creatorcontrib><creatorcontrib>Zuhair</creatorcontrib><creatorcontrib>Ferhat, A.</creatorcontrib><creatorcontrib>Sekimoto, H.</creatorcontrib><collection>OSTI.GOV</collection></facets><delivery><delcategory>Remote Search Resource</delcategory><fulltext>fulltext</fulltext></delivery><addata><au>Meriyanti</au><au>Su’ud, Zaki</au><au>Rijal, K.</au><au>Zuhair</au><au>Ferhat, A.</au><au>Sekimoto, H.</au><au>Su’ud, Zaki</au><au>Waris, A.</au><format>book</format><genre>proceeding</genre><ristype>CONF</ristype><atitle>Preliminary Design Study of Medium Sized Gas Cooled Fast Reactor with Natural Uranium as Fuel Cycle Input</atitle><btitle>AIP Conference Proceedings</btitle><date>2010-06-22</date><risdate>2010</risdate><volume>1244</volume><issue>1</issue><spage>62</spage><epage>69</epage><pages>62-69</pages><issn>0094-243X</issn><eissn>1551-7616</eissn><coden>APCPCS</coden><abstract>In this study a fesibility 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 criticallity was obtained for this
reactor.</abstract><cop>United States</cop><doi>10.1063/1.4757158</doi><tpages>8</tpages></addata></record> |
| fulltext | fulltext |
| identifier | ISSN: 0094-243X |
| ispartof | AIP Conference Proceedings, 2010, Vol.1244 (1), p.62-69 |
| issn | 0094-243X 1551-7616 |
| language | eng |
| recordid | cdi_scitation_primary_10_1063_1_4757158 |
| source | AIP Journals Complete |
| subjects | ACTINIDES BURNUP COOLANTS ELEMENTS ENERGY SOURCES EPITHERMAL REACTORS FAST REACTORS FISSION FUEL CYCLE FUELS GAS COOLED REACTORS MATERIALS METALS NATURAL URANIUM NUCLEAR FACILITIES NUCLEAR FUELS NUCLEAR POWER PLANTS NUCLEAR REACTIONS OPTIMIZATION POWER DENSITY POWER PLANTS REACTOR FUELING REACTOR MATERIALS REACTORS SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS SPECTRA THERMAL POWER PLANTS URANIUM |
| title | Preliminary Design Study of Medium Sized Gas Cooled Fast Reactor with Natural Uranium as Fuel Cycle Input |
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