Performance analysis of 233U for fixed bed nuclear reactors
Criticality and burn up behavior of the Fixed Bed Nuclear Reactor (FBNR) are investigated for the mixed fuel UO /ThO as an alternative to low enriched UO fuel. CERMET fuel with a zirconium matrix and cladding has been used throughout the study. The main results of the study can be summarized as foll...
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| Veröffentlicht in: | Kerntechnik (1987) 2010-09, Vol.75 (5), p.243-247 |
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| container_title | Kerntechnik (1987) |
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| creator | Şahin, S. Acır, A. Şahin, H. M. |
| description | Criticality and burn up behavior of the Fixed Bed Nuclear Reactor (FBNR) are investigated for the mixed fuel
UO
/ThO
as an alternative to low enriched
UO
fuel. CERMET fuel with a zirconium matrix and cladding has been used throughout the study. The main results of the study can be summarized as follows: Reactor criticality is already achieved by ∼2%
UO
with the mixed
UO
/ThO
fuel. At higher
U fractions, reactor criticality rises rapidly and exceeds k
> 1.5 already by 9%
UO
. With 100%
UO
, start up criticality can reach k
= 2.0975. Time dependent reactor criticality k
and fuel burn up have been investigated for two different mixed fuel
UO
/ThO
compositions, namely: 4%
UO
+ 96% ThO
for a reactor power of 40 MW
(120 MW
) and 9%
UO
+ 91% ThO
for a reactor power of 70 MW
(210 MW
). Sufficient reactor criticality (k
> 1.06) for continuous operation without fuel change can be sustained during ∼5 and 12 years with 4% and 9%
UO
fractions in the mixed fuel, leading to burn ups of ∼36000 and >105000MWD/t, respectively. Thorium based fuel produces no prolific uranium. Plutonium production remains negligible. |
| doi_str_mv | 10.3139/124.110097 |
| format | Article |
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UO
/ThO
as an alternative to low enriched
UO
fuel. CERMET fuel with a zirconium matrix and cladding has been used throughout the study. The main results of the study can be summarized as follows: Reactor criticality is already achieved by ∼2%
UO
with the mixed
UO
/ThO
fuel. At higher
U fractions, reactor criticality rises rapidly and exceeds k
> 1.5 already by 9%
UO
. With 100%
UO
, start up criticality can reach k
= 2.0975. Time dependent reactor criticality k
and fuel burn up have been investigated for two different mixed fuel
UO
/ThO
compositions, namely: 4%
UO
+ 96% ThO
for a reactor power of 40 MW
(120 MW
) and 9%
UO
+ 91% ThO
for a reactor power of 70 MW
(210 MW
). Sufficient reactor criticality (k
> 1.06) for continuous operation without fuel change can be sustained during ∼5 and 12 years with 4% and 9%
UO
fractions in the mixed fuel, leading to burn ups of ∼36000 and >105000MWD/t, respectively. Thorium based fuel produces no prolific uranium. Plutonium production remains negligible.</description><identifier>ISSN: 0932-3902</identifier><identifier>EISSN: 2195-8580</identifier><identifier>DOI: 10.3139/124.110097</identifier><language>eng</language><publisher>De Gruyter</publisher><ispartof>Kerntechnik (1987), 2010-09, Vol.75 (5), p.243-247</ispartof><lds50>peer_reviewed</lds50><woscitedreferencessubscribed>false</woscitedreferencessubscribed></display><links><openurl>$$Topenurl_article</openurl><openurlfulltext>$$Topenurlfull_article</openurlfulltext><thumbnail>$$Tsyndetics_thumb_exl</thumbnail><linktopdf>$$Uhttps://www.degruyter.com/document/doi/10.3139/124.110097/pdf$$EPDF$$P50$$Gwalterdegruyter$$H</linktopdf><linktohtml>$$Uhttps://www.degruyter.com/document/doi/10.3139/124.110097/html$$EHTML$$P50$$Gwalterdegruyter$$H</linktohtml><link.rule.ids>314,780,784,27922,27923,66524,68308</link.rule.ids></links><search><creatorcontrib>Şahin, S.</creatorcontrib><creatorcontrib>Acır, A.</creatorcontrib><creatorcontrib>Şahin, H. M.</creatorcontrib><title>Performance analysis of 233U for fixed bed nuclear reactors</title><title>Kerntechnik (1987)</title><description>Criticality and burn up behavior of the Fixed Bed Nuclear Reactor (FBNR) are investigated for the mixed fuel
UO
/ThO
as an alternative to low enriched
UO
fuel. CERMET fuel with a zirconium matrix and cladding has been used throughout the study. The main results of the study can be summarized as follows: Reactor criticality is already achieved by ∼2%
UO
with the mixed
UO
/ThO
fuel. At higher
U fractions, reactor criticality rises rapidly and exceeds k
> 1.5 already by 9%
UO
. With 100%
UO
, start up criticality can reach k
= 2.0975. Time dependent reactor criticality k
and fuel burn up have been investigated for two different mixed fuel
UO
/ThO
compositions, namely: 4%
UO
+ 96% ThO
for a reactor power of 40 MW
(120 MW
) and 9%
UO
+ 91% ThO
for a reactor power of 70 MW
(210 MW
). Sufficient reactor criticality (k
> 1.06) for continuous operation without fuel change can be sustained during ∼5 and 12 years with 4% and 9%
UO
fractions in the mixed fuel, leading to burn ups of ∼36000 and >105000MWD/t, respectively. Thorium based fuel produces no prolific uranium. Plutonium production remains negligible.</description><issn>0932-3902</issn><issn>2195-8580</issn><fulltext>true</fulltext><rsrctype>article</rsrctype><creationdate>2010</creationdate><recordtype>article</recordtype><sourceid/><recordid>eNqljkEKwjAURIMoWLQbT5ALVH-Sxja4FMWlC12H2CbSEhtIWrS3N6I3cGCYgeF_HkIrAmtGmNgQmq8JARDFBCWUCJ6VvIQpSkAwmjEBdI7SEFqI2tKC55Cg3Vl74_xDdZXGqlN2DE3AzmDK2BXHBZvmpWt8i-6Gymrlsdeq6p0PSzQzygad_nKByuPhsj9lT2V77Wt998MYi2zd4OPrIAnID6mMpPJLWnBOc8b-OH0D-g1IdQ</recordid><startdate>20100901</startdate><enddate>20100901</enddate><creator>Şahin, S.</creator><creator>Acır, A.</creator><creator>Şahin, H. M.</creator><general>De Gruyter</general><scope/></search><sort><creationdate>20100901</creationdate><title>Performance analysis of 233U for fixed bed nuclear reactors</title><author>Şahin, S. ; Acır, A. ; Şahin, H. M.</author></sort><facets><frbrtype>5</frbrtype><frbrgroupid>cdi_FETCH-walterdegruyter_journals_10_3139_124_1100977552433</frbrgroupid><rsrctype>articles</rsrctype><prefilter>articles</prefilter><language>eng</language><creationdate>2010</creationdate><toplevel>peer_reviewed</toplevel><toplevel>online_resources</toplevel><creatorcontrib>Şahin, S.</creatorcontrib><creatorcontrib>Acır, A.</creatorcontrib><creatorcontrib>Şahin, H. M.</creatorcontrib><jtitle>Kerntechnik (1987)</jtitle></facets><delivery><delcategory>Remote Search Resource</delcategory><fulltext>fulltext</fulltext></delivery><addata><au>Şahin, S.</au><au>Acır, A.</au><au>Şahin, H. M.</au><format>journal</format><genre>article</genre><ristype>JOUR</ristype><atitle>Performance analysis of 233U for fixed bed nuclear reactors</atitle><jtitle>Kerntechnik (1987)</jtitle><date>2010-09-01</date><risdate>2010</risdate><volume>75</volume><issue>5</issue><spage>243</spage><epage>247</epage><pages>243-247</pages><issn>0932-3902</issn><eissn>2195-8580</eissn><abstract>Criticality and burn up behavior of the Fixed Bed Nuclear Reactor (FBNR) are investigated for the mixed fuel
UO
/ThO
as an alternative to low enriched
UO
fuel. CERMET fuel with a zirconium matrix and cladding has been used throughout the study. The main results of the study can be summarized as follows: Reactor criticality is already achieved by ∼2%
UO
with the mixed
UO
/ThO
fuel. At higher
U fractions, reactor criticality rises rapidly and exceeds k
> 1.5 already by 9%
UO
. With 100%
UO
, start up criticality can reach k
= 2.0975. Time dependent reactor criticality k
and fuel burn up have been investigated for two different mixed fuel
UO
/ThO
compositions, namely: 4%
UO
+ 96% ThO
for a reactor power of 40 MW
(120 MW
) and 9%
UO
+ 91% ThO
for a reactor power of 70 MW
(210 MW
). Sufficient reactor criticality (k
> 1.06) for continuous operation without fuel change can be sustained during ∼5 and 12 years with 4% and 9%
UO
fractions in the mixed fuel, leading to burn ups of ∼36000 and >105000MWD/t, respectively. Thorium based fuel produces no prolific uranium. Plutonium production remains negligible.</abstract><pub>De Gruyter</pub><doi>10.3139/124.110097</doi><tpages>5</tpages></addata></record> |
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| ispartof | Kerntechnik (1987), 2010-09, Vol.75 (5), p.243-247 |
| issn | 0932-3902 2195-8580 |
| language | eng |
| recordid | cdi_walterdegruyter_journals_10_3139_124_110097755243 |
| source | De Gruyter journals |
| title | Performance analysis of 233U for fixed bed nuclear reactors |
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