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Advanced micro-reactor concepts
Nuclear power systems capable of outputting low powers (
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| Published in: | Progress in nuclear energy (New series) 2018-08, Vol.107, p.61-70 |
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| Main Authors: | , , |
| Format: | Article |
| Language: | English |
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| cited_by | cdi_FETCH-LOGICAL-c337t-91487abf1360ec4a2a76bfc4299c39c401ea5014bc7cddcf3b661cc438718d533 |
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| cites | cdi_FETCH-LOGICAL-c337t-91487abf1360ec4a2a76bfc4299c39c401ea5014bc7cddcf3b661cc438718d533 |
| container_end_page | 70 |
| container_issue | |
| container_start_page | 61 |
| container_title | Progress in nuclear energy (New series) |
| container_volume | 107 |
| creator | Peakman, Aiden Hodgson, Zara Merk, Bruno |
| description | Nuclear power systems capable of outputting low powers ( |
| doi_str_mv | 10.1016/j.pnucene.2018.02.025 |
| format | article |
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The reactor technology chosen based on the results of the review were: low vapour pressure coolants like molten salt or liquid metal; solid moderator material; and conventional solid UO2 fuel. Initial infinite lattice neutronic studies indicated a series of positive reactivity coefficients. A finite system was also modelled using a molten salt as the coolant. When modelling the finite system the coolant temperature reactivity coefficient became negative, the void coefficient strongly negative and moderator temperature coefficient negative to weakly positive. Given that a number of reactivity coefficients were negative to strongly negative in the finite system, the weakly positive moderator temperature coefficient is not thought to be prohibitive. Thus the design should exhibit acceptable safety performance.
Whilst the importance of leakage in fast reactor cores is well known, a key outcome from this study is the strong influence of leakage on all safety related parameters for the thermal reactor designs considered here with solid moderator material. Thus it seems that safety studies for such small cores should be based on full core calculations instead of the traditional infinite lattice studies for fuel assemblies.</description><identifier>ISSN: 0149-1970</identifier><identifier>EISSN: 1878-4224</identifier><identifier>DOI: 10.1016/j.pnucene.2018.02.025</identifier><language>eng</language><publisher>Oxford: Elsevier Ltd</publisher><subject>Coefficients ; Competition ; Coolants ; Desalination ; Electric power systems ; Electricity generation ; Fast nuclear reactors ; Leakage ; Mathematical models ; Micro-reactors ; Microreactors ; Molten salts ; Nuclear engineering ; Nuclear fuels ; Nuclear reactors ; Nuclear safety ; Process heat ; Reactivity ; Reactor cores ; Reactor technology ; SMR ; Turbogenerators ; Uranium dioxide ; Vapor pressure ; Yttrium hydride</subject><ispartof>Progress in nuclear energy (New series), 2018-08, Vol.107, p.61-70</ispartof><rights>2018</rights><rights>Copyright Elsevier BV Aug 2018</rights><lds50>peer_reviewed</lds50><woscitedreferencessubscribed>false</woscitedreferencessubscribed><citedby>FETCH-LOGICAL-c337t-91487abf1360ec4a2a76bfc4299c39c401ea5014bc7cddcf3b661cc438718d533</citedby><cites>FETCH-LOGICAL-c337t-91487abf1360ec4a2a76bfc4299c39c401ea5014bc7cddcf3b661cc438718d533</cites></display><links><openurl>$$Topenurl_article</openurl><openurlfulltext>$$Topenurlfull_article</openurlfulltext><thumbnail>$$Tsyndetics_thumb_exl</thumbnail><link.rule.ids>314,780,784,27924,27925</link.rule.ids></links><search><creatorcontrib>Peakman, Aiden</creatorcontrib><creatorcontrib>Hodgson, Zara</creatorcontrib><creatorcontrib>Merk, Bruno</creatorcontrib><title>Advanced micro-reactor concepts</title><title>Progress in nuclear energy (New series)</title><description>Nuclear power systems capable of outputting low powers (<100 MWth) are increasingly receiving interest internationally for deployment not only as electricity production systems, capable of operating off-grid, but also as systems able to provide industrial process heat. These ‘micro-reactor’ concepts must demonstrate economic competitiveness with other potential solutions capable of providing similar power outputs. With this in mind, reactor technologies that offer inherent advantages associated with improved power density and simplified operation, both of which are important attributes that determine economic competitiveness, are reviewed in the context of the fundamental safety functions provided by the IAEA.
The reactor technology chosen based on the results of the review were: low vapour pressure coolants like molten salt or liquid metal; solid moderator material; and conventional solid UO2 fuel. Initial infinite lattice neutronic studies indicated a series of positive reactivity coefficients. A finite system was also modelled using a molten salt as the coolant. When modelling the finite system the coolant temperature reactivity coefficient became negative, the void coefficient strongly negative and moderator temperature coefficient negative to weakly positive. Given that a number of reactivity coefficients were negative to strongly negative in the finite system, the weakly positive moderator temperature coefficient is not thought to be prohibitive. Thus the design should exhibit acceptable safety performance.
Whilst the importance of leakage in fast reactor cores is well known, a key outcome from this study is the strong influence of leakage on all safety related parameters for the thermal reactor designs considered here with solid moderator material. Thus it seems that safety studies for such small cores should be based on full core calculations instead of the traditional infinite lattice studies for fuel assemblies.</description><subject>Coefficients</subject><subject>Competition</subject><subject>Coolants</subject><subject>Desalination</subject><subject>Electric power systems</subject><subject>Electricity generation</subject><subject>Fast nuclear reactors</subject><subject>Leakage</subject><subject>Mathematical models</subject><subject>Micro-reactors</subject><subject>Microreactors</subject><subject>Molten salts</subject><subject>Nuclear engineering</subject><subject>Nuclear fuels</subject><subject>Nuclear reactors</subject><subject>Nuclear safety</subject><subject>Process heat</subject><subject>Reactivity</subject><subject>Reactor cores</subject><subject>Reactor technology</subject><subject>SMR</subject><subject>Turbogenerators</subject><subject>Uranium dioxide</subject><subject>Vapor pressure</subject><subject>Yttrium hydride</subject><issn>0149-1970</issn><issn>1878-4224</issn><fulltext>true</fulltext><rsrctype>article</rsrctype><creationdate>2018</creationdate><recordtype>article</recordtype><recordid>eNqFUF1Lw0AQPETBWv0JYsHnxNv7yF2epBSrQsEXfT4umw0k2CTeJQX_vVfad2FgYZmZnR3G7oHnwKF46vKxn5F6ygUHm3ORoC_YAqyxmRJCXbIFB1VmUBp-zW5i7DgHA1ov2MO6PvgeqV7tWwxDFsjjNIQVDmk5TvGWXTX-O9LdeS7Z1_blc_OW7T5e3zfrXYZSmikrQVnjqwZkwQmVF94UVYNKlCXKEhUH8jplqNBgXWMjq6IARCWtAVtrKZfs8eQ7huFnpji5bphDn046wa0oJChpEkufWClqjIEaN4Z278OvA-6OXbjOnbtwxy4cFwk66Z5POkovHFoKLmJLx7fbQDi5emj_cfgDUrlo2Q</recordid><startdate>201808</startdate><enddate>201808</enddate><creator>Peakman, Aiden</creator><creator>Hodgson, Zara</creator><creator>Merk, Bruno</creator><general>Elsevier Ltd</general><general>Elsevier BV</general><scope>AAYXX</scope><scope>CITATION</scope><scope>7TB</scope><scope>8FD</scope><scope>FR3</scope><scope>KR7</scope></search><sort><creationdate>201808</creationdate><title>Advanced micro-reactor concepts</title><author>Peakman, Aiden ; Hodgson, Zara ; Merk, Bruno</author></sort><facets><frbrtype>5</frbrtype><frbrgroupid>cdi_FETCH-LOGICAL-c337t-91487abf1360ec4a2a76bfc4299c39c401ea5014bc7cddcf3b661cc438718d533</frbrgroupid><rsrctype>articles</rsrctype><prefilter>articles</prefilter><language>eng</language><creationdate>2018</creationdate><topic>Coefficients</topic><topic>Competition</topic><topic>Coolants</topic><topic>Desalination</topic><topic>Electric power systems</topic><topic>Electricity generation</topic><topic>Fast nuclear reactors</topic><topic>Leakage</topic><topic>Mathematical models</topic><topic>Micro-reactors</topic><topic>Microreactors</topic><topic>Molten salts</topic><topic>Nuclear engineering</topic><topic>Nuclear fuels</topic><topic>Nuclear reactors</topic><topic>Nuclear safety</topic><topic>Process heat</topic><topic>Reactivity</topic><topic>Reactor cores</topic><topic>Reactor technology</topic><topic>SMR</topic><topic>Turbogenerators</topic><topic>Uranium dioxide</topic><topic>Vapor pressure</topic><topic>Yttrium hydride</topic><toplevel>peer_reviewed</toplevel><toplevel>online_resources</toplevel><creatorcontrib>Peakman, Aiden</creatorcontrib><creatorcontrib>Hodgson, Zara</creatorcontrib><creatorcontrib>Merk, Bruno</creatorcontrib><collection>CrossRef</collection><collection>Mechanical & Transportation Engineering Abstracts</collection><collection>Technology Research Database</collection><collection>Engineering Research Database</collection><collection>Civil Engineering Abstracts</collection><jtitle>Progress in nuclear energy (New series)</jtitle></facets><delivery><delcategory>Remote Search Resource</delcategory><fulltext>fulltext</fulltext></delivery><addata><au>Peakman, Aiden</au><au>Hodgson, Zara</au><au>Merk, Bruno</au><format>journal</format><genre>article</genre><ristype>JOUR</ristype><atitle>Advanced micro-reactor concepts</atitle><jtitle>Progress in nuclear energy (New series)</jtitle><date>2018-08</date><risdate>2018</risdate><volume>107</volume><spage>61</spage><epage>70</epage><pages>61-70</pages><issn>0149-1970</issn><eissn>1878-4224</eissn><abstract>Nuclear power systems capable of outputting low powers (<100 MWth) are increasingly receiving interest internationally for deployment not only as electricity production systems, capable of operating off-grid, but also as systems able to provide industrial process heat. 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The reactor technology chosen based on the results of the review were: low vapour pressure coolants like molten salt or liquid metal; solid moderator material; and conventional solid UO2 fuel. Initial infinite lattice neutronic studies indicated a series of positive reactivity coefficients. A finite system was also modelled using a molten salt as the coolant. When modelling the finite system the coolant temperature reactivity coefficient became negative, the void coefficient strongly negative and moderator temperature coefficient negative to weakly positive. Given that a number of reactivity coefficients were negative to strongly negative in the finite system, the weakly positive moderator temperature coefficient is not thought to be prohibitive. Thus the design should exhibit acceptable safety performance.
Whilst the importance of leakage in fast reactor cores is well known, a key outcome from this study is the strong influence of leakage on all safety related parameters for the thermal reactor designs considered here with solid moderator material. Thus it seems that safety studies for such small cores should be based on full core calculations instead of the traditional infinite lattice studies for fuel assemblies.</abstract><cop>Oxford</cop><pub>Elsevier Ltd</pub><doi>10.1016/j.pnucene.2018.02.025</doi><tpages>10</tpages></addata></record> |
| fulltext | fulltext |
| identifier | ISSN: 0149-1970 |
| ispartof | Progress in nuclear energy (New series), 2018-08, Vol.107, p.61-70 |
| issn | 0149-1970 1878-4224 |
| language | eng |
| recordid | cdi_proquest_journals_2082631437 |
| source | ScienceDirect Journals |
| subjects | Coefficients Competition Coolants Desalination Electric power systems Electricity generation Fast nuclear reactors Leakage Mathematical models Micro-reactors Microreactors Molten salts Nuclear engineering Nuclear fuels Nuclear reactors Nuclear safety Process heat Reactivity Reactor cores Reactor technology SMR Turbogenerators Uranium dioxide Vapor pressure Yttrium hydride |
| title | Advanced micro-reactor concepts |
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