Temperature Distributions In Cylindrical Plain-Canned Fuel Elements Under Some Transient Conditions
Two critical requirements in the design and operation of natural uranium reactors are the maintenance at all times of the maximum fuel temperature below 600°C, the phase change value and the limiting of the temperature of the can to a value such that its strength and corrosion-resistance properties...
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| Veröffentlicht in: | Journal of nuclear energy. Part B, Reactor technology Reactor technology, 1960, Vol.1 (3), p.161-166 |
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| container_end_page | 166 |
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| container_issue | 3 |
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| container_title | Journal of nuclear energy. Part B, Reactor technology |
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| creator | Strickland, R.E. Angelopoulos, M. |
| description | Two critical requirements in the design and operation of natural uranium reactors are the maintenance at all times of the maximum fuel temperature below 600°C, the phase change value and the limiting of the temperature of the can to a value such that its strength and corrosion-resistance properties are adequate. It is necessary, therefore, to examine temperature distributions in the fuel and can under possible significant transient conditions. Three such conditions are numerically examined using the experimental heat transfer data of HUGHES and SLACK (1958). In two cases, the temperature response to a step change in flux and to a typical flux control disturbance, the results show the time-lag effect due to the dominant time constant which has a characteristic value for each fuel-plus-can system. In the third case, the maximum temperature reached during fuel element charging under load is examined. |
| doi_str_mv | 10.1016/S0368-3273(15)30018-3 |
| format | Article |
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It is necessary, therefore, to examine temperature distributions in the fuel and can under possible significant transient conditions. Three such conditions are numerically examined using the experimental heat transfer data of HUGHES and SLACK (1958). In two cases, the temperature response to a step change in flux and to a typical flux control disturbance, the results show the time-lag effect due to the dominant time constant which has a characteristic value for each fuel-plus-can system. 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Part B, Reactor technology</title><description>Two critical requirements in the design and operation of natural uranium reactors are the maintenance at all times of the maximum fuel temperature below 600°C, the phase change value and the limiting of the temperature of the can to a value such that its strength and corrosion-resistance properties are adequate. It is necessary, therefore, to examine temperature distributions in the fuel and can under possible significant transient conditions. Three such conditions are numerically examined using the experimental heat transfer data of HUGHES and SLACK (1958). In two cases, the temperature response to a step change in flux and to a typical flux control disturbance, the results show the time-lag effect due to the dominant time constant which has a characteristic value for each fuel-plus-can system. In the third case, the maximum temperature reached during fuel element charging under load is examined.</description><subject>CONTROL</subject><subject>CORROSION</subject><subject>CYLINDERS</subject><subject>DISTRIBUTION</subject><subject>ENGINEERING AND EQUIPMENT</subject><subject>FUEL CANS</subject><subject>FUEL ELEMENTS</subject><subject>HEAT TRANSFER</subject><subject>NATURAL URANIUM FUEL</subject><subject>NEUTRON FLUX</subject><subject>OSCILLATIONS</subject><subject>PHASE DIAGRAMS</subject><subject>REACTOR FUELING</subject><subject>REACTORS</subject><subject>TEMPERATURE</subject><subject>TENSILE PROPERTIES</subject><subject>TRANSIENTS</subject><issn>0368-3273</issn><fulltext>true</fulltext><rsrctype>article</rsrctype><creationdate>1960</creationdate><recordtype>article</recordtype><recordid>eNqFkNFLwzAQxvOg4Jz-CULwSR-qSS_tlieRuulgoLDuOaTJFSNtOpJO2H9vu4mvPh338d3v7j5Cbjh74IznjxsG-TyBdAZ3PLsHxvjQnZHJn3xBLmP8Yiydi1xOiCmx3WHQ_T4gfXGxD67a967zka48LQ6N8zY4oxv60Wjnk0J7j5Yu99jQRYMt-j7SrbcY6KZrkZZB--gGlRadt-5IuiLntW4iXv_WKdkuF2XxlqzfX1fF8zoxPJUiEWArDsirWQVoZS255TxLa2aYBalriRosA2lA27kBlEKbXEthuK4hMwBTcnvidrF3KhrXo_k03XCw6ZXgkgkmBlN2MpnQxRiwVrvgWh0OijM1RqiOEaoxK8UzdYxQjfCn0xwOH3w7DOMC9AatCyPfdu4fwg9kKHwH</recordid><startdate>1960</startdate><enddate>1960</enddate><creator>Strickland, R.E.</creator><creator>Angelopoulos, M.</creator><general>Elsevier Ltd</general><scope>AAYXX</scope><scope>CITATION</scope><scope>OTOTI</scope></search><sort><creationdate>1960</creationdate><title>Temperature Distributions In Cylindrical Plain-Canned Fuel Elements Under Some Transient Conditions</title><author>Strickland, R.E. ; Angelopoulos, M.</author></sort><facets><frbrtype>5</frbrtype><frbrgroupid>cdi_FETCH-LOGICAL-c1294-43db13e1b7b3ed9f91d1152f0c0d39af9ea3d039c3ad8c3e94ac6a94c1af35c33</frbrgroupid><rsrctype>articles</rsrctype><prefilter>articles</prefilter><language>eng</language><creationdate>1960</creationdate><topic>CONTROL</topic><topic>CORROSION</topic><topic>CYLINDERS</topic><topic>DISTRIBUTION</topic><topic>ENGINEERING AND EQUIPMENT</topic><topic>FUEL CANS</topic><topic>FUEL ELEMENTS</topic><topic>HEAT TRANSFER</topic><topic>NATURAL URANIUM FUEL</topic><topic>NEUTRON FLUX</topic><topic>OSCILLATIONS</topic><topic>PHASE DIAGRAMS</topic><topic>REACTOR FUELING</topic><topic>REACTORS</topic><topic>TEMPERATURE</topic><topic>TENSILE PROPERTIES</topic><topic>TRANSIENTS</topic><toplevel>online_resources</toplevel><creatorcontrib>Strickland, R.E.</creatorcontrib><creatorcontrib>Angelopoulos, M.</creatorcontrib><creatorcontrib>Imperial Coll. of Science and Tech., London</creatorcontrib><creatorcontrib>Technical Univ., Athens</creatorcontrib><collection>CrossRef</collection><collection>OSTI.GOV</collection><jtitle>Journal of nuclear energy. 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Part B, Reactor technology</jtitle><date>1960</date><risdate>1960</risdate><volume>1</volume><issue>3</issue><spage>161</spage><epage>166</epage><pages>161-166</pages><issn>0368-3273</issn><abstract>Two critical requirements in the design and operation of natural uranium reactors are the maintenance at all times of the maximum fuel temperature below 600°C, the phase change value and the limiting of the temperature of the can to a value such that its strength and corrosion-resistance properties are adequate. It is necessary, therefore, to examine temperature distributions in the fuel and can under possible significant transient conditions. Three such conditions are numerically examined using the experimental heat transfer data of HUGHES and SLACK (1958). In two cases, the temperature response to a step change in flux and to a typical flux control disturbance, the results show the time-lag effect due to the dominant time constant which has a characteristic value for each fuel-plus-can system. In the third case, the maximum temperature reached during fuel element charging under load is examined.</abstract><pub>Elsevier Ltd</pub><doi>10.1016/S0368-3273(15)30018-3</doi><tpages>6</tpages></addata></record> |
| fulltext | fulltext |
| identifier | ISSN: 0368-3273 |
| ispartof | Journal of nuclear energy. Part B, Reactor technology, 1960, Vol.1 (3), p.161-166 |
| issn | 0368-3273 |
| language | eng |
| recordid | cdi_osti_scitechconnect_4190404 |
| source | Alma/SFX Local Collection |
| subjects | CONTROL CORROSION CYLINDERS DISTRIBUTION ENGINEERING AND EQUIPMENT FUEL CANS FUEL ELEMENTS HEAT TRANSFER NATURAL URANIUM FUEL NEUTRON FLUX OSCILLATIONS PHASE DIAGRAMS REACTOR FUELING REACTORS TEMPERATURE TENSILE PROPERTIES TRANSIENTS |
| title | Temperature Distributions In Cylindrical Plain-Canned Fuel Elements Under Some Transient Conditions |
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