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Use of Thorium-Plutonium MOX in the inner pins of CANDU fuel bundles
This research is focused on using Thorium-Plutonium MOX fuel in the inner fuel pins of the CANDU fuel bundles for plutonium incineration and reduction of uranium demand and to reduce coolant void reactivity. The delayed neutron fraction and the power distribution amongst the fuel elements of the fue...
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Published in: | Progress in nuclear energy (New series) 2016-08, Vol.91, p.49-55, Article 49 |
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creator | Mohamed, Nader M.A. Badawi, Alya |
description | This research is focused on using Thorium-Plutonium MOX fuel in the inner fuel pins of the CANDU fuel bundles for plutonium incineration and reduction of uranium demand and to reduce coolant void reactivity. The delayed neutron fraction and the power distribution amongst the fuel elements of the fuel bundle have been considered as main safety parameters.
The 700 MWe Advanced CANDU Reactor (ACR-700) was selected as a case study. The inner eight UO2 fuel pins of the ACR-700 fuel bundle are replaced by Thorium-Plutonium MOX fuel pins in the proposed design with 3% reactor grade PuO2. This amount represents 23.4 w/o of the fuel in the bundle. The outer two fuel rings (35 pins) enrichment is reduced from 2.1 w/o U-235 to 2 w/o U-235. The simulation using MCNP6 showed that about 27% reduction of uranium demand can be achieved. The proposed fuel bundle eliminate the use of burnable poisons in the central pin that was used for negative coolant void reactivity and more reduction in the coolant void reactivity was achieved (about 3.5 mk less than the reference fuel bundle). The power distribution throughout the fuel bundle is more flat in the proposed fuel bundle. Use of this fuel bundle reduces the delayed neutron fraction from 540 pcm in the reference case to 480 pcm in the proposed case.
•Use of Th-Pu MOX in the inner fuel pins of the CANDU fuel bundles has been studied.•The 700 MWe Advanced CANDU Reactor was selected as a case study and was simulated using MCNP6.•The impact on coolant void reactivity, delayed neutron fraction and power distribution has been studied. |
doi_str_mv | 10.1016/j.pnucene.2016.04.008 |
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The 700 MWe Advanced CANDU Reactor (ACR-700) was selected as a case study. The inner eight UO2 fuel pins of the ACR-700 fuel bundle are replaced by Thorium-Plutonium MOX fuel pins in the proposed design with 3% reactor grade PuO2. This amount represents 23.4 w/o of the fuel in the bundle. The outer two fuel rings (35 pins) enrichment is reduced from 2.1 w/o U-235 to 2 w/o U-235. The simulation using MCNP6 showed that about 27% reduction of uranium demand can be achieved. The proposed fuel bundle eliminate the use of burnable poisons in the central pin that was used for negative coolant void reactivity and more reduction in the coolant void reactivity was achieved (about 3.5 mk less than the reference fuel bundle). The power distribution throughout the fuel bundle is more flat in the proposed fuel bundle. Use of this fuel bundle reduces the delayed neutron fraction from 540 pcm in the reference case to 480 pcm in the proposed case.
•Use of Th-Pu MOX in the inner fuel pins of the CANDU fuel bundles has been studied.•The 700 MWe Advanced CANDU Reactor was selected as a case study and was simulated using MCNP6.•The impact on coolant void reactivity, delayed neutron fraction and power distribution has been studied.</description><identifier>ISSN: 0149-1970</identifier><identifier>DOI: 10.1016/j.pnucene.2016.04.008</identifier><language>eng</language><publisher>Elsevier Ltd</publisher><subject>ACR-700 ; Bundles ; CANDU ; Fuel bundles ; Fuels ; Nuclear engineering ; Nuclear reactor components ; Reduction ; Thorium-Plutonium MOX ; Uranium ; Voids</subject><ispartof>Progress in nuclear energy (New series), 2016-08, Vol.91, p.49-55, Article 49</ispartof><rights>2016 Elsevier Ltd</rights><lds50>peer_reviewed</lds50><woscitedreferencessubscribed>false</woscitedreferencessubscribed><citedby>FETCH-LOGICAL-c342t-8a795565a45807070e83e7142c3250e75fc18ed1ee3caa1505dd4ebef2e712973</citedby><cites>FETCH-LOGICAL-c342t-8a795565a45807070e83e7142c3250e75fc18ed1ee3caa1505dd4ebef2e712973</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>Mohamed, Nader M.A.</creatorcontrib><creatorcontrib>Badawi, Alya</creatorcontrib><title>Use of Thorium-Plutonium MOX in the inner pins of CANDU fuel bundles</title><title>Progress in nuclear energy (New series)</title><description>This research is focused on using Thorium-Plutonium MOX fuel in the inner fuel pins of the CANDU fuel bundles for plutonium incineration and reduction of uranium demand and to reduce coolant void reactivity. The delayed neutron fraction and the power distribution amongst the fuel elements of the fuel bundle have been considered as main safety parameters.
The 700 MWe Advanced CANDU Reactor (ACR-700) was selected as a case study. The inner eight UO2 fuel pins of the ACR-700 fuel bundle are replaced by Thorium-Plutonium MOX fuel pins in the proposed design with 3% reactor grade PuO2. This amount represents 23.4 w/o of the fuel in the bundle. The outer two fuel rings (35 pins) enrichment is reduced from 2.1 w/o U-235 to 2 w/o U-235. The simulation using MCNP6 showed that about 27% reduction of uranium demand can be achieved. The proposed fuel bundle eliminate the use of burnable poisons in the central pin that was used for negative coolant void reactivity and more reduction in the coolant void reactivity was achieved (about 3.5 mk less than the reference fuel bundle). The power distribution throughout the fuel bundle is more flat in the proposed fuel bundle. Use of this fuel bundle reduces the delayed neutron fraction from 540 pcm in the reference case to 480 pcm in the proposed case.
•Use of Th-Pu MOX in the inner fuel pins of the CANDU fuel bundles has been studied.•The 700 MWe Advanced CANDU Reactor was selected as a case study and was simulated using MCNP6.•The impact on coolant void reactivity, delayed neutron fraction and power distribution has been studied.</description><subject>ACR-700</subject><subject>Bundles</subject><subject>CANDU</subject><subject>Fuel bundles</subject><subject>Fuels</subject><subject>Nuclear engineering</subject><subject>Nuclear reactor components</subject><subject>Reduction</subject><subject>Thorium-Plutonium MOX</subject><subject>Uranium</subject><subject>Voids</subject><issn>0149-1970</issn><fulltext>true</fulltext><rsrctype>article</rsrctype><creationdate>2016</creationdate><recordtype>article</recordtype><recordid>eNqFkD1PwzAQhj2ARCn8BCSPLAl2YudDDKhqKSAVytBKbJbrXFRXqR1sB4l_j6t2YqluuDvped_hQeiOkpQSWjzs0t4MCgykWXxTwlJCqgs0IpTVCa1LcoWuvd8RQkvK-QjN1h6wbfFqa50e9slnNwRr4oXfl19YGxy2EJcBh3tt_AGdTj5ma9wO0OHNYJoO_A26bGXn4fa0x2g9f15NX5PF8uVtOlkkKmdZSCpZ1pwXXDJekTIOVDmUlGUqzziBkreKVtBQgFxJSTnhTcNgA20Wqawu8zG6P_b2zn4P4IPYa6-g66QBO3hBq5wXBY1tEeVHVDnrvYNW9E7vpfsVlIiDKbETJ1PiYEoQJqKpmHv8l1M6yKCtCU7q7mz66ZiGaOFHgxNeaTAKGu1ABdFYfabhD1ZSiOw</recordid><startdate>201608</startdate><enddate>201608</enddate><creator>Mohamed, Nader M.A.</creator><creator>Badawi, Alya</creator><general>Elsevier Ltd</general><scope>AAYXX</scope><scope>CITATION</scope><scope>7TB</scope><scope>8FD</scope><scope>FR3</scope><scope>KR7</scope></search><sort><creationdate>201608</creationdate><title>Use of Thorium-Plutonium MOX in the inner pins of CANDU fuel bundles</title><author>Mohamed, Nader M.A. ; Badawi, Alya</author></sort><facets><frbrtype>5</frbrtype><frbrgroupid>cdi_FETCH-LOGICAL-c342t-8a795565a45807070e83e7142c3250e75fc18ed1ee3caa1505dd4ebef2e712973</frbrgroupid><rsrctype>articles</rsrctype><prefilter>articles</prefilter><language>eng</language><creationdate>2016</creationdate><topic>ACR-700</topic><topic>Bundles</topic><topic>CANDU</topic><topic>Fuel bundles</topic><topic>Fuels</topic><topic>Nuclear engineering</topic><topic>Nuclear reactor components</topic><topic>Reduction</topic><topic>Thorium-Plutonium MOX</topic><topic>Uranium</topic><topic>Voids</topic><toplevel>peer_reviewed</toplevel><toplevel>online_resources</toplevel><creatorcontrib>Mohamed, Nader M.A.</creatorcontrib><creatorcontrib>Badawi, Alya</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>Mohamed, Nader M.A.</au><au>Badawi, Alya</au><format>journal</format><genre>article</genre><ristype>JOUR</ristype><atitle>Use of Thorium-Plutonium MOX in the inner pins of CANDU fuel bundles</atitle><jtitle>Progress in nuclear energy (New series)</jtitle><date>2016-08</date><risdate>2016</risdate><volume>91</volume><spage>49</spage><epage>55</epage><pages>49-55</pages><artnum>49</artnum><issn>0149-1970</issn><abstract>This research is focused on using Thorium-Plutonium MOX fuel in the inner fuel pins of the CANDU fuel bundles for plutonium incineration and reduction of uranium demand and to reduce coolant void reactivity. The delayed neutron fraction and the power distribution amongst the fuel elements of the fuel bundle have been considered as main safety parameters.
The 700 MWe Advanced CANDU Reactor (ACR-700) was selected as a case study. The inner eight UO2 fuel pins of the ACR-700 fuel bundle are replaced by Thorium-Plutonium MOX fuel pins in the proposed design with 3% reactor grade PuO2. This amount represents 23.4 w/o of the fuel in the bundle. The outer two fuel rings (35 pins) enrichment is reduced from 2.1 w/o U-235 to 2 w/o U-235. The simulation using MCNP6 showed that about 27% reduction of uranium demand can be achieved. The proposed fuel bundle eliminate the use of burnable poisons in the central pin that was used for negative coolant void reactivity and more reduction in the coolant void reactivity was achieved (about 3.5 mk less than the reference fuel bundle). The power distribution throughout the fuel bundle is more flat in the proposed fuel bundle. Use of this fuel bundle reduces the delayed neutron fraction from 540 pcm in the reference case to 480 pcm in the proposed case.
•Use of Th-Pu MOX in the inner fuel pins of the CANDU fuel bundles has been studied.•The 700 MWe Advanced CANDU Reactor was selected as a case study and was simulated using MCNP6.•The impact on coolant void reactivity, delayed neutron fraction and power distribution has been studied.</abstract><pub>Elsevier Ltd</pub><doi>10.1016/j.pnucene.2016.04.008</doi><tpages>7</tpages></addata></record> |
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source | ScienceDirect Journals |
subjects | ACR-700 Bundles CANDU Fuel bundles Fuels Nuclear engineering Nuclear reactor components Reduction Thorium-Plutonium MOX Uranium Voids |
title | Use of Thorium-Plutonium MOX in the inner pins of CANDU fuel bundles |
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