Use of Neptunium-containing Fuel in Lead-cooled Fast Reactor
The paper analyzes a principal capability to transmute neptunium, the main component of transuranium radiowastes (TRW), in lead-cooled fast BREST-type reactor. High-energy neutron spectrum of the BREST-type fast reactor makes it possible either to eliminate neptunium in fission reactions or convert...
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Veröffentlicht in: | Physics of atomic nuclei 2018-12, Vol.81 (11), p.1531-1535 |
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container_title | Physics of atomic nuclei |
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creator | Apse, V. A. Shmelev, A. N. Kulikov, G. G. Kulikov, E. G. |
description | The paper analyzes a principal capability to transmute neptunium, the main component of transuranium radiowastes (TRW), in lead-cooled fast BREST-type reactor. High-energy neutron spectrum of the BREST-type fast reactor makes it possible either to eliminate neptunium in fission reactions or convert neptunium to plutonium with large fraction of
238
Pu in radiative neutron capture reactions. According to the IAEA regulatory documents, plutonium containing above 80%
238
Pu is regarded as an unsuitable material for manufacturing of nuclear explosive devices. Besides, good neutron-multiplying properties of
238
Pu and
239
Pu can prolong substantially the reactor core lifetime. Thus, introduction of neptunium into fresh fuel composition can eliminate the largest TRW fraction, strengthen regime of nuclear non-proliferation, produce some additional amount of thermal energy and prolong the reactor core lifetime. |
doi_str_mv | 10.1134/S1063778818120013 |
format | Article |
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238
Pu in radiative neutron capture reactions. According to the IAEA regulatory documents, plutonium containing above 80%
238
Pu is regarded as an unsuitable material for manufacturing of nuclear explosive devices. Besides, good neutron-multiplying properties of
238
Pu and
239
Pu can prolong substantially the reactor core lifetime. Thus, introduction of neptunium into fresh fuel composition can eliminate the largest TRW fraction, strengthen regime of nuclear non-proliferation, produce some additional amount of thermal energy and prolong the reactor core lifetime.</description><identifier>ISSN: 1063-7788</identifier><identifier>EISSN: 1562-692X</identifier><identifier>DOI: 10.1134/S1063778818120013</identifier><language>eng</language><publisher>Moscow: Pleiades Publishing</publisher><subject>Analysis ; Arms control ; Energy (Physics) ; Explosive devices ; Fast nuclear reactors ; Fission Physics ; Neptunium ; Nuclear capture ; Nuclear energy ; Nuclear fuels ; Nuclear industry ; Nuclear nonproliferation ; Nuclear reactions ; Nuclear reactors ; Particle and Nuclear Physics ; Physics ; Physics and Astronomy ; Plutonium ; Production management ; Thermal energy ; Uranium</subject><ispartof>Physics of atomic nuclei, 2018-12, Vol.81 (11), p.1531-1535</ispartof><rights>Pleiades Publishing, Ltd. 2018</rights><rights>COPYRIGHT 2018 Springer</rights><rights>Copyright Springer Nature B.V. 2018</rights><lds50>peer_reviewed</lds50><woscitedreferencessubscribed>false</woscitedreferencessubscribed><citedby>FETCH-LOGICAL-c350t-bb6c80e4ac23e356a7dc4f6eeb8b7dff341d574c208945a8d480b2af743674d73</citedby></display><links><openurl>$$Topenurl_article</openurl><openurlfulltext>$$Topenurlfull_article</openurlfulltext><thumbnail>$$Tsyndetics_thumb_exl</thumbnail><linktopdf>$$Uhttps://link.springer.com/content/pdf/10.1134/S1063778818120013$$EPDF$$P50$$Gspringer$$H</linktopdf><linktohtml>$$Uhttps://link.springer.com/10.1134/S1063778818120013$$EHTML$$P50$$Gspringer$$H</linktohtml><link.rule.ids>314,776,780,27901,27902,41464,42533,51294</link.rule.ids></links><search><creatorcontrib>Apse, V. A.</creatorcontrib><creatorcontrib>Shmelev, A. N.</creatorcontrib><creatorcontrib>Kulikov, G. G.</creatorcontrib><creatorcontrib>Kulikov, E. G.</creatorcontrib><title>Use of Neptunium-containing Fuel in Lead-cooled Fast Reactor</title><title>Physics of atomic nuclei</title><addtitle>Phys. Atom. Nuclei</addtitle><description>The paper analyzes a principal capability to transmute neptunium, the main component of transuranium radiowastes (TRW), in lead-cooled fast BREST-type reactor. High-energy neutron spectrum of the BREST-type fast reactor makes it possible either to eliminate neptunium in fission reactions or convert neptunium to plutonium with large fraction of
238
Pu in radiative neutron capture reactions. According to the IAEA regulatory documents, plutonium containing above 80%
238
Pu is regarded as an unsuitable material for manufacturing of nuclear explosive devices. Besides, good neutron-multiplying properties of
238
Pu and
239
Pu can prolong substantially the reactor core lifetime. Thus, introduction of neptunium into fresh fuel composition can eliminate the largest TRW fraction, strengthen regime of nuclear non-proliferation, produce some additional amount of thermal energy and prolong the reactor core lifetime.</description><subject>Analysis</subject><subject>Arms control</subject><subject>Energy (Physics)</subject><subject>Explosive devices</subject><subject>Fast nuclear reactors</subject><subject>Fission Physics</subject><subject>Neptunium</subject><subject>Nuclear capture</subject><subject>Nuclear energy</subject><subject>Nuclear fuels</subject><subject>Nuclear industry</subject><subject>Nuclear nonproliferation</subject><subject>Nuclear reactions</subject><subject>Nuclear reactors</subject><subject>Particle and Nuclear Physics</subject><subject>Physics</subject><subject>Physics and Astronomy</subject><subject>Plutonium</subject><subject>Production management</subject><subject>Thermal energy</subject><subject>Uranium</subject><issn>1063-7788</issn><issn>1562-692X</issn><fulltext>true</fulltext><rsrctype>article</rsrctype><creationdate>2018</creationdate><recordtype>article</recordtype><recordid>eNp1kE1Lw0AQhhdRsFZ_gLeAJw_R_cruBryUYrVQFFoL3pbNZhJS0k3dTUD_vVsieBBPM8z7vPOF0DXBd4Qwfr8hWDAplSKKUIwJO0ETkgmaipy-n8Y8yulRP0cXIewiQVSGJ-hhGyDpquQFDv3gmmGf2s71pnGNq5PFAG3SuGQFpoz1roUyWZjQJ2swtu_8JTqrTBvg6idO0Xbx-DZ_TlevT8v5bJValuE-LQphFQZuLGXAMmFkaXklAApVyLKqGCdlJrmlWOU8M6rkChfUVJIzIXkp2RTdjH0PvvsYIPR61w3exZGaEqUEl0LQSN2OVG1a0I07HgKffW2GEPRys9azLFeCEszzyJKRtb4LwUOlD77ZG_-lCdbHh-o_D40eOnpCZF0N_neL_03fx411Kg</recordid><startdate>20181201</startdate><enddate>20181201</enddate><creator>Apse, V. A.</creator><creator>Shmelev, A. N.</creator><creator>Kulikov, G. G.</creator><creator>Kulikov, E. G.</creator><general>Pleiades Publishing</general><general>Springer</general><general>Springer Nature B.V</general><scope>AAYXX</scope><scope>CITATION</scope><scope>ISR</scope></search><sort><creationdate>20181201</creationdate><title>Use of Neptunium-containing Fuel in Lead-cooled Fast Reactor</title><author>Apse, V. A. ; Shmelev, A. N. ; Kulikov, G. G. ; Kulikov, E. G.</author></sort><facets><frbrtype>5</frbrtype><frbrgroupid>cdi_FETCH-LOGICAL-c350t-bb6c80e4ac23e356a7dc4f6eeb8b7dff341d574c208945a8d480b2af743674d73</frbrgroupid><rsrctype>articles</rsrctype><prefilter>articles</prefilter><language>eng</language><creationdate>2018</creationdate><topic>Analysis</topic><topic>Arms control</topic><topic>Energy (Physics)</topic><topic>Explosive devices</topic><topic>Fast nuclear reactors</topic><topic>Fission Physics</topic><topic>Neptunium</topic><topic>Nuclear capture</topic><topic>Nuclear energy</topic><topic>Nuclear fuels</topic><topic>Nuclear industry</topic><topic>Nuclear nonproliferation</topic><topic>Nuclear reactions</topic><topic>Nuclear reactors</topic><topic>Particle and Nuclear Physics</topic><topic>Physics</topic><topic>Physics and Astronomy</topic><topic>Plutonium</topic><topic>Production management</topic><topic>Thermal energy</topic><topic>Uranium</topic><toplevel>peer_reviewed</toplevel><toplevel>online_resources</toplevel><creatorcontrib>Apse, V. A.</creatorcontrib><creatorcontrib>Shmelev, A. N.</creatorcontrib><creatorcontrib>Kulikov, G. G.</creatorcontrib><creatorcontrib>Kulikov, E. G.</creatorcontrib><collection>CrossRef</collection><collection>Gale In Context: Science</collection><jtitle>Physics of atomic nuclei</jtitle></facets><delivery><delcategory>Remote Search Resource</delcategory><fulltext>fulltext</fulltext></delivery><addata><au>Apse, V. A.</au><au>Shmelev, A. N.</au><au>Kulikov, G. G.</au><au>Kulikov, E. G.</au><format>journal</format><genre>article</genre><ristype>JOUR</ristype><atitle>Use of Neptunium-containing Fuel in Lead-cooled Fast Reactor</atitle><jtitle>Physics of atomic nuclei</jtitle><stitle>Phys. Atom. Nuclei</stitle><date>2018-12-01</date><risdate>2018</risdate><volume>81</volume><issue>11</issue><spage>1531</spage><epage>1535</epage><pages>1531-1535</pages><issn>1063-7788</issn><eissn>1562-692X</eissn><abstract>The paper analyzes a principal capability to transmute neptunium, the main component of transuranium radiowastes (TRW), in lead-cooled fast BREST-type reactor. High-energy neutron spectrum of the BREST-type fast reactor makes it possible either to eliminate neptunium in fission reactions or convert neptunium to plutonium with large fraction of
238
Pu in radiative neutron capture reactions. According to the IAEA regulatory documents, plutonium containing above 80%
238
Pu is regarded as an unsuitable material for manufacturing of nuclear explosive devices. Besides, good neutron-multiplying properties of
238
Pu and
239
Pu can prolong substantially the reactor core lifetime. Thus, introduction of neptunium into fresh fuel composition can eliminate the largest TRW fraction, strengthen regime of nuclear non-proliferation, produce some additional amount of thermal energy and prolong the reactor core lifetime.</abstract><cop>Moscow</cop><pub>Pleiades Publishing</pub><doi>10.1134/S1063778818120013</doi><tpages>5</tpages></addata></record> |
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subjects | Analysis Arms control Energy (Physics) Explosive devices Fast nuclear reactors Fission Physics Neptunium Nuclear capture Nuclear energy Nuclear fuels Nuclear industry Nuclear nonproliferation Nuclear reactions Nuclear reactors Particle and Nuclear Physics Physics Physics and Astronomy Plutonium Production management Thermal energy Uranium |
title | Use of Neptunium-containing Fuel in Lead-cooled Fast Reactor |
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