{"title":"用熔融氯化铀冷却的熔融氯化钚快中子增殖反应堆","authors":"M. Taube, J. Ligou","doi":"10.1016/0302-2927(74)90045-2","DOIUrl":null,"url":null,"abstract":"<div><p>A fast breeder reactor of ∼2000 MW(t) output using molten chlorides as fuel and coolant is discussed. Some of the most significant characteristics are:</p><p>The liquid fuel contains only PuCl<sub>3</sub>/NaCl.</p><p>The coolant is molten UCl<sub>3</sub>/NaCl and also forms the fertile material along with the blanket system, again UCl<sub>3</sub>/NaCl: the coolant blanket system is divided into 2 or more indeendent circuits.</p><p>The fuel circulates through the core by forced convection; the core is not divided. The thermal stability of the reactor is very good. Power excursions or fuel temperature transients are quickly damped by the phenomena of fuel expansion pushing part of the fissile material out of the critical zone.</p><p>The loss of coolant accident results in a loss of half (or <span><math><mtext>1</mtext><mtext>3</mtext><mtext> </mtext><mtext>2</mtext><mtext>3</mtext></math></span>) of blanket which without relying on a reactor scram, results in an automatic adjustment of the reactor power level.</p><p>Corrosion effects form the most difficult problem. Thermodynamic studies suggest the use of molybdenum alloys as structural materials.</p></div>","PeriodicalId":100094,"journal":{"name":"Annals of Nuclear Science and Engineering","volume":"1 4","pages":"Pages 277-281"},"PeriodicalIF":0.0000,"publicationDate":"1974-04-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"https://sci-hub-pdf.com/10.1016/0302-2927(74)90045-2","citationCount":"33","resultStr":"{\"title\":\"Molten plutonium chlorides fast breeder reactor cooled by molten uranium chloride\",\"authors\":\"M. Taube, J. Ligou\",\"doi\":\"10.1016/0302-2927(74)90045-2\",\"DOIUrl\":null,\"url\":null,\"abstract\":\"<div><p>A fast breeder reactor of ∼2000 MW(t) output using molten chlorides as fuel and coolant is discussed. Some of the most significant characteristics are:</p><p>The liquid fuel contains only PuCl<sub>3</sub>/NaCl.</p><p>The coolant is molten UCl<sub>3</sub>/NaCl and also forms the fertile material along with the blanket system, again UCl<sub>3</sub>/NaCl: the coolant blanket system is divided into 2 or more indeendent circuits.</p><p>The fuel circulates through the core by forced convection; the core is not divided. The thermal stability of the reactor is very good. Power excursions or fuel temperature transients are quickly damped by the phenomena of fuel expansion pushing part of the fissile material out of the critical zone.</p><p>The loss of coolant accident results in a loss of half (or <span><math><mtext>1</mtext><mtext>3</mtext><mtext> </mtext><mtext>2</mtext><mtext>3</mtext></math></span>) of blanket which without relying on a reactor scram, results in an automatic adjustment of the reactor power level.</p><p>Corrosion effects form the most difficult problem. Thermodynamic studies suggest the use of molybdenum alloys as structural materials.</p></div>\",\"PeriodicalId\":100094,\"journal\":{\"name\":\"Annals of Nuclear Science and Engineering\",\"volume\":\"1 4\",\"pages\":\"Pages 277-281\"},\"PeriodicalIF\":0.0000,\"publicationDate\":\"1974-04-01\",\"publicationTypes\":\"Journal Article\",\"fieldsOfStudy\":null,\"isOpenAccess\":false,\"openAccessPdf\":\"https://sci-hub-pdf.com/10.1016/0302-2927(74)90045-2\",\"citationCount\":\"33\",\"resultStr\":null,\"platform\":\"Semanticscholar\",\"paperid\":null,\"PeriodicalName\":\"Annals of Nuclear Science and Engineering\",\"FirstCategoryId\":\"1085\",\"ListUrlMain\":\"https://www.sciencedirect.com/science/article/pii/0302292774900452\",\"RegionNum\":0,\"RegionCategory\":null,\"ArticlePicture\":[],\"TitleCN\":null,\"AbstractTextCN\":null,\"PMCID\":null,\"EPubDate\":\"\",\"PubModel\":\"\",\"JCR\":\"\",\"JCRName\":\"\",\"Score\":null,\"Total\":0}","platform":"Semanticscholar","paperid":null,"PeriodicalName":"Annals of Nuclear Science and Engineering","FirstCategoryId":"1085","ListUrlMain":"https://www.sciencedirect.com/science/article/pii/0302292774900452","RegionNum":0,"RegionCategory":null,"ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":null,"EPubDate":"","PubModel":"","JCR":"","JCRName":"","Score":null,"Total":0}
Molten plutonium chlorides fast breeder reactor cooled by molten uranium chloride
A fast breeder reactor of ∼2000 MW(t) output using molten chlorides as fuel and coolant is discussed. Some of the most significant characteristics are:
The liquid fuel contains only PuCl3/NaCl.
The coolant is molten UCl3/NaCl and also forms the fertile material along with the blanket system, again UCl3/NaCl: the coolant blanket system is divided into 2 or more indeendent circuits.
The fuel circulates through the core by forced convection; the core is not divided. The thermal stability of the reactor is very good. Power excursions or fuel temperature transients are quickly damped by the phenomena of fuel expansion pushing part of the fissile material out of the critical zone.
The loss of coolant accident results in a loss of half (or ) of blanket which without relying on a reactor scram, results in an automatic adjustment of the reactor power level.
Corrosion effects form the most difficult problem. Thermodynamic studies suggest the use of molybdenum alloys as structural materials.
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