V.B. Dubrovskii, N.V. Krasnoyarov, M.Ya. Kulakovskii, B.K. Pergamenshchik, M.S. Pinkhasik, V.I. Savitskii
{"title":"用混凝土屏蔽高温反应堆","authors":"V.B. Dubrovskii, N.V. Krasnoyarov, M.Ya. Kulakovskii, B.K. Pergamenshchik, M.S. Pinkhasik, V.I. Savitskii","doi":"10.1016/0368-3230(66)90145-5","DOIUrl":null,"url":null,"abstract":"<div><p>The possibility is examined of constructing thermal shields of reactors from chromite and fireclay heat-resistant concretes. Neutron fluxes of different intensities (up to 10<sup>13</sup> n/cm<sup>2</sup> sec, close in spectrum to the fission spectrum) absorbed by shields of these materials are examined. The passage of neutrons, y-ray fluxes and generation of heat in the shield are taken into account. The temperatures in the shield are calculated for different neutron fluxes, thicknesses of concrete and cooling conditions. A static calculation of the temperature stresses in a shield constructed from heat-proof reinforced concrete is carried out.</p><p>It is established that heat-resistant reinforced concrete can be used for the shields of nuclear reactors for neutron fluxes to the concrete up to 10<sup>13</sup> n/cm<sup>2</sup> sec, temperatures up to 1000–1100°C and temperature drops of up to 900°C.</p></div>","PeriodicalId":100815,"journal":{"name":"Journal of Nuclear Energy. Parts A/B. Reactor Science and Technology","volume":"20 11","pages":"Pages 1031-1038"},"PeriodicalIF":0.0000,"publicationDate":"1966-11-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"https://sci-hub-pdf.com/10.1016/0368-3230(66)90145-5","citationCount":"3","resultStr":"{\"title\":\"The use of concrete for shielding high-temperature reactors\",\"authors\":\"V.B. Dubrovskii, N.V. Krasnoyarov, M.Ya. Kulakovskii, B.K. Pergamenshchik, M.S. Pinkhasik, V.I. Savitskii\",\"doi\":\"10.1016/0368-3230(66)90145-5\",\"DOIUrl\":null,\"url\":null,\"abstract\":\"<div><p>The possibility is examined of constructing thermal shields of reactors from chromite and fireclay heat-resistant concretes. Neutron fluxes of different intensities (up to 10<sup>13</sup> n/cm<sup>2</sup> sec, close in spectrum to the fission spectrum) absorbed by shields of these materials are examined. The passage of neutrons, y-ray fluxes and generation of heat in the shield are taken into account. The temperatures in the shield are calculated for different neutron fluxes, thicknesses of concrete and cooling conditions. A static calculation of the temperature stresses in a shield constructed from heat-proof reinforced concrete is carried out.</p><p>It is established that heat-resistant reinforced concrete can be used for the shields of nuclear reactors for neutron fluxes to the concrete up to 10<sup>13</sup> n/cm<sup>2</sup> sec, temperatures up to 1000–1100°C and temperature drops of up to 900°C.</p></div>\",\"PeriodicalId\":100815,\"journal\":{\"name\":\"Journal of Nuclear Energy. Parts A/B. Reactor Science and Technology\",\"volume\":\"20 11\",\"pages\":\"Pages 1031-1038\"},\"PeriodicalIF\":0.0000,\"publicationDate\":\"1966-11-01\",\"publicationTypes\":\"Journal Article\",\"fieldsOfStudy\":null,\"isOpenAccess\":false,\"openAccessPdf\":\"https://sci-hub-pdf.com/10.1016/0368-3230(66)90145-5\",\"citationCount\":\"3\",\"resultStr\":null,\"platform\":\"Semanticscholar\",\"paperid\":null,\"PeriodicalName\":\"Journal of Nuclear Energy. Parts A/B. Reactor Science and Technology\",\"FirstCategoryId\":\"1085\",\"ListUrlMain\":\"https://www.sciencedirect.com/science/article/pii/0368323066901455\",\"RegionNum\":0,\"RegionCategory\":null,\"ArticlePicture\":[],\"TitleCN\":null,\"AbstractTextCN\":null,\"PMCID\":null,\"EPubDate\":\"\",\"PubModel\":\"\",\"JCR\":\"\",\"JCRName\":\"\",\"Score\":null,\"Total\":0}","platform":"Semanticscholar","paperid":null,"PeriodicalName":"Journal of Nuclear Energy. Parts A/B. Reactor Science and Technology","FirstCategoryId":"1085","ListUrlMain":"https://www.sciencedirect.com/science/article/pii/0368323066901455","RegionNum":0,"RegionCategory":null,"ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":null,"EPubDate":"","PubModel":"","JCR":"","JCRName":"","Score":null,"Total":0}
The use of concrete for shielding high-temperature reactors
The possibility is examined of constructing thermal shields of reactors from chromite and fireclay heat-resistant concretes. Neutron fluxes of different intensities (up to 1013 n/cm2 sec, close in spectrum to the fission spectrum) absorbed by shields of these materials are examined. The passage of neutrons, y-ray fluxes and generation of heat in the shield are taken into account. The temperatures in the shield are calculated for different neutron fluxes, thicknesses of concrete and cooling conditions. A static calculation of the temperature stresses in a shield constructed from heat-proof reinforced concrete is carried out.
It is established that heat-resistant reinforced concrete can be used for the shields of nuclear reactors for neutron fluxes to the concrete up to 1013 n/cm2 sec, temperatures up to 1000–1100°C and temperature drops of up to 900°C.