Knowledge Resource Center for Ecological Environment in Arid Area
DOI | 10.2172/5664449 |
报告编号 | ORNL-5398(Exec.Summ.) |
来源ID | OSTI_ID: 5664449 |
Interim assessment of the denatured /sup 233/U fuel cycle: feasibility and nonproliferation characteristics | |
Abbott, L.S.; Bartine, D.E.; Burns, T.J. (eds.) | |
英文摘要 | A fuel cycle that employs /sup 233/U denatured with /sup 238/U and mixed with thorium fertile material is examined with respect to its proliferation-resistance characteristics and its technical and economic feasibility. The rationale for considering the denatured /sup 233/U fuel cycle is presented, and the impact of the denatured fuel on the performance of Light-Water Reactors, Spectral-Shift-Controlled Reactors, Gas-Cooled Reactors, Heavy-Water Reactors, and Fast Breeder Reactors is discussed. The scope of the R, D and D programs to commercialize these reactors and their associated fuel cycles is also summarized and the resource requirements and economics of denatured /sup 233/U cycles are compared to those of the conventional Pu/U cycle. In addition, several nuclear power systems that employ denatured /sup 233/U fuel and are based on the energy center concept are evaluated. |
出版年 | 1979 |
报告类型 | Technical Report |
语种 | 英语 |
国家 | 美国 |
来源学科分类 | 21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS ; BWR TYPE REACTORS ; FUEL CYCLE ; FEASIBILITY STUDIES ; HEAVY WATER MODERATED REACTORS ; HTGR TYPE REACTORS ; LMFBR TYPE REACTORS ; PWR TYPE REACTORS ; DENATURED FUEL ; ECONOMICS ; REPROCESSING ; BREEDER REACTORS ; ENERGY SOURCES ; EPITHERMAL REACTORS ; FAST REACTORS ; FBR TYPE REACTORS ; FUELS ; GAS COOLED REACTORS ; GRAPHITE MODERATED REACTORS ; LIQUID METAL COOLED REACTORS ; NUCLEAR FUELS ; REACTOR MATERIALS ; REACTORS ; SEPARATION PROCESSES ; WATER COOLED REACTORS ; WATER MODERATED REACTORS 210802* -- Nuclear Power Plants-- Economics-- Fuel Cycle ; 210100 -- Power Reactors, Nonbreeding, Light-Water Moderated, Boiling Water Cooled ; 210200 -- Power Reactors, Nonbreeding, Light-Water Moderated, Nonboiling Water Cooled ; 210300 -- Power Reactors, Nonbreeding, Graphite Moderated ; 210500 -- Power Reactors, Breeding |
URL | http://www.osti.gov/scitech/servlets/purl/5664449 |
资源类型 | 科技报告 |
条目标识符 | http://119.78.100.177/qdio/handle/2XILL650/262549 |
推荐引用方式 GB/T 7714 | Abbott, L.S.,Bartine, D.E.,Burns, T.J. . Interim assessment of the denatured /sup 233/U fuel cycle: feasibility and nonproliferation characteristics,1979. |
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