干旱区生态环境知识资源中心(Arid): Self-Sustaining Thorium Boiling Water Reactors

Arid

DOI	10.2172/1183773
报告编号	DOE/NEUP--11-3023
来源ID	OSTI_ID: 1183773
	Self-Sustaining Thorium Boiling Water Reactors
	Greenspan, Ehud [Univ. of California, Berkeley, CA (United States)]; Gorman, Phillip M. [Univ. of California, Berkeley, CA (United States)]; Bogetic, Sandra [Univ. of California, Berkeley, CA (United States)]; Seifried, Jeffrey E. [Univ. of California, Berkeley, CA (United States)]; Zhang, Guanheng [Univ. of California, Berkeley, CA (United States)]; Varela, Christopher R. [Univ. of California, Berkeley, CA (United States)]; Fratoni, Massimiliano [Univ. of California, Berkeley, CA (United States)]; Vijic, Jasmina J. [Univ. of California, Berkeley, CA (United States)]; Downar, Thomas [Univ. of Michigan, Ann Arbor, MI (United States)]; Hall, Andrew [Univ. of Michigan, Ann Arbor, MI (United States)]; Ward, Andrew [Univ. of Michigan, Ann Arbor, MI (United States)]; Jarrett, Michael [Univ. of Michigan, Ann Arbor, MI (United States)]; Wysocki, Aaron [Univ. of Michigan, Ann Arbor, MI (United States)]; Xu, Yunlin [Univ. of Michigan, Ann Arbor, MI (United States)]; Kazimi, Mujid [Massachusetts Inst. of Technology (MIT), Cambridge, MA (United States)]; Shirvan, Koroush [Massachusetts Inst. of Technology (MIT), Cambridge, MA (United States)]; Mieloszyk, Alexander [Massachusetts Inst. of Technology (MIT), Cambridge, MA (United States)]; Todosow, Michael [Brookhaven National Lab. (BNL), Upton, NY (United States)]; Brown, Nicolas [Brookhaven National Lab. (BNL), Upton, NY (United States)]; Cheng, Lap [Brookhaven National Lab. (BNL), Upton, NY (United States)]
英文摘要	The primary objectives of this project are to: Perform a pre-conceptual design of a core for an alternative to the Hitachi proposed fuel-self- sustaining RBWR-AC, to be referred to as a RBWR-Th. The use of thorium fuel is expected to assure negative void coefficient of reactivity (versus positive of the RBWR-AC) and improve reactor safety; Perform a pre-conceptual design of an alternative core to the Hitachi proposed LWR TRU transmuting RBWR-TB2, to be referred to as the RBWR-TR. In addition to improved safety, use of thorium for the fertile fuel is expected to improve the TRU transmutation effectiveness; Compare the RBWR-Th and RBWR-TR performance against that of the Hitachi RBWR core designs and sodium cooled fast reactor counterparts - the ARR and ABR; and, Perform a viability assessment of the thorium-based RBWR design concepts to be identified along with their associated fuel cycle, a technology gap analysis, and a technology development roadmap. A description of the work performed and of the results obtained is provided in this Overview Report and, in more detail, in the Attachments. The major findings of the study are summarized.
出版年	2015
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 ; REACTOR SAFETY ; VOID COEFFICIENT ; THORIUM ; SODIUM COOLED REACTORS ; DESIGN ; REACTOR CORES ; TRANSURANIUM ELEMENTS ; NUCLEAR FUELS ; COMPARATIVE EVALUATIONS ; FUEL CYCLE ; COMMERCIALIZATION ; PERFORMANCE ; TRANSMUTATION ; BWR TYPE REACTORS
URL	http://www.osti.gov/scitech/servlets/purl/1183773
资源类型	科技报告
条目标识符	http://119.78.100.177/qdio/handle/2XILL650/271118
推荐引用方式 GB/T 7714	Greenspan, Ehud [Univ. of California, Berkeley, CA ,Gorman, Phillip M. [Univ. of California, Berkeley, CA ,Bogetic, Sandra [Univ. of California, Berkeley, CA ,et al. Self-Sustaining Thorium Boiling Water Reactors,2015.