THE CONCEPT STUDY ON THE NEW STEAM COOLING REACTOR

	THE CONCEPT STUDY ON THE NEW STEAM COOLING REACTOR
	ASME ; Yan, Xuesong1,3,4 ; Zhang, Xunchao1,3,4 ; Zhang, Yaling1,3,4 ; Yang, Yangyang 1,3,4; Yang, Lei1,3,4 ; Duan, Wenshan 2
	2017
英文摘要	Coolant is an important part of the nuclear reactor, which can convert the fission energy into heat. At the same time, it can cool the core, and control the various components of the reactor in the allowable temperature. In this paper, gas-liquid two-phase flow is proposed as the coolant in the nuclear reactor. Based on the Monte Carlo method of, particle transport program GMT program and LITAC program, the neutron performance, thermal hydraulic of nuclear reactor were calculated and analyzed. The operation of the new reactor will not be refuel for decades. The gas-liquid two-phase flow coolant can be used as one of the existing alternative coolants.
会议录	PROCEEDINGS OF THE 25TH INTERNATIONAL CONFERENCE ON NUCLEAR ENGINEERING, 2017, VOL 5
会议录出版者	AMER SOC MECHANICAL ENGINEERS
会议录出版地	THREE PARK AVENUE, NEW YORK, NY 10016-5990 USA
语种	英语
资助项目	"Strategic Priority Research Program" of the Chinese Academy of Sciences[XDA03030100]
WOS研究方向	Nuclear Science & Technology
WOS记录号	WOS:000426020300054
内容类型	会议论文
源URL	[http://119.78.100.186/handle/113462/58559]
专题	中国科学院近代物理研究所
通讯作者	Yan, Xuesong
作者单位	1.Chinese Acad Sci, Coll Phys & Elect Engn, Lanzhou 730000, Gansu, Peoples R China 2.Northwest Normal Univ, Coll Phys & Elect Engn, Lanzhou 730070, Peoples R China 3.Chinese Acad Sci, Inst Modern Phys, Joint Lab Atom & Mol Phys NWNU & IMP CAS, Lanzhou 730000, Gansu, Peoples R China 4.Northwest Normal Univ, Lanzhou 730070, Gansu, Peoples R China
推荐引用方式 GB/T 7714	ASME,Yan, Xuesong,Zhang, Xunchao,et al. THE CONCEPT STUDY ON THE NEW STEAM COOLING REACTOR[C]. 见:.