THE CONCEPT STUDY ON THE NEW STEAM COOLING REACTOR
文献类型：会议论文
| 作者 | Yan, Xuesong1,2,3 ; Zhang, Xunchao1,2,3; Zhang, Yaling1,2,3; Yang, Yangyang1,2,3; Yang, Lei1,2,3; Duan, Wenshan4; ASME
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| 出版日期 | 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
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| 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 |
| 源URL | [http://119.78.100.186/handle/113462/58560]  |
| 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, Lanzhou 730070, Gansu, 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, Coll Phys & Elect Engn, Lanzhou 730070, Peoples R China |
| 推荐引用方式 GB/T 7714 | Yan, Xuesong,Zhang, Xunchao,Zhang, Yaling,et al. THE CONCEPT STUDY ON THE NEW STEAM COOLING REACTOR[C]. 见:. |
入库方式： OAI收割
来源：近代物理研究所
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