1 |
MacPherson H G. Molten-salt reactor program quarterly progress report[R]. Tennessee: ORNL-2890,1960: 1-76.
|
2 |
Litman A P, Goldman A E, Corrosion associated with fluorination in the oak ridge national laboratory fluoride volatility process[R]. Tennessee: ORNL-2832,1960: 1-188.
|
3 |
Haubenreich P N, Engel J R, Prince B E,et al. MSRE design and operations report, Ⅲ Part, nuclear analysis[R]. Tennessee: ORNL-TM-730, 1964: 1-199.
|
4 |
Cantor S, Cooke J W, Dworkin A S,et al. Physical properties of molten-salt reactor fuel, coolant and flush salts[R]. Tennessee: ORNL-TM-2316,1968: 1-49.
|
5 |
ORNL. Conceptual design study of a single-fluid molten-salt breeder reactor[R]. Tennessee: ORNL-TM-4541, 1971: 1-189. DOI: 10.2172/4030941
|
6 |
Bulmer J J, Gift E H, Holl R J, et al. Reactor design and feasibility study: fused salt fast breeder[R]. Tennessee: Oak Ridge School of Reactor Technology, 1956.
|
7 |
Whatley M E, Mcneese L E, Carter W L, et al. Engineering development of the MSBR fuel recycle[J]. Nuclear Applications and Technology, 1970, 8(2): 170–178. DOI: 10.13182/NT70-A28623.
doi: 10.13182/NT70-A28623
|
8 |
何迅, 曾畅, 余小权, 等. 双流体熔盐快堆概念设计可行性研究[J]. 核动力工程, 2019, 40(1): 42-47. DOI: 10.13832/j.jnpe.2019.01.0042.
doi: 10.13832/j.jnpe.2019.01.0042
|
|
HE Xun, ZENG Chang, YU Xiaoquan, et al. Feasibility study on conceptual design of dual fluid fast reactor[J]. Nuclear Power Engineering, 2019, 40(1): 42-47. DOI: 10.13832/j.jnpe.2019.01.0042.
doi: 10.13832/j.jnpe.2019.01.0042
|
9 |
彭一鹏, 余呈刚, 崔德阳. 钍基氯盐快堆燃耗性能分析[J]. 核技术, 2018, 41(7): 070602. DOI: 10.11889/j.0253-3219.2018.hjs.41.070602.
doi: 10.11889/j.0253-3219.2018.hjs.41.070602
|
|
PENG Yipeng, YU Chenggang, CUI Deyang, et al. Analysis of burnup performance for a molten chloride salt fast reactor based on thorium fuel[J]. Nuclear Techniques, 2018, 41(7): 070602. DOI: 10.11889/j.0253-3219.2018.hjs.41.070602.
doi: 10.11889/j.0253-3219.2018.hjs.41.070602
|
10 |
彭一鹏, 奚坤潘, 登朱帆. 双区氯盐快堆的增殖及嬗变性能分析[J]. 核安全, 2019, 18(2): 36-42. DOI: 10.16432/j.cnki.1672-5360.2019.02.004.
doi: 10.16432/j.cnki.1672-5360.2019.02.004
|
|
Yipenɡ PENɡ, XI Kunpɑn, Zhufɑn DENɡ. Analysis of breeding and transmutation performance for a double-zone chloride salt fast reactor[J]. Nuclear Safety, 2019, 18(2): 36-42. DOI: 10.16432/j.cnki.1672-5360.2019.02.004.
doi: 10.16432/j.cnki.1672-5360.2019.02.004
|
11 |
Scott I, Abram T, Negri O. Stable salt reactor design concept[C]. Proceedings of the International Thorium Energy Conference: Gateway to Thorium Energy, 2015.
|
12 |
Huke A, Ruprecht G, Weißbach D, et al. The dual fluid reactor - a novel concept for a fast nuclear reactor of high efficiency[J]. Annals of Nuclear Energy, 2015, 80: 225-235. DOI: 10.1016/j.anucene.2015.02.016.
doi: 10.1016/j.anucene.2015.02.016
|
13 |
Heuer D, Merle-Lucotte E, Allibert M, et al. Towards the thorium fuel cycle with molten salt fast reactors[J]. Annals of Nuclear Energy, 2014, 64: 421-429. DOI: 10.1016/j.anucene.2013.08.002
doi: 10.1016/j.anucene.2013.08.002
|
14 |
Chloride reactor research founded by DOE[EB/OL]. 2015-7-31. .
|
15 |
张书成, 刘平, 仉宝聚. 钍资源及其利用[J]. 世界核地质科学, 2005, (2): 98-103. DOI: 10.3969/j.issn.1672-0636.2005.02.008.
doi: 10.3969/j.issn.1672-0636. 2005.02.008
|
|
ZHANG Shucheng, LIU Ping, XI Baoju, Thorium resources and utilization[J]. World Nuclear Geology, 2005, (2): 98-103. DOI: 10.3969/j.issn.1672-0636. 2005.02.008
doi: 10.3969/j.issn.1672-0636. 2005.02.008
|
16 |
张家桦, 包伯荣, 夏源贤. 钍铀核燃料循环研究[J]. 核技术, 1988, 11(10): 27-33.
|
|
ZHANG Jiahua, BAO Borong, XIA Yuanxian, Thorium uranium nuclear fuel cycle research[J]. Nuclear Techniques, 1988, 11(10): 27-33
|
17 |
江绵恒, 徐洪杰, 戴志敏. 未来先进核裂变能——TMSR核能系统[J]. 中国科学院院刊, 2012, 27(3): 366–374. DOI: 10.3969/j.issn.1000-3045.2012.03.016.
doi: 10.3969/j.issn.1000-3045.2012.03.016
|
|
JIANG Mianheng, XU Hongjie, DAI Zhimin. Advanced fission energy program - TMSR nuclear energy system[J]. Chinese Academy Journal Electronic Publishing House, 2012, 27(3): 366-374. DOI: 10.3969/j.issn.1000-3045.2012.03.016.
doi: 10.3969/j.issn.1000-3045.2012.03.016
|
18 |
谢仲生. 核反应堆物理分析[M]. 西安: 西安交通大学出版社, 2004: 191-198.
|
|
XIE Zhongsheng, Nuclear reactor physical analysis[J]. Xi'an: Xi'an Jiaotong University Press, 2004: 191-198.
|
19 |
徐怠. 快堆的燃料增殖[J]. 高技术通讯, 1998, 10: 54-56.
|
|
XU Dai, Fast reactor fuel proliferation[J]. Chinese High Technology Letters, 1998, 10: 54-56.
|
20 |
Thoma R E, Grimes W R. Phase equilibrium diagrams for fused salt systems[R]. ORNL-2295,1957: 1-86.
|
21 |
Janz G J, Gardner G L, Krebs U, et al. Fluorides and mixtures electrical conductance, density, viscosity, and surface tension data[J]. Journal of Physical and Chemical Reference Data, 1974, 3(1): 1-115.
|
22 |
Mourogov A, Bokov P M. Potentialities of the fast spectrum molten salt reactor concept: REBUS-3700[J]. Energy Conversion and Management, 2006, 47(17): 2761-2771. DOI: 10.1016/j.enconman.2006.02.013.
doi: 10.1016/j.enconman.2006.02.013
|
23 |
Bystrai G P, Desyatnik V N, Zlokazov V A. Thermal conductivity of molten mixtures of uranium tetrachloride with sodium and potassium chlorides[J]. Soviet Atomic Energy, 1974, 36: 654-65. DOI: 10.1007/BF01127242.
doi: 10.1007/BF01127242
|