Periodically Reloading and Transmutation Characteristics Numerical Analysis of TRU Fueled Thermal Molten Salt Reactor

被引：0

作者：

Yu T. ^{[1
]}

Xie J. ^{[1
]}

Zhao W. ^{[1
]}

Chen Z. ^{[1
]}

Xie Q. ^{[1
]}

Liu Z. ^{[1
]}

机构：

[1] University of South China, School of Nuclear Science and Technology, Hengyang, 421001, Hunan

来源：

Hedongli Gongcheng/Nuclear Power Engineering | 2018年 / 39卷 / 03期

关键词：

Long refueling cycle; Thermal spectrum MSR; Transmutation; TRU fuel;

D O I：

10.13832/j.jnpe.2018.03.0018

中图分类号：

学科分类号：

摘要：

The molten salt reactor (MSR) features convenient fuel fabrication, good neutron economy and flexible fuel management, has and there is the potential to utilize the TRU produced in the spent fuel of the light water reactor directly. The selection of fuel, lattice parameters and fuel/graphite volume fraction has been optimized in this paper. Through the calculating and analyzing the core lifetime of the TRU fueled thermal spectrum MSR, the stock of TRU, MA-fission ratio and TRU-fission ratio, it proves that thermal spectrum MSR can operate for a long period with long refueling cycle, which can reduce the difficulty of online refueling and have a better transmutation ratio of MA and TRU with lower radioactive toxicity. © 2018, Editorial Board of Journal of Nuclear Power Engineering. All right reserved.

引用

页码：18 / 22

页数：4

共 8 条

[1]

Yu T., Wu X., Xie J.-S., Et al., A study on the burn-up characteristics of inert matrix fuels, Progress in Nuclear Energy, 78, pp. 341-345, (2015)

[2]

Ignatiev V., Feynberg O., Gnidoi I., Et al., Progress in development of Li, Be, Na/F molten salt actinide recycler and transmuter concept, Proceedings of ICAPP, (2007)

[3]

Vergnes J., The AMSTER Concept (Actinide Molten Salt TransmutER), Physor 2000 Conference, (2000)

[4]

Ignatiev V., Surenkov A., Material Performance in Molten Salts, (2012)

[5]

Vanderhaegen M., Janssens-Maenhout G., Considerations on safety and proliferation-resistant aspects for the MSBR design, Nuclear Engineering & Design, 240, 3, pp. 482-488, (2010)

[6]

Bell M.J., Calculated radioactivity of MSRE fuel salt, (1970)

[7]

Sheu R.J., Chang C.H., Chao C.C., Depletion analysis on long-term operation of the conceptual molten salt actinide recycler & transmuter (mosart) by using a special sequence based on SCALE6/TRITON, Annals of Nuclear Energy, 53, pp. 1-8, (2013)

[8]

Royc R., Conceptual design study of a singlefluid molten-salt breeder reactor, (1971)

← 1 →