Preliminary analysis of Tritium fuel cycle in Z-pinch driven fusion-fission hybrid reactor

Yong-Gang Mo; Zhi-Lin Chen; Hong-Hu Song; Yang Yang; Jing Wu; Dong Zhang

doi:10.1007/s41365-018-0441-x

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Preliminary analysis of Tritium fuel cycle in Z-pinch driven fusion-fission hybrid reactor

NUCLEAR ENERGY SCIENCE AND ENGINEERING | Updated：2021-02-07

- Preliminary analysis of Tritium fuel cycle in Z-pinch driven fusion-fission hybrid reactor
- Nuclear Science and Techniques Vol. 29, Issue 7, Article number: 101(2018)
- Affiliations：
  
  1.China Academy of Engineering Physics, Institute of Nuclear Physics and Chemistry, Mianyang 621000, China
- Author bio：
  
  Corresponding author: zd0823@caep.cn
- Funds：
- DOI：10.1007/s41365-018-0441-x
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Yong-Gang Mo, Zhi-Lin Chen, Hong-Hu Song, et al. Preliminary analysis of Tritium fuel cycle in Z-pinch driven fusion-fission hybrid reactor. [J]. Nuclear Science and Techniques 29(7):101(2018)
DOI：

Yong-Gang Mo, Zhi-Lin Chen, Hong-Hu Song, et al. Preliminary analysis of Tritium fuel cycle in Z-pinch driven fusion-fission hybrid reactor. [J]. Nuclear Science and Techniques 29(7):101(2018) DOI： 10.1007/s41365-018-0441-x.

摘要

Abstract

Attaining tritium self-sufficiency is indispensable in a Z-pinch driven fusion-fission hybrid reactor (Z-FFR). In this paper a conceptual design is presented in which the Z-FFR tritium cycle system was divided into eight subsystems. A theoretical analysis of tritium inventory based on the mean residence time was performed to quantitatively obtain the tritium distribution in each subsystem. Tritium self-sufficiency judgment criteria was established using a tritium mass flow analysis method. The dependency relationships between the burning rate, tritium breeding ratio, extraction efficiency, and tritium self-sufficiency were also specified for the steady state.

关键词

Keywords

Z-FFRTritiumSelf-sufficiency

references

J. Freidberg, P. Finck, C. Bolton et al., Research needs for fusion-fission hybrid systems. Report of the research needs workshop (ReNeW), Gaithersburg, Maryland. 2009

T.A. Mehlhorn, B.B. Cipiti, C.L. Olson et al., Fusion-fission hybrids for nuclear waste transmutation: A synergistic step between Gen-IV fission and fusion reactors. Fusion Eng. Des. 83, 948-953 (2008). doi: 10.1016/j.fusengdes.2008.05.003http://doi.org/10.1016/j.fusengdes.2008.05.003

E.I. Moses, A sustainable nuclear fuel cycle based on laser inertial fusion energy. Fusion Sci Tech. 56, 547-565 (2009). doi: 10.13182/FST09-34http://doi.org/10.13182/FST09-34

B.B. Cipiti, V.D. Cleary, J.T. Cook et al., Fusion transmutation of waste: design and analysis of the in-zinerator concept. Sandia National Laboratories. To be published SAND report, SAND, 2006

L. El-Guebaly, B. Cipiti, P.H. Wilson et al., Engineering issues facing transmutation of actinides in Z-pinch fusion power plant. Paper presented at the 17th ANS topical meeting on fusion energy, Albuquerque, NM, 13-15 November 2006

M. Sawan, L. El-Guebaly, P. Wilson, Three-dimensional nuclear assessment for the chamber of Z-Pinch power plant. Paper presented at the 17th ANS topical meeting on fusion energy, Albuquerque, NM, 13-15 November 2006

X.J. Peng, Z-pinch Fusion-fission Hybrid Reactor——The Energy Technology Road with Great Competitive Power. J Southwest Univer Sci Technol. 4, 002(2010). doi: 10.3969/j.issn.1671-8755.2010.04.001http://doi.org/10.3969/j.issn.1671-8755.2010.04.001(in Chinese)

X.J. Peng, Z. Wang, Conceptual research on Z-pinch driven fusion-fission hybrid reactor. High Power Laser and Particle Beams. 26, 090201(2014). doi: 10.11884/HPLPB201426.090201http://doi.org/10.11884/HPLPB201426.090201(in Chinese)

J.M. Ma, H.B. Guo, Z.Y. Liu et al., Neutronic analysis of Z-pinch driven fusion-fission hybrid reactor blanket. High Power Laser and Particle Beams. 27,205-210(2015). doi: 10.11884/HPLPB201527.016002http://doi.org/10.11884/HPLPB201527.016002(in Chinese)

T. Tanabe, Tritium handling issues in fusion reactor materials. J. Nucl. Mater. 417, 545-550(2011). doi: 10.1016/j.jnucmat.2010.12.112http://doi.org/10.1016/j.jnucmat.2010.12.112

T. Tanabe, Tritium issues to be solved for establishment of a fusion reactor. Fusion Eng. Des. 87, 722-727(2012). doi: 10.1016/j.fusengdes.2012.02.009http://doi.org/10.1016/j.fusengdes.2012.02.009

B. Bornschein, C. Day, D. Demange et al., Tritium management and safety issues in ITER and DEMO breeding blankets. Fusion Eng. Des. 88, 466-471(2013). doi: 10.1016/j.fusengdes.2013.03.032http://doi.org/10.1016/j.fusengdes.2013.03.032

C. Day, T. Giegerich, The direct internal recycling concept to simplify the fuel cycle of a fusion power plant. Fusion Eng. Des. 88, 616-620(2013). doi: 10.1016/j.fusengdes.2013.05.026http://doi.org/10.1016/j.fusengdes.2013.05.026

Z.H. Li, H.W. Huang, Z. Wang et al., Conceptual design of Z-pinch driven fusion-fission hybrid power reactor. High Power Laser and Particle Beams. 26, 14-20(2014). doi: 10.11884/HPLPB201426.100202http://doi.org/10.11884/HPLPB201426.100202(in Chinese)

B. Deng, J. Huang, Mean residence time method of tritium inventory calculation. Fusion Eng. Des. 55,359-364(2001). doi: 10.1016/S0920-3796(01)00180-6http://doi.org/10.1016/S0920-3796(01)00180-6

M.A. Abdou, E.L. Vold, C.Y. Gung et al., Deuterium-tritium fuel self-sufficiency in fusion reactors. Fusion. Technol. 9,250-285 (1986). doi: 10.13182/FST86-1http://doi.org/10.13182/FST86-1

M.Y. Ni. Research on fuel cycle and tritium resource sustainability for fusion reactor. Univer Sci Technol China, 2013(in Chinese)

J.L. Anderson, The status of tritium technology development for magnetic fusion energy. Paper presented at the 5th topical meeting on technology of fusion energy, Knoxville, TN, USA, 26 Apr. 1983

C.L. Talcott, J.L. Anderson, R.V. Carlson et al., Three tritium systems test assembly (TSTA) off-loop experiments. Paper presented at Symposium on fusion engineering, Hyannis, MA, USA, 11 Oct. 1993

J.L. Anderson, J.R. Bartlit, The development of tritium technology at the tritium systems test assembly. Paper presented at the 12th symposium on fusion technology, Juelich, F.R. Germany, 13 Sep. 1982

H.L. Chen, L. Pan, Z. Lv et al., Tritium fuel cycle modeling and tritium breeding analysis for CFETR. Fusion Eng. Des. 106, 17-20(2016). doi: 10.1016/j.fusengdes.2016.02.100http://doi.org/10.1016/j.fusengdes.2016.02.100

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