Neutronics Analysis and Optimization for Fusion Driven Subcritical Spent Fuel Burning System

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• 作者：Minghuang Wang ; Qiusun Zeng ; Jieqiong Jiang ; Yican Wu
• 关键词：Spent fuel burning ; Neutronics ; Fusion ; fission hybrid reactor
• 刊名：Journal of Fusion Energy
• 出版年：2015
• 出版时间：June 2015
• 年：2015
• 卷：34
• 期：3
• 页码：598-603
• 全文大小：723 KB
• 参考文献：1.W. Stacey, Capabilities of a DT tokamak fusion neutron source for driving a spent fuel transmutation reactor. Nucl. Fusion 41, 135-54 (2001)View Article ADS
  2.W. Stacey, C. Stewart et al., Resolution of fission and fusion technology integration issues: an upgraded design concept for the subcritical advanced burner reactor. Nucl. Technol. 187, 15-3 (2014)
  3.W. Stacey, Georgia tech studies of sub-critical advanced burner reactors with a D-T fusion tokamak neutron source for the transmutation of spent nuclear fuel. J. Fusion Energ 28, 328-33 (2009)View Article ADS
  4.L. Qiu, Y. Wu, B. Xiao, Q. Huang, B. Wu, Y. Chen, X. Liu, A low aspect ratio tokamak transmutation system. Nucl. Fusion 40, 629-33 (2000)View Article ADS
  5.Y. Wu et al., A fusion neutron source driven sub-critical nuclear energy system: a way for early application of fusion technology. Plasma Sci. Technol. 3, 1085-092 (2001)View Article ADS
  6.Y. Wu, S. Zheng et al., Conceptual design of the fusion-driven subcritical system FDS-I. Fusion Eng. Des. 81, 1305-311 (2006)View Article
  7.Y. Wu, FDS Team, Conceptual design activities of FDS series fusion power plants in China. Fusion Eng. Des. 81, 2713-718 (2006)View Article
  8.Y. Wu, Progress in fusion-driven hybrid system studies in China. Fusion Eng. Des. 63-4, 73-0 (2002)View Article
  9.Y. Wu, J. Qian, J. Yu, The fusion-driven hybrid system and its material selection. J. Nucl. Mater. 207-11, 1629-636 (2002)View Article
  10.M. Wang, J. Jiang et al., Neutronics analysis on helium-cooled blanket of a fusion-driven spent fuel burner. Chin. J. Nucl. Sci. Eng. 32, 260-65 (2012)
  11.Y. Wu et al., Neutronics analysis of the dual-cooled waste transmutation blanket for the FDS. Fusion Eng. Des. 63-4, 133-38 (2002)View Article
  12.Y. Wu et al., A fusion-driven subcritical system concept based on viable technologies. Nucl. Fusion 51, 103036 (2011)View Article ADS
  13.J. Jiang, B. Yuan, J. Zou, Y. Wu, Activation analysis and waste management for blanket materials of multi-functional experimental fusion-fission hybrid reactor (FDS-MFX). Fusion Eng. Des. 89, 405-11 (2014)View Article
  14.M. Ni, Y. Song, M. Jin, J. Jiang, Q. Huang, Design and analysis on tritium system of multi-functional experimental fusion-fission hybrid reactor (FDS-MFX). Fusion Eng. Des. 87(7-), 1004-008 (2012)View Article
  15.Y. Wu, J. Song, H. Zheng et al., CAD-based Monte Carlo program for integrated simulation of nuclear system SuperMC. Ann. Nucl. Energ. (2014). doi:10.-016/?j.?anucene.-014.-8.-58
  16.Y. Wu, FDS Team, CAD-based interface programs for fusion neutron transport simulation. Fusion Eng. Des. 84(7-1), 1987-992 (2009)View Article
  17.Y. Wu, Z. Xie, U. Fischer, A discrete ordinates nodal method for one-dimensional neutron transport calculation in curvilinear geometries. Nucl. Sci. Eng. 133(3), 350-57 (1999)
  18.J. Zou et al., Design and production of fine-group cross section library HENDL3.0/FG for subcritical system, in Proceeding of PHYSOR 2012, Advances in Reactor Physics, Knoxville, TN, USA, 15-0 April 2012
  19.J. Jiang et al., Integral data benchmark of HENDL2.0/MG compared with neutronics shielding experiments. Plasma Sci. Technol. 11, 625-31 (2009)View Article ADS
  20.Q. Huang et al., Progress in development of China low activation martensitic steel for fusion application. J. Nucl. Mater. 367-70, 142-46 (2007)View Article
  21.L.R. Greenwood, R.K. Smither, SPECTER: Neutron Damage Calculations For Materials Irradiations, ANL/FPP/TM-197, Report (Argonne NL, IL, USA, 1985)View Article
  
• 作者单位：Minghuang Wang (1)
  Qiusun Zeng (1)
  Jieqiong Jiang (1)
  Yican Wu (1)
  
  1. Key Laboratory of Neutronics and Radiation Safety, Institute of Nuclear Energy Safety Technology, Chinese Academy of Sciences, No. 350 Shushanhu Road, Hefei, 230031, Anhui, China
  
• 刊物类别：Engineering
• 刊物主题：Nuclear Engineering
  
• 出版者：Springer Netherlands
• ISSN：1572-9591

文摘

Neutronics analysis and optimization including general performances, burnup calculation analysis, materials activation characteristic and irradiation damage analysis of blanket for fusion driven subcritical spent fuel burner (FDS-SFB) were performed. The results showed the fission blanket could reach high performance in a long burn up when the mass percent of transuranic nuclides reach to 15?%, depleted uranium added to the blanket could improve the ability of nuclear waste incineration and fuel breeding and FDS-SFB is able to achieve efficient utilization of nuclear waste to produce energy without additional new nuclear waste production.