Nuclear Science and Techniques ›› 2019, Vol. 42 ›› Issue (3): 30601-030601.doi: 10.11889/j.0253-3219.2019.hjs.42.030601

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Uncertainties analysis of reactivity parameters caused by nuclear data of molten salt experiment reactor

Jifeng HU1,2,Xiaohe WANG1,2,Wenjiang LI1,2,Xiaoxiao LI1,2,Jianlong HAN1,2()   

  1. 1. Shanghai Institute of Applied Physics, Chinese Academy of Sciences, Shanghai 201800, China
    2. Innovative Academies in TMSR Energy System, Chinese Academy of Sciences, Shanghai 201800, China
  • Received:2018-11-07 Revised:2018-12-27 Online:2019-03-10 Published:2019-03-14
  • Contact: Jianlong HAN E-mail:hanjianlong@sinap.ac.cn;hanjianlong@sinap.ac.cm
  • About author:<named-content content-type="corresp-name">HU Jifeng</named-content>, male, born in 1984, graduated from Lanzhou University with a master’s degree in 2010, focusing on the nuclear data|<named-content content-type="corresp-name">HU Jifeng</named-content>, male, born in 1984, graduated from Lanzhou University with a master’s degree in 2010, focusing on the nuclear data|HAN Jianlong, E-mail:<email>hanjianlong@sinap.ac.cn</email>
  • Supported by:
    Supported by Strategic Priority Research Program of Chinese Academy of Sciences (No.XDA02010000), Frontier Science Key Program of Chinese Academy of Sciences(No.QYZDY-SSW-JSC016);Supported by Strategic Priority Research Program of Chinese Academy of Sciences (No.XDA02010000), Frontier Science Key Program of Chinese Academy of Sciences (No.QYZDY-SSW-JSC016)

Abstract: Background

Uncertainty analysis is an essential and mandatory work for reactor design. Nuclear data is an important origin of uncertainty in reactivity parameters.

Purpose

This study aims to obtain and analyze the uncertainty of reactivity parameters and the more significant nuclear data of molten salt experiment reactor.

Methods

The transport rigor implemented with time-dependent operation for neutronic depletion (TRITON), tools for sensitivity and uncertainty analysis methodology implementation in three dimensions (TSUNAMI-3D) and tool for sensitivity analysis of reactivity responses (TSAR) modules of SCALE code are combined with its 44-group covariance data library to analyze the uncertainties of k eff at the beginning of life (BOL) and the end of life (EOL), control rod worth (CRW) and temperature coefficients (TC) for molten salt experiment reactor, etc.

Results

The uncertainties are 522×10-5 and 506×10-5 for k eff at BOL and EOL, and 96.70×10-5, 8.90×10-5 for CRW and TC respectively.

Conclusion

The analysis for sensitivity coefficients and covariation data shows that the reaction data of 235U( ν ˉ ), (n,γ), 238U(n,γ), C-graphite (n,el), 7Li(n,γ), 239Pu( ν ˉ ), (n,f) and 135Xe(n,γ) are more significant for k eff uncertainty, and 19F(n,el), 58Ni(n,γ), 6Li(n,t) are important for uncertainties of CRW and TC.

Key words: Molten salt experiment reactor, Nuclear data, Reactivity, Uncertainty and sensitivity

CLC Number: 

  • TL329