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Study of on-the-fly Doppler broadening in JMCT program

Liu Xiong-Guo Deng Li Hu Ze-Hua Li Rui Fu Yuan-Guang Li Gang Wang Jia

Study of on-the-fly Doppler broadening in JMCT program

Liu Xiong-Guo, Deng Li, Hu Ze-Hua, Li Rui, Fu Yuan-Guang, Li Gang, Wang Jia
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  • Received Date:  22 December 2015
  • Accepted Date:  24 January 2016
  • Published Online:  05 May 2016

Study of on-the-fly Doppler broadening in JMCT program

    Corresponding author: Deng Li,
  • 1. Graduate School of China Academy of Engineering Physics, Beijing 100088, China;
  • 2. Institute of Applied Physics and Computed Mathematics (IAPCM), Beijing 100088, China;
  • 3. CAEP Software Center for High Performance Numerical Simulation, Beijing 100088, China
Fund Project:  Project supported by the Project of Bureau of Energy, China (Grant No. 2015 ZX06002008), the Key Program of the National Natural Science Foundation of China (Grant No. 91118001), the Project of the Defense Department Labor Bureau, China (Grant No. [2012]1523), the Science Foundation of China Academy of Engineering Physics (Grant No. 2014B0202029), and the National High Technology Research and Development Program of China (Grant No. 2012AA01A303).

Abstract: In this paper, we introduce the on-the-fly (OTF) Doppler method which is used to calculate the temperature-dependent cross section. After substituting Adler-Adler multilevel representation into Doppler formulation, the theoretical formulation of temperature dependent cross section is obtained. This theoretical formulation can be approximated by a Taylor series expansion and asymptotic series expansion, which is the base of OTF method. The OTF method can be used to calculate the cross section of any nuclide at any temperature in a range of 300-3000 K based on cross section library of 300 K. For the OTF method, firstly, a series of temperature dependent cross section libraries is produced by NJOY. Secondly, a uniform energy grid is evaluated by the temperature dependent cross section libraries. Thirdly, a polynomial is used to fit the temperature dependent cross section on each energy grid. The coefficient of the polynomial is obtained by single value decomposition algorithm. Finally, the coefficients of the polynomial in all energy grids and the energy grids themselves are written in a text file. To test the cross section polynomial produced by OTF method, we compare the total and absorption cross sections of 238U and 235U calculated by the polynomial with those produced by NJOY. The errors of these cross sections obtained by these two programs are presented in the paper. The text file produced by OTF method can be read by the Monte Carlo code JMCT, which is a coupled neutron/photon transport code developed by IAPCM. After providing the temperature and energy of the particle, the temperature dependent cross sections in two adjacent energy grids are calculated by the polynomial respectively. The cross section of target energy is obtained by linear interpolation. Two benchmarks including a pin-cell model and an assembly model are used to verify the applications of OTF method in JMCT. The results are presented in the paper.

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