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Volume 34 Issue 4
Mar.  2025
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HU Wen-chao, OUYANG Xiao-ping, LIU Bin, WANG Kai, HUANG Li-ming. Validation of Accelerator Driven Subcritical Reactors Utilizing MCNP Code[J]. Nuclear Power Engineering, 2013, 34(4): 12-15.
Citation: HU Wen-chao, OUYANG Xiao-ping, LIU Bin, WANG Kai, HUANG Li-ming. Validation of Accelerator Driven Subcritical Reactors Utilizing MCNP Code[J]. Nuclear Power Engineering, 2013, 34(4): 12-15.

Validation of Accelerator Driven Subcritical Reactors Utilizing MCNP Code

  • Received Date: 2012-03-26
  • Rev Recd Date: 2012-09-06
  • Available Online: 2025-03-08
  • In this paper,some characteristics of the ADS subcritical reactor core is described using the Monte Carlo code(MCNP).The keff value,neutron energy spectrum and neutron flux of a ADS system are obtained by the MCNP code under certain ADS core size as the ADS target and coolant are lead,lead-bismuth alloy,bismuth and mercury respectively.The data and the ADS system parameters obtained from the MCNP simulation calculation are compared and analyzed.The results show that the lead-bismuth alloy is the best material for ADS target and coolant among all the materials tested.

     

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