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Volume 33 Issue 3
Mar.  2025
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ZOU Yang. Study on MCNP Related to Temperature-Dependent Neutron Cross Section Library Based on Different ENDF Format Databases[J]. Nuclear Power Engineering, 2012, 33(3): 12-16.
Citation: ZOU Yang. Study on MCNP Related to Temperature-Dependent Neutron Cross Section Library Based on Different ENDF Format Databases[J]. Nuclear Power Engineering, 2012, 33(3): 12-16.

Study on MCNP Related to Temperature-Dependent Neutron Cross Section Library Based on Different ENDF Format Databases

  • Received Date: 2011-04-11
  • Rev Recd Date: 2011-11-01
  • Available Online: 2025-03-08
  • Using the cross section processing procedures NJOY,two temperature-dependent neutron cross section libraries with the ACE(A Compact ENDF) format are generated based on the latest released ENDF/B-VII and CENDL-3.1,and are verified by PWR Doppler numerical benchmark problems.The results showed that these two cross section libraries were in good agreement with the original benchmark problems in the effective multiplication factor,Doppler reactivity loss and Doppler reactivity coefficient,which indicated that the two cross section libraries ENDF/B-VII and CENDL-3.1can be used in the production of ACE format cross section libraries.

     

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