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Volume 35 Issue S2
Feb.  2025
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Tang Songqian, Tan Yi, Ying Dongchuan, Wei Shuping. Research of Neutron Fluence Computation Methods for MOX Fuelled Reactor Core[J]. Nuclear Power Engineering, 2014, 35(S2): 27-30. doi: 10.13832/j.jnpe.2014.S2.0027
Citation: Tang Songqian, Tan Yi, Ying Dongchuan, Wei Shuping. Research of Neutron Fluence Computation Methods for MOX Fuelled Reactor Core[J]. Nuclear Power Engineering, 2014, 35(S2): 27-30. doi: 10.13832/j.jnpe.2014.S2.0027

Research of Neutron Fluence Computation Methods for MOX Fuelled Reactor Core

doi: 10.13832/j.jnpe.2014.S2.0027
  • Received Date: 2014-11-06
  • Rev Recd Date: 2015-01-27
  • Available Online: 2025-02-15
  • Changes in the mechanical properties of reactor vessel materials result from the exposure to the fast neutron. The use of MOX fuel in LWRs presents different neutron characteristics, and it is worthy to study whether the present software can calculate the structural integrity of reactor components. This paper use MCNP, TORT and SCALE to calculate VENUS-2 benchmark, and the calculation shows that all this software can get reasonable result that can be used in the design. MCNP has the highest accuracy.

     

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