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Volume 38 Issue S1
Feb.  2025
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Hu Tianliang, CAO Liangzhi, Wu Hongchun, ZHuang Kun. Calculation and Analysis of Effective Delayed Neutron Fraction βeff in MSR[J]. Nuclear Power Engineering, 2017, 38(S1): 37-40. doi: 10.13832/j.jnpe.2017.S1.0037
Citation: Hu Tianliang, CAO Liangzhi, Wu Hongchun, ZHuang Kun. Calculation and Analysis of Effective Delayed Neutron Fraction βeff in MSR[J]. Nuclear Power Engineering, 2017, 38(S1): 37-40. doi: 10.13832/j.jnpe.2017.S1.0037

Calculation and Analysis of Effective Delayed Neutron Fraction βeff in MSR

doi: 10.13832/j.jnpe.2017.S1.0037
  • Received Date: 2017-02-20
  • Rev Recd Date: 2017-04-26
  • Available Online: 2025-02-09
  • The effective delayed neutron fraction(βeff) plays an extremely important role in the dynamics behavior of the reactors. In molten salt reactors(MSRs), because of the adoption of the fluid fuel, the calculation of the βeff is different with that in the traditional solid-fuel reactor. This work concentrates on the calculation of the βeff in MSRs. The βeff of the MOSART was calculated and the effect of external-loop transit time and inlet velocity on the βeff is analyzed in detail in this paper. The results indicate that the increasing of the external-transit time decreases the βeff, and the increasing of the inlet-velocity also decreases the βeff.

     

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