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Volume 27 Issue 4
Aug.  2006
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LI Dong-sheng. In-Core Fuel Management Design for CNP1500[J]. Nuclear Power Engineering, 2006, 27(4): 1-4.
Citation: LI Dong-sheng. In-Core Fuel Management Design for CNP1500[J]. Nuclear Power Engineering, 2006, 27(4): 1-4.

In-Core Fuel Management Design for CNP1500

  • Received Date: 2005-10-25
  • Rev Recd Date: 2006-04-27
  • Available Online: 2025-07-29
  • CNP 1500 is a four-loop PWR nuclear power plant with light water as moderator and coolant. The reactor core is composed of 205 AFA-3GXL fuel assemblies.The active core height at cold is 426.4cm and equivalent diameter is 347.0cm.The reactor thermal output is 4250MW,and the average linear power density is 179.5W/cm.Calculation results show that the cycle length of equilibrium cycle core reaches to 470 equivalent full power days,and for all cycles,the moderator temperature coefficients at all conditions are negative values,the nuclear enthalpy rise factors F△H at hot full power,all control rods out and equilibrium xenon are less than the limit value,the maximum discharge assembly burnup is less 55000MW·d/t(U),and the shutdown margin values at the end of life meet design criteria.The low-leakage core loading reduces ra- diation damage on pressure vessel and is beneficial to prolong use lifetime of it.This paper presents the in-core fuel management design scheme and main calculation results:for CNP 1500 nuclear power plant.

     

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      沈阳化工大学材料科学与工程学院 沈阳 110142

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