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Research on alarm threshold of damage monitoring channel for fuel element in PWR nuclear power plant |
JIA Jingxuan1, WU Rongjun1, WANG Yiyuan1, LI Wenzhi2, NIE Lingxiao1, XU Jingjing1 |
1. Wuhan Secondary Institute of Ships, Wuhan 4300642 China; 2. Dalian Institute of Measurement and Control Technology |
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Abstract Objective The calculation method of the fuel element cladding damage monitoring channel measurement value in PWR (Rressurized Water Rector) nuclear power plant under different operating conditions is established.The dose rate of the channel was calculated under the condition of three primary coolant concentrations. Guide the setting of alarm threshold for the monitoring channel.Methods This article analyzed the radioactive nuclides in the primary coolant under different operating conditions of PWR nuclear power plant.According to the actual design of the fuel element damage monitoring channel, the calculation model is established by MCAM modeling software. The model can be used for MCNP software calculation. The measured values of the fuel element damage monitoring channel are calculated in three different operating conditions.Results Under three operating conditions, the calculated value of the monitoring channel are 8.0×10-6Gy/h、5.3×10-4Gy/h、1.6×10-3Gy/h.Conclusion It is suggested that 5.3×10-4Gy/h and 1.6×10-3Gy/h are set to two alarm thresholds. The setting of the alarm threshold is equivalent to the operating threshold of the active power station.
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Received: 22 January 2018
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