RADIATION PROTECTION ›› 2020, Vol. 40 ›› Issue (6): 631-639.

• Radiological Risk Management • Previous Articles     Next Articles

Analysis on γ radiation variation of the spent fuel pool in PWR NPP

HU Yipeng   

  1. Fujian Fuqing Nuclear Power Co. Ltd.,Fujian Fuqing 350500
  • Online:2020-11-20 Published:2021-01-27

Abstract: 58Co is the key γ radiation source of activated corrosion products of PWR nuclear power plant.Influenced by pH value and temperature variation,the solubility of activated corrosion products containing 58Co will change continuously.During a shutdown process in Fuqing NPP,the specific activity of 58Co in primary coolant was found to increase continuously as the coolant temperature drops.Meanwhile after completing fuel unloading within an outage period,the water temperature raised,leading an increase of the 58Co specific activity in the spent-fuel pool,of which the maximum surface γ dose rate was reaching about 10 times of the designed value.By analyzing the specific activity of 58Co,γ dose rate level and temperature variation trend in the two cases,as well as the system operation records comparison,it can be confirmed that the increase of 58Co specific activity for both cases is closely related to the solution temperature.Under acidic environment,the solubility of activated corrosion products containing 58Co has a positive temperature coefficient within a certain temperature range,which means the solubility will increase with the temperature rise.After reaching the maximum value,the solubility,decreasing with the temperature raise,shows a negative temperature coefficient.According to the conclusion,the specific activity of 58Co was successfully reduced by starting the spare cooling circuit for the spent-fuel pool,of which the tem-perature drops.Finally,the surface γ dose rate of the spent-fuel pool quickly returned to the normal level,avoiding additional radiation exposure for the subsequent fuel operators.This successful practice provided a new idea for inhibiting and removing 58Co in the activated corrosion products of PWR nuclear power plants.

Key words: template, format, SRP, academic conference, proceedings

CLC Number: 

  • TL75