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; Chatani, Keiji; ; ; ;
PNC TN9410 92-345, 166 Pages, 1992/10
An evaluation about the radioactive corrosion product (CP) behaviour in sodium cooling systems of a fast reactor is presented in this report, based on the obtained measurement results in the operating experience of JOYO. The objective of this work is to update the calculational model for predicting the release and deposition behaviour of CP in primary sodium cooling systems of a fast reactor. The evaluation results are as follows; (1)The main radionuclides of CPs transported to the out-of-reactor primary sodium loop are Mn and Co, and Mn is the most dominant. On the other hand, Co is the most dominant nuclide found in the liquid waste from spent fuel cleaning, which is produced by removal of activated CP deposits from surfaces of core sub-assemblies in sodium cleaning. (2)The deposition rate of Mn onto the hot-leg (HL) piping walls corresponds fairly with the saturation of radioactivity induced in core materials by activation, on the other hand, that onto the cold-leg (CL) piping walls has been being accelerated. The deposition rate of Co, due to the dependency of activation and release in a core, is strongly affected by the re-fuelling pattern and the oxygen concentration in sodium, and suggests the detouching process of deposits from wall surfaces. (3)Although Mn was transported and deposited preferentially in the HL of the primary cooling system in an early stage, the transport and deposition in the CL regions has overcomed that in the HL along operating time. Co was transported and deposited preferentially in the HL and the similar distribution pattern has been maintained thoroughout the operating periods. (4)The solution - precipitation model for CP behaviour in flowing sodium system was verified via the sensitivity test of model parameters and optimizing them on the above mentioned results, giving the measured to caluculated values of 1.36 or 1.03 for Mn or Co buildup, and 1.61 ...