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Vol.9 No.2previous AASP17 (125-126-127-128-129-130-131-132-133-134-135-136-137-138-139-140-141-142) NT85

Academic Articles
Regular Paper Vol.9 No.2 (2017) p.145 - p.151

Treatment of spent radioactive cationic exchange resins used in nuclear power plants by Fenton-like oxidation process

Xu Lejin1,2,*, Sui Zengguang1, Yang Jun1, Wan Zhong2 and Wang Jianlong2

1 Nuclear Engineering and Technology Department, School of Energy and Power Engineering, Huazhong University of Science & Technology, Wuhan 430074, PR China
2 Collaborative Innovation Center for Advanced Nuclear Energy Technology, INET, Tsinghua University, Beijing 100084, PR China

Fenton and Fenton-like oxidation processes have been developed to effectively disintegrate and mineralize spent radioactive ion exchange resins from nuclear power plants. In this paper, the degradation of spent cationic resins by Fenton-like process for chemical oxygen demand (COD) removal and weight reduction was investigated. The effects of initial pH, Cu2+ concentration and H2O2 dosage on resin degradation by the Cu2+/H2O2 oxidation process was studied. The results showed that lower initial pH value brought higher COD removal rate. With the increasing amount of Cu2+ concentration and H2O2 dosage, the COD removal rate of resins first increased and then decreased. The degradation efficiency (in term of COD removal rate) and weight reduction percentages were 99% and 39%, respectively, at pH 0.75 and T 95 C with 0.2 M Cu2+, and 35 mL 30% H2O2. The scanning electron microscopy images provided the information of morphological changes of resin during the dissolution process, which clearly revealed the degradation of resins.
Spent radioactive resin, Fenton-like oxidation, Treatment, COD removal, Weight reduction, Morphological change
Full Paper: PDF
Article Information
Article history:
Received 6 November 2016
Accepted 27 April 2017