Effect of burn-up on the radioactivation behavior of cladding hull materials studied using the ORIGEN-S code

Jeon, Min Ku; Lee, Chang Hwa; Park, Chang Je; Choi, Jung Hoon; Cho, In Hak; Kang, Kweon Ho; Park, Hwan-Seo; Park, Geun Il

doi:10.1007/s10967-013-2543-6

Cited by 9 publications

(6 citation statements)

References 11 publications

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“…This is caused not only by the radionuclides included in the residual used fuel, but also the ones newly generated from cladding hull components by irradiation. In our other study [8], we calculated radioactivity of each nuclides using the ORIGEN-S code [12] to investigate effect of burn-up on the radioactivation behavior of cladding materials. In the results of irradiation calculation, concentrations of Co-60 and Sb-125 are 9.96×10 6 and 7.47×10 3 for Zircaloy-4 cladding hull wastes with a burn-up of 60,000 MWd/tU, respectively.…”

Section: Cross-sectional Analysis Of Cladding Hull Wastesmentioning

confidence: 99%

“…The alloy elements and impurities including in the cladding matrix are also activated by neutron irradiation in the reactor [8]. For better understanding of the waste properties, the characterization of the cladding hull waste such as radioactivity and oxide layer thickness is required because it greatly influences the activity level, treatment method, immobilization, and recycling of the waste.…”

Section: Introductionmentioning

confidence: 99%

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Characterization Of Cladding Hull Wastes From Used Nuclear Fuels

Kang¹,

Lee²,

Jeon³

et al. 2015

Archives of Metallurgy and Materials

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Used cladding hulls from pressurized water reactor (PWR) are characterized to provide useful information for the treatment and disposal of cladding hull wastes. The radioactivity and the mass of gamma emitting nuclides increases with an increase in the fuel burn-up and their removal ratios are found to be more than 99 wt.% except Co-60 and Cs-137. In the result of measuring the concentrations of U and Pu included in the cladding hull wastes, most of the residues are remained on the surface and the removal ratio of U and Pu are revealed to be over 99.98 wt.% for the fuel burn-up of 35,000 MWd/tU. An electron probe micro-analyzer (EPMA) line scanning shows that radioactive fission products are penetrated into the Zr oxide layer, which is proportional to the fuel burn-up. The oxidative decladding process exhibits more efficient removal ratio of radionuclides.

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Section: Cross-sectional Analysis Of Cladding Hull Wastesmentioning

confidence: 99%

Section: Introductionmentioning

confidence: 99%

Characterization Of Cladding Hull Wastes From Used Nuclear Fuels

Kang¹,

Lee²,

Jeon³

et al. 2015

Archives of Metallurgy and Materials

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“…Compared to the filter and electrolyte wastes, the metal waste did not bring much attention in the early stage of the pyroprocessing research owing to its relatively low radioactivity and decay heat. But, recent reports showed that the hardware and cladding hull wastes need more investigation owing to their large volume and radioactivity [3,4]. The radioactivation calculation results revealed that these wastes might be categorized into intermediate level waste (ILW) according to the Korean regulation owing to high radioactivity [3].…”

Section: Introductionmentioning

confidence: 99%

“…But, recent reports showed that the hardware and cladding hull wastes need more investigation owing to their large volume and radioactivity [3,4]. The radioactivation calculation results revealed that these wastes might be categorized into intermediate level waste (ILW) according to the Korean regulation owing to high radioactivity [3]. In addition, these wastes cannot be disposed of in the Wolsung LILW (Low and Intermediate Level Waste) disposal center (WLDS) located in Gyeongju City of Republic of Korea (ROK).…”

Section: Introductionmentioning

confidence: 99%

A thermo-gravimetric analysis study on the chlorination reaction of ZIRLO cladding hulls

Jeon

Choi

Hur

et al. 2015

Journal of Nuclear Materials

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“…The acid washing is a convenient method to remove residual UNF from the cladding hulls that are stuck on the inner surface, but it is also well known that the acid washing procedure is insufficient to classify the cladding hull waste as a low-level waste [3,4]. In addition, it was revealed that the radioactivity of 94 Nb, which is one of the major radioactivation products of Nb contained in ZIR-LO (ZIRconium Low Oxidation) cladding hull material, exceeds acceptance limit of the Wolsong LILW (Low and Intermediate Level Waste) disposal center (WLDC) of Korea [5]. Thus, a selective recovery of Zr from the cladding hull waste is an attractive approach to minimize the generation of mid-/high-level waste regardless of UNF treatment methods.…”

Section: Introductionmentioning

confidence: 99%

Surface Analysis Study on ZIRLO Cladding Hulls Oxidized at Low Temperatures

Jeon

Choi²,

Lee³

et al. 2014

Journal of the Nuclear Fuel Cycle and Waste Technology

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Surface oxidation behavior of ZIRLO (ZIRconium Low Oxidation) hulls was investigated using an X-ray photoelectron spectroscopy (XPS) technique. The effects of oxidation time (10-336 h at 500℃) and temperature (400-700℃ for 10 h) were studied. Deconvolution results of the hulls oxidized at 500℃ revealed that a ZrO 2 phase appeared after 24 h (11.86%), and an increase in the ZrO 2 ratio was observed when the hulls were oxidized for 336 h (17.93%). On the other hand, the ZrO phase which employed 5.68% in the 10 h oxidized sample disappeared when the oxidation time increased to 24 h. The XPS results also showed that an increase in the oxidation temperature resulted in an increase in the ratio of ZrO, which increased from 0 to 5.68, 8.31, and 9.16% when the oxidation temperature increased from 400 to 500, 600, and 700℃, respectively. ZrO 2 phase was observed only in the sample that was oxidized at 700℃. The mechanism of ZrO formation was not conclusive, but it was suggested that a formation of hydroxide might have been accelerated at elevated temperatures leading to a formation of a Zr(OH) 4 phase. The relationship between the surface oxidation status of the hulls oxidized at 500℃ and their chlorination reaction feasibility was discussed, and it was suggested that the thickness of the oxide layer is an important parameter that determines the chlorination reaction feasibility.

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Effect of burn-up on the radioactivation behavior of cladding hull materials studied using the ORIGEN-S code

Cited by 9 publications

References 11 publications

Characterization Of Cladding Hull Wastes From Used Nuclear Fuels

Characterization Of Cladding Hull Wastes From Used Nuclear Fuels

A thermo-gravimetric analysis study on the chlorination reaction of ZIRLO cladding hulls

Surface Analysis Study on ZIRLO Cladding Hulls Oxidized at Low Temperatures

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