Process Development Studies for Zirconium Recovery/Recycle from used Nuclear Fuel Cladding

Collins, E.D.; DelCul, Guillermo Daniel; Spencer, Barry B.; Brunson, R. R.; Johnson, Jesse W.; Terekhov, D.S.; Emmanuel, N. V.

doi:10.1016/j.proche.2012.10.013

Cited by 44 publications

(17 citation statements)

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“…The chlorination process was previously demonstrated at the Institute of Research and Innovation (IRI, Japan) [9], KAERI (Korea) [10], and Oak Ridge National Laboratory (ORNL, USA) [1]. At the IRI, a recovery of Zr from Zircaloy-2 cladding hulls was successfully demonstrated in the presence of Ni and Co, which are major sources of radioactivity of cladding hull waste [9].…”

Section: During the Chlorination Process The Purity Of Recoveredmentioning

confidence: 97%

“…Compared to the electro-refining process, it is suggested that the chlorination process is more convenient to control the reaction rate and scale-up, while a reduction of recovered ZrCl 4 should be followed if it cannot be recycled during cladding hull production [1].…”

Section: During the Chlorination Process The Purity Of Recoveredmentioning

confidence: 99%

“…At KAERI, Zircaloy-4 cladding hulls were employed for the chlorination reaction, and highly pure ZrCl 4 (99.97wt%) was recovered without further heat treatments [10]. At the ORNL, an actual cladding hull (Zircaloy-2) of UNF was employed for the chlorination reaction, and high decontamination factors (> 1200 for total radiation) were reported [1]. It should be noted that the previous reports employed Zircaloy alloys for the chlorination process because they are major cladding materials stacked in reactor site pools.…”

Section: During the Chlorination Process The Purity Of Recoveredmentioning

confidence: 99%

“…Cladding hull waste is an interesting subject in the nuclear waste treatment field, owing to its large portion (about 25wt%) in used nuclear fuel (UNF) and high content of Zr (about 97wt%) [1,2]. Currently, acid washing and compaction techniques are widely employed to manage the cladding hull waste.…”

Section: Introductionmentioning

confidence: 99%

“…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. The selective recovery of Zr is also considered as a pre-treatment of dry storage systems, because a separation of cladding hulls from nuclear materials can eliminate the risk of fractured cladding and handling issues during storage and transportation [1].…”

Section: Introductionmentioning

confidence: 99%

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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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Section: During the Chlorination Process The Purity Of Recoveredmentioning

confidence: 97%

Section: During the Chlorination Process The Purity Of Recoveredmentioning

confidence: 99%

Section: During the Chlorination Process The Purity Of Recoveredmentioning

confidence: 99%

Section: Introductionmentioning

confidence: 99%

Section: Introductionmentioning

confidence: 99%

See 3 more Smart Citations

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

Jeon

Lee

Park

et al. 2013

J Radioanal Nucl Chem

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

Jeon

Lee

Park

et al. 2013

J Radioanal Nucl Chem

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Unfortunately in the original publication some errors were found in the input data of simulation program. Consequently, the values of Tables 2, 3, 4, and 5 and Fig. 1 have been changed and the revised version of tables and figures are given in the following pages. In the original work, the authors have mentioned an increase of total radioactivity which was about 16.7-24 % when fuel burn-up increased from 30 to 75 GWD/MTU. But it should be noted that in the new calculation results, a significant increase in the radioactivity was observed between 30 and 45 GWD/MTU, and the total radioactivity values increased by 167, 262, 280, and 318 % for the Zry-4, Zirlo, HANA-4, and HANA-6 cases, respectively, when the fuel burn-up increased from 30 to 75 GWD/MTU. Although the values were changed, the conclusion for the view point of 94 Nb and 60 Co still remains same as shown in the new Fig. 1.

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Process Development Studies for Zirconium Recovery/Recycle from used Nuclear Fuel Cladding

Cited by 44 publications

References 0 publications

Surface Analysis Study on ZIRLO Cladding Hulls Oxidized at Low Temperatures

Surface Analysis Study on ZIRLO Cladding Hulls Oxidized at Low Temperatures

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

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

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