• Nuclear Engineering and Technology
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• 제55권12호
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• pp.4543-4553
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• 2023

The dose from a possible accident at a microwave-based spent resin mixture treatment facility that was to be installed and operated at the Wolsong nuclear power plant was analyzed to evaluate the radiological safety prior to its installation and operation. The dose to which workers and nearby residents are likely to be exposed was calculated based on the atmospheric dispersion and deposition factors using the XOQDOQ code. The highest atmospheric dispersion factors were 1.349E-05 s/m³ (workers) and 1.534E-06 s/m³ (residents). The highest doses due to emissions from the mock-up tank before operation were 1.91E-06 mSv (workers) and 1.78E-07 mSv (residents). Even after 3 h of operation, emissions from the mock-up tank had the greatest impact ranging from 4.63E-08 to 1.24E-06 mSv (workers) and 2.74E-10 to 1.16E-07 mSv (residents), respectively. The doses were 7.09E-09-4.55E-07 mSv and 4.18E-11-4.25E-08 mSv at 4-5 h of operation, and the maximum doses after operation reached 5.69E-07 mSv and 5.31E-08 mSv for the workers and residents, respectively. Even at the exclusion area boundary (EAB), 4.76E-08-9.51E-07 mSv (annual dose:9.52E-05–1.90E-03 mSv/y) was below the dose limit of the EAB, and the safety of the facility installation inside the NPP was confirmed.

• 방사성폐기물학회지
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• 제22권2호
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• pp.227-235
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• 2024

After the permanent shut down of Kori Unit 1, various decommissioning activities will be implemented, including decontamination, segmentation, waste management, and site restoration. During the decommissioning period, waste management is among the most important activities to ensure that the process proceeds smoothly and within the expected timeframe. Furthermore, the radioactive waste generated during the operation should be sent to a disposal facility to complete the decommissioning project. Square and cylindrical concrete re-package drums were generated during the 1980s and 1990s. The square, containing boron concentrates, and cylindrical, containing spent resin, concrete re-package drums have been stored in a radioactive waste storage building. Homogeneous radioactive waste, including boron concentrates, spent resin, and sludge, should be solidified or packaged in high-integrity containers (HICs). This study investigates the sequential segmentation process for the separation of contaminated and non-contaminated regions, the re-packaging process of segmented or crushed cement-solidified boron concentrate, and re-packaging in HICs. The conceptual design evaluates the re-packaging plan for the segmented and crushed cement-solidified waste using HICs, which is acceptable in a disposal facility, and the quantity of generated HICs from the treatment process.

• 분석과학
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• 제15권1호
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• pp.1-6
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• 2002

사용후핵연료 침출액중 비방사능이 작은 핵종들의 정확한 분석을 위해서는 비방사능이 큰세슘을 제거하여야 한다. 이를 위하여 세슘만을 선택적으로 흡착한다고 알려진 ammonium molybdophosphate(AMP) 를 이용하여 사용후 핵연류 침출액의 구성원소들(Cs, U, Ce, La, Co, Sr)과 사용후핵연료와 접한 벤토나이트의 성분들(Ca, Na, K)에 대한 제거율을 검토하였다. 그 결과 0.1 M 질산매질에서 AMP로 90% 이상의 세슘이 제거되었고 대부분의 Ca, Na, Co, Sr은 용액중에 남아 있었다. 그러나 일부 세늄을 포함한 란탄족 3가 이온들은 세슘과 같이제거 되었다. 벤토나이트 성분중일부 칼륨도 AMP에 흡착하였으나 실제 시료와 같이 묽은 벤토나이트 용액에서의 칼륨은 AMP이 유효치환량에 큰 영향을 주지 않았다. 한편 사용후핵연료의 침출 기준원소인 스트론튬을 분리하기 위하여 8.0 M 질산매질의 용리할 경우 95% 이상의 스트론튬을 회수 할 수 있었다.

• 자원리싸이클링
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• 제30권4호
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• pp.54-63
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• 2021

SCR 탈질 폐촉매로부터 바나듐과 텅스텐은 소다배소-수침출 공정을 통해 얻은 침출액으로부터 분리/회수하여 얻을 수 있다. 본 연구에서는 강염기성 음이온교환수지인 Lewatit monoplus MP 600을 사용하여 연속식 이온교환칼럼에서 수용액에 용해되어 있는 바나듐과 텅스텐의 흡·탈착 거동을 알아보고, 바나듐/텅스텐 분리를 위한 연속식 이온교환칼럼 운전조건을 제시하고자 하였다. 수용액 pH 8.5에서 단일 성분 수용액으로 연속식 흡착실험을 수행한 결과, 흡착용량은 바나듐 44.75 mg/(g of resin)과 텅스텐 64.92 mg/(g of resin)으로 바나듐보다 텅스텐의 흡착용량이 크게 나타났으며 이는 이온교환수지에 흡착되는 이온의 전하수가 바나듐 보다는 텅스텐이 작기 때문이라고 사료된다. 텅스텐이 흡착된 이온교환수지에 바나듐 함유 수용액이 공급됨에 따라 이온교환수지에 흡착되었던 텅스텐이 바나듐과 교환되며 탈착되는 거동을 보였으며, 이로부터 MP 600에 대하여 바나듐이 텅스텐보다 친화도(affinity)가 높음을 알 수 있었다. SCR 탈질 폐촉매 침출액과 동일한 농도의 바나듐과 텅스텐 혼합용액으로 pH 8.5에서 연속식 실험을 수행한 결과 바나듐의 흡착 용량은 48.72 mg/(g or resin)으로 공급량의 80%가 흡착된 반면 텅스텐의 경우 이온교환수지에 흡착된 양이 거의 0에 근접하며 바나듐과 텅스텐의 분리가 효과적으로 이루어졌다. 바나듐이 흡착된 이온교환수지로부터 2M HCl를 15 mL/h로 공급하여 97.7%의 바나듐을 99%의 순도로 탈착시킬 수 있었다. 탈착용액으로부터 염화암모늄을 침전제로 사용하여 90℃에서 암모늄폴리바나데이트 형태로 93%의 바나듐을 회수하였다.

• Nuclear Engineering and Technology
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• 제40권6호
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• pp.489-496
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• 2008

Ferrocyanide-anion exchange resin was prepared and the prepared ion exchange resins were tested on the ability to uptake $Cs^+$ ion. The prepared ion exchange resins were resin-KCoFC, resin-KNiFC, and resin-KCuFC. The three tested ion exchange resins showed ion exchange selectivity on the $Cs^+$ ion of the surrogate soil decontamination solution, and resin-KCoFC showed the best $Cs^+$ ion uptake capability among the tested ion exchange resins. The ion exchange behaviors were explained well by the modified Dubinin-Polanyi equation. A regeneration feasibility study of the spent ion exchange resins was also performed by the successive application of hydrogen peroxide and hydrazine. The desorption of the $Cs^+$ ion from the ion exchange resin satisfied the electroneutrality condition in the oxidation step; the desorption of the $Fe^{2+}$ ion in the reduction step could also be reduced by adding the $K^+$ ion.

• 한국물환경학회지
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• 제29권6호
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• pp.777-781
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• 2013

Ion-exchange technology is one of the best for removing nitrate from drinking water. However, problems related to the disposal of spent brine from regeneration of exhausted resins must be overcome so that ion exchange can be applied more widely and economically, especially in small communities. In this background, a combined bio-regeneration and ion-exchange system was operated in order to prove that nitrate-laden resins could be bio-regenerated through direct contact with denitrifying bacteria. A nitrate-selective A520E resin was successfully regenerated by denitrifying bacteria. The bio-regeneration efficiency of nitrate-laden resins increased with the amount of flow passed through the ion-exchange column. When the fully exhausted resin was bio-regenerated for 5 days at the flowrate of 30 BV/hr and MLSS concentration of $125{\pm}25mg/L$, 97.5% of ion-exchange capacity was recovered. Measurement of nitrate concentrations in the column effluents also revealed that less than 5% of nitrate was eluted from the resin during 5 days of bio-regeneration. This result indicates that the main mechanism of bio-regeneration is the direct reduction of nitrate by denitrifying bacteria on the resin.

• 한국원자력학회:학술대회논문집
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• 한국원자력학회 2005년도 춘계학술발표회
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• pp.265-266
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• 2005

• 한국방사성폐기물학회:학술대회논문집
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• 한국방사성폐기물학회 2018년도 추계학술논문요약집
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• pp.436-437
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• 2018

• 한국방사성폐기물학회:학술대회논문집
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• 한국방사성폐기물학회 2018년도 추계학술논문요약집
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• pp.327-328
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• 2018

• 한국방사성폐기물학회:학술대회논문집
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• 한국방사성폐기물학회 2017년도 추계학술논문요약집
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• pp.315-316
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• 2017