• Nuclear Engineering and Technology
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• 제54권10호
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• pp.3957-3961
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• 2022

Deposition behaviors of Sr and Cs in various liquid cathodes, such as Zn, Bi, Cd, and Pb, were examined to evaluate their recovery from LiCl-KCl eutectic salt. Cations in the salt were deposited on the liquid cathode, exhibiting potential of -1.8 to -2.1 V (vs. Ag/AgCl). Zn cathode had successful deposition of Sr and exhibited the highest recovery efficiency, up to 55%. Meanwhile, the other liquid cathodes showed low current efficiencies, below 18%, indicating LiCl-KCl salt decomposition. Sr was recovered from the Zn cathode as irregular rectangular SrZn₁₃ particles. A negligible amount of Cs was deposited on the entire liquid cathode, indicating that Cs was hardly deposited on liquid cathodes. Based on these results, we propose that liquid Zn cathode can be used for cleaning Sr in LiCl-KCl salt.

• Nuclear Engineering and Technology
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• 제52권1호
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• pp.115-122
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• 2020

A promising method for removal of Cs ions from water and their incorporation into stable crystal structure ready for safe and permanent disposal was described. Cs-exchanged X zeolite was hot-pressed at temperature ranging from 800 to 950 ℃ to fabricate dense pollucite ceramics. It was found that the application of external pressure reduced the pollucite formation temperature. The effect of sintering temperature on density, phase composition and mechanical properties was investigated. The highest density of 92.5 %TD and the highest compressive strength of 79 MPa were measured in pollucite hot-pressed at 950 ℃ for 3 h. Heterogeneity of samples obtained at 950 ℃ was determined using scanning electron microscopy. The pollucite hot-pressed at 950 ℃ had low linear thermal expansion coefficient of ~4.67 × 10^-6 K^-1 in the temperature range from 100 to 1000 ℃.

• 한국군사과학기술학회지
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• 제13권6호
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• pp.1147-1152
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• 2010

This paper reports a safe and environmentally-benign demilitarization method for the K305 35mm CS gas grenades launcher set(also known as E-8 launcher). The launcher system was disposed by a two-step process; complete recovery of the explosive cords and the gas grenades from the launcher followed by incineration of the recovered items in the APE-1236 Flashing Furnace. All of the 64 grenades within the 16 tubes of the E-8 launcher were safely recovered and incinerated. In this study, 32 sets of the launcher were used to make a standard operating procedure for the safe demilitarization of the launcher system and the 35mm CS cartridges were all safely destroyed in the experimental burning tests meeting the related environmental regulations.

• Nuclear Engineering and Technology
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• 제33권2호
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• pp.231-240
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• 2001

When it is assumed that PWR, CANDU and DUPIC spent fuels are disposed of in deep geological repository, consequent annual individual doses are calculated, and it is shown that doses meet the regulatory limit. From these results, the hazardous radionuclides applicable to partitioning and transmutation are selected. These selected radionuclides such as Tc-99, Ⅰ-129, Cs-135 and Np-237 are then reviewed in terms of partitioning and transmutation. Separation of I-129, Np-237 and Tc-99 from spent fuels is considered desirable, and transmutation of these radionuclides results in remarkable hazard reduction. However, it is concluded that separation and transmutation of Cs-135 may be ineffective although it is classified into a hazardous radionuclide.

• Nuclear Engineering and Technology
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• 제27권1호
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• pp.25-32
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• 1995

저준위 방사성 폐기물의 대표핵종인 Cs의 국내 대표 암반구성 물질인 화강암과 응회암에의 흡착특성을 조사하기 위해 회분식 흡착실험을 수행하였다. 반응표면분석법을 이용하여 ［Cs］, ［Vol/Wt］, ［pH］의 독립변수가 흡착에 미치는 영향을 정량적으로 평가하였다. 결과, 초기 세슘이온의 농도가 가장 중요한 변수로 나타났다. Cs의 흡착능의 pH 의존성은 미약한 것으로 나타났다. 핵종의 응회암에의 흡착량이 화강암보다 더 많았다. 이들 핵종흡착의 낮은 pH 비의존성을 매질의 전기적 표면특성과 핵종의 수용액상 특성으로 설명하였다. 핵종간과 매질간의 흡착능 비교는 물구조 변환론으로 설명하였다.

• 한국방사성폐기물학회:학술대회논문집
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• 한국방사성폐기물학회 2017년도 추계학술논문요약집
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• pp.153-154
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• 2017

• 한국방사성폐기물학회:학술대회논문집
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• 한국방사성폐기물학회 2017년도 추계학술논문요약집
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• pp.157-158
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• 2017

• Nuclear Engineering and Technology
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• 제10권3호
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• pp.153-163
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• 1978

부지주변 환경과 관련한 방사성 고체 폐기물의 지중처분 문제는, 비록 안전하고 경제적이라 할지라도, 대단히 중요하다. 지중처분을 위한 방사성 핵중(Sr-90, Cs-137)의 이동과 물의 이동에 관한 연구가 실험실과 야외에서 수행되었다. 방사성 핵종에 대한 토양의 친화력은 알칼리성 용액에서 더 강하고, 흡착은 시간에 대한 함수관계가 있음을 나타내었다. 방사성스트론티움과 세시움의 이동율은 3.73$\times$$10^{-3}$-10.9$\times$$^{-3}$cm/day로서, 물의 이동 속도 보다 훨씬 낮은 값을 나타내었으며, 이것은 아마도 높은 이온이온교환능에 기인되는 것이다. 확산에 기초를 둔 수학적인 모형에 의거 얻은 값과 측정 트리티움의 분포가 비교되었다. 지하에서의 물의 이동 현상을 규명하는데 삼중수를 추적자료로 이용할 수 있음을 암시하고 있다.

• Nuclear Engineering and Technology
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• 제35권5호
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• pp.387-398
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• 2003

For reference human intrusion scenarios constructed in previous study, a probabilistic safety assessment to derive the radionuclide concentration limits for the low- and intermediate- level radioactive waste disposal facility is conducted. Statistical approach by the Latin Hypercube Sampling method is introduced and new assumptions about the disposal facility system are examined and discussed. In our previous study of deterministic approach, the post construction scenarios appeared as most limiting scenario to derive the radionuclide concentration limits. Whereas, in this statistical approach, the post drilling and the post construction scenarios are mutually competing for the scenario selection according to which radionuclides are more important in safety assessment context. Introduction of new assumption shows that the post drilling scenario can play an important role as the limiting scenario instead of the post-construction scenario. When we compare the concentration limits between the previous and this study, concentrations of radionuclides such as Nb-94, Cs-137 and alpha-emitting radionuclides show elevated values than the case of the previous study. Remaining radionuclides such as Sr-90, Tc-99 I-129, Ni-59 and Ni-63 show lower values than the case of the previous study.

• 한국지하수토양환경학회지:지하수토양환경
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• 제26권5호
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• pp.29-38
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• 2021

This study investigated the mineralogical properties of bentonite and illite and evaluated the Cs sorption at various concentrations (C_w≈1-10⁵ ㎍/L). Bentonite samples, collected from South Korea and USA, majorly consisted of Ca- and Na-montmorillonite, showed large cation exchange capacity (CEC, 91.4 and 47.3 meq/100 g) and specific surface area (SSA, 46.1 and 39.7 m²/g). In contrast, illite sample (USA) had relatively low values for 14.4 meq/100g of CEC and 29.3 m²/g of SSA, respectively. Bentonite and illite had different non-linear sorption for Cs along with C_w. At low C_w<10 ㎍/L, illite showed higher sorption capacity than bentonite despite low CEC because of the existence of specific sorption sites at the weathered mineral edge. However, as C_w increased, bentonite represented high sorption capacity because the cation exchange between Cs and interlayer cations was effective at high C_w conditions. These results implicated that the Cs concentration is important to evaluate the sorption performance of bentonite and illite. Finally, the Cuadros' kinetic model for illitization using various K concentrations (2×10^-5 and 1.7×10^-3 mol/L) and temperature (100-200℃) showed that up to 50% of the montmorillonite in bentonite could be converted to illite, suggesting that the illitization should be considered to evaluate the sorption performance of the bentonite in deep geological disposal repository.