• Nuclear Engineering and Technology
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• 제54권7호
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• pp.2475-2490
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• 2022

The Accident Tolerant Fuel (ATF) is a new concept of fuel, which can not only withstand the consequences of the accident for a longer time, but also maintain or improve the performance under operating conditions. ISAA is a self-developed severe accident analysis code, which uses modular structures to simulate the development processes of severe accidents in nuclear plants. The basic version of ISAA is developed based on UO₂-Zr fuel. To study the potential safety gain of ATF cladding, an improved version of ISAA, referred to as ISAA-ATF, is introduced to analyze the station blackout accident of PWR using ATF cladding. The results show that ATF cladding enable the core to maintain a longer time compared to zirconium alloy cladding, thereby enhancing the accident mitigation capability. Meanwhile, the generation of hydrogen is significantly reduced and delayed, which proves that ATF can improve the safety characteristics of the nuclear reactor.

• 한국방사성폐기물학회:학술대회논문집
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• 한국방사성폐기물학회 2003년도 가을 학술논문집
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• pp.689-695
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• 2003

Electrochemical decontamination process has been applied for recycle or self disposal with authorization of large amount of metallic wastes contaminated with uranium compounds such as $UO_2$, ammonium uranyl carbonate (AUC), ammonium di-uranate (ADU), and uranyl nitrate(UN) with tributylphosphate(TBP) and dodecane, which are generated by dismantling the contaminated system components and equipment of a retired uranium conversion plant in Korea Atomic Energy Research Institute (KAERI). Electrochemical decontamination for metallic wastes contaminated with uranium compounds was evaluated through the experiments on the electrolytic dissolution of stainless steel as the material of the system components in neutral salt electrolytes. The effects of type of neutral salt as the electrolyte, current density, and concentration of electrolyte on the dissolution of the materials were evaluated. Decontamination performance tests using the specimens taken from a uranium conversion plant were quite successful with the application electrochemical decontamination conditions obtained through the basic studies on the electrolytic dissolution of structural material of the system components.

• Nuclear Engineering and Technology
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• 제56권3호
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• pp.846-854
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• 2024

FEMAXI-ATF is being developed for fuel performance modeling of SiC cladded UO2 fuel with focuses on modeling pellet-cladding mechanical interactions (PCMI). The code considers probability distributions of mechanical strengths of monolithic SiC (mSiC) and SiC fiber reinforced SiC matrix composite (SiC/SiC), while it models pseudo-ductility of SiC/SiC and propagation of cladding failures across the wall thickness direction in deterministic manner without explicitly modeling cracks based on finite element method in one-dimensional geometry. Some hypothetical BWR power ramp conditions were used to test sensitivities of different model parameters on the analyzed PCMI behavior. The results showed that propagation of the cladding failure could be modeled by appropriately reducing modulus of elasticities of the failed wall element, so that the mechanical load of the failed element could be re-distributed to other intact elements. The probability threshold for determination of the wall element failure did not have large influence on the predicted power at failure when the threshold was varied between 25 % and 75 %. The current study is still limited with respect to mechanistic modeling of SiC failure as it only models the propagation of the cladding wall element failure across the homogeneous continuum wall without considering generations and propagations of cracks.

• Nuclear Engineering and Technology
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• 제55권5호
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• pp.1644-1650
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• 2023

In spent fuel reprocessing, UO₂(DBP)₂ (U-DBP) can be deposited in stainless steel equipment. U-DBP must be removed by dissolution and the process must not cause corrosion to stainless steel. This study was conducted to find the best scheme for dissolution. U-DBP was manufactured by the titrimetric sedimentation method. The effects of different factors on the dissolution of U-DBP were investigated. For example, solid-liquid ratio, hydrazine carbonate solutions with different mass components, mixed solutions containing different concentrations of H₂O₂, and different carbonates. The results indicated that U-DBP does not have a regular crystal morphology. With the increase of the solid-liquid ratio and the mass fraction of hydrazine carbonate, the concentration of U(VI) at the dissolution equilibrium increases gradually. The addition of H₂O₂ has a great promotion effect on the dissolution. However, when the concentration of H₂O₂ is greater than 0.5 M, the dissolution solution may have an erosive effect on the stainless steel. (NH₄)₂CO₃ can increase the dissolution capacity of dissolved U-DBP, but it may also accelerate the corrosion of stainless steel.

• 대한화학회지
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• 제44권1호
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• pp.17-23
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• 2000

전기화학적으로 중합한 $[Ru(v-bpy)_3]^{2+}$의 다가 양이은성 고분자 피막전극을 $PF6^-/ClO_4^-$대이온의 비가 1:1 정도 되게 한 후에 우라늄과의 착물의 안정도상수가 각각 38.6과 17.5인 xylenoI orange와 diethyldithiocarbamate로 변성한 전극을 제작하였다. 이를 이용하여 용액중의 U(VI)을 정량할 수 있는 여러 회 사용이 가능한 전극을 제작하였다. 이 때에 분석용 신호를 얻기 위한 전극은 Pt/p-$[Ru(v-bpy)_3]^{2+}$, ligand, U(VI)이며 염화은 기준전극을 사용하였다. 벗김전압전류 과정에서는 전자전달이 지배적인 과정이었으며, 검정선은 $1.0{\times}10^{-3}{\sim}1.0{\times}10^{-7}$ M 범위에서 0.99의 좋은 상관관계와 5${\sim}$8%의 상대 표준편차를 나타냈다.

• 한국방사성폐기물학회:학술대회논문집
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• 한국방사성폐기물학회 2003년도 가을 학술논문집
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• pp.632-635
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• 2003

원자력 발전소에서 배출되고 있는 방사성 폐기물의 운반 및 처분과 관련하여 규제가 예상되는 대상 핵종을 선정하고, 특히 방사능 계측기로 직접 측정이 불가능한 드럼 내 방출핵종에${\alpha}{\cdot}{\beta}$ 대한 농도 예측과 검증방법에 관한 연구가 진행되고 있다. 본 연구에서는 $\beta$방출 핵종이면서 반감기가 매우 긴 $^129I(t_{1/2}=1.57{\times}10^7)$의 정량을 위하여 모의 폐기물 중에 함유되어 있는 요오드의 분리 및 회수율을 측정하였다. 모의 폐기물중 가용성 및 난용성 시료의 전처리 방법으로 혼합산 분해법과 알칼리 용융방법을 각각 이용하였으며 두 방법에 대한 요오드의 회수율을 비교하였다. 요오드의 측정방법으로 이온 크로마토그라피를 이용하였으며 매질의 음이온성분에 의한 영향은 없었다. 두 방법의 전체 공정에서 혼합산분해에 의한 요오드의 회수율은 76.7 (RSD 1.7%)이고 알칼리용융에 의한 방법에서 모직물의 경우에는 74.3(RSD 2.2%)이고 Resin의 경우 56.5(5.6%)로 각각 나타났다.

• 대한화학회지
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• 제65권2호
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• pp.93-105
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• 2021

Mononuclear Cu(II), Ni(II), Co(II), Mn(II), Zn(II), Fe(III), Ru(III), and UO2(II) complexes of 2-hydroxy-4-(p-tolyldiazenyl)benzylidene)-2-(p-tolylamino)acetohydrazide (H2L) were prepared by direct method. The ligand and its complexes were isolated in solid state and characterized by analytical techniques such as elemental and thermal analyses, molar conductance, magnetic susceptibility measurements and spectroscopic techniques such as UV-Visible, IR, 1H-NMR and 13C-NMR. The spectral data indicated that the ligand acted as neutral/monobasic bidentate or monobasic/dibasic tridentate ligand bonded to the metal ions through the oxygen atom of ketonic or enolic carbonyl group, azomethine nitrogen atom and deprotonated/protonated phenolic oxygen atom forming either tetragonally distorted octahedral or octahedral. Antimicrobial activities of the ligand and its complexes were evaluated against Escherichia coli, Bacillus subtilis and Aspergillus niger by well diffusion method. The results of antifungal activity showed that the Fe(III) complex (10) exhibited higher antifungal against Aspergillus niger than the other complexes. However, the results of antibacterial activity revealed that Cu(II) complex (4) is the most active against Escherichia coli while the Cu(II) complex (5) and Fe(III) complex (10) exhibited higher antibacterial effect on Bacillus subtilis than the other complexes.

• Nuclear Engineering and Technology
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• 제54권1호
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• pp.1-10
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• 2022

This study discusses the effect of using ²³²Th instead of ²³⁸U on the neutronic characteristics and the main operating parameters of the pressurized water reactor (PWR). MCNPX version 2.7 was used to compare the neutronic characteristics of UO₂ with (Th, ²³⁵U)O₂ and (Th, ²³³U) O₂. Firstly, the infinity multiplication factor (K_inf), thermal neutron flux, and power distribution have been studied for the investigated fuel types. Secondly, the effect of Gd₂O₃ and Er₂O₃ on the K_inf and on the radial thermal neutron flux and thermal power has been investigated to distinguish which of them is more suitable than the other in reactivity management. Thirdly, to illustrate the effectiveness of ²³²Th in decreasing the inventory of both the actinides and non-actinides, the concentration of plutonium (Pu) isotopes and minor actinides (MAs) has been simulated with the fuel burnup. Besides, due to their large thermal neutron absorption cross-section, the concentrations of ¹³⁵Xe, ¹⁴⁹Sm, and ¹⁵¹Sm with the fuel burnup have been investigated. Finally, the main safety parameters such as the reactivity worth of the control rods (ρ_CR), the effective delayed neutron fraction β_eff, and the Doppler reactivity coefficient (DRC) were calculated to determine to which extent these fuel types achieve the acceptable limits.

• 공업화학
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• 제27권5호
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• pp.478-482
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• 2016

본 연구는 0.076 m 지름과 0.8 m 높이를 가지는 기포유동층 열분해로를 이용하여 국내에서 풍부한 낙엽송 톱밥의 급속 열분해 특성을 고찰한 것이다. 유동층 열분해로의 운전 조건인 반응온도($350-550^{\circ}C$), 유동화 속도비($U_o/U_{mf} $: 2.0-6.0), 원료 주입 속도(2.2-7.0 g/min)에 따른 열분해 수율과 바이오 오일의 조성 변화를 고찰하였다. 바이오 오일에 포함된 화학 성분들의 수는 반응 온도 증가에 따른 2차 열분해로 인하여 반응 온도가 증가함에 따라서 감소하였다. 유동화 속도비와 원료 주입 속도가 유동층 열분해에 미치는 영향은 반응 온도의 영향보다 작아 열분해 온도가 가장 중요한 인자임을 확인하였다.

• Nuclear Engineering and Technology
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• 제49권8호
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• pp.1733-1739
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• 2017

Molecular dynamics simulations were performed to investigate the uniaxial tensile properties of nanocrystalline $U_{0.5}Th_{0.5}O_2$ solid solution with the Born-Mayer-Huggins potential. The results indicated that the elastic modulus increased linearly with the density relative to a single crystal, but decreased with increasing temperature. The simulated nanocrystalline $U_{0.5}Th_{0.5}O_2$ exhibited a breakdown in the Halle-Petch relation with mean grain size varying from 3.0 nm to 18.0 nm. Moreover, the elastic modulus of $U_{1-y}Th_yO_2$ solid solutions with different content of thorium at 300 K was also studied and the results accorded well with the experimental data available in the literature. In addition, the fracture mode of nanocrystalline $U_{0.5}Th_{0.5}O_2$ was inclined to be ductile because the fracture behavior was preceded by some moderate amount of plastic deformation, which is different from what has been seen earlier in simulations of pure $UO_2$.