• Journal of Hydrogen and New Energy
• /
• v.22 no.1
• /
• pp.21-28
• /
• 2011

Fe, Ni and Co, typical active components, were dispersed on $Al_2O_3$ and $TiO_2$ for $SO_3$ decomposition. $SO_3$ decomposition was conducted at the temperature ranges from $750^{\circ}C$ to $950^{\circ}C$ using the prepared catalysts. Alumina based catalysts showed the surface areas higher than Titania based catalysts, which resulted from spinel structure formation of alumina based catalysts. Catalytic $SO_3$ decomposition reaction rates were in the order of Fe>Co${\gg}$Ni. The metal sulfate decomposition temperature were in the order of Ni>Co>Fe from TGA/DTA analysis of metal sulfate. During $SO_3$ decomposition, metal sulfate can form on the catalysts. $SO_2$ and $O_2$ can be produced from the decomposition of metal sulfate. In that point of view, the less is the metal sulfate deomposition temperature, the higher can be the $SO_3$ decomposition activity of the metal component. Therefore, it can be concluded that metal component with the low metal sulfate decomposition temperature is the pre-requisite condition of the catalysts for $SO_3$ decomposition reaction.

• Journal of Korean Society of Environmental Engineers
• /
• v.22 no.7
• /
• pp.1307-1318
• /
• 2000

The purpose of this study is to investigate the degradation characteristics of oxalic acid and citric acid by $UV/H_2O_2$ oxidation. For this purpose, the effects of pH, $H_2O_2$ dosage and the concentration of each compounds on the degradation of oxalic acid and citric acid by $UV/H_2O_2$ were investigated. Oxalic acid was effectively degraded at the wavelength of 254 nm, while the degradation efficiency of citric acid was very low at the same wavelength. It was also found that both organic substances were not degraded by the injection of $H_2O_2$ only. The optimum pH of degradation of oxalic acid and citric acid was 4 and 4 to 6, respectively. In the case of $UV/H_2O_2$ oxidation, the degradation efficiency was increased by increasing $H_2O_2$ dosage. The degradation efficiency decreased when the dose of $H_2O_2$ exceeds 200 mg/L. From these results, it can be concluded that the optimum reaction conditions for the degradation of oxalic acid and citric acid by $UV/H_2O_2$ oxidation were pH 4 and 200mg/L of $H_2O_2$.

• Proceedings of the Korean Nuclear Society Conference
• /
• 1996.05c
• /
• pp.46-51
• /
• 1996

본 연구는 MDD(modified direct denitration)공정의 주 우라늄염인 암노늄 우라닐 나이트레이트의 화학특성을 밝히고 이들 화합물의 열분해 및 환원반응의 반응기구에 대하여 조사되었다. 암모늄 우라닐 나이트레이트는 제조 조건에 따라 N $H_4$$UO_2$N $O_3$와 (N $H_4$)$_2$$UO_2$(N $O_3$)$_4$.2$H_2O$의 두가지 형태의 복염으로 존재함이 화학 및 원소분석, X산 회절 분석, 그리고 적외선 분광분석에 의하여 확인되었다. 암모늄 우라닐 나이트레이트는 질소분위기에서 N $H_4$$UO_2$(N $O_3$)$_3$$\longrightarrow$ Amorphous $UO_3$$\longrightarrow$ a-$UO_3$$\longrightarrow$ U$_3$ $O_{8}$$\longrightarrow$ $\alpha$-U$_3$ $O_{8}$의 경로를 따라서 열분해 되며, 수소분위기에서는 N $H_4$$UO_2$(N $O_3$)$_3$$\longrightarrow$ $UO_3$$\longrightarrow$ U$_3$ $O_{8}$$\longrightarrow$ U$_4$ $O_{9}$ $\longrightarrow$ $UO_2$의 경로로 환원되었다.

• Nuclear Engineering and Technology
• /
• v.20 no.1
• /
• pp.54-64
• /
• 1988

This paper assesses the models in the SCDAP code using the results of the FLHT-2 test. Calculations show that the SCDAP correctly predicts Ire temperatures, oxidation front movement, overall hydrogen generation and peak generation rate, internal fuel rod pressure, and cladding rupture due to ballooning. A comparison of the calculated results with measured data shows that two phase level is underpredicted, and that radiation heat transfer and auto-catalytic reaction temperature of zircaloy are overpredicted. These models are recommended to be modified. The analysis also shows that the simulation of the gap in a fuel rod improves the code prediction on core damage progression.

• Proceedings of the Korean Nuclear Society Conference
• /
• 1995.05b
• /
• pp.921-927
• /
• 1995

수지충전식 전해재생조내에서 바나듐-철-Picolinate 착화물이 함유된 모의 LOMI 제염폐액의 재생거동에 대한 공정변수의 영향을 조사하였다. 전기투석에 의해 양이온종이 제염 폐액으로부터 제거되는 재생 분리효율에 대한 전류밀도, 제염폐액 공급유량 및 재생조내 수지층두께 등 공정변수의 영향은 바나듐이온이 가장 크게 받는다. 공정변수의 영향을 총괄 파라미터인 공정변수비 $\alpha$로 정의하여 나타낼 때 재생 분리효율 95%이상을 얻기 위해서는 $\alpha$가 0.2 이하로 유지되어야 한다. LOMI 제염폐액의 재생시 전기투석 flux는 공정변수비, $\alpha$값이 증가함에 따라 철이온이 바나듐이온에 비해 더욱 커지는 경향을 보였다. 재생종료 후 발생되는 음극폐액내 철 및 코발트 등 방사성이온종은 음극액의 초기 수소이온 농도를 조절하면 침전제의 첨가 얼이 음극반응에 의해 음극액의 pH를 산성에서 알카리성으로 바꿀 수 있어, 수산화물 형태의 침전물 입자로 만들어 쉽게 제거할 수 있다. 재생시 바나듐이온은 대부분 $V^{III}$(Pic)$_2$$^{+}$ 착화물형태로 전기투석된다. 음극액으로 formate용액을 사용하면 철 및 코발트 등 방사성이온종을 제거한 음극액은 농축된 LOMI제염제로 회수하여 필요시 산화가를 조정한 후 재생된 착화제와 혼합하여 제염제로 재사용할 수 있어, 더욱 효과적으로 제염폐액을 재생하는 향상된 재생방법이다.다.

• Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
• /
• v.16 no.4
• /
• pp.421-429
• /
• 2018

Hydrazine based reductive dissolution applied on magnetite oxide was investigated. Dissolution of Fe(II) and Fe(III) from magnetite takes place either by protonation, surface complexation, or reduction. Solution containing hydrazine and sulfuric acid provides hydrogen to break bonds between Fe and oxygen by protonation and electrons for the reduction of insoluble Fe(III) to soluble Fe(II) in acidic solution of pH 3. In terms of dissolution rate, numerous transition metal ions were examined and Cu(II) ion was found to be the most effective to speed up the dissolution. During the cycle of Cu(I) ions to Cu(II) ions, the released electron promoted the reduction of Fe(III) and Cu(II) ions returned to Cu(I) ion due to the oxidation of hydrazine. In the experimental results, the addition of a very low amount of cupric ion (about 0.5 mM) to the solution increased the dissolution rate about 40% on average and up to 70% for certain specific conditions. It is confirmed that even though the coordination structure of copper ions with hydrazine is not clear, the $Cu(II)/H^+/N_2H_4$ system is acceptable regarding the dissolution performance as a decontamination reagent.

• Journal of Radiation Protection and Research
• /
• v.34 no.4
• /
• pp.195-200
• /
• 2009

effluents to the environment. The activity of carbon-14, one of the radioactive effluents, in the environment is already high level and its effect on radiation exposure to the public and the environment is insignificant; thus, NPPs did not perform the carbon-14 monitoring in effluents in the past. By the way, effluents of noble gas and particulate radioactive materials originated from nuclear fuels has been continuously reduced due to both the advancement of manufacturing and integrity technology for nuclear fuels and the improvement of operation methods of NPPs. Futhermore, the portion of dose assessment by tritium and carbon-14 to the public has been relatively increased because the lower limit of detection for low-energy beta sources, such as tritium and carbon-14, is low due to the advancement of radiation detection technology. In this paper, the technical background for carbon-14 monitoring in nuclear facilities was investigated using United States technical reports and papers. This paper also reviews whether carbon-14 monitoring is necessary or not based on the investigated documents.

• CORROSION AND PROTECTION
• /
• v.12 no.1
• /
• pp.30-38
• /
• 2013

Austenitic stainless steels and Ni-base alloys are widely used as structural materials for major components and piping system in pressurized water reactors (PWRs). These austenitic alloys are known to be susceptible to environmental assisted cracking (EAC), such as environmentally-assisted fatigue (EAF) and primary water stress corrosion cracking (PWSCC) during long-term exposure to PWR primary water environment. In this paper, the current understanding on the phenomena and mechanisms of these EAC are briefly introduced using experimental results and literature review. The mechanisms for EAF and PWSCC for austenitic stainless steels and Ni-base alloys are discussed. Currently, austenitic stainless steels are known to be more susceptible to EAF, while less susceptible to PWSCC than Ni-base alloys. The possible explanations to such behaviors are proposed and discussed in view of the role of hydrogen and internal oxidation.

• Journal of the Mineralogical Society of Korea
• /
• v.20 no.4
• /
• pp.351-356
• /
• 2007

The crystal structure of $Li(ND_4)SO_4$ was analyzed by X-ray and neutron diffraction methods. The crystal is a deuterated $Li(NH_4)SO_4$ and one of the ferroelectric materials with hydrogen atoms. The crystal is orthorhombic at room temperature, $P2_1nb$, with lattice parameters of $a=5.2773(5)\;{\AA},\;b=9.1244(23)\;{\AA},\;c=8.7719(11)\;{\AA}$ and Z=4. Neutron intensity data were collected on the Four-Circle diffractometer (FCD) at HANARO in Korea Atomic Energy Research Institute and X-ray date were given by Prof. Y. Noda of Tohoku University Japan. The structure was refined by full-matrix least-square to final R value of 0.070 for 1450 observed reflections by X-ray diffraction and to final R=0.049 for 745 observed reflections by neutron diffraction. With X-ray data we obtained only one hydrogen atomic position. However, not only all atomic positions of four hydrogen atoms at $NH_4$ but also the occupation factors of D and H were refined with neutron data. From this results we obtained the average chemical structure of this sample, $LiND_{3.05}H_{0.95}SO_4$.

• Nuclear Engineering and Technology
• /
• v.16 no.3
• /
• pp.141-154
• /
• 1984

An analysis is presented of key phenomena and scenario which imply some general trends for beyond design-basis-accident in Kori-1 PWR dry containment. The study covers a wide range of severe accident sequences initiated by small break LOCA. The MARCH computer code, with KAERI modifications was used in this analysis. The major emphasis of the paper are two folds, 1) the phenomenologic understanding of severe accident and 2) a study of H2 combustion and debris/ water interactions in a specific small break LOCA for Kori-1 plant. The sensitivity studies for the specific plant data and thermal interaction modelings used in the SASA were performed. The results show that if hydrogen burning does occur at low concentration, the resulting peak pressure does not exceed the design value, while the lower concentration assumption results in repeated burning due to the continuing H$_2$ generation. For debris/water interaction, the particle size has no effect on the magnitude of peak pressure for the amount of water assumed to be in the reactor cavity. But, the occurrence of peak pressure is considerably delayed in case of using the dryout correlation. The peak containment pressure predicted from the hydrogen combustion and steam pressure spite during full core meltdown scenario does not present a severe threat to the containment integrity.