• Proceedings of the Optical Society of Korea Conference
• /
• 2005.07a
• /
• pp.300-301
• /
• 2005

• Proceedings of the Korean Radioactive Waste Society Conference
• /
• 2012.05a
• /
• pp.391-392
• /
• 2012

• Proceedings of the Korean Radioactive Waste Society Conference
• /
• 2003.11a
• /
• pp.351-357
• /
• 2003

Transuranic elements such as Pu, Am and Cm in synthetic solution of spent nuclear fuel samples were determined by electrodeposition followed by alpha-spectrometry after separation using anion exchange and extraction chromatography in order to determine the transuranic elements in radwaste samples from nuclear power plants. Plutonium was separated by 12M HC1-0.1M HI as an eluent on anion exchange column. As a second step Am and Cm were separated in a group by DTPA-Lactic acid as the eluent on HDEHP coated column. The nuclides of $^{239}Pu$, $^{241}Am$및 $^{244}Cm$ separated were determined by alpha-spectrometry after electrodeposition in 0.1M $NaHSo_4$-0.53M $Na_2SO_4$buffer solution as an electrolyte. The recovery yields of $^{239}Pu$, $^{241}Am$및 $^{244}Cm$ were 83.8%, 85.2% and 86.3%, respectively, from the synthetic solution containing uranium and non-radioactive metal elements.

• Korean Journal of Materials Research
• /
• v.6 no.3
• /
• pp.324-332
• /
• 1996

DLC 박막을 RF 플라즈마 화학증착법(PECVD)을 이용하여 CH4와 CO2기체로부터 합성하였다. 증착압력, CH4와 CO2가스의 조성비, 바이어스 전압(-VB) 등의 증착조건 변화에 따른 증착속도는 증착층의 두께를 알파스텝으로 측정하여 결정하였으며, 박막의 구조 변화에 따른 증착속도는 증착층의 두께를 알파스텝으로 측정하여 결정하였으며, 박막의 구조 변화는 FTIR 분광분석을 이용하여 분석을 행하였다. 이 연구로부터 얻은 실험 결과는 다음과 같다: 1) 증착속도는 증착압력 및 바이어스 전압의 증가에 따라 증가한다. 2)바이어스 전압 300V이상에서, CO2량 증가는 순증착속도를 증가 시킨다. 3) 순수한 CH4가스를 사용할 경우에는 바이어스전압(-VB)이 증가함에 따라 박막내 수소의 함량과 sp3/sp2비는 감소하는 경향을 나타낸다. 4)증착압력이 증가함에 따라 박막내 수소함량은 증가하며, sp3/sp2비는 감소한다. 5)50mTorr의 증착압력에 증착시, CH4-+Co2 혼합가스에서 이산화탄소의 부피분율에 따라서는 박막내 수소함량은 감소하며, sp3/sp2비는 증가한다.

• Journal of Radiation Protection and Research
• /
• v.35 no.3
• /
• pp.105-110
• /
• 2010

Using N-type HPGe gamma spectrometer, uranium analysis technique of soil sample is developed where the chemical preprocessing is not a necessity. The results of uranium activities using the method presented in this paper were compared with those results with conventional alpha spectrometer and two results were similar from within uncertainty range. Therefore, this new method will be applied in uranium activity analysis of soil sample.

• Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
• /
• v.3 no.1
• /
• pp.1-7
• /
• 2005

Anion exchange chromatography and HDEHP extraction chromatography using DTPA-lactic acid as an eluent were applied in series for the separation of $^{241}$Am and $^{244}$Cm in radwaste samples. The separated elements were determined by electrodeposition at the sodium hydrogen sulfate-sodium sulfate buffer solution followed by alpha-spectrometry. The recovery yields of $^{241}$Am and $^{244}$Cm were 85.2$\pm$$15.3\%$, respectively, from the synthetic solution of spent nuclear fuel sample. The amounts of 241Am and 2440m determined in radwaste sample solutions of condensate bottoms were at the range of 1.5-1.9 Bq/g and -1.7 Bq/g, respectively.

• Journal of Radiation Protection and Research
• /
• v.38 no.3
• /
• pp.132-137
• /
• 2013

Cryogenic particle detectors have recently been adopted in radiation detection and measurement because of their high energy resolution. Many of these detectors have demonstrated energy resolutions better than the theoretical limit of semiconductor detectors. We report the development of alpha spectrometer using a micro-fabricated magnetic calorimeter coupled to a large-area particle absorber. A piece of gold foil of $2{\times}2{\times}0.05mm^3$ was glued to the paramagnetic temperature sensor made of sputtered Au:Er film to serve as an absorber for incident alpha particles. We performed experiments with 241Am source at cryogen free adiabatic demagnetization refrigerator (CF-ADR). A high energy resolution of 6.8 keV in FWHM was obtained for 5.5 MeV alpha particles.

• Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
• /
• v.16 no.4
• /
• pp.397-410
• /
• 2018

When considering the long-term safety assessment of spent-nuclear fuel management, americium is one of the most radio-toxic actinides. Although spectroscopic methods are widely used for the study of actinide chemistry, application of those methods to americium chemistry has been limited. Herein, we purified $^{241}Am$ to obtain a highly pure stock solution required for spectroscopic studies. Quantitative and qualitative analyses of purified $^{241}Am$ were carried out using liquid scintillation counting, and gamma and alpha radiation spectrometry. Highly sensitive absorption spectrometry coupled with a liquid waveguide capillary cell and time-resolved laser fluorescence spectroscopy were employed for the study of Am(III) hydrolysis and oxalate (Ox) complexation. $Am^{3+}$ ions under acidic conditions exhibit maximum absorbance at 503 nm, with a molar absorption coefficient of $424{\pm}8cm^{-1}{\cdot}M^{-1}$. $Am(OH)_3(s)$ colloidal particles formed under near neutral pH conditions were identified by monitoring the absorbance at around 506-507 nm. The formation of ${Am(Ox)_3}^{3-}$ was detected by red-shifts of the absorption and luminescence spectra of 4 and 5 nm, respectively. In addition, considerable enhancements of the luminescence intensities were observed. The luminescence lifetime of ${Am(Ox)_3}^{3-}$ increased from 23 to 56 ns, which indicates that approximately six water molecules are replaced by carboxylate ligands in the inner-sphere of the Am(III). These results suggest that ${Am(Ox)_3}^{3-}$ is formed through the bidentate coordination of the oxalate ligands.

• Journal of Life Science
• /
• v.12 no.4
• /
• pp.464-468
• /
• 2002

Enzymatic activities and fluorescence spectroscopic properties of the double mutant proteins P96L/F139W, P96L/F258W and a triple mutant protein P96L/F139W/F258W of tryptophan synthase $\alpha$ subunit from Escherichia coli was examined to study tertiary and local structure changes around the tryptophan residues. The enzymatic activities of P96l./F139W and P96L/F258W were similar, but P96L/F139W/F258W had lower activity, as compared to wild type. The fluorescence intensities of double mutant, P96L/F139W and P96L/F258W, were decreased but that of a triple mutant, P96L/F139W/F258W, was increased when compared to wild type. The sum of the maximum fluorescence intensity (fluorescence intensity at the λ$_{max}$) for the double mutant proteins was not equal to the intensity seen in the triple mutant protein. The enzymatic activity and fluorescence data indicate that the replacement of Pro$^{96}$ longrightarrowLeu might affect on the stability of helix 8 and the loop located between strand 4 and helix4. The result suggests that the tertiary structure of triple mutant (P96L/F139W/F258W), being different from wild type, might have more compact residual structure at the vicinity of 139 and 258.8.

• Journal of Radiation Protection and Research
• /
• v.38 no.3
• /
• pp.138-142
• /
• 2013

This study was conducted to measure the uranium concentrations in urine of some members of the general public in Busan and Daejeon and to assess the annual committed effective doses from uranium analysis of daily excretion. As a result, the ranges of total uranium concentrations in the urine for the residents in Busan and Daejeon were found to be 0.556 - 1.53 $mBq\;L^{-1}$ and 2.18 - 4.55 $mBq\;L^{-1}$, respectively. It was noted that the uranium concentrations for the residents in Daejeon were observed to be higher than those for the residents in Busan. This result assumes that the uranium concentrations in the urines for the residents in Daejeon are probably related to the high uranium concentrations contained in the drinking water of Daejeon city. The bedrock of Daejeon, known as granitic rocks formed in the Jurassic period of the Mesozoic Era, contains high uranium contents. Also, results showed no significant correlation with age or sex. The ranges of annual committed effective doses from ingestion of uranium for the residents in Busan and Daejeon were calculated to be 0.472-1.41 ${\mu}Sv$ and 1.99-4.15 ${\mu}Sv$, respectively.