• 제목/요약/키워드: Isotopic Analysis

검색결과 161건 처리시간 0.024초

Stable Isotope Chemistry of Bone Collagen and Carbonate Assessed by Bone Density Fractionation

  • Shin, Ji-Young
    • Bulletin of the Korean Chemical Society
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    • 제32권10호
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    • pp.3618-3623
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    • 2011
  • This paper presents a stable isotope chemistry of bone collagen and carbonate. Bone carbonate has the potential to provide additional isotopic information. However, it remains controversial as to whether archaeological bone carbonate retains its original biogenic signature. I used a novel application of bone density fractionation and checked the integrity of ${\delta}^{13}C_{apa}$ values using radiocarbon dating. Diagenesis in archaeological bone carbonate still remains to be resolved in extracting biogenic information. The combined use of bone density fractionation and differential dissolution method shows a large shift in the ${\delta}^{13}C_{apa}$ values. Although ${\delta}^{13}C_{apa}$ values are improved in lighter density fractions, a large percentage of contamination in bone carbonate was reported via $^{14}C$ dating compared to that noted with bone collagen.

Novel homogeneous burnable poisons in pressurized water reactor ceramic fuel

  • Dodd, Brandon;Britt, Taylor;Lloyd, Cody;Shah, Manit;Goddard, Braden
    • Nuclear Engineering and Technology
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    • 제52권12호
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    • pp.2874-2879
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    • 2020
  • Due to excess reactivity, fresh nuclear fuel often contains burnable poisons. This research looks at six different burnable poisons and their impacts on reactivity, material attractiveness, and waste management. An MCNP simulation of a PWR fuel pin was performed with a fuel burnup of 60 GWd/MTHM to determine when each burnable poison fuel type would decrease below a k of 1. For determining the plutonium material attractiveness in each burnable poison fuel type, the plutonium isotopic content of the used fuel was evaluated using Bathke's Figure of Merit formula. For the waste management analysis, the thermal output of each burnable poison fuel type was determined through ORIGEN decay simulations at 100 and 300 years after being discharged from the core. The performance of all six burnable poisons varied over the three criteria considered and no single burnable poison performed best in all three considerations.

Revised Geology and Geological Structures of the Northeastern Chungnam Basin in the Southwestern Korean Peninsula

  • Yujung Kwak;Seung-Ik Park;Jeong-Yeong Park;Taejin Choi;Eun Hye Jeong
    • 자원환경지질
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    • 제55권6호
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    • pp.597-616
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    • 2022
  • The Chungnam basin is a crucial area for studying the Mesozoic crustal evolutionary history of the Korean Peninsula. This study reports the revised geology and new isotopic ages from the northeastern Chungnam Basin based on detailed geological mapping and LA-ICP-MS zircon U-Pb analysis. Our renewed geologic map defines intra-basin, basin-bounding, and basement fault systems closely related to hydrothermal gold-bearing quartz vein injections. Here, we propose the directions of (micro)structural and geochronological future work to address issues on the relationship between the tectonic process, basin evolution, and hydrothermal fluid migration in the southwestern Korean Peninsula.

Uncertainty quantification in decay heat calculation of spent nuclear fuel by STREAM/RAST-K

  • Jang, Jaerim;Kong, Chidong;Ebiwonjumi, Bamidele;Cherezov, Alexey;Jo, Yunki;Lee, Deokjung
    • Nuclear Engineering and Technology
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    • 제53권9호
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    • pp.2803-2815
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    • 2021
  • This paper addresses the uncertainty quantification and sensitivity analysis of a depleted light-water fuel assembly of the Turkey Point-3 benchmark. The uncertainty of the fuel assembly decay heat and isotopic densities is quantified with respect to three different groups of diverse parameters: nuclear data, assembly design, and reactor core operation. The uncertainty propagation is conducted using a two-step analysis code system comprising the lattice code STREAM, nodal code RAST-K, and spent nuclear fuel module SNF through the random sampling of microscopic cross-sections, fuel rod sizes, number densities, reactor core total power, and temperature distributions. Overall, the statistical analysis of the calculated samples demonstrates that the decay heat uncertainty decreases with the cooling time. The nuclear data and assembly design parameters are proven to be the largest contributors to the decay heat uncertainty, whereas the reactor core power and inlet coolant temperature have a minor effect. The majority of the decay heat uncertainties are delivered by a small number of isotopes such as 241Am, 137Ba, 244Cm, 238Pu, and 90Y.

Evaluation of peak-fitting software for magnesium quantification through k0-instrumental neutron activation analysis

  • Dasari, Kishore B.;Cho, Hana;Jacimovic, Radojko;Park, Byung-Gun;Sun, Gwang-Min
    • Nuclear Engineering and Technology
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    • 제54권2호
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    • pp.462-468
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    • 2022
  • The selection and effective utilization of peak-fitting software for conventional gamma-ray spectrum analysis is significant for accurate determination of the mass fraction of elements, particularly in complex peak regions. Majority of the peak-fitting programs can derive similar peak characteristics for singlet peaks, but very few programs can deconvolute multi-peaks in a complex region. The deconvolution of multi-peaks requires special peak-fitting functions, such as left and right-skew distributions. In the this study, 843.76 keV (27Mg) peak area from the complex region (840 keV-850 keV) determined and compared using four different peak-fitting programs, namely, GammaVision, Genie2000, HyperLab, and HyperGam. The 843.76 keV peak interfered with 841.63 keV (152mEu) and 846.81 keV (56Mn). The total Mg concentration was determined through k0-instrumental neutron activation analysis by applying the isotopic interference correction factor 27Al(n,p)27Mg through the simultaneous determination of Al concentration. HyperLab and HyperGam peak-fitting programs reported consistent peak areas, and resultant concentrations agreed with the certified values of matrix-certified reference materials.

Quadrupole Mass Spectrometry를 이용한 핵연료봉내 기체분석 (Analysis of Gases in Nuclear Fuel Rod by Quadrupole Mass Spectrometry)

  • 김승수;강문자;박순달;박용준;조기수
    • 분석과학
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    • 제12권2호
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    • pp.94-98
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    • 1999
  • Quadrupole Mass Spectrometer를 이용하여 핵연료봉으로부터 포집된 1기업이하 소량의 기체들로부터 그들의 조성과 동위원소비를 구하는 방법을 검토하였다. He, $N_2$, $O_2$, Ar, Kr, Xe의 개별기체와 혼합기체를 이용하여 기체압력과 조성비에 따른 검정곡선의 직선성을 조사하였다. Sample chamber와 analyser chamber 사이에 부착된 molecular leak의 영향을 조사하였으며, 시료와 유사한 조성을 갖는 혼합표준기체로부터 각 기체의 감도를 얻은 후 동일조건에서 시료를 분석하였다. 측정압력 범위에서 Kr과 Xe의 동위원소간 감도차는 크게 나타나지 않았다.

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Impact of molybdenum cross sections on FHR analysis

  • Ramey, Kyle M.;Margulis, Marat;Read, Nathaniel;Shwageraus, Eugene;Petrovic, Bojan
    • Nuclear Engineering and Technology
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    • 제54권3호
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    • pp.817-825
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    • 2022
  • A recent benchmarking effort, under the auspices of the Organization for Economic Cooperation and Development (OECD) Nuclear Energy Agency (NEA), has been made to evaluate the current state of modeling and simulation tools available to model fluoride salt-cooled high temperature reactors (FHRs). The FHR benchmarking effort considered in this work consists of several cases evaluating the neutronic parameters of a 2D prismatic FHR fuel assembly model using the participants' choice of simulation tools. Benchmark participants blindly submitted results for comparison with overall good agreement, except for some which significantly differed on cases utilizing a molybdenum-bearing control rod. Participants utilizing more recently updated explicit isotopic cross sections had consistent results, whereas those using elemental molybdenum cross sections observed reactivity differences on the order of thousands of pcm relative to their peers. Through a series of supporting tests, the authors attribute the differences as being nuclear data driven from using older legacy elemental molybdenum cross sections. Quantitative analysis is conducted on the control rod to identify spectral, reaction rate, and cross section phenomena responsible for the observed differences. Results confirm the observed differences are attributable to the use of elemental cross sections which overestimate the reaction rates in strong resonance channels.

Relative Quantification of Glycans by Metabolic Isotope Labeling with Isotope Glucose in Aspergillus niger

  • Choi, Soo-Hyun;Cho, Ye-Eun;Kim, Do-Hyun;Kim, Jin-il;Yun, Jihee;Jo, Jae-Yoon;Lim, Jae-Min
    • Mass Spectrometry Letters
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    • 제13권4호
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    • pp.139-145
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    • 2022
  • Protein glycosylation is a common post-translational modification by non-template-based biosynthesis. In fungal biotechnology, which has great applications in pharmaceuticals and industries, the importance of research on fungal glycoproteins and glycans is accelerating. In particular, the importance of quantitative analysis of fungal glycans is emerging in research on the production of filamentous fungal proteins by genetic modification. Reliable mass spectrometry-based techniques for quantitative glycomics have evolved into chemical, enzymatic, and metabolic stable isotope labeling methods. In this study, we intend to expand quantitative glycomics by metabolic isotope labeling of glycans in Aspergillus niger, a filamentous fungus model, by the MILPIG method. We demonstrate that incubation of filamentous fungi in a culture medium with carbon-13 labeled glucose (1-13C1) efficiently incorporates carbon-13 into N-linked glycans. In addition, for quantitative validation of this method, light and heavy glycans are mixed 1:1 to show the performance of quantitative analysis of various N-linked glycans simultaneously. We have successfully quantified fungal glycans by MILPIG and expect it to be widely applicable to glycan expression levels under various biological conditions in fungi.

Fissile Measurement in Various Types Using Nuclear Resonances

  • YongDeok Lee;Seong-Kyu Ahn
    • 방사성폐기물학회지
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    • 제21권2호
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    • pp.235-246
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    • 2023
  • Neutron resonance transmission technique was applied for assaying isotopic fissile materials produced in the pyro-process. In each process of the pyro-process, a different composition of the fissile material is produced. Simulation was basically performed on 235U and 239Pu assay for TRU-RE product, hull waste, and uranium addition. The resonance energies were evaluated for uranium and plutonium in the simulation, and the linearity in the detection response was examined on the fissile content variation. The linear resonance energies were determined for the analysis of 235U and 239Pu on the different fissile materials. For enriched TRU-RE assay, the sample condition was suggested; The sample density, content, and thickness are the key factors to obtain accurate fissile content. The detection signal is discriminated for uranium and plutonium in neutron resonance technique. The transmitted signal for fissile resonance has a direct relation with the content of fissile. The simulation results indicated that the neutron resonance technique is promising to analyze 235U and 239Pu for various types of the pyro-process material. An accurate fissile assay will contribute toward safeguarding the pyro-processing system.

다검출기 유도결합 플라즈마 질량분석기를 이용한 스트론튬 동위원소비 분석법 개선 (Improving Strontium Isotope Ratio Analysis Using MC-ICP-MS)

  • 이신우;박재선;박현우;황종연;김금희;정현미;최종우
    • 환경분석과 독성보건
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    • 제21권4호
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    • pp.237-242
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    • 2018
  • Strontium (Sr) commonly exists in rock, groundwater, soil, plants, and animals. The Sr isotope ratio offers important information as a tracer on nature because the Sr isotopic composition is not fractionated by any biological process in these ecosystems. Hence, Sr isotope ratio has been used in several studies on tracing the Sr source for contaminated sites and human migration. In this study, we developed a separation method for Sr content, and then improved Sr isotope analysis using multi-collector inductively coupled plasma mass spectrometry (MC-ICP-MS). A powdered rock standard (NIST 2710a) was used to determine the removal of interference elements (Rb and Ca) and the recovery rate of Sr content. The results ranged from 98% to 106%. Additionally, three standard samples (NBS 987, IAPSO and NIST 1486) were analyzed to evaluate the precision and accuracy of the results. The measured $^{87}Sr/^{86}Sr$ ratio for all the samples were consistent with the reported values, within an error. These results indicate that our established Sr separation and Sr isotope measurement methods are reliable and can hence be useful in the fields of environmental and forensic sciences.