• Nuclear Engineering and Technology
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• 제54권8호
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• pp.2792-2800
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• 2022

In the core of the WWR-K reactor, a long-term irradiation of tristructural isotopic (TRISO)-coated fuel particles (CFPs) with a UO₂ kernel was carried out under high-temperature gas-cooled reactor (HTGR)-like operating conditions. The temperature of this TRISO fuel during irradiation varied in the range of 950-1100 ℃. A fission per initial metal atom (FIMA) of uranium burnup of 9.9% was reached. The release of gaseous fission products was measured in-pile. The release-to-birth ratio (R/B) for the fission product isotopes was calculated. Aspects of fuel safety while achieving deep fuel burnup are important and relevant, including maintaining the integrity of the fuel coatings. The main mechanisms of fuel failure are kernel migration, silicon carbide corrosion by palladium, and gas pressure increase inside the CFP. The formation of gaseous fission products and carbon monoxide leads to an increase in the internal pressure in the CFP, which is a dominant failure mechanism of the coatings under this level of burnup. Irradiated fuel compacts were subjected to electric dissociation to isolate the CFPs from the fuel compacts. In addition, nondestructive methods, such as X-ray radiography and gamma spectrometry, were used. The predicted R/B ratio was evaluated using the fission gas release model developed in the high-temperature test reactor (HTTR) project. In the model, both the through-coatings of failed CFPs and as-fabricated uranium contamination were assumed to be sources of the fission gas. The obtained R/B ratio for gaseous fission products allows the finalization and validation of the model for the release of fission products from the CFPs and fuel compacts. The success of the integrity of TRISO fuel irradiated at approximately 9.9% FIMA was demonstrated. A low fuel failure fraction and R/B ratios indicated good performance and reliability of the studied TRISO fuel.

• Nuclear Engineering and Technology
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• 제54권7호
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• pp.2367-2375
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• 2022

In this work, we propose a new mechanistic model for the treatment of helium behaviour at the grain boundaries in oxide nuclear fuel. The model provides a rate-theory description of helium inter-granular behaviour, considering diffusion towards grain edges, trapping in lenticular bubbles, and thermal resolution. It is paired with a rate-theory description of helium intra-granular behaviour that includes diffusion towards grain boundaries, trapping in spherical bubbles, and thermal re-solution. The proposed model has been implemented in the meso-scale software designed for coupling with fuel performance codes SCIANTIX. It is validated against thermal desorption experiments performed on doped UO₂ samples annealed at different temperatures. The overall agreement of the new model with the experimental data is improved, both in terms of integral helium release and of the helium release rate. By considering the contribution of helium at the grain boundaries in the new model, it is possible to represent the kinetics of helium release rate at high temperature. Given the uncertainties involved in the initial conditions for the inter-granular part of the model and the uncertainties associated to some model parameters for which limited lower-length scale information is available, such as the helium diffusivity at the grain boundaries, the results are complemented by a dedicated uncertainty analysis. This assessment demonstrates that the initial conditions, chosen in a reasonable range, have limited impact on the results, and confirms that it is possible to achieve satisfying results using sound values for the uncertain physical parameters.

• 한국식품영양과학회지
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• 제35권2호
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• pp.231-237
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• 2006

알긴산을 선택적으로 분해하는 Bacillus licheniformis AL-577 균주가 생산하는 균체 외 효소를 정제하고 특성을 밝혔다. CM-Cellulose, DEAE-Sepharose 및 Gel 크로마토 그래프 등의 순서대로 정제하여 정제도가 약 98배 정도인 효소를 얻었다. 정제효소의 활성 최적 pH 및 온도는 5.0 및 $35^{\circ}C$이었고, pH 5.5이하와 pH 9.5이상의 반응조건에서는 불안정하였으며, $20^{\circ}C$이상의 온도에서는 불활성화가 쉽게 일어나는 효소였다. 얻어진 효소를 SDS-PAGE로 분자량을 측정한 결과 25,500 Da으로 추정되었다. NaCl 0.2 M 농도에서 최대의 활성을 나타내었고, 무첨가시에도 활성은 약간 나타내었다. $Cu^{2+},\;Fe^{2+},\;Mg^{2+},\;Zn^{2+}$ 등과 같은 2가 금속이 온에 의해서는 활성이 현저히 억제되었고, $K^+,\;Li^+$ 이온에 의해서 활성이 촉진됨을 알 수 있었다. 화학약품인 dithiothreitol 와 O-phenanthroline의 첨가로 인하여 약간의 활성 증가를 가져 왔으며 반면 EDTA, L-cysteine는 현저하게 감소하였다. 이 효소는 알긴산에만 특이적으로 작용함으로써 본 효소는 alginase 또는 alginate lyase인 것으로 판단되었다.

• 한국광물학회:학술대회논문집
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• 한국광물학회.한국암석학회 2003년도 공동학술발표회 논문집
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• pp.67-67
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• 2003

The chemical compositions and textural relationships of the Nb-Zr oxide minerals including pyrochlore [ideally (Ca,Na)$_2$Nb$_2$O$\sub$6/(OH,F), with up to 24% UO$_2$ and 16% Ta$_2$O$\sub$5/] and baddeleyite [ideally ZrO$_2$, with up to 6% Nb$_2$O$\sub$5/] in the Sokli carbonatite complex, Kola Peninsula, Arctic are described. These two minerals in carbonatites are the major hosts for the HFSEs such as U, Th, Ta, Nb, Zr and Hf and thus are interest both economically and petrologically. The Sokli carbonatite complex (360-370 Ma) in Northern Finland, which forms a part of the Paleozoic Kola Alkaline Province (KAP), is mainly composed of multi-stages of carbonatite and phoscorite associations (P1-C1 P2-C2, P3-C3, D4 and D5) surrounded by altered ultramafic rocks (olivinite and pyroxenite) and cut by numerous small dikes of ultramafic lamprophyre. The Sokli complex contains the highest concentration in niobium and probably in tantalum, which are economically very important to modern steel technology, among the ultramafic-alkaline complexes of the KAP. Pyrochlore and baddeleyite mostly concentrate in the phoscorites. Pyrochlores in the Sokli complex are generally rounded octahedra and cubes in shape, red brown to grey yellow in color, and 0.2 to 5 mm in size. They are found in all calcite carbonatites, phoscorites and dolomite carbonatites, except P1-C1 rocks. These pyrochlores display remarkable zonations which depend on host rock compositions, and have significant compositional variations with evolution of the Sokli complex. The common variation scheme is that (1) early pyrochlore is highly enriched in U and Ta; (2) these elements decrease abruptly in the intermediate stage, while Th and Ce increase, and (3) late stage pyrochlore is low in U, Ta, Th, and Ce, and correspondingly high in Nb. Baddeleyites in the Sokli complex occur in the early P1-C1 and P2-C2 rocks and rarely in P3. They crystallized earlier than pyrochlores, and occasionally show post-magmatic corrosion and replacement. The FeO and TiO$_2$ contents of baddeleyites are much lower than those of the other terrestrial and lunar baddeleyites, whereas Nb$_2$O$\sub$5/ and Ta$_2$O$\sub$5/ contents are the highest among the reported compositions. Ta/Nb and Zr/Nb ratios of pyrochlores and baddeleyites decrease towards later stage facies, which is in accordance with the whole rock compositions. The variation of Ta/Nb and Zr/Nb ratios of pyrochlores and baddeleyites is considered to be a good indicator to trace an evolution of the carbonatite complexes.

• 자원환경지질
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• 제30권5호
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• pp.395-406
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• 1997

Some RE (Zr, Nb, REE) ore deposits are located in the middle part of the Korean peninsula. Geotectonically, the RE ore deposits situated on the Kyemyeongsan Formation of northern margin of the Okcheon geosynclinal belt and in the transitional zone between Kyeonggi massif and Okcheon belt. The rare metal deposits distributed in Kyemyeongsan Formation which consists of schist and alkaline granite. The alkali granite has suffered extensive post-magmatic metasomatism and hydrothermal processes. The ore contains mainly Ce-La, Ta-Nb, Y, Y-Nb, Ti-Nb-(U), Nd-Th group minerals. Fergusonite, one of Nb-Y rich REE minerals belonging to the A-B oxides, is most common mineral in the rare metal deposits. The fergusonite bearing rocks may be devided into four types by occurrence features and mineral association, that is, zircon type, allanite vein, feldspar type, and fluorite type. Fergusonites show wide variations in optical properties, due to part of differences in their chemical composition (depending on the types), but also the degree of crystalinity of the individual specimens. Fergusonite metamicts enclosed in biotite are generally surrounded by well developed pleochroic haloes. Usually, fergusonite is accompanied with zircon and other REE-bearing minerals. Petrographical and chemical data are presented for fergusonites which collected different types. $Nb_2O_3$ and $Y_2O_3$ contents range from 48.51 to 53.01 wt.% and 29.18 to 42.02 wt.% respectively. Also, $ThO_2$, (1.83~6.93), $UO_2$, (0.17~2.84), ${\sum}RE_2O_3$ (except to Y) (1.11~8.73), and $TiO_2$, (0.19~1.19 wt.%) contents show variational compositions according to fergusonite types. The ${\sum}RE_2O_3$ of fergusonites are positive relation with $Y_2O_3$ and negative relaton with $ThO_2$ and $({\sum}{RE_2O_3}-{Y_2O_3})$. The $Nb_2O_3$ is sightly negative relation with $Ta_2O_3$. Back-scattered electron microscope images (BEI) of fergusonite show the mineral composition and textural feature is very complicated. The variation of Nb, Th and REE content of fergusonite and the modes of occurrence of mineral, suggests that REE may have been mobilized during the circulation of hydrothermal fluids related to contact metamorphism (metasomatism). The chemical variation of the fergusonites with occurrences and mineral association can be related to metasomatism of alkaline fluid was probably the dominant ore-forming process in Chungju district.

• Nuclear Engineering and Technology
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• 제46권4호
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• pp.547-556
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• 2014

Korea expects a shortage in storage capacity for spent fuels at reactor sites. Therefore, a need for more metal and/or concrete casks for storage systems is anticipated for either the reactor site or away from the reactor for interim storage. For the purpose of interim storage and transportation, a dual purpose metal cask that can load 21 spent fuel assemblies is being developed by Korea Radioactive Waste Management Corporation (KRMC) in Korea. At first the gamma and neutron flux for the design basis fuel were determined assuming in-core environment (the temperature, pressure, etc. of the moderator, boron, cladding, $UO_2$ pellets) in which the design basis fuel is loaded, as input data. The evaluation simulated burnup up to 45,000 MWD/MTU and decay during ten years of cooling using the SAS2H/OGIGEN-S module of the SCALE5.1 system. The results from the source term evaluation were used as input data for the final shielding evaluation utilizing the MCNP Code, which yielded the effective dose rate. The design of the cask is based on the safety requirements for normal storage conditions under 10 CFR Part 72. A radiation shielding analysis of the metal storage cask optimized for loading 21 design basis fuels was performed for two cases; one for a single cask and the other for a $2{\times}10$ cask array. For the single cask, dose rates at the external surface of the metal cask, 1m and 2m away from the cask surface, were evaluated. For the $2{\times}10$ cask array, dose rates at the center point of the array and at the center of the casks' height were evaluated. The results of the shielding analysis for the single cask show that dose rates were considerably higher at the lower side (from the bottom of the cask to the bottom of the neutron shielding) of the cask, at over 2mSv/hr at the external surface of the cask. However, this is not considered to be a significant issue since additional shielding will be installed at the storage facility. The shielding analysis results for the $2{\times}10$ cask array showed exponential decrease with distance off the sources. The controlled area boundary was calculated to be approximately 280m from the array, with a dose rate of 25mrem/yr. Actual dose rates within the controlled area boundary will be lower than 25mrem/yr, due to the decay of radioactivity of spent fuel in storage.

• 분석과학
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• 제23권6호
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• pp.566-571
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• 2010

양이온 교환능력을 갖는 합성 K-birnessite를 이용하여 수용성 우라늄 이온($UO_2^{2+}$)에 대한 흡착 거동을 조사하였다. K-birnessite는 KMnO4 수용액과 염산을 반응시켜 합성하였으며, 합성된 K-birnessite의 구조, 비표면적 및 표면전하 등 물리화학적 특성을 규명하였다. $K^+$ 이온은 층상구조를 갖는 $MnO_2$ 층간에 존재하였으며, BET 비표면적은 $38.30\;m^2/g$이었다. 우라늄 흡착실험 조건인 pH 5.00, 이온세기 0.010M $NaClO_4$에서 측정된 K-birnessite의 표면전하는 $-1.65\;C/m^2$이었다. 우라늄 이온은 K-birnessite 층간의 $K^+$와 이온교환 반응을 통하여 흡착하였으며, 분배계수는 일반적인 이온교환물질과 유사하였다. 본 연구결과는 고준위 방사성 폐기물 지하처분장으로부터 유출될 수 있는 방사성물질의 이동을 저지하는 방법으로 활용될 수 있을 것이다.

• 한국패류학회지
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• 제18권2호
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• pp.77-82
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• 2002

피조개 D형 유생을 냉동보존하기 위한 적절한 첨가제 종류와 농도 및 동해방지제로 적용한 ethylene glycol 농도에 대한 냉동보존 효과실험을 실시하였다. 유생을 0$^{\circ}C$로 설정된 프로그램 냉동기로 옮겨 -1$^{\circ}C$/분의 냉동율로 -12$^{\circ}C$까지 냉동한 후 10분 동안 유지한 상태에서 식빙하고 -35$^{\circ}C$까지 재냉동한 다음, 즉시 액체질소통에 저장하였다. 1.0 M과 2.0 M ethylene glycol을 동해방지제로 사용하여 첨가제별로 D형 유생을 냉동한 결과, 0.5 M sucrose에서 생존율이 각각 50.5 ${\pm}$ 1.3%, 51.9 ${\pm}$ 1.7%로 가장 좋았다. 0.5 M sucrose를 첨가한 ethylene glycol의 농도별 냉동에서는 2.0 M이 생존율 51.9 ${\pm}$ 1.7%로 가장 높았다. 주사 및 투과전자현미경을 이용하여 유생을 관찰한 결과, 냉동 전, 후 유생의 외부형태 및 세포내 구조의 차이가 인정되지 않았다.

• Nuclear Engineering and Technology
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• 제49권7호
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• pp.1547-1554
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• 2017

VESTA (Verification of Ex-vessel corium STAbilization) and VESTA-S (-small) test facilities were constructed at the Korea Atomic Energy Research Institute in 2010 to perform various corium melt experiments. Since then, several tests have been performed for the verification of an ex-vessel core catcher design for the EU-APR1400. Ablation tests of an impinging $ZrO_2$ melt jet on a sacrificial material were performed to investigate the ablation characteristics. $ZrO_2$ melt in an amount of 65-70 kg was discharged onto a sacrificial material through a well-designed nozzle, after which the ablation depths were measured. Interaction tests between the metallic melt and sacrificial material were performed to investigate the interaction kinetics of the sacrificial material. Two types of melt were used: one is a metallic corium melt with Fe 46%, U 31%, Zr 16%, and Cr 7% (maximum possible content of U and Zr for C-40), and the other is a stainless steel (SUS304) melt. Metallic melt in an amount of 1.5-2.0 kg was delivered onto the sacrificial material, and the ablation depths were measured. Penetration tube failure tests were performed for an APR1400 equipped with 61 in-core instrumentation penetration nozzles and extended tubes at the reactor lower vessel. $ZrO_2$ melt was generated in a melting crucible and delivered down into an interaction crucible where the test specimen is installed. To evaluate the tube ejection mechanism, temperature distributions of the reactor bottom head and in-core instrumentation penetration were measured by a series of thermocouples embedded along the specimen. In addition, lower vessel failure tests for the Fukushima Daiichi nuclear power plant are being performed. As a first step, the configuration of the molten core in the plant was investigated by a melting and solidification experiment. Approximately 5 kg of a mixture, whose composition in terms of weight is $UO_2$ 60%, Zr 10%, $ZrO_2$ 15%, SUS304 14%, and $B_4C$ 1%, was melted in a cold crucible using an induction heating technique.

• 공업화학
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• 제28권3호
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• pp.345-350
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• 2017

원자력연료 제조공정에서 생산되는 우라늄산화물(uranium oxide, UOX) 소결체의 밀도 분석은 일반적으로 소결공정을 거친 후, 소결체의 표본을 가지고 측정한다. 본 연구에서는 우라늄산화물의 중간물질인 중우라늄산암모늄(ammonium diuranate)의 색도를 분광기(spectrophotometer)로 측정함으로써 소결공정 이전에 우라늄산화물 소결체의 밀도를 분석해 보았다. 중우라늄산암모늄 표준 샘플 5개를 통해 얻은 명도 및 색의 좌푯(L, a, b)값과 통상적인 방법으로 얻은 소결체 밀도의 상관관계 추세선을 바탕으로 표적 샘플의 밀도를 분석한 결과, L 값에 대한 소결체의 밀도 분석이 결정계수 $R^2$ 값 0.9967로 가장 신뢰성이 높게 나왔음을 확인하였다. a 값에 대한 결정계수 $R^2$ 값은 0.9534로 상관관계가 높은 편이나 L 값보다는 낮았다. 이에 반해 b 값에 대한 결정계수 $R^2$ 값은 0.4349로 상관관계가 거의 없었다.