• 정보관리학회지
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• 제23권1호
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• pp.159-179
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• 2006

북아이오와주립대학 도서관은 우수한 교양 커리큘럼을 지원하는 개별화 학습 환경과 다양한 지적, 문화적 커뮤니티를 지원하는 것을 사명으로 하고 있다. 1987년부터 전략적 계획을 수립하기 시작하여 현재 5년 단위로 전략적 계획을 수립하고 있으며, 최근 전략이 어느 정도 달성되고 있는가에 대한 성과측정의 필요성이 제기되었다. 이에 본 연구는 북아이오와주립 대학도서관의 최근 전략적 계획 2004-2009의 내용을 분석하여 전략을 균형성과표의 네 관점으로 전환하는 BSC 모형과 전략지도를 개발하였다. 이와 함께 각 관점별 전략적 목적을 측정하는 핵심성과측정지표와 이를 이끄는 동인들의 인과관계 모형을 개발하여 제시하였다.

• Nuclear Engineering and Technology
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• 제53권3호
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• pp.741-751
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• 2021

There has been a deep interest in trying to find better-performing fuel clad motivated by the desire to decrease the likelihood of the reactor barrier failure like what happened in Fukushima in recent years. In this study, the effect of move towards accident tolerant fuel (ATF) cladding as the most attracting concept for improving reactor safety is investigated for SMART modular reactor. These reactors have less production cost, short construction time, better safety and higher power density. The SiC and FeCrAl materials are considered as the most potential candidate for ATF cladding, and the results are compared with Zircaloy cladding material from reactor physics point of view. In this paper, the calculations are performed by generating PMAX library by DRAGON lattice physics code to be used for further reactor core analysis by PARCS code. The differential and integral worth of control and safety rods, reactivity coefficient, power and temperature distributions, and boric acid concentration during the cycle are analyzed and compared from the conventional fuel cladding. The rod ejection accident (REA) is also performed to study how the power changed in response to presence of the ATF cladding in the reactor core. The key quantitative finding can be summarized as: 20 ℃ (3%) decrease in average fuel temperature, 33 pcm (3%) increase in integral rod worth and cycle length, 1.26 pcm/℃ (50%) and 1.05 pcm/℃ (16%) increase in reactivity coefficient of fuel and moderator, respectively.

• Nuclear Engineering and Technology
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• 제52권12호
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• pp.2725-2732
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• 2020

This paper presents the neutronics benchmark analysis of the first core of the Indonesian multipurpose research reactor RSG-GAS (Reaktor Serba Guna G.A. Siwabessy) calculated by the Serpent Monte Carlo code and the newly released ENDF/B-VIII.0 nuclear data library. RSG-GAS is a 30 MWth pool-type material testing research reactor loaded with plate-type low-enriched uranium fuel using light water as a coolant and moderator and beryllium as a reflector. Two groups of critical benchmark problems are derived on the basis of the criticality and control rod calibration experiments of the first core of RSG-GAS. The calculated results, such as the neutron effective multiplication factor (k) value and the control rod worth are compared with the experimental data. Moreover, additional calculated results, including the neutron spectra in the core, fission rate distribution, burnup calculation, sensitivity coefficients, and kinetics parameters of the first core will be compared with the previous nuclear data libraries (interlibrary comparison) such as ENDF/B-VII.1 and JENDL-4.0. The C/E values of ENDF/B-VIII.0 tend to be slightly higher compared with other nuclear data libraries. Furthermore, the neutron reaction cross-sections of ¹⁶O, ⁹Be, ²³⁵U, ²³⁸U, and S(𝛼,𝛽) of ¹H in H₂O from ENDF/B-VIII.0 have substantial updates; hence, the k sensitivities against these cross-section changes are relatively higher than other isotopes in RSG-GAS. Other important neutronics parameters such as kinetics parameters, control rod worth, and fission rate distribution are similar and consistent among the nuclear data libraries.

• Nuclear Engineering and Technology
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• 제50권1호
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• pp.35-42
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• 2018

This article presents clean core criticality calculations and control rod worth calculations for TRIGA (Training, Research, Isotope production-General Atomics) Mark II research reactor benchmark cores using Winfrith Improved Multi-group Scheme-D/4 (WIMS-D/4) and Program for Reactor In-core Analysis using Diffusion Equation (PRIDE) codes. Cores 133 and 134 were analyzed in 2-D (r, ${\theta}$) and 3-D (r, ${\theta}$, z), using WIMS-D/4 and PRIDE codes. Moreover, the influence of cross-section data was also studied using various libraries based on Evaluated Nuclear Data File (ENDF/B-VI.8 and VII.0), Joint Evaluated Fission and Fusion File (JEFF-3.1), Japanese Evaluated Nuclear Data Library (JENDL-3.2), and Joint Evaluated File (JEF-2.2) nuclear data. The simulation results showed that the multiplication factor calculated for all these data libraries is within 1% of the experimental results. The reactivity worth of the control rods of core 134 was also calculated with different homogenization approaches. A comparison was made with experimental and reported Monte Carlo results, and it was found that, using proper homogenization of absorber regions and surrounding fuel regions, the results obtained with PRIDE code are significantly improved.

• Nuclear Engineering and Technology
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• 제53권8호
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• pp.2454-2463
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• 2021

The objective of this research is to the use of americium (AmO₂) as a burnable absorber effectively instead of conventional gadolinium (Gd₂O₃) for VVER-1200 reactor by analyzing its impacts on reactivity, power peaking factor (PPF), safety factor, and quality of the spent fuel. The assembly is burned to 60 GWd/t by using SRAC-2006 code and JENDL-4.0 data library for finding the optimum amount and effective way of using AmO₂ as a burnable absorber. From these studies, it is found that AmO₂ can decrease the excess reactivity like Gd₂O₃ without changing the criticality life span and enrichment of ²³⁵U. A homogeneous mixture of the 0.20% AmO₂+ 4.95% enriched UO₂ fuel rod (model MF-4) decreases the PPF than the reference assembly. The use of AmO₂+UO₂ in the integral burnable absorber (IBA) rod or the outer layer could also decrease the PPF up to 10 GWd/t but increases rapidly after 30 GWd/t, which could be a safety threat. The fuel temperature coefficient and void coefficient of the model MF-4 are the same as the reference assembly. In addition, 22% of initially loaded Am are burning effectively and contributing to the power production.

• Journal of Periodontal and Implant Science
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• 제29권3호
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• pp.663-676
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• 1999

Porphyromonas gingivalis, a Gram negative, anaerobic, asaccharolytic rod, is one of the most frequently implicated pathogens in human periodontal disease and has a requirement for hemin for growth. A 30 kDa (heated 24 kDa) hemin-binding protein whose expression is both hemin and iron regulated has recently been purified and characterized in this oral pathogen. This study has identified a hemin-binding P. gingivalis protein by expression of a P. gingivalis genomic library in Escherichia coli, a bacterium which does not require or transport exogenous hemin. A library of genomic DNA fragments from P. gingivalis was constructed in plasmid pUC18, transformed into Escherichia coli strain $DH5{\alpha}$ , and screened for recombinant clones with hemin-binding activity by plating onto hemin-containing agar. Of approximately 10,000 recombinant E. coli colonies screened on LB-amp-hemin agar, 10 exhibited a clearly pigmented phenotype. Each clone contained various insert DNA. The Hind III fragment transferred to the T7 RNA polymerase/promoter expression vector system produced a sligltly smaller (21 kDa) protein, a precursor form, immunoreactive to the antibody against the 24 kDa protein, suggesting that the cloned DNA fragment probably carried an entire gene for the 24 kDa hemin-binding protein.

• 한국자원식물학회지
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• 제20권6호
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• pp.491-498
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• 2007

It has been hypothesized that efficient exclusion of methylated retrotransposons and repeated DNA region is one of the rapid and cost-effective approaches for comprehensive gene discovery in large genome size of maize. Three kinds of methylation-sensitive restriction enzymes, HapII, MspI and McrBC, were used to identify the restriction frequency of cytosine methylation sites in maize genome. Roughly 60% of total maize genomic DNA was restricted less than 500bp by McrBC, and the most of restricted small size fraction was composed retrotransposon. In order to validate the efficient construction of gene-rich shotgun library, we compare two gene-rich methyl-filtration shotgun libraries using in vivo and in vitro methyl-filtration system. The size selected DNA fraction by Sau3A-McrBC enzyme treated was very stable and has not appeared modification in E. coli, but most insert DNA size of partially digested with Sau3A were decrease less than 500bp by bacterial methylation-modification system. In compare of retroelements portion, A 44.6% of the sequences were retroelement in unmethyl-filtered library, and the most of them was Copia type, such as Prem, Opie and Ji. The portion of retroelement was drastically decreased to 25% and 20% by in vivo and in vitro filtration system, respectively.

• Nuclear Engineering and Technology
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• 제54권10호
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• pp.3888-3896
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• 2022

Nuclear data is the basis of reactor physics analysis. This paper aim at studying the influence of major evaluated nuclear data libraries, CENDL-3.2, ENDF/B-VIII.0, JEFF-3.3, and JENDL-4.0u, on the neutronics modelling of CEFR start-up tests. Results show these four libraries have a good performance and consistency in the modelling CEFR start-up tests. The JEFF-3.3 results exhibit only an 8 pcm k_eff difference with the measurement. The difference in criticality is decomposed by nuclide, which shows the large overestimation of CENDL-3.2 is mainly from the cross-section of ⁵²Cr. Except for few cases, the calculation results are within 1σ of measurement uncertainty in control rod worth, sodium void reactivity, temperature reactivity, and subassembly swap reactivity. In the evaluation of axial and radial reaction distribution, there are about 65% of relative errors that are less than 5% and 82% of relative errors that are less than 10%.

• Genomics & Informatics
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• 제2권4호
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• pp.174-179
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• 2004

We developed various plasmid cloning vectors that are useful in the construction of genomic and shotgun libraries. Two medium copy vectors, pCUGlblu21 (pCb21) and pAGlblu21 (pAb21), which are resistant to kanamycin ($Km^R$) and chloramphenicol ($Cam^R$), respectively, are useful for cloning DNA inserts ranging from 5kb to 15kb. Two high copy vectors, pCUGlblu31 (pCb31) and pAGlblu31 (pAb31), containing $Km^R$ and $Cam^R$, respectively, are useful for DNA inserts less than 5kb. These vectors are well adapted for large-scale genome sequencing projects by providing choice of copy number and selectable marker. The small vector size is another advantage of these vectors. All vectors contain lacZa including multicloning sites that originated from pBluscriptllsk- for easy cloning and sequencing. Two medium copy vectors contain unique and rare cutting Swal (ATTTAAAT) restriction enzyme sites for easy determination of insert size. We developed two combined vectors, pC21A31 and pC31A21, which are combinations of (pCb21 + pAb31) and (pCb31 + pAb21), respectively. These two vectors provide four choices of vectors such as $Km^R$ and medium, $Cam^R$ and high, $Cam^R$ and medium, and $Km^R$ and high copy vectors by restriction enzyme cutting, dephosphorylation, and gel purification. These vectors were successfully applied to high throughput shotgun sequencing of rice, tomato, and brassica BAC clones. With an example of extremely biased hydro sheared 3 kb shotgun library of a tomato BAC clone, which is originated from cytogenetically defined peri-centromeric region, we suggest the utility of an additional 10 kb library for sequence assembly of the difficult-to-assemble BAC clone.

• Nuclear Engineering and Technology
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• 제52권1호
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• pp.14-18
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• 2020

Korea Atomic Energy Research Institute (KAERI) has carried out various neutronics experiments in the commissioning stage of the Jordan Research and Training Reactor (JRTR), and this paper introduces the results of first criticality prediction and experiment for the JRTR. The Monte Carlo Code for Advanced Reactor Design and analysis (McCARD) with the ENDF/B-VII.0 nuclear library was used for prediction calculations in the process of the first criticality approach, which was performed to provide reference for the first criticality experiment. In the experiment, fuel loading was carried out by measuring the inverse multiplication factor (1/M) to predict the number of fuel assemblies at the first criticality, and the first critical was reached on April 25, 2016. Comparing the first criticality prediction and experiment, the calculated and measured CAR (Control Absorber Rod) heights for the first criticality were 575 mm and 570.5 mm, respectively, that is, the difference between the two results was approximately 5 mm. From this result, it was confirmed that JRTR manufacturing and various experiments had successfully progressed as designed.