• Title/Summary/Keyword: Energy Library

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Construction and Characterization of a cDNA Library from the Camelina sativa L. as an Alternative Oil-Seed Crop (신 바이오디젤 원료 작물인 Camelina의 cDNA library 제작 및 유전자 특성)

  • Park, Won;Jang, Young-Seok;Ahn, Sung-Ju
    • KOREAN JOURNAL OF CROP SCIENCE
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    • v.55 no.2
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    • pp.151-158
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    • 2010
  • Camelina sativa L., known as popular names "gold-of-pleasure" or "false flax" is an alternative oilseed crop that can be grown under different climatic and soil conditions. Up to date, however, the genomic information of Camelina has not been studied in detail. Therefore, a cDNA library was constructed and characterized from young leaves. The constructed cDNA library incorporated of 1334 cDNA clones and the size of the insertion fragments average was 736 base pair. We generated a total of 1269 high-quality expressed sequence tags (ESTs) sequences. The result of cluster analysis of EST sequences showed that the number of unigene was 851. According to subsequent analysis, the 476 (55.9%) unigenes were highly homologous to known function genes and the other 375 (44.1%) unigenes were unknown. Remaining 63 (7.4%) unigenes had no homology with any other peptide in NCBI database, indicating that these seemed to be novel genes expressed in leaves of Camelina. The database-matched ESTs were further classified into 17 categories according to their functional annotation. The most abundant of categories were "protein with binding function or cofactor requirement (27%)", "metabolism (11%)", "subcellular localization (11%)", "cellular transport, transport facilities and transport routes (7%)", "energy (6%)", "regulation of metabolism and protein function (6%)". Our result in this study provides an overview of mRNA expression profile and a basal genetic information of Camelina as an oilseed crop.

The TANDEM Euratom project: Context, objectives and workplan

  • C. Vaglio-Gaudard;M.T. Dominguez Bautista;M. Frignani;M. Futterer;A. Goicea;E. Hanus;T. Hollands;C. Lombardo;S. Lorenzi;J. Miss;G. Pavel;A. Pucciarelli;M. Ricotti;A. Ruby;C. Schneidesch;S. Sholomitsky;G. Simonini;V. Tulkki;K. Varri;L. Zezula;N. Wessberg
    • Nuclear Engineering and Technology
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    • v.56 no.3
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    • pp.993-1001
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    • 2024
  • The TANDEM project is a European initiative funded under the EURATOM program. The project started on September 2022 and has a duration of 36 months. TANDEM stands for Small Modular ReacTor for a European sAfe aNd Decarbonized Energy Mix. Small Modular Reactors (SMRs) can be hybridized with other energy sources, storage systems and energy conversion applications to provide electricity, heat and hydrogen. Hybrid energy systems have the potential to strongly contribute to the energy decarbonization targeting carbon-neutrality in Europe by 2050. However, the integration of nuclear reactors, particularly SMRs, in hybrid energy systems, is a new R&D topic to be investigated. In this context, the TANDEM project aims to develop assessments and tools to facilitate the safe and efficient integration of SMRs into low-carbon hybrid energy systems. An open-source "TANDEM" model library of hybrid system components will be developed in Modelica language which, by coupling, will extend the capabilities of existing tools implemented in the project. The project proposes to specifically address the safety issues of SMRs related to their integration into hybrid energy systems, involving specific interactions between SMRs and the rest of the hybrid systems; new initiating events may have to be considered in the safety approach. TANDEM will study two hybrid systems covering the main trends of the European energy policy and market evolution at 2035's horizon: a district heating network and power supply in a large urban area, and an energy hub serving energy conversion systems, including hydrogen production; the energy hub is inspired from a harbor-like infrastructure. TANDEM will provide assessments on SMR safety, hybrid system operationality and techno-economics. Societal considerations will also be encased by analyzing European citizen engagement in SMR technology safety.

The multigroup library processing method for coupled neutron and photon heating calculation of fast reactor

  • Teng Zhang;Xubo Ma;Kui Hu;GuanQun Jia
    • Nuclear Engineering and Technology
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    • v.56 no.4
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    • pp.1204-1212
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    • 2024
  • To accurately calculate the heating distribution of the fast reactor, a neutron-photon library in MATXS format named Knight-B7.1-1968n × 94γ was processed based on the ENDF/B-VII.1 library for ultrafine groups. The neutron cross-section processing code MGGC2.0 was used to generate few-group neutron cross sections in ISOTXS format. Additionally, the self-developed photon cross-section processing code NGAMMA was utilized to generate photon libraries for neutron-photon coupled heating calculations, including photo-atom cross sections for the ISOTXS format, prompt photon production cross sections, and kinetic energy release in materials (KERMA) factors for neutrons and photons, and the self-shielding effect from the capture and fission cross sections of neutron to photon have been taken into account when the photon source generated by neutron is calculated. The interface code GSORCAL was developed to generate the photon source distribution and interface with the DIF3D code to calculate the neutron-photon coupling heating distribution of the fast reactor core. The neutron-photon coupled heating calculation route was verified using the ZPPR-9 benchmark and the RBEC-M benchmark, and the results of the coupled heating calculations were analyzed in comparison with those obtained from the Monte Carlo code MCNP. The calculations show that the library was accurately processed, and the results of the fast reactor neutron-photon coupled heating calculations agree well with those obtained from MCNP.

Radiation Shield Analysis for Spent Fuel Shipping Cask (핵연료 수송용기의 방사선 차폐해석)

  • Cho, Kun-Woo;Kim, Hee-Won;Kwon, Seog-Kun;Kwak, Eun-Ho;Moon, Philip-S.
    • Journal of Radiation Protection and Research
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    • v.10 no.2
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    • pp.148-154
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    • 1985
  • Radiation shield design for a shipping cask, KSC-1, was evaluated to verify that the cask can be used in the transportation of a spent fuel assembly discharged from KNU 5 & 6. Radiation source term of the spent fuel assembly was calculated with the computer program ORIGEN-79, QAD-CG, ANISN-KA and DOT 3.5 codes Were used in the shielding calculations and the nuclear cross section data needed was extracted from the DLC-23/CASK library. It is concluded that KSC-1 shipping cask satisfies the requirements specified in the relevant regulations under normal conditions of transport and under accident conditions in transport.

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A Model for Radiological Dose Assessment in an Urban Environment (도시환경에서 방사성물질 오염에 따른 선량평가모델)

  • Hwang, Won-Tae;Kim, Eun-Han;Jeong, Hyo-Joon;Suh, Kyung-Suk;Han, Moon-Hee
    • Journal of Radiation Protection and Research
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    • v.32 no.1
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    • pp.1-8
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    • 2007
  • A model for radiological dose assessment in an urban environment, METRO-K has been developed. Characteristics of the model are as follows ; 1) mathematical structures are simple (i.e. simplified input parameters) and easy to understand due to get the results by analytical methods using experimental and empirical data, 2) complex urban environment can easily be made up using only 5 types of basic surfaces, 3) various remediation measures can be applied to different surfaces by evaluating the exposure doses contributing from each contamination surface. Exposure doses contributing from each contamination surface at a particular location of a receptor were evaluated using the data library of kerma values as a function of gamma energy and contamination surface. A kerma data library was prepared fur 7 representative types of Korean urban buildings by extending those data given for 4 representative types of European urban buildings. Initial input data are daily radionuclide concentration in air and precipitation, and fraction of chemical type. Final outputs are absorbed dose rate in air contributing from the basic surfaces as a function of time following a radionuclide deposition, and exposure dose rate contributing from various surfaces constituting the urban environment at a particular location of a receptor. As the result of a contaminative scenario for an apartment built-up area, exposure dose rates show a distinct difference for surrounding environment as well as locations of a receptor.

Pepper Blight Disease Inhibition Metagenome Clone Screening Using Soil Metagenome Library (토양 Metagenome Library로부터 고추역병 저해 클론 탐색)

  • Park, Hae-Chul;Sung, So-Ra;Kim, Dong-Gwan;Koo, Bon-Sung;Jeong, Byeong-Moon;Kim, Jin-Heung;Yoon, Moon-Young
    • Korean Journal of Microbiology
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    • v.45 no.2
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    • pp.228-231
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    • 2009
  • We have purified Phytophthora capsici alpha and beta tubulin from Escherchia coli BL21(DE3). The recombinant alpha and beta tubulins were assembled into microtubule in vitro with specific conditions. The metagenome library was isolated from soil in the Mt. Yeo-Ki, Suwon, Korea and manufactured with the method mentioned in experiment contents for in vitro screening of microtubule assembly screening. FRET effect was used for microtubule assembly inhibitor screening with metagenome library. We got 2 metagenome clones from in vitro screening, and these 2 hit clones showed P. capsici growth inhibition activity on the growing pepper plants. These results suggest that new development of potent inhibitor for pepper blight disease and new approach to prevention of pepper blight disease.

Long-term thermal performance of evacuated tubular solar collector for demonstration system (태양열 실증시스템의 진공관형 태양열 집열기 장기 열성능)

  • Lee, Ho;Joo, Hong-Jin;Yoon, Eung-Sang;Kim, Sang-Jin;Kwak, Hee-Youl
    • 한국태양에너지학회:학술대회논문집
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    • 2008.04a
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    • pp.104-110
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    • 2008
  • This paper presents demonstration study results derived through field testing of a part load solar energized cooling system for the library of a cultural center building located in Gwangju, Korea. First operating demonstration system was set up in Gwangju in 2005. These system comprises the $200m^2$ evacuated tubular solar collector, a $6m^3$ heat storage tank. In a 2006, daily average of insolation showed about $506W/m^2$, the solar collector efficiency was 44%. In a 2007, daily average of insolation showed about$507W/m^2$, the solar collector efficiency was 42%. As a result, evacuated tubular solar collector kept the high efficiency for two years.

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Updated Comparison Study of Extensive Air Shower Simulations with COSMOS and CORSIKA

  • Kim, Ji-Hee;Roh, Soon-Young;Ryu, Dong-Su
    • The Bulletin of The Korean Astronomical Society
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    • v.36 no.2
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    • pp.128.2-128.2
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    • 2011
  • Experiments to study high-energy cosmic rays (CRs) employ Monte Carlo codes for extensive air shower (EAS) simulations to figure out the properties of CRs. COSMOS and CORSIKA among EAS simulation codes are currently being used to analyze the data of the Telescope Array experiment. We have generated a library of about 10,000 simulated EASs with the primary energy ranging from $10^{18.5}eV$ to $10^{20}eV$ and the zenith angle of primary particles ranging from 0 to 45 degree for proton and iron primaries. We have compared the results predicted by CORSIKA and COSMOS under the same condition. In this talk, we show the differences in the energy spectra at the ground, the longitudinal shower profile as a function of atmospheric depth, the Calorimetric energy, and the Xmax distribution. We also discuss the lateral distribution function obtained from GEANT4 simulations which is being used to measure the detector response.

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An inter-comparison between ENDF/B-VIII.0-NECP-Atlas and ENDF/B-VIII.0-NJOY results for criticality safety benchmarks and benchmarks on the reactivity temperature coefficient

  • Kabach, Ouadie;Chetaine, Abdelouahed;Benchrif, Abdelfettah;Amsil, Hamid
    • Nuclear Engineering and Technology
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    • v.53 no.8
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    • pp.2445-2453
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    • 2021
  • Since the nuclear data forms a vital component in reactor physics computations, the nuclear community needs processing codes as tools for translating the Evaluated Nuclear Data Files (ENDF) to simulate nuclear-related problems such as an ACE format that is used for MCNP. Errors, inaccuracies or discrepancies in library processing may lead to a calculation that disagrees with the experimentally measured benchmark. This paper provides an overview of the processing and preparation of ENDF/B-VIII.0 incident neutron data with NECP-Atlas and NJOY codes for implementation in the MCNP code. The resulting libraries are statistically inter-compared and tested by conducting benchmark calculations, as the mutualcomparison is a source of strong feedback for further improvements in processing procedures. The database of the benchmark experiments is based on a selection taken from the International Handbook of Evaluated Criticality Safety Benchmark Experiments (ICSBEP handbook) and those proposed by Russell D. Mosteller. In general, there is quite good agreement between the NECP-Atlas1.2 and NJOY21(1.0.0.json) results with no substantial differences, if the correct input parameters are used.

An Operation Status Analysis of Library Building using BEMS Data; Energy Performance Evaluation on Initial Stage of Completion (BEMS 데이터를 활용한 도서관 건물의 운전현황 분석 -준공 초기단계의 건물 에너지 성능 평가)

  • Park, Seong-cheol;Ha, Ju-wan;Kim, Hwan-yong;Song, Young-hak
    • Journal of Korean Institute of Architectural Sustainable Environment and Building Systems
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    • v.12 no.6
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    • pp.669-679
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    • 2018
  • Energy consumption savings in buildings should be reviewed in diverse areas such as air conditioning system and lighting responsible for cooling and heating, and energy management systems such as BAS (Building Automation System) and BEMS (Building Energy Management System) are introduced to improve energy consumption efficiency and to promote economic control of related facilities by integrated management of energy generated and consumption in buildings. The measured building of this study uses regenerative geothermal system. Measured values of heat pump and system COP were 4.7 and 4.2 respectively, and they were found to be higher 11.9% and 23.5% than rated values. As a result of analyzing the air conditioning and lighting energy from the first floor to the fourth floor performing the air conditioning, the second and third floors, which have a high frequency of use, are compared with the first and fourth floors 50% higher energy consumption ratio. On the other hand, the general heat storage system uses the nighttime power of the previous day to store heat and use it the next day. The total number of days of abnormal operation during the summer season is 61 days. The electricity cost corresponding to the abnormal operation is 1,840,641 KRW, and the normal operation using the nighttime power is 1,363,561 KRW, which is difference of 477,080 KRW, 35% increase in cost. We will utilize it as the main data of BEMS through analysis of winter operation characteristics as well as summer operation characteristics.