• Title/Summary/Keyword: Energy plant

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A New LMR SG with a Double Tube Bundle Free from SWR

  • Sim Yoon-Sub;Kim Seong-O;Kim Eui Kwang;Hahn Do Hee
    • Nuclear Engineering and Technology
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    • v.35 no.6
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    • pp.566-580
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    • 2003
  • To resolve the concern of the SWR possibility in LMR and improve the economic feature of LMR, relative performance of various SG designs using a double tube bundle configuration is evaluated and a new SG design concept is proposed. The new steam generator design houses two tube bundles that are functionally different and its tube bundle region is radially divided into two. It prevents the occurrence of sodium water reaction while sodium is still used as the coolant for the primary heat transport system. The feasibility of the SG with a double tube bundle for actual use in an LMR plant is evaluated by setting up the skeleton of the NSSS for various possible configurations of the SG tube bundles. The evaluation revealed the relative advantages and disadvantages of the configurations and the new SG design concept performs good and can be actually used in an LMR plant.

DEVELOPMENT OF DESKTOP SEVERE ACCIDENT TRAINING SIMULATOR

  • Kim, Ko-Ryuh;Park, Soo-Yong;Song, Yong-Mann;Ahn, Kwang-Il
    • Nuclear Engineering and Technology
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    • v.42 no.2
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    • pp.151-162
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    • 2010
  • A severe accident training simulator that can simulate important severe accident phenomena and nuclear plant behaviors is developed. The simulator also provides several interactive control devices, which are helpful to assess results of a particular accident management behavior. A simple and direct dynamic linked library (DLL) data communication method is used for the development of the simulator. Using the DLL method, various control devices were implemented to provide an interactive control function during simulation. Finally, a training model is suggested for accident mitigation training and its performance is verified through application runs.

Hydrologic Performance Change of Small Scale Hydro Power Plant with Rainfall Condition Change (강우형태변화에 의한 소수력발전소 수문학적 성능의 변화)

  • Park, Wan-Soon;Lee, Chul-Hyung
    • Journal of the Korean Solar Energy Society
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    • v.29 no.6
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    • pp.56-61
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    • 2009
  • The effects of design parameters for small scale hydro power(SSHP) plants due to climate change have been studied. The model to predict hydrologic performance for SSHP plants is used in this study. The results from analysis far rainfall conditions based on KIER model show that the capacity and load factor of SSHP site had large difference between the period. Especially, the hydrologic performance of SSHP site due to rainfall condition of recent period varied in design flowrate sensitively. However climate change gave small effect in load factor of existing SSHP plant. And also, the methodology represented in this study can be used to decide the primary design specifications of SSHP sites.

Methodology of Feasibility Assessment for Small Hydropower Plant (소수력발전소의 건설 타당성분석 기법)

  • Park, W.S.;Lee, C.H.;Jeong, S.M.
    • Solar Energy
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    • v.18 no.3
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    • pp.153-160
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    • 1998
  • The methodology and feasibility analysis model for small hydropower plant has been studied and developed. It consists of two main part, the performance prediction model to estimate the performance characteristics and economics anaysis model to evaluate economical characteristics for surveyed sites. The performance characteristics and feasibility assessment for surveyed sites were analyzed, using developed models. Also, primary design specifications such as design flowrate, capacity, load factor were estimated and discussed for surveyed sites in Dan-yang and feasibility was suggested through analyzing the investment, unit cost and payback period.

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Performance Analyzing Technique of Small Hydro Power (소수력발전 성능특성 분석기법 연구)

  • Park, W.S.;Lee, C.H.
    • Journal of the Korean Solar Energy Society
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    • v.21 no.1
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    • pp.21-25
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    • 2001
  • A methodology to predict the output performance of small hydro power using discharge of sewage treatment plant has been studied. Two sewage treatment plants existing in Chunrabuk-Do were selected and the output performance characteristics for these plants were analyzed, using developed model. As a result, it was found that the developed model in this study can be used to analyze the output characteristics for small hydro power using discharge of sewage treatment plant. Additionally, primary design specifications such as design flowrate, capacity, operational rate and annual electricity production were estimated and discussed for two plants.

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Comparison between ISO 9000 Specification and Nuclear Quality Assurance Specification and Expected Application Effect (ISO 9000규격과 원자력품질보증 규격과의 비교 및 예상 적용 효과)

  • Lee, Tae-Hoon;Ha, Ji-Hoon
    • Journal of Korean Society of Industrial and Systems Engineering
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    • v.34 no.3
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    • pp.79-89
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    • 2011
  • Since commercial operation of Kori-1 nuclear power plant in 1978, twenty units are under operation and six units are under construction at 2011 present. Nuclear power become a main energy source in our country. However, the plant was constructed by a USA vendor in its beginning period, the Quality Assurance requirements of USA was applied. Even though Quality Assurance requirements were newly established to the Korea Atomic Energy Act, its contents are quite similar to those of USA. And 10 CFR 50 App.B, ASME NQA-1 apply to most of nuclear industries as a quality assurance plan. In this paper, Quality Assurance requirement of domestic nuclear industries has been investigated and applicable method of ISO Quality Assurance application to the nuclear industries is suggested by a comparison ISO 9000 and nuclear quality assurance specification.

Development of logical structure for multi-unit probabilistic safety assessment

  • Lim, Ho-Gon;Kim, Dong-San;Han, Sang Hoon;Yang, Joon Eon
    • Nuclear Engineering and Technology
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    • v.50 no.8
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    • pp.1210-1216
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    • 2018
  • Site or multi-unit (MU) risk assessment has been a major issue in the field of nuclear safety study since the Fukushima accident in 2011. There have been few methods or experiences for MU risk assessment because the Fukushima accident was the first real MU accident and before the accident, there was little expectation of the possibility that an MU accident will occur. In addition to the lack of experience of MU risk assessment, since an MU nuclear power plant site is usually very complex to analyze as a whole, it was considered that a systematic method such as probabilistic safety assessment (PSA) is difficult to apply to MU risk assessment. This paper proposes a new MU risk assessment methodology by using the conventional PSA methodology which is widely used in nuclear power plant risk assessment. The logical failure structure of a site with multiple units is suggested from the definition of site risk, and a decomposition method is applied to identify specific MU failure scenarios.

Preliminary Economic Analysis based on Optimization of Green Ammonia Plant Configuration in the Middle East for Import into Korea

  • Hyun-Chang Shin;Hak-Soo Mok;Woo-Hyun Son
    • Journal of the Korean Society of Industry Convergence
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    • v.27 no.2_1
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    • pp.277-285
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    • 2024
  • Hydrogen is considered a key energy source to achieve carbon neutrality through the global goal of 'net zero'. Due to limitations in producing green hydrogen domestically, Korean companies are interested in importing green hydrogen produced overseas. The Middle East has high-quality solar energy resources and is attracting attention as a region producing green hydrogen using renewable energy. To build a green ammonia plant, optimization of the production facility configuration and economic feasibility analysis are required. It is expected that it will contribute to reviewing the economic feasibility of constructing overseas hydrogen production plants through preliminary economic feasibility analysis.

MARS/MASTER Solution to OECD Main Steam Line Break Benchmark Exercise III

  • Jeong, Jae-Jun;Joo, Han-Gyu;Chung, Bub-Dong;Ha, Kwi-Seok;Lee, Won-Jae;Cho, Byung-Oh;Zee, Sung-Quun
    • Nuclear Engineering and Technology
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    • v.32 no.3
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    • pp.214-226
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    • 2000
  • In an effort to assess the performance of KAERI's coupled 3D kinetics - system T/H code, MARS/MASTER, Exercise III of the OECD main steam line break benchmark is solved. The analysis model of the reference plant, TMI-1 - a 2772 MWth B&W plant, consists of three major components: a core neutronics model involving 241$\times$28 neutronic nodes, a vessel 3D T/H model consisting of 374 hydrodynamic volumes, and a 1D system T/H model containing 157 hydrodynamic volumes. The results show that there is a significant amount of flow mixing occurring in the upper and lower plenum regions and the core power distribution evolves to a highly localized shape due to the presence of a stuck rod, as well as the asymmetric flow distribution. It is judged that MARS/MASTER properly captures these drastic 3-dimensional effects. Comparisons with other results submitted to OECD confirm the accuracy of the MARS/MASTER solution.

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