• Title/Summary/Keyword: Demonstration plant

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A new design concept for ocean nuclear power plants using tension leg platform

  • Lee, Chaemin;Kim, Jaemin;Cho, Seongpil
    • Structural Engineering and Mechanics
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    • v.76 no.3
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    • pp.367-378
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    • 2020
  • This paper presents a new design concept for ocean nuclear power plants (ONPPs) using a tension leg platform (TLP). The system-integrated modular advanced reactor, which is one of the successful small modular reactors, is mounted for demonstration. The authors define the design requirements and parameters, modularize and rearrange the nuclear and other facilities, and propose a new total general arrangement. The most fundamental level of design results for the platform and tendon system are provided, and the construction procedure and safety features are discussed. The integrated passive safety system developed for the gravity based structure-type ONPP is also available in the TLP-type ONPP with minor modifications. The safety system fully utilizes the benefits of the ocean environment, and enhances the safety features of the proposed concept. For the verification of the design concept, hydrodynamic analyses are performed using the commercial software ANSYS AQWA with the Pierson-Moskowitz and JONSWAP wave spectra that represent various ocean environments and the results are discussed.

LARGE SCALE FINITE ELEMENT THERMAL ANALYSIS OF THE BOLTS OF A FRENCH PWR CORE INTERNAL BAFFLE STRUCTURE

  • Rupp, Isabelle;Peniguel, Christophe;Tommy-Martin, Michel
    • Nuclear Engineering and Technology
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    • v.41 no.9
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    • pp.1171-1180
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    • 2009
  • The internal core baffle structure of a French Pressurized Water Reactor (PWR) consists of a collection of baffles and formers that are attached to the barrel. The connections are done thanks to a large number of bolts (about 1500). After inspection, some of the bolts have been found cracked. This has been attributed to the Irradiation Assisted Stress Corrosion Cracking (IASCC). The $Electricit\acute{e}$ De France (EDF) has set up a research program to gain better knowledge of the temperature distribution, which may affect the bolts and the whole structure. The temperature distribution in the structure was calculated thanks to the thermal code SYRTHES that used a finite element approach. The heat transfer between the by-pass flow inside the cavities of the core baffle and the structure was accounted for thanks to a strong thermal coupling between the thermal code SYRTHES and the CFD code named Code_Saturne. The results for the CP0 plant design show that both the high temperature and strong temperature gradients could potentially induce mechanical stresses. The CPY design, where each bolt is individually cooled, had led to a reduction of temperatures inside the structures. A new parallel version of SYRTHES, for calculations on very large meshes and based on MPI, has been developed. A demonstration test on the complete structure that has led to about 1.1 billion linear tetraedra has been calculated on 2048 processors of the EDF Blue Gene computer.

Overview of CRISPR/Cas9: a chronicle of the CRISPR system and application to ornamental crops

  • Lee, Hyunbae;Subburaj, Saminathan;Tu, Luhua;Lee, Ka-Yeon;Park, Gwangsu;Lee, Geung-Joo
    • Korean Journal of Agricultural Science
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    • v.47 no.4
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    • pp.903-920
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    • 2020
  • Since its first demonstration as a practical genome editing tool in the early 2010s, the use of clustered regularly interspaced short palindromic repeat (CRISPR) along with the endonuclease Cas9 (CRISPR/Cas9) has become an essential choice for generating targeted mutations. Due to its relative simplicity and cost-effectiveness compared to other molecular scissors, i.e., zinc finger nuclease (ZFN) and transcription activator-like effector nuclease (TALEN), the CRISPR/Cas9 system has been shown to have a massive influence on genetic studies regardless of the biological kingdom. Although the system is in the process of being established, numerous protocols have already been released for the system and there have been various topics of CRISPR related papers published each year in ever-increasing manner. Here, we will briefly introduce CRISPR/Cas9 system and discuss the variants of the CRISPR system. Also, their applications to crop improvement will be dealt with mainly ornamental crops among horticultural crops other than Arabidopsis as a model plant. Finally, some issues on the barriers restraining the use of CRISPR system on floricultural crops, the prospect of CRISPR system as a DNA-free genome editing tool with efficient facilitators and finally, the future perspectives on the CRISPR system will be described.

A novel aerodynamic vibration and fuzzy numerical analysis

  • Timothy Chen;Yahui Meng;Ruei-Yuan Wang;ZY Chen
    • Wind and Structures
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    • v.38 no.3
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    • pp.161-170
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    • 2024
  • In recent years, there have been an increasing number of experimental studies showing the need to include robustness criteria in the design process to develop complex active control designs for practical implementation. The paper investigates the crosswind aerodynamic parameters after the blocking phase of a two-dimensional square cross-section structure by measuring the response in wind tunnel tests under light wind flow conditions. To improve the accuracy of the results, the interpolation of the experimental curves in the time domain and the analytical responses were numerically optimized to finalize the results. Due to this combined effect, the three aerodynamic parameters decrease with increasing wind speed and asymptotically affect the upper branch constants. This means that the aerodynamic parameters along the density distribution are minimal. Taylor series are utilized to describe the fuzzy nonlinear plant and derive the stability analysis using polynomial function for analyzing the aerodynamic parameters and numerical simulations. Due to it will yield intricate terms to ensure stability criterion, therefore we aim to avoid kinds issues by proposing a polynomial homogeneous framework and utilizing Euler's functions for homogeneous systems. Finally, we solve the problem of stabilization under the consideration by SOS (sum of squares) and assign its fuzzy controller based on the feasibility of demonstration of a nonlinear system as an example.

Offshore CCS Plant Technology for 3Mt-CO2 Storage (연간 300만톤급 온실가스 감축을 위한 해양 CCS 플랜트 기술)

  • Huh, Cheol;Kang, Seong-Gil;Lee, Keum-Suk;Park, Young-Gyu
    • Transactions of the KSME C: Technology and Education
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    • v.1 no.1
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    • pp.123-128
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    • 2013
  • Carbon dioxide Capture and Storage (CCS) is one of the key players in greenhouse gas (GHG) reduction portfolio for mitigating climate change. CCS makes it possible not only to reduce a huge amount of carbon dioxide directly from coal power plant but also to maintain the carbon concentrated-energy infrastructure. The objective of the present paper is to review and introduce R&D progress and large scale demonstration plan focused on marine geological storage in Republic of Korea.

Study of fission gas products effect on thermal hydraulics of the WWER1000 with enhanced subchannel method

  • Bahonar, Majid;Aghaie, Mahdi
    • Advances in Energy Research
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    • v.5 no.2
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    • pp.91-105
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    • 2017
  • Thermal hydraulic (TH) analysis of nuclear power reactors is utmost important. In this way, the numerical codes that preparing TH data in reactor core are essential. In this paper, a subchannel analysis of a Russian pressurized water reactor (WWER1000) core with enhanced numerical code is carried out. For this, in fluid domain, the mass, axial and lateral momentum and energy conservation equations for desired control volume are solved, numerically. In the solid domain, the cylindrical heat transfer equation for calculation of radial temperature profile in fuel, gap and clad with finite difference and finite element solvers are considered. The dependence of material properties to fuel burnup with Calza-Bini fuel-gap model is implemented. This model is coupled with Isotope Generation and Depletion Code (ORIGEN2.1). The possibility of central hole consideration in fuel pellet is another advantage of this work. In addition, subchannel to subchannel and subchannel to rod connection data in hexagonal fuel assembly geometry could be prepared, automatically. For a demonstration of code capability, the steady state TH analysis of a the WWER1000 core is compromised with Thermal-hydraulic analysis code (COBRA-EN). By thermal hydraulic parameters averaging Fuel Assembly-to-Fuel Assembly method, the one sixth (symmetry) of the Boushehr Nuclear Power Plant (BNPP) core with regular subchannels are modeled. Comparison between the results of the work and COBRA-EN demonstrates some advantages of the presented code. Using the code the thermal modeling of the fuel rods with considering the fission gas generation would be possible. In addition, this code is compatible with neutronic codes for coupling. This method is faster and more accurate for symmetrical simulation of the core with acceptable results.

Quantification of Reactor Safety Margins for Large Break LOCA with Application of Realistic Evaluation Methodology (최적평가 방법론의 적용에 의한 대형냉각재 상실사고시의 원자로 안전여유도의 정량화)

  • B.D. Chung;Lee, Y.J.;T.S. Hwang;Lee, W.J.;Lee, S.Y.
    • Nuclear Engineering and Technology
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    • v.26 no.3
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    • pp.355-366
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    • 1994
  • The USNRC issued a revised ECCS rule that allows the use of best estimate computer codes for safety analysis. The rule also requires an estimation of uncertainty in calculated system response when applying the best estimate computer codes. A practical realistic evaluation methodology to evaluate the ECCS performance that satisfies the requirements of the ECCS rule has been developed and this paper describes the application of new realistic evaluation methodology to large break LOCA for, the demonstration of the new methodology. The computer code RELAP5/MOD3/KAERI, which was improved from RELAP5/MOD3.1, was used as the best estimate code in the application. The uncertainty of the code was evaluated by assessing several separate and integral effect tests, and for the application to actual plant Kori 3 & 4 was selected as the reference plant. Response surfaces for blowdown and reflood PCTs were generated from the results of the sensitivity analyses and probability distribution functions were established by random sampling or Monte-Carlo method for each response surface. Final uncertainties were quantified at 95% probability level and safety margins for large break LOCA were discussed.

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Application of Dynamic $\bar{x}$-R Control Chart for Advanced Phase Isolation Ditch (APID) Process (APID공정 내 공정진단을 위한 dynamic $\bar{x}$-R 관리도의 적용)

  • An, Sang-Woo;Kwak, Sung-Keun;Jung, Young-Wook;Chung, Mu-Keun;Park, Jae-Woo
    • Journal of Korean Society on Water Environment
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    • v.25 no.5
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    • pp.704-712
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    • 2009
  • Advanced Phase Isolation Ditch (APID) process was studied to develop economic retrofitting technology, for the plants where retrofitting of common activated sludge process is required. In this study, to evaluate and monitor the effluent water quality ($BOD_5$, SS, T-N, and T-P) and operating conditions (Influent, SVI, SRT, and HRT) as process capable and stable parameters for treating municipal wastewater, a demonstration plant was installed and operated in the existing sewage treatment plant of P city. During this study, the average effluent $BOD_5$, SS, T-N, and T-P concentrations were 7.7, 5.6, 10.8, and 1.6 mg/L. Trend analysis of influent $BOD_5$, SS, T-N, and T-P in APID process were illustrated that APID process need for more strong APID process management on the winter session, such as developing new intermediated aeration mode, operating methods, and managements strategy. At the application of control chart, the signal of uncommon effects at APID process was determined much higher existing control chart tntr conventional control chart in this study. These results indicate that conventional control chart has been collected and determined cleary signal at only stable situation. Therefore, newly developed APID process of dynamic control chart can be one of the useful tool for monitoring and management process.

Ozone-Activated Carbon Treatment in Middle Keum River containing Ammonia-Nitrogen (암모니아성질소를 함유한 금강중류 하천수의 오존-활성탄처리)

  • Kim, Chung-Hwan;Jung, Sang-Gi;Kim, Hag-Seong
    • Journal of Korean Society on Water Environment
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    • v.18 no.4
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    • pp.355-363
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    • 2002
  • A demonstration plant was carried out to investigate the removal efficiency of $NH_3-N$ and $KMnO_4$ consumption depending on the existence of pre-chlorination for the ozonation and activated carbon process in the S water treatment plant which is located at the middle of Keum River. The averge removal efficiency of $KMnO_4$ consumption for $O_3/GAC$ processes with pre-chlorination and $O_3/BAC$ processes without pre-chlorination were 48.6% and 50% respectively. It is similar to removal effect of $KMnO_4$ consumption for GAC and BAC process depending on the existence of pre-chlorination. Otherwise, the removal of THMFP for GAC and BAC process was 58% and 68% respectively. $NH_3-N$ was not almost removed by sand filter and ozonation, but the average removal efficiency in the BAC process was about 31%. Especially, $NH_3-N$ was not almost removed by $O_3/BAC$ processes at the low temperature (below $$10^{\circ}C$$) in the winter season, $O_3/BAC$ processes have the advantage of removal of organic substance when it is compared to pre -chlorination followed by $O_3/GAC$ processes. Pre-chlorination followed by $O_3/GAC$ processes were required to remove $NH_3-N$ in the winter season because the removal of $NH_3-N$ was almost ineffective by $O_3/BAC$ process.

Practical Demonstration of YPNR Process to Elimination the Total Nitrogen Ingredient in Sewage (하수 내 총질소 성분 제거를 위한 YPNR 공정의 실증 연구)

  • Lim, Eun-Tae;Jeong, Gwi-Taek;Bhang, Sung-Hun;Kim, Yong-Un;Park, Jae-Hee;Park, Seok-Hwan;Park, Don-Hee
    • KSBB Journal
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    • v.24 no.3
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    • pp.291-295
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    • 2009
  • This study performed verification experiment for the removal of total nitrogen in sewage from a Town M village sewage treatment plant using YPNR processes. The total nitrogen discharged after the denitrification process was maintained at a level of 8-15 mg/L, which results in the total nitrogen removal efficiency above 68% on average. The total nitrogen components in discharged water consisted of 16% of ammonia nitrogen, 6% of nitrite nitrogen, and 77% of nitrate nitrogen, which reaches a 95% nitrification efficiency. Hence, the YPNR advanced treatment process used in this study can be successfully applied to sewage treatment.