• Title/Summary/Keyword: nuclear power engineering

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A review on thermohydraulic and mechanical-physical properties of SiC, FeCrAl and Ti3SiC2 for ATF cladding

  • Qiu, Bowen;Wang, Jun;Deng, Yangbin;Wang, Mingjun;Wu, Yingwei;Qiu, S.Z.
    • Nuclear Engineering and Technology
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    • v.52 no.1
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    • pp.1-13
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    • 2020
  • At present, the Department of Energy (DOE) in Unite State are directing the efforts of developing accident tolerant fuel (ATF) technology. As the first barrier of nuclear fuel system, the material selection of fuel rod cladding for ATFs is a basic but very significant issue for the development of this concept. The advanced cladding is attractive for providing much stronger oxidation resistance and better in-pile behavior under sever accident conditions (such as SBO, LOCA) for giving more coping time and, of course, at least an equivalent performance under normal condition. In recent years, many researches on in-plie or out-pile physical properties of some suggested cladding materials have been conducted to solve this material selection problem. Base on published literatures, this paper introduced relevant research backgrounds, objectives, research institutions and their progresses on several main potential claddings include triplex SiC, FeCrAl and MAX phase material Ti3SiC2. The physical properties of these claddings for their application in ATF area are also reviewed in thermohydraulic and mechanical view for better understanding and simulating the behaviors of these new claddings. While most of important data are available from publications, there are still many relevant properties are lacking for the evaluations.

Deep-learning-based system-scale diagnosis of a nuclear power plant with multiple infrared cameras

  • Ik Jae Jin;Do Yeong Lim;In Cheol Bang
    • Nuclear Engineering and Technology
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    • v.55 no.2
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    • pp.493-505
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    • 2023
  • Comprehensive condition monitoring of large industry systems such as nuclear power plants (NPPs) is essential for safety and maintenance. In this study, we developed novel system-scale diagnostic technology based on deep-learning and IR thermography that can efficiently and cost-effectively classify system conditions using compact Raspberry Pi and IR sensors. This diagnostic technology can identify the presence of an abnormality or accident in whole system, and when an accident occurs, the type of accident and the location of the abnormality can be identified in real-time. For technology development, the experiment for the thermal image measurement and performance validation of major components at each accident condition of NPPs was conducted using a thermal-hydraulic integral effect test facility with compact infrared sensor modules. These thermal images were used for training of deep-learning model, convolutional neural networks (CNN), which is effective for image processing. As a result, a proposed novel diagnostic was developed that can perform diagnosis of components, whole system and accident classification using thermal images. The optimal model was derived based on the modern CNN model and performed prompt and accurate condition monitoring of component and whole system diagnosis, and accident classification. This diagnostic technology is expected to be applied to comprehensive condition monitoring of nuclear power plants for safety.

Artificial neural network reconstructs core power distribution

  • Li, Wenhuai;Ding, Peng;Xia, Wenqing;Chen, Shu;Yu, Fengwan;Duan, Chengjie;Cui, Dawei;Chen, Chen
    • Nuclear Engineering and Technology
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    • v.54 no.2
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    • pp.617-626
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    • 2022
  • To effectively monitor the variety of distributions of neutron flux, fuel power or temperatures in the reactor core, usually the ex-core and in-core neutron detectors are employed. The thermocouples for temperature measurement are installed in the coolant inlet or outlet of the respective fuel assemblies. It is necessary to reconstruct the measurement information of the whole reactor position. However, the reading of different types of detector in the core reflects different aspects of the 3D power distribution. The feasibility of reconstruction the core three-dimension power distribution by using different combinations of in-core, ex-core and thermocouples detectors is analyzed in this paper to synthesize the useful information of various detectors. A comparison of multilayer perceptron (MLP) network and radial basis function (RBF) network is performed. RBF results are more extreme precision but also more sensitivity to detector failure and uncertainty, compare to MLP networks. This is because that localized neural network could offer conservative regression in RBF. Adding random disturbance in training dataset is helpful to reduce the influence of detector failure and uncertainty. Some convolution neural networks seem to be helpful to get more accurate results by use more spatial layout information, though relative researches are still under way.

Phenomena Identification and Ranking Table for the APR-1400 Main Steam Line Break

  • Song, J.H.;Chung, B.D.;Jeong, J.J.;Baek, W.P.;Lee, S.Y.;Choi, C.J.;Lee, C.S.;Lee, S.J.;Um, K.S.;Kim, H.G.;Bang, Y.S.
    • Nuclear Engineering and Technology
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    • v.36 no.5
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    • pp.388-402
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    • 2004
  • A phenomena identification and ranking table(PIRT) was developed for a main steam line break (MSLB) event for the Advanced Power Reactor-1400 (APR-1400). The selectee event was a double-ended steam line break at full power, with the reactor coolant pump running. The developmental panel selected the fuel performance as the primary safety criterion during the ranking process. The plant design data, the results of the APR-1400 safety analysis, and the results of an additional best-estimate analysis by the MARS computer code were used in the development of the PIRT. The period of the transient was composed of three phases: pre-trip, rapid cool-down, and safety injection. Based on the relative importance to the primary evaluation criterion, the ranking of each system, component, and phenomenon/process was performed for each time phase. Finally, the knowledge-level for each important process for certain components was ranked in terms of existing knowledge. The PIRT can be used as a guide for planning cost-effective experimental programs and for code development efforts, especially for the quantification of those processes and/or phenomena that are highly important, but not well understood.

Elasticity of substitution of renewable energy for nuclear power: Evidence from the Korean electricity industry

  • Kim, Kwangil
    • Nuclear Engineering and Technology
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    • v.51 no.6
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    • pp.1689-1695
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    • 2019
  • This study suggests a simple economic model to analyze electricity grid that consists of different power sources. The substitutability of renewable energy for nuclear power in Korean electricity transmission network is investigated by suggested model. The monthly data from January 2006 to December 2013 reported by Electricity Power Statistics Information System (EPSIS) of Korea Power EXchange (KPX) are used. To estimate the elasticities of substitution among four power sources (i.e. coal, natural gas, nuclear power, and renewable energy), this paper uses the trans-log cost function model on which local concavity restrictions are imposed. The estimated Hicks-Allen and Morishima elasticity of substitution shows that renewable electricity and nuclear power are complementary. The results also evidenced that renewable electricity and fossil fueled thermal power generation are substitutes.

MSET PERFORMANCE OPTIMIZATION THROUGH REGULARIZATION

  • HINES J. WESLEY;USYNIN ALEXANDER
    • Nuclear Engineering and Technology
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    • v.37 no.2
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    • pp.177-184
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    • 2005
  • The Multivariate State Estimation Technique (MSET) is being used in Nuclear Power Plants for sensor and equipment condition monitoring. This paper presents the use of regularization methods for optimizing MSET's predictive performance. The techniques are applied to a simulated data set and a data set obtained from a nuclear power plant currently implementing empirical, on-line, equipment condition monitoring techniques. The results show that regularization greatly enhances the predictive performance. Additionally, the selection of prototype vectors is investigated and a local modeling method is presented that can be applied when computational speed is desired.

Corrosion release behavior of alloy 690 and its application in high-temperature water with Zn injection

  • Liao, Jiapeng;Hu, Yousen;Li, Jinggang;Jin, Desheng;Meng, Shuqi;Ruan, Tianming;Hu, Yisong;Zhang, Ziyu
    • Nuclear Engineering and Technology
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    • v.54 no.3
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    • pp.984-990
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    • 2022
  • Corrosion release behavior of Alloy 690 in high-temperature water was investigated under the conditions of injected Zn concentrations of 0 ppb, 10 ppb and 50 ppb. A protective oxide film composed of Zn(FexCr1-x)2O4 and Cr2O3 was formed with Zn injection, resulting in a better corrosion resistance. In comparison with the Zn-free condition, the corrosion release rate under the Zn-injection conditions was smaller. The corrosion release inhibiting factors were 1.7 and 1.9 under the conditions of 10 ppb and 50 ppb Zn-injection respectively. A foreseen application of the corrosion and corrosion release rates has been proposed and discussed.

Penetration of Korean EPC Companies into International Market for Nuclear Power Plant (플랜트 EPC 기업의 해외 원자력 발전 프로젝트 진출방안)

  • Cho, Chan-Hyoung;Moon, Seung-Jae;Yoo, Hoseon
    • Plant Journal
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    • v.5 no.3
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    • pp.66-73
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    • 2009
  • This study aims to develop a strategy for South Korean companies to penetrate into the global NPP(nuclear power plant) market with their strength as the sixth biggest nuclear power generator in the world. With 20 nuclear plants in commercial operation and 6 more in construction, South Korea has the best technology in construction and operation of NPP. Despite these capabilities as demonstrated on its domestic market, Korean companies' constraint to enter and play a key role in global NPP market would be the lack of experience in overseas NPP projects, original technologies, and diplomatic effectiveness. This study analyzes the competitiveness of Korean standardized nuclear power plant, construction management skills, construction technologies, manufacturing equipment and materials and operation skills. In this research the current status of existing NPP and the forecast of building NPP according to countries was analyzed in order to work out strategies with technology, cost-effectiveness, and diplomatic consideration.

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