• Title/Summary/Keyword: Advanced Design Features

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THE DESIGN FEATURES OF THE ADVANCED POWER REACTOR 1400

  • Lee, Sang-Seob;Kim, Sung-Hwan;Suh, Kune-Yull
    • Nuclear Engineering and Technology
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    • v.41 no.8
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    • pp.995-1004
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    • 2009
  • The Advanced Power Reactor 1400 (APR1400) is an evolutionary advanced light water reactor (ALWR) based on the Optimized Power Reactor 1000 (OPR1000), which is in operation in Korea. The APR1400 incorporates a variety of engineering improvements and operational experience to enhance safety, economics, and reliability. The advanced design features and improvements of the APR1400 design include a pilot operated safety relief valve (POSRV), a four-train safety injection system with direct vessel injection (DVI), a fluidic device (FD) in the safety injection tank, an in-containment refueling water storage tank (IRWST), an external reactor vessel cooling system, and an integrated head assembly (IHA). Development of the APR1400 started in 1992 and continued for ten years. The APR1400 design received design certification from the Korean nuclear regulatory body in May of2002. Currently, two construction projects for the APR1400 are in progress in Korea.

FAULT-TOLERANT DESIGN FOR ADVANCED DIVERSE PROTECTION SYSTEM

  • Oh, Yang Gyun;Jeong, Kin Kwon;Lee, Chang Jae;Lee, Yoon Hee;Baek, Seung Min;Lee, Sang Jeong
    • Nuclear Engineering and Technology
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    • v.45 no.6
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    • pp.795-802
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    • 2013
  • For the improvement of APR1400 Diverse Protection System (DPS) design, the Advanced DPS (ADPS) has recently been developed to enhance the fault tolerance capability of the system. Major fault masking features of the ADPS compared with the APR1400 DPS are the changes to the channel configuration and reactor trip actuation equipment. To minimize the fault occurrences within the ADPS, and to mitigate the consequences of common-cause failures (CCF) within the safety I&C systems, several fault avoidance design features have been applied in the ADPS. The fault avoidance design features include the changes to the system software classification, communication methods, equipment platform, MMI equipment, etc. In addition, the fault detection, location, containment, and recovery processes have been incorporated in the ADPS design. Therefore, it is expected that the ADPS can provide an enhanced fault tolerance capability against the possible faults within the system and its input/output equipment, and the CCF of safety systems.

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.

Insights from the KNGR Preliminary Level 1 Probabilistic Safety Assessment

  • Na, Jang-Hwan;Oh, Hae-Cheol;Oh, Seung-Jong
    • Proceedings of the Korean Nuclear Society Conference
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    • 1998.05a
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    • pp.862-868
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    • 1998
  • Korean Next Generation Reactor(KNGR) is a standardized evolutionary Advanced Light Water Reactor design under development Korea Power Company(KEPCO). It incorporates design enhncements such as active and passive advanced design features(ADFs) to increase the plant safety. A Preliminary level 1 Probabilistic Safety Assessment(PSA) has been performed for KNGR to examine the effect of these safety features. The preliminary PSA result shows that it meets the KNGR safety goal on core damage frequency(CDF). The result of this safety assessment shows that the four-train safety systems, and the ADFs such as Passive Secondary Cooling System (PSCS) contributes greatly to the reduction the CDF. Furthermore, several design changes are made or proposed for detailed review based on the PSA insights.

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Steam Turbine Technology for Advanced Steam Condition (증기조건 향상에 따른 증기터빈 기술 동향)

  • Nah, U.H.;Cho, S.I.;Shin, H.;Kim, Y.S.;Yang, S.H.
    • Proceedings of the KSME Conference
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    • 2003.04a
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    • pp.2174-2179
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    • 2003
  • For many years, T/G Supplier has constructed a number of thermal power plants and researched to improve the performance and the reliability of steam turbine, which are achieved by advances in design and materials technology. In recent, interest is renewed in advanced steam condition as means of improving economy of thermal power plant and reducing environmental pollution. Improvements in the maximum power have been driven by the development of advanced rotor and bucket material and longer last stage bucket. Improvements in efficiency have been brought through advances in mechanical efficiency and thermodynamic efficiency. This paper describes a number of new steam path design features introduced to the steam turbine product. And also this paper describes new design technologies' development, new technologies' trend and technologies' development for ultra-super critical steam turbine.

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Design of comprehensive mechanical properties by machine learning and high-throughput optimization algorithm in RAFM steels

  • Wang, Chenchong;Shen, Chunguang;Huo, Xiaojie;Zhang, Chi;Xu, Wei
    • Nuclear Engineering and Technology
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    • v.52 no.5
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    • pp.1008-1012
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    • 2020
  • In order to make reasonable design for the improvement of comprehensive mechanical properties of RAFM steels, the design system with both machine learning and high-throughput optimization algorithm was established. As the basis of the design system, a dataset of RAFM steels was compiled from previous literatures. Then, feature engineering guided random forests regressors were trained by the dataset and NSGA II algorithm were used for the selection of the optimal solutions from the large-scale solution set with nine composition features and two treatment processing features. The selected optimal solutions by this design system showed prospective mechanical properties, which was also consistent with the physical metallurgy theory. This efficiency design mode could give the enlightenment for the design of other metal structural materials with the requirement of multi-properties.

A New Active Lossless Snubber for Half-Bridge Dual converter (하프 브릿지 듀얼 컨버터를 위한 새로운 능동형 무손실 스너버)

  • Han Sang-Kyoo;Kang Jeong-Il;Moon Gun-Woo;Youn Myung-Joong;Kim Youn-Ho
    • Proceedings of the KIPE Conference
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    • 2002.07a
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    • pp.480-484
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    • 2002
  • A new active lossless snubber for half-bridge dual converter(that is called 'dual converter') is proposed in this paper. It features soft switching(ZVS) as well as turn-off snubbing in both main and auxiliary switches. As it uses parasitic components, such as leakage inductances and switch output capacitances etc, it helps the dual converter to operate at the higher frequency with a higher efficiency and smaller size reactive components. The operational principle, theoretical analysis, and design consideration are presented. To confirm the operation, features and validity of the proposed circuit, simulated results from an 1kW, 24V/DC-250V/DC are presented.

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A Generating Cost Evaluation of APR+ Standard Design (APR+ 표준설계 발전원가 분석)

  • Ha, Gag-Hyeon;Kim, Sung-Hwan;Lee, Jae-Ho
    • Journal of Energy Engineering
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    • v.23 no.4
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    • pp.236-239
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    • 2014
  • KHNP CRI has been developing APR+ nuclear power plant since 2007, which is GEN III+ model with 1500 MWe capacity. To develop safer and more economical nuclear power plant than APR1400, we investigated advanced design features of ALWR(advanced light water reactor) being constructed in Korea and being developed/constructed in foreign countries. We applied the advanced design features and lessons learned from Fukushima accident to develop APR+ standard design suitable for both domestic construction and overseas construction business. Three economic assessments have performed during standard design phase of APR+. The result of the 3th(final) economic analysis for APR+ standard design showed that APR+ N-th plant was about 23% more economical than coal-fired 1,000MW power plant.

Relation Based Bayesian Network for NBNN

  • Sun, Mingyang;Lee, YoonSeok;Yoon, Sung-eui
    • Journal of Computing Science and Engineering
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    • v.9 no.4
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    • pp.204-213
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    • 2015
  • Under the conditional independence assumption among local features, the Naive Bayes Nearest Neighbor (NBNN) classifier has been recently proposed and performs classification without any training or quantization phases. While the original NBNN shows high classification accuracy without adopting an explicit training phase, the conditional independence among local features is against the compositionality of objects indicating that different, but related parts of an object appear together. As a result, the assumption of the conditional independence weakens the accuracy of classification techniques based on NBNN. In this work, we look into this issue, and propose a novel Bayesian network for an NBNN based classification to consider the conditional dependence among features. To achieve our goal, we extract a high-level feature and its corresponding, multiple low-level features for each image patch. We then represent them based on a simple, two-level layered Bayesian network, and design its classification function considering our Bayesian network. To achieve low memory requirement and fast query-time performance, we further optimize our representation and classification function, named relation-based Bayesian network, by considering and representing the relationship between a high-level feature and its low-level features into a compact relation vector, whose dimensionality is the same as the number of low-level features, e.g., four elements in our tests. We have demonstrated the benefits of our method over the original NBNN and its recent improvement, and local NBNN in two different benchmarks. Our method shows improved accuracy, up to 27% against the tested methods. This high accuracy is mainly due to consideration of the conditional dependences between high-level and its corresponding low-level features.