• 제목/요약/키워드: 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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    • 제41권8호
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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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    • 제45권6호
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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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    • 제76권3호
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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
    • 한국원자력학회:학술대회논문집
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    • 한국원자력학회 1998년도 춘계학술발표회논문집(1)
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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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증기조건 향상에 따른 증기터빈 기술 동향 (Steam Turbine Technology for Advanced Steam Condition)

  • 나운학;조성일;신훈;김영상;양승헌
    • 대한기계학회:학술대회논문집
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    • 대한기계학회 2003년도 춘계학술대회
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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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    • 제52권5호
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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.

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

  • 한상규;강정일;문건우;윤명중;김윤호
    • 전력전자학회:학술대회논문집
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    • 전력전자학회 2002년도 전력전자학술대회 논문집
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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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APR+ 표준설계 발전원가 분석 (A Generating Cost Evaluation of APR+ Standard Design)

  • 하각현;김성환;이재호
    • 에너지공학
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    • 제23권4호
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    • pp.236-239
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    • 2014
  • 한수원 중앙연구원은 2007년부터 정부과제의 하나로 전기출력이 1500MWe급인 GEN.III+ 원전 APR+를 개발하고 있다. APR1400에 비해 보다 개선된 안전성과 경제성을 갖는 원전을 개발하기 위해 국내 건설 중인 원전과 해외에서 개발 또는 건설 중인 ALWR(Advanced Light Water Reactor)의 설계내용 및 후쿠시마 원전사고로부터 도출된 개선사항을 반영하여 한국 실정에도 맞고, 해외 수출형 원전에도 부합되는 원전을 설계하고 있다. APR+의 경쟁력을 확인하기 위해 APR+ 표준설계개발 단계에서 3회의 경제성 평가를 수행하였다. 표준설계개발 단계에의 3차(최종) 경제성 평가 결과 APR+ N-th호기는 국내석탄화력 1000MWe급 대비 약 23% 경쟁력 우위인 것으로 평가되었다.

Relation Based Bayesian Network for NBNN

  • Sun, Mingyang;Lee, YoonSeok;Yoon, Sung-eui
    • Journal of Computing Science and Engineering
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    • 제9권4호
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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.