scholarly journals Computer Security for Commercial Nuclear Power Plants - Literature Review for Korea Hydro Nuclear Power Central Research Institute

2013 ◽  
Author(s):  
Felicia Angelica Duran ◽  
Russell L. Waymire
Keyword(s):  
Literature Review ◽  
Computer Security ◽  
Nuclear Power ◽  
Power Plants ◽  
Nuclear Power Plants ◽  
Central Research Institute ◽  
Central Research ◽  
Power Central ◽  
Research Institute

Seismic Test Results of Air-Operated Valve Actuators for Nuclear Power Plants (Air-Operated Butterfly Valve (Direct-Coupled Type))

2019 ◽  
Author(s):  
Yoshinao Matsubara ◽  
Yoshitaka Tsutsumi ◽  
Koji Nishino ◽  
Nobuo Kojima ◽  
Yasuyuki Ito ◽  
...  
Keyword(s):  
Nuclear Power ◽  
Power Plants ◽  
Nuclear Power Plants ◽  
Vertical Direction ◽  
Electric Power Industry ◽  
Central Research Institute ◽  
Shaking Table ◽  
Central Research ◽  
Functional Requirements ◽  
Seismic Tests

Abstract The functional requirements of air-operated valves provided in nuclear power plants during an earthquake have been previously evaluated via seismic tests and so forth; however, since the response acceleration has increased in line with a recent reassessment of standard earthquake ground motions, it is necessary to evaluate functional maintenance with respect to high acceleration. It is also necessary to determine practical functionality from the viewpoint of equipment fragility in seismic Probability Risk Assessment (PRA) Here, we used a resonant shaking table (see Ref. [1]) in the Central Research Institute of the Electric Power Industry (CRIEPI), which is capable of seismic tests at acceleration levels that have been unachievable until now. From the results of seismic tests on air-operated valve actuators, the operability of active components used with an existing design was confirmed to be more than 15 × 9.8 m/s2 (horizontal directions (X and Y)) and more than 20 × 9.8 m/s2 (vertical direction (Z)).

A Literature Review: Smart Grids Impacts on Nuclear Power Plants Task 4: Project Final Report

2016 ◽  
Author(s):  
Michael Villaran ◽  
◽  
Meng Yue ◽  
Robert Lofaro ◽  
Athi Varuttamaseni ◽  
...  
Keyword(s):  
Literature Review ◽  
Smart Grids ◽  
Nuclear Power ◽  
Power Plants ◽  
Nuclear Power Plants ◽  
Final Report

scholarly journals Spesifikasi, Kode dan Standar Baja Nasional dan Potensinya untuk Mendukung Program PLTN Tipe LWR di Indonesia

2019 ◽  
Vol 20 (2) ◽  
pp. 111 ◽  
Author(s):  
Dharu Dewi ◽  
Sriyana Sriyana
Keyword(s):  
Literature Review ◽  
Structural Steel ◽  
Research Methodology ◽  
Steel Industry ◽  
Nuclear Power ◽  
Power Plants ◽  
Nuclear Power Plants ◽  
International Standards ◽  
Code Standard ◽  
Standard Steel

SPESIFIKASI, KODE DAN STANDAR BAJA NASIONAL DAN POTENSINYA UNTUK MENDUKUNG PROGRAM PLTN TIPE LWR DI INDONESIA. Spesifikasi, kode dan standar baja nasional sangat penting diidentifkasi agar dapat dicocokkan atau dibandingkan  dengan spesifikasi, kode dan standar internasional untuk komponen PLTN sehingga industri baja diharapkan dapat berpartisipasi dalam pembangunan Pembangkit Listrik Tenaga Nuklir (PLTN). Spesifikasi kode dan standar  baja mengacu pada ASTM, ASME, AISC dan lain - lain. Tujuan studi ini adalah mengidentifikasi  spesifikasi, kode dan standar baja yang dimiliki industri nasional dan kemudian dicocokkan dengan spesifikasi, kode dan standar baja sesuai standar internasional untuk PLTN. Metodologi penelitian adalah kajian literatur, pengiriman kuesioner, survei dan kunjungan teknis ke industri baja. Disimpulkan bahwa baja struktur pada dasarnya memenuhi persyaratan untuk konstruksi PLTN.Kata kunci: spesifikasi, kode, standar, baja, industriSPECIFICATION, CODE AND STANDARD OF NATIONAL STEEL AND THE POTENCY TO SUPPORT THE NUCLEAR POWER PROGRAMME OF LWR TYPE IN INDONESIA. Specification, codes and standards are important to identify in order to be matched or compared to international specifications, codes and standards for NPP components so that the steel industry is expected to participate in the construction of Nuclear Power Plants (NPPs). The specifications, code and standards of steel refer to ASTM, ASME, AISC and others. The purpose of this study is to identify specifications, codes and steel standards owned by national industries and then compared it to international standards for nuclear power plants. The research methodology is literature review, questionnaire submission, surveys and technical visits to the steel industry. It was concluded that the structural steel basically meets the requirements for NPP construction.Keywords: specification, code, standard, steel, industry

scholarly journals Parameters influencing the low-cycle fatigue life of materials in pressure water reactor nuclear power plants / Parametry ovlivòující únavové chování materiálù pro tlakovodní jaderné reaktory v režimu nízkocyklové únavy

2015 ◽  
Vol 59 (3) ◽  
pp. 91-98
Author(s):  
V. Šefl
Keyword(s):  
Stainless Steel ◽  
Fatigue Life ◽  
Carbon Steel ◽  
Austenitic Stainless Steel ◽  
Literature Review ◽  
Nuclear Power ◽  
Power Plants ◽  
Nuclear Power Plants ◽  
Low Cycle Fatigue ◽  
Cycle Fatigue

Abstract In this literature review we identify and quantify the parameters influencing the low-cycle fatigue life of materials commonly used in nuclear power plants. The parameters are divided into several groups and individually described. The main groups are material properties, mode of cycling and environment parameters. The groups are further divided by the material type - some parameters influence only certain kind of material, e.g. sulfur content may decreases fatigue life of carbon steel, but is not relevant for austenitic stainless steel; austenitic stainless steel is more sensitive to concentration of dissolved oxygen in the environment compared to the carbon steel. The combination of parameters i.e. conjoint action of several detrimental parameters is discussed. It is also noted that for certain parameters to decrease fatigue life, it is necessary for other parameter to reach certain threshold value. Two different approaches have been suggested in literature to describe this complex problem - the Fen factor and development of new design fatigue curves. The threshold values and examples of commonly used relationships for calculation of fatigue lives are included. This work is valuable because it provides the reader with long-term literature review with focus on real effect of environmental parameters on fatigue life of nuclear power plant materials.

Seismic Test Results of the Main Steam Isolation Valve for Japanese Boiling Water Reactor Nuclear Power Plants

2020 ◽  
Author(s):  
Hideaki Itabashi ◽  
Yoshitaka Tsutsumi ◽  
Koji Nishino ◽  
Shin Kumagai
Keyword(s):  
Nuclear Power ◽  
Power Plants ◽  
Nuclear Power Plants ◽  
Shaking Table ◽  
Boiling Water ◽  
Boiling Water Reactor ◽  
Central Research ◽  
Water Reactor ◽  
Seismic Tests ◽  
Main Steam

Abstract The functional requirements of Main Steam Isolation Valves (MSIVs) provided in the Boiling Water Reactor (BWR) nuclear power plants in Japan have been previously evaluated via seismic tests and so forth. However, since the response acceleration has increased in line with a recent reassessment of standard earthquake ground motions, it is necessary to evaluate seismic operability with respect to high acceleration. In addition, from the viewpoint of equipment fragility in seismic PRA, it is necessary to determine practical seismic operability limits. We used a resonant shaking table in the Central Research Institute of the Electric Power Industry (CRIEPI), which is capable of seismic tests at acceleration levels previously unachievable, and in seismic tests carried out on an MSIV, we obtained results confirming that validated seismic operability was possible even at response accelerations as high as 15 × 9.8 m/s2. The seismic operability results obtained for this MSIV will be applied to a fragility analysis of seismic PRA.

Modularity in nuclear power plants: a review

2016 ◽  
Vol 14 (3) ◽  
pp. 526-542 ◽  
Author(s):  
Ashok Kumar Upadhyay ◽  
Karuna Jain
Keyword(s):  
Literature Review ◽  
Nuclear Power ◽  
Power Plants ◽  
Nuclear Power Plants ◽  
Medium Size ◽  
Construction Time ◽  
Content Type ◽  
Emerging Trends ◽  
Comprehensive Classification ◽  
Design And Construction

Purpose Modularity in design and construction of nuclear power plants (NPPs) is widely used for reduction in project construction time and cost. This paper aims to improve understanding of existence, rationale, relevance, types and definitions of modularity in NPPs. Design/methodology/approach The paper approaches study of modularity in NPPs through review of existing literature. The objective of this paper is to answer the questions such as “what is the meaning of module in the context of NPPs?”, “what is the meaning of modularity in the context of NPPs?”, “why modularity is considered in the design and construction of NPPs?”, “what are the types of modules and modularity?” and “what are the emerging trends?” Findings Findings of the paper indicate towards widespread use of modularity to reduce construction time and cost, improve safety performance and enable smarter applications of NPPs. Large NPPs tend to use modularity to shorten the project gestation period, and thereby reduce capital cost. Small and medium size NPPs plan to use modularity for simpler and safer reactors that can be factory manufactured, transported, installed and scaled up as permitted by the economic environment. Research limitations/implications This being a review, it has the usual limitations associated with the literature review papers. Practical implications Findings of the paper may influence policy regarding option, type, size, design, engineering, procurement and construction of NPPs. Social implications Findings of the paper may influence the safety, cost, time and quality performance of future NPPs and facilitate cheaper and more reliable supply of electricity to consumers. Originality/value The systematic literature review presents issues and emerging trends in modularity of NPPs, enabling the future work to progress as modularity continues to develop and evolve. The paper also proposes a comprehensive classification and definitions of modules and modularity in NPPs that may facilitate understanding of these terms precisely and uniformly by researchers and practitioners alike.

Seismic Test Result of Motor-Operated Valve Actuators for Nuclear Power Plant

2017 ◽  
Author(s):  
Nobuo Kojima ◽  
Yoshitaka Tsutumi ◽  
Kazuyoshi Yonekura ◽  
Koji Nishino ◽  
Yukio Watanabe ◽  
...  
Keyword(s):  
Nuclear Power ◽  
Power Plants ◽  
Electric Power Industry ◽  
Central Research Institute ◽  
Shaking Table ◽  
Central Research ◽  
Functional Requirements ◽  
Active Components ◽  
High Acceleration ◽  
Seismic Tests

Functional requirements of motor-operated valves provided in nuclear power plants during an earthquake have been previously evaluated via seismic tests and so forth; however, since the response acceleration has increased in line with a recent reassessment of standard earthquake ground motions, it is necessary to evaluate functional maintenance with respect to high acceleration. From the viewpoint of equipment fragility in seismic Probability Risk Assessment (PRA) also, it is necessary to determine practical functionality. Here, we used a resonant shaking table (see Ref. [1]) in the Central Research Institute of the Electric Power Industry (CRIEPI), which is capable of seismic tests at acceleration levels that have been unachievable until now, and in seismic tests carried out on motor-operated valve actuators, we obtained results confirming that operability of active components used with an existing design was achieved even at large accelerations exceeding 20×9.8 m/s2,. The results of seismic operability of motor-operated valve actuators will be applied to a fragility analysis of seismic PRA.

Seismic Test Results of the Main Steam Safety Relief Valve for Japanese Boiling Water Reactor Nuclear Power Plants

2017 ◽  
Author(s):  
Koji Nishino ◽  
Yoshitaka Tsutsumi ◽  
Kazuyoshi Yonekura ◽  
Nobuo Kojima ◽  
Yukio Watanabe ◽  
...  
Keyword(s):  
Nuclear Power ◽  
Power Plants ◽  
Nuclear Power Plants ◽  
Boiling Water ◽  
Boiling Water Reactor ◽  
Central Research ◽  
Relief Valve ◽  
Water Reactor ◽  
Seismic Tests ◽  
Main Steam

The functional requirements of Main Steam Safety Relief Valves (SRVs) provided in Boiling Water Reactor (BWR) nuclear power plants in Japan have been previously evaluated via seismic tests and so forth; however, since the response acceleration has increased in line with a recent reassessment of standard earthquake ground motions, it is necessary to evaluate seismic operability with respect to high acceleration. In addition, from the viewpoint of equipment fragility in seismic PRA also, it is necessary to determine the practical seismic operability limits. We used a resonant shaking table in the Central Research Institute of the Electric Power Industry (CRIEPI) [1], which is capable of seismic tests at acceleration levels that have been unachievable until now, and in seismic tests carried out on an SRV, we obtained results confirming that validated seismic operability was possible even at response accelerations as high as 20×9.8 m/s2. The seismic operability results obtained for this SRV will be applied to a fragility analysis of seismic PRA.

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