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Journal articles on the topic 'REACTOR PROTECTION SYSTEMS'

Author: Grafiati

Published: 4 June 2021

Last updated: 10 February 2022

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1

Fischer, H. D., and L. Piel. "Diversity in computerized reactor protection systems." Reliability Engineering & System Safety 63, no. 1 (1999): 91–97. http://dx.doi.org/10.1016/s0951-8320(98)00033-7.

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2

Pereguda, A. I., and A. A. Petrenko. "Ensuring required reliability for nuclear reactor protection systems." Soviet Atomic Energy 67, no. 6 (1989): 859–63. http://dx.doi.org/10.1007/bf01124957.

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3

Zhao, Bo Ya, Song Yang, Zhe Zhang, and Ri Sheng Sun. "Control Improvement of the Reactor Protection System." Applied Mechanics and Materials 71-78 (July 2011): 4199–202. http://dx.doi.org/10.4028/www.scientific.net/amm.71-78.4199.

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In this paper an optimal maintenance policy for a Reactor Protection System (RPS) for a nuclear plant was developed. RPS consists of continuously operating sub-systems that were subject to random failures. A block system diagram for RPS had been proposed that facilitates analyzing of individual sub-systems separately. The proposed maintenance policy is the Age Replacement model, which incorporated both corrective and preventive maintenances. A Markov model was used to optimize the preventive maintenance interval of those sub-systems whose failure and repair rates were exponentially distributed

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4

Suryono, Tulis Jojok, Sudarno Sudarno, and Sigit Santoso. "INFORMATION PROCESSING IN THE REACTOR PROTECTION SYSTEMS OF HIGH TEMPERATURE GAS-COOLED REACTORS." JURNAL TEKNOLOGI REAKTOR NUKLIR TRI DASA MEGA 22, no. 3 (2020): 81. http://dx.doi.org/10.17146/tdm.2020.22.3.5947.

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Reactor protection systems (RPS) transform process variable signals from the sensors into initiation and actuation signals to trip the reactor if the signal's value exceeds the predefined trip setpoints of the RPS. Information on the current value of the process variables signals and the trip setpoint should be displayed properly on the visual display unit (VDU) in order to maintain the situation awareness of the operators in main control rooms (MCR). In addition, it is also helpful for them to investigate the cause of an accident after the reactor trip and to mitigate the accident based on th

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5

Barrett, P. A., and A. Saeed. "On Requirements Analysis for Reactor Control and Protection Systems." IFAC Proceedings Volumes 28, no. 25 (1995): 77–82. http://dx.doi.org/10.1016/s1474-6670(17)44827-0.

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6

Jeong, Jiye, Kibeom Son, and Gyunyoung Heo. "Unavailability analysis of a digital hybrid platform for reactor protection systems." Annals of Nuclear Energy 160 (September 2021): 108351. http://dx.doi.org/10.1016/j.anucene.2021.108351.

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7

Kropik, Martin, and Monika Jurickova. "Software for protection system of VR-1 training reactor." Journal of Systems and Software 83, no. 9 (2010): 1605–11. http://dx.doi.org/10.1016/j.jss.2009.06.046.

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8

Kee In, Wang, Dae Hyun Hwang, Yeon Jong Yoo, and Sung Qunn Zee. "Assessment of core protection and monitoring systems for an advanced reactor SMART." Annals of Nuclear Energy 29, no. 5 (2002): 609–21. http://dx.doi.org/10.1016/s0306-4549(01)00058-5.

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9

Sun, Sida, Hong Li, and Sheng Fang. "The Optimization of Radiation Protection in the Design of the High Temperature Reactor-Pebble-Bed Module." Science and Technology of Nuclear Installations 2017 (2017): 1–15. http://dx.doi.org/10.1155/2017/3984603.

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The optimization of radiation protection is an important task in both the design and operation of a nuclear power plant. Although this topic has been considerably investigated for pressurized water reactors, there are very few public reports on it for pebble-bed reactors. This paper proposes a routine that jointly optimizes the system design and radiation protection of High Temperature Reactor-Pebble-Bed Module (HTR-PM) towards the As Low As Reasonably Achievable (ALARA) principle. A systematic framework is also established for the optimization of radiation protection for pebble-bed reactors.

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10

Gustin, Jean-Louis, Jean Fillion, Guy Tréand, and Kaddour El Biyaali. "The phenol + formaldehyde runaway reaction. Vent sizing for reactor protection." Journal of Loss Prevention in the Process Industries 6, no. 2 (1993): 103–13. http://dx.doi.org/10.1016/0950-4230(93)90007-k.

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11

Luo, Run, Shripad T. Revankar, and Fuyu Zhao. "Comparative Safety Analysis of Accelerator Driven Subcritical Systems and Critical Nuclear Energy Systems." Applied Sciences 11, no. 17 (2021): 8179. http://dx.doi.org/10.3390/app11178179.

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The accelerator driven subcritical system (ADS) has been chosen as one of the best candidates for Generation IV nuclear energy systems which could not only produce clean energy but also incinerate nuclear waste. The transient characteristics and operation principles of ADS are significantly different from those of the critical nuclear energy system (CNES). In this work, the safety characteristics of ADS are analyzed and compared with CNES by a developed neutronics and thermal-hydraulics coupled code named ARTAP. Three typical accidents are carried out in both ADS and CNES, including reactivity

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12

Aldemir, Tunc, Don W. Miller, Michael Stovsky, et al. "Methodologies for the Probabilistic Risk Assessment of Digital Reactor Protection and Control Systems." Nuclear Technology 159, no. 2 (2007): 167–91. http://dx.doi.org/10.13182/nt07-a3863.

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13

Jung, Sejin, Junbeom Yoo, and Young-Jun Lee. "A PLC platform-independent structural analysis on FBD programs for digital reactor protection systems." Annals of Nuclear Energy 103 (May 2017): 454–69. http://dx.doi.org/10.1016/j.anucene.2017.02.006.

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14

Bakhri, Syaiful, Joko Tri Susilo, Restu Maerani, Sudarno, and Doni Agus Ardiyanto. "Preliminary Development of the FPGA based Reactor Protection Systems for Reaktor Daya Eksperimental (RDE)." Journal of Physics: Conference Series 1772, no. 1 (2021): 012045. http://dx.doi.org/10.1088/1742-6596/1772/1/012045.

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15

Stryczewska, Henryka Danuta. "Supply Systems of Non-Thermal Plasma Reactors. Construction Review with Examples of Applications." Applied Sciences 10, no. 9 (2020): 3242. http://dx.doi.org/10.3390/app10093242.

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A review of the supply systems of non-thermal plasma reactors (NTPR) with dielectric barrier discharge (DBD), atmospheric pressure plasma jets (APPJ) and gliding arc discharge (GAD) was performed. This choice is due to the following reasons: these types of electrical discharges produce non-thermal plasma at atmospheric pressure, the reactor design is well developed and relatively simple, the potential area of application is large, especially in environmental protection processes and biotechnologies currently under development, theses reactors can be powered from similar sources using non-linea

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16

Cheng, S., Z. Li, H. P. Mang, X. Liu, and F. Yin. "Prefabricated biogas reactor-based systems for community wastewater and organic waste treatment in developing regions." Journal of Water, Sanitation and Hygiene for Development 4, no. 1 (2013): 153–58. http://dx.doi.org/10.2166/washdev.2013.135.

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Population densities in cities of developing countries are much higher than in other parts of the world, and the predominance of poverty in urban slums is ubiquitous throughout the region. In many urban areas, the lack of wastewater and waste management continues to be a huge challenge for environment and health protection. Decentralized approaches are proposed to provide practical, alternative options for sustainable urban wastewater and waste management in urban conditions. Conventionally, on-site constructed brick/concrete biogas reactors are the most used models. However, long construction

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17

Yao, Wan Ye, and Jin Bai. "Analysis of DAS and ATWS Mitigation System in Nuclear Power Plant." Applied Mechanics and Materials 397-400 (September 2013): 1383–86. http://dx.doi.org/10.4028/www.scientific.net/amm.397-400.1383.

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As the backup systems of RPS (reactor protection system), Diverse Actuation System and ATWS( Anticipated transients without scram) mitigation system are diversely designed from RPS system so as to offer protection for the normal operation of nuclear power plant. Both of the systems bear the function of mitigating the anticipated transients without scram events. Being isolated from RPS system, the design of DAS and ATWS system meeting the requirement of diversity and influences of CCFs (common cause failure) are effectively prevented. This article mainly analyzed the structure and function of t

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18

Jung, Sejin, Junbeom Yoo, and Young-Jun Lee. "A Software Fault Tree Analysis Technique for Formal Requirement Specifications of Nuclear Reactor Protection Systems." Reliability Engineering & System Safety 203 (November 2020): 107064. http://dx.doi.org/10.1016/j.ress.2020.107064.

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19

Ameyaw, F., R. Abrefah, S. Yamoah, and S. Birikorang. "Analysis and Estimation of Core Damage Frequency of Flow Blockage and Loss of Coolant Accident: A Case Study of a 10 MW Water-Water Research Reactor-PSA Level 1." Science and Technology of Nuclear Installations 2021 (June 26, 2021): 1–17. http://dx.doi.org/10.1155/2021/9423176.

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Fault trees (FT) and event trees (ET) are widely used in industry to model and evaluate the reliability of safety systems. This work seeks to analyze and estimate the core damage frequency (CDF) due to flow blockage (FB) and loss of coolant accident (LOCA) due to large rupture of primary circuit pipe with respect to a specific 10 MW Water-Water Research Reactor in Ghana using the FT and ET technique. Using FT, the following reactor safety systems: reactor protection system, primary heat removal system, isolation of the reactor pool, emergency core cooling system (ECCS), natural circulation hea

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20

Galiev, Ilnar I., Alexey N. Chernyaev, and Stanislav V. Bibik. "Development of seismic protection system for design extension conditions." Nuclear Energy and Technology 4, no. 1 (2018): 43–50. http://dx.doi.org/10.3897/nucet.4.29853.

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Development of seismic protection system for design extension conditions (SPSDEC) is suggested for enhancing safety of operation of NPP located on the territories with unfavorable seismic conditions. The idea of the system consists of the creation of a network of seismic stations arranged at a certain distance from the NPP and equipped with data transmission system. In case of detection by seismic sensors of movements of the ground with magnitude of vibrations exceeding a certain preset value, seismic stations transmit over radio-channel a signal indicating exceedance of the setting before the

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21

Mesquita, Amir Z., Adriano de A. M. Felippe, Aldo M. F. Lage, and Patrícia A. M. Ribeiro. "Visual interfaces for the digital simulation system of the IPR-R1 Triga nuclear research reactor." ACCENTS Transactions on Image Processing and Computer Vision 6, no. 21 (2020): 80–90. http://dx.doi.org/10.19101/tipcv.2020.618054.

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Nuclear Technology Development Center (CDTN) offers the Training Course for Research Reactor Operator (Ctorp). This course is offered since 1974 and about 250 nuclear professionals were certificated by CDTN. Thus, a digital simulation system for the IPR-R1 Triga research reactor was developed to be a tool for teaching, training and recycling professionals. The simulator was developed using the LabVIEW® (Laboratory Virtual Instruments Engineering Workbench), with support calculation software, where mathematical models and graphical interface configurations form a friendly platform, which allows

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22

Koo, BonSeung, DaeHyun Hwang, WangKee In, and JaeSeung Song. "Design features and thermal margin assessment of core protection and monitoring systems of an integral reactor, SMART." Journal of Nuclear Science and Technology 51, no. 3 (2013): 390–404. http://dx.doi.org/10.1080/00223131.2014.864456.

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23

Kang, Hyun Gook, and Hee Eun Kim. "Unavailability and spurious operation probability of k-out-of-n reactor protection systems in consideration of CCF." Annals of Nuclear Energy 49 (November 2012): 102–8. http://dx.doi.org/10.1016/j.anucene.2012.06.012.

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24

Tarantino, Mariano, Massimo Angiolini, Serena Bassini, et al. "Overview on Lead-Cooled Fast Reactor Design and Related Technologies Development in ENEA." Energies 14, no. 16 (2021): 5157. http://dx.doi.org/10.3390/en14165157.

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The next generation of nuclear energy systems, also known as Generation IV reactors, are being developed to meet the highest targets of safety and reliability, sustainability, economics, proliferation resistance, and physical protection, with improved performances compared with the currently licensed plants or those presently being built. Among the proposed technologies, lead-cooled fast reactors (LFRs) have been identified by nuclear industries in both Western and developing countries as being among the optimal Generation IV candidates. Since 2000, ENEA, the Italian National Agency for New Te

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25

Almeida, Maria Leonor Silva de, Larissa Marques Peres, and Guilherme Gomes dos Santos. "Air‐core dry‐type shunt reactor protection based on an alternative current alpha plane." IET Generation, Transmission & Distribution 15, no. 1 (2020): 34–44. http://dx.doi.org/10.1049/gtd2.12005.

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26

Kim, Jung-Wun, and Chan-Geun Park. "Fire Protection Regulations for Ensuring Fire Safety during Decommissioning Nuclear Power Plants in Korea." Fire Science and Engineering 34, no. 3 (2020): 134–40. http://dx.doi.org/10.7731/kifse.c3462cff.

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Nuclear power plants (NPPs) in Korea are required to be maintained using a defense in-depth approach to prevent leakage of radioactive substances outside the plant and allow safe shutdown in the event of a fire. Periodic testing must be conducted to ensure that the fire protection facilities perform as required by the laws for various nuclear reactor types. In June 2017, for the first time in Korea, a nuclear plant, Kori Unit 1, was permanently shut down. It was prepared for decommissioning in accordance with the fire protection regulations imposed by the regulatory body. However, a standard p

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27

Evtikhin, V. A., I. E. Lyublinski, A. V. Vertkov, V. G. Belan, I. K. Konkashbaev, and L. B. Nikandrov. "Calculation and experimental investigation of fusion reactor divertor plate and first wall protection by capillary-pore systems with lithium." Journal of Nuclear Materials 271-272 (May 1999): 396–400. http://dx.doi.org/10.1016/s0022-3115(98)00793-4.

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28

Guo, Chao, Huasheng Xiong, Xiaojin Huang, and Duo Li. "Design and Development Framework of Safety-Critical Software in HTR-PM." Science and Technology of Nuclear Installations 2017 (2017): 1–9. http://dx.doi.org/10.1155/2017/2981943.

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With the development of information technology, the instrumentation and control system of nuclear power plant nowadays rely heavily on the massive and complex software to ensure the safe and efficient operation of the power plant. The improvement of the software design and development for the safety systems has been a research focus for its decisive impact on the nuclear safety. The framework of the software design and development for reactor protection system in High Temperature Gas-Cooled Reactor-Pebble bed Module was introduced in this paper. Firstly, during the design period, in addition t

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29

Kumar, Mohit. "A Novel Weakest t-Norm based Fuzzy Importance Measure for Fuzzy Fault Tree Analysis of Combustion Engineering Reactor Protection System." International Journal of Uncertainty, Fuzziness and Knowledge-Based Systems 27, no. 06 (2019): 949–67. http://dx.doi.org/10.1142/s0218488519500429.

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Recently, a new fuzzy fault tree analysis (FFTA) has been developed to propagate and quantify the epistemic uncertainties occurring in qualitative data such as expert opinions or judgments. It is well known that the weakest triangular norm (Tw) based fuzzy arithmetic operations preserve the shape of the fuzzy numbers, provide more exact fuzzy results and effectively reduce uncertainty range. The objective of this paper is to develop a novel Tw-based fuzzy importance measure to identify the critical basic events in FFTA. The proposed approach has been demonstrated by applying it to a case study

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30

Lettinga, G. "Sustainable integrated biological wastewater treatment." Water Science and Technology 33, no. 3 (1996): 85–98. http://dx.doi.org/10.2166/wst.1996.0061.

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The actual and potential benefits of anaerobic wastewater treatment when implemented at the core of a sustainable and non-vulnerable environmental protection programme are described. The paper focuses on the anaerobic sludge bed (and in particular the expanded granular sludge bed (EGSB)) reactor concept. Start-up of these systems is shown to be rapid, within a few days with granular seed sludges, and they may be applied across a wide range of conditions and strengths of wastewater. EGSB systems are particularly suited to low temperatures (10°C) and very low strengths (&lt;&lt;1000mg/1)

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31

In, Wang-Kee, Young-Ho Park, Chang-Ho Kim, Seung-Yeob Baeg, and Tae-Young Yoon. "ICONE19-43115 ASSESSMENT OF ADVANCED REACTOR CORE PROTECTION SYSTEM FOR PRESSURIZED WATER REACTOR." Proceedings of the International Conference on Nuclear Engineering (ICONE) 2011.19 (2011): _ICONE1943. http://dx.doi.org/10.1299/jsmeicone.2011.19._icone1943_42.

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32

Cornu, B., C. Roure, D. Moulin, et al. "Non-Destructive Examination Development for the JHR Material Testing Reactor." EPJ Web of Conferences 225 (2020): 04001. http://dx.doi.org/10.1051/epjconf/202022504001.

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The Jules Horowitz Reactor (JHR) is a European material testing reactor (MTR) under construction at the CEA Cadarache centre. It will be dedicated to material and fuel irradiation tests, as well as to the production of medical isotopes. Gamma and X-Ray benches will be implemented in the reactor pool (RER), the irradiated component storage pool (EPI) and in a shielded hot cell for measuring either the whole underwater test device still containing the experimental sample or just the experimental sample before its extraction in the hot cell. The CEA/Cadarache Nuclear Measurement Laboratory (LMN)

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33

Le, Dai Dien. "Comparative analysis of reactor coolant pump coastdown transient using VVER-1200 NPP simulator." Nuclear Science and Technology 7, no. 1 (2021): 10–20. http://dx.doi.org/10.53747/jnst.v7i1.114.

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Verification has been performed to check the VVER-1200 NPP simulator installed atNuclear training Center, VINATOM by comparing main parameters in nominal power operation with design data given in safety analysis report of VVER-1200/V392M as well as Ninh Thuan FSSAR. A good agreement was found between the VVER-1200 NPP simulator and VVER-1200/V392M. In this study, the reactor coolant coastdown transient is investigated using the VVER-1200 NPP simulator in comparison with SAR documents. The real time feature of the simulator as well as simulated results performed in the simulator through switchi

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34

Torres, Patricia, Jenny A. Rodríguez, Luz E. Barba, Luis F. Marmolejo, and Carlos A. Pizarro. "Combined treatment of leachate from sanitary landfill and municipal wastewater by UASB reactors." Water Science and Technology 60, no. 2 (2009): 491–95. http://dx.doi.org/10.2166/wst.2009.365.

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Landfills are among the most affordable and acceptable methods in terms of public health and environmental protection for the final disposal of solid waste. Leachate treatment incorporated into anaerobic domestic wastewater systems could be a viable and efficient alternative which would allow minimizing implementation and operation costs of the landfill, to reduce requirements of chemical inputs such as pH conditioners and phosphorus supply. This study showed the potential of anaerobic treatment in an UASB reactor treating a combination of domestic wastewater and leachate in a 5% volumetric ra

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35

Salaun, Frederic, and David R. Novog. "Analysis of Control Rod Drop Accidents for the Canadian SCWR Using Coupled 3-Dimensional Neutron Kinetics and Thermal Hydraulics." Science and Technology of Nuclear Installations 2018 (2018): 1–17. http://dx.doi.org/10.1155/2018/1706590.

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The Canadian Supercritical Water-cooled Reactor (SCWR), a GEN IV reactor design, is a hybrid design of the well-established CANDU™ and Boiling Water Reactor with water above its thermodynamic critical point. Given the batch fueled design, control rods are used to manage the reactivity throughout the fuel cycle. This paper examines the consequences of a control rod drop accident (CRDA) for the Canadian SCWR. The asymmetry generated by the dropped rod requires an accurate 3-dimensional neutron kinetics calculation coupled to a detailed thermal-hydraulic model. Before simulating the CRDAs, the pr

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36

Sumita, Junya, Taiju Shibata, Tatsuo Iyoku, Masahiro Ishihara, and Tetsuo Nishihara. "Principle Design of Graphite Components for HTTR and R&D on Nuclear Graphite for HTGR in JAEA." Key Engineering Materials 697 (July 2016): 797–806. http://dx.doi.org/10.4028/www.scientific.net/kem.697.797.

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Nuclear energy is one of the most promising energy sources to satisfy energy security, environmental protection, and efficient supply. The High Temperature Gas-cooled Reactor (HTGR) has attractive inherent safety features and it can be used as many kinds of heat applications such as hydrogen production, electricity generation, process heat supply, district heating and desalination. Many countries, especially developing countries, show their interests in HTGR. Graphite materials are used for the core components of the HTGR. IG-110 graphite, fine-grained isotropic graphite, with high strength an

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37

Kropik, Martin, Jan Rataj, and Michal Sunka. "ICONE23-2160 VALIDATION OF NEW PROTECTION SYSTEM FOR LVR-15 RESEARCH REACTOR." Proceedings of the International Conference on Nuclear Engineering (ICONE) 2015.23 (2015): _ICONE23–2—_ICONE23–2. http://dx.doi.org/10.1299/jsmeicone.2015.23._icone23-2_62.

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38

Kratzsch, Alexander, Frank Drager, Thomas Gebhardt, Daniel Fiss, and Christian Vogel. "ICONE23-2182 ADVANCED ANALYSIS OF THE STRUCTURE OF A REACTOR PROTECTION SYSTEM." Proceedings of the International Conference on Nuclear Engineering (ICONE) 2015.23 (2015): _ICONE23–2—_ICONE23–2. http://dx.doi.org/10.1299/jsmeicone.2015.23._icone23-2_71.

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39

Mikheev, Dmitry V., Yelena N. Ryzhkova, Alex V. Udaratin, and Regina Salikhova. "Experimental study of the operating modes of the resonant current-limiting device." E3S Web of Conferences 220 (2020): 01049. http://dx.doi.org/10.1051/e3sconf/202022001049.

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Decreasing of short-circuit currents in power supply systems enables the usage of less expensive switching-protective devices with a lower breaking capacity and reduction of damage from the consequences of emergency events. In electrical networks of low, medium and high voltage classes, resonant current-limiting devices are used to solve this problem, along with other technical solutions. However, these devices have unsatisfactory weight and dimensions, high cost and other disadvantages. The technical and economic indicators of such devices can be improved through the use of a coil-capacitor (

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40

Fujita, T. "Earthquake isolation technology for industrial facilities." Bulletin of the New Zealand Society for Earthquake Engineering 18, no. 3 (1985): 224–49. http://dx.doi.org/10.5459/bnzsee.18.3.224-249.

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In Japan earthquake isolation technology has become increasingly necessary with the growing dominance of so-called "high technology" industries and is now being used to provide effective aseismic protection for precision equipment which is of major importance in such countries. The present applications are for computer systems and semiconductor manufacturing equipment. For computers, particularly those of banks, earthquake isolation of the floors is widely used. For semiconductor manufacturing equipment, earthquake isolation has begun to be used for the components; the isolation of the floors

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41

Fox, Shane, Michael Cahill, Edmond O'Reilly, and Eoghan Clifford. "Decentralized wastewater treatment using ‘Pumped Flow Biofilm Reactor’ (PFBR) technology." Water Practice and Technology 11, no. 1 (2016): 93–103. http://dx.doi.org/10.2166/wpt.2016.011.

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Clean water resources are imperative for sustainable development. Thus, protection and management of waters receiving wastewater discharges have received significant attention from policy and regulatory bodies. The quality of wastewater effluent must meet regional (e.g. Water Framework Directive), national and local discharge standards. In addition, there is now significant pressure on engineers and operators to reduce energy consumption, sludge production and operation/maintenance issues, particularly at small-scale and decentralized wastewater facilities. Therefore, significant interest has

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42

Miller, Don W., Joseph W. Talnagi, Steven A. Arndt, Gregory S. Rowe, and Alireza Behbahani. "The application of radiation detection noise as an in situ method of surveillance and performance verification of nuclear instrumentation channels for reactor protection systems." Progress in Nuclear Energy 15 (January 1985): 165–73. http://dx.doi.org/10.1016/0149-1970(85)90036-8.

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43

El-Gohary, F. A., S. I. Abou-Elela, and H. I. Aly. "Evaluation of biological technologies for wastewater treatment in the pharmaceutical industry." Water Science and Technology 32, no. 11 (1995): 13–20. http://dx.doi.org/10.2166/wst.1995.0389.

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Wastewater from a pharmaceutical and chemical company provides the material of this study. The company produces drugs, diuretics, laboratory chemicals and others. The company is located 30 km north of Cairo, and discharges both industrial (1050 m3/d) and human wastewater (8400 m3/d) without treatment into a near-by evaporation pond. Reduction of pollutants in the wastewater down to permissible concentrations is necessary for the protection of ground water and the environment. Analysis of the combined wastes indicated that it is very acidic and contains high concentrations of organic compounds

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44

Kirillov, Pavel L., and Galina P. Bogoslovskaya. "Generation IV supercritical water-cooled nuclear reactors: Realistic prospects and research program." Nuclear Energy and Technology 5, no. 1 (2019): 67–74. http://dx.doi.org/10.3897/nucet.5.34293.

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Existing conditions make possible obtaining information that being discussed openly by wide scientific community could help outlining or even establishing the expediency of a particular area of present and future research. Use link http://www.sciencedirect.com to learn about the topics or areas that most attract researchers from different countries. The Generation IV International Forum (GIF-IV) established in January 2000 has set a goal to improve the new generation of nuclear technologies in the following areas: stability, safety and reliability, economic competitiveness, proliferation resis

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45

PURBA, JULWAN HENDRY, JIE LU, GUANGQUAN ZHANG, and DA RUAN. "AN AREA DEFUZZIFICATION TECHNIQUE TO ASSESS NUCLEAR EVENT RELIABILITY DATA FROM FAILURE POSSIBILITIES." International Journal of Computational Intelligence and Applications 11, no. 04 (2012): 1250022. http://dx.doi.org/10.1142/s1469026812500228.

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Reliability data is essential for a nuclear power plant probabilistic safety assessment by fault tree analysis to assess the performance of the safety-related systems. The limitation of conventional reliability data arises from insufficient historical data for probabilistic calculation. This study describes a new approach to calculate nuclear event reliability data by utilizing the concept of failure possibilities, which are expressed in qualitative natural languages, mathematically represented by membership functions of fuzzy numbers, and subjectively justified by a group of experts based on

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46

Gallucci, Raymond HV. "Risk-Reduction Credit for Very Early Warning Fire Detection at Nuclear Power Plants: From FAQ to Fiction." Civil Engineering Journal 5, no. 2 (2019): 309. http://dx.doi.org/10.28991/cej-2019-03091246.

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In 2004, the U.S. Nuclear Regulatory Commission (NRC), with support from the commercial nuclear power industry, adopted the 2001 Edition of National Fire Protection Association (NFPA) Standard 805, “Performance-Based Standard for Fire Protection for Light Water Reactor Electric Generating Plants,” as the means by which commercial nuclear power licensees could comply with Title 10 of the Code of Federal Regulations, Part 50.48(c), to replace deterministic fire protection licensing bases with ones that are risk-informed and performance-based. To facilitate licensee “transitions” to the new licen

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Bajpai, Mukul, Surjit Singh Katoch, and Naveen Kumar Chaturvedi. "Comparative study on decentralized treatment technologies for sewage and graywater reuse – a review." Water Science and Technology 80, no. 11 (2019): 2091–106. http://dx.doi.org/10.2166/wst.2020.039.

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Abstract Currently, reservoirs, lakes, rivers etc. are being overloaded by the demand for fresh water, due to rapid industrialization and population explosion, and also the effluents from industries and domestic wastewater are continuously polluting these resources. To address this issue, several decentralized wastewater treatment system (DWTS) have been installed all over the globe to reuse and recycle wastewater/graywater for non-potable uses such as fire protection, toilet-flushing, and landscape irrigation. In this review, a comparison between different DWTS was carried out to evaluate the

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Liu, Zhaohui, Zhiqiang Wu, and Xiaohua Yang. "ICONE23-1427 APPLICATION OF STPA TO THE DIGITAL REACTOR PROTECTION SYSTEM IN NPP FOR SYSTEM SAFETY ANALYSIS." Proceedings of the International Conference on Nuclear Engineering (ICONE) 2015.23 (2015): _ICONE23–1—_ICONE23–1. http://dx.doi.org/10.1299/jsmeicone.2015.23._icone23-1_199.

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Flemming, Hans-Curt, Thomas Griebe, and Gabriela Schaule. "Antifouling strategies in technical systems – a short review." Water Science and Technology 34, no. 5-6 (1996): 517–24. http://dx.doi.org/10.2166/wst.1996.0591.

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The undesired deposition of microorganisms and the formation of biofilms is called “biofouling”. The consequences of biofouling for water purification, transport and storage are considerable both economically and ecologically. Countermeasures against biofouling include three steps: i) detection, ii) sanitization and iii) prevention of biofouling. The detection has to refer to surfaces. Cell counts in water water samples do not reflect the location or the extent of biofilms. Biocides display only limited value in terms of removal of biofouling layers. First, biofilm organisms are protected agai

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Khalil Ur, Rahman, Jinsoo Shin, Muhammad Zubair, Gyunyoung Heo, and Hanseong Son. "Sensitivity Study on Availability of I&C Components Using Bayesian Network." Science and Technology of Nuclear Installations 2013 (2013): 1–10. http://dx.doi.org/10.1155/2013/656548.

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The objective of this study is to find out the impact of instrumentation and control (I&C) components on the availability of I&C systems in terms of sensitivity analysis using Bayesian network. The analysis has been performed on I&C architecture of reactor protection system. The analysis results would be applied to develop I&C architecture which will meet the desire reliability features and save cost. RPS architecture unavailabilityP(x=0)and availabilityP(x=1)were estimated to6.1276E-05and9.9994E-01for failure (0) and perfect (1) states, respectively. The impact of I&C comp

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