Relevant bibliographies by topics / REACTOR PROTECTION SYSTEMS

Contents

  1. Journal articles
  2. Dissertations / Theses
  3. Books
  4. Book chapters
  5. Conference papers
  6. Reports

Academic literature on the topic 'REACTOR PROTECTION SYSTEMS'

Author: Grafiati
Published: 4 June 2021
Last updated: 10 February 2022

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Journal articles on the topic "REACTOR PROTECTION SYSTEMS"

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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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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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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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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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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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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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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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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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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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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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Dissertations / Theses on the topic "REACTOR PROTECTION SYSTEMS"

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LOPES, PAULO R. de L. "Estudo da metodologia de analise de series temporais aplicada a monitoracao do tempo de resposta dos instrumentos ligados ao sistema de protecao de reatores nucleares." reponame:Repositório Institucional do IPEN, 1995. http://repositorio.ipen.br:8080/xmlui/handle/123456789/10459.

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CONCEICAO, JUNIOR OSMAR. "Aplicacao da tecnica de analise de modos de falha e efeitos ao sistema de resfriamento de emergencia de uma instalacao nuclear experimental." reponame:Repositório Institucional do IPEN, 2009. http://repositorio.ipen.br:8080/xmlui/handle/123456789/9367.

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BENKO, PEDRO L. "Estudo de arquitetura de hardware para aplicacao em sistemas digitais de protecao de reatores nucleares. Metodos de analise de confiabilidade e seguranca." reponame:Repositório Institucional do IPEN, 1997. http://repositorio.ipen.br:8080/xmlui/handle/123456789/10678.

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Made available in DSpace on 2014-10-09T12:42:57Z (GMT). No. of bitstreams: 0<br>Made available in DSpace on 2014-10-09T14:08:02Z (GMT). No. of bitstreams: 1 05358.pdf: 6193324 bytes, checksum: c9b68865b6cec7bb9c83ee65a4e97865 (MD5)<br>Dissertacao (Mestrado)<br>IPEN/D<br>Instituto de Pesquisas Energeticas e Nucleares - IPEN/CNEN-SP
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VAZ, ANTONIO C. A. "Implementação e avaliação do sistema de proteção física do reator IEA-R1." reponame:Repositório Institucional do IPEN, 2016. http://repositorio.ipen.br:8080/xmlui/handle/123456789/26621.

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Submitted by Marco Antonio Oliveira da Silva (maosilva@ipen.br) on 2016-08-26T13:58:31Z No. of bitstreams: 0<br>Made available in DSpace on 2016-08-26T13:58:31Z (GMT). No. of bitstreams: 0<br>Os ataques terroristas ocorridos nos Estados Unidos em setembro de 2001, o acidente ocorrido na central nuclear de Fukushima em março de 2011 e os recentes ataques em Paris em novembro de 2015 são exemplos de eventos que corroboram a necessidade da Agência Internacional de Energia Atômica em melhorar a segurança nas instalações nucleares. O governo brasileiro vem contribuindo com este projeto e investind
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MELLO, JOSÉ ROBERTO de. "Regulamentação do sistema elétrico do reator IEA-R1." reponame:Repositório Institucional do IPEN, 2016. http://repositorio.ipen.br:8080/xmlui/handle/123456789/26928.

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Submitted by Marco Antonio Oliveira da Silva (maosilva@ipen.br) on 2016-12-21T12:55:48Z No. of bitstreams: 0<br>Made available in DSpace on 2016-12-21T12:55:48Z (GMT). No. of bitstreams: 0<br>O reator IEA-R1 do Instituto de Pesquisas Energéticas e Nucleares (IPENCNEN/ SP) é um reator de pesquisa tipo piscina aberta, projetado e construído pela empresa norte-americana \"Babcock & Wilcox\", tendo, como refrigerante e moderador, água leve deionizada e berílio e grafite como refletores. Até cerca de 1988, os sistemas de segurança do reator recebiam alimentação de uma única fonte de energia. Nos a
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RIBEIRO, MARIA A. M. "Estudo sobre sistemas de alivio da contencao aplicados a reatores de pequeno porte." reponame:Repositório Institucional do IPEN, 2001. http://repositorio.ipen.br:8080/xmlui/handle/123456789/10959.

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SOUZA, ROSE M. G. do P. "Determinação do fator de pico de potência utilizando barras de controle, detectores ex-core e redes neurais." reponame:Repositório Institucional do IPEN, 2005. http://repositorio.ipen.br:8080/xmlui/handle/123456789/11296.

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DeWitte, Jacob D. (Jacob Dominic). "Reactor protection system design alternatives for sodium fast reactors." Thesis, Massachusetts Institute of Technology, 2011. http://hdl.handle.net/1721.1/76523.

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Thesis (S.M.)--Massachusetts Institute of Technology, Dept. of Nuclear Science and Engineering, 2011.<br>"January 2011." Cataloged from PDF version of thesis.<br>Includes bibliographical references (p. 110-112).<br>Historically, unprotected transients have been viewed as design basis events that can significantly challenge sodium-cooled fast reactors. The perceived potential consequences of a severe unprotected transient in a sodium-cooled fast reactor include an energetic core disruptive accident, vessel failure, and a large early release. These consequences can be avoided if unprotected tran
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Verma, Vasudha. "Development of a Neutron Flux Monitoring System for Sodium-cooled Fast Reactors." Doctoral thesis, Uppsala universitet, Tillämpad kärnfysik, 2017. http://urn.kb.se/resolve?urn=urn:nbn:se:uu:diva-319945.

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Safety and reliability are one of the key objectives for future Generation IV nuclear energy systems. The neutron flux monitoring system forms an integral part of the safety design of a nuclear reactor and must be able to detect any irregularities during all states of reactor operation. The work in this thesis mainly concerns the detection of in-core perturbations arising from unwanted movements of control rods with in-vessel neutron detectors in a sodium-cooled fast reactor. Feasibility study of self-powered neutron detectors (SPNDs) with platinum emitters as in-core power profile monitors fo
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Wang, Yung Hsu, and 王永旭. "Risk-Based Evalution of Test Frequency for the Reactor Protection System." Thesis, 1995. http://ndltd.ncl.edu.tw/handle/82599808277964687018.

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Books on the topic "REACTOR PROTECTION SYSTEMS"

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Lawrence, Jim. Software reliability and safety in nuclear reactor protection systems. Division of Reactor Controls and Human Factors, Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission, 1993.

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Lawrence, J. D. Software reliability and safety in nuclear reactor protection systems. Division of Reactor Controls and Human Factors, Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission, 1993.

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Chu, Tsong-Lun. Development of quantitative software reliability models for digital protection systems of nuclear power plants. United States Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, 2013.

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Foley, W. J. Closeout of IE bulletin 80-19: Failures of mercury-wetted matrix relays in reactor protective systems of operating nuclear power plants designed by Combustion Engineering. Division of Operational Events Assessment, Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission, 1988.

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D, Schrader, Yamamoto R, U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Engineering Technology., and Lawrence Livermore National Laboratory, eds. Review templates for computer-based reactor protection systems. U.S. Nuclear Regulatory Commission, 2000.

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U.S. Nuclear Regulatory Commission. Division of Reactor Controls and Human Factors. and Lawrence Livermore National Laboratory, eds. Method for performing diversity and defense-in-depth analyses of reactor protection systems. Division of Reactor Controls and Human Factors, Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission, 1994.

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Aging assessment of reactor instrumentation and protection system components: Aging-related operating experiences. Division of Engineering, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1992.

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Functional issues and environmental qualification of digital protection systems of advanced light-water nuclear reactors. Division of Engineering, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1994.

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Kessler, Günter. Sustainable and Safe Nuclear Fission Energy: Technology and Safety of Fast and Thermal Nuclear Reactors (Power Systems). Springer, 2012.

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J, Lambright, U.S. Nuclear Regulatory Commission. Division of Safety Issue Resolution., and Sandia National Laboratories, eds. Risk evaluation for a B&W pressurized water reactor, effects of fire protection system actuation on safety-related equipment: Evaluation of generic issue 57. Division of Safety Issue Resolution, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1992.

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Book chapters on the topic "REACTOR PROTECTION SYSTEMS"

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Fischer, H. D. "Special Features of a Computer-Based German Reactor Protection System." In Fault-Tolerant Computing Systems. Springer Berlin Heidelberg, 1991. http://dx.doi.org/10.1007/978-3-642-76930-6_23.

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Prince, Robert. "Radiological Aspects of PWR Systems." In Radiation Protection at Light Water Reactors. Springer Berlin Heidelberg, 2012. http://dx.doi.org/10.1007/978-3-642-28388-8_2.

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Prince, Robert. "Radiological Aspects of BWR Systems." In Radiation Protection at Light Water Reactors. Springer Berlin Heidelberg, 2012. http://dx.doi.org/10.1007/978-3-642-28388-8_3.

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Nzeba, K. A., J. J. Justo, Aishwarya Biju, and Ramesh Bansal. "Protection of Reactors and FACTS Devices." In Power System Protection in Smart Grid Environment. CRC Press, 2019. http://dx.doi.org/10.1201/9780429401756-9.

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Varga, István, Tamás Bartha, Géza Szabó, and Bálint Kiss. "Status and Actual Risk Monitoring in a NPP Reactor Protection System." In Probabilistic Safety Assessment and Management. Springer London, 2004. http://dx.doi.org/10.1007/978-0-85729-410-4_425.

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Christmansson, Jörgen, Zbigniew Kalbarczyk, and Jan Torin. "An Attempt to Evaluate Functional Diversity Employed in a Reactor Protection System." In Safe Comp 95. Springer London, 1995. http://dx.doi.org/10.1007/978-1-4471-3054-3_23.

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Li, Le, Zhi-Hui Zhang, Jian-Xin Ma, and Chao Gao. "Research on a Low-Latency Communication Module for the Reactor Protection System." In Lecture Notes in Electrical Engineering. Springer Singapore, 2021. http://dx.doi.org/10.1007/978-981-16-3456-7_75.

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Bartha, Tamás, István Varga, Alexandros Soumelidis, and Géza Szabé. "Implementation of a Testing and Diagnostic Concept for an NPP Reactor Protection System." In Dependable Computing - EDCC 5. Springer Berlin Heidelberg, 2005. http://dx.doi.org/10.1007/11408901_29.

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Jee, Eunkyoung, Suin Kim, Sungdeok Cha, and Insup Lee. "Automated Test Coverage Measurement for Reactor Protection System Software Implemented in Function Block Diagram." In Lecture Notes in Computer Science. Springer Berlin Heidelberg, 2010. http://dx.doi.org/10.1007/978-3-642-15651-9_17.

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Kim, Young-Jin, and Peter L. Andresen. "Protective Insulated Coating for SCC Mitigation in BWRs." In 15th International Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors. John Wiley & Sons, Inc., 2012. http://dx.doi.org/10.1002/9781118456835.ch218.

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Conference papers on the topic "REACTOR PROTECTION SYSTEMS"

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Dobrzynski, Krzysztof, Zbigniew Lubosny, Jacek Klucznik, and Stanislaw Czapp. "Neutral earthing reactor protection." In 2017 IEEE International Conference on Environment and Electrical Engineering and 2017 IEEE Industrial and Commercial Power Systems Europe (EEEIC / I&CPS Europe). IEEE, 2017. http://dx.doi.org/10.1109/eeeic.2017.7977448.

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Kuranov, Alexander, and Alexey Korabelnikov. "Hydrocarbon Fuel Conversion in the Thermal Protection Reactor." In 16th AIAA/DLR/DGLR International Space Planes and Hypersonic Systems and Technologies Conference. American Institute of Aeronautics and Astronautics, 2009. http://dx.doi.org/10.2514/6.2009-7376.

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Marais, Johan, and Charles F. Ridolfo. "Challenges and Opportunities in Providing a Digital Protection System for the PBMR." In Fourth International Topical Meeting on High Temperature Reactor Technology. ASMEDC, 2008. http://dx.doi.org/10.1115/htr2008-58173.

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The Republic of South Africa is currently developing the Pebble Bed Modular Reactor (PBMR); an advanced, fourth-generation reactor that incorporates inherent safety features, which require no human intervention and which provide an unprecedented level of nuclear safety. In addition to electrical power generation, the reactor is uniquely suited for a variety of non-traditional nuclear applications including oil sands extraction, desalination, and hydrogen production. A state-of-the-art digital Protection System for the PBMR is currently being developed in conjunction with Westinghouse Electric
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Bakhmach, Ievgenii S., Alexander A. Siora, Volodymyr T. Bezsalyi, and Mikhail A. Yastrebenetsky. "Digital Systems for Reactor Control: Design, Experience of Operation." In 16th International Conference on Nuclear Engineering. ASMEDC, 2008. http://dx.doi.org/10.1115/icone16-48205.

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Conversion of traditional analog NPP I&amp;C systems to digital systems is a common tendency for many countries. Digital systems for reactor control designed by «Radiy» Company (Kirovograd, Ukraine) are described below. FPGA (Field Programmable Gates Arrays) were used for implementation of control algorithms. An equivalence between FPGA-projects implementation and schemes of control technological algorithms permitted to simplify development and verification processes and decrease the number of development errors. The platform was used for implementation of different safety important systems: r
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Lee, Dong-Ah, Junbeom Yoo, and Jang-Soo Lee. "Guidelines for the Use of Function Block Diagram in Reactor Protection Systems." In 2014 21st Asia-Pacific Software Engineering Conference (APSEC). IEEE, 2014. http://dx.doi.org/10.1109/apsec.2014.29.

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Kumar, Manoj, Ashutosh Kabra, G. Karmakar, and P. P. Marathe. "A review of defences against common cause failures in reactor protection systems." In 2015 4th International Conference on Reliability, Infocom Technologies and Optimization (ICRITO) (Trends and Future Directions). IEEE, 2015. http://dx.doi.org/10.1109/icrito.2015.7359232.

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JEZIERSKA, Angelika, Cezary DZIENIS, Yilmaz YELGIN, and Kai STRUNZ. "Improving Handling of Shunt-Reactor Effects during Fault with Focus on Protection Devices." In 2019 Modern Electric Power Systems (MEPS). IEEE, 2019. http://dx.doi.org/10.1109/meps46793.2019.9395005.

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Li, Duo, Zhaojun Hao, Shuqiao Zhou, and Chao Guo. "Application of Monte Carlo Methods in Reactor Protection System Reliability Research." In 2018 26th International Conference on Nuclear Engineering. American Society of Mechanical Engineers, 2018. http://dx.doi.org/10.1115/icone26-81300.

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Digital Reactor Protection System (RPS) is one of the most important systems in instrumentation and control systems of Nuclear Power Plants (NPP). The reliability analysis of RPS plays an important role both in theory and engineering application. Traditional reliability methods, such as fault tree analysis and Markov chain theory, have many limitations in the research of RPS reliability, since the number of system states increases exponentially with the growth of system complexity. Aiming at the reliability analysis of complex system like RPS, the Monte Carlo method simulates the system behavi
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Asadi, Qasem, Mohammad Qasemi, Amir Amini, and Sayed Ali Ghoreishi Feriz. "Minimizing Overvoltages on Medium Voltage VCBs Due to Shunt Reactor Switching." In 2020 15th International Conference on Protection and Automation of Power Systems (IPAPS). IEEE, 2020. http://dx.doi.org/10.1109/ipaps52181.2020.9375585.

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He, Zhiyong, Wenjuan Cui, Qiang Zhao, Yichuan He, and Yuxi Luo. "Design of Control Systems for Accelerator Driven Sub-Critical System." In 2016 24th International Conference on Nuclear Engineering. American Society of Mechanical Engineers, 2016. http://dx.doi.org/10.1115/icone24-60075.

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An accelerator driven sub-critical (ADS) system consists of an accelerator, a sub-critical reactor, and a spallation target located at the centre of the reactor core. In this paper, we report the conceptual design of the control system for ADS system, which will integrate two big nuclear facilities, an accelerator and a reactor, into an overall system for the first time in the world. Because varied expectations on redundancy, diversity, availability, reliability, communication speed and latency are required for both accelerator and reactor, at least six systems have been designed for an ADS sy
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Reports on the topic "REACTOR PROTECTION SYSTEMS"

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Meyer, L. C. Nuclear plant-aging research on reactor protection systems. Office of Scientific and Technical Information (OSTI), 1988. http://dx.doi.org/10.2172/5122402.

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Lawrence, J. D. Software reliability and safety in nuclear reactor protection systems. Office of Scientific and Technical Information (OSTI), 1993. http://dx.doi.org/10.2172/10108329.

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Josephson, Gary B., Russell G. Tonkyn, J. G. Frye, Brian J. Riley, and Kenneth G. Rappe. Hybrid Plasma Reactor/Filter for Transportable Collective Protection Systems. Office of Scientific and Technical Information (OSTI), 2011. http://dx.doi.org/10.2172/1015276.

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Josephson, G. B., R. G. Tonkyn, J. G. Frye, B. J. Riley, and K. G. Rappe. Hybrid Plasma Reactor/Filter for Transportable Collective Protection Systems. Defense Technical Information Center, 2011. http://dx.doi.org/10.21236/ada545917.

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Josephson, Gary B., Russell G. Tonkyn, Kenneth G. Rappe, and John G. Frye. Annual Report for Hybrid Plasma Reactor/Filter for Transportable Collective Protection Systems?Phase 1B. Office of Scientific and Technical Information (OSTI), 2009. http://dx.doi.org/10.2172/982963.

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Evans, Alan. Impact of Extreme Weather Events on Physical Protection System Effectiveness for a Hypothetical Small Modular Reactor Facility: Systems Analysis and Considerations. Office of Scientific and Technical Information (OSTI), 2021. http://dx.doi.org/10.2172/1817296.

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Gehl, A. C., and E. W. Hagen. Aging assessment of reactor instrumentation and protection system components. Aging-related operating experiences. Office of Scientific and Technical Information (OSTI), 1992. http://dx.doi.org/10.2172/10167631.

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Ornstein, H. L. Operating experience feedback report -- turbine-generator overspeed protection systems: Commercial power reactors. Volume 11. Office of Scientific and Technical Information (OSTI), 1995. http://dx.doi.org/10.2172/71337.

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9

Korsah, K., R. L. Clark, and R. T. Wood. Functional issues and environmental qualification of digital protection systems of advanced light-water nuclear reactors. Office of Scientific and Technical Information (OSTI), 1994. http://dx.doi.org/10.2172/10150860.

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10

Akinleye, Taiwo, Idil Deniz Akin, Amanda Hohner, et al. Evaluation of Electrochemical Treatment for Removal of Arsenic and Manganese from Field Soil. Illinois Center for Transportation, 2021. http://dx.doi.org/10.36501/0197-9191/21-019.

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Abstract:
Soils containing inorganic compounds are frequently encountered by transportation agencies during construction within the right-of-way, and they pose a threat to human health and the environment. As a result, construction activities may experience project delays and increased costs associated with management of inorganic compounds containing soils required to meet environmental regulations. Recalcitrance of metal-contaminated soils toward conventional treatment technologies is exacerbated in clay or organic content-rich fine-grained soils with low permeability and high sorption capacity becaus
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