WorldWideScience

Sample records for plant protection system

  1. FPGA-Based Plant Protection System

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Yoon Hee; Ha, Jae Hong; Kim, Hang Bae [KEPCO E and C, Daejeon (Korea, Republic of)

    2011-08-15

    This paper relates to a plant protection system which detects non-permissible conditions and determines initiation of protective actions for nuclear power plants (NPPs). Conventional plant protection systems were designed based on analog technologies. It is well known that existing protection systems for NPPs contain many components which are becoming obsolete at an increasing rate. Nowadays maintenance and repair for analog-based plant protection systems may be difficult as analog parts become obsolete or difficult to obtain. Accordingly, as an alternative to the analog technology, the digitalisation of the plant protection system was required. Recently digital plant protection systems which include programmable logic controllers (PLCs) and/or computers have been introduced. However PLC or computer-based plant protection systems use an operating system and application software, and so they may result in a common mode failure when a problem occurs in the operating system or application software. Field Programmable Gate Arrays (FPGAs) are highlighted as an alternative to conventional protection or control systems. The paper presents the design of a four-channel plant protection system whose protection functions are implemented in FPGAs without any central processing unit or operating system.

  2. FPGA-Based Plant Protection System

    International Nuclear Information System (INIS)

    Lee, Yoon Hee; Ha, Jae Hong; Kim, Hang Bae

    2011-01-01

    This paper relates to a plant protection system which detects non-permissible conditions and determines initiation of protective actions for nuclear power plants (NPPs). Conventional plant protection systems were designed based on analog technologies. It is well known that existing protection systems for NPPs contain many components which are becoming obsolete at an increasing rate. Nowadays maintenance and repair for analog-based plant protection systems may be difficult as analog parts become obsolete or difficult to obtain. Accordingly, as an alternative to the analog technology, the digitalisation of the plant protection system was required. Recently digital plant protection systems which include programmable logic controllers (PLCs) and/or computers have been introduced. However PLC or computer-based plant protection systems use an operating system and application software, and so they may result in a common mode failure when a problem occurs in the operating system or application software. Field Programmable Gate Arrays (FPGAs) are highlighted as an alternative to conventional protection or control systems. The paper presents the design of a four-channel plant protection system whose protection functions are implemented in FPGAs without any central processing unit or operating system

  3. Digital protection in power plants. Electrical unit and line protection. Digital protection systems for NPP

    International Nuclear Information System (INIS)

    Kaczmarek, A.

    2000-01-01

    In this presentation author deals with the digital protection systems for nuclear power plants. The evolution of protection devices, protection concept for power plants, concept of functional redundancy, references for digital protection, benefits for the customer well as concept fault recorder are presented. (author)

  4. Programmed system for nuclear power plant protection

    International Nuclear Information System (INIS)

    Jover, Pierre.

    1980-06-01

    The progress in the field of microprocessors and large scale integration circuits, have incited to introduce this new technologies into nuclear power plant protection system. The hardware and software design principles are briefly listed; then, a quad-redundant protection system for 1300 MWe PWR, developed in France is described [fr

  5. Localization of equipment for digital plant protection system

    Energy Technology Data Exchange (ETDEWEB)

    Koo, I. S.; Park, H. Y.; Lee, C. K. and others

    2000-10-01

    The objective of this project lies on the development of design requirements, establishment of structure and manufacture procedures, development of the software verification and validation(V and V) techniques of the digital plant protection system. The functional requirements based on the analog protection system and digital design requirements are introduced, the processor and system bus for safety grade equipment are selected and the interface requirements and the design specification have been developed in order to manufacture the quick prototype of the digital plant protection system. The selection guidelines of parts, software development and coding and testing for digital plant protection system have been performed through manufacturing the quick prototype based on the developed design specification. For the software verification and validation, the software review plan and techniques of verification and validation have been researched. The digital validation system is developed in order to verify the quick prototype. The digital design requirements are reviewed by the software safety plan and V and V plans. The formal methods for verifying the safety-grade software are researched, then the methodology of formal analysis and testing have been developed.

  6. Localization of equipment for digital plant protection system

    International Nuclear Information System (INIS)

    Koo, I. S.; Park, H. Y.; Lee, C. K. and others

    2000-10-01

    The objective of this project lies on the development of design requirements, establishment of structure and manufacture procedures, development of the software verification and validation(V and V) techniques of the digital plant protection system. The functional requirements based on the analog protection system and digital design requirements are introduced, the processor and system bus for safety grade equipment are selected and the interface requirements and the design specification have been developed in order to manufacture the quick prototype of the digital plant protection system. The selection guidelines of parts, software development and coding and testing for digital plant protection system have been performed through manufacturing the quick prototype based on the developed design specification. For the software verification and validation, the software review plan and techniques of verification and validation have been researched. The digital validation system is developed in order to verify the quick prototype. The digital design requirements are reviewed by the software safety plan and V and V plans. The formal methods for verifying the safety-grade software are researched, then the methodology of formal analysis and testing have been developed

  7. High-temperature gas-cooled reactor steam-cycle/cogeneration lead plant. Plant Protection and Instrumentation System design description

    International Nuclear Information System (INIS)

    1983-01-01

    The Plant Protection and Instrumentation System provides plant safety system sense and command features, actuation of plant safety system execute features, preventive features which maintain safety system integrity, and safety-related instrumentation which monitors the plant and its safety systems. The primary function of the Plant Protection and Instrumentation system is to sense plant process variables to detect abnormal plant conditions and to provide input to actuation devices directly controlling equipment required to mitigate the consequences of design basis events to protect the public health and safety. The secondary functions of the Plant Protection and Instrumentation System are to provide plant preventive features, sybsystems that monitor plant safety systems status, subsystems that monitor the plant under normal operating and accident conditions, safety-related controls which allow control of reactor shutdown and cooling from a remote shutdown area

  8. Plant dynamics studies towards design of plant protection system for PFBR

    Energy Technology Data Exchange (ETDEWEB)

    Natesan, K., E-mail: natesan@igcar.gov.in [Nuclear and Safety Engineering Group, Indira Gandhi Centre for Atomic Research, Kalpakkam 603 102 (India); Kasinathan, N.; Velusamy, K.; Selvaraj, P.; Chellapandi, P. [Nuclear and Safety Engineering Group, Indira Gandhi Centre for Atomic Research, Kalpakkam 603 102 (India)

    2012-09-15

    Highlights: Black-Right-Pointing-Pointer Analysis of various design basis events in a fast breeder reactor towards design of plant protection system. Black-Right-Pointing-Pointer Plant dynamic modeling of a sodium cooled fast breeder reactor. Black-Right-Pointing-Pointer Selection of optimum set of plant parameters for considering best plant availability. - Abstract: Prototype fast breeder reactor (PFBR) is a 500 MWe (1250 MWt) liquid sodium cooled pool type reactor currently under construction in India. For a safe and efficient operation of the plant, it is necessary that the reactor is protected from all the transients that may occur in the plant. In order to accomplish this, adequate number of SCRAM parameters is required in the plant protection system with reliable instrumentation. For identifying the SCRAM parameters, the neutronic and thermal hydraulic responses of the plant for various possible events need to be established. Towards this, a one dimensional plant dynamics code DYANA-P has been developed with thermal hydraulic models for reactor core, hot and cold pools, intermediate heat exchangers, pipelines, steam generator, primary sodium circuits and secondary sodium circuits. The code also incorporates neutron kinetics and reactivity feedback models. By a comprehensive plant dynamics study an optimum list of SCRAM parameters and the maximum permissible response time for various instruments used for deriving them have been arrived at.

  9. Study on aging management of fire protection system in nuclear power plant

    International Nuclear Information System (INIS)

    Fang Huasong; Du Yu; Li Jianwen; Shi Haining; Tu Fengsheng

    2010-01-01

    Fire prevention, fire fighting and fire automatic alarms are three aspects which be included in fire protection system in nuclear power plants. The fire protection system can protect personnel, equipment etc in the fire, so their performance will have a direct influence on the safe operation in nuclear power plants. The disabled accidents caused by aging have happened continuously with the extension of time in the fire protection system, which is the major security risk during the running time in nuclear power plants. In view of the importance of fire protection system and the severity of aging problems, the aging are highly valued by the plant operators and related organizations. Though the feedback of operating experience in nuclear power plant, the impact of the fire-fighting equipment aging on system performance and reliability be assessed, the aging sensitive equipment be selected to carry out the aging analysis and to guide the management and maintenance to guarantee the healthy operation in life time of fire protection system in nuclear power plant. (authors)

  10. Fail-safe computer-based plant protection systems

    International Nuclear Information System (INIS)

    Keats, A.B.

    1983-01-01

    A fail-safe mode of operation for computers used in nuclear reactor protection systems was first evolved in the UK for application to a sodium cooled fast reactor. The fail-safe properties of both the hardware and the software were achieved by permanently connecting test signals to some of the multiplexed inputs. This results in an unambiguous data pattern, each time the inputs are sequentially scanned by the multiplexer. The ''test inputs'' simulate transient excursions beyond defined safe limits. The alternating response of the trip algorithms to the ''out-of-limits'' test signals and the normal plant measurements is recognised by hardwired pattern recognition logic external to the computer system. For more general application to plant protection systems, a ''Test Signal Generator'' (TSG) is used to compute and generate test signals derived from prevailing operational conditions. The TSG, from its knowledge of the sensitivity of the trip algorithm to each of the input variables, generates a ''test disturbance'' which is superimposed upon each variable in turn, to simulate a transient excursion beyond the safe limits. The ''tripped'' status yielded by the trip algorithm when using data from a ''disturbed'' input forms part of a pattern determined by the order in which the disturbances are applied to the multiplexer inputs. The data pattern formed by the interleaved test disturbances is again recognised by logic external to the protection system's computers. This fail-safe mode of operation of computer-based protection systems provides a powerful defence against common-mode failure. It also reduces the importance of software verification in the licensing procedure. (author)

  11. System and Software Design for the Plant Protection System for Shin-Hanul Nuclear Power Plant Units 1 and 2

    International Nuclear Information System (INIS)

    Hwang, In Seok; Kim, Young Geul; Choi, Woong Seock; Sohn, Se Do

    2015-01-01

    The Reactor Protection System(RPS) protects the core fuel design limits and reactor coolant system pressure boundary for Anticipated Operational Occurrences (AOOs), and provides assistance in mitigating the consequences of Postulated Accidents (PAs). The ESFAS sends the initiation signals to Engineered Safety Feature - Component Control System (ESF-CCS) to mitigate consequences of design basis events. The Common Q platform Programmable Logic Controller (PLC) was used for Shin-Wolsung Nuclear Power Plant Units 1 and 2 and Shin-Kori Nuclear Power Plant Units 1, 2, 3 and 4 since Digital Plant Protection System (DPPS) based on Common Q PLC was applied for Ulchin Nuclear Power Plant Units 5 and 6. The PPS for Shin-Hanul Nuclear Power Plant Units 1 and 2 (SHN 1 and 2) was developed using POSAFE-Q PLC for the first time for the PPS. The SHN1 and 2 PPS was delivered to the sites after completion of Man Machine Interface System Integrated System Test (MMIS-IST). The SHN1 and 2 PPS was developed to have the redundancy in each channel and to use the benefits of POSAFE-Q PLC, such as diagnostic and data communication. The PPS application software was developed using ISODE to minimize development time and human errors, and to improve software quality, productivity, and reusability

  12. System and Software Design for the Plant Protection System for Shin-Hanul Nuclear Power Plant Units 1 and 2

    Energy Technology Data Exchange (ETDEWEB)

    Hwang, In Seok; Kim, Young Geul; Choi, Woong Seock; Sohn, Se Do [KEPCO EnC, Daejeon (Korea, Republic of)

    2015-10-15

    The Reactor Protection System(RPS) protects the core fuel design limits and reactor coolant system pressure boundary for Anticipated Operational Occurrences (AOOs), and provides assistance in mitigating the consequences of Postulated Accidents (PAs). The ESFAS sends the initiation signals to Engineered Safety Feature - Component Control System (ESF-CCS) to mitigate consequences of design basis events. The Common Q platform Programmable Logic Controller (PLC) was used for Shin-Wolsung Nuclear Power Plant Units 1 and 2 and Shin-Kori Nuclear Power Plant Units 1, 2, 3 and 4 since Digital Plant Protection System (DPPS) based on Common Q PLC was applied for Ulchin Nuclear Power Plant Units 5 and 6. The PPS for Shin-Hanul Nuclear Power Plant Units 1 and 2 (SHN 1 and 2) was developed using POSAFE-Q PLC for the first time for the PPS. The SHN1 and 2 PPS was delivered to the sites after completion of Man Machine Interface System Integrated System Test (MMIS-IST). The SHN1 and 2 PPS was developed to have the redundancy in each channel and to use the benefits of POSAFE-Q PLC, such as diagnostic and data communication. The PPS application software was developed using ISODE to minimize development time and human errors, and to improve software quality, productivity, and reusability.

  13. Problems of New Plant Variety Protection System in China and Countermeasures

    OpenAIRE

    GUAN, Yuwu

    2013-01-01

    Protection of new plant varieties has been long neglected in China, which has already restricted agricultural technological renovation, and influenced export of Chinese agricultural products. The current scientific and technological management system is not favorable for the output of right of new plant variety, and high cost of protecting new plant varieties directly results in agricultural researchers’ ignorance of right of new plant variety. Major causes were concluded as poor intellectu...

  14. Reliability Analysis Study of Digital Reactor Protection System in Nuclear Power Plant

    International Nuclear Information System (INIS)

    Guo, Xiao Ming; Liu, Tao; Tong, Jie Juan; Zhao, Jun

    2011-01-01

    The Digital I and C systems are believed to improve a plants safety and reliability generally. The reliability analysis of digital I and C system has become one research hotspot. Traditional fault tree method is one of means to quantify the digital I and C system reliability. Review of advanced nuclear power plant AP1000 digital protection system evaluation makes clear both the fault tree application and analysis process to the digital system reliability. One typical digital protection system special for advanced reactor has been developed, which reliability evaluation is necessary for design demonstration. The typical digital protection system construction is introduced in the paper, and the process of FMEA and fault tree application to the digital protection system reliability evaluation are described. Reliability data and bypass logic modeling are two points giving special attention in the paper. Because the factors about time sequence and feedback not exist in reactor protection system obviously, the dynamic feature of digital system is not discussed

  15. Modernization of the WWER 440/230 nuclear power plant environmental protection system

    Energy Technology Data Exchange (ETDEWEB)

    Mikheev, N.V.; Kamenskaya, A.N.; Kulyukhin, S.A.; Novichenko, V.L.; Rumer, I.A. [Russian Academy of Sciences, Institute of Physical Chemistry, Moscow (Russian Federation); Antonov, B.V.; Kornienko, A.G.; Meshkov, V.M.; Rogov, M.F. [Rosenergoatom Concern, Moscow (Russian Federation)

    2001-07-01

    The papers reports a new approach to the problem of increasing environmental protection during severe accidents at WWER 440/230 nuclear power plants. The environmental protection system that we propose has three, not two protection levels, and can be introduced with minor modernization of the equipment available at WWER 440/230 nuclear power plants: 1. a jet-vortex condenser; 2. the sprinkler system; 3. a sorption module. The proposed modernization not only makes it possible to avoid emergency discharge of radioactive air and steam mix into the environment under any accident scenario, but also would substantially contribute to the safety of WWER 440/230 nuclear power plants. (author)

  16. Software V ampersand V methods for digital plant protection system

    International Nuclear Information System (INIS)

    Kim, Hung-Jun; Han, Jai-Bok; Chun, Chong-Son; Kim, Sung; Kim, Kern-Joong.

    1997-01-01

    Careful thought must be given to software design in the development of digital based systems that play a critical role in the successful operation of nuclear power plants. To evaluate the software verification and validation methods as well as to verify its system performance capabilities for the upgrade instrumentation and control system in the Korean future nuclear power plants, the prototype Digital Plant, Protection System (DPPS) based on the Programmable Logic Controller (PLC) has been constructed. The system design description and features are briefly presented, and the software design and software verification and validation methods are focused. 6 refs., 2 figs

  17. Wind Plant Collector System Fault Protection and Coordination

    Energy Technology Data Exchange (ETDEWEB)

    Bradt, M. [IEEE PES Wind Plant Collector System Design Working Group; Behnke, M. R. [IEEE PES Wind Plant Collector System Design Working Group; Bloethe, W.G. [IEEE PES Wind Plant Collector System Design Working Group; Brooks, C. [IEEE PES Wind Plant Collector System Design Working Group; Camm, E H [IEEE PES Wind Plant Collector System Design Working Group; Dilling, W. [IEEE PES Wind Plant Collector System Design Working Group; Goltz, B. [IEEE PES Wind Plant Collector System Design Working Group; Li, J. [IEEE PES Wind Plant Collector System Design Working Group; Niemira, J. [IEEE PES Wind Plant Collector System Design Working Group; Nuckles, K. [IEEE PES Wind Plant Collector System Design Working Group; Patino, J. [IEEE PES Wind Plant Collector System Design Working Group; Reza, M [IEEE PES Wind Plant Collector System Design Working Group; Richardson, B. [IEEE PES Wind Plant Collector System Design Working Group; Samaan, N. [IEEE PES Wind Plant Collector System Design Working Group; Schoene, Jens [IEEE PES Wind Plant Collector System Design Working Group; Smith, Travis M [ORNL; Snyder, Isabelle B [ORNL; Starke, Michael R [ORNL; Walling, R. [IEEE PES Wind Plant Collector System Design Working Group; Zahalka, G. [IEEE PES Wind Plant Collector System Design Working Group

    2010-01-01

    This paper presents a summary of the most important protection and coordination considerations for wind power plants. Short-circuit characteristics of both aggregate wind plant and individual wind turbine genera- tors, as well as general interconnection protection requirements are discussed. Many factors such as security, reliability, and safety are considered for proper conservative protection of the wind power plant and individual turbines.

  18. Estimation of reliability on digital plant protection system in nuclear power plants using fault simulation with self-checking

    International Nuclear Information System (INIS)

    Lee, Jun Seok; Kim, Suk Joon; Seong, Poong Hyun

    2004-01-01

    Safety-critical digital systems in nuclear power plants require high design reliability. Reliable software design and accurate prediction methods for the system reliability are important problems. In the reliability analysis, the error detection coverage of the system is one of the crucial factors, however, it is difficult to evaluate the error detection coverage of digital instrumentation and control system in nuclear power plants due to complexity of the system. To evaluate the error detection coverage for high efficiency and low cost, the simulation based fault injections with self checking are needed for digital instrumentation and control system in nuclear power plants. The target system is local coincidence logic in digital plant protection system and a simplified software modeling for this target system is used in this work. C++ based hardware description of micro computer simulator system is used to evaluate the error detection coverage of the system. From the simulation result, it is possible to estimate the error detection coverage of digital plant protection system in nuclear power plants using simulation based fault injection method with self checking. (author)

  19. A development of digital plant protection system architecture

    International Nuclear Information System (INIS)

    Seong, S. H.; Park, H. Y.; Kim, D. H.; Seo, Y. S.; Gu, I. S.

    2000-01-01

    The digital plant protection system (DPPS) which have a large number of advantages compared to current analog protection system has been developed in various field. The major disadvantages of digital system are, however, vulnerable to faults of processor and software. To overcome the disadvantages, the concept of segment and partition in a channel has been developed. Each segment in a channel is divided from sensor to reactor trip and engineered safety features, which is based on the functional diversity of input signals against the various plant transient phenomena. Each partition allocates the function module to an independent processing module in order to process and isolate the faults of each module of a segment. A communication system based on the deterministic protocol with the predictable and hard real-time characteristics has been developed in order to link the various modules within a segment. The self-diagnostics including online test and periodic test procedures are developed in order to increase the safety, reliability and availability of DPPS. The developed DPPS uses the off-the-shelf DSP (digital signal processor) and adopts VME bus architecture, which have sufficient operation experience in the industry. The verification and validation and quality assurance of software has been developed and the architecture and protocol of deterministic communication system has been researched

  20. Advanced digital PWR plant protection system based on optimal estimation theory

    International Nuclear Information System (INIS)

    Tylee, J.L.

    1981-04-01

    An advanced plant protection system for the Loss-of-Fluid Test (LOFT) reactor plant is described and evaluated. The system, based on a Kalman filter estimator, is capable of providing on-line estimates of such critical variables as fuel and cladding temperature, departure from nucleate boiling ratio, and maximum linear heat generation rate. The Kalman filter equations are presented, as is a description of the LOFT plant dynamic model inherent in the filter. Simulation results demonstrate the performance of the advanced system

  1. Quantitative evaluation of physical protection system in nuclear power plant

    International Nuclear Information System (INIS)

    Sun Yahua; Li Bin; Li Shiju

    2009-01-01

    Based on the prompt detection analysis, this paper introduced one analysis model of intrusion path in nuclear power plant by means of morphology analysis and developed the evaluation software for path model analysis of physical protection system. Quantitative analysis on three elements (detection, delay, and response) of physical protection system was presented with an imaginary intrusion event example in Mac Arthur nuclear center. The results indicated that the path prompt detection analysis worked effectively to find the weak point of the physical protection system in NPP, and meantime we can also get the high cost-effectiveness improved measures. It is an effective approach to evaluate the overall performance of the system. (authors)

  2. Advanced digital instrumentation and control system for nuclear power plant protection

    International Nuclear Information System (INIS)

    Sabino, D.

    1997-01-01

    The Diverse Protection System (DPS) is described. The DPS is a state-of-the-art digital protection system developed as a back-up to the primary reactor protection system at the Temelin nuclear power plant, featuring a compact hardware design based on VMEbus technology. This technology allows for ease in adding or modifying the number and type of input modules and processors. The DPS software is written in a high level language suitable for safety critical applications. The software is both modular and configurable allowing for potential future modifications and software reuse

  3. 48 CFR 252.217-7016 - Plant protection.

    Science.gov (United States)

    2010-10-01

    ... 48 Federal Acquisition Regulations System 3 2010-10-01 2010-10-01 false Plant protection. 252.217... Clauses 252.217-7016 Plant protection. As prescribed in 217.7104(a), use the following clause: Plant Protection (DEC 1991) (a) The Contractor shall provide, for the plant and work in process, reasonable...

  4. Advanced digital instrumentation and control system for nuclear power plant protection

    Energy Technology Data Exchange (ETDEWEB)

    Sabino, D [VVER Engineering, Westinghouse Electric Corporation (United States)

    1998-12-31

    The Diverse Protection System is a back-up to the Primary Reactor Protection System developed for use at the Temelin nuclear power plant. The DPS is a digital system which provides a wealth of benefits from today`s advanced technology. These benefits include a compact hardware design with high performance microprocessors and a structured software design using a high level language. An overview of the DPS functions, hardware and software is provided. (author). 1 fig., 1 tab.

  5. Modelling of core protection and monitoring system for PWR nuclear power plant simulator

    International Nuclear Information System (INIS)

    Jung Kun Lee; Byoung Sung Han

    1997-01-01

    A nuclear power plant simulator was developed for Younggwang units 3 and 4 nuclear power plant (YGN Nos 3 and 4) in Korea; it has been in operation on training center since November 1996. The core protection calculator (CPC) and the core operating limit supervisory system (COLSS) for the simulator were also developed. The CPC is a digital computer-based core protection system, which performs on-line calculation of departure from nucleate boiling ratio (DNBR) and local power density (LPD). It initiates reactor trip when the core conditions exceed designated DNBR or LPD limitations. The COLSS is designed to assist operators by implementing the limiting conditions for operations in the technical specifications. With these systems, it is possible to increase capacity factor and safety of nuclear power plants, because the COLSS data can show accurate operation margin to plant operators and the CPC can protect reactor core. In this study, the function of CPC/COLSS is analyzed in detail, and then simulation model for CPC/COLSS is presented based on the function. Compared with the YGN Nos 3 and 4 plant operation data and CEDIPS/COLSS FORTRAN code test results, the predictions with the model show reasonable results. (Author)

  6. Applying formal method to design of nuclear power plant embedded protection system

    International Nuclear Information System (INIS)

    Kim, Jin Hyun; Kim, Il Gon; Sung, Chang Hoon; Choi, Jin Young; Lee, Na Young

    2001-01-01

    Nuclear power embedded protection systems is a typical safety-critical system, which detects its failure and shutdowns its operation of nuclear reactor. These systems are very dangerous so that it absolutely requires safety and reliability. Therefore nuclear power embedded protection system should fulfill verification and validation completely from the design stage. To develop embedded system, various V and V method have been provided and especially its design using Formal Method is studied in other advanced country. In this paper, we introduce design method of nuclear power embedded protection systems using various Formal-Method in various respect following nuclear power plant software development guideline

  7. Refurbishing the reactor protection systems of VVER-440/230 and VVER-1000/320 nuclear power plants with exclusively digital IandC systems

    International Nuclear Information System (INIS)

    Martin, M.

    1997-01-01

    The refurbishment of reactor protection systems of nuclear power plants is based on two sets of requirements: engineering aspects such as performance, qualification and licensing, as well as interfaces to other systems; and cost-benefit relationships, ease of service and maintenance as well as installation during scheduled outages. A number of WWER-440 and WWER-1000 nuclear plants have announced their intention to refurbish their protection systems. Since 1994, these plants have been placing orders with Siemens for new protection systems, including the neutron flux monitoring system utilizing the advanced system TELEPERM XS. This exclusively digital IandC system provides an excellent foundation for the remaining plant service life

  8. Periodic inspections of lightning protection systems in intermediate storage facilities of nuclear technological plants

    International Nuclear Information System (INIS)

    Witzel, Andre; Schulz, Olav

    2013-01-01

    Especially for nuclear technological plants, periodic inspections of lightning protection systems are of great importance. This article shows the sequence of maintenance programs using the examples of the intermediate storage facilities of the nuclear technological plants Grohnde and Unterweser as well as the central intermediate storage facility in Gorleben and gives a description of the extensive measures of inspecting the external and internal lightning protection and the global earth termination system.

  9. Strategy and system of fire protection at Guangdong Daya Bay Nuclear Power Plant

    International Nuclear Information System (INIS)

    Zhou Weihong

    1999-12-01

    The fire protection is an important safety issue of nuclear power utilities. The author depicts the strategy and management system of fire protection implemented successfully at Guangdong Daya Bay Nuclear Power Plant of China

  10. Optimization of redundancy by using genetic algorithm for reliability of plant protection system

    International Nuclear Information System (INIS)

    Yoo, D. W.; Seong, S. H.; Kim, D. H.; Park, H. Y.; Gu, I. S.

    2000-01-01

    The design and development of a reliable protection system has been becoming a key issue in industry field because the reliability of system is considered as an important factor to perform the system's function successfully. Plant Protection System(PPS) guarantees the safety of plant by accident detection and control action against the transient conditions of plant. This paper presents the analysis of PPS reliability and the formal problem statement about optimal redundancy based on the reliability of PPS. And the optimization problem is solved by genetic algorithm. The genetic algorithm is a useful tool to solve the problems, in the case of large searching, complex gradient, existence local minimum. The effectiveness of the proposed optimization technique is proved by the target reliability of one channel of PPS, using the failure rate based on the MIL-HDBK-217

  11. An evaluation method of fault-tolerance for digital plant protection system in nuclear power plants

    International Nuclear Information System (INIS)

    Lee, Jun Seok; Kim, Man Cheol; Seong, Poong Hyun; Kang, Hyun Gook; Jang, Seung Cheol

    2005-01-01

    In recent years, analog based nuclear power plant (NPP) safety related instrumentation and control (I and C) systems have been replaced to modern digital based I and C systems. NPP safety related I and C systems require very high design reliability compare to the conventional digital systems so that reliability assessment is very important. In the reliability assessment of the digital system, fault tolerance evaluation is one of the crucial factors. However, the evaluation is very difficult because the digital system in NPP is very complex. In this paper, the simulation based fault injection technique on simplified processor is used to evaluate the fault-tolerance of the digital plant protection system (DPPS) with high efficiency with low cost

  12. Safety analysis of an expert reactor protection system in nuclear power plants

    International Nuclear Information System (INIS)

    EL-Kafas, A.E.A.E.

    1996-01-01

    the purpose of the dissertation is to develop a real time expert reactor protection system (ERPS) for operational safety of pressurized water reactor nuclear power plant. The system is developed to diagnose plant failures and for identification of plant transients (with and without scram). for this ERPS. probabilistic safety analysis techniques are used to check the availability and priority of the recommended safety system in case of plant accidents . the real- time information during transients and accidents can be obtained to asses the operator in his decision - making . Also, the ERPS is able to give advice for the reactor operator to take the appropriate corrective action during abnormal situations. The system model consists of the dynamic differential equations for reactor core, pressurizer, steam generator, turbine and generator, piping and plenums. The system of equations can be solved by appropriate codes also displayed directly from sensors of the plant. All scenarios of transients, accidents and fault tress for plant systems are learned to ERPS

  13. Safety analysis of an expert reactor protection system in nuclear power plants

    International Nuclear Information System (INIS)

    El-Kafas, A.A.

    1997-01-01

    The purpose of the dissertation is to develop real time expert reactor protection system (ERPS) for operational safety of pressurized water reactor nuclear power plant. The system is developed to diagnose plant failures and for identification plant transients (with and without scram). For this erps, probabilistic safety analysis techniques are used to check the availability and priority of the recommended safety system in case of plant accidents. The real - time information during transients and accidents can be obtained to assess the operator in his decision - making. Also, the ERPS is able to give advice for the reactor operator to take the appropriate corrective action during abnormal situations. 5-15 figs., 42 refs

  14. An Improved Setpoint Determination Methodology for the Plant Protection System Considering Beyond Design Basis Events

    International Nuclear Information System (INIS)

    Lee, C.J.; Baik, K.I.; Baek, S.M.; Park, K.-M.; Lee, S.J.

    2013-06-01

    According to the nuclear regulations and industry standards, the trip setpoint and allowable value for the plant protection system have been determined by considering design basis events. In order to improve the safety of a nuclear power plant, an attempt has been made to develop an improved setpoint determination methodology for the plant protection system trip parameter considering not only a design basis event but also a beyond design basis event. The results of a quantitative evaluation performed for the Advanced Power Reactor 1400 nuclear power plant in Korea are presented herein. The results confirmed that the proposed methodology is able to improve the nuclear power plant's safety by determining more reasonable setpoints that can cover beyond design basis events. (authors)

  15. Radiation protection service for a nucleonic control system of continuous casting plant after events of accident

    International Nuclear Information System (INIS)

    Chakrabarti, Santanu; Massand, O.P.

    1998-01-01

    Extensive use of nucleonic control systems like level controllers was observed during radiation protection surveys in industries such as refineries, steel plants etc., located in the eastern region of India. There were two accidents at continuous casting plant in 1995 which affected the nucleonic control system installed in 1992. The authorities contacted Bhabha Atomic Research Centre (BARC) for radiation protection surveys for the involved nucleonic gauges. The present paper describes the radiation protection services rendered by BARC during such accidents. (author)

  16. Safety Evaluation of Full Digital Plant Protection System of Shin-Kori 3 and 4 in Korea

    International Nuclear Information System (INIS)

    Koh, J. S.; Kim, D. I.; Jeong, C. H.; Park, H. S.; Ji, S. H.; Kang, Y. D.; Park, G. Y.

    2009-01-01

    Keeping pace with the emerging trend of digital computer technologies, KHNP has utilized full digital plant protection system into the design of I and C systems at SKN 3 and 4. This paper presents safety review activities and results related to digital plant protection systems during the licensing of construction permit for the Shin-Kori 3 and 4(SKN 3 and 4) in Korea. The major licensing issues regarding the digital systems were software quality and cyber security during planning stage, system integrity with fail-safe design, EMI equipment qualification of digital systems, FPGA qualification and communication independence between safety and non-safety System. This paper addresses our approach to evaluate full digital protection systems with revised safety review guidelines and the resulting discussion to resolve the licensing issues

  17. Testing methodology of embedded software in digital plant protection system

    International Nuclear Information System (INIS)

    Seong, Ah Young; Choi, Bong Joo; Lee, Na Young; Hwang, Il Soon

    2001-01-01

    It is necessary to assure the reliability of software in order to digitalize RPS(Reactor Protection System). Since RPS causes fatal damage on accidental cases, it is classified as Safety 1E class. Therefore we propose the effective testing methodology to assure the reliability of embedded software in the DPPS(Digital Plant Protection System). To test the embedded software effectively in DPPS, our methodology consists of two steps. The first is the re-engineering step that extracts classes from structural source program, and the second is the level of testing step which is composed of unit testing, Integration Testing and System Testing. On each testing step we test the embedded software with selected test cases after the test item identification step. If we use this testing methodology, we can test the embedded software effectively by reducing the cost and the time

  18. Proposal of a concept and reliability analysis for a fusion plant magnet protection system

    International Nuclear Information System (INIS)

    Schnauder, H.; Pamfilie, E.

    1993-05-01

    The unavailability for the current switch down in case of a demand in the magnet coils of a fusion demonstration plant must be decreased by a few orders of magnitude as compared to the one of experimental facilities. The safety requirements to prevent initiation of event sequences which might lead to the release of radioactivity and energy by the plant must be fulfilled with the same standards as applied in a normally applicable plant. On the basis of this proven technology a general usable magnet protection system will be proposed, which achieves some considerable improvements in the failure detectability as compared to the conventional protection systems. It will be demonstrated by fault tree analysis that the principal demands on safety can be satisfied by that approach. The improvements are achieved by the use of an additional microprocessor supported system for failure detection without being used for initiation of any safety related actions. An influence on a safety action by the additional system therefore is excluded. (orig.) [de

  19. Computer aided radiation protection system at Tokai reprocessing plant

    International Nuclear Information System (INIS)

    Ishida, J.; Saruta, J.; Yonezawa, R.

    1996-01-01

    Radiation control for workers and workforce has been carried out strictly and effectively taking into account ALARA principle at Tokai Reprocessing Plant (TRP) which has treated about 860 tons of irradiated fuels by now since 1977. The outline of radiation control method at TRP has already been described. This paper briefly describes our experiences and the capabilities of Radiological Information Management System (RIMS) for the safety operation of TRP, followed by radiation exposure control and activity discharge control as examples. By operating the RIMS, the conditions of workplace such as dose equivalent rate and air-contamination are easily and rapidly grasped to take prompt countermeasures for radiological protection, localization and elimination of contamination, and also the past experience data are properly applied to new radiological works to reduce exposures associated with routine and special repetitive maintenance operations at TRP. Finally, authors would like to emphasize that the form and system for radiological control of reprocessing plant has been established throughout our 15-year-experience at TRP. (author)

  20. Application of fault tree methodology to modeling of the AP1000 plant digital reactor protection system

    International Nuclear Information System (INIS)

    Teolis, D.S.; Zarewczynski, S.A.; Detar, H.L.

    2012-01-01

    The reactor trip system (RTS) and engineered safety features actuation system (ESFAS) in nuclear power plants utilizes instrumentation and control (IC) to provide automatic protection against unsafe and improper reactor operation during steady-state and transient power operations. During normal operating conditions, various plant parameters are continuously monitored to assure that the plant is operating in a safe state. In response to deviations of these parameters from pre-determined set points, the protection system will initiate actions required to maintain the reactor in a safe state. These actions may include shutting down the reactor by opening the reactor trip breakers and actuation of safety equipment based on the situation. The RTS and ESFAS are represented in probabilistic risk assessments (PRAs) to reflect the impact of their contribution to core damage frequency (CDF). The reactor protection systems (RPS) in existing nuclear power plants are generally analog based and there is general consensus within the PRA community on fault tree modeling of these systems. In new plants, such as AP1000 plant, the RPS is based on digital technology. Digital systems are more complex combinations of hardware components and software. This combination of complex hardware and software can result in the presence of faults and failure modes unique to a digital RPS. The United States Nuclear Regulatory Commission (NRC) is currently performing research on the development of probabilistic models for digital systems for inclusion in PRAs; however, no consensus methodology exists at this time. Westinghouse is currently updating the AP1000 plant PRA to support initial operation of plants currently under construction in the United States. The digital RPS is modeled using fault tree methodology similar to that used for analog based systems. This paper presents high level descriptions of a typical analog based RPS and of the AP1000 plant digital RPS. Application of current fault

  1. Installation and commissioning of operation nuclear power plant reactor protection system modernization project

    International Nuclear Information System (INIS)

    Lu Weiwei

    2010-01-01

    Qinshan Nuclear Power Plant is the first nuclear power plant in mainland China; it is also the first one which realizes the modernization of analog technology based Reactor Protection System in the operation nuclear power plant of China. The implementation schedule is the shortest one which use same digital technology platform (TELEPERM XS of AREVA NP) to modifying the safety class I and C system in the world, the whole project spent 28 months from equipment contract signed to putting system into operation. It open up a era for operation nuclear power plant using mature digital technology to make safety class I and C system modernization in China. The important practical significance of this successful project is very obvious. This article focus on two important project stage--equipment installation and system commissioning, it is based on a large number of engineering implementation fact, it covers the problems and solutions happened during the installation and commission. The purpose of the article is to share the experience and lessons of safety I and C system modernization for other operation nuclear power plant. (authors)

  2. Intercropping System for Protection the Potato Plant from Insect Infestation

    Directory of Open Access Journals (Sweden)

    Aziza Sharaby

    2015-06-01

    Full Text Available The use of intercropping system provides an option for insect control for organic farmers that are limited in their chemical use. Additionally, intercropping systems can be attractive to conventional growers as a cost-effective insect control solution. A study was carried out for two seasons 2011-2012 and 2012-2013 to evaluate the effect of intercropping of potato (Solanum tuberosum L. with onion (Allium cepa L. on whitefly (Bemicia tabasi Gennadius and aphids’ Myzus persicae Sulz. and Aphis gossypii Glover infestation in potato fields. Results indicated that intercropping significantly reduced potato plant infestation with whitefly by 42.7, 51.3% while it was 62.69% reduction with aphids during the two successive winter seasons than when potato plants were cultivated alone. Therefore, intercropping could be recommended as a protection method of reducing pest population in the fields.

  3. SMART core protection system design

    International Nuclear Information System (INIS)

    Lee, J. K.; Park, H. Y.; Koo, I. S.; Park, H. S.; Kim, J. S.; Son, C. H.

    2003-01-01

    SMART COre Protection System(SCOPS) is designed with real-tims Digital Signal Processor(DSP) board and Network Interface Card(NIC) board. SCOPS has a Control Rod POSition (CRPOS) software module while Core Protection Calculator System(CPCS) consists of Core Protection Calculators(CPCs) and Control Element Assembly(CEA) Calculators(CEACs) in the commercial nuclear plant. It's not necessary to have a independent cabinets for SCOPS because SCOPS is physically very small. Then SCOPS is designed to share the cabinets with Plant Protection System(PPS) of SMART. Therefor it's very easy to maintain the system because CRPOS module is used instead of the computer with operating system

  4. TECHNICAL AND TECHNOLOGICAL ASPECTS IN PLANT PROTECTION IN THE PRECISION FARMING SYSTEM

    Directory of Open Access Journals (Sweden)

    Mladen Jurišić

    2015-06-01

    Full Text Available The basic premise of precision farming as a larger amount of information is its availability to the farmer in making decision. Direct comparison of perennial parameters obtained from the plot results in purposefully, argumentative and optimal use of resources for work (while keeping in mind the ecological impact. Today, the development of satellite navigation technology and monitoring of agricultural machinery, and reducing the cost of these devices again revived the question of the precision agriculture application. Advanced farmers in developed agricultural countries already regularly apply some of the technological possibilities of precision farming. Precision agriculture and plant protection allow the farmer realizing high incomes while keeping safe natural resources. Using modern GIS technology machines collect data directly from the plot using sensors and integrate themselves into the data processing system. Processed information is used by a farmer taking GreenStar system for the new planned operation and achieving significant time and money spare. Precision agriculture offers the possibility of optimal care of each plant, not just the average, or the entire field. Low risk investments are one of the main factors of choice precise plant protection. The use of pilotless aircrafts remote sensing allow fast and economical obtaining data and sufficient precision information. Using modern technology such as Variable Rate Application (applying a variable volume and GreenStar software package it is possible to regulate the amount of care and protection.

  5. Real-time corrosion control system for cathodic protection of buried pipes for nuclear power plant

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Ki Tae; Kim, Hae Woong; Kim, Young Sik [School of Materials Science and Engineering, Andong National University, Andong (Korea, Republic of); Chang, Hyun Young; Lim, Bu Taek; Park, Heung Bae [Power Engineering Research Institute, KEPCO Engineering and Construction Company, Seongnam (Korea, Republic of)

    2015-02-15

    Since the operation period of nuclear power plants has increased, the degradation of buried pipes gradually increases and recently it seems to be one of the emerging issues. Maintenance on buried pipes needs high quality of management system because outer surface of buried pipe contacts the various soils but inner surface reacts with various electrolytes of fluid. In the USA, USNRC and EPRI have tried to manage the degradation of buried pipes. However, there is little knowledge about the inspection procedure, test and manage program in the domestic nuclear power plants. This paper focuses on the development and build-up of real-time monitoring and control system of buried pipes. Pipes to be tested are tape-coated carbon steel pipe for primary component cooling water system, asphalt-coated cast iron pipe for fire protection system, and pre-stressed concrete cylinder pipe for sea water cooling system. A control system for cathodic protection was installed on each test pipe which has been monitored and controlled. For the calculation of protection range and optimization, computer simulation was performed using COMSOL Multiphysics (Altsoft co.)

  6. Real-time corrosion control system for cathodic protection of buried pipes for nuclear power plant

    International Nuclear Information System (INIS)

    Kim, Ki Tae; Kim, Hae Woong; Kim, Young Sik; Chang, Hyun Young; Lim, Bu Taek; Park, Heung Bae

    2015-01-01

    Since the operation period of nuclear power plants has increased, the degradation of buried pipes gradually increases and recently it seems to be one of the emerging issues. Maintenance on buried pipes needs high quality of management system because outer surface of buried pipe contacts the various soils but inner surface reacts with various electrolytes of fluid. In the USA, USNRC and EPRI have tried to manage the degradation of buried pipes. However, there is little knowledge about the inspection procedure, test and manage program in the domestic nuclear power plants. This paper focuses on the development and build-up of real-time monitoring and control system of buried pipes. Pipes to be tested are tape-coated carbon steel pipe for primary component cooling water system, asphalt-coated cast iron pipe for fire protection system, and pre-stressed concrete cylinder pipe for sea water cooling system. A control system for cathodic protection was installed on each test pipe which has been monitored and controlled. For the calculation of protection range and optimization, computer simulation was performed using COMSOL Multiphysics (Altsoft co.)

  7. Insights from a reliability review of digital plant protection system

    International Nuclear Information System (INIS)

    Kim, I.S.; Hwang, S.W.; Kim, B.S.; Jeong, C.H.; Oh, S.H.

    2001-01-01

    The full text follows: As part of the design efforts for Ulchin nuclear power plant units 5 and 6 of Korea, a reliability analysis of digital plant protection system (DPPS) was performed by ABB-CE. An independent review of the DPPS reliability analysis was undertaken by Hanyang University to assist Korea Institute of Nuclear Safety (KINS), the nuclear regulatory body of Korea, in evaluating the design acceptability of the digital system. The DPPS is designed to encompass both reactor trip function and ESFAS (engineered safety feature actuation system) initiation function. The major methods used by the ABB-CE to assess the Ulchin 5-6 DPPS reliability are failure mode and effect analysis (FMEA) and fault tree analysis. Hence, our independent review was conducted focusing on: -) the establishment of review criteria based on various sources, such as the standard review plan of KINS, 10CFR50 Appendix A, IEEE standards 279, 577, and 603; -) the suitability of the FMEA and fault tree analysis for the Ulchin 5-6 DPPS, including the specific methods used (e.g., for human reliability analysis and common-cause failure analysis), the assumptions made (e.g., with respect to test frequency and watchdog timer coverage), and the data employed (e.g., CCF parameter, human error probability, and processor failure rate); and -) the design acceptability of the DPPS especially as compared to the analog plant protection system from a reliability and safety perspective. The paper shall also discuss key issues requiring further in-depth investigation, such as reliability of programmable logic controllers (PLCs), coverage factor of watchdog timers, and susceptibility of redundant digital units to common cause failure. Sensitivity analyses were carried out to investigate the impact of several parameters of special interest, like the coverage factor of watchdog timer and human error probability (e.g. an operator error to manually trip the reactor, or to mis-calibrate the trip parameters) on

  8. Evaluation of Control and Protection System for Loss of Electrical Power Supply System of Water-Cooling Nuclear Power Plant

    International Nuclear Information System (INIS)

    Suhaemi, Tjipta; Djen Djen; Setyono; Jambiar, Riswan; Rozali, Bang; Setyo P, Dwi; Tjahyono, Hendro

    2000-01-01

    Evaluation of control and protection system for loss of electrical power supply system of water-cooled nuclear power plant has been done. The loss of electrical power supply. The accident covered the loss of external electrical load and loss of ac power to the station auxiliaries. It is analysed by studying and observing the mechanism of electrical power system and mechanism of related control and protection system. The are two condition used in the evaluation i e without turbine trip and with turbine trip. From the evaluation it is concluded that the control and protection system can handled the failure caused by the loss of electrical power system

  9. Creating space for ‘informal’ seed systems in a plant variety protection system that is based on UPOV 1991

    NARCIS (Netherlands)

    Jonge, de B.; Munyi, P.

    2017-01-01

    Summary
    Plant variety protection (PVP) gives a right holder
    (breeder) the possibility to exclude others from using his
    or her invention (plant variety) for a particular period.
    African regional organizations are currently establishing
    PVP systems that are in line with the

  10. Protected-area boundaries as filters of plant invasions.

    Science.gov (United States)

    Foxcroft, Llewellyn C; Jarošík, Vojtěch; Pyšek, Petr; Richardson, David M; Rouget, Mathieu

    2011-04-01

    Human land uses surrounding protected areas provide propagules for colonization of these areas by non-native species, and corridors between protected-area networks and drainage systems of rivers provide pathways for long-distance dispersal of non-native species. Nevertheless, the influence of protected-area boundaries on colonization of protected areas by invasive non-native species is unknown. We drew on a spatially explicit data set of more than 27,000 non-native plant presence records for South Africa's Kruger National Park to examine the role of boundaries in preventing colonization of protected areas by non-native species. The number of records of non-native invasive plants declined rapidly beyond 1500 m inside the park; thus, we believe that the park boundary limited the spread of non-native plants. The number of non-native invasive plants inside the park was a function of the amount of water runoff, density of major roads, and the presence of natural vegetation outside the park. Of the types of human-induced disturbance, only the density of major roads outside the protected area significantly increased the number of non-native plant records. Our findings suggest that the probability of incursion of invasive plants into protected areas can be quantified reliably. ©2010 Society for Conservation Biology.

  11. Development of digital plant protection system for Korean Next Generation Reactor

    International Nuclear Information System (INIS)

    Suk-Joon Park

    1998-01-01

    A Digital Plant Protection System (DPPS) for Korean Next Generation Reactor (KNGR) is being developed using the Programmable Logic Controller (PLC) technology. For the design verification, the development of the DPPS prototype is progressing at this time. The prototype hardware equipment is installed and software coding is started. DPPS software is being coded by strict software V and V activities and function block language that uses simple graphical symbols. By adopting the PLC technology, the design of DPPS is possible to take full advantages in areas such as automatic testing, simplified calibration, improved isolation between redundant channels, reduced internal and external wiring and increased plant availability. (author)

  12. Soil microflora and enzyme activities in rhizosphere of Transgenic Bt cotton hybrid under different intercropping systems and plant protection schedules

    Science.gov (United States)

    Biradar, D. P.; Alagawadi, A. R.; Basavanneppa, M. A.; Udikeri, S. S.

    2012-04-01

    Field experiments were conducted over three rainy seasons of 2005-06 to 2007-08 on a Vertisol at Dharwad, Karnataka, India to study the effect of intercropping and plant protection schedules on productivity, soil microflora and enzyme activities in the rhizosphere of transgenic Bt cotton hybrid. The experiment consisted of four intercropping systems namely, Bt cotton + okra, Bt cotton + chilli, Bt cotton + onion + chilli and Bt cotton + redgram with four plant protection schedules (zero protection, protection for Bt cotton, protection for intercrop and protection for both crops). Observations on microbial populations and enzyme activities were recorded at 45, 90, 135 and 185 (at harvest) days after sowing (DAS). Averaged over years, Bt cotton + okra intercropping had significantly higher total productivity than Bt cotton + chilli and Bt cotton + redgram intercropping system and was similar to Bt cotton + chilli + onion intercropping system. With respect to plant protection schedules for bollworms, protection for both cotton and intercrops recorded significantly higher yield than the rest of the treatments. Population of total bacteria, fungi, actinomycetes, P-solubilizers, free-living N2 fixers as well as urease, phosphatase and dehydrogenase enzyme activities increased up to 135 days of crop growth followed by a decline. Among the intercropping systems, Bt cotton + chilli recorded significantly higher population of microorganisms and enzyme activities than other cropping systems. While Bt cotton with okra as intercrop recorded the least population of total bacteria and free-living N2 fixers as well as urease activity. Intercropping with redgram resulted in the least population of actinomycetes, fungi and P-solubilizers, whereas Bt cotton with chilli and onion recorded least activities of dehydrogenase and phosphatase. Among the plant protection schedules, zero protection recorded maximum population of microorganisms and enzyme activities. This was followed by the

  13. Safety philosophy in upgrading the EBR-II plant protection system

    International Nuclear Information System (INIS)

    Sackett, J.I.

    1976-01-01

    The EBR-II plant protection system (PPS) has been substantially modified, upgrading its performance to more fully comply with modern safety philosophy and criteria. The upgrading effort required that the total reactor system be evaluated for possible faults and that a PPS be designed to accommodate them. The result was deletion of a number of existing trip functions and upgrading of others. Particular attention was given to loss of primary pumping power and reactivity insertion events. The design and performance criteria for the PPS has been more firmly established, understanding of the PPS function has been improved and the reactor has been subjected to fewer spurious trips, improving operational reliability

  14. Design and implementation of an advanced protection system for the Shin-Kori 3 and 4 nuclear power plant

    International Nuclear Information System (INIS)

    Kim, Yonghak; Choi, Woongseock; Kwon, Jongsoo; Wilkosz, Stephen J.; Ridolfo, Charles F.; Yanosy, Paul L.

    2008-01-01

    The Nuclear Power Industry is currently embracing modern digital technology for upgrades to existing Instrumentation and Control (I and C) infrastructures as well as for incorporation into the next generation of new plants which will be coming 'on-line' during the next decade. This technology is being fully exploited for the next generation of advanced plant protection systems which will be initially deployed on the Shin-Kori 3 and 4 Nuclear Power Plant in the Republic of Korea. The system design for this plant protection system is being performed by the Korea Power Engineering Company (KOPEC) and builds upon the past generation of digital safety systems which were initially implemented at Ulchin 5 and 6. The advanced protection system is an evolution of this existing design and includes a number of improved operating attributes including: · Integration of Reactor Protection, Engineered Safety Features Actuation, and Qualified Indication and Alarm functions which were previously implemented by separate systems in the past. · Use of a 'soft control' interface which provides convenient accessibility to the safety systems from 'operator workstations' · Implementation of a Large Display Panel (LDP) which provides a consistent and constant representation of the overall plant state and of the plant safety status. The equipment for the advanced plant protection system is being provided by Westinghouse Electric Company (WEC) and utilizes the Westinghouse 'Common Q' Standardized qualified platform (where 'Q' denotes 'qualified'). The 'Common Q' platform is comprised of commercially dedicated Programmable Logic Controllers (PLC's), color-graphic Flat Panel Displays (FPD's) with integral touch screens, and high speed data communication links. It is a mature product that is in wide use for a number of safety-related applications. Among its key attributes are: · High overall system availability, which is achieved via use of a multiple channel configuration that is tolerant

  15. Development of digital plant protection system for Korean Next Generation Reactor

    Energy Technology Data Exchange (ETDEWEB)

    Park, Suk-Joon [NSSS Engineering and Development Division, Korea Power Engineering Company, Taejon (Korea, Republic of)

    1998-10-01

    A Digital Plant Protection System (DPPS) for Korean Next Generation Reactor (KNGR) is being developed using the Programmable Logic Controller (PLC) technology. For the design verification, the development of the DPPS prototype is progressing at this time. The prototype hardware equipment is installed and software coding is started. DPPS software is being coded by strict software V and V activities and function block language that uses simple graphical symbols. By adopting the PLC technology, the design of DPPS is possible to take full advantages in areas such as automatic testing, simplified calibration, improved isolation between redundant channels, reduced internal and external wiring and increased plant availability. (author) 8 refs, 4 figs, 3 tabs

  16. Analytic study for physical protection system (PPS) in nuclear power plants (NPPs)

    Energy Technology Data Exchange (ETDEWEB)

    Woo, Tae Ho, E-mail: thw@snu.ac.kr

    2013-12-15

    Highlights: • The physical protection system (PPS) is investigated. • General NPPs are modeled in the study. • Possible terror cases, likelihood, and consequence are studied. • PPS is constructed by analytical methods. - Abstract: The nuclear safeguard is analyzed in the aspect of the physical protection system (PPS) in nuclear power plants (NPPs). The PPS is reviewed and its related terror scenarios are investigated. The PPS is developed using analytical methods. In the terror scenarios, there are 8 possible cases for the terror attacks to the NPPs. Then, the likelihood of terror is classified by the general terror incidents. The consequence of terror is classified by Design Basis Threat (DBT) of the International Atomic Energy Agency (IAEA) scale. The physical protection method is suggested by defense-in-depth constraints and severe accident countermeasures. Finally, the advanced PPS is constructed, which could be used for the preparation for the possible terror attacks in the NPPs.

  17. Analytic study for physical protection system (PPS) in nuclear power plants (NPPs)

    International Nuclear Information System (INIS)

    Woo, Tae Ho

    2013-01-01

    Highlights: • The physical protection system (PPS) is investigated. • General NPPs are modeled in the study. • Possible terror cases, likelihood, and consequence are studied. • PPS is constructed by analytical methods. - Abstract: The nuclear safeguard is analyzed in the aspect of the physical protection system (PPS) in nuclear power plants (NPPs). The PPS is reviewed and its related terror scenarios are investigated. The PPS is developed using analytical methods. In the terror scenarios, there are 8 possible cases for the terror attacks to the NPPs. Then, the likelihood of terror is classified by the general terror incidents. The consequence of terror is classified by Design Basis Threat (DBT) of the International Atomic Energy Agency (IAEA) scale. The physical protection method is suggested by defense-in-depth constraints and severe accident countermeasures. Finally, the advanced PPS is constructed, which could be used for the preparation for the possible terror attacks in the NPPs

  18. Mathematical verification of a nuclear power plant protection system function with combined CPN and PVS

    Energy Technology Data Exchange (ETDEWEB)

    Koo, Seo Ryong; Son, Han Seong; Seong, Poong Hyun [Korea Advanced Institute of Science and Technology, Taejon (Korea, Republic of)

    1999-12-31

    In this work, an automatic software verification method for Nuclear Power Plant (NPP) protection system is developed. This method utilizes Colored Petri Net (CPN) for modeling and Prototype Verification System (PVS) for mathematical verification. In order to help flow-through from modeling by CPN to mathematical proof by PVS, a translator has been developed in this work. The combined method has been applied to a protection system function of Wolsong NPP SDS2(Steam Generator Low Level Trip) and found to be promising for further research and applications. 7 refs., 10 figs. (Author)

  19. Mathematical verification of a nuclear power plant protection system function with combined CPN and PVS

    Energy Technology Data Exchange (ETDEWEB)

    Koo, Seo Ryong; Son, Han Seong; Seong, Poong Hyun [Korea Advanced Institute of Science and Technology, Taejon (Korea, Republic of)

    1998-12-31

    In this work, an automatic software verification method for Nuclear Power Plant (NPP) protection system is developed. This method utilizes Colored Petri Net (CPN) for modeling and Prototype Verification System (PVS) for mathematical verification. In order to help flow-through from modeling by CPN to mathematical proof by PVS, a translator has been developed in this work. The combined method has been applied to a protection system function of Wolsong NPP SDS2(Steam Generator Low Level Trip) and found to be promising for further research and applications. 7 refs., 10 figs. (Author)

  20. Regulatory Guidance for Lightning Protection in Nuclear Power Plants

    International Nuclear Information System (INIS)

    Kisner, Roger A.; Wilgen, John B.; Ewing, Paul D.; Korsah, Kofi; Antonescu, Christina E.

    2006-01-01

    Oak Ridge National Laboratory (ORNL) was engaged by the U.S. Nuclear Regulatory Commission (NRC) Office of Nuclear Regulatory Research (RES) to develop the technical basis for regulatory guidance to address design and implementation practices for lightning protection systems in nuclear power plants (NPPs). Lightning protection is becoming increasingly important with the advent of digital and low-voltage analog systems in NPPs. These systems have the potential to be more vulnerable than older analog systems to the resulting power surges and electromagnetic interference (EMI) when lightning strikes facilities or power lines. This paper discusses the technical basis for guidance to licensees and applicants covered in Regulatory Guide (RG) 1.204, Guidelines for Lightning Protection of Nuclear Power Plants, issued August 2005. RG 1.204 describes guidance for practices that are acceptable to the NRC staff for protecting nuclear power structures and systems from direct lightning strikes and the resulting secondary effects.

  1. Fire protection maintenance at Browns Ferry Nuclear Plant

    International Nuclear Information System (INIS)

    Kern, J.R.

    1989-01-01

    This paper describes two approaches to staffing and organizing a fire protection maintenance group. Both have been used at Browns Ferry Nuclear Plant. One takes traditional craft functions and relocates them from the plant maintenance department to the fire protection section. The other expands the role to include response to fire, medical, and hazardous material emergencies. Both approaches remove the fire protection supervisor from a purely staff role, and involve him/her in direct-line management functions. This results in improved technical direction to the craftsmen, improved quality of the work performed, and improved craft morale. It also assures the fire protection supervisor of much more detailed knowledge of the overall status of the fire protection systems

  2. Computer Security: Protect your plant: a "serious game" about control system cyber-security

    CERN Multimedia

    Stefan Lueders, Computer Security Team

    2015-01-01

    Control system cyber-security is attracting increasing attention: from cybercriminals, from the media and from security researchers.   After the legendary “Stuxnet” attacks of 2010 against an Iranian uranium enrichment plant, the infiltration of Saudi Aramco in 2012, and most recently the hacking of German blast furnaces, we should be prepared. Just imagine what would happen if hackers turned off the lights in Geneva and the Pays-de-Gex for a month? (“Hacking control systems, switching lights off!"). Or if attackers infiltrated CERN’s accelerator or experiment control systems and stopped us from pursuing our core business: delivering beams and recording particle collisions (“Hacking control systems, switching... accelerators off?"). Now you can test your ability to protect an industrial plant against cyber-threats! The Computer Security Team, in collaboration with Kaspersky Lab, is organising a so-...

  3. Radio protective effects of some medicinal plants

    International Nuclear Information System (INIS)

    Barupal, G.K.

    2012-01-01

    Many plants are known to have beneficial therapeutic effects as noted in the traditional Indian system of medicine, Ayurveda and used since time immemorial for curing diseases. Even today, nearly 70% of the world's population is dependent on plants for handling their health related problems and plants have been utilized successfully for the treatment of free radical-mediated diseases in human such as Rheumatoid arthritis, Atherosclerosis, Cancer, Alzheimer's disease, Parkinson's disease, aging and several other conditions including inflammatory diseases. Plant extracts eliciting radio protective efficacy contain a plethora of compounds including antioxidants, immunostimulants, cell proliferation stimulators, anti-inflammatory and antimicrobial agent, some of which may act in isolation as well as in combination with other constituents from the same plants. Glycyrrhiza glabra, Allium sepa, Allium sativum, Aloe arborescens, Amaranthus paniculatus, Curcuma longa, Moringa olefera and Syzygium cumini are some important radio protective plants. Alium sativum has been reported to possess antioxidant antimicrobial, antitumor, antimutagenic and anti-inflammatory properties. Aloe arborescens acts as a cell proliferate, healer and allergy reducer. Amaranthus paniculatus is used for purifying blood and treating scrofulous sores. Curcuma longa is widely used in antitumor and antibacterial activities. Leaf extract of Moringa oleifera is significantly used in nervous debility and healing of wound. Chlorella is well known nutrient dense superfood that contains 60% protein, 18 amino acids (including all the essential amino acids), more than 20 vitamins and minerals. Chlorell has been used to treat cancer and also protect the body from the effects of cancer radiation treatment due to its chlorophyll in abundance level. However they have little attention for their radio protective as well as antioxidant. There is an urgent need to develop newer, more efficient and reliable bioassays

  4. Power system protection

    International Nuclear Information System (INIS)

    Venkata, S.S.; Damborg, M.J.; Jampala, A.K.

    1991-01-01

    Power systems of the 21st century will be more modern, and complex, utilizing the latest available technologies. At the same time, generating plants will have to operate with minimal spinning margins and energy transportation has to take place at critical levels due to environmental and economical constraints. These factors dictate that the power systems be protected with optimum sensitivity, selectivity and time of operation to assure maximum reliability, and security at minimal cost. With an increasing role played by digital computers in every aspect of protection, it is important to take a critical and fresh look at the art and science of relaying and protection. The main objective of this paper is to review the past, present and future of power system protection from a software point of view

  5. Separation review program for reactor protection system and engineered safeguard systems in a nuclear power plant

    International Nuclear Information System (INIS)

    Lamb, F.J.; Walrod, B.E.

    1980-01-01

    This review program is utilized during the design of a nuclear power plant to insure separation between interdiscipline design for the Reactor Protection System (RPS) and Engineered Safeguard Systems (ESS). Color coded transparent drawings of the RPS and ESS are produced by each discipline. The separation is then reviewed by overlaying drawings of different disciplines on a light table. When this inspection shows that RPS or ESS elements have less than the established minimum separation, an analysis is performed to determine what, if any, design revision is necessary to insure proper separation. ''Hazard'' drawings are also made for determination of each type of potential hazard in each area of the plant. The review is a continuing process as the design progresses and is revised by any discipline. 5 refs

  6. Fire protection of nuclear power plant cable ducts

    International Nuclear Information System (INIS)

    Kandrac, J.; Lukac, L.

    1987-01-01

    Fire protection of cable ducts in the Bohunice and Dukovany V-2 nuclear power plants is of a fourtier type. The first level consists in preventive measures incorporated in the power plant design and layout. The second level consists in early detection and a quick repressive action provided by an electric fire alarm system and a stationary spray system, respectively. Fire partitions and glands represent the third level while special spray, paint and lining materials represent the fourth level of the protection. Briefly discussed are the results of an analysis of the stationary spray system and the effects reducing the efficiency of a fire-fighting action using this system. The analysis showed the need of putting off cable duct fires using mobile facilities in case the stationary spray system cannot cope any longer. (Z.M.). 3 figs., 2 refs

  7. Nuclear plant-aging research on reactor protection systems

    International Nuclear Information System (INIS)

    Meyer, L.C.

    1988-01-01

    This report presents the rsults of a review of the Reactor Trip System (RTS) and the Engineered Safety Feature Actuating System (ESFAS) operating experiences reported in Licensee Event Reports (LER)s, the Nuclear Power Experience data base, Nuclear Plant Reliability Data System, and plant maintenance records. Our purpose is to evaluate the potential significance of aging, including cycling, trips, and testing as contributors to degradation of the RTS and ESFAS. Tables are presented that show the percentage of events for RTS and ESFAS classified by cause, components, and subcomponents for each of the Nuclear Steam Supply System vendors. A representative Babcock and Wilcox plant was selected for detailed study. The US Nuclear Regulatory Commission's Nuclear Plant Aging Research guidelines were followed in performing the detailed study that identified materials susceptible to aging, stressors, environmental factors, and failure modes for the RTS and ESFAS as generic instrumentation and control systems. Functional indicators of degradation are listed, testing requirements evaluated, and regulatory issues discussed

  8. Ageing study of protection automation components of Olkiluoto nuclear power plant

    International Nuclear Information System (INIS)

    Simola, K.; Haenninen, S.

    1993-07-01

    A study on ageing of reactor protection system of the Olkiluoto nuclear power plant is described. The objective of the study was to present an ageing analysis approach and apply in to the automation chains of reactor protection system of the Olkiluoto nuclear power plant. The study includes the measuring instrumentation, the protection logics, and the control electronics of some pumps and valves. The analysis is based on the information collected on the structure of the system, environmental conditions and maintenance practices of components, and operating experience. Based on this information, the possible ageing effects of equipment and their safety significance are evaluated. (orig.). (15 refs., 16 figs., 12 tabs.)

  9. Safety guide on fire protection in nuclear power plants

    International Nuclear Information System (INIS)

    1976-01-01

    The purpose of the Safety Guide is to give specific design and operational guidance for protection from fire and explosion in nuclear power plants, based on the general guidance given in the relevant sections of the 'Safety Code of Practice - Design' and the 'Safety Code of Practice - Operation' of the International Atomic Energy Agency. The guide will confine itself to fire protection of safety systems and items important to safety, leaving the non-safety matters of fire protection in nuclear power plants to be decided upon the basis of the various available national and international practices and regulations. (HP) [de

  10. Wind Power Plant Grounding, Overvoltage Protection, and Insulation Coordination

    Energy Technology Data Exchange (ETDEWEB)

    Camm, E H [IEEE PES Wind Plant Collector System Design Working Group; Behnke, M. R. [IEEE PES Wind Plant Collector System Design Working Group; Bolado, O. [IEEE PES Wind Plant Collector System Design Working Group; Bollen, M. [IEEE PES Wind Plant Collector System Design Working Group; Bradt, M. [IEEE PES Wind Plant Collector System Design Working Group; Brooks, C. [IEEE PES Wind Plant Collector System Design Working Group; Dilling, W. [IEEE PES Wind Plant Collector System Design Working Group; Edds, M. [IEEE PES Wind Plant Collector System Design Working Group; Hejdak, W. J. [IEEE PES Wind Plant Collector System Design Working Group; Houseman, D. [IEEE PES Wind Plant Collector System Design Working Group; Klein, S. [IEEE PES Wind Plant Collector System Design Working Group; Li, Fangxing [ORNL; Li, J. [IEEE PES Wind Plant Collector System Design Working Group; Maibach, P. [IEEE PES Wind Plant Collector System Design Working Group; Nicolai, T. [IEEE PES Wind Plant Collector System Design Working Group; Pasupulati, S. V. [IEEE PES Wind Plant Collector System Design Working Group; Patino, J. [IEEE PES Wind Plant Collector System Design Working Group; Samaan, N. [IEEE PES Wind Plant Collector System Design Working Group; Saylors, S. [IEEE PES Wind Plant Collector System Design Working Group; Siebert, T. [IEEE PES Wind Plant Collector System Design Working Group; Smith, Travis M [ORNL; Starke, Michael R [ORNL; Walling, R. [IEEE PES Wind Plant Collector System Design Working Group

    2009-01-01

    Proper insulation coordination is critical to achieving expected life from wind plant equipment. The collector systems of large wind plants require the application of surge arresters to protect the equipment insulation from transient overvoltages. The application of surge arresters is constrained by maximum operating and temporary overvoltage levels. This paper provides a tutorial description of the process of selecting and applying surge arresters to wind plant medium voltage collector systems, with emphasis on the peculiar properties of this application.

  11. Computerized reactor protection and safety related systems in nuclear power plants. Proceedings of a specialists' meeting. Working material

    International Nuclear Information System (INIS)

    1998-01-01

    Though the majority of existing control and protection systems in nuclear power plants use old analogue technology and design philosophy, the use of computers in safety and safety related systems is becoming a current practice. The Specialists Meeting on ''Computerized Reactor Protection and Safety Related Systems in Nuclear Power Plants'' was organized by IAEA (jointly by the Division of Nuclear Power and the Fuel Cycle and the Division of Nuclear Installation Safety), in co-operation with Paks Nuclear Power Plant in Hungary and was held from 27-29 October 1997 in Budapest, Hungary. The meeting focused on computerized safety systems under refurbishment, software reliability issues, licensing experiences and experiences in implemented computerized safety and safety related systems. Within a meeting programme a technical visit to Paks NPP was organized. The objective of the meeting was to provide an international forum for the presentation and discussion on R and D, in-plant experiences in I and C important to safety, backfits and arguments for and reservations against the digital safety systems. The meeting was attended by 70 participants from 16 countries representing NPPs and utility organizations, design/engineering, research and development, and regulatory organizations. In the course of 4 sessions 25 technical presentations were made. The present volume contains the papers presented by national delegates and the conclusions drawn from the final general discussion

  12. Forum for fire protection and safety in power plants[Norway

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2005-07-01

    The conference contains 16 presentations on topics in the fields of fire protection and safety in plants in Western Norway, reorganization and reconstruction of power systems and plants in Norway, various aspects of risk and vulnerability analysis, technological aspects of plant management and construction and problems and risks with particularly transformers. Some views on challenges of the fire departments and the new Norwegian regulations for electrical power supply systems are included. One presentation deals with challenges for Icelandic power production plants.

  13. Environmental protection in thermal power plants

    International Nuclear Information System (INIS)

    1987-01-01

    This workbook is a compilation of the most important facts and data that are relevant today for environmental protection in thermal power plants. Unlike the other issues the text is not in the form of a random collection of data but in the form of a complete presentation. Possible elaboration projects for pupils can be easily derived from the individual sections. These deal with: the discussion about environmental protection; forest decline; sources of emission; nuisances in the Federal Republic of Germany; environmental protection in fossil-fuel power plants - clean air - cooling water utilization and water protection - noise; environmental protection in nuclear power plants - radioactive material produced in nuclear reactors and the retention of such materials - radioactive waste materials - monitoring of radioactive emissions; accessory materials and hints. (orig./HSCH) [de

  14. Developments in power plant cooling systems

    International Nuclear Information System (INIS)

    Agarwal, N.K.

    1993-01-01

    A number of cooling systems are used in the power plants. The condenser cooling water system is one of the most important cooling systems in the plant. The system comprises a number of equipment. Plants using sea water for cooling are designed for the very high corrosion effects due to sea water. Developments are taking place in the design, materials of construction as well as protection philosophies for the various equipment. Power optimisation of the cycle needs to be done in order to design an economical system. Environmental (Protection) Act places certain limitations on the effluents from the plant. An attempt has been made in this paper to outline the developing trends in the various equipment in the condenser cooling water systems used at the inland as well as coastal locations. (author). 5 refs., 6 refs

  15. Protection and environmental supervision activities at ROMAG PROD Plant

    International Nuclear Information System (INIS)

    Chilom, Rodica

    2002-01-01

    The protection and environmental supervision activity at ROMAG PROD heavy water plant is embodied in the very production process. The environmental supervision is done by: 1. the sensing system for H 2 S which monitors H 2 S and other gases 24 h/day on three zones of production storage and transport of H 2 S; 2. daily tightness checking of the installations working with H 2 S; 3. daily analytical checking of the air and water pollutants at seven air sampling checking points in dwelled zones, at the industrial area boundary and at purification stations and water waste discharge points. The water and air environmental components are protected through safe operation of the heavy water installations and of the flue gas installation. The water protection is ensured through optimal operation of the purification facilities, namely: the purification of the water resulting from the isotopic exchange; acid water neutralization station which process the waste water collected from the whole plant; neutralization reservoir for water resulting from ionic exchange; purification station of the sulfate waters resulting from the H 2 S fabrications installation; mud pool. The ROMAG PROD Plant operates according to the ISO 9001 and ISO 14001 standards and reports regularly its activity to the Environmental Protection and Water System Management Authority

  16. A Cause-Consequence Chart of a Redundant Protection System

    DEFF Research Database (Denmark)

    Nielsen, Dan Sandvik; Platz, O.; Runge, B.

    1975-01-01

    A cause-consequence chart is applied in analysing failures of a redundant protection system (a core spray system in a nuclear power plant). It is shown how the diagram provides a basis for calculating two probability measures for malfunctioning of the protection system. The test policy of compone...... of components is taken into account. The possibility of using parameter variation as a basis for the choice of test policy is indicated.......A cause-consequence chart is applied in analysing failures of a redundant protection system (a core spray system in a nuclear power plant). It is shown how the diagram provides a basis for calculating two probability measures for malfunctioning of the protection system. The test policy...

  17. Oak Ridge Y-12 Plant groundwater protection program management plan

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1996-06-01

    The Oak Ridge Y- 1 2 Plant (Y-12 Plant) is owned by the United States Department of Energy (DOE) and managed by Lockheed Martin Energy Systems, Inc. (Energy Systems) under contract No. DE-AC05-84OR21400. The Y-12 Plant Groundwater Protection Program (GWPP), which was initiated in 1975, provides for the protection of groundwater resources consistent with Federal, State, and local regulations, and in accordance with DOE orders and Energy Systems policies and procedures. The Y-12 Plant is located in Anderson County, Tennessee, and is within the corporate limits of the City of Oak Ridge. The Y-12 Plant is one of three major DOE complexes that comprise the 37,000-acre Oak Ridge Reservation (ORR) located in Anderson and Roane counties. The Y-12 Plant is located in Bear Creek Valley at an elevation of about 950 feet (ft) above sea level. Bear Creek Valley is bounded on the northwest and southeast, and is isolated from populated areas of Oak Ridge, by parallel ridges that rise about 300 ft above the valley floor. The Y-12 Plant and its fenced buffer area are about 0.6 mile wide by 3.2 miles long and cover approximately 4,900 acres. The main industrialized section encompasses approximately 800 acres.

  18. Oak Ridge Y-12 Plant groundwater protection program management plan

    International Nuclear Information System (INIS)

    1996-06-01

    The Oak Ridge Y- 1 2 Plant (Y-12 Plant) is owned by the United States Department of Energy (DOE) and managed by Lockheed Martin Energy Systems, Inc. (Energy Systems) under contract No. DE-AC05-84OR21400. The Y-12 Plant Groundwater Protection Program (GWPP), which was initiated in 1975, provides for the protection of groundwater resources consistent with Federal, State, and local regulations, and in accordance with DOE orders and Energy Systems policies and procedures. The Y-12 Plant is located in Anderson County, Tennessee, and is within the corporate limits of the City of Oak Ridge. The Y-12 Plant is one of three major DOE complexes that comprise the 37,000-acre Oak Ridge Reservation (ORR) located in Anderson and Roane counties. The Y-12 Plant is located in Bear Creek Valley at an elevation of about 950 feet (ft) above sea level. Bear Creek Valley is bounded on the northwest and southeast, and is isolated from populated areas of Oak Ridge, by parallel ridges that rise about 300 ft above the valley floor. The Y-12 Plant and its fenced buffer area are about 0.6 mile wide by 3.2 miles long and cover approximately 4,900 acres. The main industrialized section encompasses approximately 800 acres

  19. Status of physical protection systems of nuclear facilities; survey report

    International Nuclear Information System (INIS)

    Hwang, In Koo; Kwack, Eun Ho; Ahn, Jin Soo; Lee, Hyun Chul; Kim, Jung Soo

    2002-02-01

    This report presents a survey on the physical protection equipment for a nuclear power plant. This survey was conducted by Korea Atomic Energy Research Institute as a part of the project, 'Development of Technologies for National Control of and Accountancy for Nuclear Material,' funded by the Ministry of Science and Technology of Korea. A physical protection system of a nuclear plant includes outer and inner fences, intrusion detection sensors, alarm generation system, illumination equipment, central monitoring and control station, entry control and management system, etc. The outermost fence indicates the boundary of the plant area and prevents a simple or unintentional intrusion. The inner fence area of each plant unit associated with intrusion detection sensors, illuminators, monitoring cameras, serves the key role for physical protection function for the nuclear plant

  20. Applications of cathodic protection for the protection of aqueous and soil corrosion of power plant components

    International Nuclear Information System (INIS)

    Sinha, A.K.; Mitra, A.K.; Bhakta, U.C.; Sanyal, S.K.

    2000-01-01

    Power plant components exposed to environments such as water and soil are susceptible to severe corrosion. Many times the effect of corrosion in power plant components can be catastrophic. The problem is aggravated for underground pipelines due to additional factors such as large network of pipelines, proximity to earth mat, high voltage transmission lines, corrosive chemicals, inadequate approach etc. Other components such as condenser water boxes, internals of pipelines, clarifier bridge structures, cooling water inlet gates and pipes etc. which are in continuous contact with water, are subjected to severe corrosion. The nature and locations of all such components are at places which are not accessible for routine maintenance and hence they require long term reliable protection against corrosion. Experience has shown that anti-corrosive coatings are inadequate in preventing corrosion and due to their location regular maintenance coatings are also not feasible. Under such circumstances the applications of cathodic protection provides a long term solution the design of cathodic protection, for such applications differs from the commonly employed cathodic protection for cross-country pipelines and submerged structures due to other complexities in the plant region and maintenance of the applied system. The present paper intends to discuss the applications of cathodic protection with suitable anti-corrosive coatings for protection of various power plant components and the specific features of each type of application. (author)

  1. Relay Protection Coordination for Photovoltaic Power Plant Connected on Distribution Network

    OpenAIRE

    Nikolovski, Srete; Papuga, Vanja; Knežević, Goran

    2014-01-01

    This paper presents a procedure and computation of relay protection coordination for a PV power plant connected to the distribution network. In recent years, the growing concern for environment preservation has caused expansion of photovoltaic PV power plants in distribution networks. Numerical computer simulation is an indispensable tool for studying photovoltaic (PV) systems protection coordination. In this paper, EasyPower computer program is used with the module Power Protector. Time-curr...

  2. LMFBR plant design features for sodium spill and fire protection

    International Nuclear Information System (INIS)

    Palm, R.E.

    1982-01-01

    Design features have been developed for an LMFBR plant to protect the concrete structures from potential liquid spills and fires and prevent sodium-concrete reactions. The inclusion of these features in the plant design reduces the severity of design basis accident conditions imposed on containment and other critical plant structures. Steel liners are provided in cells containing radioactive sodium systems, and catch pans are located in non-radioactive sodium system cells. The design requirements and descriptions of each of these protective features are presented. The loading conditions, analytical approach and numerical results are also included. Design of concrete cell structures that are subject to high temperature effects from sodium spills is discussed. The structural design considers the influence of high temperature on design properties of concrete and carbon steel materials based on results of a comprehensive test program. The development of these design features and high temperature design considerations for the Clinch River Breeder Reactor Plant (CRBRP) are presented in this paper

  3. Design of reactor protection systems for HTR plants generating electric power and process heat problems and solutions

    International Nuclear Information System (INIS)

    Craemer, B.; Dahm, H.; Spillekothen, H.G.

    1982-06-01

    The design basis of the reactor protection system (RPS) for HTR plants generating process heat and electric power is briefly described and some particularities of process heat plants are indicated. Some particularly important or exacting technical measuring positions for the RPS of a process heat HTR with 500 MWsub(th) power (PNP 500) are described and current R + D work explained. It is demonstrated that a particularly simple RPS can be realized in an HTR with modular design. (author)

  4. Fire protection at nuclear power plants

    International Nuclear Information System (INIS)

    1999-11-01

    The guide presents specific requirements for the design and implementation of fire protection arrangements at nuclear power plants and for the documents relating to the fire protection that are to be submitted to STUK (Finnish Radiation and Nuclear Safety Authority). Inspections of the fire protection arrangements to be conducted by STUK during the construction and operation of the power plants are also described in this guide. The guide can also be followed at other nuclear facilities

  5. Corrosion protection pays off for coal-fired power plants

    Energy Technology Data Exchange (ETDEWEB)

    Hansen, T.

    2006-11-15

    Zinc has long been used to hot-dip galvanise steel to deliver protection in harsh environments. Powder River Basin or eastern coal-fired plants benefit from using galvanized steel for conveyors, vibratory feeders, coal hoppers, chutes, etc. because maintenance costs are essentially eliminated. When life cycle costs for this process are compared to an alternative three-coal paint system for corrosion protection, the latter costs 5-10 times more than hot-dip galvanizing. An AEP Power Plant in San Juan, Puerto Rico and the McDuffie Coal Terminal in Mobile, AL, USA have both used hot-dip galvanized steel. 1 fig., 1 tab.

  6. Improved design architecture to minimize functional complexity of plant protection system for nuclear power plant

    Energy Technology Data Exchange (ETDEWEB)

    Jung, JaeCheon, E-mail: jcjung@kings.ac.kr

    2016-12-01

    An improved design architecture method to minimize the functional complexity of PPS (Plant Protection System) is proposed in this work. Firstly, the design concerns are identified with both AHP (Analytic Hierarchy Process) analysis. AHP is able to identify the source of design concerns using pairwise comparison. AHP result shows CCF is the primary concern and the complexity is the secondly. Even though complexity is the second largest concern to the effectiveness of digital I&C system, but it has not been highlighted as CCF. This is the reason why this work focuses on the sources of complexity to maximize the effectiveness of digital system in the viewpoint of design architecture. The proposed methods are, separating non-safety functions from bistable logics and simplifying communication links and network. In order to verify the new concept, EFFBD (Enhanced Functional Flow Block Diagram) models are developed for two bistable logics of PPS and the complexities are measured using Halstead’s program maintainability measures. This measure specifies what provokes functional complexity. Periodic testing and operating bypass function are the source of complexity in this analysis.

  7. Improved design architecture to minimize functional complexity of plant protection system for nuclear power plant

    International Nuclear Information System (INIS)

    Jung, JaeCheon

    2016-01-01

    An improved design architecture method to minimize the functional complexity of PPS (Plant Protection System) is proposed in this work. Firstly, the design concerns are identified with both AHP (Analytic Hierarchy Process) analysis. AHP is able to identify the source of design concerns using pairwise comparison. AHP result shows CCF is the primary concern and the complexity is the secondly. Even though complexity is the second largest concern to the effectiveness of digital I&C system, but it has not been highlighted as CCF. This is the reason why this work focuses on the sources of complexity to maximize the effectiveness of digital system in the viewpoint of design architecture. The proposed methods are, separating non-safety functions from bistable logics and simplifying communication links and network. In order to verify the new concept, EFFBD (Enhanced Functional Flow Block Diagram) models are developed for two bistable logics of PPS and the complexities are measured using Halstead’s program maintainability measures. This measure specifies what provokes functional complexity. Periodic testing and operating bypass function are the source of complexity in this analysis.

  8. Operational, control and protective system transient analyses of the closed-cycle GT-HTGR power plant

    International Nuclear Information System (INIS)

    Openshaw, F.L.; Chan, T.W.

    1980-07-01

    This paper presents a description of the analyses of the control/protective system preliminary designs for the gas turbine high-temperature gas-cooled reactor (GT-HTGR) power plant. The control system is designed to regulate reactor power, control electric load and turbine speed, control the temperature of the helium delivered to the turbines, and control thermal transients experienced by the system components. In addition, it provides the required control programming for startup, shutdown, load ramp, and other expected operations. The control system also handles conditions imposed on the system during upset and emergency conditions such as loop trip, reactor trip, or electrical load rejection

  9. Hazard rate for a two-channel protective system subject to a high demand rate

    International Nuclear Information System (INIS)

    Oliveira, L.F.; Youngblood, R.; Melo, P.F.F.

    1989-01-01

    A basic figure of merit associated with a protective system for an industrial plant is the number of accidents expected to occur in the plant within a given period of time, with the system installed. By definition, in a plant equipped with a protective system, an accident can only happen if an initiating event (a demand) occurs while the protective system is unavailable, that is, while it is in one of its possible failed states. This means that the hazard rate or accident frequency depends on the demand rate and on the unavailability of the protective systems. It has long been recognized that the demand rate influences the unavailability of the protective system, and practical expressions incorporating that effect have been developed for single-channel (Lees, 1982) and multi-channel (Kumamoto and Henley 1978) protective systems. The effect has also been incorporated into a Markovian treatment of a plant protection system (Papazoglou and Cho, 1985). In a previous paper (Oliveira and Netto, 1987) a Markovian approach was used to derive analytical expressions for the evaluation of the plant hazard rate for a single-channel protective system, properly accounting for the effects of the demand and the repair rates. In this paper the authors present an extension of that model to the case of a plant equipped with a two-channel protective system

  10. Protective role of plants against harmful radiation

    Energy Technology Data Exchange (ETDEWEB)

    Gautam, Shreesh Kumar; Kumar, Pawan; Singh, Abhishek; Kumar, Vikas; Bharti, Navaldey [Department of Applied Plant Science-Horticulture, Babasaheb Bhimrao Ambedkar University, Lucknow (India)

    2012-07-01

    The rapid technological advancement has increased human exposure to ionizing radiations enormously. Ionizing radiations produces deleterious effects in the living organisms. Widespread use of radiation in diagnosis therapy, industry, energy sector and inadvertent exposure during air and space travel, nuclear accidents and nuclear terror attacks requires safeguard against human exposures. Lead shielding and other physical measures can be used in such situations but with difficulty to manage; thus pharmacological intervention could be the most prudent strategy to protect humans against the harmful effect of ionizing radiations. These pharmacological agents are radioprotectives; The development of radioprotective agents has been the subject of intense research in view of their potential for use within a radiation environment. However, no ideal, safe synthetic radio protectors are available to date, so the search for alternative sources including plants has been ongoing. In Ayurveda, the traditional Indian system of medicine, several plants have been used to treat free radical-mediated ailments and, therefore, it is logical to expect that such plants may also render some protection against radiation damage. This all is due to antioxidant enzymes, nitroxides, and melatonin, antiemetic, anti-inflammatory. haemopoitic and immunostimulant compounds. Some of the plants which are found to be radioprotective are Centella asiatica, Ginkgo biloba, Hippophae rhamnoides, Ocimum sanctum, Podophyllurn hexandrum, Tinospora cordifolia, Emblica officinalis, Phyllanthus amarus, etc. So there is an urgent need to identify and characterize the many of the plants in relation to the radioprotection. Besides these medicinal plants there are also some fruits and vegetables which are having good response against harmful radiations such as Kiwifruit Actinidia deliciosa (Actinidaceae), Cape Gooseberry Physalis peruviana (Solanaceae). They protect against the radiation-induced damage by

  11. Protective role of plants against harmful radiation

    International Nuclear Information System (INIS)

    Gautam, Shreesh Kumar; Kumar, Pawan; Singh, Abhishek; Kumar, Vikas; Bharti, Navaldey

    2012-01-01

    The rapid technological advancement has increased human exposure to ionizing radiations enormously. Ionizing radiations produces deleterious effects in the living organisms. Widespread use of radiation in diagnosis therapy, industry, energy sector and inadvertent exposure during air and space travel, nuclear accidents and nuclear terror attacks requires safeguard against human exposures. Lead shielding and other physical measures can be used in such situations but with difficulty to manage; thus pharmacological intervention could be the most prudent strategy to protect humans against the harmful effect of ionizing radiations. These pharmacological agents are radioprotectives; The development of radioprotective agents has been the subject of intense research in view of their potential for use within a radiation environment. However, no ideal, safe synthetic radio protectors are available to date, so the search for alternative sources including plants has been ongoing. In Ayurveda, the traditional Indian system of medicine, several plants have been used to treat free radical-mediated ailments and, therefore, it is logical to expect that such plants may also render some protection against radiation damage. This all is due to antioxidant enzymes, nitroxides, and melatonin, antiemetic, anti-inflammatory. haemopoitic and immunostimulant compounds. Some of the plants which are found to be radioprotective are Centella asiatica, Ginkgo biloba, Hippophae rhamnoides, Ocimum sanctum, Podophyllurn hexandrum, Tinospora cordifolia, Emblica officinalis, Phyllanthus amarus, etc. So there is an urgent need to identify and characterize the many of the plants in relation to the radioprotection. Besides these medicinal plants there are also some fruits and vegetables which are having good response against harmful radiations such as Kiwifruit Actinidia deliciosa (Actinidaceae), Cape Gooseberry Physalis peruviana (Solanaceae). They protect against the radiation-induced damage by

  12. Reactor protection system design using micro-computers

    International Nuclear Information System (INIS)

    Fairbrother, D.B.

    1977-01-01

    Reactor Protection Systems for Nuclear Power Plants have traditionally been built using analog hardware. This hardware works quite well for single parameter trip functions; however, optimum protection against DNBR and KW/ft limits requires more complex trip functions than can easily be handled with analog hardware. For this reason, Babcock and Wilcox has introduced a Reactor Protection System, called the RPS-II, that utilizes a micro-computer to handle the more complex trip functions. This paper describes the design of the RPS-II and the operation of the micro-computer within the Reactor Protection System

  13. Reactor protection system design using micro-computers

    International Nuclear Information System (INIS)

    Fairbrother, D.B.

    1976-01-01

    Reactor protection systems for nuclear power plants have traditionally been built using analog hardware. This hardware works quite well for single parameter trip functions; however, optimum protection against DNBR and KW/ft limits requires more complex trip functions than can easily be handled with analog hardware. For this reason, Babcock and Wilcox has introduced a Reactor Protection System, called the RPS-II, that utilizes a micro-computer to handle the more complex trip functions. The paper describes the design of the RPS-II and the operation of the micro-computer within the Reactor Protection System

  14. INTEGRATED SYSTEMS IN PLANT PROTECTION MANAGEMENT: FIRE BLIGHT OF ROSACEOUS PLANTS (Erwinia amylovora (Burrill - Winslow IN AN APPLE ORCHARD IN SIBIU COUNTY

    Directory of Open Access Journals (Sweden)

    Maria TĂNASE

    2013-12-01

    Full Text Available Integrated protection represents a modern approach, denoting a protection strategy of agro-ecosystems; and it represents a complex system employing all appropriate methods in a manner as consistent and smooth as possible, in order to maintain the biocenotic balance of agrosystems and to keep pathogens at a level at which they do not cause economic damage (so-called level of eco-efficiency. A biocenotic approach to issues of agrosystem protection against disease attack requires an acknowledgement of all aspects regarding the evolution of pests in time and space, so as to be able to intervene at the right time with all possible means. And such protection measures are not supposed to restrain existing tendencies in the agrosystem. Therefore, this implies the awareness that any applied protection measures do not affect solely a certain pathogen, but the entire plant and animal community, as well as the soil and water.

  15. Evaluation of Applicability for the Core Protection Method with 4-Channel CEA Positions to OPR-1000 Plants

    International Nuclear Information System (INIS)

    Koo, B. S.; Cho, J. Y.; Song, J. S.

    2008-05-01

    To increase the applicability of research results established during the process of integral reactor development program, a new core protection method with 4-channel CEA positions was applied to the domestic commercial plants and its feasibility was evaluated. To achieve above object, state-of-the-art related to core protection system was analyzed as followings: - Unusual CPC operating experience in Korea - Evaluate the proposals of CPC improvement suggested by CPC Task Force Team - Review the conventional CPC used in Yonggwang and Ulchin plants - Review the Common-Q CPC to be implemented in Shin-Kori Units 1 and 2 - Evaluate the SENTINEL core protection system in US and COPS core protection system in Germany - Examine the applied patents in Korea, US and Japan - Analyze the copyright for computer programs used in core protection system design and license agreement for PWR technology between Westinghouse and Korea. In addition, study for the formation of system, design requirement, algorithm improvement and enhancement of operator interface was performed to apply the newly suggested core protection method to the commercial plants. By adopting this method, it is expected that unnecessary channel of reactor trips will be decreased considerably. Although change of system including CEA must be set forth as a prerequisite to apply this method to the domestic commercial plants as well as scheduled plants, this study suggests the strategy and direction for the development of core protection system in domestic. This study, moreover, will provide the valuable information as a basic data in establishing the detailed development plan for the advanced core protection system in the future

  16. Recent digital control and protection retrofits in power plants

    International Nuclear Information System (INIS)

    Fournier, R.D.; Hammer, M.; Smith, J.E.

    1987-01-01

    Digital computers are now being retrofitted to all types of power plants, replacing analog equipment and solving problems such as equipment obsolescence and low reliability. Three diverse examples of retrofits are presented in this paper, representing trends in man/machine interface design at an oil-fired plant, protection system in pressurized heavy-water reactors, and control systems in light water reactors (LWRs). The examples have been chosen to illustrate diverse reasons for the retrofits and the benefits derived. The cases presented report retrofits at Northern States Power's Monticello boiling water reactor, New Brunswick Electric Power Commission's (NBEPC's) Point Lepreau Nuclear Generating Station, and finally NBEPC's oil-fired plant at Courtney Bay

  17. Expert systems for protective monitoring of facilities

    International Nuclear Information System (INIS)

    Carr, K.R.

    1987-01-01

    In complex plants, the possibility of serious operator error always exists to some extent, but, this can be especially true during an experiment or some other unusual exercise. Possible contributing factors to operational error include personnel fatigue, misunderstanding in communication, mistakes in executing orders, uncertainty about the delegated authority, pressure to meet a demanding schedule, and a lack of understanding of the possible consequences of deliberate violations of the facility's established operating procedures. Authoritative reports indicate that most of these factors were involved in the disastrous Russian Chernobyl-4 nuclear reactor accident in April 1986, which, ironically, occurred when a safety experiment was being conducted. Given the computer hardware and software now available for implementing expert systems together with integrated signal monitoring and communications, plant protection could be enhanced by an expert system with extended features to monitor the plant. The system could require information from the operators on a rigidly enforced schedule and automatically log in and report on a scheduled time basis to authorities at a central remote site during periods of safe operation. Additionally, the system could warn an operator or automatically shut down the plant in case of dangerous conditions, while simultaneously notifying independent, responsible, off-site personnel of the action taken. This approach would provide protection beyond that provided by typical facility scram circuits. This paper presents such an approach to implementing an expert system for plant protection, together with specific hardware and software configurations. The Chernobyl accident is used as the basis of discussion

  18. Fire protection in nuclear power plants

    International Nuclear Information System (INIS)

    1992-01-01

    The Code on Design (Safety Series 50-C-D (Rev. 1)) within the NUSS (Nuclear Safety Standards) programme of the IAEA points out the necessity of measures for protecting plant items which are important to safety against fires of internal and external origin. Experience of the past two decades in the operation of nuclear power plants and modern analysis techniques confirm that fire may be a real threat to nuclear safety and should receive adequate attention from the beginning of the design process throughout the life of the plant. Within the framework of the NUSS programme, a Safety Guide on fire protection had therefore been developed to enlarge on the general requirements given in the Code. Since its first publication in 1979, there has been considerable development in protection technology and analysis methods and after the Chernobyl accident it was decided to revise the existing Guide. The present Safety Guide is intended to advise designers, safety assessors and regulators on the concept of fire protection in the design of nuclear power plants and on recommended ways of implementing the concept in some detail in practice. Figs, 1 tab

  19. Software reliability evaluation of digital plant protection system development process using V and V

    International Nuclear Information System (INIS)

    Lee, Na Young; Hwang, Il Soon; Seong, Seung Hwan; Oh, Seung Rok

    2001-01-01

    In the nuclear power industry, digital technology has been introduced recently for the Instrumentation and Control (I and C) of reactor systems. For its application to the safety critical system such as Reactor Protection System(RPS), a reliability assessment is indispensable. Unlike traditional reliability models, software reliability is hard to evaluate, and should be evaluated throughout development lifecycle. In the development process of Digital Plant Protection System(DPPS), the concept of verification and validation (V and V) was introduced to assure the quality of the product. Also, test should be performed to assure the reliability. Verification procedure with model checking is relatively well defined, however, test is labor intensive and not well organized. In this paper, we developed the methodological process of combining the verification with validation test case generation. For this, we used PVS for the table specification and for the theorem proving. As a result, we could not only save time to design test case but also get more effective and complete verification related test case set. Add to this, we could extract some meaningful factors useful for the reliability evaluation both from the V and V and verification combined tests

  20. Official control of plant protection products in Poland: detection of illegal products.

    Science.gov (United States)

    Miszczyk, Marek; Płonka, Marlena; Stobiecki, Tomasz; Kronenbach-Dylong, Dorota; Waleczek, Kazimierz; Weber, Roland

    2018-04-03

    Market presence of illegal and counterfeit pesticides is now a global problem. According to data published in 2012 by the European Crop Protection Association (ECPA), illegal products represent over 10% of the global market of plant protection products. Financial benefits are the main reason for the prevalence of this practice. Counterfeit and illegal pesticides may contain substances that may pose a threat to the environment, crops, animals, and humans, inconsistent with the label and registration dossier. In Poland, action against illegal and counterfeit plant protection products is undertaken by the Main Inspectorate of Plant Health and Seed Inspection (PIORiN), the police, the prosecution, and the pesticide producers. Results of chemical analyses carried out by the Institute of Plant Protection - National Research Institute Sośnicowice Branch, Pesticide Quality Testing Laboratory (PQTL IPP-NRI Sosnicowice Branch) indicate that a majority of illegal pesticides in Poland are detected in the group of herbicides. Products from parallel trade tend to have the most irregularities. This article describes the official quality control system of plant protection products in Poland and presents the analytical methods for testing pesticides suspected of adulteration and recent test results.

  1. Protective underpressure system for nuclear power plants

    International Nuclear Information System (INIS)

    Anon.

    1979-01-01

    A vacuum protection system for a nuclear reactor is described containng the possible accident in the immediate area where it happened. The system uses underpressure in the air-tight primary circuit jacket. Immediately after the accident, part of air is forced out from the area where coolant is being lost to another area which is then separated from the accident area. The desired underpressure is attained by steam condensation. A system diagram is shown and the time-dependent pressure changes in the contained areas are presented. (J.B.)

  2. Mathematical verification of a nuclear power plant protection system function with combined CPN and PVS

    International Nuclear Information System (INIS)

    Koo, Seo Ryong; Son, Han Seong; Seong, Poong Hyun

    1999-01-01

    In this work, an automatic software verification method for Nuclear Power Plant (NPP) protection system is developed. This method utilizes Colored Petri Net (CPN) for system modeling and Prototype Verification System (PVS) for mathematical verification. In order to help flow-through from modeling by CPN to mathematical proof by PVS, an information extractor from CPN models has been developed in this work. In order to convert the extracted information to the PVS specification language, a translator also has been developed. ML that is a higher-order functional language programs the information extractor and translator. This combined method has been applied to a protection system function of Wolsung NPP SDS2 (Steam Generator Low Level Trip). As a result of this application, we could prove completeness and consistency of the requirement logically. Through this work, in short, an axiom or lemma based-analysis method for CPN models is newly suggested in order to complement CPN analysis methods and a guideline for the use of formal methods is proposed in order to apply them to NPP software verification and validation. (author). 9 refs., 15 figs

  3. Radiation protection of population under normal operation conditions of nuclear power plants

    International Nuclear Information System (INIS)

    Kunz, Eh.; Shvets, I.

    1976-01-01

    Evolution of shielding is defined in short; approaches suggested for applying in radiation protection or being used are evaluated and classified. Modern views analysis of a risk of biological irradiation consequences in public approaches to health protection in connection with the technical progress side by side with provision of separate persons protection requires attentin to the nuclear power plants protection optimization. Protection optimization suggests the analysis of separate components of technology and protection systems, used materials and constructive solutions, maintenance rules and operating load with respect to environmental discharge of radioactive products. It is expedient to carry out similtaneously the similar analysis with respect to the nuclear power plant personnel irradiation, as separate measures can affect both personnel and population irradiation [ru

  4. Safety Analysis for Power Reactor Protection System

    International Nuclear Information System (INIS)

    Eisawy, E.A.; Sallam, H.

    2012-01-01

    The main function of a Reactor Protection System (RPS) is to safely shutdown the reactor and prevents the release of radioactive materials. The purpose of this paper is to present a technique and its application for used in the analysis of safety system of the Nuclear Power Plant (NPP). A more advanced technique has been presented to accurately study such problems as the plant availability assessments and Technical Specifications evaluations that are becoming increasingly important. The paper provides the Markov model for the Reactor Protection System of the NPP and presents results of model evaluations for two testing policies in technical specifications. The quantification of the Markov model provides the probability values that the system will occupy each of the possible states as a function of time.

  5. Advanced nuclear control and protection system ANCAP-80

    International Nuclear Information System (INIS)

    Asai, Takashi; Okano, Michihiko; Ishibashi, Kengo; Hasegawa, Masakoto; Fukuda, Hiroyoshi; Hosomichi, Renichi.

    1983-01-01

    Advanced reactor protection systems were developed to improve operational reliability and availability and to ease the burden of operators of Mitsubishi PWR Nuclear Power Stations. (Called ANCAP-80; Advanced Nuclear Control And Protection System) For the PWR plants now being planned and in future plans, Mitsubishi will adopt these systems with the following functional features; (1) Four channel protection logic, (2) Automatic bypass logic, (3) Automatic test provision, (4) Optical isolators. (author)

  6. Upgrading Planning and Executive Strategy for Reactor Protection System and Relative Equipment in Qinshan Nuclear Power Plant

    International Nuclear Information System (INIS)

    Jiang Zuyue

    2010-01-01

    Qinshan Nuclear Power Plant (QNPP) is the first nuclear power plant in China which completed the reactor protection system (RPS) upgrading with new digital safety instrumentation and control (I and C) platform instead of original analog system. At the same time,the nuclear instrumentation system (NIS) was upgraded with the same digital I and C platform. For adapting QNPP's actual engineering situation,the upgrading planning was taken by comprehensively investigating current development and application of digital safety I and C platform in the worldwide scope and by reviewing plant's original systems operation history. The project executive strategy-QNPP's leading role with necessary overseas cooperation and internal technical supports as great as possible, was determined. Some significant factors might influence and restrict the RPS and relative equipment upgrading executive actions in an operating NPP were analyzed.Finally, the engineering feasibility was briefly assessed to recognize the anticipated issues and difficulties and to prepare the relative solutions in advance for the purpose of ensuring the RPS upgrading objectives completely realized. (authors)

  7. Protection of warehouses and plants under capacity constraint

    International Nuclear Information System (INIS)

    Bricha, Naji; Nourelfath, Mustapha

    2015-01-01

    While warehouses may be subjected to less protection effort than plants, their unavailability may have substantial impact on the supply chain performance. This paper presents a method for protection of plants and warehouses against intentional attacks in the context of the capacitated plant and warehouses location and capacity acquisition problem. A non-cooperative two-period game is developed to find the equilibrium solution and the optimal defender strategy under capacity constraints. The defender invests in the first period to minimize the expected damage and the attacker moves in the second period to maximize the expected damage. Extra-capacity of neighboring functional plants and warehouses is used after attacks, to satisfy all customers demand and to avoid the backorders. The contest success function is used to evaluate success probability of an attack of plants and warehouses. A numerical example is presented to illustrate an application of the model. The defender strategy obtained by our model is compared to the case where warehouses are subjected to less protection effort than the plants. This comparison allows us to measure how much our method is better, and illustrates the effect of direct investments in protection and indirect protection by warehouse extra-capacities to reduce the expected damage. - Highlights: • Protection of warehouses and plants against intentional attacks. • Capacitated plant and warehouse location and capacity acquisition problem. • A non-cooperative two-period game between the defender and the attacker. • A method to evaluate the utilities and determine the optimal defender strategy. • Using warehouse extra-capacities to reduce the expected damage

  8. Fault Transient Analysis and Protection Performance Evaluation within a Large-scale PV Power Plant

    Directory of Open Access Journals (Sweden)

    Wen Jinghua

    2016-01-01

    Full Text Available In this paper, a short-circuit test within a large-scale PV power plant with a total capacity of 850MWp is discussed. The fault currents supplied by the PV generation units are presented and analysed. According to the fault behaviour, the existing protection coordination principles with the plant are considered and their performances are evaluated. Moreover, these protections are examined in simulation platform under different operating situations. A simple measure with communication system is proposed to deal with the foreseeable problem about the current protection scheme in the PV power plant.

  9. Aging assessment for active fire protection systems

    International Nuclear Information System (INIS)

    Ross, S.B.; Nowlen, S.P.; Tanaka, T.

    1995-06-01

    This study assessed the impact of aging on the performance and reliability of active fire protection systems including both fixed fire suppression and fixed fire detection systems. The experience base shows that most nuclear power plants have an aggressive maintenance and testing program and are finding degraded fire protection system components before a failure occurs. Also, from the data reviewed it is clear that the risk impact of fire protection system aging is low. However, it is assumed that a more aggressive maintenance and testing program involving preventive diagnostics may reduce the risk impact even further

  10. Coil protection for a utility scale superconducting magnetic energy storage plant

    International Nuclear Information System (INIS)

    Loyd, R.J.; Schoenung, S.M.; Rogers, J.D.; Hassenzahl, W.V.; Purcell, J.R.

    1986-01-01

    Superconducting Magnetic Energy Storage (SMES) is proposed for electric utility load leveling. Attractive costs, high diurnal energy efficiency (≥ 92%), and rapid response are advantages relative to other energy storage technologies. Recent industry-led efforts have produced a conceptual design for a 5000 MWh/1000 MW energy storage plant which is technically feasible at commercially attractive estimated costs. The SMES plant design includes a protection system which prevents damage to the magnetic coil if events require a rapid discharge of stored energy. This paper describes the design and operation of the coil protection system, which is primarily passive and uses the thermal capacity of the coil itself to absorb the stored electromagnetic energy

  11. Biochemical analysis of plant protection afforded by a nonpathogenic endophytic mutant of Colletotrichum magna

    Energy Technology Data Exchange (ETDEWEB)

    Redman, R.S.; Rodriguez, R.J. (Geological Survey, Seattle, WA (United States) Univ. of Washington, Seattle, WA (United States). Dept. of Botany); Clifton, D.R.; Morrel, J.; Brown, G. (Geological Survey, Seattle, WA (United States)); Freeman, S. (Volcani Center, Bet Dagan (Israel). Dept. of Plant Pathology)

    1999-02-01

    A nonpathogenic mutant of Colletotrichum magna (path-1) was previously shown to protect watermelon (Citrullus lanatus) and cucumber (Cucumis sativus) seedlings from anthracnose disease elicited by wild-type C. magna. Disease protection was observed in stems of path-1-colonized cucurbits but not in cotyledons, indicating that path-1 conferred tissue-specific and/or localized protection. Plant biochemical indicators of a localized and systemic (peroxidase, phenylalanine ammonia-lyase, lignin, and salicylic acid) plant-defense response were investigated in anthracnose-resistant and-susceptible cultivars of cucurbit seedlings exposed to four treatments: (1) water (control), (2) path-1 conidia, (3) wild-type conidia, and (4) challenge conditions (inoculation into path-1 conidia for 48 h and then exposure to wild-type conidia). Collectively, these analyses indicated that disease protection in path-1-colonized plants was correlated with the ability of these plants to mount a defense response more rapidly and to equal or greater levels than plants exposed to wild-type C. magna alone. Watermelon plants colonized with path-1 were also protected against disease caused by Colletotrichum orbiculare and Fusarium oxysporum. A model based on the kinetics of plant-defense activation is presented to explain the mechanism of path-1-conferred disease protection.

  12. Updates of the fire protection system of the Juzbado Nuclear Fuel Fabrication Plant; Actualizaciones del Sistema de Proteccion Contra Incendios de la Fabrica de Combustible Nuclear de Juzbado

    Energy Technology Data Exchange (ETDEWEB)

    Dorado, P.; Palomo, J. J.; Romano, A.

    2015-07-01

    The Juzbado Nuclear Fuel Fabrication Plant fire protection system is one of the most important safety system of the plant. Every year, a large part of the annual investment is employed to improve this system, to update its technology, in order to improve detection and extinction capability to minimize fire risk. Over the last few years, several improvement projects have been carried out that focused on fire detection technology update and on optimization of local detectors integration with a centralized control system, as well as on an advanced public address system, which used clear and unambiguous messages improving personnel response to a plant evacuation. Planned projects and those, which are currently under development, focus on improving passive fire protection means as well as fire protection of key emergency response equipment s such as emergency diesel generators and fire extinguishing bombs. (Author)

  13. [Artificial intelligence] AI for protection systems

    Energy Technology Data Exchange (ETDEWEB)

    Aggarwal, R.; Johns, A.

    1997-12-31

    The reliable operation of large power systems with small stability margins is highly dependent on control systems and protection devices. Progress in the field of microprocessor systems and demanding requirements in respect of the performance of protective relays are the reasons for digital device applications to power system protection. The superiority of numeric protection over its analogue alternatives is attributed to such factors as accurate extraction of the fundamental voltage and current components through filtering, functional benefits resulting from multi-processor design and extensive self-monitoring, etc. However, all these reasons have not led to a major impact on speed, sensitivity and selectivity of primary protective relays, and the gains are only marginal; this is so because conventional digital relays still rely on deterministic signal models and a heuristic approach for decision making, so that only a fraction of the information contained within voltage and current signals as well as knowledge about the plant to be protected is used. The performance of digital relays may be substantially improved if the decision making is based on elements of artificial intelligence (AI). (Author)

  14. Analysis of a control and data acquisition system for radiation protection monitors of spent fuel reprocessing plant

    International Nuclear Information System (INIS)

    Liu Boxue

    1997-01-01

    For the radiation protection monitoring of spent nuclear fuel reprocessing plant, the paper analyzes the composition and requirements of a control and data acquisition system. With the concepts of typical distributing and opening models, the hardware consists of IPC, communication of RS-485 bus lines and data multiplexer. The software consists of real-time multi-services operation system and modelling program. It can sample monitoring data, control monitor's operation, and process data and other information. It has good expansive and compatible features

  15. Improved core protection calculator system algorithm

    International Nuclear Information System (INIS)

    Yoon, Tae Young; Park, Young Ho; In, Wang Kee; Bae, Jong Sik; Baeg, Seung Yeob

    2009-01-01

    Core Protection Calculator System (CPCS) is a digitized core protection system which provides core protection functions based on two reactor core operation parameters, Departure from Nucleate Boiling Ratio (DNBR) and Local Power Density (LPD). It generates a reactor trip signal when the core condition exceeds the DNBR or LPD design limit. It consists of four independent channels which adapted a two out of four trip logic. CPCS algorithm improvement for the newly designed core protection calculator system, RCOPS (Reactor COre Protection System), is described in this paper. New features include the improvement of DNBR algorithm for thermal margin, the addition of pre trip alarm generation for auxiliary trip function, VOPT (Variable Over Power Trip) prevention during RPCS (Reactor Power Cutback System) actuation and the improvement of CEA (Control Element Assembly) signal checking algorithm. To verify the improved CPCS algorithm, CPCS algorithm verification tests, 'Module Test' and 'Unit Test', would be performed on RCOPS single channel facility. It is expected that the improved CPCS algorithm will increase DNBR margin and enhance the plant availability by reducing unnecessary reactor trips

  16. Fire protection in nuclear power plants

    International Nuclear Information System (INIS)

    1979-01-01

    The Safety Guide gives design and some operational guidance for protection from fire and fire-related explosions in nuclear power plants (NPP). It confines itself to fire protection of items important to safety, leaving the aspects of fire protection not related to safety in NPP to be decided upon the basis of the national practices and regulations

  17. Earthquake protection of nuclear power plant equipment

    Energy Technology Data Exchange (ETDEWEB)

    Nawrotzki, Peter [GERB Vibration Control Systems, Berlin (Germany)

    2010-05-15

    Power plant machinery can be dynamically decoupled from the substructure by the effective use of helical steel springs and viscous dampers. Turbine foundations, boiler feed pumps and other machine foundations benefit from this type of elastic support systems to mitigate the transmission of operational vibration. The application of these devices may also be used to protect against earthquakes and other catastrophic events, i.e. airplane crash, of particular importance in nuclear facilities. This article illustrates basic principles of elastic support systems and applications on power plant buildings in medium and high seismic areas. Spring-damper combinations with special stiffness properties are used to reduce seismic acceleration levels of turbine components and other safety or non-safety related structures. For turbine buildings, the integration of the turbine substructure into the machine building can further reduce stress levels in all structural members. (orig.)

  18. Earthquake protection of nuclear power plant equipment

    International Nuclear Information System (INIS)

    Nawrotzki, Peter

    2010-01-01

    Power plant machinery can be dynamically decoupled from the substructure by the effective use of helical steel springs and viscous dampers. Turbine foundations, boiler feed pumps and other machine foundations benefit from this type of elastic support systems to mitigate the transmission of operational vibration. The application of these devices may also be used to protect against earthquakes and other catastrophic events, i.e. airplane crash, of particular importance in nuclear facilities. This article illustrates basic principles of elastic support systems and applications on power plant buildings in medium and high seismic areas. Spring-damper combinations with special stiffness properties are used to reduce seismic acceleration levels of turbine components and other safety or non-safety related structures. For turbine buildings, the integration of the turbine substructure into the machine building can further reduce stress levels in all structural members. (orig.)

  19. Literature study regarding fire protection in nuclear power plants. Part 2: Fire detection and -extinguishing systems

    International Nuclear Information System (INIS)

    Isaksson, S.

    1996-01-01

    This literature study has been made on behalf of the Swedish Nuclear Power Inspectorate. The aim is to describe different aspects of fire protection in nuclear power plants. Detection and extinguishing systems in Swedish nuclear power plants have only to a limited extent been designed after functional demands, such as a maximum acceptable damage or a maximum time to detect a fire. The availability of detection systems is difficult to assess, partly because of lack of statistics. The user interface is very important in complex systems as nuclear plants. An extinguishing system designed according to the insurance companies' regulations will only fulfill the basic demands. It should be noted that normal sprinkler design does not aim for extinguishing fires, the objective is to control fire until manual extinguishment is possible. There is a great amount of statistics on wet and dry pipe sprinkler systems, while statistics are more scarce for deluge systems. The statistics on the reliability of gaseous extinguishing systems have been found very scarce. A drawback of these systems is that they are normally designed for one shot only. There are both traditional and more recent extinguishing systems that can replace halons. From now on there will be a greater need for a thorough examination of the properties needed for the individual application and a quantification of the acceptable damage. There are several indications on the importance of a high quality maintenance program as well as carefully developed routines for testing and surveillance to ensure the reliability of detection and extinguishing systems. 78 refs, 8 figs, 10 tabs

  20. Design of the interlock and protection system for the SPIDER experiment

    International Nuclear Information System (INIS)

    Pomaro, N.; Grando, L.; Luchetta, A.; Paolucci, F.; Sartori, F.

    2013-01-01

    Highlights: •A custom designed interlock and protection system for SPIDER experiment is described. •It includes two subsystems implementing slow and fast protection functions. •High reliability PLCs are adopted for slow protection. •Fiber-optic based, custom designed fast logic circuitry is proposed for fast protection. •Accelerators breakdown events are also managed by the fast subsystem. -- Abstract: Unprecedented levels of beam energy and power are required for ITER Neutral Beam Heating systems. SPIDER experiment is an experimental device aimed to test and optimize a full size beam source satisfying ITER requirements. SPIDER experiment operation involves high power, voltage, temperature, and gas pressure. All these critical conditions are present simultaneously, so that any failure if not properly detected and managed is likely to cause severe damage. The Interlock and Protection System is a high-reliability system devoted to the investment protection of SPIDER. Its main purpose is to manage abnormal events occurring in one or more plants in order to minimize adverse consequences. The Interlock System also manages the SPIDER Operating Modes, defining the set and status of the Plants used in the various possible experimental configurations. In addition, the Interlock and Protection System takes care of particular events occurring during normal SPIDER operation, i.e. electrical arcs between accelerator grids, named breakdowns. Their treatment is committed to the Interlock and Protection System, as they need to be managed timely and with absolute reliability like actual faults. To perform the required functions, the Interlock and Protection System is interfaced with most SPIDER plants and with the SPIDER Control and Data Acquisition System. The paper describes the rationale of the protection functions, their implementation in the design and the technical specifications of the system

  1. Added value by rule IEC61850. Modernizing the electrical protection of Gundremmingen nuclear power plant

    International Nuclear Information System (INIS)

    Hoetzel, A.; Willems, D.; Maier, K.L.; Herrmann, H.J.; Einsiedler, G.

    2006-01-01

    After many years in operation the large power plant generating units B and C at Gundremmingen nuclear power plant are due for inspection and maintenance, which also requires modernizing the electrical protection. Unlike the construction of new power plants, additional constraints apply to modernization in existing plants. The new solution has to fit as seamlessly as possible into the existing units, such as signaling systems with their multitude of signaling contacts and printers, or the connection to the power plant automation system. Apart from purely technical requirements, economic factors such as short standstill times, limited budgets or phased conversions also influence the choice of a suitable solution. Planning, construction and commissioning of the electrical generating unit protection was implemented by the Secondary Systems Technology Center, a technical department of RWE-Rhein-Ruhr Netzservice GmbH, in coordination with the operator. (orig.)

  2. Distributed systems for the protection of nuclear stations

    International Nuclear Information System (INIS)

    Jover, P.

    1980-01-01

    The advantages of distributed control systems usually mentioned are improved exploitation, cost reduction, and adaptation to changes in technology. These advantages are obviously very interesting for nuclear power plant applications, and many such systems have been proposed. This note comments on the application of the distributed system concept to protection systems - what should be distributed - and closes with a brief description of a protection system based on microprocessors for pressurized water stations being built in France. (auth) [fr

  3. Vehicle bomb protection for nuclear power plants

    International Nuclear Information System (INIS)

    James, J.W.; Veatch, J.D.; Goldman, L.; Massa, R.

    1989-01-01

    The six-step methodology presented in this paper can be applied to nuclear power reactors to provide protection measures and considerations against vehicle bomb threats. The methodology provides a structured framework for examining the potential vulnerability of a plant to a postulated vehicle bomb and for developing contingency planning strategies for dealing with such a possibility. The six steps are as follows: (1) identify system options available to establish and maintain a safe reactor shutdown; (2) identify buildings or other structures containing critical components and equipment associated with each system option; (3) determine survival envelopes for the system options; (4) review site features to determine vehicle access approach paths and distances as they relate to the survival envelopes; (5) identify measures to limit or thwart vehicle access, and protect and preserve preferred system options; (6) prepare contingency plans and make advance arrangements for implementation of contingency measures for a vehicle bomb attack. Portions of this methodology related to blast effects from vehicle bombs on power reactor components are implemented using BombCAD, a proprietary computer-aided design (CAD)-based blast effects analysis technique

  4. General digitalized system on nuclear power plants

    International Nuclear Information System (INIS)

    Akagi, Katsumi; Kadohara, Hozumi; Taniguchi, Manabu

    2000-01-01

    Hitherto, instrumentation control system in a PWR nuclear power plant has stepwisely adopted digital technology such as application of digital instrumentation control device to ordinary use (primary/secondary system control device, and so on), application of CRT display system to monitoring function, and so forth, to realize load reduction of an operator due to expansion of operation automation range, upgrading of reliability and maintenance due to self-diagnosis function, reduction of mass in cables due to multiple transfer, and upgrading of visual recognition due to information integration. In next term PWR plant instrumentation control system, under consideration of application practice of conventional digital technology, application of general digitalisation system to adopt digitalisation of overall instrumentation control system containing safety protection system, and central instrumentation system (new type of instrumentation system) and to intend to further upgrade economics, maintenance, operability/monitoring under security of reliability/safety is planned. And, together with embodiment of construction program of the next-term plant, verification at the general digitalisation proto-system aiming at establishment of basic technology on the system is carried out. Then, here was described on abstract of the general digitalisation system and characteristics of a digital type safety protection apparatus to be adopted in the next-term plant. (G.K.)

  5. Possibilities of Botanical Insecticides in Plant Protection

    Czech Academy of Sciences Publication Activity Database

    Pavela, R.; Sajfrtová, Marie; Sovová, Helena; Bárnet, M.

    2008-01-01

    Roč. 2, č. 1 (2008), s. 16-23 ISSN 1313-2563 Grant - others:MŠk(CZ) 2B08049 Institutional support: RVO:67985858 Keywords : botanical insecticides * plant extracts * supercritical fluid extraction Subject RIV: GF - Plant Pathology, Vermin, Weed, Plant Protection

  6. Researching and improving the reliability of reactor protection system of Qinshan nuclear power plant

    International Nuclear Information System (INIS)

    Jiang Zuyue; Sheng Jiannan

    1997-01-01

    Due to the original design defects of the Reactor Protection System (RPS) of Qinshan Nuclear Power Plant, this system has brought about a number of reactor shutdown accidents and Engineered Safety Features (ESF) mis-activation events which have seriously endangered safe and steady operation of the nuclear power plant. So over three years have been spent on research on the reform of the original design on the premise that the general wiring of the system should remain the same and that the system size should also remain small to be contained in the original cabinets. The following improvements were made: (1) Increase the system's anti-disturbance capability. The system's zero volt bus floating designs were modified to surmount the disturbance resulting from the bad isolation performance of impedance-isolated amplifier; Double grounds have been added to logical modules to surmount the disturbance resulting from zero volt floating bus during the replacement of single module with two connectors; The opto-coupling circuit in its oscillation input stage of Engineered Safety Features have been improved to increase its reliability. (2)Modify to output activation part of the system. The new type of output relays were selected and the relay activation circuits were redesigned in which switcher activation mode is used instead of amplifier activation mode so as to increase the reliability of relay operation and reduce the power consumption; CMOS buffer gates in the input and output stage of the circuit were used to match TTL circuits to CMOS circuits of the system

  7. Inventory of cassava plant protection and development projects in ...

    African Journals Online (AJOL)

    A total of 303 cassava protection and development projects were identified of which about half are plant protection-oriented. Most activities on cassava protection have been centred on biological control and host plant resistance. The least activity has been on chemical control. The applicability of the collected database is ...

  8. Advanced liquid metal reactor plant control system

    International Nuclear Information System (INIS)

    Dayal, Y.; Wagner, W.; Zizzo, D.; Carroll, D.

    1993-01-01

    The modular Advanced Liquid Metal Reactor (ALMR) power plant is controlled by an advanced state-of-the-art control system designed to facilitate plant operation, optimize availability, and protect plant investment. The control system features a high degree of automatic control and extensive amount of on-line diagnostics and operator aids. It can be built with today's control technology, and has the flexibility of adding new features that benefit plant operation and reduce O ampersand M costs as the technology matures

  9. Application of Digital Technology for the Plant Protection System in Ulchin Nuclear Power Plant Units 5 and 6

    International Nuclear Information System (INIS)

    Deucksoo, Lee; Insik, Kim

    2006-01-01

    Since the completion of construction of Ulchin Nuclear Power Plant Units 3 and 4 (UCN 3 and 4), the first units of the OPR (Optimized Power Reactor) series, various advanced design features have been incorporated to the following OPRs. The Ulchin Nuclear Power Plant Units 5 and 6(UCN 5 and 6) which started commercial operation in Korea from 2004 and 2005 respectively, are designed to provide improvements in safety, reliability and costs by applying both advanced proven technology and experiences gained from the construction and operation of the previous OPRs. Among those improvements, the digital plant protection system (DPPS) and the digital engineered safety feature actuation system (DESFAS) are the key elements to the UCN 5 and 6 designs. The DPPS and DESFAS utilizing the digital computer technology offer a solution to the obsolescence problem of analog system. These features also provide the potential for additional benefits such as ease of maintenance, increased performance, reduction of internal and external cross channel wiring, improvement of the surveillance testability and flexibility of control logic programming change. During the initial design stage, the Korean regulatory body had evaluated these design concepts intensively and concluded it to be acceptable for the safety point of view. Also, in-depth review on the detailed design and the special evaluation/audit for the software design process has been performed to secure the quality of the software. As a result, every issue raised during licensing review has been clarified and the operating licenses for the UCN 5 and 6 were issued in October, 2003 and October, 2004 respectively, by the government. In this paper, design characteristics of the UCN 5 and 6 are introduced, and advanced design features and implementation process are presented focused on the DPPS/DESFAS with some benefit analysis results. (authors)

  10. Plant protection means used in organic farming throughout the European Union.

    Science.gov (United States)

    Matyjaszczyk, Ewa

    2018-03-01

    Following the obligatory implementation of integrated pest management in the European Union (EU), the plant protection means suitable for application in organic agriculture attracted the attention of quite a wide group of potential users. In spite of the common rules of organic production, as well as the uniform principles of placing plant protection products on the market, the availability of products that can be legally used in organic crop protection differs significantly among the Member States. There is a uniform list of 10 basic substances that can be used in the protection of organic crops throughout the entire EU. Twelve Member States have official registers of plant protection products for use in organic agriculture, and the total number of qualified products per country varies from 11 in Lithuania to 576 in Italy. Some products that improve plant vigour or resistance and may be of use in protection of organic crops are placed on the market as biostimulants. They fall under the law that governs fertilisers and the systems of their registration vary widely among the Member States. In addition, there exist a number of products that have been legally introduced onto the markets of some Member States without registration as a consequence of a loophole in the law. The use of unregistered products in organic agriculture raises some doubts, but currently it seems that there is no legal basis on which to explicitly prohibit the practice. © 2017 Society of Chemical Industry. © 2017 Society of Chemical Industry.

  11. Protection of nuclear power plants against external events

    International Nuclear Information System (INIS)

    Suetterlin, L.

    1978-01-01

    The different aspects for the selection of external events to be accounted for in designing nuclear power plants and in defining load assumptions are illustrated: 1) In case of earthquake the severest possible events according to the state of science and technology are assumed. 2) For events where it is not or only to a certain extent possible to apply this method, e.g. in the load case airplane crash, load assumptions are defined in a combined probabilitic-deterministic way. By the example of plant protection, it is shown that by integrating all measures for protecting against interference of third parties (sabotage) or other external events, optimum protection concepts may be achieved. In all considerations on interference of third parties or other external events, one has to take into account that absolute protection is not possible. Nevertheless, it may be confirmed that nuclear power plants not only have a much higher level of protection than other, non-nuclear plants with equal or even higher potential hazard, but also that they meet the requirement not to increase significantly the current risk of society. (orig./HP) [de

  12. Report on task I: fire protection system study

    International Nuclear Information System (INIS)

    Bernard, E.A.; Cano, G.L.

    1977-02-01

    This study (1) evaluates, on a comparative basis, the national and international regulatory and insurance standards that serve as guidance for fire protection within the nuclear power industry; (2) analyzes the recommendations contained in the major reports on the Browns Ferry Fire; (3) proposes quantitative safety goals and evaluation methods for Nuclear Power Plant Fire Protection Systems (NPPFPS); (4) identifies potential improvements that may be incorporated into NPPFPS; and (5) recommends a plan of action for continuation of the fire protections systems study

  13. Possibilities of Botanical Insecticides in Plant Protection

    Czech Academy of Sciences Publication Activity Database

    Pavela, R.; Sajfrtová, Marie; Sovová, Helena; Bárnet, M.

    2008-01-01

    Roč. 2, č. 1 (2008), s. 16-23 ISSN 1313-2563 Grant - others:GA MŠMT(CZ) 2B08049 Institutional research plan: CEZ:AV0Z40720504 Keywords : botanical insecticides * plant exctracts * supercritical fluid extraction Subject RIV: GF - Plant Pathology, Vermin, Weed, Plant Protection

  14. Chemical plant protection outlays in vast areas farming at the beginning of 21st century

    Directory of Open Access Journals (Sweden)

    Maria Golinowska

    2009-01-01

    Full Text Available In 2008, several investigations were conducted in the area of chemical plant protection outlays in two vast area farms where simplified system of farming was applied. Analysed outlays consisted of: use of pesticides in kilograms of active substance per 1 ha and real costs of plant protection procedures. Profitability of the outlay was identified with approximate indicator of outlay E1 and E2. The research showed that farm during plant production use from 1 to 10.28 kg AS/ha. Costs of these procedures ranged from 100.50 to 1253.84 PLN/ha depending on the cultivated plant. Profitability of plant protection procedures in wheat and rape cultivation was at the same level in both farms. The highest profitability was reached by maize cultivation.

  15. The protection system to Brazilian Nuclear Program

    International Nuclear Information System (INIS)

    Andreuzza, Mario Giussepp Santezzi Bertottelli

    1997-01-01

    The Sistema de Protecao ao Programa Nuclear Brasileiro-SIPRON (Protection System to Brazilian Nuclear Program) was established in 1980. It is intended to accomplish in only one system, all the actions related to security and protection for Nuclear Facilities in Brazil. The author presents in detail the protection system SIPRON, describing the system structure and organization, the functions and obligations of the system involved main organizations, as well as, the system operation and behaviour during an postulated occurrence of a nuclear emergency. It is also described an Exercise that happened in June of 1997 at the Nuclear Power Plant (NPP) Angra I, after two simulated tests in December of 1996 and April of 1997. The NPP Angra I Emergency Plan Exercise was a good opportunity to test the SIPRON structure and preparedness program. It was verified, included by International Atomic Energy Agency observers, the system involved organizations effectiveness and the procedures efficacy to protect the public and the environmental. Finally, it is shown the SIPRON activities of routine, the system obstacles and the expected future performances. (author)

  16. Fires: what plant locations should we really protect

    International Nuclear Information System (INIS)

    Berry, D.L.

    1980-01-01

    A fire protection analysis technique was developed from earlier work involving the protection of nuclear power plants against acts of sabotage. Characteristics unique to fire phenomena were used to modify the sabotage analysis methodology. These characteristics include the effects of fuel loads, ventilation rates, heat loss areas, barrier ratings, and plant locations. The new fire analysis technique was applied to an example nuclear power plant having 85 different plant areas. It was found that some safety and nonsafety areas were both highly vulnerable to fire spread and important to overall safety, while other areas were found to be of marginal importance to fire safety

  17. Importance of plants in radiation protection

    International Nuclear Information System (INIS)

    Rawat, Shalini

    2015-01-01

    Radioactive substances from nuclear programme structures are one of the major toxicant causing serious health hazards. These manmade radiations include X-ray machines radioactive fall-outs, nuclear reactor waste, TV, computers etc. Effect of radiation may be somatic and genetic. Most genetic effects are brought by manmade radiations. Plants on one hand using the electromagnetic radiation from sun for one of the most important vital activity of earth called Photosynthesis and on the other hand protecting us from harmful radiations. There are however, many natural compounds with radio-protective activity. Such compounds include sulfhydryl-containing compounds and anti-oxidant nutrients such as vitamins C and E, beta-carotene, N-acetylcysteine and selenium, along with a range of phytochemicals found in plants such as Ginkgo biloba, Vitis vinifera (Grape), Ocimum sanctum (Tulsi or holy basil). Some plants have capacity to absorb harmful radiation of computers like Aloe, Cactus, etc. Such study can be helpful in minimizing radiation pollution. Present review paper emphasizing Botanical, Ecological and Economic aspects of some plants. (author)

  18. Reactor protection system including engineered features actuation system

    International Nuclear Information System (INIS)

    Palmaers, W.

    1982-01-01

    The safety concept requires to ensure that - the reactor protection system - the active engineered safeguard - and the necessary auxiliary systems are so designed and interfaced in respect of design and mode of action that, in the event of single component failure reliable control of the consequences of accidents remains ensured at all times and that the availability of the power plant is not limited unnecessarily. In order to satisfy these requirements due, importance was attached to a consistent spacial separation of the mutually redundant subsystems of the active safety equipment. The design and layout of the reactor protection system, of the power supply (emergency power supply), and of the auxiliary systems important from the safety engineering point of view, are such that their subsystems also largely satisfy the requirements of independence and spacial separation. (orig./RW)

  19. Public Lakes, Private Lakeshore: Modeling Protection of Native Aquatic Plants

    Science.gov (United States)

    Schroeder, Susan A.; Fulton, David C.

    2013-07-01

    Protection of native aquatic plants is an important proenvironmental behavior, because plant loss coupled with nutrient loading can produce changes in lake ecosystems. Removal of aquatic plants by lakeshore property owners is a diffuse behavior that may lead to cumulative impacts on lake ecosystems. This class of behavior is challenging to manage because collective impacts are not obvious to the actors. This paper distinguishes positive and negative beliefs about aquatic plants, in models derived from norm activation theory (Schwartz, Adv Exp Soc Psychol 10:221-279, 1977) and the theory of reasoned action (Fishbein and Ajzen, Belief, attitude, intention, and behavior: an introduction to theory and research, Addison-Wesley, Boston 1975), to examine protection of native aquatic plants by Minnesota lakeshore property owners. We clarify how positive and negative evaluations of native aquatic plants affect protection or removal of these plants. Results are based on a mail survey ( n = 3,115). Results suggest that positive evaluations of aquatic plants (i.e., as valuable to lake ecology) may not connect with the global attitudes and behavioral intentions that direct plant protection or removal. Lakeshore property owners' behavior related to aquatic plants may be driven more by tangible personal benefits derived from accessible, carefully managed lakeshore than intentional action taken to sustain lake ecosystems. The limited connection of positive evaluations of aquatic plants to global attitudes and behavioral intentions may reflect either lack of knowledge of what actions are needed to protect lake health and/or unwillingness to lose perceived benefits derived from lakeshore property.

  20. Public lakes, private lakeshore: Modeling protection of native aquatic plants

    Science.gov (United States)

    Schroeder, Susan A.; Fulton, David C.

    2013-01-01

    Protection of native aquatic plants is an important proenvironmental behavior, because plant loss coupled with nutrient loading can produce changes in lake ecosystems. Removal of aquatic plants by lakeshore property owners is a diffuse behavior that may lead to cumulative impacts on lake ecosystems. This class of behavior is challenging to manage because collective impacts are not obvious to the actors. This paper distinguishes positive and negative beliefs about aquatic plants, in models derived from norm activation theory (Schwartz, Adv Exp Soc Psychol 10:221–279, 1977) and the theory of reasoned action (Fishbein and Ajzen, Belief, attitude, intention, and behavior: an introduction to theory and research, Addison-Wesley, Boston 1975), to examine protection of native aquatic plants by Minnesota lakeshore property owners. We clarify how positive and negative evaluations of native aquatic plants affect protection or removal of these plants. Results are based on a mail survey (n = 3,115). Results suggest that positive evaluations of aquatic plants (i.e., as valuable to lake ecology) may not connect with the global attitudes and behavioral intentions that direct plant protection or removal. Lakeshore property owners’ behavior related to aquatic plants may be driven more by tangible personal benefits derived from accessible, carefully managed lakeshore than intentional action taken to sustain lake ecosystems. The limited connection of positive evaluations of aquatic plants to global attitudes and behavioral intentions may reflect either lack of knowledge of what actions are needed to protect lake health and/or unwillingness to lose perceived benefits derived from lakeshore property.

  1. Screening agrochemicals as potential protectants of plants against ozone phytotoxicity

    International Nuclear Information System (INIS)

    Saitanis, Costas J.; Lekkas, Dimitrios V.; Agathokleous, Evgenios; Flouri, Fotini

    2015-01-01

    We tested seven contemporary agrochemicals as potential plant protectants against ozone phytotoxicity. In nine experiments, Bel-W3 tobacco plants were experienced weekly exposures to a) 80 nmol mol −1 of ozone-enriched or ozone-free air in controlled environment chambers, b) an urban air polluted area, and c) an agricultural-remote area. Ozone caused severe leaf injury, reduced chlorophylls' and total carotenoids' content, and negatively affected photosynthesis and stomatal conductance. Penconazole, (35% ± 8) hexaconazole (28% ± 5) and kresoxim-methyl (28% ± 15) showed higher plants’ protection (expressed as percentage; mean ± s.e.) against ozone, although the latter exhibited a high variability. Azoxystrobin (21% ± 15) showed lower protection efficacy and Benomyl (15% ± 9) even lower. Trifloxystrobin (7% ± 11) did not protect the plants at all. Acibenzolar-S-methyl + metalaxyl-M (Bion MX) (−6% ± 17) exhibited the higher variability and contrasting results: in some experiments it showed some protection while in others it intensified the ozone injury by causing phytotoxic symptoms on leaves, even in control plants. - Highlights: • Penconazole and hexaconazole offered some protection to plants against ozone. • Bion MX fungicide caused phytotoxic symptoms to Bel-W3 tobacco plants. • Stomatal conductance was reduced in ozone-fumigated plants. - Seven agrochemicals were assessed as potential protectants against ozone phytotoxicity – triazoles fungicides were the most effective

  2. Suitability review of FMEA and reliability analysis for digital plant protection system and digital engineered safety features actuation system

    Energy Technology Data Exchange (ETDEWEB)

    Kim, I. S.; Kim, T. K.; Kim, M. C.; Kim, B. S.; Hwang, S. W.; Ryu, K. C. [Hanyang Univ., Seoul (Korea, Republic of)

    2000-11-15

    Of the many items that should be checked out during a review stage of the licensing application for the I and C system of Ulchin 5 and 6 units, this report relates to a suitability review of the reliability analysis of Digital Plant Protection System (DPPS) and Digital Engineered Safety Features Actuation System (DESFAS). In the reliability analysis performed by the system designer, ABB-CE, fault tree analysis was used as the main methods along with Failure Modes and Effect Analysis (FMEA). However, the present regulatory technique dose not allow the system reliability analysis and its results to be appropriately evaluated. Hence, this study was carried out focusing on the following four items ; development of general review items by which to check the validity of a reliability analysis, and the subsequent review of suitability of the reliability analysis for Ulchin 5 and 6 DPPS and DESFAS L development of detailed review items by which to check the validity of an FMEA, and the subsequent review of suitability of the FMEA for Ulchin 5 and 6 DPPS and DESFAS ; development of detailed review items by which to check the validity of a fault tree analysis, and the subsequent review of suitability of the fault tree for Ulchin 5 and 6 DPPS and DESFAS ; an integrated review of the safety and reliability of the Ulchin 5 and 6 DPPS and DESFAS based on the results of the various reviews above and also of a reliability comparison between the digital systems and the comparable analog systems, i.e., and analog Plant Protection System (PPS) and and analog Engineered Safety Features Actuation System (ESFAS). According to the review mentioned above, the reliability analysis of Ulchin 5 and 6 DPPS and DESFAS generally satisfies the review requirements. However, some shortcomings of the analysis were identified in our review such that the assumed test periods for several equipment were not properly incorporated in the analysis, and failures of some equipment were not included in the

  3. Promises in intelligent plant control systems

    International Nuclear Information System (INIS)

    Otaduy, P.J.

    1987-01-01

    The control system is the brain of a power plant. The traditional goal of control systems has been productivity. However, in nuclear power plants the potential for disaster requires safety to be the dominant concern, and the worldwide political climate demands trustworthiness for nuclear power plants. To keep nuclear generation as a viable option for power in the future, trust is the essential critical goal which encompasses all others. In most of today's nuclear plants the control system is a hybrid of analog, digital, and human components that focuses on productivity and operates under the protective umbrella of an independent engineered safety system. Operation of the plant is complex, and frequent challenges to the safety system occur which impact on their trustworthiness. Advances in nuclear reactor design, computer sciences, and control theory, and in related technological areas such as electronics and communications as well as in data storage, retrieval, display, and analysis have opened a promise for control systems with more acceptable human brain-like capabilities to pursue the required goals. This paper elaborates on the promise of futuristic nuclear power plants with intelligent control systems and addresses design requirements and implementation approaches

  4. Design concepts to enhance nuclear power plant protection

    International Nuclear Information System (INIS)

    Ericson, D.M. Jr.; Varnado, G.B.

    1980-01-01

    Using a modern design for a nuclear power plant as a point of departure, this study examines the enhancement of protection which may be achieved by changes to the design. These changes include concepts such as complete physical separation of redundant trains of safety equipment, hardened enclosures for water storage tanks, and hardened shutdown heat removal systems. The degree of enhancement (value) is examined in terms such as the potential reduction in the number of vital areas and the increase in probability of adversary sequence interruption. The impacts considered include constraints imposed upon operations and maintenance personnel and increased capital and operating costs. The study concludes that structural design changes alone do not provide significant increases in protection

  5. Systems Thinking Safety Analysis: Nuclear Security Assessment of Physical Protection System in Nuclear Power Plants

    Directory of Open Access Journals (Sweden)

    Tae Ho Woo

    2013-01-01

    Full Text Available The dynamical assessment has been performed in the aspect of the nuclear power plants (NPPs security. The physical protection system (PPS is constructed by the cyber security evaluation tool (CSET for the nuclear security assessment. The systems thinking algorithm is used for the quantifications by the Vensim software package. There is a period of 60 years which is the life time of NPPs' operation. The maximum possibility happens as 3.59 in the 30th year. The minimum value is done as 1.26 in the 55th year. The difference is about 2.85 times. The results of the case with time delay have shown that the maximum possibility of terror or sabotage incident happens as 447.42 in the 58th year and the minimum value happens as 89.77 in the 51st year. The difference is about 4.98 times. Hence, if the sabotage happens, the worst case is that the intruder can attack the target of the nuclear material in about one and a half hours. The general NPPs are modeled in the study and controlled by the systematic procedures.

  6. Preinspection of nuclear power plant systems

    International Nuclear Information System (INIS)

    1975-01-01

    The general plans of the systems affecting the safety of the nuclear power plants are accepted by the Institute of Radiation Protection (IRP) on the basis of the preinspection of the systems. This is the prerequisite of the preinspection of the structures and components belonging to these systems. Exceptionally, when separately agreed, the IRP may perform the preinspection of a separate structure or component, although the preinspection documentation of the whole system, e.g. the nuclear heat generating system, has not been accepted. This guide applies to the nuclear power plant systems that have been defined to be preinspected in the classification document accepted by the IRP

  7. Radiological protection in nuclear power plants

    International Nuclear Information System (INIS)

    Zorrilla R, S.

    2008-12-01

    several fronts, the number of dosimetry transactions, increases up to 30 times the normal operation, and so on. For these reasons during the reloads, the electronic dosimetry system and the monitoring system output contamination staff becomes critical systems whose functioning must be ensured to avoid becoming a bottleneck. Reloads must also be planned for a perfect manning of critical supplies such as clothing and protection accessories against contamination. (Author)

  8. Screening agrochemicals as potential protectants of plants against ozone phytotoxicity.

    Science.gov (United States)

    Saitanis, Costas J; Lekkas, Dimitrios V; Agathokleous, Evgenios; Flouri, Fotini

    2015-02-01

    We tested seven contemporary agrochemicals as potential plant protectants against ozone phytotoxicity. In nine experiments, Bel-W3 tobacco plants were experienced weekly exposures to a) 80 nmol mol(-1) of ozone-enriched or ozone-free air in controlled environment chambers, b) an urban air polluted area, and c) an agricultural-remote area. Ozone caused severe leaf injury, reduced chlorophylls' and total carotenoids' content, and negatively affected photosynthesis and stomatal conductance. Penconazole, (35% ± 8) hexaconazole (28% ± 5) and kresoxim-methyl (28% ± 15) showed higher plants' protection (expressed as percentage; mean ± s.e.) against ozone, although the latter exhibited a high variability. Azoxystrobin (21% ± 15) showed lower protection efficacy and Benomyl (15% ± 9) even lower. Trifloxystrobin (7% ± 11) did not protect the plants at all. Acibenzolar-S-methyl + metalaxyl-M (Bion MX) (-6% ± 17) exhibited the higher variability and contrasting results: in some experiments it showed some protection while in others it intensified the ozone injury by causing phytotoxic symptoms on leaves, even in control plants. Copyright © 2014 Elsevier Ltd. All rights reserved.

  9. Unavailability Analysis of the Reactor Core Protection System using Reliability Block Diagram

    International Nuclear Information System (INIS)

    Shin, Hyun Kook; Kim, Sung Ho; Choi, Woong Suk; Kim, Jae Hack

    2006-01-01

    The reactor core of nuclear power plants needs to be monitored for the early detection of core abnormal conditions to protect plants from a severe accident. The core protection calculator system (CPCS) has been provided to calculate the departure from nucleate boiling ratio (DNBR) and the local power density (LPD) based on measured parameters of reactor and coolant system. The original CPCS for OPR 1000 has been designed and implemented based on the concurrent 3205 computer system whose components are obsolete. The CPCS based on Westinghouse Common-Q system has recently been implemented for the Shin-Kori Nuclear Power Plant, Units 1 and 2(SKN 1 and 2). An R and D project has been launched to develop new core protection system called as RCOPS (Reactor Core Protection System) with the partnership of KOPEC and Doosan Heavy Industries and Construction Co. RCOPS is implemented on the HFC-6000 safety class programmable logic controller (PLC). In this paper, the reliability of RCOPS is analyzed using the reliability block diagram (RBD) method. The calculated results are compared with that of the CPCS for SKN 1 and 2

  10. Particular features of fire protection in nuclear power plants

    International Nuclear Information System (INIS)

    Krueger, W.

    1985-01-01

    The particular features of fire protection in nuclear power plants that are connected with the need to ensure nuclear and radiation safety even during an emergency are outlined followed by the recommendation to lay them down in special fire protection standards. These, in conjunction with comprehensive fire hazard analyses, could serve to work out complex concepts for the fire protection of individual nuclear power plants. Such concepts would be very useful for review and assessment of the fire protection design during the licensing process and for later inspections. (author)

  11. Research directions in plant protection chemistry

    Directory of Open Access Journals (Sweden)

    Andras Szekacs

    2017-09-01

    Full Text Available This Opinion paper briefly summarizes the views of the authors on the directions of research in the area of plant protection chemistry. We believe these directions need to focus on (1 the discovery of new pesticide active ingredients, and (2 the protection of human health and the environment. Research revenues are discussed thematically in topics of target site identification, pesticide discovery, environmental aspects, as well as keeping track with the international trends. The most fundamental approach, target site identification, covers both computer-aided molecular design and research on biochemical mechanisms. The discovery of various classes of pesticides is reviewed including classes that hold promise to date, as well as up-to-date methods of innovation, e.g. utilization of plant metabolomics in identification of novel target sites of biological activity. Environmental and ecological aspects represent a component of increasing importance in pesticide development by emphasizing the need to improve methods of environmental analysis and assess ecotoxicological side-effects, but also set new directions for future research. Last, but not least, pesticide chemistry and biochemistry constitute an integral part in the assessment of related fields of plant protection, e.g. agricultural biotechnology, therefore, issues of pesticide chemistry related to the development and cultivation of genetically modified crops are also discussed.

  12. System of nuclear power reactor protection using dynamic logic

    International Nuclear Information System (INIS)

    Carvalho, P.V.R. de; Silva, L.C.R.P. da

    1990-01-01

    The aim of this work is the design of a Reactor Protection System (RPS) using dynamic logic as basic circuitry principle. This concept was developed to permit the electronic and eletromagnetic components employment in 'fail-safe' mode applied to automatic shutdown systems. 'Fail-safe' here means that a fail always yields a constant state that leads to a plant shutdown condition. So the normal condition of operation corresponds to an oscillating state response and the fail or abnormal condition to a static one. At present, almost all modern nuclear plant reactor protection systems use dynamic logic, just differing in the kind of technology employed in the construction of the system. In this work we define what technology best fits our necessities, setting out to design a RPS based on this philosophy. (author) [pt

  13. Improving CANDU plant operation and maintenance through retrofit information technology systems

    International Nuclear Information System (INIS)

    Lupton, L. R.; Judd, R. A.

    1998-01-01

    CANDU plant owners are facing an increasingly competitive environment for the generation of electricity. To meet this challenge, all owners have identified that information technology offers opportunities for significant improvements in CANDU operation, maintenance and administration (OM and A) costs. Targeted information technology application areas include instrumentation and control, engineering, construction, operations and plant information management. These opportunities also pose challenges and issues that must be addressed if the full benefits of the advances in information technology are to be achieved. Key among these are system hardware and software maintenance, and obsolescence protection. AECL has been supporting CANDU stations with the initial development and evaluation of systems to improve plant performance and cost. Five key initiatives that have been implemented or are in the process of being implemented in some CANDU plants to achieve cooperational benefits include: critical safety parameter monitor system; advanced computerized annunciation system; plant historical data system; plant display system; and digital protection system. Each system will be described in terms of its role in enhancing current CANDU plant performance and how they will contribute to future CANDU plant performance. (author). 8 refs., 3 figs

  14. New probabilistic decision-making tools for fire protection systems

    International Nuclear Information System (INIS)

    Ksobiech, C.; Mowrer, F.

    1991-01-01

    The FIVE methodology provides guidance to utilities in performing an examination of potential plant severe accidents caused by fire initiated events. FIVE is oriented toward uncovering limiting plant design or operating characteristics (vulnerabilities) that make certain fire-initiated events more likely than others. It provides a combination of deterministic and probabilistic techniques for examining a power plant's fire probability and protection characteristics. It includes a two phase progressive screening method and a third phase consisting of a plant walkdown/verification process. The FIVE methodology centers on providing assurance of the availability of at least one train of the safe shutdown systems. FIVE has been developed for implementation by plant personnel who are most experienced with their plant's operations, fire hazards and fire protection features. The methodology provides these plant personnel with guidelines to quickly screen the plant down to the most significant locations where vulnerabilities may exist and then identify options to reduce the vulnerabilities

  15. Implementation of FPGA-Based Diverse Protection System

    International Nuclear Information System (INIS)

    Hwang, Soo Yun; Lee, Yoon Hee; Shon, Se Do; Baek, Seung Min

    2015-01-01

    Obsolete analog and digital hardware platforms in NPPs are commonly replaced with programmable logic controller (PLC) and distributed control system (DCS). Field programmable gate arrays (FPGAs) are highlighted as an alternative to obsolete hardware platforms. FPGAs are digital integrated circuits (ICs) that contain the configurable (programmable) blocks of logic along with configurable interconnections among these blocks. Designers can configure (program) such devices to perform a tremendous variety of tasks. FPGAs have been evolved from the technology of programmable logic device (PLD). Nowadays, they can contain millions of logic gates by nanotechnology and can be used to implement extremely large and complex functions that previously could be realized only using application specific integrated circuits (ASICs). This paper presents the implementation of an FPGA-based diverse protection system (DPS) which executes the protective functions in NPP when the protective functions of the plant protection system (PPS) fails

  16. Implementation of FPGA-Based Diverse Protection System

    Energy Technology Data Exchange (ETDEWEB)

    Hwang, Soo Yun; Lee, Yoon Hee; Shon, Se Do; Baek, Seung Min [KEPCO Engineering and Construction Company Inc., Daejeon (Korea, Republic of)

    2015-10-15

    Obsolete analog and digital hardware platforms in NPPs are commonly replaced with programmable logic controller (PLC) and distributed control system (DCS). Field programmable gate arrays (FPGAs) are highlighted as an alternative to obsolete hardware platforms. FPGAs are digital integrated circuits (ICs) that contain the configurable (programmable) blocks of logic along with configurable interconnections among these blocks. Designers can configure (program) such devices to perform a tremendous variety of tasks. FPGAs have been evolved from the technology of programmable logic device (PLD). Nowadays, they can contain millions of logic gates by nanotechnology and can be used to implement extremely large and complex functions that previously could be realized only using application specific integrated circuits (ASICs). This paper presents the implementation of an FPGA-based diverse protection system (DPS) which executes the protective functions in NPP when the protective functions of the plant protection system (PPS) fails.

  17. Specification and verification of the RTOS for plant protection systems

    International Nuclear Information System (INIS)

    Kim, Jin Hyun; Ahn, Young Ah; Lee, Su-Young; Choi, Jin Young; Lee, Na Young

    2004-01-01

    PLC is a computer system for instrumentation and control (I and C) systems such as control of machinery on factory assembly lines. control of machinery on factory assembly lines and Nucleare power plants. In nuclear power industry, systems is classified into 3 classes- Non-safety, safety-related and safety-critical up to integrity on system's using purpose. If PLC is used for controlling reactor in nuclear power plant, it should be identified as safety-critical. PLC has several I and C logics in software, including real-time operating system (RTOS). Hence, RTOS must be also proved that it is safe and reliable by various way and methods. In this paper, we apply formal methods to a development of RTOS for PLC in safety-critical level; Statecharts for specification and model checking for verification. In this paper, we give the results of applying formal methods to RTOS. (author)

  18. The Diamond machine protection system

    International Nuclear Information System (INIS)

    Heron, M.T.; Lay, S.; Chernousko, Y.; Hamadyk, P.; Rotolo, N.

    2012-01-01

    The Diamond Light Source Machine Protection System (MPS) manages the hazards from high power photon beams and other hazards to ensure equipment protection on the booster synchrotron and storage ring. The system has a shutdown requirement, on a beam mis-steer of under 1 msec and has to manage in excess of a thousand interlocks. This is realised using a combination of bespoke hardware and programmable logic controllers. The MPS monitors a large number of interlock signals from diagnostics instrumentation, vacuum instrumentation, photon front ends and plant monitoring subsystems. Based on logic it can then remove the source of the energy to ensure protection of equipment. Depending on requirements, interlocks are managed on a Local or a Global basis. The Global system is structured as two layers, and supports fast- and slow-response-time interlock requirements. A Global MPS module takes the interlock permits for a given interlock circuit from each of the cells of the accelerator, and, subject to all interlocks being good, produces a permit to operate the source of energy: the RF amplifier for vessel protection and the PSU for magnet protection. The Local MPS module takes fast Interlock inputs from one cell of the Storage Ring or one quadrant of the Booster. Fast interlocks are those that must drop the beam in under 400 μsec (the maximum speed of the interlock) in the event of failure. EPIC provides the user interface to the MPS system

  19. Dehydrins Impart Protection against Oxidative Stress in Transgenic Tobacco Plants.

    Science.gov (United States)

    Halder, Tanmoy; Upadhyaya, Gouranga; Basak, Chandra; Das, Arup; Chakraborty, Chandrima; Ray, Sudipta

    2018-01-01

    Environmental stresses generate reactive oxygen species (ROS) which might be detrimental to the plants when produced in an uncontrolled way. However, the plants ameliorate such stresses by synthesizing antioxidants and enzymes responsible for the dismutation of ROS. Additionally, the dehydrins were also able to protect the inactivation of the enzyme lactate dehydrogenase against hydroxyl radicals (OH ⋅ ) generated during Fenton's reaction. SbDhn1 and SbDhn2 overexpressing transgenic tobacco plants were able to protect against oxidative damage. Transgenic tobacco lines showed better photosynthetic efficiency along with high chlorophyll content, soluble sugar and proline. However, the malonyl dialdehyde (MDA) content was significantly lower in transgenic lines. Experimental evidence demonstrates the protective effect of dehydrins on electron transport chain in isolated chloroplast upon methyl viologen (MV) treatment. The transgenic tobacco plants showed significantly lower superoxide radical generation () upon MV treatment. The accumulation of the H 2 O 2 was also lower in the transgenic plants. Furthermore, in the transgenic plants the expression of ROS scavenging enzymes was higher compared to non-transformed (NT) or vector transformed (VT) plants. Taken together these data, during oxidative stress dehydrins function by scavenging the () directly and also by rendering protection to the enzymes responsible for the dismutation of () thereby significantly reducing the amount of hydrogen peroxides formed. Increase in proline content along with other antioxidants might also play a significant role in stress amelioration. Dehydrins thus function co-operatively with other protective mechanisms under oxidative stress conditions rendering protection in stress environment.

  20. Provision of operational radiation protection services at nuclear power plants

    International Nuclear Information System (INIS)

    1990-01-01

    The purpose of this publication is to provide practical guidance on establishing and maintaining a radiation protection programme for a nuclear power plant that is consistent with the optimization process recommended in the Basic Safety Standards. This publication is written with a view to providing guidance to every person associated with the radiation protection programme for a nuclear power plant and develops the theme that radiation protection requires the commitment of all plant staff, including higher levels of executive management. 12 refs, 2 figs

  1. Impact of Y2K problem on physical protection system

    International Nuclear Information System (INIS)

    Kumar, R.; Swadia, N.S.; Zanwar, P.S.; Mishra, G.P.; Salunke, A.S.; Nigam, R.K.

    1999-01-01

    Year 2000 related system failures/problems in Physical Protection System pose no threat to general safety and functioning of any nuclear facility. But there can be potential security threats having radiation safety and non-proliferation concern and hence should be given due importance. Reviewing and testing Physical Protection System for Y2K compliance are easier than other systems as it does not directly affect operation of the plant. The existing emergency response capability at the nuclear facilities should be utilizes effectively to mitigate any Y2K induced events on Physical Protection System with dedicated manpower and channeled efforts

  2. European protection principles against external hazards by means of Emergency Power Supply and Control Safety System Building in Nuclear Power Plants

    Energy Technology Data Exchange (ETDEWEB)

    Gallinat, Dipl Ing [Max Aicher Engineering GmbH, Freilassing (Germany)

    2016-10-15

    One of the most important nuclear power plant safety requirements is a redundant and independent power system. This requires such a design of emergency power systems that failure of one will not adversely impact the other. External hazards of natural origin or linked to human activity could potentially affect plant safety. The general objective of the design provisions is to ensure that the safety functions of the systems and components required to return the plant to a safe shutdown state and to prevent and limit radioactive release are not adversely affected. As external hazards are site dependent, Technical Guidelines specify that 'it is not necessary to take all of the hazards in a standardized design; such external hazards as external flooding, drought, ice formation and toxic, corrosive or combustible gases may be dealt with only for a specific plant, on a plant specific basis'. In accordance with the Technical Guidelines, external hazards are taken into consideration at the design stage consistently with internal events or hazards. The basic design principle is to protect against external hazards in accordance with the Technical Guidelines using a 'load case' procedure.

  3. Radiation protection by medicinal plants

    International Nuclear Information System (INIS)

    Jagetia, Ganesh Chandra

    2002-01-01

    The development of effective non-toxic radioprotective agents is of considerable interest in the improvement of radiotherapy of cancer and protection against unplanned exposures. The synthetic drugs developed in post-world war II have had serious constrains in clinical applicable due to their toxicity at the optimal protective dose. Search for non-toxic protectors from natural sources have indicated that some of the commonly used medicinal plants and the poly herbal formulation could prove to be valuable sources of clinically useful radioprotectors as their ratio of effective dose to toxic dose is very high

  4. Lightning protection design of nuclear power plants. KTA safety code, version 6/99

    International Nuclear Information System (INIS)

    1999-06-01

    This KTA safety code does not cover calculation methods for determination of lightning-induced voltage inputs to control room systems within the reactor building, as the literature presents a variety of applicable methods, which however cannot be directly applied to any power plant, due to the great diversity of geometries of the electrical systems and control room systems in nuclear power plants. Compliance with the design requirements of this safety code for shielding of buildings, and installation and shielding of cables, can be considered to offer the appropriate protection. (orig./CB) [de

  5. Technical evaluation of the electrical, instrumentation, and control design aspects of the low temperature overpressure protection system for the Yankee Rowe nuclear power plant

    International Nuclear Information System (INIS)

    Latorre, V.R.; Mayn, B.G.

    1979-08-01

    This report documents the technical evaluation of the electrical, instrumentation, and control design aspects for the low temperature overpressure protection system of the Yankee Rowe nuclear power plant. Design basis criteria used to evaluate the acceptability of the system included operator action, system testability, single failure criterion, and seismic Category I and IEEE Std-279-1971 criteria

  6. Technical evaluation of the electrical, instrumentation, and control design aspects of the low temperature overpressure protection system for the Maine Yankee nuclear power plant

    International Nuclear Information System (INIS)

    Latorre, V.R.; Mayn, B.G.

    1979-08-01

    This report documents the technical evaluation of the electrical, instrumentation, and control design aspects for the low temperature overpressure protection system of the Maine Yankee nuclear power plant. Design basis criteria used to evaluate the acceptability of the system included operator action, system testability, single failure criterion, and seismic Category I and IEEE Std-279-1971 criteria

  7. The use of process computers in reactor protection systems

    International Nuclear Information System (INIS)

    1973-04-01

    The report contains the papers presented at the LRA information meeting in spring 1972, concerning the use of process computers in reactor protection systems. The main interest was directed at a system conception as proposed from AEG for future BWR-plants. (orig.) [de

  8. The System 80+ Standard Plant design control document. Volume 15

    International Nuclear Information System (INIS)

    1997-01-01

    This Design Control Document (DCD) is a repository of information comprising the System 80+trademark Standard Plant Design. The DCD also provides that design-related information to be incorporated by reference in the design certification rule for the System 80+ Standard Plant Design. Applicants for a combined license pursuant to 10 CFR 52 must ensure that the final Design Certification Rule and the associated Statements of Consideration are used when making all licensing decisions relevant to the System 80+ Standard Plant Design. The Design Control Document contains the DCD introduction, The Certified Design Material (CDM) [i.e., ''Tier 1''] and the Approved Design Material (ADM) [i.e., ''Tier 2''] for the System 80+ Standard Plant Design. The CDM includes the following sections: (1) Introductory material; (2) Certified Design Material for System 80+ systems and structures; (3) Certified Design Material for non-system-based aspects of the System 80+ Certified design; (4) Interface requirements; and (5) Site parameters. The ADM, to the extent applicable for the System 80+ Standard Plant Design, includes: (1) the information required for the final safety analysis report under 20 CFR 50.34; (2) other relevant information required by 10 CFR 52.47; and (3) emergency operations guidelines. This volume contains all five parts of section 12 (Radiation Protection) of the ADM Design and Analysis. Topics covered are: ALARA exposures; radiation sources; radiation protection; dose assessment; and health physics program. All six parts and appendices A and B for section 13 (Conduct of Operations) of the ADM Design and Analysis are also contained in this volume. Topics covered are: organizational structure; training program; emergency planning; review and audit; plant procedures; industrial security; sabotage protection (App 13A); and vital equipment list (App 13B)

  9. A New Physical Protection System Design and Evaluation Process

    Energy Technology Data Exchange (ETDEWEB)

    Lim, Heoksoon; Kim, Myungsu; Bae, Yeongkyoung; Na, Janghwan [KHNP-CRI, Daejeon (Korea, Republic of)

    2014-10-15

    International Atomic Energy Agency(IAEA) had established security-related department and has been strengthening security measures against possible sabotage. IAEA enforces the recommendations for the physical protection of NPPs in the INFCIRC/ 225/Rev.5 to the member states and U.S. NRC also enforces the similar requirements in 10 CFR 73.55. Thus, in order to let Korean NPPs meet the new requirements in INFCIRC/225/Rev.5 or U.S. NRC requirements, Korea nuclear licensee should develop or establish appropriate physical protection system (PPS) design methods for the physical protection of the operating NPPs and new NPPs. KHNP is doing the project of 'Development of APR1400 Physical Protection System Design (2012- 2015, KHNP/KAERI /KEPCO E-C)'. This paper describes overview of a physical protection system (PPS) design and evaluation for an advanced nuclear power plant. It found that a new physical protection system (PPS)design and evaluation. KHNP is doing the project of Physical Protection System design according to U.S. NRC requirements and IAEA requirements in INFCIRC /225 /Rev.5 and will complete by 7.31, 2015 for development of APR1400 Physical Protection System. After completing this project, the results of project are expected to apply new NPPs.

  10. Reactor limitation system improves the safety and availability of the Angra 2 nuclear power plant

    International Nuclear Information System (INIS)

    Souza Mendes, J.E. de

    1987-01-01

    Beyond the classic Reactor Protection System and Reactor Control System, nuclear plant Angra 2 has a third system called Reactor Limitation System which combines the intelligence features of the control systems with the high reliability of the protection systems. In determined events, which are not controlled by the control system (e.g.: load rejection, failure of one main reactor coolant pump), the Reactor Limitation System actuates automatically in order to lead the plant to a safe operating condition and so it avoids the actuation of the Reactor Protection System and consequently the reactor trip. This increases safety and availability of the plant and reduces component stresses. After the safe operating condition is reached, the process guidance automatically returns to the control systems. (Author) [pt

  11. French experience in the programmed systems for nuclear reactor control and protection

    International Nuclear Information System (INIS)

    Jover, P.

    1986-03-01

    The analysis of incidents during the start-up of the first nuclear power plant 1300 MWe has made possible to obtain good performances evaluation of the two computerized control and protection systems: the protection system (SPIN) and the logic control system (CONTROBLOC). The results of this experiment have shown that the objectives have been attained [fr

  12. Defense-in-depth and diversity evaluation to cope with design bases events concurrent with common mode failure in digital plant protection system for KNGR

    International Nuclear Information System (INIS)

    Shin, Lee Cheol; Park, Chan Eok; Jin, Choi Chul; Tae, Seo Jong

    2001-01-01

    The Korean Next Generation Reactor (KNGR) has been evolved to adopt an advanced design feature, a digital Plant Protection System (PPS) as an effort of enhancing reliability and safety of the plant. Although the digital PPS can be designed with high reliability, it is considered to be vulnerable to the Common Mode Failure (CMF) in the system software resulting in a total loss of the built-in hardware redundancy. Therefore, a comprehensive evaluation has been performed to demonstrate the intrinsic capability of the KNGR design in coping with the design basis events concurrent with CMF in the digital PPS. Instead of the conservative bounding analysis methodology, a best-estimate analysis methodology has been developed and utilized since the design basis events accompanied by CMF in the digital PPS are categorized as beyond design bases events. A variety of diverse means such as Alternate Protection System (APS), process control systems, and timely operator actions have been verified to be effective in mitigating the design basis events with CMF in the digital PPS

  13. Technical evaluation of the electrical, instrumentation, and control design aspects of the low temperature overpressure protection system for the Salem nuclear power plant, Unit 1

    International Nuclear Information System (INIS)

    Laudenbach, D.H.

    1979-03-01

    The technical evaluation is presented for the electrical, instrumentation, and control design aspects of the low temperature overpressure protection system for the Salem nuclear power plant, Unit 1. Design basis criteria used to evaluate the acceptability of the system include operator action, system testability, single failure criterion, and seismic Category I and IEEE Std-279-1971 criteria

  14. Technical evaluation report on the monitoring of electric power to the reactor-protection system for the Brunswick Steam Electric Plant, Units 1 and 2

    International Nuclear Information System (INIS)

    Selan, J.C.

    1982-01-01

    This report documents the technical evaluation of the monitoring of electric power to the reactor protection system (RPS) at the Brunswick Steam Electric Plant, Units 1 and 2. The evaluation is to determine if the proposed design modification will protect the RPS from abnormal voltage and frequency conditions which could be supplied from the power supplies and will meet certain requirements set forth by the Nuclear Regulatory Commission. The proposed design modifications with time delays verified by GE, will protect the RPS from sustained abnormal voltage and frequency conditions from the supplying sources

  15. A new career path in radiation protection training. Certified power plant shift supervisor. Radiation protection

    International Nuclear Information System (INIS)

    Terbeek, Christoph

    2011-01-01

    Apart from theoretical knowledge, effective day-to-day radiation protection operations also require a certain measure of practical experience. Therefore, the professional degree of 'Certified Radiation Worker', issued by the Chamber of Industry and Commerce (CIC) Aachen, Germany, established at an early stage. In order to provide experienced radiation protection specialists with an attractive career path, POWERTECH TRAINING CENTER e.V., in co-operation with VGB PowerTech. e.V., the Paul Scherrer Institute (Switzerland) and the Swiss Atomic Energy Agency (ENSI), has devised a new power plant shift supervisor training course specialising in radiation protection. The vocational training degree called 'Certified Power Plant Shift Supervisor - Radiation Protection' is awarded after successful completion of the advanced training examination conducted by the CIC in Essen, Germany. (orig.)

  16. Protecting chemical plants against terrorist attacks: a review

    NARCIS (Netherlands)

    Khakzad Rostami, N.; Reniers, G.L.L.M.E.

    2015-01-01

    Protection of hazardous establishments such as chemical plants intentional incidents has drawn attention from safety and security experts since 9/11 terrorist attacks in the U.S. Although major steps have been taken since, the recent intentional incidents in two chemical plants in France in June and

  17. Inflammatory Effects of the Plant Protection Product Stifenia (FEN560 on Vertebrates

    Directory of Open Access Journals (Sweden)

    Olivier Lamotte

    2017-04-01

    Full Text Available Plant defense stimulators (PDSs rely on the activation of plant innate immunity in order to protect crops against various pests. These molecules are thought to be a safer alternative to classical plant protection products. Given that innate immune systems share common features in plants and vertebrates, PDS can potentially cross-react with innate immunity of non-target organisms. To test this hypothesis, we studied effects of the commercial PDS Stifenia (FEN560, which is composed of crushed fenugreek seeds. We tested various concentrations of Stifenia (0.03–1 mg mL−1 on human peripheral blood mononuclear cells and checked, 20 h later, cell metabolic activity (MA using XTT assay, cell death by flow cytometry analysis, and IL-1β inflammatory cytokine released in the culture medium using ELISA. Stifenia induced a general decrease of the cell MA, which was concomitant with a dose-dependent release of IL-1β. Our results highlight the activation of human immune cells. The inflammatory effect of Stifenia was partially inhibited by pan-caspase inhibitor. Accordingly, Stifenia induced the release of p20 caspase-1 fragment into the culture medium suggesting the involvement of the NLRP3 inflammasome. Furthermore, we observed that Stifenia can induce cell death. We also tested the effect of Stifenia on Zebrafish larvae. After 24 h of exposure, Stifenia induced a dose-dependent IL-1β and TNFα gene expression. The human-cell-based approach developed in this work revealed a high sensitivity concerning inflammatory properties of a plant protection product. These tests could be routinely used to screen the potential adverse effects of this type of compounds. Finally, our results suggest a potential danger of using extensively certain PDS for crop protection.

  18. Protective Effect against Oxidative Stress in Medicinal Plant Extracts

    International Nuclear Information System (INIS)

    Kim, Jeong Hee; Lee, Eun Ju; Shin, Dong O; Hong, Sung Eun; Kim, Jin Kyu

    2000-01-01

    Protective effect of medicinal plant extracts against oxidative stress were screened in this study. Methanol extracts from 48 medicinal plants, which were reported to have antioxidative or anti-inflammatory effect were prepared and screened for their protective activity against chemically-induced and radiation-induced oxidative stress by using MTT assay. Thirty three samples showed protective activity against chemically-induced oxidative stress in various extent. Among those samples, extract of Glycyrrhiza uralensis revealed the strongest activity (25.9% at 100 μg/ml) with relatively lower cytotoxicity. Seven other samples showed higher than 20% protection at 100 μg/ml. These samples were tested for protection activity against radiation-induced oxidative stress. Methanol extract of Alpina officinarum showed the highest activity (17.8% at 20 μg/ml). Five fractions were prepared from the each 10 methanol extracts which showed high protective activity against oxidative stress. Among those fraction samples butanol fractions of Areca catechu var. dulcissima and Spirodela polyrrhiza showed the highest protective activities (78.8% and 77.2%, respectively, at 20 μg/ml)

  19. Course in fire protection training for nuclear power plant personnel

    International Nuclear Information System (INIS)

    Walker, K.L.; Bates, E.F.; Randall, J.D.

    1979-01-01

    Proposed Regulatory Guide 1.120, entitled ''Fire Protection Guidelines for Nuclear Power Plants,'' provides detailed requirements for the overall fire protection programs at nuclear power plant sites in the United States. An essential element in such a program in the training of plant fire brigade personnel is the use of proper firefighting techniques and equipment. The Texas A and M University Nuclear Science Center (NSC) in conjunction with the Fire Protection Training Division of the Texas Engineering Extension Service has developed a one-week course to meet this training need. The program emphasizes hands-on exercises. The course is designed for up to 18 students with all protective clothing provided. Fire instructors are certified by the State of Texas, and registered nuclear engineers and certified health physicists supervise the radiological safety exercises. The first course was conducted during the week of January 8--12, 1979

  20. BIODIVERSITY AND THE PROTECTED AREAS SYSTEM IN ALBANIA

    Directory of Open Access Journals (Sweden)

    Mehmet Metaj

    2009-06-01

    Full Text Available Albania possesses a wide range of ecological systems including coastal zones, estuaries and lagoons, lakes and wetlands, grasslands, middle-low altitude coppice forests, high altitude forests, alpine vegetation and glacial areas. The country possesses about 3,250 species of vascular plants, 165 families and more than 900 genera. Medicinal plants (botanicals and non-timber forest products have a long history of importance in the culture and traditional knowledge of Albania. Proper legislation and especially legal and regulatory framework enforcement for the regulation of this developing industry remains lacking. A Strategy of Biodiversity plan developed in 2000 calls for an increase in the Protected Areas system which currently covers some 6 % of Albania's area to a total area of 435,600 ha, approximately 15 % of the country's territory. Changes in the legal and policy framework as well as institutional structures is required to move forward and provide an environment for biodiversity conservation and a sustainable protected areas system. The various threats to biodiversity and constraints to improvement are outlined as well as recommendations for sustainable use, assessment and regulation.

  1. Arrangement of the Krsko NPP protection scheme for the power system malfunction cases

    International Nuclear Information System (INIS)

    Omahen, P.; Pavsek, J.; Dirnbek, V.

    1996-01-01

    The Krsko NPP has been designed with the capability to reject 100% of its rated power and runback to the station electrical load. However, an adequate detection system of the outside network degradation is needed for the activation of the existing load drop anticipated (LDA) function. The Krsko NPP electrical, turbine and generator protection systems were carefully evaluated in order to redesign some of its functions. These additional functions should be able to protect and disconnect the plant from the system whenever some serious trouble of the outside electric power system is detected. On the other side, preventive measures should be introduced to avoid unnecessary plant disconnection or unnecessary power system collapse due to such disconnection. At the end, the paper presents a precise design of additional function possibilities for the Krsko NPP electrical protection system. A critical evaluation of these functions is given and the best option is proposed. (author)

  2. Seaweed Polysaccharides and Derived Oligosaccharides Stimulate Defense Responses and Protection Against Pathogens in Plants

    Directory of Open Access Journals (Sweden)

    Alejandra Moenne

    2011-11-01

    Full Text Available Plants interact with the environment by sensing “non-self” molecules called elicitors derived from pathogens or other sources. These molecules bind to specific receptors located in the plasma membrane and trigger defense responses leading to protection against pathogens. In particular, it has been shown that cell wall and storage polysaccharides from green, brown and red seaweeds (marine macroalgae corresponding to ulvans, alginates, fucans, laminarin and carrageenans can trigger defense responses in plants enhancing protection against pathogens. In addition, oligosaccharides obtained by depolymerization of seaweed polysaccharides also induce protection against viral, fungal and bacterial infections in plants. In particular, most seaweed polysaccharides and derived oligosaccharides trigger an initial oxidative burst at local level and the activation of salicylic (SA, jasmonic acid (JA and/or ethylene signaling pathways at systemic level. The activation of these signaling pathways leads to an increased expression of genes encoding: (i Pathogenesis-Related (PR proteins with antifungal and antibacterial activities; (ii defense enzymes such as pheylalanine ammonia lyase (PAL and lipoxygenase (LOX which determine accumulation of phenylpropanoid compounds (PPCs and oxylipins with antiviral, antifugal and antibacterial activities and iii enzymes involved in synthesis of terpenes, terpenoids and/or alkaloids having antimicrobial activities. Thus, seaweed polysaccharides and their derived oligosaccharides induced the accumulation of proteins and compounds with antimicrobial activities that determine, at least in part, the enhanced protection against pathogens in plants.

  3. Using Patents to Protect Traditional Knowledge on the Medicinal Uses of Plants in South Africa

    Directory of Open Access Journals (Sweden)

    Emeka Polycarp Amechi

    2015-06-01

    Full Text Available The movement towards the protection of traditional knowledge particularly on the medicinal uses of plants (TKMUP in South Africa reflects a global albeit belated interest in the protection of traditional knowledge associated with biological resources. Hence, it was not surprising South Africa like most developing nation, sought in response to instances of the misappropriation of its TKMUP and other TK associated with its biological resources, to provide a measure of protection for such knowledge using the intellectual property (IP system. This is evident in the adoption of the Policy Framework for the Protection of Indigenous Knowledge through the Intellectual Property System in 2008 which identified patent as one of the major IP tools in the protection of the TK. The Policy Framework represents a paradigmatic shift from South Africa’s earlier sceptical and dialectical approach to, and experience with the IP system in context of TK. This paper therefore examines the benefits and challenges involved in using the patent system in the protection of TK particularly those relating to the medicinal uses of plants (TKMUP. Such examination became necessary as South Africa’s natural capital of biological diversity, together with its wealth of indigenous TK, has been recognised as an important resource base for promoting economic growth through biological innovations under the recently adopted Bio-economy Strategy. It finds that patents offer a great potential in not only protecting TKMUP from misappropriation, but also in promoting the commercialisation of innovative TKMUP or inventions based on or derived from TKMUP in South Africa. However, this can only be possible if the challenges identified in this paper can be successfully navigated.

  4. Safety and radiation protection in Indian nuclear power plants

    International Nuclear Information System (INIS)

    Ghadge, S.G.

    2008-01-01

    Full text: Nuclear energy, an important option for electricity generation is environment friendly, technologically proven, economically competitive and associated with the advantages of energy security and diversity. At present, India has an installed nuclear power generation capacity of 4120 M We with 6 more reactors are under construction/ commissioning at 4 sites. Nuclear power program, in India, as of now is primarily based on pressurized heavy water technology and these reactors are designed with safety features, such as, independent and diverse shut down systems, emergency core cooling system, double containment; pressure suppression pool etc. The principles of redundancy, diversity, fail-safe and passive systems are used in the design. The fundamental safety objective is to protect people and the environment from harmful effects of ionizing radiation. In this regard the prime responsibility for safety rests with the organization responsible for facilities and activities that give rise to radiation risks and is achieved by establishing and maintaining the necessary competence, providing adequate training and information, establishing procedures and arrangements to maintain safety under all conditions; verifying appropriate design and the adequate quality of facilities and activities and of their associated equipment; ensuring the safe control of all radioactive material that is used, produced, stored or transported, ensuring the safe control of all radioactive waste that is generated. 'Radiation Protection for Nuclear Facilities', issued by Atomic Energy Regulatory Board (the regulatory authority for NPPs in India) is the basic document for following radiation protection procedures in NPPs. Approved work procedures for all radiation jobs exist. Pre job briefing and post job analysis are carried out. Radiation protection is integrated with plant operation. Radiation levels indicate the performance of several systems. Several measures are adopted in design and

  5. Radiological respiratory protection in Angra-1 Nuclear Power Plant

    International Nuclear Information System (INIS)

    Amaral, Marcos A. do

    1996-01-01

    The present paper has the purpose to describe the actual situation of the Radiological respiratory Protection in Angra I Nuclear Power Plant, the difficulties found and the goals to achieve, in order of the radiological protection excellence. (author)

  6. Adoption of digital safety protection system in Japan

    International Nuclear Information System (INIS)

    Ogiso, Z.

    1998-01-01

    The application of micro-processor-based digital controllers has been widely propagated among various industries in recent years. While in the nuclear power plant industry, the application of them has also been expanding gradually starting from non-safety related systems, taking advantage of their reliability and maintainability over the conventional analog devices. Based on the careful study of the feasibility of digital controllers to the safety protection system, the Tokyo Electric Power Company proposed on May 1989 the adoption of digital controllers to the safety protection system in the Application for Permission of Establishment of Kashiwazaki-Kariwa units 6 and 7 (ABWR-1350Mwe each). MITI, Ministry of International Trade and Industry, the Japanese regulatory body for electric power generating facilities, had approved this application after careful review. This paper describes a series of supporting activities leading to the MITI's approval of the digital safety protection system and the MITI's licensing activities. (author)

  7. Erosion Corrosion and Protection of Recycle System with Seawater

    Directory of Open Access Journals (Sweden)

    Xue Jin

    2016-01-01

    Full Text Available In order to investigate the corrosion of recycle system with seawater in rights of power plant, the erosion behavior and mechanism of erosion corrosion in this system constructed with several corrosionresistance alloys have been studied and tested in the condition of high speed fluid with a sand particles. Both special protection technologies and results, one designed by high temperature epoxy resin powder coating and another of the associating method of anode protection together with such same coating, have been discussed as well in this case.

  8. Political problems in the system of radiation protection laws of Japan

    International Nuclear Information System (INIS)

    Nakagawa, Haruo

    2008-01-01

    The lack of hierarchy and multiple restrictions by the radiation protection laws in Japan, causes multiple dose records of individual and scattering dose records. To solve the problem, the National Radiation Dose Registration Systems was proposed already by Atomic Energy Commission about 40 years ago. But only one radiation dose registration system is partly effective, which was applied for workers in nuclear plants. This paper reports political problems in the system of radiation protection laws of Japan, and proposes the new national radiation dose registration systems which will be able to have a function of supplementation of quality assurance of radiation protection laws. (author)

  9. Fire protection guidelines for nuclear power plants

    International Nuclear Information System (INIS)

    1976-06-01

    Guidelines acceptable to the NRC staff for implementing in the development of a fire protection program for nuclear power plants. The purpose of the fire protection program is to ensure the capability to shut down the reactor and maintain it in a safe shutdown condition and to minimize radioactive releases to the environment in the event of a fire. If designs or methods different from the guidelines presented herein are used, they must provide fire protection comparable to that recommended in the guidelines. Suitable bases and justification should be provided for alternative approaches to establish acceptable implementaion of General Design Criterion 3

  10. Design aspects of radiation protection for nuclear power plants

    International Nuclear Information System (INIS)

    1985-01-01

    This Safety Guide deals with the provisions to be made in the design of thermal neutron reactor power plants to protect site personnel and the public from undue exposure to ionizing radiation during operational states and accident conditions. The effective radiation protection is a combination of good design, high quality construction and proper operation. The document gives guidance on how to satisfy the objectives contained in Subsection 2.2 and Section 9 of the Code of Practice on Design for Safety of Nuclear Power Plants

  11. Interactions among predators and plant specificity protect herbivores from top predators.

    Science.gov (United States)

    Bosc, Christopher; Pauw, Anton; Roets, Francois; Hui, Cang

    2018-05-04

    The worldwide loss of top predators from natural and agricultural systems has heightened the need to understand how important they are in controlling herbivore abundance. The effect of top predators on herbivore species is likely to depend on 1) the importance of the consumption of intermediate predators by top predators (intra-guild predation; IGP), but also on 2) plant specificity by herbivores, because specialists may defend themselves better (enemy-free space; EFS). Insectivorous birds, as top predators, are generally known to effectively control herbivorous insects, despite also consuming intermediate predators such as spiders, but how this effect varies among herbivore species in relation to the cascading effects of IGP and EFS is not known. To explore this, we excluded birds from natural fynbos vegetation in South Africa using large netted cages and recorded changes in abundance relative to control plots for 199 plant-dwelling intermediate predator and 341 herbivore morpho-species that varied in their estimated plant specificity. We found a strong negative effect of birds on the total abundance of all intermediate predators, with especially clear effects on spiders (strong IGP). In contrast with previous studies, which document a negative effect of birds on herbivores, we found an overall neutral effect of birds on herbivore abundance, but the effect varied among species: some species were negatively affected by birds, suggesting that they were mainly consumed by birds, whereas others, likely released from spiders by IGP, were positively affected. Some species were also effectively neutrally affected by birds. These tended to be more specialized to plants compared to the other species, which may imply that some plant specialists benefited from protection provided by EFS from both birds and spiders. These results suggest that the response of herbivore species to top predators may depend on cascading effects of interactions among predators and on their degree

  12. Analysis of fire protection in nuclear power plants

    International Nuclear Information System (INIS)

    Hosser, D.; Schneider, U.

    1982-01-01

    Regulations and test specifications for fire prevention in nuclear power plants are presented as well as the fire protection measures in a newly constructed nuclear power plant. Although the emphasis is placed differently, all rules are based on the following single measures: Fire prevention, fire detection, fire fighting, fire checking, attack, flight, and rescue, organisational measures. (orig./GL) [de

  13. Analysis of the impact of connecting a larger number of small hydroelectric power plants to the short-circuit currents values and relay protection system of distribution network

    Directory of Open Access Journals (Sweden)

    Sučević Nikola

    2017-01-01

    Full Text Available In this paper the influence of a large number of small hydro power plants on the short-circuit currents is analysed, as well as the operation of the relay protection system within the real distribution network in Serbia. The necessary modification of the existing protection functions, as well as the implementation of the new proposed protection functions, are presented and discussed. Network modeling and analysis are performed using the program tool DIgSILENT PowerFactory.

  14. Use of digital computers in the protection system for Savannah River reactors

    International Nuclear Information System (INIS)

    Gimmy, K.L.

    1977-06-01

    Each production reactor at the Savannah River Plant has recently been provided with a protective system using dual digital computers. The dual ''safety computers'' monitor coolant temperature and flow in each of the 600 fuel assemblies in the reactor. The system provides alarms and automatic reactor shutdown (SCRAM) if these variables exceed predetermined setpoints. The system provides the primary protection for unwanted local or general power increase or assembly coolant flow reduction. Standard process control computers are used and all scanning, data output, and protective action are controlled by software prepared by Du Pont

  15. Safety assessment principles for reactor protection systems in the United Kingdom

    International Nuclear Information System (INIS)

    Philp, W.

    1990-01-01

    The duty of Nuclear Installations Inspectorate (NII) is to see that the appropriate standards are developed, achieved and maintained by the plant operators, and to monitor and regulate the safety of the plant by means of its powers under the licence. It does not issue standards or codes of practice for NPPs, but it requires each plant operator to develop its own safety criteria and requirements. The following relevant issues are described: NII assessment principles and societal risks; principles and guidance for the assessment of rector protection systems; assessment of reactor shutdown systems

  16. Safety assessment principles for reactor protection systems in the United Kingdom

    Energy Technology Data Exchange (ETDEWEB)

    Philp, W

    1990-07-01

    The duty of Nuclear Installations Inspectorate (NII) is to see that the appropriate standards are developed, achieved and maintained by the plant operators, and to monitor and regulate the safety of the plant by means of its powers under the licence. It does not issue standards or codes of practice for NPPs, but it requires each plant operator to develop its own safety criteria and requirements. The following relevant issues are described: NII assessment principles and societal risks; principles and guidance for the assessment of rector protection systems; assessment of reactor shutdown systems.

  17. Radiation protection during operation of nuclear power plants

    International Nuclear Information System (INIS)

    1983-01-01

    This Guide describes a Radiation Protection Programme for nuclear power plants. It includes: (1) An outline of the basic principles as well as practical aspects of the programme; (2) A description of the responsibilities of the operating organization to establish an effective programme based upon these principles; (3) A description of the administrative and technical measures to establish and implement the programme. This Guide also deals with the operational aspects to be considered by the operating organization in reviewing design in order to facilitate implementation of the Radiation Protection Programme. This Guide covers the requirements for a Radiation Protection Programme for all operational states of the nuclear power plant. It also includes guidelines for handling planned special exposures and for coping with unplanned exposures and contamination of personnel, areas, and equipment. Additional information concerning emergency situations involving releases of radioactive materials is given in Safety Guides 50-SG-O6, ''Preparedness of the Operating Organization (Licensee) for Emergencies at Nuclear Power Plants'', and 50-SG-G6, ''Preparedness of Public Authorities for Emergencies at Nuclear Power Plants''. This Guide covers the principles of dose limitation to site personnel and to the public, but it does not include detailed instructions on the techniques used for the actual measurement and evaluation of the exposures. This Guide does not include detailed instructions on environmental surveys, but it does mention principal steps in environmental monitoring which may be required for confirmation of the acceptability of radioactive discharges

  18. Extensions and renovations of reactor protection systems

    International Nuclear Information System (INIS)

    Hellmerichs, K.

    1985-01-01

    Increase of requirements by the authorities as to the design of reactor protection systems affected in the last years not only plans being under construction, but also resulted in partly spacious extensions and renovations. While working on the extensions and renovations a lot of problems arose: far-reaching performance of newest guidelines and rules in spite of old plant concepts; partly higher degree of redundancy requirements of the new systems in contrast to the present systems; use of present safeguard systems for new accident countermeasures; designation of priorities between present and new functions, especially in view of fault behaviour of present systems; adaptation of the new I and C equipment to the present signalisation-, operation- and information-arrangements under consideration of the present operational philosophy; spatial incorporation of new equipments; construction as to time without expanding of the planned refuelling phases. Because the KWU has planned and constructed such alterations in nearly 10 plants a lot of experience has been gathered. (author)

  19. Habitat models to assist plant protection efforts in Shenandoah National Park, Virginia, USA

    Science.gov (United States)

    Van Manen, F.T.; Young, J.A.; Thatcher, C.A.; Cass, W.B.; Ulrey, C.

    2005-01-01

    During 2002, the National Park Service initiated a demonstration project to develop science-based law enforcement strategies for the protection of at-risk natural resources, including American ginseng (Panax quinquefolius L.), bloodroot (Sanguinaria canadensis L.), and black cohosh (Cimicifuga racemosa (L.) Nutt. [syn. Actaea racemosa L.]). Harvest pressure on these species is increasing because of the growing herbal remedy market. We developed habitat models for Shenandoah National Park and the northern portion of the Blue Ridge Parkway to determine the distribution of favorable habitats of these three plant species and to demonstrate the use of that information to support plant protection activities. We compiled locations for the three plant species to delineate favorable habitats with a geographic information system (GIS). We mapped potential habitat quality for each species by calculating a multivariate statistic, Mahalanobis distance, based on GIS layers that characterized the topography, land cover, and geology of the plant locations (10-m resolution). We tested model performance with an independent dataset of plant locations, which indicated a significant relationship between Mahalanobis distance values and species occurrence. We also generated null models by examining the distribution of the Mahalanobis distance values had plants been distributed randomly. For all species, the habitat models performed markedly better than their respective null models. We used our models to direct field searches to the most favorable habitats, resulting in a sizeable number of new plant locations (82 ginseng, 73 bloodroot, and 139 black cohosh locations). The odds of finding new plant locations based on the habitat models were 4.5 (black cohosh) to 12.3 (American ginseng) times greater than random searches; thus, the habitat models can be used to improve the efficiency of plant protection efforts, (e.g., marking of plants, law enforcement activities). The field searches also

  20. Machine protection systems

    CERN Document Server

    Macpherson, A L

    2010-01-01

    A summary of the Machine Protection System of the LHC is given, with particular attention given to the outstanding issues to be addressed, rather than the successes of the machine protection system from the 2009 run. In particular, the issues of Safe Machine Parameter system, collimation and beam cleaning, the beam dump system and abort gap cleaning, injection and dump protection, and the overall machine protection program for the upcoming run are summarised.

  1. Ultraviolet-B-effects on plants: Spectra of harmful effects, primary damage and UV protective mechanisms

    International Nuclear Information System (INIS)

    Wellmann, E.; Beggs, C.; Moehle, B.; Schneider-Ziebert, U.; Steinmetz, V.; Koch, U.

    1986-01-01

    In two model systems of higher plants, damage caused by ultraviolet-B-radiation was analysed as to its mechanism of action and the spectral quantum efficiency. These investigations were to provide information on the relevance of such UV effects in cases of increased ultraviolet-B-irradiation owing to the destruction of ozone. The results indicate the very high tolerance of the plants to ultraviolet-B-radiation which obviously is the result of very effective protective mechanisms, and show at the same time that potential damage must already be reckoned with, given the current share of ultraviolet-B-radiation in solar radiation. Should ultraviolet-B-radiation be increased, then indirect damage to the plant from the destruction of ultraviolet protective mechanisms through UV-B-radiation will probably constitute a particular risk. (orig./MG) [de

  2. Dependability Evaluation of Advanced Diverse Protection System

    International Nuclear Information System (INIS)

    Oh, Yang Gyun; Lee, Yoon Hee; Sohn, Se Do; Baek, Seung Min; Lee, Sang Jeong

    2014-01-01

    For the mitigation of anticipated transients without scram (ATWS) as well as common cause failure (CCF) within the plant protection system (PPS) and the emergency safety feature . component control system (ESF-CCS), the diverse protection system (DPS) has been designed by KEPCO Engineering and Construction Company. Recently KEPCO E and C has developed the advanced diverse protection system (ADPS), which has four redundant channels, in an attempt to enhance a fault-tolerant capability of the system. For the evaluation of overall system improvement effects of the ADPS compared with the DPS, the dependability evaluation results are described herein. For all dependability attributes, this paper suggests a practical dependability evaluation method which uses quantitative dependability scores and indices. An overall dependability evaluation index (DEI) for the ADPS is evaluated with the average value of reliability/ security/maintainability/safety indices (i.e., RID, SID, MID, and SID') for dependability. The evaluation results show that the DEI value of ADPS can be improved by approximately 23% compared with that of the DPS, thanks to its fault-tolerant system architecture, software design changes, and external interface design features. Several suggestions have been made, in this paper, of an overall quantitative dependability evaluation method for the nuclear instrumentation and control (I and C) systems including the DPS and ADPS, and the usefulness of dependability evaluation on nuclear I and C systems has been confirmed

  3. Plant protection system optimization studies to mitigate consequences of large breaks in the advanced neutron source reactor

    International Nuclear Information System (INIS)

    Khayat, M.I.; March-Leuba, J.

    1993-01-01

    This paper documents some of the optimization studies performed to maximize the performance of the engineered safety features and scram systems to mitigate the consequences of large breaks in the primary cooling system of the advanced neutron source (ANS) reactor. The ANS is a new basic and applied research facility based on a powerful steady-state research reactor that provides beams of neutrons for measurements and experiments in the field of material science and engineering, biology, chemistry, material analysis, and nuclear science. To achieve the high neutron fluxes for these state-of-the-art experiments, the ANS design has a very high power density core (330 MW fission with an active volume of 67.6 ell) surrounded by a large heavy-water reflector, where most neutrons are moderated. This design maximizes the number of neutrons available for experiments but results in a low heat capacity core that creates unique challenges to the design of the plant protection system

  4. State-of-the-art explosion protection for dedusting of coal grinding plants; Explosionsschutz fuer die Entstaubung von Kohlemahlanlagen

    Energy Technology Data Exchange (ETDEWEB)

    Neuhaus, Tim [Intensiv-Filter GmbH und Co. KG, Velbert-Langenberg (Germany). Development; Schrooten, Theo [Intensiv-Filter GmbH und Co. KG, Velbert-Langenberg (Germany). Technology Dept.; Baldauf, Joerg [Thorwesten Vent GmbH, Beckum (Germany). Sales

    2010-07-01

    With dedusting of coal grinding plants, the state of the technology is determined by the explosion protection measures, the filtration performance and the design of the plant. To ensure safe operation of a plant, only certified and tested concepts and components should be used for its design and manufacture. With plants protected against explosion, such issues will always affect the plant's resistance, its explosion relief venting and its explosion decoupling systems. Economic factors, where the aim is minimising the filter level and lean design, should not be forgotten with dedusting and it is important that plants are aligned to the latest state of technological development. With their years of experience and continuing development in the area of dedusting for coal grinding plants, Intensiv-Filter and Thorwesten Vent have succeeded in implementing the state of the art. (orig.)

  5. Plant nematodes in South Africa. 11. Checklist of plant nematodes of the protected areas of KwaZulu-Natal

    Directory of Open Access Journals (Sweden)

    Mariette Marais

    2013-03-01

    Full Text Available Nematodes are some of the most abundant soil organisms and are an essential part of soil ecology. These organisms are used as indicator organisms and can be linked to soil health. Biological collections contain vast amounts of data, with the National Collection of Nematodes housed at the Plant Protection Research Institute, Agricultural Research Council being no different. During the digitising of the collection a number of unpublished records of plant nematodes reported from protected areas in KwaZulu-Natal were found in the South African Plant-Parasitic Nematode Survey database. A total of 222 plant nematode species belonging to 39 genera were reported from the province, with only 94 of these species reported from the protected areas and 172 and 159 species reported from uncultivated (outside the protected areas and cultivated areas, respectively. Only nine species, Criconema silvum, Criconema talanum, Helicotylenchus marethae, Ogma dracomontanum, Ogma louisi, Ogma ueckermanni, Paralongidorus deborae, Trichodorus rinae and Xiphinemella marindae were described from protected areas, whilst O. dracomontanum, P. deborae and T. rinae were subsequently also reported from other provinces. Conservation implications: A higher degree of diversity of nematodes was observed in the unprotected areas of the province. The observation suggests that nematode fauna, and by implication also other invertebrates, are not adequately protected.

  6. Plant nematodes in South Africa. 11. Checklist of plant nematodes of the protected areas of KwaZulu-Natal

    Directory of Open Access Journals (Sweden)

    Mariette Marais

    2013-02-01

    Full Text Available Nematodes are some of the most abundant soil organisms and are an essential part of soil ecology. These organisms are used as indicator organisms and can be linked to soil health. Biological collections contain vast amounts of data, with the National Collection of Nematodes housed at the Plant Protection Research Institute, Agricultural Research Council being no different. During the digitising of the collection a number of unpublished records of plant nematodes reported from protected areas in KwaZulu-Natal were found in the South African Plant-Parasitic Nematode Survey database. A total of 222 plant nematode species belonging to 39 genera were reported from the province, with only 94 of these species reported from the protected areas and 172 and 159 species reported from uncultivated (outside the protected areas and cultivated areas, respectively. Only nine species, Criconema silvum, Criconema talanum, Helicotylenchus marethae, Ogma dracomontanum, Ogma louisi, Ogma ueckermanni, Paralongidorus deborae, Trichodorus rinae and Xiphinemella marindae were described from protected areas, whilst O. dracomontanum, P. deborae and T. rinae were subsequently also reported from other provinces. Conservation implications: A higher degree of diversity of nematodes was observed in the unprotected areas of the province. The observation suggests that nematode fauna, and by implication also other invertebrates, are not adequately protected.

  7. Material protection control and accounting program activities at the Urals electrochemical integrated plant

    International Nuclear Information System (INIS)

    McAllister, S.

    1997-01-01

    The Urals Electrochemical Integrated Plant (UEIP) is the Russian Federation's largest uranium enrichment plant and one of three sites in Russia blending high enriched uranium (HEU) into commercial grade low enriched uranium. UEIP is located approximately 70 km north of Yekaterinburg in the closed city of Novouralsk (formerly Sverdlovsk- 44). DOE's MPC ampersand A program first met with UEIP in June of 1996, however because of some contractual issues the work did not start until September of 1997. The six national laboratories participating in DOE's Material Protection Control and Accounting program are cooperating with UEIP to enhance the capabilities of the physical protection, access control, and nuclear material control and accounting systems. The MPC ampersand A work at UEIP is expected to be completed during fiscal year 2001

  8. Training of fire protection personnel in nuclear power plants

    International Nuclear Information System (INIS)

    Blaser, W.

    1980-01-01

    Training of fire protection personnel in nuclear power plants is divided up in three categories: training of fire protection commissioners which is mostly carried out externally; training of fire fighting personnel in the form of basic and repeated training usually by the fire protection commissioner; training of other employers with regard to behaviour in case of fire and during work involving a fire hazard. (orig.) [de

  9. Measures for the explosion protection for gas systems; Massnahmen des Explosionsschutzes fuer Gasanlagen

    Energy Technology Data Exchange (ETDEWEB)

    Faber, Wolfgang [Thyssengas GmbH, Duisburg (Germany). Anlagentechnik Nord; Seemann, Albert [BG ETEM Berufsgenossenschaft Energie Textil Elektro Medienerzeugnisse, Koeln (Germany)

    2012-04-15

    In order to protect employees, technical and organizational measures for explosion protection have to be provided to gas plants with potentially explosive areas. These measures have to be documented in the explosion protection document in accordance with paragraph 6 section 1 of the regulation of industrial safety. The contribution under consideration presents an overview on the measures for explosion protection for gas systems.

  10. Preliminary Uncertainty Analysis for SMART Digital Core Protection and Monitoring System

    International Nuclear Information System (INIS)

    Koo, Bon Seung; In, Wang Kee; Hwang, Dae Hyun

    2012-01-01

    The Korea Atomic Energy Research Institute (KAERI) developed on-line digital core protection and monitoring systems, called SCOPS and SCOMS as a part of SMART plant protection and monitoring system. SCOPS simplified the protection system by directly connecting the four RSPT signals to each core protection channel and eliminated the control element assembly calculator (CEAC) hardware. SCOMS adopted DPCM3D method in synthesizing core power distribution instead of Fourier expansion method being used in conventional PWRs. The DPCM3D method produces a synthetic 3-D power distribution by coupling a neutronics code and measured in-core detector signals. The overall uncertainty analysis methodology which is used statistically combining uncertainty components of SMART core protection and monitoring system was developed. In this paper, preliminary overall uncertainty factors for SCOPS/SCOMS of SMART initial core were evaluated by applying newly developed uncertainty analysis method

  11. Current trends towards a new regulation and evolution of fire protection systems technologies in nuclear power plants

    International Nuclear Information System (INIS)

    Rodriguez Sanjuan, G.

    1996-01-01

    For some time now, the field of Fire Protection in Nuclear Power Plants has, with its own peculiarities in an otherwise general process, been the centre of some controversy caused by tendencies to reduce regulatory inflexibility by transforming what was originally a prescriptive, pro grammatical and deterministic regulatory system into a system based on risk assessment and operating experience. Such tendencies include: Cost Beneficial Licensing Actions (CBLA) Use of the Probabilistic Safety Analysis (PSA) as a tool for evaluating the impact of postulated fires in nuclear safety Improvement of communications between the regulatory body and the industry These trends have coincided with the arduous process of requalifying passive fire-resistant protection materials, such as Thermo lag and others, which are used to separate redundant Safe Shutdown trains with fire-resistance ranges of one (1) hour or three (3) hours, in compliance with some of the alternatives that Appendix R to 10 CFR 50 offers. The process has involved a lot of effort and financial cost in requalification and in employing compensatory measures until operability of the fire-resistant materials is reestablished. A new test methodology has been created for these barriers (GL 86-10, Supplement 1) and new materials have become available and are currently undergoing qualification. (Author)

  12. 7 CFR 371.3 - Plant protection and quarantine.

    Science.gov (United States)

    2010-01-01

    ...) Regulating the field release into the environment, interstate movement, and importation of genetically modified organisms. (7) Serving as a member of the North American Plant Protection Organization (NAPPO...

  13. Support of protective work of human error in a nuclear power plant

    International Nuclear Information System (INIS)

    Yoshizawa, Yuriko

    1999-01-01

    The nuclear power plant human factor group of the Tokyo Electric Power Co., Ltd. supports various protective work of human error conducted at the nuclear power plant. Its main researching theme are studies on human factor on operation of a nuclear power plant, and on recovery and common basic study on human factor. In addition, on a base of the obtained informations, assistance to protective work of human error conducted at the nuclear power plant as well as development for its actual use was also promoted. Especially, for actions sharing some dangerous informations, various assistances such as a proposal on actual example analytical method to effectively understand a dangerous information not facially but faithfully, construction of a data base to conveniently share such dangerous information, and practice on non-accident business survey for a hint of effective promotion of the protection work, were promoted. Here were introduced on assistance and investigation for effective sharing of the dangerous informations for various actions on protection of human error mainly conducted in nuclear power plant. (G.K.)

  14. Radiological protection and nuclear power plants

    International Nuclear Information System (INIS)

    Delpla, M.

    Dosimetric results obtained inside and outside nuclear power plants are examined with a review to proposing revision of the radiological protection standards. Dose limits are considered with regard to leukemia and genetic effects. Other topics discussed are: observed collective damage and mean risk; lethal exposure; healing and sign change of additional risk; and genetic effects of radiation on mice

  15. 78 FR 55765 - Compensatory and Alternative Regulatory Measures for Nuclear Power Plant Fire Protection (CARMEN...

    Science.gov (United States)

    2013-09-11

    ... Nuclear Power Plant Fire Protection (CARMEN-FIRE) AGENCY: Nuclear Regulatory Commission. ACTION: Draft..., ``Compensatory and Alternative Regulatory Measures for Nuclear Power Plant Fire Protection (CARMEN-FIRE).'' In... caused by impaired fire protection features at nuclear power plants. The report documents the history of...

  16. Radiation protection/shield design: a need for a systems approach

    International Nuclear Information System (INIS)

    Disney, R.K.

    1977-01-01

    Radiation protection/shielding design of a nuclear facility requires a coordinated effort of many engineering disciplines to meet the requirements imposed by regulations. The system approach to Clinch River Breeder Reactor Plant (CRBRP) radiation protection is described, and the program developed to implement this approach is defined. In addition, the principal shielding design problems for LMFBR nuclear reactor systems are discussed in relation to LWR nuclear reactor system shielding designs. The methodology used to analyze these problems in the U.S. LMFBR program, the resultant design solutions, and the experimental verification of these designs and/or methods are discussed

  17. Plant protection in post-Soviet Kazakhstan: the loss of an ecological perspective

    NARCIS (Netherlands)

    Toleubayev, K.

    2009-01-01

    This thesis examines why and how plant protection issues are embedded in political, economic and social contexts. It analyses the domain of plant protection in Kazakhstan under two different socio-economic and political formations, namely the Soviet period before 1991 and the post-Soviet period

  18. The Automatic Test Features of the IDiPS Reactor Protection System

    International Nuclear Information System (INIS)

    Hur, Seop; Kim, Dong-Hoon; Hwang, In-Koo; Lee, Cheol-Kwon; Lee, Dong-Young

    2007-01-01

    The reactor protection system (RPS) is designed to minimize a propagation of abnormal or accident conditions of nuclear power plants. A digital RPS (Integrated Digital Protection System (IDiPS) RPS) is being developed in the Korea Nuclear Instrumentation and Control System (KNICS) R and D project. To make good use of the advantages of the digital technology, it is necessary to improve the reliability and availability of a system through automatic test features including an on-line testing, a self-diagnostics, an auto calibration, etc. This paper summarizes the system test strategy and the automatic test features of the IDiPS RPS

  19. Engineering development of a digital replacement protection system at an operating US PWR nuclear power plant: Installation and operational experiences

    International Nuclear Information System (INIS)

    Miller, M.H.

    1995-01-01

    The existing Reactor Protection Systems (RPSs) at most US PWRs are systems which reflect 25 to 30 year-old designs, components and manufacturing techniques. Technological improvements, especially in relation to modern digital systems, offer improvements in functionality, performance, and reliability, as well as reductions in maintenance and operational burden. The Nuclear power industry and the US nuclear regulators are poised to move forward with the issues that have slowed the transition to modern digital replacements for nuclear power plant safety systems. The electric utility industry is now more than ever being driven by cost versus benefit decisions. Properly designed, engineered, and installed digital systems can provide adequate cost-benefit and allow continued nuclear generated electricity. This paper describes various issues and areas related to an ongoing RPS replacement demonstration project which are pertinant for a typical US nuclear plant to consider cost-effective replacement of an aging analog RPS with a modern digital RPS. The following subject areas relative to the Oconee Nuclear Station ISAT trademark Demonstrator project are discussed: Operator Interface Development; Equipment Qualification; Validation and Verification of Software; Factory Testing; Field Changes and Verification Testing; Utility Operational, Engineering and Maintenance; Experiences with Demonstration System; and Ability to operate in parallel with the existing Analog RPS

  20. Engineering development of a digital replacement protection system at an operating US PWR nuclear power plant: Installation and operational experiences

    Energy Technology Data Exchange (ETDEWEB)

    Miller, M.H. [Duke Power Co., Seneca, SC (United States)

    1995-04-01

    The existing Reactor Protection Systems (RPSs) at most US PWRs are systems which reflect 25 to 30 year-old designs, components and manufacturing techniques. Technological improvements, especially in relation to modern digital systems, offer improvements in functionality, performance, and reliability, as well as reductions in maintenance and operational burden. The Nuclear power industry and the US nuclear regulators are poised to move forward with the issues that have slowed the transition to modern digital replacements for nuclear power plant safety systems. The electric utility industry is now more than ever being driven by cost versus benefit decisions. Properly designed, engineered, and installed digital systems can provide adequate cost-benefit and allow continued nuclear generated electricity. This paper describes various issues and areas related to an ongoing RPS replacement demonstration project which are pertinant for a typical US nuclear plant to consider cost-effective replacement of an aging analog RPS with a modern digital RPS. The following subject areas relative to the Oconee Nuclear Station ISAT{trademark} Demonstrator project are discussed: Operator Interface Development; Equipment Qualification; Validation and Verification of Software; Factory Testing; Field Changes and Verification Testing; Utility Operational, Engineering and Maintenance; Experiences with Demonstration System; and Ability to operate in parallel with the existing Analog RPS.

  1. Technical evaluation of the electrical, instrumentation, and control design aspects of the low temperature overpressure protection system for the Haddam Neck Nuclear Power Plant

    International Nuclear Information System (INIS)

    Laudenbach, D.H.

    1979-03-01

    The technical evaluation of the electrical, instrumentation, and control design aspects of the low temperature overpressure protection system for the Haddam Neck Nuclear Power Plant is presented. Design basis criteria used to evaluate the acceptability of the system included operator action, system testability, single failure criterion, and seismic Category I and IEEE Std-279-1971 criteria. This report is supplied as part of the Selected Electrical, Instrumentation, and Control Systems Issues Support Program being conducted for the U.S. Nuclear Regulatory Commission by Lawrence Livermore Laboratory

  2. 78 FR 45573 - Compensatory and Alternative Regulatory Measures for Nuclear Power Plant Fire Protection (CARMEN...

    Science.gov (United States)

    2013-07-29

    ... Nuclear Power Plant Fire Protection (CARMEN-FIRE) AGENCY: Nuclear Regulatory Commission. ACTION: Notice of... Nuclear Power Plant Fire Protection (CARMEN-FIRE), Draft Report for Comment.'' DATES: Comments on this... caused by impaired fire protection features at nuclear power plants. The report documents the history of...

  3. Regulatory aspects of radiation protection in Indian nuclear plants

    International Nuclear Information System (INIS)

    Chander, Vipin; Pawar, S.K.; Duraisamy, S.

    2012-01-01

    Atomic Energy Act of 1962 covers the radiation safety aspects in the development, control and use of atomic energy. To carry out certain regulatory and safety functions under this act, Atomic Energy Regulatory Board (AERB) was constituted in November 15, 1983. Operating Nuclear Power Plants (NPPs) account for about 60% of occupational collective dose and about 65% of the number of radiation workers in the nuclear fuel cycle facilities. Therefore radiation protection aspects in NPPs are of prime importance. In 1970s and 1980s the high radiation exposures in NPPs was an issue with TAPS-1 and 2 reaching annual collective dose of 50 Person-Sv. In response to this, AERB constituted an expert committee to investigate the possibility of reducing collective doses in NPPs in 1988. Subsequently the recommendations of this committee were implemented in all NPPs. In 1990, International Commission on Radiological Protection (ICRP) recommended a downward revision of occupational dose limit to 20 mSv/yr from the earlier limit of 50 mSv/yr. Regulatory body endorsed these recommendations and gradually brought down the annual dose limits from 40 mSv in 1991 to 30 mSv in 1994 with the limit of 100 mSv averaged over a five year period in line with ICRP recommendations. Over the years, the regulatory body has put in place a sound regulatory frame work and mechanism to ensure adequate protection of occupational workers, members of public and environment due to operation of NPPs. Vast experiences in the field of radiation protection vis-à-vis stringent regulatory requirements such as review of exposure cases and special regulatory inspections during Biennial Shut Down (BSD) has helped in downward trends in occupational and public doses. This paper highlights the role of regulatory body in controlling the radiation doses to both occupational workers and members of public in the NPPs through a three-tier review system. The regulatory oversight, inspections and reviews has resulted in

  4. Weed control by direct injection of plant protection products according to specific situations

    Directory of Open Access Journals (Sweden)

    Krebs, Mathias

    2016-02-01

    Full Text Available Precision Farming in agriculture allows a site-specific management of the crop. The aim of plant protection is to apply plant protection products (PPP according to the site specific requirements on the field. Within the context of a research program to promote innovation, a sprayer with direct injection of plant protection products was developed. The direct injection offers site specific spraying of different individual PPP in a single pass. The sprayer prototype is equipped with a special spray boom combining three nozzle lines. In order to prevent delay times, the nozzle lines are preloaded before spraying. First results for weed control from test stand measurements and field trials showed that the injection pumps work with high accuracy. The prototype can be used without delay times site specific with up to three different herbicides. Field trials for site-specific weed control in winter wheat demonstrate the applicability of the system under practical conditions. By treatment of subareas herbicides and therefore costs could be saved. A reduction in yield compared with the conventionally treated field areas could not be ascertained. Also an efficacy reduction through washout of active ingredient from target surfaces due to simultaneous use of all three nozzle lines with up to 1050 l/ha application rate could not be detected. At high water spray rates, the efficacy effect occurs delayed. Overall, the newly developed direct injection system proved fieldabillity during the first tests. So weed control can be carried out situation-responsive, which can save herbicides and environmental impacts are reduced.

  5. Protective barrier systems for final disposal of Hanford Waste Sites

    International Nuclear Information System (INIS)

    Phillips, S.J.; Hartley, J.N.

    1986-01-01

    A protecting barrier system is being developed for potential application in the final disposal of defense wastes at the Hanford Site. The functional requirements for the protective barrier are control of water infiltration, wind erosion, and plant and animal intrusion into the waste zone. The barrier must also be able to function without maintenance for the required time period (up to 10,000 yr). This paper summarizes the progress made and future plans in this effort to design and test protective barriers at the Hanford Site

  6. Chitosan Effects on Plant Systems

    Directory of Open Access Journals (Sweden)

    Massimo Malerba

    2016-06-01

    Full Text Available Chitosan (CHT is a natural, safe, and cheap product of chitin deacetylation, widely used by several industries because of its interesting features. The availability of industrial quantities of CHT in the late 1980s enabled it to be tested in agriculture. CHT has been proven to stimulate plant growth, to protect the safety of edible products, and to induce abiotic and biotic stress tolerance in various horticultural commodities. The stimulating effect of different enzyme activities to detoxify reactive oxygen species suggests the involvement of hydrogen peroxide and nitric oxide in CHT signaling. CHT could also interact with chromatin and directly affect gene expression. Recent innovative uses of CHT include synthesis of CHT nanoparticles as a valuable delivery system for fertilizers, herbicides, pesticides, and micronutrients for crop growth promotion by a balanced and sustained nutrition. In addition, CHT nanoparticles can safely deliver genetic material for plant transformation. This review presents an overview on the status of the use of CHT in plant systems. Attention was given to the research that suggested the use of CHT for sustainable crop productivity.

  7. Nanotechnology based surface treatments for corrosion protection and deposit control of power plant equipment. Phase 1

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2009-05-15

    Nanotechnology can provide possibilities for obtaining new valuable information regarding performance and corrosion protection in power plants. In general the desired performance of the contact surfaces is an easy-to-release effect. This is in order to prolong the time interval between cleaning periods or make the cleaning procedures easier and less expensive. Corrosion protection is also desired in order to extend the life time of various parts in the power plants and thus optimize the energy output and overall efficiency of the plant. Functional sol-gel coating based on nanotechnology is tested in a variety of conditions. Applications of functional sol-gel coatings were performed in the condenser and on seven air preheaters at Fynsvaerket, Odense, with corrosion protection as the main issue. Coatings with easy-to-clean effects were tested in the Flue Gas Desulphurization plant at Nordjyllandsvaerket, Aalborg, with the aim of reducing gipsum deposit. Thermo stabilized coatings were tested on tube bundles between in the passage from the 1st to 2end pass and on the wall between 1st and 2end pass at Amagervaerket, Copenhagen, and in the boiler at Haderslev CHP plant. The objective of this test were reducing deposits and increasing corrosion protection. The tested coatings were commercial available coatings and coatings developed in this project. Visual inspections have been performed of all applications except at Nordjyllandsvaerket. Corrosion assessment has been done at DTU - Mechanical Engineering. The results range from no difference between coated and uncoated areas to some improvements. At Amagervaerket the visual assessment showed in general a positive effect with a sol-gel hybrid system and a commercial system regarding removal of deposits. The visual assessment of the air preheaters at Fynsvaerket indicates reduced deposits on a sol-gel nanocomposite coated air preheater compared to an uncoated air preheater. (Author)

  8. 45 CFR 670.25 - Designation of specially protected species of native mammals, birds, and plants.

    Science.gov (United States)

    2010-10-01

    ... native mammals, birds, and plants. 670.25 Section 670.25 Public Welfare Regulations Relating to Public... Protected Species of Mammals, Birds, and Plants § 670.25 Designation of specially protected species of native mammals, birds, and plants. The following species has been designated as Specially Protected...

  9. Laws and ordinances on electric arc protection. Electric arc protection of electric plants; Gesetze und Verordnungen zur Stoerlichtbogensicherheit. Stoerlichtbogensicherheit von elektrischen Betriebsstaetten

    Energy Technology Data Exchange (ETDEWEB)

    Bernards, Stefan; Buenger, Stefan; Grote, Martin [Fritz Driescher KG - Spezialfabrik fuer Elektrizitaetswerksbedarf GmbH und Co., Wegberg (Germany); Boettcher, Lutz-Michael [Ingenieurbuero Boettcher-Consult, Schulzendorf (Germany); Weck, Karl-Heinz [Forschungsgemeinschaft fuer Elektrische Anlagen und Stromwirtschaft (FGH e.V.), Mannheim (Germany)

    2011-02-28

    With the publication of the new standards IEC 62271-200/VDE 0671 part 200-2003: AC metal-enclosed switchgear and controlgear for rated voltages above 1 kV and up to and including 52 kV, and IEC 62271-202/VDE 0671 part 202-2007: High voltage/low voltage prefabricated substations and their revision, the fundamentals of arc protection qualification of plants and stations were redefined with a view to personnel protection. In the case of new transformer stations, the application of these standards is state of the art. The publications and the application of the new standards for staff protection, plant protection and object protection via electric arc qualification has raised questions concerning the safety of older plants and stations, modernization, reconstruction, enhancement, maintenance, and the re-use of used stations and plants.

  10. Carbon steel protection in G.S. [Girldler sulphide] plants: Pt. 7

    International Nuclear Information System (INIS)

    Lires, Osvaldo; Delfino, Cristina; Rojo, Enrique.

    1989-01-01

    In order to protect carbon steel towers and piping of a GS experimental heavy water plant against corrosion produced by the action of aqueous solutions of hydrogen sulphide, a method, elsewhere published, was developed. Carbon steel exposed to saturated aqueous solutions of hydrogen sulphide forms iron sulphide scales. In oxygen free solutions, evolution of corrosion follows the sequence mackinawite → cubic ferrous sulphide → troilite → pyrrotite → pyrite. Scales formed by pyrrotite and pyrite are the most protective layers (these are obtained at 130 deg C, 2 MPa for a period of 14 days). During a plant shutdown procedures, the carbon steel protected with those scales is exposed to water and highly humid air; under such conditions oxidation is unavoidable. Later, treatment in plant conditions does not regenerate scales because the composition of regenerated scales involves more soluble iron sulphides such as mackinawite and troilite. Therefore, it is not recommendable to expose the protective scales to atmospherical conditions. (Author)

  11. Agroecological Importance of the Protective Forest Plantings in Lower Volga Region

    Directory of Open Access Journals (Sweden)

    Ivantsova Elena Anatolyevna

    2014-12-01

    Full Text Available The positive role of protective forest plantings in maintaining the stability of biotic communities and ensuring stabilization of a phytosanitary situation in the agricultural and woodland landscape of steppe and semiarid zones of Lower Volga region is established. The analysis of long-term data testifies that in general, the number of a harmful complex on fields of winter wheat (Triticum and brown mustard (Brassica juncea in the system of forest strips is lower than in opened agrocoenosis in average by 20,6 % and 16,2 %, respectively. The regularities of distribution of harmful and useful insects in corn and mustard agrocoenosis are noted. The obtained data on distribution of harmful insects and their concentration in a forested field gives the grounds to include regional processings of agrocoenosis of agricultural and woodland landscape in the system of protective measures. It is established that the existence of fields afforestation in Volgograd region creates the favorable conditions for development and accumulation of entomophages in fields. It leads to restriction of mass reproduction of harmful insects and to the decrease in their injuriousness. The essential distinctions in distribution and development of diseases in the agrocoenosis protected by forest plantings and the treeless fields are revealed. The maximal values of development of a complex of diseases on winter wheat are observed in zones, adjacent to forest strips (I and III, minimum – in the middle of a field. The estimated values of development of diseases in forested field is less, and in certain cases it slightly differs from the data obtained in a treeless field.

  12. Development of In-Core Protection System

    International Nuclear Information System (INIS)

    Cho, J. H; Kim, C. H.; Kim, J. H.; Jeong, S. H.; Sohn, S. D.; BaeK, S. M.; YOON, J. H.

    2016-01-01

    In-core Protection System (ICOPS) is an on-line digital computer system which continuously calculates Departure from Nucleate Boiling Ratio (DNBR) and Local Power Density (LPD) based on plant parameters to make trip decisions based on the computations. The function of the system is the same as that of Core Protection Calculator System (CPCS) and Reactor Core Protection System (RCOPS) which are applied to Optimized Power Reactor 1000 (OPR1000) and Advanced Power Reactor 1400 (APR1400). The ICOPS has been developed to overcome the algorithm related obstacles in overseas project. To achieve this goal, several algorithms were newly developed and hardware and software design was updated. The functional design requirements document was developed by KEPCO-NF and the component design was conducted by Doosan. System design and software implementation were performed by KEPCO-E and C, and software Verification and Validation (V and V) was performed by KEPCO-E and C and Sure Softtech. The ICOPS has been developed to overcome the algorithm related obstacles in overseas project. The function of I/O simulator was improved even though the hardware platform is the same as that of RCOPS for Shin-Hanul 1 and 2. SCADE was applied to the implementation of ICOPS software, and the V and V system for ICOPS which satisfies international standards was developed. Although several further detailed design works remain, the function of ICOPS has been confirmed. The ICOPS will be applied to APR+ project, and the further works will be performed in following project

  13. Development of In-Core Protection System

    Energy Technology Data Exchange (ETDEWEB)

    Cho, J. H; Kim, C. H.; Kim, J. H.; Jeong, S. H.; Sohn, S. D.; BaeK, S. M.; YOON, J. H. [KEPCO Engineering and Construction Co., Deajeon (Korea, Republic of)

    2016-10-15

    In-core Protection System (ICOPS) is an on-line digital computer system which continuously calculates Departure from Nucleate Boiling Ratio (DNBR) and Local Power Density (LPD) based on plant parameters to make trip decisions based on the computations. The function of the system is the same as that of Core Protection Calculator System (CPCS) and Reactor Core Protection System (RCOPS) which are applied to Optimized Power Reactor 1000 (OPR1000) and Advanced Power Reactor 1400 (APR1400). The ICOPS has been developed to overcome the algorithm related obstacles in overseas project. To achieve this goal, several algorithms were newly developed and hardware and software design was updated. The functional design requirements document was developed by KEPCO-NF and the component design was conducted by Doosan. System design and software implementation were performed by KEPCO-E and C, and software Verification and Validation (V and V) was performed by KEPCO-E and C and Sure Softtech. The ICOPS has been developed to overcome the algorithm related obstacles in overseas project. The function of I/O simulator was improved even though the hardware platform is the same as that of RCOPS for Shin-Hanul 1 and 2. SCADE was applied to the implementation of ICOPS software, and the V and V system for ICOPS which satisfies international standards was developed. Although several further detailed design works remain, the function of ICOPS has been confirmed. The ICOPS will be applied to APR+ project, and the further works will be performed in following project.

  14. Functional safeguards for computers for protection systems for Savannah River reactors

    International Nuclear Information System (INIS)

    Kritz, W.R.

    1977-06-01

    Reactors at the Savannah River Plant have recently been equipped with a ''safety computer'' system. This system utilizes dual digital computers in a primary protection system that monitors individual fuel assembly coolant flow and temperature. The design basis for the (SRP safety) computer systems allowed for eventual failure of any input sensor or any computer component. These systems are routinely used by reactor operators with a minimum of training in computer technology. The hardware configuration and software design therefore contain safeguards so that both hardware and human failures do not cause significant loss of reactor protection. The performance of the system to date is described

  15. Improving CANDU plant operation and maintenance through retrofit information technology systems

    International Nuclear Information System (INIS)

    Lupton, L.R.; Judd, R.A.; MacBeth, M.J.

    1998-01-01

    CANDU plant owners are facing an increasingly competitive environment for the generation of electricity. To meet this challenge, all owners have identified that information technology offers opportunities for significant improvements in CANDU operation, maintenance and administration (OM and A) costs. Targeted information technology application areas include instrumentation and control, engineering, construction, operations and plant information management. These opportunities also pose challenges and issues that must be addressed if the full benefits of the advances in information technology are to be achieved. Key among these are system hardware and software maintenance, and obsolescence protection; AECL has been supporting CANDU stations with the initial development and evaluation of systems to improve plant performance and cost. Key initiatives that have been implemented or are in the process of being implemented in some CANDU plants to achieve operational benefits include: critical safety parameter monitor system; advanced computerized annunciation system; plant historical data system; and plant display system. Each system will be described in terms of its role in enhancing current CANDU plant performance and how they will contribute to future CANDU plant performance

  16. Lightning protection of oil and gas industrial plants

    Energy Technology Data Exchange (ETDEWEB)

    Bouquegneau, Christian [Polytechnical University of Mons (Belgium)

    2007-07-01

    The paper brings some cases and presents the general principles, what the IEC 62305 international standard says, the warning and avoidance and the conclusion about lightning protection of oil and gas industrial plants.

  17. Upgrade of Control and Protection System of the Ignalina Nuclear Power Plant Units 1 and 2

    International Nuclear Information System (INIS)

    Wright, Ronald E.; Fletcher, Norman; Sidnev, Victor E.; Bickel, John H.; Vianello, Aldo; Pearsall, Raymond D.

    2003-01-01

    The Ignalina nuclear power plant (NPP) Units 1 and 2 are Soviet-designed, RBMK (Reaktor Bolshoi Moschnosti Kipyashchiy), channelized, large power-type reactors. The original-design electrical capacity for each unit was 1500 MW. Unit 1 began operating in 1983, and Unit 2 was started up in 1987. In 1994, the government of Lithuania agreed to accept grant support for the Ignalina NPP Safety Improvement Program with funding supplied by the Nuclear Safety Account of the European Bank for Reconstruction and Development (EBRD). As conditions for receiving this funding, the Ignalina NPP agreed to prepare a comprehensive safety analysis report that would undergo independent peer review after it was issued. The EBRD Safety Panel oversaw preparation and review of the report. In 1996, the safety analysis report for Unit 1 was completed and delivered to the EBRD. Part of the analyses covered anticipated transients without scram (ATWS). The analysis showed that some ATWS scenarios could lead to unacceptable consequences in <1 min. The EBRD Safety Panel recommended to the government of Lithuania that the Ignalina NPP develop and implement a program of compensatory measures for the control and protection system before the unit would be allowed to return to operation following its 1998 maintenance outage. A compensatory control and protection system that would mitigate the unacceptable consequences was designed, procured, manufactured, tested, and installed. The project was funded by U.S. Department of Energy

  18. Physical protection of power reactors

    International Nuclear Information System (INIS)

    Darby, J.L.

    1979-01-01

    Sandia Laboratories has applied a systematic approach to designing physical protection systems for nuclear facilities to commercial light-water reactor power plants. A number of candidate physical protection systems were developed and evaluated. Focus is placed on the design of access control subsystems at each of three plant layers: the protected area perimeter, building surfaces, and vital areas. Access control refers to barriers, detectors, and entry control devices and procedures used to keep unauthorized personnel and contraband out of the plant, and to control authorized entry into vital areas within the plant

  19. Summary report of workshop on sabotage protection in nuclear power plant design

    International Nuclear Information System (INIS)

    1977-02-01

    During the Summer of 1976, Sandia Laboratories hosted a workshop on Sabotage Protection in Nuclear Power Plant Design in which 11 consultants from the nuclear power industry participated. Each consultant is highly qualified and experienced in nuclear power plant design. The objective of the workshop was to identify practicable design measures which could be employed in future nuclear power plants to provide increased protection against sabotage. The report summarizes the conclusions and recommendations of the workshop

  20. Fire protection in nuclear power plants

    International Nuclear Information System (INIS)

    Wright, H.A.

    1981-01-01

    This lecture describes briefly the chronological order of events which may arise for a very serious emergency situation in a nuclear power plant for which preparations should be made even though the situation has an extremely low probability of happening. The planning and preparedness required are expected to cope with a whole spectrum of emergency situations, from minor accidents to serious plant failures which also lead to releases of significant quantities of radioactive material beyond the site boundary. Fire protection aspects will be briefly covered, and some guidance will be provided on exercises to ensure the plans are feasible and the appropriate personnel and facilities are in a satisfactory state of preparedness. (orig./RW)

  1. Qualification issues for advanced light-water reactor protection systems

    International Nuclear Information System (INIS)

    Korsah, K.; Clark, R.L.; Antonescu, C.

    1993-01-01

    The instrumentation and control (I ampersand C) systems in advanced reactors will make extensive use of digital controls, microprocessors, multiplexing, and fiber optic transmission. Elements of these advances in I ampersand C have been implemented on some current operating plants. However, the widespread use of the above technologies, as well as the use of artificial intelligence with minimum reliance on human operator control of reactors, highlights the need to develop standards for qualifying the I ampersand C used in the next generation of nuclear power plants. As a first step in this direction, the protection system I ampersand C for present-day plants was compared to that proposed for advanced light-water reactors (ALWRs). An evaluation template was developed by assembling a configuration of a safety channel instrument string for a generic ALWR, then comparing the impact of environmental stressors on that string to their effect on an equivalent instrument string from an existing light-water reactor. The template was then used to suggest a methodology for the qualification of microprocessor-based protection systems. The methodology identifies standards/regulatory guides (or lack thereof) for the qualification of microprocessor-based safety I ampersand C systems. This approach addresses in part issues raised in NRC policy document SECY-91-292, which recognizes that advanced I ampersand C systems for the nuclear industry are ''being developed without consensus standards. as the technology available for design is ahead of the technology that is well understood through experience and supported by application standards.''

  2. Functional issues and environmental qualification of digital protection systems of advanced light-water nuclear reactors

    Energy Technology Data Exchange (ETDEWEB)

    Korsah, K.; Clark, R.L.; Wood, R.T. [Oak Ridge National Lab., TN (United States)

    1994-04-01

    Issues of obsolescence and lack of infrastructural support in (analog) spare parts, coupled with the potential benefits of digital systems, are driving the nuclear industry to retrofit analog instrumentation and control (I&C) systems with digital and microprocessor-based systems. While these technologies have several advantages, their application to safety-related systems in nuclear power plants raises key issues relating to the systems` environmental qualification and functional reliability. To bound the problem of new I&C system functionality and qualification, the authors focused this study on protection systems proposed for use in ALWRs. Specifically, both functional and environmental qualification issues for ALWR protection system I&C were addressed by developing an environmental, functional, and aging data template for a protection division of each proposed ALWR design. By using information provided by manufacturers, environmental conditions and stressors to which I&C equipment in reactor protection divisions may be subjected were identified. The resulting data were then compared to a similar template for an instrument string typically found in an analog protection division of a present-day nuclear power plant. The authors also identified fiber-optic transmission systems as technologies that are relatively new to the nuclear power plant environment and examined the failure modes and age-related degradation mechanisms of fiber-optic components and systems. One reason for the exercise of caution in the introduction of software into safety-critical systems is the potential for common-cause failure due to the software. This study, however, approaches the functionality problem from a systems point of view. System malfunction scenarios are postulated to illustrate the fact that, when dealing with the performance of the overall integrated system, the real issues are functionality and fault tolerance, not hardware vs. software.

  3. Functional issues and environmental qualification of digital protection systems of advanced light-water nuclear reactors

    International Nuclear Information System (INIS)

    Korsah, K.; Clark, R.L.; Wood, R.T.

    1994-04-01

    Issues of obsolescence and lack of infrastructural support in (analog) spare parts, coupled with the potential benefits of digital systems, are driving the nuclear industry to retrofit analog instrumentation and control (I ampersand C) systems with digital and microprocessor-based systems. While these technologies have several advantages, their application to safety-related systems in nuclear power plants raises key issues relating to the systems' environmental qualification and functional reliability. To bound the problem of new I ampersand C system functionality and qualification, the authors focused this study on protection systems proposed for use in ALWRs. Specifically, both functional and environmental qualification issues for ALWR protection system I ampersand C were addressed by developing an environmental, functional, and aging data template for a protection division of each proposed ALWR design. By using information provided by manufacturers, environmental conditions and stressors to which I ampersand C equipment in reactor protection divisions may be subjected were identified. The resulting data were then compared to a similar template for an instrument string typically found in an analog protection division of a present-day nuclear power plant. The authors also identified fiber-optic transmission systems as technologies that are relatively new to the nuclear power plant environment and examined the failure modes and age-related degradation mechanisms of fiber-optic components and systems. One reason for the exercise of caution in the introduction of software into safety-critical systems is the potential for common-cause failure due to the software. This study, however, approaches the functionality problem from a systems point of view. System malfunction scenarios are postulated to illustrate the fact that, when dealing with the performance of the overall integrated system, the real issues are functionality and fault tolerance, not hardware vs. software

  4. Bio-protective microbial agents from rhizosphere eco-systems trigger plant defense responses provide protection against sheath blight disease in rice (Oryza sativa L.).

    Science.gov (United States)

    Singh, Udai B; Malviya, Deepti; Wasiullah; Singh, Shailendra; Pradhan, Jatindra K; Singh, Bhanu P; Roy, Manish; Imram, Mohd; Pathak, Neelam; Baisyal, B M; Rai, Jai P; Sarma, B K; Singh, Rajiv K; Sharma, P K; Kaur, Saman Deep; Manna, M C; Sharma, Sushil K; Sharma, Arun K

    2016-11-01

    Sheath blight of rice (Oryza sativa L.) caused by Rhizoctonia solani is a major disease and attempts are being made to develop microbe based technologies for biocontrol of this pathogen. However, the mechanisms of biocontrol are not fully understood and still require indepth study in the backdrop of emerging concepts in biological systems. The present investigation was aimed at deciphering the mechanisms of biocontrol of sheath blight of rice employing Pseudomonas fluorescens and Trichoderma harzianum as model agents for biocontrol. Initially 25, 5 and 5 strains of P. fluorescens, T. viride and T. harzianum, respectively, were screened for their biocontrol potential. Out of which, six strains with higher value of percent inhibition of fungal mycelium in dual plate assay were selected. The role of P. fluorescens, T. viride and T. harzianum were investigated in induction and bioaccumulation of natural antioxidants, defence-related biomolecules and other changes in plant which lead not only to growth promotion but also protection from pathogenic stress conditions in rice. The two most promising strains, P. fluorescens PF-08 and T. harzianum UBSTH-501 selected on the basis of in planta evaluation, when applied individually or in combination, significantly enhanced the accumulation of defence-related biomolecules, enzymes and exhibited biocontrol potential against R. solani. A modified/newly developed delivery system was applied for the first time in the experiments involving inoculation of plants with both bioagents, viz. P. fluorescens PF-08 and T. harzianum UBSTH-501. Results suggested that application of P. fluorescens PF-08 and T. harzianum UBSTH-501 alone or in combination, not only helps in control of the disease but also increases plant growth along with reduction in application of toxic chemical pesticides. Copyright © 2016 Elsevier GmbH. All rights reserved.

  5. Protective clothing use at the Savannah River Plant Nuclear Facility

    International Nuclear Information System (INIS)

    Cabbil, C.C.

    1987-01-01

    The mission of the Savannah River Plant in producing nuclear materials does pose some unique protective clothing and equipment requirements not usually seen in the general industry. In addition to protection from the chemicals and physical agents encountered, radioactive hazards must also be managed. This paper describes the protective clothing and respiratory protection used at SRP, and focuses particularly on the development of a new plastic suit. 5 refs., 7 figs., 3 tabs

  6. Safety rule of the KTA. Alarm system, staff locator systems, and internal and external communication lines of nuclear power plants. Pt. 1

    International Nuclear Information System (INIS)

    1977-01-01

    This rule aims at stipulating the requirements on type and extent of communication means for personnel within the nuclear power plant, and from the nuclear power plant to the outside. Requirements on design, construction, operating equipment, and alarm and locator system tests for nuclear power plants are defined. The rule applies to stationary nuclear power plants with one power station unit, but not to facilities of process control, radiation protection control, fire protection control, environmental control, and plant security. (orig./HP) [de

  7. Verification Results of Safety-grade Optical Modem for Core Protection Calculator (CPC) in Korea Standard Nuclear Power Plant (KSNP)

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Jangyeol; Son, Kwangseop; Lee, Youngjun; Cheon, Sewoo; Cha, Kyoungho; Lee, Jangsoo; Kwon, Keechoon [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2013-05-15

    We confirmed that the coverage criteria for a safety-grade optical modem of a Core Protection Calculator is satisfactory using a traceability analysis matrix between high-level requirements and lower-level system test case data set. This paper describes the test environment, test components and items, a traceability analysis, and system tests as a result of system verification and validation based on Software Requirement Specifications (SRS) for a safety-grade optical modem of a Core Protection Calculator (CPC) in a Korea Standard Nuclear Power Plant (KSNP), and Software Design Specifications (SDS) for a safety-grade optical modem of a CPC in a KSNP. All tests were performed according to the test plan and test procedures. Functional testing, performance testing, event testing, and scenario based testing for a safety-grade optical modem of a Core Protection Calculator in a Korea Standard Nuclear Power Plant as a thirty-party verifier were successfully performed.

  8. Plant foods and plant-based diets: protective against childhood obesity?

    Science.gov (United States)

    Newby, P K

    2009-05-01

    The objective of this article is to review the epidemiologic literature examining the role of plant foods and plant-based diets in the prevention of childhood obesity. Available data suggest a protective effect of ready-to-eat cereal on risk of obesity, although prospective studies are still needed. Studies on fruit and vegetables; grains other than cereal; high-protein foods, including beans, legumes, and soy; fiber; and plant-based dietary patterns are inconsistent or generally null. The evidence base is limited, and most studies are fraught with methodologic limitations, including cross-sectional design, inadequate adjustment for potential confounders, and lack of consideration of reporting errors, stage of growth, and genetic influences. Well-designed prospective studies are needed. The lack of evidence showing an association between plant-based diets and childhood obesity does not mean that such diets should not be encouraged. Plant foods are highlighted in the Dietary Guidelines for Americans, and children do not meet the current recommendations for most plant foods. Although the advice to consume a plant-based, low-energy-dense diet is sound, ethical questions arise concerning the relatively high price of these diets in the United States and the way in which such diets are perceived in other parts of the world. Reducing the burden of childhood obesity, eliminating health disparities, and preventing the further spread of the disease around the globe will require not only policy interventions to ensure that plant foods are affordable and accessible to children of all income levels but also awareness of sociocultural norms that affect consumption.

  9. Physical protection of nuclear power plants-technical and legal aspects

    International Nuclear Information System (INIS)

    Castro Martins, O.J. de.

    1978-04-01

    The nuclear power plants are defined according to the definitions included in the Brazilian legislation and international conventions and their physical protection is analysed. Besides, the differences and the relations among nuclear security, safeguards and physical protection are established. (A.L.) [pt

  10. Integration of the ITER diagnostic plant systems with CODAC

    International Nuclear Information System (INIS)

    Simrock, S.; Barnsley, R.; Bertalot, L.; Hansalia, C.; Klotz, W.D.; Makijarvi, P.; Reichle, R.; Vayakis, G.; Yonekawa, I.; Walker, C.; Wallander, A.; Walsh, M.; Winter, A.

    2011-01-01

    ITER requires extensive diagnostic systems in order to meet the requirements for machine operation, protection, plasma control and physics studies. The realization of these systems is a major challenge not only because of the harsh environment and the nuclear requirements but also with respect to Instrumentation and Control (I and C) of all the 59 diagnostics plants. The Plant Systems I and C are mostly 'in-kind', i.e. procured by the seven ITER Domestic Agencies (DAs), while the Central I and C Systems are 'in-fund', i.e. procured by ITER Organization (IO). Standardization of Plant Systems I and C is of primary importance and has been one of the highest priority tasks of CODAC. The standards are published in the Plant Control Design Handbook (PCDH) which will be followed to ensure a homogeneous design, guarantee high availability and simplify maintenance and support future upgrades. Most important for a successful commissioning and operation of the ITER facility are the concepts of interfacing the diagnostics plant systems with CODAC and the standards for instrumentation and control which must be followed all contributing parties. In this paper, we will elaborate on the concepts of interfacing the diagnostics plant systems with CODAC and the standards that must be followed for the design.

  11. Software for computers in safety systems of nuclear power plants

    International Nuclear Information System (INIS)

    Gallagher, J.M.

    1983-01-01

    The application of distributed digital processing techniques to the protection systems of nuclear power plants provides a means to significantly improve the functional capability of the protection system with respect to the operability and availability of the power plant. A major factor in the realization of this improvement is the development and maintenance of essentially error-free software. A joint program for the development of principles for the design, testing and documentation of software to achieve this goal is presented. Results from two separate experiences in the application of these principles in terms of detected software errors are summarized. The low number of errors detected during the verification testing phase demonstrates the effectiveness of the design and documentation principles in the realization of highly reliable software. (author)

  12. History of Plant Phenological Observation in Hungary and Plans for Renewal of System to detect Evidence of the Climate Change

    Science.gov (United States)

    Hunkar, M.; Dunkel, Z.

    2009-04-01

    The first plant protection warning was issued 1760 by the Senate of the Town of Debrecen concerning the destruction of caterpillar's nest. In the middle of the 19th century the first responsible Hungarian Government issued a note in which the minister takes measurements for the phytosanitary safety of agricultural products. Though Hungary had not got independent institutional system for plant protection at the end of the 19th c., still in the middle of the 1870s, the territory of the country was protected with harmonised quarantine measures from the introduction of Colorado beetle. A new era started both in Europe and in Hungary with the devastation caused by Phylloxera vastatrix in vineyards. In 1876, the Act 29 definitely specified the measures to be taken for preventing the spread of the pest and the damages caused by it; and it was proclaimed in both Chambers of the Parliament. This incident resulted basically in the launching for the establishment of an independent plant protection institution. In l880, the National Committee on Phylloxera, then in 1881, the National Experimental Station for Phylloxera was set up, this latter considered as the first nucleus of the Hungarian plant protection organisation. The international plant protection convention, concluded in 1929 and signed by our country, had a great role in the history of the development of the plant protection organisation. Hungary agreed to establish an official plant protection organization which should consist of a plant protection service and a research institute. In compliance with the Ministerial Decree 49.000/1932 the Hungarian Plant Protection Service was set up which can now be taken for the first organisation of the uniform national plant protection administration system. Plant protection stations were established in 1954. The plant phenological observation network was run by the plant protection administration but financially was maintained by OMSZ therefore the main aim of the phenological

  13. Clinch River breeder reactor sodium fire protection system design and development

    International Nuclear Information System (INIS)

    Foster, K.W.; Boasso, C.J.; Kaushal, N.N.

    1984-01-01

    To assure the protection of the public and plant equipment, improbable accidents were hypothesized to form the basis for the design of safety systems. One such accident is the postulated failure of the Intermediate Heat Transfer System (IHTS) piping within the Steam Generator Building (SGB), resulting in a large-scale sodium fire. This paper discusses the design and development of plant features to reduce the consequences of the accident to acceptable levels. Additional design solutions were made to mitigate the sodium spray contribution to the accident scenario. Sodium spill tests demonstrated that large sodium leaks can be safely controlled in a sodium-cooled nuclear power plant

  14. Oral delivery of ACE2/Ang-(1-7) bioencapsulated in plant cells protects against experimental uveitis and autoimmune uveoretinitis.

    Science.gov (United States)

    Shil, Pollob K; Kwon, Kwang-Chul; Zhu, Ping; Verma, Amrisha; Daniell, Henry; Li, Qiuhong

    2014-12-01

    Hyperactivity of the renin-angiotensin system (RAS) resulting in elevated Angiotensin II (Ang II) contributes to all stages of inflammatory responses including ocular inflammation. The discovery of angiotensin-converting enzyme 2 (ACE2) has established a protective axis of RAS involving ACE2/Ang-(1-7)/Mas that counteracts the proinflammatory and hypertrophic effects of the deleterious ACE/AngII/AT1R axis. Here we investigated the hypothesis that enhancing the systemic and local activity of the protective axis of the RAS by oral delivery of ACE2 and Ang-(1-7) bioencapsulated in plant cells would confer protection against ocular inflammation. Both ACE2 and Ang-(1-7), fused with the non-toxic cholera toxin subunit B (CTB) were expressed in plant chloroplasts. Increased levels of ACE2 and Ang-(1-7) were observed in circulation and retina after oral administration of CTB-ACE2 and Ang-(1-7) expressing plant cells. Oral feeding of mice with bioencapsulated ACE2/Ang-(1-7) significantly reduced endotoxin-induced uveitis (EIU) in mice. Treatment with bioencapsulated ACE2/Ang-(1-7) also dramatically decreased cellular infiltration, retinal vasculitis, damage and folding in experimental autoimmune uveoretinitis (EAU). Thus, enhancing the protective axis of RAS by oral delivery of ACE2/Ang-(1-7) bioencapsulated in plant cells provide an innovative, highly efficient and cost-effective therapeutic strategy for ocular inflammatory diseases.

  15. Fuzzy control applied to nuclear power plant pressurizer system

    International Nuclear Information System (INIS)

    Oliveira, Mauro V.; Almeida, Jose C.S.

    2011-01-01

    In a pressurized water reactor (PWR) nuclear power plants (NPPs) the pressure control in the primary loop is very important for keeping the reactor in a safety condition and improve the generation process efficiency. The main component responsible for this task is the pressurizer. The pressurizer pressure control system (PPCS) utilizes heaters and spray valves to maintain the pressure within an operating band during steady state conditions, and limits the pressure changes, during transient conditions. Relief and safety valves provide overpressure protection for the reactor coolant system (RCS) to ensure system integrity. Various protective reactor trips are generated if the system parameters exceed safe bounds. Historically, a proportional-integral derivative (PID) controller is used in PWRs to keep the pressure in the set point, during those operation conditions. The purpose of this study has two main goals: first is to develop a pressurizer model based on artificial neural networks (ANNs); second is to develop a fuzzy controller for the PWR pressurizer pressure, and compare its performance with the P controller. Data from a simulator PWR plant was used to test the ANN and the controllers as well. The reference simulator is a Westinghouse 3-loop PWR plant with a total thermal output of 2785 MWth. The simulation results show that the pressurizer ANN model response are in reasonable agreement with the simulated power plant, and the fuzzy controller built in this study has better performance compared to the P controller. (author)

  16. Fuzzy control applied to nuclear power plant pressurizer system

    Energy Technology Data Exchange (ETDEWEB)

    Oliveira, Mauro V.; Almeida, Jose C.S., E-mail: mvitor@ien.gov.b, E-mail: jcsa@ien.gov.b [Instituto de Engenharia Nuclear (IEN/CNEN-RJ), Rio de Janeiro, RJ (Brazil)

    2011-07-01

    In a pressurized water reactor (PWR) nuclear power plants (NPPs) the pressure control in the primary loop is very important for keeping the reactor in a safety condition and improve the generation process efficiency. The main component responsible for this task is the pressurizer. The pressurizer pressure control system (PPCS) utilizes heaters and spray valves to maintain the pressure within an operating band during steady state conditions, and limits the pressure changes, during transient conditions. Relief and safety valves provide overpressure protection for the reactor coolant system (RCS) to ensure system integrity. Various protective reactor trips are generated if the system parameters exceed safe bounds. Historically, a proportional-integral derivative (PID) controller is used in PWRs to keep the pressure in the set point, during those operation conditions. The purpose of this study has two main goals: first is to develop a pressurizer model based on artificial neural networks (ANNs); second is to develop a fuzzy controller for the PWR pressurizer pressure, and compare its performance with the P controller. Data from a simulator PWR plant was used to test the ANN and the controllers as well. The reference simulator is a Westinghouse 3-loop PWR plant with a total thermal output of 2785 MWth. The simulation results show that the pressurizer ANN model response are in reasonable agreement with the simulated power plant, and the fuzzy controller built in this study has better performance compared to the P controller. (author)

  17. Bio-based resistance inducers for sustainable plant protection against pathogens

    Czech Academy of Sciences Publication Activity Database

    Burketová, Lenka; Trdá, Lucie; Ott, P.G.; Valentová, O.

    2015-01-01

    Roč. 33, č. 6 (2015), s. 994-1004 ISSN 0734-9750 R&D Projects: GA MŠk(CZ) LD14056 Institutional support: RVO:61389030 Keywords : Induced resistance * Elicitor * Chitosan Subject RIV: GF - Plant Pathology, Vermin, Weed, Plant Protection Impact factor: 9.848, year: 2015

  18. Kainic Acid-Induced Excitotoxicity Experimental Model: Protective Merits of Natural Products and Plant Extracts

    Directory of Open Access Journals (Sweden)

    Nur Shafika Mohd Sairazi

    2015-01-01

    Full Text Available Excitotoxicity is well recognized as a major pathological process of neuronal death in neurodegenerative diseases involving the central nervous system (CNS. In the animal models of neurodegeneration, excitotoxicity is commonly induced experimentally by chemical convulsants, particularly kainic acid (KA. KA-induced excitotoxicity in rodent models has been shown to result in seizures, behavioral changes, oxidative stress, glial activation, inflammatory mediator production, endoplasmic reticulum stress, mitochondrial dysfunction, and selective neurodegeneration in the brain upon KA administration. Recently, there is an emerging trend to search for natural sources to combat against excitotoxicity-associated neurodegenerative diseases. Natural products and plant extracts had attracted a considerable amount of attention because of their reported beneficial effects on the CNS, particularly their neuroprotective effect against excitotoxicity. They provide significant reduction and/or protection against the development and progression of acute and chronic neurodegeneration. This indicates that natural products and plants extracts may be useful in protecting against excitotoxicity-associated neurodegeneration. Thus, targeting of multiple pathways simultaneously may be the strategy to maximize the neuroprotection effect. This review summarizes the mechanisms involved in KA-induced excitotoxicity and attempts to collate the various researches related to the protective effect of natural products and plant extracts in the KA model of neurodegeneration.

  19. New technology for reactor protection system of CAREM reactor

    International Nuclear Information System (INIS)

    Dezzutti, J.C.; Verrastro, C.; Estryk, D.

    2009-01-01

    The use of FPGA in safety functions in a nuclear power plant, increase the reliability of software based systems, without loose any of the function required by the supervision and control systems. In this work the architecture of a Reactor Protection System is described, it use four independent measurement channels in 2 oo 4 configuration, each channel is based on diverse approach in 1 oo 2 configuration, the reliability of this system is near the same than the hardwired logic, with full performance like software based system. (author)

  20. Software Safety Analysis of Digital Protection System Requirements Using a Qualitative Formal Method

    International Nuclear Information System (INIS)

    Lee, Jang-Soo; Kwon, Kee-Choon; Cha, Sung-Deok

    2004-01-01

    The safety analysis of requirements is a key problem area in the development of software for the digital protection systems of a nuclear power plant. When specifying requirements for software of the digital protection systems and conducting safety analysis, engineers find that requirements are often known only in qualitative terms and that existing fault-tree analysis techniques provide little guidance on formulating and evaluating potential failure modes. A framework for the requirements engineering process is proposed that consists of a qualitative method for requirements specification, called the qualitative formal method (QFM), and a safety analysis method for the requirements based on causality information, called the causal requirements safety analysis (CRSA). CRSA is a technique that qualitatively evaluates causal relationships between software faults and physical hazards. This technique, extending the qualitative formal method process and utilizing information captured in the state trajectory, provides specific guidelines on how to identify failure modes and the relationship among them. The QFM and CRSA processes are described using shutdown system 2 of the Wolsong nuclear power plants as the digital protection system example

  1. Cooperation of nuclear, thermal and hydroelectric power plants in the power system

    International Nuclear Information System (INIS)

    1984-01-01

    The conference heard 36 papers of which 23 were incorporated in INIS. The subjects discussed were: the development of power industry in Czechoslovakia, methods of statistical analysis of data regarding nuclear power plant operation, the incorporation of WWER nuclear power plants in the power supply system, the standardization of nuclear power plants, the service life of components, use of nuclear energy sources, performance of the reactor accident protection system, the use of nuclear power and heating plants in Hungary, risk analysis, optimization of nuclear power plants, accidents caused by leakage of the primary and secondary circuit. (J.P.)

  2. Measures of radiation protection in the operation of nuclear power plants in the German Democratic Republic

    International Nuclear Information System (INIS)

    Richter, D.; Schreiter, W.

    1975-11-01

    A survey is given on the provisions concerning (a) radiation protection at nuclear power plants in the GDR including the instructions applying within the plant, (b) the organization of radiation protection services, and (c) the measures of radiation protection surveillance inside and outside the plant during operation. (author)

  3. Design concepts for the reactor protection and control process instrumentation digital upgrade project at the Donald C. Cook Nuclear Plant units 1 and 2

    International Nuclear Information System (INIS)

    Carruth, R.C.; Sotos, W.G.

    1996-01-01

    As the nation's nuclear power plants age, the need to consider upgrading of their electronic protection and control systems becomes more urgent. Hardware obsolescence and mechanical wear out resulting from frequent calibration and surveillance play a major role in defining their useful life. At Cook Nuclear Plant, a decision was made to replace a major portion of the plant's protection and control systems with newer technology. This paper describes the engineering processes involved in this successful upgrade and explains the basis for many decisions made while performing the digital upgrade

  4. 5-Point programme for sustainable plant protection.

    Science.gov (United States)

    Frische, Tobias; Egerer, Sina; Matezki, Steffen; Pickl, Christina; Wogram, Jörn

    2018-01-01

    This position paper intends to stimulate a profound rethinking of contemporary agricultural practice. We criticise the current intensity of chemical plant protection in Germany as ecologically unsustainable and thus threatening the achievement of key targets of environmental protection and nature conservation policies. In the first part of the paper, we provide background information on the use of plant protection products (PPP) in German agriculture, the role of agricultural policy, European pesticide legislation, the principles of and framework for environmental risk assessment and risk management of PPP, as well as environmental effects of PPP. The second part is presented against the backdrop of the European "Sustainable Use Directive" (2009/128/EC). This directive requires that "Member States shall adopt National Action Plans to set up their quantitative objectives, targets, measures, and timetables to reduce risks and impacts of pesticide use on human health and the environment and to encourage the development and introduction of integrated pest management and of alternative approaches or techniques to reduce dependency on the use of pesticides." Reflecting on the corresponding debate in Germany, we suggest the following five key principles for a sustainable use of PPP and provide recommendations for their implementation: (1) minimising use; (2) identifying, quantifying, and communicating risks; (3) optimising risk management; (4) compensating for unavoidable effects; (5) internalising external costs.

  5. Reactor protection systems for the Replacement Research Reactor, ANSTO

    International Nuclear Information System (INIS)

    Morris, C.R.

    2003-01-01

    The 20-MW Replacement Research Reactor Project which is currently under construction at ANSTO will have a combination of a state of the art triplicated computer based reactor protection system, and a fully independent, and diverse, triplicated analogue reactor protection system, that has been in use in the nuclear industry, for many decades. The First Reactor Protection System (FRPS) consists of a Triconex triplicated modular redundant system that has recently been approved by the USNRC for use in the USA?s power reactor program. The Second Reactor Protection System is a hardwired analogue system supplied by Foxboro, the Spec 200 system, which is also Class1E qualified. The FRPS is used to drop the control rods when its safety parameter setpoints have been reached. The SRPS is used to drain the reflector tank and since this operation would result in a reactor poison out due to the time it would take to refill the tank the FRPS trip setpoints are more limiting. The FRPS and SRPS have limited hardwired indications on the control panels in the main control room (MCR) and emergency control centre (ECC), however all FRPS and SRPS parameters are capable of being displayed on the reactor control and monitoring system (RCMS) video display units. The RCMS is a Foxboro Series I/A control system which is used for plant control and monitoring and as a protection system for the cold neutron source. This paper will provide technical information on both systems, their trip logics, their interconnections with each other, and their integration into the reactor control and monitoring system and control panels. (author)

  6. War protected underground siting of nuclear power plants -a summary

    International Nuclear Information System (INIS)

    1974-06-01

    In connection with studies concerning the need of war protected nuclear power production the technical and economical conditions with war protection of nuclear power plants have been studied within CDL. Comprehensively one have shown that no technical construction obstacles for siting a nuclear power plant underground exist that the additional costs for underground siting with price level mid 1973 are some 175-250 MSwCr (In today's price level 250 MSwCr will probably correspond to some 300 MSwCr per unit) and that the construction time is some one year longer than for an above ground plant. A study ought to examine more closely the consequences of underground siting from a radiological point of view and what demands on that occasion ought to be put on the technical design. (author)

  7. Cathodic corrosion protection for the inside areas of metallic plants (KKS-I); Kathodischer Korrosionsschutz fuer die Innenflaechen von metallischen Anlagen (KKS-I)

    Energy Technology Data Exchange (ETDEWEB)

    Tenzer, Norbert [TZ-International Corrosion Consulting, Hagen (Germany)

    2012-07-01

    Cathodic corrosion protection for the inside areas of metallic plants (KKS-I) is a worldwide used technology in order to afford a safe protection of metallic plans against corrosion. This technology is used for plants in the treatment and storage of drinking water, for containers and reaction vessels in the chemical industry, for plants in the oil and gas industry as well as for containers and large-dimension pipelines containing seawater for the cooling of air liquefaction plants, power plants and seawater desalination plants, for examples. Furthermore, there exist further special applications for wastewater systems and biogas plants. The general description of the KKS-I shall supply the information to the operators of appropriate plants, that the cathodic corrosion protection also offers a wide range of applications for the protection of the inside areas of the plants against corrosion. Beside the previously mentioned standard areas of application there exist manifold further possibilities of application for metallic plants. It has to be emphasized that there are application possibilities not only for unalloyed or low alloy steels but also for stainless steels, aluminium, lead, copper, titanium and zinc. The regulation DIN EN 12499 firstly edited in 2003 contains the fundamentals, areas of application and specifications.

  8. Recent advances in reactor protection and control system technology

    International Nuclear Information System (INIS)

    Anon.

    1997-01-01

    After a first-generation digital integrated protection system has been installed on all 1300 MWe PWR units in France, a new digital protection system was developed for the 1450 MWe units, using local area networks, fiber optics, Motorola 68000 microprocessors, and a modular design allowing for the design of any system on the basis of around 50 types of standard cards. In 1993, an upgrading program for this equipment was launched in order to reduce costs, in particular software development costs, further improve hardware modularity and facilitate integration and connection to existing equipment. The basic principles of the units are described together with the implementation of computer-aided software engineering (CASE) tools, interfaces with hard-wired equipment, and multiplexed connections. The nuclear instrumentation systems at the Fessenheim and Bugey plants have been renovated with these equipment

  9. Plant invasions in protected areas of tropical pacific islands, with special reference to Hawaii

    Science.gov (United States)

    Hughes, R. Flint; Meyer, Jean-Yves; Loope, Lloyd L.

    2013-01-01

    Isolated tropical islands are notoriously vulnerable to plant invasions. Serious management for protection of native biodiversity in Hawaii began in the 1970s, arguably at Hawaii Volcanoes National Park. Concerted alien plant management began there in the 1980s and has in a sense become a model for protected areas throughout Hawaii and Pacific Island countries and territories. We review the relative successes of their strategies and touch upon how their experience has been applied elsewhere. Protected areas in Hawaii are fortunate in having relatively good resources for addressing plant invasions, but many invasions remain intractable, and invasions from outside the boundaries continue from a highly globalised society with a penchant for horticultural novelty. There are likely few efforts in most Pacific Islands to combat alien plant invasions in protected areas, but such areas may often have fewer plant invasions as a result of their relative remoteness and/or socio-economic development status. The greatest current needs for protected areas in this region may be for establishment of yet more protected areas, for better resources to combat invasions in Pacific Island countries and territories, for more effective control methods including biological control programme to contain intractable species, and for meaningful efforts to address prevention and early detection of potential new invaders.

  10. Depth protection system

    International Nuclear Information System (INIS)

    Arita, Setsuo; Izumi, Shigeru; Suzuki, Satoru; Noguchi, Atomi.

    1988-01-01

    Purpose: To previously set a nuclear reactor toward safety side by the reactor scram if an emergency core cooling system is failed to operate. Constitution If abnormality occurs in an emergency core cooling system or an aqueous boric acid injection system, a reactor protection system is operated and, if the reactor protection system shows an abnormal state, a control rod withdrawal inhibition system is operated as a fundamental way. For instance, when the driving power source voltage for the emergency core cooling system is detected and, if it is lower than a predetermined value, the reactor protection system is operated. Alternatively, if the voltage goes lower than the predetermined value, the control rod withdrawal is inhibited. In addition, stopping for the feedwater system is inhibited. Further, integrity of the driving means for the emergency core cooling system is positively checked and the protection function is operated depending on the result of check. Since the nuclear reactor can be set toward the safety side even if the voltage for the driving power source of the aqueous boric acid injection system is lower than a predetermined value, the reactor safety can further be improved. (Horiuchi, T.)

  11. Operating experience feedback report -- turbine-generator overspeed protection systems: Commercial power reactors. Volume 11

    International Nuclear Information System (INIS)

    Ornstein, H.L.

    1995-04-01

    This report presents the results of the US Nuclear Regulatory Commission's Office for Analysis and Evaluation of Operational Data (AEOD) review of operating experience of main turbine-generator overspeed and overspeed protection systems. It includes an indepth examination of the turbine overspeed event which occurred on November 9, 1991, at the Salem Unit 2 Nuclear Power Plant. It also provides information concerning actions taken by other utilities and the turbine manufacturers as a result of the Salem overspeed event. AEOD's study reviewed operating procedures and plant practices. It noted differences between turbine manufacturer designs and recommendations for operations, maintenance, and testing, and also identified significant variations in the manner that individual plants maintain and test their turbine overspeed protection systems. AEOD's study provides insight into the shortcomings in the design, operation, maintenance, testing, and human factors associated with turbine overspeed protection systems. Operating experience indicates that the frequency of turbine overspeed events is higher than previously thought and that the bases for demonstrating compliance with NRC's General Design Criterion (GDC) 4, Environmental and dynamic effects design bases, may be nonconservative with respect to the assumed frequency

  12. Concept for the Emergency Protection in the Vicinity of Nuclear Power Plants

    International Nuclear Information System (INIS)

    1998-03-01

    In 1991, the Swiss Federal Nuclear Safety Inspectorate (HSK) issued a concept of the regulations for the cloud phase 1 of an nuclear power plant accident in Switzerland valid at that time in co-operation with the Federal Commission for AC Protection (KOMAC) and the Swiss Federal Nuclear Safety Commission (KSA). This concept replaced the version of 1977, which then formed the basis for emergency preparedness in Switzerland. Legal changes, such as the civil protection legislation and the ordinance on the distribution of iodine tablets to the population, as well as experience gained from the emergency exercises necessitated a revision of the existing concept. The present concept is issued by the Federal Commission for AC Protection (KOMAC) and deals with all phases of an accident sequence in a Swiss nuclear power plant focussing on the pre- and cloud phase. It also gives an overview of responsibilities and alert procedures for accidents at foreign nuclear power plants and other nuclear installations, as well as of accidents in connection with transportation of radioactive materials. The concept is designed to help the federal and cantonal authorities in the vicinity of nuclear power plants in charge of emergency protection in preparing their emergency procedure specifications, and in the realisation of the readiness for emergencies. Furthermore, it shall serve the cantons as a guideline for the preparation of emergency specifications for the communities. The concept is based on the assumption that the executive bodies and emergency forces provided for the general civil protection are employed in case of an accident at a nuclear power plant. (authors)

  13. System level ESD protection

    CERN Document Server

    Vashchenko, Vladislav

    2014-01-01

    This book addresses key aspects of analog integrated circuits and systems design related to system level electrostatic discharge (ESD) protection.  It is an invaluable reference for anyone developing systems-on-chip (SoC) and systems-on-package (SoP), integrated with system-level ESD protection. The book focuses on both the design of semiconductor integrated circuit (IC) components with embedded, on-chip system level protection and IC-system co-design. The readers will be enabled to bring the system level ESD protection solutions to the level of integrated circuits, thereby reducing or completely eliminating the need for additional, discrete components on the printed circuit board (PCB) and meeting system-level ESD requirements. The authors take a systematic approach, based on IC-system ESD protection co-design. A detailed description of the available IC-level ESD testing methods is provided, together with a discussion of the correlation between IC-level and system-level ESD testing methods. The IC-level ESD...

  14. Vital area identification software VIP for the physical protection of nuclear power plants

    International Nuclear Information System (INIS)

    Jung, Woo Sik; Park, Chang Kue; Yang, Joon Eon

    2004-01-01

    There are two major factors to be considered for the physical protection of nuclear power plants. They are a design basis threat (DBT) and the vital area identification (VAI). The DBT has been considered as 'the maximum credible threat.' The vital area is defined as 'an area inside a protected area containing equipment, systems or devices, or nuclear materials, the sabotage of which could directly or indirectly lead to unacceptable radiological consequences.' For the VAI of nuclear power plants, a software VIP (Vital area Identification Package based on PSA method) is being developed. The VIP is based on the current probabilistic safety assessment (PSA) techniques. The PSA method, including internal as well as external events, is known as the most complete and consistent method for identifying various accident sequences that might result in a core melt and radioactive material release to the environment. Thus, the VIP employs a fault tree analysis method in the PSA and utilizes the PSA results

  15. Antimicrobial peptide production and plant-based expression systems for medical and agricultural biotechnology.

    Science.gov (United States)

    Holaskova, Edita; Galuszka, Petr; Frebort, Ivo; Oz, M Tufan

    2015-11-01

    Antimicrobial peptides (AMPs) are vital components of the innate immune system of nearly all living organisms. They generally act in the first line of defense against various pathogenic bacteria, parasites, enveloped viruses and fungi. These low molecular mass peptides are considered prospective therapeutic agents due to their broad-spectrum rapid activity, low cytotoxicity to mammalian cells and unique mode of action which hinders emergence of pathogen resistance. In addition to medical use, AMPs can also be employed for development of innovative approaches for plant protection in agriculture. Conferred disease resistance by AMPs might help us surmount losses in yield, quality and safety of agricultural products due to plant pathogens. Heterologous expression in plant-based systems, also called plant molecular farming, offers cost-effective large-scale production which is regarded as one of the most important factors for clinical or agricultural use of AMPs. This review presents various types of AMPs as well as plant-based platforms ranging from cell suspensions to whole plants employed for peptide production. Although AMP production in plants holds great promises for medicine and agriculture, specific technical limitations regarding product yield, function and stability still remain. Additionally, establishment of particular stable expression systems employing plants or plant tissues generally requires extended time scale for platform development compared to certain other heterologous systems. Therefore, fast and promising tools for evaluation of plant-based expression strategies and assessment of function and stability of the heterologously produced AMPs are critical for molecular farming and plant protection. Copyright © 2015 Elsevier Inc. All rights reserved.

  16. Development and testing of an integrated signal validation system for nuclear power plants

    International Nuclear Information System (INIS)

    Upadhyaya, B.R.; Kerlin, T.W.; Gaudio, P.J. Jr.

    1989-09-01

    Since the incident at Three Mile Island unit 2, computerized plant status display, implementation of human factors in control room design, and plant monitoring based on expert system technology have seen a tremendous growth. One such proposed operator assist device is a plant signal validation system. This system is used to check the consistency of redundant measurements (sensors) of selected process variables, estimate their expect values from plant-wide data, and detect, isolate and characterize the type of anomaly in the instrument channel outputs. In large process control systems signals from several hundred instrument channels are routed via data highways to control systems, protection (safety) systems and plant monitoring systems. The need of automated signal validation is necessary because of the large amount of information available, and as a result the operator's inability to validate information from many diverse sources. This is also useful for improved plant control (minimize challenges on control systems), minimizing plant downtime, and for predictive maintenance advising. 107 refs., 56 figs., 6 tabs

  17. The role of NOSA five-star management system for occupational management of nuclear power plants

    International Nuclear Information System (INIS)

    Zhang Qin

    2011-01-01

    The occupational safety management of nuclear power plant is developed towards integrated management, risk management, process management, all-round and full staff participation. Appropriate management method integrated with nuclear power plant safety, health and environmental protection could be organically combined with the nuclear safety operation management system, and could jointly lay a solid foundation for building up good nuclear safety culture. NOSA five-star management system is such a kind of risk management based on safety, health and environmental management system, with an aim to protect the personal safety. The concepts of NOSA management and nuclear safety culture are coincident, with strong workability, and meeting the need of nuclear power plant occupational safety management. Adopting NOSA five-star management system and keeping continuous improvement is one of the effective ways to improve the level of occupational safety management of nuclear power plant. It can be organically combined with nuclear safety operation management system and continuously improved safety culture to play an important role in improving the safety and economics of nuclear power plant. (author)

  18. Survey results of corroding problems at biological treatment plants, Stage II Protection of concrete - State of the Art

    Energy Technology Data Exchange (ETDEWEB)

    Edwards, Ylva (CBI, Boraas (Sweden)); Henriksson, Gunilla (SP, Boraas (Sweden))

    2011-07-01

    A pilot study on the degradation and corrosion of concrete in biological treatment plants was conducted in 2009/2010 in a Waste Refinery Project WR-27 'Survey results of corroding problems at biological treatment plants'. The results showed that the concrete does not have sufficient resistance in the current aggressive plant environment. Furthermore, it is stated that some form of surface protection system is needed to ensure the good performance of concrete constructions, and that the system must withstand the aggressive environment and the traffic that occurs on site. Consequently, a new study was proposed in order to develop specifications for surface protection of concrete in aggressive food waste environments. Results from that study are presented in this report. The report includes various types of waterproofing/protection coating for concrete in biological treatment plants. A number of proposals from the industry are presented in the light of results from project WR-27, i.e., the materials must, among other things, withstand the aggressive leachate from waste food at temperatures up to 70 deg C, and some degree of wear. Some systems are compared in terms of technical material properties as reported by the manufacturer. It turns out that different testing methods were used, and the test results are thus generally not directly comparable. A proposal for a test program has been developed, focusing on chemical resistance and wear resistance. A test solution corresponding to leachate is specified. Laboratory tests for verification of the proposed methodology and future requirements are proposed, as well as test sites and follow-up in the field

  19. Evaluation of Generic Issue 57: Effects of fire protection system actuation on safety-related equipment

    International Nuclear Information System (INIS)

    Lambright, J.; Bohn, M.; Lynch, J.; Ross, S.; Brosseau, D.

    1992-12-01

    Nuclear power plants have experienced actuations of fire protection systems (FPSs) under conditions for which these systems were not intended to actuate and also have experienced advertent actuations with the presence of a fire. These actuations have often damaged safety-related equipment. A review of the impact of past occurrences of both types of such events and their impact on plant safety systems, an analysis of the risk impacts of such events on nuclear power plant safety, and a cost-benefit analysis of potential corrective measures have been performed. Thirteen different scenarios leading to actuation of fire protection systems due to a variety of causes were identified. These scenarios ranged from inadvertent actuation caused by human error to hardware failure, and include seismic root causes and seismic/fire interactions. A quantification of these thirteen root causes, where applicable, was performed on generically applicable scenarios. This document, Volume 4, contains appendices E and F of this report

  20. ECOTOXICITY AND PHYTOTOXICITY OF PLANT PROTECTION PRODUCTS TO RHIZOSPHERE FUNGI AND WINTER WHEAT SEEDLINGS

    Directory of Open Access Journals (Sweden)

    Anna Daria Stasiulewicz-Paluch

    2015-11-01

    Full Text Available Registration of plant protection products involves the analysis of their effects on soil microorganisms. The residues of plant protection products penetrate the soil, but their impact on fungi remains scarcely researched. In this study, the influence of selected plant protection products on the abundance of rhizosphere-dwelling fungi and the growth of winter wheat seedlings was evaluated under greenhouse conditions. The analysed plant protection products had an inhibitory effect on the growth of filamentous fungi in the rhizosphere, whereas yeasts were resistant to those products applied to soil. Tebuconazole exerted the strongest suppressive effect on the growth of filamentous fungi, and propiconazole was characterized by the greatest phytotoxic activity against winter wheat seedlings. Azoxystrobin had the weakest ecotoxic and phytotoxic effects, and its application to soil usually led to a rapid increase in the counts of fungi of the genus Acremonium.

  1. Systematic evaluation of the Cernavoda nuclear power plant physical protection system

    International Nuclear Information System (INIS)

    Ionescu, D.S.

    2002-01-01

    Full text: For three years at Cernavoda NPP is working a process to systematic evaluating the effectiveness of the Physical Protection System (PPS). Due to the fact that this evaluation has to be continuous, the first important step is to define a baseline to compare periodically the performance of PPS against it. The necessity of that process has been identified as follows: the continuous changes in the field of perceived threats against Cernavoda NPP and the necessary measures to respond to that changing climate; the needful to improve the performance of PPS against certain threats in conjunction with the needful to allocate substantially financial and human resources to cover the discovered weakness in the system; an assistant to take the appropriate measure in case of indisponibility of one or more components or parts of the PPS. The second step is the continuous tracking of the behavior of PPS in order to determine: the maintenance resource allocation and the priorities of the work; the predictive behavior of installed components to determine the future appropriate measures, including budget dimensioning. SAVI is a PC compatible program developed by SANDIA Laboratory (USA) for comprehensive analysis of PPS effectiveness. That program is organized in two modules: the Adversary Sequence Diagram (ASD) module and the outsider module modeling trough specific codes both the characteristics of PPS and of the predicted adversary. Combining the two modules related to a specific PPS and adversary is possible to find out the effectiveness of the physical protection system for each vital zone along to ten possible paths to penetrate by adversary, starting with the most vulnerable one. Because of two conservative assumption considered by the SAVI algorithm (adversary know the PPS characteristics and they use an optimal penetration strategy), the measure of effectiveness (probability of interruption - P I ) is very realistic and conservative related to the necessary

  2. Protective action alternatives for accidents at nuclear power plants

    International Nuclear Information System (INIS)

    Tingle, A.; Pratt, W.T.; McGuire, S.A.

    1987-06-01

    Protective action calculations have been performed for five different light water reactors (LWRs) and containment designs using high and low fission product releases for early and late containment failures for each plant. These fission product release estimates were obtained from studies performed for the recently published ''Reactor Risk Reference Document'' (NUREG-1150). Five protective actions were considered for the risks of exceeding various dose levels to the red marrow versus centerline distance from the plants using site-specific meteorology. The strategies considered were 4 hours of normal activity, basement sheltering, large building sheltering, evacuation at release, and evacuation 1 hour after release. The evacuations were computed using 10 mph evacuation speed for all sites. Additional calculations were performed for the dose contributions due to the cloud, ground, and inhalation pathways

  3. Regulatory inspections in nuclear plants in the field of radiation protection

    International Nuclear Information System (INIS)

    Hort, M.; Fuchsova, D.

    2014-01-01

    State Office for Nuclear Safety executes state administration and performs inspections at peaceful use of nuclear energy and ionizing radiation in the field of radiation protection and nuclear safety. Inspections on radiation protection at nuclear power plants are secured by inspectors of the Department of Radiation Protection in Fuel Cycle, who work at the Regional centre Brno and Ceske Budejovice. (authors)

  4. Safety and Radiation Protection at Swedish Nuclear Power Plants 2007

    Energy Technology Data Exchange (ETDEWEB)

    2008-07-01

    The safety level of the plants is maintained at an acceptable level. SKI has in its regulatory supervision not found any known deficiencies in the barriers which could result in release of radioactive substances in excess of the permitted levels. SKI considers that improvements have been implemented during the year in the management, control and following up of safety work at the plants. In some cases, SKI has imposed requirements that improvements be made. Extensive measures are under way at the nuclear power plants to comply with the safety requirements in SKI's regulations, SKIFS 2004:2 concerning the design and construction of nuclear power reactors, and the stricter requirements regarding physical protection. Concurrently preparations are underway at eight of the ten units for thermal power increases. At the Forsmark plant considerable efforts have been during the year to correct the deficiencies in the safety culture and quality assurance system that became apparent in 2006. A programme to improve the execution of activities has been established in accordance with SKI's decision. SKI considers that the plant has developed in a positive direction but that there are further possibilities for improvement with regard to internal control. This is amongst other things concerns the areas internal auditing, independent safety review function, and working methods. SKI has had special supervision of the plant since 28 September, 2006. At the Oskarshamn plant work has been carried out to improve the organisation and routines in several areas. The plant has established routines which provide the basis to ensure that decisions are taken in a stringent manner. The quality assurance system has a clearer structure and there is a better defined division of work. Some measures remain to be dealt with in 2008. The Ringhals plant has also worked with attitudes to routines and internal control. SKI considers that the measures have good prerequisites to provide a

  5. Fire protection programme during construction of the Chashma nuclear power plant

    International Nuclear Information System (INIS)

    Mian Umer, M.

    1998-01-01

    A clear view is given of several measures that have been taken with regard to fire prevention, protection and fire fighting during all phases of the construction, installation and commissioning of the Chasma nuclear power plant to protect personnel and equipment so that any delays in plant operation as a result of fire incident can be avoided. These measures include the precautions taken, the provisions made for fire extinguishers and hydrants, and the setting up of a fire brigade. An overview is also given of the fire incidents that have occurred. (author)

  6. Safety aspect of digital reactor protection system in Japan

    International Nuclear Information System (INIS)

    Ogiso, Zen-Ichi

    1998-01-01

    It was early in 1980's that the digital controllers were first applied to nuclear power plant in japan. After that, their application area had been expanding gradually, reaching to the overall integrated digital system including the safety system in Kashiwazaki-Kariwa units 6 and 7. The software for computer-based systems has been produced using the graphical language ''POL'' in Japanese nuclear power plants. It is the fundamental principle that the reliability of the software should be assured through the properly managed quality assurance. The POL-based system is fitted to this principle. In applying POL-based systems to safety system, the MITI, Ministry of International Trade and Industry, identified the licensing issues as the regulatory body, while the utilities had developed the digital technology feasible to the safety application. Through the activities, a specific industrial design guide for the software important to safety was established and the adequacy of the technology was certified through the demonstration tests of the integrated system. In the safety examination of the digital reactor protection system of K-6/7, the application of POL were approved. The POL-based systems in nuclear power plants were successful design and production process of the POL-based systems. This paper describes the activities in licensing and maintaining the computer-based systems by the utilities and manufacturers as well as the MITI. (author)

  7. Dynamics of Change in Human-Driven and Natural Systems: Fast Forward, Slow Motion, Same Movie? A Case Study from Plant Protection

    Directory of Open Access Journals (Sweden)

    Didier Andrivon

    2012-03-01

    Full Text Available Evolutionary biology and evolutionary ecology deal with change in species and ecosystems over time, and propose mechanisms to explain and predict these. In particular, they look for generic elements that will drive any organism or phylum to adaptive changes or to extinction. This paper, using examples from the field of plant protection against pests and diseases, shows that the patterns of change observed in natural and in human-driven systems are comparable, and proposes that their similarities result from the same mechanisms operating at different paces. Human-driven systems can thus be seen simply as ‘fast-forward’ versions of natural systems, making them tractable tools to test and predict elements from evolutionary theory. Conversely, the convergence between natural and human-driven systems opens opportunities for a more widespread use of evolutionary theory when analyzing and optimizing any human-driven system, or predicting its adaptability to changing conditions.

  8. Fire protection guidelines for nuclear power plants, June 1976

    International Nuclear Information System (INIS)

    Anon.

    1977-01-01

    Guidelines acceptable to the NRC staff for implementing in the development of a fire protection program for nuclear power plants. The purpose of the fire protection program is to ensure the capability to shut down the reactor and maintain it in a safe shutdown condition and to minimize radioactive releases to the environment in the event of a fire. If designs or methods different from the guidelines presented herein are used, they must provide fire protection comparable to that recommended in the guidelines. Suitable bases and justification should be provided for alternative approaches to establish acceptable implementation of General Design Criterion 3

  9. Development of a computerized operator support system for BWR power plant

    International Nuclear Information System (INIS)

    Monta, K.; Sekimizu, K.; Sato, N.; Araki, T.; Mori, N.

    1985-01-01

    A computerized operator support system for BWR power plant has been developed since 1980 supported by the Japanese government. The main functions of the systems are post trip operational guidance, disturbance analysis, standby system management, operational margin monitoring and control rod operational guidance. The former two functions aim at protection against incidents during operation of nuclear power plants and the latter three functions aim at their prevention. As the final stage of the development, these functions are combined with the plant supervision function and are organized as an advanced man-machine interface for BWR power plant. During the above process, operator task analyses are performed to enable synthesis of these support functions for right fit to operator tasks and to realize a hierarchical structure for CRT displays for right fit to operators cognitive needs. (author)

  10. Man as a protective barrier in nuclear power plants

    International Nuclear Information System (INIS)

    Fechner, J.B.

    1980-01-01

    Evaluation of nuclear power plant incidents frequently reveals man as a major element of risk. Yet, in a nuclear power plant man has the function of an important protective barrier, either by maintaining the plant, by detecting and limiting faults or incidents, or by taking proper measures in accidents. This is true despite, or perhaps because of, the high degree of plant automation. For this reason, it is indispensable that a high level of engineered plant safeguards be accompanied by a minimum of faults contributed by human action. This implies that the staff and their working conditions must meet the same stringent safety requirements as the nuclear power plant proper. Reactor manufacturers, nuclear power plant operators and the responsible authorities try to optimize this human contribution. The Federal Ministry of the Interior, through its Special Technical Guidelines and its continuation training measures, occupies an important position in this respect. Further measures and ordinances are being prepared by that Ministry. (orig.) [de

  11. Engineered chitosan based nanomaterials: Bioactivities, mechanisms and perspectives in plant protection and growth.

    Science.gov (United States)

    Kumaraswamy, R V; Kumari, Sarita; Choudhary, Ram Chandra; Pal, Ajay; Raliya, Ramesh; Biswas, Pratim; Saharan, Vinod

    2018-07-01

    Excessive use of agrochemicals for enhancing crop production and its protection posed environmental and health concern. Integration of advanced technology is required to realize the concept of precision agriculture by minimizing the input of pesticides and fertilizers per unit while improving the crop productivity. Notably, chitosan based biodegradable nanomaterials (NMs) including nanoparticles, nanogels and nanocomposites have eventually proceeded as a key choice in agriculture due to their inimitable properties like antimicrobial and plant growth promoting activities. The foreseeable role of chitosan based NMs in plants might be in achieving sustainable plant growth through boosting the intrinsic potential of plants. In-spite of the fact that chitosan based NMs abode immense biological activities in plants, these materials have not yet been widely adopted in agriculture due to poor understanding of their bioactivity and modes of action towards pathogenic microbes and in plant protection and growth. To expedite the anticipated claims of chitosan based NMs, it is imperative to line up all the possible bioactivities which denote for sustainable agriculture. Herein, we have highlighted, in-depth, various chitosan based NMs which have been used in plant growth and protection mainly against fungi, bacteria and viruses and have also explained their modes of action. Copyright © 2018 Elsevier B.V. All rights reserved.

  12. A Study of Distributed Generation System Characteristics and Protective Load Control Strategy

    DEFF Research Database (Denmark)

    Wei, Mu; Chen, Zhe

    2011-01-01

    Due to the smaller inertia feature of a Wind Turbine (WT) involved Distributed Generation System (DGS), the WT’s induction generator are more vulnerable to frequency and voltage disturbances. Therefore the study investigates the DGS characteristics respectively from power plants, i.e. WTs and load....... Two kinds of wind turbines: Doubly-fed Induction Generator (DFIG) and Fixed-speed Wind Turbine (FSWT) are compared in this study. A conventional power system protective scheme may not response promptly, which could lead an undesired disconnection of WTs for the turbine protection purpose. Consequently...

  13. Digital System Reliability Test for the Evaluation of safety Critical Software of Digital Reactor Protection System

    Directory of Open Access Journals (Sweden)

    Hyun-Kook Shin

    2006-08-01

    Full Text Available A new Digital Reactor Protection System (DRPS based on VME bus Single Board Computer has been developed by KOPEC to prevent software Common Mode Failure(CMF inside digital system. The new DRPS has been proved to be an effective digital safety system to prevent CMF by Defense-in-Depth and Diversity (DID&D analysis. However, for practical use in Nuclear Power Plants, the performance test and the reliability test are essential for the digital system qualification. In this study, a single channel of DRPS prototype has been manufactured for the evaluation of DRPS capabilities. The integrated functional tests are performed and the system reliability is analyzed and tested. The results of reliability test show that the application software of DRPS has a very high reliability compared with the analog reactor protection systems.

  14. Aging assessment of surge protective devices in nuclear power plants

    International Nuclear Information System (INIS)

    Davis, J.F.; Subudhi, M.; Carroll, D.P.

    1996-01-01

    An assessment was performed to determine the effects of aging on the performance and availability of surge protective devices (SPDs), used in electrical power and control systems in nuclear power plants. Although SPDs have not been classified as safety-related, they are risk-important because they can minimize the initiating event frequencies associated with loss of offsite power and reactor trips. Conversely, their failure due to age might cause some of those initiating events, e.g., through short circuit failure modes, or by allowing deterioration of the safety-related component(s) they are protecting from overvoltages, perhaps preventing a reactor trip, from an open circuit failure mode. From the data evaluated during 1980--1994, it was found that failures of surge arresters and suppressers by short circuits were neither a significant risk nor safety concern, and there were no failures of surge suppressers preventing a reactor trip. Simulations, using the ElectroMagnetic Transients Program (EMTP) were performed to determine the adequacy of high voltage surge arresters

  15. The Remotely Controlled Robot System for Nuclear Power Plants

    International Nuclear Information System (INIS)

    Koh, Kwangill; Lee, Gwangnam; Lim, Kyeyoung

    1993-01-01

    The problem of radioactivity has been our major concern. So, it makes the needs of remotely controlled robot system necessary for maintenance and repair services. Up to now, several foreign companies have been contracted for the maintenance of the steam generators of nuclear power plants in Korea, to acquire its own capability of maintaining the steam generators of it impossible for Korea to acquire its own capability of maintaining the steam generators. In case of emergency, it is difficult to take appropriate steps on its own. In order to resolve the above problems, it seems inevitable to develop the robot system for the inspection and repair of steam generator. This project intends to acquire domestic capabilities of maintaining steam generators, so that this advanced skills could be applied to the related areas. As a result, it will save immense money in the future. the purposes of development of the remotely controlled robot system are : to perform the desired tasks at the polluted area without requiring entry of personnel. to closely inspect the steam generator U-tubes at high speed. to inspect the steam generator intelligently and efficiently under the extreme circumstances where radioactivity problem is very severe. to use for the repair of steam generator tube. Considering from the social and technical standpoint, we can say that the development of the remotely controlled robot system for nuclear power plants resulted in great achievements. From the social standpoint, it should be recognized that domestic robot for nuclear power plant was successfully developed and operator was protected against radioactivity. Also, we advanced our skills in the area of mechanical and control system design for an articulated robot. Using the robot controller in hierarchical structure, it was possible to control the robot remotely. In addition, resolver feedback typed A C servo drive was proven to be sturdy in hazardous environment. Now we are confident that our robot will

  16. Radiation protection aspects in decommissioning of a fuel reprocessing plant

    International Nuclear Information System (INIS)

    Kotrappa, P.; Joshi, P.P.; Theyyunni, T.K.; Sidhwa, B.M.; Nadkarni, M.N.

    1980-01-01

    The decontamination of a fuel reprocessing plant which underwent partial decommissioning is described. The following radiation protection aspects of the work are discussed: dismantling and removal of process vessels, columns and process off-gas filters; decontamination of various process areas; and management of liquid and solid wastes. The work was completed safely by using personnel protective equipment such as plastic suits and respirators (gas, particulate and fresh air). Total dose commitment for this work was around 3000 man-rems, including dose received by staff for certain jobs related to the operation of a section of the plant. The external dose was kept below the annual limit of 5000 mrems for any individual. No internal contamination incident occurred which caused a dose commitment in excess of 10% of the annual limit. The fact that all the work was completed by the staff normally associated with the operation of the plant contributed significantly to the management and control of personnel exposures. (H.K.)

  17. Distributed radiation protection console system

    International Nuclear Information System (INIS)

    Chhokra, R.S.; Deshpande, V.K.; Mishra, H.; Rajeev, K.P.; Thakur, Bipla B.; Munj, Niket

    2004-01-01

    Radiation exposure control is one of the most important aspects in any nuclear facility . It encompasses continuous monitoring of the various areas of the facility to detect any increase in the radiation level and/or the air activity level beyond preset limits and alarm the O and M personnel working in these areas. Detection and measurement of radiation level and the air activity level is carried out by a number of monitors installed in the areas. These monitors include Area Gamma Monitors, Continuous Air Monitors, Pu-In-Air Monitors, Criticality Monitors etc. Traditionally, these measurements are displayed and recorded on a Central Radiation Protection Console(CRPC), which is located in the central control room of the facility. This methodology suffers from the shortcoming that any worker required to enter a work area will have to inquire about the radiation status of the area either from the CRPC or will get to know the same directly from the installed only after entering the area. This shortcoming can lead to avoidable delays in attending to the work or to unwanted exposure. The authors have designed and developed a system called Distributed Radiation Protection Console (DRPC) to overcome this shortcoming. A DRPC is a console which is located outside the entrance of a given area and displays the radiation status of the area. It presents to health physicist and the plant operators a graphic over-view of the radiation and air activity levels in the particular area of the plant. It also provides audio visual annunciation of the alarm status. Each radioactive area in a nuclear facility will have its own DRPC, which will receive as its inputs the analog and digital signals from radiation monitoring instruments installed in the area and would not only show those readings on its video graphic screen but will also provide warning messages and instructions to the personnel entering the active areas. The various DRPCs can be integrated into a Local Area Network, where the

  18. Replacement of the control and instrumentation system with the microprocessor based systems in Japanese PWR plants

    International Nuclear Information System (INIS)

    Hayashi, N.

    1998-01-01

    In Ohi Units 3 and 4, Ikata Unit 3, and Genkai Units 3 and 4, the latest of PWR plants now under operation in Japan, the reactor control system and turbine control system employ the microprocessor base digital control systems with a view to improving reliability, operability and maintainability. In the next stage plants, another application of such digital system is also planned for the instrumentation rack for the reactor protection system for further improvement. On the other hand, in Mihama Unit 1, the first of domestic PWR plants, and later plants except for the latest 5 plants, analog control systems are employed for the instrumentation racks. For the analog control systems of these plants, FOXBORO H-Line instruments, equivalent domestic box type instruments or WH7300 Series card type instruments were initially employed, and later replaced with domestic card type control systems after 10-15 year operation. However, 8-12 years have passed since these replacements, so the 15th year generally quoted as an interval for replacing C and I systems is near at hand. This is the time to consider next replacement. This replacement will be based on the latest digital technology. However, it is not practical way for the existing plants to apply the same integrated digital C and I system configuration for the next stage plants, because it requires the drastic change of the C and I system configuration and significant cost-up. Therefore, we must investigate the optimum digital C and I system configuration for the existing system. (author)

  19. Open-Phase Condition Detecting System for Transformers in Nuclear Power Plant

    International Nuclear Information System (INIS)

    Ha, Che-Wung; Lee, Do-Hwan

    2015-01-01

    Recently, several events involving the loss of one of the three phases of the offsite power circuit occurred in the US nuclear power plants (NPPs).. In some cases, the open-phase condition existed undetected for an extended period and in other case, was not properly responded to. Accordingly, the Nuclear Regulatory Commission (NRC) requested all license holders to take corrective actions to address the open-phase condition. It was also requested that all holders or applicant for a standard design certification (DC) include a description of a protection system to detect and separate the open circuit into design control document (DCD). Currently, NPPs including Duke Energy, Exelon, and institutes including Electric Power Research Institute (EPRI) are working together to resolve issues associated with detecting an open-phase condition. This paper, using Electromagnetic Transients Program (EMTP), presents a system to detect and address the loss of one of three phases of the offsite power circuit connected to main, auxiliary and standby transformers, which is hard to be detected in the current protection system. This paper, using EMTP, presents a system to detect and address the loss of one of three phases of the offsite power circuit running to MT, UAT or SAT which is hard to be detected in the current protection system. The system presented in this paper will be useful not only for the KHNP to meet the NRC requirement, but also for nuclear power plants at home and abroad to take corrective actions to provide protection from a single phase open circuit condition for offsite power sources

  20. Open-Phase Condition Detecting System for Transformers in Nuclear Power Plant

    Energy Technology Data Exchange (ETDEWEB)

    Ha, Che-Wung; Lee, Do-Hwan [KHNP Central Research Institute, Daejeon (Korea, Republic of)

    2015-05-15

    Recently, several events involving the loss of one of the three phases of the offsite power circuit occurred in the US nuclear power plants (NPPs).. In some cases, the open-phase condition existed undetected for an extended period and in other case, was not properly responded to. Accordingly, the Nuclear Regulatory Commission (NRC) requested all license holders to take corrective actions to address the open-phase condition. It was also requested that all holders or applicant for a standard design certification (DC) include a description of a protection system to detect and separate the open circuit into design control document (DCD). Currently, NPPs including Duke Energy, Exelon, and institutes including Electric Power Research Institute (EPRI) are working together to resolve issues associated with detecting an open-phase condition. This paper, using Electromagnetic Transients Program (EMTP), presents a system to detect and address the loss of one of three phases of the offsite power circuit connected to main, auxiliary and standby transformers, which is hard to be detected in the current protection system. This paper, using EMTP, presents a system to detect and address the loss of one of three phases of the offsite power circuit running to MT, UAT or SAT which is hard to be detected in the current protection system. The system presented in this paper will be useful not only for the KHNP to meet the NRC requirement, but also for nuclear power plants at home and abroad to take corrective actions to provide protection from a single phase open circuit condition for offsite power sources.

  1. Flood protection of Crystal River Unit 3 Nuclear Plant

    International Nuclear Information System (INIS)

    Noble, R.M.; Simpson, B.

    1975-01-01

    To satisfy U.S. Atomic Energy Commission (AEC) safety criteria, a required evaluation of the worst site-related flood is performed for the Crystal River Plant, located on the Gulf Coast of Florida, the probable maximum stillwater flood levels are likely to be a result of the probable maximum hurricane. Flood protection requirements for the Crystal River Plant are determined by considering the most severe combination of probable maximum hurricane parameters for the Gulf Coast Region. These parameters are used as input to a model of hurricane surge generation and attendant wave activity in order to determine the maximum flood levels at the Crystal River Plant. 4 refs

  2. Plant Phenotype Characterization System

    Energy Technology Data Exchange (ETDEWEB)

    Daniel W McDonald; Ronald B Michaels

    2005-09-09

    This report is the final scientific report for the DOE Inventions and Innovations Project: Plant Phenotype Characterization System, DE-FG36-04GO14334. The period of performance was September 30, 2004 through July 15, 2005. The project objective is to demonstrate the viability of a new scientific instrument concept for the study of plant root systems. The root systems of plants are thought to be important in plant yield and thus important to DOE goals in renewable energy sources. The scientific study and understanding of plant root systems is hampered by the difficulty in observing root activity and the inadequacy of existing root study instrumentation options. We have demonstrated a high throughput, non-invasive, high resolution technique for visualizing plant root systems in-situ. Our approach is based upon low-energy x-ray radiography and the use of containers and substrates (artificial soil) which are virtually transparent to x-rays. The system allows us to germinate and grow plant specimens in our containers and substrates and to generate x-ray images of the developing root system over time. The same plant can be imaged at different times in its development. The system can be used for root studies in plant physiology, plant morphology, plant breeding, plant functional genomics and plant genotype screening.

  3. Buffer moisture protection system

    International Nuclear Information System (INIS)

    Ritola, J.; Peura, J.

    2013-11-01

    With the present knowledge, bentonite blocks have to be protected from the air relative humidity and from any moisture leakages in the environment that might cause swelling of the bentonite blocks during the 'open' installation phase before backfilling. The purpose of this work was to design the structural reference solution both for the bottom of the deposition hole and for the buffer moisture protection and dewatering system with their integrated equipment needed in the deposition hole. This report describes the Posiva's reference solution for the buffer moisture protection system and the bottom plate on basis of the demands and functional requirements set by long-term safety. The reference solution with structural details has been developed in research work made 2010-2011. The structural solution of the moisture protection system has not yet been tested in practice. On the bottom of the deposition hole a copper plate which protects the lowest bentonite block from the gathered water is installed straight to machined and even rock surface. The moisture protection sheet made of EPDM rubber is attached to the copper plate with an inflatable seal. The upper part of the moisture protection sheet is fixed to the collar structures of the lid which protects the deposition hole in the disposal tunnel. The main function of the moisture protection sheet is to protect bentonite blocks from the leaking water and from the influence of the air humidity at their installation stage. The leaking water is controlled by the dewatering and alarm system which has been integrated into the moisture protection liner. (orig.)

  4. Safety and Radiation Protection at Swedish Nuclear Power Plants 2007

    International Nuclear Information System (INIS)

    2008-01-01

    The safety level of the plants is maintained at an acceptable level. SKI has in its regulatory supervision not found any known deficiencies in the barriers which could result in release of radioactive substances in excess of the permitted levels. SKI considers that improvements have been implemented during the year in the management, control and following up of safety work at the plants. In some cases, however, SKI has imposed requirements that improvements be made. Extensive measures are under way at the nuclear power plants to comply with the safety requirements in SKI's regulations, SKIFS 2004:2 concerning the design and construction of nuclear power reactors, and the stricter requirements regarding physical protection. Concurrently preparations are underway at eight of the ten units for thermal power increases. At the Forsmark plant considerable efforts have been during the year to correct the deficiencies in the safety culture and quality assurance system that became apparent in 2006. A programme to improve the execution of activities has been established in accordance with SKI's decision. SKI considers that the plant has developed in a positive direction but that there are further possibilities for improvement with regard to internal control. This is amongst other things concerns the areas internal auditing, independent safety review function, and working methods. SKI has had special supervision of the plant since 28 September, 2006. At the Oskarshamn plant work has been carried out to improve the organisation and routines in several areas. The plant has established routines which provide the basis to ensure that decisions are taken in a stringent manner. The quality assurance system has a clearer structure and there is a better defined division of work. Some measures remain however to be dealt with in 2008. The Ringhals plant has also worked with attitudes to routines and internal control. SKI considers that the measures have good prerequisites to provide a

  5. FIRE PROTECTION SYSTEMS AND TECHNOLOGIES

    Directory of Open Access Journals (Sweden)

    Aristov Denis Ivanovich

    2016-03-01

    Full Text Available The All-Russian Congress “Fire Stop Moscow” was de-voted to the analysis of the four segments of the industry of fire protection systems and technologies: the design of fire protec-tion systems, the latest developments and technologies of active and passive fire protection of buildings, the state and the devel-opment of the legal framework, the practice of fire protection of buildings and structures. The forum brought together the repre-sentatives of the industry of fire protection systems, scientists, leading experts, specialists in fire protection and representatives of construction companies from different regions of Russia. In parallel with the Congress Industrial Exhibition of fire protection systems, materials and technology was held, where manufacturers presented their products. The urgency of the “Fire Stop Moscow” Congress in 2015 organized by the Congress Bureau ODF Events lies primarily in the fact that it considered the full range of issues related to the fire protection of building and construction projects; studied the state of the regulatory framework for fire safety and efficiency of public services, research centers, private companies and busi-nesses in the area of fire safety. The main practical significance of the event which was widely covered in the media space, was the opportunity to share the views and information between management, science, and practice of business on implementing fire protection systems in the conditions of modern economic relations and market realities. : congress, fire protection, systems, technologies, fire protection systems, exhibition

  6. Conceptual Framework for Physical Protection Against Sabotage Considering Plant-specific Radiological Consequences

    International Nuclear Information System (INIS)

    Lee, Joung Hoon; Yu, Dong Han

    2010-01-01

    According to the Generation IV (Gen IV) Technology Roadmap, Gen IV nuclear energy systems (NESs) should highlight proliferation resistance and physical protection (PR and PP) as one of the four goals along with sustainability, safety and reliability, and economics. Especially, physical protection (PP) is the typical important characteristic of an NES that impedes the theft of materials suitable for nuclear explosives or radiation dispersal devices (RDD) and the sabotage of facilities and transportation by subnation entities and other non-Host State adversaries. These two subjects have been studied separately. Proliferation is commonly considered as an international concern and the past work on the PR assessments can be found. On the other hands, PP is regarded as a State security concern, much of which is classified and facility-dependent. Recently, more concern has been focused on the PP design and regulation because of rapid environment changes including radiological consequences by internal sabotage and nuclear terrorism by RDDs. The current PP Regulation has been applied intensively to the existing nuclear facilities and could be a possible guidance for the future GEN-IV NESs. This paper first reviews the IAEA guide document, INFCIRC/225, which was accepted as the standard international guideline in the physical protection area. It has been updated several times up to now, and is undergoing another revision. The paper introduces current substantial changes in the document regarding PP including the national nuclear security and sabotage in the nuclear facilities. Then, it presents a conceptual framework for physical protection against sabotage considering plant-specific radiological consequence after malicious acts within certain vital areas. The framework combines the newly developed method of vital area identification, the current PSA level 2 works, and physical protection concepts. This would help to improve a design concept of new physical protection

  7. Conceptual Framework for Physical Protection Against Sabotage Considering Plant-specific Radiological Consequences

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Joung Hoon; Yu, Dong Han [Korea Institute of Nuclear Nonproliferation and Control, Daejeon (Korea, Republic of)

    2010-10-15

    According to the Generation IV (Gen IV) Technology Roadmap, Gen IV nuclear energy systems (NESs) should highlight proliferation resistance and physical protection (PR and PP) as one of the four goals along with sustainability, safety and reliability, and economics. Especially, physical protection (PP) is the typical important characteristic of an NES that impedes the theft of materials suitable for nuclear explosives or radiation dispersal devices (RDD) and the sabotage of facilities and transportation by subnation entities and other non-Host State adversaries. These two subjects have been studied separately. Proliferation is commonly considered as an international concern and the past work on the PR assessments can be found. On the other hands, PP is regarded as a State security concern, much of which is classified and facility-dependent. Recently, more concern has been focused on the PP design and regulation because of rapid environment changes including radiological consequences by internal sabotage and nuclear terrorism by RDDs. The current PP Regulation has been applied intensively to the existing nuclear facilities and could be a possible guidance for the future GEN-IV NESs. This paper first reviews the IAEA guide document, INFCIRC/225, which was accepted as the standard international guideline in the physical protection area. It has been updated several times up to now, and is undergoing another revision. The paper introduces current substantial changes in the document regarding PP including the national nuclear security and sabotage in the nuclear facilities. Then, it presents a conceptual framework for physical protection against sabotage considering plant-specific radiological consequence after malicious acts within certain vital areas. The framework combines the newly developed method of vital area identification, the current PSA level 2 works, and physical protection concepts. This would help to improve a design concept of new physical protection

  8. Security technology discussion for emergency command system of nuclear power plant

    International Nuclear Information System (INIS)

    Liu Zhenjun

    2014-01-01

    Nuclear power plant emergency command system can provide valuable data for emergency personnel, such as the unit data, weather data, environmental radiation data. In the course of emergency response, the emergency command system provides decision support to quickly and effectively control and mitigate the consequences of the nuclear accident, to avoid and reduce the dose received by staff and the public, to protect the environment and the public. There are high performance requirements on the security of the system and the data transmission. Based on the previous project and new demand after the Fukushima incident, the security technology design of emergency system in nuclear power plant was discussed. The results show that the introduction of information security technology can effectively ensure the security of emergency systems, and enhance the capacity of nuclear power plant to deal with nuclear accidents. (author)

  9. Advancement adopted for physical protection system at BARC facilities Tarapur

    International Nuclear Information System (INIS)

    Jaroli, Manish; Ameta, Rohit; Patil, V.H.; Dubey, K.

    2015-01-01

    Considering the prevailing security situation and threat perception to the nuclear installations in particular, it has become essential to strengthen security system at BARC Tarapur in an effective manner to avert any attempt of sabotage and to ensure smooth functioning of security and safety of the nuclear installations. International Atomic Energy Agency (IAEA) and Atomic Energy Regulatory Board (AERB) have provided various security guides for the physical protection system (PPS) for nuclear installations and there has been advancement in physical and personnel protection system due to evolution of new technologies. In line with this, latest technologies have been adopted in PPS for BARC facilities, Tarapur recently. This includes state of art RFID card based access control, visitor and contractor management system, electronic key management system. Digital signature based biometric visitor and contractor management system; Digital signature based leave management system; Distress alarm system (DAS); Guard tour monitoring system (GTMS); Secure network access system (SNAS) as well as multilayered access control system at plant level. This will strengthen the surveillance and monitoring of personnel and visitors at BARC facilities. (author)

  10. An analysis of the development and application of plant protection UAV based on advanced materials

    Science.gov (United States)

    Huang, Yuan-hui; Wei, Neng; Quan, Zhi-cheng; Huang, Yu-rong

    2018-06-01

    The development and application of a number of advanced materials plant protection unmanned aerial vehicle (UAV) is an important part of the comprehensive production of agricultural modernization. The paper is taken as an example of Guangxi No. 1 agricultural service aviation science and Technology Co., Ltd. This paper introduces the internal and external environment of the research and development of the plant protection UAV for the advanced materials of the company. The external environment focuses on the role of the plant protection UAV on the development of the agricultural mechanization; the internal environment focuses on the advantages of the UAV in technology research, market promotion and application, which is imperative. Finally, according to the background of the whole industry, we put forward some suggestions for the developing opportunities and challenges faced by plant protection UAV, hoping to proving some ideas for operators, experts and scholars engaged in agricultural industry.

  11. Nuclear power plant fire protection: fire detection (subsystems study Task 2)

    International Nuclear Information System (INIS)

    Berry, D.L.

    1977-12-01

    This report examines the adequacy of fire detection in the context of nuclear power plant safety. Topics considered are: (1) establishing area detection requirements, (2) selecting specific detector types, (3) locating and spacing detectors, and (4) performing installation tests and maintenance. Based on a thorough review of fire detection codes and standards and fire detection literature, the report concludes that current design and regulatory guidelines alone are insufficient to ensure satisfactory fire detection system performance. To assure adequate fire detection, this report recommends the use of in-place testing of detectors under conditions expected to occur normally in areas being protected

  12. Protection against internal fires and explosions in the design of nuclear power plants. Safety guide

    International Nuclear Information System (INIS)

    2004-01-01

    Experience of the past two decades in the operation of nuclear power plants and modern analysis techniques confirm that fire may be a real threat to nuclear safety and should receive adequate attention from the beginning of the design process throughout the life of the plant. Within the framework of the NUSS programme, a Safety Guide on fire protection had therefore been developed to enlarge on the general requirements given in the Code. Since its first publication in 1979, there has been considerable development in protection technology and analysis methods and after the Chernobyl accident it was decided to revise the existing Guide. This Safety Guide supplements the requirements established in Safety of Nuclear Power Plants: Design. It supersedes Safety Series No. 50-SG-D2 (Rev. 1), Fire Protection in Nuclear Power Plants: A Safety Guide, issued in 1992.The present Safety Guide is intended to advise designers, safety assessors and regulators on the concept of fire protection in the design of nuclear power plants and on recommended ways of implementing the concept in some detail in practice

  13. Model-based system engineering to evaluate I and C systems human performance in nuclear power plants - 15207

    International Nuclear Information System (INIS)

    Alves, P.; Mesquita, F.; Kessel, D.; Jung, J.

    2015-01-01

    In a Nuclear Power Plant, many advantages can be obtained by introducing digital instrumentation and control (I and C) systems, such as safety improvement in fault tolerance, self-testing, signal validation, better calibration and greater data capacity. The digital system must be able to meet the needs of the plants and also be compatible with operator capabilities, in a matter that will reduce human error probability. The safety systems must be reliable, with high functionality and availability, and it is essential to have redundancy, independence and diversity among components. I and C systems require a full understanding from plant operators. This paper is intent to propose, by using the C4ISR framework, a simpler and more comprehensive way to represent the architecture of the I and C system framework. The C4ISR framework gives the possibility to define the system under 3 different views: Operational View, Systems View, and Technical View; By using the CORE model-based system engineering software, the systems view of the Plant Protection System is analyzed

  14. SEVESO: which protections for plants?

    International Nuclear Information System (INIS)

    Jouette, Isabelle

    2015-01-01

    As some recent incidents resulted in a decision to strengthen the control of SEVESO-classified sites in order to prevent malevolent and terrorist acts, this article recalls the origin of the SEVESO directive which aims at preventing major industrial risks, briefly indicates organisational measures which must me implemented on these sites (1171 sites are classified in France, an 670 as particularly dangerous), and measures taken after an explosion in a petrochemical plant in southern France (in Berre). The next part proposes an overview of the legal context and measures of protection of nuclear installations against malevolent acts, as these installations are outside the scope of the Seveso directive but depend on a specific regulation

  15. Styrene vapor control systems in FRP yacht plants.

    Science.gov (United States)

    Todd, W F

    1985-01-01

    The production of large (greater than 25-ft) fiber-reinforced plastic (FRP) yachts has presented problems of styrene exposure in excess of the Occupational Safety and Health Administration permissible exposure level (OSHA PEL) of 100 ppm. Also, the National Institute for Occupational Safety and Health (NIOSH) is currently recommending a 10-hour workshift, 40-hour workweek time weighted average (TWA) of 50 ppm for styrene. Meeting this challenge will require a system of engineering, work practice, personal protective equipment, and monitoring control measures. NIOSH has performed a study of the engineering controls in three FRP yacht plants. Work practices and the use of personal protective equipment (PPE) were also considered in the evaluation. The three systems evaluated included a dilution system, a local ventilation system, and a push-pull ventilation system. The cost of constructing and operating these systems was not evaluated in this study. Study results indicated that each type of ventilation system can meet the present PEL of 100 ppm styrene; however, it is not certain that these systems can meet a lower PEL of 50 ppm styrene.

  16. Organisation of radiation protection at Sizewell Nuclear Power Plant in the UK. Report n. 290

    International Nuclear Information System (INIS)

    Crouail, P.; Jeannin, B.; Lefaure, C.; Panisset, L.

    2004-01-01

    This report first describes the organisation and management of radiation protection at Sizewell Nuclear Power Plant (UK): general organisation, organisation of the radiation protection department, goals of radiation protection at plant and corporate levels, measurement of radiation protection performance, presence of health physicists in the plant, national and international comparisons. Then, it addresses the training of workers and radiation protection specialists with respect to radiation protection, the management of zoning and surveillance (action to address the radiation risk and the contamination risk). It describes the relationships of Health physicists with contractors and other workers teams, and the relationships with safety authorities. It indicates the different outages of this organisation: general planning, information sheets, physicists work planning, reviews and meetings. It describes the management of personal dosimetry with radiation work permits and actions aimed at the reduction of doses during various operations. The last part proposes a feedback experience report and evokes the generated database, and addresses events reporting

  17. A relay rack for a control and protection system for nuclear reactors

    International Nuclear Information System (INIS)

    Miyata, Yasuyuki; Oda, Noriaki; Akiyama, Toyoshi

    1975-01-01

    It is obvious that all the equipment in the various systems that constitute a nuclear power plant must exhibit the highest levels of reliability, but the reactor control and protection system is of vital importance, and thus it requires a particularly thorough approach, incorporating redundancy, independence and separation. The paper describes the functions, construction and specifications of the relay rack - one of the most important items of equipment for reactor control and protection in a generating facility using a pressurized-water reactor - and it gives details of the extent to which these three requirements are satisfied. (author)

  18. Firewall systems for protection of data communication in power stations; Firewall-Systeme zum Schutz der Datenkommunikation in Kraftwerken

    Energy Technology Data Exchange (ETDEWEB)

    Schoenfeld, P [Siemens AG KWU (Germany)

    1999-12-31

    Networking of power plant computer systems is becoming increasingly common. Furthermore, instrumentation and control systems are being connected with general power plant networks to make process information available to administrative personnel. This increases the risk of accidental or intentional access from outside the system (e.g. by hackers). Firewall systems are used to prevent such outside access. A firewall is the sole gateway between two networks which are to be kept separate, and is used to filter and control access to the protected network. Cryptography and personal chip cards are also used to provide additional protection. (orig.) [Deutsch] Rechnersysteme im Kraftwerk werden heute mehr und mehr vernetzt. Auch werden Rechnersysteme zum Messen, Steuern und Regeln (sogenannte Instrumentation and Control Systems) mit allgemeinen Kraftwerksnetzen verbunden, um Prozessinformationen auch in der Verwaltung zugaenglich zu machen. Damit waechst die Gefahr von zufaelligen oder beabsichtigten Eingriffen von aussen (z.B. Hacker). Zum Schutz vor solchen Eingriffen von aussen werden sogenannte Firewall-Systeme eingesetzt. Ein Firewall ist der alleinige Uebergang zwischen zwei zu trennenden Netzen und dient zur Filterung und Kontrolle der Zugriffe auf ein zu schuetzendes Netz. Ergaenzende Schutzmassnahmen sind der Einsatz kryptographischer Verfahren, sowie persoenlicher Chipkarten. (orig.)

  19. Firewall systems for protection of data communication in power stations; Firewall-Systeme zum Schutz der Datenkommunikation in Kraftwerken

    Energy Technology Data Exchange (ETDEWEB)

    Schoenfeld, P. [Siemens AG KWU (Germany)

    1998-12-31

    Networking of power plant computer systems is becoming increasingly common. Furthermore, instrumentation and control systems are being connected with general power plant networks to make process information available to administrative personnel. This increases the risk of accidental or intentional access from outside the system (e.g. by hackers). Firewall systems are used to prevent such outside access. A firewall is the sole gateway between two networks which are to be kept separate, and is used to filter and control access to the protected network. Cryptography and personal chip cards are also used to provide additional protection. (orig.) [Deutsch] Rechnersysteme im Kraftwerk werden heute mehr und mehr vernetzt. Auch werden Rechnersysteme zum Messen, Steuern und Regeln (sogenannte Instrumentation and Control Systems) mit allgemeinen Kraftwerksnetzen verbunden, um Prozessinformationen auch in der Verwaltung zugaenglich zu machen. Damit waechst die Gefahr von zufaelligen oder beabsichtigten Eingriffen von aussen (z.B. Hacker). Zum Schutz vor solchen Eingriffen von aussen werden sogenannte Firewall-Systeme eingesetzt. Ein Firewall ist der alleinige Uebergang zwischen zwei zu trennenden Netzen und dient zur Filterung und Kontrolle der Zugriffe auf ein zu schuetzendes Netz. Ergaenzende Schutzmassnahmen sind der Einsatz kryptographischer Verfahren, sowie persoenlicher Chipkarten. (orig.)

  20. Waste Isolation Pilot Plant Groundwater Protection Management Program Plan

    International Nuclear Information System (INIS)

    1993-01-01

    The DOE has mandated in DOE Order 5400.1 that its operations will be conducted in an environmentally safe manner. The Waste Isolation Pilot Plant (WIPP) will comply with DOE Order 5400.1 and will conduct its operations in a manner that ensures the safety of the environment and the public. This document outlines how the WIPP will protect and preserve groundwater within and surrounding the WIPP facility. Groundwater protection is just one aspect of the WIPP environmental protection effort. The WIPP groundwater surveillance program is designed to determine statistically if any changes are occurring in groundwater characteristics within and surrounding the WIPP facility. If a change is noted, the cause will be determined and appropriate corrective action initiated

  1. Waste Isolation Pilot Plant Groundwater Protection Management Program Plan

    Energy Technology Data Exchange (ETDEWEB)

    Washington TRU Solutions

    2002-09-24

    U.S. Department of Energy (DOE) Order 5400.1, General Environmental Protection Program, requires each DOE site to prepare a Groundwater Protection Management Program Plan. This document fulfills the requirement for the Waste Isolation Pilot Plant (WIPP). This document was prepared by the Hydrology Section of the Westinghouse TRU Solutions LLC (WTS) Environmental Compliance Department, and it is the responsibility of this group to review the plan annually and update it every three years. This document is not, nor is it intended to be, an implementing document that sets forth specific details on carrying out field projects or operational policy. Rather, it is intended to give the reader insight to the groundwater protection philosophy at WIPP.

  2. Audit program for physical security systems at nuclear power plants

    International Nuclear Information System (INIS)

    Minichino, C.

    1982-01-01

    Licensees of nuclear power plants conduct audits of their physical security systems to meet the requirements of 10 CFR 73, Physical Protection of Plants and Materials. Section 73.55, Requirements for physical Protection of Licensed Activities in Nuclear Power Reactors Against Radiological Sabotage, requires that the security programs be reviewed at least every 12 months, that the audit be conducted by individuals independent of both security management and security supervision, and that the audit program review all aspects of the physical security system: hardware, personnel, and operational and maintenance procedures. This report contains information for the Nuclear Regulatory Commission (NRC) and for the licensees of nuclear power reactors who carry out these comprehensive audits. Guidance on the overall management of the audit function includes organizational structure and issues concerning the auditors who perform the review: qualifications, independence, due professional care, and standards. Guidance in the audit program includes purpose and scope of the audit, planning, techniques, post-audit procedures, reporting, and follow-up

  3. The knowledge-based off-site emergency response system for a nuclear power plant

    International Nuclear Information System (INIS)

    Ho, L.W.; Loa, W.W.; Wang, C.L.

    1987-01-01

    A knowledge-based expert system for a nuclear power plant off-site emergency response system is described. The system incorporates the knowledge about the nuclear power plant behaviours, site environment and site geographic factors, etc. The system is developed using Chinshan nuclear power station of Taipower Company, Taiwan, ROC as a representative model. The objectives of developing this system are to provide an automated intelligent system with functions of accident simulation, prediction and with learning capabilities to supplement the actions of the emergency planners and accident managers in order to protect the plant personnel and the surrounding population, and prevent or mitigate property damages resulting from the plant accident. The system is capable of providing local and national authorities with rapid retrieval data from the site characteristics and accident progression. The system can also provide the framework for allocation of available resources and can handle the uncertainties in data and models

  4. Common Cause Failure Analysis for the Digital Plant Protection System

    International Nuclear Information System (INIS)

    Kagn, Hyun Gook; Jang, Seung Cheol

    2005-01-01

    Safety-critical systems such as nuclear power plants adopt the multiple-redundancy design in order to reduce the risk from the single component failure. The digitalized safety-signal generation system is also designed based on the multiple-redundancy strategy which consists of more redundant components. The level of the redundant design of digital systems is usually higher than those of conventional mechanical systems. This higher redundancy would clearly reduce the risk from the single failure of components, but raise the importance of the common cause failure (CCF) analysis. This research aims to develop the practical and realistic method for modeling the CCF in digital safety-critical systems. We propose a simple and practical framework for assessing the CCF probability of digital equipment. Higher level of redundancy causes the difficulty of CCF analysis because it results in impractically large number of CCF events in the fault tree model when we use conventional CCF modeling methods. We apply the simplified alpha-factor (SAF) method to the digital system CCF analysis. The precedent study has shown that SAF method is quite realistic but simple when we consider carefully system success criteria. The first step for using the SAF method is the analysis of target system for determining the function failure cases. That is, the success criteria of the system could be derived from the target system's function and configuration. Based on this analysis, we can calculate the probability of single CCF event which represents the CCF events resulting in the system failure. In addition to the application of SAF method, in order to accommodate the other characteristics of digital technology, we develop a simple concept and several equations for practical use

  5. The 10 MWe Solar Thermal Central Receiver Pilot Plant: Solar facilities design integration. Pilot-plant station manual (RADL Item 2-1). Volume 1: System description

    Science.gov (United States)

    1982-09-01

    The complete Barstow Solar Pilot Plant is described. The plant requirements and general description are presented, the mechanical, electric power, and control and instrumentation systems as well as civil engineering and structural aspects and the station buildings are described. Included in the mechanical systems are the heliostats, receiver, thermal storage system, beam characterization system, steam, water, nitrogen, and compressed air systems, chemical feed system, fire protection system, drains, sumps and the waste disposal systems, and heating, ventilating, and air conditioning systems.

  6. Program of social protection for Chornobyl nuclear power plant staff and Slavutich town residents in the aftermath of the plant shutdown

    International Nuclear Information System (INIS)

    Komarov, V.A.

    2001-01-01

    In order to solve social issues related to ChNPP shutdown, the Ukrainian Government approved 'Program of Social Protection for Chornobyl Nuclear Power Plant Staff and Slavutich Town Residents in Aftermath of Plant Shutdown' on 29 November 2000. The Program Objective is to ensure social protection and support of well being of ChNPP staff and Slavutich town residents after the plant shutdown. Preserve and develop town infrastructure. Create compensatory jobs; efficiently manage human resources; provide social allowances and guarantees to the ChNPP staff that is being released, and Slavutich town residents

  7. The continuous improvement system of nuclear power plant of Laguna Verde

    International Nuclear Information System (INIS)

    Rivera C, A.

    2009-10-01

    This paper describes the continuous improvement system of nuclear power plant of Laguna Verde and the achievements in implementing the same and additionally two study cases are presents. In February 2009 is noteworthy because the World Association of Nuclear Operators we identified as a learning organization, qualification which shows that the continuous improvement system has matured, and this system will expose as I get to learn to capitalize on our own experiences and external experiences diffused by the nuclear industry. In 2007 the management of nuclear power plants integrates its improvement systems and calls it continuous improvement system and is presented in the same extensive report that won the National Quality Award. This system is made up of 5 subsystems operating individually and are also related 1) human performance; 2) referential comparison or benchmarking; 3) self-assessment; 4) corrective action and 5) external operating experience. Five subsystems that plan, generate, capture, manage, communicate and protect the knowledge generated during the processes execution of nuclear power plant of Laguna Verde, as well as from external sources. The target set in 2007 was to increase the intellectual capital to always give response to meeting the security requirements, but creating a higher value to quality, customer, environment protection and society. In brief each of them, highlighting the objective, expectations management, implementation and some benefits. At the end they will describe two study cases selected to illustrate these cases as the organization learns by their continuous improvement system. (Author)

  8. Proposal for guidelines for the physical protection of nuclear materials, plants and transports in Denmark

    International Nuclear Information System (INIS)

    1978-03-01

    The guidelines are based on recommendations in the IAEA's ''Physical Protection of Nuclear Material,'' INFCIRC/225/rev.1. In accordance with practice in other countries, the guidelines give more detailed requirements for the protection of reactor plants than those given in the IAEA's present recommendations, which put more emphasis on the protection of nuclear materials. The measures to be taken for nuclear plants, or nuclear transports, are proposed made to fit the potential risk that the more closely defined actions imply. It is suggested that the more detailed rules for the scope of the protection of plants or materials should be laid down by the National Agency on the basis of recommendations made by the Inspectorate of Nuclear Installations, which in turn are based on the safety documentation of the plant/material owners. It is further proposed that the National Agency, again on a recommendation from the Inspectorate, should lay down more detailed guidelines for the reporting of changes in stocks or transports of nuclear materials. (author)

  9. The Ural Electrochemical Integrated Plant Process for Managing Equipment Intended for Nuclear Material Protection, Control and Accounting System Upgrades

    International Nuclear Information System (INIS)

    Yuldashev, Rashid; Nosov, Andrei; Carroll, Michael F.; Garrett, Albert G.; Dabbs, Richard D.; Ku, Esther M.

    2008-01-01

    Since 1996, the Ural Electrochemical Integrated Plant (UEIP) located in the town of Novouralsk, Russia, (previously known as Sverdlovsk-44) and the United States Department of Energy (U.S. DOE) have been cooperating under the Nuclear Material Protection, Control and Accounting (MPC and A) Program. Because UEIP is involved in the processing of highly enriched uranium (HEU) into low enriched uranium (LEU), and there are highly enriched nuclear materials on its territory, the main goal of the MPC and A cooperation is to upgrade those systems that ensure secure storage, processing and transportation of nuclear materials at the plant. UEIP has completed key upgrades (equipment procurement and installation) aimed at improving MPC and A systems through significant investments made by both the U.S. DOE and UEIP. These joint cooperative efforts resulted in bringing MPC and A systems into compliance with current regulations, which led to nuclear material (NM) theft risk reduction and prevention from other unlawful actions with respect to them. Upon the U.S. MPC and A project team's suggestion, UEIP has developed an equipment inventory control process to track all the property provided through the MPC and A Program. The UEIP process and system for managing equipment provides many benefits including: greater ease and efficiency in determining the quantities, location, maintenance and repair schedule for equipment; greater assurance that MPC and A equipment is in continued satisfactory operation; and improved control in the development of a site sustainability program. While emphasizing UEIP's equipment inventory control processes, this paper will present process requirements and a methodology that may have practical and helpful applications at other sites.

  10. Protection of nuclear power plants against external events

    International Nuclear Information System (INIS)

    Kinet, P.; Roch, R.

    1978-01-01

    The paper describes the methodology of the safety design of nuclear power plants against external events with particular emphasis of the Belgian Plants. The site analysis and potential hazards evaluation are explained. The different designs incorporating various combinations of reinforced structures and dedicated systems are analysed. The particular lay-out and systems of the Belgian Plants are explained. (author)

  11. Plant protection under conditions of radioactive contamination of agricultural lands

    International Nuclear Information System (INIS)

    Filipas, A.S.; Oulianenko, L.N.; Pimenov, E.P.

    1995-01-01

    Increasing influence of anthropogenic contaminants as well as substantiated risk of the action of ionizing radiation on agroecosystems suggest the necessity of studying both the state of separate components of cenosis and search for methods on retention of ecosystem stability as a whole. In this case it should be taken into account that by retention of resistance of living organisms to the action of stress agents not only genetically conditioned potential but induction of protective reactions at the expense of ecogene action is of deciding significance as well. Protection of agricultural plants on the territories subjected to radioactive contamination resulting from the ChNPP accident brings attention of research works to a series of problems, the main one being the minimization of pesticide use by the total ecologization of technological processes, in plant growing. But an ordinary discontinuance of conducting protective chemical measures leads to growth in the number of harmful organisms in crop sowings and as a consequence an increase of crop loss and decrease of its quality. It is possible to solve this problem by introduction of measures increasing the resistance of agricultural plants to the action of unfavorable factors of environment. Application of biologically active substances (BAS) of natural and synthetic nature for incrustation of seeds fits into these methods. For the territories with increased content of radionuclides and especially by their rehabilitation the methods of preventive treatments directed to retarding the development of harmful organisms in crop sowings and excluding subsequent technological operations on chemical protection of sowings takes on special significance as it is directly connected with the problem of radiation burden on workers of agroindustrial complex

  12. Optimization of radiological protection in Spanish nuclear power plants

    International Nuclear Information System (INIS)

    O'Donnell, P.; Amor, I.; Butragueno, J.L.

    1997-01-01

    Optimizing the radiological protection of occupationally exposed nuclear power plant workers has become one further item in what is called the safety culture. Spanish facilities are implementing programme with this in mind, grounded on a personal motivation policy with the backing of a suitable organizational structure. (Author)

  13. Reactor protection system

    International Nuclear Information System (INIS)

    Fairbrother, D.B.; Lesniak, L.M.; Orgera, E.G.

    1977-10-01

    The report describes the reactor protection system (RPS-II) designed for use on Babcock and Wilcox 145-, later 177-, and 205-fuel assembly pressurized water reactors. In this system, relays in the trip logic have been replaced by solid state devices. A calculating module for the low DNBR, pump status, and offset trip functions has replaced the overpower trip (based on flow and imbalance), the power/RC pump trip, and the variable low-pressure trip. Included is a description of the changes from the present Oconee-type reactor protection system (RPS-I), a functional and hardware description of the calculating module, a description of the software programmed in the calculating module, and a discussion of the qualification program conducted to ensure that the degree of protection provided by RPS-II is not less than that provided by previously licensed systems supplied by B and W

  14. Technical evaluation of the electrical, instrumentation, and control design aspects of the low temperature overpressure protection system for the Point Beach Nuclear Power Plant, Units 1 and 2

    Energy Technology Data Exchange (ETDEWEB)

    Laudenbach, D.H.

    1979-03-01

    The technical evaluation is presented for the electrical, instrumentation, and control design aspects of the low temperature overpressure protection system for the Point Beach nuclear power plant, Units 1 and 2. Design basis criteria used to evaluate the acceptability of the system included operator action, system testability, single failure criterion, and seismic Category I and IEEE Std-279-1971 criteria. This report is supplied as part of the Selected Electrical, Instrumentation, and Control Systems Issues Support Program being conducted for the U.S. Nuclear Regulatory Commission by Lawrence Livermore Laboratory.

  15. Technical evaluation of the electrical, instrumentation, and control design aspects of the low temperature overpressure protection system for the Point Beach Nuclear Power Plant, Units 1 and 2

    International Nuclear Information System (INIS)

    Laudenbach, D.H.

    1979-03-01

    The technical evaluation is presented for the electrical, instrumentation, and control design aspects of the low temperature overpressure protection system for the Point Beach nuclear power plant, Units 1 and 2. Design basis criteria used to evaluate the acceptability of the system included operator action, system testability, single failure criterion, and seismic Category I and IEEE Std-279-1971 criteria. This report is supplied as part of the Selected Electrical, Instrumentation, and Control Systems Issues Support Program being conducted for the U.S. Nuclear Regulatory Commission by Lawrence Livermore Laboratory

  16. Development of a coordinated control system for BWR nuclear power plant and HVDC transmission system

    International Nuclear Information System (INIS)

    Ishikawa, M.; Hara, T.; Hirayama, K.; Sekiya, K.

    1986-01-01

    The combined use of dc and ac transmissions or so-called hybrid transmission was under study, employing both dc and ac systems to enable stable transmission of 10,000 MW of electric power generated by the BWR nuclear plant, scheduled to be built about 800 km away from the center of the load. It was thus necessary to develop a hybrid power transmission control system, the hybrid power transmission system consisting of a high voltage dc transmission system (HVDC) and an ultrahigh ac transmission system (UHVAC). It was also necessary to develop a control system for HVDC transmission which protects the BWR nuclear power plant from being influenced by any change in transmission mode that occurs as a result of faults on the UHVAC side when the entire power of the BWR plant is being sent by the HVDC transmission. This paper clarifies the requirements for the HVDC system control during hybrid transmission and also during dc transmission. The control method that satisfies these requirements was studied to develop a control algorithm

  17. Protected-area boundaries as filters of plant invasions

    Czech Academy of Sciences Publication Activity Database

    Foxcroft, L. C.; Jarošík, Vojtěch; Pyšek, Petr; Richardson, D. M.; Rouget, M.

    2010-01-01

    Roč. 25, č. 2 (2010), s. 400-405 ISSN 0888-8892 R&D Projects: GA MŠk LC06073; GA ČR GA206/09/0563 Grant - others: European Comission(XE) KBBE-212459 Institutional research plan: CEZ:AV0Z60050516 Keywords : protected areas * invasive plants * Kruger National Park Subject RIV: EF - Botanics Impact factor: 4.894, year: 2010

  18. Catch the Best: Novel Screening Strategy to Select Stress Protecting Agents for Crop Plants

    Directory of Open Access Journals (Sweden)

    Christin Zachow

    2013-11-01

    Full Text Available Climate change increases stress levels for crops and affects the economic and environmental aspects of agricultural management systems. The application of stress tolerance-mediating microorganisms is an auspicious strategy for improving crop protection, and as such, we developed a direct selection strategy to obtain cultivable microorganisms from promising bioresources using the bait plants, maize, oilseed rape, sorghum and sugar beet. Alpine mosses, lichens and primrose were selected as bioresources, as each is adapted to adverse environmental conditions. A 10% crop-specific selection was found for bait plant rhizosphere communities using cultivation-independent fingerprints, and their potential role as stress protecting agents (SPA was evaluated following the cultivation of captured bacteria. In addition to assays identifying phytopathogen antagonism and plant growth promotion capacities, our evaluation included those that test the ability to allocate nutrients. Moreover, we developed new assays to measure tolerance in diverse stress conditions. A score scheme was applied to select SPAs with desired properties, and three Pseudomonas species with pronounced antagonistic activity that showed elevated tolerance to desiccation and an improved seed germination rate were subsequently chosen. Screening for environmentally-conditioned and host-adapted microorganisms provides a novel tool for target-oriented exploitation of microbial bioresources for the management of ecofriendly crops facing biotic and abiotic stresses.

  19. Variation in the effectiveness of biotic defence: the case of an opportunistic ant-plant protection mutualism.

    Science.gov (United States)

    Giusto, Bruno; Anstett, Marie-Charlotte; Dounias, Edmond; McKey, Doyle B

    2001-11-01

    Benefits to plants in facultative ant protection mutualisms are highly variable. This allows examination of the sources of this variation and the mechanisms by which ants protect plants. We studied opportunistic interactions between ants and an extrafloral nectary-bearing vine, Dioscorea praehensilis, during 3 different years. Variation in plant protection among years was striking. Several factors affected the effectiveness of the biotic defence. Stems recently emerged from the underground tuber were self-supporting, contacting no other plants and encountering few foraging ants. Stems then became lianescent, and contact with supporting plants greatly increased ant recruitment. Both species and number of ant workers influenced the effect of ants on the major herbivore, the chrysomelid beetle Lilioceris latipennis. Protective actions included limitation of oviposition (reduction in the number of eggs laid on the plant) and predation, leading to increased larval mortality. The probability of successful predation was strongly dependent on larval size. If temporarily low ant-patrolling activity allows larvae to grow beyond a critical size, their mechanical (thick integument) or chemical (plant-derived compounds in a fecal shield) defences become more effective against ants. Secondary metabolites derived from the host plant thus appear to be important for the anti-predator mechanisms of this beetle, being necessary for its survival and reproduction on a host plant that actively recruits ants as a biotic defence against herbivores.

  20. The physical protection systems at the Czech nuclear installations and the Y2K issue

    International Nuclear Information System (INIS)

    Malach, J.; Seifert, Z.; Sedlacek, J.; Bartak, L.; Polanka, J.

    1999-01-01

    The paper describes the joint effort of the State Office for Nuclear Safety, EZ, a.s., Nuclear Power Plant Dukovany and EBIS Ltd., as a subcontractor, to solve the problem of the Y2K particularly in connection with real time operation of the integrated physical protection system at Nuclear Power Plant Dukovany. (author)

  1. System 80+{trademark} standard design incorporates radiation protection lessons learned

    Energy Technology Data Exchange (ETDEWEB)

    Crom, T.D.; Naugle, C.L. [Duke Engineering & Services, Inc., Charlotte, NC (United States); Turk, R.S. [ABB Combustion Engineering Nuclear Power, Windsor, CT (United States)

    1995-03-01

    Many lessons have been learned from the current generation of nuclear plants in the area of radiation protection. The following paper will outline how the lessons learned have been incorporated into the design and operational philosophy of the System 80+{trademark} Standard Design currently under development by ABB Combustion Engineering (ABB-CE) with support from Duke Engineering and Services, Inc. and Stone and Webster Engineering Corporation in the Balance-of-Plant design. The System 80+{trademark} Standard Design is a complete nuclear power plant for national and international markets, designed in direct response to utility needs for the 1990`s, and scheduled for Nuclear Regulatory Commission (NRC) Design Certification under the new standardization rule (10 CFR Part 52). System 80+{trademark} is a natural extension of System 80{sup R} technology, an evolutionary change based on proven Nuclear Steam Supply System (NSSS) in operation at Palo Verde in Arizona and under construction at Yonggwang in the Republic of Korea. The System 80+{trademark} Containment and much of the Balance of Plant design is based upon Duke Power Company`s Cherokee Plant, which was partially constructed in the late 1970`s, but, was later canceled (due to rapid declined in electrical load growth). The System 80+{trademark} Standard Design meets the requirements given in the Electric Power Research Institute (EPRI) Advanced Light Water Reactor (ALWR) Requirements Document. One of these requirements is to limit the occupational exposure to 100 person-rem/yr. This paper illustrates how this goal can be achieved through the incorporation of lessons learned, innovative design, and the implementation of a common sense approach to operation and maintenances practices.

  2. Systems approach to tamper protection

    International Nuclear Information System (INIS)

    Myre, W.C.; Eaton, M.J.

    1980-01-01

    Tamper-protection is a fundamental requirement of effective containment and surveillance systems. Cost effective designs require that the tamper protection requirements be considered early in the design phase and at the system level. A discussion of tamper protection alternatives as well as an illustrative example system is presented

  3. The impact of faulty response of overload protection systems on the reliability of electricity supply

    International Nuclear Information System (INIS)

    Schweigert, J.; Schnuerer, G.

    1988-01-01

    Protection equipment of the engineered safety system which is to prevent the triggering of actions via signals from the reactor protection system is to be made so reliable that it has no impact on the non-availability of the supplied systems. Design and functional mode of the various overload protection equipment and the relevant switching device and combinations are explained together with the requirements such as choice, design, and adjustment of the protection equipment, followed by a survey of possible causes of faulty response of overload protection device and of the means and measures available for improvement. The now presented version of September 1987 of the 'overload protection report deals basically with all main topics of the Juli 1985 version, but has been updated and extended by material taking into account practice-oriented data on the new developments in convoy power plant design. (orig./HP) [de

  4. Diurnal adjustment in ultraviolet sunscreen protection is widespread among higher plants.

    Science.gov (United States)

    Barnes, Paul W; Flint, Stephan D; Tobler, Mark A; Ryel, Ronald J

    2016-05-01

    The accumulation of ultraviolet (UV)-absorbing compounds (flavonoids and related phenylpropanoids) in the epidermis of higher plants reduces the penetration of solar UV radiation to underlying tissues and is a primary mechanism of acclimation to changing UV conditions resulting from ozone depletion and climate change. Previously we reported that several herbaceous plant species were capable of rapid, diurnal adjustments in epidermal UV transmittance (T UV), but how widespread this phenomenon is among plants has been unknown. In the present study, we tested the generality of this response by screening 37 species of various cultivated and wild plants growing in four locations spanning a gradient of ambient solar UV and climate (Hawaii, Utah, Idaho and Louisiana). Non-destructive measurements of adaxial T UV indicated that statistically significant midday decreases in T UV occurred in 49 % of the species tested, including both herbaceous and woody growth forms, and there was substantial interspecific variation in the magnitude of these changes. In general, plants in Louisiana exhibited larger diurnal changes in T UV than those in the other locations. Moreover, across all taxa, the magnitude of these changes was positively correlated with minimum daily air temperatures but not daily UV irradiances. Results indicate that diurnal changes in UV shielding are widespread among higher plants, vary both within and among species and tend to be greatest in herbaceous plants growing in warm environments. These findings suggest that plant species differ in their UV protection "strategies" though the functional and ecological significance of this variation in UV sunscreen protection remains unclear at present.

  5. Fire protection in Angra-2 nuclear power plant. The use of fire protection collars on plastic piping systems

    International Nuclear Information System (INIS)

    Oliveira Segabinaze, R. de

    1994-01-01

    The object of this paper is to briefly the use of fire protection collars on plastic piping systems passing through wall and floor penetration. The fire protection collars consist of a stainless steel housing, in which the leading edges of two pivoting plates are in constant pressure contact with the pipe. In case of fire these plates react on the softened pipe with a guillotine action, thereby stopping the flow; within the housing a foam material expands to fill the space when subject to the heat of the fire. The piping project has to be modified to permit the fixing of the collars to walls and floor penetrations. (author). 2 refs, 9 figs

  6. Physical protection system design and evaluation

    International Nuclear Information System (INIS)

    Williams, J.D.

    1997-01-01

    The design of an effective physical protection system includes the determination of physical protection system objectives, initial design of a physical protection system, design evaluation, and probably a redesign or refinement. To develop the objectives, the designer must begin by gathering information about facility operation and conditions, such as a comprehensive description of the facility, operating conditions, and the physical protection requirements. The designer then needs to define the threat. This involves considering factors about potential adversaries: class of adversary, adversary's capabilities, and range of adversary's tactics. Next, the designer should identify targets. Determination of whether or not the materials being protected are attractive targets is based mainly on the ease or difficulty of acquisition and desirability of the material. The designer now knows the objectives of the physical protection system, that is, open-quotes what to protect against whom.close quotes The next step is to design the system by determining how best to combine such elements as fences, vaults, sensors and assessment devices, entry control elements, procedures, communication devices, and protective forces personnel to meet the objectives of the system. Once a physical protection system is designed, it must be analyzed and evaluated to ensure it meets the physical protection objectives. Evaluation must allow for features working together to ensure protection rather than regarding each feature separately. Due to the complexity of the protection systems, an evaluation usually requires modeling techniques. If any vulnerabilities are found, the initial system must be redesigned to correct the vulnerabilities and a reevaluation conducted. This paper reviews the physical protection system design and methodology mentioned above. Examples of the steps required and a brief introduction to some of the technologies used in modem physical protections system are given

  7. Concept of voltage monitoring for a nuclear power plant emergency power supply system (PWR 1300 MWe)

    International Nuclear Information System (INIS)

    Andrade, R.B. de

    1988-01-01

    Voltage monitoring concept for a Nuclear Power Plant Emergency Power Supply Systems (PWR 1300 MWe) is described based on the phylosophy adopted for Angra 2 and 3 NPP's. Some suggested setpoints are only guidance values and can be modified during plant commissioning for a better performance of the whole protection system. (author) [pt

  8. IRSN's Position on Safety and Radiation Protection at Nuclear Power Plants in France, 2012

    International Nuclear Information System (INIS)

    2014-01-01

    After working a year to consolidate the data, the annual report on the radiation protection and safety of nuclear power plants in France gives the IRSN's independent point of view on all progress and problems concerning safety and radiation protection encountered in the French nuclear power plant fleet in 2012. The first part of the report presents the main trends that emerge from IRSN's overall assessment of the radiation protection and safety performance of currently operating nuclear power plants for the year 2012. The year 2012 has witnessed an increase in the total number of significant events. However, IRSN notes the absence in 2012 of incidents with a potentially significant impact on nuclear power plant safety, the surrounding environment or nearby communities in a context of large-scale personnel renewal. This increase can mainly be explained by EDF's implementation of an improved nonconformance detection and handling procedure which led to the identification, in 2012, of various non-conformances presumably present for several years but previously undetected. With regard to radiation protection, IRSN notes that the effective dose received by the majority of exposed workers over a period of 12 consecutive months is below the annual public radiation dose limit. Faults may occur with nuclear power plant equipment or reactor monitoring systems. Given the standardisation of EDF nuclear power plant reactors, such faults may affect an entire reactor series or even the entire reactor fleet. A few examples deemed particularly significant by IRSN are presented in the second part of this report. French nuclear reactors are subject to modifications throughout their operating lives, particularly with a view to ensuring continuous safety improvement, this is the subject of the third part of the report. Most of these modifications are the result of studies conducted within the framework of ten-yearly safety reviews, leading to the definition and

  9. A Westinghouse designed distributed mircroprocessor based protection and control system

    International Nuclear Information System (INIS)

    Bruno, J.; Reid, J.B.

    1980-01-01

    For approximately five years, Westinghouse has been involved in the design and licensing of a distributed microprocessor based system for the protection and control of a pressurized water reactor nuclear steam supply system. A 'top-down' design methodology was used, in which the system global performance objectives were specified, followed by increasingly more detailed design specifications which ultimately decomposed the system into its basic hardware and software elements. The design process and design decisions were influenced by the recognition that the final product would have to be verified to ensure its capability to perform the safety-related functions of a class 1E protection system. The verification process mirrored the design process except that it was 'bottom-up' and thus started with the basic elements and worked upwards through the system in increasingly complex blocks. A number of areas which are of interest in a distributed system are disucssed, with emphasis on two systems. The first, the Integrated Protection System is primarily responsible for processing signals from field mounted sensors to provide for reactor trips and the initiation of the Engineered Safety Features. The Integrated Control System, which is organized in a parallel manner, processes other sensor signals and generates the necessary analog and on-off signals to maintain the plant parameters within specified limits. Points covered include system structure, systems partitioning strategies, communications techniques, software design concepts, reliability and maintainability, commercial component availability, interference susceptibility, licensing issues, and applicability. (LL)

  10. Evolution of the radiation protection system; L'evolution du systeme de protection radiologique

    Energy Technology Data Exchange (ETDEWEB)

    Clarke, R.H. [International Commission on Radiological Protection, Stockholm (Sweden); Schieber, C.; Cordoliani, Y.S. [Societe Francaise de Radioprotection, 92 - Fontenay aux Roses (France); Brechignac, F. [CEA Cadarache, Institut de Radioprotection et de Surete Nucleaire, Dept. de Protection de l' Environnement, 13 - Saint Paul Lez Durance (France)

    2003-07-01

    The evolution of the system of radiological protection: justification for new ICRP recommendations, thoughts of the SFRP work group about the evolution of the system of radiation protection proposed by the ICRP, protection of environment against ionizing radiations seen by the ICRP are the three parts of this chapter. (N.C.)

  11. Feasibility study for core protection calculator development

    International Nuclear Information System (INIS)

    In, W. K.; Han, J. B.

    2003-06-01

    This project confirmed the development feasibility of new digital core protection system and established development plan for ITOPS that can replace the CPC system. The development plan and implementation strategy for ITOPS proposed in this project will be useful to successfully develop advanced digital core protection system for the CPC replacement in KSNP plants. YGN units 3 and 4 are expected to replace the CPC system within next ten years and the other KSNP plants are followed. The localization model for advanced digital core protection system, ITOPS, is judged to upgrade the Common Q CPC system in both system configuration and algorithm performance and can reduce the cost for supply and maintenance. Hence, ITOPS is expected to be installed in new Korea nuclear power plants and also useful to export the associated technology in the future

  12. Digital integrated protection system

    International Nuclear Information System (INIS)

    Savornin, M.; Furet, M.

    1978-01-01

    As a result of technological progress it is now possible to achieve more elaborate protection functions able to follow more closely the phenomena to be supervised. For this reason the CEA, Framatome and Merlin/Gerin/CERCI have undertaken in commonn to develop a Digital Integrated Protection System (D.I.P.S.). This system is designed with the following aims: to improve the safety of the station, . to improve its availability, . to facilitate installation, . to facilitate tests and maintenance. The main characteristics adopted are: . possibilities of obtaining more elaborate monitoring and protection algorithm treatments, . order 4 redundancy of transducers, associated instruments and signal processing, . possibility of inhibiting part of the protection system, . standardisation of equipment, physical and electrical separation of redundant units, . use of multiplexed connections, . automation of tests. Four flow charts are presented: - DIPS with four APUP (Acquisition and Processing Unit for Protection) - APUP - LSU (Logic Safeguard Unit), number LSU corresponding to number fluidic safeguard circuits, - structure of a function unit, - main functions of the APUP [fr

  13. Surface protection of inner shells of cooling towers. Positive long-term experience with coating systems.; Oberflaechenschutz von Kuehlturminnenschalen. Positive Langzeiterfahrungen mit Beschichtungssystemen

    Energy Technology Data Exchange (ETDEWEB)

    Heine, Peer [MC-Bauchemie Mueller GmbH und Co.KG, Bottrop (Germany)

    2010-07-15

    Natural-draught cooling tower are modern power plant components with great importance for safe and reliable power supply. Due to the complex effects of operating and environmental conditions especially on the inner shell, the concrete must be protected by special resin-based surface coating systems. Parallel to the development of the power plant technology, also the coating systems are under constant improvement in order to ensure reliable and permanent protection. The positive long-term experience suggests that power plant operators may rely on a high level of safety here. (orig.)

  14. Modern cooling systems in thermal power plants relieve environmental pollution. Pt. 2

    International Nuclear Information System (INIS)

    Brosche, D.

    1983-01-01

    Direct and indirect dry recirculation cooling, wet cooling tower, natural-draught wet cooling tower, combined cooling processes, hybrid cooling systems, cell cooling systems, auxiliary water preparation, cooling process design, afterheat removal in nuclear power plants, environmental effects, visible plumes as a function of weather conditions, environmental protection and energy supply assurance. (orig.) [de

  15. Review of the radiation protection calculations for the encapsulation plant

    International Nuclear Information System (INIS)

    Ranta-aho, A.

    2008-09-01

    The radiation protection calculations of the encapsulation plant have been carried out with the MCNP5 Monte Carlo code. The focus of the study has been in the parts of the encapsulation plant where the spent fuel is handled after discharge from the transportation casks i.e. the fuel handling cell, the fuel drying station, the canister transfer corridor, the welding chamber, the weld inspection room, the canister buffer storage and the canister lift. The protection against radiation hazard has been mainly designed with thick concrete walls. Additionally, the entrances to the rooms with shielding requirements have been equipped with mazes. The present design excludes doors with shielding properties. The aim of this work was to verify and evaluate the necessary wall thicknesses and the functioning of the mazes in the current design. The calculations verified that for the most parts of the facility, the currently designed walls thicknesses provide adequate protection against radiation from the different spent fuel assembly configurations. Some corrective actions however seem necessary in order to stay clearly below desired radiation limits. For the most parts the functioning of the mazes was inadequate. In some of the cases a different design of the maze will be sufficient action but in some cases the radiation protection can only be secured by heavy doors for practical reasons. (orig.)

  16. Laboratory evaluation of four medicinal plants as protectants against ...

    African Journals Online (AJOL)

    The petroleum ether extract of four medicinal plants; Aristolochia ringens (Vahl), Allium sativum (L), Ficus exasperata (L) and Garcinia kola (H), were evaluated as grain protectant against the maize weevil, Sitophilus zeamais (Mots) in the laboratory at 0.5, 1.0 and 1.5% (w/v) concentrations. Parameters assessed were adult ...

  17. Control system for technological processes in tritium processing plants with process analysis

    International Nuclear Information System (INIS)

    Retevoi, Carmen Maria; Stefan, Iuliana; Balteanu, Ovidiu; Stefan, Liviu; Bucur, Ciprian

    2005-01-01

    Integration of a large variety of installations and equipment into a unitary system for controlling the technological process in tritium processing nuclear facilities appears to be a rather complex approach particularly when experimental or new technologies are developed. Ensuring a high degree of versatility allowing easy modifications in configurations and process parameters is a major requirement imposed on experimental installations. The large amount of data which must be processed, stored and easily accessed for subsequent analyses imposes development of a large information network based on a highly integrated system containing the acquisition, control and technological process analysis data as well as data base system. On such a basis integrated systems of computation and control able to conduct the technological process could be developed as well protection systems for cases of failures or break down. The integrated system responds to the control and security requirements in case of emergency and of the technological processes specific to the industry that processes radioactive or toxic substances with severe consequences in case of technological failure as in the case of tritium processing nuclear plant. In order to lower the risk technological failure of these processes an integrated software, data base and process analysis system are developed, which, based on identification algorithm of the important parameters for protection and security systems, will display the process evolution trend. The system was checked on a existing plant that includes a removal tritium unit, finally used in a nuclear power plant, by simulating the failure events as well as the process. The system will also include a complete data base monitoring all the parameters and a process analysis software for the main modules of the tritium processing plant, namely, isotope separation, catalytic purification and cryogenic distillation

  18. The capacity of Australia's protected-area system to represent threatened species.

    Science.gov (United States)

    Watson, James E M; Evans, Megan C; Carwardine, Josie; Fuller, Richard A; Joseph, Liana N; Segan, Dan B; Taylor, Martin F J; Fensham, R J; Possingham, Hugh P

    2011-04-01

    The acquisition or designation of new protected areas is usually based on criteria for representation of different ecosystems or land-cover classes, and it is unclear how well-threatened species are conserved within protected-area networks. Here, we assessed how Australia's terrestrial protected-area system (89 million ha, 11.6% of the continent) overlaps with the geographic distributions of threatened species and compared this overlap against a model that randomly placed protected areas across the continent and a spatially efficient model that placed protected areas across the continent to maximize threatened species' representation within the protected-area estate. We defined the minimum area needed to conserve each species on the basis of the species' range size. We found that although the current configuration of protected areas met targets for representation of a given percentage of species' ranges better than a random selection of areas, 166 (12.6%) threatened species occurred entirely outside protected areas and target levels of protection were met for only 259 (19.6%) species. Critically endangered species were among those with the least protection; 12 (21.1%) species occurred entirely outside protected areas. Reptiles and plants were the most poorly represented taxonomic groups, and amphibians the best represented. Spatial prioritization analyses revealed that an efficient protected-area system of the same size as the current protected-area system (11.6% of the area of Australia) could meet representation targets for 1272 (93.3%) threatened species. Moreover, the results of these prioritization analyses showed that by protecting 17.8% of Australia, all threatened species could reach target levels of representation, assuming all current protected areas are retained. Although this amount of area theoretically could be protected, existing land uses and the finite resources available for conservation mean land acquisition may not be possible or even effective

  19. Surface treatments for material protection in nuclear power plants

    International Nuclear Information System (INIS)

    De, P.K.; Gadiyar, H.S.

    1987-01-01

    The paper highlights some of the surface treatment methods used in nuclear power plants to improve their performance. The corrosion resistance of zirconium alloys results from the formation of an adherent and protective film of ZrO 2 . Graphite coating of zircaloy-2 cladding minimizes the susceptibility to environmental induced cracking. Magnetite formation during the hot conditioning operation improves the corrosion resistance of carbon steel as well as controls the spread of radioactivity. It has been illustrated how the surface treatment is helpful for redistributing residual stress to facilitate conversion of tensile stress to compressive stress to mitigate failures due to stress corrosion and fatigue corrosion. Inhibitors and passivators can modify the surface conditions (in situ) of condenser tubes and cooling water systems. These aspects have been dealt in the text of the paper. (author). 8 refs., 3 figures

  20. Improvement of fire protection measures for nuclear power plants

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2013-08-15

    Improvements of fire protection measures for nuclear power plants were performed as following items: Development of fire hazard analysis method. Application of developed Fire Dynamic Tool to actual plants (FDT{sup S}), With regard to fire tests for the fire data acquisition, cable fire test and High Energy Arcing Faults (HEAF) fire test were performed. Implementation of fire hazard analysis code and simulation were performed as following items: Fire analysis codes FDS, SYLVIA, and CFAST were implemented in order to analyze the fire progression phenomena. Trial simulation of HEAF accident of Onagawa NPP in Tohoku earthquake. (author)

  1. Improvement of fire protection measures for nuclear power plants

    International Nuclear Information System (INIS)

    2012-01-01

    Improvements of fire protection measures for nuclear power plants were performed as following items: Development of fire hazard analysis method. Application of developed Fire Dynamic tool to actual plants, With regard to fire tests for the fire data acquisition, cable fire test and oil fire test were performed. Implementation of fire hazard analysis code and simulation were performed as following items: Fire analysis codes FDS, SYLVIA, CFAST were implemented in order to analyze the fire progression phenomena, Trial simulation of fire hazard as Metal-Clad Switch Gear Fire of ONAGAWA NPP in Tohoku earthquake (HEAF accident). (author)

  2. System Simulation of Nuclear Power Plant by Coupling RELAP5 and Matlab/Simulink

    International Nuclear Information System (INIS)

    Meng Lin; Dong Hou; Zhihong Xu; Yanhua Yang; Ronghua Zhang

    2006-01-01

    Since RELAP5 code has general and advanced features in thermal-hydraulic computation, it has been widely used in transient and accident safety analysis, experiment planning analysis, and system simulation, etc. So we wish to design, analyze, verify a new Instrumentation And Control (I and C) system of Nuclear Power Plant (NPP) based on the best-estimated code, and even develop our engineering simulator. But because of limited function of simulating control and protection system in RELAP5, it is necessary to expand the function for high efficient, accurate, flexible design and simulation of I and C system. Matlab/Simulink, a scientific computation software, just can compensate the limitation, which is a powerful tool in research and simulation of plant process control. The software is selected as I and C part to be coupled with RELAP5 code to realize system simulation of NPPs. There are two key techniques to be solved. One is the dynamic data exchange, by which Matlab/Simulink receives plant parameters and returns control results. Database is used to communicate the two codes. Accordingly, Dynamic Link Library (DLL) is applied to link database in RELAP5, while DLL and S-Function is applied in Matlab/Simulink. The other problem is synchronization between the two codes for ensuring consistency in global simulation time. Because Matlab/Simulink always computes faster than RELAP5, the simulation time is sent by RELAP5 and received by Matlab/Simulink. A time control subroutine is added into the simulation procedure of Matlab/Simulink to control its simulation advancement. Through these ways, Matlab/Simulink is dynamically coupled with RELAP5. Thus, in Matlab/Simulink, we can freely design control and protection logic of NPPs and test it with best-estimated plant model feedback. A test will be shown to illuminate that results of coupling calculation are nearly the same with one of single RELAP5 with control logic. In practice, a real Pressurized Water Reactor (PWR) is

  3. Physical protection systems and Y2K issue in the Slovak Republic

    International Nuclear Information System (INIS)

    Bezak, S.

    1999-01-01

    After political and economical changes in the end of eighties the utility operating nuclear power plants in the Slovak Republic (SE, a.s.) decided to upgrade physical protection system of nuclear installations. System based on guards army police) was replaced by sophisticated one comprising barriers with detection and controlled by computers. Due to date format used by control software the utility is facing a problems approaching the year 2000. (author)

  4. The potential impact of invasive woody oil plants on protected areas in China under future climate conditions.

    Science.gov (United States)

    Dai, Guanghui; Yang, Jun; Lu, Siran; Huang, Conghong; Jin, Jing; Jiang, Peng; Yan, Pengbo

    2018-01-18

    Biodiesel produced from woody oil plants is considered a green substitute for fossil fuels. However, a potential negative impact of growing woody oil plants on a large scale is the introduction of highly invasive species into susceptible regions. In this study, we examined the potential invasion risk of woody oil plants in China's protected areas under future climate conditions. We simulated the current and future potential distributions of three invasive woody oil plants, Jatropha curcas, Ricinus communis, and Aleurites moluccana, under two climate change scenarios (RCP2.6 and RCP8.5) up to 2050 using species distribution models. Protected areas in China that will become susceptible to these species were then identified using a spatial overlay analysis. Our results showed that by 2050, 26 and 41 protected areas would be threatened by these invasive woody oil plants under scenarios RCP2.6 and RCP8.5, respectively. A total of 10 unique forest ecosystems and 17 rare plant species could be potentially affected. We recommend that the invasive potential of woody oil plants be fully accounted for when developing forest-based biodiesel, especially around protected areas.

  5. Effect of Remote Back-Up Protection System Failure on the Optimum Routine Test Time Interval of Power System Protection

    Directory of Open Access Journals (Sweden)

    Y Damchi

    2013-12-01

    Full Text Available Appropriate operation of protection system is one of the effective factors to have a desirable reliability in power systems, which vitally needs routine test of protection system. Precise determination of optimum routine test time interval (ORTTI plays a vital role in predicting the maintenance costs of protection system. In the most previous studies, ORTTI has been determined while remote back-up protection system was considered fully reliable. This assumption is not exactly correct since remote back-up protection system may operate incorrectly or fail to operate, the same as the primary protection system. Therefore, in order to determine the ORTTI, an extended Markov model is proposed in this paper considering failure probability for remote back-up protection system. In the proposed Markov model of the protection systems, monitoring facility is taken into account. Moreover, it is assumed that the primary and back-up protection systems are maintained simultaneously. Results show that the effect of remote back-up protection system failures on the reliability indices and optimum routine test intervals of protection system is considerable.

  6. Health protection and industrial safety. Nuclear power plants

    International Nuclear Information System (INIS)

    1987-03-01

    The standard applies to components of the primary circuit including its auxiliary facilities, and of the secondary circuit of nuclear power plants with pressurized water reactors; to lifting gear and load take-ups for the transport of nuclear fuel and primary circuit components; to elevators within the containment, electrical installations, and piping and valves of radiation protection monitoring equipment. Part 1 defines the terms and specifies engineered safety requirements

  7. Concept of system safety on operating nuclear power plant

    International Nuclear Information System (INIS)

    Miyano, Hiroshi; Yamaguchi, Akira; Demachi, Kazuyuki; Takata, Takashi; Arai, Shigeki; Sugiyama, Naoki

    2015-01-01

    The total system design on Nuclear Plant ensures 'Nuclear safety' with making practically achievable efforts to prevent and mitigate nuclear and radiological accidents. The performance based system design with 'Defence in depth (D-I-D)' has been laid out as the key means in 'preventing accidents', 'controlling escalation to serious consequences', and 'preventing harmful consequences to the public'. D-I-D is extended to the management of severe accidents, and is an approach intended to provide protection against the development of a wide variety of events by means of redundant, diverse and independent protective barriers. It is crucial to maintain plant integrity with mass quantity of radioactive material present in reactor core, against potential consequences (risk) on people and the environment caused by external hazards, particularly, earthquake and tsunami. The fundamental approach on D-I-D is to address uncertainties by means of successive measures, so that if one measure fails, other, or subsequent measure will be available to ensure safety. Risk analysis should be conducted to validate and enhance reliability of the defence barriers against consequences on people and the environment. (author)

  8. Novel roles for genetically modified plants in environmental protection

    Czech Academy of Sciences Publication Activity Database

    Macek, Tomáš; Kotrba, Pavel; Svatoš, Aleš; Nováková, Martina; Demnerová, K.; Macková, Martina

    2008-01-01

    Roč. 26, č. 3 (2008), s. 146-152 ISSN 0167-7799 R&D Projects: GA AV ČR IAA4055204; GA MŠk 1M06030 Institutional research plan: CEZ:AV0Z40550506 Keywords : transgenic plant * environmental protection * insect pheromone * phytoremediation Subject RIV: EI - Biotechnology ; Bionics Impact factor: 6.624, year: 2008

  9. Advanced plant design recommendations from Cook Nuclear Plant experience

    International Nuclear Information System (INIS)

    Zimmerman, W.L.

    1993-01-01

    A project in the American Electric Power Service Corporation to review operating and maintenance experience at Cook Nuclear Plant to identify recommendations for advanced nuclear plant design is described. Recommendations so gathered in the areas of plant fluid systems, instrument and control, testing and surveillance provisions, plant layout of equipment, provisions to enhance effective maintenance, ventilation systems, radiological protection, and construction, are presented accordingly. An example for a design review checklist for effective plant operations and maintenance is suggested

  10. Guideline of Cyber Security Policy for Digital I and C Systems in Nuclear Power Plant

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Zeen; Kim, Jang Seong; Kim, Kwang Jo [Information and Communications University, Daejeon (Korea, Republic of); Kang, Young Doo; Kim, Dai Il; Jeong, Choong Heui [Korea Institute of Nuclear Safety, Daejeon (Korea, Republic of)

    2007-10-15

    Recently computers and communication systems have been developed very fast and applied to various areas in many applications. This development has raised new vulnerabilities that may endanger the critical systems for nuclear safety and physical protection at the facilities. In order to protect the critical infrastructures from these new cyber attacks, we clearly need deep considerations on the risks and threats through the cyberspace. Based on these needs, many organizations which related to nuclear power plants suggested various cyber security protection methods based on regulation or technical safeguard. Even if security countermeasures against various cyber attacks are important, it is required to establish the best practices of cyber security policy by the vendor and licensee. Based on the policy they can evaluate their activities against various cyber attacks throughout the whole life cycle. In this paper, we discuss how to establish the cyber security policy for digital instrumentation and control (I and C) systems in nuclear power plants.

  11. Guideline of Cyber Security Policy for Digital I and C Systems in Nuclear Power Plant

    International Nuclear Information System (INIS)

    Kim, Zeen; Kim, Jang Seong; Kim, Kwang Jo; Kang, Young Doo; Kim, Dai Il; Jeong, Choong Heui

    2007-01-01

    Recently computers and communication systems have been developed very fast and applied to various areas in many applications. This development has raised new vulnerabilities that may endanger the critical systems for nuclear safety and physical protection at the facilities. In order to protect the critical infrastructures from these new cyber attacks, we clearly need deep considerations on the risks and threats through the cyberspace. Based on these needs, many organizations which related to nuclear power plants suggested various cyber security protection methods based on regulation or technical safeguard. Even if security countermeasures against various cyber attacks are important, it is required to establish the best practices of cyber security policy by the vendor and licensee. Based on the policy they can evaluate their activities against various cyber attacks throughout the whole life cycle. In this paper, we discuss how to establish the cyber security policy for digital instrumentation and control (I and C) systems in nuclear power plants

  12. THE USE OF PLANTS TO PROTECT PLANTS AND FOOD AGAINST FUNGAL PATHOGENS: A REVIEW.

    Science.gov (United States)

    Shuping, D S S; Eloff, J N

    2017-01-01

    Plant fungal pathogens play a crucial role in the profitability, quality and quantity of plant production. These phytopathogens are persistent in avoiding plant defences causing diseases and quality losses around the world that amount to billions of US dollars annually. To control the scourge of plant fungal diseases, farmers have used fungicides to manage the damage of plant pathogenic fungi. Drawbacks such as development of resistance and environmental toxicity associated with these chemicals have motivated researchers and cultivators to investigate other possibilities. Several databases were accessed to determine work done on protecting plants against plant fungal pathogens with plant extracts using search terms "plant fungal pathogen", "plant extracts" and "phytopathogens". Proposals are made on the best extractants and bioassay techniques to be used. In addition to chemical fungicides, biological agents have been used to deal with plant fungal diseases. There are many examples where plant extracts or plant derived compounds have been used as commercial deterrents of fungi on a large scale in agricultural and horticultural setups. One advantage of this approach is that plant extracts usually contain more than one antifungal compound. Consequently the development of resistance of pathogens may be lower if the different compounds affect a different metabolic process. Plants cultivated using plants extracts may also be marketed as organically produced. Many papers have been published on effective antimicrobial compounds present in plant extracts focusing on applications in human health. More research is required to develop suitable, sustainable, effective, cheaper botanical products that can be used to help overcome the scourge of plant fungal diseases. Scientists who have worked only on using plants to control human and animal fungal pathogens should consider the advantages of focusing on plant fungal pathogens. This approach could not only potentially increase

  13. [Storage of plant protection products in farms: minimum safety requirements].

    Science.gov (United States)

    Dutto, Moreno; Alfonzo, Santo; Rubbiani, Maristella

    2012-01-01

    Failure to comply with requirements for proper storage and use of pesticides in farms can be extremely hazardous and the risk of accidents involving farm workers, other persons and even animals is high. There are still wide differences in the interpretation of the concept of "securing or making safe", by workers in this sector. One of the critical points detected, particularly in the fruit sector, is the establishment of an adequate storage site for plant protection products. The definition of "safe storage of pesticides" is still unclear despite the recent enactment of Legislative Decree 81/2008 regulating health and work safety in Italy. In addition, there are no national guidelines setting clear minimum criteria for storage of plant protection products in farms. The authors, on the basis of their professional experience and through analysis of recent legislation, establish certain minimum safety standards for storage of pesticides in farms.

  14. Polyamine Spermine Protects Young Pea Plants Against Ultraviolet-C Radiation

    International Nuclear Information System (INIS)

    Todorovska, D.; Katerova, Z.; Shopova, E.; Nikolova, A.; Georgieva, N.; Sergiev, I.

    2013-01-01

    The effects of ultraviolet-C - UV-C irradiation and polyamine spermine on the content of some stress marker and non-enzymatic antioxidants in leaves of young pea plants were investigated. UV-C irradiation led to a decrease in pea fresh weight, the content of leaf pigments and free proline, accompanied with an increase in malondialdehyde. The initial augmentation in the free thiol levels was transient in UV-C treated plants and finally a substantial decrease was found. Spermine led to a significant augmentation of free thiols and proline content along with a decline in total phenols, but these alterations diminished during the experimental period. Based on comparative analyses of the results obtained for plants treated with UV-C and polyamine, it could be concluded that preliminary application of spermine protects pea plants against irradiation, by maintaining normal plant growth, stabilizing cell membranes and activating non-enzymatic antioxidants

  15. Trends in radiation protection: possible effects on fusion power plant design

    International Nuclear Information System (INIS)

    Eurajoki, Tapani; Frias, Manuel Pascual; Orlandi, Sergio

    2003-01-01

    Since the design of fusion power plants involves long-term issues, ranging over several decades, it is useful to try to foresee under what kind of regulations the first fusion plants are to be operated. Application of present radiological regulations and practice to a fusion power plant concept is considered. The current design phase of fusion power plants motivates the top-down dose assessment, but it is crucial to aim at bottom-up assessments to ensure radiation doses as low as reasonably achievable. Since several issues, relating both to our knowledge on radiation as well as to the practice of radiation protection, may change in the future, it is necessary to continuously follow the development in the further design of fusion power plants

  16. Adaptive protection algorithm and system

    Science.gov (United States)

    Hedrick, Paul [Pittsburgh, PA; Toms, Helen L [Irwin, PA; Miller, Roger M [Mars, PA

    2009-04-28

    An adaptive protection algorithm and system for protecting electrical distribution systems traces the flow of power through a distribution system, assigns a value (or rank) to each circuit breaker in the system and then determines the appropriate trip set points based on the assigned rank.

  17. The System 80+ Standard Plant design control document. Volume 10

    International Nuclear Information System (INIS)

    1997-01-01

    This Design Control Document (DCD) is a repository of information comprising the System 80+trademark Standard Plant Design. The DCD also provides that design-related information to be incorporated by reference in the design certification rule for the System 80+ Standard Plant Design. Applicants for a combined license pursuant to 10 CFR 52 must ensure that the final Design Certification Rule and the associated Statements of Consideration are used when making all licensing decisions relevant to the System 80+ Standard Plant Design. The Design Control Document contains the DCD introduction, The Certified Design Material (CDM) [i.e., ''Tier 1''] and the Approved Design Material (ADM) [i.e., ''Tier 2''] for the System 80+ Standard Plant Design. The CDM includes the following sections: (1) Introductory material; (2) Certified Design Material for System 80+ systems and structures; (3) Certified Design Material for non-system-based aspects of the System 80+ Certified design; (4) Interface requirements; and (5) Site parameters. The ADM, to the extent applicable for the System 80+ Standard Plant Design, includes: (1) the information required for the final safety analysis report under 20 CFR 50.34; (2) other relevant information required by 10 CFR 52.47; and (3) emergency operations guidelines. This volume contains Appendices 6A, 6B, and 6C for section 6 (Engineered Safety Features) of the ADM Design and Analysis. Also, parts 1--5 of section 7 (Instrumentation and Control) of the ADM Design and Analysis are covered. The following information is covered in these parts: introduction; reactor protection system; ESF actuation system; system required for safe shutdown; and safety-related display instrumentation

  18. Advanced Worker Protection System

    International Nuclear Information System (INIS)

    1996-04-01

    The Advanced Worker Protection System (AWPS) is a liquid-air-based, self-contained breathing and cooling system with a duration of 2 hrs. AWPS employs a patented system developed by Oceaneering Space Systems (OSS), and was demonstrated at their facility in Houston, TX as well as at Kansas State University, Manhattan. The heart of the system is the life-support backpack that uses liquid air to provide cooling as well as breathing gas to the worker. The backpack is combined with advanced protective garments, an advanced liquid cooling garment (LCG), a respirator, and communications and support equipment. The prototype unit development and testing under Phase 1 has demonstrated that AWPS has the ability to meet performance criteria. These criteria were developed with an understanding of both the AWPS capabilities and the DOE decontamination and decommissioning (D and D) activities protection needs

  19. Observations on physical protection methods for protecting against unauthorized acts by an insider

    International Nuclear Information System (INIS)

    Ericson, D.M.; Goldman, L.A.; Lobner, R.R.

    1983-01-01

    Two basic approaches have evolved over the past several years for physical protection against sabotage by insiders. One, area-type physical protection, involves the use of access controls at area boundaries. Current practices at nuclear power plants generally fall into this category. The second, component-level physical protection, involves hardware at individual components as well as access controls at the boundary. The area-type physical protection concepts include team, area, and operational zoning. Team zoning requires the formation of multiperson teams that must be used to gain access to vital areas. Area zoning divides the plant into two or more zones, each of which is operated and maintained by separate, dedicated teams. Operational zoning is a closed-loop access control system that permits an initial vital area access, but blocks access to certain other vital areas until the operability of equipment in the first area is verified by test or inspection. Component-level physical protection is also a closed-loop system in which both area and component access are monitored. Each of the above measures can provide effective protection against an insider in certain instances, but each has weaknesses that must be recognized. An approach for protection against the insider is to take the most promising features of each of the above physical protection measures and supplement these capabilities with damage control and design changes as appropriate for a particular plant

  20. The protection system to Brazilian Nuclear Program; O sistema de protecao ao Programa Nuclear Brasileiro

    Energy Technology Data Exchange (ETDEWEB)

    Andreuzza, Mario Giussepp Santezzi Bertottelli [Secretaria de Assuntos Estrategicos (SAE), Brasilia, DF (Brazil)

    1997-12-31

    The Sistema de Protecao ao Programa Nuclear Brasileiro-SIPRON (Protection System to Brazilian Nuclear Program) was established in 1980. It is intended to accomplish in only one system, all the actions related to security and protection for Nuclear Facilities in Brazil. The author presents in detail the protection system SIPRON, describing the system structure and organization, the functions and obligations of the system involved main organizations, as well as, the system operation and behaviour during an postulated occurrence of a nuclear emergency. It is also described an Exercise that happened in June of 1997 at the Nuclear Power Plant (NPP) Angra I, after two simulated tests in December of 1996 and April of 1997. The NPP Angra I Emergency Plan Exercise was a good opportunity to test the SIPRON structure and preparedness program. It was verified, included by International Atomic Energy Agency observers, the system involved organizations effectiveness and the procedures efficacy to protect the public and the environmental. Finally, it is shown the SIPRON activities of routine, the system obstacles and the expected future performances. (author) 3 refs., 3 figs.

  1. Greater Focus Needed on Alien Plant Impacts in Protected Areas

    Czech Academy of Sciences Publication Activity Database

    Hulme, P. E.; Pyšek, Petr; Pergl, Jan; Jarošík, Vojtěch; Schaffner, U.; Vila, M.

    2014-01-01

    Roč. 7, č. 5 (2014), s. 459-466 ISSN 1755-263X R&D Projects: GA ČR(CZ) GAP504/11/1028 Institutional support: RVO:67985939 Keywords : plant invasions * impact * protected areas Subject RIV: EF - Botanics Impact factor: 7.241, year: 2014

  2. Burst protected nuclear reactor plant with PWR

    International Nuclear Information System (INIS)

    Harand, E.; Michel, E.

    1978-01-01

    In the PWR, several integrated components from the steam raising unit and the main coolant pump are grouped around the reactor pressure vessel in a multiloop circuit and in a vertical arrangement. For safety reasons all primary circuit components and pipelines are situated in burst protection covers. To reduce the area of the plant straight tube steam raising units with forced circulation are used as steam raising units. The boiler pumps are connected to the vertical tubes and to the pressure vessel via double pipelines made as twin chamber pipes. (DG) [de

  3. Fish protection at steam-electric power plants: alternative screening devices

    International Nuclear Information System (INIS)

    Cannon, J.B.

    1978-01-01

    Since the enactment of the Federal Water Pollution Control Act Amendments of 1972, very few innovations have surfaced that advance the state of intake technology for fish protection at steam-electric power plants. After careful examination of basic hydrology, hydraulics, and ecology of the source water body is completed and after a suitable location for the intake is established, the design process reduces to the development of proper screening techniques and to the provision of a means of preventing resident and migratory species from entering the intake structure. As a result of this design process, three basic fish protection concepts have evolved: fish deterrence, fish collection and removal, and fish diversion. Intake screening devices that protect fish are discussed

  4. Radiation protection in connection with the decommissioning of nuclear plants

    International Nuclear Information System (INIS)

    1997-04-01

    This document presents the SSI preliminary views and position concerning the decommissioning of nuclear plants. To prevent the exposure of the decommissioning personnel and the general public to unacceptable levels of radiation and to protect the environment and future generations, it is SSI's task to formulate and issue the necessary terms and regulations with which the reactor licensees must comply during the decommissioning work. The views and principles presented here are the basis of SSI's continued work on guidelines and regulations for the decommissioning of nuclear plants

  5. Protection of industrial power systems

    CERN Document Server

    DAVIES, T

    2006-01-01

    The protection which is installed on an industrial power system is likely to be subjected to more difficult conditions than the protection on any other kind of power system. Starting with the many simple devices which are employed and covering the whole area of industrial power system protection, this book aims to help achieve a thorough understanding of the protection necessary.Vital aspects such as the modern cartridge fuse, types of relays, and the role of the current transformer are covered and the widely used inverse definite-minimum time overcurrent relay, the theory of the M

  6. Continuous emission monitoring systems for power plants. The state-of-the-art

    International Nuclear Information System (INIS)

    Bamberger, J.A.

    1988-01-01

    Continuous monitoring of power plant emissions is performed to improve combustion and control equipment efficiency, and in response to various government agency requirements. This paper focuses upon recent developments in Continuous Emission Monitoring (CEM) and Systems (CEMS) for power plants. Topics presented include the perspective of the U.S. Environmental Protection Agency and the states: Continuous Monitoring of Power Plant Emissions - An EPA Perspective; Pennsylvania's Proposed Continuous Emission Monitoring System Data Telemetry Requirements for Municipal, Hospital and Infectious Waste Incinerators; the importance of quality assurance; Continuous Emission Monitoring and Quality Assurance Requirements for New Power Plants; Highlights of Pennsylvania's Continuous Emission Monitoring System Quality Assurance Program; improved system specifications and data acquisition methods; Improved Specifications for Continuous Emission Monitoring; A Microcomputer-Based Data Acquisition System for CEMS; CEMS applications; Expanded Use of CEMS in Acid Rain Control Programs: Opinions of Users, Control Agencies and Vendors; and an innovative measurement technique to assess electrostatic precipitator performance; The Assessment of Pulverized Coal Fly Ash Collection in Electrostatic Precipitators Using an Instrumental Assessment Technique

  7. Degraded voltage protection at nuclear plant safety buses

    International Nuclear Information System (INIS)

    Haddad, S.Z.; Berger, W.E.

    1989-01-01

    This paper reviews the events that led to the NRC's degraded voltage protection requirement and outlines the related NRC positions. It describes problems that have occurred with the protection scheme and identifies the measures required to minimize the occurrence of these problems. The paper recommends new guidelines for degraded voltage protection and proposes a protection scheme logic that aims at enhancing the reliability of the safety systems

  8. Evaluation of the degradation of the service water system in nuclear plants

    International Nuclear Information System (INIS)

    Salaices A, E.

    2003-01-01

    The service water system, the circulation water system, the cooling water system and the protection against fires system so much in nuclear plants as in fossils plants they are being degraded by a wide variety of mechanisms. These mechanisms include microbiologically influenced corrosion, cavitation, erosion-corrosion, erosion by solid particles, corrosion in cracks, stings, general corrosion, galvanic corrosion, sedimentation and obstructions and incrustations in the heat exchangers. In the last years were developed predictive models for the more common degradation forms and were installed in a new application of the CHECWORKS TM code called Cooling Water Application (CWA). This application of the code provides a new technology that so much nuclear facilities as fossil ones can use to modelling specific systems and to carry out corrosion predictions in each one of its components. Presently work the results of the employment of the CHECWORKS CWA code are described to carry out predictions of 12 different corrosion mechanisms that affect to the service water system of a nuclear plant, as well as the recommendations and options that the plant can to consider to reduce indexes of damages. This work can be used for to optimize inspections to the service water system and it gives the bases for similar changes in other nuclear plants. (Author)

  9. Relay protection coordination with generator capability curve, excitation system limiters and power system relay protections settings

    Directory of Open Access Journals (Sweden)

    Buha Danilo

    2016-01-01

    Full Text Available The relay protection settings performed in the largest thermal powerplant (TE "Nikola Tesla B" are reffered and explained in this paper. The first calculation step is related to the coordination of the maximum stator current limiter settings, the overcurrent protection with inverse characteristics settings and the permitted overload of the generator stator B1. In the second calculation step the settings of impedance generator protection are determined, and the methods and criteria according to which the calculations are done are described. Criteria used to provide the protection to fulfill the backup protection role in the event of malfunction of the main protection of the transmission system. are clarified. The calculation of all protection functions (32 functions of generator B1 were performed in the project "Coordination of relay protection blocks B1 and B2 with the system of excitation and power system protections -TENT B".

  10. Electric protections based in microprocessors in power plants; Protecciones electricas basadas en microprocesadores en centrales generadoras

    Energy Technology Data Exchange (ETDEWEB)

    Libreros, Domitilo; Castanon Jimenez, Jose Ismael [Instituto de Investigaciones Electricas, Cuernavaca (Mexico)

    1988-12-31

    This article is centered around the substitution of the conventional electric protections of a power plant in connection type unit for protections based in microprocessors. A general model of conventional protection of a power plant is described and the number of analogic and digital signals that intervene in that model are quantified. A model is setup for power plant protection with microprocessors, analyzing each one of the modules that would form it. Finally, the algorithms to carry on such protection are presented. [Espanol] Este articulo se centra en torno a la sustitucion de las protecciones electricas convencionales de una central generadora en conexion tipo unidad por protecciones basadas en microprocesadores. Se describe el modelo general de proteccion convencional de una central generadora y se cuantifica el numero de senales analogicas y digitales que interviene en dicho modelo. Se propone un modelo para proteccion de centrales generadoras mediante microprocesadores, analizandose cada uno de los modulos que lo conformarian. Finalmente, se presentan los algoritmos para realizar dicha proteccion.

  11. Electric protections based in microprocessors in power plants; Protecciones electricas basadas en microprocesadores en centrales generadoras

    Energy Technology Data Exchange (ETDEWEB)

    Libreros, Domitilo; Castanon Jimenez, Jose Ismael [Instituto de Investigaciones Electricas, Cuernavaca (Mexico)

    1987-12-31

    This article is centered around the substitution of the conventional electric protections of a power plant in connection type unit for protections based in microprocessors. A general model of conventional protection of a power plant is described and the number of analogic and digital signals that intervene in that model are quantified. A model is setup for power plant protection with microprocessors, analyzing each one of the modules that would form it. Finally, the algorithms to carry on such protection are presented. [Espanol] Este articulo se centra en torno a la sustitucion de las protecciones electricas convencionales de una central generadora en conexion tipo unidad por protecciones basadas en microprocesadores. Se describe el modelo general de proteccion convencional de una central generadora y se cuantifica el numero de senales analogicas y digitales que interviene en dicho modelo. Se propone un modelo para proteccion de centrales generadoras mediante microprocesadores, analizandose cada uno de los modulos que lo conformarian. Finalmente, se presentan los algoritmos para realizar dicha proteccion.

  12. 76 FR 20368 - Llano Seco Riparian Sanctuary Unit Restoration and Pumping Plant/Fish Screen Facility Protection...

    Science.gov (United States)

    2011-04-12

    ... Leader, Sacramento National Wildlife Refuge Complex, U.S. Fish and Wildlife Service, 752 County Road 99W... old and eroding, it plays a key role in protecting the PCGID-PID pumping plant. As the bank erodes... interdisciplinary team began studies to examine measures to protect the PCGID-PID pumping plant and fish screen...

  13. Radiation and Environmental Protection Programme for the First Upcoming Nuclear Power Plant in Indonesia

    International Nuclear Information System (INIS)

    Syahrir

    2007-01-01

    Indonesia plans to operate the first nuclear power plant (NPP) by 2016. A radiation and environmental protection arrangement for NPPs is part of the whole safety system which is embedded in every practice involved radiation exposure to workers and members of public. A radiation and environmental protection programme for the NPP should adhere to international standards and mainstream in order to be acceptable to the public and international communities. International Atomic Energy Agency (IAEA) has recommended a radiation protection standard for NPPs as studied in this paper. Focus is given to the operational aspects of radiation protection program and discharge control to the environment. Some documents related to Safety Analysis Reports were used as working examples on its implementation. The study includes the classification of working areas and access control; local rules and supervision of work; work planning and work permits; protective clothing and protective equipment; facilities, shielding and equipment; application of the principle of optimization of protection; and removal or reduction in intensity of sources of radiation. The radiological protection aspects blend together in the whole NPP practices, each individual has his/her own responsibility in association with the radiation protection program implementation. It also present in the whole steps of NPP preparation up to its decommissioning. Promise on safety improvement and significant dose reduction in the recent development in NPP technology should scrutinized so that the option of proven technology as required in commercial power reactor licensing considers this tendency. (author)

  14. Fire protection of safe shutdown capability at commercial nuclear power plants

    International Nuclear Information System (INIS)

    Sullivan, K.

    1993-01-01

    The comprehensive industrial safety standards and codes that exist today have evolved from lessons learned through past experience, research results, and improvements in technological capabilities. The current requirements for fire safety features of commercial nuclear power stations operated in the U.S. are a notable example of this practice. Although fire protection has always been an important design requirement, from the aftermath of a serious fire that occurred in 1975 at the Browns Ferry plant, it was learned that the life safety and property protection concerns of the major fire insurance underwriters may not sufficiently encompass nuclear safety issues, particularly with regard to the potential for fire damage to result in the common mode failure of redundant trains of systems, and composites important to the safe shutdown of the reactor. Following its investigations into the Browns Ferry fire, the Nuclear Regulatory Commission (NRC) promulgated guidance documents, which ultimately developed into mandatory regulations, necessary to assure the implementation of a fire protection program that would address nuclear safety concerns. The new criteria that evolved, contain prescriptive design features, as well as personnel and administrative requirements the Commission determined to be necessary to provide a defense-in-depth level of protection against the hazards of fire and its associated effects on safety related equipment. These criteria are primarily contained in Appendix R of Title 10 to the Code of Federal Regulations (10 CFR 50)

  15. Nuclear power plant component protection

    International Nuclear Information System (INIS)

    Michel, E.; Ruf, R.; Dorner, H.

    1976-01-01

    Described is a nuclear power plant installation which includes a concrete biological shield forming a pit in which a reactor pressure vessel is positioned. A steam generator on the outside of the shield is connected with the pressure vessel via coolant pipe lines which extend through the shield, the coolant circulation being provided by a coolant pump which is also on the outside of the shield. To protect these components on the outside of the shield and which are of mainly or substantially cylindrical shape, semicylindrical concrete segments are interfitted around them to form complete outer cylinders which are retained against outward separation radially from the components, by rings of high tensile steel which may be interspaced so closely that they provide, in effect, an outer steel cylinder. The invention is particularly applicable to pressurized-water coolant reactor installations

  16. Micro processors for plant protection

    International Nuclear Information System (INIS)

    McAffer, N.T.C.

    1976-01-01

    Micro computers can be used satisfactorily in general protection duties with economic advantages over hardwired systems. The reliability of such protection functions can be enhanced by keeping the task performed by each protection micro processor simple and by avoiding such a task being dependent on others in any substantial way. This implies that vital work done for any task is kept within it and that any communications from it to outside or to it from outside are restricted to those for controlling data transfer. Also that the amount of this data should be the minimum consistent with satisfactory task execution. Technology is changing rapidly and devices may become obsolete and be supplanted by new ones before their theoretical reliability can be confirmed or otherwise by field service. This emphasises the need for users to pool device performance data so that effective reliability judgements can be made within the lifetime of the devices. (orig.) [de

  17. Protective and Catching Safety Systems In Construction

    Directory of Open Access Journals (Sweden)

    Kuzhin Marat

    2017-01-01

    Full Text Available In the article is described application of protective and catching systems in construction. Classification of similar systems, their types and purpose are listed. Dangerous zones on construction site and events to for limiting their influence or protection from the factors. Protective and catching systems is one of the most effective technical equipment, applied in recent time. Protective fences and catching systems are important part in the problem solution. Protective fences protect workers from falling from height. Protective and catching systems allows avoid injuries by workers, also catch debris, fallen from constructing buildings. In regard with continuing development in technical and technological solutions, protective and catching systems require adaptation to a new requirements of construction industry and requirements of normative documents. Technical regulations in the appliance sphere of protective and catching systems requires actualization and aligning with modern normatives. Important role should be given to developing organizational and technological documentation for application of the systems. Scientific studying of technical parameters of fences and protective catching nets also has great interest.

  18. Evaluation of fault coverage for digitalized system in nuclear power plants using VHDL

    International Nuclear Information System (INIS)

    Kim, Suk Joon; Lee, Jun Suk; Seong, Poong Hyun

    2003-01-01

    Fault coverage of digital systems is found to be one of the most important factors in the safety analysis of nuclear power plants. Several axiomatic models for the estimation of fault coverage of digital systems have been proposed, but to apply those axiomatic models to real digital systems, parameters that the axiomatic models require should be approximated using analytic methods, empirical methods or expert opinions. In this paper, we apply the fault injection method to VHDL computer simulation model of a real digital system which provides the protection function to nuclear power plants, for the approximation of fault detection coverage of the digital system. As a result, the fault detection coverage of the digital system could be obtained

  19. Information system of taxones and biotopes of the State protection of nature of the Slovak Republic

    International Nuclear Information System (INIS)

    Jurecek, R.; Kuerthy, A.

    2005-01-01

    Information system of taxones and biotopes (ISTB) of the State protection of environment of the Slovak Republic (SOP SR) is a database system established in order to collection and processing of botanic, zoologic and biotopic data. It has arisen on the base of tasks of the SOP SR resulting from activities of species protection of animals and plants and their monitoring. It is an open system dedicated for exchange of data and for cooperation of specialist of the SOP SR, academic institutes, professional organisations and anon-professional naturalists

  20. Multiagent based protection and control in decentralized electric power systems

    DEFF Research Database (Denmark)

    Saleem, Arshad; Lind, Morten; Veloso, Manuela

    2010-01-01

    Electric power systems are going through a major change both in their physical and control structure. A large num- ber of small and geographically dispersed power generation units (e.g., wind turbines, solar cells, plug-in electric cars) are replacing big centralized power plants. This shift has...... created interesting possibilities for application of intelligent systems such as multiagent systems for control and automation in electric power systems. This paper describes work on designing a multiagent system for protection and control of electric power distribution networks.It demonstrates how...... explicit modeling of capabilities, states, roles and role transition in agents can capture the control and automation in electric power systems. We present illustrative results from using our proposed schema in realistic simulations....

  1. Radiation protection aspects of design for nuclear power plants. Safety guide

    International Nuclear Information System (INIS)

    2005-01-01

    . The IAEA takes seriously the enduring challenge for users and regulators everywhere: that of ensuring a high level of safety in the use of nuclear materials and radiation sources around the world. Their continuing utilization for the benefit of humankind must be managed in a safe manner, and the IAEA safety standards are designed to facilitate the achievement of that goal. This Safety Guide has been prepared as a part of the IAEA programme on safety standards for nuclear power plants. It includes recommendations on how to satisfy the requirements established in the Safety Requirements publication on the Safety of Nuclear Power Plants: Design. It addresses the provisions that should be made in the design of nuclear power plants in order to protect site personnel, the public and the environment against radiological hazards for operational states, decommissioning and accident conditions. The recommendations on radiation protection provided in this Safety Guide are consistent with the International Basic Safety Standards for Protection against Ionizing Radiation and for the Safety of Radiation Sources (BSS), which were jointly sponsored by the Food and Agriculture Organization of the United Nations (FAO), the IAEA, the International Labour Organisation (ILO), the OECD Nuclear Energy Agency (OECD/NEA), the Pan American Health Organization (PAHO) and the World Health Organization (WHO). This Safety Guide supersedes Safety Series No. 50-SG-D9, Design Aspects of Radiation Protection for Nuclear Power Plants, published in 1985. Effective radiation protection is a combination of good design, high quality construction and proper operation. Procedures that address the radiation protection aspects of operation are covered in the Safety Guide on Radiation Protection and Radioactive Waste Management in the operation of Nuclear Power Plants

  2. Protection Performance Simulation of Coal Tar-Coated Pipes Buried in a Domestic Nuclear Power Plant Using Cathodic Protection and FEM Method

    Energy Technology Data Exchange (ETDEWEB)

    Chang, H. Y.; Lim, B. T.; Kim, K. S.; Kim, J. W.; Park, H. B. [KEPCO Engineering and Construction Company, Gimcheon (Korea, Republic of); Kim, Y. S.; Kim, K. T. [Andong National University, Andong (Korea, Republic of)

    2017-06-15

    Coal tar-coated pipes buried in a domestic nuclear power plant have operated under the cathodic protection. This work conducted the simulation of the coating performance of these pipes using a FEM method. The pipes, being ductile cast iron have been suffered under considerably high cathodic protection condition beyond the appropriate condition. However, cathodic potential measured at the site revealed non-protected status. Converting from 3D CAD data of the power plant to appropriate type for a FEM simulation was conducted and cathodic potential under the applied voltage and current was calculated using primary and secondary current distribution and physical conditions. FEM simulation for coal tar-coated pipe without defects revealed over-protection condition if the pipes were well-coated. However, the simulation for coal tar-coated pipes with many defects predict that the coated pipes may be severely degraded. Therefore, for high risk pipes, direct examination and repair or renewal of pipes are strongly recommended.

  3. Fire protection requirements of the insurance industry and their impact on nuclear power plant design and construction

    International Nuclear Information System (INIS)

    Deitchman, J.V.; King, W.T. Jr.; Nashman, T.A.

    1976-01-01

    The insurance industry, with its wealth of knowledge and experience in the fire protection area and with preservation of its funds at stake, has always been heavily involved in the fire protection programs of nuclear power plants. Since it was concerned with property preservation in addition to nuclear safety, the insurance industry placed more detailed emphasis on fire protection requirements than did the nuclear regulatory bodies. Since the Browns Ferry fire, however, the insurance industry, the Nuclear Regulatory Commission, the Advisory Committee on Reactor Safeguards and the utilities themselves have re-examined their approaches to fire protection. A more coordinated approach seems to have emerged, which is based largely upon insurance industry specifications and guidelines. The paper briefly summarizes the fire protection requirements of the insurance industry as they apply to nuclear power plants. Some of the ways these requirements affect project planning, plant design, and construction timing are reviewed, as well as some of the more controversial fire protection areas

  4. Radiation safety and protection on the nuclear power plants

    International Nuclear Information System (INIS)

    Nosovskij, A.V.; Bogorad, V.I.; Vasil'chenko, V.N.; Klyuchnikov, A.A.; Litvinskaya, T.V.; Slepchenko, A.Yu.

    2008-01-01

    The main issues of the radiation safety and protection provision on the nuclear power plants are considered in this monograph. The description of the basic sources of the radiation danger on NPPs, the principles, the methods and the means of the safety and radiation monitoring provision are shown. The special attention is paid to the issues of the ionizing radiation regulation

  5. Smart machine protection system

    International Nuclear Information System (INIS)

    Clark, S.; Nelson, D.; Grillo, A.

    1992-01-01

    A Machine Protection System implemented on the SLC automatically controls the beam repetition rates in the accelerator so that radiation or temperature faults slow the repetition rate to bring the fault within tolerance without shutting down the machine. This process allows the accelerators to aid in the fault diagnostic process, and the protection system automatically restores the beams back to normal rates when the fault is diagnosed and corrected. The user interface includes facilities to monitor the performance of the system, and track rate limits, faults, and recoveries. There is an edit facility to define the devices to be included in the protection system, along with their set points, limits, and trip points. This set point and limit data is downloaded into the CAMAC modules, and the configuration data is complied into a logical decision tree for the 68030 processor. (author)

  6. Smart Machine Protection System

    International Nuclear Information System (INIS)

    Clark, S.; Nelson, D.; Grillo, A.; Spencer, N.; Hutchinson, D.; Olsen, J.; Millsom, D.; White, G.; Gromme, T.; Allison, S.; Underwood, K.; Zelazny, M.; Kang, H.

    1991-11-01

    A Machine Protection System implemented on the SLC automatically controls the beam repetition rates in the accelerator so that radiation or temperature faults slow the repetition rate to bring the fault within tolerance without shutting down the machine. This process allows the accelerator to aid in the fault diagnostic process, and the protection system automatically restores the beams back to normal rates when the fault is diagnosed and corrected. The user interface includes facilities to monitor the performance of the system, and track rate limits, faults, and recoveries. There is an edit facility to define the devices to be included in the protection system, along with their set points, limits, and trip points. This set point and limit data is downloaded into the CAMAC modules, and the configuration data is compiled into a logical decision tree for the 68030 processor. 3 figs

  7. Optimization criteria for control and instrumentation systems in nuclear power plants

    International Nuclear Information System (INIS)

    Gonzalez, A.J.

    1978-01-01

    The system of dose limitation recently recommended by the International Commission on Radiation Protection includes, as a base for deciding what is reasonably achievable in dose reduction, the optimization of radioprotection systems. This paper, after compiling relevant points in the new system, discusses the application of optimization to control and instrumentation of radioprotection systems in nuclear power plants. Furthermore, an extension of the optimization criterion to nuclear safety systems is also presented and its application to control and instrumentation is discussed; systems including majority logics are particularly scrutinized. Finally, eventual regulatory implications are described. (author)

  8. Improvements done at Heavy Water Plant (Manuguru) to increase the standards of environmental protection

    International Nuclear Information System (INIS)

    Rama Rao, V.V.S.; Gupta, R.V.; Pandey, B.L.

    1997-01-01

    The Heavy Water Plant at Manuguru is designed to produce 185 MTY of nuclear grade heavy water based on bithermal H 2 S-H 2 O exchange process and handles large inventory of H 2 S gas (about 400 MT). As H 2 S gas is very toxic, corrosive and hazardous in nature, extreme care has been taken in the design of plant, selection of equipment and materials adhering to stringent fabrication procedures and codes to ensure the production of heavy water in a safe manner. This paper highlights the improvements done at Heavy Water Plant (Manuguru) to increase the standards of environmental protection. The safety assessment of a hazardous plant is a continuous process. Apart from the extreme care taken in the design, construction, commissioning and operation of the plant, review of each and every safety related unusual occurrence by various levels of review committees as stipulated and speedy implementation of the recommendations goes in a long way in increasing the standards of environmental protection

  9. Control and Protection of Wind Power Plants with VSC-HVDC Connection

    DEFF Research Database (Denmark)

    Chaudhary, Sanjay

    oscillations, and hence, lower dc voltage overshoots in the VSC-HVDC system. On the protection side, the coordination of over-current relays has been analysed in the new environment. A simple yet reliable scheme utilizing the well-known over-current relay characteristics has been presented for the detection...... grid frequency from the onshore grid frequency. Three different methods have been evaluated here for relaying the onshore grid frequency to the offshore grid, such that the wind power plant can participate in the grid frequency control. One of the schemes does not involve communication, while the other...... of faults and the determination of faulted feeder in the offshore grid. It is demonstrated that the communication capability of modern relays can help avoid the potential cases of over-reach. The test system is modelled for real time simulation in RSCAD/RTDS platform, such that the physical relays could...

  10. ALARA-based strengthening of radiation protection in a high dose rate nuclear power plant: A practical overview

    International Nuclear Information System (INIS)

    Lips, Marcel

    2008-01-01

    In the first years of operation the dose rates at Goesgen nuclear power plant increased more strongly than expected. Co-60 has been the main radiation contributor from the beginning. As an immediate step, investigations were initiated to find and remove unknown cobalt sources. System modifications and optimization in water chemistry were carried out to reduce material and activity transport within the primary system. As a result the dose rates were stabilized after a couple of years -unfortunately on a high level. To reduce the dose rate levels and the occupational radiation exposure, further long term measures were implemented. System decontamination and source replacement were considered as well as the implementation of enhanced shielding procedures and a more source oriented chemistry. As a result the dose rates have reduced significantly and the occupational radiation exposure has been decreased by more than a factor of 2 over the last two decades. The reduction of the mean individual dose turned out even better and was cut by a factor of 5. On terms of plant and personal safety, Goesgen nuclear power plant decided to improve radiation protection using a smooth step by step action plan and has been very successful with it. Currently the technical possibilities have been developed to a high standard. Further improvements will be selective only. In future the focus will be set to personal behavior and human performance, using enhanced target settings, briefings, debriefings, experience feedback and (international) experience exchange. Nevertheless it will be essential to avoid unnecessary administrative and counterproductive short term hurdles. Strengthening of radiation protection is and will be a long term and continuous process. Goesgen nuclear power plant will continue to introduce further actions one by one. (author)

  11. IAEA activities to improve occupational radiation protection in nuclear power plants in Central and Eastern Europe

    International Nuclear Information System (INIS)

    Gustafsson, M.; Webb, G.A.M.; )

    1998-01-01

    The following aspects are highlighted: developing standards, ISOE (Information System on Occupational Exposure), providing assistance, and intercomparisons. By means of these coordinated efforts, the IAEA aims at improving occupational radiation protection in nuclear power plants in Central and Eastern Europe. The objective is not only transfer of knowledge and technology but also encouraging cooperation between health physicists in those countries as well as with health physicists in Western countries. (P.A.)

  12. Improvement of the Cubic Spline Function Sets for a Synthesis of the Axial Power Distribution of a Core Protection System

    International Nuclear Information System (INIS)

    Koo, Bon-Seung; Lee, Chung-Chan; Zee, Sung-Quun

    2006-01-01

    Online digital core protection system(SCOPS) for a system-integrated modular reactor is being developed as a part of a plant protection system at KAERI. SCOPS calculates the minimum CHFR and maximum LPD based on several online measured system parameters including 3-level ex-core detector signals. In conventional ABB-CE digital power plants, cubic spline synthesis technique has been used in online calculations of the core axial power distributions using ex-core detector signals once every 1 second in CPC. In CPC, pre-determined cubic spline function sets are used depending on the characteristics of the ex-core detector responses. But this method shows an unnegligible power distribution error for the extremely skewed axial shapes by using restrictive function sets. Therefore, this paper describes the cubic spline method for the synthesis of an axial power distribution and it generates several new cubic spline function sets for the application of the core protection system, especially for the severely distorted power shapes needed reactor type

  13. Plant air systems safety study: Portsmouth Gaseous Diffusion Plant

    International Nuclear Information System (INIS)

    1982-05-01

    The Portsmouth Gaseous Diffusion Plant Air System facilities and operations are reviewed for potential safety problems not covered by standard industrial safety procedures. Information is presented under the following section headings: facility and process description (general); air plant equipment; air distribution system; safety systems; accident analysis; plant air system safety overview; and conclusion

  14. Deficiencies in radiation protection record systems

    International Nuclear Information System (INIS)

    Martin, J.B.; Lyon, M.

    1991-01-01

    Radiation protection records are a fundamental part of any program for protecting radiation workers. Records are essential to epidemiological studies of radiation workers and are becoming increasingly important as the number of radiation exposure litigation cases increases. Ready retrievability of comprehensive records is also essential to the adequate defense of a radiation protection program. Appraisals of numerous radiation protection programs have revealed that few record-keeping systems comply with American National Standards Institute, Standard Practice N13.6-1972. Record-keeping requirements and types of deficiencies in radiation protection records systems are presented in this paper, followed by general recommendations for implementing a comprehensive radiation protection records system

  15. Deficiencies in radiation protection record systems

    International Nuclear Information System (INIS)

    Martin, J.B.; Lyon, M.

    1991-01-01

    Radiation protection records are a fundamental part of any program for protecting radiation workers. Records are essential to epidemiological studies of radiation workers and are becoming increasingly important as the number of radiation exposure litigation cases increases. Ready retrievability of comprehensive records is also essential to the adequate defense of a radiation protection program. Appraisals of numerous radiation protection programs have revealed that few record-keeping systems comply with American National Standards Institute, Standard Practice N13.6-1972. Record-keeping requirements and types of deficiencies in radiation protection records systems are presented in this paper, followed by general recommendations for implementing a comprehensive radiation protection records system. 8 refs

  16. Optimization of fire protection measures and quality controls in nuclear power plants

    International Nuclear Information System (INIS)

    Brenig, H.; Holtschmidt, H.; Liemersdorf, H.; Suetterlin, L.; Dobbernack, R.; Hahn, C.; Hosser, D.; Kordina, K.; Schneider, U.; Sprey, W.; Wesche, H.

    1985-09-01

    This study presents theoretical and experimental investigations on the evaluation of fire hazards and the optimization of fire protection measures in German nuclear power plants. Differences between the method presented here and the US ''Fire Hazard Analysis'' result from the inclusion of the stringent redundancy concept of German nuclear power plants and the emphasis placed on passive structural fire protection measures. The method includes a time-dependent quantification of fire-specific event sequences. Fire occurrence frequencies and the reliabilities of active fire protection measures were derived from German experiences and literature abroad. The reliability data of passive fire protection measures were obtained by an evaluation of experiments and probabilistic analyses. For the calculation of fire sequences fundamental experiments were taken into consideration. For the quantification of the time-dependent event trees a methodology was applied which permits an evaluation of the influence of the individual measures. The consequences of fire were investigated for ten fire events identified as decisive, and the fire sequence paths important in terms of safety were quantified. Their annual frequencies are within a range of 10 -3 to 8.10 -6 . (orig./HP) [de

  17. Assessing plant protection practices using pressure indicator and toxicity risk indicators: analysis of therelationship between these indicators for improved risk management, application in viticulture.

    Science.gov (United States)

    Oussama, Mghirbi; Kamel, Ellefi; Philippe, Le Grusse; Elisabeth, Mandart; Jacques, Fabre; Habiba, Ayadi; Jean-Paul, Bord

    2015-06-01

    The excessive use of plant protection products (PPPs) has given rise to issues of public and environmental health because of their toxicity. Reducing the use of toxic PPPs and replacing them with products that are less toxic for human health and the environment have become socially, environmentally and economically indispensable. In this article, we assess the plant protection practices of a small group of winegrowers practicing "integrated agriculture" in the south of France, in order to measure the benefit of using toxicity risk indicators as a decision-support tool for different players in land management. An analysis of plant protection practices using indicators of the risk to operator health and the environment (IRSA, IRTE), together with a frequency-of-treatment indicator (TFI), enabled us to (i) show the variability of these indicators depending on the production system and farmers' pesticide use strategies and (ii) calculate correlations between these indicators. This analysis of plant protection practices at different scales (farm, field), carried out in collaboration with the growers, enabled us to perform an initial validation of decision-support tools for determining risk management strategies regarding the use of pesticides.

  18. IEC 61850 based refurbishment strategies for protection and automation systems

    Energy Technology Data Exchange (ETDEWEB)

    Tholomier, D. [Areva T and D Automation Canada Inc., Monteal, PQ (Canada); Hossenlopp, L. [Areva T and D Automation Inc., Paris (France); Apostolov, A. [Omicron Electronics, Houston, TX (United States)

    2008-07-01

    Electric utilities are currently facing the challenge of refurbishing aging transmission networks and power system infrastructure at a time of severe economic, environmental and competitive constraints. This paper addressed the issue of an appropriate approach to retrofit the hardware and software of substation secondary systems, and how IEC standards could be used to set up a long term strategy. The first part of the paper considered an asset management strategy for refurbishing substation secondary systems, while the second part of the paper addressed the strategies for refurbishing existing power plants. The final section of the paper analyzed refurbishment strategies designed to protect power distribution systems. The impact of IEC 61850 and how legacy devices can be integrated in substation automation systems were discussed. It was concluded that new SCADA systems are needed to handle new technology. Additional features like remote control, remote settings, remote disturbance records analysis and remote maintenance are also needed to properly operate the power system. The value of preventive maintenance using remote monitoring systems to determine the status of all the digital electronic devices installed in substation was also discussed. IEC 61850 offers several opportunities to improve grid operation and control. It supports interoperability between protective relays and control devices from different manufacturers in the substation, which is required in order to achieve substation level interlocking, protection and control functions and improve the efficiency of microprocessor based relays applications. This technology has now passed the initial stage of implementation and several projects are underway worldwide. 13 figs.

  19. Suggestions of radiation protection instruments in ships used for transporting spent fuel elements from nuclear power plants to central stores and further to fuel reprocessing plants

    International Nuclear Information System (INIS)

    Warenmo, G.

    1979-01-01

    Some radiation protection measures are necessary in ships which will be used for transporting spent fuel elements from nuclear power plants to central stores and further to fuel reprocessing plants in order to protect the crew from unnecessarily high radiation doses and to ensure that not allowable values occur. Such measures are discussed in this report as well as suitable radiation protection instruments for such ships. (E.R.)

  20. Case study on the use of PSA methods: Assessment of technical specifications for the reactor protection system instrumentation

    International Nuclear Information System (INIS)

    1992-10-01

    This case study presents a methodology for the probabilistic evaluation of alternative plant technical specifications regarding system surveillance frequencies and out-of-service times. The methodology is applied to the reactor protection systems of a 4 loop BWR-RESAR-3S type nuclear power plant. The effect of the statistical characteristics of the system on the relative comparison of various sets of technical specifications is examined through sensitivity studies and an uncertainty analysis. Refs, figs and tabs

  1. Post-planting treatments and shading effects in a Fraxinus angustifolia Vahl. silvopastoral system

    Directory of Open Access Journals (Sweden)

    Giorgos Klossas

    2013-05-01

    Full Text Available Silvopastoral systems present difficulties in their management dueto their complexity. When trees are planted into grasslands, they need protection from livestock to prevent damage from trampling or browsing, especially during early years of establishment. One of the common post-planting protective treatments is the protection of individual trees with shelters. Trees also need protection from competition from herbaceous vegetation. The aim of present study was to evaluate the effects of using different types of tree shelters and of controlling competing herbaceous vegetation on the growth of planted young trees and, to assess the effects of heavy shadingon the herbage production and composition. The study was conducted in a Fraxinus angustifolia silvopastoral system of a 2 x 2.5 m spacing plantation in northern Greece. The effects of solid-walled (tubex and handmade by greenhouse nylon and wire mesh tree shelters as well as of herbicide application and mechanical removal of the competing herbaceous vegetation on tree height, height increment and the crown surface area of the trees were tested. The effects of artificial shading (80% on the production of the natural herbaceous vegetation were also investigated. All measurements were recorded three years after plantation. The use of solid wall tubex shelters resultedin higher tree height and higher crown surface area in comparison tothe other tested shelters. The solid wall Nylon shelters were more beneficial to the above growth parameters than the wire mesh ones. Both vegetation control treatments proved beneficial to all the growth parameters of Fraxinus angustifolia. The artificially applied heavy shading reduced herbage production by 54% compared to the control. The results indicated that post planting treatments in the Mediterranean droughty conditions are essential for the success of this tree species establishment. Furthermore, the later thinning of the dense spacing is important to maintain

  2. Post-planting treatments and shading effects in a Fraxinus angustifolia Vahl. silvopastoral system

    Directory of Open Access Journals (Sweden)

    Giorgos Klossas

    2013-07-01

    Full Text Available Silvopastoral systems present difficulties in their management due to their complexity. When trees are planted into grasslands, they need protection from livestock to prevent damage from trampling or browsing, especially during early years of establishment. One of the common post-planting protective treatments is the protection of individual trees with shelters. Trees also need protection from competition from herbaceous vegetation. The aim of present study was to evaluate the effects of using different types of tree shelters and of controlling competing herbaceous vegetation on the growth of planted young trees and, to assess the effects of heavy shading on the herbage production and composition. The study was conducted in a Fraxinus angustifolia silvopastoral system of a 2 x 2.5 m spacing plantation in northern Greece. The effects of solid-walled (tubex and handmade by greenhouse nylon and wire mesh tree shelters as well as of herbicide application and mechanical removal of the competing herbaceous vegetation on tree height, height increment and the crown surface area of the trees were tested. The effects of artificial shading (80% on the production of the natural herbaceous vegetation were also investigated. All measurements were recorded three years after plantation. The use of solid wall tubex shelters resulted in higher tree height and higher crown surface area in comparison to the other tested shelters. The solid wall Nylon shelters were more beneficial to the above growth parameters than the wire mesh ones. Both vegetation control treatments proved beneficial to all the growth parameters of Fraxinus angustifolia. The artificially applied heavy shading reduced herbage production by 54% compared to the control. The results indicated that post planting treatments in the Mediterranean droughty conditions are essential for the success of this tree species establishment. Furthermore, the later thinning of the dense spacing is important to

  3. Regulatory analysis for the resolution of generic issue 57: Effects of Fire Protection System Actuation on Safety-Related Equipment

    International Nuclear Information System (INIS)

    Woods, H.W.

    1993-10-01

    Actuation of Fire Protection Systems (FPS) in Nuclear Power Plants have resulted in adverse interactions with equipment important to safety. Precursor operational experience has shown that 37% of all FPS actuations damaged some equipment, and 20% of all FPS actuations have resulted in a plant transient and reactor trip. On an average 0.17 FPS actuations per reactor year have been experienced in nuclear power plants in this country. This report presents the regulatory analysis for GI-57, ''Effects of Fire Protection System Actuation on Safety-Related Equipment''. The risk reduction estimates, cost/benefit analyses, and other insights gained during this effort have shown that implementation of the recommendations contained in this report can significantly reduce risk, and that these improvements can be warranted in accordance with the backfit rule, 10 CFR 50.109(a)(3). However, plant specific analyses are required in order to identify such improvements. Generic analyses can not serve to identify improvements that could be warranted for individual, specific plants. Plant specific analyses of the type needed for this purpose are underway as part of the Individual Plant Examination of External Events (IPEEE) program

  4. Selectivity of power system protections at power swings in power system

    Directory of Open Access Journals (Sweden)

    Jan Machowski

    2012-12-01

    Full Text Available The paper discusses out-of-step protection systems such as: generator pole slip protections, out of step tripping protections, distance protections of step-up transformer, distance protections of transmission lines and transformers, power swing blocking, and special out-of-step protection. It is shown that all these protections make up a protection system, to which a setting concept uniform for the entire power system has to be applied. If a power system is inappropriately equipped with these protections, or their settings are inappropriate, they may operate unselectively, thus contributing to the development of power system blackouts. In the paper the concepts for a real power system are given for the two stages: target stage fully compliant with selectivity criteria, and transitional stage between the current and target stages.

  5. Reactor protection and shut-down system

    International Nuclear Information System (INIS)

    Klar

    1980-01-01

    The reactor protection system being a part of the reactor safety system. The requirements on the reactor protection system are: high safety with regard to signal processing, high availability, self-reporting of faults etc. The functional sections of the reactor protection system are the analog section, the logic section and the generating of output signals. Description of the operation characteristics and of the extension of function. (orig.)

  6. Plant invasion science in protected areas: progress and priorities

    Czech Academy of Sciences Publication Activity Database

    Foxcroft, L. C.; Pyšek, Petr; Richardson, D. M.; Genovesi, P.; MacFadyen, S.

    2017-01-01

    Roč. 19, č. 5 (2017), s. 1353-1378 ISSN 1387-3547 R&D Projects: GA ČR GB14-36079G Grant - others:AV ČR(CZ) AP1002 Program:Akademická prémie - Praemium Academiae Institutional support: RVO:67985939 Keywords : plant invasions * global patterns * protected areas Subject RIV: EH - Ecology, Behaviour OBOR OECD: Biodiversity conservation Impact factor: 2.473, year: 2016

  7. Concept of voltage and frequency monitoring for a nuclear power plant normal power supply system - PWR 1300 MWe

    International Nuclear Information System (INIS)

    Andrade, R.B. de

    1990-01-01

    Voltage and frequency monitoring concept for a Nuclear Power Plant Normal Power Supply System (PWR 1300 MWe) is described based on the phylosophy adopted for Angra 2 and e NPP's. Some suggested setpoints are only guidance values and can be modified during plant commissioning for a better performance of the whole protection system. (author) [pt

  8. Reliability data of fire protection equipment and features in German nuclear power plants

    International Nuclear Information System (INIS)

    Roewekamp, M.; Riekert, T.; Sehrbrock, W.

    1997-01-01

    In order to perform probabilistic fire safety analyses, a comprehensive data base is needed including physical characteristics of fire compartments and their inventory, fire occurrence frequencies, technical reliability data for all fire-related equipment, human actions and human error probabilities, etc. In order to provide updated and realistic reliability data, the operational behaviour of different fire protection features in two German nuclear power plants was analysed in the framework of the study presented here. The analyses are based on the examination of reported results of the regular inspection and maintenance programs for nuclear power plants. Besides a plant specific assessment of the reliability data a generic assessment for an application as input data for fault tree analyses in the framework of probabilistic risk studies for other German plants was carried out. The analyses of failures and unavailabilities gave the impression that most of them are single failures without relevance for the plant safety. The data gained from NPPs were compared to reliability data of the German insurance companies for the same protection features installed in non-nuclear installations and to older nuclear specific reliability data. This comparison showed up a higher reliability. (orig.) [de

  9. Regulatory analysis for the resolution of Generic Issue 115, enhancement of the reliability of the Westinghouse Solid State Protection System

    International Nuclear Information System (INIS)

    Basdekas, D.L.

    1989-05-01

    Generic Issue 115 addresses a concern related to the reliability of the Westinghouse reactor protection system for plants using the Westinghouse Solid State Protection System (SSPS). Several options for improving the reliability of the Westinghouse reactor trip function for these plants and their effect on core damage frequency (CDF) and overall risk were evaluated. This regulatory analysis includes a quantitative assessment of the costs and benefits associated with the various options for enhancing the reliability of the Westinghouse SSPS and provides insights for consideration and industry initiatives. No new regulatory requirements are proposed. 25 refs., 11 tabs

  10. The improvement of the fire protections system for nuclear cycle facilities. Formulation of a fire protection guideline for nuclear fuel cycle facilities

    International Nuclear Information System (INIS)

    2012-04-01

    The private side Fire Protection Guideline was investigated with respect to the fire having taken place at the nuclear reactor site followed by the Chuetsu-Oki earthquake in Niigata Prefecture in 2007. To improve the fire protection system especially applicable to MOX fuel fabrication facilities, JNES (Japan Nuclear Energy Safety Organization) investigated private guidelines adopted in Japanese Light Water cooled Reactors, the standardized guidelines used in Nuclear Facilities in other countries including USA, and the standards in the chemical plants. The content of the guideline concerns the prevention of the fire breakout, the prevention of fire extension, the reduction of the fire effects, as well as the facility-characteristic protection countermeasures and the fire effect evaluations. (S. Ohno)

  11. Nuclear power plant monitoring and control system software: verification and validation

    International Nuclear Information System (INIS)

    Kaneda, M.; Niki, K.; Shibata, K.

    1986-01-01

    The design philosophy, configuration, and production of process computer system software used for the monitoring and control of nuclear power plants are presented in detail. To achieve a very complex software system that not only has excellent performance, high reliability, and full fail safe protection, but also is easy to produce, verify, and validate, and has flexibility for future modifications, we developed the following software production system to support safe operation of nuclear power stations. The fundamental design philosophy of our monitoring and control system software is the complete separation of program logic from the data base. The logic section is highly standardized and applicable to a wide range of power generation plant computer application systems. The plant-unique properties and characteristics are all described in the data base. This separation of logic and data base has a dramatic effect on the reliability and productivity of the software system. One of the main features of the data base system is the use of easy-to-learn, easy-to-use, problem-oriented language that enables non-programmers to build up the data base using simple fill-in-the-blank type tables. The generation of these tables is fully automated, and the full set of online table editing utility software, which runs on the target plant process computer, has proven very effective in incorporation of changes and modifications at the site. (author)

  12. Long-term evaluation of mucosal and systemic immunity and protection conferred by different polio booster vaccines.

    Science.gov (United States)

    Xiao, Yuhong; Daniell, Henry

    2017-09-25

    Oral polio vaccine (OPV) and Inactivated Polio Vaccine (IPV) have distinct advantages and limitations. IPV does not provide mucosal immunity and introduction of IPV to mitigate consequences of circulating vaccine-derived polio virus from OPV has very limited effect on transmission and OPV campaigns are essential for interrupting wild polio virus transmission, even in developed countries with a high coverage of IPV and protected sewer systems. The problem is magnified in many countries with limited resources. Requirement of refrigeration for storage and transportation for both IPV and OPV is also a major challenge in developing countries. Therefore, we present here long-term studies on comparison of a plant-based booster vaccine, which is free of virus and cold chain with IPV boosters and provide data on mucosal and systemic immunity and protection conferred by neutralizing antibodies. Mice were primed subcutaneously with IPV and boosted orally with lyophilized plant cells containing 1μg or 25μg polio viral protein 1 (VP1), once a month for three months or a single booster one year after the first prime. Our results show that VP1-IgG1 titers in single or double dose IPV dropped to background levels after one year of immunization. This decrease correlated with >50% reduction in seropositivity in double dose and <10% seropositivity in single dose IPV against serotype 1. Single dose IPV offered no or minimal protection against serotype 1 and 2 but conferred protection against serotype 3. VP1-IgA titers were negligible in IPV single or double dose vaccinated mice. VP1 antigen with two plant-derived adjuvants induced significantly high level and long lasting VP1-IgG1, IgA and neutralizing antibody titers (average 4.3-6.8 log2 titers). Plant boosters with VP1 and plant derived adjuvants maintained the same level titers from 29 to 400days and conferred the same level of protection against all three serotypes throughout the duration of this study. Even during period, when

  13. How nitric oxide donors can protect plants in a changing environment: what we know so far and perspectives

    Directory of Open Access Journals (Sweden)

    Amedea B. Seabra

    2016-12-01

    Full Text Available The free radical nitric oxide (NO plays important roles in plant growth and defense. Owing to its small size and lipophilicity, NO acts as a crucial signaling molecule in plants, crossing cell membranes and enhancing cell communication. Indeed, NO donors have been shown to modulate a variety of physiological processes, such as plant greening, seed germination, iron homeostasis and mitochondrial respiration. Recently, several papers have reported the protective actions upon application of low molecular weight NO donors in plants under abiotic stress. Exogenous NO is able to improve plant tolerance to several abiotic stresses, such as drought, salinity, metal toxicity, and extreme temperatures. This protection is assigned to the NO-mediated redox signaling in plants, which involves interplay with reactive oxygen species and modulation of gene expression and protein function. This review reports and discusses the recent advantages, pitfalls, challenges, and perspectives in the applications of low molecular weight NO donors in plants under abiotic stress. The combination of nanotechnology and NO donors as an efficient approach to protect plants under challenging environments is also discussed.

  14. Regulatory control of physical protection systems

    International Nuclear Information System (INIS)

    Rajdeep; Mayya, Y.S.

    2017-01-01

    The safety of facilities in BARC is under the regulatory oversight of BSC. The security architecture for these facilities incorporates multiple layers of Physical Protection Systems. The demands of safety may sometimes conflict with the needs of security. Realizing the need to identify these interfaces and extend the regulatory coverage to Physical Protection Systems, a Standing Committee named Physical Protection System Review Committee (PPSRC) has been constituted as a 2"n"d tier entity of BSC. PPSRC includes experts from various domains concerned with nuclear security, viz. physical protection systems, cyber security, radiation safety, security operations, technical services and security administration

  15. OPERATIONAL EXPERIENCE: UPGRADED MPC AND A SYSTEMS FOR THE RADIOCHEMICAL PLANT OF THE SIBERIAN CHEMICAL COMBINE

    International Nuclear Information System (INIS)

    RODRIGUEZ, C.; GOLOSKOKOV, I.; FISHBONE, L.; GOODEY, K.; LOOMIS, M.; CRAIN, B. JR.; LARSEN, R.

    2003-01-01

    The success of reducing the risk of nuclear proliferation through physical protection and material control/accounting systems depends upon the development of an effective design that includes consideration of the objectives of the systems and the resources available to implement the design. Included among the objectives of the design are facility characterization, definition of threat, and identification of targets. When considering resources, the designer must consider funds available, rapid low-cost elements, technology elements, human resources, and the availability of resources to sustain operation of the end system. The Siberian Chemical Combine (SCC) is a multi-function nuclear facility located in the Tomsk region of Siberia, Russia. Beginning in 1996, SCC joined with the United States Department of Energy (US/DOE) Material Protection, Control, and Accounting (MPC and A) Program to develop and implement MPC and A upgrades for the Radiochemical, Chemical Metallurgical, Conversion, Uranium Enrichment, and Reactor Plants of the SCC. At the Radiochemical Plant the MPC and A design and implementation process has been largely completed for the Plutonium Storage Facility and related areas of the Radiochemical Plant. Design and implementation of upgrades for the Radiochemical Plant include rapid physical protection upgrades such as bricking up of doors and windows, and installation of security-hardened doors. Rapid material control and accounting upgrades include installation of modern balances and bar code equipment. Comprehensive MPC and A upgrades include the installation of access controls to sensitive areas of the Plant, alarm communication and display (AC and D) systems to detect and annunciate alarm conditions, closed circuit (CCTV) systems to assess alarm conditions, central and secondary alarm station upgrades that enable security forces to assess and respond to alarm conditions, material control and accounting upgrades that include upgraded physical

  16. Ageing management of electrical and C/I-systems in power plants of RWE Power

    International Nuclear Information System (INIS)

    Hentschel, Reinhard; Kochs, Wolfgang; Zander, Ralf-Michael

    2010-01-01

    Maintenance and enhancement of the availability and safety of fossil-fired and nuclear power plants currently in operation are increasing in importance with plants' age. The paper deals with issues related to e.g. the operation of C and I-systems at the end of production and with the challenges involved in their replacement during plant operation and describes the various measures taken for monitoring electrical equipment. Taking the improvement of the existing protection systems against internal arcs in electrical bus bars as an example, practical approaches for ageing management are described. In addition, the strategic approaches will be explained that were developed within a VGB working group due to the introduction of a new regulation on ageing management in nuclear power plants. (orig.)

  17. Distributed Supervisory Protection Interlock System

    International Nuclear Information System (INIS)

    Walz, H.V.; Agostini, R.C.; Barker, L.; Cherkassky, R.; Constant, T.; Matheson, R.

    1989-03-01

    The Distributed Supervisory Protection Interlock System, DSPI, is under development at the Stanford Linear Accelerator Center for requirements in the areas of personnel protection, beam containment and equipment protection interlocks. The DSPI system, distributed over the application site, consists of segments with microprocessor-based controller and I/O modules, local area networks for communication, and a global supervisor computer. Segments are implemented with commercially available controller and I/O modules arranged in local interlock clusters, and associated software. Segments provide local interlock data acquisition, processing and control. Local area networks provide the communication backbone between segments and a global supervisor processor. The supervisor processor monitors the overall system, reports detail status and provides human interfaces. Details of an R and D test system, which will implement the requirements for personnel protection of 4 typical linear accelerator sectors, will be described. 4 refs., 2 figs

  18. Evolution of Onsite and Offsite Power Systems in US Nuclear Power Plants

    International Nuclear Information System (INIS)

    Mathew, Roy K.

    2015-01-01

    The AC electric power system is the source of power for station auxiliaries during normal operation and for the reactor protection system and emergency safety features during abnormal and accident conditions. Since the construction of early plants in US, the functional adequacy and requirements of the offsite power systems, safety and non safety related onsite electric power systems have changed considerably to ensure that these systems have adequate redundancy, independence, quality, maintenance and testability to support safe shutdown of the nuclear plant. The design of AC systems has evolved from a single train to multiple (up to four) redundant trains in the current evolutionary designs coupled with other auxiliary AC systems. The early plants were designed to cope with a Loss of Offsite Power (LOOP) event through the use of onsite power supplies only. However operating experience has indicated that onsite and offsite power AC power systems can fail due to natural phenomena (earthquakes, lightning strikes, fires, geomagnetic storms, tsunamis, etc.) or operational abnormalities such as loss of a single phase, switching surges or human error. The onsite DC systems may not be adequately sized to support plant safe shutdown over an extended period if AC power cannot be restored within a reasonable time. This paper will discuss the requirements to improve availability and reliability of offsite and onsite alternating current (AC) power sources to U.S. Nuclear Power Plants. In addition, the paper will discuss the requirements and guidance beyond design basis events. (author)

  19. Power system protection 2 systems and methods

    CERN Document Server

    1995-01-01

    The worldwide growth in demand for electricity has forced the pace of developments in electrical power system design to meet consumer needs for reliable, secure and cheap supplies. Power system protection, as a technology essential to high quality supply, is widely recognised as a specialism of growing and often critical importance, in which power system needs and technological progress have combined to result in rapid developments in policy and practice in recent years. In the United Kingdom, the need for appropriate training in power system protection was recognised in the early 1960s with t

  20. Wind turbine with lightning protection system

    DEFF Research Database (Denmark)

    2016-01-01

    The present invention relates to a wind turbine comprising a lightning protection system comprising a waveguide interconnecting a communication device and a signal-carrying structure. In other aspects, the present invention relates to the use of a waveguide in a lightning protection system...... of a wind turbine, a power splitter and its use in a lightning protection system of a wind turbine....

  1. 10 CFR 73.26 - Transportation physical protection systems, subsystems, components, and procedures.

    Science.gov (United States)

    2010-01-01

    ... PROTECTION OF PLANTS AND MATERIALS Physical Protection of Special Nuclear Material in Transit § 73.26... of deadly force when armed escorts or armed response personnel have a reasonable belief that it is... at least one level higher than that having responsibility for the day-to-day plant operation. These...

  2. Security aspects and radiological protection analyzed in the Semi-industrial irradiation plant in Peru

    International Nuclear Information System (INIS)

    Del Valle O, C.

    1996-01-01

    The safety aspects and the radiological protection analyzed on regular and emergency operation of a multipurpose irradiation plant PIMU are shown. All its design requirements are described following a strict safety philosophy. The plant is classified into the generic category IV for storage in pool panoramic irradiators. This paper studies every aspect related to a safety operation of the gamma's facility, PIMU, being used as reference in order to obtain the corresponding licensing. Aspects related to the regular and safety operation of the whole plant are taken into account, so all the possible emergency cases and their respective answers will be known, analyzing cases and causes of accidents, as well as references to the program of radiological protection. Registers and documents are written in order to be used at the plant, all the lineament for the development of a good preventive and corrective maintenance are given, observing all the necessary adjustments. A list of the principal examinations of the technical condition of the plant is presented. (author). 2 refs

  3. Autonomous systems for plant protection

    DEFF Research Database (Denmark)

    Griepentrog, Hans W.; Ruckelhausen, Arno; Jørgensen, Rasmus N.

    2010-01-01

    Advances in automation are demanded by the market mainly as a response to high labor costs. Robotic outdoor systems are ready to allow not only economically viable operations but also increased efficiency in agriculture, horticulture and forestry. The aim of this chapter is to give examples of au...

  4. Cernavoda nuclear power plant: Modifications in the fire protection measures of the CANDU 6 standard design

    International Nuclear Information System (INIS)

    Covalschi, V.

    1998-01-01

    Having as purpose the improvement of fire safety at the Cernavoda NPP - both in the prevention and the protection aspects in the case of fire - we implemented some modifications in the CANDU 6 standard design. These improvements are inspired, mainly, from two sources: the world-wide achievements in the field of fire protection techniques, introduced in nuclear power plants since the middle of 70's, when the CANDU 6 design was completed; the national practice and experience in fire protection, usually applied in industrial objectives (conventional power plants, in particular). The absence of any incident may be considered as a proof of the efficiency of the implemented fire preventing and protection measures. (author)

  5. An Automated and Continuous Plant Weight Measurement System for Plant Factory.

    Science.gov (United States)

    Chen, Wei-Tai; Yeh, Yu-Hui F; Liu, Ting-Yu; Lin, Ta-Te

    2016-01-01

    In plant factories, plants are usually cultivated in nutrient solution under a controllable environment. Plant quality and growth are closely monitored and precisely controlled. For plant growth evaluation, plant weight is an important and commonly used indicator. Traditional plant weight measurements are destructive and laborious. In order to measure and record the plant weight during plant growth, an automated measurement system was designed and developed herein. The weight measurement system comprises a weight measurement device and an imaging system. The weight measurement device consists of a top disk, a bottom disk, a plant holder and a load cell. The load cell with a resolution of 0.1 g converts the plant weight on the plant holder disk to an analog electrical signal for a precise measurement. The top disk and bottom disk are designed to be durable for different plant sizes, so plant weight can be measured continuously throughout the whole growth period, without hindering plant growth. The results show that plant weights measured by the weight measurement device are highly correlated with the weights estimated by the stereo-vision imaging system; hence, plant weight can be measured by either method. The weight growth of selected vegetables growing in the National Taiwan University plant factory were monitored and measured using our automated plant growth weight measurement system. The experimental results demonstrate the functionality, stability and durability of this system. The information gathered by this weight system can be valuable and beneficial for hydroponic plants monitoring research and agricultural research applications.

  6. An Automated and Continuous Plant Weight Measurement System for Plant Factory

    Directory of Open Access Journals (Sweden)

    Wei-Tai eChen

    2016-03-01

    Full Text Available In plant factories, plants are usually cultivated in nutrient solution under a controllable environment. Plant quality and growth are closely monitored and precisely controlled. For plant growth evaluation, plant weight is an important and commonly used indicator. Traditional plant weight measurements are destructive and laborious. In order to measure and record the plant weight during plant growth, an automated measurement system was designed and developed herein. The weight measurement system comprises a weight measurement device and an imaging system. The weight measurement device consists of a top disk, a bottom disk, a plant holder and a load cell. The load cell with a resolution of 0.1 g converts the plant weight on the plant holder disk to an analogue electrical signal for a precise measurement. The top disk and bottom disk are designed to be durable for different plant sizes, so plant weight can be measured continuously throughout the whole growth period, without hindering plant growth. The results show that plant weights measured by the weight measurement device are highly correlated with the weights estimated by the stereo-vision imaging system; hence, plant weight can be measured by either method. The weight growth of selected vegetables growing in the National Taiwan University plant factory were monitored and measured using our automated plant growth weight measurement system. The experimental results demonstrate the functionality, stability and durability of this system. The information gathered by this weight system can be valuable and beneficial for hydroponic plants monitoring research and agricultural research applications.

  7. Environmental protection

    International Nuclear Information System (INIS)

    Martinez, A.S.

    1987-01-01

    The question of environment protection related to the use of nuclear energy aiming to power generation, based on the harmonic concept of economic and industrial development, preserving the environment, is discussed. A brief study of environmental impacts for some energy sources, including nuclear energy, to present the systems of a nuclear power plant which aim at environmental protection, is done. (M.C.K.) [pt

  8. Groundwater Protection Program Calendar Year 1998 Groundwater Monitoring Report, U.S. Department of Energy Y-12 Plant, Oak Ridge, Tennessee

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1999-03-01

    This annual monitoring report contains groundwater and surface water monitoring data obtained during calendar year (CY) 1998 by the Lockheed Martin Energy Systems, Inc. Y-12 Plant Groundwater Protection Program (GWPP) at the U.S. Department of Energy (DOE) Oak Ridge Y-12 Plant, Groundwater and surface water monitoring during CY 1998 was performed in three hydrogeologic regimes at the Y-12 Plant: the Bear Creek Hydrogeologic Regime (Bear Creek Regime), the Chestnut Ridge Hydrogeologic Regime (Chestnut Ridge Regime), and the Upper East Fork Poplar Creek Hydrogeologic Regime (East Fork Regime). The Bear Creek and East Fork regimes are located in Bear Creek Valley (BCV), and the Chestnut Ridge Regime which is located south of the Y-12 Plant.

  9. Groundwater Protection Program Calendar Year 1998 Groundwater Monitoring Report, U.S. Department of Energy Y-12 Plant, Oak Ridge, Tennessee

    International Nuclear Information System (INIS)

    1999-01-01

    This annual monitoring report contains groundwater and surface water monitoring data obtained during calendar year (CY) 1998 by the Lockheed Martin Energy Systems, Inc. Y-12 Plant Groundwater Protection Program (GWPP) at the U.S. Department of Energy (DOE) Oak Ridge Y-12 Plant, Groundwater and surface water monitoring during CY 1998 was performed in three hydrogeologic regimes at the Y-12 Plant: the Bear Creek Hydrogeologic Regime (Bear Creek Regime), the Chestnut Ridge Hydrogeologic Regime (Chestnut Ridge Regime), and the Upper East Fork Poplar Creek Hydrogeologic Regime (East Fork Regime). The Bear Creek and East Fork regimes are located in Bear Creek Valley (BCV), and the Chestnut Ridge Regime which is located south of the Y-12 Plant

  10. Quantitative Resistance to Plant Pathogens in Pyramiding Strategies for Durable Crop Protection

    Directory of Open Access Journals (Sweden)

    Marie-Laure Pilet-Nayel

    2017-10-01

    Full Text Available Quantitative resistance has gained interest in plant breeding for pathogen control in low-input cropping systems. Although quantitative resistance frequently has only a partial effect and is difficult to select, it is considered more durable than major resistance (R genes. With the exponential development of molecular markers over the past 20 years, resistance QTL have been more accurately detected and better integrated into breeding strategies for resistant varieties with increased potential for durability. This review summarizes current knowledge on the genetic inheritance, molecular basis, and durability of quantitative resistance. Based on this knowledge, we discuss how strategies that combine major R genes and QTL in crops can maintain the effectiveness of plant resistance to pathogens. Combining resistance QTL with complementary modes of action appears to be an interesting strategy for breeding effective and potentially durable resistance. Combining quantitative resistance with major R genes has proven to be a valuable approach for extending the effectiveness of major genes. In the plant genomics era, improved tools and methods are becoming available to better integrate quantitative resistance into breeding strategies. Nevertheless, optimal combinations of resistance loci will still have to be identified to preserve resistance effectiveness over time for durable crop protection.

  11. Sm2, a paralog of the Trichoderma cerato-platanin elicitor Sm1, is also highly important for plant protection conferred by the fungal-root interaction of Trichoderma with maize.

    Science.gov (United States)

    Gaderer, Romana; Lamdan, Netta L; Frischmann, Alexa; Sulyok, Michael; Krska, Rudolf; Horwitz, Benjamin A; Seidl-Seiboth, Verena

    2015-01-16

    The proteins Sm1 and Sm2 from the biocontrol fungus Trichoderma virens belong to the cerato-platanin protein family. Members of this family are small, secreted proteins that are abundantly produced by filamentous fungi with all types of life-styles. Some species of the fungal genus Trichoderma are considered as biocontrol fungi because they are mycoparasites and are also able to directly interact with plants, thereby stimulating plant defense responses. It was previously shown that the cerato-platanin protein Sm1 from T. virens - and to a lesser extent its homologue Epl1 from Trichoderma atroviride - induce plant defense responses. The plant protection potential of other members of the cerato-platanin protein family in Trichoderma, however, has not yet been investigated. In order to analyze the function of the cerato-platanin protein Sm2, sm1 and sm2 knockout strains were generated and characterized. The effect of the lack of Sm1 and Sm2 in T. virens on inducing systemic resistance in maize seedlings, challenged with the plant pathogen Cochliobolus heterostrophus, was tested. These plant experiments were also performed with T. atroviride epl1 and epl2 knockout strains. In our plant-pathogen system T. virens was a more effective plant protectant than T. atroviride and the results with both Trichoderma species showed concordantly that the level of plant protection was more strongly reduced in plants treated with the sm2/epl2 knockout strains than with sm1/epl1 knockout strains. Although the cerato-platanin genes sm1/epl1 are more abundantly expressed than sm2/epl2 during fungal growth, Sm2/Epl2 are, interestingly, more important than Sm1/Epl1 for the promotion of plant protection conferred by Trichoderma in the maize-C. heterostrophus pathosystem.

  12. Nuclear power plant diagnostic system

    International Nuclear Information System (INIS)

    Prokop, K.; Volavy, J.

    1982-01-01

    Basic information is presented on diagnostic systems used at nuclear power plants with PWR reactors. They include systems used at the Novovoronezh nuclear power plant in the USSR, at the Nord power plant in the GDR, the system developed at the Hungarian VEIKI institute, the system used at the V-1 nuclear power plant at Jaslovske Bohunice in Czechoslovakia and systems of the Rockwell International company used in US nuclear power plants. These diagnostic systems are basically founded on monitoring vibrations and noise, loose parts, pressure pulsations, neutron noise, coolant leaks and acoustic emissions. The Rockwell International system represents a complex unit whose advantage is the on-line evaluation of signals which gives certain instructions for the given situation directly to the operator. The other described systems process signals using similar methods. Digitized signals only serve off-line computer analyses. (Z.M.)

  13. Fire protection of safe shutdown capability at commercial nuclear power plants

    International Nuclear Information System (INIS)

    Sullivan, K.

    1993-01-01

    The comprehensive industrial safety standards and codes that exist today have evolved from lessons learned through past experience, research results, and improvements in technological capabilities. The current requirements for fire safety features of commercial nuclear power stations operated in the US are a notable example of this practice. Although fire protection has always been an important design requirement, from the aftermath of a serious fire that occurred in 1975 at the Browns Ferry plant, it was learned that the life safety and property protection concerns of the major fire insurance underwriters may not sufficiently encompass nuclear safety issues, particularly with regard to the potential for fire damage to result in the common mode failure of redundant trains of systems, and components important to the safe shutdown of the reactor. Following its investigations into the Browns Ferry fire, the Nuclear Regulatory Commission (NRC) promulgated guidance documents, which ultimately developed into mandatory regulations, necessary to assure the implementation of a fire protection program that would address nuclear safety concerns. The new criteria that evolved, contain prescriptive design features, as well as personnel and administrative requirements the Commission determined to be necessary to provide a defense-in-depth level of protection against the hazards of fire and its associated effects on safety related equipment. These criteria are primarily contained in Appendix R of Title 10 to the Code of Federal Regulations (10 CFR 50). Since 1983, various members of the Department of Nuclear Energy (DNE) at Brookhaven National Laboratory (BNL) have provided technical assistance to the Nuclear Regulatory Commission (NRC) in support of its evaluations of fire protection features implemented at commercial nuclear power stations operated in the US. This paper presents a discussion of the insights gained by the author during his active participation in this area

  14. Design Of Photovoltaic Powered Cathodic Protection System

    Directory of Open Access Journals (Sweden)

    Golina Samir Adly

    2017-07-01

    Full Text Available The corrosion caused by chemical reaction between metallic structures and surrounding mediums such as soil or water .the CP cathodic protection system is used to protect metallic structure against corrosion. Cathodic protection CP used to minimize corrosion by utilizing an external source of electrical current which forces the entire structure to become a cathode. There are two Types of cathodic protection system Galvanic current Impressed current.the Galvanic current is called a sacrificial anode is connected to the protected structure cathode through a DC power supply. In Galvanic current system a current passes from the sacrificing anode to the protected structure .the sacrificial anode is corroded rather than causing the protected structure corrosion .protected structure requires a constant current to stop the corrosion which determined by area structure metal and the surrounding medium. The rains humidity are decrease soil resistivity and increase the DC current .The corrosion and over protection resulting from increase in the DC current is harmful for the metallic structure. This problem can be solved by conventional cathodic protection system by manual adjustment of DC voltage periodically to obtain a constant current .the manual adjustment of DC voltage depends on experience of the technician and using the accuracy of the measuring equipment. The errors of measuring current depend on error from the technician or error from the measuring equipment. the corrosion of structure may occur when the interval between two successive adjustment is long .An automatically regulated cathodic protection system is used to overcome problems from conventional cathodic protection system .the regulated cathodic protection system adjust the DC voltage of the system automatically when it senses the variations of surrounding medium resistivity so the DC current is constant at the required level.

  15. Predicting the presence and cover of management relevant invasive plant species on protected areas.

    Science.gov (United States)

    Iacona, Gwenllian; Price, Franklin D; Armsworth, Paul R

    2016-01-15

    Invasive species are a management concern on protected areas worldwide. Conservation managers need to predict infestations of invasive plants they aim to treat if they want to plan for long term management. Many studies predict the presence of invasive species, but predictions of cover are more relevant for management. Here we examined how predictors of invasive plant presence and cover differ across species that vary in their management priority. To do so, we used data on management effort and cover of invasive plant species on central Florida protected areas. Using a zero-inflated multiple regression framework, we showed that protected area features can predict the presence and cover of the focal species but the same features rarely explain both. There were several predictors of either presence or cover that were important across multiple species. Protected areas with three days of frost per year or fewer were more likely to have occurrences of four of the six focal species. When invasive plants were present, their proportional cover was greater on small preserves for all species, and varied with surrounding household density for three species. None of the predictive features were clearly related to whether species were prioritized for management or not. Our results suggest that predictors of cover and presence can differ both within and across species but do not covary with management priority. We conclude that conservation managers need to select predictors of invasion with care as species identity can determine the relationship between predictors of presence and the more management relevant predictors of cover. Copyright © 2015 Elsevier Ltd. All rights reserved.

  16. Higher plant availability and reduced reactor scram frequency in PWRs by appropriate system and I and C design

    International Nuclear Information System (INIS)

    Frei, G.; Weber, J.

    1987-01-01

    High plant availability and reliability are guaranteed by appropriate design of reactor and BOP systems, this including the plant I and C systems. It is of advantage to have design, construction and commissioning of the plant concentrated in the hands of a single company to avoid interface problems between the different areas of the plant. The integrated overall control concept developed by KWU with control, limitation and protection systems as well as optimized operational and monitoring systems assisted by instrumentation channel redundance and logic for selection of the second highest (or second lowest) signal value as appropriate for comparison with limitation setpoints, minimize the severity of transients. This results in a reduction in the frequency of reactor scrams and of unnecessary actuation of safety systems. Dynamic plant behavior is described for a number of examples where the improved plant behavior resulting from the above design features enhances plant availability

  17. Safety and environmental protection - realization efforts regarding the authorization of power engineering plants

    International Nuclear Information System (INIS)

    Dreyhaupt, F.J.

    1982-01-01

    As to power plants the author calls special attention to three statements concerning questions on safety and environmental protection which play a decisive part in authorizing conventional and nuclear facilities. After investigating the most important legal fundamental principles for the authorization of power engineering plants, the Atomic Act and the Federal Immission Protection Act, the author discusses the problems that arise with the application of the authorization procedures. The reasons which can be made responsible for the long running periods of the authorization procedures and therewith of the realization of the site installation work are given. Finally, the author describes and judges the outlines of regulations for large scale furnaces and for the TA-air supplementary clause. (orig.) [de

  18. Component protection based automatic control

    International Nuclear Information System (INIS)

    Otaduy, P.J.

    1992-01-01

    Control and safety systems as well as operation procedures are designed on the basis of critical process parameters limits. The expectation is that short and long term mechanical damage and process failures will be avoided by operating the plant within the specified constraints envelopes. In this paper, one of the Advanced Liquid Metal Reactor (ALMR) design duty cycles events is discussed to corroborate that the time has come to explicitly make component protection part of the control system. Component stress assessment and aging data should be an integral part of the control system. Then transient trajectory planning and operating limits could be aimed at minimizing component specific and overall plant component damage cost functions. The impact of transients on critical components could then be managed according to plant lifetime design goals. The need for developing methodologies for online transient trajectory planning and assessment of operating limits in order to facilitate the explicit incorporation of damage assessment capabilities to the plant control and protection systems is discussed. 12 refs

  19. Inactivated recombinant plant virus protects dogs from a lethal challenge with canine parvovirus.

    Science.gov (United States)

    Langeveld, J P; Brennan, F R; Martínez-Torrecuadrada, J L; Jones, T D; Boshuizen, R S; Vela, C; Casal, J I; Kamstrup, S; Dalsgaard, K; Meloen, R H; Bendig, M M; Hamilton, W D

    2001-06-14

    A vaccine based upon a recombinant plant virus (CPMV-PARVO1), displaying a peptide derived from the VP2 capsid protein of canine parvovirus (CPV), has previously been described. To date, studies with the vaccine have utilized viable plant chimaeric particles (CVPs). In this study, CPMV-PARVO1 was inactivated by UV treatment to remove the possibility of replication of the recombinant plant virus in a plant host after manufacture of the vaccine. We show that the inactivated CVP is able to protect dogs from a lethal challenge with CPV following parenteral immunization with the vaccine. Dogs immunized with the inactivated CPMV-PARVO1 in adjuvant displayed no clinical signs of disease and shedding of CPV in faeces was limited following CPV challenge. All immunized dogs elicited high titres of peptide-specific antibody, which neutralized CPV in vitro. Levels of protection, virus shedding and VP2-specific antibody were comparable to those seen in dogs immunized with the same VP2- peptide coupled to keyhole limpet hemocyanin (KLH). Since plant virus-derived vaccines have the potential for cost-effective manufacture and are not known to replicate in mammalian cells, they represent a viable alternative to current replicating vaccine vectors for development of both human and veterinary vaccines.

  20. Radiological protection in nuclear power plants; La proteccion radiologica en las centrales nucleares

    Energy Technology Data Exchange (ETDEWEB)

    Zorrilla R, S. [CFE. Central Laguna Verde, Km. 42.5 Carretera Cardel-Nautla, Veracruz (Mexico)

    2008-12-15

    several fronts, the number of dosimetry transactions, increases up to 30 times the normal operation, and so on. For these reasons during the reloads, the electronic dosimetry system and the monitoring system output contamination staff becomes critical systems whose functioning must be ensured to avoid becoming a bottleneck. Reloads must also be planned for a perfect manning of critical supplies such as clothing and protection accessories against contamination. (Author)

  1. Waste processing plant eco-auditing system for minimization of environmental risk: European Communities regulatory proposal

    International Nuclear Information System (INIS)

    Brunetti, N.

    1993-01-01

    This paper delineates a system of process control and monitoring checks to be applied to municipal-industrial waste processing and disposal plants to ensure their energy efficient, environmentally safe and reliable operation. In line with European Communities environmental protection strategies, this eco-auditing system requires the preparation of environmental impacts statements on a regular basis during plant operation, as well as, prior to plant start-up. Continuous plant environmental compatibility evaluations are to ascertain: material and energy inputs and outputs; the composition and amounts of exhaust gases released into the atmosphere and the integrity of treatment liquids; control and monitoring instrumentation reliability. The implementation of the auditing system is to be carried out under the supervision of authorized auditing personnel. Waste processing and disposal plants are to make maximum use of energy and materials recovery processes so as to minimize energy consumption and risk to the environment

  2. Radiation protection aspects in the design of nuclear power plants. Safety guide

    International Nuclear Information System (INIS)

    2008-01-01

    . The IAEA takes seriously the enduring challenge for users and regulators everywhere: that of ensuring a high level of safety in the use of nuclear materials and radiation sources around the world. Their continuing utilization for the benefit of humankind must be managed in a safe manner, and the IAEA safety standards are designed to facilitate the achievement of that goal. This Safety Guide has been prepared as a part of the IAEA programme on safety standards for nuclear power plants. It includes recommendations on how to satisfy the requirements established in the Safety Requirements publication on the Safety of Nuclear Power Plants: Design. It addresses the provisions that should be made in the design of nuclear power plants in order to protect site personnel, the public and the environment against radiological hazards for operational states, decommissioning and accident conditions. The recommendations on radiation protection provided in this Safety Guide are consistent with the International Basic Safety Standards for Protection against Ionizing Radiation and for the Safety of Radiation Sources (BSS), which were jointly sponsored by the Food and Agriculture Organization of the United Nations (FAO), the IAEA, the International Labour Organisation (ILO), the OECD Nuclear Energy Agency (OECD/NEA), the Pan American Health Organization (PAHO) and the World Health Organization (WHO). This Safety Guide supersedes Safety Series No. 50-SG-D9, Design Aspects of Radiation Protection for Nuclear Power Plants, published in 1985. Effective radiation protection is a combination of good design, high quality construction and proper operation. Procedures that address the radiation protection aspects of operation are covered in the Safety Guide on Radiation Protection and Radioactive Waste Management in the operation of Nuclear Power Plants

  3. Seismic risk control of nuclear power plants using seismic protection systems in stable continental regions: The UK case

    Energy Technology Data Exchange (ETDEWEB)

    Medel-Vera, Carlos, E-mail: cbmedel@uc.cl; Ji, Tianjian, E-mail: tianjian.ji@manchester.ac.uk

    2016-10-15

    Highlights: • Strategies to reduce seismic risk for nuclear power stations in the UK are analysed. • Efficiency of devices to reduce risk: viscous-based higher than hysteretic-based. • Scenario-based incremental dynamic analysis is introduced for use in nuclear stations. • Surfaces of seismic unacceptable performance for nuclear stations are proposed. - Abstract: This article analyses three different strategies on the use of seismic protection systems (SPS) for nuclear power plants (NPPs) in the UK. Such strategies are based on the experience reported elsewhere of seismically protected nuclear reactor buildings in other stable continental regions. Analyses are conducted using an example of application based on a 1000 MW Pressurised Water Reactor building located in a representative UK nuclear site. The efficiency of the SPS is probabilistically assessed to achieve possible risk reduction for both rock and soil sites in comparison with conventionally constructed NPPs. Further analyses are conducted to study how the reduction of risk changes when all controlling scenarios of the site are included. This is done by introducing a scenario-based incremental dynamic analysis aimed at the generation of surfaces for unacceptable performance of NPPs as a function of earthquake magnitude (M{sub w}) and distance-to-site (R{sub epi}). General guidelines are proposed to potentially use SPS in future NPPs in the UK. Such recommendations can be used by the British nuclear industry in the future development of 12 new reactors to be built in the next two decades to generate 16 GWe of new nuclear capacity.

  4. Impact of power plants on aquatic systems: a social perspective

    International Nuclear Information System (INIS)

    Coutant, C.C.

    1975-01-01

    Topics discussed are: aquatic effects of thermal electric power stations; legal aspects of water pollution; EPA provisions for levels of thermal discharges to assure protection and propagation of a balanced, indigenous population of shellfish, fish, and wildlife in a body of water; cost benefit analysis of steam electric power effluents; cooling systems and siting of power plants; simulation modeling of population dynamics; and sociological aspects of water pollution

  5. Temporary physical protection systems

    International Nuclear Information System (INIS)

    Williams, J.D.; Gangel, D.J.; Madsen, R.W.

    1991-01-01

    Terrorism and other aspects of world political instability have created a high demand for temporary physical protection systems within the nuclear materials management community. They can be used when vehicles carrying important assets are away from their permanent fixed site location, around areas where experiments are being temporarily conducted, around construction areas and one portions of a fixed site physical security system which is temporarily inoperable. Physical security systems can be grouped into four categories: tactical, portable, semi-permanent, and fixed. The resources and experience gained at Sandia National Laboratories in over forty years of developing and implementing security systems for protecting nuclear weapons and fixed nuclear facilities is now being applied to temporary physical security systems. This paper emphasizes temporary physical security systems and their component parts that are presently available and identify additional system-subsystem objectives, requirements, and concepts

  6. Identification of protective actions to reduce the vulnerability of safety-critical systems to malevolent acts: A sensitivity-based decision-making approach

    International Nuclear Information System (INIS)

    Wang, Tai-Ran; Pedroni, Nicola; Zio, Enrico

    2016-01-01

    A classification model based on the Majority Rule Sorting method has been previously proposed by the authors to evaluate the vulnerability of safety-critical systems (e.g., nuclear power plants) with respect to malevolent intentional acts. In this paper, we consider a classification model previously proposed by the authors based on the Majority Rule Sorting method to evaluate the vulnerability of safety-critical systems (e.g., nuclear power plants) with respect to malevolent intentional acts. The model is here used as the basis for solving an inverse classification problem aimed at determining a set of protective actions to reduce the level of vulnerability of the safety-critical system under consideration. To guide the choice of the set of protective actions, sensitivity indicators are originally introduced as measures of the variation in the vulnerability class that a safety-critical system is expected to undergo after the application of a given set of protective actions. These indicators form the basis of an algorithm to rank different combinations of actions according to their effectiveness in reducing the safety-critical systems vulnerability. Results obtained using these indicators are presented with regard to the application of: (i) one identified action at a time, (ii) all identified actions at the same time or (iii) a random combination of identified actions. The results are presented with reference to a fictitious example considering nuclear power plants as the safety-critical systems object of the analysis. - Highlights: • We use a hierarchical framework to represent the vulnerability. • We use an empirical classification model to evaluate vulnerability. • Sensitivity indicators are introduced to rank protective actions. • Constraints (e.g., budget limitations) are accounted for. • Method is applied to fictitious Nuclear Power Plants.

  7. Amphibians and plant-protection products: what research and action is needed?

    Science.gov (United States)

    Aldrich, Annette; Junghans, Marion; Aeberli, Caroline; Brühl, Carsten A; Streissl, Franz; Schmidt, Benedikt R

    2016-01-01

    The majority of Swiss amphibians are threatened. There is a range of factors which have been discussed as possible causes for their decline, including plant protection products (PPPs). The influence of PPPs on amphibian populations has not yet been studied to any great extent, neither for active ingredients nor for the wetting agents, breakdown products or tank mixtures. A further topic of discussion was how to better protect amphibians by reducing their exposure to PPPs in agricultural fields. Experts at a workshop concluded that further research is needed.

  8. Identity management and witness protection system

    OpenAIRE

    Paunović, Saša; Starčević, Dušan; Nešić, Lazar

    2013-01-01

    The protection of participants in criminal proceedings is one of the most important tools for prosecution of war crimes and organized crime cases. The paper presents the basic characteristics and the importance of implementing the Program of protection in criminal proceedings, with emphasis on the protection system and management of identity. Special attention was paid to challenges facing the protection system in criminal proceedings and the management of identities, which are caused by the ...

  9. The regulatory evaluation of radiation protection training programmes at Canadian nuclear power plants

    International Nuclear Information System (INIS)

    Legare, M.; Tennant, D.

    1996-01-01

    The responsibility for providing the necessary assurance that the use of nuclear energy in Canada does not pose undue risk to health, safety, security and the environment is vested with the Atomic Energy Control Board (AECB). This responsibility has led the Operator Certification Division of the AECB to develop methods to obtain assurance that nuclear power plant operations personnel are well trained and adequately competent to perform their duties. The features of the AECB approach to evaluation of training programmes based on a systematic approach to training is described. An overview of the Canadian nuclear power plants' radiation protection qualification levels is given. The developing evaluation process is contributing to the improvement of licensee radiation protection training programmes. This is making possible the transfer of part of the responsibility for licensed personnel radiation protection qualification assessment to the licensees, thus enabling a reduction in the operator certification division formal qualification activities. (author)

  10. Manual of plant producers and services in environmental protection. Database in the field of environmental protection

    International Nuclear Information System (INIS)

    Serve, C.

    1992-01-01

    On the basis of an enquiry, the Stuttgart Chamber of Industry and Commerce produced a database of the services offered by regional and supraregional companies in the field of environmental protection. The data are presented in this manual, classified as follows: noise protection systems; sanitation systems and services; other systems and services. (orig.) [de

  11. 78 FR 77574 - Protection System Maintenance Reliability Standard

    Science.gov (United States)

    2013-12-24

    ... commissioning of power system protection systems.\\55\\ NERC commits in its Comments to keep the Commission... commissioning of power system protection systems.\\62\\ As explained in the NOPR, our concern is with a protection... protection system, ``resulting in line relays being placed in service with the incorrect transformer ratio...

  12. Integrated approach to fire safety at the Krsko nuclear power plant - fire protection action plan

    International Nuclear Information System (INIS)

    Lambright, J.A.; Cerjak, J.; Spiler, J.; Ioannidi, J.

    1998-01-01

    Nuclear Power Plant Krsko (NPP Krsko) is a Westinghouse design, single-unit, 1882 Megawatt thermal (MWt), two-loop, pressurized water nuclear power plant. The fire protection program at NPP Krsko has been reviewed and reports issued recommending changes and modifications to the program, plant systems and structures. Three reports were issued, the NPP Krsko Fire Hazard Analysis (Safe Shout down Separation Analysis Report), the ICISA Analysis of Core Damage Frequency Due to Fire at the NPP Krsko and IPEEE (Individual Plant External Event Examination) related to fire risk. The Fire Hazard Analysis Report utilizes a compliance - based deterministic approach to identification of fire area hazards. This report focuses on strict compliance from the perspective of US Nuclear Regulatory Commission (USNRC), standards, guidelines and acceptance criteria and does not consider variations to comply with the intent of the regulations. The probabilistic analysis methide used in the ICISA and IPEEE report utilizes a risk based nad intent based approach in determining critical at-risk fire areas. NPP Krsko has already completed the following suggestions/recommendations from the above and OSART reports in order to comply with Appendix R: Installation of smoke detectors in the Control Room; Installation of Emergency Lighting in some plant areas and of Remote Shout down panels; Extension of Sound Power Communication System; Installation of Fire Annunciator Panel at the On-site Fire Brigade Station; Installation of Smoke Detection System in the (a) Main Control Room Panels, (b) Essential Service Water Building. (c) Component Cooling Building pump area, chiller area and HVAC area, (d) Auxiliary Building Safety pump rooms, (e) Fuel Handling room, (f) Intermediate Building AFFW area and compressor room, and (g) Tadwaste building; inclusion of Auxiliary operators in the Fire Brigade; training of Fire Brigade Members in Plant Operation (9 week course); Development of Fire Door Inspection and

  13. Smart cathodic protection systems

    NARCIS (Netherlands)

    Polder, R.B.; Leggedoor, J.; Schuten, G.; Sajna, S.; Kranjc, A.

    2010-01-01

    Cathodic protection delivers corrosion protection in concrete structures exposed to aggressive environments, e.g. in de-icing salt and marine climates. Working lives of a large number of CP systems are at least more than 13 years and probably more than 25 years, provided a minimum level of

  14. National Pollution Discharge Elimination System (NPDES) Wastewater Treatment Plant Points, Region 9, 2007, US EPA Region 9

    Data.gov (United States)

    U.S. Environmental Protection Agency — Point geospatial dataset representing locations of NPDES Waste Water Treatment Plant Facilities. NPDES (National Pollution Discharge Elimination System) is an EPA...

  15. National Pollution Discharge Elimination System (NPDES) Wastewater Treatment Plant Points, Region 9, 2011, US EPA Region 9

    Data.gov (United States)

    U.S. Environmental Protection Agency — Point geospatial dataset representing locations of NPDES Waste Water Treatment Plant Facilities. NPDES (National Pollution Discharge Elimination System) is an EPA...

  16. National Pollution Discharge Elimination System (NPDES) Wastewater Treatment Plant Points, Region 9, 2012, US EPA Region 9

    Data.gov (United States)

    U.S. Environmental Protection Agency — Point geospatial dataset representing locations of NPDES Waste Water Treatment Plant Facilities. NPDES (National Pollution Discharge Elimination System) is an EPA...

  17. Physical protection system design and evaluation

    International Nuclear Information System (INIS)

    Williams, J.D.

    1997-11-01

    The design of an effective physical protection system (PPS) includes the determination of the PPS objectives, the initial design of a PPS, the evaluation of the design, and probably, the redesign or refinement of the system. To develop the objectives, the designer must begin by gathering information about facility operation and conditions, such as a comprehensive description of the facility, operating conditions, and the physical protection requirements. The designer then needs to define the threat. This involves considering factors about potential adversaries: class of adversary, adversary's capabilities, and range of adversary's tactics. Next, the designer should identify targets. Determination of whether or not the materials being protected are attractive targets is based mainly on the ease or difficulty of acquisition and desirability of the material. The designer now knows the objectives of the PPS, that is, ''what to protect against whom.'' The next step is to design the system by determining how best to combine such elements as fences, vaults, sensors and assessment devices, entry control devices, communication devices, procedures, and protective force personnel to meet the objectives of the system. Once a PPS is designed, it must be analyzed and evaluated to ensure it meets the PPS objectives. Evaluation must allow for features working together to ensure protection rather than regarding each feature separately. Due to the complexity of the protection systems, an evaluation usually requires modeling techniques. If any vulnerabilities are found, the initial system must be redesigned to correct the vulnerabilities and a reevaluation conducted. After the system is installed, the threat and system parameters may change with time. If they do, the analysis must be performed periodically to ensure the system objectives are still being met

  18. An integrated system for physical protection

    International Nuclear Information System (INIS)

    Kumar, Ranajit

    2001-01-01

    An Integrated Physical Protection System (IPPS) was developed for the consolidation of all sub systems, sensors and elements related to physical protection for an efficient and effective security environment of a facility. An effective physical protection system discharges the functions of detection, delay, communication, response, access control etc. IPPS performs, controls and monitors all the above functionality and helps in taking quick action on occurrence of unusual incidents by instantly reporting the incident in easily understandable audio, video, graphical and textual format and also by initiating automatic interactions among sub-systems

  19. Reactor protection system. Revision 1

    International Nuclear Information System (INIS)

    Fairbrother, D.B.; Vincent, D.R.; Lesniak, L.M.

    1975-04-01

    The reactor protection system-II (RPS-II) designed for use on Babcock and Wilcox 145- and 205-fuel assembly pressurized water reactors is described. In this system, relays in the trip logic have been replaced by solid state devices. A calculating module for the low DNBR, pump status, and offset trip functions has replaced the overpower trip (based on flow and imbalance), the power/RC pump trip, and the variable low pressure trip. Included is a description of the changes from the present Oconee-type reactor protection system (RPS-I), a functional and hardware description of the calculating module, and a discussion of the qualification program conducted to ensure that the degree of protection provided by RPS-II is not less than that provided by previously licensed systems supplied by B and W. (U.S.)

  20. Advanced physical protection systems for nuclear materials

    International Nuclear Information System (INIS)

    Jones, O.E.

    1976-01-01

    Because of the increasing incidence of terrorism, there is growing concern that nuclear materials and facilities need improved physical protection against theft, diversion, or sabotage. Physical protection systems for facilities or transportation which have balanced effectiveness include information systems, access denial systems, adequate and timely response, recovery capability, and use denial methods for despoiling special nuclear materials (SNM). The role of these elements in reducing societal risk is described; however, it is noted that, similar to nuclear war, the absolute risks of nuclear theft and sabotage are basically unquantifiable. Sandia Laboratories has a major US Energy Research and Development Administration (ERDA) role in developing advanced physical protection systems for improving the security of both SNM and facilities. These activities are surveyed in this paper. A computer simulation model is being developed to assess the cost-effectiveness of alternative physical protection systems under various levels of threat. Improved physical protection equipment such as perimeter and interior alarms, secure portals, and fixed and remotely activated barriers is being developed and tested. In addition, complete prototype protection systems are being developed for representative nuclear facilities. An example is shown for a plutonium storage vault. The ERDA safe-secure transportation system for highway shipments of all significant quantities of government-owned SNM is described. Adversary simulation as a tool for testing and evaluating physical protection systems is discussed. Finally, a list of measures is given for assessing overall physical protection system performance. (author)

  1. Advanced physical protection systems for nuclear materials

    International Nuclear Information System (INIS)

    Jones, O.E.

    1975-10-01

    Because of the increasing incidence of terrorism, there is growing concern that nuclear materials and facilities need improved physical protection against theft, diversion, or sabotage. Physical protection systems for facilities or transportation which have balanced effectiveness include information systems, access denial systems, adequate and timely response, recovery capability, and use denial methods for despoiling special nuclear materials (SNM). The role of these elements in reducing societal risk is described; however, it is noted that, similar to nuclear war, the absolute risks of nuclear theft and sabotage are basically unquantifiable. Sandia Laboratories has a major Energy Research and Development Administration (ERDA) role in developing advanced physical protection systems for improving the security of both SNM and facilities. These activities are surveyed. A computer simulation model is being developed to assess the cost-effectiveness of alternative physical protection systems under various levels of threat. Improved physical protection equipment such as perimeter and interior alarms, secure portals, and fixed and remotely-activated barriers is being developed and tested. In addition, complete prototype protection systems are being developed for representative nuclear facilities. An example is shown for a plutonium storage vault. The ERDA safe-secure transportation system for highway shipments of all significant quantities of government-owned SNM is described. Adversary simulation as a tool for testing and evaluating physical protection systems is discussed. A list of measures is given for assessing overall physical protection system performance. (auth)

  2. Inspection of fire protection measures and fire fighting capability at nuclear power plants. A publication within the NUSS programme

    International Nuclear Information System (INIS)

    1994-01-01

    The present publication has been developed with the help of experts from regulatory, operating and engineering organizations, all with practical experience in the field of fire protection of nuclear power plants. The publication outlines practices for inspecting the fire protection measures at nuclear power plants in accordance with Safety Series No.50-SG-D2(Rev.1), Fire Protection in Nuclear Power Plants, and includes a comprehensive fire safety inspection checklist of the specific elements to be addressed when evaluating the adequacy and effectiveness of the fire protection measures and manual fire fighting capability available at operating nuclear power plants. The publication will be useful not only to regulators and safety assessors but also to operators and designers. The book addresses a specialized topic and it is recommended that it be used in conjunction with Safety Guide No.50-SG-D2(Rev.1)

  3. Plant monitor system

    International Nuclear Information System (INIS)

    Scarola, K.; Jamison, D.; Manazir, R.; Rescori, R.; Harmon, D.

    1991-01-01

    An advanced control room complex for a nuclear power plant, including a discrete indicator and alarm system which is nuclear qualified for rapid response to changes in plant parameters and a component control system which together provide a discrete monitoring and control capability at a panel in the control room. A separate data processing system, which need not be nuclear qualified, provides integrated and overview information to the control room and to each panel, through CRTs and a large, overhead integrated process status overview board. The discrete indicator and alarm system and the data processing system receive inputs from common plant sensors and validate the sensor outputs to arrive at a representative value of the parameter for use by the operator during both normal and accident conditions, thereby avoiding the need for him to assimilate data from each sensor individually. The integrated process status board is at the apex of an information hierarchy that extends through four levels and provides access at each panel to the full display hierarchy. The control room panels are preferably of a modular construction, permitting the definition of inputs and outputs, the main machine interface, and the plant specific algorithms, to proceed in parallel with the fabrication of the panels, the installation of the equipment and the generic testing thereof. (author)

  4. Radiation protection programme at Krsko nuclear power plant

    International Nuclear Information System (INIS)

    Breznik, B.

    1996-01-01

    Krsko NPP, a Westinghouse two-loop PWR of 632 M We power, is in commercial operation since 1982. Reduction of radioactive releases to the environment and the reduction of doses to workers is the basic goal in the plant radiological protection. The radiation protection programme is established to ensure that the radiation exposures to workers and members of the public are minimized according to the As Low As Reasonably Achievable approach and controlled in accordance with international safety standards and Slovenian regulations. The basis for the operational and technical measures has been provided according to the industrial good practice. The effluent control is based on the Standard Radioactive Effluent Technical Specifications, and environmental surveillance is established according to the programme defined by the regulations. The dose constraints and performance indicators are used to assure the effectiveness of the radiation protection programme and provide a convenient follow-up tool. The monitoring programme results of each year show that there is no measurable dose to the public due to radioactive releases. The commitment to the dose burden of any member of a critical group is assessed to be below the dose constraint. Individual and collective doses of the workers are within a range typical for the PWRs of a similar type. (author)

  5. The application of plant information system on third Qinshan nuclear power plant

    International Nuclear Information System (INIS)

    Liu Wangtian

    2005-01-01

    Plant overall control has been applied in Qinshan Nuclear Power Plant, which enhances the security of plant operation, but it is not enough to improve the technical administration level. In order to integrate the overall information and to improve the technical administration level more. Third Qinshan Nuclear Power Plant applies the plant information system. This thesis introduces the application of plant information system in Third Qinshan Nuclear Power Plant and the effect to the plant after the system is carried into execution, in addition, it does more analysis and exceptions for application of plant information system in the future. (authors)

  6. Availability analysis of supervised protective systems

    International Nuclear Information System (INIS)

    Kontoleon, N.; Kontoleon, J.M.; Chrysochoides, N.G.

    1975-01-01

    The behaviour in time of a nuclear reactor supervised protective system is modelled mathematically by a Markov process, continuous in time and with three discrete states. Failure and repair rates are assumed to be exponentially distributed. An analytical expression of system availability as a function of failure and repair rates as well as the inspection intervals and duration is derived. An optimization problem is then discussed in order to maximize system availability with respect to imposed cost constraints. Finally, an example of a supervised protective system with short inactive times is given, which may be found in many practical situations of modern protective systems. (author)

  7. The LHC quench protection system

    CERN Multimedia

    2009-01-01

    The new quench protection system (QPS) has the crucial roles of providing an early warning for any part of the superconducting coils and busbars that develop high resistance, as well as triggering the switch-off of the machine. Over 2000 new detectors will be installed around the LHC to make sure every busbar segment between magnets is monitored and protected. One of the major consolidation activities for the LHC is the addition of two new detectors to the quench protection system. A magnet quench occurs when part of the superconducting cable becomes normally-conducting. When the protection system detects an increased resistance the huge amount of energy stored in the magnet chains is safely extracted and ‘dumped’ into specially designed resistors. In the case of the main dipole chain, the stored energy in a single LHC sector is roughly the same as the kinetic energy of a passenger jet at cruising speed. The first new detector is designed to monitor the superconducting...

  8. Efficient production of electricity and water in cogeneration systems. [Desalination plant

    Energy Technology Data Exchange (ETDEWEB)

    Tadros, S.K.

    1981-11-01

    This paper discusses two topping cycle steam turbine cogeneration systems. The water desalination plant selected is the multistage flash evaporator cycle which uses brine recirculation and high temperature additives for scale protection and 233F maximum brine temperature. The paper mentions briefly the impact of future fuel prices on design and factors which would further improve thermal efficiency. The fuel chargeable to power is determined. 6 refs.

  9. Radiological protection system in the era of nuclear renaissance expectation for development of radiological protection system

    International Nuclear Information System (INIS)

    Toyomatsu, Hideki

    2008-01-01

    The current radiological protection system, which was established mainly by the ICRP and UNSCEAR, has contributed to the prevention of potential radiological health hazards, and has been a fundamental concept during the development of nuclear energy. Through a detailed discussion regarding the new ICRP recommendations, the world nuclear industry has reached a consensus that the current radiological protection system keeps its integrity in principle although it involves some remaining issues, such as the disposal of radioactive waste. In order to maximize the advantages of nuclear energy while keeping the integrity of radiological protection system, it is essential to address the characteristics of radiation, which is specific to nuclear energy, so that nuclear energy can coexist with other energy sources. The three basic principles of radiological protection (i.e., justification, optimization and dose limits), which were completed in the 1990 recommendations of ICRP, should be retained as the basic concepts for the future radiological protection system in order to maintain the continuity and consistency of the radiological protection system. The radiological protection system can be furthermore developed only by combining the above three principles with best practices extracted from utilities' field experience. The significant reduction of radiation exposures received by members of the public and radiation workers in the field has resulted from the efforts by the world utilities to achieve the optimization. In order to correctly apply the theory to the work practices, it is essential to see how the theory is practically used in the field. Such a process should be also emphasized in the revision work of the IAEA Basic Safety Standards (BSS), which is currently under progress. Integrating the theory in the work practices is the key to the true development of nuclear renaissance, which could lead to the establishment of the nuclear safety regime. (author)

  10. ITER plant systems

    International Nuclear Information System (INIS)

    Kolbasov, B.; Barnes, C.; Blevins, J.

    1991-01-01

    As part of a series of documents published by the IAEA that summarize the results of the Conceptual Design Activities for the ITER project, this publication describes the conceptual design of the ITER plant systems, in particular (i) the heat transport system, (ii) the electrical distribution system, (iii) the requirements for radioactive equipment handling, the hot cell, and waste management, (iv) the supply system for fluids and operational chemicals, (v) the qualitative analyses of failure scenarios and methods of burn stability control and emergency shutdown control, (vi) analyses of tokamak building functions and design requirements, (vii) a plant layout, and (viii) site requirements. Refs, figs and tabs

  11. Power system protection 3 application

    CERN Document Server

    1995-01-01

    The worldwide growth in demand for electricity has forced the pace of developments in electrical power system design to meet consumer needs for reliable, secure and cheap supplies. Power system protection, as a technology essential to high quality supply, is widely recognised as a specialism of growing and often critical importance, in which power system needs and technological progress have combined to result in rapid developments in policy and practice in recent years. In the United Kingdom, the need for appropriate training in power system protection was recognised in the early 1960s with t

  12. The reliability of nuclear power plant safety systems

    International Nuclear Information System (INIS)

    Susnik, J.

    1978-01-01

    A criterion was established concerning the protection that nuclear power plant (NPP) safety systems should afford. An estimate of the necessary or adequate reliability of the total complex of safety systems was derived. The acceptable unreliability of auxiliary safety systems is given, provided the reliability built into the specific NPP safety systems (ECCS, Containment) is to be fully utilized. A criterion for the acceptable unreliability of safety (sub)systems which occur in minimum cut sets having three or more components of the analysed fault tree was proposed. A set of input MTBF or MTTF values which fulfil all the set criteria and attain the appropriate overall reliability was derived. The sensitivity of results to input reliability data values was estimated. Numerical reliability evaluations were evaluated by the programs POTI, KOMBI and particularly URSULA, the last being based on Vesely's kinetic fault tree theory. (author)

  13. Botanical Insecticides in Plant Protection

    OpenAIRE

    Grdiša, Martina; Gršić, Kristina

    2013-01-01

    Botanical insecticides are natural compounds with insecticidal properties and their use in crop protection is as old as agricultural practice. Although they have been in use for over one hundred years, the advent of synthetic insecticides has unfortunately displaced their use today. Due to fast action, low cost, easy application and efficiency against a wide range of harmful species, synthetic insecticides have become an important part of pest management in modern agricultural systems....

  14. 46 CFR 153.460 - Fire protection systems.

    Science.gov (United States)

    2010-10-01

    ... 46 Shipping 5 2010-10-01 2010-10-01 false Fire protection systems. 153.460 Section 153.460... Requirements for Flammable Or Combustible Cargoes § 153.460 Fire protection systems. Each self-propelled ship... protection system listed beside the cargo in Table 1 and described in the footnotes to Table 1. (b) The...

  15. WASTE HANDLING BUILDING FIRE PROTECTION SYSTEM DESCRIPTION DOCUMENT

    Energy Technology Data Exchange (ETDEWEB)

    J. D. Bigbee

    2000-06-21

    The Waste Handling Building Fire Protection System provides the capability to detect, control, and extinguish fires and/or mitigate explosions throughout the Waste Handling Building (WHB). Fire protection includes appropriate water-based and non-water-based suppression, as appropriate, and includes the distribution and delivery systems for the fire suppression agents. The Waste Handling Building Fire Protection System includes fire or explosion detection panel(s) controlling various detectors, system actuation, annunciators, equipment controls, and signal outputs. The system interfaces with the Waste Handling Building System for mounting of fire protection equipment and components, location of fire suppression equipment, suppression agent runoff, and locating fire rated barriers. The system interfaces with the Waste Handling Building System for adequate drainage and removal capabilities of liquid runoff resulting from fire protection discharges. The system interfaces with the Waste Handling Building Electrical Distribution System for power to operate, and with the Site Fire Protection System for fire protection water supply to automatic sprinklers, standpipes, and hose stations. The system interfaces with the Site Fire Protection System for fire signal transmission outside the WHB as needed to respond to a fire emergency, and with the Waste Handling Building Ventilation System to detect smoke and fire in specific areas, to protect building high-efficiency particulate air (HEPA) filters, and to control portions of the Waste Handling Building Ventilation System for smoke management and manual override capability. The system interfaces with the Monitored Geologic Repository (MGR) Operations Monitoring and Control System for annunciation, and condition status.

  16. WASTE HANDLING BUILDING FIRE PROTECTION SYSTEM DESCRIPTION DOCUMENT

    International Nuclear Information System (INIS)

    J. D. Bigbee

    2000-01-01

    The Waste Handling Building Fire Protection System provides the capability to detect, control, and extinguish fires and/or mitigate explosions throughout the Waste Handling Building (WHB). Fire protection includes appropriate water-based and non-water-based suppression, as appropriate, and includes the distribution and delivery systems for the fire suppression agents. The Waste Handling Building Fire Protection System includes fire or explosion detection panel(s) controlling various detectors, system actuation, annunciators, equipment controls, and signal outputs. The system interfaces with the Waste Handling Building System for mounting of fire protection equipment and components, location of fire suppression equipment, suppression agent runoff, and locating fire rated barriers. The system interfaces with the Waste Handling Building System for adequate drainage and removal capabilities of liquid runoff resulting from fire protection discharges. The system interfaces with the Waste Handling Building Electrical Distribution System for power to operate, and with the Site Fire Protection System for fire protection water supply to automatic sprinklers, standpipes, and hose stations. The system interfaces with the Site Fire Protection System for fire signal transmission outside the WHB as needed to respond to a fire emergency, and with the Waste Handling Building Ventilation System to detect smoke and fire in specific areas, to protect building high-efficiency particulate air (HEPA) filters, and to control portions of the Waste Handling Building Ventilation System for smoke management and manual override capability. The system interfaces with the Monitored Geologic Repository (MGR) Operations Monitoring and Control System for annunciation, and condition status

  17. French experience on renewing I and C systems in NPPs. Feedback from assessing nuclear instrumentation system (RPN) refurbishment at French CP0-series plants

    International Nuclear Information System (INIS)

    Elsensohn, O.; Fradet, F.; Peron, J.C.; Soubies, B.

    2003-01-01

    In 1996, the utility operating France's nuclear power plants launched feasibility studies for the refurbishment of the nuclear instrumentation system (RPN classed category A) installed in its CPO-series (900 MWe) units. The system was ultimately upgraded with digital I and C system, using a SPINLINE 3 platform. This article describes feedback from an evaluation conducted on the refurbishment by the Institute of Radiological Protection and Nuclear Safety (IRSN), technical support arm of the Directorate General for Nuclear Safety and Radiological Protection (DGSNR). The study begins with a historical overview of the refurbishing operation, then discusses the IRSN assessment method and the lessons learned from this first major revamp of an I and C system in the French nuclear reactor series. Based on its previous experience in evaluating I and C systems for P4/P'4 (1300 MWe) and N4 (1450 MWe) plants and to account for the first-ever aspect of such an upgrade, IRSN partitioned its assessment into four phases. This approach enabled taking into account the impact of RPN refurbishment at every level - system, hardware and qualification, software, operation, onsite requalification, health physics, fire protection and human factors. All six units in the CPO series have now been equipped with the new digital RPN. (authors)

  18. Experience in installing a microprocessor-based protection system on a UK nuclear power plant

    International Nuclear Information System (INIS)

    Jones, C.D.; Smith, I.C.

    1993-01-01

    This paper describes a recently completed project to install a microprocessor-based reactor protection system on a twin reactor station in the United Kingdom. This represented the first application of digital technology as part of such a system in the UK. The background of the application and details of the chosen solution are provided. The experience gained during the installation, commissioning and early operation of the equipment is reviewed by the operators. Interactions between the utility and the regulatory body are outlined and the impact of the regulatory process on the utility's resources and the project timescales are discussed

  19. Radiation protection training for personnel at light-water-cooled nuclear power plants

    International Nuclear Information System (INIS)

    Anon.

    1981-01-01

    Section 19.12 Instructions to Workers, of 10 CFR Part 19, Notices, Instructions, and Reports to Workers; Inspections, requires that individuals be given instruction in radiation protection that is commensurate with the potential radiation protection problems they may encounter in restricted areas as defined in para. 19.3(e) of 10 CFR Part 19. Para. 20.1(c) of 10 CFR Part 20, Standards for Protection Against Radiation, states that occupational radiation exposure should be kept as low as is reasonably achievable (ALARA). Appropriate training is an essential aspect of an ALARA program. This guide describes a radiation protection training program consistent with the ALARA objective and acceptable to the NRC staff for meeting the training requirements of 10 CFR Part 19 with respect to individuals that enter restricted areas at nuclear power plants

  20. Carbon steel protection in G.S. [Girldler sulphide] plants: Pt.9

    International Nuclear Information System (INIS)

    Rojo, Enrique.

    1990-01-01

    In heavy water plants that use the bithermal exchange H 2 S-H 2 O, a protective scale against corrosion is formed by the action of a solution of H 2 S at high temperature for a tile between 10 to 14 days. Exposure to humid air during plant shutdown produces an oxidation of the scale. The reexposure to the H 2 S-H 2 O at low temperature do not regenerate the original properties of the scale. It was concluded that a relative humidity of 50 % was enough to exclude the oxidation for a period of several months. (Author) [es