WorldWideScience

Sample records for system nuclear a

  1. NCIS - a Nuclear Criticality Information System (overview)

    International Nuclear Information System (INIS)

    Koponen, B.L.; Hampel, V.E.

    1983-07-01

    A Nuclear Criticality Information System (NCIS) is being established at the Lawrence Livermore National Laboratory (LLNL) in order to serve personnel responsible for safe storage, transport, and handling of fissile materials and those concerned with the evaluation and analysis of nuclear, critical experiments. Public concern for nuclear safety provides the incentive for improved access to nuclear safety information

  2. A philosophy for space nuclear systems safety

    International Nuclear Information System (INIS)

    Marshall, A.C.

    1992-01-01

    The unique requirements and contraints of space nuclear systems require careful consideration in the development of a safety policy. The Nuclear Safety Policy Working Group (NSPWG) for the Space Exploration Initiative has proposed a hierarchical approach with safety policy at the top of the hierarchy. This policy allows safety requirements to be tailored to specific applications while still providing reassurance to regulators and the general public that the necessary measures have been taken to assure safe application of space nuclear systems. The safety policy used by the NSPWG is recommended for all space nuclear programs and missions

  3. A nuclear power plant system engineering workstation

    International Nuclear Information System (INIS)

    Mason, J.H.; Crosby, J.W.

    1989-01-01

    System engineers offer an approach for effective technical support for operation and maintenance of nuclear power plants. System engineer groups are being set up by most utilities in the United States. Institute of Nuclear Power operations (INPO) and U.S. Nuclear Regulatory Commission (NRC) have endorsed the concept. The INPO Good Practice and a survey of system engineer programs in the southeastern United States provide descriptions of system engineering programs. The purpose of this paper is to describe a process for developing a design for a department-level information network of workstations for system engineering groups. The process includes the following: (1) application of a formal information engineering methodology, (2) analysis of system engineer functions and activities; (3) use of Electric Power Research Institute (EPRI) Plant Information Network (PIN) data; (4) application of the Information Engineering Workbench. The resulting design for this system engineer workstation can provide a reference for design of plant-specific systems

  4. Understanding Nuclear Safety Culture: A Systemic Approach

    International Nuclear Information System (INIS)

    Afghan, A.N.

    2016-01-01

    The Fukushima accident was a systemic failure (Report by Director General IAEA on the Fukushima Daiichi Accident). Systemic failure is a failure at system level unlike the currently understood notion which regards it as the failure of component and equipment. Systemic failures are due to the interdependence, complexity and unpredictability within systems and that is why these systems are called complex adaptive systems (CAS), in which “attractors” play an important role. If we want to understand the systemic failures we need to understand CAS and the role of these attractors. The intent of this paper is to identify some typical attractors (including stakeholders) and their role within complex adaptive system. Attractors can be stakeholders, individuals, processes, rules and regulations, SOPs etc., towards which other agents and individuals are attracted. This paper will try to identify attractors in nuclear safety culture and influence of their assumptions on safety culture behavior by taking examples from nuclear industry in Pakistan. For example, if the nuclear regulator is an attractor within nuclear safety culture CAS then how basic assumptions of nuclear plant operators and shift in-charges about “regulator” affect their own safety behavior?

  5. NCIS: a nuclear criticality information system

    International Nuclear Information System (INIS)

    Koponen, B.L.; Hampel, V.E.

    1984-01-01

    The NCIS is one of the developments carried out to meet the requirements in the field of criticality safety information. Its primary goal is to enhance nuclear criticality safety by dissemination of data, standards, and training material. This paper presents the ''NCIS'' progess since 1950: computer-searching, database management, nuclear critical experiments bibliography. American Nuclear Society transactions criticality safety publications compilation, edition of a personnel directory representing over 140 organizations located in 16 countries and showing a wide range of specialists involved in the field of nuclear criticality safety. The NCIS uses the information management and communication resources of TIS (Technology Information System): automated access procedures; creation of program-dependent information systems; communications. The NCIS is still in a growing, formative stage; it has concentrated first on collecting and organizing the nuclear criticality literature; nuclear critical data, calculational tools, standards, and training materials will follow. Finally the planned and contemplated resources are dealt with: expansion of bibliographic compilations; news database; fundamental criticality safety reference; criticality benchmarck database; user community; training resources; related resources; criticality accident database; dynamic databook; dynamic textbook; expert knowledge system; and, extraction of intelligence

  6. Building a medical system for nuclear facilities

    International Nuclear Information System (INIS)

    Maeda, Mitsuya

    2016-01-01

    To build a medical system for nuclear facilities, I explained what kinds of actions were performed with the TEPCO Fukushima Daiichi Nuclear Power Plant Accident and what kinds of actions are going to be performed in the future. We examined the health and medical care of the emergency workers in nuclear facilities including TEPCO Fukushima Daiichi Nuclear Power Plant from 2014 to 2015 in the Ministry of Health, Labour and Welfare (MHLW). We carried out a detailed hearing from stakeholders of electric companies and medical institutions about the medical system in nuclear facilities carrying out urgent activities. It has been said that the electric company is responsible to maintain the medical system for affected workers in nuclear facilities. However, TEPCO could not find the medical staff, such as doctors, by their own effort at the TEPCO Fukushima Daiichi Nuclear Power Plant Accident. The network of doctors familiar with emergency medical care support dispatched the medical staff after July of 2011. The stakeholders indicated that the following six tasks must be resolved: (1) the fact that no electric company performs the action of bringing up medical staff who can be dispatched into nuclear facilities in emergencies in 2015; (2) bringing up personnel in charge of radiation management and logistics other than the medical staff, such as doctors; (3) cooperation with the community medicine system given the light and shade by nuclear facilities; (4) performing training for the many concurrent wounded based on the scenario of a severe accident; (5) indicating both the condition of the contract and the guarantee of status that is appropriate for dispatched medical staffs; and (6) clarifying the organization of the network of stakeholders. The stakeholders showed the future directionality as follows: (1) To recruit the medical staff expected to be dispatched into nuclear facilities, (2) to carry out the discussion and conveyance training to strengthen cooperation with

  7. A lightning prevention system for nuclear operations

    International Nuclear Information System (INIS)

    Lanzoni, J.A.; Carpenter, R.B.; Tinsley, R.H.

    1994-01-01

    Lightning presents a significant threat to the uninterrupted operation of nuclear power generation facilities. There exists two categories of lightning protection systems-collectors and preventors. Collectors are air terminals, overhead shield wires and other devices designed to collect incoming lightning strikes. Preventors, on the other hand, lower the electrical potential between a thundercloud and ground to a level lower than that required to collect a strike. The Dissipation Array reg-sign Systems prevents lightning strikes from terminating in the protected area, consequently eliminating both the direct hazard and indirect effects of lightning. Over 1,600 Dissipation Array reg-sign Systems are currently in service, with more than 10,500 system-years of operating experience and a historical success rate of over ninety-nine percent. Lightning Eliminators ampersand Consultants has fulfilled 24 contracts for Dissipation Array reg-sign Systems at nuclear power generation facilities

  8. Passive containment system for a nuclear reactor

    International Nuclear Information System (INIS)

    Kleimola, F.W.

    1976-01-01

    A containment system is described that provides complete protection entirely by passive means for the loss of coolant accident in a nuclear power plant and wherein all stored energy released in the coolant blowdown is contained and absorbed while the nuclear fuel is continuously maintained submerged in liquid. The primary containment vessel is restored to a high subatmospheric pressure within a few minutes after accident initiation and the decay heat is safely transferred to the environment while radiolytic hydrogen is contained by passive means

  9. A CAMAC system for nuclear spectroscopy

    International Nuclear Information System (INIS)

    EL Araby, S.M.S.

    1983-01-01

    The thesis describes a computer based multichannel pulse height analyzer for acquiring, processing and displaying random signals coming from a nuclear detector for on - line γ- ray spectroscopy. The system is built around a Pdp - 11/ 04 Computer. Interfacing to the computer is carried out by CAMAC modules. The necessary hard- were required to interface the nuclear detector system to the computer- CAMAC system is developed together with the associated circuits needed to measure the dead time of the whole system. The software has been written Macro,FORTRAN and CATY languages. emphasis was placed on execution speed and it was found that accumulating a large number of data for later processing could improve the execution speed considerably thereby minimizing dead time fast FORTRAN - CAMAC callable subroutine have been developed and used in the software

  10. Nuclear safeguards - a system in transition

    International Nuclear Information System (INIS)

    Carlson, J.

    1999-01-01

    'Classical' safeguards have a strong emphasis on nuclear materials accountancy, and are primarily concerned with verifying nuclear activities as declared by the State - what has been termed the correctness of States' declarations. Following the Gulf War, failure to adequately address the possibility of undeclared nuclear activities - the issue of the completeness of States' declarations - has been recognised as a major shortcoming in the classical safeguards system, and major changes are in progress to strengthen the IAEA's capabilities in this regard. Agreement has been reached on a Model Protocol substantially extending the IAEA's authority, and there has been good progress in developing the new approaches and technologies required to ensure this authority is used effectively. IAEA safeguards are undergoing a major transition, towards greater emphasis on information collection and analysis, diversity of verification methods, incorporation of more qualitative judgments, and improved efficiency. These changes present major challenges to the IAEA and to the international community, but the end result will be a more effective safeguards system

  11. Rodded shutdown system for a nuclear reactor

    International Nuclear Information System (INIS)

    Golden, M.P.; Govi, A.R.

    1978-01-01

    A top mounted nuclear reactor diverse rodded shutdown system utilizing gas fed into a pressure bearing bellows region sealed at the upper extremity to an armature is described. The armature is attached to a neutron absorber assembly by a series of shafts and connecting means. The armature is held in an uppermost position by an electromagnet assembly or by pressurized gas in a second embodiment. Deenergizing the electromagnet assembly, or venting the pressurized gas, causes the armature to fall by the force of gravity, thereby lowering the attached absorber assembly into the reactor core

  12. Fuel transfer system for a nuclear reactor

    International Nuclear Information System (INIS)

    Katz, L.R.; Marshall, J.R.; Desmarchais, W.E.

    1977-01-01

    Disclosed is a fuel transfer system for moving nuclear reactor fuel assemblies from a new fuel storage pit to a containment area containing the nuclear reactor, and for transferring spent fuel assemblies under water from the reactor to a spent fuel storage area. The system includes an underwater track which extends through a wall dividing the fuel building from the reactor containment and a car on the track serves as the vehicle for moving fuel assemblies between these two areas. The car is driven by a motor and linkage extending from an operating deck to a chain belt drive on the car. A housing pivotally mounted at its center on the car is hydraulically actuated to vertically receive a fuel assembly which then is rotated to a horizontal position to permit movement through the wall between the containment and fuel building areas. Return to the vertical position provides for fuel assembly removal and the reverse process is repeated when transferring an assembly in the opposite direction. Limit switches used in controlling operation of the system are designed to be replaced from the operating deck when necessary by tools designed for this purpose. 5 claims, 8 figures

  13. An approach to a self-consistent nuclear energy system

    International Nuclear Information System (INIS)

    Fujii-e, Yoichi; Arie, Kazuo; Endo, Hiroshi

    1992-01-01

    A nuclear energy system should provide a stable supply of energy without endangering the environment or humans. If there is fear about exhausting world energy resources, accumulating radionuclides, and nuclear reactor safety, tension is created in human society. Nuclear energy systems of the future should be able to eliminate fear from people's minds. In other words, the whole system, including the nuclear fuel cycle, should be self-consistent. This is the ultimate goal of nuclear energy. If it can be realized, public acceptance of nuclear energy will increase significantly. In a self-consistent nuclear energy system, misunderstandings between experts on nuclear energy and the public should be minimized. The way to achieve this goal is to explain using simple logic. This paper proposes specific targets for self-consistent nuclear energy systems and shows that the fast breeder reactor (FBR) lies on the route to attaining the final goal

  14. Systems aspects of a space nuclear reactor power system

    Science.gov (United States)

    Jaffe, L.; Fujita, T.; Beatty, R.; Bhandari, P.; Chow, E.; Deininger, W.; Ewell, R.; Grossman, M.; Bloomfield, H.; Heller, J.

    1988-01-01

    Various system aspects of a 300-kW nuclear reactor power system for spacecraft have been investigated. Special attention is given to the cases of a reusable OTV and a space-based radar. It is demonstrated that the stowed length of the power system is important to mission design, and that orbital storage for months to years may be needed for missions involving orbital assembly.

  15. Seismic attenuation system for a nuclear reactor

    Energy Technology Data Exchange (ETDEWEB)

    Liszkai, Tamas; Cadell, Seth

    2018-01-30

    A system for attenuating seismic forces includes a reactor pressure vessel containing nuclear fuel and a containment vessel that houses the reactor pressure vessel. Both the reactor pressure vessel and the containment vessel include a bottom head. Additionally, the system includes a base support to contact a support surface on which the containment vessel is positioned in a substantially vertical orientation. An attenuation device is located between the bottom head of the reactor pressure vessel and the bottom head of the containment vessel. Seismic forces that travel from the base support to the reactor pressure vessel via the containment vessel are attenuated by the attenuation device in a direction that is substantially lateral to the vertical orientation of the containment vessel.

  16. SNAP: a tool for nuclear physical protection system modeling

    International Nuclear Information System (INIS)

    Engi, D.; Grant, F.H. III.

    1979-10-01

    Nuclear safeguards systems are concerned, in part, with the physical protection of nuclear materials. The function of a physical protection system is to define the facility against adversary activities which could lead to theft of nuclear material or sabotage resulting in a radiological release. The Safeguards Network Analysis Procedure (SNAP) provides a convenient and standard analysis methodology for the evaluation of physical protection system analysis. This paper describes a detailed application of SNAP to a hypothetical nuclear facility

  17. Systems aspects of a space nuclear reactor power system

    International Nuclear Information System (INIS)

    Jaffe, L.; Fujita, T.; Beatty, R.

    1988-01-01

    Selected systems aspects of a 300 kW nuclear reactor power system for spacecraft have been studied. The approach included examination of two candidate missions and their associated spacecraft, and a number of special topics dealing with the power system design and operation. The missions considered were a reusable orbital transfer vehicle and a space-based radar. The special topics included: Power system configuration and scaling, launch vehicle integration, operating altitude, orbital storage, start-up, thawing, control, load following, procedures in case of malfunction, restart, thermal and nuclear radiation to other portions of the spacecraft, thermal stresses between subsystems, boom and cable designs, vibration modes, attitude control, reliability, and survivability. Among the findings are that the stowed length of the power system is important to mission design and that orbital storage for months to years may be needed for missions involving orbital assembly

  18. A systems approach to nuclear facility monitoring

    International Nuclear Information System (INIS)

    Argo, P.E.; Doak, J.E.; Howse, J.W.

    1996-01-01

    Sensor technology for use in nuclear facility monitoring has reached an advanced stage of development. Research on where to place these sensors in a facility and how to combine their outputs in a meaningful fashion does not appear to be keeping pace. In this paper, the authors take a global view of the problem where sensor technology is viewed as only one piece of a large puzzle. Other pieces of this puzzle include the optimal location and type of sensors used in a specific facility, the rate at which sensors record information, and the risk associated with the materials/processes at a facility. If the data are analyzed off-site, how will they be transmitted? Is real-time analysis necessary? Is one monitoring only the facility itself, or might one also monitor the processing that occurs there (e.g., tank levels and concentrations)? How is one going to combine the outputs from the various sensors to give us an accurate picture of the state of the facility? This paper will not try to answer all these questions, but rather it will attempt to stimulate thought in this area by formulating a systems approach to the problem demonstrated by a prototype system and a system proposed for an actual facility. The focus will be on the data analysis aspect of the problem. Future work in this area should focus on recommendations and guidelines for a monitoring system based upon the type of facility and processing that occurs there

  19. Cooling system for auxiliary systems of a nuclear power plant

    International Nuclear Information System (INIS)

    Maerker, W.; Mueller, K.; Roller, W.

    1981-01-01

    From the reactor auxiliary and ancillary systems of a nuclear facility heat has to be removed without the hazard arising that radioactive liquids or gases may escape from the safe area of the nuclear facility. A cooling system is described allowing at every moment to make available cooling fluid at a temperature sufficiently low for heat exchangers to be able to remove the heat from such auxiliary systems without needing fresh water supply or water reservoirs. For this purpose a dry cooling tower is connected in series with a heat exchanger that is cooled on the secondary side by means of a refrigerating machine. The cooling pipes are filled with a nonfreezable fluid. By means of a bypass a minimum temperature is guaranteed at cold weather. (orig.) [de

  20. A system approach to nuclear facility monitoring

    Energy Technology Data Exchange (ETDEWEB)

    Argo, P.E.; Doak, J.E.; Howse, J.W.

    1996-09-01

    Sensor technology for use in nuclear facility monitoring has reached and advanced stage of development. Research on where to place these sensors in a facility and how to combine their outputs in a meaningful fashion does not appear to be keeping pace. In this paper, we take a global view of the problem where sensor technology is viewed as only one piece of a large puzzle. Other pieces of this puzzle include the optimal location and type of sensors used in a specific facility, the rate at which sensors record information, and the risk associated with the materials/processes at a facility. If the data are analyzed off-site, how will they be transmitted? Is real-time analysis necessary? Are we monitoring only the facility itself, or might we also monitor the processing that occurs there? How are we going to combine the output from the various sensors to give us an accurate picture of the state of the facility? This paper will not try to answer all these questions, but rather it will attempt to stimulate thought in this area by formulating a systems approach to the problem demonstrated by a prototype system and a systems proposed for an actual facility. Our focus will be on the data analysis aspect of the problem.

  1. Approach for Establishing a National Nuclear Forensics System

    International Nuclear Information System (INIS)

    Kim, Jaekwang; Hyung, Sangcheol

    2014-01-01

    The increasing number could give rise to posing a potential threat to national infrastructure which is very vulnerable to radiological sabotage with the materials. International community has been emphasizing the importance of nuclear forensics through the Nuclear Security Summit process as a countermeasure against nuclear terrorism. Global Initiative to Combat Nuclear Terrorism(GICNT) and nuclear forensics International Technology Working Group(ITWG) suggest the establishment of national nuclear forensics system which has a law enforcement for forensic management and maintenance of nuclear forensics database including nuclear material and other radioactive materials. We suggest the legal and institutional system through this paper in an effort to set up a multi expert group and the nuclear forensics DB which can contribute to effective Core capabilities

  2. Approach for Establishing a National Nuclear Forensics System

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Jaekwang; Hyung, Sangcheol [Korea Institute of Nuclear Nonproliferation and Control, Daejeon (Korea, Republic of)

    2014-05-15

    The increasing number could give rise to posing a potential threat to national infrastructure which is very vulnerable to radiological sabotage with the materials. International community has been emphasizing the importance of nuclear forensics through the Nuclear Security Summit process as a countermeasure against nuclear terrorism. Global Initiative to Combat Nuclear Terrorism(GICNT) and nuclear forensics International Technology Working Group(ITWG) suggest the establishment of national nuclear forensics system which has a law enforcement for forensic management and maintenance of nuclear forensics database including nuclear material and other radioactive materials. We suggest the legal and institutional system through this paper in an effort to set up a multi expert group and the nuclear forensics DB which can contribute to effective Core capabilities.

  3. The national nuclear material tracking system. A Korea's countermeasure against nuclear terrorism

    International Nuclear Information System (INIS)

    Moon, Joo Hyun

    2011-01-01

    Since nuclear terrorism has been identified as a real threat, the Korean government has earnestly developed elementary technologies and sub-systems for establishing an integrated defensive system against nuclear terrorism, which is based on the concept of defense-in-depth. This paper introduces the gist and implications of the studies that have been conducted in building the national nuclear material tracking system for preventing and intercepting the illicit trafficking and transporting of nuclear material in Korea. (orig.)

  4. The national nuclear material tracking system. A Korea's countermeasure against nuclear terrorism

    Energy Technology Data Exchange (ETDEWEB)

    Moon, Joo Hyun [Dongguk Univ., Gyeongbuk (Korea, Republic of)

    2011-07-15

    Since nuclear terrorism has been identified as a real threat, the Korean government has earnestly developed elementary technologies and sub-systems for establishing an integrated defensive system against nuclear terrorism, which is based on the concept of defense-in-depth. This paper introduces the gist and implications of the studies that have been conducted in building the national nuclear material tracking system for preventing and intercepting the illicit trafficking and transporting of nuclear material in Korea. (orig.)

  5. A study on LAN applications in nuclear safety systems

    International Nuclear Information System (INIS)

    Kim, Sung; Lee, Young Ryul; Koo, Jun Mo; Han, Jai Bok

    1995-01-01

    It is a general tendency to digitalize the conventional relay based I and C systems in nuclear power plant. But, the digitalisation of nuclear safety systems has many a difficulty to surmount. The typical one thing of many difficulties is the data communication problem between local controllers and systems. The network architecture built with LAN (Local Area Network) in digital systems of the other industries are general. But in case of nuclear safety systems many considerations in point of safety and license are required to implement it in the field. In this parer, some considerations for applying LAN in nuclear safety systems were reviewed

  6. The double nuclear system is a new object of nuclear physics studies

    International Nuclear Information System (INIS)

    Volkov, V.V.

    1980-01-01

    Deep inelastic collisions of two complex nuclei result in formation of the specific nuclear complex - a double nuclear system which is a new unit of nuclear microworld. In this paper we consider the conditions under which the double nuclear system is formed, its properties, the statistical regularities of its disintegration, and the nuclear shell structure effect on its evolution. The possibility of using deep inelastic transfer reactions to produce nuclear far from the region of β-stability and nuclei with high angular momentum is discussed. (author)

  7. A study on expert system applications for nuclear power plant

    International Nuclear Information System (INIS)

    Huh, Young Hwan; Kim, Yeong Jin; Park, Nam Seog; Dong, In Sook; Choi, In Seon

    1987-12-01

    The application of artificial intelligence techniques to nuclear power plants such as expert systems is rapidly emerging. expert systems can contribute significantly to the availability and the improved operation and safety of nuclear power plants. The objective of the project is to develop an expert system in a selected application area in the nuclear power plants. This project will last for 3 years. The first year's tasks are: - Information collection and literature survey on expert systems. - Analysis of several applicable areas for applying AI technologies to the nuclear power plants. - Conceptual design of a few selected domains. - Selection of hardware and software tools for the development of the expert system

  8. A Roadmap of Innovative Nuclear Energy System

    Science.gov (United States)

    Sekimoto, Hiroshi

    2017-01-01

    Nuclear is a dense energy without CO2 emission. It can be used for more than 100,000 years using fast breeder reactors with uranium from the sea. However, it raises difficult problems associated with severe accidents, spent fuel waste and nuclear threats, which should be solved with acceptable costs. Some innovative reactors have attracted interest, and many designs have been proposed for small reactors. These reactors are considered much safer than conventional large reactors and have fewer technical obstructions. Breed-and-burn reactors have high potential to solve all inherent problems for peaceful use of nuclear energy. However, they have some technical problems with materials. A roadmap for innovative reactors is presented herein.

  9. A remote maintenance robot system for a pulsed nuclear reactor

    International Nuclear Information System (INIS)

    Thunborg, S.

    1987-01-01

    This paper presents a remote maintenance robot system for use in a hazardous environment. The system consists of turntable, robot and hoist subsystems which operate under the control of a supervisory computer to perform coordinated programmed maintenance operations on a pulsed nuclear reactor. The system is operational

  10. Automatic motion inhibit system for a nuclear power generating system

    International Nuclear Information System (INIS)

    Musick, C.R.; Torres, J.M.

    1977-01-01

    Disclosed is an automatic motion inhibit system for a nuclear power generating system for inhibiting automatic motion of the control elements to reduce reactor power in response to a turbine load reduction. The system generates a final reactor power level setpoint signal which is continuously compared with a reactor power signal. The final reactor power level setpoint is a setpoint within the capacity of the bypass valves to bypass steam which in no event is lower in value than the lower limit of automatic control of the reactor. If the final reactor power level setpoint is greater than the reactor power, an inhibit signal is generated to inhibit automatic control of the reactor. 6 claims, 5 figures

  11. Nuclear Fuel Cycle Information System. A directory of nuclear fuel cycle facilities. 2009 ed

    International Nuclear Information System (INIS)

    2009-04-01

    The Nuclear Fuel Cycle Information System (NFCIS) is an international directory of civilian nuclear fuel cycle facilities, published online as part of the Integrated Nuclear Fuel Cycle Information System (iNFCIS: http://www-nfcis.iaea.org/). This is the fourth hardcopy publication in almost 30 years and it represents a snapshot of the NFCIS database as of the end of 2008. Together with the attached CD-ROM, it provides information on 650 civilian nuclear fuel cycle facilities in 53 countries, thus helping to improve the transparency of global nuclear fuel cycle activities

  12. A prototype nuclear emergency response decision making expert system

    International Nuclear Information System (INIS)

    Chang, C.; Shih, C.; Hong, M.; Yu, W.; Su, M.; Wang, S.

    1990-01-01

    A prototype of emergency response expert system developed for nuclear power plants, has been fulfilled by Institute of Nuclear Energy Research. Key elements that have been implemented for emergency response include radioactive material dispersion assessment, dynamic transportation evacuation assessment, and meteorological parametric forecasting. A network system consists of five 80386 Personal Computers (PCs) has been installed to perform the system functions above. A further project is still continuing to achieve a more complicated and fanciful computer aid integral emergency response expert system

  13. Human as a component of a nuclear material safeguard system

    International Nuclear Information System (INIS)

    Morgan, D.E.; Schechter, R.S.

    1978-01-01

    Many human vigilance experiments are summarized and principles are extracted which should be useful in designing and evaluating a nuclear material safeguard system. A human is a poor observer and is not a dependable part of any man-machine system when required to function as an observer. There are a few techniques which improve his performance by providing feedback. A conceptual model is presented which is helpful in design and evaluation of systems. There is some slight experimental support for the model. Finally, some techniques of time study and statistical control charting will be useful as a means of detecting nuclear diversion attempts

  14. Simulation of a Nuclear Steam Supply System (NSSS) of a PWR nuclear power plant

    International Nuclear Information System (INIS)

    Reis Martins Junior, L.L. dos.

    1980-01-01

    The following work intends to perform the digital simulation, of the Nuclear Steam Supply System (NSSS) of a PWR nuclear power plant for control systems design and analysis purposes. There are mathematical models for the reactor, the steam generator, the pressurizer and for transport lags of the coolant in the primary circuit. Nevertheless no one control system has been considered to permit any user the inclusion in the more convenient way of the desired control systems' models. The characteristics of the system in consideration are fundamentally equal to the ones of Almirante Alvaro Alberto Nuclear Power Plant, Unit I (Angra I) obtained in the Final Safety Analysis Report at Comissao Nacional de Energia Nuclear. (author)

  15. A Nuclear Scale System Based on LabVIEW

    International Nuclear Information System (INIS)

    Liu Shixing; Gu Qindong

    2009-01-01

    Nuclear mass scales measure the weight of materials which absorb and attenuate the nuclear radiation when the low energy γ-ray through it and is a non-contact continuous measurement device with simple structure and reliable operation. LabVIEW as a graphical programming language is a standard data acquisition and instrument control software. Based on the principle of nuclear mass scale measuring system, monitoring software for nuclear scale system is designed using LabVIEW programming environment. Software architecture mainly composed of three basic modules which include the monitoring software, databases and Web services. It achieves measurement data acquisition, status monitoring, and data management and has networking functions. (authors)

  16. Development of a 1200 fine group nuclear data library for advanced nuclear systems

    Institute of Scientific and Technical Information of China (English)

    Jun Zou; Lei-Ming Shang; Fang Wang; Li-Juan Hao

    2017-01-01

    Accurate and reliable nuclear data libraries are essential for calculation and design of advanced nuclear systems.A 1200 fine group nuclear data library Hybrid Evaluated Nuclear Data Library/Fine Group (HENDL/FG) with neutrons of up to 150 MeV has been developed to improve the accuracy of neutronics calculations and analysis.Corrections of Doppler,resonance self-shielding,and thermal upscatter effects were done for HENDL/FG.Shielding and critical safety benchmarks were performed to test the accuracy and reliability of the library.The discrepancy between calculated and measured nuclear parameters fell into a reasonable range.

  17. Thermal coupling system analysis of a nuclear desalination plant

    International Nuclear Information System (INIS)

    Adak, A.K.; Srivastava, V.K.; Tewari, P.K.

    2010-01-01

    When a nuclear reactor is used to supply steam for desalination plant, the method of coupling has a significant technical and economic impact. The exact method of coupling depends upon the type of reactor and type of desalination plant. As a part of Nuclear Desalination Demonstration Project (NDDP), BARC has successfully commissioned a 4500 m 3 /day MSF desalination plant coupled to Madras Atomic Power Station (MAPS) at Kalpakkam. Desalination plant coupled to nuclear power plant of Pressurized Heavy Water Reactor (PHWR) type is a good example of dual-purpose nuclear desalination plant. This paper presents the thermal coupling system analysis of this plant along with technical and safety aspects. (author)

  18. Feedwater system in a nuclear power plant

    International Nuclear Information System (INIS)

    Shimizu, Tadayuki.

    1975-01-01

    Object: To improve the control property of a steam turbine for a feedwater pump and plant operation characteristics where water is supplied at a low rate. Structure: In a nuclear power plant where feedwater pumps of the reactor are driven by a steam turbine, the main feedwater duct on the discharge side of the feedwater pumps is provided with a cut-off valve and is connected parallel with a bypass duct having a pressure compensated flow control valve. With this arrangement, at the time when the rate of feedwater is high the cut-off valve is open so that water supplied from the feedwater pumps driven by the steam turbine is supplied through the main feedwater duct to the reactor while in case when the rate of feedwater is low the flow control valve is opened to let the water be supplied through the bypass duct. (Kamimura, M.)

  19. Nuclear data processing using a database management system

    International Nuclear Information System (INIS)

    Castilla, V.; Gonzalez, L.

    1991-01-01

    A database management system that permits the design of relational models was used to create an integrated database with experimental and evaluated nuclear data.A system that reduces the time and cost of processing was created for computers type EC or compatibles.A set of programs for the conversion from nuclear calculated data output format to EXFOR format was developed.A dictionary to perform a retrospective search in the ENDF database was created too

  20. Coolant cleanup system for a nuclear reactor

    International Nuclear Information System (INIS)

    Shiina, Atsushi; Usui, Naoshi; Yamamoto, Michiyoshi; Osumi, Katsumi.

    1983-01-01

    Purpose: To maintain the electric conductivity of reactor water lower and to minimize the heat loss in the cleanup system by providing a low temperature cleanup system and a high temperature cleanup system together. Constitution: A low temperature cleanup system using ion exchange resins as filter aids and a high temperature cleanup system using inorganic ion exchange materials as filter aids are provided in combination. A part of the reactor water in a reactor pressure vessel is passed through a conductivity meter, one portion of which flows into the high temperature cleanup system having no heat exchanger and filled with inorganic ion exchange materials by way of a first flow rate control valve and the other portion of which flows into the low temperature cleanup system having heat exchangers and filled with the ion exchange materials by way of a second control valve. The first control valve is adjusted so as to flow, for example, about more than 15% of the feedwater flow rate to the high temperature cleanup system and the second control valve is adjusted with its valve opening degree depending on the indication of the conductivity meter so as to flow about 2 - 7 % of the feedwater flow rate into the low temperature cleanup system, to thereby control the electric conductivity to between 0.055 - 0.3 μS/cm. (Moriyama, K.)

  1. Basic components of a national control system for nuclear materials

    International Nuclear Information System (INIS)

    Rabot, G.

    1986-01-01

    The paper presents the different aspects related to the organization and the functioning of a national control and accounting system for nuclear materials. The legal aspects and the relations with the IAEA are included

  2. Outline of a computerized nuclear material accounting system applicable to nuclear power reactors

    International Nuclear Information System (INIS)

    Handshuh, J.W.

    1975-01-01

    A computerized nuclear material accounting system is described which enables a utility to account for its material throughout the entire fuel cycle. From input of transactions, the system records and reports inventories and transactions by accounts which the user may establish for discrete locations, item control areas, further subdivisions, and material types. Account numbers are designed so that accounts and records are automatically sorted in the order desired. The system also generates the Material Status Reports for the Nuclear Regulatory Commission

  3. Nuclear information access system

    International Nuclear Information System (INIS)

    Ham, C. H.; Yang, M. H.; Yoon, S. W.

    1998-01-01

    The energy supply in the countries, which have abundant energy resources, may not be affected by accepting the assertion of anti-nuclear and environment groups. Anti-nuclear movements in the countries which have little energy resources may cause serious problem in securing energy supply. Especially, it is distinct in Korea because she heavily depends on nuclear energy in electricity supply(nuclear share in total electricity supply is about 40%).The cause of social trouble surrounding nuclear energy is being involved with various circumstances. However, it is very important that we are not aware of the importance of information access and prepared for such a situation from the early stage of nuclear energy's development. In those matter, this paper analyzes the contents of nuclear information access system in France and Japan which have dynamic nuclear development program and presents the direction of the nuclear access regime through comparing Korean status and referring to progresses of the regime

  4. A portable system for nuclear, chemical agent, and explosives identification

    International Nuclear Information System (INIS)

    Parker, W.E.; Buckley, W.M.; Kreek, S.A.; Mauger, G.J.; Lavietes, A.D.; Dougan, A.D.; Caffrey, A.J.

    2001-01-01

    The FRIS/PINS hybrid integrates the LLNL-developed Field Radionuclide Identification System (FRIS) with the INEEL-developed Portable Isotopic Neutron Spectroscopy (PINS) chemical assay system to yield a combined general radioisotope, special nuclear material, and chemical weapons/explosives detection and identification system. The PINS system uses a neutron source and a high-purity germanium γ-ray detector. The FRIS system uses an electromechanically cooled germanium detector and its own analysis software to detect and identify special nuclear material and other radioisotopes. The FRIS/PINS combined system also uses the electromechanically-cooled germanium detector. There is no other currently available integrated technology that can combine a prompt-gamma neutron-activation analysis capability for CWE with a passive radioisotope measurement and identification capability for special nuclear material

  5. A Portable System for Nuclear, Chemical Agent and Explosives Identification

    International Nuclear Information System (INIS)

    Parker, W.E.; Buckley, W.M.; Kreek, S.A.; Caffrey, A.J.; Mauger, G.J.; Lavietes, A.D.; Dougan, A.D.

    2000-01-01

    The FRIS/PINS hybrid integrates the LLNL-developed Field Radionuclide Identification System (FRIS) with the INEEL-developed Portable Isotopic Neutron Spectroscopy (PINS) chemical assay system to yield a combined general radioisotope, special nuclear material, and chemical weapons/explosives detection and identification system. The PINS system uses a neutron source and a high-purity germanium γ-ray detector. The FRIS system uses an electrochemically cooled germanium detector and its own analysis software to detect and identify special nuclear material and other radioisotopes. The FRIS/PINS combined system also uses the electromechanically-cooled germanium detector. There is no other currently available integrated technology that can combine an active neutron interrogation and analysis capability for CWE with a passive radioisotope measurement and identification capability for special nuclear material

  6. A method of short range system analysis for nuclear utilities

    International Nuclear Information System (INIS)

    Eng, R.; Mason, E.A.; Benedict, M.

    1976-01-01

    An optimization procedure has been formulated and tested that is capable of solving for the optimal generation schedule of several nuclear power reactors in an electric power utility system, under short-range, resource-limited, conditions. The optimization procedure utilizes a new concept called the Opportunity Cost of Nuclear Power (OCNP) to optimally assign the resource-limited nuclear energy to the different weeks and hours in the short-range planning horizon. OCNP is defined as the cost of displaced energy when optimally distributed nuclear energy is marginally increased. Under resource-limited conditions, the short-range 'value' of nuclear power to a utility system is not its actual generation cost, but the cost of the next best alternative supply of energy, the OCNP. OCNP is a function of a week's system reserve capacity, the system's economic loading order, the customer demand function, and the nature of the available utility system generating units. The optimized OCNP value of the short-range planning period represents the utility's short-range energy replacement cost incurred when selling nuclear energy to a neighbouring utility. (author)

  7. Development of a quality management system for Brazilian nuclear installations

    International Nuclear Information System (INIS)

    Kibrit, Eduardo; Zouain, Desiree Moraes

    2005-01-01

    The present work is a proposal for developing a quality management system for Brazilian nuclear installations, based on applicable standards. The standard ISO 9001:2000 [4] establishes general requirements for the implementation of a quality management system in all kinds of organizations. The standard IAEA 50-C/SG-Q [1] establishes general requirements for the implementation of a quality assurance system in nuclear installations. The standard CNEN-NN- 1.16 [5] establishes the regulating requirements for the quality assurance systems and programs of nuclear installations, for licensing and authorization for operation of these installations in Brazil. The revision of standard IAEA 50-C/SG-Q [1], to be replaced by IAEA DS 338 [2] and IAEA DPP 349 [3], introduces the concept of 'Integrated Management System' for the nuclear area, in preference to the concept of 'Quality Assurance'. This approach is incorporated with the current tendency, because it guides the system to manage, in an integrated way, the requirements of quality, safety, health, environment, security and economics of the installation. The results of the characterization of the quality management systems established in the applicable standards are presented, with the determination of the common and conflicting points among them. Referring data to quality assurance program/quality management system in some nuclear installations of IAEA Member States are also presented. (author)

  8. A novel nuclear-powered propulsion system for ship

    International Nuclear Information System (INIS)

    Liu Tao; Han Weishi

    2003-01-01

    A novel nuclear-powered propulsion system for ship is presented in this paper. In this system, a minitype liquid sodium-cooled reactor is used as power; alkali-metal thermal-to-electric conversion (AMTEC) cells are utilized to transform the heat energy to electric energy and superconducting magneto-hydrodynamic (MHD) work as propulsion. This nuclear-powered propulsion system has great advantages in low noise, high speed, long survivability and simple manipulation. It has great significance for the development of propulsion system. (author)

  9. A mobile gamma ray spectrometer system for nuclear hazard mapping

    CERN Document Server

    Smethurst, M A

    2000-01-01

    The Geological Survey of Norway has developed a system for mobile gamma ray spectrometer surveying suitable for use in nuclear emergencies where potentially dangerous radioactive materials have been released into the environment. The measuring system has been designed for use with different kinds of transportation platforms. These include fixed-wing aircraft, helicopters and vans. The choice of transportation platform depends on the nature of the nuclear emergency. Widespread fallout from a distant source can be mapped quickly from the air while local sources of radiation can be delineated by a car-borne system. The measuring system processes gamma ray spectra in real time. The operator of the system is therefore able to guide surveying in accordance with meaningful data values and immediately report these values to decision making The operator is presented with a number of different displays suited to different kinds of nuclear emergencies that lead to more efficient surveying. Real time processing of data m...

  10. A future vision of nuclear material information systems

    International Nuclear Information System (INIS)

    Suski, N.; Wimple, C.

    1999-01-01

    To address the current and future needs for nuclear materials management and safeguards information, Lawrence Livermore National Laboratory envisions an integrated nuclear information system that will support several functions. The vision is to link distributed information systems via a common communications infrastructure designed to address the information interdependencies between two major elements: Domestic, with information about specific nuclear materials and their properties, and International, with information pertaining to foreign nuclear materials, facility design and operations. The communication infrastructure will enable data consistency, validation and reconciliation, as well as provide a common access point and user interface for a broad range of nuclear materials information. Information may be transmitted to, from, and within the system by a variety of linkage mechanisms, including the Internet. Strict access control will be employed as well as data encryption and user authentication to provide the necessary information assurance. The system can provide a mechanism not only for data storage and retrieval, but will eventually provide the analytical tools necessary to support the U.S. government's nuclear materials management needs and non-proliferation policy goals

  11. Data bank applications of a nuclear medical computer system

    International Nuclear Information System (INIS)

    Hale, T.I.; Jucker, A.; Haering, W.; Schmid, B.

    1980-01-01

    Computer systems in nuclear medicine are normally not used for data bank applications. A concept for a PDP-11-34 with RK 05 disc is presented, which serves the needs of data manipulations of a medium sized hospital including management of patient data, pharma stock control etc. besides specific use for nuclear medical work with absolute priority. The program is available upon request. (orig.) [de

  12. Future nuclear systems technology

    International Nuclear Information System (INIS)

    Brooks, H.

    1979-01-01

    Five directions can be identified for evolution of nuclear systems, possibly a sixth. These are, first, and perhaps most important, toward a means of extending fissile resources through improvement of the efficiency of their use; second, improvements in nuclear safety; third, reduction in the environmental impacts of nuclear electric power generation, particularly water requirements; fourth, improvements in proliferation resistance of the nuclear fuel cycle; and fifth, improvements in economics. And added in a sixth, and somewhat more speculative direction, the use of nuclear power for purposes other than the direct generation of electricity

  13. A nuclear data acquisition system flow control model

    International Nuclear Information System (INIS)

    Hack, S.N.

    1988-01-01

    A general Petri Net representation of a nuclear data acquisition system model is presented. This model provides for the unique requirements of a nuclear data acquisition system including the capabilities of concurrently acquiring asynchronous and synchronous data, of providing multiple priority levels of flow control arbitration, and of permitting multiple input sources to reside at the same priority without the problem of channel lockout caused by a high rate data source. Finally, a previously implemented gamma camera/physiological signal data acquisition system is described using the models presented

  14. Power conditioning system for a nuclear reactor

    International Nuclear Information System (INIS)

    Higashigawa, Yuichi; Joge, Toshio.

    1981-01-01

    Purpose: To provide a power conditioning system for a BWR type reactor which has a function to be automatically operated within a range that the relationship between the heat power of the reactor and the electric power of an electric generator does not lose the safety of fuel by eliminating the unnecessary fluctuation of the power of the reactor. Constitution: A load request error signal fed from a conventional turbine control system to recirculation flow regulator is eliminated, and a reactor power conditioning system is newly provided, to which an electric generator power signal, a reactor average power area monitor signal and a load request signal are inputted. Thus, the load request signal is compared directly with the electric power of the electric generator, the recirculation flow rate is controlled by the compared result, and whether the correlation between the heat power of the reqctor and the electric power of the generator satisfies the correlation determined to prove the safety of fuel or not is checked. If this correlation is satisfied, the recirculation flow rate is merely automatically controlled. (Yoshino, Y.)

  15. Valve arrangement for a nuclear plant residual heat removal system

    International Nuclear Information System (INIS)

    Fidler, G.L.; Hill, R.A.; Carrera, J.P.

    1978-01-01

    Disclosed is an improved valve arrangement for a two-train Residual Heat Removal System (RHRS) of a nuclear reactor plant which ensures operational integrity of the system under single failure circumstances including loss of one of two electrical power sources

  16. A radiation monitoring system for nuclear power plants

    International Nuclear Information System (INIS)

    Iwai, Masaru; Nakamori, S.; Ikeda, H.; Oda, M.

    1974-01-01

    Safety with respect to radiation is vital factor, particularly in view of the increasing number of nuclear power plants. For this purpose, a radiation monitoring system is provided to perform constant supervision. This article describes the purpose, installation location, specifications and circuitry of a system which is divided into three units: the process monitor, area monitor and off-site monitor. (auth.)

  17. Green technology into nuclear industry Eligibility of Ambidexter nuclear complex for a generation IV nuclear power system

    International Nuclear Information System (INIS)

    Park, Kwangheon; Koh, Moosung; Ryu, Jeongdong; Kim, Yangeun; Lee, Bumsik; Park, Hyuntack

    2000-01-01

    Green power is being developed up to a point that is feasible not only in an environmental sense, but also in an economical viewpoint. This paper introduces two case studies that applied green technology into nuclear industry. 1) Nuclear laundry: A laundry machine that uses liquid and supercritical Co 2 as a solvent for decontamination of contaminated working dresses in nuclear power plants was developed. The machine consists of a 16 liter reactor, a recovery system with compressors, and storage tanks. All CO 2 used in cleaning is fully recovered and reused in next cleaning, resulting in no production

  18. Pressure suppression system for a nuclear reactor

    International Nuclear Information System (INIS)

    Jost, N.

    1977-01-01

    The invention pertains to a pressure suppression system for PWR reactors where the parts enclosing the primary coolant are contained in two pressure-tight separate chambers. According to the invention, these chambers are partly filled with water and are connected with each other below the water surface. This way, gases cannot escape from the containment, not even if a valve and a line are damaged at the same time, as the vapours released condensate in the water of at least one of the other chambers. (HP) [de

  19. Supplier quality assurance systems: a study in the nuclear industry

    International Nuclear Information System (INIS)

    Singer, A.J.; Churchill, G.F.; Dale, B.G.

    1988-01-01

    The results are reported of a study which investigated the impact of quality assurance on 13 suppliers to the nuclear industry. The purpose of the study was to determine the benefits and problems of applying quality assurance in the supply of high risk plant items and material for nuclear installations. The paper discusses the problems facing the industry including: multiple audits and inspections, the irritation with having to contend with two quality system standards (namely BS 5750 and BS 5882) and the cost effectiveness of the more stringent quality system and quality control surveillance requirements imposed by the nuclear industry. It is also pointed out that companies supplying non-nuclear industrial customers were dissatisfied with the qualifications, experience and professional competence of some auditors and many inspectors. (author)

  20. Refueling system for a nuclear reactor

    International Nuclear Information System (INIS)

    Koschkin, J.N.; Ordynskij, G.V.; Schchijan, C.G.; Schapkin, A.F.; Fadeev, A.I.; Laptev, F.V.; Batjukov, V.I.; Korolkov, K.I.; Borodin, I.V.; Tschernomordik, E.N.

    1979-01-01

    With the refueling system fuel elements are transferred from the intermediate distributing chamber within the fast breeder reactor vessel to the storage tanks for new and irradiated fuel elements outside of the reactor vessel and vice versa. It consists of a hermetic chamber, filled with inert gas, within which the refueling machine, having got a vertical swing pipe, is placed. On the swing pipe there is mounted by means of a bracket a hanging support tube for a tube manipulator that can be moved over the openings to the fuel elements. At the end of the tube manipulator there is a gripping device whose drive mechanism is arranged within the support tube. The swing pipe is moved by means of a drive mechanism outside of the chamber. (DG) [de

  1. System for cooling the containment vessel of a nuclear reactor

    International Nuclear Information System (INIS)

    Costes, Didier.

    1982-01-01

    The invention concerns a post-accidental cooling system for a nuclear reactor containment vessel. This system includes in series a turbine fed by the moist air contained in the vessel, a condenser in which the air is dried and cooled, a compressor actuated by the turbine and a cooling exchanger. The cold water flowing through the condenser and in the exchanger is taken from a tank outside the vessel and injected by a pump actuated by the turbine. The application is for nuclear reactors under pressure [fr

  2. Electrical cabling system associated at a nuclear reactor

    International Nuclear Information System (INIS)

    Dejeux, P.; Desfontaines, G.

    1988-01-01

    This cabling system for an electrical device in a nuclear reactor comprises at least a first cable issued of the device, a second cable comprising a first portion, a second portion and a third portion joining the second by a multiple quick fitting connector capable to connect at least ten second portions at ten other third portions of the second cable [fr

  3. Sustainable minireactors: A framework for decentralized nuclear energy systems

    International Nuclear Information System (INIS)

    Harms, A.A.; Sassin, W.W.

    1983-01-01

    The concept of a nuclear energy system consisting of numerous small, specialized nuclear reactors providing heat or electricity for localized/regional purposes is considered. It is envisaged that a ''parent'' nuclear facility would sustain the fuel needs of many small nuclear energy ''satellites'' and possibly provide other fuel-management services. The choice of fuel cycle and the operational features of these satellites may be determined by the form of energy required, public and social preferences, and institutional factors. Three distinct classes of distributed systems, each based on extensions of existing nuclear technology, are identified and discussed. In addition to the points emphasized concerning the types of minireactors and the fuel cycles chosen, it is important to recognize the potential for mass-production of these smaller facilities. Also, if the fuel-consuming part of the system is widely distributed geographically and if the fuel can be stored, the simultaneous failure of substantial parts of the energy supply system seems unlikely. Finally, if there were a local need for medium-power facilities, provision for the stacking of minireactors to attain a specified power level could be introduced

  4. Nuclear employee data system (NEDS), a pilot project

    International Nuclear Information System (INIS)

    Britz, W.L.

    1984-01-01

    This paper describes a pilot project being funded by six east coast nuclear utilities: the Nuclear Employee Data System (NEDS). The NEDS is to be a customized computer-based information management system that will receive, update, and maintain in-processing information among the NEDS participating utilities. A comprehensive set of data requirements has been preliminarily identified and characterized into areas of: personal information, security information, health physics information, respiratory protective equipment information, medical information, and training information. The NEDS is expected to become operational next summer

  5. Towards a new system of accounting of nuclear material

    International Nuclear Information System (INIS)

    Maceiras, Elena; Fernandez Moreno, Sonia; Castro, Laura B.; Saavedra, Analia D.; Mairal, M.L.; Valentino, Lucia I.; Vicens, Hugo E.; Llacer, Carlos D.

    1999-01-01

    The Nuclear Regulatory Authority (NRA) of Argentina has, among other functions, to ensure the fulfilment of national nuclear regulatory standards and all international safeguards commitments assumed by Argentina, particularly those related to the accounting and control of nuclear materials. To fulfil this responsibility, national inspections and audits of the operator's accounting and measurement systems are carried out, generating a great deal of data to be processed and evaluated. To manage this information in an efficient way, the RNA has implemented a control system composed by three database: SCMN, SIS and SOP, which interact amongst them. The objectives and functions of this integrated system and the achieved results to date are described in the present paper. (author)

  6. A nuclear source term analysis for spacecraft power systems

    International Nuclear Information System (INIS)

    McCulloch, W.H.

    1998-01-01

    All US space missions involving on board nuclear material must be approved by the Office of the President. To be approved the mission and the hardware systems must undergo evaluations of the associated nuclear health and safety risk. One part of these evaluations is the characterization of the source terms, i.e., the estimate of the amount, physical form, and location of nuclear material, which might be released into the environment in the event of credible accidents. This paper presents a brief overview of the source term analysis by the Interagency Nuclear Safety Review Panel for the NASA Cassini Space Mission launched in October 1997. Included is a description of the Energy Interaction Model, an innovative approach to the analysis of potential releases from high velocity impacts resulting from launch aborts and reentries

  7. NUClear: A Loosely Coupled Software Architecture for Humanoid Robot Systems

    Directory of Open Access Journals (Sweden)

    Trent eHouliston

    2016-04-01

    Full Text Available This paper discusses the design and interface of NUClear, a new hybrid message-passing architecture for embodied humanoid robotics. NUClear is modular, low latency and promotes functional and expandable software design. It greatly reduces the latency for messages passed between modules as the messages routes are established at compile time. It also reduces the number of functions that must be written using a system called co-messages which aids in dealing with multiple simultaneous data. NUClear has primarily been evaluated on a humanoid robotic soccer platform and on a robotic boat platform, with evaluations showing that NUClear requires fewer callbacks and cache variables over existing message-passing architectures. NUClear does have limitations when applying these techniques on multi-processed systems. It performs best in lower power systems where computational resources are limited. Future work will focus on applying the architecture to new platforms, including a larger form humanoid platform and a virtual reality platform and further evaluating the impact of the novel techniques introduced.

  8. Development for a multi-purpose nuclear energy supply system

    International Nuclear Information System (INIS)

    Narabayashi, Tadashi; Shimazu, Yoichiro; Sato, Kotaro; Imamura, Mitsuru; Tsuji, Masashi

    2009-01-01

    Hokkaido is one of the four largest island of Japan located in the northern, most of the area, where the atmospheric temperature goes lower than the other area in winter. Thus, an average energy consumption per capita is larger in amount during cold seasons. Nowadays this energy is supplied by fossil fuels. On the other hand, problem of the green house gas emission should be controlled as much as possible in order to avoid global warming. From this point of view, the authors have discussed with local people on the possibility to utilize nuclear clean energy in the daily life in Hokkaido district. Recently some leaders in local towns become interested to such activities and they want information about nuclear energy and related systems. It is a very good chance for us to exchange information on nuclear energy with regards to public acceptance, fears of nuclear power or radiation, the extent of satisfaction to be sure for construction of urban nuclear plants and requirements for such plants. We prepared technical presentation materials and visited a selected towns and continued discussion in various aspects. For example, proposal of a proto type design concept of a small reactor, safety, heat energy supply system. The audience was mainly representatives of the towns firstly and gradually ordinal people also attended the meetings. Based on the information, it could be expected to establish a concept for such district energy supply system. In this paper, some examples and results through these activities are presented. (author)

  9. Development of a comprehensive nuclear materials accountancy system at JAEA

    International Nuclear Information System (INIS)

    Takeda, Hideyuki; Usami, Masayuki; Hirosawa, Naonori; Fujita, Yoshihisa; Kodani, Yoshiki; Komata, Kazuhiro

    2007-01-01

    The Japan Atomic Energy Agency (JAEA) is submitting various types of accounting reports of international controlled materials to the Ministry of Education, Culture, Sports, Science, and Technology (MEXT) based on domestic laws and regulations. JAEA developed a comprehensive Nuclear Material Accountancy System to achieve uniform management of the data of each facility by using a company-wide database. Personal computers in each facility are connected throughout the company using an in-house network to create the comprehensive Nuclear Material Accountancy System. This System uses personal computers to facilitate timely communication and for easy maintenance and operation. Efficient data processing and quality control functions for accountancy reporting are also realized by this System. In addition, the System has the ability to extract and summarize data about Plutonium Management in the company for public announcement. This report introduces and describes the details and functions of this System. (author)

  10. Calculations to support design of a nuclear material tracking system

    International Nuclear Information System (INIS)

    Carter, L.L.; Eggers, R.F.; Williams, T.L.

    1991-01-01

    The Westinghouse Hanford Company is developing a nuclear material tracking system called NTRAK for the US Department of Energy at the Savannah River site. The NTRAK system is designed to determine the position and approximate magnitude of packages of special nuclear material (SNM) moving through a nuclear plant. The NTRAK accomplishes this by using special assemblies of detectors called modules to measure the gamma radiation emitted by the SNM. After measurement, raw data are processed to determine the direction to and position of the gamma-ray source. In order for the NTRAK method of SNM tracking to work, the gamma-ray signal at the detector modules must be at least four standard deviations above background. This paper addresses the use of the Monte Carlo computer code for neutron and photon transport (MCNP) to (a) predict the radiation emitted by plutonium oxide sources and (b) predict the counting rate of NaI detectors measuring those sources

  11. A New Dynamic Model for Nuclear Fuel Cycle System Analysis

    International Nuclear Information System (INIS)

    Choi, Sungyeol; Ko, Won Il

    2014-01-01

    The evaluation of mass flow is a complex process where numerous parameters and their complex interaction are involved. Given that many nuclear power countries have light and heavy water reactors and associated fuel cycle technologies, the mass flow analysis has to consider a dynamic transition from the open fuel cycle to other cycles over decades or a century. Although an equilibrium analysis provides insight concerning the end-states of fuel cycle transitions, it cannot answer when we need specific management options, whether the current plan can deliver these options when needed, and how fast the equilibrium can be achieved. As a pilot application, the government brought several experts together to conduct preliminary evaluations for nuclear fuel cycle options in 2010. According to Table 1, they concluded that the closed nuclear fuel cycle has long-term advantages over the open fuel cycle. However, it is still necessary to assess these options in depth and to optimize transition paths of these long-term options with advanced dynamic fuel cycle models. A dynamic simulation model for nuclear fuel cycle systems was developed and its dynamic mass flow analysis capability was validated against the results of existing models. This model can reflects a complex combination of various fuel cycle processes and reactor types, from once-through to multiple recycling, within a single nuclear fuel cycle system. For the open fuel cycle, the results of the developed model are well matched with the results of other models

  12. Modelling adversary actions against a nuclear material accounting system

    International Nuclear Information System (INIS)

    Lim, J.J.; Huebel, J.G.

    1979-01-01

    A typical nuclear material accounting system employing double-entry bookkeeping is described. A logic diagram is used to model the interactions of the accounting system and the adversary when he attempts to thwart it. Boolean equations are derived from the logic diagram; solution of these equations yields the accounts and records through which the adversary may disguise a SSNM theft and the collusion requirements needed to accomplish this feat. Some technical highlights of the logic diagram are also discussed

  13. A short history of the CANDU nuclear power system

    Energy Technology Data Exchange (ETDEWEB)

    Brooks, G L

    1993-04-01

    This paper provides a short historical summary of the evolution of the CANDU nuclear power system with emphasis on the roles played by Ontario Hydro and private sector companies in Ontario in collaboration with Atomic Energy of Canada Limited (AECL). (author). 1 fig., 61 refs.

  14. A short history of the CANDU nuclear power system

    International Nuclear Information System (INIS)

    Brooks, G.L.

    1993-04-01

    This paper provides a short historical summary of the evolution of the CANDU nuclear power system with emphasis on the roles played by Ontario Hydro and private sector companies in Ontario in collaboration with Atomic Energy of Canada Limited (AECL). (author). 1 fig., 61 refs

  15. A Nuclear Safety System based on Industrial Computer

    International Nuclear Information System (INIS)

    Kim, Ji Hyeon; Oh, Do Young; Lee, Nam Hoon; Kim, Chang Ho; Kim, Jae Hack

    2011-01-01

    The Plant Protection System(PPS), a nuclear safety Instrumentation and Control (I and C) system for Nuclear Power Plants(NPPs), generates reactor trip on abnormal reactor condition. The Core Protection Calculator System (CPCS) is a safety system that generates and transmits the channel trip signal to the PPS on an abnormal condition. Currently, these systems are designed on the Programmable Logic Controller(PLC) based system and it is necessary to consider a new system platform to adapt simpler system configuration and improved software development process. The CPCS was the first implementation using a micro computer in a nuclear power plant safety protection system in 1980 which have been deployed in Ulchin units 3,4,5,6 and Younggwang units 3,4,5,6. The CPCS software was developed in the Concurrent Micro5 minicomputer using assembly language and embedded into the Concurrent 3205 computer. Following the micro computer based CPCS, PLC based Common-Q platform has been used for the ShinKori/ShinWolsong units 1,2 PPS and CPCS, and the POSAFE-Q PLC platform is used for the ShinUlchin units 1,2 PPS and CPCS. In developing the next generation safety system platform, several factors (e.g., hardware/software reliability, flexibility, licensibility and industrial support) can be considered. This paper suggests an Industrial Computer(IC) based protection system that can be developed with improved flexibility without losing system reliability. The IC based system has the advantage of a simple system configuration with optimized processor boards because of improved processor performance and unlimited interoperability between the target system and development system that use commercial CASE tools. This paper presents the background to selecting the IC based system with a case study design of the CPCS. Eventually, this kind of platform can be used for nuclear power plant safety systems like the PPS, CPCS, Qualified Indication and Alarm . Pami(QIAS-P), and Engineering Safety

  16. A Nuclear Safety System based on Industrial Computer

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Ji Hyeon; Oh, Do Young; Lee, Nam Hoon; Kim, Chang Ho; Kim, Jae Hack [Korea Electric Power Corporation Engineering and Construction, Daejeon (Korea, Republic of)

    2011-05-15

    The Plant Protection System(PPS), a nuclear safety Instrumentation and Control (I and C) system for Nuclear Power Plants(NPPs), generates reactor trip on abnormal reactor condition. The Core Protection Calculator System (CPCS) is a safety system that generates and transmits the channel trip signal to the PPS on an abnormal condition. Currently, these systems are designed on the Programmable Logic Controller(PLC) based system and it is necessary to consider a new system platform to adapt simpler system configuration and improved software development process. The CPCS was the first implementation using a micro computer in a nuclear power plant safety protection system in 1980 which have been deployed in Ulchin units 3,4,5,6 and Younggwang units 3,4,5,6. The CPCS software was developed in the Concurrent Micro5 minicomputer using assembly language and embedded into the Concurrent 3205 computer. Following the micro computer based CPCS, PLC based Common-Q platform has been used for the ShinKori/ShinWolsong units 1,2 PPS and CPCS, and the POSAFE-Q PLC platform is used for the ShinUlchin units 1,2 PPS and CPCS. In developing the next generation safety system platform, several factors (e.g., hardware/software reliability, flexibility, licensibility and industrial support) can be considered. This paper suggests an Industrial Computer(IC) based protection system that can be developed with improved flexibility without losing system reliability. The IC based system has the advantage of a simple system configuration with optimized processor boards because of improved processor performance and unlimited interoperability between the target system and development system that use commercial CASE tools. This paper presents the background to selecting the IC based system with a case study design of the CPCS. Eventually, this kind of platform can be used for nuclear power plant safety systems like the PPS, CPCS, Qualified Indication and Alarm . Pami(QIAS-P), and Engineering Safety

  17. Mobile nuclear power systems

    International Nuclear Information System (INIS)

    Andersson, B.

    1988-11-01

    This report is meant to present a general survey of the mobile nuclear power systems and not a detailed review of their technical accomplishments. It is based in published material mainly up to 1987. Mobile nuclear power systems are of two fundamentally different kinds: nuclear reactors and isotopic generators. In the reactors the energy comes from nuclear fission and in the isotopic generators from the radioactive decay of suitable isotopes. The reactors are primarily used as power sourves on board nuclear submarines and other warships but have also been used in the space and in remote places. Their thermal power has ranged from 30 kWth (in a satellite) to 175 MWth (on board an aircraft carrier). Isotopic generators are suitable only for small power demands and have been used on board satellites and spaceprobes, automatic weatherstations, lighthouses and marine installations for navigation and observation. (author)

  18. Demonstration of a transportable storage system for spent nuclear fuel

    International Nuclear Information System (INIS)

    Shetler, J.R.; Miller, K.R.; Jones, R.E.

    1993-01-01

    The purpose of this paper is to discuss the joint demonstration project between the Sacramento Municipal Utility District (SMUD) and the US Department of Energy (DOE) regarding the use of a transportable storage system for the long-term storage and subsequent transport of spent nuclear fuel. SMUD's Rancho Seco nuclear generating station was shut down permanently in June 1989. After the shutdown, SMUD began planning the decommissioning process, including the disposition of the spent nuclear fuel. Concurrently, Congress had directed the Secretary of Energy to develop a plan for the use of dual-purpose casks. Licensing and demonstrating a dual-purpose cask, or transportable storage system, would be a step toward achieving Congress's goal of demonstrating a technology that can be used to minimize the handling of spent nuclear fuel from the time the fuel is permanently removed from the reactor through to its ultimate disposal at a DOE facility. For SMUD, using a transportable storage system at the Rancho Seco Independent Spent-Fuel Storage Installation supports the goal of abandoning Rancho Seco's spent-fuel pool as decommissioning proceeds

  19. A sensor-based automation system for handling nuclear materials

    International Nuclear Information System (INIS)

    Drotning, W.; Kimberly, H.; Wapman, W.; Darras, D.

    1997-01-01

    An automated system is being developed for handling large payloads of radioactive nuclear materials in an analytical laboratory. The automation system performs unpacking and repacking of payloads from shipping and storage containers, and delivery of the payloads to the stations in the laboratory. The system uses machine vision and force/torque sensing to provide sensor-based control of the automation system in order to enhance system safety, flexibility, and robustness, and achieve easy remote operation. The automation system also controls the operation of the laboratory measurement systems and the coordination of them with the robotic system. Particular attention has been given to system design features and analytical methods that provide an enhanced level of operational safety. Independent mechanical gripper interlock and tool release mechanisms were designed to prevent payload mishandling. An extensive Failure Modes and Effects Analysis of the automation system was developed as a safety design analysis tool

  20. Safety assessment of a robotic system handling nuclear material

    International Nuclear Information System (INIS)

    Atcitty, C.B.; Robinson, D.G.

    1996-01-01

    This paper outlines the use of a Failure Modes and Effects Analysis for the safety assessment of a robotic system being developed at Sandia National Laboratories. The robotic system, The Weigh and Leak Check System, is to replace a manual process at the Department of Energy facility at Pantex by which nuclear material is inspected for weight and leakage. Failure Modes and Effects Analyses were completed for the robotics process to ensure that safety goals for the system had been meet. These analyses showed that the risks to people and the internal and external environment were acceptable

  1. Controllable valve in a nuclear reactor system

    International Nuclear Information System (INIS)

    Schabert, H.P.; Laurer, E.

    1980-01-01

    The quick-acting gate valve of the PWR is opened and closed by means of two pistons and live steam. One of the pistons is connected to the valve disk by a piston rod which is concentrically lead into another hollow piston rod being connected to the second piston. Stops limit the strokes of the two pistons. (GL) [de

  2. Security features of a nuclear material accounting system

    International Nuclear Information System (INIS)

    Erkkila, B.H.

    1988-01-01

    The Los Alamos Nuclear Material Accounting and Safeguards System (MASS) is a near-real-time accountability system for bulk materials, discrete items, and materials undergoing dynamic processing. MASS has evolved from a 80-column, card-based process control system to a very sophisticated computer system. Recently, the computer hardware was upgraded to a modern transaction oriented central computer system designed to accommodate extensive growth in the foreseeable future. The security of the MASS computer system is provided through various access controls. There are two kinds of access controls to be addressed. They are physical access control to the hardware which make up the system and access control to the software. There are many features which provide a measure of security to the hardware that are discussed. Access to the software is controlled by a security password. Access to various transaction activities in the system is controlled through the level of MASS under privilege. Details of MASS user privilege are discussed

  3. A study on optimization of the nuclear safety system

    International Nuclear Information System (INIS)

    Lee, Sang Hoon; Koh, Byung Joon; Kim, Jin Soo; Kim, Byoung Do; Cho, Seong Won; Kwon, Seog Kwon; Choi, Kwang Sik

    1986-12-01

    The number of nuclear facilities (nuclear power plants, research reactors, nuclear fuel facilities) under construction or in operation in Korea continues to increase and this has brought about increased importance and concerns toward nuclear safety in Korea. Also, domestic nuclear related organizations are increasingly carrying out the design/construction of nuclear power plants and the development /supply of nuclear fuels. In order to flexibly respond to these changes and to suggest direction to take, it is necessary to re-examine the current nuclear safety regulation system. This study is carried out in two stages and this report describes the results of the analysis and the assessment of the nuclear licencing system of such foreign countries as sweden and German, as the first of the two. In this regard, this study includes the analysis on the backgrounds on the choice of nuclear licensing system, the analysis on the licensing procedures, the analysis on the safety inspection system and the enforcement laws, the analysis on the structure and function of the regulatory, business and research organizations as well as the analysis on the relationship between the safety research and the regulatory duties. In this study, the German safety inspection system and the enforcement procedures and the Swedish nuclear licensing system are analyzed in detail. By comparing and assessing the finding with the current Korea Nuclear Licensing System, this study points out some reform measures of the Korean system that needs to improved. With the changing situations in mind, this study aims to develop the nuclear safety regulation system optimized for Korean situation by re-examining the current regulation system. (Author)

  4. A study on expert system applications for nuclear power plant

    International Nuclear Information System (INIS)

    Huh, Young Hwan; Kim, Kil Yoo; Kang, Soon Ju; Park, Nam Seok; Ryu, Chan Ho; Choi, In Seon; Chung, Young Moo; Chung, Tae Eon; Yim, Chang Jae; Lee, Yoon Sang.

    1990-01-01

    The objectives of this research are 1) to develop an expert system which can automatically evaluate eddy current (EC) signal during an eddy current test (ECT) of SG U tube inspection, 2) to build an effective data base management system for ECT data. By this expert system the reliability in EC signal evaluation can be improved, and the required man-power can be reduced. And this expert system can supply a stable ECT and contribute to a safe operation of the nuclear power plant. (author)

  5. Nuclear imaging system

    International Nuclear Information System (INIS)

    Barrett, H.H.; Horrigan, F.A.

    1975-01-01

    This invention relates to a nuclear imaging system for mapping the source of high energy nuclear particles from a living organ which has selectively absorbed a radioactive compound by spatially coding the energy from the source in a Fresnel pattern on a detector and decoding the detector output to prouce an image of the source. The coding is produced by a Fresnel zone plate interposed between the nuclear energy source and the detector whose position is adjustable with respect to the detector to focus the slices of the nuclear source on the detector. By adjusting the zone plate to a plurality of positions, data from a plurality of cross-sectional slices are produced from which a three-dimensional image of the nuclear source may be obtained. (Patent Office Record)

  6. Nuclear propulsion systems engineering

    International Nuclear Information System (INIS)

    Madsen, W.W.; Neuman, J.E.: Van Haaften, D.H.

    1992-01-01

    The Nuclear Energy for Rocket Vehicle Application (NERVA) program of the 1960's and early 1970's was dramatically successful, with no major failures during the entire testing program. This success was due in large part to the successful development of a systems engineering process. Systems engineering, properly implemented, involves all aspects of the system design and operation, and leads to optimization of theentire system: cost, schedule, performance, safety, reliability, function, requirements, etc. The process must be incorporated from the very first and continued to project completion. This paper will discuss major aspects of the NERVA systems engineering effort, and consider the implications for current nuclear propulsion efforts

  7. A universal measuring and monitoring system for nuclear radiation

    International Nuclear Information System (INIS)

    Genrich, V.

    1988-01-01

    Genitron Instruments, Frankfurt/Main, committed themselves to revise the 'conventional' concept of counting tube metrology. The goal was to develop a modular system that would allow large-area measuring tasks. The contribution in hand explains this development, which consists of a highly integrated measuring head that can be combined with various detector types, and complemented by various system components, to form a universal measuring and monitoring system for nuclear radiation. This modular design concept is capable of fulfilling a multitude of tasks, ranging from single, specific applications to non-stop monitoring tasks within a large-area measuring network. (orig./DG) [de

  8. Cable handling system for use in a nuclear reactor

    International Nuclear Information System (INIS)

    Crosgrove, R.O.; Larson, E.M.; Moody, E.

    1982-01-01

    A cable handling system for use in an installation such as a nuclear reactor is disclosed herein along with relevant portions of the reactor which, in a preferred embodiment, is a liquid metal fast breeder reactor. The cable handling system provides a specific way of interconnecting certain internal reactor components with certain external components, through an assembly of rotatable plugs. Moreover, this is done without having to disconnect these components from one another during rotation of the plugs and yet without interfering with other reactor components in the vicinity of the rotating plugs and cable handling system

  9. Parallel preprocessing in a nuclear data acquisition system

    International Nuclear Information System (INIS)

    Pichot, G.; Auriol, E.; Lemarchand, G.; Millaud, J.

    1977-01-01

    The appearance of microprocessors and large memory chips has somewhat modified the spectrum of tools usable by the data acquisition system designer. This is particular true in the nuclear research field where the data flow has been continuously growing as a consequence of the increasing capabilities of new detectors. This paper deals with the insertion, between a data acquisition system and a computer, of a preprocessing structure based on microprocessors and large capacity high speed memories. The results shows a significant improvement on several aspects in the operation of the system with returns paying back the investments in 18 months

  10. Nuclear systems

    CERN Document Server

    Todreas, Neil E

    2011-01-01

    Principal Characteristics of Power ReactorsIntroductionPower CyclesPrimary Coolant SystemsReactor CoresFuel AssembliesAdvanced Water- and Gas-Cooled Reactors (Generation III And III+)Advanced Thermal and Fast Neutron Spectrum Reactors (Generation IV)ReferencesProblemsThermal Design Principles and ApplicationIntroductionOverall Plant Characteristics Influenced by Thermal Hydraulic ConsiderationsEnergy Production and Transfer ParametersThermal Design LimitsThermal Design MarginFigures of Merit for Core Thermal PerformanceThe Inverted Fuel ArrayThe Equivalent Annulus ApproximationReferencesProble

  11. Implementation of a geographical information system in nuclear emergencies

    International Nuclear Information System (INIS)

    Sadaniowski, I.; Telleria, D.; Jordan, O.; Bruno, H.; Boutet, L.; Hernandez, D.

    2006-01-01

    From 2003, the Nuclear Regulatory Authority (RNA) has worked in the implementation of a Geographical Information System (SIG) for the planning and the intervention in emergencies, with special emphasis in the nuclear emergencies. The main objective of the SIG developed in the ARN is to give the necessary support for the planning, training and application of the actions of radiological protection necessary in front of a nuclear emergency, offering the geo referenced cartographic base, the readiness of logistical resources in the whole country, incorporating results of models of forecast of consequences and environmental measurements during the emergency, facilitating the analysis of this information in real time and facilitating the presentation of results for the decision making. The cartographic base is constituted of demographic, social, economic data identification of main actors interveners in the emergency, vial infrastructure and natural characteristics of the area in question. In this work the main characteristics of the implemented SIG are presented including the conceptual standards of design that contemplate the international requirements for the planning and answer in the event of nuclear emergencies, the current state of the system and the foreseen evolution. A description of the opposing problems during its implementation that can be common to many countries of the region is also presented, as well as the obtained experience of its use in preparation tasks for emergencies and in mocks. (Author)

  12. Design of a requirements system for decommissioning of a nuclear power plant based on systems engineering

    Energy Technology Data Exchange (ETDEWEB)

    Park, Hee Seong; Park, Seung Kook; Jin, Hyung Gon; Song, Chan Ho; Choi, Jong won [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2015-10-15

    The nuclear industry has required an advanced system that can manage decommissioning information ever since the Korean government decide to decommission the Gori No.1 nuclear power plant. The D and D division at KAERI has been developing a system that can secure the reliability and sustainability of the decommissioning project based on the engineering system of the KRR-2 (Korean Research Reactor-2). To establish a decommissioning information system, a WBS that needs to be managed for the decommissioning of an NPP has been extracted, and requirements management research composed of system engineering technology has progressed. This paper propose a new type of system based on systems engineering technology. Even though a decommissioning engineering system was developed through the KRR-2, we are now developing an advanced decommissioning information system because it is not easy to apply this system to a commercial nuclear power plant. An NPP decommissioning is a project requiring a high degree of safety and economic feasibility. Therefore, we have to use a systematic project management at the initial phase of the decommissioning. An advanced system can manage the decommissioning information from preparation to remediation by applying a previous system to the systems engineering technology that has been widely used in large-scale government projects. The first phase of the system has progressed the requirements needed for a decommissioning project for a full life cycle. The defined requirements will be used in various types of documents during the decommissioning preparation phase.

  13. 'Y' a distributed resource sharing system in nuclear research environment

    International Nuclear Information System (INIS)

    Popescu-Zeletin, R.

    1986-01-01

    The paper outlines the rationales for the transition from HMINET-2 to a distributed resource sharing system in Hahn-Meitner-Institute for Nuclear Research. The architecture and rationales for the planned new distributed resource system (Y) in HMI are outlined. The introduction of a distributed operating system is a prerequisite for a resource-sharing system. Y will provide not only the integration of networks of different qualities (high speed back-bone, LANs of different technologies, ports to national X.25 network and satellite) at hardware level, but also an integrated global user view of the whole system. This will be designed and implemented by decoupling the user-view from the hardware topology by introducing a netwide distributed operating system. (Auth.)

  14. A framework for AI-based nuclear design support system

    International Nuclear Information System (INIS)

    Furuta, Kazuo; Kondo, Shunsuke

    1991-01-01

    Nowadays many computer programs are being developed and used for the analytic tasks in nuclear reactor design, but experienced designers are still responsible for most of the synthetic tasks which are not amenable to algorithmic computer processes. Artificial intelligence (AI) is a promising technology to deal with these intractable tasks in design. In development of AI-based design support systems, it is desirable to choose a comprehensive framework based on the scientific theory of design. In this work a framework for AI-based design support systems for nuclear reactor design will be proposed based on an exploration model of design. The fundamental architectures of this framework will be described especially on knowledge representation, context management and design planning. (author)

  15. A quadrupole mass spectrometer system for nuclear safeguards applications

    International Nuclear Information System (INIS)

    Evans, P.J.

    1987-12-01

    An on-line enrichment monitor for nuclear safeguards-related surveillance of a pilot-scale gas centrifuge plant is described. This monitor utilises a quadrupole mass spectrometer to measure the isotopic composition of UF 6 in the feed and product gas streams. Details of the design and construction are given, and several difficulties are identified and discussed. Finally, the performance of this system is illustrated with typical results

  16. A mobile gamma ray spectrometer system for nuclear hazard mapping

    International Nuclear Information System (INIS)

    Smethurst, Mark A.

    2000-12-01

    The Geological Survey of Norway has developed a system for mobile gamma ray spectrometer surveying suitable for use in nuclear emergencies where potentially dangerous radioactive materials have been released into the environment. The measuring system has been designed for use with different kinds of transportation platforms. These include fixed-wing aircraft, helicopters and vans. The choice of transportation platform depends on the nature of the nuclear emergency. Widespread fallout from a distant source can be mapped quickly from the air while local sources of radiation can be delineated by a car-borne system. The measuring system processes gamma ray spectra in real time. The operator of the system is therefore able to guide surveying in accordance with meaningful data values and immediately report these values to decision making authorities. The operator is presented with a number of different displays suited to different kinds of nuclear emergencies that lead to more efficient surveying. Real time processing of data means that the results of a survey can be delivered to decision makers immediately upon return to base. It is also possible to deliver data via a live mobile telephone link while surveying is underway. The measuring system can be adjusted to make measurements lasting between 1 second and 5 seconds. The spatial density of measuring positions depends on the duration of each measurement and the speed of travel of the measuring system. Measuring with 1 s intervals while travelling at 50 km/h in a car results in a measurement every 14 m along the road. Measuring with 1 s intervals in an aeroplane travelling at 250 km/h produces a measurement for every 70 m travelled. Eight hours surveying can produce up to 30000 measurements over a region hundreds of kilometres across. (Author)

  17. Evaluation of the improvement suggestion system in a nuclear facility

    International Nuclear Information System (INIS)

    Carnaval, Joao Paulo Rodrigues; Moraes, Geice Almeida

    2017-01-01

    This work evaluated methods for processing improvement suggestions of a nuclear factory, with the intention to verify those which best fits to the company purposes. Two methods for processing improvement suggestions were applied in the studied organization. The first one was guided to the processing suggestions by specific independent sectors of the company and the second one was conducted to the processing of suggestions by a multidisciplinary team. It has been concluded that a multidisciplinary team focused on research and development would be the best option to the implementation of improvement suggestions and technological innovation on this facility, instead of multi sector processing which revealed to be excessive bureaucratic before the expected goals. This study can be used by nuclear facilities to optimize an existing system of improvements analysis or even guide them for the implantation of a new one. It is more significant for the companies certified on ISO and OHSAS standards for the quality management, environmental and safety and occupational health systems which requires that the continuous improvement must exist and to be demonstrated. But it is also relevant for nuclear plants aiming to implement an Integrated Management System certified on ISO Standards. (author)

  18. Evaluation of the improvement suggestion system in a nuclear facility

    Energy Technology Data Exchange (ETDEWEB)

    Carnaval, Joao Paulo Rodrigues; Moraes, Geice Almeida, E-mail: joaocarnaval@inb.gov.br, E-mail: geice@inb.gov.br [Industrias Nucleares do Brasil S.A (INB), Resende, RJ (Brazil)

    2017-11-01

    This work evaluated methods for processing improvement suggestions of a nuclear factory, with the intention to verify those which best fits to the company purposes. Two methods for processing improvement suggestions were applied in the studied organization. The first one was guided to the processing suggestions by specific independent sectors of the company and the second one was conducted to the processing of suggestions by a multidisciplinary team. It has been concluded that a multidisciplinary team focused on research and development would be the best option to the implementation of improvement suggestions and technological innovation on this facility, instead of multi sector processing which revealed to be excessive bureaucratic before the expected goals. This study can be used by nuclear facilities to optimize an existing system of improvements analysis or even guide them for the implantation of a new one. It is more significant for the companies certified on ISO and OHSAS standards for the quality management, environmental and safety and occupational health systems which requires that the continuous improvement must exist and to be demonstrated. But it is also relevant for nuclear plants aiming to implement an Integrated Management System certified on ISO Standards. (author)

  19. A self-consistent nuclear energy supply system

    International Nuclear Information System (INIS)

    Fujii-e, Y.; Morita, T.; Kawakami, H.; Arie, K.; Suzuki, M.; Iida, M.; Yamazaki, H.

    1992-01-01

    A self-consistent nuclear energy supply system (SCNESS) is investigated for a Fast Reactor. SCNESS is proposed as a future stable energy supplier with no harmful influence on humans or environment for the ultimate goal of nuclear energy development. SCNESS should be inherently safe, be able to breed fissionable material, and transmute long-lived radioactive nuclides (i.e., minor actinides and long-lived fission products). The relationship between these characteristics and the spatial assignment of excess neutrons (v-1) for each characteristic are analyzed. The analysis shows that excess neutrons play an intrinsic role in realizing SCNESS. The reactor concept of SCNESS is investigated by considering utilization of excess neutrons. Results show that a small-size axially double-layered annular core with metal fuel is a choice candidate for SCNESS. SCNESS is concluded feasible. (author). 4 refs., 9 figs

  20. Architectures of Remote Monitoring Systems for a Nuclear Power Plant

    International Nuclear Information System (INIS)

    Choi, Yoo Rark; Lee, Jae Cheol; Kim, Jae Hee

    2006-01-01

    Aina(Artificial Intelligence for Nuclear Applications) have developed remote monitoring systems since the 1990's. We have been interested in the safety of reactor vessel, steam generator, pipes, valves and pumps. We have developed several remote inspection systems and will develop some remote care systems for a nuclear power plant. There were critical problems for building remote monitoring systems for mass data processing and remote user interface techniques in the middle of the 1990's. The network capacity wasn't sufficient to transfer the monitoring data to a remote computer. Various computer operating systems require various remote user interfaces. Java provides convenient and powerful interface facilities and the network transfer speed was increased greatly in the 2000's. Java is a good solution for a remote user interface but it can't work standalone in remote monitoring applications. The restrictions of Java make it impossible to build real time based applications. We use Java and a traditional language to improve this problem. We separate the remote user interface and the monitoring application

  1. Straight-Line -- A nuclear material storage information management system

    Energy Technology Data Exchange (ETDEWEB)

    Nilsen, C. [Sandia National Labs., Livermore, CA (United States); Mangan, D. [Sandia National Labs., Albuquerque, NM (United States)

    1995-12-31

    Sandia National Laboratories is developing Straight-Line -- a pilot system to demonstrate comprehensive monitoring of nuclear material in storage. Straight-Line is an integrated system of sensors providing information that will enhance the safety, security, and international accountability of stored nuclear material. The goals of this effort are to (1) Provide the right sensor information to the right user in a timely manner. (2) Reduce the expenses, risks, and frequency of human inspection of the material. (3) Provide trustworthy data to international inspectors to minimize their need to make on site inspections. In pursuit of these goals, Straight-Line unites technology from Sandia`s Authenticated Item Monitoring System (AIMS) and other programs to communicate the authenticated status of the monitored item back to central magazine receivers. Straight-Line, however, incorporates several important features not found in previous systems: (1) Information Security -- the ability to collect and safely disseminate both classified and unclassified sensor data to users on a need-to-know basis. (2) Integrate into a single system the monitoring needs of safety, security, and international accountability. (3) Incorporate the use of sensors providing analog or digital output. This paper will present the overall architecture and status of the Straight-Line project.

  2. Straight-Line -- A nuclear material storage information management system

    International Nuclear Information System (INIS)

    Nilsen, C.; Mangan, D.

    1995-01-01

    Sandia National Laboratories is developing Straight-Line -- a pilot system to demonstrate comprehensive monitoring of nuclear material in storage. Straight-Line is an integrated system of sensors providing information that will enhance the safety, security, and international accountability of stored nuclear material. The goals of this effort are to (1) Provide the right sensor information to the right user in a timely manner. (2) Reduce the expenses, risks, and frequency of human inspection of the material. (3) Provide trustworthy data to international inspectors to minimize their need to make on site inspections. In pursuit of these goals, Straight-Line unites technology from Sandia's Authenticated Item Monitoring System (AIMS) and other programs to communicate the authenticated status of the monitored item back to central magazine receivers. Straight-Line, however, incorporates several important features not found in previous systems: (1) Information Security -- the ability to collect and safely disseminate both classified and unclassified sensor data to users on a need-to-know basis. (2) Integrate into a single system the monitoring needs of safety, security, and international accountability. (3) Incorporate the use of sensors providing analog or digital output. This paper will present the overall architecture and status of the Straight-Line project

  3. Straight-Line: A nuclear material storage information management system

    International Nuclear Information System (INIS)

    Nilsen, C.; Mangan, D.

    1995-01-01

    Sandia National Laboratories is developing Straight-Line -- a pilot system to demonstrate comprehensive monitoring of nuclear material in storage. Straight-Line is an integrated system of sensors providing information that will enhance the safety, security, and international accountability of stored nuclear material. The goals of this effort are to: (1) Provide the right sensor information to the right user immediately. (2) Reduce the expenses, risks, and frequency of human inspection of the material. (3) Provide trustworthy data to international inspectors to minimize their need to make on site inspections. In pursuit of these goals, Straight-Line unites technology from Sandia's Authenticated Item Monitoring System (AIMS) and other programs to communicate the authenticated status of the monitored item back to central magazine receivers. Straight-Line, however, incorporates several important features not found in previous systems: (1) Information Security -- the ability to collect and safely disseminate both classified and unclassified sensor data to users on a need-to-know basis. (2) Integrate into a single system the monitoring needs of safety, security, and international accountability. (3) Incorporate the use of sensors providing analog or digital output. This paper will present the overall architecture and status of the Straight-Line project

  4. Straight-Line: A nuclear material storage information management system

    Energy Technology Data Exchange (ETDEWEB)

    Nilsen, C.; Mangan, D.

    1995-07-01

    Sandia National Laboratories is developing Straight-Line -- a pilot system to demonstrate comprehensive monitoring of nuclear material in storage. Straight-Line is an integrated system of sensors providing information that will enhance the safety, security, and international accountability of stored nuclear material. The goals of this effort are to: (1) Provide the right sensor information to the right user immediately. (2) Reduce the expenses, risks, and frequency of human inspection of the material. (3) Provide trustworthy data to international inspectors to minimize their need to make on site inspections. In pursuit of these goals, Straight-Line unites technology from Sandia`s Authenticated Item Monitoring System (AIMS) and other programs to communicate the authenticated status of the monitored item back to central magazine receivers. Straight-Line, however, incorporates several important features not found in previous systems: (1) Information Security -- the ability to collect and safely disseminate both classified and unclassified sensor data to users on a need-to-know basis. (2) Integrate into a single system the monitoring needs of safety, security, and international accountability. (3) Incorporate the use of sensors providing analog or digital output. This paper will present the overall architecture and status of the Straight-Line project.

  5. Nuclear Systems Kilopower Overview

    Science.gov (United States)

    Palac, Don; Gibson, Marc; Mason, Lee; Houts, Michael; McClure, Patrick; Robinson, Ross

    2016-01-01

    The Nuclear Systems Kilopower Project was initiated by NASAs Space Technology Mission Directorate Game Changing Development Program in fiscal year 2015 to demonstrate subsystem-level technology readiness of small space fission power in a relevant environment (Technology Readiness Level 5) for space science and human exploration power needs. The Nuclear Systems Kilopower Project consists of two elements. The primary element is the Kilopower Prototype Test, also called the Kilopower Reactor Using Stirling Technology(KRUSTY) Test. This element consists of the development and testing of a fission ground technology demonstrator of a 1 kWe fission power system. A 1 kWe system matches requirements for some robotic precursor exploration systems and future potential deep space science missions, and also allows a nuclear ground technology demonstration in existing nuclear test facilities at low cost. The second element, the Mars Kilopower Scalability Study, consists of the analysis and design of a scaled-up version of the 1 kWe reference concept to 10 kWe for Mars surface power projected requirements, and validation of the applicability of the KRUSTY experiment to key technology challenges for a 10 kWe system. If successful, these two elements will lead to initiation of planning for a technology demonstration of a 10 kWe fission power capability for Mars surface outpost power.

  6. A concept of safety indicator system for nuclear power plants

    International Nuclear Information System (INIS)

    Lehtinen, E.

    1995-12-01

    The fundamental principle in the safety technology of nuclear power is embodied in the strategy of defence in depth. The defence lines of the strategy, completed with a PSA logic model and structure, are considered to provide an appropriate framework for identification and structuring of the operational safety performance areas for nuclear power plants. Once these areas are identified the safety indicators can be defined. Based on this approach a concept of safety indicator system was outlined. About one hundred indicator specifications have been collected, refined and related to the performance areas. The specifications enable the utilities and authorities to check the coverage of their indicators set from the operational safety point of view and select or refine indicators for testing and routine use. Finally various statistical approaches and methods for using indicators in performance evaluation are presented. (orig.) (16 refs., 2 figs., 2 tabs.)

  7. PEGASUS: a multi-megawatt nuclear electric propulsion system

    International Nuclear Information System (INIS)

    Coomes, E.P.; Cuta, J.M.; Webb, B.J.; King, D.Q.

    1985-06-01

    With the Space Transportation System (STS), the advent of space station Columbus and the development of expertise at working in space that this will entail, the gateway is open to the final frontier. The exploration of this frontier is possible with state-of-the-art hydrogen/oxygen propulsion but would be greatly enhanced by the higher specific impulse of electric propulsion. This paper presents a concept that uses a multi-megawatt nuclear power plant to drive an electric propulsion system. The concept has been named PEGASUS, PowEr GenerAting System for Use in Space, and is intended as a ''work horse'' for general space transportation needs, both long- and short-haul missions. The recent efforts of the SP-100 program indicate that a power system capable of producing upwards of 1 megawatt of electric power should be available in the next decade. Additionally, efforts in other areas indicate that a power system with a constant power capability an order of magnitude greater could be available near the turn of the century. With the advances expected in megawatt-class space power systems, the high specific impulse propulsion systems must be reconsidered as potential propulsion systems. The power system is capable of meeting both the propulsion system and spacecraft power requirements

  8. Systems resilience: a new analytical framework for nuclear nonproliferation

    International Nuclear Information System (INIS)

    Pregenzer, Arian Leigh

    2011-01-01

    This paper introduces the concept of systems resilience as a new framework for thinking about the future of nonproliferation. Resilience refers to the ability of a system to maintain its vital functions in the face of continuous and unpredictable change. The nonproliferation regime can be viewed as a complex system, and key themes from the literature on systems resilience can be applied to the nonproliferation system. Most existing nonproliferation strategies are aimed at stability rather than resilience, and the current nonproliferation system may be over-constrained by the cumulative evolution of strategies, increasing its vulnerability to collapse. The resilience of the nonproliferation system can be enhanced by diversifying nonproliferation strategies to include general international capabilities to respond to proliferation and focusing more attention on reducing the motivation to acquire nuclear weapons in the first place. Ideas for future research, include understanding unintended consequences and feedbacks among nonproliferation strategies, developing methodologies for measuring the resilience of the nonproliferation system, and accounting for interactions of the nonproliferation system with other systems on larger and smaller scales.

  9. Systems resilience : a new analytical framework for nuclear nonproliferation.

    Energy Technology Data Exchange (ETDEWEB)

    Pregenzer, Arian Leigh

    2011-12-01

    This paper introduces the concept of systems resilience as a new framework for thinking about the future of nonproliferation. Resilience refers to the ability of a system to maintain its vital functions in the face of continuous and unpredictable change. The nonproliferation regime can be viewed as a complex system, and key themes from the literature on systems resilience can be applied to the nonproliferation system. Most existing nonproliferation strategies are aimed at stability rather than resilience, and the current nonproliferation system may be over-constrained by the cumulative evolution of strategies, increasing its vulnerability to collapse. The resilience of the nonproliferation system can be enhanced by diversifying nonproliferation strategies to include general international capabilities to respond to proliferation and focusing more attention on reducing the motivation to acquire nuclear weapons in the first place. Ideas for future research, include understanding unintended consequences and feedbacks among nonproliferation strategies, developing methodologies for measuring the resilience of the nonproliferation system, and accounting for interactions of the nonproliferation system with other systems on larger and smaller scales.

  10. A remotely controlled CCTV system for nuclear reactor retube operations

    International Nuclear Information System (INIS)

    Stovman, J.A.

    1984-01-01

    This paper describes the CCTV Vault Observation Subsystem (VOS) under development for Ontario Hydro for the Pickering 'A' Nuclear Power Plant Large Scale Retubing program. This subsystem will be used by a supervisor and several operators to observe fuel channel replacement operations following plant shutdown and removal of the fuel bundles. VOS basically comprises 23 monochrome television camera driven circuits, a matrix switcher, 15 monitors, 9 tape recorders and 4 microphone driven sound circuits. Remote control of the camera's zoom lenses and mounts is via a digitally multiplexed control system. Design considerations include viewing requirements, reliability, radiation, redundance, and economic factors

  11. A Review of Tribomaterial Technology for Space Nuclear Power Systems

    Science.gov (United States)

    Stanford, Malcolm K.

    2007-01-01

    The National Aeronautics and Space Administration (NASA) has recently proposed a nuclear closed-cycle electric power conversion system for generation of 100-kW of electrical power for space exploration missions. A critical issue is the tribological performance of sliding components within the power conversion unit that will be exposed to neutron radiation. This paper presents a review of the main considerations that have been made in the selection of solid lubricants for similar applications in the past as well as a recommendations for continuing development of the technology.

  12. A study on the development and application of expert system for nuclear power plant

    Energy Technology Data Exchange (ETDEWEB)

    Woo, Hee Gon; Kim, Seong Bok [Korea Electric Power Corp. (KEPCO), Taejon (Korea, Republic of). Research Center

    1995-12-31

    It is a final report of the research that is a study on the development and application of expert system for nuclear power plants and development of the schemes computing environments and user interfaces for the expert system, which is a systematic and efficient development of expert system for nuclear power plants in the future. This report is consisted of -Development trends of expert system for nuclear power plants. -Classification of expert system applications for nuclear power plants. -Systematic and efficient developments schemes of expert system for nuclear power plants, and -Suitable computing environments and user interfaces for the expert systems. (author). 113 refs., 85 figs.

  13. A study on the development and application of expert system for nuclear power plant

    Energy Technology Data Exchange (ETDEWEB)

    Woo, Hee Gon; Kim, Seong Bok [Korea Electric Power Corp. (KEPCO), Taejon (Korea, Republic of). Research Center

    1996-12-31

    It is a final report of the research that is a study on the development and application of expert system for nuclear power plants and development of the schemes computing environments and user interfaces for the expert system, which is a systematic and efficient development of expert system for nuclear power plants in the future. This report is consisted of -Development trends of expert system for nuclear power plants. -Classification of expert system applications for nuclear power plants. -Systematic and efficient developments schemes of expert system for nuclear power plants, and -Suitable computing environments and user interfaces for the expert systems. (author). 113 refs., 85 figs.

  14. A new option for exploitage of future nuclear energy. Accelerator driven radioactive clean nuclear power system

    International Nuclear Information System (INIS)

    Ding Dazhao

    2000-01-01

    Nuclear energy is an effective, clean and safe energy resource. But some shortages of the nuclear energy system presently commercial available obstruct further development of the nuclear energy by heavy nuclear fission. Those are final disposal of the high level radioactive waste, inefficient use of the uranium resource and safety issue of the system. Innovative technical option is seeking for by the nuclear scientific community in recent ten years in aiming to overcome these obstacles, namely, accelerator driven sub-critical system (ADS). This hybrid system may bridge over the gap between presently commercial available nuclear power system and the full exploitation of the fusion energy. The basic principle of ADS is described and its capability in waste transmutation, conversion of the nuclear fuel are demonstrated by two examples--AD-fast reactor and AD-heavy water thermal reactor. The feasibility of ADS and some projects in US, Japan, etc are briefly discussed. The rationale in promoting the R and D of ADS in China is emphasized as China is at the beginning stage of its ambitious project in construction of the nuclear power

  15. The development of a nuclear accident risk information system

    International Nuclear Information System (INIS)

    Jeong, J. T.; Jeong, W. D.

    2001-01-01

    The computerized system NARIS (Nuclear Accident Risk Information System) was developed in order to support the estimation of health effects and the establishment the effective risk reduction strategies. Using the system, we can analyze the distribution of health effects easily by displaying the results on the digital map of the site. Also, the thematic mapping allows the diverse analyses of the distribution of the health effects. The NARIS can be used in the emergency operation facilities in order to analyze the distribution of the health effects resulting from the severe accidents of a nuclear power plant. Also, the rapid analysis of the health effect is possible by storing the health effect results in the form of a database. Therefore, the staffs of the emergency operation facilities can establish the rapid and effective emergency response strategies. The module for the optimization of the costs and benefits and the decision making support will be added. The technical support for the establishment of the optimum and effective emergency response strategies will be possible using this system

  16. A triggerless digital data acquisition system for nuclear decay experiments

    Energy Technology Data Exchange (ETDEWEB)

    Agramunt, J.; Tain, J. L.; Albiol, F.; Algora, A.; Estevez, E.; Giubrone, G.; Jordan, M. D.; Molina, F.; Rubio, B.; Valencia, E. [Instituto de Fisica Corpuscular, Centro Mixto C.S.I.C. - Univ. Valencia, Apdo. Correos 22085, 46071 Valencia (Spain)

    2013-06-10

    In nuclear decay experiments an important goal of the Data Acquisition (DAQ) system is to allow the reconstruction of time correlations between signals registered in different detectors. Classically DAQ systems are based in a trigger that starts the event acquisition, and all data related with the event of that trigger are collected as one compact structure. New technologies and electronics developments offer new possibilities to nuclear experiments with the use of sampling ADC-s. This type of ADC-s is able to provide the pulse shape, height and a time stamp of the signal. This new feature (time stamp) allows new systems to run without an event trigger. Later, the event can be reconstructed using the time stamp information. In this work we present a new DAQ developed for {beta}-delayed neutron emission experiments. Due to the long moderation time of neutrons, we opted for a self-trigger DAQ based on commercial digitizers. With this DAQ a negligible acquisition dead time was achieved while keeping a maximum of event information and flexibility in time correlations.

  17. Control Systems for a Dynamic Multi-Physics Model of a Nuclear Hybrid Energy System

    Energy Technology Data Exchange (ETDEWEB)

    Greenwood, Michael Scott [ORNL; Fugate, David W [ORNL; Cetiner, Sacit M [ORNL

    2017-01-01

    A Nuclear Hybrid Energy System (NHES) uses a nuclear reactor as the basic power generation unit, and the power generated is used by multiple customers as either thermal power, electrical power, or both. The definition and architecture of a particular NHES can be adapted based on the needs and opportunities of different local markets. For example, locations in need of potable water may be best served by coupling a desalination plant to the NHES. Similarly, a location near oil refineries may have a need for emission-free hydrogen production. Using the flexible, multi-domain capabilities of Modelica, Argonne National Laboratory, Idaho National Laboratory, and Oak Ridge National Laboratory are investigating the dynamics (e.g., thermal hydraulics and electrical generation/consumption) and cost of a hybrid system. This paper examines the NHES work underway, emphasizing the control system developed for individual subsystems and the overall supervisory control system.

  18. Nuclear fuel preheating system

    International Nuclear Information System (INIS)

    Andrea, C.

    1975-01-01

    A nuclear reactor new fuel handling system which conveys new fuel from a fuel preparation room into the reactor containment boundary is described. The handling system is provided with a fuel preheating station which is adaptd to heat the new fuel to reactor refueling temperatures in such a way that the fuel is heated from the top down so that fuel element cladding failure due to thermal expansions is avoided. (U.S.)

  19. Designing a Physical Security System for Risk Reduction in a Hypothetical Nuclear Facility

    International Nuclear Information System (INIS)

    Saleh, A.A.; Abd Elaziz, M.

    2017-01-01

    Physical security in a nuclear facility means detection, prevention and response to threat, the ft, sabotage, unauthorized access and illegal transfer involving radioactive and nuclear material. This paper proposes a physical security system designing concepts to reduce the risk associated with variant threats to a nuclear facility. This paper presents a study of the unauthorized removal and sabotage in a hypothetical nuclear facility considering deter, delay and response layers. More over, the study involves performing any required upgrading to the security system by investigating the nuclear facility layout and considering all physical security layers design to enhance the weakness for risk reduction

  20. Renovated Korean nuclear safety and security system: A review and suggestions to successful settlement

    Energy Technology Data Exchange (ETDEWEB)

    Chung, W. S.; Yun, S. W.; Lee, D. S. [Korea Atomic Energy Research Inst., Dukjin-dong 150, Yusung-gu, Daejon, R.O., 305-353 (Korea, Republic of); Go, D. Y. [Kyung Hee Univ., Kyung Hee daero 26, Dongdaemoon-gu, Seoul, R.O., 130-701 (Korea, Republic of)

    2012-07-01

    Questions of whether past nuclear regulatory body of Korea is not a proper system to monitor and check the country's nuclear energy policy and utilization have been raised. Moreover, a feeling of insecurity regarding nuclear safety after the nuclear accident in Japan has spread across the public. This has stimulated a renovation of the nuclear safety regime in Korea. The Nuclear Safety and Security Commission (NSSC) was launched on October 26, 2011 as a regulatory body directly under the President in charge of strengthening independence and nuclear safety. This was a meaningful event as the NSSC it is a much more independent regulatory system for Korea. However, the NSSC itself does not guarantee an enhanced public acceptance of the nuclear policy and stable use nuclear energy. This study introduces the new NSSC system and its details in terms of organization structure, appropriateness of specialty, budget stability, and management system. (authors)

  1. A systems analysis approach to nuclear facility siting

    International Nuclear Information System (INIS)

    Gros, J.G.; Avenhaus, R.; Linnerooth, J.; Pahner, P.D.; Otway, H.J.

    1975-01-01

    An attempt is made to demonstrate an application of the techniques of systems analysis, which have been successful in solving a variety of problems, to nuclear facility siting. Within the framework of an overall regional land-use plan, a methodology for establishing the acceptability of a combination of site and facility is discussed. The consequences (e.g. the energy produced, thermal and chemical discharges, radioactive releases, aeshetic values, etc.) of the site-facility combination are identified and compared with formalized criteria in order to ensure 'legal acceptability'. Failure of any consequences to satisfy standard requirements results in a feedback channel which works to effect design changes in the facility. When 'legal acceptability' has been assured, the project enters the public sector for consideration. The responses of individuals and of various interested groups to the external attributes of the nuclear facility gradually emerge. The criteria by which interest groups judge technological advances reflect both their rational assessment and unconscious motivations. This process operates on individual, group, societal and international levels and may result in two basic feedback loops: one which might act to change regulatory criteria; the other which might influence facility design or site selection. Such reactions and responses on these levels result in a continuing process of confrontation, collaborative interchange and possible resolution in the direction of an acceptable solution. Finally, a Paretian approach to optimizing the site-facility combination is presented for the case where there are several possible combinations of site and facility. A hypothetical example of the latter is given, based upon typical preference functions determined for four interest groups. The research effort of the IIASA Energy Systems Project and the Joint IAEA/IIASA Research Project in the area of nuclear siting is summarized. (author)

  2. Debris removal system for a nuclear fuel assembly

    International Nuclear Information System (INIS)

    Cooper, F.W. Jr.; Dailey, G.F.

    1987-01-01

    A system is described for working on an elongated nuclear fuel assembly suspended vertically and submerged in a spent fuel pool having fuel assembly racks at the bottom. The system comprises a work platform disposable in the pool and adapted to be supported on the fuel assembly racks. The platform has an opening disposed in registry with a selected one of the underlying racks; guide means carried by the platform for guiding the suspended fuel assembly into the opening and the selected rack to accommodate vertical movement of the fuel assembly into and out of the rack to make different portions of the fuel assembly accessible from the platform; and tool manipulating apparatus disposable on the platform adjacent to the opening, the tool manipulating apparatus including a tool carriage. Tool holders for respectively holding associated tools. Each of the tool holders is mounted on the tool carriage for reciprocating movement with respect along a predetermined axis between extended and retracted conditions

  3. Modular sludge collection system for a nuclear steam generator

    International Nuclear Information System (INIS)

    Appleman, R.H.; Bein, J.D.; Powasaki, F.S.

    1986-01-01

    A sludge collection system is described for a vertically oriented nuclear steam generator wherein vapors produced in the steam generator pass through means for separating entrained liquid from the vapor prior to the vapor being discharged from the steam generator. The sludge collection system comprises: an upwardly open chamber for collecting the separated liquid and feedwater entering the steam generator; upwardly open sludge collecting containers positioned within the chamber, wherein each of the containers includes a top rim encompassing an opening leading to the interior of each container; generally flat, perforated covers, each of the covers being positioned over one of the openings such that a gap is formed between the cover and the adjacent top rim; sludge agitating means on at least one of the containers; and sludge removal means on at least one of the containers

  4. A fundamental study on nuclear power plant diagnosis system

    International Nuclear Information System (INIS)

    Yoshimura, Sei-ichi; Fujimoto, Junzo

    1987-01-01

    Diagnosis of nuclear power plant is a large application field of knowledge engineering. But, the study examples are few and the diagnosis method is not established yet. This report describes the diagnosis method using cross correlation coefficients and describes the knowledge acquisition method of undefined transients in order to enhance the system performance. The usefulness of the system was verified by putting some data into the system. Main results are as follows. (1) Diagnosis method. Some transients are selected by the first judgement and one of them is identified by the second judgement using the cross correlation. (2) Knowledge aquisition method. When putting new data into the knowledge-base, the system indicates the inconsistency by arranging the aquired data, and the operators input new transient names and corresponding manipulation methods after analyzing the indicated results. (3) Usefulness of the system. Freedwater controller failures(2 transients), 2 recirculation pumps trip and a dummy datum combined 2 transients(one is feedwater controller failure and one is 2 recirculation pumps trip) were put into the system. It was proved that the system identified the transients correctly and it indicated the first hit and the inconsisency of the transients in the course of knowledge acquisition. (author)

  5. Elements of a national emergency response system for nuclear accidents

    International Nuclear Information System (INIS)

    Dickerson, M.H.

    1987-01-01

    The purpose of this paper is to suggest elements for a general emergency response system, employed at a national level, to detect, evaluate and assess the consequences of a radiological atmospheric release occurring within or outside of national boundaries. These elements are focused on the total aspect of emergency response ranging from providing an initial alarm to a total assessment of the environmental and health effects. Elements of the emergency response system are described in such a way that existing resources can be directly applied if appropriate; if not, newly developed or an expansion of existing resources can be employed. The major thrust of this paper is toward a philosophical discussion and general description of resources that would be required to implementation. If the major features of this proposal system are judged desirable for implementation, then the next level of detail can be added. The philosophy underlying this paper is preparedness - preparedness through planning, awareness and the application of technology. More specifically, it is establishment of reasonable guidelines including the definition of reference and protective action levels for public exposure to accidents involving nuclear material; education of the public, government officials and the news media; and the application of models and measurements coupled to computer systems to address a series of questions related to emergency planning, response and assessment. It is the role of a proven national emergency response system to provide reliable, quality-controlled information to decision makers for the management of environmental crises

  6. Control system for a nuclear power producing unit

    International Nuclear Information System (INIS)

    Durrant, O.W.

    1978-01-01

    The invention provides in a control system for a nuclear power producing unit comprising a pressurized water reactor, a once-through steam generator provided with feedwater supply means, a turbine-generator supplied with steam from the steam generator and means maintaining a flow of pressurized water through the reactor and steam generator. The combination comprising; means generating a feed forward control signal proportional to the desired power output of the power producing unit, a second means for adjusting the reactor heat release, a third means for adjusting the rate of flow of feedwater to the steam generator, the second and third means solely responsive to and operated in parallel from the feed forward control signal whereby the reactor heat release and the rate of flow of feedwater to the steam generator are each maintained in a discrete functional relationship to the feed forward control signal

  7. Nuclear fuel cycle system analysis

    International Nuclear Information System (INIS)

    Ko, W. I.; Kwon, E. H.; Kim, S. G.; Park, B. H.; Song, K. C.; Song, D. Y.; Lee, H. H.; Chang, H. L.; Jeong, C. J.

    2012-04-01

    The nuclear fuel cycle system analysis method has been designed and established for an integrated nuclear fuel cycle system assessment by analyzing various methodologies. The economics, PR(Proliferation Resistance) and environmental impact evaluation of the fuel cycle system were performed using improved DB, and finally the best fuel cycle option which is applicable in Korea was derived. In addition, this research is helped to increase the national credibility and transparency for PR with developing and fulfilling PR enhancement program. The detailed contents of the work are as follows: 1)Establish and improve the DB for nuclear fuel cycle system analysis 2)Development of the analysis model for nuclear fuel cycle 3)Preliminary study for nuclear fuel cycle analysis 4)Development of overall evaluation model of nuclear fuel cycle system 5)Overall evaluation of nuclear fuel cycle system 6)Evaluate the PR for nuclear fuel cycle system and derive the enhancement method 7)Derive and fulfill of nuclear transparency enhancement method The optimum fuel cycle option which is economical and applicable to domestic situation was derived in this research. It would be a basis for establishment of the long-term strategy for nuclear fuel cycle. This work contributes for guaranteeing the technical, economical validity of the optimal fuel cycle option. Deriving and fulfillment of the method for enhancing nuclear transparency will also contribute to renewing the ROK-U.S Atomic Energy Agreement in 2014

  8. Fluid shut-down system for a nuclear reactor

    International Nuclear Information System (INIS)

    Barclay, F.W.; Frey, J.R.; Wilson, J.N.; Besant, R.W.

    1975-01-01

    A nuclear reactor shut-down system is described which comprises a fluidic vortex valve for releasably maintaining a liquid neutron poison outside of the reactor core, the poison being contained by a reservoir and biased by pressure for flow into poison tubes within the reactor. The upper ends of the poison tubes communicate with the supply port of the vortex valve. A continuous gas flow into the control port maintains normal controlled operation. Shut-down is effected by interruption of the control input. One embodiment comprises three groups of poison tubes and one vortex valve associated with each group wherein shut-down is effected by poison release in two out of the three groups. Preferably, each vortex valve comprises three control ports which operate on a ''voting'' or two-out-of-three basis. (Official Gazette)

  9. Simulation of a Nuclear Steam Supply System (NSSS) of a PWR nuclear power plant. Simulacao do sistema nuclear de geracao de vapor de uma central PWR

    Energy Technology Data Exchange (ETDEWEB)

    Reis Martins Junior, L.L. dos.

    1980-01-01

    The following work intends to perform the digital simulation, of the Nuclear Steam Supply System (NSSS) of a PWR nuclear power plant for control systems design and analysis purposes. There are mathematical models for the reactor, the steam generator, the pressurizer and for transport lags of the coolant in the primary circuit. Nevertheless no one control system has been considered to permit any user the inclusion in the more convenient way of the desired control systems' models. The characteristics of the system in consideration are fundamentally equal to the ones of Almirante Alvaro Alberto Nuclear Power Plant, Unit I (Angra I) obtained in the Final Safety Analysis Report at Comissao Nacional de Energia Nuclear. (author).

  10. Nuclear reactor monitoring system

    International Nuclear Information System (INIS)

    Drummond, C.N.; Bybee, R.T.; Mason, F.L.; Worsham, H.J.

    1976-01-01

    The invention pertains to an improved monitoring system for the neutron flux in a nuclear reactor. It is proposed to combine neutron flux detectors, a thermoelement, and a background radiation detector in one measuring unit. The spatial arrangement of these elements is fixed with great exactness; they are enclosed by an elastic cover and are brought into position in the reactor with the aid of a bent tube. The arrangement has a low failure rate and is easy to maintain. (HP) [de

  11. Nuclear reactor shutdown system

    International Nuclear Information System (INIS)

    Mangus, J.D.; Cooper, M.H.

    1982-01-01

    An improved nuclear reactor shutdown system is described comprising a temperature sensitive device connected to control the electric power supply to a magnetic latch holding a body of a neutron absorbing material. The temperature sensitive device is exposed to the reactor coolant so that when the reactor coolant temperature rises above a specific level, the temperature sensitive device will cause deenergization of the magnetic latch to allow the body of neutron absorbing material to enter the reactor core. (author)

  12. A Java-based data acquisition system for nuclear physics

    International Nuclear Information System (INIS)

    Swartz, K.B.; Visser, D.W.; Baris, J.M.

    2001-01-01

    Jam is a Java-based user-friendly data acquisition and analysis system developed for CAMAC-based nuclear physics experiments. The system is menu-driven and has been designed to minimize the expertise needed to perform the essential tasks necessary to collect and sort data. The front-end hardware is VME based and includes a MVME167 running VxWorks, which is networked to a Sun workstation. The sorting, display, and control routines are all written in Java, and the front-end code is written in C. With a Sparc 5 workstation, events with 10 parameters, 15 histograms, and 10 gate checks the system can collect and sort data up to event rates of 1 kHz. By only sorting a fraction of the events, but storing all events, it can be run at the front-end limit of 10 kHz. Java's promise of platform independence has been found to be realistic, and Jam has been used with no modifications to sort offline on multiple platforms. Jam has a modular design allowing it to be easily modified. For example, Jam has an interface to allow users to write their own fitting routines. This article discusses the system's design and performance, as well as some advantages and disadvantages of using Java

  13. Fire protection system management in nuclear facilities: strengthening factor of integrated management system - a case study

    International Nuclear Information System (INIS)

    Santos, Joao Regis dos

    2005-01-01

    The present study investigated and analyzed the importance of a system of integrated safety manage, environment and health in a nuclear installation, having as perspective, the fire protection manage. The inquiry was made using a qualitative research involving a case study, where the considered environment was the Reconversion and UO 2 Plant of the Industrias Nucleares do Brasil (INB), located in Resende, Rio de Janeiro and the studied population, the managers and the staff directly involved with the aspects related to the safety of the industrial complex of the related company. The motivation for the research was the search of a bigger interaction of the questions related to the safety, environment and health in the nuclear industry having, as axle of the investigation, the fire protection. As a result, it was observed that in a nuclear installation, although dealing with diversified safety processes, integration is possible and necessary, since there are more reasons for integration than otherwise. (author)

  14. A shielded measurement system for irradiated nuclear fuel measurements

    International Nuclear Information System (INIS)

    Mosby, W.R.; Aumeier, S.E.; Klann, R.T.

    1999-01-01

    The US Department of Energy (DOE) is driving a transition toward dry storage of irradiated nuclear fuel (INF), toward characterization of INF for final disposition, and toward resumption of measurement-based material control and accountability (MC and A) efforts for INF. For these reasons, the ability to efficiently acquire radiological measurements of INF in a dry environment is important. The DOE has recently developed a guidance document proposing MC and A requirements for INF. The intent of this document is to encourage the direct measurement of INF on inventory within DOE. The guidance document reinforces and clarifies existing material safeguards requirements as they pertain to INF. Validation of nuclear material contents of non-self-protecting INF must be accomplished by direct measurement, application of validated burnup codes using qualified initial fissile content, burnup data, and age or by other valid means. The fuel units must remain intact with readable identification numbers. INF may be subject to periodic inventories with visual item accountability checks. Quantitative measurements may provide greater assurance of the integrity of INF inventories at a lower cost and with less personnel exposure than visual item accountability checks. Currently, several different approaches are used to measure the radiological attributes of INF. Although these systems are useful for a wide variety of applications, there is currently no relatively inexpensive measurement system that is readily deployable for INF measurements for materials located in dry storage. The authors present the conceptual design of a shielded measurement system (SMS) that could be used for this purpose. The SMS consists of a shielded enclosure designed to house a collection of measurement systems to allow measurements on spent fuel outside of a hot cell. The phase 1 SMS will contain 3 He detectors and ionization chambers to allow for gross neutron and gamma-ray measurements. The phase 2 SMS

  15. Safety requirements for a nuclear power plant electric power system

    Energy Technology Data Exchange (ETDEWEB)

    Fouad, L F; Shinaishin, M A

    1988-06-15

    This work aims at identifying the safety requirements for the electric power system in a typical nuclear power plant, in view of the UNSRC and the IAEA. Description of a typical system is provided, followed by a presentation of the scope of the information required for safety evaluation of the system design and performance. The acceptance and design criteria that must be met as being specified by both regulatory systems, are compared. Means of implementation of such criteria as being described in the USNRC regulatory guides and branch technical positions on one hand and in the IAEA safety guides on the other hand are investigated. It is concluded that the IAEA regulations address the problems that may be faced with in countries having varying grid sizes ranging from large stable to small potentially unstable ones; and that they put emphasis on the onsite standby power supply. Also, in this respect the Americans identify the grid as the preferred power supply to the plant auxiliaries, while the IAEA leaves the possibility that the preferred power supply could be either the grid or the unit main generator depending on the reliability of each. Therefore, it is found that it is particularly necessary in this area of electric power supplies to deal with the IAEA and the American sets of regulations as if each complements and not supplements the other. (author)

  16. Soft systems methodology as a systemic approach to nuclear safety management

    Energy Technology Data Exchange (ETDEWEB)

    Vieira Neto, Antonio S.; Guilhen, Sabine N.; Rubin, Gerson A.; Caldeira Filho, Jose S.; Camargo, Iara M.C., E-mail: asvneto@ipen.br, E-mail: snguilhen@ipen.br, E-mail: garubin@ipen.br, E-mail: jscaldeira@ipen.br, E-mail: icamargo@ipen.br [Instituto de Pesquisas Energeticas e Nucleares (IPEN/CNE-SP), Sao Paulo, SP (Brazil)

    2017-07-01

    Safety approach currently adopted by nuclear installations is built almost exclusively upon analytical methodologies based, mainly, on the belief that the properties of a system, such as its safety, are given by its constituent parts. This approach, however, does not properly address the complex dynamic interactions between technical, human and organizational factors occurring within and outside the organization. After the accident at Fukushima Daiichi nuclear power plant in March 2011, experts of the International Atomic Energy Agency (IAEA) recommended a systemic approach as a complementary perspective to nuclear safety. The aim of this paper is to present an overview of the systems thinking approach and its potential use for structuring socio technical problems involved in the safety of nuclear installations, highlighting the methodologies related to the soft systems thinking, in particular the Soft Systems Methodology (SSM). The implementation of a systemic approach may thus result in a more holistic picture of the system by the complex dynamic interactions between technical, human and organizational factors. (author)

  17. Soft systems methodology as a systemic approach to nuclear safety management

    International Nuclear Information System (INIS)

    Vieira Neto, Antonio S.; Guilhen, Sabine N.; Rubin, Gerson A.; Caldeira Filho, Jose S.; Camargo, Iara M.C.

    2017-01-01

    Safety approach currently adopted by nuclear installations is built almost exclusively upon analytical methodologies based, mainly, on the belief that the properties of a system, such as its safety, are given by its constituent parts. This approach, however, does not properly address the complex dynamic interactions between technical, human and organizational factors occurring within and outside the organization. After the accident at Fukushima Daiichi nuclear power plant in March 2011, experts of the International Atomic Energy Agency (IAEA) recommended a systemic approach as a complementary perspective to nuclear safety. The aim of this paper is to present an overview of the systems thinking approach and its potential use for structuring socio technical problems involved in the safety of nuclear installations, highlighting the methodologies related to the soft systems thinking, in particular the Soft Systems Methodology (SSM). The implementation of a systemic approach may thus result in a more holistic picture of the system by the complex dynamic interactions between technical, human and organizational factors. (author)

  18. A fault diagnosis system for nuclear power plant operation

    International Nuclear Information System (INIS)

    Ohga, Yukiharu; Hayashi, Yoshiharu; Yuchi, Hiroyuki; Utena, Shunsuke; Maeda, Akihiko

    2002-01-01

    A fault diagnosis system has been developed to support operators in nuclear power plants. In the system various methods are combined to get a diagnosis result which provides better detection sensitivity and result reliability. The system is composed of an anomaly detection part with diagnosis modules, an integration part which obtains the diagnosis result by combining results from each diagnosis module, and a prediction part with state prediction and estimation modules. For the anomaly detection part, three kinds of modules are prepared: plant signal processing, early fault detection and event identification modules. The plant signal processing module uses wavelet transform and chaos technologies as well as fast Fourier transform (FFT) to analyze vibration sensor signals and to detect signal anomaly. The early fault detection module uses the neural network model of a plant subprocess to estimate the process variable values assuming normal conditions, and to detect an anomaly by comparing the measured and estimated values. The event identification module identifies the kind of occurring event by using the neural network and knowledge processing. In the integration part the diagnosis is performed by using knowledge processing. The knowledge for diagnosis is structured based on the means-ends abstraction hierarchy to simplify knowledge input and maintenance. In the prediction part, the prediction module predicts the future changes of process variables and plant interlock statuses and the estimation module estimates the values of unmeasurable variables. A prototype system has been developed and the system performance was evaluated. The evaluation results show that the developed technologies are effective to improve the human-machine system for plant operation. (author)

  19. A semiclassical treatment of correlation energy for nuclear systems

    International Nuclear Information System (INIS)

    Nielsen, M.

    1988-01-01

    Starting with the separation of the many-body density operator in two parts, one describing the one-body aspects of the full density and the other containing all dynamic correlations information, the semiclassical approximation for the system correlation energy, was calculated. It is showm that, in this case, the Gaussian Wave Packets Phase Space Representation is more convenient than the Wely-Wigner Rrepresentation for the analysis of the semiclassical correlation energy. Using a phenomenological interaction, the correlation energy to the nuclear matter and some simmetric finite nucleus was calculated. The Fermi Surface Diffusivity, was also calculated. Finally, from the relation between this theory and the pertubation theory, we have done some considerations about the viability on the local densities expansion for energy functionals. (author) [pt

  20. Nuclear reactor safety systems

    International Nuclear Information System (INIS)

    Ball, R.M.; Roberts, R.C.

    1980-01-01

    A safety system for shutting down a nuclear reactor under overload conditions is described. The system includes a series of parallel-connected computer memory type look-up tables each of which receives data on a particular reactor parameter and in each of which a precalculated functional value for that parameter is stored indicative of the percentage of maximum reactor load that the parameter contributes. The various functional values corresponding to the actual measured parameters are added together to provide a control signal used to shut down the reactor under overload conditions. (U.K.)

  1. Nuclear reactor safety system

    International Nuclear Information System (INIS)

    Ball, R.M.; Roberts, R.C.

    1983-01-01

    The invention provides a safety system for a nuclear reactor which uses a parallel combination of computer type look-up tables each of which receives data on a particular parameter (from transducers located in the reactor system) and each of which produces the functional counterpart of that particular parameter. The various functional counterparts are then added together to form a control signal for shutting down the reactor. The functional counterparts are developed by analysis of experimental thermal and hydraulic data, which are used to form expressions that define safe conditions

  2. A system of nuclear material accountancy in the JAERI

    International Nuclear Information System (INIS)

    Kase, Toshio; Nishizawa, Satoshi; Takahashi, Yoshindo

    1983-05-01

    Pursuant to the domestic law and regulations revised in 1978 as to be conformed to the requirements specified in the Safeguards Agreement under the Non-Proliferation Treaty (NPT), the JAERI's system of nuclear material accountancy has been effectively developed. The system of accountancy in the JAERI is based on the information treatment by the computer. The data of nuclear material are retained batchwisely together with their complicate history reflected the inventory changes and other transactions. The reports represented these data are prepared and submitted to the IAEA through the Government every month. The inspections are frequently conducted to the JAERI to verify the material appeared in the reports. Item counting, item identification and non-destructive assay technique are brought to the verification. In some cases, seals of the Government and the IAEA are applied to the nuclear material at the inspections, as their containment measures. The surveillance camera is also installed in the facility to look whole view of reactor room and spent fuel pond. In this paper, the general safeguards application and its corresponding accountancy system on JAERI's nuclear facility are described. (author)

  3. NMC and A and nuclear criticality safety systems integration: A prospective way for enhancement of the nuclear industry facilities safety

    International Nuclear Information System (INIS)

    Ryazanov, Boris G.; Sviridov, Victor I.; Frolov, Vladimir V.; Shvedov, Maxim O.; Mclaughlin, Thomas P.; Pruvost, Norman L.

    2003-01-01

    A considerable body of data has now been acquired about the principles, parameters and consequences of nuclear (criticality) accidents at facilities of the atomic industry in Russia, the United States, Great Britain and Japan. The total number of such accidents stands at 22. Russian and US specialists have prepared a rather extensive survey and analysis of these accidents. The final and important section of this survey is the lessons implied by the results of analysis of these 22 accidents. Among these lessons is the necessity of unconditional enforcement of control over the movement and transformations of special nuclear materials (SNM), and in particular fissile materials, (those SNMs with criticality accident concerns) during production and processing. Inadequacies in such control have been among the causes of most of the accidents that have occurred. Nuclear materials control and accounting (MC and A) for the purpose of ensuring storage reliability and nonproliferation safeguards is a major task of nuclear facilities in any nation. MC and A systems use the latest techniques and hardware for periodic control of SNM in specifically organized material balance areas. Immediate checking, periodic inventory of SNM, and measurements of the parameters of SNM at key points are the main sources of data for these systems. Data about the presence and sites of location of SNM in material balance areas that are acquired in inventories can be used for objective assessment of the status of nuclear safety. On the other hand, the inventory itself involves performance of operations that are unlike routine process engineering, and require special consideration of nuclear safety. Use of the techniques and hardware of MC and A systems not only for purposes of storage reliability, but also to ensure nuclear safety, will reduce the risk of nuclear accidents. This paper gives a concise overview of nuclear accidents that have occurred due to inadequacies in MC and A, and demonstrates

  4. Containment hydrogen removal system for a nuclear power plant

    International Nuclear Information System (INIS)

    Callaghan, V.M.; Flynn, E.P.; Pokora, B.M.

    1984-01-01

    A hydrogen removal system (10) separates hydrogen from the containment atmosphere of a nuclear power plant using a hydrogen permeable membrane separator (30). Water vapor is removed by condenser (14) from a gas stream withdrawn from the containment atmosphere. The gas stream is then compressed by compressor (24) and cooled (28,34) to the operating temperature of the hydrogen permeable membrane separator (30). The separator (30) separates the gas stream into a first stream, rich in hydrogen permeate, and a second stream that is hydrogen depleted. The separated hydrogen is passed through a charcoal adsorber (48) to adsorb radioactive particles that have passed through the hydrogen permeable membrane (44). The hydrogen is then flared in gas burner (52) with atmospheric air and the combustion products vented to the plant vent. The hydrogen depleted stream is returned to containment through a regenerative heat exchanger (28) and expander (60). Energy is extracted from the expander (60) to drive the compressor (24) thereby reducing the energy input necessary to drive the compressor (24) and thus reducing the hydrogen removal system (10) power requirements

  5. Nuclear power system

    International Nuclear Information System (INIS)

    Yampolsky, J.S.; Cavallaro, L.; Paulovich, K.F.; Schleicher, R.W.

    1989-01-01

    This patent describes an inherently safe modular nuclear power system for producing electrical power at acceptable efficiency levels using working fluids at relatively low temperatures and pressures. The system comprising: a reactor module for heating a first fluid; a heat exchanger module for transferring heat from the first fluid to a second fluid; a first piping system effecting flow of the first fluid in a first fluid circuit successively through the reactor module and the heat exchanger module; a power conversion module comprising a turbogenerator driven by the second fluid, and means for cooling the second fluid upon emergence thereof from the turbogenerator; a second piping system comprising means for effecting flow of the second fluid in a second fluid circuit successively through the heat exchanger module and the power conversion module; and a plurality of pits for receiving the modules

  6. Draining down of a nuclear steam generating system

    International Nuclear Information System (INIS)

    Jawor, J.C.

    1987-01-01

    The method is described of draining down contained reactor-coolant water from the inverted vertical U-tubes of a vertical-type steam generator in which the upper, inverted U-shaped ends of the tubes are closed and the lower ends thereof are open. The steam generator is part of a nuclear powered steam generating system wherein the reactor coolant water is normally circulated from and back into the reactor via a loop comprising the steam generator and inlet and outlet conduits connected to the lower end of the steam generator. The method comprises continuously introducing a gas which is inert to the system and which is under pressure above atmospheric pressure into at least one of the downwardly facing open ends of each of the U-tubes from below the tube sheet in which the open ends of the U-tubes are mounted adjacent the lower end of the steam generator, while permitting the water to flow out from the open ends of the U-tubes

  7. Development of a nuclear power plant system analysis code

    International Nuclear Information System (INIS)

    Sim, Suk K.; Jeong, J. J.; Ha, K. S.; Moon, S. K.; Park, J. W.; Yang, S. K.; Song, C. H.; Chun, S. Y.; Kim, H. C.; Chung, B. D.; Lee, W. J.; Kwon, T. S.

    1997-07-01

    During the period of this study, TASS 1.0 code has been prepared for the non-LOCA licensing and reload safety analyses of the Westinghouse and the Korean Standard Nuclear Power Plants (KSNPP) type reactors operating in Korea. TASS-NPA also has been developed for a real time simulation of the Kori-3/4 transients using on-line graphical interactions. TASS 2.0 code has been further developed to timely apply the TASS 2.0 code for the design certification of the KNGR. The COBRA/RELAP5 code, a multi-dimensional best estimate system code, has been developed by integrating the realistic three-dimensional reactor vessel model with the RELAP5 /MOD3.2 code, a one-dimensional system code. Also, a 3D turbulent two-phase flow analysis code, FEMOTH-TF, has been developed using finite element technique to analyze local thermal hydraulic phenomena in support of the detailed design analysis for the development of the advanced reactors. (author). 84 refs., 27 tabs., 83 figs

  8. A system design for the nuclear material accounting reports control based on the intra-net

    International Nuclear Information System (INIS)

    Jeon, I.; Park, S. J.; Min, K. S.

    2003-01-01

    The 34 nuclear facilities, including the nuclear power plants, were on operating in Korea and the Technology Center for Nuclear Control(TCNC) has been submit the nuclear material accounting reports to the government and IAEA. At the start point of this work, all reports were controlled via manually and at now, they were controlled based on the client/server system. The fast progress of the computer and internet communication changes the environment of computing from disk operating system to web based system using internet. So, a new system to access the safeguards information and nuclear material accounting system more convenient was needed. In this thesis, a safeguards information control system including the nuclear material accounting reports at the state level based on the web was designed. The oracle RDBMS (Relational Data Base Management System) was adopted for data base management. And all users can access this program via inter-net using their own computer

  9. Assessing nuclear power plant safety and recovery from earthquakes using a system-of-systems approach

    International Nuclear Information System (INIS)

    Ferrario, E.; Zio, E.

    2014-01-01

    We adopt asystem-of-systems’ framework of analysis, previously presented by the authors, to include the interdependent infrastructures which support a critical plant in the study of its safety with respect to the occurrence of an earthquake. We extend the framework to consider the recovery of the system of systems in which the plant is embedded. As a test system, we consider the impacts produced on a nuclear power plant (the critical plant) embedded in the connected power and water distribution, and transportation networks which support its operation. The Seismic Probabilistic Risk Assessment of such system of systems is carried out by Hierarchical modeling and Monte Carlo simulation. First, we perform a top-down analysis through a hierarchical model to identify the elements that at each level have most influence in restoring safety, adopting the criticality importance measure as a quantitative indicator. Then, we evaluate by Monte Carlo simulation the probability that the nuclear power plant enters in an unsafe state and the time needed to recover its safety. The results obtained allow the identification of those elements most critical for the safety and recovery of the nuclear power plant; this is relevant for determining improvements of their structural/functional responses and supporting the decision-making process on safety critical-issues. On the test system considered, under the given assumptions, the components of the external and internal water systems (i.e., pumps and pool) turn out to be the most critical for the safety and recovery of the plant. - Highlights: • We adopt a system-of-system framework to analyze the safety of a critical plant exposed to risk from external events, considering also the interdependent infrastructures that support the plant. • We develop a hierarchical modeling framework to represent the system of systems, accounting also for its recovery. • Monte Carlo simulation is used for the quantitative evaluation of the

  10. A study of fuzzy control in nuclear scale system

    International Nuclear Information System (INIS)

    Wang Yu; Zhang Yongming; Wu Ruisheng; Du Xianbin; Liu Shixing

    2001-01-01

    The new development of the nuclear scale system which uses fuzzy control strategy is presented. Good results have been obtained in using fuzzy control to solve the problems, such as un-linearities, instabilities, time delays, which are difficultly described by formula, etc. The fuzzy variance, membership function and fuzzy rules are given, and the noise disturbances of fuzzy control and PID control are also given

  11. The Status of Development on a Web-Based Nuclear Material Accounting System at KAERI

    International Nuclear Information System (INIS)

    Lee, Byungdoo; Kim, Inchul; Lee, Seungho; Kim, Hyunjo

    2014-01-01

    The Integrated Safeguards (IS) has been applied to 10 nuclear facilities and 1 location outside facility (LOF) at the Korea Atomic Energy Research Institute (KAERI) since July 2008. One of the major changes in the implementation of safeguards under the IS is to apply the concept of a Random Interim Inspection (RII) instead of an interim inspection. The RII plan is notified within a few hours under the IS. It is thus difficult for facility operators to prepare the inspection documents within a short time if they do not periodically manage and process the nuclear material accounting data at each facility. To resolve these issues, KAERI developed a Web-based accounting system with the function of a near real-time accounting (NRTA) system to effectively and efficiently manage the nuclear material accounting data produced at the nuclear facilities and cope with a short notice inspection under the IS, called KASIS (KAeri Safeguards Information treatment System). The facility operators must input the accounting data on the inventory changes, which are the transfers of nuclear materials among the nuclear facilities and the chemical/physical composition changes, into the KASIS. KAERI also established an RFID system for controlling and managing the transfer of nuclear material and/or radioactive materials between the nuclear facilities for the purpose of nuclear safety management, and developed the nuclear material accounting system with the functions of inventory management of nuclear material at the facility level

  12. The Status of Development on a Web-Based Nuclear Material Accounting System at KAERI

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Byungdoo; Kim, Inchul; Lee, Seungho; Kim, Hyunjo [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2014-05-15

    The Integrated Safeguards (IS) has been applied to 10 nuclear facilities and 1 location outside facility (LOF) at the Korea Atomic Energy Research Institute (KAERI) since July 2008. One of the major changes in the implementation of safeguards under the IS is to apply the concept of a Random Interim Inspection (RII) instead of an interim inspection. The RII plan is notified within a few hours under the IS. It is thus difficult for facility operators to prepare the inspection documents within a short time if they do not periodically manage and process the nuclear material accounting data at each facility. To resolve these issues, KAERI developed a Web-based accounting system with the function of a near real-time accounting (NRTA) system to effectively and efficiently manage the nuclear material accounting data produced at the nuclear facilities and cope with a short notice inspection under the IS, called KASIS (KAeri Safeguards Information treatment System). The facility operators must input the accounting data on the inventory changes, which are the transfers of nuclear materials among the nuclear facilities and the chemical/physical composition changes, into the KASIS. KAERI also established an RFID system for controlling and managing the transfer of nuclear material and/or radioactive materials between the nuclear facilities for the purpose of nuclear safety management, and developed the nuclear material accounting system with the functions of inventory management of nuclear material at the facility level.

  13. Nuclear reactor sealing system

    International Nuclear Information System (INIS)

    McEdwards, J.A.

    1983-01-01

    A liquid metal-cooled nuclear reactor sealing system is disclosed. The nuclear reactor includes a vessel sealed at its upper end by a closure head. The closure head comprises at least two components, one of which is rotatable; and the two components define an annulus therebetween. The sealing system includes at least a first and second inflatable seal disposed in series in an upper portion of the annulus. The system further includes a dip seal extending into a body of insulation located adjacent a bottom portion of the closure head. The dip seal comprises a trough formed by a lower portion of one of the components, and a seal blade pendently supported from the other component and extending downwardly into the trough. A body of liquid metal is contained in the trough which submerges a portion of the seal blade. The seal blade is provided with at least one aperture located above the body of liquid metal for providing fluid communication between the annulus intermediate the dip seal and the inflatable seals, and a body of cover gas located inside the vessel. There also is provided means for introducing a purge gas into the annulus intermediate the inflatable seals and the seal blade. The purge gas is introduced in an amount sufficient to substantially reduce diffusion of radioactive cover gas or sodium vapor up to the inflatable seals. The purge gas mixes with the cover gas in the reactor vessel where it can be withdrawn from the vessel for treatment and recycle to the vessel

  14. Design of an advanced human-centered supervisory system for a nuclear fuel reprocessing system

    International Nuclear Information System (INIS)

    Riera, B.; Lambert, M.; Martel, G.

    1999-01-01

    In the field of highly automated processes, our research concerns supervisory system design adapted to supervisory and default diagnosis by human operators. The interpretation of decisional human behaviour models shows that the tasks of human operators require different information, which has repercussions on the supervisory system design. We propose an advanced human-centred supervisory system (AHCSS) which is more adapted to human-beings, because it integrates new representation of the production system,(such as functional and behavioural aspects) with the use of advanced algorithms of detection and location. Based on an approach using these new concepts, and AHCSS was created for a nuclear fuel reprocessing system. (authors)

  15. Nuclear criticality information system

    International Nuclear Information System (INIS)

    Koponen, B.L.; Hampel, V.E.

    1981-01-01

    The nuclear criticality safety program at LLNL began in the 1950's with a critical measurements program which produced benchmark data until the late 1960's. This same time period saw the rapid development of computer technology useful for both computer modeling of fissile systems and for computer-aided management and display of the computational benchmark data. Database management grew in importance as the amount of information increased and as experimental programs were terminated. Within the criticality safety program at LLNL we began at that time to develop a computer library of benchmark data for validation of computer codes and cross sections. As part of this effort, we prepared a computer-based bibliography of criticality measurements on relatively simple systems. However, it is only now that some of these computer-based resources can be made available to the nuclear criticality safety community at large. This technology transfer is being accomplished by the DOE Technology Information System (TIS), a dedicated, advanced information system. The NCIS database is described

  16. A study on the nuclear computer codes installation and management system

    International Nuclear Information System (INIS)

    Kim, Yeon Seung; Huh, Young Hwan; Kim, Hee Kyung; Kang, Byung Heon; Kim, Ko Ryeo; Suh, Soong Hyok; Choi, Young Gil; Lee, Jong Bok

    1990-12-01

    From 1987 a number of technical transfer related to nuclear power plant had been performed from C-E for YGN 3 and 4 construction. Among them, installation and management of the computer codes for YGN 3 and 4 fuel and nuclear steam supply system was one of the most important project. Main objectives of this project are to establish the nuclear computer code management system, to develop QA procedure for nuclear codes, to secure the nuclear code reliability and to extend techanical applicabilities including the user-oriented utility programs for nuclear codes. Contents of performing the project in this year was to produce 215 transmittal packages of nuclear codes installation including making backup magnetic tape and microfiche for software quality assurance. Lastly, for easy reference about the nuclear codes information we presented list of code names and information on the codes which were introduced from C-E. (Author)

  17. Planning for a space infrastructure for disposal of nuclear space power systems

    International Nuclear Information System (INIS)

    Angelo, J. Jr.; Albert, T.E.; Lee, J.

    1989-01-01

    The development of safe, reliable, and compact power systems is vital to humanity's exploration, development, and, ultimately, civilization of space. Nuclear power systems appear to present to offer the only practical option of compact high-power systems. From the very beginning of US space nuclear power activities, safety has been a paramount requirement. Assurance of nuclear safety has included prelaunch ground handling operations, launch, and space operations of nuclear power sources, and more recently serious attention has been given to postoperational disposal of spent or errant nuclear reactor systems. The purpose of this paper is to describe the progress of a project to utilize the capabilities of an evolving space infrastructure for planning for disposal of space nuclear systems. Project SIREN (Search, Intercept, Retrieve, Expulsion - Nuclear) is a project that has been initiated to consider post-operational disposal options for nuclear space power systems. The key finding of Project SIREN was that although no system currently exists to affect the disposal of a nuclear space power system, the requisite technologies for such a system either exist or are planned for part of the evolving space infrastructure

  18. 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.)

  19. A Study on the Safety Evaluation of Real-Time Operating System in Nuclear Power Plants

    International Nuclear Information System (INIS)

    Kim, Hyung Tae; Jeong, Choong Heui; Kim, Dail Il

    2008-01-01

    Along with the digitalisation of the nuclear Instrumentation and Control (I and C) system, Real-Time Operating System (RTOS) is being widely used. The RTOS used in nuclear I and C system should satisfy strict performance requirements and resolve various technical issues under complicated conditions. In this regard a careful safety evaluation of RTOS is important for the safety of Nuclear Power Plants. The objective of this study is to provide a guideline for safety evaluation of RTOS appropriate to the nuclear I and C system. In this paper, we suggest evaluation approach for the RTOS

  20. A Study on the Safety Evaluation of Real-Time Operating System in Nuclear Power Plants

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Hyung Tae; Jeong, Choong Heui; Kim, Dail Il [Korea Institute of Nuclear Safety, Daejeon (Korea, Republic of)

    2008-10-15

    Along with the digitalisation of the nuclear Instrumentation and Control (I and C) system, Real-Time Operating System (RTOS) is being widely used. The RTOS used in nuclear I and C system should satisfy strict performance requirements and resolve various technical issues under complicated conditions. In this regard a careful safety evaluation of RTOS is important for the safety of Nuclear Power Plants. The objective of this study is to provide a guideline for safety evaluation of RTOS appropriate to the nuclear I and C system. In this paper, we suggest evaluation approach for the RTOS.

  1. A Romanian energy system model and a nuclear reduction strategy

    DEFF Research Database (Denmark)

    Gota, Dan-Ioan; Lund, Henrik; Miclea, Liviu

    2011-01-01

    This paper presents a model of the Romanian energy system with the purpose of providing a tool for the analysis of future sustainable energy strategies. The model represents the total national energy system and is detailed to the level of hourly demand and production in order to be able to analyse...... the consequences of adding fluctuating renewable energy sources to the system. The model has been implemented into the EnergyPLAN tool and has been validated in order to determine if it can be used as a reference model for other simulations. In EnergyPLAN, two different future strategy scenarios for the Romanian...... energy system are compared to the actual data of Romania of year 2008. First, a comparison is made between the 2008 model and the 2013 strategy scenario corresponding to the grid of the Romanian transmission system operator (TSO) Transelectrica. Then, a comparison is made to a second strategy scenario...

  2. The nuclear disaster management system in Taiwan: a case study of the third (Maanshan) nuclear power plant.

    Science.gov (United States)

    Yang, Yung-Nane

    2016-07-01

    This paper explores the effectiveness of the nuclear disaster management system in Taiwan via a review of the third (Maanshan) nuclear power plant. In doing so, the Fukushima Daiichi nuclear disaster in Japan on 11 March 2011 is reviewed and compared with the situation in Taiwan. The latter's nuclear disaster management system is examined with respect to three key variables: information; mobilisation; and inter-organisational cooperation. In-depth interviews with 10 policy stakeholders with different backgrounds serve as the research method. The results point up the need for improvement in all dimensions. In addition, they highlight three principal problems with the nuclear disaster management system: (i) it might not be possible to provide first-hand nuclear disaster information immediately to the communities surrounding the Maanshan facility in Pingtung County, southern Taiwan; (ii) the availability of medical resources for treating radiation in Hengchun Township is limited; and (iii) the inter-organisational relationships for addressing nuclear disasters need to be strengthened. Hence, cooperation among related organisations is necessary. © 2016 The Author(s). Disasters © Overseas Development Institute, 2016.

  3. Selion offers a unique system for treating liquid nuclear waste

    Energy Technology Data Exchange (ETDEWEB)

    Tusa, E.; Kurki, H. [ed.

    1998-07-01

    Studies on the treatment of liquid nuclear waste have been conducted actively in the IVO Group since the early 1980s. And the work has borne fruit: the CsTreat and SrTreat ion exchange products, developed by the IVO Group, were launched three years ago. The ion exchangers have already been in full use at a number of sites throughout the world. In addition, they are currently being tested at many nuclear research institutes and power plants in the USA, Japan and Europe

  4. A nuclear power enterprise debt management system construction Based on Sanmen Nuclear Power Co., LTD, debt risk management case analysis

    International Nuclear Information System (INIS)

    Wu Yan; Liu Shuqing

    2010-01-01

    Building nuclear power enterprises need huge investment , often tens of billions RMB. How to do a good job in corporate debt risk management, becoming powerful large-scale development of nuclear power ,ensuring the supply of funds and existing debt service in the process of large-scale development of nuclear power ,is an important task. In this paper, managing the company's debt is very urgent and necessary through analysis of SMNPC financing and debt structure; through the analysis of SMNPC's debt risk management , the authors would like to explore how to build up the framework of the debt management under the large-scale development of nuclear power construction . Nuclear power enterprises need to strengthen supervision mechanism and internal control,build-up and perfect all-round debt risk manage system, keep watch on debt risk in order to ensure preservation and increment of the value of state assets. (authors)

  5. Scottish Nuclear's information systems strategy

    International Nuclear Information System (INIS)

    Inglis, P.

    1991-01-01

    Scottish Nuclear, the company which has owned and operated Scotland's nuclear power generating capacity since privatization, inherited a substantial amount of computer hardware and software from its predecessor, the South of Scotland Electricity Board. Each of the two power stations, Torness and Hunterston, were using Digital Vax clusters as the Scottish Nuclear company was formed. This had a major influence on the information systems strategy which has subsequently been adopted. (UK)

  6. Nuclear reactor refueling system

    International Nuclear Information System (INIS)

    Wade, E.E.

    1978-01-01

    A system for transferring fuel assemblies between a nuclear reactor core and a fuel storage area while the fuel assembies remain completely submerged in a continuous body of coolant is described. The system comprises an in-vessel fuel transfer machine located inside the reactor vessel and an ex-vessel fuel transfer machine located in a fuel storage tank. The in-vessel fuel transfer machine comprises two independently rotatable frames with a pivotable fuel transfer apparatus disposed on the lower rotatable frame. The ex-vessel fuel transfer machine comprises one frame with a pivotable fuel transfer apparatus disposed thereon. The pivotable apparatuses are capable of being aligned with each other to transfer a fuel assembly between the reactor vessel and fuel storage tank while the fuel assembly remains completely submerged in a continuous body of coolant. 9 claims, 7 figures

  7. Simulation for transient stability study of the Taiwan power system - a nuclear majority system

    International Nuclear Information System (INIS)

    Huang, J.C.C.

    1984-01-01

    A transient stability program was developed for the Taiwan Power Company, which has a high proportion of nuclear generation in its power system. This program offers a new territory to investigate nuclear plant effects on the power system transient stability. This program also provides a high speed tool for the Taipower system operational planning. A generalized procedure of synchronous machine modeling for a large-scale stability study is presented. The merits and weaknesses of machine modeling can be comprehended through each item of this procedure. Three types of nonlinear synchronous machine modeling implemented into this stability program are derived by following this procedure. A robust subroutine was derived to perform the fourth order Runge-Kutta integration method, making the software programming neat and systematical. For simulating the nuclear plant influence on the system, this program implemented an additional four functions: load-limit operation simulated by a low-value gate in the governor model, bypass valve capacity monitored by sending out a warning message, rotor overspeed protection relay, and generator anti-motoring relay

  8. Innovative nuclear energy systems roadmap

    International Nuclear Information System (INIS)

    2007-12-01

    Developing nuclear energy that is sustainable, safe, has little waste by-product, and cannot be proliferated is an extremely vital and pressing issue. To resolve the four issues through free thinking and overall vision, research activities of 'innovative nuclear energy systems' and 'innovative separation and transmutation' started as a unique 21st Century COE Program for nuclear energy called the Innovative Nuclear Energy Systems for Sustainable Development of the World, COE-INES. 'Innovative nuclear energy systems' include research on CANDLE burn-up reactors, lead-cooled fast reactors and using nuclear energy in heat energy. 'Innovative separation and transmutation' include research on using chemical microchips to efficiently separate TRU waste to MA, burning or destroying waste products, or transmuting plutonium and other nuclear materials. Research on 'nuclear technology and society' and 'education' was also added in order for nuclear energy to be accepted into society. COE-INES was a five-year program ending in 2007. But some activities should be continued and this roadmap detailed them as a rough guide focusing inventions and discoveries. This technology roadmap was created for social acceptance and should be flexible to respond to changing times and conditions. (T. Tanaka)

  9. Proposal of a national system to supervise nuclear installations out of international safeguards

    International Nuclear Information System (INIS)

    Rosa, L.P.

    1990-01-01

    It is proposed a national system to safeguard, supervise and inspect nuclear facilities in Brazil, apart from international safeguards. It discusses also the military nuclear activities and the uranium enrichment plants. The system should be controlled by Brazilian CNEN. (A.C.A.S.)

  10. Derivation of the Euler equations in Thomas-Fermi theories of a hot nuclear system

    International Nuclear Information System (INIS)

    Wang, C.

    1992-01-01

    The variational extreme condition with respect to statistical distribution of nucleons in momentum space is applied to derive the Euler equation of the nuclear density profile. The resultant Euler equation of the nuclear density profile is proven to be identical with that obtained in the usual Thomas-Fermi theories of a hot nuclear system where the variation is made with respect to the nuclear density profile. A Fermi-Dirac-type distribution appears as a result of variation in the present approach, while it is used as a given expression in obtaining the variation of the nuclear density profile in the usual Thomas-Fermi theories

  11. A reliability centered maintenance model applied to the auxiliary feedwater system of a nuclear power plant

    International Nuclear Information System (INIS)

    Araujo, Jefferson Borges

    1998-01-01

    The main objective of maintenance in a nuclear power plant is to assure that structures, systems and components will perform their design functions with reliability and availability in order to obtain a safety and economic electric power generation. Reliability Centered Maintenance (RCM) is a method of systematic review to develop or optimize Preventive Maintenance Programs. This study presents the objectives, concepts, organization and methods used in the development of RCM application to nuclear power plants. Some examples of this application are included, considering the Auxiliary Feedwater System of a generic two loops PWR nuclear power plant of Westinghouse design. (author)

  12. A review of chemical decontamination systems for nuclear facilities

    International Nuclear Information System (INIS)

    Chen, L.; Chamberlain, D.B.; Conner, C.; Vandegrift, G.F.

    1996-01-01

    With the downsizing of the Department of Energy (DOE) complex, many of its buildings and facilities will be decommissioned and dismantled. As part of this decommissioning, some form of decontamination will be required. To develop an appropriate technology for in situ chemical decontamination of equipment interiors in the decommissioning of DOE nuclear facilities, knowledge of the existing chemical decontamination methods is needed. This paper attempts to give an up-to-date review of chemical decontamination methods. This survey revealed that aqueous systems are the most widely used for the decontamination and cleaning of metal surfaces. We have subdivided the aqueous systems by types of chemical solvent: acid, alkaline permanganate, highly oxidizing, peroxide, and proprietary. Two other systems, electropolishing and foams and gels, are also described in this paper

  13. Development of a Virtual Reality (VR) system for nuclear security training

    International Nuclear Information System (INIS)

    Yamaguchi, Yasuo; Hanai, Tasuku

    2014-01-01

    The Integrated Support Center for Nuclear nonproliferation and Nuclear Security (ISCN) under the Japan Atomic Energy Agency (JAEA) began the development of Virtual Reality (VR) training system for the purpose of teaching trainees nuclear security. ISCN set up two VR training courses by 2013. One is for teaching a nuclear security system of nuclear plants. The VR training system allows trainees to have virtual experiences visiting a nuclear plant. Through these experiences, trainees are able to learn how physical protection systems work in the plant. The course focuses on learning fundamental knowledge and is suitable for trainees having little experiences in the field of nuclear security. The other is for teaching fundamental skills corresponding to a contingency plan in a Central Alarm Station (CAS) of nuclear power plant. Computers of the VR training system deploy an intrusion scenario in a virtual space. Trainees in a group sit in front of 3-D screens and play a role play game in a virtual CAS. Through the exercise, trainees are able to learn skills necessary to the contingency case of nuclear plants. In my presentation, I will introduce the two training courses, advantages and disadvantages of the VR training system, reactions of trainees and future plans. (author)

  14. Building of a CAD system for instrumentation and control system of nuclear power plant

    International Nuclear Information System (INIS)

    Ma Zhicai; Hu Chunping; Zhang Dongsheng

    2012-01-01

    Base on the analysis of deign documents and process, a database for instrumentation and control system design can be developed with a popular desktop relational database management system (RDBMS). With the RDBMS, an instrumentation and control system CAD system can be built unitizing database link feature of popular CAD software, with the function of management of design data, output of list and forms. and design of drawings. A CAD system of this kind has been used in the design practice of nuclear power plant. With this system, it is shown that, the consistency of information has been controlled and the load on the engineer has been significantly reduced. The methodology used here can also be used in the CAD system for CAP1000 and CAP1400 plant. (authors) series

  15. Development of a computerized nuclear materials control and accounting system for a fuel reprocessing plant

    International Nuclear Information System (INIS)

    Crawford, J.M.; Ehinger, M.H.; Joseph, C.; Madeen, M.L.

    1979-07-01

    A computerized nuclear materials control and accounting system (CNMCAS) for a fuel reprocessing plant is being developed by Allied-General Nuclear Services at the Barnwell Nuclear Fuel Plant. Development work includes on-line demonstration of near real-time measurement, measurement control, accounting, and processing monitoring/process surveillance activities during test process runs using natural uranium. A technique for estimating in-process inventory is also being developed. This paper describes development work performed and planned, plus significant design features required to integrate CNMCAS into an advanced safeguards system

  16. Development of a computerized nuclear materials control and accounting system for a fuel reprocessing plant

    International Nuclear Information System (INIS)

    Crawford, J.M.; Ehinger, M.H.; Joseph, C.; Madeen, M.L.

    1979-01-01

    A computerized nuclear materials control and accounting system (CNMCAS) for a fuel reprocessing plant is being developed by Allied-General Nuclear Services at the Barnwell Nuclear Fuel Plant. Development work includes on-line demonstration of near real-time measurement, measurement control, accounting, and processing monitoring/process surveillance activities during test process runs using natural uranium. A technique for estimating in-process inventory is also being developed. This paper describes development work performed and planned, plus significant design features required to integrate CNMCAS into an advanced safeguards system. 2 refs

  17. Development of a new-generation system for reloading of nuclear fuel

    International Nuclear Information System (INIS)

    Maksimov, M.; Maslov, O.; Maisyan, I.

    1995-01-01

    The modern concept of development of nuclear power, which is also reflected in the new scientific and technical documentation, moves to the forefront the general systems aspects of performing operations with nuclear fuel. It is suggested that the organizational questions of delivering, accounting for, storing, monitoring, moving, calculating overloads and mechanisms, and devices which perform manipulation with nuclear fuel, be treated as a single system

  18. Data acquisition and management system for a nuclear processes simulator

    International Nuclear Information System (INIS)

    Gonzalez M, J.A.; Santiago C, J.

    2003-01-01

    In the development of this work (Data acquisition and management system for a simulator of nuclear processes (SAMAD)), is important to mention the main modules that involve the operation of the same one. At the beginning it was necessary to contemplate the possible programming languages, as well as the compatibility and handling easiness among them. The used languages to be able to land the contemplated ideas are: C ++ , PHP, HTML, as well as the My SQL database manager. After this it was designed the database (DB), which contains the tables of each one of the components, this according to the enter file type of the RELAP5 code that will be use for each simulation, as well as, tables that will allow us to relate and to maintain the control of the information supplied to the DB. Once created the database is interacting with it through an application program based on PHP (Preprocessor). The application basically consists, in extracting the data from each one of the components to work in that moment, that is to say, to obtain the data of the enter file, as well as, to depurate the data, excluding comments. The preprocessor gives bigger easiness to place the data in the DB. Also, it was developed an graphic interface that allows to register variables to the DB, depending from the unfolding to visualize. Another application that has been implemented is the Data Collector that has as function, to obtain in a direct way the data of the display variables of the RELAP5 code, with the purpose of storing them in the DB, this will be carry out in real time and it was updated in a very small time period. (Author)

  19. Applied Nuclear Accountability Systems: A Case Study in the System Architecture and Development of NuMAC

    International Nuclear Information System (INIS)

    Campbell, Andrea Beth

    2004-01-01

    This is a case study of the NuMAC nuclear accountability system developed at a private fuel fabrication facility. This paper investigates nuclear material accountability and safeguards by researching expert knowledge applied in the system design and development. Presented is a system developed to detect and deter the theft of weapons grade nuclear material. Examined is the system architecture that includes: issues for the design and development of the system; stakeholder issues; how the system was built and evolved; software design, database design, and development tool considerations; security and computing ethics. (author)

  20. Building of a CAD system for I and C system of nuclear power plant

    International Nuclear Information System (INIS)

    Ma Zhicai; Zhang Dongsheng

    2013-01-01

    An I and C database was developed based on the design objects and properties presented in I and C design documents of nuclear power plant. With the database, a rapid-implemented CAD system for I and C engineering was designed and implemented with popular CAD software, AutoCAD and Visio, and desktop database management system, Access, to manage the design data and to automate the composing task for listings, forms and drawings. This system was applied in an engineering project for data management, document generation and drawing aid, and demonstrated its usability and efficiency. (authors)

  1. 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

  2. Nuclear Medicine National Headquarter System

    Data.gov (United States)

    Department of Veterans Affairs — The Nuclear Medicine National HQ System database is a series of MS Excel spreadsheets and Access Database Tables by fiscal year. They consist of information from all...

  3. Concerning improvement and reform towards a more effective and realisable nuclear liability legal system in Japan

    International Nuclear Information System (INIS)

    Iizuka, H.

    2006-01-01

    Japan is the only country in the world that has ever experienced being attacked by atomic bombs. Japanese people have a special feeling towards nuclear power. Japan has opted for an unlimited liability system, which is regarded as a hospitable one to victims in Japan. Under the existing unlimited liability system in Japan, however, there is a problem that nuclear operators cannot necessarily foresee the probable limit of their risks to owe. In this paper, I want to present problems of the nuclear liability legal system, and proposals for improvement and reform towards more effective and realisable system in Japan. (author)

  4. FRENDY: A new nuclear data processing system being developed at JAEA

    Science.gov (United States)

    Tada, Kenichi; Nagaya, Yasunobu; Kunieda, Satoshi; Suyama, Kenya; Fukahori, Tokio

    2017-09-01

    JAEA has provided an evaluated nuclear data library JENDL and nuclear application codes such as MARBLE, SRAC, MVP and PHITS. These domestic codes have been widely used in many universities and industrial companies in Japan. However, we sometimes find problems in imported processing systems and need to revise them when the new JENDL is released. To overcome such problems and immediately process the nuclear data when it is released, JAEA started developing a new nuclear data processing system, FRENDY in 2013. This paper describes the outline of the development of FRENDY and both its capabilities and performances by the analyses of criticality experiments. The verification results indicate that FRENDY properly generates ACE files.

  5. Establishing a nuclear medicine service within the turnkey contract system

    International Nuclear Information System (INIS)

    Horton, P.W.

    1986-01-01

    The turnkey method of developing hospitals and its effect on the provision of nuclear medicine services are described. Accommodation provided is often limited to an imaging suite and a 'hot' laboratory and additional space may be required. Alterations may also be necessary, especially for radiopharmacies to meet current standards. Major items of capital equipment are provided but these may be out of date since they were purchased when hospital building commenced. A 'shortfall' of smaller items will need to be purchased and regular supplies of radiopharmaceuticals established. Radiation protection requirements for a new service in a developing country are listed. Some suggestions for improving the value of the turnkey method are made. (author)

  6. Heat resistant materials and their feasibility issues for a space nuclear transportation system

    International Nuclear Information System (INIS)

    Olsen, C.S.

    1991-01-01

    A number of nuclear propulsion concepts based on solid-core nuclear propulsion are being evaluated for a nuclear propulsion transportation system to support the Space Exploration Initiative (SEI) involving the reestablishment of a manned lunar base and the subsequent exploration of Mars. These systems will require high-temperature materials to meet the operating conditions with appropriate reliability and safety built into these systems through the selection and testing of appropriate materials. The application of materials for nuclear thermal propulsion (NTP) and nuclear electric propulsion (NEP) systems and the feasibility issues identified for their use will be discussed. Some mechanical property measurements have been obtained, and compatibility tests were conducted to help identify feasibility issues. 3 refs., 1 fig., 4 tabs

  7. Nuclear reactor trip system

    International Nuclear Information System (INIS)

    Cook, B.M.

    1982-01-01

    Each parameter of the processes of a nuclear reactor and components operatively associated with it is monitored by a set of four like sensors. A trip system normally operates on a ''two out four'' configuration; i.e., to trip the reactor it is necessary that at least two sensors of a set sense an off-normal parameter. This assumes that all sensors are in normal operating condition. However, when a sensor is in test or is subject to maintenance or is defective or disabled, the ''two out of four''configuration would be reduced to a ''one out of three'' configuration because the affected sensor is taken out of service. This would expose the system to the possibility that a single sensor failure, which may be spurious, will cause a trip of the reactor. To prevent this, it is necessary that the affected sensor be bypassed. If only one sensor is bypassed, the system operates on a ''two out of three'' configuration. With two sensors bypassed, the sensing of an off-normal parameter by a third sensor trips the reactor. The by-pass circuit also disables the circuit coupling the by-passed sensor to the trip circuit. (author)

  8. Study of the dynamic operational characteristics of the Taiwan Power Company system - a nuclear majority system

    International Nuclear Information System (INIS)

    Yu, I.H.

    1982-01-01

    All conclusions drawn in this dissertation are based on the results of about six hundred study cases. The dynamic characteristics of the present Taiwan Power Company system are very different not only from the characteristics of any other power system in the world but also from Taipower's own history characteristics. Based on the engineers' knowledge, this dissertation takes a calculation risk approach to deal with the problems in the energy systems. Chapter I introduces the information related with the stability of the present Taipower system. Taipower operating engineers are facing the problem of committing a large amount of nuclear generation at a low base load level. The general introduction of the stability program developed for this study is described in Chapter II. In Chapter III, the processes of performing the transient stability study are explained to show how this study was performed. Critical tie flows were suggested in Chapter IV, which might help balance the nuclear generation and thermal generation at the base load level and plan the unit maintenance schedule. Several operation modes which may increase the degree of stability or minimize the number unit trippings were discussed in Chapter V. In Chapter VI, how to adjust the load shedding policy to improve the stability are discussed. The remote tripping scheme which is effective in preventing massive system blackout was studied in Chapter VII. Some broader concepts in load management are presented in Chapter VII for Taipower's management decision

  9. Nuclear medicine imaging system

    Science.gov (United States)

    Bennett, Gerald W.; Brill, A. Bertrand; Bizais, Yves J. C.; Rowe, R. Wanda; Zubal, I. George

    1986-01-01

    A nuclear medicine imaging system having two large field of view scintillation cameras mounted on a rotatable gantry and being movable diametrically toward or away from each other is disclosed. In addition, each camera may be rotated about an axis perpendicular to the diameter of the gantry. The movement of the cameras allows the system to be used for a variety of studies, including positron annihilation, and conventional single photon emission, as well as static orthogonal dual multi-pinhole tomography. In orthogonal dual multi-pinhole tomography, each camera is fitted with a seven pinhole collimator to provide seven views from slightly different perspectives. By using two cameras at an angle to each other, improved sensitivity and depth resolution is achieved. The computer system and interface acquires and stores a broad range of information in list mode, including patient physiological data, energy data over the full range detected by the cameras, and the camera position. The list mode acquisition permits the study of attenuation as a result of Compton scatter, as well as studies involving the isolation and correlation of energy with a range of physiological conditions.

  10. Work flow management systems applied in nuclear power plants management system to a new computer platform

    International Nuclear Information System (INIS)

    Rodriguez Lorite, M.; Martin Lopez-Suevos, C.

    1996-01-01

    Activities performed in most companies are based on the flow of information between their different departments and personnel. Most of this information is on paper (delivery notes, invoices, reports, etc). The percentage of information transmitted electronically (electronic transactions, spread sheets, files from word processors, etc) is usually low. The implementation of systems to control and speed up this work flow is the aim of work flow management systems. This article presents a prototype for applying work flow management systems to a specific area: the basic life cycle of a purchase order in a nuclear power plant, which requires the involvement of various computer applications: purchase order management, warehouse management, accounting, etc. Once implemented, work flow management systems allow optimisation of the execution of different tasks included in the managed life cycles and provide parameters to, if necessary, control work cycles, allowing their temporary or definitive modification. (Author)

  11. A portable meteorological station plus nuclear radiation monitoring system using a basic-8052 micro-controller

    International Nuclear Information System (INIS)

    Al-Mohamad, A.; Aghabi, S.; Weiss, C.

    2002-01-01

    a portable meteorology station capable of measuring various atmospheric parameters (mainly ambient temperature, relative humidity, atmospheric pressure, wind speed and direction) was designed and built. The physical quantities were converted to electrical signals using suitable sensors. These signals were then processed and transferred to digital values to be stored in suitable memories. A nuclear radiation alarm system was also built, on the main board, to monitor the nuclear radiation releases levels. The system consists of three main parts: control board, data acquisition board and signals conditioning board. the overall system is controlled by a BASIC-8052 micro-controller. (authors)

  12. Nuclear system vaporization

    International Nuclear Information System (INIS)

    Bougault, R.; Brou, R.; Colin, J.; Cussol, D.; Durand, D.; Le Brun, C.; Lecolley, J.F.; Lopez, O.; Louvel, M.; Nakagawa, T.; Peter, J.; Regimbart, R.; Steckmeyer, J.C.; Tamain, B.; Vient, E.; Yuasa-Nakagawa, K.; Wieloch, A.

    1998-01-01

    A particular case of the hot nuclei de-excitation is the total nuclear dislocation into light particles (n, p, d, t, 3 He and α). Such events were first observed at bombarding energies lower than 100 MeV/nucleon due to high detection performances of the INDRA multidetector. The light system Ar + Ni was studied at several bombarding energies ranging from 32 to 95 MeV/nucleon. The events associated to a total vaporization of the system occur above the energy threshold of ∼ 50 MeV/nucleon. A study of the form of these events shows that we have essentially two sources. The excitation energy of these sources may be determined by means of the kinematic properties of their de-excitation products. A preliminary study results in excitation energy values of the order 10 - 14 MeV/nucleon. The theoretical calculation based on a statistical model modified to take into account high excitation energies and excited levels in the lightest nuclei predicts that the vaporization of the two partner nuclei in the Ar + Ni system takes place when the excitation energy exceeds 12 MeV/nucleon what is qualitatively in agreement with the values deduced from calorimetric analysis

  13. Development of a utility system for nuclear reaction data file: WinNRDF

    International Nuclear Information System (INIS)

    Aoyama, Shigeyoshi; Ohbayasi, Yosihide; Masui, Hiroshi; Chiba, Masaki; Kato, Kiyoshi; Ohnishi, Akira

    2000-01-01

    A utility system, WinNRDF, is developed for charged particle nuclear reaction data of NRDF (Nuclear Reaction Data File) on the Windows interface. By using this system, we can easily search the experimental data of a charged particle nuclear reaction in NRDF than old retrieval systems on the mainframe and also see graphically the experimental data on GUI (Graphical User Interface). We adopted a mechanism of making a new index of keywords to put to practical use of the time dependent properties of the NRDF database. (author)

  14. Design of an automatic control system of a district heating nuclear plant

    International Nuclear Information System (INIS)

    Zebiri, Abderrahim.

    1980-06-01

    This paper presents the synthesis of the control system of a nuclear/oil fuelled district heating plant. Operating criteria take into account the economical background of the problem. Nuclear reactor control loops were specially conceived, due to the specific perturbations to which is submitted a district heating plant [fr

  15. US Army Nuclear Burst Detection System (NBDS)

    International Nuclear Information System (INIS)

    Glaser, R.F.

    1980-07-01

    The Nuclear Burst Detection System (NBDS) was developed to meet the Army requirements of an unattended, automatic nuclear burst reporting system. It provides pertinent data for battlefield commanders on a timely basis with high reliability

  16. Scaling a nuclear power plant as a complex system

    International Nuclear Information System (INIS)

    Zuber, N.

    2005-01-01

    This lecture summarizes and discusses the highlights of the fractional scaling analysis (FSA) and the benefits it may offer NPP technology. FSA is a quantitative methodology developed to: 1. scale time-dependent evolutionary processes involving an aggregate of interacting modules and processes (such as an NPP) and 2. integrate and organize information and data of interest to NPP design and safety analyses. The methodology is based upon three concepts: 1. fractional scaling, 2. hierarchical levels, 3. aggregate configuration. FSA is used to provide syntheses (at various hierarchical levels) and generate quantitative criteria for assessing the effects of various design and operating parameters on thermohydraulic processes in an NPP. The synthesis is carried out at three hierarchical levels: process, component and system. The methodology is illustrated by applying it to various problems at the three hierarchical levels. (author)

  17. Hydraulic simulation of the systems of a nuclear power plant for charges calculation in piping

    International Nuclear Information System (INIS)

    Masriera, N.

    1990-01-01

    This work presents a general description of the methodology used by the ENACE S.A. Fluids Working Group for hydraulics simulation of a nuclear power plant system for the calculation charges in piping. (Author) [es

  18. A multivariate statistical study on a diversified data gathering system for nuclear power plants

    International Nuclear Information System (INIS)

    Samanta, P.K.; Teichmann, T.; Levine, M.M.; Kato, W.Y.

    1989-02-01

    In this report, multivariate statistical methods are presented and applied to demonstrate their use in analyzing nuclear power plant operational data. For analyses of nuclear power plant events, approaches are presented for detecting malfunctions and degradations within the course of the event. At the system level, approaches are investigated as a means of diagnosis of system level performance. This involves the detection of deviations from normal performance of the system. The input data analyzed are the measurable physical parameters, such as steam generator level, pressurizer water level, auxiliary feedwater flow, etc. The study provides the methodology and illustrative examples based on data gathered from simulation of nuclear power plant transients and computer simulation of a plant system performance (due to lack of easily accessible operational data). Such an approach, once fully developed, can be used to explore statistically the detection of failure trends and patterns and prevention of conditions with serious safety implications. 33 refs., 18 figs., 9 tabs

  19. Design and realization of a dosimetry and radiology system for nuclear power plants

    International Nuclear Information System (INIS)

    Capelle, M.

    Computer-assisted acquisition of radiation exposure data and related tasks was established at an early stage at Biblis nuclear power plant of RWE. Due to the positive experience with this system a similar, more sophisticated system has been developed for the nuclear power plants at Grundremmingen, Muelheim-Kaerlich and Kalkar. This system, DORA (Dosimetry and radiological monitoring) is described in the article. (RW) [de

  20. Approach to a generalized real-time nuclear materials control system

    International Nuclear Information System (INIS)

    Jarsch, V.; Onnen, S.; Polster, F.J.; Woit, J.

    1978-01-01

    Untrained users and a large amount of--at first glance incompatible--processes and materials are the environment of computer-aided nuclear materials control systems. To find an efficient model of the real processes and materials descriptions and to allow the operating personnel to communicate with the system in his everyday symbolism are goals in the development of the concept presented in this paper. According to this concept a real-time minicomputer-based materials control system is being implemented in the Nuclear Research Center of Karlsruhe. The chosen approach satisfies the heterogeneous requirements of the various institutes of the Center and is also applicable to other nuclear plants

  1. Nuclear electric propulsion: A better, safer, cheaper transportation system for human exploration of Mars

    International Nuclear Information System (INIS)

    Clark, J.S.; George, J.A.; Gefert, L.P.; Doherty, M.P.; Sefcik, R.J.

    1994-03-01

    NASA has completed a preliminary mission and systems study of nuclear electric propulsion (NEP) systems for 'split-sprint' human exploration and related robotic cargo missions to Mars. This paper describes the study, the mission architecture selected, the NEP system and technology development needs, proposed development schedules, and estimated development costs. Since current administration policy makers have delayed funding for key technology development activities that could make Mars exploration missions a reality in the near future, NASA will have time to evaluate various alternate mission options, and it appears prudent to ensure that Mars mission plans focus on astronaut and mission safety, while reducing costs to acceptable levels. The split-sprint nuclear electric propulsion system offers trip times comparable to nuclear thermal propulsion (NTP) systems, while providing mission abort opportunities that are not possible with 'reference' mission architectures. Thus, NEP systems offer short transit times for the astronauts, reducing the exposure of the crew to intergalactic cosmic radiation. The high specific impulse of the NEP system, which leads to very low propellant requirements, results in significantly lower 'initial mass in low earth orbit' (IMLEO). Launch vehicle packaging studies show that the NEP system can be launched, assembled, and deployed, with about one less 240-metric-ton heavy lift launch vehicle (HLLV) per mission opportunity - a very Technology development cost of the nuclear reactor for an NEP system would be shared with the proposed nuclear surface power systems, since nuclear systems will be required to provide substantial electrical power on the surface of Mars. The NEP development project plan proposed includes evolutionary technology development for nuclear electric propulsion systems that expands upon SP-100 (Space Power - 100 kw(e)) technology that has been developed for lunar and Mars surface nuclear power

  2. WSPEEDI-II system user's manual for a nuclear or radiological emergency

    International Nuclear Information System (INIS)

    Nakanishi, Chika; Sato, Sohei; Muto, Shigeo; Furuno, Akiko; Terada, Hiroaki; Nagai, Haruyasu

    2011-03-01

    Nuclear Emergency Assistance and Training Center (NEAT) has developed the response system to evaluate the radiological consequences of an accident on a nuclear power plant or nuclear weapons testing around Japan and to support prediction of radioactive material distributions by using an atmospheric dispersion model on the framework of the Response Assistance Network (RANET) which is established by the International Atomic Energy Agency (IAEA). For the enhancement of assistance capability to external organizations at a nuclear or radiological emergency, NEAT will introduce a computer-based emergency response system, 'Worldwide version of System for Prediction of Environmental Emergency Dose Information: WSPEEDI 2nd version (WSPEEDI-II)' developed by Division of Environmental and Radiation Sciences. This manual covers the overview of the system and configuration parameters as the basic knowledge needed for operating the systems. (author)

  3. A study on the nuclear computer code maintenance and management system

    International Nuclear Information System (INIS)

    Kim, Yeon Seung; Huh, Young Hwan; Lee, Jong Bok; Choi, Young Gil; Suh, Soong Hyok; Kang, Byong Heon; Kim, Hee Kyung; Kim, Ko Ryeo; Park, Soo Jin

    1990-12-01

    According to current software development and quality assurance trends. It is necessary to develop computer code management system for nuclear programs. For this reason, the project started in 1987. Main objectives of the project are to establish a nuclear computer code management system, to secure software reliability, and to develop nuclear computer code packages. Contents of performing the project in this year were to operate and maintain computer code information system of KAERI computer codes, to develop application tool, AUTO-i, for solving the 1st and 2nd moments of inertia on polygon or circle, and to research nuclear computer code conversion between different machines. For better supporting the nuclear code availability and reliability, assistance from users who are using codes is required. Lastly, for easy reference about the codes information, we presented list of code names and information on the codes which were introduced or developed during this year. (Author)

  4. A nuclear pulse amplitude acquisition system based on 80C31 single-chip microcomputer

    International Nuclear Information System (INIS)

    Zhao Xiuliang; Qu Guopu; Guo Lanying; Zhang Songbai

    1999-01-01

    A kind of multichannel nuclear pulse amplitude signal acquisition system is described, which is composed of pulse peak detector, integrated S/H circuit, A/D converter and 80C31 single-chip microcomputer

  5. Development of a spatial nuclear electric system: RESPA sub-project

    International Nuclear Information System (INIS)

    Ishiguro, Y.

    1989-04-01

    Basic design and characteristics of a nuclear-electric system selected for future applications in the Brazilian space program is summarized. Technological difficulties are discussed and a preliminary program of research and development at IEAv is presented. (author)

  6. Nuclear Energy and Renewables: System Effects in Low-carbon Electricity Systems : Method comments to a NEA report

    OpenAIRE

    Söder, Lennart

    2012-01-01

    OECD Nuclear Energy Agency (NEA) released a new report on 29 November 2012. The study recommends that decision-makers should take full electricity system costs into account in energy choices and that such costs should be internalised according to a “generator pays” principle. The study, entitled Nuclear Energy and Renewables: System Effects in Low-carbon Electricity Systems, addresses the increasingly important interactions of variable renewables and dispatchable energy technologies, such as ...

  7. A preliminary study on the design in architecture of nuclear and radiation safety standard system

    International Nuclear Information System (INIS)

    Song Dahu; Zhang Chi; Yang Lili; Li Bin; Liu Yingwei; An Hongzhen; Gao Siyi; Liu Ting; Meng De

    2014-01-01

    The connotation and function of nuclear and radiation safety standards are analyzed, and their relationships with the relevant laws and regulations are discussed in the paper. Some suggestions and blue print of overall architecture to build nuclear and radiation safety standard system are proposed, on the basis of researching the application status quo, existing problems and needs for nuclear and radiation safety standards in China. This work is a beneficial exploration and attempt to establish China's nuclear and radiation safety standards. (authors)

  8. A protection system of low temperature thermo-supply nuclear reactor

    International Nuclear Information System (INIS)

    Jiang Binsen

    1988-09-01

    A Protection system of low temperature thermo-supply nuclear reactor is introduced. It is the first protection system, which is designed and manufactred on the basis of Chinese National Standard GB 4083-83 'General Safety Principle of Nuclear Reactor Protection System', to be considered under the circumstances of industry level in China. Advantages of the protection system are as follows: 1)The single failure criteria can fully be fulfilled by the protection system. 2) On-line testing system can be used for detecting all of failure components and quick identifying the failure points in the system. 3) It is convenience for maintenacnce of the system. To complete this project is very important and helpful in promoting the development of the protection system and safety operation of nuclear reactor in China

  9. Conceptual design of a digital control system for nuclear criticality experiments

    International Nuclear Information System (INIS)

    Rojas, S.P.

    1994-04-01

    Nuclear criticality is a concern in many areas of nuclear engineering including waste management, nuclear weapons testing and design, basic nuclear research, and nuclear reactor design and analysis. As in many areas of science and engineering, experimental work conducted in this field has provided a wealth of data and insight essential to the formulation of theory and the advancement in knowledge of fissioning systems. In light of the many diverse applications of nuclear criticality, there is a continuing interest to learn and understand more about the fundamental physical processes through continued experimentation. This thesis addresses the problem of setting up and programming a microprocessor-based digital control system (PLC) for a proposed critical experiment using, among other devices, a stepper motor, a joystick control mechanism, and switches. This experiment represents a revised configuration to test cylindrical nuclear waste packages. A Monte Carlo numerical study for the proposed critical assembly has been performed in order to illustrate how results from numerical calculations are used in the process of assembling the control system and to corroborate previous experimental data. In summary, a control system utilizing some common devices necessary to perform a critical experiment (stepper motor, push-buttons, etc.) has been assembled. Control components were sized using the results of a probabilistic computer code (MCNP). Finally, a program was written that illustrates the coupling between the hardware and the devices being controlled in the new test fixture

  10. 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

  11. Quality assurance systems - a means for an integrating organization of nuclear power plants

    International Nuclear Information System (INIS)

    Adams, H.W.

    1984-01-01

    The operators of nuclear power plants are in the process of introducing quality assurance systems of the type required in Rule 1401 by the German Kerntechnischer Ausschuss (Nuclear Technology Committee). These systems as a cross sectional function cover most of the organizational areas of a nuclear power plant. Their introduction offers an opportunity to harmonize and supplement existing systems where necessary. Integrated quality assurance systems built up on a data base allow existing DP data and other logical data to be organized in such a way that certain sequences of events can be managed by enforced control. This relieves the personnel responsible for the safety of a nuclear power plant of routine jobs and routine decisions. Greater flexibility is created for personal decisions. Organized sequences of events can be monitored by having lists printed out in which the necessary data are combined into data sets. (orig.) [de

  12. Quality assurance as a system of management control in nuclear power plants

    International Nuclear Information System (INIS)

    Raisic, N.

    1986-04-01

    Quality assurance is considered as a management control system which the owner of a nuclear power plant has to establish for a nuclear power project for ensuring that a plant is built as designed and that defects are corrected. The building up of such a system should start early enough in project activities and before the plant design and construction, in order to ensure correct performance of all activities related to selection of the site for the nuclear power plant, bid specification and evaluation and procurement of services. The QA is a regulatory requirement, but the prudent plant management would create such a system as part of their total project management systems irrespective of formulation of requirement. In fact regulatory requirement should be considered as the criteria to be used by the regulatory organization for evaluation of licensee's QA system and not as an objective to be reached. In this paper the needs for QA system are justified as part of the development of industrial infrastructure for the nuclear power project. Elements of the system are described such as documented QA programme and organizational structures with defined responsibility and functions of individual organizational units, and with control of information flow across the interfaces. The goals and objectives or the project organizations related to achievement and verification of quality are defined as well as system functions in attaining these objectives. This includes the feedback of information to the management on monitoring of performance in project activities, identifying deficiencies and initiating corrective actions. Domestic participation in the nuclear power plant construction will depend on the ability of local construction and manufacturing organizations to achieve high quality standards of products and services that can affect safety and performance of the nuclear power plant. Introduction of QA systems in project organizations, development of QA programme and

  13. The ‘Landscape’ of Nuclear Safeguards: A Comparative Analysis of the International and Regional Systems

    International Nuclear Information System (INIS)

    Colussi, I.A.

    2015-01-01

    The notion of “nuclear non-proliferation” is twofold. It refers to: (a) reduction of the number of existing arsenals (vertical non-proliferation), and (b) containment of the number of States that possess nuclear weapons, or control of non-state actors (horizontal non-proliferation). At the international law level, as vertical non-proliferation, there are bilateral or multilateral agreements that ban weapons of mass destruction in certain areas (e.g.: Nuclear–Weapon– Free Zones treaties). With respect to horizontal non-proliferation, beyond the Nuclear-Weapon-Free Zones approach, the main legal text for addressing the issue is the Treaty on the Non-Proliferation of Nuclear Weapons (NPT). For the implementation of the principles contained in the NPT, anuclear safeguards” system has been created, and the International Atomic Energy Agency (IAEA) has been assigned the role of the nuclear “watchdog” for the NPT. However, along with this international system of safeguards, there are regional safeguards bodies: (a) the European Atomic Energy Community (EURATOM) model is the cornerstone of non-proliferation in the EU, while (b) the Brazilian-Argentine Agency for Accounting for and Control of Nuclear Materials (ABACC) controls nuclear activities in Brazil and Argentina. Moreover, the existing nuclear weapons free-zone treaties contain safeguards provisions that are additional or complementary to IAEA safeguards. For instance, (a) the Agency for the Prohibition of Nuclear Weapons in Latin America and the Caribbean (OPANAL) works for the implementation of Tlatelolco Treaty, (b) the African Commission on Nuclear Energy relates to Pelindaba Treaty, and (c) a Consultative Committee of the Parties is appointed in the context of Raratonga Treaty. The paper aims at critically analysing the different safeguards systems adopted at the international and regional level, through the adoption of a comparative approach. (author)

  14. Development of a utility system for charged particle nuclear reaction data by using intelligentPad

    International Nuclear Information System (INIS)

    Aoyama, Shigeyoshi; Ohbayashi, Yoshihide; Masui, Hiroshi; Kato, Kiyoshi; Chiba, Masaki

    2000-01-01

    We have developed a utility system, WinNRDF2, for a nuclear charged particle reaction data of NRDF (Nuclear Reaction Data File) on the IntelligentPad architecture. By using the system, we can search the experimental data of a charged particle reaction of NRDF. Furthermore, we also see the experimental data by using graphic pads which was made through the CONTIP project. (author)

  15. A study on the revision of nuclear safety act to build the foundation of nuclear export and import control system in Korea

    International Nuclear Information System (INIS)

    Yang, Seung Hyo; Choi, Sun Do

    2012-01-01

    Nuclear related items require export and import control beyond the multilateral export control system according to Safeguard Agreement, Additional Protocol and bilateral agreements. Besides Korea as a nuclear supplier is needed to actively cope with its export control system, which is being reinforced internationally. In regard to this trend, this study drew the revision plan of present Nuclear Safety Act to found the nuclear export and import control system in Korea by examining the related legislations and analyzing the implementation status of nuclear export and import control

  16. A study on the revision of nuclear safety act to build the foundation of nuclear export and import control system in Korea

    Energy Technology Data Exchange (ETDEWEB)

    Yang, Seung Hyo; Choi, Sun Do [Korea Institute of Nuclear Nonproliferation and Control, Daejeon (Korea, Republic of)

    2012-10-15

    Nuclear related items require export and import control beyond the multilateral export control system according to Safeguard Agreement, Additional Protocol and bilateral agreements. Besides Korea as a nuclear supplier is needed to actively cope with its export control system, which is being reinforced internationally. In regard to this trend, this study drew the revision plan of present Nuclear Safety Act to found the nuclear export and import control system in Korea by examining the related legislations and analyzing the implementation status of nuclear export and import control.

  17. Development of a nuclear emergency preparedness support system. MEASURES and its advanced edition

    International Nuclear Information System (INIS)

    Hara, Tomohiro; Nakatsuka, Shigehiro; Watanabe, Osami; Adachi, Takeshi

    2007-01-01

    We have developed a new nuclear emergency preparedness support system for a micro scale area, called the advanced edition of MEASURES. The system simulates atmospheric dispersion of radioactive material quickly and accurately, using an airflow database and a dispersion model. It takes less than 15 minutes for 12-hour simulation, on a personal computer. The user can operate the system by GUI. (author)

  18. For establishment on nuclear disaster prevention system

    International Nuclear Information System (INIS)

    Anon.

    2000-01-01

    For increasing requirement of peoples for review of nuclear disaster countermeasure at a chance of the JCO critical accident, the Japanese Government newly established the 'Special Measure Act on Nuclear Disaster Countermeasure', which was enacted on July 16, 2000. The nuclear business relatives such as electric power company and so forth established the Business program on nuclear disaster prevention in nuclear business relatives' after their consultation with local communities at their construction, under their co-operation. Simultaneously, the electric power industry field decided to intend to provide some sufficient countermeasures to incidental formation of nuclear accident such as start of the Co-operative agreement on nuclear disaster prevention among the nuclear business relatives' and so forth. Here were described on nuclear safety and disaster prevention, nuclear disaster prevention systems at the electric power industry field, abstract on 'Business program on nuclear disaster prevention in nuclear business relatives', preparation of technical assistance system for nuclear disaster prevention, executive methods and subjects on nuclear disaster prevention at construction areas, recent business on nuclear disaster prevention at the Nuclear Technical Center, and subjects on establishment of nuclear disaster prevention system. (G.K.)

  19. A Development Framework for Software Security in Nuclear Safety Systems: Integrating Secure Development and System Security Activities

    Energy Technology Data Exchange (ETDEWEB)

    Park, Jaekwan; Suh, Yongsuk [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2014-02-15

    The protection of nuclear safety software is essential in that a failure can result in significant economic loss and physical damage to the public. However, software security has often been ignored in nuclear safety software development. To enforce security considerations, nuclear regulator commission recently issued and revised the security regulations for nuclear computer-based systems. It is a great challenge for nuclear developers to comply with the security requirements. However, there is still no clear software development process regarding security activities. This paper proposes an integrated development process suitable for the secure development requirements and system security requirements described by various regulatory bodies. It provides a three-stage framework with eight security activities as the software development process. Detailed descriptions are useful for software developers and licensees to understand the regulatory requirements and to establish a detailed activity plan for software design and engineering.

  20. Feasibility study of a dedicate nuclear desalination system: Low-pressure inherent heat sink nuclear desalination plant (LIND)

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Ho Sik; No, Hee Cheon; Jo, Yu Gwan; Wivisono, Andhika Feri; Park, Byung Ha; Choi, Jin Young; Lee, Jeong Ik; Jeong, Yong Hoon; Cho, Nam Zin [Dept. of Nuclear and Quantum Engineering, Korea Advanced Institute of Science and Technology, Daejeon (Korea, Republic of)

    2015-04-15

    In this paper, we suggest the conceptual design of a water-cooled reactor system for a low-pressure inherent heat sink nuclear desalination plant (LIND) that applies the safety-related design concepts of high temperature gas-cooled reactors to a water-cooled reactor for inherent and passive safety features. Through a scoping analysis, we found that the current LIND design satisfied several essential thermal-hydraulic and neutronic design requirements. In a thermal-hydraulic analysis using an analytical method based on the Wooton-Epstein correlation, we checked the possibility of safely removing decay heat through the steel containment even if all the active safety systems failed. In a neutronic analysis using the Monte Carlo N-particle transport code, we estimated a cycle length of approximately 6 years under 200 MW{sub th} and 4.5% enrichment. The very long cycle length and simple safety features minimize the burdens from the operation, maintenance, and spent-fuel management, with a positive impact on the economic feasibility. Finally, because a nuclear reactor should not be directly coupled to a desalination system to prevent the leakage of radioactive material into the desalinated water, three types of intermediate systems were studied: a steam producing system, a hot water system, and an organic Rankine cycle system.

  1. Feasibility study of a dedicated nuclear desalination system: Low-pressure Inherent heat sink Nuclear Desalination plant (LIND

    Directory of Open Access Journals (Sweden)

    Ho Sik Kim

    2015-04-01

    Full Text Available In this paper, we suggest the conceptual design of a water-cooled reactor system for a low-pressure inherent heat sink nuclear desalination plant (LIND that applies the safety-related design concepts of high temperature gas-cooled reactors to a water-cooled reactor for inherent and passive safety features. Through a scoping analysis, we found that the current LIND design satisfied several essential thermal–hydraulic and neutronic design requirements. In a thermal–hydraulic analysis using an analytical method based on the Wooton–Epstein correlation, we checked the possibility of safely removing decay heat through the steel containment even if all the active safety systems failed. In a neutronic analysis using the Monte Carlo N-particle transport code, we estimated a cycle length of approximately 6 years under 200 MWth and 4.5% enrichment. The very long cycle length and simple safety features minimize the burdens from the operation, maintenance, and spent-fuel management, with a positive impact on the economic feasibility. Finally, because a nuclear reactor should not be directly coupled to a desalination system to prevent the leakage of radioactive material into the desalinated water, three types of intermediate systems were studied: a steam producing system, a hot water system, and an organic Rankine cycle system.

  2. Implementation of a geographical information system in nuclear emergencies; Implementacion de un sistema de informacion geografico en emergencias nucleares

    Energy Technology Data Exchange (ETDEWEB)

    Sadaniowski, I; Telleria, D; Jordan, O; Bruno, H; Boutet, L; Hernandez, D [Autoridad Regulatoria Nuclear, Av. Del Libertador 8250, Ciudad de Buenos Aires (Argentina)

    2006-07-01

    From 2003, the Nuclear Regulatory Authority (RNA) has worked in the implementation of a Geographical Information System (SIG) for the planning and the intervention in emergencies, with special emphasis in the nuclear emergencies. The main objective of the SIG developed in the ARN is to give the necessary support for the planning, training and application of the actions of radiological protection necessary in front of a nuclear emergency, offering the geo referenced cartographic base, the readiness of logistical resources in the whole country, incorporating results of models of forecast of consequences and environmental measurements during the emergency, facilitating the analysis of this information in real time and facilitating the presentation of results for the decision making. The cartographic base is constituted of demographic, social, economic data identification of main actors interveners in the emergency, vial infrastructure and natural characteristics of the area in question. In this work the main characteristics of the implemented SIG are presented including the conceptual standards of design that contemplate the international requirements for the planning and answer in the event of nuclear emergencies, the current state of the system and the foreseen evolution. A description of the opposing problems during its implementation that can be common to many countries of the region is also presented, as well as the obtained experience of its use in preparation tasks for emergencies and in mocks. (Author)

  3. The Baker system for nuclear access authorization screening: a psychologically developed system for access screening of vendor and owner applicants at nuclear power plants

    International Nuclear Information System (INIS)

    Baker, E.G.; Crouter, F.L.

    1985-01-01

    This paper presents a comprehensive screening program for unescorted access which has proven to be highly effective in determining the intergrity, trustworthiness, socialibility, behaviors and tendencies of an employee applicant--past, present and future. This procedure, designed specifically for the nuclear industry, can be used with owner or vendor applicants, and meets or exceeds all of the NRC's requirements. The Baker system has been used for nuclear selection since 1979

  4. 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

  5. A documentation system for decommissioning of nuclear power plants

    International Nuclear Information System (INIS)

    Glock, H.J.; Mueller, F.; Schwarz, H.

    1984-01-01

    A NPP's life cycle from the beginning of planning to its complete dismantling will last about 80 to 100 years. For this long time a documentation system has to be kept in stable working condition which provides access to an information base including 1.5 to 2 million pages and 200 to 250 thousand engineering drawings. As an appropriate base the documentation system IFODOK is proposed which is supported by computer and data base management software. In cooperation with NPP operating people a ground level thesaurus has been developed which is structured according to the rules of INFODOK's documentation language. The form of the information units which INFODOK maintains has been adapted to the requirements of KKW documentation and the related data record is described. Within a layer model the requirements to the software resulting from the demanded performance of the system are explained. The model also describes the interfaces between the substantial system components (application programs, data base management system, operating system) as well as within the different layers. The requirements which the system's hardware has to meet are described functionally and quantitatively in details. The application program' components have been extended by some functions. An automatic microfilm storage and retrieval system which may be integrated to the overall system and coupled to the computer by an interface is specified. The organization of the computer assisted documentation process including the required backup and refreshment procedures is described in its basic characteristics. This description of an DP system's prototype presents the base for the application of INFODOK to the documentation of NPP's information bases during their whole life time

  6. Examination of the role of nuclear deterrence in the 21st century: a systems analysis approach

    Energy Technology Data Exchange (ETDEWEB)

    Martz, Joseph C [Los Alamos National Laboratory; Stevens, Patrice A [Los Alamos National Laboratory; Branstetter, Linda [SNL; Hoover, Edward [SNL; O' Brien, Kevin [SNL; Slavin, Adam [SNL; Caswell, David [STANFORD UNIV

    2010-01-01

    weapons? Many competing objectives have been stated across the spectrum of political, social, and military thought. These objectives include goals of ratification of the Comprehensive Test Ban Treaty, recommitment to further downsizing of the nuclear arsenal, embracing a long-term goal of the elimination of nuclear weapons, limitations on both the production complex and upgrades to nuclear weapons and delivery systems, and controls and constraints to limit proliferation of nuclear materials and weapons, particularly to rogue states and terrorist groups.

  7. A nuclear radiation multi-parameter measurement system based on pulse-shape sampling

    International Nuclear Information System (INIS)

    Qiu Xiaolin; Fang Guoming; Xu Peng; Di Yuming

    2007-01-01

    In this paper, A nuclear radiation multi-parameter measurement system based on pulse-shape sampling is introduced, including the system's characteristics, composition, operating principle, experiment data and analysis. Compared with conventional nuclear measuring apparatus, it has some remarkable advantages such as the synchronous detection using multi-parameter measurement in the same measurement platform and the general analysis of signal data by user-defined program. (authors)

  8. Transportation ALARA analysis for a nuclear waste management system

    International Nuclear Information System (INIS)

    McNair, G. W.; Schneider, K.; Smith, R.I.; Ross, W.; Faletti, D.

    1988-01-01

    In planning for implementation of a safe and cost-effective transportation system, the Department of Energy (DOE) commissioned the Pacific Northwest Laboratory (PNL) to develop estimates of the radiation doses, both public and occupational, that would result from operation of a system postulated using current designs and practices. From that evaluation, PNL identified activities/operations that result in relatively high doses, proposed conceptual alternatives that would effectively reduce such exposures, and evaluated the cost-effectiveness of such alternatives. This study contains an analysis of routine operations and estimates of the public and worker radiation doses that would occur in a postulated generic reference spent fuel transportation system using both truck and rail modes. Total risks are not estimated (i.e., consideration of nonradiological or accident risks that will be the subject of future studies in the transportation systems study plan 9TSSP) are not included). The system encompasses spent fuel loading at the reactor, transportation of the fuel to and from a receiving and handling facility and unloading of the fuel at a repository. The analysis provides cost/dose trade-offs of the postulated reference system as well as selected potential alternatives to the transportation system

  9. Development of a plastic fracture methodology for nuclear systems

    International Nuclear Information System (INIS)

    Marston, T.U.; Jones, R.L.; Kanninen, M.F.; Mowbray, D.F.

    1981-01-01

    This paper describes research conducted to develop a fundamental basis for flaw tolerance assessment procedures suitable for components exhibiting ductile behavior. The research was composed of an integrated combination of stable crack growth experiments and elastic-plastic analyses. A number of candidate fracture criteria were assembled and investigated to determine the proper basis for plastic fracture mechanics assessments. The results demonstrate that many different fracture criteria can be used as the basis of a resistance curve approach to predicting stable crack growth and fracture instability. While all have some disadvantages, none is completely unacceptable. On balance, the best criteria were found to be the J-integral for initiation and limited amounts of stable crack growth and the local crack-tip opening angle for extended amounts of stable growth. A combination of the two, which may preserve the advantages of each while reducing their disadvantages, also was suggested by these results. The influence of biaxial and mixed flat/shear fracture behavior was investigated and found to not alter the basic results. Further work in the development of simplified ductile fracture analyses for routine engineering assessments of nuclear pressure vessels and piping evolving from this research is also described

  10. A comparative study on export control systems of nuclear technology in ROK and USA

    Energy Technology Data Exchange (ETDEWEB)

    Tae, Jae Woong; Shin, Dong Hoon [Korea Institute of Nuclear Nonproliferation and Control, Daejeon (Korea, Republic of)

    2013-10-15

    Perfect removal of transferred technology is impossible because it is impossible to find all copies of technologies such as files and documents. International community concerns about Terrorists' acquirement of nuclear technologies related to nuclear reactors, enrichment and reprocessing Facilities and heavy water production facilities, which can be used for production of nuclear weapons. Non-state actors as well as concerning countries have tried to possess nuclear technology for developing nuclear weapons. Non-state actors' activities threaten global nuclear security. Korea exported four nuclear power plants to UAE and a research reactor to Jordan. Non-state actors may try to procure nuclear equipment and technology from Korean nuclear industries. Therefore, the export control system should be enhanced for national nuclear security and safety. In this study, the export control system of Korea and the United States were compared concerning to nuclear technology. In summary, controlled activities related to nuclear technology are treated more variously and more diverse activities are controlled in the United States than In Korea. Catch-all control will lose its effectiveness without this. Related to the control of ITT (Intangible Technology Transfer), Korea and the United States are trying to amend the export control regulation. Both of them are trying to control intangible technology transfers effectively. Revised Foreign Trade Act in Korea is expected to introduce a more rigorous system of nuclear technology controls. It focuses on nationality rather than residence. The revised law may face into other problems such as dual nationals like as the United States. However, this satisfies legislative requirements for control of a deemed export. The revised law will enter into force in 2014. Accurate meanings of technology and export will be defined soon in the enforcement decree and the public notice before 2014. However, it is hard to revise the definition

  11. A comparative study on export control systems of nuclear technology in ROK and USA

    International Nuclear Information System (INIS)

    Tae, Jae Woong; Shin, Dong Hoon

    2013-01-01

    Perfect removal of transferred technology is impossible because it is impossible to find all copies of technologies such as files and documents. International community concerns about Terrorists' acquirement of nuclear technologies related to nuclear reactors, enrichment and reprocessing Facilities and heavy water production facilities, which can be used for production of nuclear weapons. Non-state actors as well as concerning countries have tried to possess nuclear technology for developing nuclear weapons. Non-state actors' activities threaten global nuclear security. Korea exported four nuclear power plants to UAE and a research reactor to Jordan. Non-state actors may try to procure nuclear equipment and technology from Korean nuclear industries. Therefore, the export control system should be enhanced for national nuclear security and safety. In this study, the export control system of Korea and the United States were compared concerning to nuclear technology. In summary, controlled activities related to nuclear technology are treated more variously and more diverse activities are controlled in the United States than In Korea. Catch-all control will lose its effectiveness without this. Related to the control of ITT (Intangible Technology Transfer), Korea and the United States are trying to amend the export control regulation. Both of them are trying to control intangible technology transfers effectively. Revised Foreign Trade Act in Korea is expected to introduce a more rigorous system of nuclear technology controls. It focuses on nationality rather than residence. The revised law may face into other problems such as dual nationals like as the United States. However, this satisfies legislative requirements for control of a deemed export. The revised law will enter into force in 2014. Accurate meanings of technology and export will be defined soon in the enforcement decree and the public notice before 2014. However, it is hard to revise the definition of export

  12. Assessments of nuclear systems

    International Nuclear Information System (INIS)

    Ekholm, R.

    1978-01-01

    Assessments of competing energy systems are gaining increased importance as a means for an optimal choice of energy source for each specific major application considering the growing energy needs and the shortage of supply. However it is important to make sure that the assessments reflect scientific facts rather than private interests. If this is not achieved, scientists will lose credibility and one will lose the basis for political decisions. It is concluded that to accomplish the globally justified needs for thousands of nuclear reactors soon after the year 2000 and to save a maximum of lives with a minimum of environmental impact, emphasis must be put on low energy costs and on a good fuel and capital resource utilization. This goal can be best accomplished by expendient introduction of the fast breeders and of promising advanced reactors. The gas cooled breeder and the high temperature reactor have outstanding short and long terms merits on this respect, but are not enjoying the financial support that they deserve. (UK)

  13. A study on the funding system for efficient implementation of nuclear R and D

    International Nuclear Information System (INIS)

    Chung, Whan Sam; Yang, M. H.; Song, K. D.; Kim, H. J.; Yun, S. W.

    2000-08-01

    This study is investigated and analysed as follows : first, investigation on the general account, special account, fund system as a financial source and deep analysis on charging fee of Nuclear R and D Fund; second, background of the establishment on Nuclear R and D Fund; third, investigation on the domestic and oversea's R and D Fund system; fourth, searching for the objective and basic guideline for the reshuffle of electric power industry and the issues on public charging fee; fifth, in depth analysis on the legal background and the main issues of Nuclear R and D Fund; and sixth, comprehensive arrangement on the main issues through the study

  14. A conceptual framework to analyze and mitigate aging effects of a system in nuclear power plants

    International Nuclear Information System (INIS)

    Ahmed, S.

    1985-01-01

    A conceptual framework is developed to analyze, characterize, and mitigate the degradation of a system in a nuclear power plant due to aging. The system is evaluated, based on an aging-specific system decision model, to understand and implement decisions pertaining to surveillance, maintenance, and replacement. Decisions on other corrective measures to mitigate the effects of aging of a number of equipment items, interconnections (relationships with other systems), and interfaces (relationships within the system) can also be made based on the proposed approach

  15. A Hydrogen Ignition Mechanism for Explosions in Nuclear Facility Piping Systems

    Energy Technology Data Exchange (ETDEWEB)

    Leishear, Robert A.

    2013-09-18

    Hydrogen explosions may occur simultaneously with water hammer accidents in nuclear facilities, and a theoretical mechanism to relate water hammer to hydrogen deflagrations and explosions is presented herein. Hydrogen and oxygen generation due to the radiolysis of water is a recognized hazard in pipe systems used in the nuclear industry, where the accumulation of hydrogen and oxygen at high points in the pipe system is expected, and explosive conditions may occur. Pipe ruptures in nuclear reactor cooling systems were attributed to hydrogen explosions inside pipelines, i.e., Hamaoka, Nuclear Power Station in Japan, and Brunsbuettel in Germany. Prior to these accidents, an ignition source for hydrogen was not clearly demonstrated, but these accidents demonstrated that a mechanism was, in fact, available to initiate combustion and explosion. A new theory to identify an ignition source and explosion cause is presented here, and further research is recommended to fully understand this explosion mechanism.

  16. Nuclear power systems: Their safety

    International Nuclear Information System (INIS)

    Myers, L.C.

    1993-01-01

    Mankind utilizes energy in many forms and from a variety of sources. Canada is one of a growing number of countries which have chosen to embrace nuclear-electric generation as a component of their energy systems. As of August 1992 there were 433 power reactors operating in 35 countries and accounting for more than 15% of the world's production of electricity. In 1992, thirteen countries derived at least 25% of their electricity from nuclear units, with France leading at nearly 70%. In the same year, Canada produced about 16% of its electricity from nuclear units. Some 68 power reactors are under construction in 16 countries, enough to expand present generating capacity by close to 20%. No human endeavour carries the guarantee of perfect safety and the question of whether or not nuclear-electric generation represents an 'acceptable' risk to society has long been vigorously debated. Until the events of late April 1986, nuclear safety had indeed been an issue for discussion, for some concern, but not for alarm. The accident at the Chernobyl reactor in the USSR has irrevocably changed all that. This disaster brought the matter of nuclear safety back into the public mind in a dramatic fashion. This paper discusses the issue of safety in complex energy systems and provides brief accounts of some of the most serious reactor accidents which have occurred to date. (author). 7 refs

  17. A multiprocessor system for experiments in nuclear physics

    International Nuclear Information System (INIS)

    Neudold, M.

    1986-12-01

    In the first part of this report, a provisional version of the data acquisition system for the magnetic spectrometer LITTLE JOHN at the Karlsruhe isochronous cyclotron is described. The conceptual ideas of this first version and the problems appearing during the test of its hardware and software components are discussed. Basing on the experience with this system possible extensions and new busstructures are suggested. In the second part, some prototype programs are described, which have been developed in order to test the ADC-systems and the dataways. (orig.) [de

  18. Proliferation resistance characteristics of advanced nuclear energy systems: a safeguard ability point of view

    International Nuclear Information System (INIS)

    Sevini, F.; Cojazzi, G.G.M.; Renda, G.

    2008-01-01

    Among the international community there is a renewed interest in nuclear power systems as a major source for energy production in the near to mid future. This is mainly due to concerns connected with future availability of conventional energy resources, and with the environmental impact of fossil fuels. International initiatives have been set up like the Generation 4. International Forum (GIF), the International Project on Innovative Nuclear Reactors and Fuel Cycles (IAEA-INPRO), and, partially, the US driven Global Nuclear Energy Partnership (GNEP), aimed at defining and evaluating the characteristics, in which future innovative nuclear energy systems (INS) will have to excel. Among the identified characteristics, Proliferation Resistance plays an important role for being able to widely deploy nuclear technology worldwide in a secure way. Studies having the objective to assess Proliferation Resistance of nuclear fuel cycles have been carried out since the nineteen seventies, e.g., the International Nuclear Fuel Cycle Evaluation (INFCE) and the Non-proliferation Alternative Systems Assessment Program (NASAP) initiatives, and all agree in stating that absolute intrinsic proliferation resistance, although desirable, is not achievable in the foreseeable future. The above finding is still valid; as a consequence, every INS will have to comply with agreements related to the Non Proliferation Treaty (NPT) and will require safeguards measures, implemented through extrinsic measures. This consideration led to a renewed interest in the Safeguard ability concept which can be seen as a bridge between intrinsic features and extrinsic features and measures.

  19. Maintenance systems and procedures used in a nuclear power station and their relevance to other industries

    International Nuclear Information System (INIS)

    Kirk, R.R.

    1985-01-01

    The maintenance systems and procedures used at the Forsmark Nuclear Power Plant in Sweden can be viewed as a model which maintenance managers in other non-nuclear industries may adapt for their purposes. With the aid of a computerized information system covering the functions of work orders, preventative maintenance, documentation and others, plus a more conventional personnel structure, the result is an efficient, confident and well informed maintenance group. By following the basic design principles of the computerized information system used at the Forsmark Nuclear Power Station plus similar personnel structures, the performance of maintenance teams in non-nuclear manufacturing, processing and other industries could be improved to the standards of those observed

  20. Steam relief valve control system for a nuclear reactor

    International Nuclear Information System (INIS)

    Torres, J.M.

    1976-01-01

    Described is a turbine follow system and method for Pressurized Water Reactors utilizing load bypass and/or atmospheric dump valves to provide a substitute load upon load rejection by bypassing excess steam to a condenser and/or to the atmosphere. The system generates a variable pressure setpoint as a function of load and applies an error signal to modulate the load bypass valves. The same signal which operates the bypass valves actuates a control rod automatic withdrawal prevent to insure against reactor overpower

  1. A study on advanced man-machine interface system for autonomous nuclear power plants

    International Nuclear Information System (INIS)

    Matsuoka, Takeshi; Numano, Masayoshi; Fukuto, Junji; Sugasawa, Shinobu; Miyazaki, Keiko; Someya, Minoru; Haraki, Nobuo

    1994-01-01

    A man-machine interface(MMI) system of an autonomous nuclear power plant has an advanced function compared with that of the present nuclear power plants. The MMI has a function model of a plant state, and updates and revises this function model by itself. This paper describes the concept of autonomous nuclear power plants, a plant simulator of an autonomous power plant, a contracted function model of a plant state, three-dimensional color graphic display of a plant state, and an event-tree like expression for plant states. (author)

  2. NCS--a software for visual modeling and simulation of PWR nuclear power plant control system

    International Nuclear Information System (INIS)

    Cui Zhenhua

    1998-12-01

    The modeling and simulation of nuclear power plant control system has been investigated. Some mathematical models for rapid and accurate simulation are derived, including core models, pressurizer model, steam generator model, etc. Several numerical methods such as Runge-Kutta Method and Treanor Method are adopted to solve the above system models. In order to model the control system conveniently, a block diagram-oriented visual modeling platform is designed. And the Discrete Similarity Method is used to calculate the control system models. A corresponding simulating software, NCS, is developed for researching on the control systems of commercial nuclear power plant. And some satisfactory results are obtained. The research works will be of referential and applying value to design and analysis of nuclear power plant control system

  3. Computer systems and nuclear industry

    International Nuclear Information System (INIS)

    Nkaoua, Th.; Poizat, F.; Augueres, M.J.

    1999-01-01

    This article deals with computer systems in nuclear industry. In most nuclear facilities it is necessary to handle a great deal of data and of actions in order to help plant operator to drive, to control physical processes and to assure the safety. The designing of reactors requires reliable computer codes able to simulate neutronic or mechanical or thermo-hydraulic behaviours. Calculations and simulations play an important role in safety analysis. In each of these domains, computer systems have progressively appeared as efficient tools to challenge and master complexity. (A.C.)

  4. Real time operating system for a nuclear power plant computer

    International Nuclear Information System (INIS)

    Alger, L.S.; Lala, J.H.

    1986-01-01

    A quadruply redundant synchronous fault tolerant processor (FTP) is now under fabrication at the C.S. Draper Laboratory to be used initially as a trip monitor for the Experimental Breeder Reactor EBR-II operated by the Argonne National Laboratory in Idaho Falls, Idaho. The real time operating system for this processor is described

  5. Design concepts for a nuclear digital instrumentation and control system platform

    International Nuclear Information System (INIS)

    Ou, T. C.; Chen, C. K.; Chen, P. J.; Shyu, S. S.; Lee, C. L.; Hsieh, S. F.

    2010-10-01

    The objective of this paper is to present the development results of the nuclear instrumentation and control system in Taiwan. As the Taiwan nuclear power plants age, the need to consider upgrading of both their safety and non-safety-related instrumentation and control systems becomes more urgent. Meanwhile, the digital instrumentation and control system that is based on current fast evolving electronic and information technologies are difficult to maintain effectively. Therefore, Institute of Nuclear Energy Research was made a decision to promote the Taiwan Nuclear Instrumentation and Control System project to collaborate with domestic electronic industry to establish self-reliant capabilities on the design, manufacturing, and application of nuclear instrumentation and control systems with newer technology. In the case of safety-related applications like nuclear instrumentation and control, safety-oriented quality control is required. In order to establish a generic qualified digital platform, the world-wide licensing experience should be considered in the licensing process. This paper describes the qualification and certification tools by IEC 61508 for design and development of safety related equipment and explains the basis for many decisions made while performing the digital upgrade. (Author)

  6. Advanced nuclear systems. Review study

    International Nuclear Information System (INIS)

    Liebert, Wolfgang; Glaser, Alexander; Pistner, Christoph; Baehr, Roland; Hahn, Lothar

    1999-04-01

    The task of this review study is to from provide an overview of the developments in the field of the various advanced nuclear systems, and to create the basis for more comprehensive studies of technology assessment. In an overview the concepts for advanced nuclear systems pursued worldwide are subdivided into eight subgroups. A coarse examination raster (set pattern) is developed to enable a detailed examination of the selected systems. In addition to a focus on enhanced safety features, further aspects are also taken into consideration, like the lowering of the proliferation risk, the enhancement of the economic competitiveness of the facilities and new usage possibilities (for instance concerning the relaxation of the waste disposal problem or the usage of alternative fuels to uranium). The question about the expected time span for realization and the discussion about the obstacles on the way to a commercially usable reactor also play a substantial role as well as disposal requirements as far as they can be presently recognized. In the central chapter of this study, the documentation of the representatively selected concepts is evaluated as well as existing technology assessment studies and expert opinions. In a few cases where this appears to be necessary, according technical literature, further policy advisory reports, expert statements as well as other relevant sources are taken into account. Contradictions, different assessments and dissents in the literature as well as a few unsettled questions are thus indicated. The potential of advanced nuclear systems with respect to economical and societal as well as environmental objectives cannot exclusively be measured by the corresponding intrinsic or in comparison remarkable technical improvements. The acceptability of novel or improved systems in nuclear technology will have to be judged by their convincing solutions for the crucial questions of safety, nuclear waste and risk of proliferation of nuclear weapons

  7. The nuclear reactor systems

    International Nuclear Information System (INIS)

    Bacher, P.

    2008-01-01

    This paper describes the various nuclear reactor systems, starting with the Generation II, then the present development of the Generation III and the stakes and challenges of the future Generation IV. Some have found appropriate to oppose reactor systems or generations one to another, especially by minimizing the enhancements of generation III compared to generation II or by expecting the earth from generation IV (meaning that generation III is already obsolete). In the first part of the document (chapter 2), some keys are given to the reader to develop its proper opinion. Chapter 3 describes more precisely the various reactor systems and generations. Chapter 4 discusses the large industrial manoeuvres around the generation III, and the last chapter gives some economical references, taking into account, for the various means of power generation, the impediments linked to climate protection

  8. Nuclear excited power generation system

    International Nuclear Information System (INIS)

    Parker, R.Z.; Cox, J.D.

    1989-01-01

    A power generation system is described, comprising: a gaseous core nuclear reactor; means for passing helium through the reactor, the helium being excited and forming alpha particles by high frequency radiation from the core of the gaseous core nuclear reactor; a reaction chamber; means for coupling chlorine and hydrogen to the reaction chamber, the helium and alpha particles energizing the chlorine and hydrogen to form a high temperature, high pressure hydrogen chloride plasma; means for converting the plasma to electromechanical energy; means for coupling the helium back to the gaseous core nuclear reactor; and means for disassociating the hydrogen chloride to form molecular hydrogen and chlorine, to be coupled back to the reaction chamber in a closed loop. The patent also describes a power generation system comprising: a gaseous core nuclear reactor; means for passing hydrogen through the reactor, the hydrogen being excited by high frequency radiation from the core; means for coupling chlorine to a reaction chamber, the hydrogen energizing the chlorine in the chamber to form a high temperature, high pressure hydrogen chloride plasma; means for converting the plasma to electromechanical energy; means for disassociating the hydrogen chloride to form molecular hydrogen and chlorine, and means for coupling the hydrogen back to the gaseous core nuclear reactor in a closed loop

  9. The nuclear car wash: A system to detect nuclear weapons in commercial cargo shipments

    Science.gov (United States)

    Slaughter, D. R.; Accatino, M. R.; Bernstein, A.; Biltoft, P.; Church, J. A.; Descalle, M. A.; Hall, J. M.; Manatt, D. R.; Mauger, G. J.; Moore, T. L.; Norman, E. B.; Petersen, D. C.; Pruet, J. A.; Prussin, S. G.

    2007-08-01

    A concept for detecting the presence of special nuclear material ( 235U or 239Pu) concealed in intermodal cargo containers has been developed, studied, and recent performance results are described. It is based on interrogation with a pulsed beam of 3-7 MeV neutrons that produce fission events and subsequent detection of their β-delayed neutron emission or β-delayed high-energy γ-radiation reveals the presence of fissionable material. Fission product β-delayed γ-rays above 3 MeV are nearly 10 times more abundant than β-delayed neutrons and are distinct from natural radioactivity and from nearly all of the induced activity in a normal cargo. Detector backgrounds and potential interferences with the fission signature radiation have been identified and quantified. Their impact on detection sensitivity is relatively minor and can be addressed readily. Components of a simple laboratory prototype have been assembled, tested with the most challenging cargo threat scenarios, and results compared to computer simulations. Preliminary results will be presented.

  10. The nuclear car wash: A system to detect nuclear weapons in commercial cargo shipments

    International Nuclear Information System (INIS)

    Slaughter, D.R.; Accatino, M.R.; Bernstein, A.; Biltoft, P.; Church, J.A.; Descalle, M.A.; Hall, J.M.; Manatt, D.R.; Mauger, G.J.; Moore, T.L.; Norman, E.B.; Petersen, D.C.; Pruet, J.A.; Prussin, S.G.

    2007-01-01

    A concept for detecting the presence of special nuclear material ( 235 U or 239 Pu) concealed in intermodal cargo containers has been developed, studied, and recent performance results are described. It is based on interrogation with a pulsed beam of 3-7 MeV neutrons that produce fission events and subsequent detection of their β-delayed neutron emission or β-delayed high-energy γ-radiation reveals the presence of fissionable material. Fission product β-delayed γ-rays above 3 MeV are nearly 10 times more abundant than β-delayed neutrons and are distinct from natural radioactivity and from nearly all of the induced activity in a normal cargo. Detector backgrounds and potential interferences with the fission signature radiation have been identified and quantified. Their impact on detection sensitivity is relatively minor and can be addressed readily. Components of a simple laboratory prototype have been assembled, tested with the most challenging cargo threat scenarios, and results compared to computer simulations. Preliminary results will be presented

  11. REDNET: a distributed data acquisition system for a nuclear research reactor

    International Nuclear Information System (INIS)

    Shah, R.R.; Pensom, C.F.

    1984-05-01

    Experimental facilities such as those in the NRU nuclear research reactor at the Chalk River Nuclear Laboratories (CRNL) need a data acquisition system that combines high performance with flexibility. The REactor Data NETwork (REDNET) is a system being developed at CRNL that used distributed computer technology to meet demanding requirements. This paper describes the distributed architecture of REDNET, comprising 7 minicomputers, and presents an overview of the software configuration and data structures which have been designed to produce a versatile and interactive system that must gather and store data at rates ranging from 20 times a second to once every 30 minutes. Each experimenter is provided with a unique set of points that are referred to collectively, and manipulated together as a group. Facilities are provided to modify operating parameters for and view data values in a group without affecting other groups. Facilities incorporated for graceful degradation of REDNET and automatic recovery from failures are also described

  12. A computer-controlled electronic system for the ultrasonic NDT of components for nuclear power stations

    International Nuclear Information System (INIS)

    Rehrmann, M.; Harbecke, D.

    1987-01-01

    The paper describes an automatic ultrasonic testing system combined with a computer-controlled electronics system, called IMPULS I, for the non-destructive testing of components of nuclear reactors. The system can be used for both in-service inspection and for inspection during the manufacturing process. IMPUL I has more functions and less components than conventional ultrasonic systems, and the system gives good reproducible test results and is easy to operate. (U.K.)

  13. Emergency cooling system for a gas-cooled nuclear reactor

    International Nuclear Information System (INIS)

    Cook, R.K.; Burylo, P.S.

    1975-01-01

    The site of the gas-cooled reactor with direct-circuit gas turbine is preferably the sea coast. An emergency cooling system with safety valve and emergency feed-water addition is designed which affects at least a part of the reactor core coolant after leaving the core. The emergency cooling system includes a water emergency cooling circuit with heat exchanger for the core coolant. The safety valve releases water or steam from the emergency coolant circuit when a certain temperature is exceeded; this is, however, replaced by the emergency feed-water. If the gas turbine exhibits a high and low pressure turbine stage, which are flowed through by coolant one behind another, a part of the coolant can be removed in front of each part turbine by two valves and be added to the haet exchanger. (RW/LH) [de

  14. Multi parametric system for the acquisition and processing of nuclear data on a personal computer

    International Nuclear Information System (INIS)

    Toledo Acosta, R. B.; Osorio Deliz, J. F.; Arista Romeu, E.; Perez Sanchez, R.; Lopez Torres, E.

    1997-01-01

    A four-parameter Multi parametric System for the acquisition and processing of nuclear data is described. It is characterized for its flexibility and relatively low cost, also guaranteeing a high acquisition capacity. The system allows to be utilized in a multi parametric manner, in pulse height analysis or in any combination of both for parameter. The hardware and the software of the system are described. A general explanation of the operation and the characteristics of the system is offered. (author) [es

  15. Design and application of a nuclear data system

    International Nuclear Information System (INIS)

    Pohl, A.; Zappe, D.

    1977-03-01

    A radionuclide data system established for various uses is presented. Besides the schematic use of the data base, given by fixed and recurring classes of problems, a non-schematic use has been made possible due to random access to individual data. The applicability is demonstrated using as examples the management, revision and archiving of the data base, the incorporation of other data bases, the calculation of radionuclide decay chains, and the determination of gamma spectra of any radionuclide mixture

  16. A coordinated multivariable control system design for a HVDC linked remote ABWR nuclear power park

    International Nuclear Information System (INIS)

    Hara, T.; Kurita, A.; Younkins, T.D.; Sanchez-Gasca, J.J.; Chow, J.H.

    1987-01-01

    This paper presents a conceptual design of a coordinated output feedback multivariable control system for a remote nuclear generation park connected to a load area with an HVDC link. The control design presented in this paper is for both normal operation (e.g., load following and frequency regulation) and contingencies (e.g., loss of a dc bipole or loss of two nuclear reactors). The design is simple and compact: four control signals, five measurements, and the integrals of two measurements are used to meet all the objectives and constraints for normal operation and contingencies. The multivariable control coordinates the measurements and controls according to the time frame of response and the amount of interactions between variables. This paper describes the model of the system, the multivariable control design, and the nonlinear time domain simulation of the overall system performance

  17. Evolution of systems concepts for a 100 kWe class space nuclear power system

    International Nuclear Information System (INIS)

    Katucki, R.; Josloff, A.; Kirpich, A.; Florio, F.

    1985-01-01

    Conceptual designs for the SP-100 space nuclear power system have been prepared that meet baseline, backup and growth program scenarios. Near-term advancement in technology was considered in the design of the baseline concept. An improved silicon-germanium thermoelectric technique is used to convert the heat from a fast-spectrum, liquid lithium cooled reactor. This system produces a net power of 100 kWe with a 10-year end of life, under the specific constraints of area and volume. Output of the backup concept is estimated to be 60 kWe for a 10-year end of life. This system differs from the naseline concept because currently available thermoelectric conversion is used from energy supplied by a liquid sodium cooled reactor. The growth concept uses Stirling engine conversion to produce 100 kWe within the constraints of mass and volume. The growth concept can be scaled up to produce a 1 MWe output that uses the same type reactor developed for the baseline concept. Assessments made for each of the program scenarios indicate the key development efforts needed to initiate detailed design and hardware program phases. Development plans were prepared for each scenario that detail the work elements and show the program activities leading to a state of flight readiness

  18. Evolution of systems concepts for a 100 kWe class Space Nuclear Power System

    Science.gov (United States)

    Katucki, R.; Josloff, A.; Kirpich, A.; Florio, F.

    1985-01-01

    Conceptual designs for the SP-100 Space Nuclear Power System have been prepared that meet baseline, backup and growth program scenarios. Near-term advancement in technology was considered in the design of the Baseline Concept. An improved silicon-germanium thermoelectric technique is used to convert the heat from a fast-spectrum, liquid lithium cooled reactor. This system produces a net power of 100 kWe with a 10-year end of life, under the specific constraints of area and volume. Output of the Backup Concept is estimated to be 60 kWe for a 10-year end of life. This system differs from the Baseline Concept because currently available thermoelectric conversion is used from energy supplied by a liquid sodium cooled reactor. The Growth Concept uses Stirling engine conversion to produce 100 kWe within the constraints of mass and volume. The Growth Concept can be scaled up to produce a 1 MWe output that uses the same type reactor developed for the Baseline Concept. Assessments made for each of the program scenarios indicate the key development efforts needed to initiate detailed design and hardware program phases. Development plans were prepared for each scenario that detail the work elements and show the program activities leading to a state of flight readiness.

  19. Nuclear system test simulator

    International Nuclear Information System (INIS)

    Sawyer, S.D.; Hill, W.D.; Wilson, P.A.; Steiner, W.M.

    1987-01-01

    A transportable test simulator is described for a nuclear power plant. The nuclear power plant includes a control panel, a reactor having actuated rods for moving into and out of a reactor for causing the plant to operate, and a control rod network extending between the control panel and the reactor rods. The network serially transmits command words between the panel and rods, and has connecting interfaces at preselected points remote from the control panel between the control panel and rods. The test simulator comprises: a test simulator input for transport to and connection into the network at at least one interface for receiving the serial command words from the network. Each serial command includes an identifier portion and a command portion; means for processing interior of the simulator for the serial command words for identifying that portion of the power plant designated in the identifier portion and processing the word responsive to the command portion of the word after the identification; means for generating a response word responsive to the command portion; and output means for sending and transmitting the response word to the nuclear power plant at the interface whereby the control panel responds to the response word

  20. Nuclear fusion system

    International Nuclear Information System (INIS)

    Dow, W.G.

    1981-01-01

    The invention pertains to the method and apparatus for the confining of a stream of fusible positive ions at values of density and high average kinetic energy, primarily of tightly looping motions, to produce nuclear fusion at a useful rate; more or less intimately mixed with the fusible ions will be lowerenergy electrons at about equal density, introduced solely for the purpose of neutralizing the positive space charge of the ions

  1. International outage coding system for nuclear power plants. Results of a co-ordinated research project

    International Nuclear Information System (INIS)

    2004-05-01

    The experience obtained in each individual plant constitutes the most relevant source of information for improving its performance. However, experience of the level of the utility, country and worldwide is also extremely valuable, because there are limitations to what can be learned from in-house experience. But learning from the experience of others is admittedly difficult, if the information is not harmonized. Therefore, such systems should be standardized and applicable to all types of reactors satisfying the needs of the broad set of nuclear power plant operators worldwide and allowing experience to be shared internationally. To cope with the considerable amount of information gathered from nuclear power plants worldwide, it is necessary to codify the information facilitating the identification of causes of outages, systems or component failures. Therefore, the IAEA established a sponsored Co-ordinated Research Project (CRP) on the International Outage Coding System to develop a general, internationally applicable system of coding nuclear power plant outages, providing worldwide nuclear utilities with a standardized tool for reporting outage information. This TECDOC summarizes the results of this CRP and provides information for transformation of the historical outage data into the new coding system, taking into consideration the existing systems for coding nuclear power plant events (WANO, IAEA-IRS and IAEA PRIS) but avoiding duplication of efforts to the maximum possible extent

  2. Pipe support for use in a nuclear system

    International Nuclear Information System (INIS)

    Pollono, L.P.; Mello, R.M.

    1976-01-01

    Description is given of a vertical pipe support system. It comprises a tubular pipe support structure having the same inside diameter and the same wall thickness as the pipe, the pipe support structure having a generally triangularly shaped extension formed integral with and extending circumferentially around its outward side, the bottom side of this extension generally forming a ledge; an annular load-bearing insulation formed adjacent to the extension; means for clamping the load-bearing insulation to extension; and means for providing constant vertical support to means for clamping [fr

  3. Nuclear reactor equipped with a flooding tank and a residual heat removal and emergency cooling system

    International Nuclear Information System (INIS)

    Schabert, H.P.; Winkler, F.

    1975-01-01

    A description is given of a nuclear reactor such as a pressurized-water reactor or the like which is equipped with a flooding tank and a residual heat removal and emergency cooling system. The flooding tank is arranged within the containment shell at an elevation above the upper edge of the reactor core and contains a liquid for flooding the reactor core in the event of a loss of coolant

  4. Reliability analysis of scram system of a critical nuclear power plant

    International Nuclear Information System (INIS)

    Vieira Neto, A.S.; Souza Borges, W. de

    1986-01-01

    The object of this paper is to show the relevancy of reliability analysis of nuclear systems as a mean of evaluating their prospect performance in design phase. For this purpose a typical scram system design for light water cooled critical facilities is analized to verify the effects of alternative maintenance procedure and design redundancies in realibility characteristics. (Author) [pt

  5. 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

  6. FRENDY: A new nuclear data processing system being developed at JAEA

    Directory of Open Access Journals (Sweden)

    Tada Kenichi

    2017-01-01

    Full Text Available JAEA has provided an evaluated nuclear data library JENDL and nuclear application codes such as MARBLE, SRAC, MVP and PHITS. These domestic codes have been widely used in many universities and industrial companies in Japan. However, we sometimes find problems in imported processing systems and need to revise them when the new JENDL is released. To overcome such problems and immediately process the nuclear data when it is released, JAEA started developing a new nuclear data processing system, FRENDY in 2013. This paper describes the outline of the development of FRENDY and both its capabilities and performances by the analyses of criticality experiments. The verification results indicate that FRENDY properly generates ACE files.

  7. Computerized systems for on-line management of failures: a state-of-the-art discussion of alarm systems and diagnostic systems applied in the nuclear industry

    International Nuclear Information System (INIS)

    Kim, I.S.

    1994-01-01

    It is now well perceived in the nuclear industry that improving plant information systems is vital for enhancing the operational safety of nuclear power plants. Considerable work is underway worldwide to support operators' decision-making, particularly in their difficult tasks of managing process anomalies on-line. The work includes development of (1) advanced alarm systems, such as various kinds of computer-based alarm processing systems, Critical Function Monitoring System, Success Path Monitoring System and Safety Assessment System II, and (2) real-timer diagnostic systems, such as Disturbance Analysis System, Maryland Operator Advisory System II, Model-Integrated Diagnostic Analysis System, Diagnosis System using Knowledge Engineering Technique, Detailed Diagnosis, and Operator Advisor System. This paper presents a state-of-the-art review of plant information systems for on-line management of failures in nuclear power plants, focusing on the methodological features of computerized alarm systems and diagnostic systems. (author)

  8. A study on environmental regulation and public inquiry system of nuclear facilities

    International Nuclear Information System (INIS)

    Lee, Sang Hun; Kang, Chang Sun; Son, Ki Yon; Cho, Young Ho; Yang, Ji Won; Lee, Young Wook; Ko, Hyun Suk

    2000-03-01

    Public hearing system for domestic and foreign nuclear facilities are investigated and analyzed. As a result, Korean public hearing system are developed. Atomic Energy Act, Environmental Impact Assessment Act and Administrative Procedure Act of Korea are reviewed and appropriate acts, regulations, procedures and mandates of foreign countries including U.S.A are reviewed and analyzed. On the basis of these results the role of device to collect public opinion is identified for nuclear facility of Korea and the elementary principle of the system and recommendations are developed

  9. A study on environmental regulation and public inquiry system of nuclear facilities

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Sang Hun [Korea Association for Nuclear Technology, Taejon (Korea, Republic of); Kang, Chang Sun; Son, Ki Yon; Cho, Young Ho; Yang, Ji Won; Lee, Young Wook; Ko, Hyun Suk [Seoul National Univ., Seoul (Korea, Republic of)

    2000-03-15

    Public hearing system for domestic and foreign nuclear facilities are investigated and analyzed. As a result, Korean public hearing system are developed. Atomic Energy Act, Environmental Impact Assessment Act and Administrative Procedure Act of Korea are reviewed and appropriate acts, regulations, procedures and mandates of foreign countries including U.S.A are reviewed and analyzed. On the basis of these results the role of device to collect public opinion is identified for nuclear facility of Korea and the elementary principle of the system and recommendations are developed.

  10. A CAMAC-VME-Macintosh data acquisition system for nuclear experiments

    Science.gov (United States)

    Anzalone, A.; Giustolisi, F.

    1989-10-01

    A multiprocessor system for data acquisition and analysis in low-energy nuclear physics has been realized. The system is built around CAMAC, the VMEbus, and the Macintosh PC. Multiprocessor software has been developed, using RTF, MACsys, and CERN cross-software. The execution of several programs that run on several VME CPUs and on an external PC is coordinated by a mailbox protocol. No operating system is used on the VME CPUs. The hardware, software, and system performance are described.

  11. Development of TIG Welding System for a Nuclear Fuel Test Rig

    International Nuclear Information System (INIS)

    Joung, Changyoung; Ahn, Sungho; Hong, Jintae; Kim, Kahye

    2013-01-01

    The welding process is one of the most important among the instrumentation processes of the nuclear fuel test rig and rods. To manufacture the nuclear fuel test rig, a precision welding system needs to be fabricated to develop various welding technologies of the fuel test rig and rods jointing the various sensors and end caps on a fuel cladding tube, which is charged with fuel pellets and component parts. Thus, we designed and fabricated the precision welding system consisting of an orbital TIG welder, a low-pressure chamber, and a high-pressure chamber. Using this system, the performance tests were performed with the round and seal spot welds for each welding condition. This paper describes not only the contents for the fabrication of precision TIG welding system but also some results from weld tests using the low-pressure and high-pressure chambers to verify the performance of this system. The TIG welding system was developed to manufacture the nuclear fuel test rig and rods. It has been configured to be able to weld the nuclear fuel test rigs and rods by applying the TIG welder using a low-pressure chamber and a high-pressure chamber. The performance tests using this system were performed with the round and seal spot welds for the welding conditions. The soundness of the orbital TIG welding system was confirmed through performance tests in the low-pressure and high-pressure chambers

  12. Development of TIG Welding System for a Nuclear Fuel Test Rig

    Energy Technology Data Exchange (ETDEWEB)

    Joung, Changyoung; Ahn, Sungho; Hong, Jintae; Kim, Kahye [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2013-05-15

    The welding process is one of the most important among the instrumentation processes of the nuclear fuel test rig and rods. To manufacture the nuclear fuel test rig, a precision welding system needs to be fabricated to develop various welding technologies of the fuel test rig and rods jointing the various sensors and end caps on a fuel cladding tube, which is charged with fuel pellets and component parts. Thus, we designed and fabricated the precision welding system consisting of an orbital TIG welder, a low-pressure chamber, and a high-pressure chamber. Using this system, the performance tests were performed with the round and seal spot welds for each welding condition. This paper describes not only the contents for the fabrication of precision TIG welding system but also some results from weld tests using the low-pressure and high-pressure chambers to verify the performance of this system. The TIG welding system was developed to manufacture the nuclear fuel test rig and rods. It has been configured to be able to weld the nuclear fuel test rigs and rods by applying the TIG welder using a low-pressure chamber and a high-pressure chamber. The performance tests using this system were performed with the round and seal spot welds for the welding conditions. The soundness of the orbital TIG welding system was confirmed through performance tests in the low-pressure and high-pressure chambers.

  13. Development of a Online Nuclear Emergency Response System (ONERS) for Kalpakkam site - the design aspects

    Energy Technology Data Exchange (ETDEWEB)

    Raja Shekhar, S. S.; Bhatawadekar, Shantanu; Krishna Murthy, Y. V.N., [Regional Remote Sensing Service Centre, Department of Space, Nagpur (India); Srinivas, C. V.; Venkatesan, [Radiological Safety Division, Radiological Safety and Environmental Group, Indira Gandhi Centre for Atomic Research, Kalapakkam (India)

    2012-07-01

    An Online Nuclear Emergency Response System (ONERS) is developed for the nuclear power plant site at Kalpakkam as part of the Department of Atomic Energy (DAE) initiative. ONERS is a GIS based spatial analysis system designed indigenously to provide decision support in the event of a radioactive leak or accident from any of the nuclear facilities by assessing the dispersion and deposition patterns of the atmospheric releases, integrate with spatial geographical database for impact assessment and guidance for mitigation. The system is designed with open software tools (UMN Map server, MYSQL, PHP, Java scripts) and its main features include assessment of dose, short and long term forecast, counter measure support, impact assessment to minimize potential threat to man and environment during radiological emergencies. The system is implemented in live mode with integration of numerical models and spatial data base for the site region and is presently operational for the Kalpakkam site. (author)

  14. Development of a Online Nuclear Emergency Response System (ONERS) for Kalpakkam site - the design aspects

    International Nuclear Information System (INIS)

    Raja Shekhar, S.S.; Bhatawadekar, Shantanu; Krishna Murthy, Y.V.N.; Srinivas, C.V.; Venkatesan

    2012-01-01

    An Online Nuclear Emergency Response System (ONERS) is developed for the nuclear power plant site at Kalpakkam as part of the Department of Atomic Energy (DAE) initiative. ONERS is a GIS based spatial analysis system designed indigenously to provide decision support in the event of a radioactive leak or accident from any of the nuclear facilities by assessing the dispersion and deposition patterns of the atmospheric releases, integrate with spatial geographical database for impact assessment and guidance for mitigation. The system is designed with open software tools (UMN Map server, MYSQL, PHP, Java scripts) and its main features include assessment of dose, short and long term forecast, counter measure support, impact assessment to minimize potential threat to man and environment during radiological emergencies. The system is implemented in live mode with integration of numerical models and spatial data base for the site region and is presently operational for the Kalpakkam site. (author)

  15. A new coupled system for BWR nuclear fuel management

    International Nuclear Information System (INIS)

    Castillo, A.; Ortiz-Servin, J.J.; Montes-Tadeo, J.L.; Perusquia, R.; Rizos, R.L.M.

    2015-01-01

    In this work, a system to solve four stages of the fuel management problem is showed.The system uses different heuristic techniques to solve each stage of that area, and this problem is solved in a coupled way. Considered problems correspond to the following designs: fuel lattice, fuel assembly, fuel reload and control rod patterns. Even though, each stage of the problem can have its own objective function, the complete problem was solved using a multi-objective function. The solution strategy is to solve each stage of design in an iterative process, taking into account previous results for the next stage, until to achieve a complete solution. The solution strategy to solve the coupled problem is the following: the first solved stage is the fuel lattice design, the second one is fuel assembly design, finally an internal loop between both fuel reload design and control rod pattern design is carried out.For this internal loop, a seed reload using Haling principle is generated. The obtained results showed the advantage to solve the whole problem in a coupled way. (author)

  16. A nuclear fuel cycle system dynamic model for spent fuel storage options

    International Nuclear Information System (INIS)

    Brinton, Samuel; Kazimi, Mujid

    2013-01-01

    Highlights: • Used nuclear fuel management requires a dynamic system analysis study due to its socio-technical complexity. • Economic comparison of local, regional, and national storage options is limited due to the public financial information. • Local and regional options of used nuclear fuel management are found to be the most economic means of storage. - Abstract: The options for used nuclear fuel storage location and affected parameters such as economic liabilities are currently a focus of several high level studies. A variety of nuclear fuel cycle system analysis models are available for such a task. The application of nuclear fuel cycle system dynamics models for waste management options is important to life-cycle impact assessment. The recommendations of the Blue Ribbon Committee on America’s Nuclear Future led to increased focus on long periods of spent fuel storage [1]. This motivated further investigation of the location dependency of used nuclear fuel in the parameters of economics, environmental impact, and proliferation risk. Through a review of available literature and interactions with each of the programs available, comparisons of post-reactor fuel storage and handling options will be evaluated based on the aforementioned parameters and a consensus of preferred system metrics and boundary conditions will be provided. Specifically, three options of local, regional, and national storage were studied. The preliminary product of this research is the creation of a system dynamics tool known as the Waste Management Module (WMM) which provides an easy to use interface for education on fuel cycle waste management economic impacts. Initial results of baseline cases point to positive benefits of regional storage locations with local regional storage options continuing to offer the lowest cost

  17. MACRO1: a code to test a methodology for analyzing nuclear-waste management systems

    International Nuclear Information System (INIS)

    Edwards, L.L.

    1979-01-01

    The code is primarily a manager of probabilistic data and deterministic mathematical models. The user determines the desired aggregation of the available models into a composite model of a physical system. MACRO1 then propagates the finite probability distributions of the inputs to the model to finite probability distributions over the outputs. MACRO1 has been applied to a sample analysis of a nuclear-waste repository, and its results compared satisfactorily with previously obtained Monte Carlo statistics

  18. Energy System Expectations for Nuclear in the 21. Century: A Plausible Range

    International Nuclear Information System (INIS)

    Langlois, Lucille M.; McDonald, Alan; Rogner, Hans-Holger; Vera, Ivan

    2002-01-01

    This paper outlines a range of scenarios describing what the world's energy system might look like in the middle of the century, and what nuclear energy's most profitable role might be. The starting point is the 40 non-greenhouse-gas-mitigation scenarios in the Special Report on Emissions Scenarios (SRES) of the Intergovernmental Panel on Climate Change (IPCC, 2000). Given their international authorship and comprehensive review by governments and scientific experts, the SRES scenarios are the state of the art in long-term energy scenarios. However, they do not present the underlying energy system structures in enough detail for specific energy technology and infrastructure analyses. This paper therefore describes initial steps within INPRO (The International Project on Innovative Nuclear Reactors and Fuel Cycles of the International Atomic Energy Agency) to translate the SRES results into a range of possible nuclear energy technology requirements for mid-century. The paper summarizes the four SRES scenarios that will be used in INPRO and the reasons for their selection. It provides illustrative examples of the sort of additional detail that is being developed about the overall energy system implied by each scenario, and about specific scenario features particularly relevant to nuclear energy. As recommended in SRES, the selected scenarios cover all four SRES 'story-line families'. The energy system translations being developed in INPRO are intended to indicate how energy services may be provided in mid-century and to delineate likely technology and infrastructure implications. They will indicate answers to questions like the following. The list is illustrative, not comprehensive. - What kind of nuclear power plants will best fit the mid-century energy system? - What energy forms and other products and services provided by nuclear reactors will best fit the mid-century energy system? - What would be their market shares? - How difficult will it be to site new nuclear

  19. Control system design considerations in a modern nuclear power plant

    International Nuclear Information System (INIS)

    Foster, P.; Raiskums, G.; Harber, J.; Tikku, S.

    2010-01-01

    Applying new technologies is a challenge for instrumentation and control (I and C) designers to ensure that the overall principles of defence-in-depth, the independence of safety functions (credited in the safety case), and modern human factors engineering principles are maintained. This paper describes the Advanced CANDU Reactor (ACR-1000) I and C architecture, including the display/control systems and the design approaches employed to ensure that the fundamental premise of independence between safety and process control is not compromised and that the reliability targets for each layer of protection are fulfilled to meet the overall plant safety goals. (author)

  20. Two-fluid equations for a nuclear system with arbitrary motions

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Byoung Jae [Chungnam National University, Daejeon (Korea, Republic of); Kim, Kyung Doo [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2016-10-15

    Ocean nuclear systems include a seabed-type plant, a floating-type plant, and a nuclear-propulsion ship. We asked ourselves, 'What governing equations should be used for ocean nuclear systems?' Since ocean nuclear systems are apt to move arbitrarily, the two-fluid model must be formulated in the non-inertial frame of reference that is undergoing acceleration with respect to an inertial frame. Two-phase flow systems with arbitrary motions are barely reported. Kim et al. (1996) added the centripetal and Euler acceleration forces to the homogeneous equilibrium momentum equation embedded in the RETRAN code. However, they did not look into the mass and energy equations. The purpose of this study is to derive general two-fluid equations in the non-inertial frame of reference, which can be used for safety analysis of ocean nuclear systems. The two-fluid equation forms for scalar properties such as mass, internal energy, and enthalpy equation in the moving frame are the same as those in the absolute frame. On the other hand, the fictitious effect must be included in the momentum equation.

  1. Information flow a data bank preparation in nuclear power plant reliability information system

    International Nuclear Information System (INIS)

    Kolesa, K.; Vejvodova, I.

    1983-01-01

    In the year 1981 the reliability information system for nuclear power plants (ISS-JE) was established. The objective of the system is to make a statistical evaluation of the operation of nuclear power plants and to obtain information on the reliability of the equipment of nuclear power plants and the transmission of this information to manufacturers with the aim of inducing them to take corrective measures. The HP 1000 computer with the data base system IMAGE 100 is used which allows to process single queries and periodical outputs. The content of periodical outputs designed for various groups of subcontractors is briefly described and trends of the further development of the system indicated. (Ha)

  2. ARGOS - a decision support system for nuclear emergencies

    International Nuclear Information System (INIS)

    Hoe, S.; Mueller, H.

    2003-01-01

    Full text: The Danish developed ARGOS system is in operation in Denmark, Canada, Ireland, Norway and 4 Baltic Sea states. ARGOS is a dynamic system that is modified regularly in order to cope with new requirements. The present version of the system includes features such as: presentations of monitoring data including high-resolution data from airborne gamma surveys and use of these data in food dose modelling; presentation of meteorological data including precipitation; atmospheric dispersion calculations; food dose modelling based on atmospheric dispersion and/or monitoring; web features such as animations and exchange of source terms. Atmospheric dispersion in ARGOS is divided in two parts, a short and mesoscale dispersion model LSMC /RIMPUFF and a long-range models: DERMA (Danish) and MLDPO (Canada). The short range model -LSMC comprises a meteorological pre-processor, which calculates time and height dependent fields of meteorological parameters (deposition, stability, wind etc.) based on the data provided by the DMI-HIRLAM model or by meteorological masts. Based on these data calculations of gamma doses and concentrations are made by the puff model RIMPUFF. Input data for the Food Dose Module, FDM, are also created. RIMPUFF may be used up to distance of a few hundred kilometres from the source. RIMPUFF has been validated with success against several experiments. The long range models are executed at the National Meteorological institutes. The inputs to the long-range models are automatically uploaded from ARGOS to the Meteorological centres where the meteorological data is taken from the operational weather prediction models (NWP). At the Danish Meteorological Institute (DMI) up to 4 calculations are executed on different versions of the NWP model, with various geographical coverage and resolution. When the calculations are finalized, the monitor function in ARGOS will prompt the users for download of the results. The most recent version of ARGOS includes a

  3. Recent space nuclear power systems

    International Nuclear Information System (INIS)

    Takizuka, Takakazu; Yasuda, Hideshi; Hishida, Makoto

    1991-01-01

    For the advance of mankind into the space, the power sources of large output are indispensable, and it has been considered that atomic energy is promising as compared with solar energy and others. Accordingly in USA and USSR, the development of the nuclear power generation systems for space use has been carried out since considerable years ago. In this report, the general features of space nuclear reactors are shown, and by taking the system for the SP-100 project being carried out in USA as the example, the contents of the recent design regarding the safety as an important factor are discussed. Moreover, as the examples of utilizing space nuclear reactors, the concepts of the power source for the base on the moon, the sources of propulsive power for the rockets used for Mars exploration and others, the remote power transmission system by laser in the space and so on are explained. In September, 1988, the launching of a space shuttle of USA was resumed, and the Jupiter explorer 'Galileo' and the space telescope 'Hubble' were successfully launched. The space station 'Mir' of USSR has been used since February, 1986. The history of the development of the nuclear power generation systems for space use is described. (K.I.)

  4. A nuclear decision support system built with a real-time process control AI shell

    International Nuclear Information System (INIS)

    Nevins, M.A.

    1990-01-01

    Managing large nuclear power plants is generally approached by creating separate management teams to handle major functional areas such as operations, maintenance, training and engineering. While this approach facilitates a general understanding of the specific functions and problem areas of a nuclear plant, such broad definitions diminish the integration of information needed to understand the overall problem domain. One solution utilizes a decision support system that integrates a real-time process control AI shell, relational database manager, graphic depiction of the real-time events, and distributed knowledge bases that reside within each of the departments. The goal is to create a living model between plant components, procedures, tech specs, specific functions, maintenance and training requirements. This paper describes such a model, called Engineering Model and Simulation System (EMASS)

  5. Proposal of a system for fuel elements inspection of CDTN TRIGA nuclear reactor

    International Nuclear Information System (INIS)

    Rodrigues, Rogerio Rivail; Mesquita, Amir Zacarias

    2013-01-01

    The CDTN has in its facilities a TRIGA-type nuclear reactor. The reactor's cooling water must be treated and managed with the goal of keeping its low conductivity to minimize corrosion of the reactor components, mainly of fuel elements (FE), and reduce the level of radioactivity. The aim of this paper is to present a proposal for the development of a system for verification of some possible leaks in FE nuclear research reactors, based on the sipping test. This type of testing is a way to check for leaks of fission products from fuel element of nuclear research reactor. In the future, when the test will do, it will have a correlation between the components found in the reactor cooling water pool and integrity of nuclear fuel elements. The device development and its application will be presented here, covering results that were not previously investigated yet, giving originality to this project. (author)

  6. DIMOS: a new generation of nuclear power plant process monitoring systems

    International Nuclear Information System (INIS)

    Vlaminck, M. de; Gilliot, B.; Remacle, J.

    1993-01-01

    A new generation of nuclear power plant supervision systems is described, called DIMOS (DIstributed MOnitoring System). It was installed in August 1991 at the Doel nuclear power plant and is now monitoring reactors 1 and 2. The system represents one of the largest and most advanced process monitoring systems in operation. DIMOS has successfully provided the solution to the old system's limitations such as functional deficiencies, low response time, management and coherence of the data, maintenance costs, spare parts, and system availability. The use of the software development methodologies HOOD and ADA have not only allowed a rapid integration and installation of a robust system, but will also make further developments and improvements possible with maximum flexibility. (Z.S.) 2 figs

  7. Remote system for counting of nuclear pulses

    International Nuclear Information System (INIS)

    Nieves V, J.A.; Garcia H, J.M.; Aguilar B, M.A.

    1999-01-01

    In this work, it is describe technically the remote system for counting of nuclear pulses, an integral system of the project radiological monitoring in a petroleum distillation tower. The system acquires the counting of incident nuclear particles in a nuclear detector which process this information and send it in serial form, using the RS-485 toward a remote receiver, which can be a Personal computer or any other device capable to interpret the communication protocol. (Author)

  8. Waste management strategy for nuclear fusion power systems from a regulatory perspective

    Energy Technology Data Exchange (ETDEWEB)

    Heckman, R.A.

    1977-12-06

    A waste management strategy for future nuclear fusion power systems is developed using existing regulatory methodology. The first step is the development of a reference fuel cycle. Next, the waste streams from such a facility are identified. Then a waste management system is defined to safely handle and dispose of these wastes. The future regulator must identify the decisions necessary to establish waste management performance criteria. The data base and methodologies necessary to make these decisions must then be developed. Safe management of nuclear fusion wastes is not only a technological challenge, but encompasses significant social, political, and ethical questions as well.

  9. Waste management strategy for nuclear fusion power systems from a regulatory perspective

    International Nuclear Information System (INIS)

    Heckman, R.A.

    1977-01-01

    A waste management strategy for future nuclear fusion power systems is developed using existing regulatory methodology. The first step is the development of a reference fuel cycle. Next, the waste streams from such a facility are identified. Then a waste management system is defined to safely handle and dispose of these wastes. The future regulator must identify the decisions necessary to establish waste management performance criteria. The data base and methodologies necessary to make these decisions must then be developed. Safe management of nuclear fusion wastes is not only a technological challenge, but encompasses significant social, political, and ethical questions as well

  10. After heat removing system of a nuclear reactor

    International Nuclear Information System (INIS)

    Hayashi, Takao; Yamada, Masao; Ohashi, Kazutaka.

    1994-01-01

    In a variable conductance heat pipe of an after heat removing system, an evaporation portion and a condensator are connected by a steam diffusing path for an operation fluid and a liquid condensate recycling path. Further, incondensible gases are sealed at the inside together with the operation fluid, and a gas reservoir for the incondensible gases is disposed at the downstream of a condensation portion. If heat input is applied to the evaporation portion of the heat pipe, the incondensible gases are separated to form a boundary between both of them. When the amount of heat applied is small, the incondensible gases partially seal the condensation portion to form a local condensation insensitive portion, so that a heat conductance can be suppressed low. On the other hand, as the amount of heat inputted is increased, the incondensible gases are compressed, the heat conduction area of the condensation portion is increased and a heat conductance is increased to conduct self-control so as to increase heat transfer performance of the heat pipe. Then, the liquid condensate is recycled to the evaporation portion by spontaneous dripping of the condensate itself without wick, thereby enabling to conduct automatic switching so as to increase the heat dissipation amount to maximum. (N.H.)

  11. Conceptual design of a system for nuclear material control in a research centre according to the IAEA safeguards requirements

    International Nuclear Information System (INIS)

    Bueker, H.; Kotte, U.; Stein, G.

    1976-01-01

    In comparison with other facilities handling nuclear material, a nuclear research centre is characterized by a wider spectrum of operations. This requires a number of installations within the centre such as research reactors, critical assemblies, research institutes and central departments, operating, in general, independently of each other. Nuclear material is stored and processed in small quantities and in different chemical and physical configurations within prescribed license areas. The conceptual design of a new system for nuclear material control in a research centre has to consider the operator's and IAEA's safeguards requirements. Using the example of the Juelich Nuclear Research Centre in the Federal Republic of Germany, these requirements are being examined in conjunction with the specified peculiarities of a nuclear research centre. Following this, a division of the research centre into material balance areas and key measurement points is being proposed, based on the existing facilities and licence areas. The essential characteristic of the concept is a far-reaching displayability of the inventory and flow of nuclear material. The availability of information is based on differentiated material accountancy in conjunction with adequate measurement of nuclear material data. For data processing and generation of data, a computerized record and report system is to be provided as well as a central measurement system. The design of an integrated accountancy system with a central computer and remote terminals is described; various measuring appliances, now being developed or tested, for the non-destructive assay of nuclear material are specified. The functions of a central department for nuclear material management for operating these systems are discussed and the planned verification of nuclear material in the different material balance areas illustrated. On applying the measures described in this paper, the conceptual design of a system for nuclear material

  12. Deliberations on nuclear safety regulatory system in a changing industrial environment

    International Nuclear Information System (INIS)

    Kim, H.J.

    2001-01-01

    Nuclear safety concern, which may accompany such external environmental factors as privatization and restructuring of the electric power industry, is emerging as an international issue. In order to cope with the concern about nuclear safety, it is important to feedback valuable experiences of advanced countries that restructured their electric power industries earlier and further to reflect the current safety issues, which are raised internationally, fully into the nuclear safety regulatory system. This paper is to review the safety issues that might take place in the process of increasing competition in the nuclear power industry, and further to present a basic direction and effective measures for ensuring nuclear safety in response thereto from the viewpoint of safety regulation. It includes a political direction for a regulatory body's efforts to rationalize and enforce efficiently its regulation. It proposes to ensure that regulatory specialty and regulatory cost are stably secured. Also, this paper proposes maintaining a sound nuclear safety regulatory system to monitor thoroughly the safety management activities of the industry, which might be neglected as a result of focusing on reduction of the cost for producing electric power. (author)

  13. Coolant circulation system for a liquid metal nuclear reactor

    International Nuclear Information System (INIS)

    DeLuca, R.A.; Garabedian, G.

    1988-01-01

    This patent describes a liquid metal circulation system comprising an electromagnetic pump comprised of: (a) an elongated cylindrical pump support housing; (b) a cylindrical pressure dome structure coaxially situated and supported within the pump support housing, having a closed, hemispherical upper end and an open, cylindrical lower end; (c) a cylindrical pump coaxially situated within the pressure dome structure including: (1) a central core body of laminated transformer steel having six peripherally equally spaced helical grooves on its outer surface extending the entire length of the central core body, (2) a multiplicity of square, ceramic insulated copper wires situated in the helical grooves, (3) electrical leads extending from the terminal ends of the square copper wires through the upper end of the pressure dome structure and to a three-phase low voltage/high amperage power source, (4) an austenitic stainless steel jacket covering the outer surface of the central core body and covering the helically coiled square copper wires, the outer stainless steel jacket and the inner surface of the pressure dome structure defining an annular flow passage

  14. Using proliferation risk as a design metric in the development of nuclear systems

    International Nuclear Information System (INIS)

    Beard, C.; Lebouf, R.

    2001-01-01

    The necessity has arisen for newly proposed nuclear systems to be evaluated with regard to their potential aid to any proliferation. Thus, a mechanism is needed to introduce nonproliferation as a measure in the design phase of a new nuclear system. To accomplish this, a methodology for quantifying and measuring the proliferation risk of proposed system options is required. Such quantification has its difficulties due to inherent uncertainty, e.g. what is the probability that a quantity of material will be stolen in a given situation? Also, the lack of data on such occurrences makes the task of quantification nearly insurmountable. A systematic approach is necessary to estimate the proliferation risk. Currently, an advanced nuclear power system, the Accelerator Transmutation of Waste (ATW) program has been initiated to develop a system that will concurrently generate electricity while destroying long-lived radioactive isotopes. Therefore, because of the issues noted above, an effort to introduce proliferation risk into the design phase has been started. The purpose of this paper is to review previous work in quantification of proliferation risk in an effort to develop the proper basis for the current work. It should be noted that while proliferation on a national level has been studied extensively, efforts to quantify proliferation risk of individual nuclear systems or processes have been limited. Consequently, the available literature base is relatively sparse. (author)

  15. Using proliferation risk as a design metric in the development of nuclear systems

    Energy Technology Data Exchange (ETDEWEB)

    Beard, C.; Lebouf, R. [Texas Univ., Austin, TX (United States). Nuclear Engineering Teaching Lab.

    2001-07-01

    The necessity has arisen for newly proposed nuclear systems to be evaluated with regard to their potential aid to any proliferation. Thus, a mechanism is needed to introduce nonproliferation as a measure in the design phase of a new nuclear system. To accomplish this, a methodology for quantifying and measuring the proliferation risk of proposed system options is required. Such quantification has its difficulties due to inherent uncertainty, e.g. what is the probability that a quantity of material will be stolen in a given situation? Also, the lack of data on such occurrences makes the task of quantification nearly insurmountable. A systematic approach is necessary to estimate the proliferation risk. Currently, an advanced nuclear power system, the Accelerator Transmutation of Waste (ATW) program has been initiated to develop a system that will concurrently generate electricity while destroying long-lived radioactive isotopes. Therefore, because of the issues noted above, an effort to introduce proliferation risk into the design phase has been started. The purpose of this paper is to review previous work in quantification of proliferation risk in an effort to develop the proper basis for the current work. It should be noted that while proliferation on a national level has been studied extensively, efforts to quantify proliferation risk of individual nuclear systems or processes have been limited. Consequently, the available literature base is relatively sparse. (author)

  16. Application of a model-based fault detection system to nuclear plant signals

    International Nuclear Information System (INIS)

    Gross, K.C.; Singer, R.M.; Wegerich, S.W.; Herzog, J.P.; VanAlstine, R.; Bockhorst, F.

    1997-01-01

    To assure the continued safe and reliable operation of a nuclear power station, it is essential that accurate online information on the current state of the entire system be available to the operators. Such information is needed to determine the operability of safety and control systems, the condition of active components, the necessity of preventative maintenance, and the status of sensory systems. To this end, ANL has developed a new Multivariate State Estimation Technique (MSET) which utilizes advanced pattern recognition methods to enhance sensor and component operational validation for commercial nuclear reactors. Operational data from the Crystal River-3 (CR-3) nuclear power plant are used to illustrate the high sensitivity, accuracy, and the rapid response time of MSET for annunciation of a variety of signal disturbances

  17. An integrated methodology to evaluate a spent nuclear fuel storage system

    International Nuclear Information System (INIS)

    Yoon, Jeong Hyoun

    2008-02-01

    This study introduced a methodology that can be applied for development of a dry storage system for spent nuclear fuels. It consisted of several design activities that includes development of a simplified program to analyze the amount of spent nuclear fuels from reflecting the practical situation in spent nuclear fuel management and a simplified program to evaluate the cost of 4 types of representing storage system to choose the most competitive option considering economic factor. As verification of the implementation of the reference module to practical purpose, a simplified thermal analysis code was suggested that can see fulfillment of limitation of temperature in long term storage and oxidation analysis. From the thermal related results, the reference module can accommodate full range of PHWR spent nuclear fuels and significant portion of PWR ones too. From the results, the reference storage system can be concluded that has fulfilled the important requirements in terms of long term integrity and radiological safety. Also for the purpose of solving scattered radiation along with deep penetration problems in cooling storage system, small but efficient design alternation was suggested together with its efficiency that can reduce scattered radiation by 1/3 from the original design. Along with the countermeasure for the shielding problem, in consideration of PWR spent nuclear fuels, simplified criticality analysis methodology retaining conservativeness was proposed. The results show the reference module is efficient low enrichment PWR spent nuclear fuel and even relatively high enrichment fuels too if burnup credit is taken. As conclusive remark, the methodology is simple but efficient to plan a concept design of convective cooling type of spent nuclear fuels storage. It can be also concluded that the methodology derived in this study and the reference module has feasibility in practical implementation to mitigate the current complex situation in spent fuel

  18. A full life cycle nuclear knowledge management framework based on digital system

    International Nuclear Information System (INIS)

    Wang, Minglu; Zheng, Mingguang; Tian, Lin; Qiu, Zhongming; Li, Xiaoyan

    2017-01-01

    Highlights: • A full life cycle nuclear power plant knowledge management framework is introduced. • This framework benefits the safe design, construction, operation and maintenance. • This framework enhances safety, economy and reliability of nuclear power plant. - Abstract: The nuclear power plant is highly knowledge-intensive facility. With the rapid advent and development of modern information and communication technology, knowledge management in nuclear industry has been provided with new approaches and possibilities. This paper introduces a full cycle nuclear power plant knowledge management framework based on digital system and tries to find solutions to knowledge creation, sharing, transfer, application and further innovation in nuclear industry. This framework utilizes information and digital technology to build top-tier object driven work environment, automatic design and analysis integration platform, digital dynamic performance Verification & Validation (V&V) platform, collaborative manufacture procedure, digital construction platform, online monitoring and configuration management which benefit knowledge management in NPP full life cycle. The suggested framework will strengthen the design basis of the nuclear power plants (NPPs) and will ensure the safety of the NPP design throughout the whole lifetime of the plant.

  19. Expert systems and nuclear safety

    International Nuclear Information System (INIS)

    Beltracchi, L.

    1990-01-01

    The US Nuclear Regulatory Commission (NRC) and the Electric Power Research Institute have initiated a broad-based exploration of means to evaluate the potential applications of expert systems in the nuclear industry. This exploratory effort will assess the use of expert systems to augment the diagnostic and decision-making capabilities of personnel with the goal of enhancing productivity, reliability, and performance. The initial research effort is the development and documentation of guidelines for verifying and validating (V and V) expert systems. An initial application of expert systems in the nuclear industry is to aid operations and maintenance personnel in decision-making tasks. The scope of the decision aiding covers all types of cognitive behavior consisting of skill, rule, and knowledge-based behavior. For example, procedure trackers were designed and tested to support rule-based behavior. Further, these systems automate many of the tedious, error-prone human monitoring tasks, thereby reducing the potential for human error. The paper version of the procedure contains the knowledge base and the rules and thus serves as the basis of the design verification of the procedure tracker. Person-in-the-loop tests serve as the basis for the validation of a procedure tracker. When conducting validation tests, it is important to ascertain that the human retains the locus of control in the use of the expert system

  20. Nuclear material control systems for nuclear power plants

    International Nuclear Information System (INIS)

    1975-06-01

    Paragraph 70.51(c) of 10 CFR Part 70 requires each licensee who is authorized to possess at any one time special nuclear material in a quantity exceeding one effective kilogram to establish, maintain, and follow written material control and accounting procedures that are sufficient to enable the licensee to account for the special nuclear material in his possession under license. While other paragraphs and sections of Part 70 provide specific requirements for nuclear material control systems for fuel cycle plants, such detailed requirements are not included for nuclear power reactors. This guide identifies elements acceptable to the NRC staff for a nuclear material control system for nuclear power reactors. (U.S.)

  1. Simulation study of a system for diagnosis of nuclear power plant operation

    International Nuclear Information System (INIS)

    Wakabayashi, J.; Fukumoto, A.

    1981-01-01

    A diagnostic system of the nuclear power plant operation is proposed and the applicability of this system to the actual plant has been verified by computer simulation. A typical pressurized water reactor plant simulator was made by an analog computer and the diagnostic system was made by a digital computer. The observed signals obtained from the actual plant are simulated by superposing the equivalent observation noises generated by the digital computer on the sampled signals obtained from the plant simulator. 8 refs

  2. A microcomputer based multi parametric system for nuclear data acquisition and processing

    International Nuclear Information System (INIS)

    Toledo Acosta B, Rene; Osorio Deliz F, Juan; Arista Romeu, Eduardo; Perez Sanchez, Reinaldo; Lopes Torres, E.

    1997-01-01

    A four-parameter Multi parametric System for the acquisition and processing of nuclear data is described. It is characterized for its flexibility and relatively low cost, also guaranteeing a high acquisition capacity. The system allows to be utilized in a multi parametric manner, in pulse height analysis or in many combination of both for parameter. It is described the hardware and the software of the system

  3. Nuclear database management systems

    International Nuclear Information System (INIS)

    Stone, C.; Sutton, R.

    1996-01-01

    The authors are developing software tools for accessing and visualizing nuclear data. MacNuclide was the first software application produced by their group. This application incorporates novel database management and visualization tools into an intuitive interface. The nuclide chart is used to access properties and to display results of searches. Selecting a nuclide in the chart displays a level scheme with tables of basic, radioactive decay, and other properties. All level schemes are interactive, allowing the user to modify the display, move between nuclides, and display entire daughter decay chains

  4. A hybrid approach to quantify software reliability in nuclear safety systems

    International Nuclear Information System (INIS)

    Arun Babu, P.; Senthil Kumar, C.; Murali, N.

    2012-01-01

    Highlights: ► A novel method to quantify software reliability using software verification and mutation testing in nuclear safety systems. ► Contributing factors that influence software reliability estimate. ► Approach to help regulators verify the reliability of safety critical software system during software licensing process. -- Abstract: Technological advancements have led to the use of computer based systems in safety critical applications. As computer based systems are being introduced in nuclear power plants, effective and efficient methods are needed to ensure dependability and compliance to high reliability requirements of systems important to safety. Even after several years of research, quantification of software reliability remains controversial and unresolved issue. Also, existing approaches have assumptions and limitations, which are not acceptable for safety applications. This paper proposes a theoretical approach combining software verification and mutation testing to quantify the software reliability in nuclear safety systems. The theoretical results obtained suggest that the software reliability depends on three factors: the test adequacy, the amount of software verification carried out and the reusability of verified code in the software. The proposed approach may help regulators in licensing computer based safety systems in nuclear reactors.

  5. A regulatory frame for safety digital systems in nuclear power plants

    International Nuclear Information System (INIS)

    Mozas Garcia, A.

    1998-01-01

    The paper focuses on Spanish experience regarding software based systems for safety applications from the regulator's point of view. It describes the actual situation in Spain, number and models of reactors, modernization projects, digital systems implemented and licensing documentation and processes already followed by some upgrading projects. The paper wonders what documents should be required for safety and reliability demonstration of a safety system, when they should be reviewed, and what other activities may be necessary to acquire confidence on a particular system. It describes Spanish laws regarding nuclear safety under which, national standards from the NPP design original country apply to nuclear reactors in Spain. It finally suggests that an international standard jointly used by system manufacturers, nuclear licensees and nuclear safety authorities, both from the country where the NPP is installed, and from the original design country, should be developed so that rapid and easy agreement on licensing issues is reached among all parties. The last part of the paper describes the licensing approach proposed by CSN (Spanish Nuclear Safety Authority). It is still under development and it is based on previous experience on digital systems for non-safety applications. It consists of constructing several frames: 1) databases of existing software based systems, 2) guides for inspection and 3) questionnaires for helping in verification and validation activities evaluation. The scope is to establish a well defined procedure that helps in evaluating the particular system. However, in order for such a procedure to be useful, both regulators and utilities and, perhaps also system manufacturers, should agree on it. Joint CSN-utilities working groups may be suitable for such a purpose. (author)

  6. Integrated nuclear and radiation protection systems

    International Nuclear Information System (INIS)

    Oprea, I.; Oprea, M.; Stoica, V.; Cerga, V.; Pirvu, V.; Badea, E.

    1993-01-01

    A multifunctional radiation monitoring equipment, flexible and capable to meet virtually environmental radiation monitoring, activity measurement and computational requirements, for nuclear laboratories has been designed. It can be used as a radiation protection system, for radionuclide measurement in isotope laboratories, nuclear technology, health physics and nuclear medicine, nuclear power stations and nuclear industry. The equipment is able to measure, transmit and record gamma dose rate and isotope activities. Other parameters and functions are optionally available, such as: self-contained alarm level, system self-test, dose integrator, syringe volume calculation for a given dose corrected for decay, calibration factor, 99 Mo assays performing and background subtraction

  7. Nuclear systems of level measurement

    International Nuclear Information System (INIS)

    Lara, A.J.; Cabrera, M.J.

    1992-01-01

    In the industry there are processes in which is necessary to maintain the products level controlled which are handled for their transformation. The majority of such processes and by the operation conditions, they do not admit measure systems of level of invasive type then the application of nuclear techniques for level measurement results a big aid in these cases, since all the system installation is situated beyond frontiers of vessels that contain the product for measuring. In the Department of Nuclear Technology Applications of Mexican Petroleum Institute was developed a level measurement system by gamma rays transmission which operates in the Low Density Polyethylene plant of Petrochemical Complex Escolin at Poza Rica, Veracruz, Mexico. (Author)

  8. HASCAL -- A system for estimating contamination and doses from incidents at worldwide nuclear facilities

    International Nuclear Information System (INIS)

    Sjoreen, A.L.

    1995-01-01

    The Hazard Assessment System for Consequence Analysis (HASCAL) is being developed to support the analysis of radiological incidents anywhere in the world for the Defense Nuclear Agency (DNA). HASCAL is a component of the Hazard Prediction and Assessment Capability (HPAC), which is a comprehensive nuclear, biological, and chemical hazard effects planning and forecasting modeling system that is being developed by DNA. HASCAL computes best-guess estimates of the consequences of radiological incidents. HASCAL estimates the amount of radioactivity released, its atmospheric transport and deposition, and the resulting radiological doses

  9. Nuclear power plant annunciator systems

    International Nuclear Information System (INIS)

    Rankin, W.L.

    1983-08-01

    Analyses of nuclear power plant annunciator systems have uncovered a variety of problems. Many of these problems stem from the fact that the underlying philosophy of annunciator systems have never been elucidated so as to impact the initial annunciator system design. This research determined that the basic philosophy of an annunciator system should be to minimize the potential for system and process deviations to develop into significant hazards. In order to do this the annunciator system should alert the operators to the fact that a system or process deviation exists, inform the operators as to the priority and nature of the deviation, guide the operators' initial responses to the deviation, and confirm whether operators responses corrected the deviation. Annunciator design features were analyzed to determine to what degree they helped the system meet the functional criteria, the priority for implementing specific design features, and the cost and ease of implementing specific design features

  10. Establishment of a computerized occupational health system at the Paks Nuclear Power Plant

    International Nuclear Information System (INIS)

    Otos, M.

    1990-01-01

    An overall personnel health system has been under installation in the Paks Nuclear Power Plant Company, Hungary, for an automatic health monitoring and survey of the personnel exposed to radiation. The system will consist of nine modules when completed. The personnel fitness module is described in detail, and the periodical fitness examinations with computer control are presented. The examinations are using a personnel database system, and a statistical module is used to evaluate monitoring results. (R.P.)

  11. A fast, flexible and low cost real time data acquisition system for nuclear physics experiments

    International Nuclear Information System (INIS)

    Rassool, R.P.; O'Keefe, G.J.; Thompson, M.N.

    1991-01-01

    A system has been developed to permit fast, efficient data collection from a relatively complex nuclear experiment. Incorporated into this system is the communication framework for on-line analysis of the incoming data. The system makes extensive use of readily available low cost Intel based microprocessors. Results from recent measurements of the 16 O(γ,n) cross section made using tagged photons, performed at previously unachievable collection rates are presented. 6 refs., 6 figs

  12. A study on the establishment of national nuclear foreign policy with reference to nuclear export control system, strategy toward IAEA, and NPT review conferences

    International Nuclear Information System (INIS)

    Choi, Young Myung; Nam, Jang Soo; Lee, Han Myung

    1990-02-01

    The objectives of this study are follows: suggestion for i) our future nuclear development directions, ii) establishment of national export control system, iii) establishment of strategy toward IAEA, and suggestion of our standpoints toward the 4th NPT review conference. This study proposes the following; 1) It is desirable that nuclear power generation strategy is propelled under the premise of economics and proven technology. And international cooperation in connection with the nuclear fuel cycle should be reinforced. 2) It is recommened that nuclear export control system should be government-led. 3) Our country needs to make efforts in increasing the number of Korean staff in the IAEA, and to establish permanent mission which is wholly responsible for the IAEA affairs, and to construct a system which deals with nuclear foregin activities. 4) It is desirable that the basic position of our country toward the 4th NPT review conference should be : i) to urge parties to the NPT to conclude safeguards agreement with IAEA as early as possible, ii) to request nuclear suppliers to mitigate their nuclear technology for peaceful uses to nuclear developing countries, and iii) to urge nuclear weapon states to make further efforts for nuclear disarmament. (author)

  13. Increasing the effectiveness of the physical protection system on a nuclear facility

    International Nuclear Information System (INIS)

    Vaz, Antonio C.A.; Conti, Thadeu N.

    2017-01-01

    The malicious use of radioactive material could be devastating, particularly in the case of a nuclear explosive device, it could be unpredictably disruptive resulting in the dispersal of radioactive material, like it was in the Fukushima Daiichi Nuclear Power Plant disaster. Physical Protection System (PPS) plays an important role in ensuring that individuals, organizations and institutions remain vigilant and that sustained measures are taken to prevent and combat the threat of sabotage or of using radioactive material for malicious acts. PPS is an integrated system of people, equipment and procedures used to protect nuclear facilities and radioactive sources against threat, theft or sabotage. In the operator's perspective, this paper study factors influencing the performance of a PPS in a nuclear facility suggesting ways to increase the system effectiveness. The human factor, the physical and the psychological work environment has a large impact on how personnel perform their work and comply with nuclear security requirements. Apathy and corporatism are two human behaviors that collaborate negatively and make decrease the effectiveness of any PPS. Job satisfaction reduces the probability that personnel will become less reliable and/or obstructive in extreme cases an insider threat. Managers must recognize individual and group needs and the relationship among personnel so that they may motivate personnel by creating a supportive working environment that reduces workplace stress. An effective PPS can result in a significant increase in the effectiveness of the security of radioactive material and associated facilities. (author)

  14. Increasing the effectiveness of the physical protection system on a nuclear facility

    Energy Technology Data Exchange (ETDEWEB)

    Vaz, Antonio C.A.; Conti, Thadeu N., E-mail: acavaz@ipen.br, E-mail: tnconti@ipen.br [Instituto de Pesquisas Energéticas e Nucleares (IPEN/CNEN-SP), São Paulo, SP (Brazil)

    2017-07-01

    The malicious use of radioactive material could be devastating, particularly in the case of a nuclear explosive device, it could be unpredictably disruptive resulting in the dispersal of radioactive material, like it was in the Fukushima Daiichi Nuclear Power Plant disaster. Physical Protection System (PPS) plays an important role in ensuring that individuals, organizations and institutions remain vigilant and that sustained measures are taken to prevent and combat the threat of sabotage or of using radioactive material for malicious acts. PPS is an integrated system of people, equipment and procedures used to protect nuclear facilities and radioactive sources against threat, theft or sabotage. In the operator's perspective, this paper study factors influencing the performance of a PPS in a nuclear facility suggesting ways to increase the system effectiveness. The human factor, the physical and the psychological work environment has a large impact on how personnel perform their work and comply with nuclear security requirements. Apathy and corporatism are two human behaviors that collaborate negatively and make decrease the effectiveness of any PPS. Job satisfaction reduces the probability that personnel will become less reliable and/or obstructive in extreme cases an insider threat. Managers must recognize individual and group needs and the relationship among personnel so that they may motivate personnel by creating a supportive working environment that reduces workplace stress. An effective PPS can result in a significant increase in the effectiveness of the security of radioactive material and associated facilities. (author)

  15. Role of a national system of accounting and control of nuclear material under ABACC's (Brazilian-Argentine Agency) regional system

    International Nuclear Information System (INIS)

    Fernandez Moreno, Sonia; Estrada Oyuela, Miguel E.

    2000-01-01

    The Brazilian-Argentine Agency (ABACC) and the 'Common System of Accounting and Control of Nuclear Materials' (SCCC) are the result of a process started with nuclear cooperation between Argentina and Brazil. The SCCC reflects a common policy of transparency established by a Bilateral Agreement. Its insertion in the global context was made through a Quadripartite Agreement (Argentina, Brazil, ABBAC, IAEA). This paper describes the role of the State System of Accounting and Control (SSAC) in the framework established in the Bilateral and the Quadripartite Safeguards Agreements and in the context of new trends and perspectives in international safeguards. It could also serve as a example for initiatives in other regions. (author)

  16. A belief network approach for development of a nuclear power plant diagnosis system

    Energy Technology Data Exchange (ETDEWEB)

    Hwang, I K; Kim, J T; Lee, D Y; Jung, C H; Kim, J Y; Lee, J S; Ham, C S [Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)

    1999-12-31

    Belief network (or Bayesian network) based on Bayes` rule in probabilistic theory can be applied to the reasoning of diagnostic system. This paper describes the basic theory of concept and feasibility of using the network for diagnosis of nuclear power plants. An example shows that the probabilities of root causes of a failure are calculated from the measured or believed evidences. 6 refs., 3 figs. (Author)

  17. A belief network approach for development of a nuclear power plant diagnosis system

    Energy Technology Data Exchange (ETDEWEB)

    Hwang, I. K.; Kim, J. T.; Lee, D. Y.; Jung, C. H.; Kim, J. Y.; Lee, J. S.; Ham, C. S. [Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)

    1998-12-31

    Belief network (or Bayesian network) based on Bayes` rule in probabilistic theory can be applied to the reasoning of diagnostic system. This paper describes the basic theory of concept and feasibility of using the network for diagnosis of nuclear power plants. An example shows that the probabilities of root causes of a failure are calculated from the measured or believed evidences. 6 refs., 3 figs. (Author)

  18. A distributed process monitoring system for nuclear powered electrical generating facilities

    International Nuclear Information System (INIS)

    Sweney, A.D.

    1991-01-01

    Duke Power Company is one of the largest investor owned utilities in the United States, with a service area of 20,000 square miles extending across North and South Carolina. Oconee Nuclear Station, one of Duke Power's three nuclear generating facilities, is a three unit pressurized water reactor site and has, over the course of its 15-year operating lifetime, effectively run out of plant processing capability. From a severely overcrowded cable spread room to an aging overtaxed Operator Aid Computer, the problems with trying to add additional process variables to the present centralized Operator Aid Computer are almost insurmountable obstacles. This paper reports that for this reason, and to realize the inherent benefits of a distributed process monitoring and control system, Oconee has embarked on a project to demonstrate the ability of a distributed system to perform in the nuclear power plant environment

  19. European nuclear data studies for fast systems

    International Nuclear Information System (INIS)

    Rullhusen, P.; Hambsch, F.-J.; Mondelaers, W.; Plompen, A.J.M.; Schillebeeckx, P.

    2010-01-01

    Nuclear data needs for fast systems are highlighted and the following projects are described: Joint European research projects: MUSE Experiments for Sub-critical Neutronics Validation; High- and Intermediate Energy Nuclear Data for ADS (HINDAS); and the Time-Of-Flight facility for Nuclear Data Measurements for ADS (n T OF N D A DS); European Research Programme for the Transmutation of High Level Nuclear Waste in an Accelerator Driven System (EUROTRANS-NUDATRA); and CANDIDE; Programmes for transnational access to experimental facilities in Europe: European Facilities for Nuclear Data Measurements (EFNUDAT); Neutron Data Measurements at IRMM (NUDAME); European facility for innovative reactor and transmutation neutron data (EUFRAT) (P.A.)

  20. Project and construction of a measurement system and nuclear radiations analysis

    International Nuclear Information System (INIS)

    Castro, R. B. de.

    1983-01-01

    A counting system was designed and built, aiming to: detect and measure nuclear radiations using a Geiger-Mueller counter; and to measure the amplitudes of pulses from either a proportional or a NaI detector. The results obtained of the Cs-137 and Co-60 energy spectra were compared with results obtained from other researches. (Author) [pt

  1. A support vector machine integrated system for the classification of operation anomalies in nuclear components and systems

    International Nuclear Information System (INIS)

    Rocco S, Claudio M.; Zio, Enrico

    2007-01-01

    A support vector machine (SVM) approach to the classification of transients in nuclear power plants is presented. SVM is a machine-learning algorithm that has been successfully used in pattern recognition for cluster analysis. In the present work, single- and multiclass SVM are combined into a hierarchical structure for distinguishing among transients in nuclear systems on the basis of measured data. An example of application of the approach is presented with respect to the classification of anomalies and malfunctions occurring in the feedwater system of a boiling water reactor. The data used in the example are provided by the HAMBO simulator of the Halden Reactor Project

  2. 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)

  3. Nuclear data information system for nuclear materials

    International Nuclear Information System (INIS)

    Fujita, Mitsutane; Noda, Tetsuji; Utsumi, Misako

    1996-01-01

    The conceptual system for nuclear material design is considered and some trials on WWW server with functions of the easily accessible simulation of nuclear reactions are introduced. Moreover, as an example of the simulation on the system using nuclear data, transmutation calculation was made for candidate first wall materials such as 9Cr-2W steel, V-5Cr-5Ti and SiC in SUS316/Li 2 O/H 2 O(SUS), 9Cr-2W/Li 2 O/H 2 O(RAF), V alloy/Li/Be(V), and SiC/Li 2 ZrO 3 /He(SiC) blanket/shield systems based on ITER design model. Neutron spectrum varies with different blanket/shield compositions. The flux of low energy neutrons decreases in order of V< SiC< RAF< SUS blanket/shield systems. Fair amounts of W depletion in 9Cr-2W steel and the increase of Cr content in V-5Cr-5Ti were predicted in SUS or RAF systems. Concentration change in W and Cr is estimated to be suppressed if Li coolant is used in place of water. Helium and hydrogen production are not strongly affected by the different blanket/shield compositions. (author)

  4. A Study on Evaluation Issues of Real-Time Operating System in Nuclear Power Plants

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Y. M.; Jeong, C. H.; Koh, J. S. [Korea Institute of Nuclear Safety, Taejon (Korea, Republic of)

    2006-07-01

    Control applications such as aircraft, robotics and nuclear power plant have to maintain a very high level of safety, typically defined as the avoidance of unplanned events resulting in hazard. These applications usually operate with hard real-time operating system (RTOS). In this case, hard RTOS software should be reliable and safe. RTOS used in safety-critical I and C system is the base software for the purpose of satisfying the real-time constraints. So, careful evaluation of its safety and functionality is very important. In this paper, we present the case study for RTOSs used in real nuclear power plants (NPP), and suggest the evaluation approach for the RTOS.

  5. A Study on Evaluation Issues of Real-Time Operating System in Nuclear Power Plants

    International Nuclear Information System (INIS)

    Kim, Y. M.; Jeong, C. H.; Koh, J. S.

    2006-01-01

    Control applications such as aircraft, robotics and nuclear power plant have to maintain a very high level of safety, typically defined as the avoidance of unplanned events resulting in hazard. These applications usually operate with hard real-time operating system (RTOS). In this case, hard RTOS software should be reliable and safe. RTOS used in safety-critical I and C system is the base software for the purpose of satisfying the real-time constraints. So, careful evaluation of its safety and functionality is very important. In this paper, we present the case study for RTOSs used in real nuclear power plants (NPP), and suggest the evaluation approach for the RTOS

  6. Modeling Transients and Designing a Passive Safety System for a Nuclear Thermal Rocket Using Relap5

    Science.gov (United States)

    Khatry, Jivan

    Long-term high payload missions necessitate the need for nuclear space propulsion. Several nuclear reactor types were investigated by the Nuclear Engine for Rocket Vehicle Application (NERVA) program of National Aeronautics and Space Administration (NASA). Study of planned/unplanned transients on nuclear thermal rockets is important due to the need for long-term missions. A NERVA design known as the Pewee I was selected for this purpose. The following transients were run: (i) modeling of corrosion-induced blockages on the peripheral fuel element coolant channels and their impact on radiation heat transfer in the core, and (ii) modeling of loss-of-flow-accidents (LOFAs) and their impact on radiation heat transfer in the core. For part (i), the radiation heat transfer rate of blocked channels increases while their neighbors' decreases. For part (ii), the core radiation heat transfer rate increases while the flow rate through the rocket system is decreased. However, the radiation heat transfer decreased while there was a complete LOFA. In this situation, the peripheral fuel element coolant channels handle the majority of the radiation heat transfer. Recognizing the LOFA as the most severe design basis accident, a passive safety system was designed in order to respond to such a transient. This design utilizes the already existing tie rod tubes and connects them to a radiator in a closed loop. Hence, this is basically a secondary loop. The size of the core is unchanged. During normal steady-state operation, this secondary loop keeps the moderator cool. Results show that the safety system is able to remove the decay heat and prevent the fuel elements from melting, in response to a LOFA and subsequent SCRAM.

  7. Thermionic nuclear reactor systems

    International Nuclear Information System (INIS)

    Kennel, E.B.

    1986-01-01

    Thermionic nuclear reactors can be expected to be candidate space power supplies for power demands ranging from about ten kilowatts to several megawatts. The conventional ''ignited mode'' thermionic fuel element (TFE) is the basis for most reactor designs to date. Laboratory converters have been built and tested with efficiencies in the range of 7-12% for over 10,000 hours. Even longer lifetimes are projected. More advanced capabilities are potentially achievable in other modes of operation, such as the self-pulsed or unignited diode. Coupled with modest improvements in fuel and emitter material performance, the efficiency of an advanced thermionic conversion system can be extended to the 15-20% range. Advanced thermionic power systems are expected to be compatible with other advanced features such as: (1) Intrinsic subcritically under accident conditions, ensuring 100% safety upon launch abort; (2) Intrinsic low radiation levels during reactor shutdown, allowing manned servicing and/or rendezvous; (3) DC to DC power conditioning using lightweight power MOSFETS; and (4) AC output using pulsed converters

  8. Is there a need for hydrological modelling in decision support systems for nuclear emergencies

    International Nuclear Information System (INIS)

    Raskob, W.; Heling, R.; Zheleznyak, M.

    2004-01-01

    This paper discusses the role of hydrological modelling in decision support systems for nuclear emergencies. In particular, most recent developments such as, the radionuclide transport models integrated in to the decision support system RODOS will be explored. Recent progress in the implementation of physically-based distributed hydrological models for operational forecasting in national and supranational centres, may support a closer cooperation between national hydrological services and therefore, strengthen the use of hydrological and radiological models implemented in decision support systems. (authors)

  9. A study on improvement of export control system for the nuclear facility

    International Nuclear Information System (INIS)

    Kim, Ok Joo; Shin, Dong Hoon; Yang, Seung Hyo

    2012-01-01

    The Republic of Korea joined Nuclear Suppliers Group(NSG) in 1995 and became a major nuclear supplier both in name and reality by contracting the Project of UAE Braka Nuclear Power Plant(BNPP) in 2009 and the Project of Jordan Research and Training Reactor(JRTR) in 2010. And ROK is currently negotiating with several countries such as Finland and Vietnam for more projects, so it is expected to obtain more orders of commercial and research reactor. At this point of time, we found that it is difficult to apply individual export licensing system as it is for the big nuclear project such as BNPP and JRTR Project. Because the nuclear project in foreign country contains transfer of thousands of items and technical documents, including a considerable number of strategic items, issuing individual licenses for all items and documents can cause the inefficiency of the project. So, an appropriate export control system which can support such a project is necessary. In this study, we focused on how to improve the export control system to guarantee not only time efficiency but careful management of strategic goods

  10. A new advanced software platform for nuclear power plant process information systems

    International Nuclear Information System (INIS)

    Sorsa, A.

    1993-01-01

    In the late 80s, ABB Stromberg Power Ltd. started the development of a new generation software platform for the power plant Process Information System (PIS). This development resulted in a software platform called Procontrol PMS. Procontrol PMS is a platform for fully distributed systems which provides the following features: distributed data processing, non-stop architecture, low-cost incremental expansion path, open network architecture, high functionality, effective application development environment, and advanced user interface services. A description of the structure of the Procontrol PMS software is given. ABB has received by May 1992 six orders for nuclear power plant PISs based on Procontrol PMS (4 for PWR plants, 2 for BWRs). The first Procontrol PMS based nuclear power plant PIS was commissioned in 1989 at the Loviisa nuclear power plant and has been running with 100% availability since the commissioning. (Z.S.) 2 figs

  11. Development of web-based integrity evaluation system for primary components in a nuclear power plant

    International Nuclear Information System (INIS)

    Lee, S.M.; Kim, J.C.; Choi, J.B.; Kim, Y.J.; Choi, S.N.; Jang, K.S.; Hong, S.Y.

    2004-01-01

    A nuclear power plant is composed of a number of primary components. Maintaining the integrity of these components is one of the most critical issues in nuclear industry. In order to maintain the integrity of these primary components, a complicated procedure is required including periodical in-service inspection, failure assessment, fracture mechanics analysis, etc. Also, experts in different fields have to co-operate to resolve the integrity issues on the basis of inspection results. This integrity evaluation process usually takes long, and thus, is detrimental for the plant productivity. Therefore, an effective safety evaluation system is essential to manage integrity issues on a nuclear power plant. In this paper, a web-based integrity evaluation system for primary components in a nuclear power plant is proposed. The proposed system, which is named as WEBIES (web-based integrity evaluation system), has been developed in the form of 3-tier system architecture. The system consists of three servers; application program server, user interface program server and data warehouse server. The application program server includes the defect acceptance analysis module and the fracture mechanics analysis module which are programmed on the basis of ASME sec. XI, appendix A. The data warehouse server provides data for the integrity evaluation including material properties, geometry information, inspection data and stress data. The user interface program server provides information to all co- workers in the field of integrity evaluation. The developed system provides engineering knowledge-based information and concurrent and collaborative working environment through internet, and thus, is expected to raise the efficiency of integrity evaluation procedures on primary components of a nuclear power plant. (orig.)

  12. Development of web-based integrity evaluation system for primary components in a nuclear power plant

    Energy Technology Data Exchange (ETDEWEB)

    Lee, S.M.; Kim, J.C.; Choi, J.B.; Kim, Y.J. [SAFE Research Center, Sungkyunkwan Univ., Suwon (Korea); Choi, S.N.; Jang, K.S.; Hong, S.Y. [Korea Electronic Power Research Inst., Daejeon (Korea)

    2004-07-01

    A nuclear power plant is composed of a number of primary components. Maintaining the integrity of these components is one of the most critical issues in nuclear industry. In order to maintain the integrity of these primary components, a complicated procedure is required including periodical in-service inspection, failure assessment, fracture mechanics analysis, etc. Also, experts in different fields have to co-operate to resolve the integrity issues on the basis of inspection results. This integrity evaluation process usually takes long, and thus, is detrimental for the plant productivity. Therefore, an effective safety evaluation system is essential to manage integrity issues on a nuclear power plant. In this paper, a web-based integrity evaluation system for primary components in a nuclear power plant is proposed. The proposed system, which is named as WEBIES (web-based integrity evaluation system), has been developed in the form of 3-tier system architecture. The system consists of three servers; application program server, user interface program server and data warehouse server. The application program server includes the defect acceptance analysis module and the fracture mechanics analysis module which are programmed on the basis of ASME sec. XI, appendix A. The data warehouse server provides data for the integrity evaluation including material properties, geometry information, inspection data and stress data. The user interface program server provides information to all co- workers in the field of integrity evaluation. The developed system provides engineering knowledge-based information and concurrent and collaborative working environment through internet, and thus, is expected to raise the efficiency of integrity evaluation procedures on primary components of a nuclear power plant. (orig.)

  13. A dynamic failure evaluation of a simplified digital control system of a nuclear power plant pressurizer

    International Nuclear Information System (INIS)

    Pinto, J.M.O.; Melo, P.F. Frutuoso e; Saldanha, P.L.C.

    2010-01-01

    Given the increasing use of digital systems in nuclear power plants, a specific approach to reliability and risk analysis has been required. The digital system reflects many interactions between hardware, software, process variables, and human actions. At the same time, the software, does not have a reliability approach as well-defined as the one existing for the other physical components of the system. Then, its reliability analysis is still under development due to difficulties arising from the complexity, flexibility and interactions present in such systems.The traditional approach of using fault trees is static and does not approach the dynamic interactions in such systems, such as delays in capture and processing information, memory, logic loops, system states, etc. It is necessary to find a reliability methodology that takes into account these issues without violating the existing requirements concerning safety analysis, such as: ability to distinguish between common-cause failures, availability of relevant information to users, like minimal cut sets, and failure probabilities as long as the possibility of incorporating the results into existing probabilistic safety assessments (PSA).One approach is to trace all the possible errors of the digital system through dynamic methodologies. The DFM (Dynamic Flow-graph Methodology) is one of the methodologies that better meets the requirements for modeling dynamic systems. It discretizes the most relevant variables of the analyzed system in states that reflect their behavior, sets the logic that connects them through decision tables and finally performs a system analysis, aiming, for example, the root causes (prime implicants) of a given top event of failure. Three aspects have been addressed, the modeling of the system itself, the incorporation of results to probabilistic safety analyses and identification of software failures.To illustrate the DFM, a simplified digital control system of a typical PWR pressurizer

  14. Diagnostic systems in nuclear power plants. Proceedings of a technical committee meeting. Working material

    International Nuclear Information System (INIS)

    1998-01-01

    Nuclear power industry has a quite long tradition in on-line diagnostic of mechanical components and a considerable effort was put in developing diagnostic systems which are able to detect arising mechanical problems at an early stage. Computers are increasingly exploited to provide higher level information on process behaviour such as: early indication of the process deviation from normal conditions; rapid identification of the cause of any disturbance; prediction of the evolution of a disturbance; operator aid through computerized help. Following the recommendation of Several Member States to strengthen the activity in this field two divisions of IAEA established in 1995 the International Task Force on Nuclear Power Plant Diagnostics. The scope of the task force cover both technological developments and safety/licensing aspects of diagnostics. This report contains papers presented at the last in the series of Technical Committee Meetings on the Diagnostic Systems in Nuclear Power Plants organized in the framework of International Task Force

  15. Diagnostic systems in nuclear power plants. Proceedings of a technical committee meeting. Working material

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1999-12-31

    Nuclear power industry has a quite long tradition in on-line diagnostic of mechanical components and a considerable effort was put in developing diagnostic systems which are able to detect arising mechanical problems at an early stage. Computers are increasingly exploited to provide higher level information on process behaviour such as: early indication of the process deviation from normal conditions; rapid identification of the cause of any disturbance; prediction of the evolution of a disturbance; operator aid through computerized help. Following the recommendation of Several Member States to strengthen the activity in this field two divisions of IAEA established in 1995 the International Task Force on Nuclear Power Plant Diagnostics. The scope of the task force cover both technological developments and safety/licensing aspects of diagnostics. This report contains papers presented at the last in the series of Technical Committee Meetings on the Diagnostic Systems in Nuclear Power Plants organized in the framework of International Task Force Refs, figs, tabs

  16. A nuclear medicine information system that allows reporting and sending images through intranet

    International Nuclear Information System (INIS)

    Anselmi, C.E.; Anselmi, O.E.

    2002-01-01

    A nuclear medicine information system that allows reporting and sending images through intranet. Aim: This system was developed in order to improve the processes of typing, correcting, verifying and distribution of the reports and images, improving the efficiency of the personnel in the nuclear medicine department and reducing the time between the creation of the report and its reading by the referring physician. Materials and Methods: The system runs a web server (Personal Web Server, Microsoft) which serves web pages written in hypertext markup language (HTML) and active server pages (ASP). The database utilized is Microsoft Access 97. The whole communication between the web server and the database is performed by the programs written in ASP. Integrating the images from the patients is done through a 486 ibm-pc running Red Hat Linux, which serves as an intermediary between the isolated nuclear medicine network and the hospital's network. Results: The time from report verification and referring physician reading has decreased from approximately 24 hours to 12 hours. It is possible to run queries in the system in order to get productivity reports or clinical research. Imaging storage allows for correlation of current and previous studies. Conclusion: Bureaucratic processes have diminished to a certain extent in the department. Reports are now online as soon as they are verified by the nuclear medicine physician. There is no need to install dedicated software in the viewing stations since the whole system runs in the server

  17. Nuclear data evaluation method and evaluation system

    International Nuclear Information System (INIS)

    Liu Tingjin

    1995-01-01

    The evaluation methods and Nuclear Data Evaluation System have been developed in China. A new version of the system has been established on Micro-VAX2 computer, which is supported by IAEA under the technology assistance program. The flow chart of Chinese Nuclear Data Evaluation System is shown out. For last ten years, the main efforts have been put on the double differential cross section, covariance data and evaluated data library validation. The developed evaluation method and Chinese Nuclear Data Evaluation System have been widely used at CNDC and in Chinese Nuclear Data Network for CENDL. (1 tab., 15 figs.)

  18. National Options for a Sustainable Nuclear Energy System: MCDM Evaluation Using an Improved Integrated Weighting Approach

    Directory of Open Access Journals (Sweden)

    Ruxing Gao

    2017-12-01

    Full Text Available While the prospects look bright for nuclear energy development in China, no consensus about an optimum transitional path towards sustainability of the nuclear fuel cycle has been achieved. Herein, we present a preliminary study of decision making for China’s future nuclear energy systems, combined with a dynamic analysis model. In terms of sustainability assessment based on environmental, economic, and social considerations, we compared and ranked the four candidate options of nuclear fuel cycles combined with an integrated evaluation analysis using the Multi-Criteria Decision Making (MCDM method. An improved integrated weighting method was first applied in the nuclear fuel cycle evaluation study. This method synthesizes diverse subjective/objective weighting methods to evaluate conflicting criteria among the competing decision makers at different levels of expertise and experience. The results suggest that the fuel cycle option of direct recycling of spent fuel through fast reactors is the most competitive candidate, while the fuel cycle option of direct disposal of all spent fuel without recycling is the least attractive for China, from a sustainability perspective. In summary, this study provided a well-informed decision-making tool to support the development of national nuclear energy strategies.

  19. Outline of a future security system to provide physical protection of nuclear installations

    International Nuclear Information System (INIS)

    Rossnagel, A.

    1984-01-01

    Nuclear energy, within three or four decades, may become a main pillar of the world's energy supply. The author discusses the problems entailed by the necessity to protect nuclear facilities against assaults, and whether this can be ensured without interference with civic rights. The method applied by the author to show the significance of the problems is to explain the current situation, and to compare it with a plausible outline of the developments to be expected over the next 50 years. He shows the hazards to be taken into account due to criminal actions by persons from outside, or by persons working in nuclear facilities. A main problem is the fact that the security system to be set up has to encompass not only the nuclear installation itself, but also the surrounding area, and the measures to be taken will have an impact on the society, which necessarily will curtail personal freedom. The author presumes that the necessity to guarantee physical protection of nuclear facilities will lead to a modification of the meaning of basic rights, and states his anxiety that security for nuclear installations might affect our concept of freedom. (HSCH) [de

  20. Study of a nuclear energy supplied steelmaking system for near-term application

    International Nuclear Information System (INIS)

    Yan, Xing L.; Kasahara, Seiji; Tachibana, Yukio; Kunitomi, Kazuhiko

    2012-01-01

    Conventional steelmaking processes involve intensive fossil fuel consumption and CO 2 emission. The system resulting from this study ties a steelmaking plant to a nuclear plant. The latter supplies the former all energy and feedstock with the exception of iron ore. The actual design takes on a multi-disciplinary approach: The nuclear plant employs a proven next-generation technology of fission reactor with 950 °C outlet temperature to produce electricity and heat. The plant construction saving and high efficiency keep the cogeneration cost down. The steelmaking plant employs conventional furnaces but substitutes hydrogen and oxygen for hydrocarbons as reactant and fuel. Water decomposition through an experimentally-demonstrated thermochemical process manufactures the feedstock gases required. Through essential safety features, particular a fully-passive nuclear safety, the design achieves physical proximity and yet operational independence of the two plants to facilitate inter-plant energy transmission. Calculated energy and material balance of the integrated system yields slightly over 1000 t steel per 1 MWt yr nuclear thermal energy. The steel cost is estimated competitive. The CO 2 emission amounts to 1% of conventional processes. The sustainable performance, economical potential, robust safety, and use of verified technological bases attract near-term deployment of this nuclear steelmaking system. -- Highlights: ► A steelmaking concept is proposed based on multi-disciplinary approach. ► It ties advanced nuclear fission reactor and energy conversion to thermochemical manufacture and direct iron making. ► Technological strength of each area is exploited to integrate a final process. ► Heat and material balance of the process is made to predict performance and cost. ► The system rules out fossil fuel use and CO 2 emission, and is near-term deployable.

  1. BUTREN-RC an hybrid system for the recharges optimization of nuclear fuels in a BWR

    International Nuclear Information System (INIS)

    Ortiz S, J.J.; Castillo M, J.A.; Valle G, E. del

    2004-01-01

    The obtained results with the hybrid system BUTREN-RC are presented that obtains recharges of nuclear fuel for a BWR type reactor. The system has implemented the methods of optimization heuristic taboo search and neural networks. The optimization it carried out with the technique of taboo search, and the neural networks, previously trained, were used to predict the behavior of the recharges of fuel, in substitution of commercial codes of reactor simulation. The obtained recharges of nuclear fuel correspond to 5 different operation cycles of the Laguna Verde Nuclear Power plant, Veracruz in Mexico. The obtained results were compared with the designs of this cycles. The energy gain with the recharges of fuel proposals is of approximately 4.5% with respect to those of design. The time of compute consumed it was considerably smaller that when a commercial code for reactor simulation is used. (Author)

  2. Man/machine interface for a nuclear cask remote handling control station: system design requirements

    International Nuclear Information System (INIS)

    Clarke, M.M.; Kreifeldt, J.G.; Draper, J.V.

    1984-01-01

    Design requirements are presented for a control station of a proposed semi-automated facility for remote handling of nuclear waste casks. Functional and operational man/machine interface: controls, displays, software format, station architecture, and work environment. In addition, some input is given to the design of remote sensing systems in the cask handling areas. 18 references, 9 figures, 12 tables

  3. Remote multiplexing system application to a nuclear generating station--An update

    International Nuclear Information System (INIS)

    Mazzoni, O.S.; Cava, A.L.; Bijoor, G.D.; Wiitala, M.F.

    1979-01-01

    Washington Public Power Supply System's Nuclear Power Plant WNP-2 is a 1200 MW, boiling water reactor (BWR) nuclear generating facility now under construction at Hanford, Washington. An early study indicated that substantial savings in cost could be obtained by the substitution of the Remote Multiplexing System (RMS) for the control and signal wiring between the Control Building and the outside facilities, which required long cable runs. It is a high speed, data system providing time-sharing digital communication. The purpose of this paper is to give the details of the RMS used in the WNP-2 project. It discusses the qualification requirements for Class IE systems and includes the description of the tests on the system

  4. Establishment of nuclear data evaluation system (I)

    International Nuclear Information System (INIS)

    Chang, Jong Hwa; Lee, Chang Kun; Kim, Jeong Do; Kim, Young Sik; Kim, Young Jin; Kim, Hyung Guk; Kil, Chung Sup; Kim, Kang Suk

    1994-08-01

    Nuclear data is fundamental data for development of new type of nuclear, upgrade of nuclear fuel, treatment of radwaste, research on fusion reactor, radioisotope usage, and nuclear medical therapy. Nuclear data is produced with experiments. However rack of experimental data for thousands of nuclides and various reaction types makes it essential to do statistical evaluation and theoretical interpolation. This study is intended to join international cooperation after establishing domestic basis for nuclear data evaluation work. This project is the first year of five year plan to do followings: 1) Establishment of database system to collect experimental data, 2) Setup of computer assistance system for evaluation work, 3) Verification of established system by test evaluation of selected nuclide reaction. The system has a collection of mass data of nuclides, computer codes for test evaluation of total cross section of 0-16 and collection of EXFOR format data for 0-16. This system will be improved continuously on next years. (Author)

  5. A code guidance system for integrated nuclear data evaluation system on the basis of knowledge engineering technology

    International Nuclear Information System (INIS)

    Fukahori, Tokio; Nakagawa, Tsuneo

    1994-01-01

    The integrated nuclear data evaluation system (INDES) is being made in order to support the nuclear data evaluation work. A guidance system in INDES, 'Evaluation Tutor (ET)', is under development in order to support users in selecting the most suitable set of theoretical calculation codes by applying knowledge engineering technology and the experiences of evaluation work for JENDL-3. In this paper, the function of ET is introduced as well as the functions and databases of INDES. An example run of ET for 56 Fe in the 1-20 MeV neutron energy region is also explained. (author)

  6. Containments for consolidated nuclear steam systems

    International Nuclear Information System (INIS)

    Jabsen, F.S.

    1978-01-01

    A containment system for a consolidated nuclear steam system incorporating a nuclear core, steam generator and reactor coolant pumps within a single pressure vessel is described which is designed to provide radiation shielding and pressure suppression. Design details, including those for the dry well and wet well of the containment, are given. (UK)

  7. Modification of the Japanese first nuclear ship reactor for a regional energy supply system

    International Nuclear Information System (INIS)

    Sato, K.; Shimazu, Y.; Narabayashi, T.; Tsuji, M.

    2008-01-01

    Nuclear Ship Mutsu was developed as the first experimental nuclear ship of Japan. It has several advantages as a prototype for regional energy supply system. Considering the attractive advantages of the Mutsu reactor, we investigated the feasibility of development of a small regional energy system by adopting the Mutsu reactor as a starting model. The system could supply with not only electricity but also heat. Heat could be used for hot-water supply, a heating system of a house, melting snow and so on, especially for those in northern part of Japan. The system should satisfy the requirements for GEN IV systems and the current regulations. From this point of view, the modification of the reactor was initiated by taking into improvements and technology of the state of arts to fulfill the requirements such as (1) Longer core life without refueling, (2) Reactivity adjustment for load change without control rods or soluble boron, (3) Simpler operations for load changes and (4) Ultimate safety with sufficient passive capability. Currently it is assumed to use basic standard 17x17 fuel assembly design for WH type PWRs. Nuclear design calculations are carried out by 'SRAC 2002 ', which has been developed in Japan Atomic Energy Agency. Several problems have not been solved yet, but we confirmed the proposed core has about 10 years life time. So the proposed core has a possibility to be used for a small regional energy system. (authors)

  8. Electrical and electronic subsystems of a nuclear waste tank annulus inspection system

    International Nuclear Information System (INIS)

    Evenson, R.J.

    1981-06-01

    The nuclear waste tank annulus inspection system is designed specifically for use at the Nuclear Regulatory Commission's Nuclear Fuel Services Facility at West Valley, New York. This system sends a television and photographic camera into the space between the walls of a double-shell nuclear waste tank to obtain images of the inner and outer walls at precisely known locations. The system is capable of inspecting a wall section 14 ft wide by 27 ft high. Due to the high temperature and radiation of the annulus environment, the operating life for the inspection device is uncertain, but is expected to be at least 100 h, with 1000 R/h at 82 0 C. The film camera is shielded with 1/2 in. of lead to minimize radiation fogging of the film during a 25-min picture taking excursion. The operation of the inspection system is semiautomated with remote manual prepositioning of the camera, followed by a computer controlled wall scan. This apparatus is currently set up to take an array of contiguous pictures, but is adaptable to other modes of operation

  9. A radiation monitoring system model for the Laguna Verde nuclear power training simulator

    International Nuclear Information System (INIS)

    Ocampo, M.H.; DeAlbornoz, B.A.

    1988-01-01

    A model for the Radiation Monitoring System of the Laguna Verde Boiling Water Reactor training simulator is presented. This model comprises enough definitions to assure interactions with the processes related, directly or indirectly, with the transport of radioisotopes. It is capable of following a dynamic behavior of the plant so an operator could be trained to become aware of nuclear radiation hazards. The model is composed of three parts: the electronics for the Process and Area Radiation Monitoring System; a lumped parameter transport model for the most representative radioisotopes; and the interactions with the modeled processes as well as with process not being simulated. The first part represents the radiation monitor controls in the vertical board panels of the nuclear station. The second part allows the carrying of nuclear isotopes between processes. The third part defines the way that the process interacts with the electronics at the point of release to environment or the point of detection. Each part of the model has been tested individually, and the transport model has been incorporated as a part of each process required to simulate nuclear radiation. The model parameters has been calculated using typical BWR nuclear radiation data, and Laguna Verde heat balance data at 100% design power. However, tunning will be necessary once the Simulator is integrated and tested. The tunning allows each detecting channel to behave as expected

  10. A novel feedwater system for the RETRAN model of the Palo Verde nuclear generating station

    International Nuclear Information System (INIS)

    Secker, P.A.; Webb, J.R.

    1988-01-01

    This paper presents a feedwater system model which supplies realistic boundary conditions to the RETRAN model of a Palo Verde Nuclear Generating Station reactor plant. The RETRAN thermal hydraulic code is used to analyze nuclear reactor system transients through a generalized thermal hydraulic volume/junction network. The feedwater system model is implemented using the control block modeling option available in the RETRAN code. The output of the control block model is coupled to the thermal hydraulic network by a fill junction. A forward Euler integration scheme is used by RETRAN for control block variables. The feedwater system model is formulated to allow implicit integration within the existing code framework. The potential need for small integration time steps is, therefore, alleviated. The model results are compared with test data

  11. A simulation-based expert system for nuclear power plant diagnostics

    International Nuclear Information System (INIS)

    Hassberger, J.A.; Lee, J.C.

    1989-01-01

    An expert system for diagnosing operational transients in a nuclear power plant is discussed. Hypothesis and test is used as the problem-solving strategy with hypotheses generated by an expert system that monitors the plant for patterns of data symptomatic of known failure modes. Fuzzy logic is employed as the inferencing mechanism with two complementary implication schemes to handle scenarios involving competing failures. Hypothesis testing is performed. An artificial intelligence framework based on a critical functions approach is used to deal with the complexity of a nuclear plant. A prototype system for diagnosing transients in the reactor coolant system of a pressurized water reactor has been developed to test the algorithms described here. Results are presented for the diagnosis of data from the Three Mile Island Unit 2 loss-of-feedwater/small-break loss-of-collant accident

  12. Experiences from maintaining the reliability of a nuclear standby diesel generator system

    International Nuclear Information System (INIS)

    Tammi, P.

    1982-01-01

    The nuclear standby diesel generator system is quite complicated comprising several mechanical and electrotechnical components, on which the reliability of the system is depending. It is an important support system of the plant safety system, and like the safety system it is composed of separate redundant units. The Loviisa nuclear power station has eight diesel generators. The first four of them were taken into operation in 1976. When the frequency of some mechanical failures showed increase, a project was started at the end of 1980 with the intention to find out potential failure possibilities and means for prevention of failures. The work has been mainly concentrated on improving the reliability of the diesel engines. (Auth.)

  13. Failure modes and effects analysis as a design tool for nuclear safety systems

    International Nuclear Information System (INIS)

    Tashjian, B.M.

    1975-01-01

    The activities of nuclear power plant designers are monitored by government and industry to an unprecedented degree. This involves not only rigid design and quality assurance criteria, but extensive documentation and reporting. The failure modes and effects analysis (FMEA) is a technique for checking designs and assuring quality. Included in the FMEA is a system of documentation. A simplified example of the reactor protective system (RPS) is used to illustrate the method. (U.S.)

  14. Nuclear power plant transient identification using a neuro-fuzzy inference system

    International Nuclear Information System (INIS)

    Mol, Antonio Carlos de Abreu; Oliveira, Mauro Vitor de; Santos, Isaac Jose Antonio Luchetti dos; Carvalho, Paulo Victor Rodrigues de; Grecco, Claudio Henrique dos Santos; Auguto, Silas Cordeiro

    2005-01-01

    Transient identification in Nuclear Power Plant (NPP) is often a very hard task and may involve a great amount of human cognition. The early identification of unexpected departures from steady state behavior is an essential step for the operation, control and accident management in nuclear power plants. The basis for the identification of a change in the system is that different system faults and anomalies lead to different patterns of evolution of the involved process variables. During an abnormal event, the operator must monitor a great amount of information from the instruments, that represents a specific type of event. In this work, an approach for the identification of transients is presented, aiming at helping the operator to make a decision relative to the procedure to be followed in situations of accidents/transients at nuclear power plants. In this way, a diagnostic strategy based on hierarchical use artificial neural networks (ANN) for a first level transient diagnose. After the ANN has done a preliminary transient type identification, a fuzzy-logic system analyzes the results emitting reliability degree of it. In order to validate the method, a Nuclear Power Plant transient identification problem, comprising postulated accidents, is proposed. Noisy data was used to evaluate the method robustness. The results obtained reveal the ability of the method in dealing with dynamic identification of transients and its reliability degree. (author)

  15. Demonstration of an automated on-line surveillance system at a commercial nuclear power plant

    International Nuclear Information System (INIS)

    Smith, C.M.; Sweeney, F.J.

    1983-01-01

    As a first step in demonstrating the practicality of performing continuous on-line surveillance of the performance of nuclear steam supply systems using noise related techniques, Oak Ridge National Laboratory is operating a computerized noise signal data acquisition and processing system at the Sequoyah Unit 1 Nuclear Plant, an 1148 MWe four-loop Westinghouse pressurized water reactor (PWR) located near Chattanooga, Tennessee. The principal objective is to establish, with a degree of continuity and completeness not previously achieved, the long-term characteristics of signals from neutron detectors and process sensors in order to evaluate the feasibility of detecting and diagnosing anomalous reactor conditions by means of changes in these signals. The system is designed to automatically screen the gathered data, using a number of descriptors derived from the power spectra of the monitored signals, and thereby select for the noise analyst's perusal only those data which differ statistically from norms which the system has previously established

  16. A coupled nuclear reactor thermal energy storage system for enhanced load following operation

    International Nuclear Information System (INIS)

    Alameri, Saeed A.; King, Jeffrey C.

    2013-01-01

    Nuclear power plants operate most economically at a constant power level, providing base load electric power. In an energy grid containing a high fraction of renewable power sources, nuclear reactors may be subject to significantly variable power demands. These variable power demands can negatively impact the effective capacity factor of the reactor and result in severe economic penalties. Coupling a nuclear reactor to a large thermal energy storage block will allow the reactor to better respond to variable power demands. In the system described in this paper, a Prismatic core Advanced High Temperature Reactor supplies constant power to a lithium chloride molten salt thermal energy storage block that provides thermal power as needed to a closed Brayton cycle energy conversion system. During normal operation, the thermal energy storage block stores thermal energy during the night for use in the times of peak demand during the day. In this case, the nuclear reactor stays at a constant thermal power level. After a loss of forced circulation, the reactor reaches a shut down state in less than half an hour and the average fuel, graphite and coolant temperatures remain well within the design limits over the duration of the transient, demonstrating the inherent safety of the coupled system. (author)

  17. Nuclear energy in Canada: the CANDU system

    International Nuclear Information System (INIS)

    Robertson, J.A.L.

    1979-10-01

    Nuclear electricity in Canada is generated by CANDU nuclear power stations. The CANDU reactor - a unique Canadian design - is fuelled by natural uranium and moderated by heavy water. The system has consistently outperformed other comparable nuclear power systems in the western world, and has an outstanding record of reliability, safety and economy. As a source of energy it provides the opportunity for decreasing our dependence on dwindling supplies of conventional fossil fuels. (auth)

  18. System model for evaluation of an emergency response plan for a nuclear power plant based on an assessment of nuclear emergency exercises

    International Nuclear Information System (INIS)

    Silva, Marcos Vinicius C.; Medeiros, Jose A.C.C.

    2011-01-01

    Nuclear power plants are designed and built with systems dedicated to provide a high degree of protection to its workers, the population living in their neighborhoods and the environment. Among the requirements for ensuring safety there are the existence of the nuclear emergency plan. Due to the relationship between the actions contemplated in the emergency plan and the nuclear emergency exercise, it becomes possible to assess the quality of the nuclear emergency plan, by means of emergency exercise evaluation, The techniques used in this work aim at improving the evaluation method of a nuclear emergency exercise through the use of performance indicators in the evaluation of the structures, actions and procedures involved. The proposed model enables comparisons between different moments of an emergency plan directed to a nuclear power plant as well as comparisons between plans dedicated to different facilities. (author)

  19. System model for evaluation of an emergency response plan for a nuclear power plant based on an assessment of nuclear emergency exercises

    Energy Technology Data Exchange (ETDEWEB)

    Silva, Marcos Vinicius C.; Medeiros, Jose A.C.C. [Universidade Federal do Rio de Janeiro (PEN/COPPE/UFRJ), RJ (Brazil). Coordenacao dos Programas de Pos-Graduacao de Engenharia. Programa de Engenharia Nuclear

    2011-07-01

    Nuclear power plants are designed and built with systems dedicated to provide a high degree of protection to its workers, the population living in their neighborhoods and the environment. Among the requirements for ensuring safety there are the existence of the nuclear emergency plan. Due to the relationship between the actions contemplated in the emergency plan and the nuclear emergency exercise, it becomes possible to assess the quality of the nuclear emergency plan, by means of emergency exercise evaluation, The techniques used in this work aim at improving the evaluation method of a nuclear emergency exercise through the use of performance indicators in the evaluation of the structures, actions and procedures involved. The proposed model enables comparisons between different moments of an emergency plan directed to a nuclear power plant as well as comparisons between plans dedicated to different facilities. (author)

  20. Monitoring the radioactivity in the secondary systems of a nuclear power plant

    International Nuclear Information System (INIS)

    Labno, L.

    1979-01-01

    The direct water/steam circuit and the waste water and exhaust air systems of a nuclear power plant with boiling water reactor are slightly contaminated with radioactive nuclides during normal operation. In addition some auxiliary and subsidiary systems may show evidence of radioactivity as a result of leakages between the systems. These radioactive substances and those which are discharged to the environment in exhaust air or waste water - although present in quantities far below the admissible limits - still require supervision by a comprehensive activity monitoring system. The article sets out the concept and the technical solution adopted for the activity monitoring system for the secondary section of a nuclear power station. The system is so designed that it provides the information and performs the safety functions important for highly reliable plant operation. Particular importance has been attached to the reliability and dependability of the system, so that incorrect interpretations or reports, such as have been experienced, for example, in the nuclear power plants 'Brunsbuettel' (Federal Republic of Germany) and 'Three Mile Island', near Harrisburg (USA), will not be repeated. (Auth.)

  1. A study of PLC system vulnerability checklists in nuclear power plants

    International Nuclear Information System (INIS)

    Cha, Ki Jong; Cho, Gi Ho; Ahn, Jaeh Young; Kim, Young Mi; Kwon, Yong Il

    2012-01-01

    Because the design of the PLCs (Programmable Logic Controller) in the I and C (Instrument and Control) systems for NPP (Nuclear Power Plant) were carried out independently, the problems of cyber security were not addressed in the PLC system designs. Recently, the analysis and the countermeasure development for the PLC systems became mandatory due to the developments in cyber attack techniques and the increasingly revealed vulnerability to such attacks. A comparative analysis on the cyber security checklist of PLC in industry control system and in NPP systems was carried out, and in this paper, the cyber security regulatory trend and the PLC usage status are described

  2. A study of PLC system vulnerability checklists in nuclear power plants

    Energy Technology Data Exchange (ETDEWEB)

    Cha, Ki Jong; Cho, Gi Ho; Ahn, Jaeh Young [Convergence technology Research Commercialization Center, Daejeon (Korea, Republic of); Kim, Young Mi; Kwon, Yong Il [Korea Institute of Nuclear Safety, Daejeon (Korea, Republic of)

    2012-10-15

    Because the design of the PLCs (Programmable Logic Controller) in the I and C (Instrument and Control) systems for NPP (Nuclear Power Plant) were carried out independently, the problems of cyber security were not addressed in the PLC system designs. Recently, the analysis and the countermeasure development for the PLC systems became mandatory due to the developments in cyber attack techniques and the increasingly revealed vulnerability to such attacks. A comparative analysis on the cyber security checklist of PLC in industry control system and in NPP systems was carried out, and in this paper, the cyber security regulatory trend and the PLC usage status are described.

  3. A framework for selecting suitable control technologies for nuclear power plant systems

    International Nuclear Information System (INIS)

    Kisner, R.A.

    1992-01-01

    New concepts continue to emerge for controlling systems, subsystems, and components and for monitoring parameters, characteristics, and vital signs in nuclear power plants. The steady stream of new control theories and the evolving state of control software exacerbates the difficulty of selecting the most appropriate control technology for nuclear power plant systems. As plant control room operators increase their reliance on computerized systems, the integration of monitoring, diagnostic, and control functions into a uniform and understandable environment becomes imperative. A systematic framework for comparing and evaluating the overall usefulness of control techniques is needed. This paper describes nine factors that may be used to evaluate alternative control concepts. These factors relate to a control system's potential effectiveness within the context of the overall environment, including both human and machine components. Although not an in-depth study, this paper serves to outline an evaluation framework based on several measures of utility. 32 refs

  4. DAPHNE: a parallel multiprocessor data acquisition system for nuclear physics

    International Nuclear Information System (INIS)

    Welch, L.C.

    1984-01-01

    This paper describes a project to meet these data acquisition needs for a new accelerator, ATLAS, being built at Argonne National Laboratory. ATLAS is a heavy-ion linear superconducting accelerator providing beam energies up to 25 MeV/A with a relative spread in beam energy as good as .0001 and a time spread of less than 100 psec. Details about the hardware front end, command language, data structure, and the flow of event treatment are covered

  5. Generation of a command language for nuclear signal and image processing on the basis of a general interactive system

    International Nuclear Information System (INIS)

    Pretschner, D.P.; Pfeiffer, G.; Deutsches Elektronen-Sychnchrotron

    1981-01-01

    In the field of nuclear medicine, BASIC and FORTRAN are currently being favoured as higher-level programming languages for computer-aided signal processing, and most operating systems of so-called ''freely programmable analyzers'' in nuclear wards have compilers for this purpose. However, FORTRAN is not an interactive language and thus not suited for conversational computing as a man-machine interface. BASIC, on the other hand, although a useful starting language for beginners, is not sufficiently sophisticated for complex nuclear medicine problems involving detailed calculations. Integration of new methods of signal acquisition, processing and presentation into an existing system or generation of new systems is difficult in FORTRAN, BASIC or ASSEMBLER and can only be done by system specialists, not by nuclear physicians. This problem may be solved by suitable interactive systems that are easy to learn, flexible, transparent and user-friendly. An interactive system of this type, XDS, was developed in the course of a project on evaluation of radiological image sequences. An XDS-generated command processing system for signal and image processing in nuclear medicine is described. The system is characterized by interactive program development and execution, problem-relevant data types, a flexible procedure concept and an integrated system implementation language for modern image processing algorithms. The advantages of the interactive system are illustrated by an example of diagnosis by nuclear methods. (orig.) [de

  6. A multiprocessor system for the analysis of pictures of nuclear events

    CERN Document Server

    Bacilieri, P; Matteuzzi, P; Sini, G P; Zanotti, U

    1979-01-01

    The pictures of nuclear events obtained from the bubble chambers such as Gargamelle and BEBC at CERN and others from Serpukhov are geometrically processed at CNAF (Centro Nazionale Analysis Photogrammi) in Bologna. The analysis system includes an Erasme table and a CRT flying spot digitizer. The difficulties connected with the pictures of the four stereoscopic views of the bubble chambers are overcome by the choice of a strong interactive system. (0 refs).

  7. Integration of a nuclear power plant in electrical systems, alternative programs, optimization

    International Nuclear Information System (INIS)

    Souza, J.A.M. de.

    1991-01-01

    The problem of integration of a nuclear power plants in a electrical power system, to support the power demand of the system, and mainly also support the power demand at the critical period, I.E., peak demands, is analysed. The factors considered in this analysis are: the demand structure of the region, the availability of others power plants in the electrical net and the capacity factor. (author)

  8. A Production-Rule Analysis System for Nuclear Plant monitoring and emergency response applications

    International Nuclear Information System (INIS)

    Ragheb, M.; Tsoukalas, L.; McDonough, T.; Parker, M.

    1987-01-01

    A Production-Rule Analysis System for Nuclear Power Plant Monitoring is presented. The signals generated by the Zion-1 Plant are considered for emergency Response applications. The integrity of the Plant Radiation, the Reactor Coolant, the Fuel Clad, and the Containment Systems, is monitored. Representation of the system is in the form of a goal-tree generating a Knowledge-Base searched by an Inference Engine functioning in the forward-chaining mode. The Gaol-tree is built from Fault-Trees based on plant operational information. The system is implemented on a VAX-8500 and is programmed in OPS-5

  9. A role for distributed processing in advanced nuclear materials control and accountability systems

    International Nuclear Information System (INIS)

    Tisinger, R.M.; Whitty, W.J.; Ford, W.; Strittmatter, R.B.

    1986-01-01

    Networking and distributed processing hardware and software have the potential of greatly enhancing nuclear materials control and account-ability (MCandA) systems, both from safeguards and process operations perspectives while allowing timely integrated safeguards activities and enhanced computer security at reasonable cost. A hierarchical distributed system is proposed consisting of groups of terminals and instruments in plant production and support areas connected to microprocessors that are connected to either larger microprocessors or minicomputers. The structuring and development of a limited distributed MCandA prototype system, including human engineering concepts, are described. Implications of integrated safeguards and computer security concepts to the distributed system design are discussed

  10. Hadron properties in nuclear matter and the phase structure of a skyrmionic system

    International Nuclear Information System (INIS)

    Yakhshiev, Ulugbek; Kim, Hyun-Chul

    2010-01-01

    Hadron properties and their interactions in a nuclear environment are considered in the framework of the in-medium modified Skyrme model. Furthermore, the influence of the medium modifications of the single hadron properties and their interactions to the stability of the whole system is considered by using the variational method of the Hartree-Fock type. In addition to previous studies, we discuss the possible in-medium modifications of the stabilizing Skyrme term which can be related to the modifications of vector meson properties in a nuclear environment. (author)

  11. A stability identification system for boiling water nuclear reactors

    International Nuclear Information System (INIS)

    Belblidia, L.A.; Chevrier, A.

    1994-01-01

    Boiling water reactors are subject to instabilities under low-flow, high-power operating conditions. These instabilities are a safety concern and it is therefore important to determine stability margins. This paper describes a method to estimate a measure of stability margin, called the decay ratio, from autoregressive modelling of time series data. A phenomenological model of a boiling water reactor with known stability characteristics is used to generate time series to validate the program. The program is then applied to signals from local power range monitors from the cycle 7 stability tests at the Leibstadt plant. (author) 7 figs., 2 tabs., 12 refs

  12. Nuclear maintenance and management system

    International Nuclear Information System (INIS)

    Yamaji, Yoshihiro; Abe, Norihiko

    2000-01-01

    The Mitsubishi Electric Co., Ltd. has developed to introduce various computer systems for desk-top business assistance in a power plant such as system isolation assisting system, operation parameter management system, and so on under aiming at business effectiveness since these ten and some years. Recently, by further elapsed years of the plants when required for further cost reduction and together with change of business environment represented by preparation of individual personal computer, further effectiveness, preparation of the business environment, and upgrading of maintenance in power plant business have been required. Among such background, she has carried out various proposals and developments on construction of a maintenance and management system integrated the business assistant know-hows and the plant know-hows both accumulated previously. They are composed of three main points on rationalization of business management and document management in the further effectiveness, preparation of business environment, TBM maintenance, introduction of CBM maintenance and introduction of maintenance assistance in upgrading of maintenance. Here was introduced on system concepts aiming at the further effectiveness of the nuclear power plant business, preparation of business environment, upgrading of maintenance and maintenance, and so on, at a background of environment around maintenance business in the nuclear power plants (cost-down, highly elapsed year of the plant, change of business environment). (G.K)

  13. 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

  14. Modeling of a planning system in radiotherapy and Nuclear Medicine using the MCNP6 code

    International Nuclear Information System (INIS)

    Massicano, Felipe

    2015-01-01

    Cancer therapy has many branches and one of them is the use of radiation sources as treatment leading method. Radiotherapy and nuclear medicine are examples of these treatment types. For using the ionization radiation as main tool for the therapy, there is the need of crafting many treatment simulation in order to maximum the tumoral tissue dose without surpass the dose limit in health tissue surrounding. Treatment planning systems (TPS) are systems which have the purpose of simulating these therapy types. Nuclear medicine and radiotherapy have many distinct features linked to the therapy mode and consequently they have different TPS destined for each. The radiotherapy TPS is more developed than the nuclear medicine TPS and by that reason the development of a TPS that was similar to the radiotherapy TPS, but enough generic for include other therapy types, it will contribute with significant advances in nuclear medicine and in others therapy types with radiation. Based on this, the goal of work was to model a TPS that utilizes the Monte Carlo N-Particle Transport code (MCNP6) in order to simulate radiotherapy therapy, nuclear medicine therapy and with potential for simulating other therapy types too. The result of this work was the creation of a Framework in Java language, object oriented, named IBMC which will assist in the development of new TPS with MCNP6 code. The IBMC allowed to develop rapidly and easily TPS for radiotherapy and nuclear medicine and the results were validated with systems already consolidated. The IBMC showed high potential for developing TPS by new therapy types. (author)

  15. Enhanced defence in depth: a fundamental approach for innovative nuclear systems recommended by INPRO

    International Nuclear Information System (INIS)

    Kuczera, B.; Juhn, P.E.

    2004-01-01

    In May 2001, the IAEA initiated the 'International Project on Innovative Nuclear Reactors and Fuel Cycles (INPRO)'. Having in mind that nuclear power will be an important option for meeting future electricity needs, the scope of INPRO covers nuclear reactors expected to come into service in the next fifty years, together with their associated fuel cycles. This article deals with enhanced defence in depth (DID) strategy that is recommended by INPRO. This strategy is twofold: first, to prevent accidents and second, if prevention fails, to limit their potential consequences and prevent any evolution to more serious conditions. Accident prevention is the first priority. For innovative nuclear systems, the effectiveness of preventive measures should be enhanced compared with existing systems. DID is generally structured in 5 levels of protection, including successive barriers preventing the release of radioactive material to the environment. These levels are: 1) prevention of abnormal operation and failures, 2) control of abnormal operation and detection of failures, 3) control of accidents within the design basis, 4) control of severe plant conditions, including prevention and mitigation of the consequences of severe accidents, and 5) mitigation of radiological consequences of significant release of radioactive materials. In the area of nuclear safety, INPRO has set 5 principles: 1) incorporate DID as a part of the safety approach and make the 5 levels of DID more independent from each other than in current installations; 2) prevent, reduce or contain releases of radioactive or hazardous materials in any normal or abnormal plant operation; 3) incorporate increased emphasis on inherent safety characteristics and passive safety features; 4) include research and development work to bring the capability of computer codes used for the safety of innovative nuclear systems to the standard of codes used for the safety of current reactors; and 5) include a holistic life

  16. A systemic approach to the discussion of sustainability of nuclear energy

    International Nuclear Information System (INIS)

    Aegerter, Irene

    2001-01-01

    In 1998 the four Swiss Scientific Academies formed a working group to study sustainability of electricity production. Having been a member of this group since the beginning I witnessed the evolution of the discussion that led to a consensus. The group found the criteria of sustainability to be special for nuclear energy. While the resource uranium is not needed for any other purpose and thus the use of uranium is sustainable, the possible harm to future generations by nuclear reactors is difficult to evaluate: the potential damage can be large but the probability of its occurrence is very small. Therefore some people judge nuclear power as an environmentally friendly source of electricity production and an important contribution towards a sustainable energy future whereas others look at the potential damage and value nuclear power as not sustainable. The discussion of alternatives then reveals that it is definitely not sustainable to replace nuclear power by fossil fuels. This was a consensus reached by the members of the working group, which consists of the pro and anti nuclear camp. Sustainable energy production is a complex topic and not easy to tackle with our everyday methods. The group decided to solve the problem with a systemic approach to get to know the hidden and indirect effects of electricity production and usage. A system approach brings a new concept into the often blocked discussion of proponents and antinuclear people. In order to assure that a holistic evaluation results which reaches a high degree of consensus, several subgroups were formed representing divergent views on the issues analysed. These groups do not communicate their findings while work on their cross impact matrices (CIMs) is under way. The results are compared and discrepancies are discussed. Usually this shows that once the wording of the variables is corrected and their interpretations are shared by the parties involved, consensus concerning evaluations is achieved

  17. An approach to the successful design of a minicomputer system for nuclear materials management

    International Nuclear Information System (INIS)

    Paul, R.N.; Anderson, L.L.

    1978-08-01

    A development laboratory to study nuclear fuel fabrication techniques is in operation at the Chalk River Nuclear Laboratories (CRNL). To assist operators in the management of nuclear materials in this laboratory, a minicomputer system (INMACS) has been designed and installed. INMACS is implemented on a PDP-11 with a RSTS/E operating system. A data base management package with on-line backup capability has been developed for this application. Fifteen man-years of effort have been spent on designing and building the system. This paper will discuss the philosophy and the design approach followed for the implementation of INMACS. Clear problem definition and careful system design, effective liaison with the users, detailed program specifications, proper co-ordination of the software development effort, and thorough testing of the integrated system, have all contributed to the achievement of the design goals. INMACS has been readily accepted by the users who were previously not conversant with computers. After eight months of operation, no program changes have been necessary and the system has been performing successfully as specified. (author)

  18. A knowledge based operator support system for emergency conditions in nuclear power plants

    International Nuclear Information System (INIS)

    Venkatesh Babu, C.; Subramanium, K.

    1992-01-01

    The control centres of the operating Indian nuclear power plants contain a large number of indicators and controls spread over many panels. In the event of onset of an emergency condition, there results a profusion of information, both numeric and symbolic. The operator may succumb to an information and cognitive overload that may be compounded by a lack of knowledge. The failure to apply knowledge and reasoning to solve an operational problem can lead to human error, which has been a major contributing factor in nuclear accidents. From the viewpoint of Artificial Intelligence, human error occurs if the operational problem requires computing resources that exceed human capabilities. The application of Artificial Intelligence, particularly expert systems, to nuclear power plant control room activities has considerable potential to reduce operator error and improve safety and reliability. The purpose of this paper is to discuss an investigative study of the feasibility of developing an operator support system incorporating Artificial Intelligence techniques. An information processing model of such a system, herein designated as Knowledge Based Operator Support System - KBOSS, employing expert systems technology, has been developed. The features of this system are described, and issues involved in its development are discussed. (author). 2 refs., 5 figs., 1 tab

  19. Process information displays from a computerized nuclear materials control and accounting system

    International Nuclear Information System (INIS)

    Ellis, J.H.

    1981-11-01

    A computerized nuclear materials control and accounting system is being developed for an LWR spent fuel reprocessing facility. This system directly accesses process instrument readings, sample analyses, and outputs of various on-line analytical instruments. In this paper, methods of processing and displaying this information in ways that aid in the efficient, timely, and safe control of the chemical processes of the facility are described

  20. Decisioneering in Nuclear Energy Systems : A Real Option View

    NARCIS (Netherlands)

    Lauferts, U.

    2012-01-01

    Financial- and Energy markets have one predominant characteristic in common: A large degree of uncertainty that drives the value of an investment in them. The thesis criticises the poor decision making support for investments into new generation capacity on base of pure cost comparison and NPV

  1. A model selection support system for numerical simulations of nuclear thermal-hydraulics

    International Nuclear Information System (INIS)

    Gofuku, Akio; Shimizu, Kenji; Sugano, Keiji; Yoshikawa, Hidekazu; Wakabayashi, Jiro

    1990-01-01

    In order to execute efficiently a dynamic simulation of a large-scaled engineering system such as a nuclear power plant, it is necessary to develop intelligent simulation support system for all phases of the simulation. This study is concerned with the intelligent support for the program development phase and is engaged in the adequate model selection support method by applying AI (Artificial Intelligence) techniques to execute a simulation consistent with its purpose and conditions. A proto-type expert system to support the model selection for numerical simulations of nuclear thermal-hydraulics in the case of cold leg small break loss-of-coolant accident of PWR plant is now under development on a personal computer. The steps to support the selection of both fluid model and constitutive equations for the drift flux model have been developed. Several cases of model selection were carried out and reasonable model selection results were obtained. (author)

  2. Improvement to surface lagging systems in a nuclear reactor, particularly of the fast neutron type

    International Nuclear Information System (INIS)

    Lemercier, Guy.

    1979-01-01

    Improvements to surface lagging systems in a nuclear reactor, particularly of the fast neutron kind. This system is composed of an assembly of panels each formed of a stack of metal fabric or trellis held against the surface to be protected, by a double fixing system comprising (a) a tubular component passing through a hole in the panel and applying it against the surface through a bearing plate, and (b) a bolt fitted in the centre of the tubular component, also secured to the surface and holding a washer capable of preventing the fall of the tubular component and the panel should the tubular component fracture [fr

  3. Experiment monitoring system of a new electromagnet drive for nuclear reactor control rod

    International Nuclear Information System (INIS)

    Zhang Jige; Wang Xiaoguang; Wu Yuanqiang; Zhang Zhengming

    2003-01-01

    In order to deal with some unsolved problems in the engineering prototype design of a new electromagnet drive device for nuclear reactor control rod, the property experiment in view of principle prototype is carried out. Actual displacement of nuclear reactor control rod is measured by means of raster ruler and the test data is obtained by means of computer. The computer communicates with PLC using RS232 serial port. The experimental results show that the monitoring system have the properties of high reliability and high precision, and ensures the experiment to accomplish successfully

  4. A review on colloidal systems in general and in respect of nuclear waste disposal

    International Nuclear Information System (INIS)

    Vuorinen, Ulla

    1987-04-01

    Recently the possible importance of colloids in connection with nuclear waste disposal, especially in radionuclide migration has been emphasized. Several studies have been or are going to be initiated to investigate the occurrence of natural groundwater colloids and their properties as well as formation and properties of radiocolloids, especially pseudoradiocolloids. If colloids are found to be important, they also have to considered in the safety assessments of nuclear waste disposal. In order to do so, additional theory and equations have to be added to present codes and models. This study is a literature survey consisting first a general approach on colloidal systems and their properties. Then a review on natural groundwater colloids (clays and organs) is given following descriptions of several methods to study colloids. Lastly the role of colloids in nuclear waste disposal is discussed including especially some information about possible actinide colloids and some current research going on in this field. 96 refs

  5. Development of a Tracking System of Exotic Nuclear Beams for FAIR

    International Nuclear Information System (INIS)

    Fernandez, B.; Abou-Haidar, Z.; Alvarez, M. A. G.; Pancin, J.; Drouart, A.; Kebbiri, M.; Riallot, M.

    2010-01-01

    New accelerators like SPIRAL2 (GANIL, France) or FAIR (GSI, Germany) will be soon constructed, and they will be able to produce radioactive ion beams (RIB) with high intensities of current (≥10 6 pps). These beams, at low energy, lower than 20 MeV/n, usually have high emittance, which imposes the use of tracking detectors before the target in order to reconstruct the trajectory of the ions. The group of Nuclear Physics at CNA (Centro Nacional de Aceleradores), is in charge of developing a tracking system for the low energy branch of FAIR (the HISPEC/DESPEC project). A collaboration with CEA-SACLAY was established, with the aim of developing, building and testing low pressure Secondary electron Detectors (SeD). Within this proposal we have projected and constructed a new Nuclear Physics Line in the CNA in order to be able to receive any kind of detector tests and the associated nuclear instruments.

  6. A photomultiplier-based secondary electron imaging system for a nuclear microprobe

    International Nuclear Information System (INIS)

    Alves, L.C.; Breese, M.B.H.; Silva, M.F. da; Soares, J.C.

    2002-01-01

    The ability to define, or recognise particular regions of interest or surface features is vital to the analysis and interpretation of spatially-resolved images collected with a nuclear microprobe. However, good topographic image contrast is difficult to accomplish using PIXE or RBS images due to their inherent insensitivity to topography, lack of elemental variation or poor statistics. Topographic image contrast is commonly obtained in scanning electron microscopy (SEM) by detecting a large flux of secondary electrons produced by the focused keV electron beam. Similar systems have not been widely used on nuclear microprobes due to ion beam intensity fluctuations, which limit the minimum resolvable contrast and present a major limitation for this technique. This paper describes a secondary electron imaging system which has been developed on the Lisbon microprobe. It is based on a scintillator, a photomultiplier operated in a pulsed mode, a pulse shaping electronic chain and ADC, and requires no changes to the existing data acquisition system. Examples of the images obtained from materials such as patterned SiGe wafers and hydrogen-implanted silicon are given, and compared with SEM or optical images

  7. Multi-state system in a fault tree analysis of a nuclear based thermochemical hydrogen plant

    International Nuclear Information System (INIS)

    Zhang, Y.

    2008-01-01

    Nuclear-based hydrogen generation is a promising way to supply hydrogen for this large market in the future. This thesis focuses on one of the most promising methods, a thermochemical Cu-Cl cycle, which is currently under development by UOIT, Atomic Energy of Canada Limited (AECL) and the Argonne National Laboratory (ANL). The safety issues of the Cu-Cl cycle are addressed in this thesis. An investigation of major accident scenarios shows that potential tragedies can be avoided with effective risk analysis and safety management programs. As a powerful and systematic tool, fault tree analysis (FTA) is adapted to the particular needs of the Cu-Cl system. This thesis develops a new method that combines FTA with a reliability analysis tool, multi-state system (MSS), to improve the accuracy of FTA and also improve system reliability. (author)

  8. An expert system design incorporating fuzzy logic for diagnosing heat imbalances in a nuclear power plant

    International Nuclear Information System (INIS)

    Guth, M.A.S.

    1987-01-01

    This paper presents an expert system for diagnosing problems in the interface between the heat exchanger and the core of a nuclear power plant for a hypothetical pressurized water reactor (PWR). The expert system has a production rule backward-chaining-based architecture, and the knowledge base incorporates four kinds of information. First, the structural relationship between causes and consequences is given by nuclear engineering experts. Second, numerical values for the initiating events can be taken from observed performance of the reactor under normal conditions. Third, the causes of particular events are ranked in order of their likelihood based on a combination of a priori knowledge about the reactor design and actual data on the incidence of component failures. Fourth, Bellman-Zadeh Fuzzy Logic is introduced to maintain truth values for expert system rules that hold with varying degrees of certainty

  9. A methodological framework applied to the choice of the best method in replacement of nuclear systems

    International Nuclear Information System (INIS)

    Vianna Filho, Alfredo Marques

    2009-01-01

    The economic equipment replacement problem is a central question in Nuclear Engineering. On the one hand, new equipment are more attractive given their best performance, better reliability, lower maintenance cost etc. New equipment, however, require a higher initial investment. On the other hand, old equipment represent the other way around, with lower performance, lower reliability and specially higher maintenance costs, but in contrast having lower financial and insurance costs. The weighting of all these costs can be made with deterministic and probabilistic methods applied to the study of equipment replacement. Two types of distinct problems will be examined, substitution imposed by the wearing and substitution imposed by the failures. In order to solve the problem of nuclear system substitution imposed by wearing, deterministic methods are discussed. In order to solve the problem of nuclear system substitution imposed by failures, probabilistic methods are discussed. The aim of this paper is to present a methodological framework to the choice of the most useful method applied in the problem of nuclear system substitution.(author)

  10. International Nuclear Information System in Malaysia

    International Nuclear Information System (INIS)

    Samsurdin Ahamad

    1984-01-01

    Practice of the International Nuclear Information System (INIS) in Malaysia is reviewed. The Nuclear Energy Unit, a participating representative of Malaysia, holds the responsibilities of disseminating information through this system. Its available services relevant to the aims of INIS are discussed

  11. Nuclear Space Power Systems Materials Requirements

    International Nuclear Information System (INIS)

    Buckman, R.W. Jr.

    2004-01-01

    High specific energy is required for space nuclear power systems. This generally means high operating temperatures and the only alloy class of materials available for construction of such systems are the refractory metals niobium, tantalum, molybdenum and tungsten. The refractory metals in the past have been the construction materials selected for nuclear space power systems. The objective of this paper will be to review the past history and requirements for space nuclear power systems from the early 1960's through the SP-100 program. Also presented will be the past and present status of refractory metal alloy technology and what will be needed to support the next advanced nuclear space power system. The next generation of advanced nuclear space power systems can benefit from the review of this past experience. Because of a decline in the refractory metal industry in the United States, ready availability of specific refractory metal alloys is limited

  12. A study in improvement of administrative system in the nuclear safety regulation

    International Nuclear Information System (INIS)

    Yook, Dong Il; Kuk, Doe Hyeong; Lee, Seong Min; Kim, Jong Sam; Hwang, Sun Ho

    2001-03-01

    One of the most important tasks to improve nuclear safety regulation system is to separate nuclear regulatory institutes from public agencies which promote the development nuclear power. Moreover, nuclear safety regulation should be not only specialized but optimized to be adapted for new environments such as high-tech information age. Especially, it is necessary to reform the current nuclear safety regulation systems both to be effective under the local self-administration which began to operate in recent years and to be supported by local residents

  13. A study in improvement of administrative system in the nuclear safety regulation

    Energy Technology Data Exchange (ETDEWEB)

    Yook, Dong Il; Kuk, Doe Hyeong; Lee, Seong Min; Kim, Jong Sam; Hwang, Sun Ho [Chungnam National Univ., Taejon (Korea, Republic of)

    2001-03-15

    One of the most important tasks to improve nuclear safety regulation system is to separate nuclear regulatory institutes from public agencies which promote the development nuclear power. Moreover, nuclear safety regulation should be not only specialized but optimized to be adapted for new environments such as high-tech information age. Especially, it is necessary to reform the current nuclear safety regulation systems both to be effective under the local self-administration which began to operate in recent years and to be supported by local residents.

  14. A study of the modifications of nuclear instrumentation systems for JRR-2

    International Nuclear Information System (INIS)

    Azim, Mohammad; Horiki, Ooichiro; Sato, Mitsugu

    1978-04-01

    In this report a comparative study has been carried out between the original A.M.F. design and the modified design for the nuclear instrumentation systems of the Research Reactor JRR-2, at the Tokai Research Establishment of JAERI. Due to a fire accident in the control room, in July 1968, the originally designed nuclear instrumentation systems, using conventional vacuum tube circuits, were destroyed and were replaced by the modified design, incorporating solid state linear integrated circuits as basic circuit components. The results of the reactor instrumentation systems modification at JRR-2 are very encouraging as the operating efficiency of the Reactor registered an improvement of 43%. Moreover the safety aspects have been fully taken care of in the new design and the reactor is well guarded against all possible instrument failures and human errors. This report presents the basic theory of operation of the two designs alongwith a comparative safety analysis. (auth.)

  15. Nuclear fuel element leak detection system

    International Nuclear Information System (INIS)

    John, C.D. Jr.

    1978-01-01

    Disclosed is a leak detection system integral with a wall of a building used to fabricate nuclear fuel elements for detecting radiation leakage from the nuclear fuel elements as the fuel elements exit the building. The leak detecting system comprises a shielded compartment constructed to withstand environmental hazards extending into a similarly constructed building and having sealed doors on both ends along with leak detecting apparatus connected to the compartment. The leak detecting system provides a system for removing a nuclear fuel element from its fabrication building while testing for radiation leaks in the fuel element

  16. Developing a computerized aging management system for concrete structures in finnish nuclear power plants

    International Nuclear Information System (INIS)

    Al-Neshawy, F.; Piironen, J.; Sistonen, E.; Vesikari, E.; Tuomisto, M.; Hradil, P.; Ferreira, M.

    2013-01-01

    Finland has four nuclear reactors units in two power plants. The first unit started operation in 1977 and in the early 1980's all four units were in use. During the last few years the aging management of the Nuclear Power Plant's (NPP) concrete structures has grown an important issue because the existing structures are reaching the end of their licensed operating lifetime (about 40 years). Therefore the nuclear power companies are developing aging management systems to avoid premature degradation of NPP facilities and to be able to extend their operating lifetime. This paper is about the development of a computerized ageing management system for the nuclear power plants concrete structures. The computerized ageing management system is built upon central database and implementation applications. It will assist the personnel of power companies to implement the aging management activities at different phases of the lifetime of a power plant. It will provide systematic methods for planning, surveillance, inspection, monitoring, condition assessment, maintenance and repair of structures. (authors)

  17. A review of liquor transfer systems for use in nuclear reprocessing plants

    International Nuclear Information System (INIS)

    Singh, J.

    1982-01-01

    Liquor pumping systems for use in nuclear fuel reprocessing plants are described. Comparison of the operating characteristics and system constants are made between the air lift/Vacuum Operated Slug Lift, power fluidics and ejector pump systems. (author)

  18. A study on national innovation system for the improvement of nuclear R and D performance

    Energy Technology Data Exchange (ETDEWEB)

    Yun, S. W.; Oh, K. B.; Kim, H. J.; Cheong, H. S.; Cheong, I.; Lee, J. H.; Won, B. C.; Cheong, C. E.; Lee, K. H.; Choi, H. M

    2006-01-15

    Review basic concept and analytical method concerned with technological innovation and NIS : concept and defition of technological innovation and NIS, background and evolution of the NIS theory, basic elements of NIS and their relationship. Identification on scientific-technological characteristics of the nuclear R and D and technological innovation : special aspect of the nuclear R and D and technological innovation, difficulty(or complexity) of the nuclear R and D and technological, innovation. Defining organizational-institutional elements of nuclear R and D and innovation allowing for nuclear scientific-technological peculiarity. Developing the model of national nuclear innovation system for analysis of the national R and D performance. Developing the analytical model including performance measure and procedure for national nuclear innovation system led mainly by national Rand D in Korea. Discussion about the national innovation system with other OECD/NEA member countries.

  19. A study on national innovation system for the improvement of nuclear R and D performance

    International Nuclear Information System (INIS)

    Yun, S. W.; Oh, K. B.; Kim, H. J.; Cheong, H. S.; Cheong, I.; Lee, J. H.; Won, B. C.; Cheong, C. E.; Lee, K. H.; Choi, H. M.

    2006-01-01

    Review basic concept and analytical method concerned with technological innovation and NIS : concept and defition of technological innovation and NIS, background and evolution of the NIS theory, basic elements of NIS and their relationship. Identification on scientific-technological characteristics of the nuclear R and D and technological innovation : special aspect of the nuclear R and D and technological innovation, difficulty(or complexity) of the nuclear R and D and technological, innovation. Defining organizational-institutional elements of nuclear R and D and innovation allowing for nuclear scientific-technological peculiarity. Developing the model of national nuclear innovation system for analysis of the national R and D performance. Developing the analytical model including performance measure and procedure for national nuclear innovation system led mainly by national Rand D in Korea. Discussion about the national innovation system with other OECD/NEA member countries

  20. WALS: A sensor-based robotic system for handling nuclear materials

    International Nuclear Information System (INIS)

    Drotning, W.; Kimberly, H.; Wapman, W.

    1997-01-01

    An automated system is being developed for handling large payloads of radioactive nuclear materials in an analytical laboratory. The system uses machine vision and force/torque sensing to provide sensor-based control of the automation system to enhance system safety, flexibility, and robustness and achieve easy remote operation. The automation system also controls the operation of the laboratory measurement systems and the coordination of them with the robotic system. Particular attention has been given to system design features and analytical methods that provide an enhanced level of operational safety. Independent mechanical gripper interlock and too release mechanisms were designed to prevent payload mishandling. An extensive failure modes and effects analysis (FMEA) of the automation system was developed as a safety design analysis tool

  1. A filter system for steam-gas mixture ejections from under a nuclear reactor containment following a severe accident

    International Nuclear Information System (INIS)

    Dulepov, Ju. N.; Sharygin, L. M.; Tretjakov, S. Ja.; Shtin, A.P.; Glushko, V. V.; Babenko, E. A.; Kurakov, Ju. A.

    1997-01-01

    In this paper newly built NPPs obligatory incorporate a containment having a filter system for removing radioactive materials ejections under severe accidents including nuclear fuel melting is described. The system prevents a containment failure and provides ejected radioactive materials decontamination to permissible levels. The physical-chemical and chemical characteristics of Termoxid-58 sorbent (TiO 5 based sorbent) are presented

  2. A video imaging system and related control hardware for nuclear safeguards surveillance applications

    International Nuclear Information System (INIS)

    Whichello, J.V.

    1987-03-01

    A novel video surveillance system has been developed for safeguards applications in nuclear installations. The hardware was tested at a small experimental enrichment facility located at the Lucas Heights Research Laboratories. The system uses digital video techniques to store, encode and transmit still television pictures over the public telephone network to a receiver located in the Australian Safeguards Office at Kings Cross, Sydney. A decoded, reconstructed picture is then obtained using a second video frame store. A computer-controlled video cassette recorder is used automatically to archive the surveillance pictures. The design of the surveillance system is described with examples of its operation

  3. Study of DNA damage with a new system for irradiation of samples in a nuclear reactor

    Energy Technology Data Exchange (ETDEWEB)

    Gual, Maritza R., E-mail: mrgual@instec.c [Instituto Superior de Tecnologias y Ciencias Aplicadas, InSTEC, Avenida Salvador Allende y Luaces, Quinta de Los Molinos, Plaza de la Revolucion, Havana, AP 6163 (Cuba); Milian, Felix M. [Universidade Estadual de Santa Cruz, UESC (Brazil); Deppman, Airton [Instituto de Fisica, Universidad de Sao Paulo, IF-USP, Rua do Matao, Travessa R, no. 187, Ciudade Universitaria, Butanta, CEP 05508-900, Sao Paulo (Brazil); Coelho, Paulo R.P. [Instituto de Pesquisas Energeticas e Nucleares, IPEN-CNEN/SP (Brazil)

    2011-02-15

    In this paper, we report results of a quantitative analysis of the effects of neutrons on DNA, and, specifically, the production of simple and double breaks of plasmid DNA in aqueous solutions with different concentrations of free-radical scavengers. The radiation damage to DNA was evaluated by electrophoresis through agarose gels. The neutron and gamma doses were measured separately with thermoluminescent detectors. In this work, we have also demonstrated usefulness of a new system for positioning and removing samples in channel BH3 of the IEA-R1 reactor at the Instituto de Pesquisas Energeticas e Nucleares (Brazil) without necessity of interrupting the reactor operation.

  4. Design of a bolted flange subjected to severe nuclear system thermal transients - A case study

    International Nuclear Information System (INIS)

    Palmer, W.J.; Tomawski, R.J.; Ezekoye, L.I.; Lacey, M.L.

    1986-01-01

    Flange design standards recognize that flanged joints may develop leakage should they be exposed to severe thermal gradients and recommend that such operating conditions be avoided. In nuclear power plants, severe thermal transients may be encountered in many plant and system operating and test conditions. In such applications, conformance with standard design practice may not ensure a leak-tight joint. This paper describes the proper consideration of thermal effects on flanged joints and how that can lead to the development of a successful leak-tight design. Similar procedures may be applied generally to evaluate and upgrade flanged joints in thermal shock applications

  5. Construction of a male sterility system for hybrid rice breeding and seed production using a nuclear male sterility gene

    OpenAIRE

    Chang, Zhenyi; Chen, Zhufeng; Wang, Na; Xie, Gang; Lu, Jiawei; Yan, Wei; Zhou, Junli; Tang, Xiaoyan; Deng, Xing Wang

    2016-01-01

    Nuclear male sterility is common in flowering plants, but its application in hybrid breeding and seed production is limited because of the inability to propagate a pure male sterile line for commercial hybrid seed production. Here, we characterized a rice nuclear gene essential for sporophytic male fertility and constructed a male sterility system that can propagate the pure male sterile seeds on a large scale. This system is fundamentally advantageous over the current cytoplasmic male steril...

  6. A computerized assessment and response system for radiological emergency at Diablo Canyon Nuclear Power Plant

    International Nuclear Information System (INIS)

    Shih, C.C.; Thuillier, R.H.

    1984-01-01

    The U.S. Nuclear Regulatory Commission requires that nuclear power plants provide for rapid assessment and response in the event of a radiological emergency. At the Diablo Canyon Nuclear Power Plant, Pacific Gas and Electric Company uses a system of linked central minicomputer, satellite desktop computers and microprocessors to provide decision makers with timely and pertinent information in emergency situations. The system provides for data acquisition and microprocessing at meteorological and radiological monitoring sites. Current estimates or projections of offsite dose commitment are made in real-time by a dispersion/dose calculation model. Computerized dissemination of data and calculational results to decision makers at the government and utility levels is also available. The basic system in use is a commercially available Emergency Assessment and Response System (EARS). This generic system has been modified in-house to meet requirements specific to emergency situations at the plant. Distinctive features of the modification program includes: a highly professional man-machine interaction; consideration of site-specific factors; simulation of environmental radiology for development of drill scenarios; and concise, pertinent reports as input to decision making

  7. Development of a daily maintenance work management system for nuclear power plants

    International Nuclear Information System (INIS)

    Yoshimura, Sadanori; Maita, Keikichi; Ogawa, Koutaro; Tabata, Nobuyuki; Shibuya, Shinya

    1999-01-01

    Maintenance work plays an important role in keeping the safety and reliability of nuclear power plants. Especially, with the recent trends of reducing the outage length, safe and reliable execution of maintenance work is more earnestly required than ever. Taking this situation into account, a daily maintenance work management system has been developed to support the execution of maintenance work for nuclear power plants. This system supports maintenance personnel in writing and approving the daily work instruction sheet and reduces their workload by providing predetermined lists of items necessary for filling up the sheet and by applying an electronic approval procedure. It also provides information through a computer network to improve the communication among maintenance personnel. For work steps to be treated in the daily work instruction sheet, an analysis was made to identify potential human errors and related counter measures, which were then linked to safety and quality assurance instructions of the sheet. Based on this information, the system automatically presents the safety and quality assurance instructions related to the work content listed in the sheet to improve the appropriateness of the instructions. A prototype of the daily maintenance work management system was developed and a trial use was made for actual periodic maintenance work at a nuclear power plant. This experience shows the usefulness of the system in reducing the workload of maintenance personnel and in providing safer work instructions. (author)

  8. Development of a remote controlled robot system for monitoring nuclear power plant

    Energy Technology Data Exchange (ETDEWEB)

    Woo, Hee Gon; Song, Myung Jae; Shin, Hyun Bum; Oh, Gil Hwan; Maeng, Sung Jun; Choi, Byung Jae; Chang, Tae Woo [Korea Electric Power Research Institute, Taejon (Korea, Republic of); Lee, Bum Hee; Yoo, Jun; Choi, Myung Hwan; Go, Nak Yong; Lee, Kee Dong; Lee, Young Dae; Cho, Hae Kyeng; Nam, Yoon Suk [Electric and Science Research Center, (Korea, Republic of)

    1996-12-31

    It`s a final report of the development of remote controlled robot system for monitoring the facilities in nuclear power plant and contains as follows, -Studying the technologies in robot developments and analysing the requirements and working environments - Development of the test mobile robot system - Development of the mobile-robot - Development of the Mounted system on the Mobile robot - Development of the Monitoring system - Mobil-robot applications and future study. In this study we built the basic technologies and schemes for future robot developments and applications. (author). 20 refs., figs.

  9. Transfer system development for a remote inspection robot in nuclear power plants

    International Nuclear Information System (INIS)

    Mizuno, M.; Ohnuma, M.; Hamada, K.; Mizutani, T.; Shimada, A.; Segawa, M.; Kubo, K.

    1984-01-01

    A remote operated robot system has been developed for inspection inside the primary containment vessel (PCV) of nuclear power plants. This system consists of an inspection vehicle, a monorail driving system, a signal transmission system, a power supply system and an operator console.. The system has two main features. First is that the operator can transfer the vehicle at any time from outside the PCV to inside or vice versa through a personnel airlock. The second feature is that the vehicle can be transported from one inspection route to another route at junction points. A prototype inspection robot system was fabricated on a trial basis. Running and inspection performances were confirmed utilizing actual size test apparatus

  10. The design of photoelectric signal processing system for a nuclear magnetic resonance gyroscope based on FPGA

    Science.gov (United States)

    Zhang, Xian; Zhou, Binquan; Li, Hong; Zhao, Xinghua; Mu, Weiwei; Wu, Wenfeng

    2017-10-01

    Navigation technology is crucial to the national defense and military, which can realize the measurement of orientation, positioning, attitude and speed for moving object. Inertial navigation is not only autonomous, real-time, continuous, hidden, undisturbed but also no time-limited and environment-limited. The gyroscope is the core component of the inertial navigation system, whose precision and size are the bottleneck of the performance. However, nuclear magnetic resonance gyroscope is characteristic of the advantage of high precision and small size. Nuclear magnetic resonance gyroscope can meet the urgent needs of high-tech weapons and equipment development of new generation. This paper mainly designs a set of photoelectric signal processing system for nuclear magnetic resonance gyroscope based on FPGA, which process and control the information of detecting laser .The photoelectric signal with high frequency carrier is demodulated by in-phase and quadrature demodulation method. Finally, the processing system of photoelectric signal can compensate the residual magnetism of the shielding barrel and provide the information of nuclear magnetic resonance gyroscope angular velocity.

  11. Croatian National System of Nuclear Materials Control

    International Nuclear Information System (INIS)

    Biscan, R.

    1998-01-01

    In the process of economic and technological development of Croatia by using or introducing nuclear power or in the case of international co-operation in the field of peaceful nuclear activities, including international exchange of nuclear material, Croatia should establish and implement National System of Nuclear Materials Control. Croatian National System of accounting for and control of all nuclear material will be subjected to safeguards under requirements of Agreement and Additional Protocol between the Republic of Croatia and the International Atomic Energy Agency (IAEA) for the Application of Safeguards in Connection with the Treaty on the Non-Proliferation of Nuclear Weapons (NPT). The decision by NPT parties at the 1995 NPT Review and Extension Conference to endorse the Fullscope IAEA Safeguards Standard (FSS) as a necessary precondition of nuclear supply means that states are obliged to ensure that the recipient country has a FSS agreement in place before any nuclear transfer can take place (Ref. 1). The FSS standard of nuclear supply is a central element of the Nuclear Suppliers Group (NSG) Guidelines which the NSG adopted in 1992 and should be applied to members and non-members of the NSG. The FSS standard of nuclear supply in general allows for NPT parties or countries which have undertaken the same obligations through other treaty arrangements, to receive favourable treatment in nuclear supply arrangements. However, the Iraqi experience demonstrate that trade in nuclear and dual-use items, if not properly monitored, can contribute to a nuclear weapons program in countries acting contrary to their non-proliferation obligation. Multilateral nuclear export control mechanisms, including the FSS supply standard, provide the basis for co-ordination and standardisation of export control measures. (author)

  12. A decision support system for identifying abnormal operating procedures in a nuclear power plant

    International Nuclear Information System (INIS)

    Hsieh, Min-Han; Hwang, Sheue-Ling; Liu, Kang-Hong; Liang, Sheau-Farn Max; Chuang, Chang-Fu

    2012-01-01

    Highlights: ► A decision support system has been constructed and verified. ► The operator's decision-making time was decreased by about 25%. ► The accuracy was increased by about 18%. ► The system prevents overlooking important information. ► Fewer erroneous solutions were implemented, and the mental workload was reduced. - Abstract: In order to prevent safety hazards that can result from inappropriate decisions made by the operators of a nuclear power plant (NPP), this study was undertaken to develop a decision support system to reduce the complexity of the decision-making process by aiding operators’ cognitive activities, integrating unusual symptoms, and identifying the most suitable abnormal operating procedure (AOP) for operators. The study was conducted from the perspective of human factors engineering in order to compare the process that operators originally used to select an AOP with a process that included a support system for AOP identification. The results of the study indicated that the existence of a support system reduces errors by quickly suggesting likely AOPs. With such a support system in place, there were clear improvements in human performance, i.e., decision-making time decreased by about 25%, and the accuracy of the operators’ decisions, judged by the successful resolution of specific problems, increased by about 18%. In addition, there were fewer erroneous solutions implemented, and the mental workload was reduced. Hence, the decision support system is proposed as a training tool in identifying AOPs in the main control room (MCR).

  13. Study on deterministic response time design for a class of nuclear Instrumentation and Control systems

    International Nuclear Information System (INIS)

    Chen, Chang-Kuo; Hou, Yi-You; Luo, Cheng-Long

    2012-01-01

    Highlights: ► An efficient design procedure for deterministic response time design of nuclear I and C system. ► We model the concurrent operations based on sequence diagrams and Petri nets. ► The model can achieve the deterministic behavior by using symbolic time representation. ► An illustrative example of the bistable processor logic is given. - Abstract: This study is concerned with a deterministic response time design for computer-based systems in the nuclear industry. In current approach, Petri nets are used to model the requirement of a system specified with sequence diagrams. Also, the linear logic is proposed to characterize the state of changes in the Petri net model accurately by using symbolic time representation for the purpose of acquiring deterministic behavior. An illustrative example of the bistable processor logic is provided to demonstrate the practicability of the proposed approach.

  14. Safety Management Characteristics Reflected in Interviews at Swedish Nuclear Power Plants: A System Perspective Approach

    International Nuclear Information System (INIS)

    Salo, Ilkka

    2005-12-01

    The present study investigated safety management characteristics reflected in interviews with participants from two Swedish nuclear power plants. A document analysis regarding the plants' organization, safety policies, and safety culture work was carried out as well. The participants (n=9) were all nuclear power professionals, and the majority managers at different levels with at least 10 years of nuclear power experience. The interview comprised themes relevant for organizational safety and safety management, such as: organizational structures and organizational change, threats to safety, information feedback and knowledge transfer, safety analysis, safety policy, and accident and incident analysis and reporting. The results were in part modeled to important themes derived from a general system theoretical framework suggested by Svenson and developed by Svenson and Salo in relation to studies of 'non-nuclear' safety organizations. A primer to important features of the system theoretical framework is presented in the introductory chapter. The results from the interviews generated interesting descriptions about nuclear safety management in relation to the above themes. Regarding organizational restructuring, mainly centralizations of resources, several examples of reasons for the restructuring and related benefits for this centralization of resources were identified. A number of important reminders that ought to be considered in relation to reorganization were also identified. Regarding threats to the own organization a number of such was interpreted from the interviews. Among them are risks related to generation and competence change-over and risks related to outsourcing of activities. A thorough picture of information management and practical implications related to this was revealed in the interviews. Related to information feedback is the issue of organizational safety indicators and safety indicators in general. The interview answers indicated that the area

  15. Nuclear safety: operational aspects. 5. Data Communication in a Nuclear Digital I and C System-The Korean Experience

    International Nuclear Information System (INIS)

    Lim, Tae-Wook; Byun, Jae-Youb; Jhun, James S.

    2001-01-01

    Full-scale use of a microprocessor-based digital instrumentation and control (I and C) system for the control of nuclear power plants (NPPs) in Korea has spanned >14 yr and has covered eight plants. Experience gained from these applications is substantial. In this paper, the discussion centers on the design experience of the data communication portion of the digital I and C system along with the associated nuclear licensing issues. The data communication designs of the eight plants (four operating and four under construction) have changed from project to project and from supplier to supplier. The first two of the eight plants, Yonggwang NPP (YGN) Units 3 and 4 (YGN-3 and 4) included only the on/off (binary) controls in the digital I and C system. The subsequent six plants had a fully expanded scope of plant controls including both on/off controls as well as continuous (analog) controls. These latter six plants are Ulchin NPP (UCN) Units 3 and 4 (UCN 3 and 4), YGN Units 5 and 6 (YGN 5 and 6), and UCN Units 5 and 6 (UCN 5 and 6) in the order of their construction start dates. The digital system suppliers are Forney for YGN 3 and 4 and UCN 5 and 6; and Eaton for UCN 3 and 4 and YGN 5 and 6. The Forney system uses bus network architecture, while the Eaton system is based on a ring network configuration. The design differences, advantages, disadvantages, and specific licensing issues of these two configurations unique to the NPP operating environment are discussed in the abstract. The discussions are organized into two parts: the Forney system of YGN 3 and 4 and the Eaton system of YGN 5 and 6. The Forney system of UCN 5 and 6 is still in its early stage of design and manufacture, and it is basically similar to the design of YGN 3 and 4 except for the system upgrade from a 16- to a 32-bit system and the addition of an analog plant monitoring and control function. The Eaton system of UCN 3 and 4 is essentially identical to that of YGN 5 and 6 except that the YGN 5 and 6

  16. Development and validation of a nuclear data and calculation system for Superphenix with steel reflectors

    International Nuclear Information System (INIS)

    Bosq, J.Ch.

    1998-01-01

    This thesis concerns the definition and the validation of the ERANOS neutronic calculation system for steel reflected fast reactors. The calculation system uses JEF2.2 evaluated nuclear data, the ECCO cell code and the BISTRO and VARIANT transport codes. After a description of the physical phenomena induced by the existence of the these sub-critical media, an inventory of the past studies related to steel reflectors is reported. A calculational scheme taking into account the important physical phenomena (strong neutronic slowing-down, presence of broad resonances of the structural materials and spatial variation of the spectrum in the reflector) is defined. This method is validated with the TRIPOLI4 reference Monte-Carlo code. The use of this upgraded calculation method for the analysis of the part of the CIRANO experimental program devoted to the study of steel reflected configurations leads to discrepancies between the calculated and measured values. These remaining discrepancies obtained for the reactivity and the fission rate traverses are due to inaccurate nuclear data for the structural materials. The adjustment of these nuclear data in order to reduce these discrepancies id demonstrated. The additional uncertainty associated to the integral parameters of interest for a nuclear reactor (reactivity and power distribution) induced by the replacement of a fertile blanket by a steel reflector is determined for the Superphenix reactor and is proved to be small. (author)

  17. A strategy analysis of the fast breeder reactor introduction and nuclear fuel cycle systems deployment

    International Nuclear Information System (INIS)

    Wajima, Tsunetaka; Kawashima, Katsuyuki; Yamashita, Takashi

    1996-01-01

    A study is made on a strategy analysis of the long term nuclear fuel cycle systems deployment in accordance with the nuclear power growth projection and fast breeder reactor (FBR) introduction. In the analysis, the reprocessed plutonium (Pu) is charged into the reactor in such a way that the reprocessed Pu is not stored outside the reactor, i.e., there is no excess Pu outside the reactor. The analysis characterized the fuel cycle systems, and showed the usefulness of the present method to determine future directions for the FBR introduction and nuclear fuel cycle systems deployment. Concerning an intermediate-term strategy, the time of introduction and required capacities of a second commercial LWR reprocessing plant, Pu-thermal, and the first FBR reprocessing plant deployment are evaluated. A long term strategy analysis shows that the two or three large plants are run in parallel for each fuel cycle facility and that FBR related facilities deal with a markedly large amount of Pu. It is concluded that the early stage introduction of FBRs of significant capacities seems necessary to materialize a consistent total FBR/fuel cycle system where Pu balance becomes feasible through its flexible operation of, for instance, adjusting breeding ratio, in order to keep the transparency of the Pu utilization. (author)

  18. Improvements to the sodium supply system of a nuclear reactor core

    International Nuclear Information System (INIS)

    Chevallier, Rene; Marchais, Christian.

    1981-01-01

    This invention concerns an improvement to the sodium supply system of a nuclear reactor core and, in particular, concerns the area included between the outlet of the primary circulation pumps and the core proper. A simplified structure and a lightening of all this linking area between the circulation pumps and the distribution tank under the core is achieved and this results in a very significant reduction in the risks of deterioration and in a definite increase in the reliability of the reactor. The invention is therefore an improvement to the sodium supply system of the nuclear reactor core vessel with incorporated exchangers, in which the cool sodium, after passing through the primary exchangers, is collected in a ring compartment from whence it is taken up by the pumps and moved to at least one pipe reaching a distribution tank located under the reactor core [fr

  19. 21 CFR 892.1310 - Nuclear tomography system.

    Science.gov (United States)

    2010-04-01

    ... 21 Food and Drugs 8 2010-04-01 2010-04-01 false Nuclear tomography system. 892.1310 Section 892...) MEDICAL DEVICES RADIOLOGY DEVICES Diagnostic Devices § 892.1310 Nuclear tomography system. (a) Identification. A nuclear tomography system is a device intended to detect nuclear radiation in the body and...

  20. Experience with Nuclear Medicine Information System

    Directory of Open Access Journals (Sweden)

    Bilge Volkan-Salanci

    2012-12-01

    Full Text Available Objective: Radiology information system (RIS is basically evolved for the need of radiologists and ignores the vital steps needed for a proper work flow of Nuclear Medicine Department. Moreover, CT/MRI oriented classical PACS systems are far from satisfying Nuclear Physicians like storing dynamic data for reprocessing and quantitative analysis of colored images. Our purpose was to develop a workflow based Nuclear Medicine Information System (NMIS that fulfills the needs of Nuclear Medicine Department and its integration to hospital PACS system. Material and Methods: Workflow in NMIS uses HL7 (health level seven and steps include, patient scheduling and retrieving information from HIS (hospital information system, radiopharmacy, acquisition, digital reporting and approval of the reports using Nuclear Medicine specific diagnostic codes. Images and dynamic data from cameras of are sent to and retrieved from PACS system (Corttex© for reprocessing and quantitative analysis. Results: NMIS has additional functions to the RIS such as radiopharmaceutical management program which includes stock recording of both radioactive and non-radioactive substances, calculation of the radiopharmaceutical dose for individual patient according to body weight and maximum permissible activity, and calculation of radioactivity left per unit volume for each radionuclide according their half lives. Patient scheduling and gamma camera patient work list settings were arranged according to specific Nuclear Medicine procedures. Nuclear Medicine images and reports can be retrieved and viewed from HIS. Conclusion: NMIS provides functionality to standard RIS and PACS system according to the needs of Nuclear Medicine. (MIRT 2012;21:97-102

  1. A technical system to improve the operational monitoring of the Zaporozh'ye nuclear power plant

    International Nuclear Information System (INIS)

    Beyer, M.; Carl, H.; Schumann, P.; Seidel, A.; Weiss, F.-P.; Zschau, J.; Nowak, K.

    1997-01-01

    As part of a programme of cooperation with Central and Eastern European states, a technical system has been established for the Zaporozhe nuclear power plant, which complements existing operational checking and monitoring facilities with modern means of information technology. It makes it possible to continuously monitor the state of the units in normal operation and in cases of anomalies or incidents. The parameters selected for monitoring are listed, and the system of automatic evaluation at the power plant site is described in detail. Test operation of the technical system started in late 1995 and the industrial testing phase in mid-1996. (A.K.)

  2. Application of genetic algorithms to the maintenance scheduling optimization in a nuclear system basing on reliability

    International Nuclear Information System (INIS)

    Lapa, Celso M. Franklin; Pereira, Claudio M.N.A.; Mol, Antonio C. de Abreu

    1999-01-01

    This paper presents a solution based on genetic algorithm and probabilistic safety analysis that can be applied in the optimization of the preventive maintenance politic of nuclear power plant safety systems. The goal of this approach is to improve the average availability of the system through the optimization of the preventive maintenance scheduling politic. The auxiliary feed water system of a two loops pressurized water reactor is used as a sample case, in order to demonstrate the effectiveness of the proposed method. The results, when compared to those obtained by some standard maintenance politics, reveal quantitative gains and operational safety levels. (author)

  3. A Camac-VME-MacIntosh data acquisition system for nuclear experiments

    International Nuclear Information System (INIS)

    Anzalone, A.; Giustolisi, F.

    1989-01-01

    A multiprocessor system for data acquisition and analysis in low energy nuclear physics has been realized at the Laboratorio Nazionale del Sud. the system is built around Camac, VME-bus and MacIntosh PC. A multiprocessor software has been developed, using RTF, Macsys and Cern cross-software. The execution of several programs which run on several VME-CPU's and on an external PC, is coordinated by a mail box protocol. No operating system is used on the VME-CPU's

  4. Chemical cleaning the service water system at a nuclear power plant

    International Nuclear Information System (INIS)

    Brice, T.O.; Glover, W.A.

    1994-01-01

    Chemical cleaning a large cooling water system in a nuclear power plant presented many unique problems. The selection, qualification, and performance of the cleaning process were done using a phased approach. The piping was inspected to determine the extent of the problem. Deposit samples were removed from the service water system pipe and tested in the laboratory to determine the most effective cleaning solvent for deposit removal. An engineering study was performed to define the design parameters required to implement the system-wide chemical cleaning

  5. A comparison of nuclear power systems for Brazil using plutonium and binary cycles

    International Nuclear Information System (INIS)

    Ishiguro, Y.; Fernandes, J.E.

    1985-01-01

    Nuclear power systems based on plutonium cycle and binary cycle are compared taking into account natural uranium demand and reactor combination. The systems start with PWR type reactors (U5/U8) and change to systems composed exclusively of FBR type reactors or PWR-FBR symbiotic systems. Four loading modes are considered for the PWR and two for the FBR. The FBR is either a LMFBR loaded with PU/U or a LMFBR loaded the binary way. A linear and a non-linear capacity growth and two different criteria for the FBR introduction are considered. The results show that a 100 GWe permanent system can be established in 50 years in all cases, based on 300000 t of natural uranium and in case of delay in the FBR introduction and if a thermal-fast symbiotic system is chosen, a binary cycle could be more advantageous than a plutonium cycle. (F.E.) [pt

  6. Introduction to the use of the INPRO methodology in a nuclear energy system assessment. A report of the International Project on Innovative Nuclear Reactors and Fuel Cycles (INPRO)

    International Nuclear Information System (INIS)

    2010-01-01

    The International Project on Innovative Nuclear Reactors and Fuel Cycles (INPRO) was initiated in 2001 on the basis of an IAEA General Conference resolution in 2000 (GC(44)/RES/21). INPRO activities have since that time been continuously endorsed by resolutions of the IAEA General Conference and by the General Assembly of the United Nations. The objectives of INPRO are to: Help ensure that nuclear energy is available to contribute, in a sustainable manner, to the goal of meeting energy needs in the 21st century; Bring together technology holders and users so that they can jointly consider the international and national actions required to ensure the sustainability of nuclear energy through innovations in technology and/or institutional arrangements. To fulfil these objectives, INPRO developed a set of basic principles, user requirements and criteria, along with an assessment method, which are the basis of the INPRO methodology for evaluation of the sustainability of innovative nuclear energy systems. To provide additional guidance in using the INPRO methodology, the nine volume INPRO Manual was developed; it consists of an overview volume and eight volumes covering the areas of economics, institutional measures (infrastructure), waste management, proliferation resistance, physical protection, environment (including the impact of stressors and the availability of resources), reactor safety, and the safety of nuclear fuel cycle facilities. To assist Member States in applying the INPRO methodology, the nuclear energy system assessment (NESA) support package is being developed. This includes a database (containing input data for assessment), provision of training courses in the INPRO methodology and examples of comprehensive assessments. This publication provides guidance on how a variety of potential users, including nuclear technology developers, experienced users and prospective first time nuclear technology users (newcomers) can apply the INPRO methodology for

  7. SEMPaC - an expert system prototype associated with safety parameter display system of a nuclear power plant

    International Nuclear Information System (INIS)

    Hirama, K.

    1989-01-01

    This work presents SEMPaC, an expert system prototype: it provides means to support diagnosis and to make decisions during abnormal transients that cause the trip of nuclear power plant. The system operation is associated with Safety Parameter Display System - SPDS that was recommended by U. S. Nuclear Regulatory Commission (NRC) after the Three-Mile Island (TMI) accident analysis. (author)

  8. A literature-based preliminary characterization of risks in the nuclear waste management system

    International Nuclear Information System (INIS)

    Daling, P.M.; Rhoads, R.E.; Van Luik, A.E.

    1990-04-01

    The objectives of this study were to (1) review the literature containing information on risks in the nuclear waste management system and (2) use this information to develop preliminary estimates of the potential magnitudes of these risks. Information was collected on a broad range of risk categories to assist the US Department of Energy (DOE) in communicating information about the risks in the waste management system. The study, which was completed prior to passage of the Nuclear Waste Policy Amendments Act of 1987, examined all of the portions of the nuclear waste management system envisioned by the DOE in the 1985 ''Mission Plant for the Civilian Radioactive Waste Management Program.'' As such, there may be statements in this paper that are not consistent with current DOE positions. The scope of this paper includes the repository, the integral Monitored Retrievable Storage (MRS) facility, and the transportation system that supports the repository and the MRS facility. Based on the results of this analysis, it is concluded that the radiological risks in the waste management system are small relative to nonradiological risks and relative to the risks of exposure to natural background radiation. 6 refs., 2 figs., 2 tabs

  9. A system to obtain an optimized first design of a nuclear reactor core

    International Nuclear Information System (INIS)

    Mai, L.A.

    1988-01-01

    This work proposes a method for obtaining a first design of nuclear reactor cores. It takes into consideration the objectives of the project, physical limits, economical limits and the reactor safety. For this purpose, some simplifications were made in the reactor model: one energy-group, one-dimensional and homogeneous core. The adopted model represents a typical PWR core and the optimized parameters are the fuel thickness, reflector thickness, enrichment and moderating ratio. The objective is to gain a larger residual reactivity at the end of the cycle. This work also presents results for a PWR core. From the results, many conclusions are established: system efficiency, limitations and problems. Also some suggestions are proposed to improve the system performance for future works. (autor)

  10. Probabilistic safety assessment for digital instrumentation and control systems in nuclear power plants - a review

    International Nuclear Information System (INIS)

    Lu, L.; Jiang, J.

    2003-01-01

    Deregulation in electricity market has created a great deal of challenges for nuclear power industries [1]. To stay competitive, Nuclear Power Plants (NPPs) will have to find ways to reduce their operational costs and to improve the plant safety. Instrumentation and Control (I and C) systems play an important role in this regard. Thus, new methodologies need to be developed to manage the operation of I and C systems more economically without jeopardizing the overall plant safety. Probabilistic Safety Assessment (PSA) technique is one of the promising methods to deal with such an issue, because PSA analyzes various system operational issues from a probabilistic sense, rather than a worst-case approach. However, there are several limitations when PSA is applied to I and C systems directly. A possible solution to this problem can be found by incorporating PSA with several other approaches. To better understand the issues involved, an attempt has been made in this paper to carry out a literature survey on this and related subject, particularly the effort will be made on: 1) the development of digital I and C systems in NPP, 2) PSA and its potential benefits and limitations, and 3) applications of PSA in various aspects of I and C systems including the resource allocation, the determination of surveillance testing strategies and the design of I and C systems. Finally, some solutions to overcome the aforementioned obstacles when applying PSA in I and C systems are also examined critically. (author)

  11. Strainer device for an emergency cooling system in a nuclear power plant

    International Nuclear Information System (INIS)

    Trybom, J.

    1997-01-01

    The invention relates to a strainer device for separating contaminants from water in an emergency cooling system for a nuclear power plant. The nuclear power plant has a wet-well for water in the emergency cooling system and the strainer device comprises at least one strainer device, which is arranged in the wet-well. According to the invention the strainer is suspended in a desired position in the wet-well by means of at least a group of at least three tie rods arranged at angles to each other, each tie rod being fixed at one end to the strainer and its other end to the container or an anchor ring joined thereto. (author) figs

  12. A computerized diagnostic system for nuclear plant control rooms based on statistical quality control

    International Nuclear Information System (INIS)

    Heising, C.D.; Grenzebach, W.S.

    1990-01-01

    In engineering science, statistical quality control techniques have traditionally been applied to control manufacturing processes. An application to commercial nuclear power plant maintenance and control is presented that can greatly improve safety. As a demonstration of such an approach to plant maintenance and control, a specific system is analyzed: the reactor coolant pumps of the St. Lucie Unit 2 nuclear power plant located in Florida. A 30-day history of the four pumps prior to a plant shutdown caused by pump failure and a related fire within the containment was analyzed. Statistical quality control charts of recorded variables were constructed for each pump, which were shown to go out of statistical control many days before the plant trip. The analysis shows that statistical process control methods can be applied as an early warning system capable of identifying significant equipment problems well in advance of traditional control room alarm indicators

  13. Dynamical instabilities in hot expanding nuclear systems: a microscopic approach to the understanding of multifragmentation

    International Nuclear Information System (INIS)

    Suraud, E.

    1989-01-01

    We present a microscopic study of the quasi-fusion/explosion transition in the framework of Landau-Vlasov simulations and for intermediate energy heavy-ion collisions (beam energy from 10 to 100 MeV/A). After a short presentation of the results of schematic calculations, which furnish a guideline for microscopic investigations, we discuss the relevance of our approach for studying multifragmentation. Once the limitations of this kind of dynamical simulations exhibited, we perform a detailed analysis in terms of the equation of state of the system. In agreement with schematic models we find that the composite nuclear system formed in the collision actually explodes when it stays long enough in the mechanically unstable region (spinodal region). Quantitative estimates of the explosion threshold are given for central symmetric reactions (Ca + Ca and Ar + Ti). The link of the results with transport properties and the equation of state of nuclear matter are briefly discussed

  14. CANDU nuclear power system

    International Nuclear Information System (INIS)

    1981-01-01

    This report provides a summary of the components that make up a CANDU reactor. Major emphasis is placed on the CANDU 600 MW(e) design. The reasons for CANDU's performance and the inherent safety of the system are also discussed

  15. Development of nuclear material accountancy control system

    International Nuclear Information System (INIS)

    Hirosawa, Naonori; Kashima, Sadamitsu; Akiba, Mitsunori

    1992-01-01

    PNC is developing a wide area of nuclear fuel cycle. Therefore, much nuclear material with a various form exists at each facility in the Works, and the controls of the inventory changes and the physical inventories of nuclear material are important. Nuclear material accountancy is a basic measure in safeguards system based on Non-Proliferation Treaty (NPT). In the light of such importance of material accountancy, the data base of nuclear material control and the material accountancy report system for all facilities has been developed by using the computer. By this system, accountancy report to STA is being presented certainly and timely. Property management and rapid corresponding to various inquiries can be carried out by the data base system which has free item searching procedure. (author)

  16. 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)

  17. Dynamic flowgraph modeling of process and control systems of a nuclear-based hydrogen production plant

    Energy Technology Data Exchange (ETDEWEB)

    Al-Dabbagh, Ahmad W. [Faculty of Engineering and Applied Science, University of Ontario Institute of Technology, 2000 Simcoe Street North, Oshawa, Ontario (Canada); Lu, Lixuan [Faculty of Energy Systems and Nuclear Science, Faculty of Engineering and Applied Science, University of Ontario Institute of Technology, 2000 Simcoe Street North, Oshawa, Ontario (Canada)

    2010-09-15

    Modeling and analysis of system reliability facilitate the identification of areas of potential improvement. The Dynamic Flowgraph Methodology (DFM) is an emerging discrete modeling framework that allows for capturing time dependent behaviour, switching logic and multi-state representation of system components. The objective of this research is to demonstrate the process of dynamic flowgraph modeling of a nuclear-based hydrogen production plant with the copper-chlorine (Cu-Cl) cycle. Modeling of the thermochemical process of the Cu-Cl cycle in conjunction with a networked control system proposed for monitoring and control of the process is provided. This forms the basis for future component selection. (author)

  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)

    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)

  19. Scenario-based roadmapping assessing nuclear technology development paths for future nuclear energy system scenarios

    International Nuclear Information System (INIS)

    Van Den Durpel, Luc; Roelofs, Ferry; Yacout, Abdellatif

    2009-01-01

    Nuclear energy may play a significant role in a future sustainable energy mix. The transition from today's nuclear energy system towards a future more sustainable nuclear energy system will be dictated by technology availability, energy market competitiveness and capability to achieve sustainability through the nuclear fuel cycle. Various scenarios have been investigated worldwide each with a diverse set of assumptions on the timing and characteristics of new nuclear energy systems. Scenario-based roadmapping combines the dynamic scenario-analysis of nuclear energy systems' futures with the technology roadmap information published and analysed in various technology assessment reports though integrated within the nuclear technology roadmap Nuclear-Roadmap.net. The advantages of this combination is to allow mutual improvement of scenario analysis and nuclear technology roadmapping providing a higher degree of confidence in the assessment of nuclear energy system futures. This paper provides a description of scenario-based roadmapping based on DANESS and Nuclear-Roadmap.net. (author)

  20. A probabilistic approach to safety/reliability of space nuclear power systems

    International Nuclear Information System (INIS)

    Medford, G.; Williams, K.; Kolaczkowski, A.

    1989-01-01

    An ongoing effort is investigating the feasibility of using probabilistic risk assessment (PRA) modeling techniques to construct a living model of a space nuclear power system. This is being done in conjunction with a traditional reliability and survivability analysis of the SP-100 space nuclear power system. The initial phase of the project consists of three major parts with the overall goal of developing a top-level system model and defining initiating events of interest for the SP-100 system. The three major tasks were performing a traditional survivability analysis, performing a simple system reliability analysis, and constructing a top-level system fault-tree model. Each of these tasks and their interim results are discussed in this paper. Initial results from the study support the conclusion that PRA modeling techniques can provide a valuable design and decision-making tool for space reactors. The ability of the model to rank and calculate relative contributions from various failure modes allows design optimization for maximum safety and reliability. Future efforts in the SP-100 program will see data development and quantification of the model to allow parametric evaluations of the SP-100 system. Current efforts have shown the need for formal data development and test programs within such a modeling framework

  1. Establishment of nuclear data system

    International Nuclear Information System (INIS)

    Chang, Jong Hwa; Kim, J. D.; Oh, S. Y.; Lee, Y. O.; Gil, C. S.; Cho, Y. S.

    1997-01-01

    Fission fragment data have been collected and added to the existing nuclear database system. A computer program was written for generating on-line graphs of energy-dependent neutron reaction cross section. This program deals with about 300 major nuclides and serves on the internet. As a part of nuclear data evaluation works, the covariance data for neutron cross section of structural nuclides were evaluated. Also the elastic and inelastic cross sections were evaluated by using ABAREX and EGNASH2 code. In the field of nuclear data processing, a cross section library for TWODANT code for liquid metal reactor was generated and validated against Russian and French critical reactors. The resonance data for Pu-242 in CASMO-3 library were updated. In addition, continuous-energy libraries for MCNP were generated from ENDF/B-VI.2, JEF-2.2 and JENDL-3.2. These libraries were validated against the results from a series of critical experiments at HANARO. (author). 87 refs., 29 tabs., 23 figs

  2. Nuclear steam supply system and method of installation

    International Nuclear Information System (INIS)

    Tower, S.N.; Christenson, J.A.; Braun, H.E.

    1989-01-01

    This patent describes a method of providing a nuclear reactor power plant at a predetermined use site accessible by predetermined navigable waterways. The method is practiced with apparatus including a nuclear reactor system. The system has a nuclear steam-supply section. The method consists of: constructing a nuclear reactor system at a manufacturing site remote from the predetermined use site but accessible to the predetermined waterways for transportation from the manufacturing site to the predetermined use site, the nuclear reactor system including a barge with the nuclear steam supply section constructed integrally with the barge. Simultaneously with the construction of the nuclear reactor system, constructing facilities at the use site to be integrated with the nuclear reactor system to form the nuclear-reactor power plant; transporting the nuclear reactor system along the waterways to the predetermined use site; at the use site joining the removal parts of the altered nuclear reactor system to the remainder of the altered nuclear reactor system to complete the nuclear reactor system; and installing the nuclear reactor system at the predetermined use site and integrating the nuclear reactor system to interact with the facilities constructed at the predetermined use site to form the nuclear-reactor power plant

  3. CASKETSS: a computer code system for thermal and structural analysis of nuclear fuel shipping casks

    International Nuclear Information System (INIS)

    Ikushima, Takeshi

    1989-02-01

    A computer program CASKETSS has been developed for the purpose of thermal and structural analysis of nuclear fuel shipping casks. CASKETSS measn a modular code system for CASK Evaluation code system Thermal and Structural Safety. Main features of CASKETSS are as follow; (1) Thermal and structural analysis computer programs for one-, two-, three-dimensional geometries are contained in the code system. (2) Some of the computer programs in the code system has been programmed to provide near optimal speed on vector processing computers. (3) Data libralies fro thermal and structural analysis are provided in the code system. (4) Input data generator is provided in the code system. (5) Graphic computer program is provided in the code system. In the paper, brief illustration of calculation method, input data and sample calculations are presented. (author)

  4. MITEE: A new nuclear engine concept for ultra fast, lightweight solar system exploration missions

    Science.gov (United States)

    Powell, James; Paniagua, John; Ludewig, Hans; Maise, George; Todosow, Michael

    1998-01-01

    A new ultra compact nuclear engine concept, MITEE (MIniature R_eactor E_nginE_), is described, and its performance evaluated for various solar system exploration missions. The MITEE concept is based on the Particle Bed Reactor (PBR), with modifications that enable a smaller, lighter nuclear engine. A range of MITEE Engine designs is described. Representative design parameters for the baseline MITEE reactor are: 75MW(th) power level, 1000 second Isp, 100 kilogram mass, 10 MW/Liter fuel element power density, 39 cm core diameter/height. Total engine mass, including turbo pump assembly, nozzles, controls, and contingency, is estimated to be 200 kilograms. Using the MITEE engine, ultra fast, lightweight solar system exploration missions are enabled. A range of such missions has been analyzed using the MULIMP code, and are described.

  5. Development of an information systems to manage the fuel elements of a nuclear reactor

    International Nuclear Information System (INIS)

    Neira Orellana, Alicia Cristina

    1999-01-01

    The development of a computerized information system is presented that administers the fuel elements of a nuclear reactor. This system automates the mathematical calculations of the nuclear reactor's configuration, which have been manually controlled for many years, and it also manages the inventory of these elements for each one of the different deposits of nuclear materials. This system was designed and built based on an Object Oriented Focus (OOF), which fully meets the requirements requested and aims to facilitate the interaction between the user and the machine. The OOF methodology is based on that proposed by Peter Coad and Edward Yourdon and the development tool used is DELPHI version 3.0 (object oriented programming graphics tool that uses Pascal Object language and a Windows '98 platform). To implement the prepared tool the different stages as indicated by the authors of the above-mentioned methodology were carried out step by step, concluding with the practical benefits associated with the use of the proposed focus. A Graphic Interactive Tool is obtained that will be used in part by the people who directly operate the nuclear reactor and who do the mathematical calculations for the configuration of its nucleus. The system will allow them to considerably reduce the time needed for administering the fuel elements with the automated configuration of the operating cycle. The importance of the combination of these elements varies depending on experimental needs. All those processes linked to the configuration of the nucleus are very important, particularly the calculation of fuel element wear (burned) and the coefficient calculation that validates this configuration. These processes were used during the development of this thesis work. The system also manages an inventory of all the elements with their respective histories, facilitating follow-ups and analyses (C.W)

  6. Modeling Chilled-Water Storage System Components for Coupling to a Small Modular Reactor in a Nuclear Hybrid Energy System

    Science.gov (United States)

    Misenheimer, Corey Thomas

    The intermittency of wind and solar power puts strain on electric grids, often forcing carbonbased and nuclear sources of energy to operate in a load-follow mode. Operating nuclear reactors in a load-follow fashion is undesirable due to the associated thermal and mechanical stresses placed on the fuel and other reactor components. Various Thermal Energy Storage (TES) elements and ancillary energy applications can be coupled to nuclear (or renewable) power sources to help absorb grid instabilities caused by daily electric demand changes and renewable intermittency, thereby forming the basis of a candidate Nuclear Hybrid Energy System (NHES). During the warmer months of the year in many parts of the country, facility air-conditioning loads are significant contributors to the increase in the daily peak electric demand. Previous research demonstrated that a stratified chilled-water storage tank can displace peak cooling loads to off-peak hours. Based on these findings, the objective of this work is to evaluate the prospect of using a stratified chilled-water storage tank as a potential TES reservoir for a nuclear reactor in a NHES. This is accomplished by developing time-dependent models of chilled-water system components, including absorption chillers, cooling towers, a storage tank, and facility cooling loads appropriate for a large office space or college campus, as a callable FORTRAN subroutine. The resulting TES model is coupled to a high-fidelity mPower-sized Small Modular Reactor (SMR) Simulator, with the goal of utilizing excess reactor capacity to operate several sizable chillers in order to keep reactor power constant. Chilled-water production via single effect, lithium bromide (LiBr) absorption chillers is primarily examined in this study, although the use of electric chillers is briefly explored. Absorption chillers use hot water or low-pressure steam to drive an absorption-refrigeration cycle. The mathematical framework for a high-fidelity dynamic

  7. Development of a consensus standard for verification and validation of nuclear system thermal-fluids software

    International Nuclear Information System (INIS)

    Harvego, Edwin A.; Schultz, Richard R.; Crane, Ryan L.

    2011-01-01

    With the resurgence of nuclear power and increased interest in advanced nuclear reactors as an option to supply abundant energy without the associated greenhouse gas emissions of the more conventional fossil fuel energy sources, there is a need to establish internationally recognized standards for the verification and validation (V and V) of software used to calculate the thermal–hydraulic behavior of advanced reactor designs for both normal operation and hypothetical accident conditions. To address this need, ASME (American Society of Mechanical Engineers) Standards and Certification has established the V and V 30 Committee, under the jurisdiction of the V and V Standards Committee, to develop a consensus standard for verification and validation of software used for design and analysis of advanced reactor systems. The initial focus of this committee will be on the V and V of system analysis and computational fluid dynamics (CFD) software for nuclear applications. To limit the scope of the effort, the committee will further limit its focus to software to be used in the licensing of High-Temperature Gas-Cooled Reactors. Although software verification will be an important and necessary part of the standard, much of the initial effort of the committee will be focused on the validation of existing software and new models that could be used in the licensing process. In this framework, the Standard should conform to Nuclear Regulatory Commission (NRC) and other regulatory practices, procedures and methods for licensing of nuclear power plants as embodied in the United States (U.S.) Code of Federal Regulations and other pertinent documents such as Regulatory Guide 1.203, “Transient and Accident Analysis Methods” and NUREG-0800, “NRC Standard Review Plan”. In addition, the Standard should be consistent with applicable sections of ASME NQA-1-2008 “Quality Assurance Requirements for Nuclear Facility Applications (QA)”. This paper describes the general

  8. Future development of nuclear energy systems

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2001-03-01

    Nuclear energy development in Japan has passed about 30 years, and reaches to a step to supply about 35 % of total electric power demand. However, together with globalization of economic and technical development, its future progressing method is required for its new efforts. Among such conditions, when considering a state of future type nuclear energy application, its contribution to further environmental conservation and international cooperation is essential, and it is required for adoption to such requirement how it is made an energy source with excellent economics.The Research Committee on 'Engineering Design on Nuclear Energy Systems' established under recognition in 1998 has been carried out some discussions on present and future status of nuclear energy development. And so forth under participation of outer specialists. Here were summarized on two year's committee actions containing them and viewpoints of nuclear industries, popularization of nuclear system technology, and so forth. (G.K.)

  9. Generating a quality management system for application in the field of management of nuclear energy area

    International Nuclear Information System (INIS)

    Fernández, L.; Arias, M.

    2013-01-01

    The actual work has as a main objective to present the development of a quality management system to be applicable to the Nuclear Energy Management confines at the National Atomic Energy Commission (CNEA) in Argentina Republic. The GAEN Quality Management Section (SGC) has as main central tasks to streamline, collaborate and facilitate the development of activities and their applications on quality management systems in all the sections and projects belonging to GAEN. This achievement will tend to accredit, certificate and qualify them. Groups of work cooperating with each other integrate the GAEN. They are at present dealing with several tasks. Some outstanding ones are research activities, technology development, design, engineering, assembling, starting, services, and human resources development on Nuclear Reactors and Nuclear Supplies, particularly on powerful nuclear reactors. In 2012, at the annual CNEA Presidential meeting, it was presented one of the several projects from the SGC. It consists in the development of a quality management system available to every area belonging to the GAEN. To carry this project out, it was first begun with the elaboration of Guide Documents which were available for everybody. The documents establish the criteria and general requirements for obtaining guaranteed quality results about the performed activities. At the same time, several areas, sections and Management groups of work have been working united and well-disposed towards the application on their own Management System using the Guide Documents and considering, in addition, some own regards. In conclusion, this first step shows that the developed work facilitates the implementation of Management Systems around the GAEN. (author)

  10. Institutional interactions in developing a transportation system under the Nuclear Waste Policy Act

    International Nuclear Information System (INIS)

    Denny, S.H.

    1986-01-01

    The Department of Energy (DOE) recognizes that the success of its efforts to develop and operate a system for transporting nuclear waste under the provisions of the Nuclear Waste Policy Act of 1982 (NWPA) depends in large measure on the effectiveness of Departmental interactions with the affected parties. To ensure the necessary network of communication, the DOE is establishing lines of contact with those who are potential participants in the task of developing the policies and procedures for the NWPA transportation system. In addition, a number of measures have been initiated to reinforce broad-based involvement in program development. The Transportation Institutional Plan provides a preliminary road map of DOE's projected interactions over the next decade and is discussed in this paper

  11. Electromagnetic drive of the control and protection system of a nuclear reactor

    International Nuclear Information System (INIS)

    Zav'yalova, G.I.

    1983-01-01

    The design and operating principle of an electromagnetic drive with a linear synchronous reaction motor are described. At the present time, electromagnetic control mechanisms using linear electric motors are finding increasingly widespread application as drives for the control and protection system of nuclear reactors. In these drives there is a functional mergence of the electromagnetic mechanism with the final control element; these drives, therefore, have advantages over electromechanical drives

  12. A study on intelligent nuclear systems (HASP: Human Acts Simulation Program)

    International Nuclear Information System (INIS)

    Asai, Kiyoshi; Fujii, Minoru; Higuchi, Kenji; Kume, Etsuo; Ohtani, Takayuki; Far, B.H.; Kambayashi, Shaw; Akimoto, Masayuki

    1991-06-01

    The fourth year progress of the Human Acts Simulation Program HASP in short, has been presented in this report. The HASP started in 1987 at JAERI as a ten-year research and development program of underlying technologies for intelligent robots, intelligent nuclear plants and so on. It consists of the research and development of technologies of a knowledge-base system, robot vision, robot kinematics/kinetics, plant geometry database, dose evaluation and high speed Monte Carlo machine. (author)

  13. Supersymmetry for nuclear cluster systems

    International Nuclear Information System (INIS)

    Levai, G.; Cseh, J.; Van Isacker, P.

    2001-01-01

    A supersymmetry scheme is proposed for nuclear cluster systems. The bosonic sector of the superalgebra describes the relative motion of the clusters, while its fermionic sector is associated with their internal structure. An example of core+α configurations is discussed in which the core is a p-shell nucleus and the underlying superalgebra is U(4/12). The α-cluster states of the nuclei 20 Ne and 19 F are analysed and correlations between their spectra, electric quadrupole transitions, and one-nucleon transfer reactions are interpreted in terms of U(4/12) supersymmetry. (author)

  14. A systems engineering cost analysis capability for use in assessing nuclear waste management system cost performance

    International Nuclear Information System (INIS)

    Shay, M.R.

    1990-04-01

    The System Engineering Cost Analysis (SECA) capability has been developed by the System Integration Branch of the US Department of Energy's Office of Civilian Radioactive Waste Management for use in assessing the cost performance of alternative waste management system configurations. The SECA capability is designed to provide rapid cost estimates of the waste management system for a given operational scenario and to permit aggregate or detailed cost comparisons for alternative waste system configurations. This capability may be used as an integral part of the System Integration Modeling System (SIMS) or, with appropriate input defining a scenario, as a separate cost analysis model

  15. A rapid and continuous system for immobilization of nuclear material waste by vitrification

    International Nuclear Information System (INIS)

    Shareef, M.U.; Hussain, S.H.; Tufail, M.; Rashid, F.

    2009-01-01

    The nuclear technology has prime importance and backbone for rapid development of medical sciences, industries and in power generation as an alternate source of energy. Despite all these facts there is a major problem which is always associated with nuclear technology, that is, the generation of undesirable radioactive wastes. The radioactive wastes are quite problematic and need major attention for its treatment, conditioning and properly disposal to keep the environmental activities and human ecosystem healthy and safe. There are different large scale methods and processes to treat and dispose off the radioactive wastes. These processes are evaluated and designed by the various world competent and pronounced scientists in the light of rules and safety limits set by IAEA and other regulatory authorities to protect the environment and eventually protect our ecosystem. The research and development work on radioactive waste has been proceeding for the last fifty years but still it is a core issue and a big challenge for the nuclear scientists and radiation workers. In this study a rapid and continuous system for immobilization of nuclear waste into glass matrix by vitrification has been designed. In general treatment methods, Borosilicate glass is preferred because it is efficient, cost effective and rapid to that of other radioactive waste form. In this process the simulated waste is mixed with glass forming material and process for melting to form a glassy substrate in continuous manner. The waste is being converted into vitreous form and encapsulate into a glass matrix. (author)

  16. Composite type nuclear power system

    International Nuclear Information System (INIS)

    Nakamoto, Koichiro.

    1993-01-01

    The present invention realizes a high thermal efficiency by heating steams at the exit of a steam generator of a nuclear power plant to high temperature by a thermal super-heating boiler. That is, a thermal superheating boiler is disposed between the steam generator and a turbogenerator to heat steams from the steam generator and supply them to the turbogenerator. In this case, it may be possible that feedwater superheating boiler pipelines to the steam generator are caused to pass through the thermal superheating boiler so that they also have a performance of heating feedwater. If the system of the present invention is used, it is possible to conduct base load operation by nuclear power and a load following operation by controlling the thermal superheating boiler. Further, a hydrogen producing performance is applied to the thermal superheating boiler to produce hydrogen when electric power load is lowered. An internally sustaining type operation method can be conducted of burning hydrogen by the superheating boiler upon increased electric power load. As a result, a power generation system which has an excellent economical property and can easily cope with the load following operation can be attained. (I.S.)

  17. The disposal of Canada's nuclear fuel waste: comments on the postclosure assessment of a reference system

    International Nuclear Information System (INIS)

    Allan, C.J.; Goodwin, B.W.

    1996-07-01

    Canada, like other countries, is developing technology for disposal of its nuclear fuel waste , based on the concept of geological disposal in stable plutonic rock of the Canadian Shield. The choice of methods, materials, and designs for a disposal system will ultimately be made on the basis of safety, taking into account the characteristics of the specific site on which the facility is to be developed, costs and practicality. As part of its work in developing the technology for the disposal of Canada's nuclear fuel waste, AECL analyzed the performance of a hypothetical disposal facility that incorporates specific design choices for the engineered barriers and that assumes a specific geological setting. This system, comprising the disposal facility and the geological setting, and the results of the performance analysis, is described in an Environmental Impact Statement that AECL submitted in 1994 and in a Primary Reference for the EIS 'The Disposal of Canada's Nuclear Fuel Waste: Postclosure Assessment of a Reference System.' The performance analysis was not intended to be a general proof of the safety of disposal, but rather it presents a safety analysis of one specific system to illustrate the postclosure assessment methodology and to demonstrate that safety could be achieved for the system in question. Although the design of the disposal facility analyzed and the geological setting have specific features, the results obtained from the safety analysis can, however, be used to provide considerable insight into the performance of the various components that comprise the multibarrier geological disposal system. Moreover, the results can show how changes in the performance of specific components can affect the overall performance of the system. This report discusses these aspects of the postclosure analysis. (author)

  18. A new generation scanning system for the high-speed analysis of nuclear emulsions

    Science.gov (United States)

    Alexandrov, A.; Buonaura, A.; Consiglio, L.; D'Ambrosio, N.; De Lellis, G.; Di Crescenzo, A.; Galati, G.; Lauria, A.; Montesi, M. C.; Tioukov, V.; Vladymyrov, M.

    2016-06-01

    The development of automatic scanning systems was a fundamental issue for large scale neutrino detectors exploiting nuclear emulsions as particle trackers. Such systems speed up significantly the event analysis in emulsion, allowing the feasibility of experiments with unprecedented statistics. In the early 1990s, R&D programs were carried out by Japanese and European laboratories leading to automatic scanning systems more and more efficient. The recent progress in the technology of digital signal processing and of image acquisition allows the fulfillment of new systems with higher performances. In this paper we report the description and the performance of a new generation scanning system able to operate at the record speed of 84 cm2/hour and based on the Large Angle Scanning System for OPERA (LASSO) software infrastructure developed by the Naples scanning group. Such improvement, reduces the scanning time by a factor 4 with respect to the available systems, allowing the readout of huge amount of nuclear emulsions in reasonable time. This opens new perspectives for the employment of such detectors in a wider variety of applications.

  19. A new generation scanning system for the high-speed analysis of nuclear emulsions

    International Nuclear Information System (INIS)

    Alexandrov, A.; Buonaura, A.; Consiglio, L.; Lellis, G. De; Crescenzo, A. Di; Galati, G.; Lauria, A.; Montesi, M.C.; Tioukov, V.; D'Ambrosio, N.; Vladymyrov, M.

    2016-01-01

    The development of automatic scanning systems was a fundamental issue for large scale neutrino detectors exploiting nuclear emulsions as particle trackers. Such systems speed up significantly the event analysis in emulsion, allowing the feasibility of experiments with unprecedented statistics. In the early 1990s, R and D programs were carried out by Japanese and European laboratories leading to automatic scanning systems more and more efficient. The recent progress in the technology of digital signal processing and of image acquisition allows the fulfillment of new systems with higher performances. In this paper we report the description and the performance of a new generation scanning system able to operate at the record speed of 84 cm 2 /hour and based on the Large Angle Scanning System for OPERA (LASSO) software infrastructure developed by the Naples scanning group. Such improvement, reduces the scanning time by a factor 4 with respect to the available systems, allowing the readout of huge amount of nuclear emulsions in reasonable time. This opens new perspectives for the employment of such detectors in a wider variety of applications.

  20. Nuclear detection systems in traffic

    International Nuclear Information System (INIS)

    Farkas, T.; Pernicka, L.; Svec, A.

    2005-01-01

    Illicit trafficking in nuclear materials (nuclear criminality) has become a problem, due to the circulation of a high number of radioactive sources caused by the changes of the organisational infrastructures to supervise these material within the successor states of the former Soviet Union. Aim of this paper is to point out the technical requirements and the practicability of an useful monitoring system at preselected traffic check points (railway and highway border crossings, industrial sites entry gates, international airports). The ITRAP lab test was designed to work as strict benchmark to qualify border monitoring systems 67 with very low false alarm rates, in addition the minimum sensitivity to give an alarm has been defined for fix-installed systems, pocket type and hand held instruments. For the neutron tests a special prepared Californium source ( 252 Cf) was used to simulate the weapons plutonium. The source is shielded against gamma radiation, use a moderator and provides the required neutron rate of 20000 n/s at 2 rn distance. To test the false alarm rate (rate of false positive ) the same test facility , under the same background conditions, was used but without a radioactive test source. The ITRAP lab tests for the fix-installed systems started at May 1998 and first results were given in September 1998. Only 2 of 14 fix-installed monitoring systems could fulfil the minimum requirement for neutron detection. 7 of 14 fix-installed monitoring systems (50%) passed the ITRAP lab test. The analytical method developed and used for certification of installed radiation monitors in the Slovak Institute of Metrology consists in measurement of radiation activity of selected radionuclide in defined conditions. (authors)

  1. A formal design verification and validation on the human factors of a computerized information system in nuclear power plants

    International Nuclear Information System (INIS)

    Lee, Yong Hee; Park, Jae Chang; Cheon, Se Woo; Jung, Kwang Tae; Baek, Seung Min; Han, Seung; Park, Hee Suk; Son, Ki Chang; Kim, Jung Man; Jung Yung Woo

    1999-11-01

    This report describe a technical transfer under the title of ''A formal design verification and validation on the human factors of a computerized information system in nuclear power plants''. Human factors requirements for the information system designs are extracted from various regulatory and industrial standards and guidelines, and interpreted into a more specific procedures and checklists for verifying the satisfaction of those requirements. A formalized implementation plan is established for human factors verification and validation of a computerized information system in nuclear power plants. Additionally, a Computer support system, named as DIMS-web (design Issue Management System), is developed based upon web internet environment so as to enhance the implementation of the human factors activities. DIMS-Web has three maine functions: supporting requirements review, tracking design issues, and management if issues screening evaluation. DIMS-Web shows its benefits in practice through a trial application to the design review of CFMS for YGN nuclear unit 5 and 6. (author)

  2. Integrated engineering system for nuclear facilities building

    International Nuclear Information System (INIS)

    Tomura, H.; Miyamoto, A.; Futami, F.; Yasuda, S.; Ohtomo, T.

    1995-01-01

    In the construction of buildings for nuclear facilities in Japan, construction companies are generally in charge of the building engineering work, coordinating with plant engineering. An integrated system for buildings (PROMOTE: PROductive MOdeling system for Total nuclear Engineering) described here is a building engineering system including the entire life cycle of buildings for nuclear facilities. A Three-dimensional (3D) building model (PRO-model) is to be in the core of the system (PROMOTE). Data sharing in the PROMOTE is also done with plant engineering systems. By providing these basic technical foundations, PROMOTE is oriented toward offering rational, highquality engineering for the projects. The aim of the system is to provide a technical foundation in building engineering. This paper discusses the characteristics of buildings for nuclear facilities and the outline of the PROMOTE. (author)

  3. Design of a fault diagnosis system for next generation nuclear power plants

    International Nuclear Information System (INIS)

    Zhao, K.; Upadhyaya, B.R.; Wood, R.T.

    2004-01-01

    A new design approach for fault diagnosis is developed for next generation nuclear power plants. In the nuclear reactor design phase, data reconciliation is used as an efficient tool to determine the measurement requirements to achieve the specified goal of fault diagnosis. In the reactor operation phase, the plant measurements are collected to estimate uncertain model parameters so that a high fidelity model can be obtained for fault diagnosis. The proposed algorithm of fault detection and isolation is able to combine the strength of first principle model based fault diagnosis and the historical data based fault diagnosis. Principal component analysis on the reconciled data is used to develop a statistical model for fault detection. The updating of the principal component model based on the most recent reconciled data is a locally linearized model around the current plant measurements, so that it is applicable to any generic nonlinear systems. The sensor fault diagnosis and process fault diagnosis are decoupled through considering the process fault diagnosis as a parameter estimation problem. The developed approach has been applied to the IRIS helical coil steam generator system to monitor the operational performance of individual steam generators. This approach is general enough to design fault diagnosis systems for the next generation nuclear power plants. (authors)

  4. Developing and setting up of a nuclear medicine information management system

    International Nuclear Information System (INIS)

    Baghel, N.S.; Asopa, R.; Nayak, U.N.; Rajan, M.G.R.; Subhalakshmi, P.V.; Shailaja, A.; Rajashekharrao, B.; Karunanidhi, Y.R.

    2010-01-01

    Full text: With the advent and progress of information technology in the present decade, high-performance networks are being installed in hospitals to implement an effective and reliable Hospital Information Management Systems (HIMS). The Radiation Medicine Centre (RMC), is one of the earliest and largest nuclear medicine centres in India and several thousand patients undergo diagnostic as well as therapeutic procedures with different radiopharmaceuticals. The evolution towards a fully digital department of nuclear medicine is driven by expectations of not only improved patient management but also a well-defined workflow along with prompt and quality patient services. The aim was to develop and set up a practical and utility based Nuclear Medicine Information Management System (NMIMS) for various functional procedures at RMC. A customised NMIMS is developed with M/s ECIL using ASP.NET and SQL server technology facilitated by an IBM x3650 M3 Server, 18 thin-clients/desktop PCs and Windows 2008 server operating system and MS-SQL 2005 server software. The various modules have been developed to meet the requirements of different activities pertaining to patient appointment and scheduling, clinical assessment, radiopharmacy procedures, imaging and non-imaging studies and protocols, in-vitro laboratory tests, in-patient and out-patient treatment procedures, radiation protection and regulatory aspects and other routine operational procedures associated with patient management at RMC. The menus are developed as per scheduled workflow (SWF) in the department. The various aspects of SWF have been designed to ensure smooth, easy and trouble free patient management. Presently, the NMIMS has been developed excluding imaging data and we are in the process of setting up Picture Archiving Communication System (PACS) integrated to the existing database system, which will archive and facilitate imaging data in DICOM format in order to make a paperless department. The developed NMIMS

  5. Operating experience with a VMEbus multiprocessor system for data acquisition and reduction in nuclear physics

    International Nuclear Information System (INIS)

    Kutt, P.H.; Balamuth, D.P.

    1989-01-01

    A multiprocessor system based on commercially available VMEbus components has been developed for the acquisition and reduction of event-mode data in nuclear physics experiments. The system contains seven 68000 CPU's and 14 MB of memory. A minimal operating system handles data transfer and task allocation, and a compiler for a specially designed event analysis language produces code for the processors. The system has been in operation for four years at the University of Pennsylvania Tandem Accelerator Laboratory. Computation rates over 3 times that of a MicroVAX II have been achieved at a fraction of the cost. The use of WORM optical disks for event recording allows the processing for gigabyte data sets without operator intervention. A more powerful system is being planned which will make use of recently developed RISC processors to obtain an order of magnitude increase in computing power per node

  6. Investigation of pressure transients in nuclear filtration systems: construction details of a large shock tube

    International Nuclear Information System (INIS)

    Smith, P.R.; Gregory, W.S.

    1980-04-01

    This report documents the construction of a 0.914-m (36-in.)-dia. shock tube on the New Mexico State University caompus. Highly variable low-grade explosions can be simulated with the shock tube. We plan to investigate the response of nuclear facility ventilation system components to low-grade explosions. Components of particular interest are high-capacity, high efficiency paticulate air (HEPA) filters. Shock tube construction details, operating principles, firing sequence, and preliminary results are reported

  7. DIMCO. A new system for mechanical and bidimensional of nuclear fuel pins

    International Nuclear Information System (INIS)

    Moreno, A.

    1977-01-01

    The system developed in JEN, for: the mechanical analysis uni and bidimensional, of nuclear fuels is presented. The mathematical and numerical foundations used, are here described. And so the models developed for effects such as swelling, cracking, clad growth etc. Numerical results for several cases are presented. a) Numerical test in one and two dimensions. b) Applicability range, c) Interaction effects. d) Influence of the power history. (Author) 17 refs

  8. NJOY nuclear data processing system: user's manual

    International Nuclear Information System (INIS)

    MacFarlane, R.E.; Barrett, R.J.; Muir, D.W.; Boicourt, R.M.

    1978-12-01

    The NJOY nuclear data processing system is a comprehensive computer code package for producing cross sections for neutron and photon transport calculations from ENDF/B-IV and -V evaluated nuclear data. This user's manual provides a concise description of the code, input instructions, sample problems, and installation instructions. 1 figure, 3 tables

  9. Thermodynamic analysis and optimization of a Closed Regenerative Brayton Cycle for nuclear space power systems

    International Nuclear Information System (INIS)

    Ribeiro, Guilherme B.; Braz Filho, Francisco A.; Guimarães, Lamartine N.F.

    2015-01-01

    Nuclear power systems turned to space electric propulsion differ strongly from usual ground-based power systems regarding the importance of overall size and mass. For propulsion power systems, size and mass are essential drivers that should be minimized during conception processes. Considering this aspect, this paper aims the development of a design-based model of a Closed Regenerative Brayton Cycle that applies the thermal conductance of the main components in order to predict the energy conversion performance, allowing its use as a preliminary tool for heat exchanger and radiator panel sizing. The centrifugal-flow turbine and compressor characterizations were achieved using algebraic equations from literature data. A binary mixture of Helium–Xenon with molecular weight of 40 g/mole is applied and the impact of the components sizing in the energy efficiency is evaluated in this paper, including the radiator panel area. Moreover, an optimization analysis based on the final mass of heat the exchangers is performed. - Highlights: • A design-based model of a Closed Brayton Cycle is proposed for nuclear space needs. • Turbomachinery efficiency presented a strong influence on the system efficiency. • Radiator area presented the highest potential to increase the system efficiency. • There is maximum system efficiency for each total mass of heat exchangers. • Size or efficiency optimization was performed by changing heat exchanger proportion.

  10. Geochemical modeling of the nuclear-waste repository system. A status report

    International Nuclear Information System (INIS)

    Deutsch, W.J.

    1980-12-01

    The primary objective of the geochemical modeling task is to develop an understanding of the waste-repository geochemical system and provide a valuable tool for estimating future states of that system. There currently exists a variety of computer codes which can be used in geochemical modeling studies. Some available codes contain the framework for simulating a natural chemical system and estimating, within limits, the response of that system to environmental changes. By data-base enhancement and code development, this modeling technique can be even more usefully applied to a nuclear-waste repository. In particular, thermodynamic data on elements not presently in the data base but identified as being of particular hazard in the waste-repository system, need to be incorporated into the code to estimate the near-field as well as the far-field reactions during a hypothetical breach. A reaction-path-simulation code, which estimates the products of specific rock/water reactions, has been tested using basalt and ground water. Results show that the mass-transfer capabilities of the code will be useful in chemical-evolution studies and scenario analyses. The purpose of this report is to explain the status of geochemical modeling as it currently applies to the chemical system of a hypothetical nuclear-waste repository in basalt and to present the plan proposed for further developmet and application

  11. A dependability modeling of software under hardware faults digitized system in nuclear power plants

    International Nuclear Information System (INIS)

    Choi, Jong Gyun

    1996-02-01

    An analytic approach to the dependability evaluation of software in the operational phase is suggested in this work with special attention to the physical fault effects on the software dependability : The physical faults considered are memory faults and the dependability measure in question is the reliability. The model is based on the simple reliability theory and the graph theory with the path decomposition micro model. The model represents an application software with a graph consisting of nodes and arcs that probabilistic ally determine the flow from node to node. Through proper transformation of nodes and arcs, the graph can be reduced to a simple two-node graph and the software failure probability is derived from this graph. This model can be extended to the software system which consists of several complete modules without modification. The derived model is validated by the computer simulation, where the software is transformed to a probabilistic control flow graph. Simulation also shows a different viewpoint of software failure behavior. Using this model, we predict the reliability of an application software and a software system in a digitized system(ILS system) in the nuclear power plant and show the sensitivity of the software reliability to the major physical parameters which affect the software failure in the normal operation phase. The derived model is validated by the computer simulation, where the software is transformed to a probabilistic control flow graph. Simulation also shows a different viewpoint of software failure behavior. Using this model, we predict the reliability of an application software and a software system in a digitized system (ILS system) is the nuclear power plant and show the sensitivity of the software reliability to the major physical parameters which affect the software failure in the normal operation phase. This modeling method is particularly attractive for medium size programs such as software used in digitized systems of

  12. Study on HVAC system in nuclear facility

    International Nuclear Information System (INIS)

    Baeg, S. Y.; Song, W. S.; Oh, Y. O.; Ju, Y. S.; Hong, K. P.

    2003-01-01

    Heating, Ventilation and Air Conditioning (HVAC) system in nuclear facility should be equipped and constructed more stable and allowable than that in common facility. The purpose of HVAC system is the maintenance of optimum working environment, the protection of worker against a contaminated air and the prevention of atmospheric contamination due to an outward ventilation, etc.. The basic scheme of a safety operation of nuclear facility is to prevent the atmospheric contamination even in low level. The adaptability of HVAC system which is in operation. In this study, the design requirements of HVAC system in nuclear facility and the HVAC systems in foreign countries are reviewed, and the results can be utilized in the design of HVAC system in nuclear facility

  13. Decision support systems in nuclear emergencies: A scenario-based comparison of domestic and reference tools

    International Nuclear Information System (INIS)

    Vamanu, D.; Slavnicu, S. D.; Slavnicu, E.; Vamanu, B.

    2004-01-01

    The article reports selective results of a comparison between RODOS - an emerging decision support system for the management of nuclear emergencies in Europe developed by an international research consortium under EEC aegis, and a resident software package developed and maintained for similar purposes at IFIN-HH, Bucharest. Reproducible similarity patterns obtained in the output data distributions provide for simple normalising procedures that may ensure convergent radiological assessments. When properly consolidated on a sufficient scenario casuistry, such procedures could lend a certain resilience to domestic decision support tools over the interim lead time required by the full implementation of RODOS, or other major league, internationally accepted reference systems. (authors)

  14. A Systems Engineering Framework for Design, Construction and Operation of the Next Generation Nuclear Plant

    International Nuclear Information System (INIS)

    Edward J. Gorski; Charles V. Park; Finis H. Southworth

    2004-01-01

    Not since the International Space Station has a project of such wide participation been proposed for the United States. Ten countries, the European Union, universities, Department of Energy (DOE) laboratories, and industry will participate in the research and development, design, construction and/or operation of the fourth generation of nuclear power plants with a demonstration reactor to be built at a DOE site and operational by the middle of the next decade. This reactor will be like no other. The Next Generation Nuclear Plant (NGNP) will be passively safe, economical, highly efficient, modular, proliferation resistant, and sustainable. In addition to electrical generation, the NGNP will demonstrate efficient and cost effective generation of hydrogen to support the President's Hydrogen Initiative. To effectively manage this multi-organizational and technologically complex project, systems engineering techniques and processes will be used extensively to ensure delivery of the final product. The technological and organizational challenges are complex. Research and development activities are required, material standards require development, hydrogen production, storage and infrastructure requirements are not well developed, and the Nuclear Regulatory Commission may further define risk-informed/performance-based approach to licensing. Detailed design and development will be challenged by the vast cultural and institutional differences across the participants. Systems engineering processes must bring the technological and organizational complexity together to ensure successful product delivery. This paper will define the framework for application of systems engineering to this $1.5B - $1.9B project

  15. Nuclear material statistical accountancy system

    International Nuclear Information System (INIS)

    Argentest, F.; Casilli, T.; Franklin, M.

    1979-01-01

    The statistical accountancy system developed at JRC Ispra is refered as 'NUMSAS', ie Nuclear Material Statistical Accountancy System. The principal feature of NUMSAS is that in addition to an ordinary material balance calcultation, NUMSAS can calculate an estimate of the standard deviation of the measurement error accumulated in the material balance calculation. The purpose of the report is to describe in detail, the statistical model on wich the standard deviation calculation is based; the computational formula which is used by NUMSAS in calculating the standard deviation and the information about nuclear material measurements and the plant measurement system which are required as data for NUMSAS. The material balance records require processing and interpretation before the material balance calculation is begun. The material balance calculation is the last of four phases of data processing undertaken by NUMSAS. Each of these phases is implemented by a different computer program. The activities which are carried out in each phase can be summarised as follows; the pre-processing phase; the selection and up-date phase; the transformation phase, and the computation phase

  16. Multitudes of Stable States in a Periodically Driven Electron-Nuclear Spin System in a Quantum Dot

    OpenAIRE

    Korenev, V. L.

    2010-01-01

    The periodical modulation of circularly polarized light with a frequency close to the electron spin resonance frequency induces a sharp change of the single electron spin orientation. Hyperfine interaction provides a feedback, thus fixing the precession frequency of the electron spin in the external and the Overhauser field near the modulation frequency. The nuclear polarization is bidirectional and the electron-nuclear spin system (ENSS) possesses a few stable states. A similar frequency-loc...

  17. A risk-based review of Instrument Air systems at nuclear power plants

    International Nuclear Information System (INIS)

    DeMoss, G.; Lofgren, E.; Rothleder, B.; Villeran, M.; Ruger, C.

    1990-01-01

    The broad objective of this analysis was to provide risk-based information to help focus regulatory actions related to Instrument Air (IA) systems at operating nuclear power plants. We first created an extensive data base of summarized and characterized IA-related events that gave a qualitative indication of the nature and severity of these events. Additionally, this data base was used to calculate the frequencies of certain events, which were used in the risk analysis. The risk analysis consisted of reviewing published PRAs and NRC Accident Sequence Precursor reports for IA-initiated accident sequences, IA interactions with frontline systems, and IA-related risk significant events. Sensitivity calculations were performed when possible. Generically, IA was found to contribute less to total risk than many safety systems; however, specific design weaknesses in safety systems, non-safety systems, and the IA system were found to be significant in risk. 22 refs., 13 figs., 24 tabs

  18. Development of a remote monitoring and control system for nuclear power plants

    International Nuclear Information System (INIS)

    Lee, Seung Jun; Kim, Jong Hyun; Seong, Poong Hyun

    2002-01-01

    Nuclear Power Plants (NPPs) will be highly connected network enabled system and need to be monitored and controlled round the clock for high safety and availability. Using the network and web enabled tools, NPPs can be monitored remotely by operators at anytime from any place connected to the network via a general web browser. However, there are security and performance issues associated with such tools, as will be further discussed further. We developed a web-based Remote Monitoring and Control System (RMCS) that uses prevalent web technology. This work, as a preliminary study, performed the conceptual design of the web-based RMCS and developed the prototype

  19. A study on emergency preparedness for nuclear power plant/ Establishment of emergency communication network system

    International Nuclear Information System (INIS)

    Yang, Y. K.; Jung, Y. D.; Kim, S. Y.

    1991-12-01

    The objective of this study was to develop an emergency database search system for nuclear power plants during nuclear incidents / accidents. Image data reported from nuclear power plants to the regulatory body and other related data will be stored systematically in the computer. The data will be utilized during nuclear emergency to prevent the accident from spreading out and to minimize its effect. It will also be used in exchanging information on accident or incidents with the foreign countries. The operational documents in the Kori-4 nuclear power plant are used as the major source for the categorization and analysis in performing this research. It was not easy to access the detailed operational data due to its unique characteric for the security. Therefore, we strongly suggest to increase manpower for this project in Korea Institute of Nuclear Safety (KINS) and archive involvement from Korea Electric Power Company to establish better database retrieval system

  20. A study on emergency preparedness for nuclear power plant/ Establishment of emergency communication network system

    Energy Technology Data Exchange (ETDEWEB)

    Yang, Y K; Jung, Y D; Kim, S Y [Korea Institute of Science and Technology, Seoul (Korea, Republic of)

    1991-12-15

    The objective of this study was to develop an emergency database search system for nuclear power plants during nuclear incidents / accidents. Image data reported from nuclear power plants to the regulatory body and other related data will be stored systematically in the computer. The data will be utilized during nuclear emergency to prevent the accident from spreading out and to minimize its effect. It will also be used in exchanging information on accident or incidents with the foreign countries. The operational documents in the Kori-4 nuclear power plant are used as the major source for the categorization and analysis in performing this research. It was not easy to access the detailed operational data due to its unique characteric for the security. Therefore, we strongly suggest to increase manpower for this project in Korea Institute of Nuclear Safety (KINS) and archive involvement from Korea Electric Power Company to establish better database retrieval system.

  1. A Study of Seismic Capacity of Nuclear Equipment with Seismic Isolation System

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Min Kyu; Choun, Young Sun; Choi, In Kil; Seo, Jeong Moon

    2004-05-15

    In this study, the base isolation systems for equipment are presented and the responses of each isolation system are investigated. As for the base isolation systems, a natural rubber bearing (NRB), a high damping rubber bearing (HDRB) and a friction pendulum system (FPS) are selected. The shaking table tests are carried out for three kinds of structural types. As input motions, artificial time histories enveloping the US NRC RG 1.60 spectrum and the probability-based scenario earthquake spectra developed for the Korean nuclear power plant site as well as a typical near-fault earthquake record are used. Uniaxial, biaxial, and triaxial excitations are conducted with PGAs of 0.05, 0.1, 0.2 and 0.25g. Acceleration responses are measured at the top of the equipment model and the floors using an accelerometer. The reduction of the seismic forces transmitted to the equipment models are determined for different isolation systems and input motions.

  2. A Study of Seismic Capacity of Nuclear Equipment with Seismic Isolation System

    International Nuclear Information System (INIS)

    Kim, Min Kyu; Choun, Young Sun; Choi, In Kil; Seo, Jeong Moon

    2004-05-01

    In this study, the base isolation systems for equipment are presented and the responses of each isolation system are investigated. As for the base isolation systems, a natural rubber bearing (NRB), a high damping rubber bearing (HDRB) and a friction pendulum system (FPS) are selected. The shaking table tests are carried out for three kinds of structural types. As input motions, artificial time histories enveloping the US NRC RG 1.60 spectrum and the probability-based scenario earthquake spectra developed for the Korean nuclear power plant site as well as a typical near-fault earthquake record are used. Uniaxial, biaxial, and triaxial excitations are conducted with PGAs of 0.05, 0.1, 0.2 and 0.25g. Acceleration responses are measured at the top of the equipment model and the floors using an accelerometer. The reduction of the seismic forces transmitted to the equipment models are determined for different isolation systems and input motions

  3. A CAMAC based real-time noise analysis system for nuclear reactors

    International Nuclear Information System (INIS)

    Ciftcioglu, O.

    1987-01-01

    A CAMAC based real-time noise analysis system was designed for the TRIGA MARK II nuclear reactor at the Institute for Nuclear Energy, Istanbul. The input analog signals obtained from the radiation detectors are introduced to the system through CAMAC interface. The signals coverted into digital form are processed by a PDP-11 computer. The fast data processing based on auto/cross power spectral density computations is carried out by means of assembly written FFT algorithms in real-time and the spectra obtained are displayed on a CAMAC driven display system as an additional monitoring device. The system has the advantage of being software programmable and controlled by a CAMAC system so that it is operated under porgram control for reactor surveillance, anomaly detection and diagnosis. The system can also be used for the identification of nonstationary operational characteristics of the reactor in long term by comparing the noise power spectra with the corresponding reference noise patterns prepared in advance. (orig.)

  4. A survey on reliability and safety analysis techniques of robot systems in nuclear power plants

    Energy Technology Data Exchange (ETDEWEB)

    Eom, H S; Kim, J H; Lee, J C; Choi, Y R; Moon, S S

    2000-12-01

    The reliability and safety analysis techniques was surveyed for the purpose of overall quality improvement of reactor inspection system which is under development in our current project. The contents of this report are : 1. Reliability and safety analysis techniques suvey - Reviewed reliability and safety analysis techniques are generally accepted techniques in many industries including nuclear industry. And we selected a few techniques which are suitable for our robot system. They are falut tree analysis, failure mode and effect analysis, reliability block diagram, markov model, combinational method, and simulation method. 2. Survey on the characteristics of robot systems which are distinguished from other systems and which are important to the analysis. 3. Survey on the nuclear environmental factors which affect the reliability and safety analysis of robot system 4. Collection of the case studies of robot reliability and safety analysis which are performed in foreign countries. The analysis results of this survey will be applied to the improvement of reliability and safety of our robot system and also will be used for the formal qualification and certification of our reactor inspection system.

  5. A survey on reliability and safety analysis techniques of robot systems in nuclear power plants

    International Nuclear Information System (INIS)

    Eom, H.S.; Kim, J.H.; Lee, J.C.; Choi, Y.R.; Moon, S.S.

    2000-12-01

    The reliability and safety analysis techniques was surveyed for the purpose of overall quality improvement of reactor inspection system which is under development in our current project. The contents of this report are : 1. Reliability and safety analysis techniques suvey - Reviewed reliability and safety analysis techniques are generally accepted techniques in many industries including nuclear industry. And we selected a few techniques which are suitable for our robot system. They are falut tree analysis, failure mode and effect analysis, reliability block diagram, markov model, combinational method, and simulation method. 2. Survey on the characteristics of robot systems which are distinguished from other systems and which are important to the analysis. 3. Survey on the nuclear environmental factors which affect the reliability and safety analysis of robot system 4. Collection of the case studies of robot reliability and safety analysis which are performed in foreign countries. The analysis results of this survey will be applied to the improvement of reliability and safety of our robot system and also will be used for the formal qualification and certification of our reactor inspection system

  6. Nuclear reactor safety system

    International Nuclear Information System (INIS)

    Sato, Takashi.

    1979-01-01

    Purpose: To allow sufficient removal of radioactive substance released in the reactor containment shell upon loss of coolants accidents thus to sufficiently decrease the exposure dose to human body. Constitution: A clean-up system is provided downstream of a heat exchanger and it is branched into a pipeway to be connected to a spray nozzle and further connected by way of a valve to a reactor container. After the end of sudden transient changes upon loss of coolants accidents, the pool water stored in the pressure suppression chamber is purified in the clean-up system and then sprayed in the dry-well by way of a spray nozzle. The sprayed water dissolves to remove water soluble radioactive substances floating in the dry-well and then returns to the pressure suppression chamber. Since radioactive substances in the dry-well can thus removed rapidly and effectively and the pool water can be reused, public hazard can also be decreased. (Horiuchi, T.)

  7. A study on the direction for the development of the Korean nuclear R and D system toward the globalization

    International Nuclear Information System (INIS)

    Won, Byung Chul; Chung, Yun Ho; Kim, Myung Ro

    1994-12-01

    This study explores future directions for the development of the Korean nuclear R and D system by comparing the nuclear R and D systems in the US, France, Japan, and Canada. In an effort to search for appropriate directions, this study analyzed characteristics of the nuclear R and D systems in advanced nations in the following areas; (1) configuration of nuclear R and D, (2) morphological characteristics of major nuclear R and D organization, (3) evaluation of R and D performance, general management issues such as leadership, coordination, culture, etc., and (4) inter- organizationals with government agencies, utilities, and other regulatory organizations. On the basis of comparing the nuclear R and D system in Korea with those in the US, France, Japan, and Canada, this study tries to develop recommendations for the future directions of the Korean nuclear R and D system. The results of this research can serve as a reference to a long-term development plan for the Korean nuclear R and D system. 23 tabs., 4 figs., 34 refs. (Author)

  8. A study on the direction for the development of the Korean nuclear R and D system toward the globalization

    International Nuclear Information System (INIS)

    Won, Byung Chul; Jeong, Yeun Ho; Kim, Myung Ro; Kim, Young Pyung

    1996-02-01

    The purpose of this study is to explore future directions for the development of the Korean nuclear research system by comparing the nuclear R and D systems in the U.S., France, Japan, and Canada. In an effort to search for appropriate directions, this study analyzed the characteristics of the nuclear research systems in advanced nations in the following areas; 1. configuration of nuclear R and D, 2. morphological characteristics of major nuclear R and D organization, 3. evaluation of R and D performance, general management issues such as leadership, coordination, culture, etc., and 4. inter-organizationals with government agencies, utilities, and other regulatory organizations. On the basis of comparing the nuclear R and D system in Korea with those in the U.S., France, Japan, and Canada, this study tries to develop recommendations for the future directions of the Korean nuclear R and D system. The results of this research can serve as a reference to a long-term development plan for the Korean nuclear R and D system. 21 tabs., 11 figs., 36 refs. (Author)

  9. A study on the direction for the development of the Korean nuclear R and D system toward the globalization

    Energy Technology Data Exchange (ETDEWEB)

    Won, Byung Chul; Jeong, Yeun Ho; Kim, Myung Ro [Korea Atomic Energy Research Institute, Taejon (Korea, Republic of); Kim, Young Pyung [Korea Univ., Seoul (Korea, Republic of)

    1996-02-01

    The purpose of this study is to explore future directions for the development of the Korean nuclear research system by comparing the nuclear R and D systems in the U.S., France, Japan, and Canada. In an effort to search for appropriate directions, this study analyzed the characteristics of the nuclear research systems in advanced nations in the following areas; 1. configuration of nuclear R and D, 2. morphological characteristics of major nuclear R and D organization, 3. evaluation of R and D performance, general management issues such as leadership, coordination, culture, etc., and 4. inter-organizationals with government agencies, utilities, and other regulatory organizations. On the basis of comparing the nuclear R and D system in Korea with those in the U.S., France, Japan, and Canada, this study tries to develop recommendations for the future directions of the Korean nuclear R and D system. The results of this research can serve as a reference to a long-term development plan for the Korean nuclear R and D system. 21 tabs., 11 figs., 36 refs. (Author).

  10. A study on the direction for the development of the Korean nuclear R and D system toward the globalization

    Energy Technology Data Exchange (ETDEWEB)

    Won, Byung Chul; Chung, Yun Ho; Kim, Myung Ro [Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)

    1994-12-01

    This study explores future directions for the development of the Korean nuclear R and D system by comparing the nuclear R and D systems in the US, France, Japan, and Canada. In an effort to search for appropriate directions, this study analyzed characteristics of the nuclear R and D systems in advanced nations in the following areas; (1) configuration of nuclear R and D, (2) morphological characteristics of major nuclear R and D organization, (3) evaluation of R and D performance, general management issues such as leadership, coordination, culture, etc., and (4) inter- organizationals with government agencies, utilities, and other regulatory organizations. On the basis of comparing the nuclear R and D system in Korea with those in the US, France, Japan, and Canada, this study tries to develop recommendations for the future directions of the Korean nuclear R and D system. The results of this research can serve as a reference to a long-term development plan for the Korean nuclear R and D system. 23 tabs., 4 figs., 34 refs. (Author).

  11. Enhancement of the power system efficiency using the hybrid-type harmonic filters for a KSTAR nuclear fusion experimental system

    International Nuclear Information System (INIS)

    Yoon, Dong-Hee; Lee, Hansang; Park, Byungju; Jang, Gilsoo

    2011-01-01

    Highlights: → The low power factor and power quality problems are occurred by the operation of the PF facility in KSTAR system. We model the power system of KSTAR system including the PF facility. We show a method of the filter insertion to improve the problem and conduct the simulations to verify our method. - Abstract: The KSTAR system, which includes a large amount of nonlinear load, is a relatively high reactive power consumption load which injects harmonic currents into the power system which could result in the possibility for a power system perturbation to occur in the transmission lines, affecting nearby customers. In order to maintain the power quality and power factor in the inner system of the KSTAR system and the adjacent distribution lines, the assessment of the effect of the DC power supply in the KSTAR system is required for appropriate countermeasures to be put in place. In this paper, on the basis of a preliminary inspection of the power system near a KSTAR system, the simulation of a compensating device is performed for the prevention of abnormal voltage variations caused by a large amount of reactive and nonlinear load. In addition, through the comparison of the pre- and post-application of compensation devices in the actual power system, it is verified that a stable operation of the KSTAR nuclear fusion experimental system can be achieved.

  12. A practical system for the measurement of flows in a nuclear reactor

    International Nuclear Information System (INIS)

    Carrion V, F.J.

    1980-01-01

    With the purpose of making practical the neutron flux map in a nuclear reactor, the traditional foils are replaced by calibrated wires, and the activity rates through the wire are maked with a directional detector coupled to a collimator and to a servomechanism that moves the wire, to make the measurements through it. The servomechanism can be automatically controlled, and the information can be stored in a multichannel or directly pass to a plotter according to the continued or step by step measurements through the wire. For the system design it was necessary to fix the collimator dimensions according to the detector and the wire characteristics. In conclusion, this method is practical and exact, and their automation allows time economy. (author)

  13. Semiclassical description of hot nuclear systems

    International Nuclear Information System (INIS)

    Brack, M.

    1984-01-01

    We present semiclassical density variational calculations for highly excited nuclear systems. We employ the newly derived functionals tau[rho] and sigma[rho] of the extended Thomas-Fermi (ETF) model, generalized to finite temperatures. Excellent agreement is reached with Hartree-Fock (HF) results. We also calculated the fission barrier of 240 Pu as a function of the nuclear temperature

  14. Design and Test Plans for a Non-Nuclear Fission Power System Technology Demonstration Unit

    Science.gov (United States)

    Mason, Lee; Palac, Donald; Gibson, Marc; Houts, Michael; Warren, John; Werner, James; Poston, David; Qualls, Arthur Lou; Radel, Ross; Harlow, Scott

    2012-01-01

    A joint National Aeronautics and Space Administration (NASA) and Department of Energy (DOE) team is developing concepts and technologies for affordable nuclear Fission Power Systems (FPSs) to support future exploration missions. A key deliverable is the Technology Demonstration Unit (TDU). The TDU will assemble the major elements of a notional FPS with a non-nuclear reactor simulator (Rx Sim) and demonstrate system-level performance in thermal vacuum. The Rx Sim includes an electrical resistance heat source and a liquid metal heat transport loop that simulates the reactor thermal interface and expected dynamic response. A power conversion unit (PCU) generates electric power utilizing the liquid metal heat source and rejects waste heat to a heat rejection system (HRS). The HRS includes a pumped water heat removal loop coupled to radiator panels suspended in the thermal-vacuum facility. The basic test plan is to subject the system to realistic operating conditions and gather data to evaluate performance sensitivity, control stability, and response characteristics. Upon completion of the testing, the technology is expected to satisfy the requirements for Technology Readiness Level 6 (System Demonstration in an Operational and Relevant Environment) based on the use of high-fidelity hardware and prototypic software tested under realistic conditions and correlated with analytical predictions.

  15. NJOY. A comprehensive system for the processing of ENDF formatted nuclear data

    International Nuclear Information System (INIS)

    Muir, D.W.

    1990-07-01

    An introduction to the program system NJOY is given which processes data files of evaluated neutron nuclear data coded in ENDF format. NJOY is primarily used for neutron and photon transport calculations for nuclear power reactor design. The NJOY code is not available from the IAEA Nuclear Data Section but may be obtained from the Reactor Shielding Information Center, Oak Ridge, USA. (author). 10 refs, 1 fig

  16. A contribution to thermoluminescence dosemeter system optimisation applied to environmental monitoring around nuclear power plants

    International Nuclear Information System (INIS)

    Dies, X.; Ortega, X.; Rosell, J.

    1990-01-01

    The factors that constitute a thermoluminescence dosimetric system have been studied and optimised, with the intention of defining strategies for improving precision and accuracy of TL dosimetry systems for environmental monitoring. An optimisation technique based on fractional factorial designs permitted a reduction in the number of necessary experiments and clarified interactions between various factors. The model for fading over time showed that TL response in LiF:Mg,Ti dosemeters was independent of time between irradiation and readout, and this was applied to fading corrections in nuclear power plant environmental monitoring. (author)

  17. 4+ Dimensional nuclear systems engineering

    International Nuclear Information System (INIS)

    Suh, Kune Y.

    2009-01-01

    Nuclear power plants (NPPs) require massive quantity of data during the design, construction, operation, maintenance and decommissioning stages because of their special features like size, cost, radioactivity, and so forth. The system engineering thus calls for a fully integrated way of managing the information flow spanning their life cycle. This paper proposes digital systems engineering anchored in three dimensional (3D) computer aided design (CAD) models. The signature in the proposal lies with the four plus dimensional (4 + D) Technology TM , a critical know how for digital management. ESSE (Engineering Super Simulation Emulation) features a 4 + D Technology TM for nuclear energy systems engineering. The technology proposed in the 3D space and time plus cost coordinates, i.e. 4 + D, is the backbone of digital engineering in the nuclear systems design and management. Dased on an integrated 3D configuration management system, ESSE consists of solutions JANUS (Junctional Analysis Neodynamic Unit SoftPower), EURUS (Engineering Utilities Research Unit SoftPower), NOTUS (Neosystemic Optimization Technical Unit SoftPower), VENUS (Virtual Engineering Neocybernetic Unit SoftPower) and INUUS (Informative Neographic Utilities Unit SoftPower). NOTUS contributes to reducing the construction cost of the NPPs by optimizing the component manufacturing procedure and the plant construction process. Planning and scheduling construction projects can thus benefit greatly by integrating traditional management techniques with digital process simulation visualization. The 3D visualization of construction processes and the resulting products intrinsically afford most of the advantages realized by incorporating a purely schedule level detail based the 4 + D system. Problems with equipment positioning and manpower congestion in certain areas can be visualized prior to the actual operation, thus preventing accidents and safety problems such as collision between two machines and losses in

  18. A methodology for performing virtual measurements in a nuclear reactor system

    International Nuclear Information System (INIS)

    Ikonomopoulos, A.; Uhrig, R.E.; Tsoukalas, L.H.

    1992-01-01

    A novel methodology is presented for monitoring nonphysically measurable variables in an experimental nuclear reactor. It is based on the employment of artificial neural networks to generate fuzzy values. Neural networks map spatiotemporal information (in the form of time series) to algebraically defined membership functions. The entire process can be thought of as a virtual measurement. Through such virtual measurements the values of nondirectly monitored parameters with operational significance, e.g., transient-type, valve-position, or performance, can be determined. Generating membership functions is a crucial step in the development and practical utilization of fuzzy reasoning, a computational approach that offers the advantage of describing the state of the system in a condensed, linguistic form, convenient for monitoring, diagnostics, and control algorithms

  19. A study of a small nuclear power plant system for district heating

    International Nuclear Information System (INIS)

    Imamura, Mitsuru; Sato, Kotaro; Narabayashi, Tadashi; Shimazu, Yoichiro; Tsuji, Masashi

    2009-01-01

    We have studied nuclear power plant for district heating. Already some towns and villages in Hokkaido have requested small reactor for district heating. Using existing technology allows us to shorten development period and to keep a lid on development cost. We decided to develop new reactor based on 'MUTSU' reactor technology because 'MUTSU' had already proved its safety. And this reactor was boron free reactor. It allows plant system to reduce the chemical control system. And moderator temperature coefficient is deeply negative. It means to improve its operability and leads to dependability enhancement. We calculated burn-up calculation of erbium addition fuel. In the result, the core life became about 10 years. And we adapt the cassette type refueling during outagein in order to maintain nonproliferation. In the district heating system, a double heat exchanger system enables to response to load change in season. To obtain the acceptance of public, this system has a leak prevention system of radioactive materials to public. And road heating system of low grade heat utilization from turbine condenser leads to improve the heat utilization efficiency. We carried out performance evaluation test of district heating pipeline. Then the heat loss of pipeline is estimated at about 0.440degC/km. This result meets general condition, which is about 1degC/km. This small plant has passive safety system. It is natural cooling of containment vessel. In case of loss of coolant accident, decay heat can remove by natural convection air cooling after 6 hours. Decay heat within 6 hours can remove by evaporative heat transfer of pool on containment vessel. (author)

  20. Recycling the actinides, a beneficial contribution to the overall environmental footprint of nuclear energy systems - 5333

    International Nuclear Information System (INIS)

    Poinssot, C.; Bourg, S.; Grandjean, S.; Boullis, B.

    2015-01-01

    Full text of publication follows. Actinides recycling still remains a controversial issue for many countries which do not yet have make a definite and clear choice about the back-end of their nuclear fuel cycles. In particular, recycling is often questioned about its effective impact on the overall nuclear energy sustainability. In order to address this key issue, we developed a Life Cycle Assessment (LCA) tool, referred to as NELCAS, based on the current French nuclear energy system. Thanks to the Nuclear Safety and Transparency annual reports, detailed quantitative data were available for each of the fuel cycle plants. The whole fuel cycle from ore-mining to geological repository was considered as well as data for construction, deconstruction of any plants as well as the contribution of the transport. All the matter and energy fluxes were considered and normalised versus the electric production. Key environmental indicators as well as potential impact indicators were hence assessed and validated with comparison with the few existing LCA results. NELCAS was also used to derive other fuel cycles by correcting when necessary the relevant flux of matter and energy all along the fuel cycle. A particular focus was put on the once-through cycle with no recycling at all and the effect of the introduction of fast neutron reactors which allow actinides multi-recycling. For the very first time, it hence allows a direct and robust assessment of the effect of recycling operations on the most widely used environmental indicators. Among others, it clearly demonstrates the beneficial effect of Pu and U recycling on most of the indicators. This improvement increases with any recycling increase and is directly related to the very high contribution of the front-end operations in the overall environmental footprint. Most of the indicators are very significantly decreased with the implementation of long-term recycling strategies. This presentation will therefore detail how actinides