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Simulation Analysis of Reactor Buildings on Niigataken Chuetsu-oki Earthquake at Kashiwazaki-Kariwa Nuclear Power Plant

Simulation Analysis of Reactor Buildings on Niigataken Chuetsu-oki Earthquake at Kashiwazaki-Kariwa Nuclear Power Plant

Figure 9 shows the average shear stress and shear strain of the walls of individual floors obtained from the simulation analysis for Unit 1. As shown in the figure, shear stress generated in the walls during the earthquake became smaller than the allowable stress that could be resisted only by design reinforcing bars. Also, the shear strain generated in the wall at each floor during the earthquake was about 0.2 x 10 -3 at maximum, which was below the reference value for crack occurrence.

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Simulation Analysis of Earthquake Response of Nuclear Power Plant to the 2003 Miyagi-Oki Earthquake

Simulation Analysis of Earthquake Response of Nuclear Power Plant to the 2003 Miyagi-Oki Earthquake

On May 26, 2003 an earthquake of magnitude scale 7.1 (Japan Meteorological Agency) occurred just offshore of Miyagi Prefecture. This was the largest earthquake ever experienced by the nuclear power plant of Tohoku Electric Power Co. in Onagawa (hereafter the Onagawa Nuclear Power Plant) during the 19 years since it had started operations in 1984. The earthquake recorded a maximum acceleration of 225 Gal at the upper surface of the basemat slab (second basement level) of the reactor building in Unit 1, which was undergoing a routine inspection at the time. In addition, Unit 3, which was in operation that day, shut down automatically as a result of the large amplitude of the seismic acceleration. This was the first case in Japan where an earthquake induced a scram shutdown.
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Fire safety simulation of cable fire in nuclear power plant room based on flammability database of cables

Fire safety simulation of cable fire in nuclear power plant room based on flammability database of cables

For these tests, 4 kind of electrical cables were applied to the flammability tests. The name of cables and specification are shown in table 1. The special specifications for nuclear plans were applied to the cable specimens in Table 1. The cable specimens which include 2 conductor were applied to the tests. The hyper electrical insulation machines is able to measure insulation resistance from 2.5MΩ to 10 7 MΩ.

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Simulation of Nuclear Power Plant Containment Response During a Large-Break Loss-of-Coolant Accident

Simulation of Nuclear Power Plant Containment Response During a Large-Break Loss-of-Coolant Accident

Although actual heat structures may as- sume complex shapes, they are modeled in CON- TAIN as either spheres, cylinders or slabs, which may assume either vertical or horizontal orienta- tion. In addition, elements from the above-listed categories were not modeled individually, but were grouped into “representative” structures. Due to the inherent simplifications used in the modeling of flows and atmosphere thermodynamics, a de- tailed modeling of heat structures would not nec- essarily improve the reliability of the simulation results.

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Simulation of a Hypothetical Loss-of-Feedwater Accident in a Modernized Nuclear Power Plant

Simulation of a Hypothetical Loss-of-Feedwater Accident in a Modernized Nuclear Power Plant

degradation and melting is a likely consequence of a total loss of the secondary heat sink. Further, this may cause failure of the reactor vessel and possible containment failure and spreading of the radioactive material into the environment. Only the events including the core uncovering and heatup are analyzed here. Some comparison plots between the simulator and the RELAP5/MOD2 thermal-hydraulic computer-code predictions are given. The calculated reference data are very important as no real event of this kind has occurred at Krško NPP. This is a beyond- design-basis accident, which is not expected to occur during the plant’s lifetime. The continuation of the scenario leads to an even worse accident plant state, and to core melt. In the past decade, significant progress was made in the area of severe accidents and the use of severe-accident codes. In this regard, it is important to note that the KFSS also has the built-in capability to simulate severe accidents, starting from core heatup, core degradation, reactor vessel failure, containment response, core concrete interaction, containment failure, etc. So the simulator also represents a state-of-the-art product with the capability to simulate severe accidents in real time [12]. Developments in this direction were already indicated in [13], describing the full-scope simulator for the Leningrad NPP, and published in 1997, where it was reported that “it is the first time ever that the full-scope and analytical simulator ensure modeling of severe, beyond-the-design-basis accidents”. Otherwise, as well as for operator training simulators, they can also be used as plant analyzers or in licensing safety analyses [14].
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13 4 2a Simulation of the Primary Loop of a Nuclear Power Plant pdf

13 4 2a Simulation of the Primary Loop of a Nuclear Power Plant pdf

was -5 volts, which corresponds to a step change in reactivity of -2,5 x 10- 3 , As shown in Figure 9, the control system returned the neutron density to the initial value rapidly and wi[r]

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Case Study of Reactor Containment Building Construction in Nuclear Power Plant

Case Study of Reactor Containment Building Construction in Nuclear Power Plant

On the studies of nuclear power plant construction, Lee Dae-Su (1996) [5] studied an application case of im- proved constructability focusing on the reduction of the construction duration of nuclear power plants. Jo Yeong-Seok (2002) [6] researched independent construction based on the knowledge accumulated and devel- oped over 30 years since the first nuclear power plant, as well as the reduction effect of the construction power plant construction and improvement of quality. Mun Byeong-Seok (2009) [7] presented a development plan for an EVMS model and a simulation system to examine the concept of EVM technique and domestic and overseas application cases through the literature review. Kim Tae-Hong (2011) [8] studied the design of concrete nuclear power structures and a plan for the rationalization of construction. As of now, there have been almost no studies conducted on the reduction of construction duration of an RCB for a nuclear power plant, despite diverse studies on nuclear power plant construction project. Therefore, this study first reviewed cases of the construction of RCBs, with the aim of improving the constructability of the RCB external wall to achieve a reduction in the du- ration of construction of a nuclear power plant.
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Electricity From Nuclear Power: Is It A Solution To Greenhouse Gas Emissions In India

Electricity From Nuclear Power: Is It A Solution To Greenhouse Gas Emissions In India

Increased industrialization is associated with rapid economic growth which in turn gives the problem of increased greenhouse emissions. There is no denying the fact that Global warming has become a major concern in the past few decades. For the past few years, the earth is giving us message in different forms either it is through drought or storms or fire. The earth is getting warmer day by day. This is what global warming is! Global temperatures are increasing and the earth is becoming warmer , warmer than at any time before and it is predicted that in coming future this may surpass the levels not seen on the planet ever before. Energy is the basic component for the development of industries, people and in turn the whole country. But at the same time, it is the component which has led to so many environmental problems either in the direct form or in an indirect form. The electricity is the major form of energy which is being used in the country from the earliest times and the thermal power plant based on coal gives rise to some gaseous emissions like sulfur dioxide, nitrogen oxides, CFCs and suspended particles (SPM). [1]. Now it has become a major international concern for the climate change as the demand for electricity is increasing continuously and in order to balance the demand and supply side, generating more and more units are being installed. The percentage of carbon dioxide is only 0.03 % in the atmosphere but due to continuous combustion of fossil fuels it has been increased by about 25% as compared to the pre-industrial times.
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Seismic Stress Test of Koeberg NPP

Seismic Stress Test of Koeberg NPP

Following the events at Fukushima Daiichi Nuclear Power Plant on 11 March 2011 the International Atomic Energy Agency and South African government agreed to undertake a stress test of KNPP to identify areas of improvement for the plant. A component of this work was the seismic reassessment of various critical structures, systems and components (SSC) against a review level earthquake (RLE) beyond the original design basis. This RLE was defined at 0.5g ZPGA.

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Identification of Potential for Explosions in Nuclear Power Plant

Identification of Potential for Explosions in Nuclear Power Plant

The principle in the separation approach is to assure that the man made hazards that have the potential of generating impulsive loads are kept far from the safety related SSC’s. the separation is calculated to either reduce the effect of the impulsive load on the SSC’s to values comparable to other loads that the SSC’s are designed to withstand or to reduce the effect to nominal forces that can be neglected. An example of such an approach is locating the safety related structures far enough from the railway, highway or navigable waterway such that any explosion that might occur on these transportation routes does not have any adverse effect on plant operation or prevent the plant to achieve a safe shutdown if required. U.S. Regulatory Guide 1.91 provides safe distances for the carriers that transport explosives depending on the TNT equivalent of the explosive material on board.
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Research on RPR Technology and Its Application in Nuclear Power Plant

Research on RPR Technology and Its Application in Nuclear Power Plant

The application of network services in nuclear power plants can be divided into the following categories: (1) voice services: dispatching telephone and administrative telephone; (2) data services: dispatching automation data, management information system and office automation system data, control system data; (3) video services: video conferencing, video surveillance and so on; (4) multimedia. Business: E-mail, Web applications, videotex, multimedia conferencing, video on demand, video broadcasting, etc.

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Selected Chemical Aspects of Nuclear Power Development

Selected Chemical Aspects of Nuclear Power Development

The Fukushima nuclear power plant (NPP) accident consequences are a new challenge for nuclear power development; however the sequence of the event has illustrated importance of radiation- and radiochemistry processes on the safe operation and shut down of nuclear reactor and decontamination of formed liquid and solid wastes. A chemistry pro- gram is essential for the safe operation of a nuclear power plant. It ensures the integrity, reliability and availability of the main plant structures, systems and components important to safety, in accordance with the assumptions and intent of the design. The proper implementation of these procedures minimizes the harmful effects of chemical impurities and corrosion on plant structures, systems and components. It supports the minimization of buildup of radioactive material and occupational radiation exposure as well as limiting of the release of chemicals and radioactive material to the en- vironment [1].
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WWER-type   NPP Spray Ponds Screen (J036)

WWER-type NPP Spray Ponds Screen (J036)

is the corresponding velocity component (along x, y or z). In the case of plant windbreak (case SP12-PWB- High) this kind of a source-term has been distributed exactly over the control volumes, where the plants are located taking into account the triangular shape of the plants. In the case of steel windbreak (case SP12- SWB-10/22) the source-term has been applied to only one column of control volumes in the x-direction. In this case the value of the coefficient C 2 (which has a meaning of a minor losses coefficient) has been set

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Project Management in Nuclear Power Plant Construction

Project Management in Nuclear Power Plant Construction

The transfer of responsibility and knowledge from the construction teams to the commissioning teams and on to operational staff can be facilitated by appointing commissioning and operations teams early and actively encouraging collaboration. Making equipment suppliers and installers responsible for the work and having commissioning staff as members of their team ensures that the right expertise is made available in a timely way, experience is gained and knowledge transferred. Ensuring that foreign material is prevented from entering the process systems and taking measures, prior to nuclear power generation, to reduce the corrosion products that could circulate through the core, will reduce radiation fields and operator dose that arise from subsequent operation of the plant. A lack of cleanliness during commissioning of either circuit can result in problems several decades into operation.
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Project Characteristics Enabling the Success of Megaprojects: An Empirical Investigation in the Energy Sector

Project Characteristics Enabling the Success of Megaprojects: An Empirical Investigation in the Energy Sector

To test the correlation of this kind of database there are a limited number of suitable statistical tests: in particular, the chi squared and Fisher exact test (or Barnard's test). With large samples, a chi-squared test is usually employed. However, the significance value it provides is only an approximation, because the sampling distribution of the test statistic that is calculated is only approximately equal to the theoretical chi-squared distribution. The approximation is inadequate when sample sizes are small. The usual heuristic rule for deciding whether the chi- squared approximation is good enough is that the chi-squared test is not suitable when the expected values in any of the cells of a contingency table are below 5, or below 10, when there is only one degree of freedom. In contrast the Fisher exact test is, as its name states, exact. Chi squared is more suitable when independent variables are not binary (yes/no) but categorical (coal power plant/ Nuclear Power plant/solar power plant etc.) (Leach, 1979). Given the small sample in the statistical test the Fisher exact test is selected therefore. Considering the issue of one-side or two-sides researchers who choose one-tailed tests should be trusted to use it correctly, in this case it is very speculative to say if there is a direct or indirect correlation between the independent and dependent variable. So, it is more conservative and appropriate utilize the two-sides approach.
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NUCLEAR ENERGY: THE DEPENDABLE OPTION

NUCLEAR ENERGY: THE DEPENDABLE OPTION

Rapid economic growth has created a growing for supplies of energy. Current population in India is 1.21 billion, which is likely to touch 1.5 billion in 2030,and sparing of land for installment of other renewable energy sources by solar panels, wind farms and construction of hydroelectric energy generators will ultimately result in damage to original characteristics including biotic and abiotic components of land due to alteration caused in huge area required for installment. On other hand, India has vast nuclear fuel sources of Thorium and Uranium, which are capable of feeding of Nuclear Power Generation. Hence by utilizing both uranium and by converting thorium into uranium from spent uranium can act as dual purpose, one by utilizing energy potential and another by recovering uranium
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Miller Renewable Resources PPT.ppt

Miller Renewable Resources PPT.ppt

 Nuclear power plant Nuclear power plant : 92% of energy is wasted : 92% of energy is wasted through nuclear fuel and energy needed for.. through nuclear fuel and energy needed for.[r]

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Impact of a Disaster on Land Price: Evidence from Fukushima Nuclear Power Plant Accident

Impact of a Disaster on Land Price: Evidence from Fukushima Nuclear Power Plant Accident

The Great East Japan Earthquake, which occurred on March 11, 2011, triggered the Fukushima nuclear power plant accident. This study estimates the economic damage caused by the radioactive contamination from the plant using a hedonic approach. Our estimation results show that an increase of 1  Sv h / decreases the land price by 3.39% on average in Fukushima and Miyagi prefectures. Specifically, damage due to the radiation effect is estimated to cost approximately 64.1 billion yen in Fukushima. In addition, our result shows that commercial and business areas are more sensitive than residential areas to the radiation quantity.
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Siting Consideration for Nuclear Power Plant: A Review

Siting Consideration for Nuclear Power Plant: A Review

In conclusion, the siting of power plant is likely to be one of the most politically contentious issues if the government decided to promote the establishment of a NPP. There is a considerable amount of community opposition to the nuclear industry and siting issues are often a source of significant conflict even the countries that rely on nuclear power for a large proportion of their electricity needs. On the other perspective, safety assessment in licensing process is complicated and unfamiliar in most of the countries which need to be performed by high quality experts along with the international consultants for supporting safety assessment for an appropriate approach. It is important for licensing process, infrastructure, legal development and human development. There are still many things that we need to consider in the coming future even the current achievement gained recently is quite impressive. The critical aspect is to inform the public about nuclear energy and nuclear power besides gaining the support from the. Any new system should be designed according to sustainability principles where it will include the precautionary principle. To implement the requirement, a comprehensive framework of sustainability principles, indicators and criteria should be developed to the point where it could be used to assess the sustainability of any proposed engineered system. Lastly, further research would need to be carried out before it could be concluded that the areas are definitely suitable for NPP construction.
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Combined Cooling in the Krško Nuclear Power Plant

Combined Cooling in the Krško Nuclear Power Plant

a) After mixing with the cooling water the Sava river temperature should not change for mo­ re than two thirds of the daily measurements results on average: A7 = 2 K if the river tempera­ ture at its inlet into the nuclear plant, namely at the essential water supply point, is higher than 8 °C; however, if this temperature is lower, the allowed daily temperature increase is AT= 3K.

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