scholarly journals NUCLEAR-CONVENTIONAL POWER PLANT COST STUDY CONVENTIONAL COAL FIRED POWER PLANTS, 25,000 KW TO 325,000 KW, FOR ARGONNE NATIONAL LABORATORY, LEMONT, ILLINOIS

1959 ◽  
Author(s):  
W.A. Chittenden
Keyword(s):  
Power Plant ◽  
Power Plants ◽  
National Laboratory ◽  
Argonne National Laboratory ◽  
Cost Study ◽  
Conventional Power Plant

Thermal Stratification Modeling for Sodium-Cooled Fast Reactors: A Status Update

2018 ◽  
Author(s):  
Sarah Morgan ◽  
Sama Bilbao y Leon ◽  
Matthew Bucknor ◽  
Mark Anderson ◽  
Emilio Baglietto ◽  
...  
Keyword(s):  
Thermal Stratification ◽  
Power Plants ◽  
Gap Analysis ◽  
National Laboratory ◽  
Argonne National Laboratory ◽  
System Level ◽  
Computationally Efficient ◽  
Fast Reactors ◽  
Hydraulic Behavior ◽  
Cfd Models

Thermal hydraulic behavior in the upper plenum of pool-type sodium-cooled fast reactors (SFRs) is a major concern, as many design challenges are concentrated in this region. As SFR designs aim for licensing and commercialization, it is important to accurately analyze and predict the thermal-hydraulic behavior in this region during accident scenarios, specifically thermal stratification. Thermal stratification models are currently a major source of uncertainty in most system codes for all types of power plants. Most system codes, including SAS4A/SASSYS-1, a system level code developed by Argonne National Laboratory (Argonne), use very coarse meshes that cannot capture the complexities of the stratification phenomena. While the commonly employed lumped-volume based models for thermal stratification are able to run in a matter of seconds, they result in approximate results and can only handle simple cases. Other 2-D and 3-D methods, such as computational fluid dynamics (CFD) models, can analyze simple configurations with higher fidelity, but come with a relatively large computational expense. Finding a modeling solution that is both accurate and computationally efficient has proven difficult. This paper provides details of a review and gap analysis of the various modeling approaches proposed to date and explores a path forward for future thermal stratification modeling efforts, with a focus on developing new models for the SAS4A/SASSYS-1 system code.

RISIKO KONSTRUKSI PADA PEMBANGKIT LISTRIK KONVENSIONAL, SEBAGAI MASUKAN UNTUK KONSTRUKSI PLTN PERTAMA DI INDONESIA

2013 ◽  
Vol 14 (2) ◽  
Author(s):  
Dharu Dewi
Keyword(s):  
Risk Management ◽  
Power Plant ◽  
Nuclear Power Plant ◽  
Nuclear Power ◽  
Power Plants ◽  
Risk Identification ◽  
Construction Risk ◽  
Project Risks ◽  
Construction Risks ◽  
Conventional Power Plant

In general, Construction Risks of the Conventional Power Plants are almost the same with the Construction Risks at the Nuclear Power Plant (NPP). Construction Risks Experience in the Conventional Power Plant can be used as a lesson learned for Construction of the Nuclear Power Plant. This study method covers the survey, the relevant publication and empiric assessment on the real project risk implementation. The input data have been provided from experiences in conventional power plant. Hence, project risks must be control to make sure that construction activities in accordance to agreed shedule and free from cost overruns. This study can be expected will provide a valuable input to project risks of Construction of the NPP. It is concluded that the risk management can be carried out by risk identification, and implement the selected technique or strategyfor reduction of risk, transfer of risk and retention of risk to anticipate the all risks which is take place at the construction. Risk management system must be carried out by well in order to risk can be minimized.

Reliability and Safety Assessment of a Conceptual Thermochemical Plant for Nuclear-Based Hydrogen Generation

2008 ◽  
Author(s):  
Yuepeng Zhang ◽  
Lixuan Lu ◽  
Greg F. Naterer
Keyword(s):  
Greenhouse Gas Emissions ◽  
Greenhouse Gas ◽  
Power Plants ◽  
Nuclear Energy ◽  
Large Scale ◽  
Hydrogen Generation ◽  
National Laboratory ◽  
Argonne National Laboratory ◽  
Gas Emissions ◽  
Hydrogen Plant

Hydrogen is a clean fuel that can help to reduce greenhouse gas emissions, as its oxidation does not emit carbon dioxide (a primary greenhouse gas). Generation of hydrogen has attracted much recent worldwide attention. A promising method to generate hydrogen is to use heat from nuclear power plants. The advantages of using nuclear heat are capabilities of large-scale generation of hydrogen and zero greenhouse gas emissions. Nuclear energy is expected to have an important role for hydrogen generation in the future. In this paper, reliability and probabilistic safety assessments of a conceptual nuclear-hydrogen plant will be analyzed. There are two main methods to generate hydrogen from nuclear energy. They include: 1) thermochemical processes and 2) electrochemical processes. The conceptual plant of this paper is based on a Cu-Cl thermocycle developed by Atomic Energy of Canada Limited (AECL) and the Argonne National Laboratory (ANL). Using a flowsheet of the hydrogen plant created by an Aspen Plus simulation by ANL, four fault-trees are constructed for potential risk scenarios. Based on the results from the fault tree analyses (FTA), the risk levels of the hydrogen generation plant under different accident scenarios can be calculated. Based on the results, potential problems encountered in Cu-Cl cycle are identified and possible solutions will be recommended for future improvements.

Producing Power Using Stirling Engines by Tapping Heat from the Condenser of Power Plants

2012 ◽  
Vol 229-231 ◽  
pp. 1106-1109
Author(s):  
Nitin Sharma ◽  
Aman Goel ◽  
Avishek Ghosh ◽  
Abhimanyu Kohli
Keyword(s):  
Power Plant ◽  
Nuclear Power ◽  
Power Plants ◽  
Fossil Fuels ◽  
Peak Load ◽  
Power Production ◽  
Stirling Engine ◽  
Additional Energy ◽  
Stirling Engines ◽  
Conventional Power Plant

Mankind’s lax approach towards energy sources during its past years of incessant growth has led to chopping of fossil fuels and done immense harm to the environment. Today we are faced with a challenge to develop eco friendly systems that ensure sustainable development with minimum harm to our fragile surroundings We propose a system consisting a Stirling engine that, using the temperature difference between the condenser inlets and outlets of a power plant (nuclear or thermal), produces power. This will sooth our problems to some extent. In this paper, we will briefly discuss the working of thermal/nuclear power plants in combination with Stirling engine in order to increase the efficiency of conventional power plant systems up to the order of 80% . Above all our system causes lower emissions when compared to the already existing systems since the engine producing power has zero emission. The main advantage of our proposed system is that there will be increase in power production of the existing plants without any further increase in the energy supply. This small auxiliary system working in synchronization with the main system increases the overall efficiency of the plant by increasing the power output without additional energy being expended and also reduces the load on the power plants during peak load requirements.

Prediction of Potential Offsite TEDE, Excess Cancer Risk, Dominant Exposure Pathways and Activity Concentration for Hypothetical Onsite Soil Contamination At the Proposed Rooppur Nuclear Power Plant

2020 ◽  
Author(s):  
Md. Ashraful Islam ◽  
Md. Hossain Sahadath
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Cancer Risk ◽  
Soil Contamination ◽  
Nuclear Power ◽  
Activity Concentration ◽  
National Laboratory ◽  
Argonne National Laboratory ◽  
Exposure Pathways ◽  
Excess Cancer Risk

Abstract The present study evaluates the potential offsite radiological hazards by calculating Total Effective Dose Equivalent (TEDE) & Excess Cancer Risk if onsite soil contamination occurs at the proposed Rooppur Nuclear Power Plant (RNPP) site, Bangladesh. The assessment was perform assuming a hypothetical soil contamination associated with Fukushima Nuclear disaster with the help of the RESRAD (Residual Radioactivity) OFFSITE computer program developed by Argonne National Laboratory, USA. Six radionuclides namely Cs-134, Cs-136, Cs-137, La-140, Te-129m and Sr-90 has been considered. The maximum TEDE was found to be approximately 2.8 mSv/yr and the maximum total excess cancer risk was found to be 3.25×10-3. The number of dominant exposure pathways and maximum contributor pathways and duration of dominance of different nuclides has been identified. Ingestion of fish is identified as the principal pathway to both TEDE and excess cancer risk. Time variation of activity concentration and dose/source ratio has also been studied.

scholarly journals Possibility of use adsorption chillers for increase efficiency in conventional power plant

2019 ◽  
Vol 213 ◽  
pp. 02082
Author(s):  
Karol Sztekler ◽  
Wojciech Kalawa ◽  
Wojciech Nowak ◽  
Sebastian Stefański ◽  
Jarosław Krzywański ◽  
...  
Keyword(s):  
Power Plant ◽  
Power Unit ◽  
Air Conditioning ◽  
Power Plants ◽  
Waste Heat ◽  
Electricity Demand ◽  
Electricity Production ◽  
The Impact ◽  
Conventional Power Plant

Long-term forecasts indicate that the annual increases in electricity demand by 2030 will be approx. 2 ÷ 3% a year. At present, 40% of the world's electricity is produced using coal-fired power plants. Forecasts indicate that coal will still be the predominant fuel used to produce electricity and thus any actions aimed at increasing the efficiency of electricity production are purposeful. Enormous amounts of waste heat, which is not sufficiently used, are released during the process of electricity production. One of the ways to manage it is to use refrigeration systems based on adsorption chillers which would use waste heat to generate cold that would be employed for air-conditioning or process purposes. In this paper, the cycle of a conventional coal-fired power plant was modelled and then the possibilities of using waste heat for generation of cold as well as the impact of a chiller on the operation of a power unit were analysed using IPSEpro software.

Monitoring Critical Facilities by Using Advanced RF Devices

2013 ◽  
Author(s):  
Hanchung Tsai ◽  
Yung Y. Liu ◽  
James Shuler
Keyword(s):  
Radio Frequency Identification ◽  
Nuclear Power ◽  
Power Plants ◽  
Fuel Cycle ◽  
National Laboratory ◽  
Argonne National Laboratory ◽  
Hydrogen Gas ◽  
Spent Fuel ◽  
Gas Temperature ◽  
Critical Facilities

The ability to monitor critical environment parameters of nuclear plants at all times, particularly during and after a disruptive accident, is vital for the safety of plant personnel, rescue and recovery crews, and the surrounding communities. Conventional hard-wired assets that depend on supplied power may be decimated as a result of such events, as witnessed in the Japanese Fukushima nuclear power plant in March 2011. Self-powered monitoring devices operating on a wireless platform, on the other hand, may survive such calamity and remain functional. The devices would be prepositioned at strategic locations, particularly where the dangerous build-up of contamination and radiation may preclude subsequent manned entrance and surveillance. Equipped with sensors for β-γ radiation, neutrons, hydrogen gas, temperature, humidity, pressure, and water level, as well as with criticality alarms and imaging equipment for heat, video, and other capabilities, these devices can provide vital surveillance information for assessing the extent of plant damage, mandating responses (e.g., evacuation before impending hydrogen explosion), and enabling overall safe and efficient recovery in a disaster. A radio frequency identification (RFID)-based system — called ARG-US — may be modified and adapted for this task. Developed by Argonne for DOE, ARG-US (meaning “watchful guardian”) has been used successfully to monitor and track sensitive nuclear materials packages at DOE sites. It utilizes sensors in the tags to continuously monitor the state of health of the packaging and promptly disseminates alarms to authorized users when any of the preset sensor thresholds is violated. By adding plant-specific monitoring sensors to the already strong sensor suite and adopting modular hardware, firmware, and software subsystems that are tailored for specific subsystems of a plant, a Remote Area Modular Monitoring (RAMM) system, built on a wireless sensor network (WSN) platform, is being developed by Argonne National Laboratory. ARG-US RAMM, powered by on-board battery, can sustain extended autonomous surveillance operation during and following an incident. The benefits could be invaluable to such critical facilities as nuclear power plants, research and test reactors, fuel cycle manufacturing centers, spent-fuel dry-cask storage facilities, and other nuclear installations.

Electron and ion irradiation-induced dissolution of mechanical twins in the intermetalic U3Si: An in situ HVEM study

1989 ◽  
Vol 47 ◽  
pp. 652-653
Author(s):  
Charles W. Allen ◽  
Robert C. Birtcher
Keyword(s):  
Elevated Temperatures ◽  
Ion Irradiation ◽  
Ion Beam ◽  
National Laboratory ◽  
Argonne National Laboratory ◽  
Heavy Ion ◽  
High Energy ◽  
Mechanical Twinning ◽  
In Situ Experiments

The uranium silicides, including U3Si, are under study as candidate low enrichment nuclear fuels. Ion beam simulations of the in-reactor behavior of such materials are performed because a similar damage structure can be produced in hours by energetic heavy ions which requires years in actual reactor tests. This contribution treats one aspect of the microstructural behavior of U3Si under high energy electron irradiation and low dose energetic heavy ion irradiation and is based on in situ experiments, performed at the HVEM-Tandem User Facility at Argonne National Laboratory. This Facility interfaces a 2 MV Tandem ion accelerator and a 0.6 MV ion implanter to a 1.2 MeV AEI high voltage electron microscope, which allows a wide variety of in situ ion beam experiments to be performed with simultaneous irradiation and electron microscopy or diffraction.At elevated temperatures, U3Si exhibits the ordered AuCu3 structure. On cooling below 1058 K, the intermetallic transforms, evidently martensitically, to a body-centered tetragonal structure (alternatively, the structure may be described as face-centered tetragonal, which would be fcc except for a 1 pet tetragonal distortion). Mechanical twinning accompanies the transformation; however, diferences between electron diffraction patterns from twinned and non-twinned martensite plates could not be distinguished.

Environmental cell studies of deformation and fracture

1990 ◽  
Vol 48 (4) ◽  
pp. 516-517
Author(s):  
H. K. Birnbaum ◽  
I. M. Robertson
Keyword(s):  
National Laboratory ◽  
Argonne National Laboratory ◽  
Damage Threshold ◽  
Chromatic Aberration ◽  
Good Choice ◽  
Point Of View ◽  
Deformation And Fracture ◽  
Environmental Cell ◽  
Gas Molecules ◽  
The University

Studies of the effects of hydrogen environments on the deformation and fracture of fcc, bcc and hep metals and alloys have been carried out in a TEM environmental cell. The initial experiments were performed in the environmental cell of the HVEM facility at Argonne National Laboratory. More recently, a dedicated environmental cell facility has been constructed at the University of Illinois using a JEOL 4000EX and has been used for these studies. In the present paper we will describe the general design features of the JEOL environmental cell and some of the observations we have made on hydrogen effects on deformation and fracture.The JEOL environmental cell is designed to operate at 400 keV and below; in part because of the available accelerating voltage of the microscope and in part because the damage threshold of most materials is below 400 keV. The gas pressure at which chromatic aberration due to electron scattering from the gas molecules becomes excessive does not increase rapidly with with accelerating voltage making 400 keV a good choice from that point of view as well. A series of apertures were placed above and below the cell to control the pressures in various parts of the column.

Fuzzy multi-objective decision making approach for nuclear power plant installation

2020 ◽  
Vol 39 (5) ◽  
pp. 6339-6350
Author(s):  
Esra Çakır ◽  
Ziya Ulukan
Keyword(s):  
Linear Programming ◽  
Power Plant ◽  
Nuclear Power Plant ◽  
Energy Supply ◽  
Energy Demand ◽  
Nuclear Power ◽  
Power Plants ◽  
Total Duration ◽  
Objective Functions ◽  
Multi Objective

Due to the increase in energy demand, many countries suffer from energy poverty because of insufficient and expensive energy supply. Plans to use alternative power like nuclear power for electricity generation are being revived among developing countries. Decisions for installation of power plants need to be based on careful assessment of future energy supply and demand, economic and financial implications and requirements for technology transfer. Since the problem involves many vague parameters, a fuzzy model should be an appropriate approach for dealing with this problem. This study develops a Fuzzy Multi-Objective Linear Programming (FMOLP) model for solving the nuclear power plant installation problem in fuzzy environment. FMOLP approach is recommended for cases where the objective functions are imprecise and can only be stated within a certain threshold level. The proposed model attempts to minimize total duration time, total cost and maximize the total crash time of the installation project. By using FMOLP, the weighted additive technique can also be applied in order to transform the model into Fuzzy Multiple Weighted-Objective Linear Programming (FMWOLP) to control the objective values such that all decision makers target on each criterion can be met. The optimum solution with the achievement level for both of the models (FMOLP and FMWOLP) are compared with each other. FMWOLP results in better performance as the overall degree of satisfaction depends on the weight given to the objective functions. A numerical example demonstrates the feasibility of applying the proposed models to nuclear power plant installation problem.

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