In this study optimization of modified CANDLE burnup scheme based long life Pb-Bi Cooled Fast Rea... more In this study optimization of modified CANDLE burnup scheme based long life Pb-Bi Cooled Fast Reactors with natural Uranium as Fuel Cycle Input for small long life reactors has been performed. In this design the reactor cores are subdivided into several parts with the same volume in the axial directions. The natural uranium is initially put in region 1, after one cycle of 10 years of burn-up it is shifted to region 2 and the region 1 is filled by fresh natural uranium fuel. This concept is basically applied to all regions, i.e. shifted the core of I’th region into I+1 region after the end of 10 years burn-up cycle. In this paper we discuss the characteristics of several designs of small long life Pb-Bi cooled fast reactors with modified CANDLE burn-up scheme. Four power levels of 250MWt, 400MWt, 600MWt, and 800MWt were investigated. For 250MWt and 400MWt cores we employed 67.5% high fuel volume fraction nitride fuels with large pin diameter of 1.35 cm while for 600and 800MWt cores w...
One of the most important aspects in nuclear reactor design process is the safety aspect. Advance... more One of the most important aspects in nuclear reactor design process is the safety aspect. Advanced and accurate safety simulation must be performed before it can be built. This research aims to develop a simulation model of Nuclear Power Plant (NPP) accidents due to the loss of heat sink system. Loss of heat sink accident was triggered by the loss of cooling capability of steam generators. This accident sequence began with the loss of the reactor’s ability to remove heat from the secondary cooling loop. During the accident, the heat dissipation rate decreased whereas the coolant inlet temperatures increased till a new equilibrium level. The analysis results of the accident showed that there are large safety margin to the maximum temperature of the fuel, cladding, and coolant.
International Journal of Nuclear Energy Science and Technology, 2012
ABSTRACT In this study application of modified CANDLE burn-up scheme for medium-sized (800-1500 M... more ABSTRACT In this study application of modified CANDLE burn-up scheme for medium-sized (800-1500 MWt) long-life Pb-Bi cooled fast reactors with natural uranium as fuel cycle input has been performed. The reactor cores are subdivided into several parts with equal volume in the axial directions. The natural uranium is initially put in region 1, after one cycle of 10 years of burn-up it is shifted to region 2, and 10 years after that it is shifted to region 3. This concept is applied to all regions, i.e. shifted the core of I-th region into I+1 region after the end of 10 years burn-up cycle. The first region 1 is filled by fresh natural uranium fuel. The core radial size is optimised to give maximum power density around 400 W/cc.
ABSTRACT Corrosion of structural materials in high temperature molten lead-bismuth eutectic is a ... more ABSTRACT Corrosion of structural materials in high temperature molten lead-bismuth eutectic is a major problem for design of PbBi cooled reactor. One technique to inhibit corrosion process is to inject oxygen into coolant. In this paper we study and focus on a way of inhibiting the corrosion of iron using molecular dynamics method. For the simulation results we concluded that effective corrosion inhibition of iron may be achieved by injection 0.0532 wt% to 0.1156 wt% oxygen into liquid lead-bismuth. At this oxygen concentration the structure of iron material will be maintained at about 70% in bcc crystal structure during interaction with liquid metal.
International Journal of Nuclear Energy Science and Technology, 2010
Local blockage is one of the possible severe accidents which may occur in lead (Pb)-or lead-bismu... more Local blockage is one of the possible severe accidents which may occur in lead (Pb)-or lead-bismuth (Pb-Bi)-cooled fast reactors due to their high melting temperature. In a local blockage accident, the local temperature increase cannot significantly reduce power level ...
In this study a fesibility design study of medium sized (1000 MWt) gas cooled fast reactors which... more In this study a fesibility design study of medium sized (1000 MWt) gas cooled fast reactors which can utilize natural uranium as fuel cycle input has been conducted. Gas Cooled Fast Reactor (GFR) is among six types of Generation IV Nuclear Power Plants. GFR with its hard neuron spectrum is superior for closed fuel cycle, and its ability to be operated in high temperature (850° C) makes various options of utilizations become possible. To obtain the capability of consuming natural uranium as fuel cycle input, modified CANDLE burn-up scheme[1-6] is adopted this GFR system by dividing the core into 10 parts of equal volume axially. Due to the limitation of thermal hydraulic aspects, the average power density of the proposed design is selected about 70 W/cc. As an optimization results, a design of 1000 MWt reactors which can be operated 10 years without refueling and fuel shuffling and just need natural uranium as fuel cycle input is discussed. The average discharge burn-up is about 280 GWd/ton HM. Enough margin for criticallity was obtained for this reactor.
ABSTRACT In this paper we report molecular dynamics simulation results of iron (cladding) corrosi... more ABSTRACT In this paper we report molecular dynamics simulation results of iron (cladding) corrosion in interaction with lead coolant of fast nuclear reactor. The goal of this work is to study effect of oxygen injection to the coolant to reduce iron corrosion. By evaluating diffusion coefficients, radial distribution functions, mean-square displacement curves and observation of crystal structure of iron before and after oxygen injection, we concluded that a significant reduction of corrosion can be achieved by issuing about 2% of oxygen atoms into lead coolant.
ABSTRACT In this present work, we report numerical results of iron (cladding) corrosion study in ... more ABSTRACT In this present work, we report numerical results of iron (cladding) corrosion study in interaction with lead-bismuth eutectic coolant of advanced nuclear reactors. The goal of this work is to study how the oxygen can be used to reduce the corrosion rate of cladding. The molecular dynamics method was applied to simulate corrosion process. By evaluating the diffusion coefficients, RDF functions, MSD curves of the iron and also observed the crystal structure of iron before and after oxygen injection to the coolant then we concluded that a significant and effective reduction can be achieved by issuing about 2% number of oxygen atoms to lead-bismuth eutectic coolant.
In this paper, conceptual design study of Small Long‐life Gas Cooled Fast Reactors with Natural U... more In this paper, conceptual design study of Small Long‐life Gas Cooled Fast Reactors with Natural Uranium as Fuel Cycle Input has been performed. In this study Gas Cooled Fast Reactor is slightly modified by employing modified CANDLE burn‐up scheme so that it ...
In this study optimization of modified CANDLE burnup scheme based long life Pb-Bi Cooled Fast Rea... more In this study optimization of modified CANDLE burnup scheme based long life Pb-Bi Cooled Fast Reactors with natural Uranium as Fuel Cycle Input for small long life reactors has been performed. In this design the reactor cores are subdivided into several parts with the same volume in the axial directions. The natural uranium is initially put in region 1, after one cycle of 10 years of burn-up it is shifted to region 2 and the region 1 is filled by fresh natural uranium fuel. This concept is basically applied to all regions, i.e. shifted the core of I’th region into I+1 region after the end of 10 years burn-up cycle. In this paper we discuss the characteristics of several designs of small long life Pb-Bi cooled fast reactors with modified CANDLE burn-up scheme. Four power levels of 250MWt, 400MWt, 600MWt, and 800MWt were investigated. For 250MWt and 400MWt cores we employed 67.5% high fuel volume fraction nitride fuels with large pin diameter of 1.35 cm while for 600and 800MWt cores w...
One of the most important aspects in nuclear reactor design process is the safety aspect. Advance... more One of the most important aspects in nuclear reactor design process is the safety aspect. Advanced and accurate safety simulation must be performed before it can be built. This research aims to develop a simulation model of Nuclear Power Plant (NPP) accidents due to the loss of heat sink system. Loss of heat sink accident was triggered by the loss of cooling capability of steam generators. This accident sequence began with the loss of the reactor’s ability to remove heat from the secondary cooling loop. During the accident, the heat dissipation rate decreased whereas the coolant inlet temperatures increased till a new equilibrium level. The analysis results of the accident showed that there are large safety margin to the maximum temperature of the fuel, cladding, and coolant.
International Journal of Nuclear Energy Science and Technology, 2012
ABSTRACT In this study application of modified CANDLE burn-up scheme for medium-sized (800-1500 M... more ABSTRACT In this study application of modified CANDLE burn-up scheme for medium-sized (800-1500 MWt) long-life Pb-Bi cooled fast reactors with natural uranium as fuel cycle input has been performed. The reactor cores are subdivided into several parts with equal volume in the axial directions. The natural uranium is initially put in region 1, after one cycle of 10 years of burn-up it is shifted to region 2, and 10 years after that it is shifted to region 3. This concept is applied to all regions, i.e. shifted the core of I-th region into I+1 region after the end of 10 years burn-up cycle. The first region 1 is filled by fresh natural uranium fuel. The core radial size is optimised to give maximum power density around 400 W/cc.
ABSTRACT Corrosion of structural materials in high temperature molten lead-bismuth eutectic is a ... more ABSTRACT Corrosion of structural materials in high temperature molten lead-bismuth eutectic is a major problem for design of PbBi cooled reactor. One technique to inhibit corrosion process is to inject oxygen into coolant. In this paper we study and focus on a way of inhibiting the corrosion of iron using molecular dynamics method. For the simulation results we concluded that effective corrosion inhibition of iron may be achieved by injection 0.0532 wt% to 0.1156 wt% oxygen into liquid lead-bismuth. At this oxygen concentration the structure of iron material will be maintained at about 70% in bcc crystal structure during interaction with liquid metal.
International Journal of Nuclear Energy Science and Technology, 2010
Local blockage is one of the possible severe accidents which may occur in lead (Pb)-or lead-bismu... more Local blockage is one of the possible severe accidents which may occur in lead (Pb)-or lead-bismuth (Pb-Bi)-cooled fast reactors due to their high melting temperature. In a local blockage accident, the local temperature increase cannot significantly reduce power level ...
In this study a fesibility design study of medium sized (1000 MWt) gas cooled fast reactors which... more In this study a fesibility design study of medium sized (1000 MWt) gas cooled fast reactors which can utilize natural uranium as fuel cycle input has been conducted. Gas Cooled Fast Reactor (GFR) is among six types of Generation IV Nuclear Power Plants. GFR with its hard neuron spectrum is superior for closed fuel cycle, and its ability to be operated in high temperature (850° C) makes various options of utilizations become possible. To obtain the capability of consuming natural uranium as fuel cycle input, modified CANDLE burn-up scheme[1-6] is adopted this GFR system by dividing the core into 10 parts of equal volume axially. Due to the limitation of thermal hydraulic aspects, the average power density of the proposed design is selected about 70 W/cc. As an optimization results, a design of 1000 MWt reactors which can be operated 10 years without refueling and fuel shuffling and just need natural uranium as fuel cycle input is discussed. The average discharge burn-up is about 280 GWd/ton HM. Enough margin for criticallity was obtained for this reactor.
ABSTRACT In this paper we report molecular dynamics simulation results of iron (cladding) corrosi... more ABSTRACT In this paper we report molecular dynamics simulation results of iron (cladding) corrosion in interaction with lead coolant of fast nuclear reactor. The goal of this work is to study effect of oxygen injection to the coolant to reduce iron corrosion. By evaluating diffusion coefficients, radial distribution functions, mean-square displacement curves and observation of crystal structure of iron before and after oxygen injection, we concluded that a significant reduction of corrosion can be achieved by issuing about 2% of oxygen atoms into lead coolant.
ABSTRACT In this present work, we report numerical results of iron (cladding) corrosion study in ... more ABSTRACT In this present work, we report numerical results of iron (cladding) corrosion study in interaction with lead-bismuth eutectic coolant of advanced nuclear reactors. The goal of this work is to study how the oxygen can be used to reduce the corrosion rate of cladding. The molecular dynamics method was applied to simulate corrosion process. By evaluating the diffusion coefficients, RDF functions, MSD curves of the iron and also observed the crystal structure of iron before and after oxygen injection to the coolant then we concluded that a significant and effective reduction can be achieved by issuing about 2% number of oxygen atoms to lead-bismuth eutectic coolant.
In this paper, conceptual design study of Small Long‐life Gas Cooled Fast Reactors with Natural U... more In this paper, conceptual design study of Small Long‐life Gas Cooled Fast Reactors with Natural Uranium as Fuel Cycle Input has been performed. In this study Gas Cooled Fast Reactor is slightly modified by employing modified CANDLE burn‐up scheme so that it ...
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