babak khanbabaei - Academia.edu (original) (raw)

Uploads

Papers by babak khanbabaei

Research paper thumbnail of Study of Antiprotons as Drivers in Inertial Confinement Fusion by Fast Ignition Method

Physica Scripta

Inertial confinement fusion is a promising approach to achieve controlled nuclear fusion for clea... more Inertial confinement fusion is a promising approach to achieve controlled nuclear fusion for clean and abundant energy production. One of the key challenges in Inertial confinement fusion is achieving efficient ignition of the fusion fuel. Fast ignition offers a potential solution to this challenge by using an ultra-high intensity laser or a charged particle beam to directly ignite a pre-compressed fusion fuel. In this manuscript, we propose an approach for fast ignition in ICF, utilizing an antiproton beam to drive ignition in a deuteron-tritium fuel with a uranium-238 seed. The use of antiproton beams in Inertial confinement fusion offers unique advantages, including their ability to deposit energy deeply into the fuel, leading to enhanced energy coupling and heating. The addition of uranium-238 as a seed material in the fuel can further improve ignition conditions by enhancing energy deposition and facilitating ignition reactions. We present detailed simulations and analyses to d...

Research paper thumbnail of Effects of beam radius and wobbling frequency on the uniformity of target implosion in direct-drive heavy ion fusion approach

Indian Journal of Physics

Research paper thumbnail of Effect of inactive impurity ions on deuteron beam‐fusion in fast ignition approach

Contributions to Plasma Physics

Research paper thumbnail of An Investigation of Effective Parameters in Deuterium-Tritium Fuel Gains in Shock Ignition Method Driven by Laser Beams

Shock ignition (SI) is one of the methods considered in the concept of inertial confinement fusio... more Shock ignition (SI) is one of the methods considered in the concept of inertial confinement fusion (ICF). This two-step ICF process separates fuel assembly and ignition, relaxing the driver requirements and promising high gains. In SI scheme, a strong spherical shock wave converging at the end of the initial laser pulse ignites the pre-compressed fuel. In shock ignition, when the hot spot pressure is much higher than the surrounding cold fuel pressure, the fuel structure is considered non-isobaric. In this research, ignition conditions and fuel efficiency in shock ignition method were investigated. Then, the fuel efficiency correlations of total fuel energy, fuel gain and hot-spot radius in a non-isobaric model of fuel assembly were improved and compared with the numerical results of deuterium-tritium (DT) homogeneous fuel in SI scenario. Calculations showed that the hot spot formation conditions depend on the hot spot density and the surrounding cold fuel. Furthermore, using the im...

Research paper thumbnail of CFD-Calculation of Fluid Flow in VVER-1000 Reactors

Journal of Applied Sciences, 2008

Research paper thumbnail of CFD-Calculation of Fluid Flow in a Pressurized Water Reactor

Journal of Sciences, Islamic …, 2008

An accurate description of the fluid flow and heat transfer within a Pressurized Water Reactor (P... more An accurate description of the fluid flow and heat transfer within a Pressurized Water Reactor (PWR), for the safety analysis and reactor performance is always desirable. In this paper a mathematical model of the fundamental physical phenomena which are associated to a typical PWR is presented. The mathematical model governs the fluid dynamics in the reactor. Using commercial software CFX, a computational fluid dynamics (CFD) code, a three-dimensional flow distribution in the downcomer and the lower plenum of the reactor was also calculated and a valuable analysis of the reactor performance is given. Due to computational limits, simplifications of the core, downcomer and the lower plenum of the reactor are introduced. Nevertheless, it has been shown that computational fluid dynamics and in particular appropriate usage of CFX software improves our understanding of fluid flow distribution, velocity distribution and heat transfer in different parts of the reactor pressure vessel, in particular, in the downcomer and the lower plenum.

Research paper thumbnail of CFD analysis of coolant flow at bushehr nuclear reactor

The influence of fluid flow and heat transfer study within a Pressurized Water Reactor is of sign... more The influence of fluid flow and heat transfer study within a Pressurized Water Reactor is of significant importance for the demonstration of the reactor performance and its safety in both steady and transient states. In the present pa-per, the three dimensional flow distributions in the downcomer and the lower plenum of the reactor were calculated with the computational fluid dynamics (CFD) codes. Calculations were performed for the VVER-1000, V446 reac-tor at the Bushehr nuclear power plant, Iran. Although CFD codes provide an effective tool for the calculation of flow distribution in the reactor pressure vessel (RPV), computer capacity puts restrictions on the capacity of CFD calculations. Consequently, simplified models had to be used in simulating the RPV. Nevertheless, our investigation shows a reasonable agreement between the numerical results and the measured data.

Research paper thumbnail of The Role of Athermal Fusion in Fast Ignition Driven by Ion Beams

Romanian Journal of Physics

The fast ignition scheme is recognized as a potentially promising approach to achieve the high-en... more The fast ignition scheme is recognized as a potentially promising approach to achieve the high-energy-gain target performance needed for commercial inertial confinement fusion. The hot spot heating process by an assumed deuteron beam is evaluated in order to estimate the contribution of the energy produced by the deuteron beam-target fusion to the heating process. So, deuteron beam was considered with Maxwellian energy distribution at temperature of 3MeV. Then, the deuteron energy loss and range, Includes Coulomb and nuclear elastic interactions, in the uniformly pre-compressed fuel, with density 300gcm-3, were calculated. By calculating the contribution of alpha particles produced by the athermal nuclear reactions and nuclear elastic scattering, power deposition of deuteron beams increased up 6% compared with the fast ignition by similar ion beams. This can lead to reduced energy delivered by the external beam.

Research paper thumbnail of Deuterium–tritium catalytic reaction in fast ignition: Optimum parameters approach

Pramana, 2014

One of the main concerns about the current working on nuclear power reactors is the potential haz... more One of the main concerns about the current working on nuclear power reactors is the potential hazard of their radioactive waste. There is hope that this issue will be reduced in next generation nuclear fusion power reactors. Reactors will release nuclear energy through microexplosions that occur in a mixture of hydrogen isotopes of deuterium and tritium. However, there exist radiological hazards due to the accumulation of tritium in the blanket layer. A catalytic fusion reaction of DT x mixture may stand between DD and an equimolar DT approach in which the fusion process continues with a small amount of tritium seed. In this paper, we investigate the possibility of DT x reaction in the fast ignition (FI) scheme. The kinematic study of the main mechanism of the energy gain-loss term, which may disturb the ignition and burn process, was performed in FI and the optimum values of precompressed fuel and proton beam driver were derived. The recommended values of fuel parameters are: areal density ρR ≥ 5 g • cm −2 and initial tritium fraction x ≤ 0.025. For the proton beam, the corresponding optimum interval values are proton average energy 3 ≤ E p ≤ 10 MeV, pulse duration 5 ≤ t p ≤ 15 ps and power 5 ≤ W p ≤ 12 ×10 22 (keV • cm 3 • ps −1). It was proved that under the above conditions, a fast ignition DT x reaction stays in the catalytic regime.

Research paper thumbnail of Study of Antiprotons as Drivers in Inertial Confinement Fusion by Fast Ignition Method

Physica Scripta

Inertial confinement fusion is a promising approach to achieve controlled nuclear fusion for clea... more Inertial confinement fusion is a promising approach to achieve controlled nuclear fusion for clean and abundant energy production. One of the key challenges in Inertial confinement fusion is achieving efficient ignition of the fusion fuel. Fast ignition offers a potential solution to this challenge by using an ultra-high intensity laser or a charged particle beam to directly ignite a pre-compressed fusion fuel. In this manuscript, we propose an approach for fast ignition in ICF, utilizing an antiproton beam to drive ignition in a deuteron-tritium fuel with a uranium-238 seed. The use of antiproton beams in Inertial confinement fusion offers unique advantages, including their ability to deposit energy deeply into the fuel, leading to enhanced energy coupling and heating. The addition of uranium-238 as a seed material in the fuel can further improve ignition conditions by enhancing energy deposition and facilitating ignition reactions. We present detailed simulations and analyses to d...

Research paper thumbnail of Effects of beam radius and wobbling frequency on the uniformity of target implosion in direct-drive heavy ion fusion approach

Indian Journal of Physics

Research paper thumbnail of Effect of inactive impurity ions on deuteron beam‐fusion in fast ignition approach

Contributions to Plasma Physics

Research paper thumbnail of An Investigation of Effective Parameters in Deuterium-Tritium Fuel Gains in Shock Ignition Method Driven by Laser Beams

Shock ignition (SI) is one of the methods considered in the concept of inertial confinement fusio... more Shock ignition (SI) is one of the methods considered in the concept of inertial confinement fusion (ICF). This two-step ICF process separates fuel assembly and ignition, relaxing the driver requirements and promising high gains. In SI scheme, a strong spherical shock wave converging at the end of the initial laser pulse ignites the pre-compressed fuel. In shock ignition, when the hot spot pressure is much higher than the surrounding cold fuel pressure, the fuel structure is considered non-isobaric. In this research, ignition conditions and fuel efficiency in shock ignition method were investigated. Then, the fuel efficiency correlations of total fuel energy, fuel gain and hot-spot radius in a non-isobaric model of fuel assembly were improved and compared with the numerical results of deuterium-tritium (DT) homogeneous fuel in SI scenario. Calculations showed that the hot spot formation conditions depend on the hot spot density and the surrounding cold fuel. Furthermore, using the im...

Research paper thumbnail of CFD-Calculation of Fluid Flow in VVER-1000 Reactors

Journal of Applied Sciences, 2008

Research paper thumbnail of CFD-Calculation of Fluid Flow in a Pressurized Water Reactor

Journal of Sciences, Islamic …, 2008

An accurate description of the fluid flow and heat transfer within a Pressurized Water Reactor (P... more An accurate description of the fluid flow and heat transfer within a Pressurized Water Reactor (PWR), for the safety analysis and reactor performance is always desirable. In this paper a mathematical model of the fundamental physical phenomena which are associated to a typical PWR is presented. The mathematical model governs the fluid dynamics in the reactor. Using commercial software CFX, a computational fluid dynamics (CFD) code, a three-dimensional flow distribution in the downcomer and the lower plenum of the reactor was also calculated and a valuable analysis of the reactor performance is given. Due to computational limits, simplifications of the core, downcomer and the lower plenum of the reactor are introduced. Nevertheless, it has been shown that computational fluid dynamics and in particular appropriate usage of CFX software improves our understanding of fluid flow distribution, velocity distribution and heat transfer in different parts of the reactor pressure vessel, in particular, in the downcomer and the lower plenum.

Research paper thumbnail of CFD analysis of coolant flow at bushehr nuclear reactor

The influence of fluid flow and heat transfer study within a Pressurized Water Reactor is of sign... more The influence of fluid flow and heat transfer study within a Pressurized Water Reactor is of significant importance for the demonstration of the reactor performance and its safety in both steady and transient states. In the present pa-per, the three dimensional flow distributions in the downcomer and the lower plenum of the reactor were calculated with the computational fluid dynamics (CFD) codes. Calculations were performed for the VVER-1000, V446 reac-tor at the Bushehr nuclear power plant, Iran. Although CFD codes provide an effective tool for the calculation of flow distribution in the reactor pressure vessel (RPV), computer capacity puts restrictions on the capacity of CFD calculations. Consequently, simplified models had to be used in simulating the RPV. Nevertheless, our investigation shows a reasonable agreement between the numerical results and the measured data.

Research paper thumbnail of The Role of Athermal Fusion in Fast Ignition Driven by Ion Beams

Romanian Journal of Physics

The fast ignition scheme is recognized as a potentially promising approach to achieve the high-en... more The fast ignition scheme is recognized as a potentially promising approach to achieve the high-energy-gain target performance needed for commercial inertial confinement fusion. The hot spot heating process by an assumed deuteron beam is evaluated in order to estimate the contribution of the energy produced by the deuteron beam-target fusion to the heating process. So, deuteron beam was considered with Maxwellian energy distribution at temperature of 3MeV. Then, the deuteron energy loss and range, Includes Coulomb and nuclear elastic interactions, in the uniformly pre-compressed fuel, with density 300gcm-3, were calculated. By calculating the contribution of alpha particles produced by the athermal nuclear reactions and nuclear elastic scattering, power deposition of deuteron beams increased up 6% compared with the fast ignition by similar ion beams. This can lead to reduced energy delivered by the external beam.

Research paper thumbnail of Deuterium–tritium catalytic reaction in fast ignition: Optimum parameters approach

Pramana, 2014

One of the main concerns about the current working on nuclear power reactors is the potential haz... more One of the main concerns about the current working on nuclear power reactors is the potential hazard of their radioactive waste. There is hope that this issue will be reduced in next generation nuclear fusion power reactors. Reactors will release nuclear energy through microexplosions that occur in a mixture of hydrogen isotopes of deuterium and tritium. However, there exist radiological hazards due to the accumulation of tritium in the blanket layer. A catalytic fusion reaction of DT x mixture may stand between DD and an equimolar DT approach in which the fusion process continues with a small amount of tritium seed. In this paper, we investigate the possibility of DT x reaction in the fast ignition (FI) scheme. The kinematic study of the main mechanism of the energy gain-loss term, which may disturb the ignition and burn process, was performed in FI and the optimum values of precompressed fuel and proton beam driver were derived. The recommended values of fuel parameters are: areal density ρR ≥ 5 g • cm −2 and initial tritium fraction x ≤ 0.025. For the proton beam, the corresponding optimum interval values are proton average energy 3 ≤ E p ≤ 10 MeV, pulse duration 5 ≤ t p ≤ 15 ps and power 5 ≤ W p ≤ 12 ×10 22 (keV • cm 3 • ps −1). It was proved that under the above conditions, a fast ignition DT x reaction stays in the catalytic regime.