Author: Charles L. Whitmarsh (Jr.)
Publisher:
ISBN:
Category : Fast reactors
Languages : en
Pages : 52
Book Description
Neutronic Design for a Lithium-cooled Reactor for Space Applications
Author: Charles L. Whitmarsh (Jr.)
Publisher:
ISBN:
Category : Fast reactors
Languages : en
Pages : 52
Book Description
Publisher:
ISBN:
Category : Fast reactors
Languages : en
Pages : 52
Book Description
Neutronic Design for a Lithium-cooled Reactor for Space Applications
Author: Charles L. Whitmarsh
Publisher:
ISBN:
Category :
Languages : en
Pages : 39
Book Description
Publisher:
ISBN:
Category :
Languages : en
Pages : 39
Book Description
Neutronic Design for a Lithium-cooled Reactor for Space Applications
Author: Charles L. Whitmarsh (Jr.)
Publisher:
ISBN:
Category : Fast reactors
Languages : en
Pages : 0
Book Description
Publisher:
ISBN:
Category : Fast reactors
Languages : en
Pages : 0
Book Description
Neutronic Design and Optimization of a Porous-fuel, High-temperature, Gas-cooled Reactor for Space Power and Propulsion Applications
Author: Eddy Perez Cardentey
Publisher:
ISBN:
Category :
Languages : en
Pages :
Book Description
ABSTRACT: Nuclear reactors are currently being considered for space power and propulsion applications. The system we examined uses a porous fuel matrix as the thermal interchange medium. Its intended use is in thermal propulsion systems, but it can also be applied to electric propulsion systems, and as a source of auxiliary power. The reactor would be used as a power source for interplanetary robotic or manned missions. Our goal was to develop an optimized relation between fuel density and reactor dimensions.
Publisher:
ISBN:
Category :
Languages : en
Pages :
Book Description
ABSTRACT: Nuclear reactors are currently being considered for space power and propulsion applications. The system we examined uses a porous fuel matrix as the thermal interchange medium. Its intended use is in thermal propulsion systems, but it can also be applied to electric propulsion systems, and as a source of auxiliary power. The reactor would be used as a power source for interplanetary robotic or manned missions. Our goal was to develop an optimized relation between fuel density and reactor dimensions.
A 1-megawatt Reactor Design for Brayton-cycle Space Power Application
Author: C. L. Whitmarsh
Publisher:
ISBN:
Category : Brayton cycle
Languages : en
Pages : 36
Book Description
Publisher:
ISBN:
Category : Brayton cycle
Languages : en
Pages : 36
Book Description
NASA Technical Note
Author:
Publisher:
ISBN:
Category :
Languages : en
Pages : 574
Book Description
Publisher:
ISBN:
Category :
Languages : en
Pages : 574
Book Description
System Modeling and Reactor Design Study of an Advanced Incore Thermionic Space Reactor
Author: Hsing Hui Lee
Publisher:
ISBN:
Category : Space vehicles
Languages : en
Pages : 284
Book Description
Incore thermionic space reactor design concepts which operate at a nominal power output range of 20 to 50 kWe are described. Details of the neutronic, thermionic, thermal hydraulics and shielding performance are presented. Due to the strong absorption of thermal neutrons by natural tungsten, and the large amount of that material within the reactor core, two designs are considered. An overall system design code has been developed at Oregon State University to model advanced incore thermionic energy conversion based nuclear reactor systems for space applications. The code modules include neutronics and core criticality, a thermionic fuel element performance module with integral thermal hydraulics calculation capability, a radiation shielding module, and a module for the waste heat rejection. The results show that the driverless single cell ATI configuration, which does not have driver rods, proved to be more efficient than the driven core, which has driver rods. It also shows that the inclusion of the true axial and radial power distribution decrease the overall conversion efficiency. The flattening of the radial power distribution by three different methods would lead to a higher efficiency. The results show that only one thermionic fuel element (TFE) works at the optimum emitter temperature; all other TFEs are off the optimum performance and result in 40 % decrease of the efficiency of the overall system.
Publisher:
ISBN:
Category : Space vehicles
Languages : en
Pages : 284
Book Description
Incore thermionic space reactor design concepts which operate at a nominal power output range of 20 to 50 kWe are described. Details of the neutronic, thermionic, thermal hydraulics and shielding performance are presented. Due to the strong absorption of thermal neutrons by natural tungsten, and the large amount of that material within the reactor core, two designs are considered. An overall system design code has been developed at Oregon State University to model advanced incore thermionic energy conversion based nuclear reactor systems for space applications. The code modules include neutronics and core criticality, a thermionic fuel element performance module with integral thermal hydraulics calculation capability, a radiation shielding module, and a module for the waste heat rejection. The results show that the driverless single cell ATI configuration, which does not have driver rods, proved to be more efficient than the driven core, which has driver rods. It also shows that the inclusion of the true axial and radial power distribution decrease the overall conversion efficiency. The flattening of the radial power distribution by three different methods would lead to a higher efficiency. The results show that only one thermionic fuel element (TFE) works at the optimum emitter temperature; all other TFEs are off the optimum performance and result in 40 % decrease of the efficiency of the overall system.
Nuclear Science Abstracts
Author:
Publisher:
ISBN:
Category : Nuclear energy
Languages : en
Pages : 852
Book Description
Publisher:
ISBN:
Category : Nuclear energy
Languages : en
Pages : 852
Book Description
Space Nuclear-power Reactor Design Based on Combined Neutronic and Thermal-fluid Analyses
Author:
Publisher:
ISBN:
Category :
Languages : en
Pages :
Book Description
The design and performance analysis of a space nuclear-power system requires sophisticated analytical capabilities such as those developed during the nuclear rocket propulsion (Rover) program. In particular, optimizing the size of a space nuclear reactor for a given power level requires satisfying the conflicting requirements of nuclear criticality and heat removal. The optimization involves the determination of the coolant void (volume) fraction for which the reactor diameter is a minimum and temperature and structural limits are satisfied. A minimum exists because the critical diameter increases with increasing void fraction, whereas the reactor diameter needed to remove a specified power decreases with void fraction. The purpose of this presentation is to describe and demonstrate our analytical capability for the determination of minimum reactor size. The analysis is based on combining neutronic criticality calculations with OPTION-code thermal-fluid calculations.
Publisher:
ISBN:
Category :
Languages : en
Pages :
Book Description
The design and performance analysis of a space nuclear-power system requires sophisticated analytical capabilities such as those developed during the nuclear rocket propulsion (Rover) program. In particular, optimizing the size of a space nuclear reactor for a given power level requires satisfying the conflicting requirements of nuclear criticality and heat removal. The optimization involves the determination of the coolant void (volume) fraction for which the reactor diameter is a minimum and temperature and structural limits are satisfied. A minimum exists because the critical diameter increases with increasing void fraction, whereas the reactor diameter needed to remove a specified power decreases with void fraction. The purpose of this presentation is to describe and demonstrate our analytical capability for the determination of minimum reactor size. The analysis is based on combining neutronic criticality calculations with OPTION-code thermal-fluid calculations.
Scientific and Technical Aerospace Reports
Author:
Publisher:
ISBN:
Category : Aeronautics
Languages : en
Pages : 1460
Book Description
Lists citations with abstracts for aerospace related reports obtained from world wide sources and announces documents that have recently been entered into the NASA Scientific and Technical Information Database.
Publisher:
ISBN:
Category : Aeronautics
Languages : en
Pages : 1460
Book Description
Lists citations with abstracts for aerospace related reports obtained from world wide sources and announces documents that have recently been entered into the NASA Scientific and Technical Information Database.