The CIT (compact Ignition Tokamak) Pellet Injection System PDF Download
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Author: Publisher: ISBN: Category : Languages : en Pages : 5
Book Description
The Compact Ignition Tokamak (CIT) will use an advance, high-velocity pellet injection system to achieve and maintain ignited plasmas. Two pellet injectors are provided: a moderate-velocity (1-to 1.5-km/s), single-stage pneumatic injector with high reliability and a high-velocity (4- to 5-km/s), two-stage pellet injector that uses frozen hydrogenic pellets encased in sabots. Both pellet injectors are qualified for operation with tritium feed gas. Issues such as performance, neutron activation of injector components, maintenance, design of the pellet injection vacuum line, gas loads to the reprocessing system, and equipment layout are discussed. Results and plans for supporting research and development (R and D) in the areas of tritium pellet fabrication and high-velocity, repetitive two-stage pneumatic injectors are presented. 7 refs., 4 figs., 2 tabs.
Author: Publisher: ISBN: Category : Languages : en Pages : 5
Book Description
The Compact Ignition Tokamak (CIT) will use an advance, high-velocity pellet injection system to achieve and maintain ignited plasmas. Two pellet injectors are provided: a moderate-velocity (1-to 1.5-km/s), single-stage pneumatic injector with high reliability and a high-velocity (4- to 5-km/s), two-stage pellet injector that uses frozen hydrogenic pellets encased in sabots. Both pellet injectors are qualified for operation with tritium feed gas. Issues such as performance, neutron activation of injector components, maintenance, design of the pellet injection vacuum line, gas loads to the reprocessing system, and equipment layout are discussed. Results and plans for supporting research and development (R and D) in the areas of tritium pellet fabrication and high-velocity, repetitive two-stage pneumatic injectors are presented. 7 refs., 4 figs., 2 tabs.
Author: Publisher: ISBN: Category : Languages : en Pages :
Book Description
The conceptual design of the Compact Ignition Tokamak (CIT) is nearing completion. The CIT is a short-pulse ignition experiment, which is planned to follow the operations of the Tokamak Fusion Test Reactor (TFTR) at the Princeton Plasma Physics Laboratory (PPPL). The high neutron wall loadings, 4--5 MW/m2, associated with the operation of this device require that neutronics-related issues be considered in the overall system design. Radiation shielding is required for the protection of device components as well as personnel. A close-in igloo shield has been designed around the periphery of the tokamak structure, and the entire experiment is housed in a circular test cell facility that has a radius of 12 m. The most critical radiation concerns in the CIT design process relate to the numerous penetrations in the device. This report discusses the impact of a major penetration on the design and operation of the pellet injection system in the CIT. The pellet injector is a major component, and it has a line-of-sight penetration through the igloo and test cell wall. All current options for maintenance of the injector require hands-on-access. A nuclear analysis has been performed to establish the feasibility of hands-on-access. A coupled Monte Carlo/discrete-ordinates methodology was used to perform the analysis. This problem is characterized by deep penetration and streaming with very large length-to-diameter ratios. Results from this study indicate that personnel access to the pellet injector glovebox is possible. 14 refs., 3 figs., 3 tabs.
Author: Publisher: ISBN: Category : Languages : en Pages :
Book Description
The Compact Ignition Tokamak (CIT) is a proposed modest-size ignition experiment designed to study the physics of alpha-particle heating. The basic concept is to achieve ignition in a modest-size minimum cost experiment by using a high plasma density to achieve the condition of ntau/sub E/ approx. 2 x 102° sec m−3 required for ignition. The high density requires a high toroidal field (10 T). The high toroidal field allows a large plasma current (10 MA) which improves the energy confinement, and provides a high level of ohmic heating. The present CIT design also has a gigh degree of elongation (k approx. 1.8) to aid in producing the large plasma current. A double null poloidal divertor and a pellet injector are part of the design to provide impurity and particle control, improve the confinement, and provide flexibility for impurity and particle control, improve the confinement, and provide flexibility for improving the plasma profiles. Since auxiliary heating is expected to be necessary to achieve ignition, 10 to 20 MW of Ion Cyclotron Radio Frequency (ICRF) is to be provided.
Author: Publisher: ISBN: Category : Languages : en Pages :
Book Description
The Compact Ignition Tokamak is designed to obtain extensive scientific and technological data in support of burning-plasma operation in the Engineering Test Reactor and beyond. 8 figs., 3 tabs.
Author: Publisher: ISBN: Category : Languages : en Pages :
Book Description
Extensive experience with previous fusion experiments (TFTR, MFTF-B and others) is driving the design of the Instrumentation and Control System (I and C) for the Compact Ignition Tokamak (CIT) to be built at Princeton. The new design will reuse much equipment from TFTR and will be subdivided into six major parts: machine control, machine data acquisition, plasma diagnostic instrument control and instrument data acquisition, the database, shot sequencing and safety interlocks. In a major departure from previous fusion experiment control systems, the CIT machine control system will be a commercial process control system. Since the machine control system will be purchased as a completely functional product, we will be able to concentrate development manpower in plasma diagnostic instrument control, data acquisition, data processing and analysis, and database systems. We will discuss the issues driving the design, give a design overview and state the requirements upon any prospective commercial process control system.
Author: Publisher: ISBN: Category : Languages : en Pages :
Book Description
As the next major step in the US fusion program, the Compact Ignition Tokamak (CIT) Project has the objective of reaching ignition in order to address the scientific issues associated with ignited plasma regimes. The present level of uncertainty in plasma confinement scaling requires that the CIT have a high design margin to ensure ignition. The need for adequate margin, coupled with declining budgets in the US fusion program, requires both conservatism and flexibility in the development of the design and operating parameters for the device. To accomplish this, the design includes the provision for an upgrade in performance, which will be partially built into the initial machine installation at Princeton Plasma Physics Laboratory (PPPL). 8 refs., 9 figs., 1 tab.
Author: Publisher: ISBN: Category : Languages : en Pages :
Book Description
The Compact Ignition Tokamak (CIT) device is planned as the next major fusion device to be built at the Princeton Plasma Physics Laboratory to demonstrate ignition operations of a burning plasma. Stringent engineering requirements have been imposed on this device by physics necessities of high margins against ignition and by cost constraints in minimizing the overall cost of the project. A compact design has been developed under these design conditions incorporating many unique design features, including a hydraulic preload system to provide a compression load to the toroidal field (TF) inner leg and using a high-strength copper-Inconel composite material in the design of the TF coil and the ohmic heating solenoid. The device is inertially cooled by liquid nitrogen, and the vacuum vessel, coils, and supporting structure are contained in a thermally insulated cryostat. A close-in igloo shield surrounds the device to provide the capability for hands-on access within the test cell and also to minimize activation. Even with the compact nature of this device, there still remains the basic requirement of maximizing access to the plasma for diagnostics and heating components; access for electrical leads and coolant lines; and access to provide the capability of remotely maintaining all diagnostic and peripheral equipment that interfaces with the device. This paper describes the configurational development that has taken place during the conceptual design period of the CIT project, highlighting the major design integration features used to develop a functional device that meets the physics and component design requirements. 1 ref., 7 figs.
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Author: D. P. Stotler
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