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Author: Douglas Pulley
Publisher:
ISBN:
Category : Fusion reactors
Languages : en
Pages : 230
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Book Description
Author: Douglas Pulley
Publisher:
ISBN:
Category : Fusion reactors
Languages : en
Pages : 230
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Book Description
Author: Tetsuo Tanabe
Publisher: Springer
ISBN: 4431564608
Category : Technology & Engineering
Languages : en
Pages : 365
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Book Description
This book focuses on tritium as a fuel for fusion reactors and a next-generation energy source. Following an introduction of tritium as a hydrogen radioisotope, important issues involved in establishing safe and economical tritium fuel cycles including breeding for a fusion reactor are summarized; these include the handling of large amounts of tritium: confinement, leakage, contamination, permeation, regulation and tritium accountancy, and impacts on surrounding areas. Targeting and encouraging the students and technicians who will design and operate fusion reactors in the near future, this book offers a valuable resource on tritium science and technology.
Author: F. Mannone
Publisher: Springer Science & Business Media
ISBN: 9401119104
Category : Technology & Engineering
Languages : en
Pages : 241
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Book Description
The use of tritium as a basic fuel material in a thermonuclear fusion reactor raises particular safety issues due to the combined effects of its physico chemical properties and radioactive nature. Furthermore the possibility of attaining further significant progresses in developing and demonstrating the feasibility of tritium burning devices relies on the handling of tritium macroquantities, say ten grammes, in a safe and reliable manner. It is also undoubted that, apart from technological constraints, any validation and exploitation of thermonuclear fusion as a source of energy will be strongly conditioned by the application of stringent operational and environmental safety criteria as it derives from norms of the modern legislation and public acceptance considerations. Even if the safe handling of tritium has already been demonstrated to be feasible on a full fuel cycle scale, it is unanimously recognized that further efforts are still to be concentrated on the improvement of current concepts and development of advanced technologies. Some of the areas requiring substantial additional efforts are plasma exhaust fuel c1ean-up, tritium pellet injection, processing of inert carrier gas, development of large free-oil pumps,tritlUm process analytics, development of large detritiation systems, beryllium-tritium interaction studies, tritium hold-up studies in getter beds, adsorbers and structural materials, tritium recovery from first wall, structural and breeder materials for minimizing tritiated waste arising,tritium storage technology, tritiated waste disposal technolo~y, methodology for routine tritium accountancy,etc . . Most of them are intrinsically related to the safety requirement of tritium technology.
Author: National Research Council
Publisher: National Academies Press
ISBN: 0309272246
Category : Science
Languages : en
Pages : 247
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Book Description
The potential for using fusion energy to produce commercial electric power was first explored in the 1950s. Harnessing fusion energy offers the prospect of a nearly carbon-free energy source with a virtually unlimited supply of fuel. Unlike nuclear fission plants, appropriately designed fusion power plants would not produce the large amounts of high-level nuclear waste that requires long-term disposal. Due to these prospects, many nations have initiated research and development (R&D) programs aimed at developing fusion as an energy source. Two R&D approaches are being explored: magnetic fusion energy (MFE) and inertial fusion energy (IFE). An Assessment of the Prospects for Inertial Fusion Energy describes and assesses the current status of IFE research in the United States; compares the various technical approaches to IFE; and identifies the scientific and engineering challenges associated with developing inertial confinement fusion (ICF) in particular as an energy source. It also provides guidance on an R&D roadmap at the conceptual level for a national program focusing on the design and construction of an inertial fusion energy demonstration plant.
Author:
Publisher:
ISBN:
Category :
Languages : en
Pages :
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Book Description
The tritium handling requirements for both the ETF and the STARFIRE fusion reactor designs are analyzed. The use of a limiter/vacuum system for STARFIRE produced a high fractional burnup (0.42) which resulted in a low tritium inventory in the fueling system. The importance of a fast process flow rate is achieving a rapid cleanup after a tritium release is demonstrated; another important factor is the rate at which HTO is released from building surfaces. A complete fusion reactor tritium facility is described.
Author: International Atomic Energy Agency
Publisher:
ISBN:
Category : Business & Economics
Languages : en
Pages : 148
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Book Description
This publication contains information on the dosimetry and monitoring of tritium, the use of protective clothing for work with tritium, safe practices in tritium handling laboratories and details of tritium compatible materials. The information has been compiled from experience in the various applications of tritium and should represent valuable source material to all users of tritium, including those involved in fusion R&D.
Author: marco riva
Publisher:
ISBN:
Category :
Languages : en
Pages : 219
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Book Description
In nuclear fusion reactors, tritium dynamics plays a dominant role. An unprecedented amount of tritium is consumed in Deuterium-Tritium (D-T) nuclear fusion reactors, ~0.5 kg per day for 3 GW fusion power. However, tritium is radioactive, has short half-life (~12.33 years), and is present in nature in negligible concentration. Because of tritium scarcity, future fusion power reactors must be self-sufficient, i.e. the reactor must have a closed fuel cycle where tritium is produced in greater amounts than it is consumed. Furthermore, nuclear fusion reactors must accumulate and provide tritium start-up inventory for the next generation of fusion power plants, since natural reserves of tritium are very limited. Moreover, because of its radioactive nature, tritium presents a serious hazard to the personnel and has implications to safety and nuclear licensing. Accurate predictive models of the nuclear fusion fuel cycle are required to effectively design the fuel cycle components, understand tritium dynamics in the fusion fuel cycle, and determine the technology and physics requirements to attain tritium self-sufficiency. Moreover, accurate predictions of tritium inventories and flow rates within fusion components, and estimations of tritium releases to the environment are necessary for nuclear licensing. In this dissertation, two numerical models are developed to perform tritium transport assessment within fusion systems. First, a high fidelity numerical model is developed to simulate time-dependent tritium transport within the reactor outer fuel cycle (OFC). Detailed (high resolution) component-level models, where constitutive transport equations are implemented in COMSOL Multiphysics and solved for various fusion sub-systems, are integrated into system-level with the use of MATLAB/Simulink S-Functions to reproduce typical OFC tritium streams. The model is applied to the KOrean Helium Cooled Ceramic Reflector Test Blanket System (KO-HCCR TBS) which will be tested in the International Thermonuclear Experimental Reactor (ITER). However, the developed model offers some flexibility and can be applied to other Test Blanket Module (TBM) designs. Second, the overall fusion fuel cycle is modeled analytically by a system of time-dependent zero-dimensional ordinary differential equations with the tritium mean residence time method. This technique yields results useful for understanding the overall fuel cycle dynamics and the importance of certain components and parameters. The analysis of tritium inventories and flow rates is extended to determine the physics and technology requirements to attain tritium self-sufficiency. In particular, the state-of-the-art plasma physics and technology parameters (e.g. tritium burn fraction, fueling efficiency, processing times, etc.) and up-to-date fuel cycle design are considered in the analysis. The tritium self-sufficiency assessment and tritium start-up inventory evaluation are performed to investigate: (i) the effect of the reactor operating scenario and availability factor, e.g. to account for random failures and ordinary maintenance, (ii) the scenarios for commercialization, e.g. risk associated with tritium reserve inventory reduction, (iii) the penetration of fusion energy into power market, e.g. effect of the doubling time, and (iv) the effect of reactor power on tritium start-up inventory, e.g. for plasma-based test facilities, DEMOnstration reactors (DEMO), and power reactors. The results highlight the physics and technology R&D requirements to attain fuel self-sufficiency in fusion reactors.
Author:
Publisher:
ISBN:
Category :
Languages : en
Pages :
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A reference design study for a Mirror Fusion Hybrid Reactor has been completed which examines the tritium handling problems. Breeding pins composed of aluminum alloys contain lithium hydride with a four-year residence time for tritium production. The slip-stream helium tritium capture system is designed to handle a 0.1 percent pin failure and will reduce environmental losses to below 3 Ci/day. The neutral beam injectors and direct converters utilize small, thin electrode tubes at 700°C for accelerating the deuterium or tritium, and they will by triton implantation permeate about 3 x 105 Ci/day into the internal helium coolant flow. A capture system will reduce these losses to 6 Ci/day, combined. The reactor hall is designed with a low humidity, air atmosphere which is continuously processed in order to handle leakage and permeability losses from the nuclear island at 180 Ci/day while still maintaining levels of tritium below MPC. The precessor is also able to handle severe accidental releases of tritium at the 26 kilogram level and permit worker re-entry (with ventilated suits) in a matter of about one week. These approaches to fusion power plant are found to be technically feasible today and economically attractive.
Author:
Publisher:
ISBN:
Category :
Languages : en
Pages :
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Book Description
When tritium is used in a fusion energy experiment or reactor, several implications affect and usually restrict the design and operation of the system and involve questions of containment, inventory, and radiation damage. Containment is expected to be particularly important both for high-temperature components and for those components that are prone to require frequent maintenance. Inventory is currently of major significance in cases where safety and environmental considerations limit the experiments to very low levels of tritium. Fewer inventory restrictions are expected as fusion experiments are placed in more-remote locations and as the fusion community gains experience with the use of tritium. However, the advent of power-producing experiments with high-duty cycle will again lead to serious difficulties based principally on tritium availability; cyclic operations with significant regeneration times are the principal problems.
Author:
Publisher:
ISBN:
Category : Controlled fusion
Languages : en
Pages : 88
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