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Author: Alexander Perevezentsev
Publisher: Academic Press
ISBN: 0128243236
Category : Business & Economics
Languages : en
Pages : 368
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Book Description
Tritium Technologies for Thermonuclear Fusion Reactors summarizes the most recent research and practice in tritium technologies for the processing of hydrogen isotopes in fuel cycles. Authors Dr. Perevezentsev and Professor Rozenkevich combine their wealth of first-hand experience to present this comprehensive guide which promotes the best radiation protection practices and a more sustainable way to produce power in a thermonuclear reactor plant. Applicable to both magnetic and inertial confinements of plasma, this book covers tritium processing systems, tritium recovery from the plasma chamber, and various safety systems devoted to lessening the impact on the public and environment. The readers are also led through various modeling techniques, such as the separation of hydrogen isotopes, and the detritiation of liquid and gaseous streams in dynamic and steady state operation modes. This book is a practical guide which includes various case studies and examples which will help solidify the reader’s learning. It combines the latest research of tritium technologies with applications for fusion nuclear reactors, and includes solutions and directions for the resolution of various common challenges faced. Engineers, researchers, and students of tritium technologies, fusion energy, and nuclear power generation will gain a detailed and integrated understanding of how tritium can be used within a nuclear setting, for cleaner and more efficient power generation. Guides the reader through problem solving via step-by-step processes and models Includes case studies and examples throughout, from two of the most recognized experts in the field with firsthand knowledge of the subject Presents a comprehensive, practical reference on the tritium fuel cycle for fusion reactors
Author: Alexander Perevezentsev
Publisher: Academic Press
ISBN: 0128243236
Category : Business & Economics
Languages : en
Pages : 368
Get Book Here
Book Description
Tritium Technologies for Thermonuclear Fusion Reactors summarizes the most recent research and practice in tritium technologies for the processing of hydrogen isotopes in fuel cycles. Authors Dr. Perevezentsev and Professor Rozenkevich combine their wealth of first-hand experience to present this comprehensive guide which promotes the best radiation protection practices and a more sustainable way to produce power in a thermonuclear reactor plant. Applicable to both magnetic and inertial confinements of plasma, this book covers tritium processing systems, tritium recovery from the plasma chamber, and various safety systems devoted to lessening the impact on the public and environment. The readers are also led through various modeling techniques, such as the separation of hydrogen isotopes, and the detritiation of liquid and gaseous streams in dynamic and steady state operation modes. This book is a practical guide which includes various case studies and examples which will help solidify the reader’s learning. It combines the latest research of tritium technologies with applications for fusion nuclear reactors, and includes solutions and directions for the resolution of various common challenges faced. Engineers, researchers, and students of tritium technologies, fusion energy, and nuclear power generation will gain a detailed and integrated understanding of how tritium can be used within a nuclear setting, for cleaner and more efficient power generation. Guides the reader through problem solving via step-by-step processes and models Includes case studies and examples throughout, from two of the most recognized experts in the field with firsthand knowledge of the subject Presents a comprehensive, practical reference on the tritium fuel cycle for fusion reactors
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: 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 : Fusion reactors
Languages : en
Pages : 582
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Author:
Publisher:
ISBN:
Category :
Languages : en
Pages :
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Author: National Research Council
Publisher: National Academies Press
ISBN: 0309270626
Category : Science
Languages : en
Pages : 119
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Book Description
In the fall of 2010, the Office of the U.S. Department of Energy's (DOE's) Secretary for Science asked for a National Research Council (NRC) committee to investigate the prospects for generating power using inertial confinement fusion (ICF) concepts, acknowledging that a key test of viability for this concept-ignition -could be demonstrated at the National Ignition Facility (NIF) at Lawrence Livermore National Laboratory (LLNL) in the relatively near term. The committee was asked to provide an unclassified report. However, DOE indicated that to fully assess this topic, the committee's deliberations would have to be informed by the results of some classified experiments and information, particularly in the area of ICF targets and nonproliferation. Thus, the Panel on the Assessment of Inertial Confinement Fusion Targets ("the panel") was assembled, composed of experts able to access the needed information. The panel was charged with advising the Committee on the Prospects for Inertial Confinement Fusion Energy Systems on these issues, both by internal discussion and by this unclassified report. A Panel on Fusion Target Physics ("the panel") will serve as a technical resource to the Committee on Inertial Confinement Energy Systems ("the Committee") and will prepare a report that describes the R&D challenges to providing suitable targets, on the basis of parameters established and provided to the Panel by the Committee. The Panel on Fusion Target Physics will prepare a report that will assess the current performance of fusion targets associated with various ICF concepts in order to understand: 1. The spectrum output; 2. The illumination geometry; 3. The high-gain geometry; and 4. The robustness of the target design. The panel addressed the potential impacts of the use and development of current concepts for Inertial Fusion Energy on the proliferation of nuclear weapons information and technology, as appropriate. The Panel examined technology options, but does not provide recommendations specific to any currently operating or proposed ICF facility.
Author:
Publisher:
ISBN:
Category :
Languages : en
Pages :
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Book Description
The tritium technology requirements created by the controlled thermonuclear research program to develop a demonstration fusion power reactor by the year 2000 are reviewed. It is found that the majority of the technological advances which are needed to ensure adequate tritium containment in a tritium breeding power reactor need to be demonstrated on a pilot scale by approximately 1983, so that they may be incorporated into EPR-II, the second of two planned experimental power reactors. The most important advances include development of containment materials with permeabilities to tritium well below measured values for stainless steel; large scale, low inventory deuterium-tritium separation systems; and improved monitoring and assay systems. There are less critical requirements for information about the effects of tritium and helium on the mechanical properties of materials, the effects of tritium on biological systems, and data on physical and chemical properties of tritium. Substantial progress needs to be made on these problems early enough to permit possible solutions to be tested on EPR-I. In addition, major improvements in tritium handling equipment are required for EPR-I. Those technological problems for which solutions have not yet been demonstrated by EPR-II must be solved by 1989 if they are to be assured successful application in the demonstration reactor. (auth).
Author: Symposium on Thermonuclear Fusion Reactor Design (1970, Lubbock, Tex.)
Publisher:
ISBN:
Category : Fusion reactors
Languages : en
Pages : 452
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Author:
Publisher:
ISBN:
Category : Tritium
Languages : en
Pages : 474
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