Tritium Permeation Modelling Of A Conceptual Fusion Reactor Design
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Tritium Permeation Modelling Of A Conceptual Fusion Reactor Design
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Author : Deborah Ruth Hanchar
language : en
Publisher:
Release Date : 1981
Tritium Permeation Modelling Of A Conceptual Fusion Reactor Design written by Deborah Ruth Hanchar and has been published by this book supported file pdf, txt, epub, kindle and other format this book has been release on 1981 with Fusion reactors categories.
Tritium Permeation And Recovery For The Helium Cooled Molten Salt Fusion Breeder
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Author :
language : en
Publisher:
Release Date : 1984
Tritium Permeation And Recovery For The Helium Cooled Molten Salt Fusion Breeder written by and has been published by this book supported file pdf, txt, epub, kindle and other format this book has been release on 1984 with categories.
Design concepts are presented to control tritium permeation from a molten salt/helium fusion breeder reactor. This study assumes tritium to be a gas dissolved in molten salt, with TF formation suppressed. Tritium permeates readily through the hot steel tubes of the reactor and steam generator and will leak into the steam system at the rate of about one gram per day in the absence of special permeation barriers, assuming that 1% of the helium coolant flow rate is processed for tritium recovery at 90% efficiency per pass. The proposed permeation barrier for the reactor tubes is a 10 .mu.m layer of tungsten which, in principle, will reduce tritium blanket permeation by a factor of about 300 below the bare-steel rate. A research and development effort is needed to prove feasibility or to develop alternative barriers. A 1 mm aluminum sleeve is proposed to suppress permeation through the steam generator tubes. This gives a calculated reduction factor of more than 500 relative to bare steel, including a factor of 30 due to an assumed oxide layer. The permeation equations are developed in detail for a multi-layer tube wall including a frozen salt layer and with two fluid boundary-layer resistances. Conditions are discussed for which Sievert's or Henry's Law materials become flux limiters. An analytical model is developed to establish the tritium split between wall permeation and reactor-tube flow.
A Preliminary Concept Of Stochastic Model Of The Tritium Cycle In A Fusion Reactor
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Author : Stefan Taczanowski
language : en
Publisher:
Release Date : 1988
A Preliminary Concept Of Stochastic Model Of The Tritium Cycle In A Fusion Reactor written by Stefan Taczanowski and has been published by this book supported file pdf, txt, epub, kindle and other format this book has been release on 1988 with Fusion reactors categories.
Fusion Reactor Design Concepts
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Author : International Atomic Energy Agency
language : en
Publisher:
Release Date : 1978
Fusion Reactor Design Concepts written by International Atomic Energy Agency and has been published by this book supported file pdf, txt, epub, kindle and other format this book has been release on 1978 with Science categories.
Analysis Of Tritium Distribution And Leakage Characteristics For Two Fusion Reactor Reference Designs
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Author :
language : en
Publisher:
Release Date : 1973
Analysis Of Tritium Distribution And Leakage Characteristics For Two Fusion Reactor Reference Designs written by and has been published by this book supported file pdf, txt, epub, kindle and other format this book has been release on 1973 with categories.
From 5th sympostum on engineering problems of fusion research; Princeton, New Jersey, USA (6 Nov 1973). Results of analyses of the tritium distribution and leakage characteristics for two current fusion power reactor designs -the Princeton Reference Model Tokamak and the LASL/ANL Reference Theta Pinch Reactor--are presented and compared. The philosophy of the model used in these analyses is discussed, and the computer code, developed to carry out the calculations, is described. Consideration is given to the practical aspects of those design features which have the greatest influence on tritium inventories and leakage rates; i.e., (1) the blanket and fuel processing systems, (2) the protective atmospheres, and (3) the application of some special materials as tritium barriers. The results of these analyses have permitted several interesting comparisons to be made between a molten salt-stainless steel reactor design (the Princeton Tokamak model) and a liquid lithiumrefractory metal reactor design (the LASL/ANL Theta-Pinch model). (auth).
Some Estimates Of Tritium Permeation Rates In The Core Of A D T Fueled Fusion Reactor
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Author : Victor A. Maroni
language : en
Publisher:
Release Date : 1972
Some Estimates Of Tritium Permeation Rates In The Core Of A D T Fueled Fusion Reactor written by Victor A. Maroni and has been published by this book supported file pdf, txt, epub, kindle and other format this book has been release on 1972 with Fusion reactors categories.
Permeation Of Tritium Through The First Wall Of A Fusion Reactor Influence Of Ion Implantation
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Author : Roger Habert
language : en
Publisher:
Release Date : 1973
Permeation Of Tritium Through The First Wall Of A Fusion Reactor Influence Of Ion Implantation written by Roger Habert and has been published by this book supported file pdf, txt, epub, kindle and other format this book has been release on 1973 with categories.
Computer Simulation Of Ion Solid Interactions
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Author : Wolfgang Eckstein
language : en
Publisher: Springer Science & Business Media
Release Date : 2013-03-12
Computer Simulation Of Ion Solid Interactions written by Wolfgang Eckstein and has been published by Springer Science & Business Media this book supported file pdf, txt, epub, kindle and other format this book has been release on 2013-03-12 with Science categories.
In this book the author discusses the investigation of ion bombardment of solids by computer simulation, with the aim of demonstrating the usefulness of this approach to the problem of interactions of ions with solids. The various chapters present the basic physics behind the simulation programs, their structure and many applications to different topics. The two main streams, the binary collision model and the classical dynamics model, are discussed, as are interaction potentials and electronic energy losses. The main topics investigated are backscattering, sputtering and implantation for incident atomic particles with energies from the eV to the MeV range. An extensive overview of the literature is given, making this book of interest to the active reseacher as well to students entering the field.
Energy Research Abstracts
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Author :
language : en
Publisher:
Release Date : 1993
Energy Research Abstracts written by and has been published by this book supported file pdf, txt, epub, kindle and other format this book has been release on 1993 with Power resources categories.
Control Of Tritium Permeation Through Fusion Reactor Strucural Materials
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Author :
language : en
Publisher:
Release Date : 1978
Control Of Tritium Permeation Through Fusion Reactor Strucural Materials written by and has been published by this book supported file pdf, txt, epub, kindle and other format this book has been release on 1978 with categories.
The intention of this paper is to provide a brief synopsis of the status of understanding and technology pertaining to the dissolution and permeation of tritium in fusion reactor materials. The following sections of this paper attempt to develop a simple perspective for understanding the consequences of these phenomena and the nature of the technical methodology being contemplated to control their impact on fusion reactor operation. Considered in order are: (1) the occurrence of tritium in the fusion fuel cycle, (2) a set of tentative criteria to guide the analysis of tritium containment and control strategies, (3) the basic mechanisms by which tritium may be released from a fusion plant, and (4) the methods currently under development to control the permeation-related release mechanisms. To provide background and support for these considerations, existing solubility and permeation data for the hydrogen isotopes are compared and correlated under conditions to be expected in fusion reactor systems.