A U S High Flux Neutron Facility For Fusion Materials Development
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A U S High Flux Neutron Facility For Fusion Materials Development
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Author :
language : en
Publisher:
Release Date : 2010
A U S High Flux Neutron Facility For Fusion Materials Development written by and has been published by this book supported file pdf, txt, epub, kindle and other format this book has been release on 2010 with categories.
Materials for a fusion reactor first wall and blanket structure must be able to reliably function in an extreme environment that includes 10-15 MW-year/m2 neutron and heat fluences. The various materials and structural challenges are as difficult and important as achieving a burning plasma. Overcoming radiation damage degradation is the rate-controlling step in fusion materials development. Recent advances with oxide dispersion strengthened ferritic steels show promise in meeting reactor requirements, while multi-timescale atomistic simulations of defect-grain boundary interactions in model copper systems reveal surprising self-annealing phenomenon. While these results are promising, simultaneous evaluation of radiation effects displacement damage (≤ 200 dpa) and in-situ He generation (≤ 2000 appm) at prototypical reactor temperatures and chemical environments is still required. There is currently no experimental facility in the U.S. that can meet these requirements for macroscopic samples. The E.U. and U.S. fusion communities have recently concluded that a fusion-relevant, high-flux neutron source for accelerated characterization of the effects of radiation damage to materials is a top priority for the next decade. Data from this source will be needed to validate designs for the multi-$B next-generation fusion facilities such as the CTF, ETF, and DEMO, that are envisioned to follow ITER and NIF.
The International Fusion Materials Irradiation Facility
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Author :
language : en
Publisher:
Release Date : 1994
The International Fusion Materials Irradiation Facility written by and has been published by this book supported file pdf, txt, epub, kindle and other format this book has been release on 1994 with categories.
It is widely agreed that the development of materials for fusion systems requires a high flux, 14 MeV neutron source. The European Union, Japan, Russia and the US have initiated the conceptual design of such a facility. This activity, under the International Energy Agency (IEA) Fusion Materials Agreement, will develop the design for an accelerator-based D-Li system. The first organizational meeting was held in June 1994. This paper describes the system to be studied and the approach to be followed to complete the conceptual design by early 1997.
Neutron Irradiation Facilities For Fission And Fusion Reactor Materials Studies
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Author :
language : en
Publisher:
Release Date : 1985
Neutron Irradiation Facilities For Fission And Fusion Reactor Materials Studies written by and has been published by this book supported file pdf, txt, epub, kindle and other format this book has been release on 1985 with categories.
The successful development of energy-conversion machines based upon nuclear fission or fusion reactors is critically dependent upon the behavior of the engineering materials used to construct the full containment and primary heat extraction systems. The development of radiation damage-resistant materials requires irradiation testing facilities which reproduce, as closely as possible, the thermal and neutronic environment expected in a power-producing reactor. The Oak Ridge National Laboratory (ORNL) reference core design for the Center for Neutron Research (CNR) reactor provides for instrumented facilities in regions of both hard and mixed neutron spectra, with substantially higher fluxes than are currently available. The benefits of these new facilities to the development of radiation damage resistant materials are discussed in terms of the major US fission and fusion reactor programs.
Neutron Generators For Analytical Purposes
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Author : International Atomic Energy Agency
language : en
Publisher: IAEA Radiation Technology Repo
Release Date : 2012
Neutron Generators For Analytical Purposes written by International Atomic Energy Agency and has been published by IAEA Radiation Technology Repo this book supported file pdf, txt, epub, kindle and other format this book has been release on 2012 with Science categories.
This publication addresses recent developments in neutron generator (NG) technology. It presents information on compact instruments with high neutron yield to be used for neutron activation analysis (NAA) and prompt gamma neutron activation analysis in combination with high count rate spectrometers. Traditional NGs have been shown to be effective for applications including borehole logging, homeland security, nuclear medicine and the on-line analysis of aluminium, coal and cement. Pulsed fast thermal neutron analysis, as well as tagged and timed neutron analysis, are additional techniques which can be applied using NG. Furthermore, NG can effectively be used for elemental analysis and is also effective for analysis of hidden materials by neutron radiography. Useful guidelines for developing NG based research laboratories are also provided in this publication.
Ifmif International Fusion Materials Irradiation Facility An Accelerator Based Neutron Source For Fusion Components Irradiation Testing
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Author :
language : en
Publisher:
Release Date : 1988
Ifmif International Fusion Materials Irradiation Facility An Accelerator Based Neutron Source For Fusion Components Irradiation Testing written by and has been published by this book supported file pdf, txt, epub, kindle and other format this book has been release on 1988 with categories.
The International Fusion Materials Irradiation Facility (IFMIF) is proposed as an advanced accelerator-based neutron source for high-flux irradiation testing of large-sized fusion reactor components. The facility would require only small extensions to existing accelerator and target technology originally developed for the Fusion Materials Irradiation Test (FMIT) facility. At the extended facility, neutrons would be produced by a 0.1-A beam of 35-MeV deuterons incident upon a liquid lithium target. The volume available for high-flux (>1015 n/cm2-s) testing in IFMITF would be over a liter, a factor of about three larger than in the FMIT facility. This is because the effective beam current of 35-MeV deuterons on target can be increased by a factor of ten to 1A or more. Such an increase can be accomplished by funneling beams of deuterium ions from the radio-frequency quadruple into a linear accelerator and by taking advantage of recent developments in accelerator technology. Multiple beams and large total current allow great variety in available testing. For example, multiple simultaneous experiments, and great flexibility in tailoring spatial distributions of flux and spectra can be achieved. 5 refs., 2 figs., 1 tab.
Need For And Requirements For Neutron Irradiation Facility For Fusion Materials Testing
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Author :
language : en
Publisher:
Release Date : 1989
Need For And Requirements For Neutron Irradiation Facility For Fusion Materials Testing written by and has been published by this book supported file pdf, txt, epub, kindle and other format this book has been release on 1989 with categories.
The construction and operation of an intense 14MeV neutron source is essential for the development and eventual qualification of structural materials for a fusion reactor demonstration plant (DEMO). Because of the time required for materials developed and the scale-up of materials to commercial production, a decision to build a neutron source should precede engineering design activities for a DEMO by at least 20 years. The characteristic features of 14MeV neutron damage are summarized including effects related to cascade structure, transmutation production, and dose rate. The importance of a 14MeV neutron source for addressing fundamental radiation damage issues, alloy development activities and the development of an engineering data bases is discussed. From these considerations the basic requirements and machine parameters are derived. 14 refs., 5 figs., 5 tabs.
Design Of A Target And Moderator At The Los Alamos Spallation Radiation Effects Facility Lasref As A Neutron Source For Fusion Reactor Materials Development
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Author : PD. Ferguson
language : en
Publisher:
Release Date : 1994
Design Of A Target And Moderator At The Los Alamos Spallation Radiation Effects Facility Lasref As A Neutron Source For Fusion Reactor Materials Development written by PD. Ferguson and has been published by this book supported file pdf, txt, epub, kindle and other format this book has been release on 1994 with Fusion categories.
The LASREF facility is located in the beam stop area at LAMPF. The neutron spectrum is fission-like with the addition of a 3% to 5% component with E > 20 MeV. The present study evaluates the limits on geometry and material selection that will maximize the neutron flux. MCNP and LAHET were used to predict the neutron flux and energy spectrum for a variety of geometries. The problem considers 760 MeV protons incident on tungsten. The resulting neutrons are multiplied in uranium through (n,xn) reactions. Calculations show that a neutron flux greater than 10199 n/m2/s is achievable. The helium to dpa ratio and the transmutation product generation are calculated. These results are compared to expectations for the proposed DEMO fusion reactor and to FFTF.
Accelerator Based Intense Neutron Source For Materials R D
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Author :
language : en
Publisher:
Release Date : 1990
Accelerator Based Intense Neutron Source For Materials R D written by and has been published by this book supported file pdf, txt, epub, kindle and other format this book has been release on 1990 with categories.
Accelerator-based neutron sources for R D of materials in nuclear energy systems, including fusion reactors, can provide sufficient neutron flux, flux-volume, fluence and other attractive features for many aspects of materials research. The neutron spectrum produced from the D-Li reaction has been judged useful for many basic materials research problems, and to be a satisfactory approximation to that of the fusion process. The technology of high-intensity linear accelerators can readily be applied to provide the deuteron beam for the neutron source. Earlier applications included the Los Alamos Meson Physics Facility and the Fusion Materials Irradiation Test facility prototype. The key features of today's advanced accelerator technology are presented to illustrate the present state-of-the-art in terms of improved understanding of basic physical principles and engineering technique, and to show how these advances can be applied to present demands in a timely manner. These features include how to produce an intense beam current with the high quality required to minimize beam losses along the accelerator and transport system that could cause maintenance difficulties, by controlling the beam emittance through proper choice of the operating frequency, balancing of the forces acting on the beam, and realization in practical hardware. A most interesting aspect for materials researchers is the increased flexibility and opportunities for experimental configurations that a modern accelerator-based source could add to the set of available tools. 8 refs., 5 figs.
Neutronics Of A D Li Neutron Source An Overview
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Author :
language : en
Publisher:
Release Date : 1993
Neutronics Of A D Li Neutron Source An Overview 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 categories.
The importance of having a high energy (14 MeV) neutron source for fusion materials testing is widely recognized. The availability of a test volume with easy accessibility, with a radiation environment similar to the one expected for a fusion reactor, and with dimensions large enough to accommodate several small samples or a small blanket mock-up are requirements impossible to meet with the existing reactors and irradiation facilities. A D-Li neutron source meets the above mentioned requirements, and it uses existing technology. This paper describes some relevant topics related to beam target configuration, neutron flux spectrum, and nuclear responses for a D-Li neutron source. The target-beam configuration is analyzed for different beam cross sectional areas and trade-offs between the area of the beam and related quantities such as available volume for testing, peak fluxes, and flux or nuclear responses gradient are presented. The conclusion is that the D-Li neutron source has the necessary characteristics to be a desirable option for International Fusion Materials Irradiation Facility (IFMIF).
Accelerator Driven Neutron Sources For Fusion Materials Testing
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Author :
language : en
Publisher:
Release Date : 1991
Accelerator Driven Neutron Sources For Fusion Materials Testing written by and has been published by this book supported file pdf, txt, epub, kindle and other format this book has been release on 1991 with categories.
Several accelerator-driven neutron sources have been proposed for satisfying the requirements of a high-flux high-volume international fusion materials testing facility that could be built in the near future. This paper summarizes the features and projected performance for the three accelerator sources that are leading candidates for such a role and that are viewed by the International Energy Agency (IEA) as worthy of further evaluation. These are: (1) the d-Li source, in which 35-MeV deuteron beams are incident on flowing lithium targets, (2) the t-H2O source, in which 21-MeV triton beams strike high-speed water jets, and (3) the Spallation source in which a 600-MeV proton beam bombards a heavy-metal target.