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Thursday, July 30, 2020 | History

1 edition of HFR irradiation testing of fusion materials found in the catalog.

HFR irradiation testing of fusion materials

R. Conrad

HFR irradiation testing of fusion materials

by R. Conrad

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  • 7 Currently reading

Published by Commission of the European Communities in Luxembourg .
Written in English


Edition Notes

StatementR. Conrad [... et al.].
SeriesNuclear science and technology
ContributionsCommission of theEuropean Communities. Directorate-General for Science, Research and Development.
ID Numbers
Open LibraryOL20909985M
ISBN 109282545393

The evaluation of fission gas release from spherical fuel during irradiation testing is critical to understand expected fuel performance under real reactor conditions. Online measurements of Krypton and Xenon fission products explain coated particle performance and contributions from graphitic matrix materials used in fuel manufacture and. Available tools for testing materials exposed to ion or neutron irradiation, including their advantages and limitations when mimicking fusion conditions, are discussed in this paper.

General materials technology aspects and cross cutting issues: Remelting, dilution, refabrication, considerations on raw materials abundance Track 1B Refractory materials Refractory materials for fusion reactor applications: tungsten and its alloys, vanadium alloys, SiC/SiCSiC and SiC/SiC, oxides,Max phases, W-based composites or Cu-Nb alloys. Irradiation tests and qualifications of innovative fuels and functional/structural materials for use in next generation fission reactors with enhanced safety and performance; R&D for Fusion Reactor technologies, e.g. first wall components. For more information: HFR annual report

Get this from a library! Irradiation Technology: Proceedings of an International Topical Meeting Grenoble, France September , [Peter Hardt; Heinz Röttger] -- The International Topical Meeting on Irradiation Technology took place two the Neutron and its Applications (Cambridge, weeks after the Conference on th U.K.) marking the 50 anniversary of the. Get this from a library! Fusion materials irradiation testing facility, Hanford Reservation, Richland, Washington: final environmental impact statement: (final of draft EIS, ERDAD, high flux neutron source facility).. [United States. Department of Energy.].


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HFR irradiation testing of fusion materials by R. Conrad Download PDF EPUB FB2

The current irradiation programmes at the HFR address areas in: • R&D for nuclear fi ssion energy, i.e. materials irradiation in support of nuclear plant life extension, transient testing of pre-irradiated LWR fuel rods containing UO2 or MOX fuel, testing of fuel and materials for innovative Size: 1MB.

Nuclear irradiation parameters relevant to displacement damage and burn-up of the breeder materials Li 2 O, Li 4 SiO 4 and Li 2 TiO 3 have been evaluated and compared for a fusion power demonstration reactor and the high flux fission test reactor (HFR), Petten, the advanced test reactor (ATR, INEL) and the Japanese material test reactor (JMTR, JAERI).

Based on detailed Cited by:   The International Fusion Materials Irradiation Facility, IFMIF, is the accelerator based deuterium–lithium (d–Li) stripping neutron source for production of high-energy neutrons at sufficient intensity to test samples of the fusion candidate materials up to about the full lifetime of anticipated use in fusion energy reactors.

Two deuteron Cited by: The High Flux Reactor (HFR) Petten, owned by the Commission of the European Communities and operated by the Institute for Advanced Materials of the Joint Research Centre, is particularly suited for research on materials and components for future thermonuclear fusion Cited by: 4.

R. Conrad, P. yon der Hardt, R. L61gen, R. Scheurer and P. Zeisser, HFR irradiation testing of fusion materials, CEC- Rep. EUR EN, M.L de Vries. Effects of temperature and strain rate on the low cycle fatigue properties of neutron irradiated stainless steelASTM STP, p. M.I. de Vries and by: 3.

The International Fusion Materials Irradiation Facility, also known as IFMIF, is a projected material testing facility in which candidate materials for the use in an energy producing fusion reactor can be fully will be an accelerator-driven neutron source producing a high intensity fast neutron flux with a spectrum similar to that expected at the first wall of a fusion reactor.

Materials Irradiation. The combined effects of neutron and gamma radiation on materials are of interest for advanced materials research, fusion energy research, and for production of hardened components and systems.

A recent example is the dose response investigation of dichroic mirror ceramic materials for the fusion energy research program. The High Flux Reactor (HFR) in Petten, The Netherlands, is a materials testing research reactor with an aluminium alloy (base material: ) vessel.

The International Fusion Materials Irradiation Facility, also known as IFMIF, is a projected materials test facility in which candidate materials for the use in an energy producing fusion reactor can be fully is an accelerator-based neutron source that produces, using deuterium-lithium nuclear reactions, a large neutron flux with a spectrum similar to that expected at the first.

The International Topical Meeting on Irradiation Technology took place two the Neutron and its Applications (Cambridge, weeks after the Conference on th U. K.) marking the 50 anniversary of the discovery of the neutron. The application of neutrons from research reactors for materials testing.

Materials damage by MeV neutrons from deuterium–tritium (D–T) fusion reactions can only be characterised definitively by subjecting a relevant configuration of test materials to high.

There have been only a few international con­ ferences on irradiation testing, the last one being limited to fast breeder reactor work (Jackson, Wyoming, September ). Inhowever, two conferences picked up similar topics -the ANS Conference on Fast, Thermal, and Fusion Reactor Experiments (Salt Lake City, Utah, April ), -the.

The long-pulse target was suggested for housing a material test module. For materials irradiation purposes in the long-pulse target station of ESS, a position in the lead reflector above the.

Within the LWR fuel rod testing programmes at HFR — where more than individual fuel rod tests have been performed — neutron radiography is an important and unique non-destructive test technique. Equipment, methods and typical results related to neutron radiography, of LWR fuel rods at HFR. CiteSeerX - Document Details (Isaac Councill, Lee Giles, Pradeep Teregowda): Abstract.

The development of First Wall and Blanket materials which are capable of withstanding many years the high neutron and heat fluxes, is for material scientists a critical path to fusion power. In an energy generating fusion reactor, such structural materials will be exposed to very high levels of irradiation.

The irradiation of the inert materials (containing no fissile material) generally takes place at This measurement device uses a stack of materials with increasing fusion temperature, shutdown for non-destructive testing conducted at Phenix in June and July the nearer future to study the materials behavior under fusion relevant irradiation conditions, e.g.

specific He/dpa-ratio of 10 – 15 appm/dpa. Therefore irradiations in high flux reactors (HFR, Petten) and fast reactors ( Dimitrovgrad) have been realized. The irradiation to. The materials used in this test were thin ( mm) sheets of oxygen free high conductiv- ity (OFHC) copper contain 3. In the frame work of the European Fusion Technology Programme and the International Thermonuclear Experimental Reactor (ITER), ECN is investigating the irradiation behaviour of the structural materials for ITER.

The main structural material for ITER is austenitic stainless steel Type L(N)-IG. The operating temperatures of (parts of) the components are envisaged to range between and K.

The Materials Irradiation Experiment (MITE-E) was constructed at the University of Wisconsin-Madison Inertial Electrostatic Confinement Laboratory to test materials for potential use as plasma-facing materials (PFMs) in fusion reactors.

PFMs in fusion reactors will be bombarded with x-rays, neutrons, and ions of hydrogen and helium. More needs to be understood about the interactions between. The development of first wall, blanket and divertor materials that are capable of withstanding high neutron and heat fluxes for sufficiently high neutron fluence of at least 10–15 MW-y m −2, corresponding to a component lifetime of at least five years, is a critical path to fusion the construction of a fusion demonstration reactor, DEMO, for demonstrating competitive electrical.

Books. Publishing Support. Login. Schneider H.C. et al HFR irradiation programme Scientific Report FZKA p Lucas G.E. et al The role of small specimen test technology in fusion materials development 12th Int. Conf. on Fusion Reactor Materials .IFMIF will be an accelerator-based neutron irradiation facility that will focus on developing and characterising fusion reactor materials.

The facility’s key aim is to provide intense high energy neutrons with a sufficient irradiation volume to enable the realistic testing (in terms of intensity and duration) of candidate materials and.