Download or read book Irradiation Experiment for Lithium Ceramics written by and published by . This book was released on 1982 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: Solid breeder materials are required in D-T fusion reactor blankets to convert fusion neutrons to tritium and thermal energy while providing some neutron shielding for the magnets. Lithium compounds such as Li2O, LiAlO2, Li4SiO4 and Li2ZrO3 have been proposed as solid breeder materials. Tritium is necessary to maintain the fuel supply for the D-T fusion reaction. No high burnup irradiation performance data is available for these materials in a neutron environment prototypic of the fusion blanket. The FUBR Experiment in EBR-II has been designed and built to evaluate the irradiation performance of these materials.
Download or read book Fabrication and Properties of Lithium Ceramics written by Ian J. Hastings and published by . This book was released on 1989 with total page 216 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Tritium Release and Gamma Activity of Various Lithium Ceramics Irradiated by Fast and Thermal Neutrons COMPLIMENT Experiment written by Lothar Dörr and published by . This book was released on 2018 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Fabrication and Properties of Lithium Ceramics II written by G. W. Hollenberg and published by . This book was released on 1990 with total page 392 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Tritium Release and Gamma Activity of Various Lithium Ceramics Irradiated by Fast and Thermal Neutrons compliment Experiment written by Lothar Dörr and published by . This book was released on 1994 with total page 31 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Tritium Release from Beryllium Discs and Lithium Ceramics Irradiated in the SIBELIUS Experiment written by and published by . This book was released on 1993 with total page 12 pages. Available in PDF, EPUB and Kindle. Book excerpt: The SIBELIUS experiment was designed to obtain information on the compatibility between beryllium and ceramics, as well as beryllium and steel, in a neutron environment. This experiment comprised irradiation of eight capsules, seven of which were independently purged with a He/0.1% H2 gas mixture. Four capsules were used to examine beryllium/ceramic (Li2O, LiAlO2, Li4SiO4, and Li2ZrO3) and beryllium/steel (Types 316L and 1.4914) compacts. Isothermal anneal experiments have been run on representative beryllium and ceramic disks from each of the four capsules at 550°C to 850°C in steps of 100°C. The results indicate that tritium release from the beryllium did not exhibit burst release behavior, as previously reported, but rather a progressive release with increasing temperature. Generally, (approximately)99% of the tritium was released by 850°C. Tritium release from the ceramic discs was quite similar to the behavior shown in other dynamic tritium release experiments on lithium ceramics. The tritium content in beryllium discs adjacent to a steel sample was found to be significantly lower than that found in a beryllium disc adjacent to a ceramic sample. Recoil of tritium from the ceramic into the beryllium appears to be the source of tritium entering the beryllium, probably residing in the beryllium oxide layer.
Download or read book Irradiation of Lithium based Ceramics for Fusion Blanket Application written by Atomic Energy of Canada Limited and published by Mississauga, Ont. : Canadian Fusion Fuels Technology Project. This book was released on 1986 with total page 36 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Fabrication and Properties of Lithium Ceramics III written by Ian J. Hastings and published by . This book was released on 1992 with total page 360 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Exotic 7 written by J. G. van der Laan and published by . This book was released on 1995 with total page 24 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Applications of Lithium in Ceramics written by J. H. Fishwick and published by . This book was released on 1974 with total page 178 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Irradiation Devices for Reactor Materials written by F. Lefevre and published by . This book was released on 1987 with total page 15 pages. Available in PDF, EPUB and Kindle. Book excerpt: The study of radiation behavior is of prime importance in the investigation of fusion reactor materials. With this purpose, the "Services des Piles de Saclay" (SPS) has been using the experimental OSIRIS pool reactor, having a nominal power of 70 MW, to develop irradiation devices. The devices enable (1) the study of the crack growth on a sample under alternative stress in a neutron flux, (2) the study of stress relaxation on materials under irradiation, (3) the study of creep and growth of cylindrical test pieces in a neutron flux, (4) the irradiation of large amounts of protection ceramics of fusion reactors so as to characterize their mechanical properties, and (5) the irradiation of lithium containing ceramics, which are possible materials for the breeding blanket of a fusion reactor. The last device was used in the ALICE 1 experiment, carried out in collaboration with the "Division d'Etudes de Séparation Isotopique et de Chimie Physique" (DESICP), for the irradiation of 130 specimens of ? LiAlO2, of natural lithium 6 abundance and of various textures. The unclad samples were irradiated at 400 and 600°C, in a maximum fast flux of 2 x 1014 n . cm-2 . s-1 (E > 1 MeV) and maximum perturbed thermal flux 6 x 1013 n . cm-2 . s-1 for 26 days (from 16 Oct. to 13 Nov. 1984). The amount of tritium generated was 330 Ci. The 6Li burnup could amount to 15 to 20%. The first post irradiation examinations showed general good behavior of the samples. There were no changes in the dimensions of the samples, nor significant thermal conductivity variations. Retained tritium and helium amounts varied depending on the ceramic texture and irradiation temperature. Small variations in the sound velocity and cracks were observed only in two 600°C levels, corresponding to containers that received mechanical shocks during the dismantling of the experimental device.
Download or read book The ENEA Contribute to BEATRIX FUBR 1B Experiment written by and published by . This book was released on 1987 with total page 13 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Lithium Ceramics as the Solid Breeder Material in Fusion Reactors written by and published by . This book was released on 1982 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: Fusion blanket designs have for almost a decade considered the use of a solid breeder relying on available data and assumed performance. The conclusion from these studies is that acceptable neutronic and thermal hydraulic performance can be achieved. In the future, it will be necessary to establish that a particular material can tolerate the thermal and irradiation environment of the fusion blanket while still providing the required functions of tritium recovery, power production and neutron shielding.
Download or read book Irradiation Study of PNNL Synthesized Glass ceramics written by and published by . This book was released on 2011 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: Two types of glass-ceramic were investigated: (1) for immobilization of Ln, alkali, and alkaline earths (GC4); and (2) same as above + high (7%) molybdenum content (Mo7) multiphase specimens. The purpose was to study the radiation stability of PNNL synthesized glass-ceramics and changes in microstructure/phase composition.
Download or read book In Situ Tritium Recovery from Li2O Irradiated in a Fast Neutron Flux written by and published by . This book was released on 1994 with total page 19 pages. Available in PDF, EPUB and Kindle. Book excerpt: BEATRIX-II, Phase II was an in situ tritium recovery experiment designed to characterize the behavior of lithium ceramics irradiated to high burnup in a fast neutron flux. A thin-walled Li2O ring specimen was irradiated at temperatures in the range from 520 to 640 C in helium sweep gases containing 0, 0.01 and 0.1% H2 to a 5% lithium burnup. The tritium recovery behavior of Li2O was characterized by using temperature transients and sweep gas composition changes to effect changes in the tritium inventory.
Download or read book Ceramic Materials for Energy Applications V written by Josef Matyas and published by John Wiley & Sons. This book was released on 2015-12-23 with total page 164 pages. Available in PDF, EPUB and Kindle. Book excerpt: The Ceramic Engineering and Science Proceeding has been published by The American Ceramic Society since 1980. This series contains a collection of papers dealing with issues in both traditional ceramics (i.e., glass, whitewares, refractories, and porcelain enamel) and advanced ceramics. Topics covered in the area of advanced ceramic include bioceramics, nanomaterials, composites, solid oxide fuel cells, mechanical properties and structural design, advanced ceramic coatings, ceramic armor, porous ceramics, and more.
Download or read book Analysis of Surface Fluxes of Hydrogen Species in Lithium Ceramics written by Alya Adel Mohamed Badawi and published by . This book was released on 1991 with total page 36 pages. Available in PDF, EPUB and Kindle. Book excerpt:
