Read Books Online and Download eBooks, EPub, PDF, Mobi, Kindle, Text Full Free.
Download Tritium Storage Development full books in PDF, epub, and Kindle. Read online Tritium Storage Development ebook anywhere anytime directly on your device. Fast Download speed and no annoying ads. We cannot guarantee that every ebooks is available!
Author :
Publisher :
ISBN 13 :
Total Pages : 17 pages
Book Rating : 4.:/5 (865 download)
Download or read book Tritium storage development written by and published by . This book was released on 1977 with total page 17 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Author : Brookhaven National Laboratory. Department of Nuclear Energy. Process Technology Division
Publisher :
ISBN 13 :
Total Pages : pages
Book Rating : 4.:/5 (65 download)
Download or read book Tritium Storage Development written by Brookhaven National Laboratory. Department of Nuclear Energy. Process Technology Division and published by . This book was released on 1977 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt:
Author : Brookhaven National Laboratory. Nuclear Waste Management Research Group
Publisher :
ISBN 13 :
Total Pages : pages
Book Rating : 4.:/5 (65 download)
Download or read book Tritium storage development written by Brookhaven National Laboratory. Nuclear Waste Management Research Group and published by . This book was released on 1977 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt:
Author : Brookhaven National Laboratory. Department of Nuclear Energy. Process Technology Division
Publisher :
ISBN 13 :
Total Pages : pages
Book Rating : 4.:/5 (65 download)
Download or read book Tritium Storage Development written by Brookhaven National Laboratory. Department of Nuclear Energy. Process Technology Division and published by . This book was released on 1977 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Tritium Storage Development, Jan.-Mar. 1978 written by and published by . This book was released on 1979 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt:
Author : P. Colombo
Publisher :
ISBN 13 :
Total Pages : 0 pages
Book Rating : 4.:/5 (141 download)
Download or read book TRITIUM STORAGE DEVELOPMENT. PROGRESS REPORT NO. 15, JANUARY - MARCH 1978 written by P. Colombo and published by . This book was released on 1979 with total page 0 pages. Available in PDF, EPUB and Kindle. Book excerpt:
![Download Tritium Storage Development. Progress Report No. 10, October--December 1976. [In Metal Hydride; Polymer-impregnated Tritiated Concrete]. PDF Online Free](https://books.google.com/books/content/images/frontcover/lOPYwQEACAAJ?fife=w200-h370)
Download or read book Tritium Storage Development. Progress Report No. 10, October--December 1976. [In Metal Hydride; Polymer-impregnated Tritiated Concrete]. written by and published by . This book was released on 1976 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: Laboratory and engineering scale work has been initiated on the storage of tritium in a metal hydride. Laboratory hydriding apparatus has been assembled and a preliminary series of experiments was carried out on zirconium. Several engineering design concepts for the reaction and storage of tritium in a metal hydride are presented. The design of a three 3-in.-diam. bench scale reaction system is in progress. Developmental work is continuing on the injector technique for the fixation of tritium in polymer-impregnated concrete.
Author : F. Mannone
Publisher : Springer Science & Business Media
ISBN 13 : 9401119104
Total Pages : 241 pages
Book Rating : 4.4/5 (11 download)
Download or read book Safety in Tritium Handling Technology written by F. Mannone and published by Springer Science & Business Media. This book was released on 2012-12-06 with total page 241 pages. Available in PDF, EPUB and Kindle. Book excerpt: 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 : J Paul Guyer
Publisher :
ISBN 13 :
Total Pages : 52 pages
Book Rating : 4.5/5 (563 download)
Download or read book An Introduction to Tritium Handling and Storage Facilities written by J Paul Guyer and published by . This book was released on 2020-10-31 with total page 52 pages. Available in PDF, EPUB and Kindle. Book excerpt: Introductory technical guidance for architectural, civil, mechanical and electrical engineers interested in tritium handling and storage facilities. Here is what is discussed:1. INTRODUCTION2. SOURCES OF TRITIUM3. THE RELATIVE ABUNDANCE OF TRITIUM4. THE RADIOACTIVE DECAY OF TRITIUM5. THE CHEMICAL PROPERTIES OF TRITIUM6. MODELING THE BEHAVIOR OF TRITIUM7. THE DEVELOPMENT OF TRITIUM TECHNOLOGY8. CONFINEMENT SYSTEMS VS. CONTAINMENT SYSTEMS9. TRITIUM REMOVAL SYSTEMS.
Author : L. K. Heung
Publisher :
ISBN 13 :
Total Pages : 13 pages
Book Rating : 4.:/5 (929 download)
Download or read book Developments in Tritium Storage and Transportation at the Savannah River Site (U) written by L. K. Heung and published by . This book was released on 1993 with total page 13 pages. Available in PDF, EPUB and Kindle. Book excerpt:
![Download Tritium Storage Development. Progress Report No. 7, January--March 1976. [Polymer Impregnated Tritiated Concrete]. PDF Online Free](https://books.google.com/books/content/images/frontcover/tKJLAQAACAAJ?fife=w200-h370)
Download or read book Tritium Storage Development. Progress Report No. 7, January--March 1976. [Polymer Impregnated Tritiated Concrete]. written by and published by . This book was released on 1976 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: Polymer impregnation was shown to greatly improve the leach rate of tritiated concrete specimens on a laboratory scale. This technique is proposed for the disposal of high-level tritiated aqueous waste. Work was directed towards the development of a soak impregnation technique for large-scale samples. Four cylindrical specimens of polymer impregnated tritiated concrete (PITC) 27 cm x 28 cm long, each containing 10 Ci tritium, were produced and buried without containers in individual lysimeters at the Savannah River Plant; they are being monitored. To date, no tritium release has been noted in water or air samples taken from these lysimeters. A duplicate PITC sample also containing 10 Ci tritium was placed in static leaching in distilled water. After thirty-two days of leaching, the average fraction tritium release rate was 1.82 x 10/sup -5/ per day. A technique using an injector to distribute aqueous tritiated waste in dry cement prior to impregnation is under development. This injector method is more compatible with the glove box operations in use with high level tritiated aqueous waste than end-over-end drum tumbling. Initial PITC specimens have been produced using this technique.
Download or read book Tritium Storage Development. Progress Report No. 8, April--June 1976 written by and published by . This book was released on 1976 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: Lysimeter testing of polymer impregnated tritiated concrete (PITC) specimens at the Savannah River Laboratory (SRL) has continued. After twenty-three weeks, an average tritium fraction release rate of 3.37 x 10−7 day−1 has been determined in the percolate water with no measurable release to the air. Data from this experiment is extrapolated to estimate long-term tritium releases. A duplicate PITC specimen is in static leaching in distilled water. After seventy-two days, the average tritium fraction release rate has been 1.96 x 10−5 day−1. An estimation of the increased severity of static leaching in distilled water relative to lysimeter testing is made.
Download or read book Tritium Storage Development. Progress Report No. 15, January--March 1978 written by and published by . This book was released on 1978 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: Two hydriding--dehydriding runs were made with zirconium sponge on an engineering scale for application to retrievable tritium storage systems. The dehydriding rates were low in comparison to hydriding rates. An overall hydrogen recovery of 35% was achieved after 16 hours at 500°C. At 600°C, the overall hydrogen recovery was 66% after 48 hours. Hydriding rates were obtained for titanium rod at 450 and 525°C. The maximum reaction rates for an initial system pressure of 705--709 torr were 0.026 and 0.40 Cm3 of H2 at STP/cm2-min at 450 and 525°C, respectively. Increasing the initial system pressure to 1863 torr increased the maximum reaction rate to 1.04 cm3 of H2 at STP/CM2-min at 525°C. In general, these rates are comparable to the rates obtained with zirconium sheet.
Author : J. Paul Guyer, P.E., R.A.
Publisher : Guyer Partners
ISBN 13 :
Total Pages : 46 pages
Book Rating : 4./5 ( download)
Download or read book An Introduction to Tritium Handling and Storage Facilities written by J. Paul Guyer, P.E., R.A. and published by Guyer Partners. This book was released on 2020-10-31 with total page 46 pages. Available in PDF, EPUB and Kindle. Book excerpt: Introductory technical guidance for architectural, civil, mechanical and electrical engineers interested in tritium handling and storage facilities. Here is what is discussed: 1. INTRODUCTION 2. SOURCES OF TRITIUM 3. THE RELATIVE ABUNDANCE OF TRITIUM 4. THE RADIOACTIVE DECAY OF TRITIUM 5. THE CHEMICAL PROPERTIES OF TRITIUM 6. MODELING THE BEHAVIOR OF TRITIUM 7. THE DEVELOPMENT OF TRITIUM TECHNOLOGY 8. CONFINEMENT SYSTEMS VS. CONTAINMENT SYSTEMS 9. TRITIUM REMOVAL SYSTEMS.
Download or read book Tritium Storage Development. Progress Report No. 13, July--September 1977 written by and published by . This book was released on 1977 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: Engineering-scale operation was started on hydriding of zirconium for application to tritium storage systems. Eight runs were made with commercial-grade zirconium sponge at 338° to 499°C and 0 to 770 torr, hydrided to hydrogen-to-zirconium atom ratios up to 2. Reaction rates were determined for hydrogen flow rates of 2.72 to 9.24 cm3 at STP/g Zr-min. For each run, hydrogen pressure was plotted on a semilog scale against time and H/Zr atom ratio to elucidate the reaction mechanism in terms of reaction kinetics, diffusion, and equilibrium hydrogen vapor pressure. Lack of consistency in some of the runs is probably due to difference in the extent of the diffusion barrier formed on the metal because of reaction with oxygen and other contaminants. Static leach testing of zirconium sponge and rod in distilled water was continued; leach rates ranged from 8.9 x 10−7 to 1.7 x 10−6 cm/day for the 166 to 208 day leach period.
![Download Tritium Storage Development. Progress Report No. 9, July--September 1976. [Tritiated Concrete-polymer]. PDF Online Free](https://books.google.com/books/content/images/frontcover/YpqewgEACAAJ?fife=w200-h370)
Download or read book Tritium Storage Development. Progress Report No. 9, July--September 1976. [Tritiated Concrete-polymer]. written by and published by . This book was released on 1976 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: Lysimeter testing of the polymer impregnated tritiated concrete (PITC) specimens at the Savannah River Plant has continued. After thirty-one weeks, a constant average tritium fraction release rate of 1.16 x 10−6 day−1 was reached in the percolate water with no measurable release into the air. Data from this experiment projected to long-term tritium releases estimate that a complete tritium release from the PITC will require 2,370 years and that the maximum fraction of the initially contained tritium present in the environment will be 2.76 x 10−3 after 17.7 years. A duplicate PITC specimen is in static leaching in distilled water. After 295 days, a constant tritium fraction release rate of 1.89 x 10−5 day−1 was determined for this specimen. Development of the injector technique for PITC production has proceeded with the fabrication of a large-scale 27 gallon PITC casting. This casting was sectioned longitudinally and examined for its physical appearance, integrity, and polymer distribution. A representative of Monsanto Mound Laboratory spent one week at Brookhaven National Laboratory for PITC production technology transfer.
![Download Tritium Storage Development. Progress Report No. 14, October--December 1977. [As a Tritide in a Metal Hydride]. PDF Online Free](https://books.google.com/books/content/images/frontcover/SQBHAQAACAAJ?fife=w200-h370)
Download or read book Tritium Storage Development. Progress Report No. 14, October--December 1977. [As a Tritide in a Metal Hydride]. written by and published by . This book was released on 1977 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: Hydriding studies of zirconium on an engineering scale was continued for application to tritium storage systems. Two runs were made with zirconium sponge in the 297 to 319°C temperature range at a hydrogen flow rate of 2.72 cm3 at STP/g Zr-min. No significant difference in reaction rate was observed between 99.95 and 99.999 percent minimum purity hydrogen. Seven runs were made with 0.065-in.-thick zirconium sheet at a temperature range of 415 to 526°C. Some inconsistency was found in the zirconium sheet reaction data, which is probably the result of differences in buildup of diffusion barrier from specimen to specimen. The reaction with zirconium sheet was found to be more dependent on the degree of outgassing and hydrogen purity, compared with sponge. Maximum reaction rates were 0.080 and 1.34 cm3 of H2 at STP/cm2-min. for 99.95 and 99.999 percent minimum purity hydrogen, respectively.
