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ISBN 13 :
Total Pages : 204 pages
Book Rating : 4.3/5 (91 download)
Download or read book Irradiation Testing of Ceramic Fuels written by and published by . This book was released on 1962-09 with total page 204 pages. Available in PDF, EPUB and Kindle. Book excerpt:
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ISBN 13 :
Total Pages : 32 pages
Book Rating : 4.3/5 (91 download)
Download or read book Current Status of Irradiation Testing of Thorium Fuels at Oak Ridge National Laboratory written by and published by . This book was released on 19?? with total page 32 pages. Available in PDF, EPUB and Kindle. Book excerpt:
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ISBN 13 :
Total Pages : 114 pages
Book Rating : 4.3/5 (91 download)
Download or read book Summaries of Fuels and Materials Development Programs written by and published by . This book was released on 1960 with total page 114 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Author : J. L. Bates
Publisher :
ISBN 13 :
Total Pages : 56 pages
Book Rating : 4.3/5 (91 download)
Download or read book Irradiation Testing of Plutonium-uranium Oxide Nuclear Fuel written by J. L. Bates and published by . This book was released on 1959 with total page 56 pages. Available in PDF, EPUB and Kindle. Book excerpt:
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ISBN 13 :
Total Pages : 518 pages
Book Rating : 4.X/5 (1 download)
Download or read book Ceramic-matrix Fuels Containing Coated Particles written by and published by . This book was released on 1962 with total page 518 pages. Available in PDF, EPUB and Kindle. Book excerpt:
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ISBN 13 :
Total Pages : 140 pages
Book Rating : 4.3/5 (91 download)
Download or read book Technical Progress Report, Pressurized Water Reactor (PWR) Project for the Period ... written by and published by . This book was released on 1959-12 with total page 140 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Author : Business and Defense Services Administration
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ISBN 13 :
Total Pages : 68 pages
Book Rating : 4.F/5 ( download)
Download or read book Atomic Energy Research Reports for Sale by the U.S. Department of Commerce, Office of Technical Services written by Business and Defense Services Administration and published by . This book was released on 1963 with total page 68 pages. Available in PDF, EPUB and Kindle. Book excerpt:
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ISBN 13 :
Total Pages : 564 pages
Book Rating : 4.3/5 ( download)
Download or read book List written by and published by . This book was released on 1948 with total page 564 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Author : Sharon Marra
Publisher : John Wiley & Sons
ISBN 13 : 0470291753
Total Pages : 192 pages
Book Rating : 4.4/5 (72 download)
Download or read book Ceramics in Nuclear and Alternative Energy Applications, Volume 27, Issue 5 written by Sharon Marra and published by John Wiley & Sons. This book was released on 2009-09-29 with total page 192 pages. Available in PDF, EPUB and Kindle. Book excerpt: This volume focuses on recent developments and advances of ceramics and ceramic matrix composites for use in fission and fusion reactors, nuclear fuels and alternative energy applications. With the continued increasing demands for energy, nuclear energy has experienced a renewed interest. Recent developments associated with advanced fuel cycles have resulted in new research efforts on nuclear fuel materials. The effects of radiation on the properties of ceramics and ceramic matrix composites are also addressed.
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ISBN 13 :
Total Pages : 304 pages
Book Rating : 4.:/5 (31 download)
Download or read book Scientific and Technical Aerospace Reports written by and published by . This book was released on 1971 with total page 304 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Author : Ruth Ann Newman
Publisher :
ISBN 13 :
Total Pages : 296 pages
Book Rating : 4.3/5 (91 download)
Download or read book Nuclear Fuels and Materials Development Program Summary for 1965 written by Ruth Ann Newman and published by . This book was released on 1966 with total page 296 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Author : Robert B. Holden
Publisher :
ISBN 13 :
Total Pages : 264 pages
Book Rating : 4.3/5 (91 download)
Download or read book Ceramic Fuel Elements written by Robert B. Holden and published by . This book was released on 1966 with total page 264 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Author : Oak Ridge National Laboratory
Publisher :
ISBN 13 :
Total Pages : 1470 pages
Book Rating : 4.:/5 (319 download)
Download or read book Inventory of Current Energy Research and Development written by Oak Ridge National Laboratory and published by . This book was released on 1972 with total page 1470 pages. Available in PDF, EPUB and Kindle. Book excerpt:
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ISBN 13 :
Total Pages : 764 pages
Book Rating : 4.3/5 (91 download)
Download or read book Nuclear Science Abstracts written by and published by . This book was released on 1975 with total page 764 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Author : W. D. Fowler
Publisher :
ISBN 13 :
Total Pages : 80 pages
Book Rating : 4.3/5 (91 download)
Download or read book High Power Density Development Project written by W. D. Fowler and published by . This book was released on 1960 with total page 80 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Author : M. P. Johnson
Publisher :
ISBN 13 :
Total Pages : 38 pages
Book Rating : 4.3/5 (91 download)
Download or read book Irradiation of U-Mo Base Alloys written by M. P. Johnson and published by . This book was released on 1964 with total page 38 pages. Available in PDF, EPUB and Kindle. Book excerpt: A series of experiments was designed to assess the suitability of uranium-molybdenum alloys as high-temperature, high-burnup fuels for advanced sodium cooled reactors. Specimens with molybdenum contents between 3 and 10% were subjected to capsule irradiation tests in the Materials Testing Reactor, to burnups up to 10,000 Mwd/MTU at temperatures between 800 and 1500 deg F. The results indicated that molybdenum has a considerable effect in reducing the swelling due to irradiation. For example. 3% molybdemum reduces the swelling from 25%, for pure uranium. to 7% at approximates 3,000 Mwd/MTU at 1270 deg F. Further swelling resistance can be gained by increasing the molybdenum content, but the amount gained becomes successively smaller. At higher irradiation levels, the amount of swelling rapidly becomes greater, and larger amounts of molybdenum are required to provide similar resistance. A limit of 7% swelling, at 900 deg F and an irradiation of 7,230 Mwd/ MTU, requires the use of 10% Nonemolybdenum in the alloy. The burnup rates were in the range of 2.0 to 4.0 x 10p13s fissiom/cc-sec. Small ternary additions of silicon and aluminum were shown to have a noticeable effect in reducing swelling when added to a U-3% Mo alloy base. Under the conditions of the present experiment, 0.26% silicon or 0.38% aluminum were equivalent to 1 to 1 1/2% molybdenum. The Advanced Sodium Cooled Reactor requires a fuel capable of being irradiated to 20,000 Mwd/MTU at temperatures up to 1500 deg C in metal fuel, or equivalent in ceramic fuel. It is concluded that even the highest molybdenum contents considered did not produce a fuel capable of operating satisfactorily under these conditions. The alloys would be useful, however, for less exacting conditions. The U-3% Mo alloy is capable of use up to 3,000 Mwd/MTU at temperatures of 1300 deg F before swelling becomes excessive. The addition of silicon and aluminum would increase this limit to at least 3,000 Mwd/MTU, and possibly more if the
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ISBN 13 :
Total Pages : 24 pages
Book Rating : 4.3/5 (91 download)
Download or read book Irradiation Testing of UO2 written by and published by . This book was released on 1960 with total page 24 pages. Available in PDF, EPUB and Kindle. Book excerpt: Included are 167 references to unclassified reports and scientific journals on irradiation testing of unalloyed UO2. Irradiation behavior and effects, heat transfer calculations, fission gas release, post-irradiation examination, and irradiation capsule design are the subject areas covered.
