Read Books Online and Download eBooks, EPub, PDF, Mobi, Kindle, Text Full Free.
Behavior Of Metallic Fuel In Treat Transient Overpower Tests
Download Behavior Of Metallic Fuel In Treat Transient Overpower Tests full books in PDF, epub, and Kindle. Read online Behavior Of Metallic Fuel In Treat Transient Overpower Tests ebook anywhere anytime directly on your device. Fast Download speed and no annoying ads. We cannot guarantee that every ebooks is available!
Book Synopsis Behavior of Metallic Fuel in Treat Transient Overpower Tests by :
Download or read book Behavior of Metallic Fuel in Treat Transient Overpower Tests written by and published by . This book was released on 1988 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: Results and analyses are reported for TREAT in-pile transient overpower tests of margin to cladding failure and pre-failure axial expansion of metallic fuel. In all cases the power rise was exponential on an 8 s period until either incipient or actual cladding failure was achieved. Test fuel included EBR-II driver fuel and ternary alloy, the reference fuel of the Intergral Fast Reactor concept. Test pin burnup spanned the widest range available. The nature of the observed cladding failure and resultant fuel dispersals is described. Simple models are presented which describe observed cladding failures and pre-failure axial expansions yet are general enough to apply to all metal fuel types.
Book Synopsis Fast Reactor Safety Testing in Transient Reactor Test (TREAT) in the 1980s by :
Download or read book Fast Reactor Safety Testing in Transient Reactor Test (TREAT) in the 1980s written by and published by . This book was released on 1990 with total page 12 pages. Available in PDF, EPUB and Kindle. Book excerpt: Several series of fast reactor safety tests were performed in TREAT during the 1980s. These focused on the transient behavior of full-length oxide fuels (US reference, UK reference, and US advanced design) and on modern metallic fuels. Most of the tests addressed fuel behavior under transient overpower or loss-of-flow conditions. The test series were the PFR/TREAT tests; the RFT, TS, CDT, and RX series on oxide fuels; and the M series on metallic fuels. These are described in terms of their principal results and relevance to analyses and safety evaluation. 4 refs., 3 tabs.
Book Synopsis First Overpower Tests of Metallic IFR [Integral Fast Reactor] Fuel in TREAT [Transient Reactor Test Facility] by :
Download or read book First Overpower Tests of Metallic IFR [Integral Fast Reactor] Fuel in TREAT [Transient Reactor Test Facility] written by and published by . This book was released on 1989 with total page 214 pages. Available in PDF, EPUB and Kindle. Book excerpt: Results and analyses of margin to cladding failure and pre-failure axial expansion of metallic fuel are reported for TREAT in-pile transient overpower tests M5--M7. These are the first such tests on reference binary and ternary alloy fuel of the Integral Fast Reactor (IFR) concept with burnup ranging from 1 to 10 at. %. In all cases, test fuel was subjected to an exponential power rise on an 8 s period until either incipient or actual cladding failure was achieved. Objectives, designs and methods are described with emphasis on developments unique to metal fuel safety testing. The resulting database for cladding failure threshold and prefailure fuel expansion is presented. The nature of the observed cladding failure and resultant fuel dispersals is described. Simple models of cladding failures and pre-failure axial expansions are described and compared with experimental results. Reported results include: temperature, flow, and pressure data from test instrumentation; fuel motion diagnostic data principally from the fast neutron hodoscope; and test remains described from both destructive and non-destructive post-test examination. 24 refs., 144 figs., 17 tabs.
Book Synopsis Review of Behavior of Mixed-oxide Fuel Elements in Extended Overpower Transient Tests in EBR-II. by :
Download or read book Review of Behavior of Mixed-oxide Fuel Elements in Extended Overpower Transient Tests in EBR-II. written by and published by . This book was released on 2001 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: From a series of five tests conducted in EBR-II, a substantial data base has been established on the performance of mixed-oxide fuel elements in a liquid-metal-cooled reactor under slow-ramp transient overpower conditions. Each test contained 19 preirradiated fuel elements with varying design and prior operating histories. Elements with aggressive design features, such as high fuel smear density and/or thin cladding, were included to accentuate transient effects. The ramp rates were either 0.1 or 10%[Delta]P/P/s and the overpowers ranged between[approx]60 and 100% of the elements' prior power ratings. Six elements breached during the tests, all with aggressive design parameters. The other elements, including all those with moderate design features for the reference or advanced long-life drivers for PNC's prototype fast reactor Monju, maintained their cladding integrity during the tests. Posttest examination results indicated that fuel/cladding mechanical interaction (FCMI) was the most significant mechanism causing the cladding strain and breach. In contrast, pressure loading from the fission gas in the element plenum was less important, even in high-burnup elements. During an overpower transient, FCMI arises from fuel/cladding differential thermal expansion, transient fuel swelling, and, significantly, the gas pressure in the sealed central cavity of elements with substantial centerline fuel melting. Fuel performance data from these tests, including cladding breaching margin and transient cladding strain, are correlatable with fuel-element design and operating parameters. These correlations are being incorporated into fuel-element behavior codes. At the two tested ramp rates, fuel element behavior appears to be insensitive to transient ramp rate and there appears to be no particular vulnerability to slow ramp transients as previously perceived.
Book Synopsis First TREAT (Transient Reactor Test Facility) Transient Overpower Tests on U-Pu-Zr Fuel by :
Download or read book First TREAT (Transient Reactor Test Facility) Transient Overpower Tests on U-Pu-Zr Fuel written by and published by . This book was released on 1987 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: Transient Reactor Test Facility (TREAT) tests M5 and M6 were the first transient overpower (TOP) tests of the margin to cladding breach and prefailure elongation of metallic U-Pu-Zr ternary fuel, the reference fuel of the Integral Fast Reactor concept. Similar tests on U-Fs fueled EBR-II driver pins were previously performed and reported (1,2). Results from these earlier tests indicated a margin to failure of about 4 times nominal power and significant axial elongation prior to failure, a feature that was very pronounced at low burnups. While these two fuel types are similar in many respects, the ternary alloy exhibits a much more complex physical structure and is typically irradiated at much higher temperatures. Thus, a prime motivation for performing M5 and M6 was to compare the safety related fuel performance characteristics of U-Fs and U-Pu-Zr. This report described conditions, results, and conclusions of testing of these fuel types.
Book Synopsis Behavior of Mixed-oxide Fuel Elements During an Overpower Transient by :
Download or read book Behavior of Mixed-oxide Fuel Elements During an Overpower Transient written by and published by . This book was released on 1992 with total page 24 pages. Available in PDF, EPUB and Kindle. Book excerpt: For reliable operation of a fast breeder reactor, the fuel elements must be resistant to breaching in slow-ramp, operational overpower transients. To determine this resistance capability of mixed-oxide fuel elements, extended overpower transient tests over a range of element design and operating conditions are being conducted in the Experimental Breeder Reactor-II (EBR-II). These tests are a part of a collaborative Operational Reliability Testing (ORT) program between the US Department of Energy and the Power Reactor and Nuclear Fuel Development Corp. (PNC) of Japan. The Phase 1 portion of the program was successfully completed in 1990; the Phase 2 program is currently in progress. Four extended overpower transient tests were conducted in the Phase-1 ORT program. The results of the first three tests, TOPI-1A, -1B and -1C, using existing preirradiated mixed-oxide fuel elements from the US breeder development program. have been reported. The results of the fourth test, TOPI-1D, using fuel elements specifically designed and fabricated for the ORT program, are the subject of this paper.
Book Synopsis Behavior of Mixed-oxide Fuel Elements During the TOPI-1E Transient Overpower Test by :
Download or read book Behavior of Mixed-oxide Fuel Elements During the TOPI-1E Transient Overpower Test written by and published by . This book was released on 1993 with total page 0 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Posttest Examination Results of Recent Treat Tests on Metal Fuel by :
Download or read book Posttest Examination Results of Recent Treat Tests on Metal Fuel written by and published by . This book was released on 1986 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: A series of in-reactor transient tests is underway to study the characteristics of metal-alloy fuel during transient-overpower-without-scam conditions. The initial tests focused on determining the margin to cladding breach and the axial fuel motions that would mitigate the power excursion. The tests were conducted in flowing-sodium loops with uranium - 5% fissium EBR-II Mark-II driver fuel elements in the TREAT facility. Posttest examination of the tests evaluated fuel elongation in intact pins and postfailure fuel motion. Microscopic examination of the intact pins studied the nature and extent of fuel/cladding interaction, fuel melt fraction and mass distribution, and distribution of porosity. Eutectic penetration and failure of the cladding were also examined in the failed pins.
Book Synopsis Transient Feedback from Fuel Motion in Metal IFR (Integral Fast Reactor) Fuel by :
Download or read book Transient Feedback from Fuel Motion in Metal IFR (Integral Fast Reactor) Fuel written by and published by . This book was released on 1990 with total page 12 pages. Available in PDF, EPUB and Kindle. Book excerpt: Results from hodoscope data analyses are presented for TREAT transient-overpower tests M5 through M7 with emphasis on transient feedback mechanisms, including prefailure expansion at the tops of the fuel pins, subsequent dispersive axial fuel motion, and losses in relative worth of the fuel pins during the tests. Tests M5 and M6 were the first TOP tests of margin to cladding branch and prefailure elongation of D9-clad ternary (U-Pu-Zr) IFR-type fuel. Test M7 extended these results to high-burnup fuel and also initiated transient testing of HT9-clad binary (U-Zr) FFTF-driver fuel. Results show significant prefailure negative reactivity feedback and strongly negative feedback from fuel driven to failure. 4 refs., 6 figs.
Download or read book Energy Research Abstracts written by and published by . This book was released on 1994 with total page 806 pages. Available in PDF, EPUB and Kindle. Book excerpt: Semiannual, with semiannual and annual indexes. References to all scientific and technical literature coming from DOE, its laboratories, energy centers, and contractors. Includes all works deriving from DOE, other related government-sponsored information, and foreign nonnuclear information. Arranged under 39 categories, e.g., Biomedical sciences, basic studies; Biomedical sciences, applied studies; Health and safety; and Fusion energy. Entry gives bibliographical information and abstract. Corporate, author, subject, report number indexes.
Book Synopsis Recent Metal Fuel Safety Tests in TREAT. by :
Download or read book Recent Metal Fuel Safety Tests in TREAT. written by and published by . This book was released on 1986 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: In-reactor safety tests have been performed on metal-alloy reactor fuel to study its response to transient-overpower conditions, in particular, the margin to cladding breach and the axial self-extrusion of fuel within intact cladding. Uranium-fissium EBR-II driver fuel elements of several burnups were tested, some to cladding breach and others to incipient breach. Transient fuel motions were monitored, and time and location of breach were measured. The test results and computations of fuel extrusion and cladding failure in metal-alloy fuel are described.
Book Synopsis Behavior of Low-burnup Metallic Fuels for the Integral Fast Reactor at Elevated Temperatures in Ex-reactor Tests by :
Download or read book Behavior of Low-burnup Metallic Fuels for the Integral Fast Reactor at Elevated Temperatures in Ex-reactor Tests written by and published by . This book was released on 1991 with total page 11 pages. Available in PDF, EPUB and Kindle. Book excerpt: A series of ex-reactor heating tests on low burnup U-26wt.%Pu-10wt.%Zr metallic fuel for the PRISM reactor was conducted to evaluate fuel/cladding metallurgical interaction and its effect on cladding integrity at elevated temperatures. The reaction between the fuel and cladding caused liquid-phase formation and dissolution of the inner surface of the cladding. The rate of cladding penetration was below the existing design correlation, which provides a conservative margin to cladding failure. In a test which enveloped a wide range of postulated reactor transient events, a substantial temporal cladding integrity margin was demonstrated for an intact, whole fuel pin. The cause of the eventual pin breach was reaction-induced cladding thinning combined with fission-gas pressure loading. The behavior of the breached pin was benign. 7 refs., 7 figs., 1 tab.
Book Synopsis Performance of Metal Fuel Elements in an Operational Overpower Transient by :
Download or read book Performance of Metal Fuel Elements in an Operational Overpower Transient written by and published by . This book was released on 1995 with total page 2 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Fast Spectrum Reactors by : Alan E. Waltar
Download or read book Fast Spectrum Reactors written by Alan E. Waltar and published by Springer Science & Business Media. This book was released on 2011-09-28 with total page 717 pages. Available in PDF, EPUB and Kindle. Book excerpt: This book is a complete update of the classic 1981 FAST BREEDER REACTORS textbook authored by Alan E. Waltar and Albert B. Reynolds, which , along with the Russian translation, served as a major reference book for fast reactors systems. Major updates include transmutation physics (a key technology to substantially ameliorate issues associated with the storage of high-level nuclear waste ), advances in fuels and materials technology (including metal fuels and cladding materials capable of high-temperature and high burnup), and new approaches to reactor safety (including passive safety technology), New chapters on gas-cooled and lead-cooled fast spectrum reactors are also included. Key international experts contributing to the text include Chaim Braun, (Stanford University) Ronald Omberg, (Pacific Northwest National Laboratory, Massimo Salvatores (CEA, France), Baldev Raj, (Indira Gandhi Center for Atomic Research, India) , John Sackett (Argonne National Laboratory), Kevan Weaver, (TerraPower Corporation) ,James Seinicki(Argonne National Laboratory). Russell Stachowski (General Electric), Toshikazu Takeda (University of Fukui, Japan), and Yoshitaka Chikazawa (Japan Atomic Energy Agency).
Book Synopsis Nuclear Engineering Handbook by : Kenneth D. Kok
Download or read book Nuclear Engineering Handbook written by Kenneth D. Kok and published by CRC Press. This book was released on 2016-10-03 with total page 978 pages. Available in PDF, EPUB and Kindle. Book excerpt: Building upon the success of the first edition, the Nuclear Engineering Handbook, Second Edition, provides a comprehensive, up-to-date overview of nuclear power engineering. Consisting of chapters written by leading experts, this volume spans a wide range of topics in the areas of nuclear power reactor design and operation, nuclear fuel cycles, and radiation detection. Plant safety issues are addressed, and the economics of nuclear power generation in the 21st century are presented. The Second Edition also includes full coverage of Generation IV reactor designs, and new information on MRS technologies, small modular reactors, and fast reactors.
Author :United States. Congress. House. Committee on Appropriations. Subcommittee on Energy and Water Development Publisher : ISBN 13 : Total Pages :1454 pages Book Rating :4.F/5 ( download)
Book Synopsis Energy and water development appropriations for 1988 by : United States. Congress. House. Committee on Appropriations. Subcommittee on Energy and Water Development
Download or read book Energy and water development appropriations for 1988 written by United States. Congress. House. Committee on Appropriations. Subcommittee on Energy and Water Development and published by . This book was released on 1987 with total page 1454 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Nuclear Safety written by and published by . This book was released on 1969 with total page 1204 pages. Available in PDF, EPUB and Kindle. Book excerpt:
![Download First Overpower Tests of Metallic IFR [Integral Fast Reactor] Fuel in TREAT [Transient Reactor Test Facility] PDF Online Free](https://books.google.com/books/content/images/frontcover/GIvIswEACAAJ?fife=w200-h370)
