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Author : Alvin Boltax
Publisher :
ISBN 13 :
Total Pages : 30 pages
Book Rating : 4.:/5 (387 download)
Download or read book Reliability of Fast Reactor Mixed-oxide Fuel During Operational Transients written by Alvin Boltax and published by . This book was released on 1991 with total page 30 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Author :
Publisher :
ISBN 13 :
Total Pages : 7 pages
Book Rating : 4.:/5 (727 download)
Download or read book Performance of Fast Reactor Mixed-oxide Fuels Pins During Extended Overpower Transients written by and published by . This book was released on 1991 with total page 7 pages. Available in PDF, EPUB and Kindle. Book excerpt: The Operational Reliability Testing (ORT) program, a collaborative effort between the US Department of Energy and the Power Reactor and Nuclear Fuel Development Corp. (PNC) of Japan, was initiated in 1982 to investigate the behavior of mixed-oxide fuel pin under various slow-ramp transient and duty-cycle conditions. In the first phase of the program, a series of four extended overpower transient tests, with severity sufficient to challenge the pin cladding integrity, was conducted. The objectives of the designated TOPI-1A through -1D tests were to establish the cladding breaching threshold and mechanisms, and investigate the thermal and mechanical effects of the transient on pin behavior. The tests were conducted in EBR-2, a normally steady-state reactor. The modes of transient operation in EBR-2 were described in a previous paper. Two ramp rates, 0.1%/s and 10%/s, were selected to provide a comparison of ramp-rate effects on fuel behavior. The test pins chosen for the series covered a range of design and pre-test irradiation parameters. In the first test (1A), all pins maintained their cladding integrity during the 0.1%/s ramp to 60% peak overpower. Fuel pins with aggressive designs, i.e., high fuel- smear density and/or thin cladding, were, therefore, included in the follow-up 1B and 1C tests to enhance the likelihood of achieving cladding breaching. In the meantime, a higher pin overpower capability, to greater than 100%, was established by increasing the reactor power limit from 62.5 to 75 MWt. In this paper, the significant results of the 1B and 1C tests are presented. 4 refs., 5 figs., 1 tab.
Author :
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ISBN 13 :
Total Pages : 24 pages
Book Rating : 4.:/5 (727 download)
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.
Author : D. Faude
Publisher :
ISBN 13 :
Total Pages : 532 pages
Book Rating : 4.3/5 (91 download)
Download or read book Engineering of Fast Reactors for Safe and Reliable Operation: International Conference written by D. Faude and published by . This book was released on 1973 with total page 532 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Author : International Atomic Energy Agency
Publisher :
ISBN 13 : 9781523130191
Total Pages : 0 pages
Book Rating : 4.1/5 (31 download)
Download or read book Status of Fast Reactor Research and Technology Development written by International Atomic Energy Agency and published by . This book was released on 2012 with total page 0 pages. Available in PDF, EPUB and Kindle. Book excerpt: "Based on a recommendation from the Technical Working Group on Fast Reactors, this publication is a regular update of previous publications on fast reactor technology. The publication provides comprehensive and detailed information on the technology of fast neutron reactors. The focus is on practical issues that are useful to engineers, scientists, managers, university students and professors. The main issues of discussion are experience in design, construction, operation and decommissioning, various areas of research and development, engineering, safety and national strategies, and public acceptance of fast reactors. In the summary the reader will find national strategies, international initiatives on innovative (i.e. Generation IV) systems and an assessment of public acceptance as related to fast reactors."--Résumé de l'éditeur.
Author : H. Tsai
Publisher :
ISBN 13 :
Total Pages : 7 pages
Book Rating : 4.:/5 (391 download)
Download or read book Performance of Fast Reactor Mixed-oxide Fuel Pins During Extended Overpower Transients written by H. Tsai and published by . This book was released on 1991 with total page 7 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Author :
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ISBN 13 :
Total Pages : 484 pages
Book Rating : 4.0/5 ( download)
Download or read book Energy Research Abstracts written by and published by . This book was released on 1994-02 with total page 484 pages. Available in PDF, EPUB and Kindle. Book excerpt:
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.
Author : Karl P. Cohen
Publisher :
ISBN 13 :
Total Pages : 48 pages
Book Rating : 4.3/5 (91 download)
Download or read book The Southwest Experimental Fast Oxide Reactor written by Karl P. Cohen and published by . This book was released on 1963 with total page 48 pages. Available in PDF, EPUB and Kindle. Book excerpt:
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ISBN 13 :
Total Pages : 658 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 1976 with total page 658 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Author : J. H. Field
Publisher :
ISBN 13 :
Total Pages : 84 pages
Book Rating : 4.:/5 (319 download)
Download or read book Experimental Studies of Transient Effects in Fast Reactor Fuels written by J. H. Field and published by . This book was released on 1962 with total page 84 pages. Available in PDF, EPUB and Kindle. Book excerpt: An experimental program to evaluate the performance of FCR and EFCR fuel during transient operation is outlined, and the initial series of tests are described in some detail. Test results from five experiments in the TREAT reactor, using 1-in. OD SS-clad UO2 fuel specimens, are compared with regard to fuel temperatures, mechanical integrity, and post-irradiation appearance. Incipient fuel pin failure limits for transients are identified with maximum fuel temperatures in the range of 7000 deg F. Multiple transient damage to the cladding is likely for transients above the melting point of the fuel.
Author :
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ISBN 13 :
Total Pages : 1058 pages
Book Rating : 4.0/5 ( download)
Download or read book Nuclear Science Abstracts written by and published by . This book was released on 1969-10 with total page 1058 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Author : Willem Frederik Geert van Rooijen
Publisher : IOS Press
ISBN 13 : 9781586036966
Total Pages : 160 pages
Book Rating : 4.0/5 (369 download)
Download or read book Improving Fuel Cycle Design and Safety Characteristics of a Gas Cooled Fast Reactor written by Willem Frederik Geert van Rooijen and published by IOS Press. This book was released on 2006 with total page 160 pages. Available in PDF, EPUB and Kindle. Book excerpt: The Generation IV Forum is an international nuclear energy research initiative aimed at developing the fourth generation of nuclear reactors, envisaged to enter service halfway the 21st century. One of the Generation IV reactor systems is the Gas Cooled Fast Reactor (GCFR), the subject of study in this thesis. The Generation IV reactor concepts should improve all aspects of nuclear power generation. Within Generation IV, the GCFR concept specifically targets sustainability of nuclear power generation. The Gas Cooled Fast Reactor core power density is high in comparison to other gas cooled reactor concepts. Like all nuclear reactors, the GCFR produces decay heat after shut down, which has to be transported out of the reactor under all circumstances. The layout of the primary system therefore focuses on using natural convection Decay Heat Removal (DHR) where possible, with a large coolant fraction in the core to reduce friction losses.
Author : American Nuclear Society
Publisher :
ISBN 13 :
Total Pages : 662 pages
Book Rating : 4.3/5 (91 download)
Download or read book Transactions of the American Nuclear Society written by American Nuclear Society and published by . This book was released on 1992 with total page 662 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Author : United States. Congress. House. Committee on Appropriations. Subcommittee on Energy and Water Development
Publisher :
ISBN 13 :
Total Pages : 2288 pages
Book Rating : 4.:/5 ( download)
Download or read book Energy and Water Development Appropriations for 1987: Department of Energy FY 1987 budget justifications written by United States. Congress. House. Committee on Appropriations. Subcommittee on Energy and Water Development and published by . This book was released on 1986 with total page 2288 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Author : United States. Congress. House. Committee on Appropriations. Subcommittee on Energy and Water Development
Publisher :
ISBN 13 :
Total Pages : 2288 pages
Book Rating : 4.:/5 (319 download)
Download or read book Energy and water development appropriations for 1987 written by United States. Congress. House. Committee on Appropriations. Subcommittee on Energy and Water Development and published by . This book was released on 1986 with total page 2288 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book EXPERIMENTAL STUDIES OF TRANSIENT EFFECTS IN FAST REACTOR FUELS. SERIES III. PRE-IRRADIATED MIXED OXIDE (PuO2--UO2) IRRADIATIONS. FINAL REPORT. TRANSIENT IRRADIATIONS. written by and published by . This book was released on 1967 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt:
