Performance of Unencapsulated (U, Pu)O2 Fuel Pins (series F3A) Irradiated in EBR-II to 50,000 MWd/Te PDF Download
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Languages : en
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Category : Nuclear energy
Languages : en
Pages : 1762
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Languages : en
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Languages : en
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Author: S. A. Rabin
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Languages : en
Pages : 65
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Languages : en
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A total of 86 experimental fuel pins with various fuel, liner, and cladding candidate materials have been irradiated in the Experimental Breeder Reactor-II (EBR-II) and the Fast Flux Test Facility (FFTF) reactor as part of the SP-100 fuel pin irradiation testing program. Postirradiation examination results from these fuel pin are key in establishing performance correlations and demonstrating the lifetime and safety of the reactor fuel system. This paper provides a brief description of the in-reactor fuel pin tests and presents the most recent irradiation data on the performance of wrought rhenium (Re) liner material and high density UN fuel at goal burnup of 6 atom percent (at. %). It also provides an overview of the significant variety of other fuel/liner/cladding combinations which were irradiated as part of this program and which may be of interest to more advanced efforts.
Author: E. O. Ballard
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Languages : en
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![Steady State Irradiation Behavior of Mixed Oxide Fuel Pins Irradiated in EBR-II. [LMFBR]. PDF](https://books.google.com/books/content/images/frontcover/MTSVwgEACAAJ?fife=w80-h100)
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Languages : en
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Results are presented from the steady state fuel irradiation program in EBR-II, which is intended to provide the technology and engineering test data in near-term support of the design and operation of the Fast Flux Test Facility (FFTF) and Fast Breeder Reactors (FBR's) utilizing the reference fuel system - UO2--PuO2 mixed oxide with 25 +- 5 w/o PuO2 and 20% CW Type 316 stainless steel cladding. This program is also intended to develop the base for longer term innovative improvements and design changes required for FBR's and develop design criteria and associated computer-based design codes for accurately predicting fuel performance.
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Languages : en
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Author: Robert L. Fish
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Category : Fission gases
Languages : en
Pages : 40
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