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Author: U.S. Atomic Energy Commission
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Category :
Languages : en
Pages :
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Author: U.S. Atomic Energy Commission
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ISBN:
Category :
Languages : en
Pages :
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Author: L. J. Koch
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Category : Breeder reactors
Languages : en
Pages : 334
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The initial "Hazard Summary Report - Experimental Breeder Reactor-II (EBR-II)" was published as ANL-5719 in May, 1957. At the time of preparation of ANL-5719 (early 1957), the design of the EBR-II Facility was in progress - construction had not started. This Addendum is limited, for the most part, to changes which have been made in the EBR-II Facility, and to supporting experimental data developed, since the publication of ANL-5719.
Author: Richard W. Miller
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Category : Nuclear reactor kinetics
Languages : en
Pages : 88
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Author: University of Missouri. Research Reactor Facility
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Category :
Languages : en
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Author:
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Category :
Languages : en
Pages : 151
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This report is the second in a series of compilations of the formal Final Safety Analysis Addenda (FSAA`s) to the EBR-II Hazard Summary Report and Addendum. Sections 2 and 3 are edited versions of the original FSAA`s prepared in support of certain modifications to the reactor-shutdown-system portion of the EBR-II plant-protection system. Section 4 is an edited version of the original FSAA prepared in support of certain modifications to a system classified as an engineered safety feature. These sections describe the pre- and postmodification system, the rationale for the modification, and required supporting safety analysis. Section 5 provides an updated description and analysis of the EBR-II emergency power system. Section 6 summarizes all significant modifications to the EBR-II plant-protection system to date.
Author: Joel W. Chastain
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Category : Gas cooled reactors
Languages : en
Pages : 40
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Author:
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Category :
Languages : en
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This report evaluates abnormal and accident conditions postulated for the EBR-II cover-gas cleanup system (CGCS). Major considerations include loss of CGCS function with a high level of cover-gas activity, loss of the liquid-nitrogen coolant required for removing fission products from the cover gas, contamination of the cover gas from sources other than the reactor, and loss of system pressure boundary. Calculated exposures resulting from the maximum hypothetical accident (MHA) are less than 2% of the 25-Rem limit stipulated in U.S. Regulation 10 CFR 100; id est, a person standing at any point on an exclusion boundary (area radius of 600 m) for 2 h following onset of the postulated release would receive less than 0.45 Rem whole-body dose. The on-site whole-body dose (10 m from the source) would be less than 16 Rem.
Author: J. E. Houghtaling
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Category : Nuclear reactors
Languages : en
Pages : 108
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Author:
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Category :
Languages : en
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Author:
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Category : Energy development
Languages : en
Pages : 128
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