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Revised FINAL–REPORT NO. 2: INDEPENDENT CONFIRMATORY SURVEY SUMMARY AND RESULTS FOR THE ENRICO FERMI ATOMIC POWER PLANT, UNIT 1, NEWPORT, MICHIGAN (DOCKET NO. 50 16; RFTA 10-004) 2018-SR-02-1

Description: The Enrico Fermi Atomic Power Plant, Unit 1 (Fermi 1) was a fast breeder reactor design that was cooled by sodium and operated at essentially atmospheric pressure. On May 10, 1963, the Atomic Energy Commission (AEC) granted an operating license, DPR-9, to the Power Reactor Development Company (PRDC), a consortium specifically formed to own and operate a nuclear reactor at the Fermi 1 site. The reactor was designed for a maximum capability of 430 megawatts (MW); however, the maximum reactor power with the first core loading (Core A) was 200 MW. The primary system was filled with sodium in December 1960 and criticality was achieved in August 1963. The reactor was tested at low power during the first couple years of operation. Power ascension testing above 1 MW commenced in December 1965 immediately following the receipt of a high-power operating license. In October 1966 during power ascension, zirconium plates at the bottom of the reactor vessel became loose and blocked sodium coolant flow to some fuel subassemblies. Two subassemblies started to melt and the reactor was manually shut down. No abnormal releases to the environment occurred. Forty-two months later after the cause had been determined, cleanup completed, and the fuel replaced, Fermi 1 was restarted. However, in November 1972, PRDC made the decision to decommission Fermi 1 as the core was approaching its burn-up limit. The fuel and blanket subassemblies were shipped off-site in 1973. Following that, the secondary sodium system was drained and sent off-site. The radioactive primary sodium was stored on-site in storage tanks and 55 gallon (gal) drums until it was shipped off-site in 1984. The initial decommissioning of Fermi 1 was completed in 1975. Effective January 23, 1976, DPR-9 was transferred to the Detroit Edison Company (DTE) as a 'possession only' license (DTE 2010a). This report ...
Date: October 27, 2011
Creator: Bailey, Erika
Partner: UNT Libraries Government Documents Department

Evaporative removal of sodium: interim progress report and preliminary facility specification

Description: A summary of the current Evaporative Removal of Sodium (ERNA) activities at the Energy Systems Group is presented. Also included is a review of earlier work on sodium evaporation. As a result of this work it was concluded that the ERNA process was extremely successful and worthy of future consideration as a recognized process for reactor components. Also included in the report is a Preliminary Outline Specification for a large facility to remove sodium from full size CRBR fuel rod assemblies.
Date: September 27, 1978
Creator: Welch, F.H.
Partner: UNT Libraries Government Documents Department

Disposal of Shippingport LWBR spent Nuclear Fuel in Yucca Mountain: Waste Package Internal Criticality Analysis

Description: The paper presents the disposal criticality analysis for the Shippingport Light Water Breeder Reactor (LWBR) spent nuclear fuel (SNF) being considered for disposal at the potential Yucca Mountain repository. The methodology for disposal criticality analysis includes the evaluation of the potential configurations--intact through degraded--based on the supporting analyses of the physical and geochemical processes that degrade the fuel over time.
Date: September 27, 2000
Creator: Radulescu, H.R. & Davis, J.W.
Partner: UNT Libraries Government Documents Department

Experimental studies of a large heterogeneous LMFBR benchmark core, ZPPR-13A

Description: The ZPPR-13 program provides basic physics information for testing calculations of radially heterogeneous cores of about 700 MWe size. ZPPR-13 is part of the JUPITER cooperative program between Japan and the US. The results are presented of measurements and analysis for the first assembly, ZPPR-13A. These are the first data for heterogeneous cores of this size available in the US and complement results from ZPPR-9, a conventional LMFBR of similar size.
Date: May 27, 1983
Creator: Brumbach, S.B.; Collins, P.J.; Carpenter, S.G.; Suzuki, S. & Kawashima, M.
Partner: UNT Libraries Government Documents Department

Sodium technology activities at HEDL in support of fast reactor development and the FFTF

Description: Activities of the Hanford Engineering Development Laboratory are presented. A brief description of FFTF and some highlights of reactor operations are reviewed. The sodium technology work at HEDL is summarized by discussing several facets of the program and their tie-ins to breeder reactor development.
Date: February 27, 1984
Creator: Atwood, J.M.
Partner: UNT Libraries Government Documents Department

Alternative oxide fuel pellet fabrication for irradiation testing. [LMFBR]

Description: Fabrication of experimental breeder reactor fuel pellets by the common cold-press-and-sinter technique for irradiation testing in EBR-II is discussed. Fuel types include mixed thoria-plutonia, UO/sub 2/ enriched with 22 weight percent /sup 233/U in U, UO/sub 2/ enriched with thirty-four weight percent /sup 235/U in U, and mixed urania-plutonia.
Date: October 27, 1978
Creator: Rasmussen, D. E.; Jentzen, W. R. & McCord, R. B.
Partner: UNT Libraries Government Documents Department