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Book Spent Fuel Shipping Cask for PM 1 and PM 3A Nuclear Power Plants Hazards Summary Evaluation

Download or read book Spent Fuel Shipping Cask for PM 1 and PM 3A Nuclear Power Plants Hazards Summary Evaluation written by and published by . This book was released on 1961 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: The design of the spent fuel shipping cask proposed for use in transporting irradiated cores from both the PM-1 and PM-3A Nuclear Power Plants has been evaluated under normal and accident conditions. Specifically, the following aspects of the design were analyzed and evaluated: (1) The lead shielding provided within the walls of the shipping cask and associated attachments assures that ICC regulations of 200 mr/hr at the surface and 10 mr/hr at one meter distance are satisfied. (2) A rugged crash frame, cask shroud, and shipping pallet combination completely envelopes the cask and insures the structural integrity of the cask under all conditions of transport. (3) The fuel bundles, control rods, and poison plates are securely locked within the core shroud by means of a core handling fixture with suitable safety devices to guarantee no possible change in core geometry. (4) Based on an unirradiated core, adequate poisoning in the form of control rods and poison plates is provided to obtain a K/sub eff/ of less than 0.9 during shipment. (5) As a result of conservative calculations, sufficient heat transfer capability has been provided in the shipping cask to dissipate 2 kw of heat with coolant temperatures less than 192 deg F and cask surface temperatures less than 180 deg F with water coolant present. (6) Under loss of coolant conditions with only air as a heat transfer medium, it is shown that the peak fuel temperature is 732 deg F which is 218 deg F below the temperature at which sound fuel elements would rupture. (7) In the event of the remote accident condition in which 5% of the fuel elements are postulated to break into one foot long sections, it is shown that negligible quantities of activity are released to the surrounding environment. As a result of the foregoing conclusions, the proposed spent fuel shipping cask design is adequate for use in transporting spent cores from both the PM-1 and PM-3A plants to the Idaho Chemical Processing Plant with no undue hazard to the health and safety of operating personnel and the general public. (auth).

Book PM 1 Reactor Core Final Design Report

Download or read book PM 1 Reactor Core Final Design Report written by and published by . This book was released on 1962 with total page 200 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Book Nuclear Science Abstracts

Download or read book Nuclear Science Abstracts written by and published by . This book was released on 1975-02 with total page 850 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Book Reports Received by Division of Technical Information Extension

Download or read book Reports Received by Division of Technical Information Extension written by U.S. Atomic Energy Commission. Division of Technical Information and published by . This book was released on with total page 900 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Book Nuclear Science Abstracts

Download or read book Nuclear Science Abstracts written by and published by . This book was released on 1973 with total page 1162 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Book Probabilistic Assessment of Spent Fuel Shipping Cask Response to Severe Transportation Accident Conditions  Report Summary

Download or read book Probabilistic Assessment of Spent Fuel Shipping Cask Response to Severe Transportation Accident Conditions Report Summary written by and published by . This book was released on 1985 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: The licensing of commercial nuclear spent shipping casks in the United States is regulated by 10CFR71. In order to be licensed, casks must be designed not to fail under hypothetical test conditions specified in Appendix B of this regulation. Questions have been raised about the suitability of these tests in simulating actual transportation accident conditions. Our study addresses the adequacy of current regulations by comparing real-world accident conditions with regulatory test specifications using more complete accident statistics and more sophisticated structural analyses than have been used in studies to date. Our objective is to evaluate the protection provided by current regulations against severe accident conditions for commercial spent nuclear fuel casks that are transported by truck or rail. The complete spectrum of truck and rail accidents will be reviewed in order to determine the frequency (or infrequency) of cask failures during transportation accidents. 3 references, 1 figure.

Book Spent Fuel Transportation Risk Assessment

Download or read book Spent Fuel Transportation Risk Assessment written by U.s. Nuclear Regulatory Commission and published by Createspace Independent Pub. This book was released on 2014-05-18 with total page 510 pages. Available in PDF, EPUB and Kindle. Book excerpt: The U.S. Nuclear Regulatory Commission has conducted several risk assessments and other analysis to evaluation the safety of transportation of spent power reactor nuclear fuel during the past 35 years.

Book Evaluation of Dry Versus Wet Unloading of Spent Nuclear Fuel Shipping Casks

Download or read book Evaluation of Dry Versus Wet Unloading of Spent Nuclear Fuel Shipping Casks written by and published by . This book was released on 1980 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: The Transportation Technology Center at Sandia National Laboratories completed an evaluation of unloading methods for spent fuel by sponsoring technical programs at Exxon Nuclear Company, Inc., and General Electric Corporation. These programs provided a comprehensive assessment of the relative merits, capabilities, and limitations of dry and wet unloading methods. The results of this evaluation, when continued, are expected to impact the development of future spent fuel and waste transportation systems. In addition, final conclusions of the evaluation will provide input to designers of future receiving and shipping interfaces at away-from-reactor spent fuel storage facilities and geologic nuclear waste repositories in the United States. The results presented here apply to the case where uncanistered spent fuel from light water reactors is to be handled. The conclusions may be different if uncontaminated canistered waste forms are considered in the future.

Book Transportation of Used Fuel

Download or read book Transportation of Used Fuel written by and published by . This book was released on 1992 with total page 2 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Book Spent Fuel Shipping Cask Handling Capability Assessment of 27 Selected Light Water Reactors

Download or read book Spent Fuel Shipping Cask Handling Capability Assessment of 27 Selected Light Water Reactors written by and published by . This book was released on 1984 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: This report presents an assessment of the spent fuel shipping cask handling capabilities of those nuclear plants currently projected to lose full core reserve capability in their spent fuel storage basins in the near future. The purpose of this assessment is to determine which cask types, in the current fleet, each of the selected reactors can handle. The cask handling capability of a nuclear plant depends upon both external and internal conditions at the plant. The availability of a rail spur, the lifting capacity of the crane, the adequacy of clearances in the cask receiving, loading, and decontamination areas and similar factors can limit the types of casks that can be utilized at a particular plant. This report addresses the major facility capabilities used in assessing the types of spent fuel shipping casks that can be handled at each of the 27 selected nuclear plants approaching a critical storage situation. The results of this study cannot be considered to be final and are not intended to be used to force utilities to ship by a particular mode. In addition, many utilities have never shipped spent fuel. Readers are cautioned that the results of this study reflect the current situation at the selected plants and are based on operator perceptions and guidance from NRC related to the control of heavy loads at nuclear power plants. Thus, the cask handling capabilities essentially represent snap-shots in time and could be subject to change as plants further analyze their capabilities, even in the near-term. The results of this assessment indicate that 48% of the selected plants have rail access and 59% are judged to be candidates for overweight truck shipments (with 8 unknowns due to unavailability of verifiable data). Essentially all of the reactors can accommodate existing legal-weight truck casks. 12 references, 1 figure, 4 tables.

Book Risk Comparisons for the Transportation of Spent Fuel from Nuclear Reactors

Download or read book Risk Comparisons for the Transportation of Spent Fuel from Nuclear Reactors written by and published by . This book was released on 1985 with total page 9 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Book IMPACT ANALYSIS OF SPENT FUEL DRY CASKS UNDER ACCIDENTAL DROP SCENARIOS

Download or read book IMPACT ANALYSIS OF SPENT FUEL DRY CASKS UNDER ACCIDENTAL DROP SCENARIOS written by J. XU and published by . This book was released on 2003 with total page 8 pages. Available in PDF, EPUB and Kindle. Book excerpt: A series of analyses were performed to assess the structural response of spent nuclear fuel dry casks subjected to various handling and on-site transfer events. The results of these analyses are being used by the Nuclear Regulatory Commission (NRC) to perform a probabilistic risk assessment (PRA). Although the PRA study is being performed for a specific nuclear plant, the PRA study is also intended to provide a framework for a general methodology that could also be applied to other dry cask systems at other nuclear plants. The dry cask system consists of a transfer cask, used for handling and moving the multi-purpose canister (MPC) that contains the fuel, and a storage cask, used to store the MPC and fuel on a concrete pad at the site. This paper describes the analyses of the casks for two loading events. The first loading consists of dropping the transfer cask while it is lowered by a crane to a concrete floor at ground elevation. The second loading consists of dropping the storage cask while it is being transferred to the concrete storage pad outdoors. Three dimensional finite element models of the transfer cask and storage cask, containing the MPC and fuel, were utilized to perform the drop analyses. These models were combined with finite element models of the target structures being impacted. The transfer cask drop analyses considered various drop heights for the cask impacting the reinforced concrete floor at ground level. The finite element model of the target included a section of the concrete floor and concrete wall supporting the floor. The storage cask drop analyses evaluated a 30.5 cm (12 in.) drop of the cask impacting three different surfaces: reinforced concrete, asphalt, and gravel.

Book MND M

    Book Details:
  • Author :
  • Publisher :
  • Release : 19??
  • ISBN :
  • Pages : 200 pages

Download or read book MND M written by and published by . This book was released on 19?? with total page 200 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Book Evaluation of FSV 1 Cask for the Transport of LWR Irradiated Fuel Assemblies

Download or read book Evaluation of FSV 1 Cask for the Transport of LWR Irradiated Fuel Assemblies written by and published by . This book was released on 1980 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: The Model FSV-1 spent fuel shipping cask was designed by General Atomic Company (GA) to service the Fort St. Vrain (FSV) nuclear generating station, a High Temperature Gas Reactor (HTGR) owned and operated by Public Service Company of Colorado (PSC). This report presents an evaluation of the suitability of the FSV-1 cask for the transport of irradiated Light Water Reactor (LWR) fuel assemblies from both Pressurized Water Reactors (PWR) and Boiling Water Reactors (BWR). The FSV-1 cask evaluation parameters covered a wide spectrum of LWR fuel assemblies, based on burnup in Megawatt Days/Metric Ton of Heavy Metal (MWD/MTHM) and years of decay since irradiation. The criteria for suitability included allowable radiation dose rates, cask surface and interior temperatures and the Gross Vehicle Weight (GVW) of the complete shipping system.

Book Atomindex

    Book Details:
  • Author : International Atomic Energy Agency
  • Publisher :
  • Release : 1964
  • ISBN :
  • Pages : 1700 pages

Download or read book Atomindex written by International Atomic Energy Agency and published by . This book was released on 1964 with total page 1700 pages. Available in PDF, EPUB and Kindle. Book excerpt: