Download or read book LMFBR Spent Fuel Shipping Cask written by and published by . This book was released on 1974 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Assessment of LMFBR Spent Fuel Shipping Cask Concepts for the CRBRP and the US Conceptual Design Study written by and published by . This book was released on 1980 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: Study of conceptual shipping systems for CRBRP and CDS spent fuel has shown that systems significantly different from those used for LWR spent fuel will be required. In the conceptual design, liquid sodium was assumed to be the coolant in canisters containing the spent fuel assemblies, and multiple levels of containment were provided by canisters, an inner cask lid and an outer cask lid. Cask cooling at the reactor site during loading, and cooldown at the receiving site prior to unloading are significant but tractable problems.

Download or read book Fire Protection Device for LMFBR Spent Fuel Shipping Casks written by and published by . This book was released on 1977 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: This report describes the analysis and experimental evaluation of a device to provide fire protection for a shipping cask used to transport liquid metal fast breeder reactor (LMFBR) fuel rods. Thermal analyses of various fire protection schemes were conducted by means of the finite difference code, CINDA. The choice of materials for the cask body was determined to be less important than the dimensions and number of cooling fins attached to the cask. Of several protection methods considered, radiation/convection shields between the cooling fins looked most attractive; these were tested on a quarter-scale cask model. The shields consisted of bimetallic bands which expanded when heated, blocking the fire, and retracted when cooled. This automatic reversibility would allow the fins to dissipate internally generated heat of a full-size cask once the fire was out. Tests showed that, even in an asymmetric fire exposure, the bands expanded to provide protection to the cask. The directly exposed surface of the cask model, protected this way, reached a temperature of only 180°C compared with 295°C in the unprotected state, when subjected to a butane flame for 0.5 h at a distance of 15 cm. Greater relative effectiveness could be expected in an engulfing fire in which the bands would expand more symmetrically.

Download or read book Spent Fuel Shipping Cask Accident Evaluation written by and published by . This book was released on 1975 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: Mathematical models have been developed to simulate the dynamic behavior, following a hypothetical accident and fire, of typical casks designed for the rail shipment of spent fuel from nuclear reactors, and to determine the extent of radioactive releases under postulated conditions. The casks modeled were the IF-300, designed by the General Electric Company for the shipment of spent LWR fuel, and a cask designed by the Aerojet Manufacturing Company for the shipment of spent LMFBR fuel.

Download or read book Spent Nuclear Fuel Heat Transfer Fuel Casks and Transfer Operations written by D. J. Groetch and published by . This book was released on 1971 with total page 60 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Conceptual Designs for LMFBR Spent Fuel Shipping Casks written by and published by . This book was released on 1978 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Radiation Shield Design for LMFBR Spent fuel Shipping Casks written by and published by . This book was released on 1977 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: Previous analyses have examined a limited number of the alternatives available for designing an LMFBR spent-fuel shipping cask (SFSC) using a non-volatile neutron shield; i.e., a neutron shield which will not be lost in an accident involving a fire. The present study extends the scope of these hypothetical designs to include combinations of volatile and non-volatile neutron shield materials.

Download or read book LMFBR Spent Fuel Transport written by A. R. Irvine and published by . This book was released on 1975 with total page 23 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book LMFBR Spent Fuel Transport written by and published by . This book was released on 1972 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: Conceptual designs for 6- and 18-subassembly casks are presented. The casks are intended for transport of LMFBR spent fuel which has decayed a minimum of 30 days. These casks use sodium as the primary coolant, an auxiliary shield coolant system in normal operation, heavy steel members as both gamma shield and structure, and a eutectic mixture of LiOH and NaOH as a neutron shield. The analysis indicates that there will be no leakage of coolant or fission products under normal or hypothetical accident conditions.

Download or read book Prediction of Thermal Capability for a Proposed LMFBR Spent Fuel Shipping Cask written by and published by . This book was released on 1979 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Prediction of Thermal Capability for a Proposed LMFBR Spent Fuel Shipping Cask written by and published by . This book was released on 1979 with total page 65 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Sodium cooled LMFBR Cask Recommendations written by and published by . This book was released on 1977 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: In April of 1970 a design study to establish the parameters of a shipping cask for LMFBR Spent Fuel Assemblies from FFTF and the first demonstration plant was initiated. The basic criteria presented were that the cask should be limited to 75 tons, and that the cask should be compatible with the FFTF Fuel Assembly design and the first demonstration LMFBR Fuel Assembly design. Several features of the I-(182)-1 cask and their basis are described.

Download or read book The Environmental Impact of Transportation of Nuclear Materials in the LMFBR Program written by United States. Energy Research and Development Administration and published by . This book was released on 1975 with total page 184 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book BR 100 Spent Fuel Shipping Cask Development written by and published by . This book was released on 1990 with total page 5 pages. Available in PDF, EPUB and Kindle. Book excerpt: Continued public acceptance of commercial nuclear power is contingent to a large degree on the US Department of Energy (DOE) establishing an integrated waste management system for spent nuclear fuel. As part of the from-reactor transportation segment of this system, the B W Fuel Company (BWFC) is under contract to the DOE to develop a spent-fuel cask that is compatible with both rail and barge modes of transportation. Innovative design approaches were the keys to achieving a cask design that maximizes payload capacity and cask performance. The result is the BR-100, a 100-ton rail/barge cask with a capacity of 21 PWR or 52 BWR ten-year cooled, intact fuel assemblies. 3 figs.

Download or read book Spent Fuel Storage System for LMFBR Fuel Experiments written by and published by . This book was released on 1983 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: Fuel that had been irradiated in the Argonne National Laboratory Experimental Breeder Reactor II (EBR-II) at Idaho Falls, Idaho, and examined at the Hanford Engineering Development Laboratory at Richland, Washington, was placed in long term retrievable storage utilizing a system designed at Hanford. The Spent Fuel Storage Cask system was designed for transport and storage of a large quantity of spent fuel at the Hanford 200 Area transuranic (TRU) asphalt storage pad. The entire system is designed for long term retrievable storage to allow future reprocessing of the fuel. The system was designed to meet the criticality, shielding, and thermal requirements for a maximum fuel load of four kilograms fissile. The Spent Fuel Storage Cask was built to transport and store the fuel from EBR-II on the TRU asphalt storage pad.

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).

Download or read book Nuclear Science Abstracts written by and published by . This book was released on 1976-06 with total page 1216 pages. Available in PDF, EPUB and Kindle. Book excerpt: