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Keese, H.; Anspach, W.; Christ, R.
PATRAM '83: 7th international symposium on packaging and transportation of radioactive materials1983
PATRAM '83: 7th international symposium on packaging and transportation of radioactive materials1983
AbstractAbstract
No abstract available
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Oak Ridge National Lab., TN (USA); p. IV.14-IV.15; 1983; p. IV.14-IV.15; 7. international symposium on packaging and transportation of radioactive materials; New Orleans, LA (USA); 15-20 May 1983; Available from NTIS, PC A21/MF A01; 1 as DE83012390
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Keese, H.; Anspach, W.; Christ, R.
PATRAM '83: 7th international symposium on packaging and transportation of radioactive materials. Proceedings. Volume 11983
PATRAM '83: 7th international symposium on packaging and transportation of radioactive materials. Proceedings. Volume 11983
AbstractAbstract
[en] Qualification and application of the basic design of the TN 1300 transport/storage cask are discussed. 2 references, 4 figures
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Oak Ridge National Lab., TN (USA); p. 242-247; Dec 1983; p. 242-247; 7. international symposium on packaging and transportation of radioactive materials; New Orleans, LA (USA); 15-20 May 1983; Available from NTIS, PC A99/MF A01; 1 as TI84006239
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Pennington, C.W.; Teer, B.R.
Third international spent fuel storage technology symposium/workshop: proceedings. Volume 21986
Third international spent fuel storage technology symposium/workshop: proceedings. Volume 21986
AbstractAbstract
[en] Transnuclear's dry storage technology is presented from the perspectives of its past, present and future. Predecessor dry transport designs from the TN-8, TN-9 and TN-12 series show the demonstrated and operationally proven bases of current dry storage cask designs such as the TN-BRP and TN-REG. These current designs are reviewed in the context of their present application and utilization in development programs. Future expansion of the capabilities of current cask designs and examples of new developments in dry storage casks are also discussed
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Pacific Northwest Labs., Richland, WA (USA); Deutsche Gesellschaft fuer Wiederaufarbeitung von Kernbrennstoffen m.b.H. (DWK), Hannover (Germany, F.R.); Electric Power Research Inst., Palo Alto, CA (USA); Ontario Hydro, Toronto (Canada); p. P.91-P.93; 1986; p. P.91-P.93; 3. international symposium/workshop on irradiated fuel storage; Seattle, WA (USA); 8-10 Apr 1986; Available from NTIS, PC A23/MF A01; 1 as DE86014260
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Kaneko, H.; Tanaka, Y.; Tanuma, H.
Third international spent fuel storage technology symposium/workshop: proceedings. Volume 21986
Third international spent fuel storage technology symposium/workshop: proceedings. Volume 21986
AbstractAbstract
[en] Experience in cask storage of mixed oxide spent fuels in Japan is presented. The authors discuss and compare wet storage and dry storage, concluding that a trench type cask storage facility is considered one of the most promising methods in Japan
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Pacific Northwest Labs., Richland, WA (USA); Deutsche Gesellschaft fuer Wiederaufarbeitung von Kernbrennstoffen m.b.H. (DWK), Hannover (Germany, F.R.); Electric Power Research Inst., Palo Alto, CA (USA); Ontario Hydro, Toronto (Canada); p. P.135-P.136; 1986; p. P.135-P.136; 3. international symposium/workshop on irradiated fuel storage; Seattle, WA (USA); 8-10 Apr 1986; Available from NTIS, PC A23/MF A01; 1 as DE86014260
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[en] The need of some utilities for relatively small amounts of spent fuel storage capacity has prompted GEC Energy Systems to design a vault which could accept as little as 100t. Brief details of such a vault and the capacity for extension are given. (UK)
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Newman, D.F.
Pacific Northwest Lab., Richland, WA (USA)1984
Pacific Northwest Lab., Richland, WA (USA)1984
AbstractAbstract
[en] Dry storage is emerging as an important alternative to wet storage for management of LWR fuel. Dry storage is modular, passive, and can be implemented on a relatively short lead time, once it has been licensed. Thus, it is attractive for United States utilities which are nearing the limit of wet storage capacities. Dry storage of irradiated fuel has already been licensed in several countries. In the United States, dry storage concepts, including dry wells, silos (sealed concrete casks) and vaults, have been tested by the Department of Energy (DOE). Actions are also underway, in cooperation with utilities, to conduct additional unlicensed tests on metal storage casks at DOE facilities and to demonstrate licensed dry storage in metal casks and concrete silos at utility sites. It is anticipated that the demonstrations will confirm that there are no technical barriers that could prevent implementation of dry storage at reactor sites when needed. 6 references, 2 figures
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Jun 1984; 4 p; 25. annual meeting of the Institute of Nuclear Materials Management; Columbus, OH (USA); 15-18 Jul 1984; CONF-840734--22; Available from NTIS, PC A02/MF A01 as DE85000398
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[en] JAI examined alternative methods for structuring charges for federal interim storage (FIS) services and concluded that the combined interests of the Department and the users would be best served, and costs most appropriately recovered, by a two-part fee involving an Initial Payment upon execution of a contract for FIS services followed by a Final Payment upon delivery of the spent fuel to the Department. The Initial Payment would be an advance payment covering the pro rata share of preoperational costs, including (1) the capital costs of the required transfer facilities and storage area, (2) development costs, (3) government administrative costs including storage fund management, (4) impact aid payments made in accordance with Section 136(e) of the Act, and (5) module costs (i.e., storage casks, drywells or silos). The Final Payment would be made at the time of delivery of the spent fuel to the Department and would be calculated to cover the sum of the following: (1) any under- or over-estimation in the costs used to calculate the Initial Payment of the fee (including savings due to rod consolidation), and (2) the total estimated cost of operation and decommissioning of the FIS facilities (including government administrative costs, storage fund management and impact aid). The module costs were included in the Initial Payment to preclude the possible need to obtain appropriations for federal funds to support the purchase of the modules in advance of receipt of the Final Payment. Charges for the transport of spent fuel from the reactor site to FIS facilities would be separately assessed at actual cost since these will be specific to each reactor site and destination
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Sep 1986; 154 p; Available from NTIS, PC A08/MF A01; 1 as DE87000674; Portions of this document are illegible in microfiche products. Original copy available until stock is exhausted.
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Rasmussen, T.L.; Schoonen, D.H.; Fisher, M.W.
EG and G Idaho, Inc., Idaho Falls (USA)1986
EG and G Idaho, Inc., Idaho Falls (USA)1986
AbstractAbstract
[en] The Department of Energy's (DOE) Office of Civilian Radioactive Waste Management (OCRWM) is funding a Program to consolidate commercial spent fuel for testing in dry storage casks and to develop technology that will be fed into other OCRWM Programs, e.g., Prototypical Consolidation Demonstration Program. The Program is being conducted at the Idaho National Engineering Laboratory (INEL) by the Operating Contractor, EGandG Idaho, Inc. Hardware and software have been designed and fabricated for installation in a hot cell adjacent to the Test Area North (TAN) Hot Shop Facility. This equipment will be used to perform dry consolidation of commercial spent fuel from the Virginia Power (VP) Cooperative Agreement Spent Fuel Storage Cask (SPSC) Demonstration Program and assemblies that had previously been stored at the Engine Maintenance and Disassembly (EMAD) facility in Nevada. Consolidation will be accomplished by individual, horizontal rod pulling. A computerized semi-automatic control system with operator involvement will be utilized to conduct consolidation operations. Special features have been incorporated in the design to allow crud collection and measurement of rod pulling forces. During consolidation operations, data will be taken to characterize this technology. Still photo, video tape, and other documentation will be generated to make developed information available to interested parties. Cold checkout of the hardware and software will complete in September of 1986. Following installation in the hot cell, consolidation operations will begin in January 1987. Resulting consolidated fuel will be utilized in the VP Cooperative Agreement SFSC Program
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1986; 8 p; Waste management '87; Tucson, AZ (USA); 1-5 Mar 1987; CONF-870306--3; Available from NTIS, PC A02/MF A01 as DE87000435
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Roberts, J.P.; Sturz, F.C.
Third international spent fuel storage technology symposium/workshop: proceedings. Volume 11986
Third international spent fuel storage technology symposium/workshop: proceedings. Volume 11986
AbstractAbstract
[en] Spent fuel storage outside of reactor pools, which is licensed by NRC under 10 CFR Part 72 is now dominated by developments in modular dry storage designs for both interim and long-term storage. In response to provisions of the Nuclear Waste Policy Act of 1982, NRC is developing amendments to 10 CFR Part 72: 1) to accommodate licensing of monitored retrievable storage, should it be authorized by Congress; and 2) to develop a site independent or generic rule for dry spent storage in metal casks
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Pacific Northwest Labs., Richland, WA (USA); Deutsche Gesellschaft fuer Wiederaufarbeitung von Kernbrennstoffen m.b.H. (DWK), Hannover (Germany, F.R.); Electric Power Research Inst., Palo Alto, CA (USA); Ontario Hydro, Toronto (Canada); p. S.204-S.214; 1986; p. S.204-S.214; 3. international symposium/workshop on irradiated fuel storage; Seattle, WA (USA); 8-10 Apr 1986; Available from NTIS, PC A19/MF A01; 1 as DE86014260
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[en] Frustrated by the US government's slow progress at Yucca Mountain and failure to site an interim spent fuel store, the Mescalero/utility-consortium team formed to build a privately funded central temporary store are preparing to submit a licence application to the USNRC. They aim to start accepting fuel in 2002. (Author)
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