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Shin, Hee Sung; Shin, Young Joon; Kim, Ik Soo; Rho, Sung Kee; Shin, Myung Won; Kim, Myung Hyun
Proceedings of spent fuel management technology workshop, 1997. 11. 13 - 11. 14, Taejon, Korea1997
Proceedings of spent fuel management technology workshop, 1997. 11. 13 - 11. 14, Taejon, Korea1997
AbstractAbstract
[en] Criticality safety analysis for the infinite array of canisters containing metal spent fuel is carried out with ORIGEN2 and MCNP codes which are benchmarked. It is found that the maximum keff of the system is 0.91682, lower than maximum allowable multiplication factor ( 0.936), when the canister thickness, water concentration and the canister spacing is 8 mm, 0.35 g/cm3 and 6.5 cm, respectively. Therefore, it is believed that the system is in the subcritical condition. (author). 11 refs., 3 tabs., 4 figs
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Korea Atomic Energy Research Institute, Taejon (Korea, Republic of); 176 p; 1997; p. 85-94; KAERI; Taejon (Korea, Republic of); 1. spent fuel management technology workshop; Taejon (Korea, Republic of); 13-14 Nov 1997
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Vnukov, V.S.; Rjazanov, B.G.; Sviridov, V.I.; Frolov, V.V.; Drozko, E.G.; Dzekun, E.G.
Proceedings of the third international conference on nuclear fuel reprocessing and waste management, RECOD'911991
Proceedings of the third international conference on nuclear fuel reprocessing and waste management, RECOD'911991
AbstractAbstract
[en] The paper describes the general principles of nuclear criticality safety for handling, processing, transportation and spent fuel storing. Measures to limit the consequences of critical accidents are discussed for the fuel reprocessing plant and spent fuel storage. The system of scientific and technical measures on nuclear safety as well as the system of control and state supervision based on the rules, limits and requirements are described. The nuclear safety aspects for various stages of handling nuclear materials are considered. The paper gives description of the methods and approaches for critical risk assessments for the reprocessing plant and spent fuel storages. (author)
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Atomic Energy Society of Japan, Tokyo (Japan); Japan Atomic Industrial Forum, Inc., Tokyo (Japan); 1186 p; 1991; p. 493-497; Japan Atomic Industrial Forum; Tokyo (Japan); 3. international conference on nuclear fuel reprocessing and waste management, RECOD'91; Sendai (Japan); 14-18 Apr 1991
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McConaghy, W.J.; Lehnert, R.A.; Rasmussen, R.W.
Proceedings of the third international conference on nuclear fuel reprocessing and waste management, RECOD'911991
Proceedings of the third international conference on nuclear fuel reprocessing and waste management, RECOD'911991
AbstractAbstract
[en] The NUHOMS spent fuel storage system provides a safe and economical method for the dry storage of spent fuel assemblies either at an independent spent fuel storage installation (ISFSI) at reactor or at a centralized storage facility away from reactor. The system consists of three major safety-related components: a dry shielded canister (DSC) which provides a high integrity containment boundary and a controlled storage environment for the fuel; a reinforced concrete horizontal storage module (HSM) which houses the stored DSCs and provides radiation shielding, protection against natural phenomena and an efficient means for decay heat removal; and a transfer cask which provides for the safe shielded transfer of DSCs from a plant spent fuel pool to a HSM. The NUHOMS system is designed and licensed to the requirements of 10 CFR 72 and ANS/ANSI 57.9 for ISFSIs. The NUHOMS concept was developed in early 1980s, and in 1987, a larger version of the NUHOMS system, 24P, was developed. The operational features of NUHOMS and the loading experience at Oconee are reported. (K.I.)
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Atomic Energy Society of Japan, Tokyo (Japan); Japan Atomic Industrial Forum, Inc., Tokyo (Japan); 1186 p; 1991; p. 383-390; Japan Atomic Industrial Forum; Tokyo (Japan); 3. international conference on nuclear fuel reprocessing and waste management, RECOD'91; Sendai (Japan); 14-18 Apr 1991
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AbstractAbstract
[en] In a drive to refurbish and replace its Nuclear Installations Inspectorate transport packagings in the three years since NII licensing, AEA Technology has developed new families of containers for solid plutonium contaminated material and high-activity liquor. (Author)
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Journal Article
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[en] The purpose of this paper is to discuss the railroad industry's concerns on the movement of spent nuclear fuel including the magnitude of thermal and mechanical forces in train accidents, emergency response capability, railroad's liability for non-breach-of-cask accidents, and the importance of using dedicated trains to improve public perception of these movements; summarize the current status of the condition of the American railroads' equipment, facilities, track structure, and right-of-way; outline the continuing efforts of the railroad industry to improve customer service and profitability through downsizing and shifting of branch lines to more customer-oriented and efficient short-line carriers; and discuss potential problems of government subsidization of private railroads to enable upgrading of tracks and structures to handle rights-of-way in the future
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American Nuclear Society annual meeting; Boston, MA (United States); 7-12 Jun 1992; CONF-920606--
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[en] Rochester Gas and Electric Corporation (RG ampersand E) has been involved in two separate fuel consolidation demonstration programs. One of those programs resulted in identifying some problems that may be resolved in consolidation hardware compaction and storage in order for consolidation to be attractive. In conjunction with the Electric Power Research Institute (EPRI), a study was recently performed on hardware compaction and storage. Consolidation is probably not a commercial alternative at this point in time because there are still several problems that must be resolved. There are some potential advantages of fuel consolidation. Consolidation has attractive economics and can minimize the institutional impacts of expanding spent fuel storage by internalizing spent fuel storage operations. The licensing effort is fairly simple. Consolidation may be less likely to have public intervention since the storage expansion will occur inside the plant. Consolidation can be subcontracted and the equipment is temporary. It can be used in conjunction with other storage expansion technologies such as dry storage. Fewer dry storage casks would be needed to store consolidated fuel than would be necessary for intact spent fuel
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Supko, E.M. (Energy Resources International, Inc., Washington, DC (United States)); Electric Power Research Inst., Palo Alto, CA (United States); Energy Resources International, Inc., Washington, DC (United States); 271 p; May 1992; p. 9.1-9.19; 1991 Edison Electric Institute/UWASTE-Electric Power Research Institute (EEI/UWASTE-EPRI) workshop on at-reactor spent-fuel storage; Charlotte, NC (United States); 15-17 Oct 1991; EPRI Distribution Center, 207 Coggins Drive, PO Box 23205, Pleasant Hill, CA 94523
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AbstractAbstract
[en] An apparatus for illuminating an underwater environment in a nuclear environment is described comprising: at least one unit comprising: an arc lamp for emitting light; a base for mating with and for conducting electricity to said arc lamp; a seal for creating a watertight connection between said arc lamp and said base; a light-transmissive impact-resistant cover for enclosing said arc lamp, said base and said seal; and a releasable connector attached to said base; a polished reflector partially surrounding said at least one unit to control the direction of the reflection of light emitted from said arc lamp of said at least one unit; a cable means for providing electricity to said connector; and a ballast power supply contained in a watertight housing and connected to said cable means; wherein said unit is replaced by disconnecting said releasable connector from an old said unit and connecting it to a new said unit
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25 May 1993; 24 Jan 1992; [10 p.]; US PATENT DOCUMENT 5,213,410/A/; US PATENT APPLICATION 7-825,564; Patent and Trademark Office, Box 9, Washington, DC 20232 (United States); Application date: 24 Jan 1992
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Patent
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[en] This patent describes a container for connecting to a flow line extending between a blending tub and a well head, comprising: receptacle means for holding a radioactive slurry; means, operatively connected between the receptacle means and the flow line, for connecting the receptacle means directly to the flow line; and displacement means, mounted in the receptacle means, for displacing at least a portion of a radioactive slurry from the receptacle means into the flow line; wherein the receptacle means includes: a support member connectable to the connection means; and a removable cartridge insert member received within and connected to the support member, the insert member having a cavity defined therein for receiving the radioactive slurry
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22 Nov 1988; vp; US PATENT DOCUMENT 4,786,805/A/; Patent and Trademark Office, Box 9, Washington, DC 20232
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Patent
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AbstractAbstract
No abstract available
Original Title
Stroemungsstabilitaet der Naturzugkuehlung eines luftgekuehlten Mehrkreis-Zwischenlagers fuer radioaktive Reststoffe aus Kernkraftwerken und Wiederaufbereitungsanlagen
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Deutsches Atomforum e.V., Bonn (Germany, F.R.); Kerntechnische Gesellschaft e.V., Bonn (Germany, F.R.); 648 p; ISSN 0720-9207;
; 1986; p. 61-64; Annual meeting on nuclear technology (JK '86); Aachen (Germany, F.R.); 8-10 Apr 1986; Available from Deutsches Atomforum e.V., Bonn (Germany, F.R.); Published in summary form only.

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Snyder, B.J.
Third international spent fuel storage technology symposium/workshop: proceedings. Volume 21986
Third international spent fuel storage technology symposium/workshop: proceedings. Volume 21986
AbstractAbstract
[en] Detection of failures in a fuel assembly has been accomplished by a number of techniques, including sampling the reactor coolant system during operations, sipping each assembly after discharge, eddy current testing of removed fuel rods, and ultrasonic inspection. An advanced ultrasonic system developed by Brown Boveri with the assistance of Krautkramer has been utilized to identify individual failed fuel rods. High reliability has been demonstrated in the rapid inspection of assemblies in the US and overseas utilizing the Brown Boveri system. Analyses have been done to demonstrate the benefits of fuel inspections for a number of applications
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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.7-P.15; 1986; p. P.7-P.15; 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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