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Barendregt, T.
Proceedings of the seminar on Eurochemic experience at Mol (Belgium), June 9-11, 19831984
Proceedings of the seminar on Eurochemic experience at Mol (Belgium), June 9-11, 19831984
AbstractAbstract
[en] The construction and the startup of the Eurochemic reprocessing pilot plant is presented. (AF)
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Source
Drent, W.; Delande, E. (eds.); European Company for the Chemical Processing of Irradiated Fuels, Mol (Belgium); 224 p; 1984; p. 37-43; Eurochemic experience; Mol (Belgium); 9-11 Jun 1983
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AbstractAbstract
[en] The paper brings to light some of the reasons why technology transfer is difficult in fusion, examines some of the impediments to the process, and finally looks at a successful example of technology transfer. The paper considers some subjective features of fusion - one might call them the sociology of fusion - that are none the less real and that serve as impediments to technology transfer
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9. symposium on engineering problems of fusion research; Chicago, IL (USA); 26 - 29 Oct 1981; CONF-811040--
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Journal Article
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Proceedings of the Symposium on Engineering Problems of Fusion Research; ISSN 0145-5958;
; p. 23-25

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Brinfield, W.; McClymont, A.; Krantz, E.; Trainer, J.; Klopp, G.
Probability, reliability, and safety assessment PSA '891989
Probability, reliability, and safety assessment PSA '891989
AbstractAbstract
[en] This paper reports that to evaluate accurately the effects of a loss of offsite power at a plant site with multiple units, an approach has been developed which accounts for t myriad of multiple unit conditions which may exist. This approach has been demonstrated successfully at multiple unit sites, and has proven to be a valuable tool in the identification of potential inter-unit vulnerabilities associated with loss of offsite power events
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Anon; 1300 p; ISBN 0-89448-142-8;
; 1989; p. 796-801; American Nuclear Society; La Grange Park, IL (United States); PSA '89: international topical meeting on probability, reliability and safety assessment; Pittsburgh, PA (United States); 2-7 Apr 1989; CONF-890405--; American Nuclear Society, 555 North Kensington Ave., La Grange Park, IL 60525 (United States)

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Book
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AbstractAbstract
[en] A physico-chemical water treatment system including a clarifier and a cation ion-exchange column of sodium cycle has been designed and constructed to obtain experience in design and technology of these systems. Water hardness is reduced from 500 PPM to zero PPM by reaction of lime with raw water in clarifier and passage of this partially softened water through the cation ion-exchange column for complete softening. The system has the capacity of treating 30,000 liters of water per cycle of operation. Ascending water velocity in the clarifier and volume and concentration of the regenerant and flow rate of water in the cation ion-exchange column have been experimentally determined. The project has enhanced and upgraded ENTEC'S water experts abilities to design and construct water treatment systems at higher industrial scales. (Author)
Original Title
Tahrahi va sakhte yek system tasfieh ab
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Source
Motamed Ektessabi, A.; Shahnazi, Sh. (Atomic Energy Organization of Iran, Teheran. Nuclear Research Centre) (comps.); 360 p; Mar 1985; p. 209-214; Atomic Energy Organization of Iran; Tehran (Iran); National conference on nuclear science and technology; Bushehr (Iran); 14-19 Mar 1988
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Book
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Oster, C.A.
Battelle Pacific Northwest Labs., Richland, Wash. (USA)1972
Battelle Pacific Northwest Labs., Richland, Wash. (USA)1972
AbstractAbstract
No abstract available
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Sep 1972; 68 p
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AbstractAbstract
[en] Research and development activities would involve the scaled modelling activities in order to investigate theory, facts, thesis or concepts. In commercialisation activities, scaling-up proses is necessary for the development of pilot plants or prototypes. The issue with scaled modelling is the similarity between the small scaled model and the full scaled prototype in all aspects of the system such as physical appearance, dimension and the system behaviour. Similarly, for scaling-up process, physical parameters and behaviour of a smaller model need to be developed into a bigger prototype with similar system. Either way, the modelling process must be able to produce a reliable representation of the system or process so that the objectives or functions of the system can be achieved. This paper discusses a modelling method which may be able to produce similar representation of any system or process either in scaled-model testing or scaling-up processes. (author)
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2015; 1 p; NTC 2015: Nuclear Technical Convention 2015; Bangi (Malaysia); 3-5 Nov 2015; Also available in Malaysian Nuclear Agency Document Delivery Center; Poster presentation
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Miscellaneous
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Anghel, Vasile, E-mail: vasile@icsi.ro
The 12th International ICIT Conference Progress in Cryogenics and Isotopes Separation. Proceedings2006
The 12th International ICIT Conference Progress in Cryogenics and Isotopes Separation. Proceedings2006
AbstractAbstract
[en] Full text: This study concluded with a series of suggestions concerning the methodology of maintaining a Cryogenics Nuclear Plant where the maintenance is either fundamental or only of importance. The implementation of this methodology can be achieved in two main steps. The first step concerns the conception of the scientific basis for maintenance, while the second step regards the implementation. The first step describes the management of maintenance in conditions of quality, risk and cost constraints. The conditions are established on the basis of a project of research in maintenance. The second step notifies the aspects of design and technology in maintenance of nuclear industrial units. The nuclear complex technical systems of the Cryogenics Pilot Plant at ICSI - Rm Valcea implies the development of some dedicated software, to ensure the designing, realization and operation of the plant, and prototypes of integrated software modules, to ensure the systems operation during of the life cycle. The implementation method is based on vibration analyses and mechanical studies while a flexible data acquisition system for monitoring, and control must be developed as a platform to ensure a more precise diagnosis and prediction of machinery malfunction. With a flexible data acquisition and analysis system in operation it is possible to easily increase the number of input channels. (author)
Primary Subject
Source
Stefanescu, Ioan (ed.) (National R and D Institute for Cryogenics and Isotopic Technologies - ICIT, PO Box 10, Uzinei Street No. 4, RO-240050 Rm. Valcea (Romania)); National R and D Institute for Cryogenics and Isotopic Technologies - ICIT, PO Box 10, Uzinei Street No. 4, RO-240050 Rm. Valcea (Romania). Funding organisation: Ministry of Education and Research, Bucharest (Romania); National Authority for Scientific Research, Bucharest (Romania); 273 p; 2006; p. 59; 12. international ICIT conference Progress in Cryogenics and Isotopes Separation. Proceedings; Caciulata (Romania); 25-27 Oct 2006; Available from author(s) or National R and D Institute for Cryogenics and Isotopic Technologies - ICIT, PO Box 10, Uzinei Street No. 4, RO-240050 Rm. Valcea (RO); Available from National R and D Institute for Cryogenics and Isotopic Technologies - ICIT, PO Box 10, Uzinei Street No. 4, RO-240050 Rm. Valcea (RO). E-mail: office@icsi.ro; Available in abstract form only, full text entered in this record
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Boonthum, Narapan; Mulalee, Unchalee; Srinophakun, Thongchai, E-mail: fengtcs@hotmail.com2014
AbstractAbstract
[en] The combination of an automatic HAZOP analysis with a structural model was introduced to obtain a systematic procedure for hazard and mal-operations identification. There are three stages of the proposed procedure. The first stage was used to analyze the conventional hazard and mal-operations for each process unit, whereas the second stage extended the analysis to adjacent units. The interaction style was used to identify the cause–consequence relationships between upstream and downstream unit with the concepts of the non-local path and the dummy parameters. Therefore, a generic HAZOP library will be additional modified. The third stage created the templates for hazard and mal-operations identification for operating arbitrary units. This proposed HAZOP analysis was verified with conventional HAZOP of the defatted soy flour pilot plant with three scenarios. The analysis scheme fulfilled the library of the case study and discovered 18 new consequences for the first scenario, 10 new consequences for the second scenario. For the third scenario, the analysis specified on an arbitrary flash drum by applying three guide-words (more, less and no) and found 46 causes and 83 consequences. The proposed methodology, therefore, can simplify and reveal the guidance for hazards and mal-operations identification
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S0951-8320(13)00243-3; Available from http://dx.doi.org/10.1016/j.ress.2013.08.008; Copyright (c) 2013 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.; Country of input: International Atomic Energy Agency (IAEA)
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AbstractAbstract
No abstract available
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Review of Scientific Instruments; v. 43(3); p. 445-447
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AbstractAbstract
[en] This paper, reviews briefly the technological difficulties encountered in designing a blanket, this component of the fusion reactor which performes two crucial tasks: to recover 80% of the energy released by the fusion reaction, and to breed tritium to replace that burned in the fusion process. The four blanket concepts presently developed in the European Community have been designed so as to meet the specifications of a fusion demonstration reactor. Two of these concepts rely on the use lithiated ceramics as breeding material of beryllium as neutron multiplier material, and of helium as coolant. They mainly differ by the cooling system: pressure tubes for one externally-cooled breeder rods for the other. The two other concepts use Li17Pb83. One is water-cooled, the other self-cooled
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