Sodium technology

Typical composition of commercial-grade sodium determined by standard methods of analysis is given in Table 5.1, where 1 ppm=10 °. 

Initial impurity content due to oxygen absorption on the circuit surface is 3.4 g/m (I circuit) and 2.2 g/m (II circuit), that is in a good agreement with the experimental data (1.4-2.4 g/m ). Total amount of oxygen absorbed is about 30 kg. 

Impurities introduced during repair operation are Na20, NaOH and Na2C03. Assessments have shown that during operation (20 years) about 200 kg of substances aforementioned is introduced [5.2.]. 

Impurities added during subassembly loading. Assuming 2 g/m specific content, total amount is equal to about 200 kg. 

Impurities caused by diffusion from other sources. Diffusion rate is evaluated to be about 50 g 02/day. Total amount of impurities is about 720 kg. 

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Al. Argonne National Laboratory Proceedings of the International Conference on Sodium Technology and Large Fast Reactor Design, Report AN1 7520, 1968, especially pp. 291-388. 

Sodium, used as a heat transfer fluid, can most effectively remove heat from a fast breeder reactor. Development work on sodium handling at Argonne National Laboratory in 1945 led to the first turbine-electric power from nuclear energy in 1951. This paper presents the engineering mock-up of the experimental breeder reactor II and illustrates associated pumps, valves, and instrumentation. The past year s successful operation of the EBR-II mock-up has demonstrated that sodium technology is adequate for the job. Properly used, sodium may be the key to the problem of really using the elusive atom. 

The most obvious reason for the removal of undrained sodium films stems from the chemical activity of the metal. Scrap piles of sodium-system components, if left uncleaned, present the possibility of hydrogen fires and the added hazard of caustic burns to personnel. This is particularly true if the scrap is exposed to rain or humid atmospheric conditions. Similarly, in making extensive repairs to sodium systems or components, the removal of sodium facilitates working conditions, since it eliminates the possibility of the above-mentioned complications. After sodium recleaning, maintenance can be performed by personnel who need not be trained in the specific disciplines of sodium technology. 

YD Choi, S T Hwang, C K Park, KALIMER Program and Sodium Technology in Korea, Proceedings of IWGFR Technical Meeting on Sodium Removal and Disposed, (1997)... 

Mastering sodium technology including special aspects related to radioactive sodium ... 

The French sodium LMFRs knowledge is based on a large and consistent background four decades of R D work (1960-2000), on all the fields of sodium nuclear plants neutronics, safety, thermalhydraulics, mechanics, sodium technology... A huge database lies in test results, modelling effort and licensing documents. A number of specific databases exists in different services of the CEA and can be extensively used for the preservation project. 

Books, technical documents and general conferences on sodium technology... 

Concerning the research and development of FBR technology, some progresses on sodium technology, materials, fuels, sodium instrumentations etc. have been gained and briefly described in this paper. 

Since the end of the year 1990 it was started to build the Engineering Development Laboratiry of 18000 construction surface. The EDL includes three main buildings which will be used for sodium technology development, thermohydraulics and safety research and development and demonstration and proving of facilities and components respectively, (photo 8)... 

In 1969, the Instituto de Engenharia Nuclear-IEN (Nuclear Engineering Institute) initiated its activities related to fast reactors. As part of a contract with TECHNICATOME (France), a thermal-fast reactor has been designed, but it was not constructed due to problems with fuel supply. In 1972, a small sodium loop (100 KW) was inaugurated for studying heat transfer and several aspects of sodium technology. 

Romano, A J., Wachtel, S. J., and Bdamut, C. J., Proceedings of International Conference on Sodium Technology for Large Fast Reactor Design, ANL-7520, Pt. 1, Atgonne National Laboratoiy, 1968, p. 151. 

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