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AbstractAbstract
[en] A motor car system based on the hydrogen produced by nuclear power stations during the night in the summer, and coupled with organic liquid hydride seems to be a feasible system in the near future. Such a system is discussed and the cost is compared with gasoline. (Auth.)
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Jul 1981; 22 p
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Report
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High temperature reaction of uranium carbides and transient metal chlorides in molten chloride media
Taube, M.; Strejcek, J.; Dietler, F.
Eidgenoessisches Inst. fuer Reaktorforschung, Wuerenlingen (Switzerland)1973
Eidgenoessisches Inst. fuer Reaktorforschung, Wuerenlingen (Switzerland)1973
AbstractAbstract
No abstract available
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Source
Jun 1973; 46 p
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Report
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AbstractAbstract
[en] In the area of the total energy flow, possibilities and limits of shifts in time (storage) and in space (transfer) of secondary energy, i.e. electrical, chemical and thermal energy are examined and formulated. These shifts are linked to the qualitative conversions of secondary energy. The multiple technological possibilities, the spectrum of governing factors and the numerous technical and economical parameters show that only a complex optimization is possible. (Auth.)
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Sep 1979; 26 p
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Report
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AbstractAbstract
[en] A fast converter with one zone and an internal breeding ratio of 1.00, with liquid fuel in the form of molten plutonium- uranium- and sodium chloride, with a thermal power of 3 GW (th) allows continuous extraction of the volatile fission products (Br, I, Kr, Xe, Te) by means of helium purging in the core. The non-volatile fission products e.g. Sr and Cs can continuously be extracted in a chemical reprocessing plant at the reactor site. The impact on an accidental release of fission products is rather significant; the amounts released are 50-100 times smaller than those in a reference reactor (LWR with oxide fuel). Because the heat sink is relatively large and after heat reduced, the temperature of the fuel does not exceed 5000C after an accident, which greatly reduces the consequences of an accident. (Auth.)
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Source
Jul 1980; 69 p
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Report
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ACCIDENTS, ACTINIDE COMPOUNDS, ALKALI METAL COMPOUNDS, BREEDER REACTORS, CHLORIDES, CHLORINE COMPOUNDS, ENERGY SOURCES, EPITHERMAL REACTORS, FAST REACTORS, FLUID FUELED REACTORS, FUELS, HALIDES, HALOGEN COMPOUNDS, ISOTOPES, LIQUID FUELS, MATERIALS, MOLTEN SALT REACTORS, NUCLEAR FUELS, PLUTONIUM COMPOUNDS, RADIOACTIVE MATERIALS, REACTOR ACCIDENTS, REACTOR COMPONENTS, REACTOR MATERIALS, REACTORS, SAFETY, SODIUM COMPOUNDS, TRANSURANIUM COMPOUNDS, URANIUM COMPOUNDS
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AbstractAbstract
[en] This book covers the following topics: matter and energy; the interplay of elementary particles and elementary forces; the universe; how is it observed here and now; its past and possible future; the origin and nuclear evolution of matter; chemical evolution and the evolution of life; the cosmic phenomena; the eternal cycle of matter on the earth; the flow of energy on the earth; the biosphere; the coupling of matter and the flow of free energy; is the future development of mankind on this planet possible, and the distant future of mankind: terrestrial or cosmic
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Source
1985; 288 p; Springer-Verlag New York Inc; New York, NY (USA); ISBN 3-540-13399-2;
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Book
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AbstractAbstract
[en] This report deals with a rather exotic 'paper reactor', in which the fuel is in the form of molten chlorides. (a) Fast breeder reactor with a mixed fuel cycle of thorium/uranium-233 and uranium 238/plutonium in which all of the plutonium can be burned in situ and in which a denatured mixture of uranium-233 and uranium-238 is used to supply further reactors. The breeding ratio is relatively high, 1.58 and the specific power is 0.75 GW(th)/m3 of core. (b) Fast breeder reactor with two and three zones (internal fertile zone, intermediate fuel zone, external fertile zone) with an extremely high breeding ratio of 1.75 and a specific power of 1.1 GW(th)/m3 of core. (c) Extremely high flux reactor for the transmutation of the fission products: strontium-90 and caesium-137. The efficiency of transmutation is approximately 15 times greater than the spontaneous beta decay. This high flux burner reactor is intended as part of a complex breeder/burner system. (d) Internally cooled fast breeder in which the cooling agent is the molten fertile material, the same as in the blanket zone. This reactor has a moderate breeding ratio of 1.38, a specific power of 0.22 GW(th)/m3 of core and very good inherent safety properties. All of these reactors have the fuel in the form of molten chlorides: PuCl3 as fissile, UCl3 as fertile (if needed) and NaCl as dilutent. (Auth.)
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Source
Jan 1978; 210 p; 75 refs.
Record Type
Report
Literature Type
Numerical Data
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ACTINIDE COMPOUNDS, ALKALI METAL COMPOUNDS, BETA DECAY RADIOISOTOPES, BETA-MINUS DECAY RADIOISOTOPES, BREEDER REACTORS, CESIUM ISOTOPES, CHLORIDES, CHLORINE COMPOUNDS, CONVERSION RATIO, DATA, DOCUMENT TYPES, ENERGY SOURCES, EPITHERMAL REACTORS, EVEN-EVEN NUCLEI, FAST REACTORS, FISSIONABLE MATERIALS, FLUID FUELED REACTORS, FUELS, HALIDES, HALOGEN COMPOUNDS, INFORMATION, INTERMEDIATE MASS NUCLEI, ISOTOPES, LIQUID FUELS, MOLTEN SALT REACTORS, NUCLEAR FUELS, NUCLEI, NUMERICAL DATA, ODD-EVEN NUCLEI, PLUTONIUM COMPOUNDS, RADIOISOTOPES, REACTOR MATERIALS, REACTORS, SODIUM COMPOUNDS, STRONTIUM ISOTOPES, TRANSURANIUM COMPOUNDS, URANIUM COMPOUNDS, YEARS LIVING RADIOISOTOPES
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Taube, M.; Ligou, Jacques.
Eidgenoessisches Inst. fuer Reaktorforschung, Wuerenlingen (Switzerland)1972
Eidgenoessisches Inst. fuer Reaktorforschung, Wuerenlingen (Switzerland)1972
AbstractAbstract
No abstract available
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Secondary Subject
Source
Jun 1972; 73 p
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Report
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ALUMINIUM COMPOUNDS, BREEDER REACTORS, CHALCOGENIDES, CHLORIDES, CHLORINE COMPOUNDS, ENERGY SOURCES, EPITHERMAL REACTORS, FAST REACTORS, FUELS, HALIDES, HALOGEN COMPOUNDS, INFORMATION, ISOTOPES, LIQUID FUELS, NITROGEN COMPOUNDS, NUCLEAR FUELS, OXIDES, OXYGEN COMPOUNDS, RADIOACTIVE MATERIALS, REACTOR COMPONENTS, REACTOR COOLING SYSTEMS, REACTOR MATERIALS, REACTORS, SAFETY, SEPARATION PROCESSES
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AbstractAbstract
[en] A system of storing energy in a hydrogen containing fuel for the motor car is discussed. The recyclable liquid chemical carrier is: (Methylcyclohexane (liquid)) dehydrogenation (Toluene (liquid)) + (hydrogen (gas)). The reverse reaction, the hydrogenation of toluene, occurs in a regional plant connected to a source of hydrogen (electrolysis of water) with a significant by-product being heat at 200 0C for district heating. The system is able to store hydrogen in liquid form under ambient temperature and pressure even in a small motor car. The concentration of hydrogen is 6.1 % by weight. The release of gaseous hydrogen from the liquid methylcyclohexane needs a chemical catalytic reactor having a temperature of 300 0C and a pressure of some bars. This reaction has been well studied. The thermal energy for the dehydrogenation is taken from the exhaust gases at 780 0C. A layout of the most important processes of the system is given. (Auth.)
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Sep 1979; 53 p
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Report
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AbstractAbstract
[en] A scheme for a high flux molten salt (plutonium chlorides) fast reactor with a thermal power of 7 GW is presented. It has an internal thermal zone with a liquid target for transmutation of Sr-90 and Cs-137. These fission products are those produced by fast breeder reactors having a combined power of 23 GW and by the fast burner reactor itself with 7 GW. In the case where the power reactors have a breeding gain of G<=0.37 the doubling time for the whole system including the burner reactor is approximately 100 years. With a total neutron flux of 3.8x1016 n/cm2.s and a thermal flux of 2x1016 n/cm2.s, the steady state effective half-life of the Sr-90 and Cs-137 undergoing transmutation is approximately 1.8 years for Sr-90 and approximately 8.9 years for Cs-137. In terms of the hazard coefficient this system gives an improvement by a factor 15. These results indicate that the transmutation of Sr-90 and Cs-137 in a fission reactor, even by using very advanced technologies, may be prohibitive
Primary Subject
Source
Commission of the European Communities, Ispra (Italy). Joint Research Centre; p. 311-321; 1978; p. 311-321; 1. Technical meeting on the nuclear transmutation of actinides; Ispra, Italy; 16 - 18 Apr 1977
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Report
Literature Type
Conference; Numerical Data
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AbstractAbstract
[en] The molten salt reactor system divided into core (thermal and fast) and breeding zone (fission breeder reactor, fusion hybrid system, accelerator-spallation system) has some unique inherent safety properties: a) reduced inventory of fission products during normal operation due to on-line chemical reprocessing and in-core gas purging; b) fast removal of freshly bred fissile nuclides and fission products from the breeding zone (the so called suppressed fission system); c) pressureless fuel and primary coolant system; d) elimination of the possibility of a violent exoenergetic chemical reaction with air, water or metals; e) elimination of the possibility of gaseous hydrogen production during an accident; f) provides a non-engineered feature of dumping of fuel from the core and heat exchanger to a safe drain tank; g) presence of a large heat sink in the form of an inactive diluent salt; h) possibility of natural convection heat removal during an accident and even normal operation (by means of gas lifting); i) dissipation of the remaining decayheat by spraying water on the containment from outside, which allows to manage the worst accident; i) Even in the case of the destruction in the war by conventional or nuclear weapon the contaminated land is significantly reduced. The world-wide present activity in the field of molten salt technology is reviewed. (orig.)
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Journal Article
Journal
Atomkernenergie Kerntechnik; ISSN 0004-7198; ; v. 40(2); p. 73-81
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