Coal liquefaction method and coal liquefaction plant in combination with nuclear power generation system

Coal liquefaction method and coal liquefaction plant in combination with nuclear power generation system

05 Nuclear fuels (scientific, technical) from FTIR. Solid samples collected during the bio-sludge combustion process were analysed with SEM, wavelengt...

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05 Nuclear fuels (scientific, technical) from FTIR. Solid samples collected during the bio-sludge combustion process were analysed with SEM, wavelength-dispersive and energydispersive X-ray spectrometry and electron probe microanalysis to determine morphology, particle size, composition and metals distribution in ash particles. The bio-sludge combustion process could be divided into four stages. (1) Initial burning (T < 600°C) dominated by moisture evaporation, fibres volatilization and pyrolysis. (2) Biosludge/ash transition (600 < T < 1100°C) dominated by char oxidation, metals reduction and AI-Si spine1 formation. (3) Solid particle sintering (1100 < T < 1400°C) dominated by mullite formation, ash softening and metals segregation. (4) Ash melting (T > 1400°C). However, it is difficult to accurately establish a clear boundary between these stages because the regimes of volatiles release, char combustion and ash transformation are overlapping. Ash formed during quenching was a condensed and packed substance while during natural cooling it revealed dendritic character with needle-like features present on the particle surface. The former structure is better from the environmental point of view because it would not allow for leaching of toxic metals if ash was disposed of in a sanitary landfill. 02lOO439 Torfent, a binder from peat Rubanov, A.V. ef al. Strait. Mater., 1999, 9, 36-37. (In Russian) Production of cement from ash obtained by peat combustion was investigated. In laboratory experiments, 7.5-50% chalk was added to peat to increase the CaO content, and combustion was carried out in crucibles at 1,150-1,200”. The resulting product was milled, mixed with water, and hardened. The 28-day compressive strength was lower by 65-75% than that of conventional portland cement. Addition of lime increased the strength by S-13%. 02/00440 Treatment and utilization process of flue gas from coal boiler and eouioment Wang, Y. Faming Zhuanli Shenqing Gongkai Shuomingshu CN 1,231,273 (Cl. C05Dll/OO), 13 Ott 1999, Appl. _. 99,105,649, 19 Apr 1999. 8. (In Chinese) The process comprises allowing the fine gas to react with atomized NH,OH in desulphurizing tower, collecting produced (NH4)zS04 and flue dust, discharging desulphurized flue gas, mixing the mixture of (NH&SO4 and dust, K fertilizer (KC1 or KzS04), and P fertilizer (Ca superphosphate), pelletizing, drying, cooling, sieving, and magnetizing at 4000 Oe to obtain compound fertilizer. The desulphurizing tower consists of gas inlet, tower body, flue gas outlet, nozzles, mixing tube, material discharging tube, and baffle. 02/00441 Treatment of coal gas production wastewater Zhao, Lei Liu, J. Huanjing Eaohu (Beijing), 2000, 4, 13-14. (In Chinese) The coal gas production wastewater was treated by filtering, air flotation and biochemical catalytic oxidation. The relation of removing ratio of COD,, with different use level of coagulant agent and the relation of removing ratio of COD,, and BODs with detention period in catalytic oxidation reactor were studied. The results showed that both total removing ratio of COD,, and BODs could be up to 95%.

Unsubstituted poiyaromatic hydrocarbons in extracts of coal fly ash 02lOO442 $;F,quist,

M.D., Daves, G.D. Jr. J. Term. Acad. Sci., 1999, 73, (l-2),

Extracts of coal fly ash from the solid waste disposal test cell at Montour, PA, were analysed by isotope dilution mass spectrometry to detect, identify, and quantify trace amounts of selected, unsubstituted polyaromatic hydrocarbons (PAHs). Isotope dilution experiments using deuterated analogues of PAHs demonstrated that the concentrations of benzo[a]pyrene and anthracene were
44

Fuel and Energy Abstracts

January 2002

greatest losses of volatiles occur during the transition from the beginning to the end of the high-volatile bituminous rank. During this transition some CO must be lost. During the transition from the beginning to the end of each of the higher ranks some CHI must be lost. The increase in quantity of CHI evolved may help to explain the presence of catagenic methane found at depth.

Water and wastewater management in the Przyjazn Coking Plant in Dabrowa Gornicra

02/00444

Morel, J. et al. Karbo, 2000, 45, (2), 53-57. (In Polish) The article presents water and sewage management of the most modern coking plant in Poland. The obligation to intensify sewage treatment processes in order to obtain treated sewage with the parameters as close as possible to II class of water purity made it necessary for the coking plants to modernize sewage treatment facilities.

05

NUCLEAR

FUELS

Scientific, technical 02/00445

Beryllium R&D for fusion applications

Scaffidi-Argentina, F. et al. Fusion Engineering and Design, 2000, 5152, 23-41. Beryllium is one of the primary candidates as both plasma-facing material (PFM) and neutron multiplier in the next-step fusion reactors. Both sintered-product blocks and pebbles are considered in fusion reactor designs. Beryllium evaporated on carbon tiles has also been used in Joint European Torus (JET) and may be considered for other designs. Future efforts are directed toward the pebble form of beryllium. Research and evaluations of data are underway to determine the most attractive material processing approaches in terms of fabrication cost and quality; technical issues associated with heat transfer; thermal, mechanical and irradiation stability, safety and tritium release. Beryllium plasma-facing components will require periodic repair or replacement, therefore disposal or recycling of activated and tritiated beryllium will also be a concern. Beryllium as a component of the molten salt, Flibe is also being considered in novel approaches to the plasma-structure interface. This paper deals with main issues related to the use of Be in a fusion reactor as both neutron multiplier and first wall material. These issues include potential reactions with steam during accidents and the health and environmental aspects of its use, reprocessing and reuse, or disposal.

02/00446 Coal liquefaction method and coal liquefaction plant in combination with nuclear power generation system Ito, S. er al. Jpn. Kokai Tokkyo Koho JP 2000 87,044 (Cl. ClOGl/OO), 28 Mar 2000, Appt. 1998/263,543, 17 Sep 1998. 15. (In Japanese) The title method comprises thermal neutron irradiation of 21 natural elements (especially, Al, Si, Ti, V and Mn) to form artificial radioactive isotope having reduced half life, mixing coal powder with the artificial radioactive element, a H-donor organic solvent, a pyrite-type catalyst powder to form a coal slurry, pyrolysing the coal slurry in a catalytic hydroliquefaction reactor at 400-500” under elevated pressure, and then distillating the liquefied products to recover light oils. The artificial radioactive isotope may include 3oSi, “Ti, “Cr, ‘?r 64Ni, 65Cu and 68Zn. The integrated system consists of a coal liqueiaction plant and a nuclear power plant. The nuclear power plant comprises a thermal neutron irradiation device arranged in the outside of a nuclear reactor pressure vessels having shield layers in its inner side, and means for introducing the formed steam from the pressure vessel into turbines for power generation. The coal liquefaction plant comprises a coal slurry preparation tank for mixing coal power with artificial radioactive element, H-donor solvent and catalyst; a catalytic hydroliquefaction reactor for pyrolyseing the coal slurry; and means for separating the liquefied products to recover light oils.

02lOO447 Fuel cycle design evolution from FDR-ITER to RTOIRC-ITER Murdoch, D.K. er al. Fusion Engineering and Design, 2000,49-50, 893898. Instantaneous fuelling an plasma exhaust flow rates for the reduced technical objective/reduced cost version of International Thermonuclear Experimental Reactor (RTO/RC-ITER) are similar to those described in the Final Design Report (FDR) of ITER, despite the reduction in fusion power by a factor of about two. However, the