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Enhancing the adsorption of strontium (II) using TOPO impregnated Dowex 50 W-X8 resin
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202
Analytical Strategies Involved in the Detailed Componential Characterization of Biooil Produced from Lignocellulosic Biomass
Published 2017-01-01“…Elucidation of chemical composition of biooil is essentially important to evaluate the process of lignocellulosic biomass (LCBM) conversion and its upgrading and suggest proper value-added utilization like producing fuel and feedstock for fine chemicals. …”
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203
Methodology for Hydrogeochemical Sampling to Characterise Groundwaters in Crystalline Bedrock: Developments Made within the Swedish Radwaste Programme
Published 2020-01-01“…The search by SKB (Swedish Nuclear Fuel and Waste Management Co.) for a site to locate the deep geological repository for spent nuclear fuel in Sweden has involved geoscientific investigations at several locations since the 1970s. …”
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204
Decommissioning of the BN-350 Fast Neutron Reactor: History Review and Current Status
Published 2025-07-01“…The first stage was completed in 2010 when the spent fuel of the BN-350 reactor was placed for long-term storage. …”
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205
Applications of perovskite oxides for oxygen evolution and oxygen reduction reactions in alkaline media
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206
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Study of Thermal Deformation Behavior of Uranium-molybdenum Alloys by Compression Experiments
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208
GAMMA-SPECTROMETER FOR WATER AREAS AND BOTTOM SEDIMENTS RADIATION MONITORING
Published 2016-12-01“…In order to solve the problem of continuous or periodic monitoring of water areas affected by radioactive contamination in the result of scheduled emissions in nuclear power plants or in the result of emergency situations in nuclear fuel cycle plants we need to develop measurement instruments with advanced mathematics and program support to assess the level of radioactive contamination with required accuracy. …”
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209
Die Wasserstoffwirtschaft - eine langfristige Antwort auf das Energieproblem ?
Published 1974-07-01“…Non-fossile hydrogen, produced from water by either electrolysis or by direct use of process heat from a nuclear source is a clean, all-synthetic, automatically recyclable, and inexaustible fuel. …”
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210
Validation of the MCNP model of formation of the background wires current of the self-powered neutron detectors of VVER-1000
Published 2023-06-01“…To improve the accuracy of determining the TPR by the gamma method, a correction model for Kgm is proposed, which takes into account the effect of nuclear fuel burnup on the change in the signal of the background wires of the SPND. …”
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211
Validation of the early in-vessel phenomenon analysis model of the severe accident analysis code MOSAP
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212
WU Hongchun1, ZHENG Youqi1, CAO Liangzhi1, DU Xianan1, WANG Xuesong2, ZU Tiejun1, LIU Zhouyu1, HE Qingming1, CHEN Ronghua1, GE Li1, YANG Rui2, GAO Xinzhao2, WANG Shixi2...
Published 2025-04-01“…This paper focused on the physical characteristics and numerical analysis needs of liquid-metal fast reactor, focusing on six aspects: nuclear data processing, nuclear reactor physics, thermal hydraulics, system safety analysis, fuel performance analysis, and radiation shielding analysis. …”
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Justification of the Use of Biogas for Power Generation in the Republic of Belarus
Published 2024-12-01“…According to the results of the assessment of the theoretical and technically possible potential of biogas from livestock waste while maintaining the number of livestock in agricultural organizations at the level of the beginning of 2023, there is a possibility of annual replacement of 1,325 million m3 and 982 million m3 of natural gas in the fuel balance of our country, respectively. In the last few years, there has been an urgent need to reorient the production activities of biogas complexes due to the commissioning of the Belarusian nuclear power plant. …”
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215
Solvent Extraction of Cs+ by Using 1,3-di(4-tert-butylbenzyloxy)- calix[4]arene-(4-tert-butyl)benzo-crown-6
Published 2025-02-01“…Advanced reprocessing processes require not only the recovery of all uranium and plutonium from the spent nuclear fuel, but also the separation and recovery of some key fission products, such as 137Cs and 90Sr. …”
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216
Research of Neutron-thermal Hydraulic Coupling Calculation Method in Fast Reactor Code System MOSASAUR
Published 2025-03-01“…For the neutron-thermal hydraulic coupling calculation of fast reactor, the thermal feedback module was cooperated with the neutron transport calculation to update the coupling parameters. In the process of the iteration, the temperature distributions of fuel and coolant will be determined through thermal hydraulic calculation, which requires the core power distribution as the input information. …”
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217
Modeling of innovation research clusters in the field of radioactive waste utilization
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218
Actinide Oxide Dissolution in Tributyl Phosphate
Published 2025-01-01“…An alternative to dissolving used nuclear fuel (UNF) in an acidic solution during reprocessing is direct dissolution in an organic solution, which would eliminate an aqueous dissolution step, decrease the amount of nitrate needed, and reduce the facility size. …”
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219
Aux marges du nucléaire français : ce que veut dire démanteler l’industrie minière de l’uranium.
Published 2022-02-01“…Over half a century, the uranium mining industry in France has produced a large part of the nuclear fuel, especially in Limousin. The article analyzes its dismantling and neglect activities, with their challenges and problems. …”
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220
Water quality management program for IPR-R1 TRIGA® research reactor
Published 2023-12-01“…The IPR-R1 Triga nuclear research reactor of the Nuclear Technology Development Center (CDTN) is one of the oldest reactors in operation in the world. …”
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