The Experts below are selected from a list of 57 Experts worldwide ranked by ideXlab platform
L I Xiaohong - One of the best experts on this subject based on the ideXlab platform.
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Material Balance Calculation for high pressure loop of ammonia synthesis
Chemical Fertilizer Design, 2008Co-Authors: L I XiaohongAbstract:Author has introduced the process progress for the high pressure loop of ammonia synthesis;discussed the compiling process of Material Balance Calculation procedure in high pressure loop;taking the loads of both five compressors and six compressors as the example,the various productive conditions were simulated;the influence of different gas composition on the actual production was analyzed.The result indicates that as long as the conditions of new gas composition and flow etc.have been given,the Calculation procedure can be automatically performed,and the productive situation and various abrupt variation conditions in the high pressure loop of ammonia synthesis can be accurately described.
Zhao Zhengguang - One of the best experts on this subject based on the ideXlab platform.
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making Material Balance and Calculation for high pressure loop of synthesis ammonia by using of electron form software
Chemical Fertilizer Design, 2009Co-Authors: Zhao ZhengguangAbstract:Author has introduced a Material Balance Calculation method for high pressure loop of synthetic ammonia by using of electron form software(Excel Macro).Through application example,accumulative process for inert gases has been simulated in the production technology process;dynamic Balance has been realized for all the gas constituents by using of manually iterative or automatically iterative modes.Result indicates that this method is more simple and quick than common chemical-engineering simulation method.
Myung Seung Yang - One of the best experts on this subject based on the ideXlab platform.
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economic analysis on direct use of spent pressurized water reactor fuel in candu reactors iv dupic fuel cycle cost
Nuclear Technology, 2001Co-Authors: Hangbok Choi, Myung Seung YangAbstract:This study examines the economics of the DUPIC fuel cycle using unit costs of fuel cycle components estimated based on conceptual designs. The fuel cycle cost (FCC) was calculated by a deterministic method in which reference values of fuel cycle components are used. The FCC was then analyzed by a Monte Carlo simulation to get the uncertainty of the FCC associated with the unit costs of the fuel cycle components. From the deterministic analysis on the equilibrium fuel cycle model, the DUPIC FCC was estimated to be 6.21 to 6.34 mills/kW.h for DUPIC fuel options, which is a little smaller than that of the once-through FCC by 0.07 to 0.27 mills/kW.h. Considering the uncertainty (0.40 to 0.44 mills/kW.h) of the FCC estimated by the Monte Carlo simulation method, the cost difference between the DUPIC and once-through fuel cycle is negligible. On the other hand, the Material Balance Calculation has shown that the DUPIC fuel cycle can save natural uranium resources by {approx}20% and reduce the spent fuel arising by {approx}65% compared with the once-through fuel cycle. In conclusion, the DUPIC fuel cycle is comparable with the once-through fuel cycle from the viewpoint of FCC. In the future, it should bemore » important to consider factors such as the environmental benefit owing to natural uranium savings, the capability of reusing spent pressurized water reactor fuel, and the safeguardability of the fuel cycle when deciding on an advanced nuclear fuel cycle option.« less
Hangbok Choi - One of the best experts on this subject based on the ideXlab platform.
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economic analysis on direct use of spent pressurized water reactor fuel in candu reactors iv dupic fuel cycle cost
Nuclear Technology, 2001Co-Authors: Hangbok Choi, Myung Seung YangAbstract:This study examines the economics of the DUPIC fuel cycle using unit costs of fuel cycle components estimated based on conceptual designs. The fuel cycle cost (FCC) was calculated by a deterministic method in which reference values of fuel cycle components are used. The FCC was then analyzed by a Monte Carlo simulation to get the uncertainty of the FCC associated with the unit costs of the fuel cycle components. From the deterministic analysis on the equilibrium fuel cycle model, the DUPIC FCC was estimated to be 6.21 to 6.34 mills/kW.h for DUPIC fuel options, which is a little smaller than that of the once-through FCC by 0.07 to 0.27 mills/kW.h. Considering the uncertainty (0.40 to 0.44 mills/kW.h) of the FCC estimated by the Monte Carlo simulation method, the cost difference between the DUPIC and once-through fuel cycle is negligible. On the other hand, the Material Balance Calculation has shown that the DUPIC fuel cycle can save natural uranium resources by {approx}20% and reduce the spent fuel arising by {approx}65% compared with the once-through fuel cycle. In conclusion, the DUPIC fuel cycle is comparable with the once-through fuel cycle from the viewpoint of FCC. In the future, it should bemore » important to consider factors such as the environmental benefit owing to natural uranium savings, the capability of reusing spent pressurized water reactor fuel, and the safeguardability of the fuel cycle when deciding on an advanced nuclear fuel cycle option.« less
R. Eschbach - One of the best experts on this subject based on the ideXlab platform.
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Work plan for improving the DARWIN2.3 depleted Material Balance Calculation of nuclides of interest for the fuel cycle
EPJ Web of Conferences, 2017Co-Authors: A. Rizzo, C. Vaglio-gaudard, J.-f. Martin, G. Noguere, R. EschbachAbstract:DARWIN2.3 is the reference package used for fuel cycle applications in France. It solves the Boltzmann and Bateman equations in a coupling way, with the European JEFF-3.1.1 nuclear data library, to compute the fuel cycle values of interest. It includes both deterministic transport codes APOLLO2 (for light water reactors) and ERANOS2 (for fast reactors), and the DARWIN-PEPIN2 depletion code, each of them being developed by CEA-DEN with the support of its industrial partners. The DARWIN2.3 package has been experimentally validated for pressurized and boiling water reactors, as well as for sodium fast reactors; this experimental validation relies on the analysis of post-irradiation experiments (PIE). The DARWIN2.3 experimental validation work points out some isotopes for which the depleted concentration Calculation can be improved. Some other nuclides have no available experimental validation, and their concentration Calculation uncertainty is provided by the propagation of a priori nuclear data uncertainties. This paper describes the work plan of studies initiated this year to improve the accuracy of the DARWIN2.3 depleted Material Balance Calculation concerning some nuclides of interest for the fuel cycle.