scholarly journals The usage of probabilistic assessment for cost calculations of using NPP with hydrogen industrial production

Author(s):  
Yu. A. Kolbantcev ◽  
M. V. Konyushin ◽  
A. A. Kalyutik

THE PURPOSE. This study focused on the probability of construction of dual – purpose nuclear-hydrogen unit for cogeneration of hydrogen and electricity with nuclear power reactor VVER-1200 based on AES-2006 project. METHODS. The aim of the study is the probation of the IAEA calculation method originated for sea water desalination unit using nuclear power plant as an energy source, but with a view to same time production of high-quality hydrogen and electricity concerning the ecological issues of hydrogen generation. In particular, the method was used for probabilistic assessment of single-purpose NPP unit and dual-purpose nuclear-hydrogen unit. The supposed result of the study was construction of special building for the electrolytic process purposes. The ground location of the building was out of the main building area. The special building should consist of electrolytic units, technological water feed and removal pipelines, tanks for hydrogen and other service equipment. RESULTS. The paper introduced the theoretical possibility of hydrogen production on the rate up to 1,927∙108 m3/year in the case of full-time basis operation of 50 hydrogen units. The rate of produced hydrogen corresponds to 18,53% of inner Russian market hydrogen needs. In this case the electricity cost factor was 0,097 $/kW∙hr, the cost factor of higher quality hydrogen was 0,956 $/m3. The paper introduced the prime cost comparison of produced hydrogen according to hydrogen units total capacity and arrangement demands. CONCLUSION. This method has the limits of applicability, but in our case, it can be used to calculate key economic factors of the project and to analyze the validation of the energy source and the hydrogen unit size.

REAKTOR ◽  
2017 ◽  
Vol 16 (4) ◽  
pp. 172 ◽  
Author(s):  
Hadi - Suwarno ◽  
Meniek Rachmawati

Abstract TRISO-UN KERNEL FABRICATION AND ITS CHARACTERS, A REVIEW. High temperature nuclear reactors (HTRs) become the future nuclear power reactor due to its ability for electricity generation, hydrogen production and sea water desalination. Uranium nitride (UN) coated with tristructural isotropic (TRISO) coating materials has attracted the researchers because of its similar characteristics to UO2 buat has a higher density. There are beneficial in using UN as fuel due to the longer usage and efficient in refueling. The fabrication of UN kernel, coating of TRISO-UN, and characterics of UN have been reviewed. Among the technology provided for producing UN kernel, atomizing is selected due to its simply and less waste produced. Coating technology used follows the current technology for TRISO-UO2 that is fluidized bed chemical vapor deposition type. Since there are two types HTR fuel, block and ball types, fabrication technique of TRISO-UN fuel depends on the HTR type selected. Keywords: fabrication; coating; UN compound; TRISO-UN   Abstrak Reaktor nuklir suhu tinggi (high temperature reactors, HTR) merupakan reaktor daya masa depan karena dapat digunakan sebagai pembangkit daya listrik, penghasil gas hidrogen dan desalisasi air laut. Bahan bakar nuklir berupa senyawa uranium nitrida (UN) yang dilapisi dengan lapisan tristructural isotropic (TRISO) menjadi topik bahasan akhir-akhir ini. Pengembangan bahan bakar nuklir bentuk kernel UN untuk reaktor HTR dipromosikan karena memiliki karakter yang mirip dengan kernel UO2 namun memiliki densitas uranium lebih tinggi. UN memiliki keuntungan karena waktu pakai di reaktor lebih panjang dan penggantian bahan bakarnya lebih efisien. teknologi pembuatan kernel dan teknologi atomizing menjadi pilihan untuk pembuatan kernel UN karena proses lebih sederhana, waktu lebih cepat dan sedikit menghasilkan limbah. Teknologi pelapisan dan spesifikasi TRISO-UN yang akan dibuat mengikuti teknologi yang sudah terbukti, yaitu fluidized bed chemical vapor deposition type. Bahan bakar reaktor HTR yang ada di dunia ada dua tipe, yaitu tipe blok dan tipe bola, fabrikasi bahan bakar TRISO-UN disesuaikan dengan jenis reaktor yang akan dibangun. Kata kunci: fabrikasi; pelapisan; senyawa UN; TRISO-UN 


Author(s):  
Danrong Song ◽  
Xiaoting Ding

FRD-200 sea water desalination spent fuel reactor is a low temperature, normal pressure reactor which utilize nuclear power plant spent fuel. It can be used for sea water desalination and heat supply or refrigeration for metropolis. The FRD-200 is mainly used for sea water desalination.


Membranes ◽  
2021 ◽  
Vol 11 (6) ◽  
pp. 377
Author(s):  
Federico Leon ◽  
Alejandro Ramos-Martin ◽  
Sebastian Ovidio Perez-Baez

The water situation in the Canary Islands has been a historical problem that has been sought to be solved in various ways. After years of work, efforts have focused on desalination of seawater to provide safe water mainly to citizens, agriculture, and tourism. Due to the high demand in the Islands, the Canary Islands was a pioneering place in the world in desalination issues, allowing the improvement of the techniques and materials used. There are a wide variety of technologies for desalination water, but nowadays the most used is reverse osmosis. Desalination has a negative part, the energy costs of producing desalinated water are high. To this we add the peculiarities of the electricity generation system in the Canary Islands, which generates more emissions per unit of energy produced compared to the peninsular generation system. In this study we have selected a desalination plant located on the island of Tenerife, specifically in the municipality of Granadilla de Abona, and once its technical characteristics have been known, the ecological footprint has been calculated. To do this we have had to perform some calculations such as the capacity to fix carbon dioxide per hectare in the Canary Islands, as well as the total calculation of the emissions produced in the generation of energy to feed the desalination plant.


Desalination ◽  
1987 ◽  
Vol 67 ◽  
pp. 33-41 ◽  
Author(s):  
O. Kuroda ◽  
S. Takahashi ◽  
S. Kubota ◽  
K. Kikuchi ◽  
Y. Eguchi ◽  
...  

Author(s):  
D. F. Jefferies ◽  
C. J. Hewett

INTRODUCTIONThe caesium radionuclides, caesium-137 and caesium-134, are important constituents of aqueous radioactive effluents discharged to the environment of the United Kingdom from fuel re-processing plants and nuclear power stations (Howells, 1966; Mitchell, Harvey & Smith, 1968; Harvey, Baker & Mitchell, 1969). Their accumulation by marine fishes has been the subject of several previous studies, beginning with that of Chipman (1959) who noted that caesium-137 was accumulated in the flesh of the killifish (Fundulus heteroclitus) and that accumulation continued even after a period of 72 days. Similarly, Hiyama & Shimizu (1964) showed that the muscle of the common goby (Acanthobus flaviamus) continued to accumulate caesium-134 from sea water after periods of 30 days. Baptist & Price (1962) have examined the whole body uptake of caesium, by absorption from sea water, in two marine species, the flounder (Paralichthys dentatus) and the Atlantic croaker (Micropogon undulatus), and they also investigated the accumulation, tissue distribution and excretion of caesium-137 in the croaker, the little tuna (Euthynnus alleteratus) and the bluefish (Pomatomus saltatoux), following oral administration of single doses. These authors concluded that the heart, liver and spleen of the croaker absorbed caesium-137 from sea water at a faster rate than the muscle, and that orally administered caesium-137 was rapidly absorbed from the digestive tract. Tissue distributions were similar in the croaker, bluefish and tuna. The retention of caesium-137 in croaker tissue was described as a multiple rate process. In later experiments Hiyama & Shimizu (1969) compared turnover rates in various organs and tissues following uptake from sea water and from single injection experiments, and obtained good agreement between the values from the two methods.


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