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39 results on '"primary loop"'

2. Experimental Investigation of Cobalt Deposition on 304 Stainless Steel in Borated and Lithiated High-Temperature Water.

Author

Deng, Jian, Lei, Jieheng, Wang, Guolong, Zhong, Lin, Zhao, Mu, and Lei, Zeyong

Subjects
*PRESSURIZED water reactors, *INDUCTIVELY coupled plasma mass spectrometry, *HOT water, *X-ray photoelectron spectroscopy, *STAINLESS steel
Abstract

The radioactive corrosion products 58Co and 60Co in the primary loops of pressurized water reactors (PWRs) are the main sources of radiation doses to which workers in nuclear power plants are exposed. To understand cobalt deposition on 304 stainless steel (304SS), which is the main structural material used in the primary loop, the microstructural characteristics and chemical composition of a 304SS surface layer immersed for 240 h in borated and lithiated high-temperature water containing cobalt were investigated with scanning electron microscopy (SEM), X-ray diffraction (XRD), laser Raman spectroscopy (LRS), X-ray photoelectron spectroscopy (XPS), glow discharge optical emission spectrometry (GD-OES), and inductively coupled plasma emission mass spectrometry (ICP-MS). The results showed that two distinct cobalt deposition layers (an outer layer of CoFe2O4 and an inner layer of CoCr2O4) were formed on the 304SS after 240 h of immersion. Further research showed that CoFe2O4 was formed on the metal surface by coprecipitation of the iron preferentially dissolved from the 304SS surface with cobalt ions from the solution. The CoCr2O4 was formed by ion exchange between the cobalt ions entering the metal inner oxide layer and (Fe, Ni) Cr2O4. These results are useful in understanding cobalt deposition on 304SS and have a certain reference value for exploring the deposition behavior and mechanism of radionuclide cobalt on 304SS in the PWR primary loop water environment. [ABSTRACT FROM AUTHOR]

Published
2023
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3. Covert attacks for primary loops of PHWR nuclear power unit based on SOS-LSTM.

Author

Huang, Yu, Cui, Yan, Hao, Tongkai, Zhang, Peng, Sun, Xi, and Wang, Xiaoyan

Subjects
*NUCLEAR energy, *STANDARD deviations, *INDUSTRIAL controls manufacturing
Abstract

The ongoing advancement of industry and technology has led industrial control systems to evolve towards integration. System structures become increasingly complex, which renders them increasingly vulnerable to external attacks. Due to their clandestine and destructive character, covert attacks pose a significant threat to the secure operation of nuclear power unit control systems. In order to optimize the performance of control systems for nuclear power units, it is important to study the damage process caused by covert attacks on these systems. Facing the problem of obtaining high-precision estimation models of attack targets for covert attacks, this paper proposes a model estimation method based on long and short-term memory (LSTM) neural network and symbiotic organisms search (SOS) algorithm, which takes the feedback controller output and input signals of the attacking target as the dataset of the LSTM neural network, and optimizes the network parameters of the LSTM neural network using SOS algorithm to improve the accuracy of the model, and designs the covert attacker by obtaining the estimation model of the attacked area through training. The root mean square error of the estimation model for the primary loop of the nuclear power unit has been verified by comparative experiments to be reduced by at least 93.59%, 96.52%, and 91.11%, respectively, compared with the other methods. Loop experiment results concerning the covert attack for the primary loop of nuclear power unit illustrate that this attack method successfully meets the predefined objectives while maintaining high levels of stealthiness. [ABSTRACT FROM AUTHOR]

Published
2024
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4. Radioactive product analysis of a small molten-salt reactor in primary loop

Author

ZHOU Weilong, YAN Rui, and ZHOU Bo

Subjects
molten salt reactor, radioactivity, primary loop, actinoid nuclides, Nuclear engineering. Atomic power, TK9001-9401
Abstract

BackgroundBased on the research of molten salt reactor (MSR), a conceptual design of small MSR core with thermal power of 100 MWt is proposed to meet the power supply demand of small area. By adjusting the initial fuel load of the reactor core, the reactor can operate at full power for 1 250 days without refueling, and then batch process fuel at the end of its life.PurposeThis study aims to analyze the yield and source of radionuclides in the main loop during such a small MSR operation by providing the constitutions, main components, and parameters according to the burnup characteristics and fuel salt characteristics of the long refueling cycle.MethodsThe calculation software KENOVI for three-dimensional Monte Carlo transportation program and burnup analysis module Origen-S were employed to analyze the fuel consumption analysis module, the storage of radioactive products in the main loop and the neutron energy spectrum and other neutron parameters.ResultsThe computation results show that the radioactivity at the end-of-life this small MSR is about 7.36×1018 Bq, and the radioactivity of fission products in the end-of-life primary loop is about 5.89×1018 Bq, of which the inert gases, iodine isotopes and the volatile fission metal account for 7.35×1017 Bq, 9.56×1017 Bq, 8.17×1017 Bq respectively. The total radioactivity of actinide nuclides is about 1.47×1018 Bq, of which the 239Np accounts for 98%.ConclusionsThis study provides reference for radiation protection design and fuel reprocessing scheme of molten salt reactor.

Published
2021
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5. Development of a Qualified MELCOR Model for IR-360 NPP Using SNAP Software

Author

F Yousefpour, A Zarnooshe Farahani, M RahGoshay, and S. M Hoseyni

Subjects
pressurized nuclear power plant, primary loop, modeling, melcor code, snap software, nodalization, Nuclear and particle physics. Atomic energy. Radioactivity, QC770-798
Abstract

Development of a qualified thermal-hydraulics and the severe accident model of nuclear power plants (NPPs) is of crucial importance in their design, optimization and safety evaluation. This is also the first step in the safety analysis of the IR-360 NPP for which its design is domestically in process. Without an approved and “qualified" model, deterministic safety analysis (DSA) results are not reliable. In fact, the quality of the developed model should be assessed to ensure the reliability of the analysis results. This study attempts to develop a qualified MELCOR model for the IR-360 nuclear power plant in the SNAP nuclear analysis software. By selecting the appropriate nodalization of the problem and their proper connections, the most important thermo-hydraulics parameters such as pressure and temperature of the fluid, mass flow rate, direction and magnitude of the flow in the primary loop, etc are calculated. A comparison is made between the design parameters and calculated values to obtain the deviation of the model values from the design data. The calculated deviations shown to be below the acceptable limits, specified by the DSA practice including the suggestions of the International Atomic Energy Agency (IAEA). This confirms the qualification of the developed model for the safety analysis of the plant in the next steps.

Published
2017

6. Experimental Investigation of Cobalt Deposition on 304 Stainless Steel in Borated and Lithiated High-Temperature Water

Author

Jian Deng, Jieheng Lei, Guolong Wang, Lin Zhong, Mu Zhao, and Zeyong Lei

Subjects
304SS, cobalt, deposition, spinel, primary loop, General Materials Science
Abstract

The radioactive corrosion products 58Co and 60Co in the primary loops of pressurized water reactors (PWRs) are the main sources of radiation doses to which workers in nuclear power plants are exposed. To understand cobalt deposition on 304 stainless steel (304SS), which is the main structural material used in the primary loop, the microstructural characteristics and chemical composition of a 304SS surface layer immersed for 240 h in borated and lithiated high-temperature water containing cobalt were investigated with scanning electron microscopy (SEM), X-ray diffraction (XRD), laser Raman spectroscopy (LRS), X-ray photoelectron spectroscopy (XPS), glow discharge optical emission spectrometry (GD-OES), and inductively coupled plasma emission mass spectrometry (ICP-MS). The results showed that two distinct cobalt deposition layers (an outer layer of CoFe2O4 and an inner layer of CoCr2O4) were formed on the 304SS after 240 h of immersion. Further research showed that CoFe2O4 was formed on the metal surface by coprecipitation of the iron preferentially dissolved from the 304SS surface with cobalt ions from the solution. The CoCr2O4 was formed by ion exchange between the cobalt ions entering the metal inner oxide layer and (Fe, Ni) Cr2O4. These results are useful in understanding cobalt deposition on 304SS and have a certain reference value for exploring the deposition behavior and mechanism of radionuclide cobalt on 304SS in the PWR primary loop water environment.

Published
2023
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7. Study of tritium in the primary loop of HTR-10: Experiment and theoretical calculations.

Author

Xie, Feng, Cao, Jianzhu, Feng, Xiaogui, Tong, Jiejuan, Dong, Yujie, Zhang, Zuoyi, and Scarlat, Raluca O.

Subjects
*TRITIUM, *COPPER oxide, *MOLECULAR sieves, *GRAPHITE, *COOLANTS
Abstract

An experimental system for the measurement of tritium in the primary loop of HTR-10 has been established, sampling gas from the helium purification system. After the restart of HTR-10 in 2015, the activity of tritium in the primary loop has been obtained at three different sampling points: upstream of the copper oxide bed, downstream of the copper oxide bed, and downstream of the molecular sieve adsorber. The experimental results indicated that the activity concentration of tritium in the primary loop of HTR-10 was 1.09 (10) × 10 4 Bq/m 3 STP . The calculated value of 2.31 × 10 5 Bq/m 3 STP was highly conservative compared to the experimental results. The discrepancy between experimental data and theoretical result may come from uncertainties in the inputs to the generation term (He-3 in the helium coolant and Li-6 in the graphite), and the ability of the graphite in the primary coolant circuit to absorb and desorb tritium. The experimental data for the activity of tritium in the primary loop of HTR-10, HTTR, and AVR are presented and compared. The chemical form of H-3 and other factors affecting the experimental measurements are discussed. [ABSTRACT FROM AUTHOR]

Published
2018
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9. A Decentralized Traffic Management Approach for Ambient Networks Environments

Author

Callejo-Rodríguez, María Ángeles, Andrés-Colás, Jorge, García-de-Blas, Gerardo, Ramón-Salguero, Francisco Javier, Enríquez-Gabeiras, José, Hutchison, David, Series editor, Kanade, Takeo, Series editor, Kittler, Josef, Series editor, Kleinberg, Jon M., Series editor, Mattern, Friedemann, Series editor, Mitchell, John C., Series editor, Naor, Moni, Series editor, Nierstrasz, Oscar, Series editor, Pandu Rangan, C., Series editor, Steffen, Bernhard, Series editor, Sudan, Madhu, Series editor, Terzopoulos, Demetri, Series editor, Tygar, Dough, Series editor, Vardi, Moshe Y., Series editor, Weikum, Gerhard, Series editor, Schönwälder, Jürgen, editor, and Serrat, Joan, editor

Published
2005
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10. ASES National Solar Conference 2016: 'New Standard' Solar Hydronic Building Systems: State of the Art in New Mexico 2016.

Author

Stickney, Bristol

Subjects
HYDRONICS, BUILDING environmental engineering equipment, SOLAR heating equipment, SOLAR energy industries, RENEWABLE energy industry, EQUIPMENT & supplies
Abstract

In New Mexico over the past 15 years or so, hundreds of successful Solar Hydronic Combi-Systems have been installed using a systematic design strategy now known as the "New Standard". This well-proven, cookbook approach is the closest thing to 'plug and play' for solar/hydronics in whole buildings to date. [ABSTRACT FROM AUTHOR]

Published
2016
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12. A hybrid non-dominated sorting genetic algorithm and its application on multi-objective optimal design of nuclear power plant.

Author

Chen, Lei, Yan, Changqi, Liao, Yi, Song, Feifei, and Jia, Zhen

Subjects
*OPTIMAL designs (Statistics), *NUCLEAR power plants, *EXPERIMENTAL design, *MATHEMATICAL statistics, *NUCLEAR facilities
Abstract

The design of nuclear component can be optimized by seeking out the best combination of article operational and structural parameters. Through multi-objective optimization, the optimized scheme can not only meets the design requirements, but also satisfies the safety regulations. In this work, a hybrid non-dominated sorting genetic algorithm is proposed, and its performance is verified by comparing it with its prototype and immune memory clone constraint multi-objective algorithm through four test-functions; the designs of the steam generator and the primary loop of Qinshan I nuclear power plant are optimized by the proposed algorithm. The results show that the algorithm outperforms the other two through overall evaluation; the reactor inlet temperature is an important parameter which influences the distribution of the Pareto optimal front; through optimization, the weight of the steam generator can be reduced by 16.5%, and the primary flow-rate can be reduced by 17.0%, the weight of the primary loop can be reduced by 11.4%, and the volume can be reduced by 9.8%. [ABSTRACT FROM AUTHOR]

Published
2017
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25. Modeliranje brzine doza komponenata primarnog kruga tlakovodnog reaktora primjenom hibridne determinističko-stohastičke metodologije

Author

Matijević, Mario and Pevec, Dubravko

Subjects
pressurized water reactor (PWR), zaštitna zgrada, Monte Carlo metoda, deterministička metoda, Elektrotehnika, TEHNIČKE ZNANOSTI. Elektrotehnika, primary loop, tlakovodni reaktor, MAVRIC, udc:621.3(043.3), shielding calculations, containment, Monte Carlo method, proračun štita, TECHNICAL SCIENCES. Electrical Engineering, Electrical engineering, bor, SCALE6.0, dose rates, brzine doza, deterministic method, primarni krug, Tlakovodni reaktor
Abstract

U disertaciji je razvijen 3D simulacijski model primarnog kruga tlakovodnog reaktora PWR tipa (Pressurized Water Reactor) za efikasan proračun brzina doza koji se temelji na hibridnoj determinističko-stohastičkoj metodologiji. Provedena je analiza kritičnosti i proračun štita reaktora, primarnog kruga i zaštitne zgrade korištenjem CSAS6 i MAVRIC sekvence SCALE6.0 programskog paketa. Razvijen je detaljan model kombinatorne geometrije, materijala i karakteristika PWR postrojenja na temelju najboljih dostupnih podataka. Izvori ionizirajućeg zračenja komponenti primarnog kruga su uključili neutrone i fotone iz kritične jezgre reaktora te fotone od aktivacije primarnog hladioca kroz dvije rashladne petlje. Provedena je verifikacija razvijenog modela tehnikom plavljenja (flooding) te njegova parcijalna validacija usporedbom brzina nuklearnih reakcija s referentnim rezultatima H.B.Robinson-2 testnog primjera. Promotrena je mogućnost boriranja biološkog štita reaktora s prirodnim borom i borovim karbidom (B4C) u svrhu smanjenja emisije sekundarnog gama zračenja nastalog procesom radijativnog uhvata termaliziranih neutrona. Utvrđena je potrebna količina prirodnog bora koja dovodi do zasićenja u atenuacijskoj moći boriranog betona za smanjenje tokova čestica i doza. Analizirana je raspodjela i atenuacija brzina doza kroz elemente primarnog kruga unutar velikih struktura zaštitne zgrade fleksibilnim opisom adjungiranog izvora. Istražena je korisnost u definiciji materijalnih značajki adjungiranog izvora, kada se transport čestica dodatno usmjeruje u regije s materijalima od interesa. Kvantificirana je prednost FW-CADIS metodologije u odnosu na CADIS metodologiju i manualne tehnike redukcije varijance u MAVRIC sekvenci. Dane su preporuke za optimizaciju kontrolnih i numeričkih parametara MAVRIC sekvence u hibridnoj FW-CADIS metodologiji u svrhu efikasnog Monte Carlo modeliranja kompleksnog modela. Znanstveni doprinosi su: (1) razvijena je simulacijska procedura za određivanje brzine doza komponenti primarnog kruga reaktora bazirana na hibridnoj determinističko-stohastičkoj metodi; (2) određena je potrebna količina prirodnog bora biološkog štita reaktora za smanjenje sekundarne gama emisije; (3) optimizacija kontrolnih i numeričkih parametara hibridne metode za efikasan Monte Carlo proračun brzine doza unutar velikih struktura; (4) kvantifikacija prednosti FW-CADIS metode u odnosu na CADIS i manualne tehnike za redukciju varijance unutar MAVRIC sekvence. A 3D simulation model of pressurized water reactor (PWR) primary loop components for effective dose rates calculation based on hybrid deterministic-stochastic methodology was developed in proposed dissertation. Criticality and shielding calculations were performed using CSAS6 and MAVRIC sequences of SCALE6.0 code package. A detailed model of a combinatorial geometry, materials and characteristics of a PWR facility was based on best available input data. The sources of ionizing radiation in PWR primary loop components included neutrons and photons originating from critical core and photons from activated coolant in two primary loops. Validation and partial verification of proposed model were performed with flooding technique and with comparison of reaction rates to referenced H.B.Robinson-2 benchmark results. The reduction of secondary gamma emissions from radiative capture of thermalized neutrons in biological shield was examined via concrete boration with natural boron and boron carbide (B4C). Optimal boron concentration which leads to saturation of flux and dose rates attenuation was proposed. Distribution and attenuation of dose rates through large structures of containment building were analysed by flexible definition of adjoint source. The benefits of adjoint source definition with focus on material characteristics of a model was examined. Advantage of using FW-CADIS methodology over CADIS and manual variance reduction techniques inside MAVRIC shielding sequence has been quantified. Recommendations for optimal control and numerical parameters of a MAVRIC sequence with hybrid FW-CADIS methodology were given for effective Monte Carlo deep penetration shielding calculation. Scientific contributions are: (1) simulation procedure was developed to determine primary loop components dose rates based on a hybrid deterministic-stochastic method; (2) the required amount of natural boron was determined for reducing secondary gamma emissions inside biological shied; (3) control and numerical parameters of a MAVRIC sequence with hybrid methodology were optimized for effective Monte Carlo deep penetration shielding calculation; (4) advantage of using FW-CADIS methodology over CADIS and manual variance reduction techniques inside MAVRIC shielding sequence was quantified.

Published
2013

26. Utjecaj ograničene termičke ekspanzije na primarni cjevovod Nuklearne elektrane Krško

Author

Pino Koc, Miroslav Halilovič, and Boris Štok

Subjects
cjevovod, metod konačnih elemenata, nuklearna elektrana, ograničavač pomaka cijevi, primarni krug, termička ekspanzija, finite element method, nuclear power plant, pipe restraint, piping, primary loop, thermal expansion
Abstract

U ovom radu opisane su mehaničke analize primarnog cjevovoda Nuklearne elektrane Krško, koje obrađuju problem djelomično onemogućene termičke ekspanzije cjevovoda uslijed nedovoljnog razmaka među pločama ograničavača pomaka cijevi. Smanjenje razmaka između cijevi i pripadajućeg oslonca spriječava slobodno termičko proširenje cjevovoda tijekom zagrijavanja sistema. Time se prouzrokuju jake tlačne sile između cijevi i oslonaca, što se rezultira kao nepovoljno stanje deformacija i naprezanja i u cjevovodu i u potporama. Izvedene su serije numeričkih simulacija, koje potvrđuju dovoljnu čvrstoću primarnog cjevovoda Nuklearne elektrane Krško. Međutim, oslonci su puno više osjetljivi na opterećenja te vrste i stoga je za njih potrebno izvesti brižljivo konstrukcijsko razmatranje., Mechanical analyses of the Krško NPP primary system piping subjected to the restrained thermal expansion due to insufficient pipe shim clearances are addressed in the paper. Reduction of clearance between a pipe and respective pipe restraints preclude free thermal expansion of the pipe system during the heat-up, thus causing a rise of excessive contact forces in the pipe - pipe restraint pairs. This results in a development of unfavourable strains and stresses both in pipes and restraints. A series of numerical simulations was performed which demonstrate sufficient strength resistance of the Krško NPP primary piping, while supports are much more susceptible and need careful engineering consideration.

Published
2013

28. Pilotové základy - energetické piloty

Author

Glisníková, Věra, Leiter, Augustin, Hoza, Martin, Glisníková, Věra, Leiter, Augustin, and Hoza, Martin

Abstract

V současnosti, kdy je stále více kladen důraz na ekologii, a do popředí se dostávají obnovitelné zdroje energie, se využívání geotermální energie jeví jako jedna z vhodných alternativ. Cílem práce je vysvětlit funkci tepelných čerpadel na principu země – voda, zmínit faktory ovlivňující účinnost systému a pojednat o technologii provádění energopilot. Dále se práce věnuje rizikům spojených s teplotním ovlivňováním základové půdy a ukázkám realizací., At a time when ecology and renewable energy sources come to the fore, the use of geothermal energy appears to be one of the suitable alternatives. The aim of this paper is to explain the function of ground source heat pumps, to mention factors affecting the efficiency of the system and discuss the technology of energy piles realization. This paper also focuses at risks associated with the soil temperature influencing and shows examples of realization.

29. Obnova hermetických potrubních průchodek

Author

Kalivoda, Milan, Chladil, Josef, Kratochvíl, Zdeněk, Kalivoda, Milan, Chladil, Josef, and Kratochvíl, Zdeněk

Abstract

Řešené téma se zabývá obnovou potrubních hermetických průchodek v primárním okruhu jaderné elektrárny. Na začátku je popsána jaderná elektrárna Dukovany od obecného popisu až k detailnímu popisu obnovované komponenty s objasněním důvodu jejich výměny. Následuje popis jednotlivých technologií, které jsou aplikovány při obnově hermetických potrubních průchodek, výběr varianty umístění heterogenního svaru a sestavení pracovního postupu obnovy v prostorách primárního okruhu, za dodržení předepsané kvality a přísných bezpečnostních podmínek. V závěrečné části je kalkulace nákladů zvolené varianty a objasnění obnovy z pohledu délky odstávky., The topic of this work is the renewal of hermetic pipe penetrations within the primary loop of a nuclear power station. A description of the Dukovany nuclear power plant is included at the beginning, ranging from basic description to details of the renewed component and the reasoning for its replacement. Following is a description of the technologies, which are applied in order to restore the hermetic pipes, the choice of the placement of the heterogeneous weld and the compilation of a workflow for the renewal in the environment of the primary loop while maintaining the quality standards and the strict safety conditions. The conclusion includes a calculation of the expenses tied with the chosen variant the reasoning behind the renewal regarding the length of the outage.

30. Pilotové základy - energetické piloty

Author

Glisníková, Věra, Leiter, Augustin, Hoza, Martin, Glisníková, Věra, Leiter, Augustin, and Hoza, Martin

Abstract

V současnosti, kdy je stále více kladen důraz na ekologii, a do popředí se dostávají obnovitelné zdroje energie, se využívání geotermální energie jeví jako jedna z vhodných alternativ. Cílem práce je vysvětlit funkci tepelných čerpadel na principu země – voda, zmínit faktory ovlivňující účinnost systému a pojednat o technologii provádění energopilot. Dále se práce věnuje rizikům spojených s teplotním ovlivňováním základové půdy a ukázkám realizací., At a time when ecology and renewable energy sources come to the fore, the use of geothermal energy appears to be one of the suitable alternatives. The aim of this paper is to explain the function of ground source heat pumps, to mention factors affecting the efficiency of the system and discuss the technology of energy piles realization. This paper also focuses at risks associated with the soil temperature influencing and shows examples of realization.

31. Obnova hermetických potrubních průchodek

Author

Kalivoda, Milan, Chladil, Josef, Kratochvíl, Zdeněk, Kalivoda, Milan, Chladil, Josef, and Kratochvíl, Zdeněk

Abstract

Řešené téma se zabývá obnovou potrubních hermetických průchodek v primárním okruhu jaderné elektrárny. Na začátku je popsána jaderná elektrárna Dukovany od obecného popisu až k detailnímu popisu obnovované komponenty s objasněním důvodu jejich výměny. Následuje popis jednotlivých technologií, které jsou aplikovány při obnově hermetických potrubních průchodek, výběr varianty umístění heterogenního svaru a sestavení pracovního postupu obnovy v prostorách primárního okruhu, za dodržení předepsané kvality a přísných bezpečnostních podmínek. V závěrečné části je kalkulace nákladů zvolené varianty a objasnění obnovy z pohledu délky odstávky., The topic of this work is the renewal of hermetic pipe penetrations within the primary loop of a nuclear power station. A description of the Dukovany nuclear power plant is included at the beginning, ranging from basic description to details of the renewed component and the reasoning for its replacement. Following is a description of the technologies, which are applied in order to restore the hermetic pipes, the choice of the placement of the heterogeneous weld and the compilation of a workflow for the renewal in the environment of the primary loop while maintaining the quality standards and the strict safety conditions. The conclusion includes a calculation of the expenses tied with the chosen variant the reasoning behind the renewal regarding the length of the outage.

32. Pilotové základy - energetické piloty

Author

Glisníková, Věra, Leiter, Augustin, Glisníková, Věra, and Leiter, Augustin

Abstract

V současnosti, kdy je stále více kladen důraz na ekologii, a do popředí se dostávají obnovitelné zdroje energie, se využívání geotermální energie jeví jako jedna z vhodných alternativ. Cílem práce je vysvětlit funkci tepelných čerpadel na principu země – voda, zmínit faktory ovlivňující účinnost systému a pojednat o technologii provádění energopilot. Dále se práce věnuje rizikům spojených s teplotním ovlivňováním základové půdy a ukázkám realizací., At a time when ecology and renewable energy sources come to the fore, the use of geothermal energy appears to be one of the suitable alternatives. The aim of this paper is to explain the function of ground source heat pumps, to mention factors affecting the efficiency of the system and discuss the technology of energy piles realization. This paper also focuses at risks associated with the soil temperature influencing and shows examples of realization.

33. Pilotové základy - energetické piloty

Author

Glisníková, Věra, Leiter, Augustin, Glisníková, Věra, and Leiter, Augustin

Abstract

V současnosti, kdy je stále více kladen důraz na ekologii, a do popředí se dostávají obnovitelné zdroje energie, se využívání geotermální energie jeví jako jedna z vhodných alternativ. Cílem práce je vysvětlit funkci tepelných čerpadel na principu země – voda, zmínit faktory ovlivňující účinnost systému a pojednat o technologii provádění energopilot. Dále se práce věnuje rizikům spojených s teplotním ovlivňováním základové půdy a ukázkám realizací., At a time when ecology and renewable energy sources come to the fore, the use of geothermal energy appears to be one of the suitable alternatives. The aim of this paper is to explain the function of ground source heat pumps, to mention factors affecting the efficiency of the system and discuss the technology of energy piles realization. This paper also focuses at risks associated with the soil temperature influencing and shows examples of realization.

34. Obnova hermetických potrubních průchodek

Author

Kalivoda, Milan, Chladil, Josef, Kalivoda, Milan, and Chladil, Josef

Abstract

Řešené téma se zabývá obnovou potrubních hermetických průchodek v primárním okruhu jaderné elektrárny. Na začátku je popsána jaderná elektrárna Dukovany od obecného popisu až k detailnímu popisu obnovované komponenty s objasněním důvodu jejich výměny. Následuje popis jednotlivých technologií, které jsou aplikovány při obnově hermetických potrubních průchodek, výběr varianty umístění heterogenního svaru a sestavení pracovního postupu obnovy v prostorách primárního okruhu, za dodržení předepsané kvality a přísných bezpečnostních podmínek. V závěrečné části je kalkulace nákladů zvolené varianty a objasnění obnovy z pohledu délky odstávky., The topic of this work is the renewal of hermetic pipe penetrations within the primary loop of a nuclear power station. A description of the Dukovany nuclear power plant is included at the beginning, ranging from basic description to details of the renewed component and the reasoning for its replacement. Following is a description of the technologies, which are applied in order to restore the hermetic pipes, the choice of the placement of the heterogeneous weld and the compilation of a workflow for the renewal in the environment of the primary loop while maintaining the quality standards and the strict safety conditions. The conclusion includes a calculation of the expenses tied with the chosen variant the reasoning behind the renewal regarding the length of the outage.

35. Obnova hermetických potrubních průchodek

Author

Kalivoda, Milan, Chladil, Josef, Kalivoda, Milan, and Chladil, Josef

Abstract

Řešené téma se zabývá obnovou potrubních hermetických průchodek v primárním okruhu jaderné elektrárny. Na začátku je popsána jaderná elektrárna Dukovany od obecného popisu až k detailnímu popisu obnovované komponenty s objasněním důvodu jejich výměny. Následuje popis jednotlivých technologií, které jsou aplikovány při obnově hermetických potrubních průchodek, výběr varianty umístění heterogenního svaru a sestavení pracovního postupu obnovy v prostorách primárního okruhu, za dodržení předepsané kvality a přísných bezpečnostních podmínek. V závěrečné části je kalkulace nákladů zvolené varianty a objasnění obnovy z pohledu délky odstávky., The topic of this work is the renewal of hermetic pipe penetrations within the primary loop of a nuclear power station. A description of the Dukovany nuclear power plant is included at the beginning, ranging from basic description to details of the renewed component and the reasoning for its replacement. Following is a description of the technologies, which are applied in order to restore the hermetic pipes, the choice of the placement of the heterogeneous weld and the compilation of a workflow for the renewal in the environment of the primary loop while maintaining the quality standards and the strict safety conditions. The conclusion includes a calculation of the expenses tied with the chosen variant the reasoning behind the renewal regarding the length of the outage.

36. Obnova hermetických potrubních průchodek

Author

Kalivoda, Milan, Chladil, Josef, Kalivoda, Milan, and Chladil, Josef

Abstract

Řešené téma se zabývá obnovou potrubních hermetických průchodek v primárním okruhu jaderné elektrárny. Na začátku je popsána jaderná elektrárna Dukovany od obecného popisu až k detailnímu popisu obnovované komponenty s objasněním důvodu jejich výměny. Následuje popis jednotlivých technologií, které jsou aplikovány při obnově hermetických potrubních průchodek, výběr varianty umístění heterogenního svaru a sestavení pracovního postupu obnovy v prostorách primárního okruhu, za dodržení předepsané kvality a přísných bezpečnostních podmínek. V závěrečné části je kalkulace nákladů zvolené varianty a objasnění obnovy z pohledu délky odstávky., The topic of this work is the renewal of hermetic pipe penetrations within the primary loop of a nuclear power station. A description of the Dukovany nuclear power plant is included at the beginning, ranging from basic description to details of the renewed component and the reasoning for its replacement. Following is a description of the technologies, which are applied in order to restore the hermetic pipes, the choice of the placement of the heterogeneous weld and the compilation of a workflow for the renewal in the environment of the primary loop while maintaining the quality standards and the strict safety conditions. The conclusion includes a calculation of the expenses tied with the chosen variant the reasoning behind the renewal regarding the length of the outage.

37. Pilotové základy - energetické piloty

Author

Glisníková, Věra, Leiter, Augustin, Glisníková, Věra, and Leiter, Augustin

Abstract

V současnosti, kdy je stále více kladen důraz na ekologii, a do popředí se dostávají obnovitelné zdroje energie, se využívání geotermální energie jeví jako jedna z vhodných alternativ. Cílem práce je vysvětlit funkci tepelných čerpadel na principu země – voda, zmínit faktory ovlivňující účinnost systému a pojednat o technologii provádění energopilot. Dále se práce věnuje rizikům spojených s teplotním ovlivňováním základové půdy a ukázkám realizací., At a time when ecology and renewable energy sources come to the fore, the use of geothermal energy appears to be one of the suitable alternatives. The aim of this paper is to explain the function of ground source heat pumps, to mention factors affecting the efficiency of the system and discuss the technology of energy piles realization. This paper also focuses at risks associated with the soil temperature influencing and shows examples of realization.

38. Obnova hermetických potrubních průchodek

Author

Kalivoda, Milan, Chladil, Josef, Kratochvíl, Zdeněk, Kalivoda, Milan, Chladil, Josef, and Kratochvíl, Zdeněk

Abstract

Řešené téma se zabývá obnovou potrubních hermetických průchodek v primárním okruhu jaderné elektrárny. Na začátku je popsána jaderná elektrárna Dukovany od obecného popisu až k detailnímu popisu obnovované komponenty s objasněním důvodu jejich výměny. Následuje popis jednotlivých technologií, které jsou aplikovány při obnově hermetických potrubních průchodek, výběr varianty umístění heterogenního svaru a sestavení pracovního postupu obnovy v prostorách primárního okruhu, za dodržení předepsané kvality a přísných bezpečnostních podmínek. V závěrečné části je kalkulace nákladů zvolené varianty a objasnění obnovy z pohledu délky odstávky., The topic of this work is the renewal of hermetic pipe penetrations within the primary loop of a nuclear power station. A description of the Dukovany nuclear power plant is included at the beginning, ranging from basic description to details of the renewed component and the reasoning for its replacement. Following is a description of the technologies, which are applied in order to restore the hermetic pipes, the choice of the placement of the heterogeneous weld and the compilation of a workflow for the renewal in the environment of the primary loop while maintaining the quality standards and the strict safety conditions. The conclusion includes a calculation of the expenses tied with the chosen variant the reasoning behind the renewal regarding the length of the outage.

39. Pilotové základy - energetické piloty

Author

Glisníková, Věra, Leiter, Augustin, Hoza, Martin, Glisníková, Věra, Leiter, Augustin, and Hoza, Martin

Abstract

V současnosti, kdy je stále více kladen důraz na ekologii, a do popředí se dostávají obnovitelné zdroje energie, se využívání geotermální energie jeví jako jedna z vhodných alternativ. Cílem práce je vysvětlit funkci tepelných čerpadel na principu země – voda, zmínit faktory ovlivňující účinnost systému a pojednat o technologii provádění energopilot. Dále se práce věnuje rizikům spojených s teplotním ovlivňováním základové půdy a ukázkám realizací., At a time when ecology and renewable energy sources come to the fore, the use of geothermal energy appears to be one of the suitable alternatives. The aim of this paper is to explain the function of ground source heat pumps, to mention factors affecting the efficiency of the system and discuss the technology of energy piles realization. This paper also focuses at risks associated with the soil temperature influencing and shows examples of realization.

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