Relevant bibliographies by topics / The reactor tube

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  1. Journal articles
  2. Dissertations / Theses
  3. Books
  4. Book chapters
  5. Conference papers
  6. Reports

Academic literature on the topic 'The reactor tube'

Author: Grafiati
Published: 4 June 2021
Last updated: 1 February 2022

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Journal articles on the topic "The reactor tube"

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Hatamachi, Tsuyoshi, Tatsuya Kodama, Yuki Isobe, Daisuke Nakano, and Nobuyuki Gokon. "Double-Walled Reactor Tube with Molten Salt Thermal Storage for Solar Tubular Reformers." Journal of Solar Energy Engineering 128, no. 2 (April 8, 2005): 134–38. http://dx.doi.org/10.1115/1.2183803.

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This paper proposes a novel-type of “double-walled” reactor tube with molten-salt thermal storage at high temperatures for use in solar tubular reformers. The prototype reactor tube is demonstrated on the heat-discharge and chemical reaction performances during cooling mode of the reactor tube at laboratory scale. The Na2CO3 composite material with MgO ceramics was filled into the outer annulus of the double-walled reactor tube while the Ru-based catalyst particles were filled into the inner tube. The heat discharge form the molten Na2CO3 circumvented the rapid temperature change of the catalyst bed, which resulted in the alleviation of decrease in chemical conversion during cooling mode of the reactor tube. The application of the new reactor tubes to solar tubular reformers is expected to help realize stable operation of the solar reforming process under fluctuating insolation during a cloud passage.
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Gužela, Štefan, František Dzianik, Martin Juriga, and Juraj Kabát. "Shell and Tube Heat Exchanger – the Heat Transfer Area Design Process." Strojnícky casopis – Journal of Mechanical Engineering 67, no. 2 (November 1, 2017): 13–24. http://dx.doi.org/10.1515/scjme-2017-0014.

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AbstractNowadays, the operating nuclear reactors are able to utilise only 1 % of mined out uranium. An effective exploitation of uranium, even 60 %, is possible to achieve in so-called fast reactors. These reactors commercial operation is expected after the year 2035. Several design configurations of these reactors exist. Fast reactors rank among the so-called Generation IV reactors. Helium-cooled reactor, as a gas-cooled fast reactor, is one of them. Exchangers used to a heat transfer from a reactor active zone (i.e. heat exchangers) are an important part of fast reactors. This paper deals with the design calculation of U-tube heat exchanger (precisely 1-2 shell and tube heat exchanger with U-tubes): water – helium.
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Luyben, William L. "Effect of Peak Temperature Limitations on the Design of Processes with Cooled Tubular Reactors." International Journal of Chemical Reactor Engineering 12, no. 1 (January 1, 2014): 191–203. http://dx.doi.org/10.1515/ijcre-2013-0138.

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Abstract Maximum temperature limitations are usually encountered in exothermic catalytic reaction systems due to catalyst deactivation. Therefore, the peak temperature in a cooled tubular reactor can be constrained to some maximum limit. The peak temperature is a function of many design and operating variables such as reactor volume and heat-transfer area (number of tubes, tube diameter and tube length), coolant temperature, inlet reactant concentration, per-pass conversion and reactant feed distribution. These variables affect the design of both the reactor and the separation section of the plant. This paper explores the impact of this peak temperature limitation on the economic design of the entire process. The numerical example used is the production of cumene from benzene and propylene. Results show that costs increase as the peak temperature limitation decreases. Use of two cooled reactors in series with the limiting reactant split between the reactors is more economical than a single reactor.
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Zahradník, Jindřich, and Milan Rylek. "Design and scale-up of Venturi-tube gas distributors for bubble column reactors." Collection of Czechoslovak Chemical Communications 56, no. 3 (1991): 619–35. http://dx.doi.org/10.1135/cccc19910619.

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General principles of ejector distributors performance are surveyed and demonstrated for two particular cases of Venturi tubes commonly employed for gas dispersion in tower reactors with forced liquid circulation. Design recommendations for the two types of Venturi-tube gas distributors are presented and a general method is outlined for ejector distributors scale-up, based on the decisive effect of energy dissipation rate on the distributors performance. As an illustration, the specific case of Venturi-tube gas distributor design for an industrial reactor for catalytic hydrogenation of rape-seed oil is treated in detail. The procedure included design of a small-scale laboratory reactor for kinetic experiments at real process conditions (scale-down step) and subsequent ejector distributor scale up to dimensions corresponding to the industrial reactor (vessel diameter 1.6 m, effective reactor volume ~ 5 m3). Comparison with other modes of gas dispersion proved superiority of Venturi-tube distributors both on the laboratory- and industrial-scale level, regarding the overall rate of reaction process achieved and/or catalyst load requirements.
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Burkholder, Michael, Stanley Gilliland, Adam Luxon, Christina Tang, and B. Gupton. "Improving Productivity of Multiphase Flow Aerobic Oxidation Using a Tube-in-Tube Membrane Contactor." Catalysts 9, no. 1 (January 17, 2019): 95. http://dx.doi.org/10.3390/catal9010095.

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The application of flow reactors in multiphase catalytic reactions represents a promising approach for enhancing the efficiency of this important class of chemical reactions. We developed a simple approach to improve the reactor productivity of multiphase catalytic reactions performed using a flow chemistry unit with a packed bed reactor. Specifically, a tube-in-tube membrane contactor (sparger) integrated in-line with the flow reactor has been successfully applied to the aerobic oxidation of benzyl alcohol to benzaldehyde utilizing a heterogeneous palladium catalyst in the packed bed. We examined the effect of sparger hydrodynamics on reactor productivity quantified by space time yield (STY). Implementation of the sparger, versus segmented flow achieved with the built in gas dosing module (1) increased reactor productivity 4-fold quantified by space time yield while maintaining high selectivity and (2) improved process safety as demonstrated by lower effective operating pressures.
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Jiang, Yun Bo, and Ke Zheng Zhang. "Study of Discrete and Multi-Tube Pass Number Inorganic Membrane Reactor." Advanced Materials Research 233-235 (May 2011): 3036–39. http://dx.doi.org/10.4028/www.scientific.net/amr.233-235.3036.

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Discrete and Multi-tube Pass Number Inorganic Membrane Reactor offers supplements to single-tube membrane reactor, referencing heat exchanger can provide larger transmission area and plate column can realize multi-stage separation. It realizes the reaction and separation occurs simultaneously many times, and can change the membrane area according to the need, so that reaction and separation process can be matched better. Discrete and multi-tube membrane reactor and fixed bed reactor was experimented in sec-butyl alcohol dehydrogenation system at 150-225, the result shows the new membrane reactor structure is reasonable.
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Yoshino, M., M. Yao, H. Tsuno, and I. Somiya. "Removal and recovery of phosphate and ammonium as struvite from supernatant in anaerobic digestion." Water Science and Technology 48, no. 1 (July 1, 2003): 171–78. http://dx.doi.org/10.2166/wst.2003.0045.

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Removal of phosphorus and nitrogen is required to prevent eutrophication problems in lakes and enclosed coastal seas. And recovery of phosphorus from wastewater has been attracting attention because of lack in phosphorus resources in the near future. In this study, reaction kinetics and design parameters of struvite production are experimentally investigated by using basic reaction type and a draft-tube type reactors. Struvite production rate, which is a very important parameter in reactor design and efficiency estimation, is formulated in an equation consisting of a rate constant (k2), and magnesium, phosphate and ammonium concentrations. The value of k2 is shown to be increased with struvite concentration and mixing intensity in the reactor. The developed equation is applied to the results obtained from the draft-tube type reactor experiments and verified for its applicability. High struvite concentration of 10-25% is maintained in the draft-tube reactor experiments. 92% removal and recovery efficiency with effluent phosphorus concentration of 17 mg/L is achieved under the conditions of 4 minutes reaction time, pH of 8.5 and Mg/P molar ratio of 1.1.
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Mahendra Prabhu, N., K. A. Gopal, S. Murugan, T. K. Haneef, C. K. Mukhopadhyay, S. Venugopal, and T. Jayakumar. "Determining the feasibility of identifying creep rupture of stainless steel cladding tubes on-line using acoustic emission technique." International Journal of Structural Integrity 6, no. 3 (June 8, 2015): 410–18. http://dx.doi.org/10.1108/ijsi-08-2014-0038.

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Purpose – The purpose of this paper is to determine the feasibility of identifying the creep rupture of reactor cladding tubes using acoustic emission technique (AET). Design/methodology/approach – The creep rupture tests were carried out by pressuring stainless steel capsules upto 6 MPa at room temperature and then heating continuously in a furnace upto rupture. The acoustic emission (AE) signals generated during the creep rupture tests were recorded using a 150 kHz resonant sensor and analysed using AE Win software. Findings – When rupture occurs in the pressurized capsule tube representing the cladding tube, AE sensor attached to a waveguide captures the mechanical disturbance from the capsule and these data can be advantageously used to identify the creep rupture event of the cladding tube. Practical implications – The creep rupture data of fuel clad tube is very important in design and for smooth operation of nuclear reactors without fuel pin failure in reactors. Originality/value – AE is an advanced non-destructive evaluation technique. This technique has been successfully applied for on-line monitoring of creep rupture of the reactor cladding tube which otherwise could be detected by thermocouple readings only.
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Vakili, Reza, and Reza Eslamloueyan. "Design and Optimization of a Fixed Bed Reactor for Direct Dimethyl Ether Production from Syngas Using Differential Evolution Algorithm." International Journal of Chemical Reactor Engineering 11, no. 1 (June 18, 2013): 147–58. http://dx.doi.org/10.1515/ijcre-2012-0026.

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Abstract Dimethyl ether (DME) is traditionally produced by methanol dehydration in an adiabatic reactor. Recently, a more economical method has been proposed to produce DME in a reactor in which methanol production and dehydration take place simultaneously on a bi-functional catalyst. In the present study, the design and optimization of an industrial scale fixed bed reactor for the direct synthesis of DME from syngas are investigated. A steady state, pseudo-homogeneous model has been applied to simulate the proposed reactor. At first, the preliminary design of the reactor is done based on the reactor design heuristics for industrial reactors. Then, using differential evolution (DE) algorithm as a fast and efficient optimization method, the tentative reactor operating conditions and its internal configuration are optimized. The objective of the optimization is to maximize DME production in each tube of the reactor. The number of tubes, feed inlet and coolant water temperatures are considered as decision variables of the optimization algorithm. At the optimum conditions, the reactor size decreases due to increase of CO conversion and DME productivity in each tube. The results show that the proposed optimum reactor is more economical for large-scale production of DME in comparison to the conventional industrial DME reactor.
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Gopaul, S., V. Hopps, Ch Jacobs, M. Khan, R. Patkunam, and I. L. Pioro. "ICONE15-10829 SOME DESIGN FEATURES OF SCW PRESSURE-TUBE NUCLEAR REACTOR." Proceedings of the International Conference on Nuclear Engineering (ICONE) 2007.15 (2007): _ICONE1510. http://dx.doi.org/10.1299/jsmeicone.2007.15._icone1510_429.

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Dissertations / Theses on the topic "The reactor tube"

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Honkala, E. (Elina). "Validation and development of a novel draft tube reactor." Master's thesis, University of Oulu, 2014. http://urn.fi/URN:NBN:fi:oulu-201406191772.

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Draft tube circulators have been used in various industrial processes. They contain an inner tube located inside the reactor. An axial impeller at the top part of the inner tube pushes the fluid downwards. This reactor concept uses less energy to achieve sufficient mixing in the system. Outotec has developed a novel draft tube reactor which exploits draft tube circulator principles and consists of horizontal and vertical sections. The aim of this work was to obtain information on the flow and solid resuspension behavior of the test tube reactor for the design and further development of the OKTOP®6000 reactor. Flow velocities were measured with an ultrasound measuring probe that utilizes the Doppler effect. The aim of the experiments was to gain information about the flow profile inside the reactor annulus from different measuring points. Flow velocity results were used to validate the computational fluid dynamic simulation results made earlier. Liquid-solid and liquid-solid-gas mixing was studied with electrical impedance tomography (EIT) devices, which measure conductivity difference in the media. Experiments were done with different solids contents, impeller rotation speeds and different gas feed rates to determine what kinds of mixing conditions achieve complete off-bottom suspension. Slurry samples were taken from the upper part of the reactor to obtain information on how much sand flows to the upper part of the reactor. Based on the flow velocity and CFD simulations, the flow inside the reactor annulus is highly turbulent and the flow profile is time dependent. There is a recirculation area at the bottom of the reactor and the flow is pulsating to the upper part of the reactor. Solids suspension tests show that the reactor concept achieves complete off-bottom suspension more easily without gas feed. The gas feeding system was not optimal and some of the gas flooded from the draft tube and disturbed the flow inside the draft tube. Solids suspension tests confirmed the fact that the flow profile was pulsating and time dependent. Flow velocity and solids suspension test results can be used to dimension and further develop the novel draft tube reactor OKTOP®6000, which is part of the Outotec reactor family
Imuputkireaktoreita on käytössä monissa erilaisissa teollisissa sovelluksissa. Reaktorin sisälle on asennettu sisäputki, jonka yläosassa on tyypillisesti sekoitin, joka saa aikaan liuoskierron sisäputken kautta reaktorin annulukseen. Sisäputken ansiosta sekoitukseen tarvittava energiamäärä on pienempi kuin perinteisissä sekoitusreaktoreissa. Outotec on kehittänyt sisäputkireaktoriteknologiaa hyödyntävän OKTOP®6000-reaktorin, joka koostuu vaaka- ja pystysuuntaisista osioista. Imuputkireaktorin avulla pyrittiin selventämään reaktorin suunnittelun ja jatkokehityksen avuksi virtausominaisuuksia sekä kiintoaineen suspengointiin liittyviä ilmiöitä. Virtausnopeuksia mitattiin Doppler-ilmiötä hyödyntävällä mittalaitteella eri kohdista reaktorin ulkokehää. Tarkoituksena oli saada tietoa virtausnopeuksista muutamassa mittauspisteessä reaktorin sisältä eri sekoittajan pyörimisnopeuksilla. Tuloksien avulla pyrittiin vahvistamaan virtauslaskennan tuloksia. Toisessa osassa reaktoriin lisättiin kiintoainetta ja tutkittiin sen liikkeelle lähtöä eri hiekkamäärillä, sekoituksen kierrosmäärillä sekä happisyöttömäärillä. Tarkoituksena oli saada tietoa milloin neste-kiintoaine- sekä neste-kiintoaine-kaasu-systeemeissä saadaan aikaan sellaiset sekoitusolosuhteet, että kaikki hiekka joko liikkuu reaktorin pohjassa ja mahdollisesti virtaa reaktorin yläosaan. Mittauksessa käytettiin apuna sähköimpedanssi tomografiasauvoja (EIT), jotka mittaavat sähkönjohtavuuseroja väliaineesta. Lisäksi reaktorin yläosaan virtaavan hiekan kiintoainepitoisuutta mitattiin yläosasta otettujen näytteiden avulla. Virtausmittausten ja -simulointien perusteella voidaan sanoa, että virtaus reaktorissa on hyvin turbulenttinen ja virtausprofiili vaihtelee eri ajanhetkillä. Reaktorin pohjaan muodostuu pyörteitä kun sisäputkesta tuleva virtaus muuttaa suuntaa. Virtaus kohti reaktorin yläosaa on hyvin sykkivää. Kiintoainekokeiden perusteella nähtiin, että hiekka pysyi liikkeessä kaikilla kierrosnopeuksilla ja hiekkamäärillä ilman kaasusyöttöä. Happisyöttö puolestaan häiritsi systeemiä ja sai hiekan laskeutumaan tietyssä pisteessä. Kaasun syöttöjärjestelmä ei ollut optimaalinen tälle reaktorikonseptille, sillä isommat kaasumäärät tulvivat ulos sisäputkesta virtaamatta nestevirtauksen mukana. Virtausmittaus- ja kiintoainekokeiden tuloksia voidaan käyttää OKTOP®6000-reaktorin jatkokehityksessä ja suunnittelussa
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Hejzlar, Pavel. "Conceptual design of a large, passive, pressure-tube light water reactor." Thesis, Massachusetts Institute of Technology, 1994. http://hdl.handle.net/1721.1/28074.

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Freiwald, Martin Georg. "Transport processes in packed beds of low tube to particle diameter ratio." Thesis, University of Cambridge, 1991. http://ethos.bl.uk/OrderDetails.do?uin=uk.bl.ethos.387132.

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Chou, Jeremy Chi-Hung 1977. "A study of vacuum packaging methods for a microfabricated suspended tube reactor." Thesis, Massachusetts Institute of Technology, 2002. http://hdl.handle.net/1721.1/87419.

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Thesis (M.Eng.)--Massachusetts Institute of Technology, Dept. of Electrical Engineering and Computer Science, 2002.
Includes bibliographical references (p. 74-75).
by Jeremy Chi-Hung Chou.
M.Eng.
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Mattingly, Brett T. (Brett Thomas). "Performance analysis of matrix fuel for a passive pressure tube light water reactor." Thesis, Massachusetts Institute of Technology, 1995. http://hdl.handle.net/1721.1/38099.

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McLurgh, David Brian. "Study of a porous tube reactor for the wet air oxidation of aqueous wastes." Thesis, University of Bath, 1997. https://ethos.bl.uk/OrderDetails.do?uin=uk.bl.ethos.242783.

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Losh, James David. "Linear Stability Analysis of a Rijke Tube and Modeling of Turbulent Combustion Using Dynamic Well-Stirred Reactors." Thesis, Virginia Tech, 2004. http://hdl.handle.net/10919/42792.

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In the first part of this work, instability is correctly predicted for a Rijke tube with a new two-term acoustic forcing term derived from a one-dimensional flame dynamics model. The new two-term acoustic forcing term, which is comprised of the summation of chemical heat release rate and heat transfer due to convection, correctly predicts instability where older models of acoustic forcing based solely on chemical heat release rate incorrectly predicted stability. This stability analysis correctly predicts the inlet conditions of the instability in addition to the frequency of instability.

In the second part of this work, networks of dynamic well-stirred reactors are used to model qualitative behavior observed in turbulent combustion. First a model of dynamic well-stirred reactor is derived, and then several reactors are coupled together by recirculation. The dynamics of the various models are computed and assessed. The models exhibit interesting behavior that has been viewed experimentally including hysteresis and peaking in the dynamic response.
Master of Science

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Wasmund, Eric Bain Coley Ken. "A study of powder making by the decomposition of nickel carbonyl in an aerosol tube reactor." *McMaster only, 2005.

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9

Loubser, Karl Albie. "An experimental study of an inherently-safe, natural circulating, flash-tube type system for a nuclear reactor steam supply concept." Thesis, Stellenbosch : Stellenbosch University, 2014. http://hdl.handle.net/10019.1/96050.

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Thesis (MEng) -- Stellenbosch University, 2014.
ENGLISH ABSTRACT: This project investigates aspects of a novel inherently safe nuclear power steam supply system as safety is of paramount importance. The system envisaged has unique features namely: a) a two-phase flow flash-tube type natural circulating primary loop (also the secondary radioactive particle containment); b) a twophase flow thermosyphon heat pipe type heat exchanger secondary loop is used to transfer heat from the primary loop to the steam generators, thereby physically separating the two flow streams from one another; c) a natural convection air cooled condenser for the removal of the reactor’s residual heat; d) a unique core using TRISO type fuel (acting as the primary radioactive particle containment) with life of at least 8.9 years; e) a steel containment vessel acting as a tertiary radioactive product containment; f) a concrete containing structure with air vents to allow air to pass over the main steel containment vessel for cooling purposes in the case of an emergency, and for the removal of parasitic heat during operation. In particular the primary and secondary loops of the proposed system are investigated. This is done by design, construction and testing of a small scale experimental set-up of the primary and secondary loops as well as the development of theoretical models for the two loops. A literature survey focusing on nuclear technology, thermosyphon loops, natural circulating loop instabilities, heat pipes, and two-phase flow modelling is presented to give a brief overview of the technologies as well as tools used in the work undertaken. Observations of the inside flow behaviour of the primary loop experimental set-up were made possible by windows providing many insights into the inner workings, such as plume formation and geysering. The transient response of the secondary heat pipe loop start-up is also investigated. A thermal resistance theoretical model was developed for the secondary loop using heat transfer formulae from theory as well as experimentally semiempirical correlated formula. Different states of operation of the secondary loop were observed during testing with the theoretical model of the condensing regime correlating well, two-phase regime correlating acceptably and liquid regime correlating poorly to experimental results and thus were modelled using an experimentally determined overall heat transfer coefficient. The secondary loop model of the liquid regime is coupled with the primary loop theoretical model to predict the system’s performance. A homogeneous, one-dimensional, simple theoretical model for the primary loop was derived and computer simulated. The results did not compare well with experimental results for single phase flow and failed to capture the onset of two-phase flow. The assumptions of one dimensional model with a unidirectional flow, a hydrostatic pressure problem, a constant volumetric flow rate and the inability of the implementation of the code to handle expansion are noted as some of the flaws in the theoretical model. The following recommendations are made: a more advanced design of the pressuriser should be incorporated into the experiment; the secondary loop’s theoretical model should be characterised under a broader set of operating conditions; the computer program can be used as the basis for further research and implementation of alternative solution algorithms and models.
AFRIKKANSE OPSOMMING: Hierdie projek ondersoek aspekte van ’n ongewone, essensieel veilige kernkrag stoomtoevoer-stelsel, omdat veiligheid van kardinale belang is. Die stelsel wat voorgestel is, het unieke eienskappe, naamlik: a) ’n twee-fasevloei flits-buistipe natuurlik sirkulerende primêre lus (wat ook die sekondêre inperking van radioaktiewe materiaal bevat); b) ’n twee-fasevloei termo-heweleffek sekondêre lus hitte-pyp hitte-uitruiler word gebruik om die hitte vanaf die primêre lus oor te dra na die stoomkragopwekkers en daardeur word die twee strome se vloei fisies geskei van mekaar; c) ’n natuurlike konveksie lugverkoelde kondensor word gebruik vir die verwydering van die reaktors se oortollige hitte; d) ’n unieke kern gebruik TRISO-tipe brandstof (wat as die primêre inperking van radioaktiewe materiaal optree) met ’n lewe van minstens 8.9 jaar; e) ’n inperkingshouer van staal wat optree as ’n tersiêre radioaktiewe produkhouer; f) ’n betonstruktuur met lugventilasie om toe te laat dat lug oor die hoof staalhouer vloei vir verkoeling in ’n noodgeval, en vir die verwydering van parasitiese hitte tydens werking. Hoofsaaklik word die primêre en sekondêre lusse van die voorgestelde stelsel ondersoek. Dit word gedoen deur die ontwerp, konstruksie en die toets van ’n eksperimentele opstelling van die primêre en sekondêre lusse op klein skaal, sowel as die ontwikkeling van teoretiese modelle vir die twee lusse. ’n Literatuurstudie wat fokus op kerntegnologie, termo-heweleffeklusse, natuurlik sirkulerende lus instabiliteit, hitte-pype, en twee-fase vloeimodellering word aangebied om ’n kort oorsig te gee van die tegnologie, sowel as gereedskap gebruik in die werk wat onderneem is. Om die interne vloeigedrag van die primêre lus se eksperimentele opstelling waar te neem, word daar gebruik gemaak van vensters wat dien as ’n manier om die innerlike werking van die proses soos pluimvorming en die kook van die water in die warmwaterkolom te toon. Die oorgangsreaksie van die sekondêre hittepyplus aanvangs is ook ondersoek. ’n Teoretiese termiese weerstandmodel is ontwikkel vir die sekondêre lus met behulp van hitte-oordragformules waarvoor hitte-oordragteorie gebruik is, wat met eksperimentele semi-empiriese formules gekorreleer is. Verskillende toestande van die sekondêre lus se werking is waargeneem gedurende die toetse. Die teoretiese model het goed met die kondensasiestaat gekorreleer, terwyl by die twee-fasewerkswyse aanvaarbare korrellasies aangetref is en die uiteindelike vloeitoestand swakker gekorrelleer het met eksperimentele resultate en dus gemodelleer is met behulp van die NTU-effektiwiteitsmetode. Die sekondêre lusmodel van die vloeistoftoestand is gekoppel met die primêre lus teoretiese model om die werking van die stelsels te voorspel. ’n Homogene een-dimensionele eenvoudige teoretiese model van die primêre lus is afgelei en ’n rekenaar simulasie is uitgevoer. Die resultate vergelyk nie goed met die eksperimentele resultate vir enkelfasevloei en kon nie die aanvang van twee-fasevloei beskryf nie. Die aannemings van ’n een-dimensionele model met eenrigting vloei, ’n hidrostatiese druk probleem, ’n konstant volumetries vloeitempo en die onvermoë van die implementering van die kode om uitbreiding te hanteer is bekend as ’n paar van die foute in die teoretiese model. Die volgende aanbevelings word gemaak: ’n meer gevorderde ontwerp van drukreëlaar moet in die eksperiment ingesluit word; die sekondêre lus se teoretiese model moet gekenmerk word onder ’n wyer stel bedryfsomstandighede, en die rekenaar program kan gebruik word as die basis vir verdere navorsing en die implementering van alternatiewe algoritmes en modelle.
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Bhatelia, Tejas Jagdish. "Novel reactors for multiphase processes." Curtin University of Technology, Science and Engineering, Department of Chemical Engineering, 2009. http://espace.library.curtin.edu.au:80/R/?func=dbin-jump-full&object_id=129027.

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Process intensification tools, such as the capillary reactor, offer several benefits to the chemical process industries due to the well-defined high specific interfacial area available for heat and mass transfer, which increases the transfer rates, and due to low inventories, they also enhance the safety of the process. This has provided motivation to investigate three such tools, namely the capillary microreactor, spinning disc and rotating tube reactors, in this study.
The gas-liquid slug flow capillary microreactor intensifies reactor performance through internal circulation caused by the shear between the continuous phase/wall surface and the slug axis, which enhances the diffusivity and consequently increases the reaction rates. However, integrating the complex hydrodynamics of this reactor with its chemical kinetics is a mathematically challenging task. Therefore, in this study, a simple-to-complex approach, using a set of state-of-the-art computational fluid dynamic tools, has been used. Firstly, simulations were performed without any chemical reaction to ascertain the extent of slug flow regime. The model also clearly captured the slug flow generation mechanism which can be used to structurally optimize the angle of entry in these reactors. Finally, the hydrodynamic model was also capable of estimating the pressure drop and slug lengths. After successfully simulating the hydrodynamics of the system, a reaction model was incorporated to study the chemical reaction kinetics. The results were compared with the published experimental work and were found to be in good agreement.
The spinning disc reactor utilizes the centrifugal and shear forces to generate thin liquid films characterized with intense interfering waves. This enables a very high heat transfer coefficients to be realized between the disc and liquid, as well as very high mass transfer between the liquid and the bulk gas phase. The waves formed also produce an intense local mixing with very little back mixing. This makes a spinning disc reactor an ideal contactor for multiphase processes. The focus of this study has been to elucidate the hydrodynamic behaviour of the liquid film flow over the horizontal spinning disc. Investigations were also performed to elaborate the local and overall hydrodynamic characteristics of a fully developed spinning disc reactor. Simulation results showed a continuous linear liquid film on the horizontal spinning disc and intense mixing performance in the annulus of the reactor around the disc surface. Finally, the film thickness data from the simulations were compared with the limited amount of data available for this novel process.
Rotating tube reactor also uses centrifugal forces to generate the liquid film and a high degree of mixing along with an improved control over the reactant retention times. In this work we have conducted a CFD analysis to understand the hydrodynamics of this new technology for future developments.
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Books on the topic "The reactor tube"

1

Canada, Atomic Energy of. Assessment of Beam Tube Performance For the Maple Research Reactor. S.l: s.n, 1985.

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Govindan, D. Numerical investigation of heat transfer in the vertical annulus between pressure tube and calandria tube of the advanced heavy water reactor. Mumbai: Bhabha Atomic Research Centre, 2008.

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Canada, Atomic Energy of. In-Reactor Deformation of A Pilgerred Cold-Worked zr-2.5 wt% nb Pressure Tube. S.l: s.n, 1985.

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Moyer, R. G. Reduction of pressure-tube/calandria-tube contact conductance. Pinawa, Man: Whiteshell Laboratories, 1992.

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Abouhadra, Dia Eddin Sadek. Serpentine tube characteristics under accident conditions in gas cooled reactors. Manchester: University of Manchester, 1997.

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Chatterjee, S. Estimation of fracture resistance curve of pressure tube from ring tension test. Mumbai, India: Bhabha Atomic Research Centre, 1999.

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Rummens, H. E. C. Experimental study of flow patterns near tube support structures. Chalk River, Ont: Chalk River Laboratories, 1994.

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Kumar, Sunil. Preferred orientation parameters of KAPS 2 Zr-2.5% Nb pressure tubes. Mumbai: Bhabha Atomic Research Centre, 2005.

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S, Chatterjee. Measurement and utility of fracture toughness properties of irradiated pressure tube from the ring tension test. Mumbai: Bhabha Atomic Research Centre, 2004.

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Stubbe, E. J. Assessment study of RELAP-5 MOD-2 cycle 36.01: Based on the Doel-2 steam generator tube rupture incident of June 1979. Washington, D.C: U.S. Nuclear Regulatory Commission, 1986.

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Book chapters on the topic "The reactor tube"

1

Shaffer, Peter T. B. "Rotary Tube Reactor Processes." In Carbide, Nitride and Boride Materials Synthesis and Processing, 159–68. Dordrecht: Springer Netherlands, 1997. http://dx.doi.org/10.1007/978-94-009-0071-4_7.

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Gemoets, Hannes P. L., Volker Hessel, and Timothy Noël. "Reactor Concepts for Aerobic Liquid phase Oxidation: Microreactors and Tube Reactors." In Liquid Phase Aerobic Oxidation Catalysis: Industrial Applications and Academic Perspectives, 397–419. Weinheim, Germany: Wiley-VCH Verlag GmbH & Co. KGaA, 2016. http://dx.doi.org/10.1002/9783527690121.ch23.

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Joshi, Keshava, N. Lokeshwari, G. Srinikethan, and M. B. Saidutta. "Denitrification Under Aerobic Condition in Draft Tube Spouted Bed Reactor." In Materials, Energy and Environment Engineering, 85–92. Singapore: Springer Singapore, 2017. http://dx.doi.org/10.1007/978-981-10-2675-1_10.

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Chen, Peishi, Lixiong Li, and Earnest F. Gloyna. "Simulation of a Concentric-Tube Reactor for Supercritical Water Oxidation." In Innovations in Supercritical Fluids, 348–63. Washington, DC: American Chemical Society, 1995. http://dx.doi.org/10.1021/bk-1995-0608.ch024.

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Joseph Winston, S., S. Sakthivel, Joel Jose, D. Jagadishan, P. Visweswaran, S. Murugan, G. Amarendra, and A. K. Bhaduri. "Prototype Fast Breeder Reactor Steam Generator Inspection System for Tube Inspections." In Lecture Notes in Mechanical Engineering, 713–28. Singapore: Springer Singapore, 2018. http://dx.doi.org/10.1007/978-981-10-8597-0_61.

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Wen-Teng, Wu, and Wu Jiumn-Yih. "Fed-Batch Culture in an Airlift Reactor with a Net Draft Tube." In Biochemical Engineering for 2001, 413–16. Tokyo: Springer Japan, 1992. http://dx.doi.org/10.1007/978-4-431-68180-9_109.

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Jacobsen, Sigrid E., and Charles E. Wyman. "Heat Transfer Considerations in Design of a Batch Tube Reactor for Biomass Hydrolysis." In Twenty-Second Symposium on Biotechnology for Fuels and Chemicals, 377–86. Totowa, NJ: Humana Press, 2001. http://dx.doi.org/10.1007/978-1-4612-0217-2_32.

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Lincoln, Roger, Geoffrey Wilkinson, R. A. Walton, and T. E. Wood. "Rhenium Pentachloride and Volatile Metal Chlorides by Direct Chlorination Using a Vertical-Tube Reactor." In Inorganic Syntheses, 41–43. Hoboken, NJ, USA: John Wiley & Sons, Inc., 2007. http://dx.doi.org/10.1002/9780470132517.ch11.

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Hampp, F., and I. Janajreh. "Development of a Drop Tube Reactor to Test and Assist a Sustainable Manufacturing Process." In Advances in Sustainable Manufacturing, 141–48. Berlin, Heidelberg: Springer Berlin Heidelberg, 2011. http://dx.doi.org/10.1007/978-3-642-20183-7_21.

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Velciu, L., T. Meleg, and M. Mihalache. "Study of the Hydride Morphology in the CANDU Reactor Pressure Tube Modified by Heat Treatment." In Materials and Technologies, 237–40. Stafa: Trans Tech Publications Ltd., 2007. http://dx.doi.org/10.4028/0-87849-460-x.237.

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Conference papers on the topic "The reactor tube"

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Kupferschmidt, W. C. H., R. B. Duffey, L. Leung, and R. Didsbury. "Advances in Pressure Tube Reactor Technology." In 18th International Conference on Nuclear Engineering. ASMEDC, 2010. http://dx.doi.org/10.1115/icone18-29878.

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We provide an update on recent advances in pressure tube reactor (PTR) technology as exemplified by progress in the continuous research and development path that has been defined. This includes numerous and fruitful strategic development partnerships, both nationally and internationally, to contribute to the major areas of technological innovation, economic competitiveness, energy security, sustainability and environmental stewardship. We discuss the major areas of advancement in R&D that utilize the inherent features and advantages of the unique PTR concepts of utilizing a low pressure, heavy water moderator with a modular channel construction.
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Hatamachi, T., T. Kodama, Y. Isobe, D. Nakano, and N. Goukon. "Double-Walled Reactor Tube With Molten Salt Thermal Storage for Solar Tubular Reformers." In ASME 2005 International Solar Energy Conference. ASMEDC, 2005. http://dx.doi.org/10.1115/isec2005-76184.

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This paper proposes a novel type of “double-walled” reactor tube with molten-salt thermal storage at high temperatures for use in solar tubular reformers. The prototype reactor tube is demonstrated on the heat-discharge and chemical reaction performances during cooling mode of the reactor tube at laboratory scale. The Na2CO3 composite material with MgO ceramics was filled into the outer annulus of the double-walled reactor tube while the Ru-based catalyst particles were filled into the inner tube. The heat discharge form the molten Na2CO3 circumvented the rapid temperature change of the catalyst bed, which resulted in the alleviation of decrease in chemical conversion during cooling mode of the reactor tube. The application of the new reactor tubes to solar tubular reformers is expected to help realize stable operation of the solar reforming process under fluctuating insolation during a cloud passage.
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Kodama, Tatsuya, Nobuyuki Gokon, Shin-ichi Inuta, Shin-go Yamashita, Tsuyoshi Hatamachi, and Taebeom Seo. "Molten-Salt Tubular Absorber/Reformer (MoSTAR) Project: Metal-Plate-Bridged Double Tube Reactor." In ASME 2009 3rd International Conference on Energy Sustainability collocated with the Heat Transfer and InterPACK09 Conferences. ASMEDC, 2009. http://dx.doi.org/10.1115/es2009-90230.

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The Molten-Salt Tubular Absorber/Reformer (MoSTAR) Project, which is jointly conducted by Niigata University, Japan, and Inha University, Korea, aims to develop a novel-type of “double-walled” tubular absorbers/reformers with molten-salt thermal storage at high temperature for use in solar natural-gas reforming and solar air receiver, and to demonstrate their performances on sun with a 5-kWt dish-type solar concentrator. The new concept of “double-walled” reactor tubes was proposed for use in a solar reformer by Niigata University, Japan, and involves packing a molten salt in the annular region between the internal catalyst tube and the exterior solar absorber tube of the double reactor tube. In this work, “metal-plate-bridged” double reactor tubes are newly proposed for use in a solar reformer. Two different sized reactor tubes are constructed, and tested on chemical reaction performance for dry reforming of methane during cooling or heat-discharge mode of the reactor tube using an electric furnace. The experimental results obtained under feed gas mixture of CH4/CO2 = 1:3 at a residence time of 0.36 s and at 1 atm showed that the double reactor tube with the heat storage medium Na2CO3 in the annular region successfully sustained a high methane conversion above 90% with about 0.7-kW output power of the reformed gas based on HHV for 40 min of the heat-discharge mode. The application of the new reactor tubes to solar tubular reformers is expected to help realize stable operation of the solar reforming process under fluctuating insolation during a cloud passage.
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Saltanov, Eugene, Wargha Peiman, Amjad Farah, Krysten King, Maria Naidin, and Igor Pioro. "Steam-Reheat Options for Pressure-Tube SCWRs." In 18th International Conference on Nuclear Engineering. ASMEDC, 2010. http://dx.doi.org/10.1115/icone18-29972.

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Concepts of nuclear reactors cooled with water at supercritical pressures were studied as early as the 1950s and 1960s in the USA and Russia. After a 40-year break, the idea of developing nuclear reactors cooled with SuperCritical Water (SCW) became attractive again as the ultimate development path for water cooling. The main objectives of using SCW in nuclear reactors are: 1) to increase the thermal efficiency of modern Nuclear Power Plants (NPPs) from 30–35% to about 45–48%, and 2) to decrease capital and operational costs and hence decrease electrical energy costs. SCW NPPs will have much higher operating parameters compared to modern NPPs (pressure about 25 MPa and outlet temperature up to 625°C), and a simplified flow circuit, in which steam generators, steam dryers, steam separators, etc., can be eliminated. Also, higher SCW temperatures allow direct thermo-chemical production of hydrogen at low cost, due to increased reaction rates. To achieve higher thermal efficiency Nuclear Steam Reheat (NSR) has to be introduced inside a reactor. Currently, all supercritical turbines at thermal power plants have a steam-reheat option. In the 60’s and 70’s, Russia, the USA and some other countries have developed and implemented the nuclear steam reheat at subcritical-pressure experimental boiling reactors. There are some papers, mainly published in the open Russian literature, devoted to this important experience. Pressure-tube or pressure-channel SCW nuclear reactor concepts are being developed in Canada and Russia for some time. It is obvious that implementation of the nuclear steam reheat at subcritical pressures in pressure-tube reactors is easier task than that in pressure-vessel reactors. Some design features related to the NSR are discussed in this paper. The main conclusion is that the development of SCW pressure-tube nuclear reactors with the nuclear steam reheat is feasible and significant benefits can be expected over other thermal-energy systems.
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Koido, Kenji, Kazuma Hirosaka, Takashi Kubo, Masato Fukayama, Kazuhiro Ouryouji, and Tatsuya Hasegawa. "Numerical Study on Hydrothermal Oxidation in a Tube Reactor." In 4th International Energy Conversion Engineering Conference and Exhibit (IECEC). Reston, Virigina: American Institute of Aeronautics and Astronautics, 2006. http://dx.doi.org/10.2514/6.2006-4156.

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Mikheev, Vladimir B. "Experimental nucleation studies with a laminar flow tube reactor." In The 15th international conference on nucleation and atmospheric aerosols. AIP, 2000. http://dx.doi.org/10.1063/1.1361812.

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Mikheev, Vladimir B. "Laminar Flow Tube Reactor interface with quadrupole mass spectrometer." In The 15th international conference on nucleation and atmospheric aerosols. AIP, 2000. http://dx.doi.org/10.1063/1.1361816.

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Haussener, Sophia, David Hirsch, Christopher Perkins, Alan Weimer, Allan Lewandowski, and Aldo Steinfeld. "Modeling of a Multi-Tube Solar Reactor for Hydrogen Production at High Temperatures." In ASME 2007 Energy Sustainability Conference. ASMEDC, 2007. http://dx.doi.org/10.1115/es2007-36245.

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The thermo chemical dissociation of zinc oxide is the first step in a two-step water splitting cycle to produce hydrogen. In previous work, the dissociation of zinc oxide has been investigated in a single-tube solar reactor that was enclosed in a sealed quartz tube and irradiated by concentrated sunlight. That reactor concept allowed the successful demonstration of the zinc oxide dissociation in the temperature range 1500–2100 K at the High-Flux Solar Furnace (HFSF) at NREL in Golden, CO. The current modeling work focuses on the further development and optimization of the previously tested reactor design. The commercial software FLUENT is used to run simulations in 2 and in 3 dimensions. The new design consists of a multitube configuration in a closed cavity with a small aperture. The inner cavity wall has a layer of a highly reflective material. Parametric simulation studies have been conducted in order to investigate the influence of parameters such as solar flux concentration, number of tubes, tube size, zinc oxide mass flow and particle size (0.06 and 1 micrometer) on the overall efficiency. Solar average flux concentrations of 3000 and 6000 suns have been chosen. The secondary concentrator currently used at NREL (∼2000 suns average flux) will have to be redesigned in order to achieve about 3000 suns average flux. Between 3 and 10 tubes that are circularly positioned in the cavity have been simulated. The zinc oxide mass flow ranges from 2–20 g/min per tube. In 2D, an energy sink equation is incorporated that accounts for the heating-up of the inert gas and the zinc oxide particles and for the heat of reaction. The heat of reaction is calculated using a set of Arrhenius-type kinetic parameters that were determined experimentally. The simulation results show that the flux concentration, the zinc oxide mass flow and the number of tubes have the most significant effect on the thermal efficiency of the reactor. Conclusions are: 1) A reaction efficiency (energy solely used by the chemical reaction divided by the solar input) of about 29% with a total efficiency of about 36% is achievable. 2) Complete conversion can be obtained at temperatures in the order of 2000 K. 3) In a design for NREL’s HFSF (∼8 kW solar input power) a total zinc oxide mass flow of about 30 g/min is optimal. 4) More and smaller tubes lead to higher efficiencies. In the coming months, a new reactor will be constructed and tested at NREL’s HFSF.
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Yadav, Ashwini K., Ravi Kumar, Akhilesh Gupta, P. Majumdhar, B. Chatterjee, and H. G. Lele. "An Experimental Investigation on the Behaviour of Pressure Tube Under Symmetrical and Asymmetrical Heating Conditions in an Indian PHWR." In ASME 2011 Small Modular Reactors Symposium. ASMEDC, 2011. http://dx.doi.org/10.1115/smr2011-6533.

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Thermal behavior of fuel channel under loss of coolant accident (LOCA) is a major concern for nuclear reactor safety. LOCA along with failure of emergency cooling water system (ECC) may leads to mechanical deformations like sagging, ballooning or even release of containment in open atmosphere due to breaching of pressure tube (PT) under certain depressurization and voiding rates. In order to understand the phenomenon an experiment has been carried out using 19 pin fuel element simulator. Main purpose of the experiment was to trace temperature profiles over the pressure tube, calandria tube and clad tubes of Indian Pressurized Heavy Water Reactor (IPHWR) under symmetrical and asymmetrical heat-up conditions. For simulating the fully voided scenario, symmetrical heating of pressure was carried out by injecting 13.2 KW (2% of nominal power) to all the 19 pins and the temperatures of pressure tube, calandria tube and clad tubes were measured. During symmetrical heating the sagging of fuel channel was initiated at 460 °C and the highest temperature attained by PT was 650 °C. The decay heat from clad tubes was dissipated to moderator mainly by radiation and natural convection. The highest temperature of 680 °C was observed over the outer ring of clad tubes of fuel simulator. Again, to simulate partially voided condition, asymmetrical heating of pressure was carried out by supplying 8.0 kW power to upper 8 pins of fuel simulator and temperature profiles were measured. Along the circumference of pressure tube (PT) the highest temperature difference of 320 °C was observed, which highlights the magnitude of thermal stresses and their role in breaching of pressure tube under partially voided conditions. However, the integrity of pressure tube was intact during both symmetrical and asymmetrical heat-up conditions.
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Doddihal, Preeti, Douglas Scarth, Paula Mosbrucker, and Steven Xu. "Fracture Protection of CANDU Zr-2.5Nb Pressure Tubes With High Hydrogen Equivalent Concentration." In ASME 2015 Pressure Vessels and Piping Conference. American Society of Mechanical Engineers, 2015. http://dx.doi.org/10.1115/pvp2015-46000.

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The core of a CANDU®1 (CANada Deuterium Uranium) pressurized heavy water reactor includes horizontal Zr-2.5Nb alloy pressure tubes that contain the fuel. Pressure-temperature limits are used in CANDU® reactors for normal operation heat-up and cool-down conditions to maintain margins against fracture. The pressure-temperature limits are determined by postulating a 20 mm long axial through-wall crack in the pressure tube and using a fracture toughness-based calculation procedure. Due to a corrosion reaction with the heavy water coolant, pressure tubes absorb deuterium isotope in service, resulting in an increase in hydrogen equivalent concentration. Experiments have shown that high hydrogen equivalent concentration reduces the fracture toughness of pressure tube material at low temperatures during reactor heat-up and cool-down from normal operating temperatures. New fracture toughness curves that are applicable to material with high hydrogen equivalent concentration have been developed to address this issue. These curves are being used to develop new pressure-temperature limits for fracture protection of CANDU® pressure tubes. The methodology for deriving the pressure-temperature limits for a CANDU® Zr-2.5Nb pressure tube using the new fracture toughness curves is presented in this paper. Preliminary results of pressure-temperature limits for a CANDU® reactor are also provided.
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Reports on the topic "The reactor tube"

1

Vaughn, P. The numerical simulation of forward combustion in a tube reactor using the Sunnyside resource. Office of Scientific and Technical Information (OSTI), February 1988. http://dx.doi.org/10.2172/6271502.

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Vaughn, P. Numerical simulation of the wet forward combustion of California tar sand in a tube reactor. Office of Scientific and Technical Information (OSTI), October 1988. http://dx.doi.org/10.2172/7110381.

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Raftery, Alicia M., Christian M. Petrie, Gregory John Hirtz, Yutai Katoh, and Kory D. Linton. Completion of the Irradiation of Silicon Carbide Cladding Tube Specimens in the High Flux Isotope Reactor. Office of Scientific and Technical Information (OSTI), May 2018. http://dx.doi.org/10.2172/1439144.

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Mertz, G. E., D. M. Barnes, and R. L. Sindelar. Savannah River reactor process water heat exchanger tube structural integrity margin Task Number 92-005-1. Office of Scientific and Technical Information (OSTI), February 1992. http://dx.doi.org/10.2172/7050599.

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Schulz, K. C., and G. T. Yahr. Preliminary fracture analysis of the core pressure boundary tube for the Advanced Neutron Source Research Reactor. Office of Scientific and Technical Information (OSTI), August 1995. http://dx.doi.org/10.2172/205046.

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Mertz, G. E., D. M. Barnes, and R. L. Sindelar. Savannah River reactor process water heat exchanger tube structural integrity margin Task Number 92-005-1. Office of Scientific and Technical Information (OSTI), February 1992. http://dx.doi.org/10.2172/10163889.

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Bartram, Phillip W., Michael J. Lochner, Dennis K. Rohrbaugh, and Michael W. Ellzy. Decomposition of GD on CeO2/Alumina Adsorbents in a Gas Chromatograph On-Column Injector Tube Reactor. Fort Belvoir, VA: Defense Technical Information Center, October 2006. http://dx.doi.org/10.21236/ada457384.

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Li, M., W. K. Soppet, and K. Natesan. Fatigue Behavior of Pressure Tube Material Zr-2.5Nb in Air and in Simulated CANDU-Reactor Water Environments. Office of Scientific and Technical Information (OSTI), May 2014. http://dx.doi.org/10.2172/1130739.

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Marland, S. Analyses of the reflector tank, cold source, and beam tube cooling for ANS reactor. [Advanced Neutron Source (ANS)]. Office of Scientific and Technical Information (OSTI), July 1992. http://dx.doi.org/10.2172/7112197.

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Koyanagi, Takaaki, and Christian M. Petrie. Assembly and Delivery of Rabbit Capsules for Irradiation of Silicon Carbide Cladding Tube Specimens in the High Flux Isotope Reactor. Office of Scientific and Technical Information (OSTI), September 2017. http://dx.doi.org/10.2172/1394375.

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