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Sample records for alumel

  1. Temperature Control System for Chromel-Alumel Thermocouple

    International Nuclear Information System (INIS)

    Piping Supriatna; Nurhanan; Riswan DJ; Heru K, B.; Edi Karyanta

    2003-01-01

    Nuclear Power Plan Operation Safety needs serious handling on temperature measurement and control. In this report has been done manufacturing Temperature Control System for Chromel-Alumel Thermocouple, accordance to material, equipment and human resource ability in the laboratory. Basic component for the Temperature Control System is LM-741 type of Operation Amplifier, which is functionalized as summer for voltage comparator. Function test for this Control System shown its ability for damping on temperature reference. The Temperature Control System will be implemented on PCB Processing Machine. (author)

  2. Analysis of Precursor Properties of mixed Al/Alumel Cylindrical Wire Arrays*

    Science.gov (United States)

    Stafford, A.; Safronova, A. S.; Kantsyrev, V. L.; Esaulov, A. A.; Weller, M. E.; Shrestha, I.; Osborne, G. C.; Shlyaptseva, V. V.; Keim, S. F.; Coverdale, C. A.; Chuvatin, A. S.

    2012-10-01

    Previous studies of mid-Z (Cu and Ni) cylindrical wire arrays (CWAs) on Zebra have found precursors with high electron temperatures of >300 eV. However, past experiments with Al CWAs did not find the same high temperature precursors. New precursor experiments using mixed Al/Alumel (Ni 95%, Si 2%, and Al 2%) cylindrical wire arrays have been performed to understand how the properties of L-shell Ni precursor will change and whether Al precursor will be observed. Time gated spectra and pinholes are used to determine precursor plasma conditions for comparison with previous Alumel precursor experiments. A full diagnostic set which included more than ten different beam-lines was implemented. Future work in this direction is discussed. [4pt] *This work was supported by NNSA under DOE Cooperative Agreements DE-FC52-06NA27588, and in part by DE-FC52-06NA27586, and DE-FC52-06NA27616. Sandia is a multi-program laboratory operated by Sandia Corporation, a Lockheed Martin Company, for the United States Department of Energy under Contract DE-AC04-94AL85000.

  3. Use of indexed sensitivity factors in the analysis of nickel and iron based alloys: study of the decalibration of sheathed Chromel/Alumel thermocouples

    International Nuclear Information System (INIS)

    Christie, W.H.

    1978-01-01

    Sheathed Chromel versus Alumel thermocouples decalibrate when exposed to temperatures in excess of 1100 0 C. Thermocouples sheathed in Inconel-600 and type 304 stainless steel were studied in this work. Quantified SIMS data showed that the observed decalibrations were due to significant alterations that took place in the Chromel and Alumel thermoelements. The amount of alteration was different for each thermocouple and was influenced by the particular sheath material used in the thermocouple construction. Relative sensitivity factors, indexed by a matrix ion species ratio, were used to quantify SIMS data for three nickel-based alloys, Chromel, Alumel, and Inconel-600, and an iron-based alloy, type 304 stainless steel. Oxygen pressure >2 x 10 -6 torr in the sputtering region gave enhanced sensitivity and superior quantitative results as compared to data obtained at instrumental residual pressure

  4. Ajuste empírico da curva de calibração do termopar Chromel-Alumel através de calçuladoras programáveis

    Directory of Open Access Journals (Sweden)

    Klemensas Rimgaudas Juraitis

    1982-11-01

    Full Text Available Computation of polynomial regression with precision is possible with some programmable calculators. In this paper, a program of a polynomial regression, using a Texas 77-59 pocket calculator, is presented in a didactic manner. The method is exemplified by means of fitting data of a curve of calibration for Chromel-Alumel thermocouple in the temperature range between CR c and J. 2009 C.Uma regressão polonomial pode ser utilizada com precisão, utilizando-se certas calculadoras programáveis. No presente trabalho apresenta-se, da maneira didática, um programa de regressão polinomial, usando-se uma calculadora programável Texas Tl-59, exemplificando-se o método através do ajuste de uma curva de calibração de um termopar Chromel-Alumel na faixa de temperatura de 0 a 1200 graus centígrados.

  5. Thermocouple evaluation model and evaluation of chromel--alumel thermocouples for High-Temperature Gas-Cooled Reactor applications

    International Nuclear Information System (INIS)

    Washburn, B.W.

    1977-03-01

    Factors affecting the performance and reliability of thermocouples for temperature measurements in High-Temperature Gas-Cooled Reactors are investigated. A model of an inhomogeneous thermocouple, associated experimental technique, and a method of predicting measurement errors are described. Error drifts for Type K materials are predicted and compared with published stability measurements. 60 references

  6. Comparative evaluation of corrosion behaviour of type K thin film thermocouple and its bulk counterpart

    International Nuclear Information System (INIS)

    Mukherjee, S.K.; Barhai, P.K.; Srikanth, S.

    2011-01-01

    Highlights: → Anodic vacuum arc deposited chromel and alumel films are more 'noble' in 5% NaCl solution than their respective wires. → Chromel undergoes localised corrosion while alumel shows uniform corrosion. → Virgin samples of chromel-alumel TFTCs exhibit good thermoelectric response. → Their thermoelectric outputs remain largely unaffected when shelved under normal atmospheric conditions. → After 288 h of exposure in salt spray environment, their thermoelectric outputs show noticeable change due to size effects. - Abstract: This paper investigates the corrosion behaviour of type K thermoelements and their thin films, and compares the performance of chromel-alumel thin film thermocouple with its wire counterpart before and after exposure to 5% NaCl medium. Potentiodynamic polarisation tests reveal that chromel and alumel films are more 'noble' than their respective wires. Alumel corrodes faster when coupled with chromel in films than as wires. Secondary electron micrographs and electrochemical impedance spectroscopy measurements suggest that chromel shows localised corrosion while alumel undergoes uniform corrosion. Corrosion adversely affects the thermocouple output and introduces an uncertainty in the measurement.

  7. Linear heating system for measurement of thermoluminescence ...

    Indian Academy of Sciences (India)

    Unknown

    through the terminal keyboard enters experimental vari- ables and ... chromel alumel thermocouple is spot welded on the bot- tom of the ... (BD136), which is implemented by designing the firing ... The use of a microcontroller, the process of.

  8. Temperature measurement error due to the effects of time varying magnetic fields on thermocouples with ferromagnetic thermoelements

    International Nuclear Information System (INIS)

    McDonald, D.W.

    1977-01-01

    Thermocouples with ferromagnetic thermoelements (iron, Alumel, Nisil) are used extensively in industry. We have observed the generation of voltage spikes within ferromagnetic wires when the wires are placed in an alternating magnetic field. This effect has implications for thermocouple thermometry, where it was first observed. For example, the voltage generated by this phenomenon will contaminate the thermocouple thermal emf, resulting in temperature measurement error

  9. Calorimeter measures high nuclear heating rates and their gradients across a reactor test hole

    Science.gov (United States)

    Burwell, D.; Coombe, J. R.; Mc Bride, J.

    1970-01-01

    Pedestal-type calorimeter measures gamma-ray heating rates from 0.5 to 7.0 watts per gram of aluminum. Nuclear heating rate is a function of cylinder temperature change, measured by four chromel-alumel thermocouples attached to the calorimeter, and known thermoconductivity of the tested material.

  10. Temperature measurements at the LMFBR core outlet

    International Nuclear Information System (INIS)

    Argous, J.P.; Berger, R.; Casejuane, R.; Fournier, C.; Girard, J.P.

    1980-04-01

    Over the last few years the temperature sensors used to measure the subassembly outlet temperature in French designed LMFBRs have been modified, basically in an effort to reduce the dispersion of the chromel-alumel thermocouple time constant, and to extend the frequency spectrum of the measurement signals by adding a steel electrode to from a stainless steel-sodium thermocouple. The result of this evolution is the temperature probe immersed in sodium which will be used in the SUPER PHENIX reactor. This paper describes the tests already completed or in progress on this probe. It also presents measurement data on the two basic probe parameters: the thermoelectric power of the stainless steel-sodium thermocouple and the time constant of the chromel-alumel thermocouple

  11. THERMAL FATIGUE OF INCONEL ALLOY DA718

    Science.gov (United States)

    2016-10-27

    this material meets the required improvement and offers a low cost alternative to powder metallurgy Rene’95. However, its thermal fatigue resistance...chromel-alumel thermocouple, spot- welded to the mid-length of the specimen. The thermal strain, induced by the expansion and contraction of the...12 FOR OFFICIAL USE ONLY 13. J. F. Radavich, “The Physical Metallurgy of Cast and Wrought Alloy 718,” in Superalloy 718 – Metallurgy and

  12. Improved Nozzle Testing Techniques in Transonic Flow

    Science.gov (United States)

    1975-10-01

    axiale) et comporte un barreau dynamometrique equips de jauges de contrainte. La canne est solidaire d’un ensemble balance-bloc d’alimentation des...s a l’aide de capteurs produisant un signal ilectrique : Pressions : capteurs ä jauges Temperatures : thermocouples Chromel-Alumel - Efforts...barreau dynamometrique a jauges de contrainte. Les signaux eiectriques sont acquis et traites par la chaine automatique de la soufflerie. Les mesures

  13. The T.M. Calorimeter

    International Nuclear Information System (INIS)

    Mas, P.; Goer, J. de

    1970-01-01

    The T.M. calorimeter is the isothermal type. It consists only of a sample of graphite and a jacket of stainless steel filled with nitrogen. The chromel-alumel thermocouples which measure the temperature difference between the sample and the jacket also serve to suspend the sample. The jacket is kept at a constant temperature: i.e. that of the water in the swimming pool

  14. Solid State Research

    Science.gov (United States)

    1975-04-17

    D = n — n is the dispersion , and B = n — n is the birefringence. Differentiation of Eq. (II-l) gives 60j = | tan9j...than the measured value; therefore, the change in bi- refringence must be canceled partially by a change in dispersion . The type I room...chromel-alumel ther- mocouple that was mounted on the substrate surface with kaolin -sodium silicate paste and pro- tected from RF interference by

  15. Electronic control system for irradiation probes

    International Nuclear Information System (INIS)

    Gluza, E.; Neumann, J.; Zahalka, F.

    1980-01-01

    The EROS-78 system for the supply and power control of six heating sections of the irradiation probe of the CHOUCA type placed in the reactor vessel is described. The system allows temperature control at the location of the heat sensor with an accuracy of +-1% of the rated value within the region of 100 to 1000 degC. The equipment is provided with its own quartz controlled clock. The temperature is picked up by a chromel-alumel jacket thermocouple. The power input of the heating elements is thyristor controlled. (J.B.)

  16. Low pressure lithium condensation

    International Nuclear Information System (INIS)

    Wadkins, R.P.; Oh, C.H.

    1985-01-01

    A low pressure experiment to evaluate the laminar film condensation coefficients of lithium was conducted. Some thirty-six different heat transfer tests were made at system pressures ranging from 1.3 to 26 Pa. Boiled lithium was condensed on the inside of a 7.6-cm (ID), 409 stainless-steel pipe. Condensed lithium was allowed to reflux back to the pool boiling region below the condensing section. Fourteen chromel/alumel thermocouples were attached in various regions of the condensing section. The thermocouples were initially calibrated with errors of less than one degree Celsius

  17. Operating problems of the thermocouples in VVER

    International Nuclear Information System (INIS)

    Timonin, A.S.

    1997-01-01

    In WWER reactors, the coolant temperature at the outlet of the majority of fuel assemblies is measured with chromel-alumel cable thermocouples. The components of systematic errors in temperature measurements are discussed. Errors due to calibration drift can be avoided by periodical calibrations performed during the heating and hot test runs after reactor refueling. Errors due to radiation heating and response time can be estimated and thus eliminated. Errors due to flow stratification of the coolant can also be eliminated by an estimation of correction factors. The effects of the aging of the thermocouples are also discussed. The removal of thermocouples from their coverings for replacement presents some difficulties, which thus determine the service life of the thermocouples. (A.K.)

  18. Postirradiation thermal analysis of capsule P13T

    International Nuclear Information System (INIS)

    Ketterer, J.W.

    1978-12-01

    In determining fuel rod temperature histories for the P13T capsule, a technique which combined measured temperature and dimensional data, TAC-2D computer modeling, and a calculational procedure was employed. TAC-2D models were constructed for each of the capsule's four fuel bodies and temperature matching runs were made at five time points of the irradiation history. The agreement between TAC-calculated and measured temperatures was good; at all times the TAC-calculated temperatures were within 20 0 C of the Chromel-Alumel (C/A) measurements and 40 0 C of the corrected tungsten-rhenium (W/Re) temperatures. Thermocouple decalibration was treated in detail and corrected temperatures for all W/Re thermocouples were calculated over the irradiation period

  19. Radiation sensor

    International Nuclear Information System (INIS)

    Brown, W.L.; Geronime, R.L.

    1977-01-01

    Radiation sensor and thermocouple, respectively, which can be used for reactor in-core instrumentation. The radiation sensor consists of an inconel conductor wire and rhodium emitter wire, the thermocouple of two intertwined alumel or chromel wires. Both are arranged in the center of a metal tube relative to which they are separated by an insulator made of SiO 2 fibers. This insulator is first introduced as a loose fabric between the radiation sensor and the thermocouple, respectively, and the metal tube and then compacted to a density of 35-73% of pure SiO 2 by drawing the tube. There is no need for soldering or welding. The insulation resistivity at room temperature ist between 10 14 and 10 15 ohms. (ORU) [de

  20. Measurement of droplet dynamics across grid spacer in mist cooling of subchannel of PWR

    International Nuclear Information System (INIS)

    Lee, S.L.; Sheen, H.J.; Cho, S.K.; Issapour, I.

    1984-01-01

    An experiment was conducted of the dynamics and heat transfer of a droplet-vapor mist flow across a test grid spacer in a flow channel of 2 x 2 electrically heated simulation fuel rods. Embedded thermocouples were used to measure the rod cladding temperature and an unshielded Chromel-Alumel thermocouple was transversed in the center of the subchannel to measure the temperature of the water and steam coolant phases at various axial locations. Thermocouples were also embedded in the test grid spacer. Optical measurements of the size and velocity distributions of droplets and the velocity distribution of the superheated steam were made by special laser-Doppler anemometry techniques through quartz glass windows immediately upstream and downstream of the test grid spacer. Experiments over a range of steam and injected water flow rates and rod heat flux have been performed and some representative results and discussions are presented

  1. Measurement of grid spacer's enhanced droplet cooling under reflood condition in a PWR by LDA

    International Nuclear Information System (INIS)

    Lee, S.L.; Sheen, H.J.; Cho, S.K.; Issapour, I.; Hua, S.Q.

    1984-01-01

    Reported is an experiment designed for the measurements of grid spacer's enhanced droplet cooling under reflood condition at elevated temperatures in a steam environment. The flow channel consists of a simulated 1.60m-long pressurized water reactor (PWR) fuel rod bundle of 2 x 2 electrically heated rods. Embedded thermocouples are used to measure the rod cladding temperature at various axial levels and an unshielded Chromel-Alumel thermocouple sheathed by a small Inconel tube is traversed in the center of the subchannel to measure the temperatures of the water and steam coolant phases at various levels. The droplet dynamics across the grid spacer is directly obtained by a special laser-Doppler anemometry technique for the in situ simultaneous measurement of velocity and size of droplets through two observation windows on the test channel, one immediately before and one immediately after the grid spacer. Some results are presented and analyzed

  2. Electrical resistivity measurements in superconducting ceramics

    International Nuclear Information System (INIS)

    Muccillo, R.; Bressiani, A.H.A.; Muccillo, E.N.S.; Bressiani, J.C.

    1988-01-01

    Electrical resistivity measurements have been done in (Y, Ba, Cu, O) - and (Y, A1, Ba, Cu, O) - based superconducting ceramics. The sintered specimens were prepared by applying gold electrodes and winding on the non-metalized part with a copper strip to be immersed in liquid nitrogen for cooling. The resistivity measurements have been done by the four-probe method. A copper-constantan or chromel-alumel thermocouple inserted between the specimen and the copper cold finger has been used for the determination of the critical temperature T c . Details of the experimental set-up and resistivity versus temperature plots in the LNT-RT range for the superconducting ceramics are the major contributions of this communication. (author) [pt

  3. Electrical resistivity measurements in superconducting ceramics

    International Nuclear Information System (INIS)

    Muccillo, R.; Bressiani, A.H.A.; Muccillo, E.N.S.; Bressian, J.C.

    1988-01-01

    Electrical resistivity measurements have been done in (Y,Ba,Cu,O)- and (Y,Al,Ba,Cu,O)-based superconducting ceramics. The sintered specimens were prepared by applying gold electrodes and winding on the non-metalized part with a copper strip to be immersed in liquid nitrogen for cooling. The resistivity measurements have been done by the four-probe method. A copper constantan or chromel-alumel thermocouple inserted between the specimen and the copper cold finger has been used for the determination of the critical temperature T c . Details of the experimental set-up and resistivity versus temperature plots in the LNT-RT range for the superconducting ceramics are the major contributions of this communication. (author) [pt

  4. Ion thermometers in reactor technology

    International Nuclear Information System (INIS)

    Yakesh, D.; Kott, J.; Strnad, M.

    1980-01-01

    The width of the temperature discontinuity and the thermometric stability of the sensors are constant up to very high flux values. The immediate influence of irradiation is reduced to a decrease in the hysteresis of the conduction curve at the phase transition. When the readings of the ion thermometers are compared with the reading of Chromel-Alumel thermocouples, it is observed that the temperature difference amounts to approximately 7/degree/C in the case of thermocouples placed at the sensor socket; the temperature difference decreases to 2/degree/C in the case of the thermocouple junction situated between the electrodes. The good results obtained in the testing of the ion thermometers in nuclear reactors lead to the conclusion that these temperature sensors are promising for checking thermocouples in the core of nuclear power stations

  5. The use of thermocouples which transmute during service in nuclear reactors

    International Nuclear Information System (INIS)

    Martin, R.E.

    1980-06-01

    Some current nuclear fuel experiments at CRNL require the use of thermocouples to measure temperatures of up to 2200 0 C under reactor operating conditions. A literature search has shown that transient electrical effects and transmutation of the thermocouple alloys can cause temperature measurement errors of up to +-1% and +-30%, respectively. However, the error due to transient electrical effects can be corrected by making temperature measurements immediately following reactor shutdown. Furthermore it has been shown that transmutation effects can be corrected for by calibrating the high temperature tungsten-rhenium thermocouples against a chromel-alumel thermocouple in a cooler part of the experiment. The use of these techniques is expected to reduce temperature measurement errors to +-2% in the best case. (auth)

  6. Harwell Graphite Calorimeter

    International Nuclear Information System (INIS)

    Linacre, J.K.

    1970-01-01

    The calorimeter is of the steady state temperature difference type. It contains a graphite sample supported axially in a graphite outer jacket, the assembly being contained in a thin stainless steel outer can. The temperature of the jacket and the temperature difference between sample and jacket are measured by chromel-alumel thermocouples. The instrument is calibrated by means of an electric heater of low mass positioned on the axis of the sample. The resistance of the heater is known and both current through the heater and the potential across it may be measured. The instrument is filled with nitrogen at a pressure of one half atmosphere at room temperature. The calorimeter has been designed for prolonged operation at temperatures up to 600°C, and dose rates up to 1 Wg -1 , and instruments have been in use for periods in excess of one year

  7. Approach to the HTGR core outlet temperature measurements in the United States

    International Nuclear Information System (INIS)

    Franklin, R.; Rodriguez, C.

    1982-06-01

    The High Temperature Gas-Cooled Reactor (HTGR) constructed at Fort St. Vrain Colorado (330 MWe) used Geminol thermocouples to measure the primary coolant temperature at the core outlet. The primary coolant (helium) is heated by the graphite core to temperatures in the range of 700 deg. to 750 deg. C. The combination of the high temperature, high flow rate and radiation at the core outlet area makes it difficult to obtain accurate temperature measurements. The Geminol thermocouples installed in the Fort St. Vrain reactor have provided accurate data for several years of power operation without any failures. The indicated temperature of the core outlet thermocouples agrees with a ''traversing'' thermocouple measurement to within +-2 deg. C. The Geminol thermocouple wire was provided by the Driver-Harris Company and is similar to the chromel versus alumel thermocouple. Geminol wire is no longer distributed and on future designs, chromel versus alumel wire will be used. The next large HTGR design, which is being performed with funding support from the United States Department of Energy, will incorporate replaceable thermocouples. The thermocouples used in the Fort St. Vrain reactor were permanently installed and large in diameter (6.35 mm) to insure good reliability. The replaceable thermocouples to be used in the next large reactor will be smaller in diameter (3.18 mm). These replaceable thermocouples will be inserted into the core outlet area through long curved guide tubes that are permanently installed. These guide tubes are as long as 18 meters and must be curved to reach the core outlet regions. Tests were conducted to prove that the thermocouples could be inserted and removed through the long curved guide tubes. (author)

  8. Some problems on materials tests in high temperature hydrogen base gas mixture

    International Nuclear Information System (INIS)

    Shikama, Tatsuo; Tanabe, Tatsuhiko; Fujitsuka, Masakazu; Yoshida, Heitaro; Watanabe, Ryoji

    1980-01-01

    Some problems have been examined on materials tests (creep rupture tests and corrosion tests) in high temperature mixture gas of hydrogen (80%H 2 + 15%CO + 5%CO 2 ) simulating the reducing gas for direct steel making. H 2 , CO, CO 2 and CH 4 in the reducing gas interact with each other at elevated temperature and produce water vapor (H 2 O) and carbon (soot). Carbon deposited on the walls of retorts and the water condensed at pipings of the lower temperature gas outlet causes blocking of gas flow. The gas reactions have been found to be catalyzed by the retort walls, and appropriate selection of the materials for retorts has been found to mitigate the problems caused by water condensation and carbon deposition. Quartz has been recognized to be one of the most promising materials for minimizing the gas reactions. And ceramic coating, namely, BN (born nitride) on the heat resistant superalloy, MO-RE II, has reduced the amounts of water vapor and deposited carbon (sooting) produced by gas reactions and has kept dew points of outlet gas below room temperature. The well known emf (thermo-electromotive force) deterioration of Alumel-Chromel thermocouples in the reducing gases at elevated temperatures has been also found to be prevented by the ceramic (BN) coating. (author)

  9. Analysis of SONACO axial cooling experiments

    International Nuclear Information System (INIS)

    Sigg, B.; Dury, T.V.; Hudina, M.

    1994-01-01

    The SONACO test rig contained a sodium-cooled, electrically heated 37-pin bundle. On this rig, a series of forced, mixed and natural convection experiments have been performed with the aim of contributing to the understanding of thermal-hydraulic phenomena and providing data for code validation for a subassembly at decay heat power level with low flow or stagnant coolant. The test section and especially the heater pins were equipped with an extensive number of chromel-alumel thermocouples. In addition, special permanent-magnet probes were used for measuring local velocities. In this paper we give a survey of results from axial cooling experiments, where heat was removed by natural convection to a cooling coil situated in the coolant channel (plenum) above the bundle. The experimental conditions led to turbulent convection with a slowly varying, large scale flow pattern. It is shown that a power tilt in the bundle reduces these fluctuations but does not eliminate them. For the uniformly heated bundle, aglebraic expressions for the average turbulent heat flux as well as for temperature and velocity fluctuations are derived from a second-moments model and compared with experimental data. Furthermore, heat transfer in the plenum and the consequences of the SONACO experiments for the coolability of reactor fuel elements under loss-of-flow conditions are discussed. ((orig.))

  10. Analysis of X-ray iron and nickel radiation and jets from planar wire arrays and X-pinches

    International Nuclear Information System (INIS)

    Safronova, A S; Kantsyrev, V L; Esaulov, A A; Ouart, N D; Shlyaptseva, V; Williamson, K M; Shrestha, I; Osborne, G C; Weller, M E

    2010-01-01

    University-scale Z-pinch devices are able to produce plasmas with a broad range of sizes, temperatures, densities, their gradients, and opacity properties. Radiative properties of such plasmas depend on material, mass, and configuration of the wire array loads. Experiments with two different types of loads, double planar wire arrays (DPWA) and X-pinches, performed on the 1 MA Zebra generator at UNR are analyzed. X-pinches are made from Stainless Steel (69% Fe, 20% Cr, and 9% Ni) wires. Combined DPWAs consist of one plane from SS wires and another plane from Alumel (95% Ni, 2% Al, 2% Si) wires. The main focus of this work is on the analysis of plasma jets at the early phase of plasma formation and the K-and L-shell radiation generation at the implosion and stagnation phases in experiments with the two aforementioned wire loads. The relevant theoretical tools that guide the data analysis include non-LTE collisional-radiative and wire ablation dynamics models. The astrophysical relevance of the plasma jets as well as of spectroscopic and imaging studies are demonstrated.

  11. Ion sensors in reactor technology

    International Nuclear Information System (INIS)

    Strnad, M.; Kott, J.

    1977-01-01

    A new temperature measurement technique is shown based on the steep phase transformation of some substances accompanied with a marked change in their electric conductivity. A survey is given of the physicochemical properties of some ion crystals and the problems are discussed of interpreting the steep changes in the crystal electric conductivity for ion thermometers. Technological problems are also discussed of ion sensor production for reactor technology applications. The CdI 2 , KIO 3 , K 2 Cr 2 O 7 thermometric compounds were used sealed in the Supermax silicon-aluminium glass or in silica glass with platinum bushings. Changes are described in the hysteresis effects of ion thermometers with CdI 2 , KIO 3 and K 2 Cr 2 O 7 in dependence on neutron irradiation with doses of 1.5x10 18 n.cm -2 , 8.5x10 17 n.cm -2 and 4.5x10 22 n.cm -2 , respectively. The thermometric parameters were compared in the radiation experiments, of ion sensors, Chromel-Alumel thermocouples and platinum resistance thermometers. (B.S.)

  12. Determination of the duration of heating and cooling of titanium alloy billets for swaging

    International Nuclear Information System (INIS)

    Kushakevich, S.A.; Konovalov, M.A.; Chistyakov, N.I.

    1978-01-01

    An attempt was made to establish a connection between the duration of heat and the decrease in metal temperature during deformation to determine the beginning and duration of heating titanium alloy billets for hot stamping. The investigations were made on the VT3-1 alloy billets with chromel-alumel thermocouples inside. The results of measurements of billet surface and center temperatures during the heating in a resistance surface up to 960-1050deg C and during the cooling in the air. It is shown that heating and cooling increase with the billet cross-section. The heating duration up to 1050deg C for all cross-sections is 4 or 5 min less than up to 960deg C. The cooling duration from 960 and 1050deg C to 200deg C depends weakly on the heating temperature and varies for various cross-sections within the limits of 1-2 min. It is proposed to determine roughly the metal temperature on complection of stamping through the time elapsed after the heated billet has left the furnace

  13. Thermocouple Errors when Mounted on Cylindrical Surfaces in Abnormal Thermal Environments.

    Energy Technology Data Exchange (ETDEWEB)

    Nakos, James T. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Suo-Anttila, Jill M. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Zepper, Ethan T. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Koenig, Jerry J [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Valdez, Vincent A. [ECI Inc., Albuquerque, NM (United States)

    2017-05-01

    Mineral-insulated, metal-sheathed, Type-K thermocouples are used to measure the temperature of various items in high-temperature environments, often exceeding 1000degC (1273 K). The thermocouple wires (chromel and alumel) are protected from the harsh environments by an Inconel sheath and magnesium oxide (MgO) insulation. The sheath and insulation are required for reliable measurements. Due to the sheath and MgO insulation, the temperature registered by the thermocouple is not the temperature of the surface of interest. In some cases, the error incurred is large enough to be of concern because these data are used for model validation, and thus the uncertainties of the data need to be well documented. This report documents the error using 0.062" and 0.040" diameter Inconel sheathed, Type-K thermocouples mounted on cylindrical surfaces (inside of a shroud, outside and inside of a mock test unit). After an initial transient, the thermocouple bias errors typically range only about +-1-2% of the reading in K. After all of the uncertainty sources have been included, the total uncertainty to 95% confidence, for shroud or test unit TCs in abnormal thermal environments, is about +-2% of the reading in K, lower than the +-3% typically used for flat shrouds. Recommendations are provided in Section 6 to facilitate interpretation and use of the results. .

  14. The transient response for different types of erodable surface thermocouples using finite element analysis

    Directory of Open Access Journals (Sweden)

    Mohammed Hussein

    2007-01-01

    Full Text Available The transient response of erodable surface thermocouples has been numerically assessed by using a two dimensional finite element analysis. Four types of base metal erodable surface thermocouples have been examined in this study, included type-K (alumel-chromel, type-E (chromel-constantan, type-T (copper-constantan, and type-J (iron-constantan with 50 mm thick- ness for each. The practical importance of these types of thermocouples is to be used in internal combustion engine studies and aerodynamics experiments. The step heat flux was applied at the surface of the thermocouple model. The heat flux from the measurements of the surface temperature can be commonly identified by assuming that the heat transfer within these devices is one-dimensional. The surface temperature histories at different positions along the thermocouple are presented. The normalized surface temperature histories at the center of the thermocouple for different types at different response time are also depicted. The thermocouple response to different heat flux variations were considered by using a square heat flux with 2 ms width, a sinusoidal surface heat flux variation width 10 ms period and repeated heat flux variation with 2 ms width. The present results demonstrate that the two dimensional transient heat conduction effects have a significant influence on the surface temperature history measurements made with these devices. It was observed that the surface temperature history and the transient response for thermocouple type-E are higher than that for other types due to the thermal properties of this thermocouple. It was concluded that the thermal properties of the surrounding material do have an impact, but the properties of the thermocouple and the insulation materials also make an important contribution to the net response.

  15. Correlation between metal-ceramic bond strength and coefficient of linear thermal expansion difference

    Directory of Open Access Journals (Sweden)

    Stella Crosara Lopes

    2009-04-01

    Full Text Available The purpose of this study was to evaluate the metal-ceramic bond strength (MCBS of 6 metal-ceramic pairs (2 Ni-Cr alloys and 1 Pd-Ag alloy with 2 dental ceramics and correlate the MCBS values with the differences between the coefficients of linear thermal expansion (CTEs of the metals and ceramics. Verabond (VB Ni-Cr-Be alloy, Verabond II (VB2, Ni-Cr alloy, Pors-on 4 (P, Pd-Ag alloy, and IPS (I and Duceram (D ceramics were used for the MCBS test and dilatometric test. Forty-eight ceramic rings were built around metallic rods (3.0 mm in diameter and 70.0 mm in length made from the evaluated alloys. The rods were subsequently embedded in gypsum cast in order to perform a tensile load test, which enabled calculating the CMBS. Five specimens (2.0 mm in diameter and 12.0 mm in length of each material were made for the dilatometric test. The chromel-alumel thermocouple required for the test was welded into the metal test specimens and inserted into the ceramics. ANOVA and Tukey's test revealed significant differences (p=0.01 for the MCBS test results (MPa, with PI showing higher MCBS (67.72 than the other pairs, which did not present any significant differences. The CTE (10-6 oC-1 differences were: VBI (0.54, VBD (1.33, VB2I (-0.14, VB2D (0.63, PI (1.84 and PD (2.62. Pearson's correlation test (r=0.17 was performed to evaluate of correlation between MCBS and CTE differences. Within the limitations of this study and based on the obtained results, there was no correlation between MCBS and CTE differences for the evaluated metal-ceramic pairs.

  16. Correlation between metal-ceramic bond strength and coefficient of linear thermal expansion difference.

    Science.gov (United States)

    Lopes, Stella Crosara; Pagnano, Valéria Oliveira; Rollo, João Manuel Domingos de Almeida; Leal, Mônica Barbosa; Bezzon, Osvaldo Luiz

    2009-01-01

    The purpose of this study was to evaluate the metal-ceramic bond strength (MCBS) of 6 metal-ceramic pairs (2 Ni-Cr alloys and 1 Pd-Ag alloy with 2 dental ceramics) and correlate the MCBS values with the differences between the coefficients of linear thermal expansion (CTEs) of the metals and ceramics. Verabond (VB) Ni-Cr-Be alloy, Verabond II (VB2), Ni-Cr alloy, Pors-on 4 (P), Pd-Ag alloy, and IPS (I) and Duceram (D) ceramics were used for the MCBS test and dilatometric test. Forty-eight ceramic rings were built around metallic rods (3.0 mm in diameter and 70.0 mm in length) made from the evaluated alloys. The rods were subsequently embedded in gypsum cast in order to perform a tensile load test, which enabled calculating the CMBS. Five specimens (2.0 mm in diameter and 12.0 mm in length) of each material were made for the dilatometric test. The chromel-alumel thermocouple required for the test was welded into the metal test specimens and inserted into the ceramics. ANOVA and Tukey's test revealed significant differences (p=0.01) for the MCBS test results (MPa), with PI showing higher MCBS (67.72) than the other pairs, which did not present any significant differences. The CTE (10(-6) oC(-1)) differences were: VBI (0.54), VBD (1.33), VB2I (-0.14), VB2D (0.63), PI (1.84) and PD (2.62). Pearson's correlation test (r=0.17) was performed to evaluate of correlation between MCBS and CTE differences. Within the limitations of this study and based on the obtained results, there was no correlation between MCBS and CTE differences for the evaluated metal-ceramic pairs.

  17. A Study of the Behavior Characteristics for K-type Thermocouple

    International Nuclear Information System (INIS)

    Ye, Songhae; Kim, Yongsik; Lee, Sooill; Kim, Sungjin; Lyou, Jooon

    2014-01-01

    K-type thermocouple is widely used in nuclear power plants (NPP) and they provide reliable service. Generally, the thermocouple assembly is the finished product and usually only nondestructive tests are performed on the assembly, whereas destructive tests are confined to selected bulk cable specimens. This K-type thermocouple has been used representatively in the In-Core Instrument Assembly (ICI) in the nuclear power plants. The ICI consists of five rhodium emitter detectors that provide information on the thermal power for the core and one K-type thermocouple made with two cables (Chromel-Alumel) that provides the temperature of core exit (CET). Generally, the quantity of the ICI is absolutely different according to the number of fuel assemblies in the NPP. In the case of SKN 3 and 4, they were designed to the 61 ICI to provide information on the core cooling to the inadequate core cooling monitoring system (ICCMS). This measured temperature could be also used to check the entry condition of severe accidents. The technology of the TFDR is a generic skill to detect the fault position of the cable. In-core Instruments (ICIs) were used to detect the Core Exit Temperature (CET) in a reactor. This measured temperature was also used to check the entry condition of severe accidents. However, if a serious accident occurs, the upper portion of the core is damaged. This instrument has not been available. This paper illustrates the estimation possibility for the status of molten core through the high-temperature characteristics test of k-type thermocouple. It turns out that it is possible to measure the k-type thermocouple up to 1350 .deg. C degrees before melting during insertion into the melting furnace. Additionally, in order to measure a high temperature of 2000 .deg. C or more, the replacement possibility of k-type thermocouple was evaluated. However the tungsten-rhenium thermocouple is impossible to use in the detection of temperature at the in-core because of the

  18. MONITORAMENTO DA TEMPERATURA NO INTERIOR DE CHAPAS AGLOMERADAS DURANTE O PROCESSO DE PRENSAGEM

    Directory of Open Access Journals (Sweden)

    Elio José Santini

    2005-03-01

    Full Text Available O objetivo do presente trabalho foi analisar o comportamento da temperatura nas faces e no miolo de chapas de partículas aglomeradas, coladas com 8% de adesivo (base peso seco das partículas tanino-formaldeído. As chapas foram produzidas com três repetições por tratamento, com massa específica nominal de 0,7 g/cm³ e pressão específica de prensagem de 27 kgf/cm². Os tratamentos basearam-se na utilização de flocos de pinus (Pinus elliottii e partículas de eucalipto (Eucalytus sp, sendo que os flocos de pinus apresentavam três diferentes comprimentos nominais (40, 75 e 110 mm e duas espessuras (0,5 e 1,0 mm. Também foram analisados duas temperaturas de prensagem (140 e 180°C e dois teores de umidade nominal do colchão (17 e 21%. A temperatura no interior dos painéis durante a prensagem foi obtida por meio de fios para termopares tipo K (cromo-alumel. Os gráficos da temperatura em função do tempo de prensagem mostraram uma rápida elevação da temperatura nos primeiros 100 segundos de prensagem, mantendo-se num plateau possivelmente após atingir a temperatura de ebulição da água. A temperatura voltou a aumentar, de forma mais gradual, após a perda de grande parte da umidade do colchão. Observa-se que colchões formados por flocos de maior espessura apresentaram elevação mais rápida de temperatura no miolo. O principal fator que influenciou na velocidade de elevação da temperatura no miolo dos painéis aglomerados foi o teor de umidade do colchão, sendo que quanto maior o teor de umidade, mais rápida foi a elevação da temperatura.

  19. INFLUENCE OF STRUCTURAL PARAMETERS OF LOW-CARBON STEEL ON ELECTRIC ARC BURNING

    Directory of Open Access Journals (Sweden)

    I. O. Vakulenko

    2017-10-01

    Full Text Available Purpose. The article is aimed to evaluate the influence of structural parameters of low-carbon steel on arcing process. Methodology. The values of the micro- and substructure characteristics of the electrode wire metal were changed by varying the parameters of heat treatment and cold deformation by drawing. The degree of plastic deformation was obtained by drawing blanks from different initial diameter to final dimension of 1 mm. The thermal treatment was carried out in electric chamber furnace of the SNOL-1,6.2,5.1/11-IZ type. The temperature was measured by chromel-alumel thermocouple and the electromotive force was determined using the DC potentiometer. In order to obtain the substructure of different dispersion degree the steel (after quenching from temperatures and tempering at 650°C for 1 hour was subjected to cold drawing to reduction 17 – 80%. To form structure with different ferrite grain size the steel after drawing was annealed at 680°C for 1 hour. The microstructure was examined under a light and electron transmission microscope UEMV-100K at the accelerating voltage 100 kV. The grain and subgrain sizes were evaluated using the methodologies of quantitative metallography. A welding converter of the PSG-500 type was used to study the arc welding process of direct and reverse polarities. Findings. The experimentally detected value of the welding current, which depends on the degree of deformation during wire drawing, under conditions of stable arc burning of direct polarity is about an order of magnitude lower than the calculated value. Similar difference was found for the arc of reverse polarity: the experimental value of the welding current is 5...6 times less than the calculated value. Dependence analysis shows that, regardless of the polarity of the welding arc, a good enough agreement between the calculated and experimental values of the welding current is limited to deformations of 60%. For deformation degrees of more than 60

  20. Medida de las temperaturas de un horno artesanal de Mórrope, departamento de Lambayeque, utilizado para la fabricación tradicional de alfarería

    Directory of Open Access Journals (Sweden)

    1993-01-01

    Full Text Available MESURE DES TEMPÉRATURES D'UN FOUR ARTISANAL À MÓRROPE, DÉPARTEMENT DE LAMBAYEQUE, UTILISÉ POUR LA FABRICATION TRADITIONNELLE DE POTERIE. Cet article présente les températures enregistrées dans un four artisanal de Mórrope, Lambayeque, utilisé pour cuire la poterie de façon traditionnelle, en utilisant comme combustible du bois de caroubier et vichayo, du fumier d'animaux et des feuilles mortes de caroubier. Le four avait une forme plus au moins elliptique avec un axe majeur de ~7.9 m en direction Nord-Sud et un axe mineur de ~ 6.8 m. Sur les 15 couples thermo-électriques Chromel-Alumel et sur celui de 10%Pt-Rh Pt que nous avons utilisé pour les mesures, le dernier et 6 des premiers, sans prendre en compte un couple portatif, restèrent intacts pendant l'expérience et tous les autres se cassèrent à cause de l'atmosphère fortement oxydante du four, produite par le combustible de fumier d'animaux. Sur une couche de bois de chauffage, au fond du four et au centre de celui-ci, un couple intact atteignit la température maximale de 630°C et un des 3 autres, placés à des endroits différents et qui se cassèrent au moment où la température monta, enregistra la température maximale de 925°C. Sur les 6 couples fixés aux poteries qui se trouvaient debout sur la couche de bois de chauffage, à une distance de 15 cm, un seul, intact, atteignit la température maximale de 817°C et sur les 5 restants qui étaient cassés, un seul enregistra la température maximale de 952ºC. 4 couples, dont l'un était celui de 10%Pt-Rh Pt, furent placés à différents endroits autour des poteries couchées sur celles qui étaient debout, et restèrent intacts. Ils atteignirent des températures maximales entre 780 et 1032°C. D'autre part un couple placé dans le mur de brique crue, autour du four, à 20 cm de son côté supérieur et qui resta également intact, enregistra une température maximale de 498°C. En conclusion, 3 des poteries debout