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Sample records for ria in-pile test

  1. Gas reactor in-pile safety test project (GRIST-2)

    International Nuclear Information System (INIS)

    Kelley, A.P. Jr.; Arbtin, E.; St Pierre, R.

    1979-01-01

    Although out-of-pile tests may be expected to confirm individual phenomena models in core disruptive accident analysis codes, only in-pile tests are capable of verifying the extremely complex integrated model effects within the appropriate time phase for these accidents. For this reason, the GRIST-2 project, the purpose of which is to design and construct an in-pile helium loop capable of transient safety testing in the TREAT facility in Idaho, forms a cornerstone of the US GCFR safety program. The project organization, experiment program, facility, helium system design, and schedule which have been selected to meet the objectives are described

  2. Development of in-pile test and evaluation technology

    Energy Technology Data Exchange (ETDEWEB)

    Kang, Yung Hwan; Park, Jong Man; Joo, Kee Nam; Park, Duk Keun; Park, Se Jin; Oh, Jong Myung; Kim, Tae Ryong; Park Jin Suk; Lee, Jae Han [Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)

    1994-08-01

    To develop the in-pile test and evaluation technologies using KMRR, basic design of instrumented capsule and auxiliary system for material irradiation test and the related studies are performed. First, reactor and test hole characteristics are summarized, and conceptual design requirements of capsule to KMRR are reviewed. And fundamental principles and criteria for the instrumented capsule design are summarized. Basic design and analysis of instrumented capsule are performed, and design of capsule supporting system are also performed and structural integrity of the system is analyzed. Based on the prior studies, test mock-ups are designed and manufactured, and thermohydraulic and vibration tests are prepared. And, as in-pile test evaluation technologies, KMRR neutron dosimetry and mechanical tests related to material irradiation are investigated. 67 figs, 30 tabs, 41 refs. (Author).

  3. Enhanced in-pile instrumentation at the advanced test reactor

    Energy Technology Data Exchange (ETDEWEB)

    Rempe, J. L.; Knudson, D. L.; Daw, J. E.; Unruh, T.; Chase, B. M.; Palmer, J.; Condie, K. G.; Davis, K. L. [Idaho National Laboratory, MS 3840, P.O. Box 1625, Idaho Falls, ID 83415 (United States)

    2011-07-01

    Many of the sensors deployed at materials and test reactors cannot withstand the high flux/high temperature test conditions often requested by users at U.S. test reactors, such as the Advanced Test Reactor (ATR) at the Idaho National Laboratory. To address this issue, an instrumentation development effort was initiated as part of the ATR National Scientific User Facility in 2007 to support the development and deployment of enhanced in-pile sensors. This paper reports results from this effort. Specifically, this paper identifies the types of sensors currently available to support in-pile irradiations and those sensors currently available to ATR users. Accomplishments from new sensor technology deployment efforts are highlighted by describing new temperature and thermal conductivity sensors now available to ATR users. Efforts to deploy enhanced in-pile sensors for detecting elongation and realtime flux detectors are also reported, and recently-initiated research to evaluate the viability of advanced technologies to provide enhanced accuracy for measuring key parameters during irradiation testing are noted. (authors)

  4. Enhanced In-Pile Instrumentation at the Advanced Test Reactor

    Science.gov (United States)

    Rempe, Joy L.; Knudson, Darrell L.; Daw, Joshua E.; Unruh, Troy; Chase, Benjamin M.; Palmer, Joe; Condie, Keith G.; Davis, Kurt L.

    2012-08-01

    Many of the sensors deployed at materials and test reactors cannot withstand the high flux/high temperature test conditions often requested by users at U.S. test reactors, such as the Advanced Test Reactor (ATR) at the Idaho National Laboratory. To address this issue, an instrumentation development effort was initiated as part of the ATR National Scientific User Facility in 2007 to support the development and deployment of enhanced in-pile sensors. This paper provides an update on this effort. Specifically, this paper identifies the types of sensors currently available to support in-pile irradiations and those sensors currently available to ATR users. Accomplishments from new sensor technology deployment efforts are highlighted by describing new temperature and thermal conductivity sensors now available to ATR users. Efforts to deploy enhanced in-pile sensors for detecting elongation and real-time flux detectors are also reported, and recently-initiated research to evaluate the viability of advanced technologies to provide enhanced accuracy for measuring key parameters during irradiation testing are noted.

  5. MCNP calculations for the HCPB submodules in-pile test

    Energy Technology Data Exchange (ETDEWEB)

    Pijlgroms, B.J. [Section Nuclear and Reactor Physics, ECN Nuclear Research, Petten (Netherlands)

    1998-11-01

    This report describes the MCNP calculations that have been performed for the Helium Cooled Pebble Bed (HCPB) Submodules In-pile Test that has been planned for irradiation in the materials testing High Flux Reactor (HFR) at Petten. In this test, four HSM-8 submodules will be placed at core position H4. The report presents the neutron flux and power density profiles to be expected in the submodules. For the gamma induced heating only a rough estimation could be made. In the HCPB submodules the total specific heating does not exceed (36.7 {+-} 2.9)[W/cc]. 8 refs.

  6. Design criteria and fabrication in-pile test section of HANARO fuel test loop

    Energy Technology Data Exchange (ETDEWEB)

    Kim, J. Y.

    1997-10-01

    Safety state fuel test loop will be equipped in HANARO to obtain the development and betterments of advanced fuel and materials through the irradiation tests. The objective of this study is to determine the design criteria and technical specification of in-pile test section and to specify the manufacturing requirements of in-pile test section. HANARO fuel test loop was designed to meet the CANDU and PWR fuel testing and in-pile section will be manufactured and installed in HANARO. The design criteria and technical specification of in-pile test section could be used the fuel and materials design with for irradiation testing IPS of HANARO fuel test loop. This results will become guidances for the planning and programming of irradiation testing. (author). 12 refs., tabs., figs.

  7. The Phebus fission products in pile test programme

    International Nuclear Information System (INIS)

    Bussac, J.; Holtbecker, H.

    1988-01-01

    The need for quantifying the radioactive materials escaping from an LWR Nuclear Power Plant following a melt-down accident has arisen relatively late in the nuclear reactor technology development process. The TMI-2 accident in 1979 and the Chernobyl accident in 1986 have confirmed the importance of a good knowledge of phenomena which take place in a plant undergoing extreme accident conditions. After an extensive resarch effort which has involved the major nuclear countries for several years, we are now at the stage where a selective and converging attitude should be taken towards the wide range of problems underlying severe accidents. Selective, because we must understand what is important and what could be neglected. Converging, because we must arrive at a consensus at international level on the methods to treat these problems and a common understanding of the main scientific phenomena and the models to correctly represent them. After a large amount of separate effects tests and semi-integral in-pile and out-of-pile experiments, the Phebus FP project is being started as an experimental effort to quantify the relative importance of complicated processes and to give an insight into the interconnection of various mechanisms. The overall objective of this programme is to provide a qualified data base of integral in-pile experiments to validate codes dealing with FP transport in reactor core, primary cooling system and containment. This paper describes mainly the motivations and objectives of the Phebus PF programme

  8. Program of in-pile IASCC testing under the simulated actual plant condition. Development of technique for in-pile IASCC initiation test in JMTR

    International Nuclear Information System (INIS)

    Ugachi, Hirokazu; Tsukada, Takashi; Kaji, Yoshiyuki; Nagata, Nobuaki; Dozaki, Koji; Takiguchi, Hideki

    2003-01-01

    Irradiation assisted stress corrosion cracking (IASCC) is caused by the synergistic effects of neutron irradiation, stress and corrosion by high temperature water. It is, therefore, essential to perform in-pile SCC tests, which are material tests under the conditions simulating those of actual LWR operation, in order to clarify the precise mechanism of the phenomenon, though mainly out-of-pile SCC tests for irradiated materials have been carried out in this research field. There are, however, many difficulties to perform in-pile SCC tests. Performing in-pile SCC tests, essential key techniques must be developed. Hence as a part of development of the key techniques for in-pile SCC tests, we have embarked on development of the test technique which enables us to obtain the information concerning the effect of such parameters as applied stress level, water chemistry, irradiation conditions, etc. on the crack initiation behavior. Although it is difficult to detect the crack initiation in in-pile SCC tests, the crack initiation can be evaluated by the detection of specimen rupture if the cross section area of the specimen is small enough. Therefore, we adopted the uniaxial constant loading (UCL) test with small tensile specimens. This paper will describe the current status of the development of several techniques for in-pile SCC initiation tests in JMTR and the results of the performance tests of the designed testing unit using the out-of-pile loop facility. (author)

  9. A comprehensive in-pile test of PWR fuel bundle

    Energy Technology Data Exchange (ETDEWEB)

    Kang Rixin; Zhang Shucheng; Chen Dianshan (Academia Sinica, Beijing (China). Inst. of Atomic Energy)

    1991-02-01

    An in-pile test of PWR fuel bundle has been conducted in HWRR at IAE of China. This paper describes the structure of the test bundle (3x3-2), fabrication process and quality control of the fuel rod, irradiation conditions and the main Post Irradiation Examination (PIE) results. The test fuel bundle was irradiated under the PWR operation and water chemistry conditions with an average linear power of 381 W/cm and reached an average burnup of 25010 MWd/tU of the fuel bundle. After the test, destructive and non-destructive examination of the fuel rods was conducted at hot laboratories. The fission gas release was 10.4-23%. The ridge height of cladding was 3 to 8 {mu}m. The hydrogen content of the cladding was 80 to 140 ppm. The fuel stack height was increased by 2.9 to 3.3 mm. The relative irradiation growth was about 0.11 to 0.17% of the fuel rod length. During the irradiation test, no fuel rod failure or other abnormal phenomena had been found by the on-line fuel failure monitoring system of the test loop and water sampling analysis. The structure of the test fuel assembly was left undamaged without twist and detectable deformation. (orig.).

  10. In-pile IASCC growth tests of irradiated stainless steels in JMTR

    Energy Technology Data Exchange (ETDEWEB)

    Chimi, Yasuhiro; Kasahara, Shigeki; Ise, Hideo; Kawaguchi, Yoshihiko; Nakano, Junichi; Nishiyama, Yutaka [Japan Atomic Energy Agency, Nuclear Safety Research Center, Tokai, Ibaraki (Japan); Shibata, Akira; Ohmi, Masao [Japan Atomic Energy Agency, Oarai Research and Development Center, Oarai, Ibaraki (Japan)

    2012-03-15

    The Japan Atomic Energy Agency (JAEA) has an in-pile irradiation-assisted stress corrosion cracking (IASCC) test plan to evaluate in-situ effects of neutron/{gamma}-ray irradiation on crack growth of irradiated stainless steels under high-temperature water conditions for commercial boiling water reactors (BWRs) using the Japan Materials Testing Reactor (JMTR). Crack growth rate and its electrochemical corrosion potential (ECP) dependence are different between in-pile test and post irradiation examination (PIE), but these differences are not fully understood. The objectives of the present study are to understand the difference between in-pile and out-of-pile IASCC growth and to confirm the effectiveness of mitigation due to lowering ECP on in-pile crack growth rates. For in-pile crack growth tests, we have selected a large compact tension specimen such as 0.5T-CT because of validity of SCC growth test at a high stress intensity factor (K-value). For loading a 0.5T-CT specimen up to K - 30 MPa {radical}m, we have adopted a lever type loading unit for in-pile crack growth tests in the JMTR. In this report, an in-pile test plan for crack growth of irradiated SUS316L stainless steels under simulated BWR conditions in the JMTR and current status of development of in-pile crack growth test techniques are presented. (author)

  11. Advanced In-pile Instrumentation for Material and Test Reactors

    International Nuclear Information System (INIS)

    Rempe, J.L.; Knudson, D.L.; Daw, J.E.; Unruh, T.C.; Chase, B.M.; Davis, K.L.; Palmer, A.J.; Schley, R.S.

    2013-06-01

    The US Department of Energy sponsors the Advanced Test Reactor (ATR) National Scientific User Facility (NSUF) program to promote U.S. research in nuclear science and technology. By attracting new research users - universities, laboratories, and industry - the ATR NSUF facilitates basic and applied nuclear research and development, advancing U.S. energy security needs. A key component of the ATR NSUF effort is to design, develop, and deploy new in-pile instrumentation techniques that are capable of providing real-time measurements of key parameters during irradiation. This paper describes the strategy developed by the Idaho National Laboratory (INL) for identifying instrumentation needed for ATR irradiation tests and the program initiated to obtain these sensors. New sensors developed from this effort are identified; and the progress of other development efforts is summarized. As reported in this paper, INL staff is currently involved in several tasks to deploy real-time length and flux detection sensors, and efforts have been initiated to develop a crack growth test rig. Tasks evaluating 'advanced' technologies, such as fiber-optics based length detection and ultrasonic thermometers are also underway. In addition, specialized sensors for real-time detection of temperature and thermal conductivity are not only being provided to NSUF reactors, but are also being provided to several international test reactors. (authors)

  12. Advanced In-Pile Instrumentation for Materials Testing Reactors

    Science.gov (United States)

    Rempe, J. L.; Knudson, D. L.; Daw, J. E.; Unruh, T. C.; Chase, B. M.; Davis, K. L.; Palmer, A. J.; Schley, R. S.

    2014-08-01

    The U.S. Department of Energy sponsors the Advanced Test Reactor (ATR) National Scientific User Facility (NSUF) program to promote U.S. research in nuclear science and technology. By attracting new research users - universities, laboratories, and industry - the ATR NSUF facilitates basic and applied nuclear research and development, advancing U.S. energy security needs. A key component of the ATR NSUF effort is to design, develop, and deploy new in-pile instrumentation techniques that are capable of providing real-time measurements of key parameters during irradiation. This paper describes the strategy developed by the Idaho National Laboratory (INL) for identifying instrumentation needed for ATR irradiation tests and the program initiated to obtain these sensors. New sensors developed from this effort are identified, and the progress of other development efforts is summarized. As reported in this paper, INL researchers are currently involved in several tasks to deploy real-time length and flux detection sensors, and efforts have been initiated to develop a crack growth test rig. Tasks evaluating `advanced' technologies, such as fiber-optics based length detection and ultrasonic thermometers, are also underway. In addition, specialized sensors for real-time detection of temperature and thermal conductivity are not only being provided to NSUF reactors, but are also being provided to several international test reactors.

  13. Seismic analysis of the in-pile test section

    Energy Technology Data Exchange (ETDEWEB)

    Lee, J. M.; Park, K. N.; Chi, D. Y.; Park, S. K.; Sim, B. S.; Ahn, S. H.; Lee, C. Y.; Kim, Y. J. [Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)

    2004-07-01

    This study gives the results of the seismic analysis of the IPS (In Pile Section) with lower bracket support. The results cover the natural frequency and seismic response of the IPS for the SSE and OBE events. An FE (Finite Element) model which includes the two vessels of the IPS and its support structure were analyzed by ABAQUS.

  14. In-pile test results of HANA claddings in Halden research reactor

    Energy Technology Data Exchange (ETDEWEB)

    Baek, Jong Hyuk; Choi, Byoung Kwon; Jeong, Yong Hwan; Jung, Yun Ho [Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)

    2005-07-01

    It is a kind of facing tasks in the nuclear industry to develop advanced claddings for high burn-up fuel which is safer and more economical than the existing conventional ones. Since 1997, taking an initiative in KAERI, the Zr cladding development team has carried out the R and D activities for the development of the advanced claddings to be used in the high burn-up fuel (>70,000 MWD.MTU). The team had produced the advanced claddings (HANA, High-performance Alloy for Nuclear Application) from the patented composition and manufacturing process in the international collaboration with U.S. and Japan. Now, the HANA claddings have being demonstrated their good performances from the out-of-pile tests including the corrosion, creep, burst, tensile, microstructures LOCA, RIA, wear, and so on. In parallel to the out-of-pile performance tests, the HANA claddings are being undertaken to evaluate their in-pile properties in Halden research reactor. In this study, it is included the test overviews, conditions, and results of the HANA claddings in the Halden reactor.

  15. Development of enclosure technique of tag gas for in-pile creep test

    International Nuclear Information System (INIS)

    Izaki, Toru; Ichikawa, Shoichi; Soroi, Masatoshi; Ito, Chikara

    2004-01-01

    Outline of the enclosure technique of tag gas for in-pile creep test is stated. In order to carry out in-pile creep test, the sample can enclose tag gas before the test and then the sample is inserted into MARICO-2 (Material Testing Rig with Temperature Control) in FBR 'JOYO' MK-III for the irradiation test. Outline of in-pile creep test using tag gas, enclosure system of tag gas, detection of a part of broken sample and identification of sample are explained. 126-, 128-, 129-, 131-, 132-, and 134-Xe are used as tag gases. The samples are identified by RIMS (Laser Resonance Ionization Mass Spectroscopy) in ppt order. ODS ferritic steel will be tested by the method in the next step. (S.Y.)

  16. RIA testing capability of the transient reactor test facility

    International Nuclear Information System (INIS)

    Crawford, D.C.; Swanson, R.W.

    1999-01-01

    The advent of high-burnup fuel implementation in LWRs has generated international interest in high-burnup LWR fuel performance. Recent testing under simulated RIA conditions has demonstrated that certain fuel designs fail at peak fuel enthalpy values that are below existing regulatory criteria. Because many of these tests were performed with non-prototypically aggressive test conditions (i.e., with power pulse widths less than 10 msec FWHM and with non-protoypic coolant configurations), the results (although very informative) do not indisputably identify failure thresholds and fuel behavior. The capability of the TREAT facility to perform simulated RIA tests with prototypic test conditions is currently being evaluated by ANL personnel. TREAT was designed to accommodate test loops and vehicles installed for in-pile transient testing. During 40 years of TREAT operation and fuel testing and evaluation, experimenters have been able to demonstrate and determine the transient behavior of several types of fuel under a variety of test conditions. This experience led to an evolution of test methodology and techniques which can be employed to assess RIA behavior of LWR fuel. A pressurized water loop that will accommodate RIA testing of LWR and CANDU-type fuel has completed conceptual design. Preliminary calculations of transient characteristics and energy deposition into test rods during hypothetical TREAT RIA tests indicate that with the installation of a pressurized water loop, the facility is quite capable of performing prototypic RIA testing. Typical test scenarios indicate that a simulated RIA with a 72 msec FWHM pulse width and energy deposition of 1200 kJ/kg (290 cal/gm) is possible. Further control system enhancements would expand the capability to pulse widths as narrow as 40 msec. (author)

  17. Minutes of the workshop on bases of in-pile irradiation tests

    International Nuclear Information System (INIS)

    1997-03-01

    The Workshop on Bases of In-pile Irradiation Tests was held on January 29th and 30th, 1997 at the Ibarakiken Sangyo Kaikan in Mito, Ibaraki. The purpose is to discuss upgrading an in-pile irradiation test, promoting the utilization of the research and testing reactors and also activating the research potential of JAERI transversely. Main topics are the role and future plan of the research and testing reactors, a challenge to an advanced irradiation test, development of peripheral techniques for irradiation tests and future trends of the in-pile irradiation test in the 21st century. It was mainly pointed out that the in-pile irradiation test based on an analytical method using interpolation and extrapolation procedures met a turning point and that the upgrading of the irradiation and testing method should be indispensable for regaining the latest frontiers of an irradiation study using the research and testing reactors. The new concepts were also proposed on the irradiation correlation and modeling for the design of innovative materials. It was also recognized the key issues of the irradiation study in future should be an advanced irradiation testing method which can combine various types of irradiation field and control the irradiation conditions freely. In the next century in which large accelerator or new neutron source competes with research and testing reactors for neutron irradiation tests, themes of research using in-pile irradiation tests will be upgrading of the light water reactor, development of fusion reactor, basic research, biological and medical research, radioisotope production and semiconductors manufacturing, etc. It was also concluded the research and testing reactors will keep their main role in neutron irradiation research in future. This report briefly summarizes the content of 16 presentations and the discussion. The result of the questionnaires on the utilization of research and testing reactors to the participants is also attached. (J.P.N.)

  18. In-Pile Tests for IASCC Growth Behavior of Irradiated 316L Stainless Steel under Simulated BWR Condition in JMTR

    Science.gov (United States)

    Chimi, Yasuhiro; Kasahara, Shigeki; Ise, Hideo; Kawaguchi, Yoshihiko; Nakano, Junichi; Nishiyama, Yutaka

    The Japan Atomic Energy Agency (JAEA) has an in-pile irradiation test plan to evaluate in-situ effects of neutron/γ-ray irradiation on stress corrosion crack (SCC) growth of irradiated stainless steels using the Japan Materials Testing Reactor (JMTR). SCC growth rate and its dependence on electrochemical corrosion potential (ECP) are different between in-pile test and post irradiation examination (PIE). These differences are not fully understood because of a lack of in-pile data. This paper presents a systematic review on SCC growth data of irradiated stainless steels, an in-pile test plan for crack growth of irradiated SUS316L stainless steel under simulated BWR conditions in the JMTR, and the development of the in-pile test techniques.

  19. Thermal and mechanical analyses for the HCPB Submodules in-pile test

    Energy Technology Data Exchange (ETDEWEB)

    Bakker, K. [Fuels, Actinides and Isotopes, Nuclear Research and Consultancy Group NRG, Netherlands Energy Research Foundation ECN, Petten (Netherlands)

    1998-12-01

    A description is given of the Finite Element Method (FEM) and thermal and mechanical computations that have been performed for the Helium Cooled Pebble Bed (HCPB) Submodules in-pile tests, which have been planned for irradiation in the High Flux Reactor (HFR) at Petten. In this test, four submodules will be placed at core position H4. The report presents the temperature and stress distribution for the highest powered submodule of these four submodules. 9 refs

  20. Design of in-pile section monitoring system in fuel test loop

    Energy Technology Data Exchange (ETDEWEB)

    Sim, B. S.; Park, K. N.; Park, S. K.; Chi, D. Y.; Lee, J. M.; Ahn, S. H.; Lee, C. Y.; Kim, Y. J. [Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)

    2005-07-01

    In this paper a brief summary of the monitoring system of In-Pile Section(IPS) is described. To meet the user requirements on the test fuel and irradiation conditions, various instruments are installed on the test fuel pin itself and the appropriate locations in IPS. The requirements and descriptions for instruments, gas supply system, and the data acquisition system to sample and record parameters are described.

  1. Manufacturing and performance tests of in-pile creep measuring machine of zirconium alloys

    International Nuclear Information System (INIS)

    Choi, Y.; Kim, B. G.; Kang, Y. H.

    2000-01-01

    A mock-up of the in-pile creep test machine of zirconium alloys for HANARO was designed and manufactured, which performance tests were carried. The dimension of the in-pile creep machine is 55 mm in diameter and 700 mm in length for HANARO, respectively. Load is transferred to specimen by through the working mechanisms in which the contraction of bellows by gas pressure moves a yoke and an upper grip connected to a specimen, simultaneously. It was observed that the extension of the specimen mounted in grips was transferred to a linear voltage differential transformer perfectly by a yoke and a push rod in a bearing. The displacement of specimen with applied pressure was determined with the LVDT and a pressure gauge, respectively. Resultant stress-strain behaviors of the specimen was determined by the displacement-applied gas pressure curve, which showed similar values obtained with a standard tensile test machine

  2. In-pile irradiation test program and safety analysis report of the KAERI fuel for HANARO

    Energy Technology Data Exchange (ETDEWEB)

    Hwang, Wan; Ryu, Woo Suck; Byun, Taek Sang; Park, Jong Man; Lee, Byung Chul; Kim, Hack No; Park, Hee Tae; Kim, Chang Kyu [Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)

    1996-05-01

    Localization of HANARO fuel has been carried out successfully, and design and fabrication technologies of the fuel are recently arrived the final stage of development. The performance of the fuel which has been fabricated in KAERI is confirmed through out-of-pile characterization, and the quality assurance procedure and assessment criteria are described. In order to verify the KAERI fuel, thus, in-pile irradiation test program of the KAERI fuel is scheduled in HANARO. This report summarizes the in-pile testing schedule, design documents of test rods and assemblies, fabrication history and out-of-pile characteristics of test rods, irradiation test condition and power history, post-irradiation examination scheme, linear power generation distribution, and safety analysis results. The design code for HANARO fuel is used to analyze the centerline temperature and swelling of the KAERI fuels. The results show that at 120 kW/m of linear power the maximum centerline temperature is 267 deg C which is much lower than the limitation temperature of 350 deg C, and that the swelling is 9.3 % at 95 at% lower than criterion of 20 %. Therefore, the KAERI fuels of this in-pile irradiation test is assessed to show good performance of integrity and safety in HANARO. 10 tabs., 7 figs., 3 refs. (Author).

  3. In-pile cladding tests at NRI Rez and PIE capabilities and experience

    International Nuclear Information System (INIS)

    Zmitko, M.

    2002-01-01

    In-pile cladding corrosion test facilities and relevant post-irradiation capabilities at NRI Rez plc are overviewed. Basic information about the research rector LVR-15 and in-pile water loops is given. An experience in the field of Zr-alloy cladding corrosion testing and investigation of cladding corrosion behaviour is demonstrated for two experimental programmes conducted at NRI Rez in the past period. The first example describes results obtained at studying of corrosion behaviour of advanced Zr-alloys under PWR conditions with a special concern to a high lithium content and subcooled surface boiling. The second example informs about completion of the experimental programme supported by the IAEA which is focused on investigation of Zircaloy-4 cladding behaviour under VVER water chemistry, thermal-hydraulic and irradiation conditions with the main to obtain experimental data for an assessment of the Zircaloy-4 cladding compatibility with VVER conditions. (author)

  4. A probabilistic safety assessment of in-pile test loop in HWRR

    International Nuclear Information System (INIS)

    Cao Xuewu; Li Zhaohuan

    1991-07-01

    The PSA methodology has been applied to the in-pile test loop which is installed in the Heavy Water Research Reactor (HWRR). This loop is designed and operated for fuel assembly testing of the Qinshan PWR plant. This analysis is to assess the safety and to evaluate the design of this operating loop. The procedure and models are similar to a PSA on nuclear power plant. The major contents in the analysis consist of the familiarization of the object, the investigation and selection of accident initiators, setting events and fault trees, data collections, quantitative calculations, qualitative and result analyses and final conclusion. This analysis is only limited to the initiators of in-pile loop itself and possible errors made by operators during normal operation. The accident occurence is less than 10 -4 a -1 which may be recommended as an acceptance risk for safety operation of an in-pile test loop. Finally, suggestions have been raised to improve the design of test loop, especially in reducing operation errors by local operators

  5. In-pile test of tritium recovery from lithium oxide

    International Nuclear Information System (INIS)

    Kurasawa, Toshimasa; Yoshida, Hiroshi; Watanabe, Hitoshi; Takeshita, Hidefumi; Miyauchi, Takejiro; Matsui, Tomoaki

    1984-05-01

    In-situ tritium recovery experiment with sintered lithium oxide pellets was performed under a high neutron fluence in the JRR-2. The irradiation hole VT-10 is the vertical one in the fuel rods region of the reactor, and the neutron flux is as follows: the thermal neutron flux with the epithermal neutron; 1.12 x 10 14 n/cm 2 . sec, the fast neutron flux; 1.0 x 10 12 n/cm 2 . sec. Irradiation material is the four pellets of cylindrical Li 2 O with the size of 11mm-OD, 1.8mm-ID, 10mm-H, and their total weight is 6.67g(the apparent bulk density 86%TD). A sweep gas capsule with a inner heater was constructed for the present study. Irradiation temperatures were regulated in the high temperature range, 470 -- 760 0 C. Four cycles of irradiation tests were carried out from May to August in 1983, and the effective thermal neutron fluence and the burnup of 6 Li were 5.9 x 10 19 nvt and 0.24% of total lithium(natural abundance of Li), respectively. The amount of generated tritium was calculated to be 31.2Ci by using a value of the depression factor of the thermal neutron flux(0.148) and the effective neutron cross section(543b) for the 6 Li(n, α) 3 H reaction. Present report describes the tritium release behavior in the in-situ tritium recovery apparatus and discuss the effects of the moisture, the hydrogen spiking, the irradiation temperature, etc.. Problems relative to a real time measurement of a comparatively high tritium concentration(10 -1 -- 10 2 μCi/cm 3 ) in the helium gas stream were also investigated. (author)

  6. Evaluation of results from an in-pile creep test in the Studsvik R2 reactor

    Energy Technology Data Exchange (ETDEWEB)

    Pettersson, Kjell [Entropy Materials, Stockholm (Sweden)

    2002-01-01

    An in-pile creep test with bowing of cladding tubes has been performed in a hot water loop in the Studsvik R2 reactor . One test was performed in the core and one outside the core. The out-of-pile sample showed some minor primary creep strain while the in-pile specimen deformed at a steady rate of 5x10{sup -7}/h . However, when the results were compared to a broader data base of Zircaloy in-pile creep it became clear that the creep deformation observed is a primary creep which occurs before the irradiation creep in Zircaloy reaches a constant steady state creep rate. This primary stage is interpreted as a consequence of the development of an irradiation induced microstructure in Zircaloy which does not reach a steady state until a dose of about 10{sup 21} n/cm{sup 2} . At this stage the steady state irradiation creep starts. From this interpretation it is concluded that it is quite feasible to use the test method on pre-irradiated material in which it can be expected that the steady state will be reached already after short irradiation times.

  7. Vanadium—lithium in-pile loop for comprehensive tests of vanadium alloys and multipurpose coatings

    Science.gov (United States)

    Lyublinski, I. E.; Evtikhin, V. A.; Ivanov, V. B.; Kazakov, V. A.; Korjavin, V. M.; Markovchev, V. K.; Melder, R. R.; Revyakin, Y. L.; Shpolyanskiy, V. N.

    1996-10-01

    The reliable information on design and material properties of self-cooled Li sbnd Li blanket and liquid metal divertor under neutron radiation conditions can be obtained using the concept of combined technological and material in-pile tests in a vanadium—lithium loop. The method of in-pile loop tests includes studies of vanadium—base alloys resistance, weld resistance under mechanical stress, multipurpose coating formation processes and coatings' resistance under the following conditions: high temperature (600-700°C), lithium velocities up to 10 m/s, lithium with controlled concentration of impurities and technological additions, a neutron load of 0.4-0.5 MW/m 2 and level of irradiation doses up to 5 dpa. The design of such an in-pile loop is considered. The experimental data on corrosion and compatibility with lithium, mechanical properties and welding technology of the vanadium alloys, methods of coatings formation and its radiation tests in lithium environment in the BOR-60 reactor (fast neutron fluence up to 10 26 m -2, irradiation temperature range of 500-523°C) are presented and analyzed as a basis for such loop development.

  8. The design of in-pile test section for fuel test loop

    Energy Technology Data Exchange (ETDEWEB)

    Park, K. N.; Lee, J. M.; Shim, B. S.; Zee, D. Y.; Park, S. H.; Ahn, S. H.; Lee, J. Y.; Kim, Y. J. [KAERI, Taejon (Korea, Republic of)

    2004-07-01

    As an equipment for nuclear fuel's general performance irradiation test in HANARO, Fuel Test Loop(FTL) has been developed that can irradiate the pin to the maximum number of 3 at the core irradiation hole(IR1 hole) by considering for it's utility and user's irradiation requirement. 3-Pin FTL consists of In-Pile Test Section (IPS) and Out-of-Pile System (OPS). IPS consists for IPS Vessel assembly, In-Pool Piping, IPS Support, In-Pool Piping Support etc. Design that such IPS considers interference item consisted to do not bear in existing facilities by one. IVA that is connected to the OPS are controlled and regulated by means of system pressure, system temperature and the water quality. IPS Vessel assembly is consisted of outer pressure vessel, inner pressure vessel, IPS head, inner assembly and test fuel carrier. After 3-Pin FTL development which is expected to be finished by the 2006, FTL will be used for the irradiation test of the new PWR-type fuel and can maximize the usage of HANARO.

  9. In-pile creep test technique for zirconium alloys examination in BR-10 reactor channels

    International Nuclear Information System (INIS)

    Pevchikh, Yu.M.; Kruglov, A.S.; Troyanov, V.M.

    2002-01-01

    The irradiation enhanced creep phenomenon was discovered in stainless steels as a specific physical process accompanying high-intensity neutron flux irradiation in fast reactors. IPPE is also experienced in irradiation creep test activities, studying different types of materials under irradiation in BR-10 fast reactor. Series of in-channel type test facilities were constructed and tested in BR-10 reactor's 'dry' channels in order to carry out full-scale instrumented examination regarded to in-pile creep behaviour of different reactor materials. As a result, a specific test technique, named 'Tensometric method', has been developed and experimentally proved to be power enough in order to investigate irradiation creep of materials right in situ under neutron irradiation. The main peculiarity of test facility, which is constructed to apply the tensometric method, consists in absence of any special deformation-measurement cell at all. The in-pile creep strain measurement technique developed at IPPE is based on the non-direct measurement of specimen's deformation (either linear tensile strain or angular twisting one), which directly affects the loaded draws' tension parameters. Starting from 1993, in-pile creep experiments to investigate in-reactor creep behaviour of E110 and E635 zirconium alloys were carried out in BR-10. Experimental results and data collected during more than 20-year of BR-10 in-reactor creep test experience can be assumed as a strong evidence that the tensometric technique is a powerful instrument, which can give a chance to study different irradiation effects on reactor materials directly under irradiation. (author)

  10. In-pile tests of HTGR fuel particles and fuel elements

    International Nuclear Information System (INIS)

    Chernikov, A.S.; Kolesov, V.S.; Deryugin, A.I.

    1985-01-01

    Main types of in-pile tests for specimen tightness control at the initial step, research of fuel particle radiation stability and also study of fission product release from fuel elements during irradiation are described in this paper. Schemes and main characteristics of devices used for these tests are also given. Principal results of fission gas product release measurements satisfying HTGR demands are illustrated on the example of fuel elements, manufactured by powder metallurgy methods and having TRISO fuel particles on high temperature pyrocarbon and silicon carbide base. (author)

  11. The in-pile proving test for fuel assembly of Qinshan nuclear power plant

    International Nuclear Information System (INIS)

    Chen Dianshan; Zhang Shucheng; Kang Rixin; Wang Huarong; Chen Guanghan

    1989-10-01

    The in-pile proving test for fuel assembly of Qinshan nuclear power plant had been conducted in the experimental loop of HWRR at IAE (Institute of Atomic Energy) in Beijing, China, from January 1985 to December 1986. Average burnup of 27000 MWd/tU and peak burnup of 34000 MWd/tU of fuel rod had already been reached. The basic status of the experiment are described, emphasis is placed on the discussion of proving test parameters and analysis of experiment results

  12. Data collection for the methods of in-pile materials testing

    International Nuclear Information System (INIS)

    Markina, N.V.; Rudkevich, A.V.; Lebedeva, E.E.

    1985-01-01

    Problems, relating to the creation of automated data banks intended for accumulatioon and systematization of data according to the methods of in-pile materials testing, taking into account their specific nature are discussed. The architecture of the bank, realized on the BESM-6 computer is described. The bank contains data on about 300 methods. The library of requests, which may be used by a user comprises about 20 descriptions. A new request description preparation and input take 5-20 min. The system answering time is from 30 sec to 3-4 min

  13. Integrated, digital experiment transient control and safety protection of an in-pile test

    International Nuclear Information System (INIS)

    Thomas, R.W.; Whitacre, R.F.; Klingler, W.B.

    1982-01-01

    The Sodium Loop Safety Facility experimental program has demonstrated that in-pile loop fuel failure transient tests can be digitally controlled and protected with reliability and precision. This was done in four nuclear experiments conducted in the Engineering Test Reactor operated by EG and G Idaho, Inc., at the Idaho National Engineering Laboratory. Loop sodium flow and reactor power transients can be programmed to sponsor requirements and verified prior to the test. Each controller has redundancy, which reduces the effect of single failures occurring during test transients. Feedback and reject criteria are included in the reactor power control. Timed sequencing integrates the initiation of the controllers, programmed safety set-points, and other experiment actions (e.g., planned scram). Off-line and on-line testing is included. Loss-of-flow, loss-of-piping-integrity, boiling-window, transient-overpower, and local fault tests have been successfully run using this system

  14. Evaluation of neutronic characteristics of in-pile test reactor for fast reactor safety research

    Energy Technology Data Exchange (ETDEWEB)

    Uto, N.; Ohno, S.; Kawata, N. [Power Reactor and Nuclear Fuel Development Corp., Oarai, Ibaraki (Japan). Oarai Engineering Center

    1996-09-01

    An extensive research program has been carried out at the Power Reactor and Nuclear Fuel Development Corporation for the safety of future liquid-metal fast breeder reactors to be commercialized. A major part of this program is investigation and planning of advanced safety experiments conducted with a new in-pile safety test facility, which is larger and more advanced than any of the currently existing test reactors. Such a transient safety test reactor generally has unique neutronic characteristics that require various studies from the reactor physics point of view. In this paper, the outcome of the neutronics study is highlighted with presenting a reference core design concept and its performance in regard to the safety test objectives. (author)

  15. Evaluation on sweep gas pressure drop in fusion blanket mock-up for in-pile test

    International Nuclear Information System (INIS)

    Ishitsuka, Etsuo; Kawamura, Hiroshi; Sagawa, Hisashi; Nagakura, Masaaki; Kanzawa, Toru.

    1993-03-01

    In the ITER/CDA (Conceptual Design Activity) of a tritium breeding blanket, Japan have proposed the pebble-typed blanket. The in-pile mock-up test will be preparing in JMTR (Japan Materials Testing Reactor) for Japanese engineering design with the pebble-typed blanket. Therefore, the He sweep gas pressure drop in the pebble bed was measured for the design of the mock-up used on in-pile test. From the results of this test, it was clear that the pressure drop was predicted on Kozeny- Carman's equation within +25 ∼ -60 %, and that the pressure drop was not affected by moisture concentration (< 100 ppm). (author)

  16. Review Report on the Design of In-Pile Test Section(IPS)

    International Nuclear Information System (INIS)

    Lee, Jong Min; Park, Kook Nam; Shim, Bong Sik; Lee, Chung Young; Chi, Dae Young; Park, Su Ki; Ahn, Sung Ho; Kim, Young Ki; Lee, Kye Hong; Kim, Kwan Hyun

    2009-01-01

    The In-Pile Test Section(IPS) accommodating fuel pins has loaded IR-1 hole in HANARO has double pressure vessel for the design conditions of 350 deg. C, 17.5 MPa and is composed of outer assembly and inner assembly. Dummy fuel, dummy fuel supports and Top flange are the main components in inner assembly and inner pressure vessel, outer pressure vessel and head are the components in outer assembly. The IPS at current status has dummy fuels and confirm the requirements for the IPS design improvements during the design, manufacturing and installation process. Head, Top Flange, Instrumentation Feed through, Lifting Eye, Fuel Carrier Leg, Retainer and Nozzle cover are the main parts that the design needs to be changed. This report suggest the needs for the IPS design modification and it would be reflected to the new IPS design which would accommodating test fuel pins

  17. Probabilistic Modeling of Updating Epistemic Uncertainty In Pile Capacity Prediction With a Single Failure Test Result

    Directory of Open Access Journals (Sweden)

    Indra Djati Sidi

    2017-12-01

    Full Text Available The model error N has been introduced to denote the discrepancy between measured and predicted capacity of pile foundation. This model error is recognized as epistemic uncertainty in pile capacity prediction. The statistics of N have been evaluated based on data gathered from various sites and may be considered only as a eneral-error trend in capacity prediction, providing crude estimates of the model error in the absence of more specific data from the site. The results of even a single load test to failure, should provide direct evidence of the pile capacity at a given site. Bayes theorem has been used as a rational basis for combining new data with previous data to revise assessment of uncertainty and reliability. This study is devoted to the development of procedures for updating model error (N, and subsequently the predicted pile capacity with a results of single failure test.

  18. Review Report on the Design of In-Pile Test Section(IPS)

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Jong Min; Park, Kook Nam; Shim, Bong Sik; Lee, Chung Young; Chi, Dae Young; Park, Su Ki; Ahn, Sung Ho; Kim, Young Ki; Lee, Kye Hong; Kim, Kwan Hyun

    2009-01-15

    The In-Pile Test Section(IPS) accommodating fuel pins has loaded IR-1 hole in HANARO has double pressure vessel for the design conditions of 350 deg. C, 17.5 MPa and is composed of outer assembly and inner assembly. Dummy fuel, dummy fuel supports and Top flange are the main components in inner assembly and inner pressure vessel, outer pressure vessel and head are the components in outer assembly. The IPS at current status has dummy fuels and confirm the requirements for the IPS design improvements during the design, manufacturing and installation process. Head, Top Flange, Instrumentation Feed through, Lifting Eye, Fuel Carrier Leg, Retainer and Nozzle cover are the main parts that the design needs to be changed. This report suggest the needs for the IPS design modification and it would be reflected to the new IPS design which would accommodating test fuel pins.

  19. Capsule development and utilization for material irradiation tests; study on the in-pile creep measuring method of zirconium alloys

    Energy Technology Data Exchange (ETDEWEB)

    Choi, Yong; Lee, Byung Kee; Lee, Jong Jea; Kim, Chang Sik; Kim, B. Hun; Cho, I. Sik [Sunmoon University, Asan (Korea)

    2002-02-01

    The final objective of this project is to obtain a design and fabrication technology of an in-pile creep test machine of zirconium alloys. First, design concepts of the in-pile creep test machines of various foreign countries were reviewed and a preliminary design of the equipment was carried. Second, the mock-up of the in-pile creep test machine was fabricated based on the preliminary design. The mock-up consisted of upper and lower grips, a yoke, a pressure chamber including a bellows, a push rod and LVDT. Each part was made of 304 L stainless steel. The average surface roughness of the parts was 1.0-14.7 {mu}m. The mock-up precisely determined an extension of a specimen by gas pressure. Finally, in-pile creep capsule was designed, fabricated and modified. High pure aluminum blocks were put in the capsule. Considering heat transfer coefficients of helium and nitrogen gases, the cooling efficiency is about 4 .deg. C at the condition of 300 .deg. C creep test. Yield strength, ultimate tensile strength and elongation at 300 .deg. C were 335 MPa, 591 MPa, 19.8%, respectively. which were lower than the values at room temperature, 353 MPa, 740 MPa, 12.5%. This study gave an important technology related to design, fabrication and performance tests of the in-pile creep test machine, which is applied to the fabrication of a special capsule and also used for the fundamental data for the fabrication of various in-pile creep capsules. 6 refs., 45 figs., 5 tabs. (Author)

  20. Monitoring and Analysis of In-Pile Phenomena in Advanced Test Reactor using Acoustic Telemetry

    International Nuclear Information System (INIS)

    Agarwal, Vivek; Smith, James A.; Jewell, James Keith

    2015-01-01

    The interior of a nuclear reactor presents a particularly harsh and challenging environment for both sensors and telemetry due to high temperatures and high fluxes of energetic and ionizing particles among the radioactive decay products. A number of research programs are developing acoustic-based sensing approach to take advantage of the acoustic transmission properties of reactor cores. Idaho National Laboratory has installed vibroacoustic receivers on and around the Advanced Test Reactor (ATR) containment vessel to take advantage of acoustically telemetered sensors such as thermoacoustic (TAC) transducers. The installation represents the first step in developing an acoustic telemetry infrastructure. This paper presents the theory of TAC, application of installed vibroacoustic receivers in monitoring the in-pile phenomena inside the ATR, and preliminary data processing results.

  1. Monitoring and Analysis of In-Pile Phenomena in Advanced Test Reactor using Acoustic Telemetry

    Energy Technology Data Exchange (ETDEWEB)

    Agarwal, Vivek [Idaho National Lab. (INL), Idaho Falls, ID (United States). Dept. of Human Factors, Controls, and Statistics; Smith, James A. [Idaho National Lab. (INL), Idaho Falls, ID (United States). Dept. of Fuel Performance and Design; Jewell, James Keith [Idaho National Lab. (INL), Idaho Falls, ID (United States). Dept. of Fuel Performance and Design

    2015-02-01

    The interior of a nuclear reactor presents a particularly harsh and challenging environment for both sensors and telemetry due to high temperatures and high fluxes of energetic and ionizing particles among the radioactive decay products. A number of research programs are developing acoustic-based sensing approach to take advantage of the acoustic transmission properties of reactor cores. Idaho National Laboratory has installed vibroacoustic receivers on and around the Advanced Test Reactor (ATR) containment vessel to take advantage of acoustically telemetered sensors such as thermoacoustic (TAC) transducers. The installation represents the first step in developing an acoustic telemetry infrastructure. This paper presents the theory of TAC, application of installed vibroacoustic receivers in monitoring the in-pile phenomena inside the ATR, and preliminary data processing results.

  2. Design Improvement of Double Pressure Vessel in the In-pile Test Section

    Energy Technology Data Exchange (ETDEWEB)

    Hong, Jintae; Heo, Sung-Ho; Joung, Chang-Young; Kim, Ka-Hye [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2014-10-15

    To carry out an irradiation test of nuclear fuels, a nuclear fuel test rig should be fabricated and installed in the in-pile test section (IPS), which is installed in the reactor hall. While carrying out an irradiation test, sealing out coolant which passes through the test rig is one of the most important issues. In particular, although the double pressure vessel is assembled with the IPS head by two o-rings and six bolts, 15.5 MPa of highly pressurized coolant leaks through the gap between the vessel and IPS head. Because the temperature of the coolant in the test loop is 300 .deg. C , and the pool of HANARO is 40 .deg. C, the double pressure vessel is necessary to insulate them. Therefore, a new design to prevent the leakage of coolant needs to be developed. In this study, EB welding technique is considered to assemble the double pressure vessel and the IPS head, and their mechanical design is modified to enable the welding process. In this study, an improved design for sealing out the coolant at the pressure boundary between the double pressure vessel and the IPS head has been developed. An EB weld is applied to seal out the pressure boundary, and its sealing performance is verified by NDE, a cross section test, and a hydraulic pressure test. From the verification test results, the improved design can be used in fabricating the IPS for a nuclear fuel irradiation test.

  3. IR1 flow tube and In-Pile Test Section Pressure drop test for the 3-Pin Fuel Test Loop

    Energy Technology Data Exchange (ETDEWEB)

    Lee, H. H.; Park, K. N.; Chi, D. Y.; Sim, B. S.; Park, S. K.; Lee, J. M.; Lee, C. Y.; Kim, H. N

    2006-02-15

    The in-pile Section (IPS) of 3-pin Fuel Test Loop(FTL) shall be installed in the vertical hole call IR1 of HANARO reactor core. In order to verify the pressure drop and flow rate both the inside region of IPS at the annular region between IPS and IR1 flow tube, a pressure drop was measured by varing the flow rate on both regions. The measured pressure drop in the annular region is 209kpa at 14.9kg/s which meets the limiting condition of operation of 200kpa. The measured pressure drop in side the IPS becomes 260.25kpa which is lower than the designed value of 306.65kpa. As the pressure drop is lower than the design value, it is quite conservative from the safety and operating point of view.

  4. In situ monitored in-pile creep testing of zirconium alloys

    Science.gov (United States)

    Kozar, R. W.; Jaworski, A. W.; Webb, T. W.; Smith, R. W.

    2014-01-01

    The experiments described herein were designed to investigate the detailed irradiation creep behavior of zirconium based alloys in the HALDEN Reactor spectrum. The HALDEN Test Reactor has the unique capability to control both applied stress and temperature independently and externally for each specimen while the specimen is in-reactor and under fast neutron flux. The ability to monitor in situ the creep rates following a stress and temperature change made possible the characterization of creep behavior over a wide stress-strain-rate-temperature design space for two model experimental heats, Zircaloy-2 and Zircaloy-2 + 1 wt%Nb, with only 12 test specimens in a 100-day in-pile creep test program. Zircaloy-2 specimens with and without 1 wt% Nb additions were tested at irradiation temperatures of 561 K and 616 K and stresses ranging from 69 MPa to 455 MPa. Various steady state creep models were evaluated against the experimental results. The irradiation creep model proposed by Nichols that separates creep behavior into low, intermediate, and high stress regimes was the best model for predicting steady-state creep rates. Dislocation-based primary creep, rather than diffusion-based transient irradiation creep, was identified as the mechanism controlling deformation during the transitional period of evolving creep rate following a step change to different test conditions.

  5. In-pile Creep Tests of Zircaloy Tubing in the Studsvik R2 Reactor. Final Report

    International Nuclear Information System (INIS)

    Tomani, Hans; Lindeloew, Ulf

    2000-12-01

    In this report are presented the findings of a prototype creep test on Zr4 guide tube specimens exposed in-pile and out-of-pile and stressed by constant bending moments. The calculated initial deflection curvature caused by the applied bending moment agrees very well with the measured initial values. Furthermore, the measurement results show excellent consistency. The dominant impact of neutron irradiation is clearly demonstrated. After 3 cycles (∼1300 hours) the irradiation creep is 4 times as large as the thermal creep. This is the case at least when fresh tube material is used. Irradiation creep progresses steadily, but the creep rate is not quite constant during the 3 irradiation cycles. The thermal creep, on the other hand, quickly saturates and there is hardly any further deflection after the second cycle for the specimen situated above the core. A limitation with the rig has been that the tube deflection became limited by the rig carrier body of the rig in the neutron flux (core) that disqualified the results of a fourth irradiation cycle actually performed in the fall of 1998. The test method appears to be suitable for testing the bending creep of different guide tube materials or designs under PWR conditions

  6. Design modification of the in-pile test section for increase of sealing capability

    Energy Technology Data Exchange (ETDEWEB)

    Hong, J T; Ahn, S H; Joung, C Y; Jeong, H Y; Lee, J M; Sim, B S [Department of Research Reactor Utilization and Development, Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)

    2012-03-15

    Since KAERI established the fuel test loop (FTL) at HANARO in 2009, KAERI has carried out several experiments to verify the performances of the equipment. Based on the experiments, the design modification of the In-Pile test Section (IPS) has been processed to improve some difficulties such as difficulty in ejecting the inner assembly of the IPS from the pressure vessel, difficulty of the sealing process of the cooling water, etc. At first, because the cooling water of HANARO in KAERI consists of an open-pool type, if a certain shock is generated during the disassembly process, the cooling water can be spattered out of the pool. Therefore, two jacking bolts will be added on the top flange part of the inner assembly to decrease the shock. Second, at the pressure boundary of the IPS where MI-cables go through, the brazing process has been used to seal out the cooling water. However, because the length of the IPS is up to 5.5 meters, it is too difficult and time consuming to carry out the brazing process at the end part of the IPS. Therefore, the brazing process will be replaced with the mechanical sealing structure to simplify the assembly process. (author)

  7. In-pile experiments and test facilities proposed for fast reactor safety

    International Nuclear Information System (INIS)

    Grolmes, M.A.; Avery, R.; Goldman, A.J.; Fauske, H.K.; Marchaterre, J.F.; Rose, D.; Wright, A.E.

    1976-01-01

    The role of in-pile experiments in support of the resolution of fast breeder reactor safety and licensing issues has been re-examined, with emphasis on key safety issues. Experiment needs have been related to the specific characteristics of these safety issues and to realistic requirements for additional test facility capabilities which can be achieved and utilized within the next ten years. It is found that those safety issues related to the energetics of core disruptive accidents have the largest impact on new facility requirements. However, utilization of existing facilities with modifications can provide for a continuing increase in experiment capability and experiment results on a timely bases. Emphasis has been placed upon maximum utilization of existing facilities and minimum requirements for new facilities. This evaluation has concluded that a new Safety Test Facility, STF, along with major modifications to the EBR II facility, improvement in TREAT capabilities, the existing Sodium Loop Safety Facility and corresponding Support Facilities provide the essential elements of the Safety Research Experiment Facilities (SAREF) required for resolution of key issues

  8. Evaluation on sweep gas pressure drop in fusion blanket mock-up for in-pile test

    Energy Technology Data Exchange (ETDEWEB)

    Ishitsuka, Etsuo; Kawamura, Hiroshi; Sagawa, Hisashi (Japan Atomic Energy Research Inst., Oarai, Ibaraki (Japan). Oarai Research Establishment); Nagakura, Masaaki; Kanzawa, Toru.

    1993-03-01

    In the ITER/CDA (Conceptual Design Activity) of a tritium breeding blanket, Japan have proposed the pebble-typed blanket. The in-pile mock-up test will be preparing in JMTR (Japan Materials Testing Reactor) for Japanese engineering design with the pebble-typed blanket. Therefore, the He sweep gas pressure drop in the pebble bed was measured for the design of the mock-up used on in-pile test. From the results of this test, it was clear that the pressure drop was predicted on Kozeny- Carman's equation within +25 [approx] -60 %, and that the pressure drop was not affected by moisture concentration (< 100 ppm). (author).

  9. Evaluation on sweep gas pressure drop in fusion blanket mock-up for in-pile test

    Energy Technology Data Exchange (ETDEWEB)

    Ishitsuka, Etsuo; Kawamura, Hiroshi; Sagawa, Hisashi [Japan Atomic Energy Research Inst., Oarai, Ibaraki (Japan). Oarai Research Establishment; Nagakura, Masaaki; Kanzawa, Toru

    1993-03-01

    In the ITER/CDA (Conceptual Design Activity) of a tritium breeding blanket, Japan have proposed the pebble-typed blanket. The in-pile mock-up test will be preparing in JMTR (Japan Materials Testing Reactor) for Japanese engineering design with the pebble-typed blanket. Therefore, the He sweep gas pressure drop in the pebble bed was measured for the design of the mock-up used on in-pile test. From the results of this test, it was clear that the pressure drop was predicted on Kozeny- Carman`s equation within +25 {approx} -60 %, and that the pressure drop was not affected by moisture concentration (< 100 ppm). (author).

  10. New Sensors for In-Pile Temperature Detection at the Advanced Test Reactor National Scientific User Facility

    International Nuclear Information System (INIS)

    Rempe, J.L.; Knudson, D.L.; Daw, J.E.; Condie, K.G.; Wilkins, S. Curtis

    2009-01-01

    The Department of Energy (DOE) designated the Advanced Test Reactor (ATR) as a National Scientific User Facility (NSUF) in April 2007 to support U.S. leadership in nuclear science and technology. As a user facility, the ATR is supporting new users from universities, laboratories, and industry, as they conduct basic and applied nuclear research and development to advance the nation's energy security needs. A key component of the ATR NSUF effort is to develop and evaluate new in-pile instrumentation techniques that are capable of providing measurements of key parameters during irradiation. This paper describes the strategy for determining what instrumentation is needed and the program for developing new or enhanced sensors that can address these needs. Accomplishments from this program are illustrated by describing new sensors now available and under development for in-pile detection of temperature at various irradiation locations in the ATR.

  11. Heat transfer in the in-pile test section and penetration region of 3-pin fuel test loop

    Energy Technology Data Exchange (ETDEWEB)

    Chi, Dae Young; Lee, Chung Young; Sim, Bong Shick; Park, Kook Nam; Park, Su Ki; Lee, Jong Min; Kim, Young Jin

    2003-12-01

    This report studies two types of normal heat transfer. One is the heat loss from the pressure vessel of In-Pile Test Section to HANARO pool water via IPS insulation gas gap. The other is the heat transfer of the Penetration Cooling Water System including the effect of the Foamglas insulator at the penetration region. The heat transfer from IPS insulation gas gap has been performed according to the detail design results from NUKEM. The heat loss also occurs at the concrete penetration region between the HANARO pool water and the FTL pipe gallery. The Foamglas insulator has been already installed at the MCW piping of the penetration region. This insulation effect has been reviewed. The Penetration Cooling Water System has been designed to fulfill the design requirement not to exceed the allowable temperature at the penetration concrete wall. The cooling ability and heat loss of PCW system has been reviewed with the insulation effect.

  12. Investigation of special capsule technologies for material in-pile irradiation test and development plan in HANARO

    Energy Technology Data Exchange (ETDEWEB)

    Cho, M. S.; Son, J. M.; Kim, D. S.; Park, S. J.; Cho, Y. G.; Seo, C. K.; Kang, Y. H. [KAERI, Taejon (Korea, Republic of)

    2002-10-01

    In-pile test for several materials such as Zr alloy, stainless steel, Cr-Ni steel etc. which are used as structural material of the advanced reactor and KNGR(Korea Next Generation Reactor) like SMART, is necessary to produce the design data for developing new reactor materials. Advanced countries like USA, Europe and Japan etc. are not only performing the simple irradiation test for materials, but developing many kinds of special capsule to perform in-pile test having special purpose. For the special test items of fuel rod, fission products, total heat generation, swelling, deformation, sweep gas, temperature ramping and BOCA etc. are being actively concerned. There are capsules measuring creep, fatigue, crack growth, and controlling fluence etc. for special irradiation test of materials. In addition, the advanced countries are developing several instrument technologies suitable for the special capsules. In HANARO, non-instrumented, instrumented material capsules and non-instrumented fuel capsule have been developed and they have been utilized in the irradiation test for users, and creep capsule loading single specimen was made and is planned to test in the reactor soon. For some forthcoming years, special capsules not only measuring creep deformation with multi-specimens, fatigue, controlling fluence but crack propagation and gas sweep considering the requirements of users will be developed in HANARO.

  13. RIA type tests in ACPR

    International Nuclear Information System (INIS)

    Preda, Marin; Stefan, Violeta; Ancuta, Mirela; Negut, Gheorghe

    2008-01-01

    For a better NPP operation fuel behavior in accidental conditions (LOCA) is of great interest. Irradiation tests in ACPR can give interesting data on the CANDU fuel behavior in such kind of accidents. These data can be used for simulation, calibration and validation of fuel computer codes. The tests were accomplished in the TRIGA Annular Core Pulse Reactor (ACPR). Reactivity insertion accidents are not specific for the CANDU reactors but this type of test can contribute to a better understanding of CANDU type fuel behavior during various conditions.The tests were accomplished in the ambient pressure and temperature with fresh fuel probes. These tests gave similar results on the clad-fuel, and clad-coolant interactions which occur in LOCA accidents. The tests will be continued with instrumentation improvements what will give better statistics and information on fuel behavior in accident conditions. The structure of the paper is the following: - 1. Introduction; - 2. Irradiation device description; - 2.1. Capsule main parameters; - 2.1.1. Initial conditions; - 2.1.2. Test conditions; - 3. Tests objectives; - 4. Test of fuel; - 5. Results; - 5.1. Temperature effects; - 5.2. Pressure effects; - 6. Conclusion

  14. Joint tests at INL and CEA of a transient hot wire needle probe for in-pile thermal conductivity measurement

    International Nuclear Information System (INIS)

    Daw, J.E.; Knudson, D.L.; Villard, J.F.; Liothin, J.; Destouches, C.; Rempe, J.L.; Matheron, P.; Lambert, T.

    2015-01-01

    Thermal conductivity is a key property that must be known for proper design, testing, and deployment of new fuels and structural materials in nuclear reactors. Thermal conductivity is highly dependent on the physical structure, chemical composition, and the state of the material. Typically, thermal conductivity changes that occur during irradiation are currently measured out-of-pile using a 'cook and look' approach. But repeatedly removing samples from a test reactor to make measurements is expensive, has the potential to disturb phenomena of interest, and only provides understanding of the sample's end state when each measurement is made. There are also limited thermo-physical property data available for advanced fuels; and such data are needed for simulation codes, the development of next generation reactors, and advanced fuels for existing nuclear plants. Being able to quickly characterize fuel thermal conductivity during irradiation can improve the fidelity of data, reduce costs of post-irradiation examinations, increase understanding of how fuels behave under irradiation, and confirm or improve existing thermal conductivity measurement techniques. This paper discusses efforts to develop and evaluate an innovative in-pile thermal conductivity sensor based on the transient hot wire thermal conductivity method (THWM), using a single needle probe (NP) containing a line heat source and thermocouple embedded in the fuel. The sensor that has been designed and manufactured by the Idaho National Laboratory (INL) includes a unique combination of materials, geometry, and fabrication techniques that make the hot wire method suitable for in-pile applications. In particular, efforts were made to minimize the influence of the sensor and maximize fuel hot-wire heating. The probe has a thermocouple-like construction with high temperature resistant materials that remain ductile while resisting transmutation and materials interactions. THWM-NP prototypes were

  15. Joint tests at INL and CEA of a transient hot wire needle probe for in-pile thermal conductivity measurement

    Energy Technology Data Exchange (ETDEWEB)

    Daw, J.E.; Knudson, D.L. [Idaho National Laboratory, Idaho Falls, ID 83415, (United States); Villard, J.F.; Liothin, J.; Destouches, C. [CEA, DEN, DER, Instrumentation Sensors and Dosimetry Laboratory, Cadarache, F-13108 St Paul-Lez-Durance, (France); Rempe, J.L. [Rempe and Associates, LLC, Idaho Falls, ID, 83404 (United States); Matheron, P. [CEA, DEN, DEC, Uranium Fuels Laboratory, Cadarache, F-13108 St Paul-Lez-Durance, (France); Lambert, T. [CEA, DEN, DEC, Innovative Fuel Design and Irradiation Laboratory, Cadarache, F-13108 St Paul-Lez-Durance, (France)

    2015-07-01

    Thermal conductivity is a key property that must be known for proper design, testing, and deployment of new fuels and structural materials in nuclear reactors. Thermal conductivity is highly dependent on the physical structure, chemical composition, and the state of the material. Typically, thermal conductivity changes that occur during irradiation are currently measured out-of-pile using a 'cook and look' approach. But repeatedly removing samples from a test reactor to make measurements is expensive, has the potential to disturb phenomena of interest, and only provides understanding of the sample's end state when each measurement is made. There are also limited thermo-physical property data available for advanced fuels; and such data are needed for simulation codes, the development of next generation reactors, and advanced fuels for existing nuclear plants. Being able to quickly characterize fuel thermal conductivity during irradiation can improve the fidelity of data, reduce costs of post-irradiation examinations, increase understanding of how fuels behave under irradiation, and confirm or improve existing thermal conductivity measurement techniques. This paper discusses efforts to develop and evaluate an innovative in-pile thermal conductivity sensor based on the transient hot wire thermal conductivity method (THWM), using a single needle probe (NP) containing a line heat source and thermocouple embedded in the fuel. The sensor that has been designed and manufactured by the Idaho National Laboratory (INL) includes a unique combination of materials, geometry, and fabrication techniques that make the hot wire method suitable for in-pile applications. In particular, efforts were made to minimize the influence of the sensor and maximize fuel hot-wire heating. The probe has a thermocouple-like construction with high temperature resistant materials that remain ductile while resisting transmutation and materials interactions. THWM-NP prototypes were

  16. In-pile test of Li 2TiO 3 pebble bed with neutron pulse operation

    Science.gov (United States)

    Tsuchiya, K.; Nakamichi, M.; Kikukawa, A.; Nagao, Y.; Enoeda, M.; Osaki, T.; Ioki, K.; Kawamura, H.

    2002-12-01

    Lithium titanate (Li 2TiO 3) is one of the candidate materials as tritium breeder in the breeding blanket of fusion reactors, and it is necessary to show the tritium release behavior of Li 2TiO 3 pebble beds. Therefore, a blanket in-pile mockup was developed and in situ tritium release experiments with the Li 2TiO 3 pebble bed were carried out in the Japan Materials Testing Reactor. In this study, the relationship between tritium release behavior from Li 2TiO 3 pebble beds and effects of various parameters were evaluated. The ( R/ G) ratio of tritium release ( R) and tritium generation ( G) was saturated when the temperature at the outside edge of the Li 2TiO 3 pebble bed became 300 °C. The tritium release amount increased cycle by cycle and saturated after about 20 pulse operations.

  17. Annealing tests of in-pile irradiated oxide coated U-Mo/Al-Si dispersed nuclear fuel

    Science.gov (United States)

    Zweifel, T.; Valot, Ch.; Pontillon, Y.; Lamontagne, J.; Vermersch, A.; Barrallier, L.; Blay, T.; Petry, W.; Palancher, H.

    2014-09-01

    U-Mo/Al based nuclear fuels have been worldwide considered as a promising high density fuel for the conversion of high flux research reactors from highly enriched uranium to lower enrichment. In this paper, we present the annealing test up to 1800 °C of in-pile irradiated U-Mo/Al-Si fuel plate samples. More than 70% of the fission gases (FGs) are released during two major FG release peaks around 500 °C and 670 °C. Additional characterisations of the samples by XRD, EPMA and SEM suggest that up to 500 °C FGs are released from IDL/matrix interfaces. The second peak at 670 °C representing the main release of FGs originates from the interaction between U-Mo and matrix in the vicinity of the cladding.

  18. In-Pile Testing and Instrumentation for Development of Generation-IV Fuels and Materials. Proceedings of a Technical Meeting

    International Nuclear Information System (INIS)

    2013-12-01

    For many years, the increase in efficiency in the production of nuclear electricity has been an economic challenge in many countries which have developed this kind of energy. The increase in fuel burnup and fuel residence time leads to a reduction in the volume of fresh fuel loaded and spent fuel discharged, respectively. More demanding nuclear fuel cycle parameters are combined with a need to operate nuclear power plants with maximal availability and load factors, in load-follow mode and with longer fuel cycles. In meeting these requirements, fuel has to operate in a demanding environment of high radiation fields, high temperatures, high mechanical stresses and high coolant flow. Requirements of increased fuel reliability and minimal fuel failures also remain in force. Under such circumstances, continuous development of more radiation resistant fuel materials, especially advanced cladding, careful and incremental examinations, and improved understanding and modelling of high burnup fuel behaviour are required. Following a recommendation of the IAEA Technical Working Group on Fuel Performance and Technology, the Technical Meeting on In-pile Testing and Instrumentation for Development of Generation-IV Fuels and Materials was held in Halden, Norway, on 21-24 August 2012. The purpose of the meeting was to review the current status and the progress in methods and technologies used for the in-pile testing of nuclear fuel achieved since the previous IAEA meeting on In-core Instrumentation and Reactor Core Assessment, also held in Halden in 2007. Emphasis was placed on advanced techniques applied for the understanding of high burnup fuel behaviour of water cooled power reactors that represent the vast majority of the current nuclear reactor fleet. However, the meeting also included papers and discussion on testing techniques applied or developed specifically for new fuel and structural materials considered for Generation-IV systems. The meeting was attended by 43

  19. Thermal-hydraulic analyses for in-pile SCWR fuel qualification test loops and SCWR material loop

    Energy Technology Data Exchange (ETDEWEB)

    Vojacek, A.; Mazzini, G.; Zmitkova, J.; Ruzickova, M. [Research Centre Rez (Czech Republic)

    2014-07-01

    One of the R&D directions of Research Centre Rez is dedicated to the supercritical water-cooled reactor concept (SCWR). Among the developed experimental facilities and infrastructure in the framework of the SUSEN project (SUStainable ENergy) is construction and experimental operation of the supercritical water loop SCWL focusing on material tests. At the first phase, this SCWL loop is assembled and operated out-of-pile in the dedicated loop facilities hall. At this out-of-pile operation various operational conditions are tested and verified. After that, in the second phase, the SCWL loop will be situated in-pile, in the core of the research reactor LVR-15, operated at CVR. Furthermore, it is planned to carry out a test of a small scale fuel assembly within the SuperCritical Water Reactor Fuel Qualification Test (SCWR-FQT) loop, which is now being designed. This paper presents the results of the thermal-hydraulic analyses of SCWL loop out-of-pile operation using the RELAP5/MOD3.3. The thermal-hydraulic modeling and the performed analyses are focused on the SCWL loop model validation through a comparison of the calculation results with the experimental results obtained at various operation conditions. Further, the present paper focuses on the transient analyses for start-up and shut-down of the FQT loop, particularly to explore the ability of system codes ATHLET 3.0A to simulate the transient between subcritical conditions and supercritical conditions. (author)

  20. In-Pile Experiment of a New Hafnium Aluminide Composite Material to Enable Fast Neutron Testing in the Advanced Test Reactor

    Energy Technology Data Exchange (ETDEWEB)

    Donna Post Guillen; Douglas L. Porter; James R. Parry; Heng Ban

    2010-06-01

    A new hafnium aluminide composite material is being developed as a key component in a Boosted Fast Flux Loop (BFFL) system designed to provide fast neutron flux test capability in the Advanced Test Reactor. An absorber block comprised of hafnium aluminide (Al3Hf) particles (~23% by volume) dispersed in an aluminum matrix can absorb thermal neutrons and transfer heat from the experiment to pressurized water cooling channels. However, the thermophysical properties, such as thermal conductivity, of this material and the effect of irradiation are not known. This paper describes the design of an in-pile experiment to obtain such data to enable design and optimization of the BFFL neutron filter.

  1. In-pile data analysis of the comparative WWER/PWR test IFA-503.1. Final report.

    Energy Technology Data Exchange (ETDEWEB)

    Volkov, B.; Devold, H.; Ryazantzev, E.; Yakovlev, V.

    1999-04-15

    The comparative WWER/PWR test in IFA-503.1 was commenced in July 1995 and successfully finished at the end of November 1998. The main objective of the test was generation of representative and comparative data of standard WWER-440 fuel fabricated at the 'MSZ' Electrostal (Russia) and PWR type fuel manufactured at IFE Kjeller (Norway). The test assembly comprised two clusters, each with 3 WWER rods and 3 PWR type rods. Eight rods with two types of fuel were instrumented with expansion thermometers, four rods were equipped with both fuel stack elongation detectors and pressure transducers. All sensors worked satisfactorily during the test. The average burnups achieved in the lower and upper clusters were around 25 and 20 MWd/kgUO{sub 2}, respectively. Some difference in densification of the two types of fuel was revealed during the first irradiation period. However, the fuel temperatures and commencement of fuel stack swelling were similar despite this fact. At the end of the test the rig was moved to a higher flux position in the HBWR core with the aim of promoting FGR and to compare the behaviour of the two types of fuel under higher power. Pressure measurements indicated a comparable low FGR (around 1 percent) in both types of rods. The centreline temperatures measured in the PWR rods were very close to the Halden FGR threshold whilst the WWER fuel temperatures were slightly lower. Despite the differences found in the behaviour of the two types of fuel during the test, the analysis of the in-pile data showed that these differences would not affect the fuel efficiency, at least, up to the burnup achieved in the test. It is supposed that these differences can be related to the fuel microstructure, in particular to the fuel grain and pore sizes (author) (ml)

  2. In-pile data analysis of the comparative WWER/PWR test IFA-503.1. Final report

    Energy Technology Data Exchange (ETDEWEB)

    Volkov, B.; Devold, H.; Ryazantzev, E.; Yakovlev, V

    1999-04-15

    The comparative WWER/PWR test in IFA-503.1 was commenced in July 1995 and successfully finished at the end of November 1998. The main objective of the test was generation of representative and comparative data of standard WWER-440 fuel fabricated at the 'MSZ' Electrostal (Russia) and PWR type fuel manufactured at IFE Kjeller (Norway). The test assembly comprised two clusters, each with 3 WWER rods and 3 PWR type rods. Eight rods with two types of fuel were instrumented with expansion thermometers, four rods were equipped with both fuel stack elongation detectors and pressure transducers. All sensors worked satisfactorily during the test. The average burnups achieved in the lower and upper clusters were around 25 and 20 MWd/kgUO{sub 2}, respectively. Some difference in densification of the two types of fuel was revealed during the first irradiation period. However, the fuel temperatures and commencement of fuel stack swelling were similar despite this fact. At the end of the test the rig was moved to a higher flux position in the HBWR core with the aim of promoting FGR and to compare the behaviour of the two types of fuel under higher power. Pressure measurements indicated a comparable low FGR (around 1 percent) in both types of rods. The centreline temperatures measured in the PWR rods were very close to the Halden FGR threshold whilst the WWER fuel temperatures were slightly lower. Despite the differences found in the behaviour of the two types of fuel during the test, the analysis of the in-pile data showed that these differences would not affect the fuel efficiency, at least, up to the burnup achieved in the test. It is supposed that these differences can be related to the fuel microstructure, in particular to the fuel grain and pore sizes (author) (ml)

  3. In-pile test of Li{sub 2}TiO{sub 3} pebble bed with neutron pulse operation

    Energy Technology Data Exchange (ETDEWEB)

    Tsuchiya, K. E-mail: tsuchiya@oarai.jaeri.go.jp; Nakamichi, M.; Kikukawa, A.; Nagao, Y.; Enoeda, M.; Osaki, T.; Ioki, K.; Kawamura, H

    2002-12-01

    Lithium titanate (Li{sub 2}TiO{sub 3}) is one of the candidate materials as tritium breeder in the breeding blanket of fusion reactors, and it is necessary to show the tritium release behavior of Li{sub 2}TiO{sub 3} pebble beds. Therefore, a blanket in-pile mockup was developed and in situ tritium release experiments with the Li{sub 2}TiO{sub 3} pebble bed were carried out in the Japan Materials Testing Reactor. In this study, the relationship between tritium release behavior from Li{sub 2}TiO{sub 3} pebble beds and effects of various parameters were evaluated. The (R/G) ratio of tritium release (R) and tritium generation (G) was saturated when the temperature at the outside edge of the Li{sub 2}TiO{sub 3} pebble bed became 300 deg. C. The tritium release amount increased cycle by cycle and saturated after about 20 pulse operations.

  4. Physics design of fast reactor safety test facilities for in-pile experiments

    International Nuclear Information System (INIS)

    Travelli, A.; Matos, J.E.; Snelgrove, J.L.; Shaftman, D.H.; Tzanos, C.P.; Lam, S.K.; Pennington, E.M.; Woodruff, W.L.

    1976-01-01

    A determined effort to identify and resolve current Fast Breeder Reactor safety testing needs has recently resulted in a number of conceptual designs for FBR safety test facilities which are very complex and diverse both in their features and in their purpose. The paper discusses the physics foundations common to most fast reactor safety test facilities and the constraints which they impose on the design. The logical evolution, features, and capabilities of several major conceptual designs are discussed on the basis of this common background

  5. Conceptual Design for the In-Pile Test Section(IPS) Improvement

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Jong Min; Shim, Bong Sik; Lee, Chung Young; Chi, Dae Young; Park, Su Ki; Ahn, Sung Ho; Kim, Young Ki; Lee, Kye Hong; Kim, Kwan Hyun

    2009-01-15

    Conceptual design on the IPS, instrumentation and 1/4' Tubing, test fuel supports, test fuel inspection station and inner assembly O-ring replacement was suggested for their improvement. There is a need Jacking bolt on the Top flange for the inner assembly disassemble from the outer assembly and the replacement about the top flange O-ring to metal gasket to secure pressure boundary. Mechanical sealing was suggested instead of brazing. Instrumentation and tubing route should be modified for the reduction of bending and protection from unexpected occasion. Concept on the test fuel inspection station under the consideration of canal dimension. Top flange Bolt handling tool, O-ring replacement platform and O-ring replacement tool was designed for the O-ring replacement at the inner assembly.

  6. Safety analyses for an in-pile SCWR fuel qualification test loop

    Energy Technology Data Exchange (ETDEWEB)

    Schulenberg, T.; Raque, M. [Karlsruhe Inst. of Tech., Karlsruhe (Germany)

    2014-07-01

    As a nuclear facility cooled with supercritical water has never been built nor operated in the past, the planned SCWR fuel qualification test will give the first experience with supercritical water-cooled nuclear systems in general. With a fuel inventory of almost 1 kg of UO{sub 2} with almost 20% enrichment, the supercritical pressure test section inside a low pressure, pool type research reactor needs to be cooled properly even in case of a number of postulated design basis accidents. Depressurization systems and emergency cooling systems will need to be designed with similar reliability as for a prototype reactor to ensure the integrity of barriers retaining the radioactive material. The paper reports about the safety concept and summarizes the safety analyses which have been performed in this context. (author)

  7. In-pile loop OWL-2 and irradiation tests done with it

    International Nuclear Information System (INIS)

    Suzuki, Shinobu; Ikeshima, Yoshiaki; Kawano, Masakatsu; Watanabe, Hiroyuki; Sato, Hitoshi; Tanaka, Isao

    1990-11-01

    The OWL-2 which was built in the JMTR as the biggest water loop in Japan has been operating for irradiation service since February 1972. The desired objective of the OWL-2, contributing to the development of various nuclear fuels and materials for the light water power reactor and to reactor engineering, has been so fully achieved that the OWL-2 is planned to be dismantled. After the dismantling, a loop, needed for the research and development of the breeding blanket for the fusion reactor, is going to be installed in place of the OWL-2 as a part of the JMTR Modification Program. This paper deals with the history of the OWL-2 with an emphasis on the technical affairs taken into consideration when designing the OWL-2, the irradiation tests, development of the turbine flowmeter, results of the surveillance test of the material of the in-reactor tube, the knowledge gained in the course of the investigation into the cause of transgranular stress corrosion cracking (TGSCC) which developed in the wall of the in-reactor tube, and countermeasures taken to prevent TGSCC from recurring. (author)

  8. RIA tests in CABRI with MOX fuel

    International Nuclear Information System (INIS)

    Schmitz, F.; Papin, J.; Gonnier, C.

    2000-01-01

    Three MOX-fuel tests have been successfully performed within the framework of the CABRI REP-Na test program. From the experimental findings which are presently available, no evidence for thermal effects resulting from the heterogeneous nature of the fuel can be given. There are very clear hints however that fission gas effects are enhanced with regard to the behaviour of UO 2 . The clad rupture observed in REP-Na 7 is of different nature than the failures observed in Cabri tests with UO 2 fuel. Failures of UO 2 fuel rods only occurred when the clad mechanical properties were severely affected by the presence of hydride blisters, while in REP-Na 7 a clear indication is made that the loading potential of the MOX fuel pellets was high enough to break a sound cladding. Concerning the transient fuel behaviour after reaching the critical heat-flux under reactor typical conditions (pressure, temperature and flow), no data base could be provided by the tests in the present sodium test loop (as for the UO 2 fuel behaviour). The IPSN project to implement into the Cabri reactor a pressurised water loop which will allow to simulate the complete RIA accident sequence under PWR reactor typical conditions, aims at providing this missing data base. (author)

  9. In-Pile Sub-Miniature Fission Chambers Testing in BR2

    Science.gov (United States)

    Vermeeren, L.; Wéber, M.; Blandin, Ch.; Breaud, S.

    2003-06-01

    Three innovative sub-miniature fission chambers (SMFC), designed and manufactured at the Nuclear Measurement Systems Laboratory (LSMN) of CEA/Cadarache, were extensively tested in the BR2 research reactor at SCK•CEN, Mol. We present the experimental results for the (thermal) neutron sensitivity, the gamma-induced signal, the signal due to activation, the current picked up by the signal cable, the global current/voltage characteristics and the long term behaviour up to a thermal neutron fluence of 2.7·1021 n/cm2. We also compare the data with results from calculations with our FCD computer code. The onset of the saturation domain is well predicted by FCD; the neutron sensitivities can be accounted for perfectly after a refinement of the FCD model.

  10. In-pile testing of ITER first wall mock-ups at relevant thermal loading conditions

    Science.gov (United States)

    Litunovsky, N.; Gervash, A.; Lorenzetto, P.; Mazul, I.; Melder, R.

    2009-04-01

    The paper describes the experimental technique and preliminary results of thermal fatigue testing of ITER first wall (FW) water-cooled mock-ups inside the core of the RBT-6 experimental fission reactor (RIAR, Dimitrovgrad, Russia). This experiment has provided simultaneous effect of neutron fluence and thermal cycling damages on the mock-ups. A PC-controlled high-temperature graphite ohmic heater was applied to provide cyclic thermal load onto the mock-ups surface. This experiment lasted for 309 effective irradiation days with a final damage level (CuCrZr) of 1 dpa in the mock-ups. About 3700 thermal cycles with a heat flux of 0.4-0.5 MW/m 2 onto the mock-ups were realized before the heater fails. Then, irradiation was continued in a non-cycling mode.

  11. In-pile instrumentation improvements for fuel irradiations in test reactor

    International Nuclear Information System (INIS)

    Blanc, J.Y.; Bernard, J.L.; Estrade, J.; Geoffroy, G.

    1996-01-01

    Knowledge of fuel limits and safety margins in normal and off-normal transients in nuclear power plants remains a constant preoccupation for electricity producers and fuel manufacturers. Accurate determination of such limits, through fuel irradiation testing in the OSIRIS reactor at Saclay is closely linked to the reliability of appropriate instrumentation techniques. Two paths are currently followed to obtain short experimental rods: segmented fuel coming directly from power plants, or re-fabrication of rods in hot cells with our FABRICE process. It can be associated with instrumentation such as fuel centerline thermocouple in annular pellets, pressure transducer or fission gas release measurement by gamma-spectrometry using helium sweeping, in analytic experiments. Our present development, to be implemented in 1993, is the the centerline instrumentation of a fuel column with solid pellets. Inserting the thermocouple requires a cold drilling machine, using CO 2 freezing of broken UO 2 (with liquid nitrogen). During the fuel rod irradiation itself, we try to lower the uncertainties associated to power determination, using thermal balance or neutronic calibration, or even gamma spectrometry. A description of the new test train designed for the ISABELLE water loop in OSIRIS is given, with special emphasis on instrumentation: a LVDT for measuring fuel rod elongation and eventual clad failure, and increased number and better localization of thermocouples and SPDN. The third part is devoted to the measurements by optical microdensitometry of neutron radiographs of the fuel pellet dish modification after irradiation. Dishes are generally disappearing through thermal and mechanical deformation of the pellet, and this can eventually be modelized to better understand pellet-cladding mechanical interaction. (author). 3 refs, 5 figs

  12. Development of in-pile instruments for fuel and material irradiation tests

    Energy Technology Data Exchange (ETDEWEB)

    Shibata, Akira; Kitagishi, Shigeru; Kimura, Nobuaki; Saito, Takashi; Nakamura, Jinichi; Ohmi, Masao; Izumo, Hironobu; Tsuchiya, Kunihiko [Japan Atomic Energy Agency, Oarai Research and Development Center, Oarai, Ibaraki (Japan)

    2012-03-15

    To get measurement data with high accuracy for fuel and material behavior studies in irradiation tests, two kinds of measuring equipments have been developed; these are the Electrochemical Corrosion Potential (ECP) sensor and the Linear Voltage Differential Transformer (LVDT) type gas pressure gauge. The ECP sensor has been developed to determine the corrosive potential under high temperature and high pressure water conditions. The structure of the joining parts was optimized to avoid stress concentration. The ECP sensor showed enough performance at 288degC and at 9MPa conditions. The LVDT type rod inner gas pressure gauge has been developed to measure gas pressure in a fuel element during neutron irradiation. To perform stable measurements with high accuracy under high temperature, high pressure and high dosed environment, the coil material of LVDT was changed to MI cable. As a result of this development, the LVDT type gas pressure gauge showed high accuracy within 1.8% of a full scale, and good stability. (author)

  13. Development of in-pile instruments for fuel and material irradiation tests

    International Nuclear Information System (INIS)

    Shibata, Akira; Kitagishi, Shigeru; Kimura, Nobuaki; Saito, Takashi; Nakamura, Jinichi; Ohmi, Masao; Izumo, Hironobu; Tsuchiya, Kunihiko

    2012-01-01

    To get measurement data with high accuracy for fuel and material behavior studies in irradiation tests, two kinds of measuring equipments have been developed; these are the Electrochemical Corrosion Potential (ECP) sensor and the Linear Voltage Differential Transformer (LVDT) type gas pressure gauge. The ECP sensor has been developed to determine the corrosive potential under high temperature and high pressure water conditions. The structure of the joining parts was optimized to avoid stress concentration. The ECP sensor showed enough performance at 288degC and at 9MPa conditions. The LVDT type rod inner gas pressure gauge has been developed to measure gas pressure in a fuel element during neutron irradiation. To perform stable measurements with high accuracy under high temperature, high pressure and high dosed environment, the coil material of LVDT was changed to MI cable. As a result of this development, the LVDT type gas pressure gauge showed high accuracy within 1.8% of a full scale, and good stability. (author)

  14. Study of In-Pile test facility for fast reactor safety research: performance requirements and design features

    Energy Technology Data Exchange (ETDEWEB)

    Nonaka, N.; Kawatta, N.; Niwa, H.; Kondo, S.; Maeda, K

    1996-12-31

    This paper describes a program and the main design features of a new in-pile safety facility SERAPH planned for future fast reactor safety research. The current status of R and D on technical developments in relation to the research objectives and performance requirements to the facility design is given.

  15. Verification of tritium production evaluation procedure using Monte Carlo code MCNP for in-pile test of fusion blanket with JMTR

    Energy Technology Data Exchange (ETDEWEB)

    Nagao, Y. E-mail: nagao@jmtr.oarai.jaeri.go.jp; Nakamichi, K.; Tsuchiya, M.; Ishitsuka, E.; Kawamura, H

    2000-11-01

    To evaluate exactly the total amount of tritium production in tritium breeding materials during in-pile test with JMTR, the 'tritium monitor' has been produced and evaluation of total tritium generation was done by using 'tritium monitor' in preliminary in-pile mock-up, and verification of procedure concerning tritium production evaluation was conducted by using Monte Carlo code MCNP and nuclear cross section library of FSXLIBJ3R2. Li-Al alloy (Li 3.4 wt.%, 95.5% enrichment of {sup 6}Li) was selected as tritium monitor material for the evaluation on the total amount of tritium production in high {sup 6}Li enriched materials. From the results of preliminary experiment, calculated amounts of total tritium production at each 'tritium monitor', which was installed in the preliminary in-pile mock-up, were about 50-290% higher than the measured values. Concerning tritium measurement, increase of measurement error in tritium leak form measuring system to measure small amount of tritium (0.2-0.7 mCi in tritium monitor) was found in the results of present experiment. The tendency for overestimation of calculated thermal neutron flux in the range of 1-6x10{sup 13} n cm{sup -2} per s was found in JMTR and the reason may be due to the beryllium cross section data base in JENDL3.2.

  16. Verification of tritium production evaluation procedure using Monte Carlo code MCNP for in-pile test of fusion blanket with JMTR

    International Nuclear Information System (INIS)

    Nagao, Y.; Nakamichi, K.; Tsuchiya, M.; Ishitsuka, E.; Kawamura, H.

    2000-01-01

    To evaluate exactly the total amount of tritium production in tritium breeding materials during in-pile test with JMTR, the 'tritium monitor' has been produced and evaluation of total tritium generation was done by using 'tritium monitor' in preliminary in-pile mock-up, and verification of procedure concerning tritium production evaluation was conducted by using Monte Carlo code MCNP and nuclear cross section library of FSXLIBJ3R2. Li-Al alloy (Li 3.4 wt.%, 95.5% enrichment of 6 Li) was selected as tritium monitor material for the evaluation on the total amount of tritium production in high 6 Li enriched materials. From the results of preliminary experiment, calculated amounts of total tritium production at each 'tritium monitor', which was installed in the preliminary in-pile mock-up, were about 50-290% higher than the measured values. Concerning tritium measurement, increase of measurement error in tritium leak form measuring system to measure small amount of tritium (0.2-0.7 mCi in tritium monitor) was found in the results of present experiment. The tendency for overestimation of calculated thermal neutron flux in the range of 1-6x10 13 n cm -2 per s was found in JMTR and the reason may be due to the beryllium cross section data base in JENDL3.2

  17. In-pile and out-of-pile testing of a molybdenum-uranium dioxide cermet fueled themionic diode

    Science.gov (United States)

    Diianni, D. C.

    1972-01-01

    The behavior of Mo-UO2 cermet fuel in a diode for thermionic reactor application was studied. The diode had a Mo-0.5 Ti emitter and niobium collector. Output power ranged from 1.4 to 2.8 W/cm squared at emitter and collector temperatures of 1500 deg and 540 C. Thermionic performance was stable within the limits of the instrumentation sensitivity. Through 1000 hours of in-pile operation the emitter was dimensionally stable. However, some fission gases (15 percent) leaked through an inner clad imperfection that occurred during fuel fabrication.

  18. Pre-test prediction and post-test analysis of PWR fuel rod ballooning in the MT-3 in-pile LOCA simulation experiment in the NRU reactor

    International Nuclear Information System (INIS)

    Donaldson, A.T.; Horwood, R.A.; Healey, T.

    1983-01-01

    The USNRC and the UKAEA have jointly funded a series of in-pile LOCA simulation experiments in the Canadian NRU reactor in order to secure further information on the thermal hydraulic and clad deformation response of PWR fuel rod bundles. Test MT-3 in the series was performed using reflood rate and rod internal pressure conditions specified by the UK nuclear industry. The parameters were selected to ensure the development of a near-isothermal clad temperature history during which zircaloy was required to balloon and rupture near the alpha-alpha/beta phase transition. Specification of the reflood rate conditions was assisted by the performance of a precursor test on an unpressurised rod bundle and by complementary application of appropriate thermal hydraulic analyses. Identification of the rod internal pressure needed to cause ballooning and rupture was achieved using a creep deformation model, BALLOON, in conjunction with the clad thermal history defined by the prior thermal hydraulic test. This paper presents the basis of the BALLOON analysis and describes its application in calculating the fill gas pressure for rods MT-3, their axial ballooning profile and the clad temperature at peak radial strain elevations. (author)

  19. Test-element assembly and loading parameters for the in-pile test of HCPB ceramic pebble beds

    Energy Technology Data Exchange (ETDEWEB)

    Laan, J.G. van der E-mail: vanderlaan@nrg-nl.com; Boccaccini, L.V.; Conrad, R.; Fokkens, J.H.; Jong, M.; Magielsen, A.J.; Pijlgroms, B.J.; Reimann, J.; Stijkel, M.P.; Malang, S

    2002-11-01

    In the framework of developing the helium cooled pebble-bed (HCPB) blanket an irradiation test of pebble-bed assemblies is prepared at the HFR Petten. The test objective is to concentrate on the effect of neutron irradiation on the thermal-mechanical behaviour of the HCPB breeder pebble-bed at DEMO representative levels of temperature and defined thermal-mechanical loads. The paper reports on the project status, and presents the results of pre-tests, material characteristics, the manufacturing of the pebble-bed assemblies, and the nuclear and thermo-mechanical loading parameters.

  20. Manufacturing of In-Pile Test Section(IPS) Mock-up for the 3-Pin Fuel Test Loop

    Energy Technology Data Exchange (ETDEWEB)

    Lee, J. M.; Park, K. N.; Chi, D. Y. (and others)

    2005-10-15

    Manufacturing process of IPS Mock-up was initiated in late of 2003 with DAEWOO Precision industries Company. Manufacturing drawings due to detail drawings are composed of Outer assembly and Inner assembly. Welding of IPS Mock-up was performed by the GMAW(Gas Metal Arc Welding) process. After the welding process, non-destructive examination was conducted. Leak test was performed to the Main cooling water part and Neon gas inter-space gap part by the He gas injection with the pressure of 6.0 kg{sub f}/cm{sup 2} and 30 minutes holding time. the result was shown that there was no leak at the Neon gas inter-space gap part but leak was occurred at Main cooling water part according to imperfect screw of purge plug. so, it was re-finished and test was performed to certify the leak tightness. To satisfy the HANARO Limiting Operation Condition, IPS should be tested ahead of installation at the HANARO reactor by the use of test facilities. IPS Mock-up and its test facilities will be designed and used for the test of 'HANARO flow tube pressure drop', 'IPS inner pressure drop' and 'IPS inner vibration'.

  1. In-pile TREAT Test L04: simulating a lead sub-assembly in an unprotected LMFBR loss-of-coolant accident

    International Nuclear Information System (INIS)

    Tylka, J.P.; Bauer, T.H.; Wright, A.E.; Davies, A.L.; Herbert, R.; Woods, W.J.

    1983-01-01

    Test L04 in the PFR/TREAT series is the first multi-pin, in-pile simulation of a LMFBR transient undercooling/overpower (TUCOP) accident using full length prototypic fuel irradiated in a fast reactor. L04 is a gridded 7-pin bundle test performed in the ANL Mk-III integral loop in a flowing sodium environment and uses prototypic, bottom plenum, UK reactor fuel, preirradiated in the PFR to an axial peak burn-up of 4.2 a/o. The objective of L04 was the study, by simulation, of coolant voiding and fuel motion during the initiating phase of a hypothetical TUCOP accident in a large LMFBR. Test L04 is intended to study the behavior of a centrally located, lead subassembly with the highest power-to-flow ratio

  2. In-pile test results of U-silicide or U-nitride coated U-7Mo particle dispersion fuel in Al

    Science.gov (United States)

    Kim, Yeon Soo; Park, J. M.; Lee, K. H.; Yoo, B. O.; Ryu, H. J.; Ye, B.

    2014-11-01

    U-silicide or U-nitride coated U-Mo particle dispersion fuel in Al (U-Mo/Al) was in-pile tested to examine the effectiveness of the coating as a diffusion barrier between the U-7Mo fuel kernels and Al matrix. This paper reports the PIE data and analyses focusing on the effectiveness of the coating in terms of interaction layer (IL) growth and general fuel performance. The U-silicide coating showed considerable success, but it also provided evidence for additional improvement for coating process. The U-nitride coated specimen showed largely inefficient results in reducing IL growth. From the test, important observations were also made that can be utilized to improve U-Mo/Al fuel performance. The heating process for coating turned out to be beneficial to suppress fuel swelling. The use of larger fuel particles confirmed favorable effects on fuel performance.

  3. In-pile test results of U-silicide or U-nitride coated U-7Mo particle dispersion fuel in Al

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Yeon Soo, E-mail: yskim@anl.gov [Argonne National Laboratory, 9700 South Cass Avenue, Argonne, IL 60439 (United States); Park, J.M.; Lee, K.H.; Yoo, B.O. [Korea Atomic Energy Research Institute, 989-111 Daedeokdaero, Yuseong-gu, Daejeon 305-353 (Korea, Republic of); Ryu, H.J. [Dept. of Nuclear and Quantum Engineering, Korea Advanced Institute of Science and Technology, 291 Daehak-ro, Yuseong-gu, Daejeon 305-701 (Korea, Republic of); Ye, B. [Argonne National Laboratory, 9700 South Cass Avenue, Argonne, IL 60439 (United States)

    2014-11-15

    U-silicide or U-nitride coated U-Mo particle dispersion fuel in Al (U-Mo/Al) was in-pile tested to examine the effectiveness of the coating as a diffusion barrier between the U-7Mo fuel kernels and Al matrix. This paper reports the PIE data and analyses focusing on the effectiveness of the coating in terms of interaction layer (IL) growth and general fuel performance. The U-silicide coating showed considerable success, but it also provided evidence for additional improvement for coating process. The U-nitride coated specimen showed largely inefficient results in reducing IL growth. From the test, important observations were also made that can be utilized to improve U-Mo/Al fuel performance. The heating process for coating turned out to be beneficial to suppress fuel swelling. The use of larger fuel particles confirmed favorable effects on fuel performance.

  4. The MOX fuel behaviour test IFA-597.4/.5/.6/.7; Summary of in-pile fuel temperature and gas release data

    Energy Technology Data Exchange (ETDEWEB)

    Koike, Hisashi

    2003-11-15

    It is considered important to study the in-reactor behaviour of MOX fuel in order to enhance the database on such fuel. For this reason, IFA-597.4/.5/.6/.7 were included in the joint research programme of the Halden Project. The series of tests, containing two MIMAS-MOX fuel rods, both equipped with a fuel centre thermocouple and a pressure bellows transducer, has been irradiated in the Halden Reactor since July 1997 under HBWR conditions. The objectives of the test series were to study the thermal and fission gas release (FGR) behaviour of MOX fuel and to explore potential differences in behaviour between solid and hollow pellets. One of the rods had mainly solid pellets, while the other contained only hollow pellets. Both rods had an initial Pu-fissile enrichment of 6.07%. The cladding outside diameter was 9.50 mm, and the initial fuel-clad gap was 180 mum. In the course of the test, power upratings for FGR studies of the MOX fuel were planned at burnup intervals of about 10 MWd/kg MOX. The power uprating was successfully performed at approx10 MWd/kg MOX, where the estimated fuel peak temperature of the solid pellets exceeded the FGR threshold temperature for UO{sub 2} fuel, while that of the hollow pellets remained below the threshold. For the solid fuel, the temperature at onset of FGR was consistent with the empirical threshold temperature for UO{sub 2} fuel. For the hollow fuel, gas release was observed at temperatures below the threshold. FGRs at the end-of-life were approx17% for the solid pellet rod and approx14% for the hollow pellet rod, respectively. As a result of discussions in HPG meetings, IFA-597.7 was unloaded in January 2002. PIE was carried out to check in-pile pressure measurements and examine fuel structural characteristics. The discharge burn-up of the MOX fuel was 32 MWd/kg MOX as determined from in-pile power data. This report supersedes HWR-712 (June 2002) previously issued on in-pile data from IFA-597.4/5/6/7. (Author)

  5. In-pile testing of ITER first wall mock-ups at relevant thermal loading conditions in the LVR-15 nuclear research reactor

    Energy Technology Data Exchange (ETDEWEB)

    Kysela, Jan [Research Centre Rez, Hlavni 130, 250 68 Husinec-Rez (Czech Republic); Entler, Slavomir, E-mail: slavomir.entler@cvrez.cz [Research Centre Rez, Hlavni 130, 250 68 Husinec-Rez (Czech Republic); Vsolak, Rudolf; Klabik, Tomas [Research Centre Rez, Hlavni 130, 250 68 Husinec-Rez (Czech Republic); Zlamal, Ondrej [CEZ, Duhova 2/1444, 140 53 Praha 4 (Czech Republic); Bellin, Boris; Zacchia, Francesco [Fusion for Energy, Josep Pla, 2, Torres Diagonal Litoral B3, 08019 Barcelona (Spain)

    2015-10-15

    Highlights: • Irradiated thermal fatigue testing of the ITER primary first wall mock-ups. • Cyclic heat flux of 0.5 MW/m{sup 2} in the neutron field of the nuclear reactor core. • 17,040 thermal cycles. • Radiation damage in the range of 0.41–1.17 dpa depending on the material. - Abstract: The TW3 in-pile rig enabled the thermal fatigue testing of ITER primary first wall mock-ups in the core of the nuclear reactor. This experiment investigated the neutron irradiation influence on the design performance under high heat flux testing. A thermal flux of 0.5 MW/m{sup 2} in the neutron field of the core of the LVR-15 nuclear reactor was applied. Within the scope of the tests with simultaneous neutron irradiation, the TW3 rig reached a record of 17,040 thermal cycles with the radiation damage in the range of 0.41–1.17 dpa depending on the material. Even after a high number of thermal cycles, while being irradiated by neutrons, no damage of the tested mock-ups was visually observed. Further testing and analysis will follow in the Forschungszentrum Juelich.

  6. Experiment data report for Test RIA 1-2 (Reactivity Initiated Accident Test Series)

    International Nuclear Information System (INIS)

    Zimmermann, C.L.; White, C.E.; Evans, R.P.

    1979-06-01

    Recorded test data are presented for the second of six planned tests in the Reactivity Initiated Accident (RIA) Test Series I, Test RIA 1-2. This test, conducted at the Power Burst Facility, had the following objectives: (1) characterize the response of preirradiated fuel rods during an RIA event conducted at boiling water reactor hot-startup conditions; and (2) evaluate the effect of rod internal pressure on preirradiated fuel rod response during an RIA event. The data from Test RIA 1-2 are graphed in engineering units and have been appraised for quality and validity. These uninterpreted data are presented for use in the nuclear fuel behavior research field before detailed analysis and interpretation have been completed

  7. Simulation of the in-pile test Phebus-FPT3 using ASTEC V2 and ATHLET-CD 2.1A

    Energy Technology Data Exchange (ETDEWEB)

    Kruse, Philipp; Koch, Marco K. [Bochum Univ. (Germany). Chair of Energy Systems and Energy Economics

    2011-07-01

    The Phebus-FPT programme, initiated in 1988 by the 'Institut de Radioprotection et de Surete Nucleaire' (IRSN) and the Joint Research Centre (JRC) of the European Commission (EC), was performed in the Phebus facility operated by 'Commissariat a'Energie Atomique' (CEA). The facility represent a 900 MWe Pressurized Water Reactor (PWR) scaled down by a factor 1:5000 which objective is to study fuel degradation and the subsequent release, transport and retention of fission products, structure, control rod and fuel materials, in case of a severe accident. The Phebus-FPT programme consists of integral in-pile tests, varying the fuel burn-up and geometry, the control rod nature, the thermal hydraulic conditions in the bundle and through the experimental circuit as well as in the containment. In primary, the integral experiments should outline a detailed description of the main phenomena of core degradation, fission product release and transport as well as radionuclide interactions. Due to that it is possible to analyse the physical and chemical processes due to a severe accident. With the ascertained data, an evaluation of the accident management measures could be made as well. A secondary aim of the Phebus tests was to enable model development and evaluation of severe accident codes such like ASTEC and ATHLET-CD. (orig.)

  8. Status of the in-pile test of HCPB pebble-bed assemblies in the HFR Petten

    Energy Technology Data Exchange (ETDEWEB)

    Laan, J.G. van der; Fokkens, J.H.; Hofmans, H.E.; Jong, M.; Magielsen, A.J.; Pijlgroms, B.J.; Stijkel, M.P. [NRG, Petten (Netherlands); Conrad, R. [JRC, Inst. for Energy, Petten (Netherlands); Malang, S.; Reimann, J. [FZK, Karlsruhe (Germany); Roux, N. [CEA Saclay (France)

    2002-06-01

    In the framework of developing the helium cooled pebble-bed (HCPB) blanket an irradiation test of pebble-bed assemblies is prepared at the HFR Petten. The test objective is to concentrate on the effect of neutron irradiation on the thermal-mechanical behaviour of the HCPB breeder pebble-bed at DEMO representative levels of temperature and defined thermal-mechanical loads. The basic test elements are EUROFER-97 cylinders with a horizontal bed of ceramic breeder pebbles sandwiched between two beryllium beds. The pebble beds are separated by EUROFER-97 steel plates. The heat flow is managed such as to have a radial temperature distribution in the ceramic breeder pebble-bed as flat as reasonably possible. The paper reports on the project status, and presents the results of pre-tests, material characteristics, the manufacturing of the pebble-bed assemblies, and the nuclear and thermo-mechanical loading parameters. (orig.)

  9. Neutronic design of pulse operation simulating device for in-pile functional test of fusion blanket by MCNP

    Energy Technology Data Exchange (ETDEWEB)

    Nagao, Yoshiharu; Nakamichi, Masaru; Kawamura, Hiroshi [Japan Atomic Energy Research Inst., Oarai, Ibaraki (Japan)

    2000-03-01

    The pulse operation of a fusion reactor can be simulated in a fission reactor by controlling the neutron flux entering a test section by using a rotating 'hollow cylinder with window' made of hafnium. The rotating cylinder is installed between the test section and the fixed outer neutron absorber cylinder and is also made of hafnium with an opening in the direction to the core center. For gathering engineering data for the tritium breeding blanket such as characteristics of temperature change, tritium release and recovery, etc., it is desirable that the ratio of minimum to maximum thermal neutron fluxes is greater than 1:10. Design calculations were performed for the test assembly which considered local neutronic effects and the mechanical constraints of the device. From the results of these calculations, the ratio of minimum to maximum thermal neutron flux under irradiation would be about 1:10 using a pulse operation simulating device which has a thickness of 6.5 mm and a 150deg window angle for the rotating hollow cylinder and 5.0 mm in thickness of fixed neutron absorber. (author)

  10. Lay out and materials for in pile tritium transport testing of breeder-inside-tube pin assemblies

    International Nuclear Information System (INIS)

    Alvani, C.; Casadio, S.; Mancini, M.R.; Nannetti, C.A.; Avon, J.; Ravel, S.; Pruzzo, G.; Terrosi; Roux, N.; Terlain, A.; and others.

    1994-01-01

    An irradiation experiment (90 FPD in SILOE reactor) has been designed in order to evaluate the in-situ effect of red-ox power of sweeping gas (helium with 100 vpm of H 2 /H 2 O with relative concentrations varying from pure H 2 to pure H 2 O ) on tritium removal from LiAlO 2 and Li 2 ZrO 3 ; and tritium permeation through AlSl-316L SS tubes with bare and coated surfaces. The conditions and materials explored were selected in order to test possible improvements with respect to critical issues for the 'Breeder Inside Tube' (BIT) blanket concept development. (author) 6 refs.; 4 figs.; 2 tabs

  11. Recent results on the RIA test in IGR reactor

    International Nuclear Information System (INIS)

    Asmolov, V.; Yegorova, L.

    1997-01-01

    At the 23d WRSM meeting the data base characterizing results of VVER high burnup fuel rods tests under reactivity-initiated accident (RIA) conditions was presented. Comparison of PWR and VVER failure thresholds was given also. Additional analysis of the obtained results was being carried out during 1996. The results of analysis show that the two different failure mechanisms were observed for PWR and VVER fuel rods. Some factors which can be as the possible reasons of these differences are presented. First of them is the state of preirradiated cladding. Published test data for PWR high burnup fuel rods demonstrated that the PWR high burnup fuel rods failed at the RIA test are characterized by very high level of oxidation and hydriding for the claddings. Corresponding researches were performed at Institute of Atomic Reactors (RLAR, Dimitrovgrad, Russia) for large set of VVER high burnup fuel rods. Results of these investigations show that preirradiated commercial Zr-1%Nb claddings practically keep their initial levels of oxidation and H 2 concentration. Consequently the VVER preirradiated cladding must keep the high level of mechanical properties. The second reason leading to differences between failure mechanisms for two types of high burnup fuel rods can be the test conditions. Now such kind of analysis have been performed by two methods

  12. RIA simulation tests using driver tube for ATF cladding

    Energy Technology Data Exchange (ETDEWEB)

    Cinbiz, Mahmut N. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Brown, N. R. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Lowden, R. R. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Linton, K. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Terrani, K. A. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)

    2017-07-01

    Pellet-cladding mechanical interaction (PCMI) is a potential failure mechanism for accident-tolerant fuel (ATF) cladding candidates during a reactivity-initiated accident (RIA). This report summarizes Fiscal Year (FY) 2017 research activities that were undertaken to evaluate the PCMI-like hoop-strain-driven mechanical response of ATF cladding candidates. To achieve various RIA-like conditions, a modified-burst test (MBT) device was developed to produce different mechanical pulses. The calibration of the MBT instrument was accomplished by performing mechanical tests on unirradiated Generation-I iron-chromium-aluminum (FeCrAl) alloy samples. Shakedown tests were also conducted in both FY 2016 and FY 2017 using unirradiated hydrided ZIRLO™ tube samples. This milestone report focuses on testing of ATF materials, but the benchmark tests with hydrided ZIRLO™ tube samples are documented in a recent journal article.a For the calibration and benchmark tests, the hoop strain was monitored using strain gauges attached to the sample surface in the hoop direction. A novel digital image correlation (DIC) system composed of a single high-speed camera and an array of six mirrors was developed for the MBT instrument to better resolve the failure behavior of samples and to provide useful data for validation of high-fidelity modeling and simulation tools. The DIC system enable a 360° view of a sample’s outer surface. This feature was added to the instrument to determine the precise failure location on a sample’s surface for strain predictions. The DIC system was tested on several silicon carbide fiber/silicon carbide matrix (SiC/SiC) composite tube samples at various pressurization rates of the driver tube (which correspond to the strain rates for the samples). The hoop strains for various loading conditions were determined for the SiC/SiC composite tube samples. Future work is planned to enhance understanding of the failure behavior of the ATF cladding candidates of age

  13. Reactivity initiated accident test series Test RIA 1-4 fuel behavior report

    International Nuclear Information System (INIS)

    Cook, B.A.; Martinson, Z.R.

    1984-09-01

    This report presents and discusses results from the final test in the Reactivity Initiated Accident (RIA) Test Series, Test RIA 1-4, conducted in the Power Burst Facility (PBF) at the Idaho National Engineering Laboratory. Nine preirradiated fuel rods in a 3 x 3 bundle configuration were subjected to a power burst while at boiling water reactor hot-startup system conditions. The test resulted in estimated axial peak, radial average fuel enthalpies of 234 cal/g UO 2 on the center rod, 255 cal/g UO 2 on the side rods, and 277 cal/g UO 2 on the corner rods. Test RIA 1-4 was conducted to investigate fuel coolability and channel blockage within a bundle of preirradiated rods near the present enthalpy limit of 280 cal/g UO 2 established by the US Nuclear Regulatory Commission. The test design and conduct are described, and the bundle and individual rod thermal and mechanical responses are evaluated. Conclusions from this final test and the entire PBF RIA Test Series are presented

  14. Visual in-pile fuel disruption experiments

    International Nuclear Information System (INIS)

    Cano, G.L.; Ostensen, R.W.; Young, M.F.

    1978-01-01

    In a loss-of-flow (LOF) accident in an LMFBR, the mode of disruption of fuel may determine the probability of a subsequent energetic excursion. To investigate these phenomena, in-pile disruption of fission-heated irradiated fuel pellets was recorded by high speed cinematography. Instead of fuel frothing or dust-cloud breakup (as used in the SAS code) massive and very rapid fuel swelling, not predicted by analytical models, occurred. These tests support massive fuel swelling as the initial mode of fuel disruption in a LOF accident. (author)

  15. Out-of pile mechanical test: simulating reactivity initiated accident (RIA) of zircaloy-4 cladding tube

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Myung Ho; Kim, Jun Hwan; Choi, Byoung Kwon; Jeong, Young Hwan [Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)

    2004-07-01

    The ejection or drop of a control rod in a reactivity initiated accident (RIA) causes a sudden increase in reactor power and in turn deposits a large amount of energy into the fuel. In a RIA, cladding tubes bear thermal expansion due to sudden reactivity and may fail from the resulting mechanical damage. Thus, RIA can be one of the safety margin reducers because the oxide on the tubes makes their thickness to support the load less as well as hydrides from the corrosion reduce the ductility of the tubes. In a RIA, the peak of reactor power from reactivity change is about 0.1m second and the temperature of the cladding tubes increases up to 1000 .deg. C in several seconds. Although it is hard to fully simulate the situation, several attempts to measure the change of mechanical properties under a RIA situation has done using a reduction coil, ring tension tests with high speed. This research was done to see the effect of oxide on the change of circumferential strength and ductility of Zircaloy-4 tubes in a RIA. The ring stretch tensile tests were performed with the strain rate of 1/sec and 0.01/s to simulate a transient of the cladding tube under a RIA. Since the test results of the ring tensile test are very sensitive to the lubricant, the tests were also carried out to select a suitable lubricant before the test of oxided specimens.

  16. Reactivity Initiated Accident Test Series: Test RIA 1-2. Quick look report

    International Nuclear Information System (INIS)

    Martinson, Z.R.; Semken, R.S.; Smith, R.H.; Osetek, D.J.

    1978-12-01

    The primary objectives of Test RIA 1-2 were to (a) characterize the response of preirradiated fuel rods during an RIA event conducted at boiling water reactor (BWR) hot-startup conditions for an axial peak pellet surface energy of 200 cal/g UO 2 , and (b) evaluate the effect of internal rod pressure on preirradiated fuel rod response during an RIA event. The test consisted of four, individually shrouded, pressurized water reactor-type fuel rods previously irradiated to burnups of about 4800 MWd/t. In addition to the power calibration and preconditioning, the fuel rods were subjected to a single power burst that deposited a total pellet surface energy of approximately 200 cal/gm UO 2 at the axial peak power location (estimated using the core power chambers to relate steady state and transient powers). The test data indicate that the two irradiated fuel rods prepressurized to 2.41 MPa did not fail. FRAP-T4 calculations had predicted that prompt cladding rupture would occur for pellet surface energy depositions of 206 cal/g or greater. Although the two fuel rods prepressurized to 2.41 MPa did not fail, the data indicate that at least one of the two fuel rods prepressurized to 0.1 MPa did fail. Based on the core power chamber data, this rod failure indicates a threshold for the preirradiated fuel rods near or below 200 cal/g UO 2 total pellet surface energy at the axial flux peak

  17. In-pile Instrumentation Development

    International Nuclear Information System (INIS)

    Vermeeren, L.

    2005-01-01

    Advanced irradiations in research reactors require the on-line monitoring of crucial parameters like neutron fluxes, gamma dose rates, central fuel rod temperatures, fission gas release pressures and small geometry changes. Our activities in this field aim at a detailed understanding of the sensor behaviour in the irradiation conditions in order to extract reliable real-time information. The objectives of work performed by SCK-CEN are to study of the on-line in-pile measurement of gamma and neutron fluxes in real time and to investigate parasitic radiation-induced signals in instrumentation cables

  18. New trends in pile safety instrumentation

    International Nuclear Information System (INIS)

    Furet, J.

    1961-01-01

    This report addresses the protection of nuclear piles against damages due to operation incidents. The author discusses the current trends in the philosophy of safety of atomic power piles, identifies the parameters which define safety systems, presents tests to be performed on safety chains, comments the relationship between safety and the decrease of the number of pile inadvertent shutdowns, discusses the issues of instrument failures and chain multiplicity, comments the possible improvement of the operation of elements which build up safety chains (design simplification, development of semiconductors, replacement of electromechanical relays by static relays), the role of safety logical computers and the development of automatics in pile safety, presents automatic control as a safety factor (example of automatic start-up), and finally comments the use of fuses

  19. Qualification of power determination and in-pile measurements in the UO{sub 2} Gd{sub 2} 0{sub 2} fuel irradiation test IFA 636

    Energy Technology Data Exchange (ETDEWEB)

    Tverberg, T.; Volkov, B.; Kim, J-C.

    2004-04-15

    IFA-S36 is irradiated with the main objective of extending the database on the performance of UO{sub 2}Gd{sub 2}O{sub 2} fuel (with 8% absorbing gadolinia isotopes) compared with commercial UO{sub 2}. The rig carries 6 rods in the lower cluster (including three Gd-doped fuel rods) and 3 rods in the upper cluster (one rod with Gd-doped fuel). The rods are instrumented with expansion thermometers (ETs), fuel and cladding elongation detectors (EFs and ECs) and pressure transducers (PFs). Repeated calorimetric power measurements, physics calculations by the HELIOS code and gamma scans of selected rods in both clusters enabled the power and burnup determination to be qualified and corrected. The data suggest that as of May 2004 the power ratings in both fuels are much alike and burnups are about 30 and 34 MW/kgUO{sub 2} in the Gd-doped and ordinary UO{sub 2} rods respectively. Analysis of in-pile measurements compared with calculations shows that neutron absorption affects fuel temperature, power and burnup radial distributions in Gd-doped fuel at BOL compared with UO{sub 2} fuel. Sensitivity analyses performed with the HELIOS and FTEMP3 codes show that fuel centreline temperature in Gd-doped fuel is influenced by radial power depression, depletion of fissile materials and absorbing Gd isotopes as well as thermal conductivity of the fuel matrix and its degradation during irradiation. Analysis of the fuel dimension changes revealed densification only in the UO{sub 2} fuel whereas fuel elongation measurements in the Gd-doped fuel rods indicated essentially constant swelling with burnup. At burnups above 5 MWd/kgUO{sub 2} the swelling rate was about 0.5-O.fi % DELTAV/V per 10 MWd/kgUO{sub 2} for both fuel types. Internal pressure measured in the Gd-doped rod at BOL showed slight fuel densification and possibly He gas absorption, whereas derived swelling rate was somewhat Iarger than values obtained from the fuel elongation measurements. Cladding elongation measurements

  20. NEET In-Pile Ultrasonic Sensor Enablement-Final Report

    Energy Technology Data Exchange (ETDEWEB)

    J. Daw; J. Rempe; J. Palmer; P. Ramuhalli; R. Montgomery; H.T. Chien; B. Tittmann; B. Reinhardt; P. Keller

    2014-09-01

    Ultrasonic technologies offer the potential to measure a range of parameters during irradiation of fuels and materials, including geometry changes, temperature, crack initiation and growth, gas pressure and composition, and microstructural changes under harsh irradiation test conditions. There are two primary issues that currently limit in-pile deployment of ultrasonic sensors. The first is transducer survivability. The ability of ultrasonic transducer materials to maintain their useful properties during an irradiation must be demonstrated. The second issue is signal processing. Ultrasonic testing is typically performed in a lab or field environment, where the sensor and sample are accessible. The harsh nature of in-pile testing and the variety of desired measurements demand that an enhanced signal processing capability be developed to make in-pile ultrasonic sensors viable. To address these issues, the NEET ASI program funded a three year Ultrasonic Transducer Irradiation and Signal Processing Enhancements project, which is a collaborative effort between the Idaho National Laboratory, the Pacific Northwest National Laboratory, the Argonne National Laboratory, and the Pennsylvania State University. The objective of this report is to document the objectives and accomplishments from this three year project. As summarized within this document, significant work has been accomplished during this three year project.

  1. As-built measurement of the in-pool structure for the installation of In-Pile Test Section in HANARO

    Energy Technology Data Exchange (ETDEWEB)

    Park, K. N.; Cho, Y. G.; Lee, Y. S.; Sim, B. S.; Lee, J. M.; Chi, D. Y.; Park, S. K.; Lee, H. H.; Whang, D. K.; Lee, C. Y. [Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)

    2005-07-01

    Fuel Test Loop (FTL) is designed at the operation condition of power reactor such as high temperature, high pressure and neutron flux etc. As the design of the FTL has been completed, purchasing and manufacturing hardware are underway at present. Installation of the facility is going to do during reactor shutdown period in 2006. This paper describes the preparation of measurement and as-built measurement about in pool structure.

  2. Parametric study of the behaviour of a pre irradiated BWR fuel rod under conditions of LOCA simulated in the halden in pile test system with the FALCON code

    Energy Technology Data Exchange (ETDEWEB)

    Khvostov, G.; Zimmermann, M. A. [Laboratory for Reactor Physics and Systems Behaviour, Paul Scherrer Institut, Villigen (Switzerland); Ledergerber, G. [Kernkraftwerk Leibstadt AG, Leibstadt (Switzerland); Kolstad, E. [Institute for Energy Technology - OECD Halden Reactor Project, Halden (Norway); Montgomery, R. O. [Anatech Corporation, San Diego (United States)

    2008-10-15

    A new LOCA test at Halden was planned as the first experiment within the Halden LOCA program addressing the behaviour of commercially irradiated BWR fuel of medium burn up with burst of the cladding expected to occur at a temperature of about 1050.deg.C, which is essentially higher than in the preceding experiments. The specific measures to be adopted have been suggested based upon a parametric study using the FALCON fuel behaviour code and aimed at an optimized design of the test fuel rod for the given high target cladding temperature of 1150 .deg. C (peak local). The analysis has shown a reasonable agreement with the fundamental experimental findings, such as correlations of NUREG 0630, as well as consistency with the data from Halden LOCA testing available so far. Thus, a general conclusion is drawn about the applicability of the methodology developed at PSI to the analysis of LWR fuel rod behaviour during LOCA, in consideration of the effects of fuel burn up.

  3. SAS validation and analysis of in-pile TUCOP experiments

    International Nuclear Information System (INIS)

    Morman, J.A.; Tentner, A.M.; Dever, D.J.

    1985-01-01

    The validation of the SAS4A accident analysis code centers on its capability to calculate the wide range of tests performed in the TREAT (Transient Reactor Test Facility) in-pile experiments program. This paper presents the SAS4A analysis of a simulated TUCOP (Transient-Under-Cooled-Over-Power) experiment using seven full-length PFR mixed oxide fuel pins in a flowing sodium loop. Calculations agree well with measured thermal-hydraulic, pin failure time and post-failure fuel motion data. The extent of the agreement confirms the validity of the models used in the SAS4A code to describe TUCOP accidents

  4. In-pile experiments on fuel rod behaviour during a LOCA

    International Nuclear Information System (INIS)

    Sepold, E.H.; Karb, E.H.; Pruessmann, M.

    1981-07-01

    This report describes the results of the Test Series G2/3 within the in-pile experimental program for the investigation of LWR fuel rod behavior. The results were obtained with single rods of a PWR design in the DK loop of the FR2 reactor at the Kernforschungszentrum Karlsruhe (KfK). The in-pile tests with the objective of investigating the influence of a nuclear environment on the mechanisms of fuel rod failure were being performed with irradiated and unirradiated rods. The main parameter of the test program ist the burnup, ranging from 2500 to 35000 MWd/t. The results of test series G2/3 (35000 MWd/t) with respect to the burst data, i.e. burst temperature, burst pressure, and burst strain, do not indicate major differences from the in-pile tests with unirradiated test specimens. (orig.) [de

  5. In-pile experiemts on fuel rod behavior during a LOCA

    International Nuclear Information System (INIS)

    Pruessmann, M.; Karb, E.H.; Sepold, L.

    1981-02-01

    This report describes the results of the Test Series G1 within the in-pile experimental program for the investigation of LWR fuel rod behavior. The results were obtained with single rods of a PWR design in the DK loop of the FR2 reactor at the Kernforschungszentrum Karlsruhe (KfK). The in-pile tests with the objective of investigating the influence of a nuclear environment on the mechansims of fuel rod failure were being performed with irradiated and unirradiated rods. The main parameter of the test program is the burnup ranging from 2500 to 35 000 MWd/t. The results of test series G1 (35 000 MWd/t) with respect to the burst data, i.e. burst temperature, burst pressure, and burst strain, do not indicate major differences from the in-pile tests with unirradiated test specimens. (orig.) [de

  6. In pile helium loop ''COMEDIE''

    International Nuclear Information System (INIS)

    Abassin, J.J.; Blanchard, R.J.; Gentil, J.

    1981-01-01

    The SR1 test in the COMEDIE loop has permitted to demonstrate particularly the device operation reliability with a fuel loading. The post-irradiation examinations have pointed out the good filter efficiency and have enabled to determine the deposition profiles either for the activation products (e.g.: 51 Cr, 60 Co) or for the fission products (e.g.: sup(110m)Ag, 131 I, 134 Cs, 137 Cs). (author)

  7. In-pile experimental device for Sirene thermionic converters

    International Nuclear Information System (INIS)

    Bliaux, J.; Durand, J.; Lazare-Chopard, G.

    1969-01-01

    The irradiation device described here, was built for in pile life tests of 100 We SIRENE converters. The nuclear converter is located in a sealed vacuum chamber, which is plugged at the lower end of a coaxial tubing acting as electrical leads. The output power is available on a variable resistive load on the bank of the reactor pool. Thermal, electrical and neutronic parameters of the converter are recorded. Since 1967, two permanent devices allowed five experiments in the swimming pool TRITON (CEN-FAR) and the results, obtained till now, are presented. (authors) [fr

  8. In pile helium loop ''Comedie''

    International Nuclear Information System (INIS)

    Blanchard, R.J.

    1985-01-01

    The loop is located in the SILOE reactor at Centre d'Etudes Nucleaires de Grenoble. The purpose and objectives are divided into two groups, principal and secondary. The primary objective was to provide basic data on the deposition behavior of important condensable fission products on a variety of steel surfaces, i.e. temperature (sorption isotherms) and mass transfer (physical adsorption) dependencies; to provide information concerning the degree of penetration of important fission products into the metals comprising the heat exchanger-recuperator tubes as a function of alloy type and/or metal temperature; to provide complementary information on the reentrainment (liftoff) of important fission and activation products by performing out-of-pile blowdown experiments on tube samples representative of the alloy types used in the heat exchanger-recuperator and of the surface temperatures experienced during plateout. The secondary objective was to provide information concerning the migration of important fission products through graphite. To this end, concentration profiles in the web between the fuel rods containing the fission product source and the coolant channels and in the graphite diffusion sample will be measured to study the corrosion of metallic specimens placed in the conditions of high temperature gas cooled reactor. The first experiment SRO enables to determine the loop characteristics and possibilities related to thermal, thermodynamic, chemical and neutronic properties. The second experiment has been carried out in high temperature gas cooled reactor operating conditions. It enables to determine in particular the deposition axial profile of activation and fission products in the plateout section constituting the heat exchanger, the fission products balance trapped in the different filter components, and the cumulated released fraction of solid fission products. The SR1 test permits to demonstrate in particular the Comedie loop operation reliability, either

  9. Summary on out-of-pile and in-pile properties of M5 alloy

    International Nuclear Information System (INIS)

    Zhao Wenjin

    2001-01-01

    The out-of-pile and in-pile corrosion, mechanical properties, microstructure,hydrogen absorption, creep and growth resistances of M5 alloy using as PWR fuel rod cladding materials developed by FRAMATOME in France has been summarized with reference to the literatures. The results obtained from in-pile irradiation tests show that the corrosion and hydrogen absorption resistances, creep and irradiation growth resistances of M5 alloy cladding are superior to that of the optimized Zircaloy-4. It could be estimated that the M5 alloy enables rod burnups close to 65GWd/tU to be reached

  10. Progress In Developing An In-Pile Acoustically Telemetered Sensor Infrastructure

    Energy Technology Data Exchange (ETDEWEB)

    Smith, James A.; Garrett, Steven L.; Heibel, Michael D.; Agarwal, Vivek; Heidrich, Brenden J.

    2016-09-01

    A salient grand challenge for a number of Department of Energy programs such as Fuels Cycle Research and Development ( includes Accident Tolerant Fuel research and the Transient Reactor Test Facility Restart experiments), Light Water Sustainability, and Advanced Reactor Technologies is to enhance our fundamental understanding of fuel and materials behavior under irradiation. Robust and accurate in-pile measurements will be instrumental to develop and validate a computationally predictive multi-scale understanding of nuclear fuel and materials. This sensing technology will enable the linking of fundamental micro-structural evolution mechanisms to the macroscopic degradation of fuels and materials. The in situ sensors and measurement systems will monitor local environmental parameters as well as characterize microstructure evolution during irradiation. One of the major road blocks in developing practical robust, and cost effective in-pile sensor systems, are instrument leads. If a wireless telemetry infrastructure can be developed for in-pile use, in-core measurements would become more attractive and effective. Thus to be successful in accomplishing effective in-pile sensing and microstructure characterization an interdisciplinary measurement infrastructure needs to be developed in parallel with key sensing technology. For the discussion in this research, infrastructure is defined as systems, technology, techniques, and algorithms that may be necessary in the delivery of beneficial and robust data from in-pile devices. The architecture of a system’s infrastructure determines how well it operates and how flexible it is to meet future requirements. The limiting path for the effective deployment of the salient sensing technology will not be the sensors themselves but the infrastructure that is necessary to communicate data from in-pile to the outside world in a non-intrusive and reliable manner. This article gives a high level overview of a promising telemetry

  11. Remote-welding technique for assembling in-pile IASCC capsule in hot cell

    International Nuclear Information System (INIS)

    Kawamata, Kazuo; Ishii, Toshimitsu; Kanazawa, Yoshiharu; Iwamatsu, Shigemi; Ohmi, Masao; Shimizu, Michio; Matsui, Yoshinori; Saito, Jun-ichi; Ugachi, Hirokazu; Kaji, Yoshiyuki; Tsukada, Takashi

    2006-01-01

    In order to investigate behavior of the irradiation assisted stress corrosion cracking (IASCC) caused by the simultaneous effects of neutron irradiation and high temperature water environment in such a light water reactor (LWR), it is necessary to perform crack growth tests in an in-pile IASCC capsule irradiated in the Japan Materials Testing Reactor (JMTR). The development of the remote-welding technique is essential for remotely assembling the in-pile IASCC capsule installing the pre-irradiated CT specimens. This report describes a new remote-welding machine developed for assembling the in-pile IASCC capsule. The remote-welding technique that the capsule tube is rotated light under the fixed torch was applied to the machine for the welding of thick and large-diameter tubes. The assembly work of four in-pile IASCC capsules having pre-irradiated CT specimens in the hot cell was succeeded for performing the crack growth test under the neutron irradiation in JMTR. The irradiation test of two capsules has been already finished in JMTR without problems. (author)

  12. NEET In-Pile Ultrasonic Sensor Enablement-FY 2012 Status Report

    Energy Technology Data Exchange (ETDEWEB)

    JE Daw; JL Rempe; BR Tittmann; B Reinhardt; P Ramuhalli; R Montgomery; HT Chien

    2012-09-01

    Several Department Of Energy-Nuclear Energy (DOE-NE) programs, such as the Fuel Cycle Research and Development, Advanced Reactor Concepts, Light Water Reactor Sustainability, and Next Generation Nuclear Plant programs, are investigating new fuels and materials for advanced and existing reactors. A key objective of such programs is to understand the performance of these fuels and materials when irradiated. The Nuclear Energy Enabling Technology (NEET) Advanced Sensors and Instrumentation (ASI) in-pile instrumentation development activities are focused upon addressing cross-cutting needs for DOE-NE irradiation testing by providing higher fidelity, real-time data, with increased accuracy and resolution from smaller, compact sensors that are less intrusive. Ultrasonic technologies offer the potential to measure a range of parameters, including geometry changes, temperature, crack initiation and growth, gas pressure and composition, and microstructural changes, under harsh irradiation test conditions. There are two primary issues associated with in-pile deployment of ultrasonic sensors. The first is transducer survivability. The ability of ultrasonic transducer materials to maintain their useful properties during an irradiation must be demonstrated. The second issue is signal processing. Ultrasonic testing is typically performed in a lab or field environment, where the sensor and sample are accessible. Due to the harsh nature of in-pile testing, and the range of measurements that are desired, an enhanced signal processing capability is needed to make in-pile ultrasonic sensors viable. This project addresses these technology deployment issues.

  13. Test Review: Reynolds, C. R., & Kamphaus, R. W. (2003). "RIAS--Reynolds Intellectual Assessment Scales." Lutz, FL--Psychological Assessment Resources, Inc.

    Science.gov (United States)

    Dombrowski, Stefan C.; Mrazik, Martin

    2008-01-01

    In this article, the authors review the Reynolds Intellectual Assessment Scales (RIAS; Reynolds & Kamphaus, 2003), an individually administered test of intelligence for use with individuals between the ages of 3 and 94. The RIAS represents the newest intelligence test on the marketplace and incorporates the most current intelligence test theory…

  14. Physics calculations for the RIA 1-3 irradiated rod test

    International Nuclear Information System (INIS)

    Young, T.E.

    1981-06-01

    The RIA 1-3 test would employ a square array of four pre-irradiated BWR rods to provide information on fuel failure modes and consequences of postulated Reactivity Initiated Accidents in power reactors. Calculations were done to: (1) predict R-O power distributions in the test rods for thermal-hydraulic and fuel-failure analysis; and (2) predict the steady-state and transient ratios of test fuel energy deposition to core energy deposition (Figures of Merit). Fission distributions for the test were computed with the RAFFL Monte Carlo code using an external neutron current source from a complete-reactor radial calculation with the SCAMP S/sub n/ code. Energies per fission for the rods were computed using the SINBAD buildup and depletion code, the GAMSOR gamma ray source code, and the QAD-BSA point-kernel shielding code. The calculated rod average-to-test average energy deposition ratios are 0.99, 0.99, and 0.97 for the rods irradiated to approximately 12 CWd/tu, and 1.04 for the rod irradiated to 4.8 GWd/tu. The maximum deviation of the power density of 1/12-rod azimuthal segments from the rod average is 4%. For an estimated control rod position of 0.591 m withdrawn the predicted radial average energy deposition at the axial peak in an average test rod is 1.71 (kW/m)/MW during preconditioning, and 1.84 (kJ/kg UO 2 ) MW.S during the burst. 16 figures, 7 tables

  15. In-pile loop experiments in water chemistry and corrosion

    International Nuclear Information System (INIS)

    Kysela, J.; Jindrich, K.; Masarik, V.; Fric, Z.; Chotivka, V.; Hamerska, H.; Vsolak, R.; Erben, O.

    1986-08-01

    Methods and techniques used were as follows: (a) Method of polarizing resistance for remote monitoring of instantaneous rate of uniform corrosion. (b) Out-of-pile loop at the temperature 350 degC, pressure 19 MPa, circulation 20 kgs/h, testing time 1000 h. (c) High temperature electromagnetic filter with classical solenoid and ball matrix for high pressure filtration tests. (d) High pressure and high temperature in-pile water loop with coolant flow rate 10 000 kgs/h, neutron flux in active channel 7x10 13 n/cm 2 .s, 16 MPa, 330 degC. (e) Evaluation of experimental results by chemical and radiochemical analysis of coolant, corrosion products and corrosion layer on surface. The results of measurements carried out in loop facilities can be summarized into the following conclusions: (a) In-pile and out-of-pile loops are suitable means of investigating corrosion processes and mass transport in the nuclear power plant primary circuit. (b) In studying transport phenomena in the loop, it is necessary to consider the differences in geometry of the loop and the primary circuit, mainly the ratio of irradiated and non-irradiated surfaces and volumes. (c) In the experimental facility simulating the WWER-type nuclear power plant primary circuit, solid suspended particles of a chemical composition corresponding most frequently to magnetite or nickel ferrite, though with non-stoichiometric composition Me x 2+ Fe 3-x 3+ O 4 , were found. (d) Continuous filtration of water by means of an electromagnetic filter removing large particles of corrosion products leads to a decrease in radioactivity of the outer epitactic layer only. The effect of filtration on the inner topotactic layer is negligible

  16. Results from In-pile experiments on LWR fuel rod behavior under LOCA conditions with unirradiated rods

    International Nuclear Information System (INIS)

    Sepold, L.; Karb, E.H.; Pruessmann, M.

    1981-06-01

    This report summarizes the results of the FR2-in-pile tests at KfK (Kernforschungszentrum Karlsruhe) with unirradiated test rods. The in-pile tests with the objective of investigating the influence of a nuclear environment on the mechanisms of fuel rod failure were being performed with irradiated and unirradiated single rods of a PWR design in the DK loop of the FR2 reactor. The main parameter of the test program was the burnup, ranging from 2.500 to 35.000 MWd/t. The program with unirradiated specimens comprised the series A and B with a total of 14 tests. (orig.) [de

  17. Concept and basic performance of an in-pile experimental reactor for fast breeder reactors using fast driver core

    International Nuclear Information System (INIS)

    Obara, Toru; Sekimoto, Hiroshi

    1997-01-01

    The possibility of an in-pile experimental reactor for fast breeder reactors using a fast driver core is investigated. The driver core is composed of a particle bed with diluted fuel. The results of various basic analyses show that this reactor could perform as follows: (1) power peaking at the outer boundary of test core does not take place for large test core; (2) the radial power distribution in test fuel pin is expected to be the same as a real reactor; (3) the experiments with short half width pulse is possible; (4) for the ordinary MOX core, enough heating-up is possible for core damage experiments; (5) the positive effects after power burst can be seen directly. These are difficult for conventional thermal in-pile experimental reactors in large power excursion experiments. They are very attractive advantages in the in-pile experiments for fast breeder reactors. (author)

  18. In pile AISI 316L. Low cycle fatigue. Final report

    International Nuclear Information System (INIS)

    Van Nieuwenhove, R.; Moons, F.

    1994-12-01

    In pile testing of the effect of neutron irradiation on the fatigue life of the reference material AISI 316L was performed in the framework of the European fusion technology program. The overall programme, carried out at SCK CEN (Mol,Belgium), exists of two instrumented rigs for low cycle fatigue testing, which were consecutively loaded in the BR-2 reactor during periods Jan (94) June (94) and Aug (94)-Dec(94). In each experiment, two identical samples were loaded by means of a pneumatically driven system. The samples were instrumented with thermocouples, strain gages, linear variable displacement transducers, and activation monitors. The experimental conditions are given. Type of fatigue test: load controlled, symmetric, uniaxial, triangular wave shape; stress range: about 580 MPa; sample shape: hourglass, diameter 3.2 mm, radius 12.5 mm; environment: NaK (peritectic); temperature: 250 C; maximum dpa value up to fracture: 1.7. Two of four samples were broken (one in each experiment) after having experienced 17 419 respectively 11 870 stress cycles. These new data points confirm earlier results from pile fatigue tests: irradiation causes no degradation of fatigue life of AISI 316L steel, at least for the parameters corresponding to these experiments

  19. Thermal and in-pile densification of MOX fuels: Some recent results

    International Nuclear Information System (INIS)

    Caillot, L.; Malgouyres, P.P.; Souchon, F.; Gotta, M.J.; Warin, D.; Chotard, A.; Couty, J.C.

    1997-01-01

    In-pile densification of PWR fuels is one of the main phenomena which determine the evolution of the pellet-clad gap during the first stage of the irradiation, and thus has consequences onto the thermo-mechanical behaviours of fuel rods. It can be predicted using the results of resintering tests and appropriate correlations. In this context, CEA, FRAMATOME and EDF have undertaken a joint research programme aiming to characterize the densification of MOX fuels. Different fuels were prepared by the MIMAS process using different UO 2 powders as matrix. After a detailed characterization, fuel pellets were submitted to isothermal resintering tests and analytical irradiations. Correlations between in-pile and thermal densification were established. This paper presents the results obtained with two types of MOX fuel: one fabricated wit the AUC UO 2 powder (ammonium uranyl carbonate conversion process) and another one fabricated with the SFEROX powder (peroxide conversion process). 8 refs, 8 figs

  20. Design and performance evaluation of a cryogenic condenser for an in-pile experiment

    Science.gov (United States)

    Graham, R. W.; Crum, R. J.; Hsu, Y.

    1972-01-01

    An apparatus was designed to enable in-pile irradiation of materials in liquid hydrogen at cryogenic temperatures. One of the principal components of this apparatus was a horizontal tube condenser. The performance of the condenser was evaluated by running a liquid-nitrogen prototype of the apparatus at heat loads comparable to or greater than those expected during the irradiation. The test showed that the condenser was capable of handling the design heat load and that the design procedure was sound.

  1. The use of RIA tests for screening and for monitoring of some diseases

    International Nuclear Information System (INIS)

    Hegesippe, M.

    1979-01-01

    Some examples are described concerning the progress realized in the antenatal and neonatal diagnoses of congenital anomalies and in the follow-up of cancer patients using RIA techniques. The frequencies of some well known congenital abnormalities are recalled. The first example concerns Duchene myopathy. A second example, much more advanced, is the antenatal diagnosis of neural tube defects. A third example, already in routine state by state in north America and in Europe is the neonatal screening of congenital hypothyroidism. The last example concerns the use of CEA assay in the evaluation, the prognosis and the follow-up of cancer patient's state. These RIA examples were chosen to illustrate and also to situate the important place of this analytical response among informations available to the clinician

  2. A 20 kw beam-on-target test of a high-power liquid lithium target for RIA

    International Nuclear Information System (INIS)

    Reed, Claude B.; Nolen, Jerry A.; Specht, James R.; Novick, Vincent J.; Plotkin, Perry

    2004-01-01

    The high-power heavy-ion beams produced by the Rare Isotope Accelerator (RIA) driver linac have large energy deposition density in solids and in many cases no solid materials would survive the full beam power. Liquid lithium technology has been proposed to solve this problem in RIA. Specifically, a windowless target for the production of radioactive ions via fragmentation, consisting of a jet of about 3 cm thickness of flowing liquid lithium, exposed to the beamline vacuum [1,2] is being developed. To demonstrate that power densities equivalent to a 200-kW RIA uranium beam, deposited in the first 4 mm of a flowing lithium jet, can be handled by the windowless target design, a high power 1 MeV Dynamitron was leased and a test stand prepared to demonstrate the target's capability of absorbing and carrying away a 20kW heat load without disrupting either the 5 mm x 10 mm flowing lithium jet target or the beam line vacuum

  3. Preliminary results from initial in-pile debris bed experiments

    International Nuclear Information System (INIS)

    Rivard, J.B.

    1977-01-01

    An accident in a liquid metal fast breeder reactor (LMFBR) in which molten core material is suddenly quenched with subcooled liquid sodium could result in extensive fragmentation and dispersal of fuel as subcritical beds of frozen particulate debris within the reactor vessel. Since this debris will continue to generate power due to decay of retained fission products, containment of the debris is threatened if the generated heat is not removed. Therefore, the initial safety question is the capacity which debris beds may have for transfer of the decay heat to overlying liquid sodium by natural processes--i.e., without the aid of forced circulation of the coolant. Up to the present time, all experiments on debris bed behavior either have used substitute materials (e.g., sand and water) or have employed actual materials, but atypical heating methods. Increased confidence in the applicability of debris bed simulations is afforded if the heat is generated within the fuel component of the appropriate fast reactor materials. The initial series of in-pile tests reported on herein constitutes the first experiments in which the internal heating mode has been produced in particulate oxide fuel immersed in liquid sodium. Fission heating of the fully-enriched UO 2 in the experiment while it is contained within Sandia Laboratories Annular Core Pulse Reactor (ACPR), operating in its steady-state mode, approximates the decay heating of debris. Preliminary results are discussed

  4. Neutronic and thermal estimation of blanket in-pile mockup with Li2TiO3 pebbles

    International Nuclear Information System (INIS)

    Nagao, Y.; Nakamichi, M.; Tsuchiya, K.; Kawamura, H.

    2001-01-01

    To evaluate exactly temperature distribution in large volume of tritium breeding materials during the blanket in-pile tests with the JMTR, neutronic and thermal calculations were conducted by using Monte Carlo code 'MCNP' with nuclear cross section library of 'FSXLIBJ3R2' and the transient and steady-state distribution code 'TRUMP'. From the results of preliminary estimation of temperature distribution in the blanket in-pile mockup, the calculated values were 24-28% higher than the measured values. One of the reasons is due to overestimation of calculated thermal neutron flux

  5. Interpretation of the TRADE In-Pile source multiplication experiments

    International Nuclear Information System (INIS)

    Mercatali, Luigi; Carta, Mario; Peluso, Vincenzo

    2006-01-01

    Within the framework of the neutronic characterization of the TRIGA RC-1 reactor in support to the TRADE (TRiga Accelerator Driven Experiment) program, the interpretation of the subcriticality level measurements performed in static regime during the TRADE In-Pile experimental program is presented. Different levels of subcriticality have been measured using the MSA (Modified Source Approximated) method by the insertion of a standard fixed radioactive source into different core positions. Starting from a reference configuration, fuel elements were removed: control rods were moved outward as required for the coupling experiments envisioned with the proton accelerator and fission chambers were inserted in order to measure subcritical count rates. A neutron-physics analysis based on the modified formulation of the source multiplication method (MSM) has been carried out, which requires the systematic solution for each experimental configuration of the homogeneous, both in the forward and adjoint forms, and inhomogeneous Boltzmann equations. By means of such a methodology calculated correction factors to be applied to the MSA measured reactivities were produced in order to take into account spatial and energetic effects creating changes in the detector efficiencies and effective source with respect to the calibration configuration. The methodology presented has been tested against a large number of experimental states. The measurements have underlined the sensitivity of the MSA measured reactivities to core geometry changes and control rod perturbations; the efficiency of MSM factors to dramatically correct for this sensitivity is underlined, making of this technique a relevant methodology in view of the incoming US RACE program to be performed in TRIGA reactors

  6. Irradiation technology (1). Development of new in-pile instrumentation at JMTR

    International Nuclear Information System (INIS)

    Shibata, Akira; Kimura, Nobuaki; Tanimoto, Masataka; Nakamura, Jinichi; Saito, Takashi; Tsuchiya, Kunihiko

    2012-01-01

    Development of instrumentation which can use under severe accident condition is important issue for the purpose to cope with severe accident at nuclear reactors. And also to improve the quality of irradiation tests data and to increase the reliability of safety management system of reactors, the development of new instrumentation is key issue. JAEA is developing several in-pile instrumentations to conduct irradiation tests at JMTR. This study includes the developments of three new instrumentations and describes the characteristics of the instrumentations. These are ECP sensor, new water level indicator and in-reactor observation system using Cherenkov light. (author)

  7. Stress analysis of primary pipe rigid support of the in pile loop

    International Nuclear Information System (INIS)

    Hasibuan, Dj.

    1998-01-01

    Base on requirement of the safety analysis report and operation planning preparation on the in pile loop by using the fuel bundle in the test section, the stress analysis of primary pipe support has been done. The analysis was performed for the 3 (three) points of pipe support, which are chosen by random selection, i.e.: GU 2001, GU 2002, and GU 2331. The analysis result showed that the maximum allowable stress was greater then the actual stress. It is concluded that the existing supports fulfil the safety requirement

  8. Eficiência dos testes cromáticos de comparação na discromatopsia hereditária: relato de casos

    OpenAIRE

    Fernandes,Luciene Chaves; Urbano,Lúcia Carvalho de Ventura

    2008-01-01

    As autoras relatam dois casos de discromatopsia hereditária e discutem a eficiência dos testes cromáticos no diagnóstico de uma discromatopsia. Os pacientes foram reprovados em diferentes concursos públicos federais por apresentarem diagnóstico de discromatopsia hereditária pelo teste de Ishihara. Submeteram-se a exame oftalmológico, com resultados dentro da normalidade. Procuraram novo parecer para melhor caracterização da sua discromatopsia. Não havia sintomas relacionados à deficiência. Os...

  9. Report On Design And Preliminary Data Of Halden In-Pile Creep Rig

    Energy Technology Data Exchange (ETDEWEB)

    Terrani, Kurt A [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Karlsen, T. M. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Yamamoto, Yukinori [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)

    2015-09-01

    A set of in-pile creep tests is ongoing in the Halden reactor on ORNL’s candidate accident tolerant fuel cladding materials. These tests are meant to provide essential material property information that is needed for an informed analysis of these fuel concepts under normal operating conditions. These tests provide detailed information regarding swelling, thermal creep, and irradiation creep rates of these materials. The results to date have been compared with the limited set of information available in literature that is form irradiation tests in other reactors or out-of-pile tests. Most of the results are in good agreement with prior literature, except for irradiation creep rate of SiC. To elucidate the difference between the HFIR and Halden test results continued testing is necessary. The tests describe in this progress report are ongoing and will continue for at least another year.

  10. Analysis of Sandia in-pile EOS experiments

    International Nuclear Information System (INIS)

    Breitung, W.; Gorham-Bergeron, E.; Murata, K.K.

    1979-01-01

    Preliminary analysis has been carried out of the dynamic in-pile equation-of-state measurements for UO 2 , conducted at Sandia Laboratories, aimed at reducing the uncertainties in the effective UO 2 enthalpy corresponding to the measured pressures. Of the remaining width of the p-H band of some 350 J/g, about 200 J/g originate in the uncertainties of the analytical modelling and about 150 J/g result from the scatter in the experimental data

  11. In-pile experimental facility needs for LMFR safety research

    International Nuclear Information System (INIS)

    Kawata, Norio; Niwa, Hajime

    1994-01-01

    Although the achievement of the safety research during the past years has been significant, there still exists a strong need for future research, especially when there is prospect for future LMFR commercialization. In this paper, our current views are described on future research needs especially with a new in-pile experimental facility. The basic ideas and progress are outlined of a preliminary feasibility study. (author)

  12. The MOZART in-pile tritium extraction experiment

    International Nuclear Information System (INIS)

    Briec, M.

    1990-01-01

    In-pile tritium extraction behavior of various ceramics was compared in the MOZART experiment. The influence of temperature and purge gas composition was studied. The experimental results are analyzed by taking into account the processes of diffusion in the grain and desorption at grain surface. This analysis confirms that a better knowledge of the desorption process is necessary for a satisfactory explanation of the experimental data

  13. Memória em idoso: relação entre percepção subjetiva e desempenho em testes objetivos

    OpenAIRE

    BOURSCHEID,Fábio Rodrigo; MOTHES,Luíza; IRIGARAY,Tatiana Quarti

    2016-01-01

    Resumo A relação entre a percepção subjetiva de memória e o desempenho em testes objetivos tem sido alvo de diversos estudos em vista de sua utilidade no diagnóstico do declínio cognitivo. Dada a ausência de consenso em relação ao tema, avaliou-se o desempenho de idosos em testes objetivos de memória, correlacionando-o com a percepção subjetiva dos participantes acerca de sua memória. Cento e cinquenta e dois idosos preencheram uma ficha de dados sociodemográficos, na qual foi incluída uma qu...

  14. C peptide and insulin releasing RIA test for the investigation of β cell function in diabetic patients

    International Nuclear Information System (INIS)

    Shi Ailan; Zhu Chengmo; Wang Qiyu; Wang Ping

    1993-01-01

    Results of C-peptide releasing RIA test in 15 normals, and 100 diabetes were summarized and compared with glucose tolerance test and serum insulin for investigating the characteristics in different types of diabetes and evaluating the functional state of islet β cell. In 36 cases of IDDM the fasting blood sugar was significantly increased, and further elevated after eating of bread, but its peak time delay in 2 hours (normalin 1 hour). The level of basal C-peptide is very low, but shows slightly weak on no response after bread stimulating test, all of this denotes that β cell function of islets severely injured. The increasing of fasting blood sugar in 64 cases of NIDDM was lower than those of IDDM. Fasting C-peptide and insulin was normal or increased, their peak value increased after bread stimulation with peak time delayed also at 2 hours. Above results demonstrated that the function of islets B cell decreased but not fully deprived. It is concluded that C-peptide and insulin stimulating test, together with OGTT can accurately assess the islets β cell function, and also have important significance in the pathogenesis, classification and staging, prognostic evaluation and monitoring of therapeutic effects in diabetes

  15. Thermal conductivity of sintered UO2 under in-pile conditions

    International Nuclear Information System (INIS)

    Stora, J.P.; Bernardy De Sigoyer, B.; Delmas, R.; Deschamps, P.; Lavaud, B.; Ringot, C.

    1964-01-01

    The temperature distribution in a stack of sintered UO 2 cylinders has been studied both in the laboratory where the heat energy is produced by an axial heating element, and in-pile, where the heating is due solely to nuclear effects. Under a high thermal gradient the UO 2 cracks both along radial planes and along pseudo-cylindrical surfaces: these latter act as thermal barriers to the heat flow, It is therefore an apparent thermal conductivity k a (T), lower than the intrinsic value k(T) of this parameter which is measured. The efficiency of these barriers decreases when the gap decreases and when the external pressure acting on the cracked stack increases: in the limiting case, for high values of the binding strain, k a (T) ≅ k(T). In the domain of phonon conduction (T ≤ 1350 deg C), the expression kw.cm -1 .C -1 =1/(11+0.024*T) accounts for the real thermal conductivity. Above 1350 deg C the thermal conductivity increases. Two in-pile measurements up to 1250 deg C carried out using cartridges fitted with thermocouples confirm, within the limits of experimental error, the above expression and the qualitative effects of the binding strains. Similar tests have been carried out-of-pile and in-pile on the real shape of the EL-4 fuel 'pencils'. Out-of-pile, the influence of the initial free gap, of the nature of the gas filing the 'pencil' and of the external pressure have been studied; the results are compatible with the above interpretation; It appears that an external pressure of 60 kg/cm 2 is insufficient to restore completely the thermal conductivity of the fuel. (authors) [fr

  16. RIA: Principles and application

    International Nuclear Information System (INIS)

    Pappas, A.A.; Glassman, A.B.

    1983-01-01

    What is the future of RIA? Has the application of RIA peaked? Will other and competing tests such as immunofluorescence and ELISA systems displace or replace the method? RIA is a sensitive, precise, and very often specific analytical tool. Its primary advantage is exquisite sensitivity. Problems related to specificity of antibody and/or antigen identification are reviewed in this paper. The same limitations will be encountered in the similar techniques of enzyme immunologic determination. Increasing difficulties with waste disposal of either radioactive material and/or organic solvents will cause those who utilize radionuclides to look again at alternatives. RIA has been an exciting developmental tool that has led the authors to look at dynamic physiologic and biochemical interactions. The time may come when there is replacement of the radionuclide portion by enzymes or fluorescent material

  17. Ultrasonic Thermometry for In-Pile Temperature Detection

    International Nuclear Information System (INIS)

    Daw, J.E.; Rempe, J.L.; Wilkins, S.C.

    2002-01-01

    example, signal processing can be very complicated, as multiple echoes may overlap. Contact between the sensor and solid materials can cause extraneous echoes. If a sheath is required, contact bonding at high temperatures may cause extraneous echoes or attenuation of primary echoes. The most successful materials used in previous studies, tungsten and rhenium, are unattractive for nuclear applications due to material transmutation. Clearly, in order for ultrasonic thermometers to be viable for an in-pile sensor, these issues must be resolved through the use of modern signal processing and materials technologies. As part of the INL feasibility study, all of the issues associated with UT use and proposed resolution options will be identified and evaluated. Once most promising options are proven, it is planned to produce one or more prototype ultrasonic temperature sensors for evaluation. Ultimately, a full test should include a long term installation in a high temperature test assembly installed in a high neutron flux environment, such as that found in the Idaho National Laboratory's Advanced Test Reactor.

  18. In-pile critical heat flux and post-dryout heat transfer measurements – A historical perspective

    Energy Technology Data Exchange (ETDEWEB)

    Groeneveld, D.C., E-mail: degroeneveld@gmail.com

    2017-06-15

    In the 1960s’ and 1970s’ Canada was a world leader in performing in-reactor heat transfer experiments on fuel bundles instrumented with miniature sheath thermocouples. Several Critical Heat Flux (CHF) and Post-CHF experiments were performed in Chalk River’s NRU and NRX reactors on water-cooled 3-, 18-, 19-, 21-, and 36-element fuel bundles. Most experiments were obtained at steady-state conditions, where the power was raised gradually from single-phase conditions up to the CHF and beyond. Occasionally, post-dryout temperatures up to 600 °C were maintained for several hours. In some tests, the fuel behaviour during loss-of-flow and blowdown transients was investigated – during these transients sheath temperatures could exceed 2000 °C. Because of the increasingly more stringent licensing requirements for in-pile heat transfer tests on instrumented fuel bundles, no in-pile CHF and post-dryout tests on fuel bundles have been performed anywhere in the world for the past 40 years. This paper provides details of these unique in-pile experiments and describes some of their heat transfer results.

  19. In-pile gamma spectrometry and irradiation control at Osiris

    International Nuclear Information System (INIS)

    Farny, G.; Destot, M.; Corre, J.; Texier, D.; Faugere, J.L.; Mouchnino, M.

    1975-01-01

    A new gamma spectrometry facility is available near Osiris reactor core, at Saclay. This device enables nuclear fuels to be examined in loops or capsules all along their irradiation, a few minutes being sufficient to transfer the fuel from the irradiation place to the measurement bench. So, spacelike and timelike history of a lot of fission products, especially short-lived radionuclides, can be observed. Using such in-pile spectrometry device, of original design, allows to avoid radioactive decay corrections and the risks of any information less. Performance of the device is given together with some preliminary results and their interpretation [fr

  20. ECP measurements under neutron and gamma ray in in-pile loop and their data evaluation by water radiolysis calculations

    Energy Technology Data Exchange (ETDEWEB)

    Hanawa, S.; Nakamura, T.; Uchida, S. [Japan Atomic Energy Agency, Tokai-mura, Ibaraki (Japan); Kus, P.; Vsolak, R.; Kysela, J. [Nuclear Research Inst. Rez plc, Husinec - Rez (Czech Republic)

    2010-07-01

    In order to establish reliable electrochemical corrosion potential (ECP) sensors for applying in reactor core peripherals of power plants, performance tests of sensors under irradiation were carried out in the in-pile loop of the experimental reactor, LVR-15, at the Nuclear Research Institute (NRI) in Czech Republic. Responses of different kinds of sensors under neutron and gamma irradiation conditions have been compared each other. Corrosive conditions along the in-pile loop were calculated by water radiolysis calculation code, WRAC-J and calculated corrosive conditions were compared with the measured results. As a result of the evaluation, it was confirmed that the ECP sensors could be applied to irradiation conditions of reactor peripherals, while the water radiolysis model could be also applied for evaluation of corrosive conditions of reactor peripherals. (author)

  1. Thyroid Function Test in Thyroid Diseases and Pregnancy - The diagnostic value of free thyroxine by RIA -

    International Nuclear Information System (INIS)

    Yoo, M. H.; Yoon, H. J.; Shin, Y. T.; Lee, J. C.; Chung, S. I.; Cho, B. Y.; Lee, M. H.; Lee, M. C.

    1981-01-01

    To evaluate the diagnostic accuracy of the measurement of free thyroxine(FT4) by radioimmunoassay, we measured free T 4 and T 4 , T 3 , T 3 RU, TSH and TBG serum levels by radioimmunoassay in 18 healthy persons and 52 patients with various thyroid diseases and 11 normal pregnant women. The results are as follows. 1) In 19 cases of overt hyperthyroidism, T 3 , free T 4 and FTI, T 4 /TBG ratio reflect hyperfunction in all cases. T 4 is increased in 94%(18/19) and TBG and TSH are decreased in 79%(15/19). 2) In 8 patients with overt hypothyroidism, TSH is increased in all cases and free T 4 and FTI is decreased in all cases. T 4 is decreased in 87.5%(7/8), T 3 is decreased in 75%(6/8) and T 4 /TBG ratio is decreased in 62.5%(5/8). 3) In 5 patients who are clinically in euthyroid state after treatment of hyperthyroidism, T , 4 free T 4 , FTI and TSH are in the normal range in all cases and T 3 is normal in 60%(3/5) and slightly increased in 40%(2/5). 4) In 10 patients who showed clinically borderline hypothyroidism after treatment of hyperthyroidism, TSH is increased in all cases and free T 4 and FTI are decreased in all cases, but T 4 and T 3 , T 4 /TBG ratio are in the normal limit in all cases. So after treatment of hyperthyroidism, TSH, free T 4 or FTI are recommended as optimal function test. 5) In normal pregnancy, free T 4 , FTI and T 4 /TBG ratio reflect normal function, but the other parameters unreliable due to the influence of increased TBG. Also TBG and TSH level in pregnancy is increased significantly compared with normal healthy control group. 6) The coefficients of correlation between T 4 and FTI were 0.862(p 4 and T 4 /TBG ratio. In most patients, diagnostic value of free T 4 was comparable and even superior to FTI, so free T 4 measurement can be used routinely with thyrotropin assay in the diagnosis of hypothyroidism or with T 3 for the diagnosis of hyperthyroidism.

  2. New in-pile water loop facility for IASCC studies at JMTR

    International Nuclear Information System (INIS)

    Tsukada, T.; Tsuji, H.; Nakajima, H.; Komori, Y.; Ito, H.

    2002-01-01

    Irradiation assisted stress corrosion cracking (IASCC) is caused by the synergistic effects of neutron and gamma radiation, residual and applied stresses and high temperature water environment on the structural materials of vessel internals. IASCC has been studied since the beginning of the 1980's and the phenomenological knowledge on IASCC is accrued extensively. However, mainly due to the experimental difficulties, data for the mechanistic understanding and prediction of failures of the specific in-vessel components are still insufficient and further well-controlled experiments are needed [1]. In recent years, efforts to perform the in-pile materials test for IASCC study have been made at some research reactors [2-4]. At JAERI, a high temperature water loop facility was designed to install at the Japan Materials Testing Reactor (JMTR) to carry out the in-core IASCC testing. This report describes an overview of design and specification of the loop facility. (authors)

  3. In-pile Thermal Conductivity Characterization with Time Resolved Raman

    Energy Technology Data Exchange (ETDEWEB)

    Wang, Xinwei [Iowa State Univ., Ames, IA (United States). Dept. of Mechanical Engineering; Hurley, David H. [Idaho National Lab. (INL), Idaho Falls, ID (United States)

    2018-03-19

    The project is designed to achieve three objectives: (1) Develop a novel time resolved Raman technology for direct measurement of fuel and cladding thermal conductivity. (2) Validate and improve the technology development by measuring ceramic materials germane to the nuclear industry. (3) Conduct instrumentation development to integrate optical fiber into our sensing system for eventual in-pile measurement. We have developed three new techniques: time-domain differential Raman (TD-Raman), frequency-resolved Raman (FR-Raman), and energy transport state-resolved Raman (ET-Raman). The TD-Raman varies the laser heating time and does simultaneous Raman thermal probing, the FR-Raman probes the material’s thermal response under periodical laser heating of different frequencies, and the ET-Raman probes the thermal response under steady and pulsed laser heating. The measurement capacity of these techniques have been fully assessed and verified by measuring micro/nanoscale materials. All these techniques do not need the data of laser absorption and absolute material temperature rise, yet still be able to measure the thermal conductivity and thermal diffusivity with unprecedented accuracy. It is expected they will have broad applications for in-pile thermal characterization of nuclear materials based on pure optical heating and sensing.

  4. In-pile loop experiments in water chemistry and corrosion

    International Nuclear Information System (INIS)

    Kysela, J.

    1986-09-01

    Results on the study of Zr-1% Nb alloy corrosion, in out-of and in-pile loops simulating the working conditions of the VVER-440 reactor (Soviet, PWR type), covered the time period May 1982-April 1986 were reported, as well as, results on transport and filtration of corrosion products. Methods and techniques used in the study included remote measurement of corrosion rate by polarizing resistance, out-of-pile loop at the temperature 350 deg. C, pressure 19 MPa, circulation 20 kgs/h and in-pile water loop with constant flow rate 10,000 kgs/h, pressure 16 MPa, temperature 330 deg. C and neutron flux 7x10 13 n/cm 2 .s. It was shown that solid suspended particles with chemical composition corresponding most frequently to magnetite or nickelous ferrite, though with non-stoichiometric composition Me x 2+ Fe 3- x 3+ O 4 were found. Continuous filtration of water by means of electromagnetic filter leads to a decrease of radioactivity of the outer epitactic layer only. Effect of filtration on the inner topotactic layer is negligible. The corrosion rates for the above-mentioned parameters are given

  5. Characteristics of pressure control system on PWR/PHWR in pile loop facility

    International Nuclear Information System (INIS)

    Sarwani; Hendro, P.; Suwoto; Sutrisno

    1998-01-01

    PWR/PHWR in-pile loop facility is used for testing of fuel element bundle which is correspond to the condition of power reactor operation. So, this facility is designed at 150 bar of pressure and 350 o C of temperature. Pressure control system is one of the components of the facility and it is equipped with 6 electrical heaters (30 KW), water spray, pressure and temperature monitors. The characterization test of pressure control system has been carried out with operating of 2 electrical heaters (10 KW). The K eff calculation value is different 5.2% from pressure in the pressure control system can be increased to 160 bar within 27 hours. After the system pressure reached the nominal pressure, the pressure control system was in the steady state condition

  6. In-pile Hydrothermal Corrosion Evaluation of Coated SiC Ceramics and Composites

    Energy Technology Data Exchange (ETDEWEB)

    Carpenter, David [Massachusetts Inst. of Technology (MIT), Cambridge, MA (United States); Ang, Caen [Univ. of Tennessee, Knoxville, TN (United States); Katoh, Yutai [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Linton, Kory D. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Terrani, Kurt A. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)

    2017-09-01

    Hydrothermal corrosion accelerated by water radiolysis during normal operation is among the most critical technical feasibility issues remaining for silicon carbide (SiC) composite-based cladding that could provide enhanced accident-tolerance fuel technology for light water reactors. An integrated in-pile test was developed and performed to determine the synergistic effects of neutron irradiation, radiolysis, and pressurized water flow, all of which are relevant to a typical pressurized water reactor (PWR). The test specimens were chosen to cover a range of SiC materials and a variety of potential options for environmental barrier coatings. This document provides a summary of the irradiation vehicle design, operations of the experiment, and the specimen loading into the irradiation vehicle.

  7. In-pile measurement of the thermal conductivity of irradiated metallic fuel

    International Nuclear Information System (INIS)

    Bauer, T.H.; Holland, J.W.

    1995-01-01

    Transient test data and posttest measurements from recent in-pile overpower transient experiments are used for an in situ determination of metallic fuel thermal conductivity. For test pins that undergo melting but remain intact, a technique is described that relates fuel thermal conductivity to peak pin power during the transient and a posttest measured melt radius. Conductivity estimates and their uncertainty are made for a database of four irradiated Integral Fast Reactor-type metal fuel pins of relatively low burnup (<3 at.%). In the assessment of results, averages and trends of measured fuel thermal conductivity are correlated to local burnup. Emphasis is placed on the changes of conductivity that take place with burnup-induced swelling and sodium logging. Measurements are used to validate simple empirically based analytical models that describe thermal conductivity of porous media and that are recommended for general thermal analyses of irradiated metallic fuel

  8. Measurement data of cesium 137 yields in primary coolant of an in-pile water loop in fission products release experiment

    International Nuclear Information System (INIS)

    Ishiwatari, Nasumi; Nagai, Hitoshi; Takeda, Tsuneo

    1979-03-01

    Series of fuel rods (UO 2 pellets sheathed with stainless steel) having an artificial pinhole were irradiated in the in-pile test section of water loop JMTR OWL-1. Presented are the results of measurements of cesium 137 yields in primary coolant of OWL-1 from 1975 to 1978. (author)

  9. QC in RIA

    International Nuclear Information System (INIS)

    Little, J.

    1989-01-01

    A Regional Health Authority expert from the service which performs radioimmunoassays (RIA) and immunoradiometric assays (IRMA) discusses the importance of quality control in these techniques. Originally developed as an aid to endocrinology, applications are now much more widely based and include virology, microbiology, drugs testing, immunology, parasitology, veterinary science and the food industry. The origins of errors in the practice of RIA are examined, with and between batches and the limitations placed on accuracy are explained. Measurement variability between laboratories is also mentioned. (U.K.)

  10. Acoustic sensor for in-pile fuel rod fission gas release measurement

    International Nuclear Information System (INIS)

    Fourmentel, D.; Villard, J. F.; Ferrandis, J. Y.; Augereau, F.; Rosenkrantz, E.; Dierckx, M.

    2009-01-01

    We have developed a specific acoustic sensor to improve the knowledge of fission gas release in Pressurized Water Reactor (PWR) fuel rods when irradiated in materials testing reactors. In order to perform experimental programs related to the study of the fission gas release kinetics, the CEA (French Nuclear Energy Commission) acquired the ability to equip a pre-irradiated PWR fuel rod with three sensors, allowing the simultaneous on-line measurements of the following parameters: - fuel temperature with a centre-line thermocouple type C, - internal pressure with a specific counter-pressure sensor, - fraction of fission gas released in the fuel rod with an innovative acoustic sensor. The third detector is the subject of this paper. This original acoustic sensor has been designed to measure the molar mass and pressure of the gas contained in the fuel rod plenum. For in-pile instrumentation, the fraction of fission gas, such as Krypton and Xenon, in Helium, can be deduced online from this measurement. The principle of this acoustical sensor is the following: a piezoelectric transducer generates acoustic waves in a cavity connected to the fuel rod plenum. The acoustic waves are propagated and reflected in this cavity and then detected by the transducer. The data processing of the signal gives the velocity of the acoustic waves and their amplitude, which can be related respectively to the molar mass and to the pressure of the gas. The piezoelectric material of this sensor has been qualified in nuclear conditions (gamma and neutron radiations). The complete sensor has also been specifically designed to be implemented in materials testing reactors conditions. For this purpose some technical points have been studied in details: - fixing of the piezoelectric sample in a reliable way with a suitable signal transmission, - size of the gas cavity to avoid any perturbation of the acoustic waves, - miniaturization of the sensor because of narrow in-pile experimental devices

  11. In-pile post-DNB behavior of a nine-rod PWR-type fuel bundle

    International Nuclear Information System (INIS)

    Gunnerson, F.S.; MacDonald, P.E.

    1980-01-01

    The results of an in-pile power-cooling-mismatch (PCM) test designed to investigate the behavior of a nine-rod, PWR-type fuel bundle under intermittent and sustained periods of high temperature film boiling operation are presented. Primary emphasis is placed on the DNB and post-DNB events including rod-to-rod interactions, return to nucleate boiling (RNB), and fuel rod failure. A comparison of the DNB behavior of the individual bundle rods with single-rod data obtained from previous PCM tests is also made

  12. Use of standard reliability levels in design and safety assessment of in-pile loops

    International Nuclear Information System (INIS)

    Bogani, G.; Verre, A.; Balestreri, S.; Colombo, A.G.; Luisi, T.

    1975-01-01

    This paper describes a logic-probabilistic analysis technique for a critical design review and safety assessment of in-pile loops. The examples in this paper refer to the analysis performed for the experimental loops already constructed or under construction in the ESSOR reactor of the Joint Research Centre of Ispra, as irradiation facilities for fuel element research and development tests. The proposed technique is based on the classification into categories of components and protective device malfunctions. Such subdivision into categories was agreed upon by the Italian Safety Authority and Euratom JRC, and adopted for the safety assessment of the ESSOR reactor in-pile loops. For each category, the method makes a link with a corresponding malfunction probability range (probability level). This probability level is defined taking into account design, construction, inspection and maintenance criteria as well as periodic controls; therefore the quality level and consequently the reliability level are thus also defined. The analysis is developed in the following stages: (1) definition of the analysis object (top event) and drawing of the relative fault-tree; (2) loop design analysis and preliminary optimization based on logic criteria; (3) classification into categories of the fault-tree primary events; (4) final loop design analysis and optimization based on defined component quality requirements. Stages 2 and 4 are quite different since stage 2 mainly consists of a redundance optimization, while stage 4 acts on the component quality level in such a way that each minimum cut-set leading to the top has an acceptable probability level. During analysis development, use is made of computer codes which, among other things enable the verification of fault-tree logic makeup, the listing of the minimum cut-sets with and without event categorization, and the evaluation of each cut-set order. (author)

  13. Fuel disruption mechanisms determined in-pile in the ACRR

    International Nuclear Information System (INIS)

    Wright, S.A.; Fischer, E.A.

    1984-09-01

    Over thirty in-pile experiments were performed to investigate fuel disruption behavior for LMFBR loss of flow (LOF) accidents. These experiments reproduced the heating transients for a variety of accidents ranging from slow LOF accidents to rapid LOF-driven-TOP accidents. In all experiments the timing and mode of the fuel disruption were observed with a high speed camera, enabling detailed comparisons with a fuel pin code, SANDPIN. This code transient intra- and inter-granular fission gas behavior to predict the macroscopic fuel behavior, such as fission gas induced swelling and frothing, cracking and breakup of solid fuel, and fuel vapor pressure driven dispersal. This report reviews the different modes of fuel disruption as seen in the experiments and then describes the mechanism responsible for the disruption. An analysis is presented that describes a set of conditions specifying the mode of fuel disruption and the heating conditions required to produce the disruption. The heating conditions are described in terms of heating rate (K/s), temperature gradient, and fuel temperature. A fuel disruption map is presented which plots heating rate as a function of fuel temperature to illustrate the different criteria for disruption. Although this approach to describing fuel disruption oversimplifies the fission gas processes modeled by SANDPIN, it does illustrate the criteria used to determine which fuel disruption mechanism is dominant and on what major fission gas parameters it depends

  14. Evaluation of the in-pile pressure data from instrumented fuel assemblies IFA-431 and IFA-432

    International Nuclear Information System (INIS)

    Bradley, E.R.; Cunningham, M.E.; Lanning, D.D.; Williford, R.E.

    1979-10-01

    This report includes results of the examination of the in-pile pressure data from instrumented test assemblies IFA-431 and 432. The pressure data have been used to estimate the fission gas release fraction as a function of fuel burnup. Included are comparisons of the estimated release functions and those predicted by three fission gas release models using the experimental temperature histories of the fuel rods. These comparisons show that fuel temperature is the primary factor in determining fission gas release and that burnup-enhanced fission gas release is not important in UO 2 fuels irradiated to 1700 GJ/kgU

  15. Study of a device for the direct measurement of the fission gas pressure inside an in-pile fuel element

    International Nuclear Information System (INIS)

    Lavaud, B.; Uschanoff, S.

    1964-01-01

    The fission gas pressure inside a fuel element made of a refractory fuel constitutes an important limiting factor for the burn-up. Although it is possible to calculate approximately the volume of gas produced outside the fuel during its life-time; it is nevertheless very difficult to evaluate the pressure since the volume allowed to the fission gases, as well as their temperature are known only very approximately. This physical value, which is essential for the technologist, can only be known by direct in-pile measurement of the pressure. The report describes the equipment which has been developed for this test. (authors) [fr

  16. In-pile creep behaviour of Zry-4 and ZrNb3Sn1 cladding under uniaxial and biaxial stress

    International Nuclear Information System (INIS)

    Boehner, G.; Wildhagen, B.; Wilhelm, H.

    1987-01-01

    An irradiation programme - started in 1977 - was performed at the research reactor FRG-2 at Geesthacht, Germany, as a joint project of GKSS and KWU in order to study the in-pile creep behaviour of zirconium alloy cladding tubes of PWR fuel rods. The test objective was to establish a data base which allows refined modelling of the in-pile creep phenomenon. A wide test matrix was realized in which each of the precisely monitored test conditions (hoop stress, temperature, fast neutron flux) was varied separately. Different cladding materials (Zircaloy-4 and Zirconium-Niob-Tin alloy ZrNb3Sn1) were subjected to those varying test conditions. Cladding tube specimens of 10.75 mm outer diameter were irradiated in test capsules under various stress conditions and levels up to approx. 6000 h, at temperatures ranging from 300 0 C to 400 0 C and fast neutron flux (E > 1 MeV) of approx. 3x10 13 cm -2 .s -1 . Diametrical and/or axial creep deformation of all tubes were measured in the Hot Cells several times in the course of the tests. In order to extract the irradiation induced creep strain some out-pile experiments were carried out under the very same test conditions as the in-pile tests concerned. (orig./GL)

  17. A review of radionuclide release and transport in recent in-pile experiments

    International Nuclear Information System (INIS)

    Harman, N.F.; Clough, P.N.

    1992-01-01

    The experimental series, reviewed in this work, are LOFT-LP-FP-2, PBF SFD ST to 1-4, Treat/STEP I to 4, and ACRR ST-1 and ST-2. These have the common features of in-core heating of a test fuel bundle to high temperatures (usually with some fuel melting) in an experimental reactor core, and of collecting and analysing the released fission products. They were designed to provide detailed information on the release from fuel of fission products and other radionuclides under LWR severe accident conditions, and on the chemical and physical forms and transport of the fission products. The main aim of this review is to bring together, in a systematic way, information on the conduct of the tests, on their successes and failures, and particularly on the information they generated on the chemical and physical behaviour of released fission products. By examining and analysing the data from all of the tests together, patterns of fission product behaviour may become apparent and insights may be gained, which would not be arrived at from individual test results. Moreover, important lessons may be learned, and useful guidance obtained, relating to the aims and conduct of future experimental programmes of fission product release from fuel and transport behaviour. The conclusions should be particularly relevant to the imminent Phebus-FP in-pile test series at Cadarache

  18. O uso de provas de atividade inflamatória em reumatologia The use of inflammatory laboratory tests in rheumatology

    Directory of Open Access Journals (Sweden)

    Nilton Salles Rosa Neto

    2009-08-01

    Full Text Available A inflamação, localizada ou sistêmica, é uma das características de doenças reumatológicas. A resposta a uma lesão tecidual desencadeia uma série de modificações que promovem eliminação de patógenos, limitação do dano tecidual e restauração da estrutura lesada. Essas modificações dependem do aumento ou da diminuição da concentração sérica de proteínas, conhecidas como biomarcadores inflamatórios, que atuam na resposta inflamatória. A análise laboratorial desses marcadores permite, juntamente com os dados clínicos e outros exames complementares, acessar a atividade de algumas doenças e monitorar a resposta à terapêutica, assim como pode sugerir presença de infecção. Atualmente, o reumatologista tem à sua disposição algumas opções de exames que avaliam a resposta inflamatória, como a proteína C-reativa, a velocidade de hemossedimentação e a eletroforese de proteínas, entre outros. Este artigo revisa as características de alguns desses biomarcadores e o emprego das provas de atividade inflamatória em doenças reumatológicas.Inflammation is the hallmark of rheumatic diseases. Tissue injury response promotes several modifications, which result in elimination of the offending agent, limitation of tissue damage, and restoration of affected structures. Such modifications depend on the increase or decrease of the serum concentration of certain proteins known as inflammatory biomarkers. Laboratory analysis of these markers assists in monitoring disease activity and treatment response. Rheumatologists have available methods that evaluate inflammatory reaction such as C-reactive protein, erythrocyte sedimentation rate, and protein electrophoresis, among others. In this paper, we review some of those biomarkers and their use in rheumatic diseases.

  19. Development of In-pile Plug Assembly and Primary Shutter for Cold Neutron Guide System

    Energy Technology Data Exchange (ETDEWEB)

    Shin, Jin Won; Cho, Yeong Garp; Ryu, Jeong Soo; Lee, Jung Hee [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2008-12-15

    The HANARO, a 30 MW multi-purpose research reactor in Korea, will be equipped with a neutron guide system, in order to transport cold neutrons from the neutron source to the neutron scattering instruments in the neutron guide hall near the reactor building. The neutron guide system of HANARO consists of the in-pile plug assembly with in-pile guides, the primary shutter with in-shutter guides, the neutron guides in the guide shielding room with dedicated secondary shutters, and the neutron guides connected to the instruments in the neutron guide hall. The functions of the in-pile plug assembly are to shield the reactor environment from a nuclear radiation and to support the neutron guides and maintain them precisely oriented. The primary shutter is a mechanical device to be installed just after the in-pile plug assembly, which stops neutron flux on demand. This report describes the mechanical design, fabrication, and installation procedure of the in-pile plug assembly and the primary shutter for the neutron guide system at HANARO. A special tool and procedure for a replacement of in-pile plug and guide cassette is also presented with the interface condition in the reactor hall.

  20. Innovations for In-Pile Measurements in the Framework of the CEA-SCK•CEN Joint Instrumentation Laboratory

    Science.gov (United States)

    Villard, Jean-Francois; Schyns, Marc

    2010-12-01

    Optimizing the life cycle of nuclear systems under safety constraints requires high-performance experimental programs to reduce uncertainties on margins and limits. In addition to improvement in modeling and simulation, innovation in instrumentation is crucial for analytical and integral experiments conducted in research reactors. The quality of nuclear research programs relies obviously on an excellent knowledge of their experimental environment which constantly calls for better online determination of neutron and gamma flux. But the combination of continuously increasing scientific requirements and new experimental domains -brought for example by Generation IV programsnecessitates also major innovations for in-pile measurements of temperature, dimensions, pressure or chemical analysis in innovative mediums. At the same time, the recent arising of a European platform around the building of the Jules Horowitz Reactor offers new opportunities for research institutes and organizations to pool their resources in order to face these technical challenges. In this situation, CEA (French Nuclear Energy Commission) and SCK'CEN (Belgian Nuclear Research Centre) have combined their efforts and now share common developments through a Joint Instrumentation Laboratory. Significant progresses have thus been obtained recently in the field of in-pile measurements, on one hand by improvement of existing measurement methods, and on the other hand by introduction in research reactors of original measurement techniques. This paper highlights the state-of-the-art and the main requirements regarding in-pile measurements, particularly for the needs of current and future irradiation programs performed in material testing reactors. Some of the main on-going developments performed in the framework of the Joint Instrumentation Laboratory are also described, such as: - a unique fast neutron flux measurement system using fission chambers with 242Pu deposit and a specific online data processing

  1. Nuclear heating measurements by in-pile calorimetry: prospective works for a microsensor design

    Energy Technology Data Exchange (ETDEWEB)

    Reynard-Carette, C.; Carette, M.; Aguir, K.; Bendahan, M.; Fiorido, T. [Aix Marseille Universite, CNRS, Universite de Toulon, IM2NP UMR 7334, 13397, Marseille (France); Lyoussi, A.; Fourmentel, D.; Villard, J.F. [CEA, DEN, DER, Instrumentation Sensors and Dosimetry Laboratory, Cadarache, F-13108 (France); Barthes, M.; Lanzetta, F.; Layes, G.; Vives, S. [FEMTO-ST, UMR 6174, Departement ENERGIE, Universite de Franche-Comte, 90000, Belfort (France)

    2015-07-01

    Since 2009 works have been performed in the framework of joint research programs between CEA and Aix-Marseille University. The main aim of these programs is to design and develop in-pile instrumentations, advanced calibration procedure and accurate measurement methods in particular for the new Material Testing Reactor (MTR) under construction in the South of France: Jules Horowitz Reactor (JHR). One major sensor is a specific radiometric calorimeter, which was studied out-of-pile from a thermal point of view and in-pile during irradiation campaigns. This sensor type is dedicated to measurements of nuclear heating (energy deposition rate per mass unit induced by interactions between nuclear rays and matter) inside experimental channels of MTRs. This kind of in-pile calorimeter corresponds to heat flux calorimeter exchanging with the external cooling fluid. This thermal running mode allows the establishment of steady thermal conditions inside the sensor to carry out online continuous measurements inside the reactor (core or reflector). Two main types of calorimeters exist. The first type consists of a single cell calorimeter. It is divided into a sample of material to be tested and a jacket instrumented with two thermocouples or a single thermocouple (Gamma Thermometer). The second, called a differential calorimeter, is composed of two superposed twin cells (a measurement cell containing a sample of material, and a reference cell to remove the heating of the cell body) instrumented with four thermocouples and two electrical heaters. Contrary to a single-cell calorimeter, a differential calorimeter allows the compensation of the parasite nuclear heating of the sensor body or jacket. Moreover, it possesses interesting advantages: thanks to the heaters embedded in the cells, three different measurement methods can be applied during irradiations to quantify nuclear heating. The first one is based on the use of out-of-pile calibration curves obtained by generating a heat

  2. In-Pile thermal fatigue of First Wall mock-ups under ITER relevant conditions

    International Nuclear Information System (INIS)

    Blom, F.; Schmalz, F.; Kamer, S.; Ketema, D.J.

    2006-01-01

    The objective of this study is to perform in-pile thermal fatigue testing of three actively cooled First Wall (FW) mock-ups to check the effect of neutron irradiation on the Be/CuCrZr joints under representative FW operation conditions. Three FW mock-ups with Beryllium armor tiles will be neutron irradiated at 1 dpa (in Be) with parallel thermal fatigue testing for 30,000 cycles. The temperatures, stress distributions and stress amplitudes at the Be/CuCrZr interface of the mock-ups will be as close as possible to the values calculated for ITER FW panels. For this objective the PWM mocks-up subjected to thermal fatigue will be integrated with high density (W) plates on the Be-side to provide heat flux by nuclear heating. The assembly will be placed in the pool-side facility of the HFR and thermal cycling is then arranged by mechanical movement towards and from the core box. As the thermal design of the irradiation rig is very critical a pilot-irradiation will be performed to cross check the models used in the thermal design of the rig. The project is currently in the design phase of both the pilot and actual irradiation rig. The irradiation of the actual rig is planned to start at mid 2007 and last for two years. (author)

  3. In-pile experiments on fuel rod behavior during a LOCA

    International Nuclear Information System (INIS)

    Karb, E.; Pruessmann, M.; Sepold, L.

    1980-05-01

    This report describes the results of the Test Series F, Tests F 1 through F 5, in the in-pile experimental program with single rods in the DK loop of the FR2 reactor at the Kernforschungszentrum Karlsruhe (KfK). The research is part of the Nuclear Safety Project's (PNS) fuel behavior program. The main objective of the FR2-LOCA tests is to provide information about the effects of a nuclear environment on the mechanisms of fuel rod failure in the second heatup phase of a LOCA. The test rods have a heated length of 50 cm, and their radial dimensions are identical with those of a commercial German PWR. The main parameter of the FR2-LOCA test program is the burnup. The F tests were perfomed from Oct. 25, 1977 to Nov. 22, 1977. They were the first tests in this program to use pre-irradiated fuel rods. The nominal burnup of the test rods was 20 000 MWd/t. During the transient test, the test rods were subjected to rod powers between 36 and 41 W/cm and were pressurized with He to hot internal pressures between 46 and 83 bar. The test rods during the heatup phase at pressures of 56, 53, 42, 72 and 60 bar, respectively. The burst temperatures were determined to be 890, 893, 932, 835 and 880 0 C for test F 1 through F 5. The maximum total circumferential elongations amount to 59, 38, 27, 34 and 41%, respectively. The F tests revealed a fragmentation of the fuel after the irradiation (prior to the tests) and a disintegration of the fuel pellet column after the transient tests due to cladding ballooning. The post-test results indicated a significant reduction of the pellet stack length for all five test rods. The burst data of the F tests did not reveal any difference between tests with unirradiated fuel rods and the irradiated fuel rods of this test series. (orig./HP) [de

  4. Study of behavior of cermet fuel elements on IGR reactor under RIA type accident condition

    International Nuclear Information System (INIS)

    Vasil'ev, Yu.S.; Vurim, A.D.; Koltyshev, S.M.; Pakhnits, V.A.; Tukhvatulin, Sh.T.; Popov, V.V.; Ryzhkov, A.N.

    1996-01-01

    In 1993 December in IGR reactor of Inst. of Atomic Energy of National Nuclear Center of Republic of Kazakstan the second batch of in-pile testing of perspective cermet fuel elements under the condition, simulating RIA type accident was conducted. In the second batch of testing during eight start-ups 10 cermet fuel elements were examined. Among which 8 of monolith type and 2 fuel elements with false jacket beside cladding (FJF), as well as, 6 standard fuel elements of WWER-1000 type reactor with dioxide fuel were tested. 2 fuel elements - cermet and standard were placed into capsule filled with water. To measure energy release for the each start-up two fission monitor and inside core control gauge were placed. In all the start-ups operation mode of IGR was neutron pulse. Power of fuel element kept changing from 151 to 336 k W; energy release was 38-93 kJ/gr m 235 U; maximum temperature of cermet fuel was 1943-2173 K, of dioxide fuel - 1923-2843 K. The testing has demonstrated that operability of cermet fuel elements under reactivity accident condition with pulse width of 0,2 s is, at least, not less that operability of dioxide fuel elements, through advantages of cermet fuel under these conditions are revealed to the least extent

  5. In-pile creep strain and failure of CW 316 Ti pressurized tubes

    International Nuclear Information System (INIS)

    Boutard, J.L.; Maillard, A.; Carteret, Y.; Levy, V.; Meny, L.

    1984-06-01

    The in-pile creep and failure behavior of CW 316 Ti pressurized tubes irradiated in the same rig at 660-680 0 C and 81.4 dpaF max in Phenix is presented and compared to monitors of the same heat. The in-pile plastic strains are of the same order of what is expected from the monitors and are rather independent of the dose rate in the range 4 to 9 x 10 -3 dpaF/h. Such a behavior supports the assumption that the out-of-pile deformation mechanisms are operative in pile and a certain balance occurs between modification of the microstructure, dynamic hardening and deformation mechanisms due to irradiation. Examinations by fractography and optical micrography, show that the failures are intergranular either in-pile or out-of-pile. In both cases the damage consists in intergranular wedge cracks, and no cavitation can be observed by transmission electron microscopy. Then the in-pile embrittlement which gives lower failure strain and time is to be associated with a decrease of the surface energy of grain-boundaries rather then growth and coalescence of cavities

  6. Reprodutibilidade do teste de caminhada de 6 minutos e marcadores autonômicos cardíacos em idosas ativas e sedentárias

    Directory of Open Access Journals (Sweden)

    André Igor Fonteles

    2016-07-01

    Full Text Available DOI: http://dx.doi.org/10.5007/1980-0037.2016v18n3p287   Objetivou-se verificar a reprodutibilidade do teste de caminhada de 6 minutos (TC6 e de marcadores autonômicos cardíacos pós-esforço em idosas fisicamente ativas e sedentárias. Dezoito idosas ativas (64,2 ± 3,1 anos; 63,0 ± 2,7 kg; 1,52 ± 0,06 m; 26,9 ± 2,7 kg.m-2 praticantes de Tai Chi Chuan (≥6 meses de prática e 18 idosas sedentárias (64,0 ± 3,7 anos; 63,8 ± 8,9 kg; 1,49 ± 0,05 m; 28,4 ± 3,5 kg.m-2 foram submetidas a dois TC6 com uma semana de intervalo. Foram medidas a frequência cardíaca de recuperação (FCR de um e dois minutos (FCR1’ e FCR2’, respectivamente e variabilidade da frequência cardíaca (VFC pós-esforço. A reprodutibilidade foi verificada pelos: coeficiente de correlação intraclasse (CCI com 95% de intervalo de confiança; análise de concordância de Bland-Altman; e coeficiente de variação (CV. O desempenho no TC6 (528,8±71,4 m e 473,2±62,4 m; CV=7,9% e CV=8,5% apresentou alta reprodutibilidade (CCI=0,86 em idosas ativas e sedentárias, respectivamente. Similarmente, as medidas pós-esforço da FCR1’ (29,0±11,0 bpm e 17,0±8,0 bpm; CV=30,1% e CV=40,2% e FCR2’ (36,0±10,0 bpm e 24,0±9,0 bpm; CV=23,7% e CV=22,8% apresentaram alta reprodutibilidade (CCI≥0,84 e CCI≥0,80 em ambos os grupos. Quanto a VFC verificou-se reprodutibilidade moderada (CCI≥0,57; CV=35-47% em idosas ativas e moderada-alta nas sedentárias (CCI=0,65-0,76; CV=34-69%. Todas as variáveis apresentaram concordância em ambos os grupos. Conclui-se que o TC6, FCR e VFC pós-esforço são instrumentos reprodutíveis na avaliação da capacidade funcional e controle autonômico cardíaco em idosas ativas e sedentárias.

  7. Complex paraclinoidal and giant cavernous aneurysms: importance of preoperative evaluation with temporary balloon occlusion test and SPECT Aneurismas paraclinoideos complexos e cavernosos gigantes: importância da avaliação pré-operatória com teste de oclusão temporária com balão e SPECT

    Directory of Open Access Journals (Sweden)

    Antônio Aversa do Souto

    2006-09-01

    Full Text Available In the treatment of complex paraclinoidal and giant cavernous aneurysms, preservation of the patency of the internal carotid artery (ICA is not always possible, and therapeutic occlusion of the carotid is still an important option for their management. A complete preoperative evaluation of the carotid reserve circulation, including the use of temporary balloon occlusion test and single photon emission computerized tomography (SPECT should be included in the current paradigms of paraclinoidal and intracavernous aneurysms management. We present a series of fifteen patients with sixteen giant or complex carotid cavernous or ophthalmic aneurysms that were treated following a protocol for our preoperative decision-making analysis. Extracranial to intracranial saphenous vein bypass was reserved to the cases where carotid occlusion would be associated with high risk of ischemic complications and was performed in three patients. Besides the difficulties in dealing with those complex aneurysms, good clinical outcome was possible in our experience with the designed paradigm.No tratamento de aneurismas paraclinoideos complexos e cavernosos gigantes, a preservação da patência vascular nem sempre é possível, e a oclusão terapêutica da carótida ainda é uma opção importante no seu manejo. Uma avaliação pré-operatória completa da reserva circulatória carotídea, incluindo o uso do teste de oclusão temporária por balão associado à tomografia computadorizada por emissão de fóton único (SPECT podem ser de grande utilidade para definir a opção terapêutica a ser adotada. Nós apresentamos uma série de quinze pacientes com dezesseis aneurismas complexos ou gigantes do segmento oftálmico e cavernoso da artéria carótida, que foram tratados de acordo com determinado protocolo de investigação pré-operatória. Anastomose com enxerto de veia safena entre a carótida extra e intracraniana foi reservada para os casos em que a oclusão carot

  8. Viability of Pushrod Dilatometry Techniques for High Temperature In-Pile Measurements

    Energy Technology Data Exchange (ETDEWEB)

    J. E. Daw; J. L. Rempe; D. L. Knudson; K. G. Condie; J. C. Crepeau

    2008-03-01

    To evaluate the performance of new fuel, cladding, and structural materials for use in advanced and existing nuclear reactors, robust instrumentation is needed. Changes in material deformation are typically evaluated out-of-pile, where properties of materials are measured after samples were irradiated for a specified length of time. To address this problem, a series of tests were performed to examine the viability of using pushrod dilatometer techniques for in-pile instrumentation to measure deformation. The tests were performed in three phases. First, familiarity was gained in the use and accuracy of this system by testing samples with well defined thermal elongation characteristics. Second, high temperature data for steels, specifically SA533 Grade B, Class 1 (SA533B1) Low Alloy Steel and Stainless Steel 304 (SS304), found in Light Water Reactor (LWR) vessels, were aquired. Finally, data were obtained from a short pushrod in a horizontal geometry to data obtained from a longer pushrod in a vertical geometry, the configuration likely to be used for in-situ measurements. Results of testing show that previously accepted data for the structural steels tested, SA533B1 and SS304, are inaccurate at high temperatures (above 500 oC) due to extrpolation of high temperature data. This is especially true for SA533B1, as previous data do not account for the phase transformation of the material between 730 oC and 830 oC. Also, comparison of results for horizontal and vertical configurations show a maximum percent difference of 2.02% for high temperature data.

  9. Acoustic Emission Signal Processing Technique to Characterize Reactor In-Pile Phenomena

    Energy Technology Data Exchange (ETDEWEB)

    Vivek Agarwal; Magdy Samy Tawfik; James A Smith

    2014-07-01

    Existing and developing advanced sensor technologies and instrumentation will allow non-intrusive in-pile measurement of temperature, extension, and fission gases when coupled with advanced signal processing algorithms. The transmitted measured sensor signals from inside to the outside of containment structure are corrupted by noise and are attenuated, thereby reducing the signal strength and signal-to-noise ratio. Identification and extraction of actual signal (representative of an in-pile phenomenon) is a challenging and complicated process. In this paper, empirical mode decomposition technique is proposed to reconstruct actual sensor signal by partially combining intrinsic mode functions. Reconstructed signal corresponds to phenomena and/or failure modes occurring inside the reactor. In addition, it allows accurate non-intrusive monitoring and trending of in-pile phenomena.

  10. Distúrbio específico de linguagem: desempenho em testes de memória de trabalho fonológica e de habilidades auditivas

    Directory of Open Access Journals (Sweden)

    Lidiane Yumi Sawasaki

    2017-01-01

    Full Text Available Hipóteses vêm sendo apontadas para explicar as dificuldades linguísticas de crianças com Distúrbio Específico de Linguagem (DEL, e, dentre elas, podemos citar alterações na memória de trabalho fonológica (MTF e no processamento auditivo temporal (PAT. Assim, o objetivo do presente estudo foi verificar o desempenho de sujeitos com DEL em testes de MTF, de PAT e de atenção auditiva sustentada (AAS e, ainda, verificar se há correlação entre eles. Foram selecionadas 12 crianças com idades entre 6 e 10 anos, sendo nove meninos, com diagnóstico de DEL da Clínica de Fonoaudiologia da FOBjUSP de Bauru. Foram aplicados os seguintes testes: prova de memória de trabalho fonológica (MTF não palavras e dígitos, teste da habilidade de resolução temporallZl Random Gap Detection Test (RGDT !li e teste de habilidade de atenção auditiva sustentada (THAAS. Nas três provas aplicadas IZIMTF, AAS e PAT !li foram encontrados resultados inferiores à normalidade. Na literatura há fortes evidências de que crianças com DEL apresentam desempenho inadequado em tarefas de MTF que envolvem o armazenamento de um estímulo verbal, fato também confirmado neste trabalho. Como se verificou neste trabalho, DEL pode também estar associado a dificuldades no processamento de elementos acústicos breves e na atenção sustentada. Foi possível verificar com este estudo que quadros de DEL podem apresentar dificuldades de MTF, de atenção sustentada e em habilidades de resolução temporal. Mesmo não havendo correlação entre os testes, a grande maioria das crianças com DEL apresentou desempenho deficitário nas habilidades testadas. O DEL decorre de uma dificuldade constitucional para o processamento neuropsicológico da linguagem, e, desse modo, pessoas com esse quadro podem apresentar disfunção em qualquer nível do processamento, incluindo o processamento auditivo.  

  11. Eficiência dos testes cromáticos de comparação na discromatopsia hereditária: relato de casos Efficiency of color vision tests in hereditary dyschromatopsia: case report

    Directory of Open Access Journals (Sweden)

    Luciene Chaves Fernandes

    2008-08-01

    Full Text Available As autoras relatam dois casos de discromatopsia hereditária e discutem a eficiência dos testes cromáticos no diagnóstico de uma discromatopsia. Os pacientes foram reprovados em diferentes concursos públicos federais por apresentarem diagnóstico de discromatopsia hereditária pelo teste de Ishihara. Submeteram-se a exame oftalmológico, com resultados dentro da normalidade. Procuraram novo parecer para melhor caracterização da sua discromatopsia. Não havia sintomas relacionados à deficiência. Os testes Panel D15 simples, D28 de Roth mostraram-se normais e o D15 dessaturado confirmou deutanomalia no caso 1. No segundo caso os testes de comparação mostraram alterações sem significado cromático. O diagnóstico de uma discromatopsia é muito complexo. As autoras destacam a importância de realização de testes de visão cromática complementares ao teste de Ishihara para diagnóstico de uma discromatopsia.The authors describe two cases of hereditary dyschromatopsia and discuss the efficiency of the color vision tests. The patients were disapproved in different federal public examinations because Ishihara's test diagnosed hereditary dyschromatopsia. Ophthalmological evaluation was normal. No symptoms related to dyschromatopsia were presented. Panels D15 and Roth D 28 were normal. Desaturated D 15 showed deuteranomaly in case one. In the second case the comparative color vision tests showed nonspecific disorder. The diagnosis of dyschromatopsia is complex. The authors recommend comparative color vision tests to complement the Ishihara test for a better understanding of the color deficiency.

  12. In-Pile Loop Safety in Integrated with the Multipurpose Reactor in the case of in-Pile Loop Leakage at the Core Position

    International Nuclear Information System (INIS)

    Suharno; Sugianto; Giarno; Aliq; Widodo, Surip; Aji, Bintoro; Purba, Julwan Hendry; Karyanta, Edy

    1999-01-01

    In-Pile Loop Safety analysis in integrated with the multipurpose reactor in the case of In-Pile Loop leakage at the core position has been conducted which intended to evaluate the failure of fuel element. By considering design of In-Pile Loop and the highest possibility position of of leakage, the failure of fuel element is emphasized on mechanical aspect. The thermal hydraulic aspect is not taken into account due to the condition that when the leakage occurred the reactor has been in shut down condition. It is determined that the spray attacks the top position of fuel element, and to be calculated the force, of spray that produces 1 cm deflection on the single fuel element. Using that four (4) fuel elements is calculated because in the real condition 4 fuel elements will undergo deflection of 43.8 kg is obtained that producing 1 cm deflection and the force of 1228 kg that causes failure on the bottom of fuel element as shear force is also obtained. Whatever the force, high or low, the damage of fuel element occurred at the bottom part or at the position of grid plate. Therefore there is no damage on the fuel part (uranium meat) and the releasing of radioactive material from fuel plate is not happened

  13. In-Pile Qualification of the Fast-Neutron-Detection-System

    Science.gov (United States)

    Fourmentel, D.; Villard, J.-F.; Destouches, C.; Geslot, B.; Vermeeren, L.; Schyns, M.

    2018-01-01

    In order to improve measurement techniques for neutron flux assessment, a unique system for online measurement of fast neutron flux has been developed and recently qualified in-pile by the French Alternative Energies and Atomic Energy Commission (CEA) in cooperation with the Belgian Nuclear Research Centre (SCK•ECEN). The Fast-Neutron-Detection-System (FNDS) has been designed to monitor accurately high-energy neutrons flux (E > 1 MeV) in typical Material Testing Reactor conditions, where overall neutron flux level can be as high as 1015 n.cm-2.s-1 and is generally dominated by thermal neutrons. Moreover, the neutron flux is coupled with a high gamma flux of typically a few 1015 γ.cm-2.s-1, which can be highly disturbing for the online measurement of neutron fluxes. The patented FNDS system is based on two detectors, including a miniature fission chamber with a special fissile material presenting an energy threshold near 1 MeV, which can be 242Pu for MTR conditions. Fission chambers are operated in Campbelling mode for an efficient gamma rejection. FNDS also includes a specific software that processes measurements to compensate online the fissile material depletion and to adjust the sensitivity of the detectors, in order to produce a precise evaluation of both thermal and fast neutron flux even after long term irradiation. FNDS has been validated through a two-step experimental program. A first set of tests was performed at BR2 reactor operated by SCK•CEN in Belgium. Then a second test was recently completed at ISIS reactor operated by CEA in France. FNDS proved its ability to measure online the fast neutron flux with an overall accuracy better than 5%.

  14. RIA for indol alkaloids

    International Nuclear Information System (INIS)

    Arens, H.

    1979-01-01

    The technique of RIAs for indol alkaloids (ajmaline, ergotamine, ergocristine, ergometrine, and lysergic acid) is described, and applications for this RIA and the RIA for raubasine and serpentine are mentioned. The indol alkaloide RIAs are shown to be suitable both for alkaloid distribution measurements in Catharantus and Rauwolfia plants and C. purpurea sclerotia as well as for the selection of high-efficiency strains and the optimisation of cultures of plant tissues and saprophytic fungi. (orig./MG) [de

  15. Variação temporal no desempenho em testes de memória em pacientes com doença vascular cerebral Temporal variation in memory tests performance in cerebral vascular disease patients

    Directory of Open Access Journals (Sweden)

    Tania Fernandes Campos

    2007-01-01

    Full Text Available Buscando adequar a avaliação neuropsicológica à organização temporal do organismo humano, avaliou-se o desempenho em testes de memória em 12 pacientes pós Doença Vascular Cerebral e 12 indivíduos controle, de ambos os sexos, com idade de 45 a 65 anos. Foram aplicados dois testes de memória com estímulos visuais (figuras e dois com estímulos verbais (palavras, em 3 dias consecutivos por semana, às 08:00, 10:00 e 12:00 h na primeira semana e às 14:00 e 16:00 h na seguinte. Os pacientes apresentaram menor número de acertos do que os indivíduos controle em todos os testes aplicados (pThis study intended to investigate the performance in memory tests in order to adequate the neuropsychological evaluation to the temporal order of the human organism. Twelve cerebral vascular accident patients and 12 controls, of both sexes and 45-65 years old were studied. Two memory tests with visual stimuli (pictures and two with verbal stimuli (words were applied three times a day (08:00, 10:00 and 12:00 h during the first week and twice a day (14:00 and 16:00 h in the second week, during three consecutive days in two consecutive weeks. The patients showed lower scores than control subjects in all applied tests (p<0,05. The greater test sensitivity was at 14:00 h for the free recall test and at 16:00 h for recognition tests. According to these results, it is concluded that neuropsychological evaluations should be conducted preferably in the afternoon, as well for the first evaluation as for the re-evaluations.

  16. Behavior of pre-irradiated fuel under a simulated RIA condition. Results of NSRR Test JM-5

    International Nuclear Information System (INIS)

    Fuketa, Toyoshi; Sasajima, Hideo; Mori, Yukihide; Tanzawa, Sadamitsu; Ishijima, Kiyomi; Kobayashi, Shinsho; Kamata, Hiroshi; Homma, Kozo; Sakai, Haruyuki.

    1995-11-01

    This report presents results from the power burst experiment with pre-irradiated fuel rod, Test JM-5, conducted in the Nuclear Safety Research Reactor (NSRR). The data concerning test method, pre-irradiation, pre-pulse fuel examination, pulse irradiation, transient records and post-pulse fuel examination are described, and interpretations and discussions of the results are presented. Preceding to the pulse irradiation in the NSRR, test fuel rod was irradiated in the Japan Materials Testing Reactor (JMTR) up to a fuel burnup of 25.7 MWd/kgU with average linear heat rate of 33.4 kW/m. The fuel rod was subjected to the pulse irradiation resulting in a desposited energy of 223 ± 7 cal/g·fuel (0.93 ± 0.03 kJ/g·fuel) and a peak fuel enthalpy of 167 ± 5 cal/g·fuel (0.70 ± 0.02 kJ/g·fuel) under stagnant water cooling condition at atmospheric pressure and ambient temperature. Test fuel rod behavior was assessed from pre- and post-pulse fuel examinations and transient records during the pulse. The Test JM-5 resulted in cladding failure. More than twenty small cracks were found in the post-test cladding, and most of the defects located in pre-existing locally hydrided region. The result indicates an occurrence of fuel failure by PCMI (pellet/cladding mechanical interaction) in combination with decreased integrity of hydrided cladding. (author)

  17. New In-pile Instrumentation to Support Fuel Cycle Research and Development

    Energy Technology Data Exchange (ETDEWEB)

    J. Rempe; H. MacLean; R. Schley; D. Hurley; J. Daw; S. Taylor; J. Smith; J. Svoboda; D. Kotter; D. Knudson; M. Guers; S. C. Wilkins

    2011-01-01

    New and enhanced nuclear fuels are a key enabler for new and improved reactor technologies. For example, the goals of the next generation nuclear plant (NGNP) will not be met without irradiations successfully demonstrating the safety and reliability of new fuels. Likewise, fuel reliability has become paramount in ensuring the competitiveness of nuclear power plants. Recently, the Office of Nuclear Energy in the Department of Energy (DOE-NE) launched a new direction in fuel research and development that emphasizes an approach relying on first principle models to develop optimized fuel designs that offer significant improvements over current fuels. To facilitate this approach, high fidelity, real-time, data are essential for characterizing the performance of new fuels during irradiation testing. A three-year strategic research program is proposed for developing the required test vehicles with sensors of unprecedented accuracy and resolution for obtaining the data needed to characterize three-dimensional changes in fuel microstructure during irradiation testing. When implemented, this strategy will yield test capsule designs that are instrumented with new sensor technologies for the Advanced Test Reactor (ATR) and other irradiation locations for the Fuel Cycle Research and Development (FC R&D) program. Prior laboratory testing, and as needed, irradiation testing, of these sensors will have been completed to give sufficient confidence that the irradiation tests will yield the required data. Obtaining these sensors must draw upon the expertise of a wide-range of organizations not currently supporting nuclear fuels research. This document defines this strategic program and provides the necessary background information related to fuel irradiation testing, desired parameters for detection, and an overview of currently available in-pile instrumentation. In addition, candidate sensor technologies are identified in this document, and a list of proposed criteria for ranking

  18. New trends in pile safety instrumentation; Les tendances nouvelles dans l'instrumentation de securite des piles

    Energy Technology Data Exchange (ETDEWEB)

    Furet, J.

    1961-04-19

    This report addresses the protection of nuclear piles against damages due to operation incidents. The author discusses the current trends in the philosophy of safety of atomic power piles, identifies the parameters which define safety systems, presents tests to be performed on safety chains, comments the relationship between safety and the decrease of the number of pile inadvertent shutdowns, discusses the issues of instrument failures and chain multiplicity, comments the possible improvement of the operation of elements which build up safety chains (design simplification, development of semiconductors, replacement of electromechanical relays by static relays), the role of safety logical computers and the development of automatics in pile safety, presents automatic control as a safety factor (example of automatic start-up), and finally comments the use of fuses.

  19. Estudo das propriedades psicométricas do Teste de Memória de Reconhecimento – TEM-R

    Directory of Open Access Journals (Sweden)

    Fabián Javier Marín Rueda

    2012-06-01

    Full Text Available The purpose was to verify the psychometric qualities of the Memory Test of Recognition (TEM-R. In a first moment an initial version of the TEM-R was applied at 137 college students. It was found that from the 64 initial items, 15 did not show any frequency response. Based on this it was proceeded a reconfiguration of the instrument, fixing the number of 49 items. It was accomplished a new enforcement where participated 531 college students. The results of the internal structure showed an adequacy to the Rasch model, a absence of bias in the items through the analysis of differential items functioning, and an appropriate factor structure. We observed satisfactory reability indexes. Thus, the TEM-R presented adequate psychometric properties for use in the Brazilian reality.   Keywords: memory; psychological tests; psychometry; validity; reability.

  20. Seismic analysis for shroud facility in-pile tube and saturated temperature capsules

    International Nuclear Information System (INIS)

    Iimura, Koichi; Yamaura, Takayuki; Ogawa, Mitsuhiro

    2009-07-01

    At Oarai Research and Development Center, Japan Atomic Energy Agency (JAEA), the plan of repairing and refurbishing Japan Materials Testing Reactor (JMTR) has progressed in order to restart JMTR operation in the fiscal 2011. As a part of effective use of JMTR, the neutron irradiation tests of LWR fuels and materials has been planned in order to study their soundness. By using Oarai Shroud Facility (OSF-1) and Fuel Irradiation Facility with the He-3 gas control system for power lamping test using Boiling Water Capsules (BOCA Irradiation Facility), the irradiation tests with power ramping will be carried out to study the soundness of fuel under LWR Transient condition. OSF-1 is the irradiation facility of shroud type that can insert and eject the capsule under reactor operation, and is composed of 'In-pile Tube', 'Cooling system' and 'Capsule exchange system'. BOCA Irradiation Facility is the facility which simulates irradiation environment of LWR, and is composed of 'Boiling water Capsule', 'Capsule control system' and 'Power control system by He-3'. By using Saturated temperature Capsules and the water environment control system, the material irradiation tests under the water chemistry condition of LWR will be carried out to clarify the mechanism of IASCC. In JMTR, these facilities are in service at the present. However, the detailed design for renewal or remodeling was carried out based on the new design condition in order to be correspondent to the irradiation test plan after restart JMTR operation. In this seismic analysis of the detailed design, each equipment classification and operating state were arranged with 'Japanese technical standards of the structure on nuclear facility for test research' and 'Technical guidelines for seismic design of nuclear power plants on current, and then, stress calculation and evaluation were carried out by FEM piping analysis code 'SAP' and structure analysis code 'ABAQUS'. About the stress of the seismic force, it was proven

  1. In-Pile Section(IPS) Inner Assembly Manufacturing Report

    International Nuclear Information System (INIS)

    Lee, Jong Min; Shim, Bong Sik; Lee, Chung Yong

    2009-12-01

    The objective of this report is to present the manufacturing, assembling and testing process of IPS Inner Assembly used in Fuel Test Loop(FTL) pre-operation test. The majority of the manufactured components are test fuels, inner assembly structures and subsidiary tools that is needed during the assembly process. In addition, Mock-up test for the welding and brazing is included at this stage. Lower structure, such as test fuels, fuel carrier legs are assembled and following structures, such as fuel carrier stem in the middle structure, top flange in the top structure are assembled together each other. To Verify the Reactor Coolant Pressure Boundary(RCPB) function in IPS Inner Assembly helium leak test and hydraulic test is performed with its acceptance criteria. According to the ASME III code Authorized Nuclear Inspector(ANI) is required during the hydraulic test. As-built measurement and insulation resistance test are performed to the structures and instrumentations after the test process. All requirements are satisfied and the IPS Inner Assembly was loaded in HANARO IR-1 hole in September 25, 2009

  2. In-pile thermocycling testing and post-test analysis of beryllium divertor mockups

    Energy Technology Data Exchange (ETDEWEB)

    Giniatulin, R.; Mazul, I. [Efremov Inst., St. Petersburg (Russian Federation); Melder, R.; Pokrovsky, A.; Sandakov, V.; Shiuchkin, A.

    1998-01-01

    The main damaging factors which impact the ITER divertor components are neutron irradiation, cyclic surface heat loads and hydrogen environment. One of the important questions in divertor mockups development is the reliability of beryllium/copper joints and the beryllium resistance under neutron irradiation and thermal cycling. This work presents the experiment, where neutron irradiation and thermocyclic heat loads were applied simultaneously for two beryllium/copper divertor mockups in a nuclear reactor channel to simulate divertor operational conditions. Two mockups with different beryllium grades were mounted facing each other with the tantalum heater placed between them. This device was installed in the active zone of the nuclear reactor SM-2 (Dimitrovgrad, Russia) and the tantalum block was heated by neutron irradiation up to a high temperature. The main part of the heat flux from the tantalum surface was transported to the beryllium surface through hydrogen, as a result the heat flux loaded two mockups simultaneously. The mockups were cooled by reactor water. The device was lowered to the active zone so as to obtain the heating regime and to provide cooling lifted. This experiment was performed under the following conditions: tantalum heater temperature - 1950degC; hydrogen environment -1000 Pa; surface heat flux density -3.2 MW/m{sup 2}; number of thermal cycles (lowering and lifting) -101; load time in each cycle - 200-5000 s; dwell time (no heat flux, no neutrons) - 300-2000 s; cooling water parameters: v - 1 m/s, Tin - 50degC, Pin - 5 MPa; neutron fluence -2.5 x 10{sup 20} cm{sup -2} ({approx}8 years of ITER divertor operation from the start up). The metallographic analysis was performed after experiment to investigate the beryllium and beryllium/copper joint structures, the results are presented in the paper. (author)

  3. Study on the technical parameters of two different systems of RIA performed with solid-phase antibody test tubes prepared with magnetic microparticle covalence conjagation or conventional physical absorption

    International Nuclear Information System (INIS)

    Chen Zhiqiang; Wang Chengmin; Tang Baojun

    2007-01-01

    Objective: To investigate a new method of preparation of solid-phase antibody with flurorescein isothioeynate (FITC)-anti FITC magnetic nanoparticles system (for FT 3 and TSH). Methods: FT 3 and TSH monoclonal antibody IgC was la- belied with FITC. Anti-FITC magnetic mieroparticles was prepared and conjugated with the FITC labelled antibody to form the solid - phase coated test tube for RIA. Solid-phase test tube prepared with the conventional physical absorption method was also used for RIA and the technical parameters of the two systems were compared. Results: For FT 3 , the sensitivity was 0.18pmol/L with the new method and 0.43pmol/L with the conventional method. Other parameters were; intra-CV, 8.96% vs 16.26%; inter-CV, 15.25% vs 18.83%, correlation with PR method r=0.9825 vs r=0.9102. For TSH, sensitivity was 0.061 μIU/ml vs 0.04 μ IU/ml, intra- CV, 7.6% vs 6.92%, inter-CV, 8.55% vs 14.23%, correlation between the new and conventional method, r=0. 9987. TSH RIA was especially rapid with the new technic: 79 min vs 190 min. Conclusion: For FT 3 and TSH RIA, the new method takes much less time with increased homogeniety. (authors)

  4. Teste de hemaglutinação na sorologia da malária humana empregando hemácias parasitadas pelo Plasmodium berghei

    Directory of Open Access Journals (Sweden)

    Maria Carmen Arroyo Sanchez-Ruiz

    1985-06-01

    Full Text Available Foi padronizado um teste de hemaglutinação para a sorologia da malária humana, com reagente constituído de suspensão de hemácias de camundongos infectadas pelo Plasmodium berghei e preservadas por fixação aldeídica. Em pacientes com parasitemia por P. falciparum ou P. vivax obteve-se uma sensibilidade de 98,9% nos 88 casos estudados, o teste apresentando títulos entre 40 e 640. Para o grupo de 476 soros de indivíduos não-maláricos, obteve-se uma especificidade de 96,0%. O teste apresentou elevada reprodutibilidade, mesmo para diferentes lotes de antígenos. Nos 200 soros, obtidos ao acaso, de indivíduos de área endêmica, o teste apresentou positividade de 48,5%, contra 88,0% do teste de imunofluorescência-IgG. A baixa positividade pode ser devida a que o teste de hemaglutinação detecta anticorpos IgM. Após tratamento com 2-mercaptoetanol, todos os soros de pacientes com parasitemia tornaram-se não reagentes. Em relação ao teste de imunofluorescência-IgG, o teste de hemaglutinação apresentou índice de co-positívidade de 0,989 para os soros de maláricos com parasitemia. Para os soros de não-maláricos o teste de hemaglutinação apresentou índice de co-negatividade de 0,969. Por outro lado, no grupo de soros de área endêmica, o índice de co-positividade foi de 0,528 e o de co-negatividade, de 0,833.A hemagglutination test is described for human malaria serodiagnosis with aldehyde-fixed Plasmodium berghei infected mouse erythrocytes. In patients with a P. falciparum or P. vivax patent parasitemia positive results were seen in 98.9% ofthe 88 cases tested. Titres rangedfrom 40 to 640. A 96.0% specificity wasfoundfor 476 non-malarialpatients. A close reproducibility was observed forthe test, even for dijferent reagent batches. The test was positive in 48.5% of 200 residents in malaria endemic areas, taken at random. These subjects showed 88.0% positivity of the IgG-immunofluorescence test. This lower positivity for

  5. Studies of Nuclear Fuel Performance Using On-site Gamma-ray Spectroscopy and In-pile Measurements

    International Nuclear Information System (INIS)

    Matsson, Ingvar

    2006-01-01

    Presently there is a clear trend of increasing demands on in-pile performance of nuclear fuel. Higher target burnups, part length rods and various fuel additives are some examples of this trend. Together with an increasing demand from the public for even safer nuclear power utilisation, this implies an increased focus on various experimental, preferably non-destructive, methods to characterise the fuel. This thesis focuses on the development and experimental evaluation of such methods. In its first part, the thesis presents a method based on gamma-ray spectroscopy with germanium detectors that have been used at various power reactors in Europe. The aim with these measurements is to provide information about the thermal power distribution within fuel assemblies in order to validate core physics production codes. The early closure of the Barsebaeck 1 BWR offered a unique opportunity to perform such validations before complete depletion of burnable absorbers in Gd-rods had taken place. To facilitate the measurements, a completely submersible measuring system, LOKET, was developed allowing for convenient in-pool measurements to be performed. In its second part, the thesis describes methods that utilise in-pile measurements. These methods have been used in the Halden test-reactor for determination of fission gas release, pellet-cladding interaction studies and fuel development studies. Apart from the power measurements, the LOKET device has been used for fission gas release (FGR) measurements on single fuel rods. The significant reduction in fission gas release in the modern fuel designs, in comparison with older designs, has been demonstrated in a series of experiments. A FGR database covering a wide range of burnup, power histories and fuel designs has been compiled and used for fuel performance analysis. The fission gas release has been measured on fuel rods with average burnups well above 60 MWd/kgU. The comparison between core physics calculations (PHOENIX-4/POLCA

  6. Post-Irradiation Examination and In-Pile Measurement Techniques for Water Reactor Fuels

    International Nuclear Information System (INIS)

    2009-12-01

    in the 1960s when the construction of NPPs was being started. Evidently it can be assumed that infrastructure with basic unique equipments is old enough, both morally and physically, and needs to be up-graded or replaced. Thus, a sharp increase of the hydrocarbon fuel cost, green-house effect, necessity to construct more safe and efficient NPPs, justification of the lifetime prolongation of the existing NPPs, moral and physical ageing of the hot labs and research reactors equipment lead to the strong necessity to develop more perfect and more precise methods and equipment to examine irradiated components of nuclear reactors, first of all the most expensive one - nuclear fuel. Now the national hot laboratories and material testing reactors usually act as individual independent research establishments without any common and coordinated technical and business strategy towards the future needs and challenges. Even if there are not many joint programs for the development of nuclear power engineering in different countries, the method base and accumulated experience of the in- and post-reactor experiments should be widely shared so as to decrease the cost of this base in each country and to enforce its development. Thus, both problems and results of the application of new techniques to examine nuclear reactor components, as well as the conditions of separate labs should be discussed at the international level. The IAEA technical meetings are one of the most convenient means of arranging such discussion on the problems of the hot labs and research reactors development and application of new original techniques for examination of reactor materials properties. This publication represents a summary and proceedings of the two technical meetings (TMs) organized by IAEA on the subjects of Hot Cell Post-Irradiation Examination (PIE) Techniques and Pool Side Inspection of Water Reactor Fuel Assemblies and Fuel Rod Instrumentation and In-Pile Measurement Techniques. The first TM was

  7. Evaluation of Candidate In-Pile Thermal Conductivity Techniques

    International Nuclear Information System (INIS)

    Fox, B.; Ban, H.; Daw, J.; Condie, K.; Knudson, D.; Rempe, J.

    2009-01-01

    Thermophysical properties of materials must be known for proper design, test, and application of new fuels and structural properties in nuclear reactors. In the case of nuclear fuels during irradiation, the physical structure and chemical composition change as a function of time and position within the rod. Typically, thermal conductivity changes, as well as other thermophysical properties being evaluated during irradiation in a materials and test reactor, are measured out-of-pile in 'hot-cells'. Repeatedly removing samples from a test reactor to make out-of-pile measurements is expensive, has the potential to disturb phenomena of interest, and only provide understanding of the sample's end state at the time each measurement is made. There are also limited thermophysical property data for advanced fuels. Such data are needed for the development of next generation reactors and advanced fuels for existing nuclear plants. Having the capacity to effectively and quickly characterize fuels and material properties during irradiation has the potential to improve the fidelity of nuclear fuel data and reduce irradiation testing costs

  8. Estudo de correlação entre provas funcionais respiratórias e o teste de caminhada de seis minutos em pacientes portadores de doença pulmonar obstrutiva crônica

    Directory of Open Access Journals (Sweden)

    RODRIGUES SÉRGIO LEITE

    2002-01-01

    Full Text Available Introdução: A espirometria e a gasometria são largamente utilizadas na estimativa da limitação ventilatória e do prognóstico de pacientes portadores de doença pulmonar obstrutiva crônica. Entretanto, testes físicos funcionais, como o teste de caminhada de seis minutos (Tc6, têm surgido como complemento na avaliação dinâmica de portadores de doença pulmonar obstrutiva crônica. Objetivo: Determinar as correlações entre as provas funcionais respiratórias e o teste de caminhada de seis minutos em portadores de DPOC. Pacientes e métodos: 45 pacientes foram submetidos à coleta de história clínica e a exame físico completo realizado pela equipe médica do Serviço de Pneumologia do Hospital Universitário de Brasília. Em seguida, foi realizada a avaliação das variáveis espirométricas, gasométricas, das pressões respiratórias e o teste de caminhada de seis minutos (Tc6. Resultados: Observaram-se correlações positivas estatisticamente significativas (p < 0,05 das variáveis VEF1, PaO2, SpO2 e Pe máx em relação ao teste de caminhada de seis minutos. Conclusões: O teste de caminhada de seis minutos correlacionou-se de forma significativa (p < 0,05 e positiva e pode ser utilizado como instrumento alternativo na avaliação funcional do paciente portador de DPOC.

  9. In-pile vapor pressure measurements on UO2 and (U,Pu)O2

    International Nuclear Information System (INIS)

    Breitung, W.; Reil, K.O.

    1985-08-01

    The Effective-Equation-of-State (EEOS) experiments investigated the saturation vapor pressures of ultra pure UO 2 , reactor grade UO 2 , and reactor grade (Usub(.77)Pusub(.23))O2 using newly developed in-pile heating techniques. For enthalpies between 2150 and 3700 kJ/kg (about 4700 to 8500 K) vapor pressures from 1.3 to 54 MPa were measured. The p-h curves of all three fuel types were identical within the experimental uncertainties. An assessment of all published p-h measurements showed that the p-h saturation curve of UO 2 appears now well established by the EEOS and the CEA in-pile data. Using an estimate for the heat capacity of liquid UO 2 , the in-pile results were also compared to earlier p-T measurements. The assessments lead to proposal of two equations. Equation I, which includes a factor-of-2 uncertainty band, covers all p-T equilibrium evaporation measurements. Equation I yields 3817 K for the normal boiling point, 415.4 kJ/mol for the corresponding heat of vaporization, and 1.90 MPa for the vapor pressure at 5000 K. Equations I and II, which represent a parametric form of the p-h curve (T=parameter), also give a good description of the EEOS and CEA in-pile data. Thus the proposed equations allow a consistent representation of both p-T and p-h measurements, they are sufficiently precise for CDA analyses and cover the whole range of interest (3120-8500 K, 1400-3700 kJ/kg). (orig./HP) [de

  10. Aluminum cladding oxidation of prefilmed in-pile fueled experiments

    Energy Technology Data Exchange (ETDEWEB)

    Marcum, W.R., E-mail: marcumw@engr.orst.edu [Oregon State University, School of Nuclear Science and Engineering, 116 Radiation Center, Corvallis, OR 97331 (United States); Wachs, D.M.; Robinson, A.B.; Lillo, M.A. [Idaho National Laboratory, Nuclear Fuels & Materials Department, 2525 Fremont Ave., Idaho Falls, ID 83415 (United States)

    2016-04-01

    A series of fueled irradiation experiments were recently completed within the Advanced Test Reactor Full size plate In center flux trap Position (AFIP) and Gas Test Loop (GTL) campaigns. The conduct of the AFIP experiments supports ongoing efforts within the global threat reduction initiative (GTRI) to qualify a new ultra-high loading density low enriched uranium-molybdenum fuel. This study details the characterization of oxide growth on the fueled AFIP experiments and cross-correlates the empirically measured oxide thickness values to existing oxide growth correlations and convective heat transfer correlations that have traditionally been utilized for such an application. This study adds new and valuable empirical data to the scientific community with respect to oxide growth measurements of highly irradiated experiments, of which there is presently very limited data. Additionally, the predicted oxide thickness values are reconstructed to produce an oxide thickness distribution across the length of each fueled experiment (a new application and presentation of information that has not previously been obtainable in open literature); the predicted distributions are compared against experimental data and in general agree well with the exception of select outliers. - Highlights: • New experimental data is presented on oxide layer thickness of irradiated aluminum fuel. • Five oxide growth correlations and four convective heat transfer correlations are used to compute the oxide layer thickness. • The oxide layer thickness distribution is predicted via correlation for each respective experiment. • The measured experiment and predicted distributions correlate well, with few outliers.

  11. Solid-phase enzyme immunoassay or radioimmunoassay for the detection of immune complexes based on their recognition by conglutinin: conglutinin-binding test. A comparative study with /sup 125/I-labelled Clq binding and Raji-cell RIA tests

    Energy Technology Data Exchange (ETDEWEB)

    Casali, P; Bossus, A; Carpentier, N A; Lambert, P H [Hopital Cantonal Geneve (Switzerland)

    1977-01-01

    Bovine conglutinin was used in a solid-phase assay for the detection of immune complexes. In a first step, the tested serum sample was incubated in polypropylene tubes coated with conglutinin to allow C3-coated immune complexes to bind to solid-phase conglutinin. In a second step, the conglutinin-bound complexes were detected using an enzyme-conjugated or radiolabelled anti-immunoglobulin antibody. The conglutinin-binding (KgB) test did not suffer from the interference of DNA, heparin or endotoxins. Its limit of sensitivity for aggregated IgG was 3 ..mu..g/ml undiluted human serum. Immune complexes prepared in vitro using tetanus toxoid, or DNA, and corresponding antibodies in human sera could be detected at various antigen/antibody ratios and at antibody concentrations lower than 8 ..mu..g/ml. The KgB test allowed for the detection of immune complexes in sera from patients with systemic lupus erythematosus, rheumatoid arthritis, idiopathic vasculitis, leprosy and leukemia. These sera were also tested using the /sup 125/I-labelled Clq-binding activity (BA) test and the KgB test simultaneously, and a significant rank order correlation was observed. In patients with leukemia, a significant correlation was observed using three tests, KgB, /sup 125/I-labelled Clq BA and Raji-cell radioimmunoassay (RIA). Therefore, the KgB test appears as a simple and reproducible method, utilizing a very stable reagent, with a sensitivity and specificity comparable to the other tests studied and allowing for clinical application.

  12. Synergistic Smart Fuel For In-pile Nuclear Reactor Measurements

    Energy Technology Data Exchange (ETDEWEB)

    James A. Smith; Dale K. Kotter; Randall A. Ali; Steven L . Garrett

    2013-10-01

    In March 2011, an earthquake of magnitude 9.0 on the Richter scale struck Japan with its epicenter on the northeast coast, near the Tohoku region. In addition to the immense physical destruction and casualties across the country, several nuclear power plants (NPP) were affected. It was the Fukushima Daiichi NPP that experienced the most severe and irreversible damage. The earthquake brought the reactors at Fukushima to an automatic shutdown and because the power transmission lines were damaged, emergency diesel generators (EDGs) were activated to ensure that there was continued cooling of the reactors and spent fuel pools. The situation was being successfully managed until the tsunami hit about forty-five minutes later with a maximum wave height of approximately 15 m. The influx of water submerged the EDGs, the electrical switchgear, and dc batteries, resulting in the total loss of power to the reactors.2 At this point, the situation became critical. There was a loss of the sensors and instrumentation within the reactor that could have provided valuable information to guide the operators to make informed decisions and avoid the unfortunate events that followed. In the light of these events, we have developed and tested a potential self-powered thermoacoustic system, which will have the ability to serve as a temperature sensor and can transmit data independently of electronic networks. Such a device is synergistic with the harsh environment of the nuclear reactor as it utilizes the heat from the nuclear fuel to provide the input power.

  13. Development of remote welding techniques for in-pile IASCC capsules and evaluation of material integrity on capsules for long irradiation period

    Science.gov (United States)

    Shibata, A.; Nakano, J.; Ohmi, M.; Kawamata, K.; Nakagawa, T.; Tsukada, T.

    2012-03-01

    To simulate irradiation assisted stress corrosion cracking (IASCC) behavior by in-pile experiments, it is necessary to irradiate specimens up to a neutron fluence that is higher than the IASCC threshold fluence. Pre-irradiated specimens must be relocated from pre-irradiation capsules to in-pile capsules. Hence, a remote welding machine has been developed. And the integrity of capsule housing for a long term irradiation was evaluated by tensile tests in air and slow strain rate tests in water. Two type specimens were prepared. Specimens were obtained from the outer tubes of capsule irradiated to 1.0-3.9 × 1026 n/m2 (E > 1 MeV). And specimens were irradiated in a leaky capsule to 0.03-1.0 × 1026 n/m2. Elongation more than 15% in tensile test at 423 K was confirmed and no IGSCC fraction was shown in SSRT at 423 K which was estimated as temperature at the outer tubes of the capsule under irradiation.

  14. Development of remote welding techniques for in-pile IASCC capsules and evaluation of material integrity on capsules for long irradiation period

    International Nuclear Information System (INIS)

    Shibata, A.; Nakano, J.; Ohmi, M.; Kawamata, K.; Nakagawa, T.; Tsukada, T.

    2012-01-01

    To simulate irradiation assisted stress corrosion cracking (IASCC) behavior by in-pile experiments, it is necessary to irradiate specimens up to a neutron fluence that is higher than the IASCC threshold fluence. Pre-irradiated specimens must be relocated from pre-irradiation capsules to in-pile capsules. Hence, a remote welding machine has been developed. And the integrity of capsule housing for a long term irradiation was evaluated by tensile tests in air and slow strain rate tests in water. Two type specimens were prepared. Specimens were obtained from the outer tubes of capsule irradiated to 1.0–3.9 × 10 26 n/m 2 (E > 1 MeV). And specimens were irradiated in a leaky capsule to 0.03–1.0 × 10 26 n/m 2 . Elongation more than 15% in tensile test at 423 K was confirmed and no IGSCC fraction was shown in SSRT at 423 K which was estimated as temperature at the outer tubes of the capsule under irradiation.

  15. Clarification on RIA Novosti Story

    International Nuclear Information System (INIS)

    2014-01-01

    Full text: ''On 21 May, RIA Novosti news agency published a story headlined IAEA Says Impossible for Ukraine to Switch to US Nuclear Fuel, based on apparent remarks by an Agency official during a News Conference in Moscow. There was some confusion about the official's remarks, which were made in Russian. The resulting RIA Novosti story does not accurately reflect his words, nor the position of the IAEA, which is as follows: The choice of supplier for nuclear fuel is the prerogative of the nuclear operator. Such an approach is not unique to Ukraine. Any change in the supply of fuel to a nuclear power plant requires careful safety assessment and testing. Any such modifications should be approved by the national regulatory body in accordance with national laws, applicable safety regulations and industry best practices.''. (author)

  16. LOCA and RIA studies at JAERI

    International Nuclear Information System (INIS)

    Sugiyama, Tomoyuki; Nagase, Fumihisa; Nakamura, Jinichi; Fuketa, Toyoshi

    2004-01-01

    To provide a data base for the regulatory guide of light water reactors, behavior of reactor fuels during off-normal and postulated accident conditions such as loss-of-coolant accident (LOCA) and reactivity-initiated accident (RIA) is being studied at the Japan Atomic Energy Research Institute (JAERI). The LOCA program consists of integral thermal shock tests and other separate tests for oxidation rate and mechanical property of fuel claddings. Prior to the tests on irradiated claddings, the tests have been conducted on non-irradiated claddings to examine separate effects of corrosion and hydrogen absorption during reactor operation. The tests on irradiated claddings have recently been started and results have been obtained. As for an RIA study, a series of experiments with high burnup fuel rods is being performed by using pulse irradiation capability of the NSRR. This paper presents recent results obtained from the LOCA and RIA studies at JAERI. (Author)

  17. Theoretical interpretation of SCARABEE single pin in-pile boiling experiments

    International Nuclear Information System (INIS)

    Struwe, D.; Bottoni, M.; Fries, W.; Elbel, H.; Angerer, G.

    1977-01-01

    In the framework of LMFBR safety analysis a theoretical interpretation of some of the most representative of the single pin experiments of the in-pile SCARABEE project has been performed from both viewpoints of thermohydraulic and fuel behaviour using the computer codes CAPRI-2 and SATURN-1. The analysis is aimed at investigating the pin behavior from the preirradiation history, through the observed sequence of events following a coolant mass flow reduction from boiling inception up to pin breakdown. A comparison of theoretical results with experimentally recorded data has allowed a deeper insight into the peculiar features of the experiments and enabled a valuable code verification. (Auth.)

  18. In-pile intragranular densification of oxide fuels (AWBA Development Program)

    International Nuclear Information System (INIS)

    Dollins, C.C.; Nichols, F.A.

    1977-10-01

    This report proposes a model to describe in-pile densification of oxide fuels, by both vacancy boil-off due to thermal excitation and vacancy knockout by the passage of fission fragments through the pores. The model includes the migration rates of both vacancies and interstitials to pores and the production of vacancy-rich damage cascades by fission fragments. It has been coupled with a previously reported swelling and gas release model so that it can predict the total dimensional changes of the fuel as well as predicting intragranular densification for both ThO 2 and UO 2 fuels for advanced water breeder reactor applications development effort

  19. Analytical out-of-pile and in-pile experiments on gadolinia bearing fuels

    International Nuclear Information System (INIS)

    Bruet, M.; Francois, B.; Do, Q.; Bergeron, J.; Trotabas, M.

    1986-06-01

    New fuel management schemes in PWRs can be achieved through the use of burnable poisons like gadolinia bearing fuel rods. However, the introduction of such a design has required a qualification program, which has been performed in collaboration between CEA, FRAGEMA and/or FRAMATOME by specialized teams in CEA facilities. The main scoops of this program concern: the fabrication process; the out of pile physical properties determination: the in pile thermomechanical behaviour and fission product release; the neutronic studies in view to validate the Computed Gd efficiency and the LBP depletion calculation schemes and to analyse and assess various schemes of core calculations

  20. In pile measurement of creep rate of stainless steel cladding tubes for fast reactor pins

    International Nuclear Information System (INIS)

    Calza Bini, A.; Cosoli, G.; Filacchioni, G.; Lanchi, M.; Nobili, A.; Pesce, E.; Rocca, U.V.; Rotoloni, P.L.

    1975-01-01

    Results are reported of a direct in pile measurement of creep on a cladding sample of 10cm length, under tensile stress of 22.82kg/mm 2 at a temperature of 550 0 during about 500 hours, up to an integrated flux of 2.6.10 20 n/cm 2 . Two identical samples were irradiated in the same temperature and flux conditions to be submitted to out of pile creep measurements together with other unirradiated samples. The aim of this first experiment was mainly to set up the device and to evaluate the kind and the quality of the available data

  1. Safety analysis report for packaging: the ORNL in-pile capsule shipping cask

    International Nuclear Information System (INIS)

    Evans, J.H.; Chipley, K.K.; Haynie, C.B.; Crowley, W.K.; Just, R.A.

    1977-11-01

    The ORNL in-pile capsule shipping cask is used to transport irradiated experimental capsules and spent fuel elements. The cask was analytically evaluated to determine its compliance with the applicable regulations governing containers in which radioactive materials are transported. Computational procedures were used to determine the structural integrity and thermal behavior of the cask relative to the general standards for normal conditions of transport and the standards for the hypothetical accident conditions. The results of the evaluation show that the cask is in compliance with the applicable regulations

  2. In-pile experimental device for Sirene thermionic converters; Dispositif d'experimentation en pile des convertisseurs thermoioniques sirene

    Energy Technology Data Exchange (ETDEWEB)

    Bliaux, J; Durand, J; Lazare-Chopard, G [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

    1969-07-01

    The irradiation device described here, was built for in pile life tests of 100 We SIRENE converters. The nuclear converter is located in a sealed vacuum chamber, which is plugged at the lower end of a coaxial tubing acting as electrical leads. The output power is available on a variable resistive load on the bank of the reactor pool. Thermal, electrical and neutronic parameters of the converter are recorded. Since 1967, two permanent devices allowed five experiments in the swimming pool TRITON (CEN-FAR) and the results, obtained till now, are presented. (authors) [French] Le dispositif d'irradiation SIRENE decrit ici a ete concu en vue d'une etude statistique de performances de convertisseurs thermoioniques nucleaires de puissance unitaire 100 We. Le dispositif doit assurer la bonne marche du convertisseur en pile, permettre le changement de la position verticale du convertisseur dans le coeur, sortir du coeur la puissance electrique convertie sans degradation notable et enregistrer les differents parametres thermiques, electriques et neutroniques du convertisseur. Depuis 1967, deux dispositifs fonctionnent en permanence et ont permis de faire cinq experiences dans le reacteur piscine TRITON du CEN-FAR. Les resultats obtenus jusqu'a present, sont presentes. (auteurs)

  3. Results of postirradiation examination of the in-pile blockage experiments MOL-7C/4 and MOL-7C/5

    International Nuclear Information System (INIS)

    Weimar, P.; Schleisiek, K.

    1991-01-01

    The Mol-7C in-pile local blockage experiments are performed in the BR-2 reactor at Mol, Belgium as a joint project of Kernforchungszentrum Karlsruhe (KfK) and Studiecentrum voor Kernenergie/Centre d'Etude de l'Energie Nuclearire-Mol. The main objective is to investigate the consequences of local cooling disturbances in liquid-metal-cooled reactor (LMR) fuel subassemblies. In the tests Mol-7C/4 and MOL-7C/5, fuel pins from KNK II are used with a burnup of 5 and 1.7%, respectively. An active central porous blockage is used to simulate the cooling disturbance. During irradiation, the blockage causes significant local damage, including melting of cladding and fuel. Extensive postirradiation examinations (PIE) are performed to investigate the extent of damage. In this paper a description and interpretation of results of the destructive PIE performed at the Hot Cells Laboratory at KfK is given, along with some conclusions related to LMR safety

  4. Research on in-pile release of fission products from coated particle fuels

    International Nuclear Information System (INIS)

    Fukuda, K.; Iwamoto, K.

    1985-01-01

    Coated particle fuels fabricated in accordance with VHTR (Very High Temperature gas-cooled Reactor) fuel design have been irradiated by both capsules and an in-pile gas loop (OGL-1), and data on the fission products release under irradiation were obtained for loose coated particles, fuel compacts and fuel rods in the temperature range between 800 deg. C and 1600 deg. C. For the fission gases, temperature- and time dependences of the fractional release(R/B) were measured. Relation between release and failure fraction of the coated particles was elucidated on the VHTR reference fuels. Also measured was tritium concentration in the helium coolant of OGL-1. In-pile release behavior of the metallic fission products was studied by measuring the activities of the fission products adsorbed in the graphite sleeves of the OGL-1 fuel rods and the graphite fuel container of the sweep gas capsules in the PIE. Investigation on palladium interaction with SiC coating layer was included. (author)

  5. Caigudes en població anciana comunitària: característiques epidemiològiques i utilitat clínica dels tests d'equilibri i marxa Timed up and go i Tinetti

    OpenAIRE

    Jiménez González, Mª Mercè

    2009-01-01

    Objectiu: 1-Conèixer la capacitat predictiva i la utilitat clínica per predir caigudes de dos tests d'equilibri i marxa "Timed up & go" i Tinetti en població geriàtrica ambulatòria ≥65 anys. 2-Conèixer la incidència,característiques epidemiològiques, i factors de risc que estan relacionats amb major risc de caigudes en el nostre medi.Estudi: Cohorts prospectiu multicèntric. Subjectes: 555 pacients majors de 65 anys visitats en els centres de salut del Maresme (Alella, Mataró, Premià i C...

  6. Desperdício de exames complementares na avaliação pré-operatória em cirurgias de catarata Waste of medical tests in preoperative evaluation for cataract surgery

    Directory of Open Access Journals (Sweden)

    Carlos Eduardo Leite Arieta

    2004-02-01

    Full Text Available O objetivo deste experimento clínico foi determinar a freqüência dos exames considerados dispensáveis numa rotina pré-operatória de facectomias e avaliar os gastos com eles. Se o paciente foi sorteado para testes-seletivos, solicitou-se que nenhum teste fosse executado, a menos que o paciente apresentasse um novo problema médico, ou piora de uma doença preexistente, a qual requeresse os testes independentemente da realização da cirurgia. Para pacientes sorteados para testes-rotineiros, foram solicitados: eletrocardiograma, dosagem de hemoglobina e glicemia de jejum. Foram calculados os gastos com exames considerados desnecessários. A amostra de 1.025 pacientes incluiu 513 sorteados para testes seletivos e 512 para testes rotineiros. A freqüência de eventos adversos intra-operatórios foi semelhante nos dois grupos (p = 0,923. O grupo de testes seletivos realizou de 60,7% menos exames que o de testes rotineiros. Os resultados sugerem que a requisição seletiva de exames pré-operatórios em facectomias, além de não prejudicar o paciente do ponto de vista de complicações clínicas intra-operatórias, possibilita expressiva economia de recursos quando comparada à atual rotina.The objective of this clinical trial was to determine the frequency of medical tests considered unnecessary in routine preoperative evaluation for cataract surgery. Unnecessary costs with these tests were also evaluated. For patients assigned to the selective testing group, it was requested that no preoperative testing be performed unless the patient presented a new or worsening medical problem warranting medical evaluation with testing. For patients assigned to the routine testing group, three tests were requested: a 12-lead electrocardiogram, complete blood count, and serum glucose level. The costs of tests considered unnecessary were calculated. The sample of 1,025 patients consisted of 512 assigned to the routine testing group and 513 to the selective

  7. Beryllium data base for in-pile mockup test on blanket of fusion reactor, (1)

    Energy Technology Data Exchange (ETDEWEB)

    Kawamura, Hiroshi; Ishitsuka, Etsuo (Japan Atomic Energy Research Inst., Oarai, Ibaraki (Japan). Oarai Research Establishment); Sakamoto, Naoki; Kato, Masakazu; Takatsu, Hideyuki.

    1992-11-01

    Beryllium has been used in the fusion blanket designs with ceramic breeder as a neutron multiplier to increase the net tritium breeding ratio (TBR). The properties of beryllium, that is physical properties, chemical properties, thermal properties, mechanical properties, nuclear properties, radiation effects, etc. are necessary for the fusion blanket design. However, the properties of beryllium have not been arranged for the fusion blanket design. Therefore, it is indispensable to check and examine the material data of beryllium reported previously. This paper is the first one of the series of papers on beryllium data base, which summarizes the reported material data of beryllium. (author).

  8. Design computations and safety report of a cell for in pile irradiation tests

    International Nuclear Information System (INIS)

    Verri, A.

    1987-01-01

    The criteria adopted in positioning the irradiation cell within the 1Mw TRIGA reactor of the ENEA Casaccia are reported. Maximum heat which can be released by the cell is then evaluated. The final configuration of the cell as a whole, the heating system for the sample under irradiation, the procedure used in the calculations, are also reported. The selection and the design of the safety system, including auxiliary equipments are discussed

  9. In-pile test of tritium release from tritium breeding materials (VOM-21H experiment)

    International Nuclear Information System (INIS)

    Kurasawa, Toshimasa; Takeshita, Hidefumi; Watanabe, Hitoshi; Yoshida, Hiroshi.

    1986-10-01

    Material development and blanket design of lithium-based ceramics such as lithium oxide, lithium aluminate, lithium silicate and lithium zirconate have been performed in Japan, United State of America and Europian Communities. Lithium oxide is a most attractive candidate for tritium breeding materials because of its high lithium density, high thermal conductivity and good tritium release performance. This work has been done to clarify the characteristics of tritium release and recovery from Li 2 O by means of in-situ tritium release measurement. The effects of temperature and sweep gas composition on the tritium release were investigated in this VOM-21H Experiment. Good measurement of tritium release was achieved but there were uncertainties in reproduciblity of data. The experimental results show that the role of surface adsorption/desorption makes a significant contribution to the tritium release and tritium inventory. Also, it is necessary to define the rate limiting process either diffusion or surface adsorption/desorption. (author)

  10. Current in-pile absorbed dose measurements at the Boris Kidric Institute of nuclear sciences - Vinca, Status report

    Energy Technology Data Exchange (ETDEWEB)

    Draganic, G I [Institute of nuclear sciences Boris Kidric, Vinca, Beograd (Yugoslavia)

    1966-11-15

    So far in-pile absorbed dose measurements have been limited only to experiments in the RA reactor at the Boris Kidric Institute of Nuclear Sciences at Vinca (6.5 D{sub 2}O moderated and 2% enriched uranium). The methods used for absorbed dose and neutron flux measurements were 1,2 discussed in some earlier reports at the IAEA meetings. The purpose of the present report is to illustrate the further development of methods of determining in-pile absorbed doses (author)

  11. In-pile study of the reaction between breeder fuel and sodium

    International Nuclear Information System (INIS)

    Hugot, J.P.

    1982-10-01

    Studies carried out until now show that the determinant parameter of fuel can failure evolution is the development of the reaction between mixed uranium and plutonium dioxide and sodium. The parameters of the reaction are presented from results of an out of pile study, as also results obtained from examination on pins failed in reactors. The best way to study in pile the development of the reaction was to irradiate at a constant power a fuel pin containing sodium. In the experiment, the pin was equipped with a central thermocouple. It shows, that the reaction is developing intergranularly, from cracks and interpellet spaces, in an internal fringe of the fuel before spreading to the periphery. An overheating of the pin is associated to the development of the reaction as also a modification of the fuel pin geometry and a reduction of the oxide [fr

  12. ACTIV, Sandwich Detector Activity from In-Pile Slowing-Down Spectra Experiment

    International Nuclear Information System (INIS)

    Bozzi, L. and others

    1978-01-01

    1 - Nature of physical problem solved: Calculates the activities of a sandwich detector, to be used for in-pile measurements in slowing-down spectra below a few keV. The effect of scattering with energy degradation in the filter and in the detectors has been included to a first approximation. 2 - Method of solution: An iterative procedure is used: the calculation starts with a flux guess in which one assumes that each measured reactivity difference depends on the principal resonance only. The secondary resonance contribution is computed through the iterative process. For self-shielded cross-section calculations the model of Pearlstein and Weinstock (ref. 3) is used. The neutron spectrum can optionally be constant or 1/E inside each finite energy group relative to the resonance considered. 3 - Restrictions on the complexity of the problem: Maximum number of energy groups : 60

  13. State-of-the-art review of some artificial intelligence applications in pile foundations

    Directory of Open Access Journals (Sweden)

    Mohamed A. Shahin

    2016-01-01

    Full Text Available Geotechnical engineering deals with materials (e.g. soil and rock that, by their very nature, exhibit varied and uncertain behavior due to the imprecise physical processes associated with the formation of these materials. Modeling the behavior of such materials in geotechnical engineering applications is complex and sometimes beyond the ability of most traditional forms of physically-based engineering methods. Artificial intelligence (AI is becoming more popular and particularly amenable to modeling the complex behavior of most geotechnical engineering applications because it has demonstrated superior predictive ability compared to traditional methods. This paper provides state-of-the-art review of some selected AI techniques and their applications in pile foundations, and presents the salient features associated with the modeling development of these AI techniques. The paper also discusses the strength and limitations of the selected AI techniques compared to other available modeling approaches.

  14. Investigation of in-pile grown corrosion films on zirconium-based alloys

    International Nuclear Information System (INIS)

    Gebhardt, O.; Hermann, A.; Bart, G.; Blank, H.; Ray, I.L.F.

    1996-01-01

    In-pile grown corrosion films on different fuel rod claddings (standard Zircaloy-4, extra low tin Zircaloy (ELS), and Zr2.5Nb) have been studied using a variety of experimental techniques. The aim of the investigations was to find out common features and differences between the corrosion layers grown on zirconium alloys having different composition. Methods applied were scanning and transmission electron microscopy (SEM, TEM), electrochemical impedance spectroscopy (EIS), and electrochemical anodization. The morphological differences have been observed between the specimens that could explain the irradiation enhancement of corrosion of Zircaloy-4. The features of the compact oxide close to the oxide/metal interface have been characterized by electrochemical methods. The relationship between the thickness of this protective oxide and the overall oxide thickness has been investigated by EIS. It was found that this relation is dependent on the location of the oxide along the fuel rod and on the corrosion rate

  15. State-of-the-art review of some artificial intelligence applications in pile foundations

    Institute of Scientific and Technical Information of China (English)

    Mohamed A. Shahin

    2016-01-01

    Geotechnical engineering deals with materials (e.g. soil and rock) that, by their very nature, exhibit varied and uncertain behavior due to the imprecise physical processes associated with the formation of these materials. Modeling the behavior of such materials in geotechnical engineering applications is complex and sometimes beyond the ability of most traditional forms of physically-based engineering methods. Artificial intelligence (AI) is becoming more popular and particularly amenable to modeling the complex behavior of most geotechnical engineering applications because it has demonstrated superior predictive ability compared to traditional methods. This paper provides state-of-the-art review of some selected AI techniques and their applications in pile foundations, and presents the salient features associated with the modeling development of these AI techniques. The paper also discusses the strength and limitations of the selected AI techniques compared to other available modeling approaches.

  16. MCNP simulation to optimise in-pile and shielding parts of the Portuguese SANS instrument.

    Science.gov (United States)

    Gonçalves, I F; Salgado, J; Falcão, A; Margaça, F M A; Carvalho, F G

    2005-01-01

    A Small Angle Neutron Scattering instrument is being installed at one end of the tangential beam tube of the Portuguese Research Reactor. The instrument is fed using a neutron scatterer positioned in the middle of the beam tube. The scatterer consists of circulating H2O contained in a hollow disc of Al. The in-pile shielding components and the shielding installed around the neutron selector have been the object of an MCNP simulation study. The quantities calculated were the neutron and gamma-ray fluxes in different positions, the energy deposited in the material by the neutron and gamma-ray fields, the material activation resulting from the neutron field and radiation doses at the exit wall of the shutter and around the shielding. The MCNP results are presented and compared with results of an analytical approach and with experimental data collected after installation.

  17. Visual observations of fuel disruption in in-pile LMFBR accident experiments

    International Nuclear Information System (INIS)

    Wright, S.A.; Mast, P.K.

    1982-01-01

    Sandia National Laboratories has been investigating initiation phase phenomena in a series of Fuel Disruption (FD) experiments since 1977. In this program high speed cinematography is used to observe fuel disruption in in-pile experiments that simulate loss of flow accidents. Thus, these experiments provide high resolution measurements of initial fuel and clad motion with prototypic materials and prototypic heating conditions. The main objective of the FD experiment is to determine the timing (relative to fuel temperature) and the mode of fuel disruption under LOF heating conditions. Observed modes of disruption include fuel swelling, solid state breakup, cracking, ejection of a molten fuel jet, slumping, and rapid expansion of small particles. Because the temperature and character of the fuel at disruption are known, disruption can be correlated with the mechanisms driving the disruption such as fuel vapor pressure, molten fuel expansion, fission gases, and impurity gases

  18. Analyses with the FSTATE code: fuel performance in destructive in-pile experiments

    International Nuclear Information System (INIS)

    Bauer, T.H.; Meek, C.C.

    1982-01-01

    Thermal-mechanical analysis of a fuel pin is an essential part of the evaluation of fuel behavior during hypothetical accident transients. The FSTATE code has been developed to provide this required computational ability in situations lacking azimuthal symmetry about the fuel-pin axis by performing 2-dimensional thermal, mechanical, and fission gas release and redistribution computations for a wide range of possible transient conditions. In this paper recent code developments are described and application is made to in-pile experiments undertaken to study fast-reactor fuel under accident conditions. Three accident simulations, including a fast and slow ramp-rate overpower as well as a loss-of-cooling accident sequence, are used as representative examples, and the interpretation of STATE computations relative to experimental observations is made

  19. An In-Pile Kinetic Method for Determining the Delayed Neutron Fraction βeff

    International Nuclear Information System (INIS)

    Gilad, E.; Rivin, O.; Ettedgui, H.; Yaar, I.; Geslot, B.; Pepino, A.; Di Salvo, J.; Gruel, A.; Blaise, P.

    2014-01-01

    Delayed neutrons are of fundamental importance in the field of nuclear reactor dynamics and control. Although only a small fraction of the neutrons emitted by fission are not prompt, the knowledge of the delayed neutrons parameters is essential for transient analysis, such as startup or shutdown of the reactor, as well as for accidents analysis and control system design [1]. One of the main delayed neutron parameters used in the point reactor model equations is the effective delayed neutron fraction, which incorporates both delayed neutron spectral properties and core geometrical configuration [1,2]. Additional delayed neutron parameters include the fraction of fission neutrons emitted in each delayed group, and the delayed neutron precursors decay constants . Experimental efforts aimed at determining the value ofβ, which provide experimental support for the evaluation of delayed neutron parameters, are extremely valuable. This is due to the fact that unlike other fields in reactor physics, e.g. criticality safety or shielding, the availability of experimental data and benchmark problems for validating delayed neutron parameters and its implementation in different models is highly limited. Furthermore, the existing experimental data exhibit significant discrepancies between the different sets of parameter, which lead to substantial disparity in the analysis of kinetic experiments and reactor dynamic behavior]. In this work, a method for determining the effective delayed neutron fraction using in-pile reactivity oscillation and Fourier analysis is presented. The method is based on measurements of the reactor's power response to small periodic in-pile reactivity perturbations and utilizes Fourier analysis for reconstruction of the reactor zero power transfer function. Knowledge of the reactor transfer function enables the estimation of theβ value using multi-parameter nonlinear fit. The method accounts for higher harmonics, which are excited by the trapezoidal

  20. Evaluation of the in pile performance of boron containing fuel pellets

    International Nuclear Information System (INIS)

    Jeong, Gwanyoon; Sohn, Dongseong

    2012-01-01

    The world rare earth resource are heavily concentrated in certain area and if these natural resources are weaponized by a country, we may confront serious difficulty because rare earth element gadolinium(Gd) is used as burnable poison material in some nuclear power plants (NPP) in Korea. Gd is used as a neutron absorbing material in Gd 2 O 3 form and mixed with UO 2 When boron is used as burnable poison in nuclear fuel, in fuel pellets. The burnable poison mixed in the fuel pellets is called integral burnable absorber (BA) design which differentiates it from the old separate BA design. In the old separate BA design, boron(B) was used in borosilicate glass (PYREX) form and placed in guide tubes. With the development of the concern over the availability of rare earth material Gd, B is considered as a candidate material replacing Gd for the case when the rare earth material is weaponized. However the idea for new boron BA design is integral type because the integral type BA design has several benefits over the separate BA design, such as reduction of radioactive waste, more positions for BA location, etc. 10 B absorbs a neutron and produces helium by the following reaction: 10 B + n → 7 Li + 4 He The helium produced by the nuclear reaction may cause the increase of rod internal pressure and change the gap conductivity if the significant amount of helium gas is released to the gap between the pellet and the cladding. Thus, it is necessary to investigate the in-pile behaviors of B containing pellet. However, few experiment have been carried out so far on the behavior of in-pile produced helium in UO 2 fuel pellets, especially for the cases boron compound is mixed with UO 2 In this paper, we will evaluate the production and the release of helium depending on fuel. 10 B concentration in the fuel

  1. Correlação entre os testes da caminhada, marcha estacionária e TUG em hipertensas idosas Correlation between the walk, 2-minute step and TUG tests among hypertensive older women

    Directory of Open Access Journals (Sweden)

    R Pedrosa

    2009-06-01

    Full Text Available CONTEXTUALIZAÇÃO: O aumento de doenças crônicas em idosos, principalmente da Hipertensão Arterial Sistêmica, doença intimamente relacionada ao declínio da capacidade funcional, determina a necessidade do estudo de métodos de avaliação da realização das atividades, possibilitando detecção de níveis de capacidade funcional, prescrição de exercícios e acompanhamento das funções cardiovascular e motora. O teste da caminhada de 6 minutos (TC6', o teste da Marcha Estacionária de 2 minutos (TME2' e o teste Timed Up and Go (TUG são indicados para esta avaliação. Estudos em idosos saudáveis mostram a associação entre esses testes, facilitando a avaliação da capacidade funcional. Porém, em hipertensos, não existem estudos que avaliem a relação entre TC6', TME2'e TUG, justificando a realização desta pesquisa. OBJETIVOS: Verificar se existe associação entre endurance aeróbia e a mobilidade funcional em idosas hipertensas. MÉTODOS: Estudo observacional, analítico e transversal, com 32 hipertensas idosas, avaliadas por meio do TC6', TME2' e TUG. RESULTADOS:Houve correlação positiva moderada entre TC6' e TME2', r=0,36 (p=0,04 e correlação negativa moderada entre TC6'e TUG, r=-0,59 (p=0,000 e entre TME2' e TUG, r=-0,66 (p=0,000. CONCLUSÕES: Para hipertensas idosas, o TC6' pode ser substituído pelo TME2', assim como em idosos saudáveis. Quanto à correlação entre os TC6', TME2' e TUG, pode-se concluir que existe uma íntima relação entre resistência cardiovascular e mobilidade funcional; havendo menor resistência cardiovascular, há mobilidade funcional precária e vice-versa.BACKGROUND: The increase in chronic diseases among older adults, especially systemic arterial hypertension, a disease that is closely related to declining functional capacity, has created the need to study methods for activity evaluation in order to detect functional capacity levels, prescribe exercises and monitor motor and

  2. Thermal-hydraulic calculation and analysis on helium cooled ceramic breeder pebble bed assembly for in-pile irradiation and in-situ tritium extraction

    International Nuclear Information System (INIS)

    Guo Chunqiu; Xie Jiachun; Liu Xingmin

    2013-01-01

    In-pile irradiation and in-situ tritium extraction experiment is one of associated domestic research projects in ITER special program. According to the technical requirements of in-pile irradiation experiment of helium cooled ceramic breeder (ceramic) pebble bed assembly in a research reactor, the feasibility of the design for the in-pile irradiation and in-situ tritium extraction experiment of ceramic pebble bed assembly was evaluated. By conducting thermal-hydraulic design calculation with different in-pile irradiation channels, locations and structure parameters for ceramic pebble bed assembly, a reasonable design scheme of ceramic pebble bed assembly satisfying the design requirements for in-pile irradiation was obtained. (authors)

  3. MTR and PWR/PHWR in-pile loop safety in integration with the operation of multipurpose reactor - GAS

    International Nuclear Information System (INIS)

    Suharno; Aji, Bintoro; Sugiyanto; Rohman, Budi; Zarkasi, Amin S.; Giarno

    1998-01-01

    MTR and PWR/PHWR In-Pile Loop safety analysis in integration with the operation of Multipurpose Reactor - Gas has been carried out and completed. The assessment is emphasized on the function of the interface systems from the dependence of the operation and the evaluation to the possibility of leakage or failure of the in-pile part inside the reactor pool and reactor core. The analysis is refers to the logic function of the interface system and the possibility of leakage or failure of the in-pile part inside reactor pool and reactor core to consider the integrity of the core qualitatively. The results show that in normal and in transient conditions , the interface system meet the function requirement in safe integrated operation of in-pile loop and reactor. And the results of the possibility analysis of the leakage shows that the possibility based on mechanically assessment is very low and the impact to core integrity is nothing or can be eliminated. The possible position for leakage is on the flen on which one meter above the top level of the core, therefore no influence of leakage to the core

  4. Estradiol RIA kit in clinical practice

    International Nuclear Information System (INIS)

    Friedrich, W.; Lisse, K.; Bienert, R.; Flentje, H.; Koerner, H.; Wilken, T.; Akademie der Wissenschaften der DDR, Berlin-Buch. Zentralinstitut fuer Isotopen- und Strahlenforschung)

    1985-01-01

    First clinical experience with a estradiol RIA kit developed in the Central Institute for Isotope- and Radiation Research is reported. The kit was used for the daily control of estradiol level in patients, which were treated within the program for in vitro fertilization and embryo transfer. The time of incubation could be shortened by means of a double antibody technique and by use of a precipitation mixture to 2 h. The intraassay variation is 9.2%, the interassay variation is 15.1%, the recovery rate is 94%. The sensitivity of the test (B 0 -3SD) is about 120 pmol/l. The estradiol RIA kit satisfies clinical requirements. (author)

  5. Disfunção gustatória e olfatória em laringectomizados

    Directory of Open Access Journals (Sweden)

    Ada Salvetti Cavalcanti Caldas

    2013-10-01

    Full Text Available Após a cirurgia de laringectomia total, o fluxo aéreo nasal é transferido definitivamente para o traqueostoma, comprometendo a chegada de moléculas odoríferas até a cavidade nasal, podendo repercutir em alterações na percepção olfatória e gustatória nesses indivíduos. OBJETIVO: Avaliar as funções do olfato e do paladar em laringectomizados totais. Desenho do estudo: Estudo de série. MÉTODO: A amostra envolveu um grupo com 25 pacientes submetidos à laringectomia total e outro grupo de comparação com 25 pacientes não laringectomizados. A função gustatória foi avaliada por tiras gustativas de papel de filtro. Para avaliação da função olfatória, foi aplicado o teste Brief Smell Identification Test. RESULTADOS: No grupo de laringectomizados, houve maior frequência de hipogeusia (80%; p < 0,05, assim como de hiposmia (88%; p < 0,001, isoladas e concomitantes (72%; p < 0,001. Na discriminação dos sabores, o sabor amargo não diferiu entre os grupos, diferentemente dos demais sabores. No aspecto olfatório, os laringectomizados tiveram pior desempenho na detecção de odores de alerta e os relacionados à alimentação. Identificou-se que história de tabagismo e de alcoolismo foi significantemente mais frequente dentre laringectomizados. CONCLUSÃO: A diminuição das funções olfatória e gustatória em laringectomizados totais foi evidenciada nesse estudo.

  6. RIA Fuel Codes Benchmark - Volume 1

    International Nuclear Information System (INIS)

    Marchand, Olivier; Georgenthum, Vincent; Petit, Marc; Udagawa, Yutaka; Nagase, Fumihisa; Sugiyama, Tomoyuki; Arffman, Asko; Cherubini, Marco; Dostal, Martin; Klouzal, Jan; Geelhood, Kenneth; Gorzel, Andreas; Holt, Lars; Jernkvist, Lars Olof; Khvostov, Grigori; Maertens, Dietmar; Spykman, Gerold; Nakajima, Tetsuo; Nechaeva, Olga; Panka, Istvan; Rey Gayo, Jose M.; Sagrado Garcia, Inmaculada C.; Shin, An-Dong; Sonnenburg, Heinz Guenther; Umidova, Zeynab; Zhang, Jinzhao; Voglewede, John

    2013-01-01

    Reactivity-initiated accident (RIA) fuel rod codes have been developed for a significant period of time and they all have shown their ability to reproduce some experimental results with a certain degree of adequacy. However, they sometimes rely on different specific modelling assumptions the influence of which on the final results of the calculations is difficult to evaluate. The NEA Working Group on Fuel Safety (WGFS) is tasked with advancing the understanding of fuel safety issues by assessing the technical basis for current safety criteria and their applicability to high burnup and to new fuel designs and materials. The group aims at facilitating international convergence in this area, including the review of experimental approaches as well as the interpretation and use of experimental data relevant for safety. As a contribution to this task, WGFS conducted a RIA code benchmark based on RIA tests performed in the Nuclear Safety Research Reactor in Tokai, Japan and tests performed or planned in CABRI reactor in Cadarache, France. Emphasis was on assessment of different modelling options for RIA fuel rod codes in terms of reproducing experimental results as well as extrapolating to typical reactor conditions. This report provides a summary of the results of this task. (authors)

  7. In-Pile Instrumentation Multi- Parameter System Utilizing Photonic Fibers and Nanovision

    Energy Technology Data Exchange (ETDEWEB)

    Burgett, Eric [Idaho State Univ., Pocatello, ID (United States)

    2015-10-13

    An advanced in-pile multi-parameter reactor monitoring system is being proposed in this funding opportunity. The proposed effort brings cutting edge, high fidelity optical measurement systems into the reactor environment in an unprecedented fashion, including in-core, in-cladding and in-fuel pellet itself. Unlike instrumented leads, the proposed system provides a unique solution to a multi-parameter monitoring need in core while being minimally intrusive in the reactor core. Detector designs proposed herein can monitor fuel compression and expansion in both the radial and axial dimensions as well as monitor linear power profiles and fission rates during the operation of the reactor. In addition to pressure, stress, strain, compression, neutron flux, neutron spectra, and temperature can be observed inside the fuel bundle and fuel rod using the proposed system. The proposed research aims at developing radiation-hard, harsh-environment multi-parameter systems for insertion into the reactor environment. The proposed research holds the potential to drastically increase the fidelity and precision of in-core instrumentation with little or no impact in the neutron economy in the reactor environment while providing a measurement system capable of operation for entire operating cycles.

  8. In-Pile Instrumentation Multi- Parameter System Utilizing Photonic Fibers and Nanovision

    International Nuclear Information System (INIS)

    Burgett, Eric

    2015-01-01

    An advanced in-pile multi-parameter reactor monitoring system is being proposed in this funding opportunity. The proposed effort brings cutting edge, high fidelity optical measurement systems into the reactor environment in an unprecedented fashion, including in-core, in-cladding and in-fuel pellet itself. Unlike instrumented leads, the proposed system provides a unique solution to a multi-parameter monitoring need in core while being minimally intrusive in the reactor core. Detector designs proposed herein can monitor fuel compression and expansion in both the radial and axial dimensions as well as monitor linear power profiles and fission rates during the operation of the reactor. In addition to pressure, stress, strain, compression, neutron flux, neutron spectra, and temperature can be observed inside the fuel bundle and fuel rod using the proposed system. The proposed research aims at developing radiation-hard, harsh-environment multi-parameter systems for insertion into the reactor environment. The proposed research holds the potential to drastically increase the fidelity and precision of in-core instrumentation with little or no impact in the neutron economy in the reactor environment while providing a measurement system capable of operation for entire operating cycles.

  9. Pneumatic capsule with a measuring system for in-pile irradiation

    International Nuclear Information System (INIS)

    Oshima, Keiichi; Yamazaki, Yasaburo; Hirata, Mitsuho; Ishii, Toshio; Shimozawa, Ryohei.

    1967-01-01

    A prior-art in-pile irradiation apparatus wherein a rabbit containing an irradiation specimen therein is inserted into and removed from a pile by a pneumatic system does not include means for measuring the temperature and pressure of the specimen under irradiation. When the rabbit is deformed during irradiation, it cannot be reliably recovered. A pneumatic capsule assembly with a measuring system according to this invention has a double structure which consists of an inner capsule containing the specimen therein and an outer capsule evacuated or filled with a gas. A thermocouple lace wire and a strain gauge are welded on the outside surface of the inner capsule as detection terminals for measuring the temperature and pressure. A rupture plate which bursts when the pressure in the inner capsule reaches a predetermined value is provided at a part of the inner capsule, and a fin for heat transmission is provided between the inner and outer capsules to thus prevent the deformation of the pneumatic capsule assembly as a whole. (Takasuka, S.)

  10. Development of gas cooled reactors and experimental setup of high temperature helium loop for in-pile operation

    Energy Technology Data Exchange (ETDEWEB)

    Miletić, Marija, E-mail: marija_miletic@live.com [Czech Technical University in Prague, Prague (Czech Republic); Fukač, Rostislav, E-mail: fuk@cvrez.cz [Research Centre Rez Ltd., Rez (Czech Republic); Pioro, Igor, E-mail: Igor.Pioro@uoit.ca [University of Ontario Institute of Technology, Oshawa (Canada); Dragunov, Alexey, E-mail: Alexey.Dragunov@uoit.ca [University of Ontario Institute of Technology, Oshawa (Canada)

    2014-09-15

    Highlights: • Gas as a coolant in Gen-IV reactors, history and development. • Main physical parameters comparison of gas coolants: carbon dioxide, helium, hydrogen with water. • Forced convection in turbulent pipe flow. • Gas cooled fast reactor concept comparisons to very high temperature reactor concept. • High temperature helium loop: concept, development, mechanism, design and constraints. - Abstract: Rapidly increasing energy and electricity demands, global concerns over the climate changes and strong dependence on foreign fossil fuel supplies are powerfully influencing greater use of nuclear power. In order to establish the viability of next-generation reactor concepts to meet tomorrow's needs for clean and reliable energy production the fundamental research and development issues need to be addressed for the Generation-IV nuclear-energy systems. Generation-IV reactor concepts are being developed to use more advanced materials, coolants and higher burn-ups fuels, while keeping a nuclear reactor safe and reliable. One of the six Generation-IV concepts is a very high temperature reactor (VHTR). The VHTR concept uses a graphite-moderated core with a once-through uranium fuel cycle, using high temperature helium as the coolant. Because helium is naturally inert and single-phase, the helium-cooled reactor can operate at much higher temperatures, leading to higher efficiency. Current VHTR concepts will use fuels such as uranium dioxide, uranium carbide, or uranium oxycarbide. Since some of these fuels are new in nuclear industry and due to their unknown properties and behavior within VHTR conditions it is very important to address these issues by investigate their characteristics within conditions close to those in VHTRs. This research can be performed in a research reactor with in-pile helium loop designed and constructed in Research Center Rez Ltd. One of the topics analyzed in this article are also physical characteristic and benefits of gas

  11. A aplicação de adesivo de cianoacrilato por histeroscopia e os testes de perviedade na esterilização tubária de ovelhas

    Directory of Open Access Journals (Sweden)

    Sergio Bigolin

    Full Text Available OBJETIVO: avaliar, por meio de testes de prenhez e de perviedade, a eficácia da obstrução tubária de ovelhas com adesivo de cianoacrilato aplicado por via histeroscópica. MÉTODO: 12 ovelhas adultas, com uma gestação anterior, foram distribuídas em três grupos: G-PO (n=3 submetidas à laqueadura tubária tipo Pomeroy; G-SH (n=3 aplicação de solução salina no istmo tubário por histeroscopia, e G-AD (n=6 aplicação de 0,5mL de n-butil-2-cianoacrilato no interior do istmo tubário, por histeroscopia. Depois de acasaladas por 90 dias com machos de comprovada fertilidade, as ovelhas não prenhas foram submetidas à laparotomia, retiradas as tubas uterinas, medidos os seus diâmetros e preparadas para testes de perviedade pela aplicação de azul de metileno e de pressão hidráulica (80mmHg. RESULTADOS: As ovelhas de G-PO e G-AD não ficaram prenhas (0%, em contraste com as SH (100%. O G-PO apresentou maior concentração de aderências (66,6% e de granulomas (100% em relação ao grupo AD (0%; o adesivo manteve-se íntegro no lúmen tubário. O diâmetro da tuba uterina em G-AD (0,650 ± 0,16 cm foi significantemente maior do que o das tubas em G-PO (0,195 ± 0,04* cm (p=0,01. Os testes de perviedade de pressão e corante foram negativos para todo o grupo PO e somente um animal em AD mostrou-se positivo para o teste de pressão. CONCLUSÃO: a aplicação histeroscópica de cianoacrilato no lúmen tubário de ovelhas impediu eficientemente a fecundação, constituindo procedimento eficaz e de boas perspectivas para aplicação futura em humanos.

  12. Práticas de política econômica: um teste das atas do Comitê de Política Monetária do Banco Central do Brasil (2003-2014

    Directory of Open Access Journals (Sweden)

    Andrea Ribeiro

    Full Text Available Resumo Falta uma análise discursiva mais profunda sobre os temas de política econômica e suas implicações, sob a perspectiva da Ciência Política. Nesse sentido, o objetivo do artigo é testar o uso da análise textual como ferramenta de pesquisa em política econômica. Busca-se analisar textualmente as atas das reuniões do Comitê de Política Monetária (COPOM do Banco Central (Bacen produzidas entre 2003 e 2014, de modo a identificar as variações dos termos e verificar se há alguma relação positiva entre os termos identificados e o modo como a política econômica foi conduzida durante os três governos do Partido dos Trabalhadores (PT. Essa avaliação é feita a partir do uso do software de análise textual Iramuteq, considerando-se os momentos de inflexão na política econômica, assim como os momentos de maior aproximação e distanciamento entre o Bacen e o Ministério da Fazenda. A pesquisa envolveu o levantamento das atas do COPOM, extraídas da base de dados do Bacen disponível na internet, sua seleção e tratamento para análise e a produção de nuvens de palavras e gráficos de similitude. Como teste da hipótese, esperava-se identificar esses pontos de inflexão na fonte primária na variação de termos. O uso do “text mining” em estudos de política econômica é recente. A vantagem de testar a hipótese usando essa ferramenta é abrir a “caixa preta” da produção de política econômica. Isso permite (1 um melhor conhecimento dos termos utilizados e suas implicações; (2 análises temporalmente mais abrangentes que escrutinem uma grande quantidade de dados simultaneamente. Foi possível identificar e perceber a variação ao longo do tempo dos termos utilizados e de sua distribuição, o que confirma parcialmente a hipótese inicial. Embora essas variações sejam bastante sutis, em função do tratamento e da restrição temporal da amostra (que contemplou apenas governos de um mesmo partido, é poss

  13. RIA in cardiovascular disease

    International Nuclear Information System (INIS)

    Hourani, M.H.

    1983-01-01

    When one discusses the management of chronic cardiac diseases, and in particular congestive heart failure (CHF), one cannot but think of digitalis and the important role it plays in the management of CHF. One also has to think about digitalis toxicity and the narrow margin between the therapeutic and toxic doses of digitalis and the important role that monitoring the serum level of the drug play in preventing and/or recognizing its toxic effects. Again, RIA has something to offer the clinician in this area. The purpose of this chapter is to discuss the radioassays for CPK-MB and digoxin mainly, as well as touch upon other assays of use in evaluating patients with cardiovascular disease

  14. Fabrication, characteristics, and in-pile performance of UO2 pellets prepared from dry route powder

    International Nuclear Information System (INIS)

    Chotard, A.; Ledac, A.; Bernardin, M.

    1991-01-01

    The dry route conversion process of UF 6 to sinterable UO 2 powder has been used in France on a large scale for more than 10 years for the fabrication of PWR fuels. Thus, our fabrication and irradiation experience relates to more than 10,000 tons of fuel. As everyone knows, the dry route conversion process only involves gas-gas and gas-solid reactions which present the advantage of producing very little contaminated wastes and no liquid effluents. Powders obtained by this process are characterized by: - a very high purity, - a low specific surface area (around 2 m 2 /g), therefore a high resistance to spontaneous oxidation, - a good compressibility, - a very high sinterability (.98% T.D.), - a very high reproducibility. This powder also shows a high fineness which leads to very homogeneous blends with additives like pore former, U 3 O 8 or Gd 2 O 3 . On the other hand this fineness requires a granulation step which is actually not a disadvantage since it allows to adjust the granulate size to optimize the filling of press dies and so as to guarantee a good stability of the pellet dimensions and density. This pelletizing process leads to pellets characterized by: - a good thermal stability (0.5% T.D. after 34 hours at 1700degC), - no open porosity, - low H 2 content (0,3 ppm), - an homogeneous microstructure (grain size and porosity). Such characteristics mean that the UO 2 pellets from dry route conversion present an excellent in pile behaviour for high burnup up to 58,000 MWd/MtU in commercial plant, with: - low fission gas release, - good dimensional stability (densification, swelling), of which examples and results of PIE are described in the paper. The qualities of the dry route conversion powder and its flexibility of use make it possible to consider adjustment of the pellet characteristics, mainly: density, grain size and pore size distribution for specific uses or performance upgrade. (orig.)

  15. The Acoustic Emission signal acquired by the microphones placed in the CABRI test device along the fourteen last R.I.A. experiments: an example of reproducible research in nuclear science

    International Nuclear Information System (INIS)

    Laurent Pantera, Oumar Traore

    2015-01-01

    The CABRI facility is an experimental nuclear reactor of the French Atomic Energy Commission. It is located at the Cadarache Research Centre in southern France and it is designed to act as a support to the French nuclear infrastructure. The purpose of the new testing programme termed, 'CABRI International Programme' (CIP) is to study the behaviour of PWR-type fuel rods at high burnup, equipped with an 'advanced' cladding, under Reactivity Initiated Accident (RIA) conditions (such as the scenario of a control rod ejection). Within the framework of this programme, piloted and funded by the French Institute of Nuclear Radioprotection and Safety (IRSN), ten tests are to be conducted with a frequency of two tests per year. The LPRE laboratory of the CEA which is in charge of the Preparation, realisation and breakdown of the test results studies the possibility to set up a new test analysis based on the processing of signals coming from sensors placed within the test equipment. During the experimental phase, the behaviour of the fuel element generates acoustic waves which can be detected by two microphones placed upstream and downstream of the test device. Studies showed the interest to realize temporal and spectral analyses on these signals by showing the existence of signatures which can be correlated with physical phenomena as the rod failure or the test shutdown (i.e. scram). The work presented in this article results from the will to consolidate these studies. Since the main phenomenon to be tracked is the fuel rod failure, the aim would be to highlight specific events which would have been precursors of the rod failure in order to use in the future these signals for further interpretation. Such an antecedent works resumption leads to a better understanding of the experimental needs and constitutes a good initial state to prepare the new very fast digital data acquisition systems. Although all the raw data are accessible in the form of text files

  16. The Acoustic Emission signal acquired by the microphones placed in the CABRI test device along the fourteen last R.I.A. experiments: an example of reproducible research in nuclear science

    Energy Technology Data Exchange (ETDEWEB)

    Laurent Pantera, Oumar Traore [CEA, DEN, DER/SRES, Cadarache, F-13108 Saint Paul lez Durance (France)

    2015-07-01

    The CABRI facility is an experimental nuclear reactor of the French Atomic Energy Commission. It is located at the Cadarache Research Centre in southern France and it is designed to act as a support to the French nuclear infrastructure. The purpose of the new testing programme termed, 'CABRI International Programme' (CIP) is to study the behaviour of PWR-type fuel rods at high burnup, equipped with an 'advanced' cladding, under Reactivity Initiated Accident (RIA) conditions (such as the scenario of a control rod ejection). Within the framework of this programme, piloted and funded by the French Institute of Nuclear Radioprotection and Safety (IRSN), ten tests are to be conducted with a frequency of two tests per year. The LPRE laboratory of the CEA which is in charge of the Preparation, realisation and breakdown of the test results studies the possibility to set up a new test analysis based on the processing of signals coming from sensors placed within the test equipment. During the experimental phase, the behaviour of the fuel element generates acoustic waves which can be detected by two microphones placed upstream and downstream of the test device. Studies showed the interest to realize temporal and spectral analyses on these signals by showing the existence of signatures which can be correlated with physical phenomena as the rod failure or the test shutdown (i.e. scram). The work presented in this article results from the will to consolidate these studies. Since the main phenomenon to be tracked is the fuel rod failure, the aim would be to highlight specific events which would have been precursors of the rod failure in order to use in the future these signals for further interpretation. Such an antecedent works resumption leads to a better understanding of the experimental needs and constitutes a good initial state to prepare the new very fast digital data acquisition systems. Although all the raw data are accessible in the form of text files

  17. Results of water chemistry control in the in-pile ''Callisto'' loop (an experimental PWR rig installed in the BR2 reactor)

    International Nuclear Information System (INIS)

    Weber, M.; Benoit, P.; Dekeyser, J.; Verwimp, A.

    1994-01-01

    Since June 1992, a new experimental facility, called CALLISTO, is being irradiated in the BR2 materials testing reactor at Mol, Belgium. The main objective of the present test campaign is to study the behaviour of advanced fuel to high burn-up rates in a realistic PWR environment. Three in-pile sections, containing each 9 fuel rods, are loaded inside the reactor vessel and are connected to a common out-of-pile pressurized water circulation loop (ref.1). The later is branched-off into a purification circuit (feed-bleed concept) and further equipped with safety and auxiliary systems. To cope with the test programme, the equipments are designed so that the guidelines of a PWR primary water chemistry can be followed (ref.2). Real steady-state conditions cannot be observed because the typical BR2 cycle (3 weeks running/3 weeks shut-down) is much shorter and because the rig is cooled down during each reactor shut-down. The purpose of this poster is to provide results of chemical parameters recorded during the cycling behaviour of the CALLISTO primary water. (authors). 4 figs., 1 tab., 2 refs

  18. Mixed RIA standard

    International Nuclear Information System (INIS)

    Talan, P.; Mucha, J.; Krizan, J.

    1986-01-01

    For the radioimmunoassay of digoxin, 3,5,3'-triiodothyronine, 17β-estradiol, progesterone, testosterone and α 1 -fetoprotein a mixed standard was prepared of these substances in a gamma globulin solution at a concentration of 0.8 to 1.4 wt.% in an aqueous buffer at pH within the range of 6 - 9. The standard contains digoxin at a concentration of 10 -4 to 10 nmol/l, 17β-estradiol at 10 -4 to 2 nmol/l, progesteron at 10 -4 to 100 nmol/l, testosterone at 1o -4 to 21 nmol/l, and α 1 -fetoprotein at 10 -4 to 10 nmol/l with at least two of these substances having concentrations higher than 10 -3 nmol/l. Examples are given of the preparation of the mixed standard with different concentrations of the components. The use of the standard has the following advantages: it is labor saving, reduces the risk of failure in the manufacture of RIA kits, eliminates mistakes in the selection of kits for the determination of different substances and allows a more economical use of material. (E.S.)

  19. In-pile behavior of controlled beta-quenched fuel channels

    Energy Technology Data Exchange (ETDEWEB)

    Moeckel, Andreas; Pflaum, Wolfgang; Cremer, Ingo [AREVA NP GmbH, Erlangen (Germany); Zbib, Ali A. [AREVA NP Inc., Richland, WA (United States)

    2011-07-01

    of a German boiling water reactor (BWR) nuclear power plant in 2004. Since then, additional beta-quenched lead fuel channels have been placed in the core of some other European BWRs to broaden the in-pile experience with such channels in different nuclear power plants. (orig.)

  20. Exame simples de urina no diagnóstico de infecção urinária em gestantes de alto risco Urine test to diagnose urinary tract infection in highh-risk pregant women

    Directory of Open Access Journals (Sweden)

    Gláucia Virgínia de Queiroz Lins Guerra

    2012-11-01

    Full Text Available OBJETIVO: Identificar a acurácia do exame simples de urina para diagnóstico de infecção urinária em gestantes de alto risco. MÉTODOS: Realizou-se um estudo transversal, prospectivo, em 164 gestantes admitidas na enfermaria de alto risco do Instituto de Medicina Integral Prof. Fernando Figueira (IMIP, no período de janeiro a junho de 2011. Foram excluídas as pacientes em uso de antibiótico nos últimos dez dias. Todas as pacientes foram submetidas aos exames de urina simples e urocultura no início de sua admissão. A concordância entre os resultados dos exames foi avaliada pelo índice Kappa (K, sendo, ainda, determinados a acurácia, sensibilidade, especificidade e valor preditivo positivo (VPP e negativo (VPN. RESULTADOS: Utilizando como critério de diagnóstico apenas a presença de piócitos no exame simples de urina para sugerir bacteriúria, observou-se uma fraca concordância quando comparado à urocultura (K=0,16. A acurácia foi de 61%, com sensibilidade de 62,5% e especificidade de 60,6%. O VPP foi de 27,78% e o VPN, de 87%. CONCLUSÃO: Na presença de alteração do exame simples de urina não necessariamente está em curso uma infecção urinária, sendo necessária a realização da urocultura. Porém, quando o exame simples de urina for normal, a urocultura pode ser dispensada.PURPOSE: To identify the accuracy of urinalysis in the diagnosis of urinary tract infection in pregnant women at high risk. METHODS: a prospective, cross-sectional study was conducted on 164 pregnant women admitted to the high-risk the ward of the Instituto de Medicina Integral Prof. Fernando Figueira (IMIP during the period from January to June 2011. Patients who had been taking antibiotics in the last ten days were excluded. All patients were subjected to simple urine tests and urine culture at the beginning of their admission. The agreement between the results of the examinations was evaluated by Kappa indices (K, and accuracy, sensitivity

  1. Radioimmunoassay with heterologous antibody (hetero-antibody RIA)

    International Nuclear Information System (INIS)

    Iwasawa, Atsushi; Hayashi, Hiroaki; Itoh, Zen; Wakabayashi, Katsumi

    1991-01-01

    To develop a homologous radioimmunoassay (RIA) for a hormone of a small or rare animal often meets difficulty in collecting a large amount of purified antigen required for antibody production. On the other hand, to employ a heterologous RIA to estimate the hormone often gives poor sensitivity. To overcome this difficulty, a 'hetero-antibody' RIA was studied. In a hetero-antibody RIA system, a purified preparation of a hormone is used for radioiodination and standardization and a heterologous antibody to the hormone is used for the first antibody. Canine motilin and rat LH were selected as examples, and anti-porcine motilin and anti-hCG, anti-hCGβ or anti-ovine LHβ was used as the heterologous antibody. The sensitivities of the hetero-antibody RIAs were much higher than those of heterologous RIAs in any case, showing that these hetero-antibody RIA systems were suitable for practical use. To clarify the principle of hetero-antibody RIA, antiserum to porcine motilin was fractionated on an affinity column where canine motilin was immobilized. The fraction bound had greater constants of affinity with both porcine and canine motilins than the rest of the antibody fractions. This fraction also reacted with a synthetic peptide corresponding to the C-terminal sequence common to porcine and canine motilins in a competitive binding test with labeled canine motilin. These results suggest that an antibody population having high affinity and cross-reactivity is present in polyclonal antiserum and indicate that the population can be used in hetero-antibody RIA at an appropriate concentration. (author)

  2. Out-of-pile and in-pile temperature noise investigations: a survey of methods results and models

    International Nuclear Information System (INIS)

    Dentico, G.; Giovannini, R.; Marseguerra, M.; Pacilio, N.; Taglienti, S.; Tosi, V.; Vigo, A.; Oguma, R.

    1982-01-01

    A review is given of the main results obtained from temperature noise measurements performed in out-of-pile sodium loops on fast fuel element mock-ups. Sources of data were thermocouples placed in the central axis of the channel downstream from the bundle end. Autoregressive moving average (ARMA) models have been applied to several temperature time series; the analysis shows that a simple ARMA (3, 2) model adequately accounts for the observed fluctuations. Finally, highlights of a heat transfer stochastic model are also reported together with a preliminary validation against in-pile experimental data. (author)

  3. In-pile observations of fuel and clad relocation during LMFBR initiation phase accident experiments - the STAR experiments

    International Nuclear Information System (INIS)

    Wright, S.A.; Schumacher, G.; Henkel, P.R.; Royl, P.

    1987-01-01

    A series of seven in-pile experiments (the STAR experiments) were performed in which clad motion and fuel dispersal were observed in small pin bundles with high-speed cinematography. The experimental heating conditions reproduced a range of Loss of Flow (LOF) accident scenarios for the lead subassemblies in LMFBRs. The experiments show strong tendencies for limited clad motion in multiple pin bundles, early fuel disruption and dispersal (prior to fuel melting) in moderate power transients having simultaneous clad melting and fuel disruption. The more recent experiments indicate a possibility of steel vapor driven fuel dispersal after fuel breakup and intimate fuel/steel mixing. (author)

  4. Multi-channel mechanical test machine for HANARO (I)

    International Nuclear Information System (INIS)

    Song, M. S.; Choi, Y.; Cho, M. S.; Kim, B. G.; Kang, Y. H.

    2004-01-01

    Design and fabrication of multi-channel mechanical test machine is useful and important for the study of in-pile test of nuclear materials in HANARO. The dimension and shape of the multi-channel mechanical test machine should be fixed to a test reactor and their objectives. KAERI successfully developed a non-instrumented multi-channel mechanical test machine for material irradiation tests in a domestic research reactor, HANARO. This results in strongly stimulating and accelerating irradiation tests of materials in domestic industry and research fields with HANARO. Although various types of in-pile creep capsule were made for well installation in each test reactor, there is no in-pile creep multi-channel mechanical test machine for HANARO. Hence, the objectives of this study are to fabricate and test a multi-channel mechanical test machine of HANARO

  5. Development of Electrical Capacitance Sensors for Accident Tolerant Fuel (ATF) Testing at the Transient Reactor Test (TREAT) Facility

    Energy Technology Data Exchange (ETDEWEB)

    Liu, Maolong; Ryals, Matthew; Ali, Amir; Blandford, Edward; Jensen, Colby; Condie, Keith; Svoboda, John; O' Brien, Robert

    2016-08-01

    A variety of instruments are being developed and qualified to support the Accident Tolerant Fuels (ATF) program and future transient irradiations at the Transient Reactor Test (TREAT) facility at Idaho National Laboratory (INL). The University of New Mexico (UNM) is working with INL to develop capacitance-based void sensors for determining the timing of critical boiling phenomena in static capsule fuel testing and the volume-averaged void fraction in flow-boiling in-pile water loop fuel testing. The static capsule sensor developed at INL is a plate-type configuration, while UNM is utilizing a ring-type capacitance sensor. Each sensor design has been theoretically and experimentally investigated at INL and UNM. Experiments are being performed at INL in an autoclave to investigate the performance of these sensors under representative Pressurized Water Reactor (PWR) conditions in a static capsule. Experiments have been performed at UNM using air-water two-phase flow to determine the sensitivity and time response of the capacitance sensor under a flow boiling configuration. Initial measurements from the capacitance sensor have demonstrated the validity of the concept to enable real-time measurement of void fraction. The next steps include designing the cabling interface with the flow loop at UNM for Reactivity Initiated Accident (RIA) ATF testing at TREAT and further characterization of the measurement response for each sensor under varying conditions by experiments and modeling.

  6. Validade da autopercepção da presença de cárie dentária como teste diagnóstico e fatores associados entre adultos

    OpenAIRE

    Haikal, Desirée Sant’Ana; Roberto, Luana Leal; Martins, Andréa Maria Eleutério de Barros Lima; Paula, Alfredo Maurício Batista de; Ferreira, Efigênia Ferreira e

    2017-01-01

    Resumo: Objetivou-se investigar a validade da autopercepção da presença da cárie dentária e fatores associados, mediante estudo com 795 adultos (35-44 anos). A variável dependente foi autopercepção da presença da cárie dentária, as independentes reunidas em blocos. Três modelos logísticos foram conduzidos: (1) todos os adultos; (2) adultos com lesões de cárie normativa; e (3) adultos sem tais lesões. A autopercepção da presença da cárie dentária apresentou sensibilidade de 77,7%, especificida...

  7. Isolamento e teste de susceptibilidade a antimicrobianos de bactérias em infecções uterinas de éguas Isolation and antimicrobial susceptibility of bacteria in uterine infections in mares

    Directory of Open Access Journals (Sweden)

    N. Silva

    1999-06-01

    Full Text Available Foram examinados 206 "swabs" cervicais e uterinos de éguas de várias raças, de diversas regiões do Estado de Minas Gerais, durante o período de 1986 a 1996. Cerca de 164 "swabs" foram positivos para a presença de microrganismos causadores de endometrites. Streptococcus equi subsp. zooepidemicus (25,7% e Escherichia coli (15,1% foram os principais agentes infecciosos isolados. Outros microrganismos presentes foram: Staphylococcus aureus (9,2%, Streptococcus alfa-hemolítico (9,2%, Pseudomonas aeruginosa (3,9%, Staphylococcus coagulase negativo (6,3%, Bacillus spp. (1,9%, Rhodococcus equi (3,4% e Proteus mirabilis (1,5%. As provas de susceptibilidade aos antimicrobianos revelaram que amicacina e gentamicina (70,2%, ampicilina (59,5% e cloranfenicol (59,5% foram os antibióticos de maior ação in vitro contra os microrganismos isolados.This study examined 206 cervical and uterine swabs collected from infected mares from herds in the Minas Gerais State, Brazil, from 1986 to 1996. Amongst 164 successful isolations, 25.7% were identified as Streptococcus equi, subsp. zooepidemicus, and 15.1% as Escherichia coli, both considered the most important isolates. Other bacteria found included Staphylococcus aureus (9.2%, Streptococcus alpha-hemolytic (9.2%, Pseudomonas aeruginosa (3.9%, coagulase negative Staphylococcus (6.3%, Bacillus spp. (1.9%, Rhodococcus equi (3.4% and Proteus mirabilis (1.5%. The antibiotic susceptibility tests revealed amikacin and gentamicin (70.2%, ampicillin and chloramphenicol (59.5% as the most effective in vitro antibiotics against these microorganisms.

  8. Status of the EXOTIC-8 programme and first in-pile results for Li{sub 2}TiO{sub 3} pebbles

    Energy Technology Data Exchange (ETDEWEB)

    Van der Laan, J G; Stijkel, M P [Netherlands Energy Research Foundation (ECN), Petten (Netherlands); Conrad, R

    1998-03-01

    After renewal of the Tritium Measuring Station the HFR is again fully operational for in-pile breeder irradiations. The EXOTIC-8 series has started with first three experiments on June 12, 1997. First in-pile results have been obtained for Li{sub 2}TiO{sub 3}-pebbles supplied by CEA: preliminary analyses indicate satisfactory in-pile behaviour with fast recovery from transient conditions. Five further experiments have been defined which implies that in the present planning EXOTIC-8 is filled completely up to Fall`98 and 2 of 4 positions are occupied up to Spring`99. P.I.E. results will be obtained from Spring`98 onwards. (J.P.N.)

  9. Avaliação da cognição de mulheres no climatério com o Mini-Exame do Estado Mental e o Teste de Memória da Lista de Palavras Cognitive function in menopausal women evaluated with the Mini-Mental State Examination and Word-List Memory Test

    Directory of Open Access Journals (Sweden)

    Rita de Cássia Leite Fernandes

    2009-09-01

    Full Text Available No Brasil, há pouca investigação sobre cognição no climatério, apesar da grande freqüência de queixas neuropsíquicas nessa fase da vida feminina. Apresentamos estudo transversal, cujo objetivo foi descrever os escores de 156 mulheres climatéricas no Mini-Exame do Estado Mental (MEEM e no Teste de Memória da Lista de Palavras (TMLP. A média obtida no MEEM foi de 25,86 pontos (DP = 2,67, semelhante a outros estudos, exceto pelo melhor desempenho das analfabetas; os escores nos subitens "atenção e cálculo" e "memória imediata" apresentaram valores inferiores. No TMLP, a média também foi condizente com a literatura (18,83 palavras; DP = 3,82. As únicas associações significativas com as pontuações foram a escolaridade em ambos os testes e a hipertensão arterial no TMLP. Concluímos que o desempenho cognitivo dessas mulheres climatéricas se assemelha ao de outras amostras brasileiras, confirmando-se, inclusive, a maior variabilidade de pontuação entre indivíduos de baixa escolaridade. As queixas de dificuldades de memória na meia-idade feminina podem estar relacionadas à redução da sua atenção.There is little research in Brazil on cognition and menopause, despite the high frequency of neuropsychiatric complaints in this phase of women's life. The authors present a cross-sectional study aimed at describing the scores by 156 menopausal women on the Mini-Mental State Examination (MMSE and the Word-List Memory Test (WLMT. The mean score on the MMSE was 25.86 points (SD = 2.67, similar to other studies, except for better performance by illiterate women; scores on the sub-items "attention and calculation" and "immediate recall" showed lower values. In the WLMT, the mean was also consistent with the literature (M = 18.83 words; SD = 3.82. The only significant associations with score were for schooling in both tests and arterial hypertension in the WLMT. The authors conclude that cognitive performance in these menopausal

  10. Coriorretinite esclopetária

    Directory of Open Access Journals (Sweden)

    Isaac Carvalho de Oliveira Ramos

    2015-06-01

    Full Text Available O objetivo deste trabalho é relatar um caso de trauma ocular por projétil de arma de fogo, que atingiu e se alojou na cavidade orbitária, desenvolvendo coriorretinite esclopetária. Foram abordados o mecanismo fisiopatológico, os principais achados clínicos e de exames complementares, além das opções de tratamento. As características do caso relatado reforçam a importância de uma abordagem multidisciplinar no trauma ocular.

  11. Validade da autopercepção da presença de cárie dentária como teste diagnóstico e fatores associados entre adultos

    Directory of Open Access Journals (Sweden)

    Desirée Sant’Ana Haikal

    2017-08-01

    Full Text Available Resumo: Objetivou-se investigar a validade da autopercepção da presença da cárie dentária e fatores associados, mediante estudo com 795 adultos (35-44 anos. A variável dependente foi autopercepção da presença da cárie dentária, as independentes reunidas em blocos. Três modelos logísticos foram conduzidos: (1 todos os adultos; (2 adultos com lesões de cárie normativa; e (3 adultos sem tais lesões. A autopercepção da presença da cárie dentária apresentou sensibilidade de 77,7%, especificidade de 58%, acurácia de 65%, valor preditivo positivo de 52% e valor preditivo negativo de 81%. No Modelo 1, a autopercepção da presença da cárie dentária foi associada ao tempo de uso dos serviços odontológicos, acesso à informação, uso de fio dental, lesões normativas, percepção da necessidade de tratamento, dor, insatisfação com a saúde bucal e geral. No Modelo 2, a autopercepção da presença da cárie dentária foi associada ao tempo de uso dos serviços odontológicos, percepção da necessidade de tratamento e insatisfação com a saúde bucal e geral. No Modelo 3, autopercepção da presença da cárie dentária foi associada ao tempo de uso dos serviços odontológicos, acesso à informação, percepção da necessidade de tratamento, insatisfação com a saúde bucal e uso de fio dental. A autopercepção da presença da cárie dentária mostrou utilidade limitada como método de diagnóstico.

  12. The evaluation of CLIA, RIA and MSP-ELISA for measurement of thyroid hormones

    International Nuclear Information System (INIS)

    Jing Hua; Li Dan; Chen Yiguang; Zhou Huiqin; Xu Liyan

    2005-01-01

    To compare the characteristics of chemiluminescent immunoassay (CLIA), RIA and magnetic solid phase enzyme-linked immnosorbent assay (MSP-ELISA) in measuring thyroid hormones, TT 3 , TT 4 , FT 3 , FT 4 and TSH were tested in 40 samples of human serum and in standard samples of thyroid hormones by CLIA, RIA and MSP-ELISA respectively. The linearity, relativiy, precision, recovery of these three met hods were compared. The result showed that there were no statistical differences between CLIA, RIA and MSP-ELISA in linearity and relativity. CLIA was better than RIA and MSP-ELISA in precision and accuracy. (authors)

  13. Temporal variation in memory tests performance in cerebral vascular disease patients / Variação temporal no desempenho em testes de memória em pacientes com doença vascular cerebral

    Directory of Open Access Journals (Sweden)

    Tania Fernandes Campos

    2007-01-01

    Full Text Available This study intended to investigate the performance in memory tests in order to adequate the neuropsychological evaluation to the temporal order of the human organism. Twelve cerebral vascular accident patients and 12 controls, of both sexes and 45-65 years old were studied. Two memory tests with visual stimuli (pictures and two with verbal stimuli (words were applied three times a day (08:00, 10:00 and 12:00 h during the first week and twice a day (14:00 and 16:00 h in the second week, during three consecutive days in two consecutive weeks. The patients showed lower scores than control subjects in all applied tests (p<0,05. The greater test sensitivity was at 14:00 h for the free recall test and at 16:00 h for recognition tests. According to these results, it is concluded that neuropsychological evaluations should be conducted preferably in the afternoon, as well for the first evaluation as for the re-evaluations.

  14. Alpha radiation and in-pile annealing effects on the fracture properties of a sintered alumino borosilicate glass

    International Nuclear Information System (INIS)

    Bevilacqua, Arturo M.; Prado, Miguel O.; Messi de Bernasconi, Norma B.; Heredia, Arturo D.; Sanfilippo, Miguel

    1999-01-01

    The alpha radiation and the in-pile during irradiation effects on the hardness, the crack nucleation and the fracture toughness of the German alumino borosilicate glass SG7 were investigated by using the Vickers indentation. Cold pressed and sintered samples were irradiated with thermal neutrons, in the Argentine nuclear reactors RA-3 and RA-6, to produce alpha particles in the whole volume of the glass by means of the (n, alpha)-reaction with B-10. The Vickers hardness, the crack nucleation, as 50 percent fracture probability load, plotted as the Weibull's fracture probability distribution function and the fracture toughness, as critical stress intensity factor K Ic , were correlated to the four cumulative disintegration values. It was ascertained that: a) the Vickers hardness decreases from 5.6 GPa for the non-irradiated sample up to 4.7 GPa for the sample irradiated 70 h at the lower neutron flux (4.0 x 10 - sup 18 - alpha disintegration per cm - sup 3 -), b) the 50 % fracture probability load increases from 1.4 N for the non-irradiated sample up to 4.7 g for the sample irradiated 22 h at the higher flux (6.8 x 10 - sup 18 - alpha disintegration per cm - sup 3 -), and c) the stress intensity factor increases from 0.80 MPa.m - sup 1/2 - for the non irradiated sample up to 0.86 MPa.m - sup 1/2 - for the sample mentioned in b). The in-pile annealing was analyzed by comparing the crack nucleation after irradiation with data obtained by heavy ion irradiation followed by thermal annealing. Results for the SG7 glass were compared to those for soda-lime and borosilicate glasses. (author)

  15. Relação da função muscular respiratória e de membros inferiores de idosos comunitários com a capacidade funcional avaliada por teste de caminhada Relationship between functional capacity assessed by walking test and respiratory and lower limb muscle function in community-dwelling elders

    Directory of Open Access Journals (Sweden)

    Leonardo A. Simões

    2010-02-01

    Full Text Available CONTEXTUALIZAÇÃO: A sarcopenia é considerada o fator mais significativo na redução da força muscular periférica e respiratória e pode ocasionar incapacidades progressivas, perda de independência e interferir na capacidade funcional dos idosos. OBJETIVOS: Caracterizar a força dos músculos respiratórios (pressão inspiratória máxima - PImax e pressão expiratória máxima - PEmax e de membros inferiores (MMII, bem como as possíveis correlações existentes com a capacidade funcional dos idosos. MÉTODOS: Sessenta e cinco idosos, com 71,7±4,9 anos; foram avaliados por dinamometria isocinética para flexores e extensores dos joelhos, manovacuometria analógica para os músculos respiratórios pelo teste de caminhada de 6 minutos para capacidade funcional. Foram utilizados os testes Mann-Whitney e t de Student para comparação entre os gêneros. As correlações foram calculadas pelo coeficiente de correlação de Pearson. Para todos os testes foi considerado pBACKGROUND: Sarcopenia is the most significant factor in the decline of peripheral and respiratory muscle strength. It can lead to progressive disability, loss of independence and impaired functional capacity. OBJECTIVES: To determine the strength of respiratory muscles (maximal inspiratory pressure - MIP and maximal expiratory pressure - MEP and lower limb muscles, and to explore the possible relationships between these variables and the functional capacity of the elderly. METHODS: Sixty-five elderly patients (71.7±4.9 years old took part in the study. Isokinetic dynamometry was used to assess the knee flexors and extensors, an analog vacuum manometer was used to assess the respiratory muscles, and the six-minute walking test was used as an outcome of functional capacity. The Mann-Whitney test and Student's t-test were used for gender comparison. The relationships were investigated using Pearson's correlation. The significance level was p<0.05. RESULTS: The lower limb and

  16. Estrutura & História.

    Directory of Open Access Journals (Sweden)

    Alicia Ferreira Gonçalves

    2015-06-01

    Full Text Available O presente artigo discorre sobre as ligações entre estrutura e história a partir das perspectivas estruturalista francesa e culturalista norte-americana, focalizando as interlocuções teóricas entre Claude Lévi-Strauss e Marshall Sahlins entre o final dos anos 1940 e ao longo dos anos 1990 do século XX.

  17. Principles of RIA data management

    International Nuclear Information System (INIS)

    Chase, G.D.

    1983-01-01

    The ultimate objective of an RIA is to correlate observed values of radioactivity with observed clinical manifestations that may indicate the existence of a particular disease or metabolic malfunction. To achieve this objective, a two-step process may be considered. First, it is necessary to measure the concentration of a particular chemical entity, the analyte, in the sample presented for analysis. In most cases the analyte is a drug, hormone, or vitamin, or another well-defined chemical substance of known structure and molecular weight. The principal responsibility for measuring the analyte concentration rests with the clinical chemist performing the assay. Second, it is necessary to interpret the assay results in the light of patient history and clinical observations. The principal responsibility for this step lies with the clinician. In this paper, only the first step, the RIA, is considered. Although RIAs in particular are discussed, many of the topics considered apply equally well to radioassays in which the specific binder is not an antibody and to immunoassays in which the tag is not a radioisotope

  18. In-Pile Qualification of the Fast-Neutron-Detection-System

    Directory of Open Access Journals (Sweden)

    Fourmentel D.

    2018-01-01

    FNDS has been validated through a two-step experimental program. A first set of tests was performed at BR2 reactor operated by SCK•CEN in Belgium. Then a second test was recently completed at ISIS reactor operated by CEA in France. FNDS proved its ability to measure online the fast neutron flux with an overall accuracy better than 5%.

  19. IN-PILE INSTRUMENTATION TO SUPPORT FUEL CYCLE RESEARCH AND DEVELOPMENT - FY12 STATUS REPORT

    Energy Technology Data Exchange (ETDEWEB)

    J. . Rempe; J. Daw; D. Knudson; R. Schley

    2012-09-01

    As part of the FCRD program objective to emphasize science-based, goal-oriented research, a strategic research program is underway to develop new sensors that can be used to obtain the high fidelity, real-time, data required for characterizing the performance of new fuels during irradiation testing. The overarching goal of this initiative is to develop new test vehicles with new sensors of unprecedented accuracy and resolution that can obtain the required data. Prior laboratory testing and, as needed, irradiation testing of sensors in these capsules will be completed as part of this initiative to give sufficient confidence that the irradiation tests will yield the required data. This report documents FY12 progress in this initiative.

  20. In vitro antibiotic susceptibilities of ocular bacteria isolates from the cornea and conjunctiva to moxifloxacin, gatifloxacin and other fluoroquinolones Testes de sensibilidade antimicrobiana de bactérias isoladas da córnea e da conjuntiva à moxifloxacina, gatifloxacina e outras fluoroquinolonas

    Directory of Open Access Journals (Sweden)

    Ana Luisa Höfling-Lima

    2004-12-01

    Full Text Available PURPOSE: To assess and compare the in vitro susceptibility of ocular bacterial isolates to fluoroquinolones, including moxifloxacin and gatifloxacin. METHODS: A total of 154 bacterial ocular isolates from keratitis and conjunctivitis were tested for sensitivity to the studied antibiotics, using the disk diffusion method. RESULTS: Of the 51 corneal isolates, 46 (90.2% were sensitive to ciprofloxacin, 45 (88.2% to ofloxacin and 41 (80.4% to lomefloxacin. All corneal isolates were sensitive to moxifloxacin and gatifloxacin. Of the 103 bacterial conjunctival isolates, 101 (98.1% and 103 (100% were sensitive to gatifloxacin and moxifloxacin, respectively. Two strains of Streptococcus sp viridans group were resistant to gatifloxacin. A total of 82 (79.6% specimens were sensitive to lomefloxacin, 89 (86.4% and 96 (93.2% to ciprofloxacin and ofloxacin, respectively. CONCLUSION: Fourth generation fluoroquinolones, herein exemplified by moxifloxacin and gatifloxacin, seem to be more effective than previous generation fluoroquinolones against frequently encountered organisms isolated from patients with bacterial keratitis and conjunctivitis.OBJETIVOS: Conhecer e comparar a susceptibilidade in vitro de bactérias isoladas do olho à fluoroquinolonas, incluindo moxifloxacina e gatifloxacina. MÉTODOS: Um total de 154 bactérias isoladas de ceratites e conjuntivites foram submetidas a testes de sensibilidade antimicrobiana aos antibióticos usando o método de difusão em disco. RESULTADOS: Das 51 bactérias isoladas da córnea, 46 (90,2% foram sensíveis a ciprofloxacina, 45 (88,2% a ofloxacina e 41 (80,4% a lomefloxacina. Todas as bactérias isoladas da córnea foram sensíveis a moxifloxacina e a gatifloxacina. Das 103 bactérias isoladas da conjuntiva 101 (98,1% e 103 (100% foram sensíveis a gatifloxacina e moxifloxacina, respectivamente. Duas cepas de Streptococcus sp do grupo viridans mostraram-se resistentes à gatifloxacina. Um total de 82 (79,6% esp

  1. Design data for the 1/4-in. thick alloy 718 in-pile tube

    International Nuclear Information System (INIS)

    Reuter, W.G.

    1977-05-01

    Design data applicable to the proposed 0.64-cm (1/4-in.) thick inpile tube (IPT) used in the experimental test loop of the Power Burst Facility (PBF) are reported, together with fracture toughness results which were also desired to complement the design data. These data were required for temperatures ranging from room temperature (RT) to 811 K (1000 0 F). Tests were conducted on transverse-oriented specimens for base metal and longitudinal- and transverse-oriented weld metal specimens. Tensile test results from base metal (Heats 3 and 6) and weld metal (Heat C), for test temperatures ranging from RT to 811 K (1000 0 F), were used to develop curves for ultimate and yield tensile strength. The design fatigue curves for transverse-oriented base metal and longitudinal- and transverse-oriented weld metal specimens were developed using the tensile test results plus an analytical approach. Experimental fatigue data were generated to augment the analytically determined values. The design curves for cycles to failure ranging from 10 1 to 10 6 and for temperatures for RT to 811 K (1000 0 F) are contained in this report. Instrumented precracked-Charpy specimens were tested over a range of temperatures to provide some estimate of the dynamic fracture toughness (K/sub Id/). On the basis of these tests, K/sub Id/ values for the base metal and weldments are quite satisfactory

  2. Current and prospective fuel test programmes in the MIR reactor

    Energy Technology Data Exchange (ETDEWEB)

    Izhutov, A.L.; Burukin, A.V.; Iljenko, S.A.; Ovchinnikov, V.A.; Shulimov, V.N.; Smirnov, V.P. [State Scientific Centre of Russia Research Institute of Atomic Reactors, Ulyanovsk region (Russian Federation)

    2007-07-01

    MIR reactor is a heterogeneous thermal reactor with a moderator and a reflector made of metal beryllium, it has a channel-type design and is placed in a water pool. MIR reactor is mainly designed for testing fragments of fuel elements and fuel assemblies (FA) of different nuclear power reactor types under normal (stationary and transient) operating conditions as well as emergency situations. At present six test loop facilities are being operated (2 PWR loops, 2 BWR loops and 2 steam coolant loops). The majority of current fuel tests is conducted for improving and upgrading the Russian PWR fuel, these tests involve issues such as: -) long term tests of short-size rods with different modifications of cladding materials and fuel pellets; -) further irradiation of power plant re-fabricated and full-size fuel rods up to achieving 80 MW*d/kg U; -) experiments with leaking fuel rods at different burnups and under transient conditions; -) continuation of the RAMP type experiments at high burnup of fuel; and -) in-pile tests with simulation of LOCA and RIA type accidents. Testing of the LEU (low enrichment uranium) research reactor fuel is conducted within the framework of the RERTR programme. Upgrading of the gas cooled and steam cooled loop facilities is scheduled for testing the HTGR fuel and sub-critical water-cooled reactor, correspondingly. The present paper describes the major programs of the WWER high burn-up fuel behavior study in the MIR reactor, capabilities of the applied techniques and some results of the performed irradiation tests. (authors)

  3. Determination of triiodothyronine using RIA-Mat T3 kit

    International Nuclear Information System (INIS)

    Hara, Masao

    1975-01-01

    A RIA-Mat T 3 kit was used for an in vitro measurement of triiodothyronine in serum. A resin strip was utilized to absorb free triiodothyronine after the serum was incubated with antibody against triiodothyronine. This test was easy to manipulate and the reproducibility test with same sera, dilution test, and recovery test were also satisfactory. The normal range of triiodothyronine determined with this test kit was 119 +- 40 ng/dl using 50 test sera. Ninety sera with various thyroid diseases were also determined. (auth.)

  4. Urticária Urticaria

    Directory of Open Access Journals (Sweden)

    Paulo Ricardo Criado

    2005-12-01

    Full Text Available A urticária apresenta-se com diversas formas clínicas e causas distintas. Constitui uma das dermatoses mais freqüentes: 15% a 20% da população têm pelo menos um episódio agudo da doença em sua vida, resultando em percentual que varia de um a 2% dos atendimentos nas especialidades de Dermatologia e Alergologia. A urticária é classificada do ponto de vista de duração da evolução temporal em aguda (inferior a seis semanas ou crônica (superior a seis semanas. O tratamento da urticária pode compreender medidas não farmacológicas e intervenções medicamentosas, as quais são agrupadas em tratamentos de primeira (anti-histamínicos, segunda (corticosteróides e antileucotrienos e terceira linha (medicamentos imunomoduladores. As medidas terapêuticas de segunda e terceira linha apresentam maiores efeitos adversos, devendo ser reservadas aos doentes que não apresentaram controle da doença com os de primeira linha, ou àqueles a respeito dos quais não é possível estabelecer uma etiologia, tal como nas urticárias auto-imunes.Urticaria has diverse clinical presentations and causes. It is one of the most frequent dermatological conditions: 15% to 20% of population has at least one acute eruption during their lifetime, resulting in 1% to 2% of dermatological and allergological visits. Urticaria is classified based on its temporal evolution as acute (less than 6 weeks or chronic (more than 6 weeks. Management strategies may involve non-pharmacological measures and drug interventions, which are grouped into first- (antihistamines, second- (corticosteroids and anti-leukotrienes and third-line therapies (immunomodulators. Stronger, but potentially riskier, second- and third-line management may be justified for patients who do not respond to first-line therapy, or whenever a specific etiology cannot be determined, such as in autoimmune urticaria.

  5. Parametric analysis of LIBRETTO-4 and 5 in-pile tritium transport model on EcosimPro

    Energy Technology Data Exchange (ETDEWEB)

    Alcalde, Pablo Martínez, E-mail: pablomiguel.martinez@externos.ciemat.es [Universidad Nacional de Educación a Distancia (UNED), c/Juan del Rosal 12, 28040 Madrid (Spain); Moreno, Carlos; Ibarra, Ángel [CIEMAT, Avda. Complutense 40, 28040 Madrid (Spain)

    2014-10-15

    Highlights: • Introduction of a new tritium transport model of LIBRETTO-4 and 5 on EcosimPro{sup ®}. • Analysis of model input parameter and variable sensitivities and effects on tritium simulated fluxes. • Demonstrations of high tritium out-flux dependencies on lead-lithium parameters. • Rough fitting achievements proposed by Li17Pb solubility or recombination increase. - Abstract: A new model for LIBRETTO-4/1, 4/2 and 5 experiments have been developed on ECOSIMPro{sup ©} tool to simulate tritium in-pile breeding and transport into two separate purge gas channels with He + 0.1%H{sub 2}. Release from lead lithium eutectic plenum with coupled permeation through an austenitic steel wall on the first and single permeation through EUROFER-97 in the temperature ranges of 300–550 °C can be simulated tuning the transport parameters involved. A parametric study has been performed to reduce the degrees of freedom and to determine the error caused in the simulation due to the uncertainty in experimental input data. The information obtained is essential for the experimental benchmarking. The Tritium Permeation Percentage (TPP) is an output calculated parameter with low variations between 2 and 6% along the whole experimental time easy to compare (730 Full Power Days for LIBRETTO-4 and 520 for 5). Tritium transport parameter ranges verifying this output are defined herein.

  6. Some aspects of in-pile swelling of fissile materials, 1. part: non-alloyed α uranium

    International Nuclear Information System (INIS)

    Mikailoff, H.

    1964-01-01

    An examination has been carried out of non-alloyed uranium samples, having various structural states, cold-worked and recrystallized, as-cast and β-treated, and irradiated at temperatures of between 450 and 600 C and with burn-ups from 1300 to 5500 MW days/metric ton. These samples swelled because of precipitation of the fission gases the porosity thus produced has a morphology depending mainly on the type of deformation to which the metal has been subjected and which is due to in-pile growth. The most homogeneous distribution of pores, and thus that leading to the minimum swelling, is only observed in the material having a marked [010] texture in which the growth and perhaps the thermal cycling introduce little or no strain. For other materials the deformation /swelling association causes a more rapid destruction of the samples either by cracking when the deformation is due to twinning, or by pronounced swelling localized in the bands when deformation is due to slipping. Finally the fission-gas precipitation considerably facilitates, above 500 C, the germination and growth of the intergranular cracks which can then develop at low stresses. (author) [fr

  7. Analysis of ULOF accident in Monju reflecting the knowledge from CABRI in-pile experiments and others

    International Nuclear Information System (INIS)

    Sato, Ikken; Tobita, Yoshiharu; Suzuki, Tohru; Kawada, Ken-ichi; Fukano, Yoshitaka; Fujita, Satoshi; Kamiyama, Kenji; Ishikawa, Makoto; Nonaka, Nobuyuki; Usami, Shin

    2007-05-01

    In the safety evaluation in the original licensing procedure of the prototype FBR Monju, mechanical energy release during an unprotected loss-of-flow (ULOF) event, one of technically inconceivable events postulated beyond design basis, was evaluated and shown that the radiological consequence is suitably limited. Since the sodium leakage accident in the secondary heat-transport system, the Monju plant has been kept under the stand-by condition for more than ten years and the composition of fuel in the current reactor core has changed due to decay of a plutonium isotope into americium. This change in fuel composition affects the neutronic characteristics of the core, requiring assessment of its effect on safety. In this study, event sequences of ULOF were analyzed to assess the effect of the change in neutronic characteristics on the mechanical energy release during ULOF. A significant advance has been made in the safety analysis codes reflecting the knowledge obtained through extensive safety research programs in the last decades, notably the CABRI in-pile experiments. The present results with the advanced analysis codes showed that the mechanical energy release in the current Monju core with the changed neutronic characteristics would not exceed the value evaluated formerly. (author)

  8. Risk analysis for a radiolysis gas detonation in an in-pile loop with supercritical water

    International Nuclear Information System (INIS)

    Zeiger, T.; Raque, M.; Kuznetsov, M.; Redlinger, R.; Schulenberg, T.

    2012-01-01

    The SCWR (supercritical water reactor) -FQT project is a cooperation between European and Chinese partners aimed to test the fuel SCWR elements under reactor conditions. In the frame of this work the risk of radiolysis gas production in the active range of the test track was assessed. The radiolysis gas could accumulate in an emergency cooling system with stagnating coolant. The ignition of this radiolysis gas could cause pressure peaks that are able to damage the primary coolant circuit. Pressure increase and deformations in case of ignition of accumulated gas were investigated. As piping material the Ti stabilized austenitic steel 08Ch18N10T was assumed, the simulation was performed using the ANSYS code. The results show that pipes without significant wall thickness enhancement cannot withstand the radiolysis gas detonation.

  9. RIA Quick, AUSRIA II-125, AUSAB. Comparative study on isolated and simultaneous radioimmunoassay of hepatitis B surface antigen and antibodies

    Energy Technology Data Exchange (ETDEWEB)

    Kselikova, M; Urbankova, J [Institut fuer Haematologie und Bluttransfusion, Prag (Czechoslovakia)

    1983-01-01

    The surface antigen of hepatitis B (HBsAg) and the antibodies against HBsAg can be determined separately by the radioimmunoassay (RIA) test kits AUSRIA II-125 and AUSAB, respectively. Using the test kit RIA Quick (IMMUNO, Wien) it is possible to perform both the determinations in one preparation simultaneously. The sensitivity of RIA Quick for HBsAg corresponds to that of AUSRIA II-125 and for HBsAB it is considerably lower than that of AUSAB. RIA Quick is of excellent technical design and is by a quarter cheaper than the kits for isolated determination of HBsAg and HBsAb.

  10. In vitro screening of Amazonian plants for hemolytic activity and inhibition of platelet aggregation in human blood Testes in vitro de plantas Amazônicas para atividade hemolítica e inibição da agregação plaquetária em sangue humano

    Directory of Open Access Journals (Sweden)

    Viviana Maria Araújo de Oliveira

    2009-01-01

    Full Text Available In the present study, different aerial parts from twelve Amazonian plant species found in the National Institute for Amazon Research's (INPA's Adolpho Ducke Forest Reserve (in Manaus, Amazonas, Brazil were collected. Separate portions of dried, ground plant materials were extracted with water (by infusion, methanol and chloroform (by continuous liquid-solid extraction and solvents were removed first by rotary evaporation, and finally by freeze-drying which yielded a total of seventy-one freeze-dried extracts for evaluation. These extracts were evaluated initially at concentrations of 500 and 100 µg/mL for in vitro hemolytic activity and in vitro inhibition of platelet aggregation in human blood, respectively. Sixteen extracts (23 % of all extracts tested, 42 % of all plant species, representing the following plants: Chaunochiton kappleri (Olacaceae, Diclinanona calycina (Annonaceae, Paypayrola grandiflora (Violaceae, Pleurisanthes parviflora (Icacinaceae, Sarcaulus brasiliensis (Sapotaceae, exhibited significant inhibitory activity towards human platelet aggregation. A group of extracts with antiplatelet aggregation activity having no in vitro hemolytic activity has therefore been identified. Three extracts (4 %, all derived from Elaeoluma nuda (Sapotaceae, exhibited hemolytic activity. None of the plant species in this study has known use in traditional medicine. So, these data serve as a baseline or minimum of antiplatelet and hemolytic activities (and potential usefulness of non-medicinal plants from the Amazon forest. Finally, in general, these are the first data on hemolytic and inhibitory activity on platelet aggregation for the genera which these plant species represent.No presente estudo, partes aéreas obtidas de doze (12 espécies vegetais da Amazônia encontradas na Reserva Florestal Adolpho Ducke (localizada na cidade de Manaus, Estado do Amazonas, Brasil do Instituto Nacional de Pesquisas da Amazônia foram coletadas, secadas e mo

  11. Use of Kalman filter methods in analysis of in-pile LMFBR accident simulations

    International Nuclear Information System (INIS)

    Meek, C.C.; Doerner, R.C.

    1983-01-01

    Kalman filter methodology has been applied to inpile liquid-metal fast breeder reactor simulation experiments to obtain estimates of the fuel-clad thermal gap conductance. A transient lumped parameter model of the experiment is developed. An optimal estimate of the state vector chosen to characterize the experiment is obtained through the use of the Kalman filter. From this estimate, the fuel-clad thermal gap conductance is calculated as a function of time into the test and axial position along the length of the fuel pin

  12. Summarizing evaluation of the results of in-pile experiments for the transient fission gas release under accidental conditions of fast breeders

    International Nuclear Information System (INIS)

    Fischer, E.A.; Vaeth, L.

    1989-04-01

    The transient fission gas behaviour and the fission gas induced fuel motion were studied in in-pile experiments in different countries, under conditions typical for hypothetical accidents. This report summarizes first the different experiment series and the main results. Then, a comparative evaluation is given, which provides a basis for the choice of the fission gas parameters in the accident code SAS3D

  13. Thermal annealing behaviour of sulphur-35 produced in pile-irradiated mixed crystals AlCl/sub 3/-FeCl/sub 3/

    Energy Technology Data Exchange (ETDEWEB)

    Dyakovich, V; Todorovski, D S; Kostadinova, Z D [Sofia Univ. (Bulgaria). Khimicheski Fakultet

    1983-12-19

    The regression analysis of the experimental results on the thermal annealing behaviour of /sup 35/S produced in pile-irradiated mixed crystals AlCl/sub 3/-FeCl/sub 3/ confirms some suppositions made in a previous paper. The chemical state of /sup 35/S is defined by the target prehistory and the iron concentration. The influence of Fe/sup 3 +/ can be observed indirectly through its influence on the defect structure formed.

  14. Test Pile Reactivity Loss Due to Trichloroethylene

    International Nuclear Information System (INIS)

    Plumlee, K.E.

    2001-01-01

    The presence of trichloroethylene in the test pile caused a continual decrease in pile reactivity. A system which removed, purified, and returned 12,000 cfh helium to the pile has held contamination to a negligible level and has permitted normal pile operation

  15. Matéria atrai matéria... e a antimatéria?

    OpenAIRE

    Chalub, Fabio Augusto da Costa Carvalho

    2016-01-01

    A lei da Gravidade de Newton afirma que duas partículas se atraem, sobre a linha que as une, com uma força proporcional ao produto das massas e inversamente proporcional ao quadrado da distância. Mas o que aconteceria se tivéssemos partículas de massa negativa? Será possível que tenhamos por aí partículas que se repelem? Será a antimatéria uma candidata a sentir a força antigravitacional? Uma nova pesquisa lança luz nestes antigos mistérios. publishersversion published

  16. Efeitos da rottlerin na esquizogonia eritrocitária de Plasmodium falciparum e implementação e avaliação de teste in vitro por fluorescência de atividade antiplasmodial

    OpenAIRE

    Cordeiro, Thuany de Moura

    2014-01-01

    A malária é uma doença infecciosa causada por protozoários Plasmodium spp. O P. falciparum é considerado o mais severo por ser o responsável pela maioria dos casos de morte causados pela doença. Devido ao rápido surgimento de cepas de P. falciparum resistentes às drogas antimalariais dá-se a importância de realizar um screening de compostos da biodiversidade, além de elucidar os mecanismos de ação de substâncias com comprovada ação antiplasmodial, como por exemplo, a rottlerin, um inibidor da...

  17. In-pile loop studies of the effect of PWR coolant pH on corrosion product radionuclide deposition

    International Nuclear Information System (INIS)

    Driscoll, M.J.; Harling, O.K.; Kohse, G.E.

    1992-02-01

    An in-pile loop which simulates the primary coolant system of a PWR has been constructed and operated in the MIT research reactor. A total of seven one-month-long irradiations have been carried out to evaluate the effect of coolant pH controlled by variation in LiOH/H 3 BO 3 concentrations. With the exception of one run at zero boron, all employed 800 ppm B; pH 300degreesC values of 6.5, 7.0, 7.2, 7.5 were studied, and two runs each at 7.0 and 7.2 were carried out. Finally, one of the runs at a pH 300degreesC of 7.2 was conducted with special care to exclude zinc because of its potential effects on cobalt deposition. The results show the expected benefits of high pH in reducing the rate of activity deposition on plant surfaces, but pH 300degreesC = 7.2 is approximately as effective as 7.5, while pH 300degreesC = 6.5 exhibits much larger activity transport and qualitatively different deposition behavior. Significant heat flux effects not predicted by current models have been consistently observed. While not as extensively studied, the zero-boron run suggests that the presence of boron species, at fixed pH, may reduce the net amount of activity deposited on ex-core surfaces. Neutron activation analysis of a variety of samples ruled out Zircaloy as an important source of Co-60, since its cobalt content is less than one ppm, considerably less than the applicable ASTM specification of ≤ 20 ppm. Amendment of the latter has been recommended

  18. RER conception and it's application in RIA quality assessment

    International Nuclear Information System (INIS)

    Wu Defu

    1998-01-01

    The history, developing and applications in analysing of RIA random error are discussed. Some function expressions of RIA quality parameters are established. It supply the effective mathematic methods for the theory analysis of RIA error and the normalized quality control

  19. DeBeNe Test Facilities for Fast Breeder Development

    International Nuclear Information System (INIS)

    Storz, R.

    1980-10-01

    This report gives an overview and a short description of the test facilities constructed and operated within the collaboration for fast breeder development in Germany, Belgium and the Netherlands. The facilities are grouped into Sodium Loops (Large Facilities and Laboratory Loops), Special Equipment including Hot Cells and Reprocessing, Test Facilities without Sodium, Zero Power Facilities and In-pile Loops including Irradiation Facilities

  20. Estudo das habilidades de memória e raciocínio simbólico e não-simbólico de crianças e adolescentes surdas por meio da bateria padrão do Universal Nonverbal Intelligence Test Study of memory and symbolic and non-symbolic reasoning skills of deaf children and adolescents using standard battery of Universal Nonverbal Intelligence Test

    Directory of Open Access Journals (Sweden)

    Cláudia Furtado Borges

    2010-04-01

    Full Text Available Este estudo explorou as habilidades de memória e raciocínio simbólico e não simbólico de crianças e adolescentes com deficiência auditiva através das análises de desempenho da Bateria Padrão do Universal Nonverbal Intelligence Test (UNIT. Participaram deste estudo 55 crianças e adolescentes surdos. Os dados coletados foram analisados através de análises paramétricas. Os dados mostram que a memória simbólica, a capacidade de manipular e representar a informação simbólica memorizada está sendo melhorada por atividades escolares e/ou extracurriculares.This study aimed to explore memory and symbolic and non symbolic reasoning skills of deaf children and adolescents using the analyses of performance of the standard battery of Universal Nonverbal Intelligence Test (UNIT. Fifty five participants took part in the study. The collected data were analyzed through parametric statistics. The data suggest that the capacity to manipulate and to represent memorized symbolic information may be enhanced by school and/or extracurricular activities.

  1. New facilities in Japan materials testing reactor for irradiation test of fusion reactor components

    International Nuclear Information System (INIS)

    Kawamura, H.; Sagawa, H.; Ishitsuka, E.; Sakamoto, N.; Niiho, T.

    1996-01-01

    The testing and evaluation of fusion reactor components, i.e. blanket, plasma facing components (divertor, etc.) and vacuum vessel with neutron irradiation is required for the design of fusion reactor components. Therefore, four new test facilities were developed in the Japan Materials Testing Reactor: an in-pile functional testing facility, a neutron multiplication test facility, an electron beam facility, and a re-weldability facility. The paper describes these facilities

  2. Equações de predição da aptidão cardiorrespiratória sem testes de exercício e sua aplicabilidade em estudos epidemiológicos: uma revisão sistemática Prediction of aerobic fitness without stress testing and applicability to epidemiological studies: a systematic review

    Directory of Open Access Journals (Sweden)

    Geraldo de Albuquerque Maranhão Neto

    2004-02-01

    Full Text Available Uma baixa aptidão cardiorrespiratória é considerada fator de risco independente para o óbito por todas as causas, mas principalmente por doença coronariana. Devido a essa importância e à dificuldade de avaliá-la por meio de testes de exercícios, formas alternativas de avaliação foram sugeridas, envolvendo equações de predição sem a necessidade de realização de exercícios. O presente estudo objetivou analisar criticamente esses modelos e, principalmente, sua aplicabilidade em estudos epidemiológicos. Foi realizada uma revisão de artigos publicados entre 1966 e 2002. Os critérios para julgar a qualidade dos estudos foram: (a inclusão de variáveis explicativas com base teórica; (b critérios de validação (padrão-ouro; (c equações apresentadas por completo, incluindo erro padrão da estimativa; (d equações submetidas a processo de validação cruzada. Apenas cinco dos 23 estudos selecionados atenderam a todos os critérios de qualidade. Conclui-se que, em princípio, os modelos sem exercícios podem constituir alternativa viável para avaliação da aptidão cardiorrespiratória em estudos epidemiológicos. No entanto, ainda são poucas as equações disponíveis cuja validação permite grau aceitável de generalização.Cardiorespiratory fitness is used as an independent factor for evaluating risk of all-cause mortality, but mainly from coronary heart disease. Nevertheless, evaluation of fitness based on stress tests poses numerous epidemiological difficulties. Alternative forms of evaluation have therefore been suggested using non-exercise-based regression models. This study aimed to analyze these models and their applicability to epidemiological studies. A systematic review was conducted of articles published from 1966 to 2002. The models were classified according to: (a theoretical justification for the explanatory variables included in the model; (b validation criteria (gold standard; (c regression models fully

  3. Comparative study of the enzyme linked immunosorbent assay (ELISA) and two radioimmunoassays (RIA'S) for in-sulin

    Energy Technology Data Exchange (ETDEWEB)

    Klimes, I; Jurcovicova, J; Palkovic, M [Slovenska Akademia Vied, Bratislava (Czechoslovakia). Ustav Experimentalnej Endokrinologie

    1978-06-30

    The results of the quality control tests for enzyme linked immunosorbent assay (ELISA) were compared with the results of two different radioimmunoassays (RIA'S) for insulin. Using the manufacturer's procedure for the ELISA kit we found that the analytical variables such as assay sensitivity, recovery study and the 50% binding intercept were in good agreement with those obtained with the RIA method.

  4. Leituras de operárias

    Directory of Open Access Journals (Sweden)

    Betty Mindlin

    2008-03-01

    Full Text Available Defensora de causas sociais, paladina poética contra injustiças e desigualdade, Ecléa Bosi em seu livro Cultura Popular e Cultura de Massa: Leituras de Operárias, pesquisa as leituras de cerca de 50 operárias, procurando ver que acesso têm ao imaginário, aos livros, quais as suas condições de vida, como a sociedade industrial as privam da criação artística e literária, apesar de sua sede de conhecimento e de expressão.

  5. Astrophysics at RIA (ARIA) Working Group

    International Nuclear Information System (INIS)

    Smith, Michael S.; Schatz, Hendrik; Timmes, Frank X.; Wiescher, Michael; Greife, Uwe

    2006-01-01

    The Astrophysics at RIA (ARIA) Working Group has been established to develop and promote the nuclear astrophysics research anticipated at the Rare Isotope Accelerator (RIA). RIA is a proposed next-generation nuclear science facility in the U.S. that will enable significant progress in studies of core collapse supernovae, thermonuclear supernovae, X-ray bursts, novae, and other astrophysical sites. Many of the topics addressed by the Working Group are relevant for the RIKEN RI Beam Factory, the planned GSI-Fair facility, and other advanced radioactive beam facilities

  6. 2003 RIA R AND D WORKSHOP.

    Energy Technology Data Exchange (ETDEWEB)

    OZAKI, S.ET AL.

    2003-08-26

    The 2003 RIA R&D Workshop was held on August 26-28, 2003 at the Four Points Sheraton Hotel in Bethesda, Maryland. This Workshop was chaired by Satoshi Ozaki of BNL and sponsored by the Nuclear Physics Division of DOE, with the help of Oak Ridge Institute for Science and Education (ORISE). The purpose of this workshop was to understand the present status of R&D efforts for RIA, to evaluate the needs for further R&D, and to identify opportunities for international collaborations. The workshop examined and documented the current pre-conceptual design for RIA, identifying areas where decisions on technical options remain. The status of the current RIA R&D program was documented, recognizing areas where efforts were needed in light of what had been learned. The ongoing and planned R&D activities for operating and planned rare-isotope facilities were presented, enabling the workshop to be a venue to develop coordinated R&D efforts of mutual benefit to U.S. and international efforts. The scientific program for the first day (August 26, 2003) consisted mostly of invited talks presented by major research groups involved in RIA and other RI beam facilities. The talks included those covering: Science of RIA and the RIA Facility Performance Requirements; The Reference RIA Facility Pre-CDR design that was used for the NSAC cost exercise (M. Harrison Sub-Panel) in January 2001; New or latest perspectives on the RIA design at ANL & MSU; and RI Beam facility plans and overview of the R&D activities at overseas laboratories. The second day (August 27, 2003) was devoted to contributed talks on continuing R&D, including that which had been supported by DOE RIA R&D funds. The third day (August 28, 2003) began with open panel discussions in the morning, including further input from participants. The panel members discussed the present status of the RIA planning and R&D needs in a closed session for the rest of the day, and then worked on report planning and writing. This Workshop

  7. 2003 RIA R AND D WORKSHOP

    International Nuclear Information System (INIS)

    OZAKI, S.

    2003-01-01

    The 2003 RIA R and D Workshop was held on August 26-28, 2003 at the Four Points Sheraton Hotel in Bethesda, Maryland. This Workshop was chaired by Satoshi Ozaki of BNL and sponsored by the Nuclear Physics Division of DOE, with the help of Oak Ridge Institute for Science and Education (ORISE). The purpose of this workshop was to understand the present status of R and D efforts for RIA, to evaluate the needs for further R and D, and to identify opportunities for international collaborations. The workshop examined and documented the current pre-conceptual design for RIA, identifying areas where decisions on technical options remain. The status of the current RIA R and D program was documented, recognizing areas where efforts were needed in light of what had been learned. The ongoing and planned R and D activities for operating and planned rare-isotope facilities were presented, enabling the workshop to be a venue to develop coordinated R and D efforts of mutual benefit to U.S. and international efforts. The scientific program for the first day (August 26, 2003) consisted mostly of invited talks presented by major research groups involved in RIA and other RI beam facilities. The talks included those covering: Science of RIA and the RIA Facility Performance Requirements; The Reference RIA Facility Pre-CDR design that was used for the NSAC cost exercise (M. Harrison Sub-Panel) in January 2001; New or latest perspectives on the RIA design at ANL and MSU; and RI Beam facility plans and overview of the R and D activities at overseas laboratories. The second day (August 27, 2003) was devoted to contributed talks on continuing R and D, including that which had been supported by DOE RIA R and D funds. The third day (August 28, 2003) began with open panel discussions in the morning, including further input from participants. The panel members discussed the present status of the RIA planning and R and D needs in a closed session for the rest of the day, and then worked on report

  8. Results of applications of DISKOT system and of RIA determination of progesterone

    International Nuclear Information System (INIS)

    Beranek, J.

    1989-01-01

    Milk for progesterone determination was taken from cows picked out for insemination, cows following insemination and cows with reproduction disorders. The samples were taken in test tubes containing potassium dichromate. Progesterone was determined by RIA of skimmed milk and the results were transmitted to the DISKOT system in the data processing centre. The use of the DISKOT system output and the monitoring of progesterone in milk by the RIA laboratory improved reproduction indexes of the herd under study. (E.J.). 2 tabs

  9. Part 1: Logging residues in piles - Needle loss and fuel quality. Part 2: Nitrogen leaching under piles of logging residues

    International Nuclear Information System (INIS)

    Lehtikangas, P.; Lundkvist, H.

    1991-01-01

    Part 1: Experimental piles were built in three geographical locations during May-Sept. 1989. Logging residues consisted of 95% spruce and 5% pine. Height of the piles varied between 80 and 230 cm. Needles were collected by placing drawers under 40 randomely chosen piles. The drawers were emptied every two weeks during the storage period. Natural needle loss was between 18 and 32% of the total amount of needles after the first two months of storage. At the end of the storage period, 24-42% of the needles had fallen down to the drawers. At the end of the experiment the total needle fall was 95-100% in the shaken piles. According to the results of this study piles smaller than 150 cm had the most effective needle fall. Piles should be placed on open places where the air and sun heat penetrate and dry them. Needles were the most sensitive fraction to variations in precipitation compared to the other components, such as branches. Piles usually dried quickly, but they also rewet easily. This was especially true in the smaller piles. The lowest moisture content was measured at the end of June. The ash content in needles varied between 4 and 8%. 16 refs., 15 figs. Part 2: Three field experiments were equipped with no-tension humus lysimeters. Pairs of lysimeters with the same humus/field layer vegetation material were placed in pairs, one under a pile of felling residues and another in the open clear felling. Leaching of nitrogen as well as pH and electric conductivity in the leachate was followed through sampling of the leachate at regular intervals. The results from the investigation show that: * the amount of leachate was higher in lysimeters in the open clear felling, * pH in the leachate was initially lower under piles of felling residues, * the amount of nitrogen leached was higher in the open clear felling. Thus, storing of felling residues in piles during the summer season did not cause any increase in nitrogen leaching, which had been considered to be a risk

  10. Thermal conductivity of sintered UO{sub 2} under in-pile conditions; Conductibilite thermique de l'UO{sub 2} fritte dans les conditions d'utilisation en pile

    Energy Technology Data Exchange (ETDEWEB)

    Stora, J P; Bernardy De Sigoyer, B; Delmas, R; Deschamps, P; Lavaud, B; Ringot, C [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

    1964-07-01

    The temperature distribution in a stack of sintered UO{sub 2} cylinders has been studied both in the laboratory where the heat energy is produced by an axial heating element, and in-pile, where the heating is due solely to nuclear effects. Under a high thermal gradient the UO{sub 2} cracks both along radial planes and along pseudo-cylindrical surfaces: these latter act as thermal barriers to the heat flow, It is therefore an apparent thermal conductivity k{sub a}(T), lower than the intrinsic value k(T) of this parameter which is measured. The efficiency of these barriers decreases when the gap decreases and when the external pressure acting on the cracked stack increases: in the limiting case, for high values of the binding strain, k{sub a}(T) {approx_equal} k(T). In the domain of phonon conduction (T {<=} 1350 deg C), the expression kw.cm{sup -1}.C{sup -1}=1/(11+0.024*T) accounts for the real thermal conductivity. Above 1350 deg C the thermal conductivity increases. Two in-pile measurements up to 1250 deg C carried out using cartridges fitted with thermocouples confirm, within the limits of experimental error, the above expression and the qualitative effects of the binding strains. Similar tests have been carried out-of-pile and in-pile on the real shape of the EL-4 fuel 'pencils'. Out-of-pile, the influence of the initial free gap, of the nature of the gas filing the 'pencil' and of the external pressure have been studied; the results are compatible with the above interpretation; It appears that an external pressure of 60 kg/cm{sup 2} is insufficient to restore completely the thermal conductivity of the fuel. (authors) [French] La distribution de temperature dans un empilement de cylindres d'UO{sub 2} fritte est etudiee a la fois au laboratoire, ou l'energie calorifique est produite par un element chauffant axial, et en pile, ou l'echauffement est uniquement nucleaire. Sous gradient thermique eleve, l'UO{sub 2} se fracture a la fois suivant des plans radiaux et

  11. Colorimetric test for the monitoring of microcystins in cyanobacterial culture and environmental samples from southeast - Brazil Teste colorimétrico usado para o monitoramento de microcistina em cultivo de cianobactérias e em amostras de florações ambientais do sudeste do Brasil

    Directory of Open Access Journals (Sweden)

    Vanessa P.S. Almeida

    2006-06-01

    Full Text Available Microcystins are hepatotoxic heptapeptides produced by some cyanobacterial genera under determined physico-chemical conditions in the environment, which are responsible for the intoxication and death of animals and humans. The detection of microcystins in potable water or recreational water is not carried out routinely in the majority of Brazilian states. The protein phosphatase 1 (PP1 inhibition test is a simple, rapid and reproducible colorimetric method. The applicability of the PP1 inhibition test was tested using Microcystis aeruginosa (strain 1, UFRJ- toxin producer grown under controlled light and temperature condition (12/12h light/dark using 30 muE.m².s-1 at 23ºC in a bioreactor. The total concentrations of P (24, 6 and 4 muM and Fe (4 and 1 muM were varied in ASM-1medium and their effects on the growth rates and toxin production were analyzed. A standard curve of PP1 inhibition by microcystin-LR reached detection limit of 0.01 ng.mL-1. Under the highest concentrations of P (24 muM and Fe (4 muM, the production of microcystin was detected throughout the growth experiment. The highest concentration of microcystin was observed at 6 muM P while at 1 muM Fe, PP1 inhibition was not detected. Samples from environmental blooms in water reservoirs used for human and animal consumption, from southeast Brazil (Belo Horizonte/MG, were tested and quantified for microcystin presence by the PP1 colorimetric test. The concentration of microcystin varied from undetectable to 100 ng.mL-1 in the environmental samples with Microcistis flos-aquae as the predominant cyanobacterial strain.Microcistinas (MC são heptapeptídeos de ação neuro e hepatotóxica produzidas por alguns gêneros de cianobactérias em determinadas condições físico-químicas do ambiente e são responsáveis pela morte e intoxicação de animais e humanos. A detecção de MC em água destinada ao consumo no Brasil ainda não é realizada na maioria dos estados brasileiros. O

  12. A review of experiments and computer analyses on RIAs

    International Nuclear Information System (INIS)

    Jernkvist, L.O.; Massih, A.R.; In de Betou, J.

    2010-01-01

    Reactivity initiated accidents (RIAs) are nuclear reactor accidents that involve an unwanted increase in fission rate and reactor power. Reactivity initiated accidents in power reactors may occur as a result of reactor control system failures, control element ejections or events caused by rapid changes in temperature or pressure of the coolant/moderator. our current understanding of reactivity initiated accidents and their consequences is based largely on three sources of information: 1) best-estimate computer analyses of the reactor response to postulated accident scenarios, 2) pulse-irradiation tests on instrumented fuel rodlets, carried out in research reactors, 3) out-of-pile separate effect tests, targeted to explore key phenomena under RIA conditions. In recent years, we have reviewed, compiled and analysed these 3 categories of data. The results is a state-of-the-art report on fuel behaviour under RIA conditions, which is currently being published by the OECD Nuclear Energy Agency. The purpose of this paper is to give a brief summary of this report

  13. Modeling RIA scenarios with the FRAPTRAN and SCANAIR codes

    International Nuclear Information System (INIS)

    Sagrado Garcia, I. C.; Vallejo, I.; Herranz, L. E.

    2013-01-01

    The need of defining new RIA safety criteria has pointed out the importance of performing a rigorous assessment of the transient codes capabilities. The present work is a comparative exercise devoted to identify the origin of the key deviations found between the predictions of FRAPTRAN-1.4 and SCANAIR-7.1. To do so, the calculations submitted by CIEMAT to the OECD/NEA RIA benchmark have been exploited. This work shows that deviations in clad temperatures mainly come from the treatment of the oxide layer. The systematically higher deformations calculated by FRAPTRAN-1.4 in early failed tests are caused by the different gap closure estimation. Besides, the dissimilarities observed in the FGR predictions are inherent to the different modeling strategies adopted in each code.

  14. Modeling RIA scenarios with the FRAPTRAN and SCANAIR codes

    Energy Technology Data Exchange (ETDEWEB)

    Sagrado Garcia, I. C.; Vallejo, I.; Herranz, L. E.

    2013-07-01

    The need of defining new RIA safety criteria has pointed out the importance of performing a rigorous assessment of the transient codes capabilities. The present work is a comparative exercise devoted to identify the origin of the key deviations found between the predictions of FRAPTRAN-1.4 and SCANAIR-7.1. To do so, the calculations submitted by CIEMAT to the OECD/NEA RIA benchmark have been exploited. This work shows that deviations in clad temperatures mainly come from the treatment of the oxide layer. The systematically higher deformations calculated by FRAPTRAN-1.4 in early failed tests are caused by the different gap closure estimation. Besides, the dissimilarities observed in the FGR predictions are inherent to the different modeling strategies adopted in each code.

  15. Determination of serum digosin. A comparison between RIA and EIA

    Energy Technology Data Exchange (ETDEWEB)

    Spitz, J; Braun, J S; Schmidt, M [Krankenhausstiftung Bamberg (Germany, F.R.). Nuklearmedizinische Abt.; Abt fuer Labormedizin, Krankenhausstiftung Bamberg [Germany, F.R.

    1979-12-01

    The results of two radioimmunoassays (RIA, precipitating technique), of a homogenous (EMIT) and a heterogenous (ELISA) enzyme immunoassay (EIA) for ascertaining the amounts of digoxin showed a good correlation in precision and a reasonably AK satisfying correlation in the recovery. However, there was a clear discrepancy in the amounts of digoxin concentrate in the serum of patients. Only the RIA of Abbott and the EIA of Boehringer showed no significant differences. Particularly noticeable was the tendency towards lower values in the EMIT-technique as well as its liability to unspecific serum changes (lipaemia etc.), which often made the detection of digoxin impossible. The routine use of this technique appears problematic. The need for establishing one's own laboratory and test-specific therapeutical range is pointed out.

  16. Determination of serum digosin. A comparison between RIA and EIA

    International Nuclear Information System (INIS)

    Spitz, J.; Braun, J.S.; Schmidt, M.; Krankenhausstiftung Bamberg

    1979-01-01

    The results of two radioimmunoassays (RIA, precipitating technique), of a homogenous (EMIT) and a heterogenous (ELISA) enzyme immunoassay (EIA) for ascertaining the amounts of digoxin showed a good correlation in precision and a reasonably AK satisfying correlation in the recovery. However, there was a clear discrepancy in the amounts of digoxin concentrate in the serum of patients. Only the RIA of Abbott and the EIA of Boehringer showed no significant differences. Particularly noticeable was the tendency towards lower values in the EMIT-technique as well as its liability to unspecific serum changes (lipaemia etc.), which often made the detection of digoxin impossible. The routine use of this technique appears problematic. The need for establishing one's own laboratory and test-specific therapeutical range is pointed out. (orig.) [de

  17. Advanced instrumentation and analysis methods for in-pile thermal and nuclear measurements: from out-of-pile studies to irradiation campaigns

    International Nuclear Information System (INIS)

    Reynard-Carette, C.; Lyoussi, A.

    2015-01-01

    Research and development on nuclear fuel behavior under irradiations and accelerated ageing of structure materials is a key issue for sustainable nuclear energy in order to meet specific needs by keeping the best level of safety. A new Material Testing Reactor (MTR), the Jules Horowitz Reactor (JHR) currently under construction in the South of France in the CEA Cadarache research centre will offer a real opportunity to perform R and D programs and hence will crucially contribute to the selection, optimization and qualification of innovative materials and fuels. To perform such programs advanced accurate and innovative experiments, irradiation devices that contain material and fuel samples are required to be set up inside or beside the reactor core. These experiments needs beforehand in situ and on line sophisticated measurements to accurately reach specific and determining parameters such as thermal and fast neutron fluxes, nuclear heating and temperature conditions to precisely monitor and control the conducted assays. Consequently, since 2009 CEA and Aix-Marseille University collaborate in order to design and develop a new multi-sensor device which will be dedicated to measuring profiles of such conditions inside the experimental channels of the JHR. These works are performed in the framework of two complementary joint research programs called MAHRI-BETHY and INCORE. These programs couple experimental studies carried out both out-of nuclear fluxes (in laboratory) and under irradiation conditions (in OSIRIS MTR reactor in France and MARIA MTR reactor in Poland) with numerical works realized by thermal simulations (CAST3M code) and Monte Carlo simulations (MCNP code). These programs deal with three main aims. The first one corresponds to the design and/or the test of new in-pile instrumentation. The second one concerns the development of advanced calibration procedures in particular in the case of one specific sensor: a differential calorimeter used to quantify

  18. Advanced instrumentation and analysis methods for in-pile thermal and nuclear measurements: from out-of-pile studies to irradiation campaigns

    Energy Technology Data Exchange (ETDEWEB)

    Reynard-Carette, C. [Aix Marseille Universite, CNRS, Universite de Toulon, IM2NP UMR 7334, 13397, Marseille (France); Lyoussi, A. [CEA, DEN, DER, Instrumentation Sensors and Dosimetry Laboratory, Cadarache, F-13108 (France)

    2015-07-01

    Research and development on nuclear fuel behavior under irradiations and accelerated ageing of structure materials is a key issue for sustainable nuclear energy in order to meet specific needs by keeping the best level of safety. A new Material Testing Reactor (MTR), the Jules Horowitz Reactor (JHR) currently under construction in the South of France in the CEA Cadarache research centre will offer a real opportunity to perform R and D programs and hence will crucially contribute to the selection, optimization and qualification of innovative materials and fuels. To perform such programs advanced accurate and innovative experiments, irradiation devices that contain material and fuel samples are required to be set up inside or beside the reactor core. These experiments needs beforehand in situ and on line sophisticated measurements to accurately reach specific and determining parameters such as thermal and fast neutron fluxes, nuclear heating and temperature conditions to precisely monitor and control the conducted assays. Consequently, since 2009 CEA and Aix-Marseille University collaborate in order to design and develop a new multi-sensor device which will be dedicated to measuring profiles of such conditions inside the experimental channels of the JHR. These works are performed in the framework of two complementary joint research programs called MAHRI-BETHY and INCORE. These programs couple experimental studies carried out both out-of nuclear fluxes (in laboratory) and under irradiation conditions (in OSIRIS MTR reactor in France and MARIA MTR reactor in Poland) with numerical works realized by thermal simulations (CAST3M code) and Monte Carlo simulations (MCNP code). These programs deal with three main aims. The first one corresponds to the design and/or the test of new in-pile instrumentation. The second one concerns the development of advanced calibration procedures in particular in the case of one specific sensor: a differential calorimeter used to quantify

  19. Avaliação do teste de imunofluorescência indireta para diagnóstico da filariose bancroftiana usando a microfilária de W. bancrofti como antígeno, em Recife-PE, Brasil Evaluation of indirect immunofluorescence test for bancroftian filariasis using Wuchereria bancroft microfilariae as the antigen in Recife, Brazil

    Directory of Open Access Journals (Sweden)

    Gerusa Dreyer

    1991-10-01

    Full Text Available Analisou-se o teste de imunofluorescência indireta com microfilárias de W. bancrofti tratadas pela papaína, como antígeno, amplamente utilizado em Recife para o imunodiagnóstico da filariose linfática. Foram testados soros de 50 pacientes portadores das diversas formas clínicas da doença, incluindo microfilaremia assintomática, eosinofilia pulmonar tropical, elefantíase de membros inferiores, linfagite aguda e quilúria. Para o grupo controle, foram selecionados 50 indivíduos vivendo pelo menos há 5 anos em área endêmica, sem nenhuma evidencia clínica e/ou laboratorial da doença, constituindo os chamados endêmicos normais. A sensibilidade e especificidade do teste, segundo diferentes pontos de corte, mostraram a impossibilidade de diferenciação entre o grupo controle e o grupo sabidamente infectado. Também não foi possível estabelecer correlação entre os títulos encontrados e as diferentes formas clínicas. Foi considerada a existência de reações cruzadas relacionadas a helmintíases intestinais, porém nenhuma relação direta foi encontrada.The authors analysed the indirect immunofluorescence assay, for the diagnosis of bancroftian filariasis using papain treated W. bancrofti microfilariae as antigen, widely used in Recife - Brazil. Sera from 50 patients with several clinical forms of the disease including asymptomatic carriers, tropical pulmonary eosinophilia, elephantiasis, filarial fever and chyluria were analysed. For the control group, 50 individuals were selected, living at least 5 years in endemic area, with neither previous DEC treatment nor clinical-laboratory evidences of the disease, called normals endemic. The sensitivity and specificity were analised taking into account different cut off values. It was not possible to differentiate infected individuals from the control group. It was not even possible to establish any correlation with IMF titers among different clinical presentation of the disease

  20. RIA for calcitonin detection in human serum

    International Nuclear Information System (INIS)

    Mander, M.

    1977-01-01

    A RIA for human calcitonin (HCT) was adapted to the microtiter system. The method had a sensitivity of 60 pmol/l which is, however, not sufficient for measurements of the HCT level in healthy persons. Oral and i.v. administration of calcium, oral administration of vitamin D, and glucose tolerance tests did not result in a calcitonin increase over the detection limit. In two patients with histologically confirmed medullary thyroid carcinoma, there are extremely increased calcitonin levels: 16,000 and 120,000 pmol/l. In two other patients with medullary thyroid carcinoma after total resection of the thyroid, HCT levels were below the detection limit. In patients with hypercalcaemia (tumor hypercalcaemia), increased HCT levels were not observed. On the other hand, a HCT value of 150 pmol/l was found in a patient with vitamin D intoxication. As is normal in tumour cases of this kind, the two patients with medullar thyroid carcinoma examined during the study suffered from severe diarrhoea. In both cases, the family anamnesis showed that the mothers of the two patients had also suffered from thyroid cancer. (orig.) [de

  1. RIA determination of aflatoxin B1 in food

    International Nuclear Information System (INIS)

    Bludovsky, R.

    1986-01-01

    The possibility was tested of the application of a commercial RIA kit in determining aflatoxin B 1 in foodstuffs. Stability, sensitivity, specificity and the effect of interfering materials were studied. Alternative methods were tested of sample preparation and a technique was proposed usable for food analysis. The kit was found to be mainly suitable for screening and for the determination of aflatoxin B 1 in concentrations exceedings 1 μg/kg. Lipids were found to cause a systematic positive error and should thus be removed by extraction prior to analysis. (author). 10 tabs., 15 refs

  2. A probabilistic approach for RIA fuel failure criteria

    International Nuclear Information System (INIS)

    Carlo Vitanza, Dr.

    2008-01-01

    Substantial experimental data have been produced in support of the definition of the RIA safety limits for water reactor fuels at high burn up. Based on these data, fuel failure enthalpy limits can be derived based on methods having a varying degree of complexity. However, regardless of sophistication, it is unlikely that any deterministic approach would result in perfect predictions of all failure and non failure data obtained in RIA tests. Accordingly, a probabilistic approach is proposed in this paper, where in addition to a best estimate evaluation of the failure enthalpy, a RIA fuel failure probability distribution is defined within an enthalpy band surrounding the best estimate failure enthalpy. The band width and the failure probability distribution within this band are determined on the basis of the whole data set, including failure and non failure data and accounting for the actual scatter of the database. The present probabilistic approach can be used in conjunction with any deterministic model or correlation. For deterministic models or correlations having good prediction capability, the probability distribution will be sharply increasing within a narrow band around the best estimate value. For deterministic predictions of lower quality, instead, the resulting probability distribution will be broad and coarser

  3. Aula de história: subjetividade e memória na aprendizagem de alunos

    OpenAIRE

    Scoz, Beatriz Judith Lima; Rodrigues, Vilma Nardes Silva

    2015-01-01

    Este artigo apresenta o relato de uma pesquisa sobre as relações entre memória individual e memória coletiva nas aulas de História para compreender suas interferências na produção de sentidos subjetivos dos alunos na aprendizagem de História. A coleta de dados foi feita a partir do filme "Narradores de Javé" e da "conversação livre" com alunos da 8a série de uma escola pública de São Paulo. A pesquisa fundamenta-se nas concepções teóricas de Halbwachs e Placco, & Souza acerca da memória. No q...

  4. Review of RIA and LOCA criteria for WWER fuel

    International Nuclear Information System (INIS)

    Hozer, Z.

    2006-01-01

    The RIA and LOCA fuel safety criteria are under revision in the international community of fuel suppliers, authorities and research organizations. The main criteria will be reviewed in the paper for WWER fuel. Experimental data on the fuel failure behaviour under reactivity-initiated accident (RIA) conditions produced in the last decade in French and Japanese test reactors indicated low failure enthalpy for high burnup fuel compared to fresh fuel. However the high burnup was not the only phenomenon influencing the fuel failure. The oxide scale on the external surface of the fuel rod, hydrogen content of the Zr cladding and the local hydriding seemed also be responsible for the failure at low enthalpy. Furthermore differences have been found between Western design fuel and Russian type WWER fuel. The burnup dependence of fuel failure for WWER fuel was found much less, probably due to the low oxidation during normal operational conditions compared to other PWRs. The recently published Vitanza and KAERI correlations for RIA failure enthalpy have been applied to 23 WWER tests. Experimental data from Russian IGR and BIGR reactors have been used. The calculations have shown that both burnup and cladding oxidation effects must be considered, however the pulse width dependence of failure enthalpy has not been confirmed. During loss of coolant accidents (LOCA) the peak cladding temperature and local oxidation criteria have to be met. The oxidation criterion is under discussion today in many laboratories. The AEKI carried out several experimental series with Zr1%Nb cladding used in WWER reactors. The paper will describe the main results of the tests and present the limit for ductile-brittle transition derived from ring compression test. The behaviour of Zr1%Nb (E110) and Zircaloy-4 claddings under LOCA conditions will be compared as well. (author)

  5. Mycotoxin determination using RIA and ELISA methods

    Energy Technology Data Exchange (ETDEWEB)

    Fukal, L; Sova, Z

    1985-12-01

    Experience is summed up of various authors with the determination of some mycotoxins (aflatoxin, ochratoxin A, T-2 toxin, rubratoxin, zearalenon, sterigmatocystine) using radioimmunoassay and enzyme immunoassay. For RIA purposes, tritium or sometimes iodine 125 is frequently used for labelling mycotoxins. Mycotoxins do not show immunogenic properties and must thus be conjugated with a high-molecular compound (serum albumin, polylysine) prior to immunozation. Factors are discussed making mycotoxin determination in foods difficult. Specificity of the obtained antisera is total between the individual mycotoxin groups while cross reactions are always recorded within the groups. RIA makes it possible to determine down to 200 pg (labelled with /sup 3/H) or 5 pg (labelled with /sup 125/I) of mycotoxins in a standard solution. In addition to high sensitivity and specificity, immunoassays of mycotoxins minimize the quantities of samples and solvents needed for extraction. Large series of samples can be processed using automatic analyzers. ELISA generally is more advantageous than RIA.

  6. The rare isotope accelerator (RIA) facility project

    International Nuclear Information System (INIS)

    Christoph Leemann

    2000-01-01

    The envisioned Rare-Isotope Accelerator (RIA) facility would add substantially to research opportunities for nuclear physics and astrophysics by combining increased intensities with a greatly expanded variety of high-quality rare-isotope beams. A flexible superconducting driver linac would provide 100 kW, 400 MeV/nucleon beams of any stable isotope from hydrogen to uranium onto production targets. Combinations of projectile fragmentation, target fragmentation, fission, and spallation would produce the needed broad assortment of short-lived secondary beams. This paper describes the project's background, purpose, and status, the envisioned facility, and the key subsystem, the driver linac. RIA's scientific purposes are to advance current theoretical models, reveal new manifestations of nuclear behavior, and probe the limits of nuclear existence [3]. Figures 1 and 2 show, respectively, examples of RIA research opportunities and the yields projected for pursuing them. Figure 3 outlines a conceptual approach for delivering the needed beams

  7. Detection of IgE in the sera of rodents: comparison of the applicability of ELISA and RIA

    Energy Technology Data Exchange (ETDEWEB)

    Reiner, G; Zahner, H [Institut fuer Parasitologie der Justus-Liebig-Universitaet Giessen, Germany, F.R.; Haque, A [Institut Pasteur, 59 - Lille (France). Centre d' Immunologie et de Biologie Parasitaire

    1984-04-13

    RIA and ELISA were compared for their ability to detect IgE in different rodent species. With a sheep anti-rat IgE antibody good correlation (P < 0.001) between the 2 assay methods for IgE was found in rats. RIA failed to detect the IgE of Mastomys natalensis while ELISA proved to be a suitable test. However, both tests failed to measure IgE in sera of Nile rats.

  8. Unes pinzellades d'Història

    OpenAIRE

    Cedó, Ferran

    2006-01-01

    Al llarg de la història, hi ha hagut personatges famosos que han contribuït notablement a l’evolució de la matemàtica. Aquí, presentem una ressenya biogràfica d’alguns d’ells. Això no vol dir que aquests siguin els més importants. La història de la matemàtica és llarga i complexa, i és difícil decidir quins han estat els que han incidit més en el seu desenvolupament.

  9. A memória de Borges

    Directory of Open Access Journals (Sweden)

    Eneida Maria Souza

    2010-08-01

    nefasta ou de outra ordem? Sem atribuir algum juízo de valor ao debate, pretende-se apontar um dos pontos da poética borgiana responsável por sua consagração mundial, qual seja, o da autonomia literária. A presença/ausência da imagem do escritor/autor transforma-se em tema literário, intriga que se enreda/desenreda como espelho reduplicador da vida literária e da literatura.

  10. Methodological background of the Amersham Amerlex free thyroxine RIA

    International Nuclear Information System (INIS)

    Midgley, J.E.M.

    1982-01-01

    This contribution describes the essential rules underlying a valid estimation of FT4 and compares the way in which various methods deviate from ideal behaviour. The Amerlexsup((R)) FT4RIA test has been validated by several approaches. A practical demonstration of the ability of various methods to correct for differences in T4-binding protein concentration has been made by independent studies in a UK hospital on euthyroid non-pregnant, euthyroid contraceptive and euthyroid pregnant women. The Amersham kit has been shown to correspond closely to theoretical expectations for FT4 values in these groups. (orig.) [de

  11. Researches of WWER fuel rods behaviour under RIA accident conditions

    International Nuclear Information System (INIS)

    Nechaeva, O.; Medvedev, A.; Novikov, V.; Salatov, A.

    2003-01-01

    Unirradiated fuel rod and refabricated fuel rod tests in the BIGR as well as acceptance criteria proving absence of fragmentation and the settlement modeling of refabricated fuel rods thermomechanical behavior in the BIGR-tests using RAPTA-5 code are discussed in this paper. The behaviour of WWER type simulators with E110 and E635 cladding was researched at the BIGR reactor under power pulse conditions simulating reactivity initiated accident. The results of the tests in four variants of experimental conditions are submitted. The behaviour of 12 WWER type refabricated fuel rods was researched in the BIGR reactor under power pulse conditions simulating reactivity initiated accident: burnup 48 and 60 MWd/kgU, pulse width 3 ms, peak fuel enthalpy 115-190 cal/g. The program of future tests in the research reactor MIR with high burnup fuel rod (up to 70 MWd/kgU) under conditions simulating design RIA in WWER-1000 is presented

  12. Chemical effects of 13N produced by recoil protons and deuterons in pile-irradiated methanol and methanol-d4

    International Nuclear Information System (INIS)

    Sensui, Y.; Tomura, K.; Matsuura, T.

    1982-01-01

    The stabilized chemical forms of 13 N resulting from the reactions 13 C(p,n) 13 N by a recoil proton and 12 C(d,n) 13 N by a recoil deuteron, were studied in pile-irradiated methanol and methanol-d 4 in the temperature range from 77 to 295 K. Contrary to the target of benzene, cyclohexane, acetone and diethyl ether previously studied, the relative yield of 13 N-compounds did not depend on the irradiation temperature in the present media. In the yield of 13 N-compounds no marked change was observed between methanol and methanol-d 4 , differing from the results between benzene and benzene-d 6 . A mechanism is proposed to explain the results. (author)

  13. Absolute on-line in-pile measurement of neutron fluxes using self-powered neutron detectors: Monte Carlo sensitivity calculations

    Energy Technology Data Exchange (ETDEWEB)

    Vermeeren, L. [SCK/CEN, B-2400 Mol (Belgium)

    2001-07-01

    Self-powered neutron detectors (SPND) are well suited to monitor continuously the neutronic operating conditions of driver fuel of research reactors and to follow its burnup evolution. This is of particular importance when advanced or new MTR fuel designs need to be qualified. We have developed a detailed MCNP-4B based Monte Carlo approach for the calculation of neutron sensitivities of SPNDs. Results for the neutron sensitivity of a Rh SPND are in excellent agreement with experimental data recently obtained at the BR2 research reactor. A critical comparison of the Monte Carlo results with results from standard analytical methods reveals an important deficiency of the analytical methods in the description of the electron transport efficiency. Our calculation method allows a reliable on-line determination of the absolute in-pile neutron flux. (author)

  14. Absolute on-line in-pile measurement of neutron fluxes using self-powered neutron detectors: Monte Carlo sensitivity calculations

    International Nuclear Information System (INIS)

    Vermeeren, L.

    2001-01-01

    Self-powered neutron detectors (SPND) are well suited to monitor continuously the neutronic operating conditions of driver fuel of research reactors and to follow its burnup evolution. This is of particular importance when advanced or new MTR fuel designs need to be qualified. We have developed a detailed MCNP-4B based Monte Carlo approach for the calculation of neutron sensitivities of SPNDs. Results for the neutron sensitivity of a Rh SPND are in excellent agreement with experimental data recently obtained at the BR2 research reactor. A critical comparison of the Monte Carlo results with results from standard analytical methods reveals an important deficiency of the analytical methods in the description of the electron transport efficiency. Our calculation method allows a reliable on-line determination of the absolute in-pile neutron flux. (author)

  15. Development of ECR ion source and LEBT technology for RIA

    International Nuclear Information System (INIS)

    Leitner, Daniela; Lyneis, Claude M.; Abbott, Steven R.; Dwinell, Roger D.; Leitner, Matthaeus; Silver, Charles S.; Taylor, Clyde E.

    2004-01-01

    The Rare Isotope Accelerator (RIA) Linac driver requires a great variety of high charge state ion beams with up to a magnitude higher intensity than currently achievable for the heaviest masses. The goal of the RIA injector R and D program for VENUS is the reliable production of intense medium charge state ion beams, e.g., 8 puA (particle mu A) of U29+. Therefore, the superconducting ECR ion source VENUS has been designed from the beginning for optimum operation at 28 GHz at high power (10 kW). In addition, a high intensity Low Energy Beam Transport, LEBT, that was developed to analyze and transport these multiply-charged, space charge dominated beams. During the last year VENUS was commissioned at 18 GHz and preparations for 28 GHz operation continued. Tests with various gases and recently metals have been performed with up to 2000 W of 18 GHz RF power. Promising performance has been measured in those preliminary beam tests. For example, 180 p mu A of O6+, 15 p mu A of Ar12+, 7.5 puA of X e20+ and 4puA of Bi24+ were produced in the early commissioning phase, ranking VENUS among the currently highest performance 18 GHz ECR ion sources. In FY04 a 10 kW 28 gyrotron system will be added, which will enable VENUS to reach full performance. The emittance of the beams produced at 18 GHz was measured with a two axis emittance scanner developed with earlier RIA R and D funds

  16. New RIA kit for determination of progesterone in cow milk

    International Nuclear Information System (INIS)

    Byszewska-Szpocinska, E.; Markiewicz, A.

    2006-01-01

    The determination of progesterone concentration in whole and fat-free milk 19-24 days after conception enables to distinguish fertile and non-fertile insemination, which is important in cattle breeding. The aim of this work was to develop a simple and quick radioimmunoassay test for the determination of progesterone in cow milk. Two types of solid-phase tubes coated with specific polyclonal anti-progesterone antibody from ORION Diagnostica and BIOSOURCE International, two different progesterone derivatives viz. progesterone-3- carboxymethyl oxime (CMO) and progesterone-11α-hemisuccinate (HS) conjugated to 125 I-histamine and the HPLC system with Lichrospher RP-18 column along with 65% acetonitrile/water as eluent to purify the tracers were used to carry out this work. Progesterone-3CMO- 125 I-histamine had a retention time of 13.2 min and progesterone-11α-hemisuccinate- 125 I-histamine had a retention time of 7.8 min. Two kinds of kits (kit I and kit II) were prepared, first with progesterone-3CMO- 125 I-histamine as the tracer and coated tubes from Progesterone Veterinary RIA kit of ORION Diagnostica and the second with progesterone-11αHS- 125 I-histamine as the tracer and coated tubes from Progesterone Veterinary RIA kit from BIOSOURCE International. Progesterone from Sigma and selected fat-free cow's milk without progesterone as zero progesterone milk matrix were used for standard preparation. The optimal assay procedure was as follows: 50μL standards, controls and fat-free milk samples were pipetted into coated tubes followed by addition of 500μL of diluted tracer. The tubes were incubated for 2h in case of kit I and 3h for kit II at RT. After the incubation, the tubes were decanted and counted. The assay range was 0 to 270 nmol/L for kit I and 0 to 300 nmol/L for kit II. The sensitivity of the kit with ORION coated tubes was better (0.8 nmol/L) than that of BIOSOURCE tubes which was 1.5 nmol/L. Validation of these assays in terms of specificity, accuracy

  17. Review of high burn-up RIA and LOCA database and criteria

    International Nuclear Information System (INIS)

    Vitanza, C.; Hrehor, M.

    2006-01-01

    This document is intended to provide regulators, their technical support organizations and industry with a concise review of existing fuel experimental data at RIA and LOCA conditions and considerations on how these data affect fuel safety criteria at increasing burn-up. It mostly addresses experimental results relevant to BWR and PWR fuel and it encompasses several contributions from the various experts that participated in the CSNI SEGFSM activities. It also covers the information presented at the joint CSNI/CNRA Topical Discussion on high burn-up fuel issues that took place on this subject in December 2004. The report is organized in the following way: the CABRI RIA database (14 tests), the NSRR database (26 tests) and other databases, RIA failure thresholds, comparison of failure thresholds for the HZP case, LOCA database ductility tests and quench tests, LOCA safety limit, provisional burn-up dependent criterion for Zr-4. The conclusions are as follows. On RIA, there is a well-established testing method and a significant and relatively consistent database from NSRR and Cabri tests, especially on high burn-up Zr-2 and Zr-4 cladding. It is encouraging that several correlations have been proposed for the RIA fuel failure threshold. Their predictions are compared and discussed in this paper for a representative PWR case. On LOCA, there are two different test methods, one based on ductility determinations and the other based on 'integral' quench tests. The LOCA database at high burn-up is limited to both testing methods. Ductility tests carried out with pre-hydrided non-irradiated cladding show a pronounced hydrogen effect. Data for actual high burn-up specimens are being gathered in various laboratories and will form the basis for a burn-up dependent LOCA limit. A provisional burn-up dependent criterion is discussed in the paper

  18. Irradiation experiments of 3rd, 4th and 5th fuel assemblies by an in-pile gas loop, OGL-1

    International Nuclear Information System (INIS)

    Fukuda, Kousaku; Kobayashi, Fumiaki; Hayashi, Kimio; Minato, Kazuo; Kikuchi, Teruo; Adachi, Mamoru; Iwamoto, Kazumi; Ikawa, Katsuichi; Itami, Hiroharu.

    1986-07-01

    Three irradiation experiments for 3rd, 4th and 5th fuel assemblies which had been composed of VHTR reference coated particle fuels and graphite components were carried out by an in-pile gas loop, OGL-1 during 1979 and 1982. The main purposes of these experiments were to study on bowing of the fuel rod by irradiation for the 3rd fuel assembly, to study on fuel behavior under relatively low burnup irradiation for the 4th fuel assembly, and to study on fuel behavior up to full burnup of VHTR design for the 5th fuel assembly. For understanding in-pile fuel behavior, fractional releases of fission gases from each fuel assembly were estimated by measuring the fission gas concentrations in the primary loop of OGL-1. The post-irradiation examination (PIE) was carried out extensively on the fuel block, the fuel rods and the fuel compacts in Tokai Hot Laboratory. Also, made were the measurements of metallic fission product distributions in the fuel assemblies and the fuel rods. The results in these experiments were given as follows ; bowing of the fuel rod in the 3rd fuel assembly was 0.7 mm, but integrity of the rod was kept under irradiation. Fractional release of the fission gas from the 4th fuel assembly remained in the order of 10 -7 during irradiation, suggesting that the fuel performance was excellent. The fractional release from the 5th fuel assembly, on the other hand, was in the order of 10 -5 which was the same level in the VHTR design. (author)

  19. Preparation of a thermal-hydraulic design method for driver core fuel pins of a new in-pile experimental reactor for FBR safety research

    International Nuclear Information System (INIS)

    Mizuno, Masahiro; Yamaguchi, Katsuhisa; Uto, Nariaki

    1999-07-01

    A design study of a new in-pile experimental reactor, SERAPH (Safety Engineering Reactor for Accident PHenomenology), for FBR safety research has progressed at JNC (Japan Nuclear Cycle Development Institute). SERAPH is intended for various in-pile experiments to be performed under quasi-steady state and various transient operation modes. In order to evaluate the driver core performance in conducting such experiments, clarify the relating design issues to be resolved and refine the experimental needs, it is indispensable to comprehend the allowable margin for the thermal-hydraulic fuel pin design since it largely affects the strategy for the driver core design. This report presents a thermal-hydraulic design method for the driver core fuel pins, which is a combination of a two-dimensional time-dependent heat transfer analysis code TAC-2D and a general non-linear finite-element structural analysis code FINAS. In TAC-2D, the allowable spatial mesh and the time step sizes are evaluated. The code is modified so as to treat time-dependent thermal properties, include an improved gap heat-transfer model and treat the change of intra-pin gap width under transient modes, for the purpose of improving the accuracy of evaluating heat transfer characteristics which gives a significant impact on the thermal-hydraulic design. As for FINAS, the number of element nodes and spatial meshes required to obtain adequate accuracy for the thermal stress characteristics of a fuel pellet during transient modes are investigated. In addition, post-processing tools are newly developed to process the calculation results obtained from these codes. The results of this work contribute to advancing the fuel pin design study for SERAPH as well with the investigation on the technique of manufacturing fuel pins. (author)

  20. Safety test facilities - status, needs, future directions

    International Nuclear Information System (INIS)

    Heusener, G.; Cogne, F.

    1979-08-01

    A survey is given of the in-pile programs which are presently or in the near future being performed in the DeBeNe-area and in France. Only those in-pile programs are considered which are dealing with severe accidents that might lead to disruption of major parts of the core. By comparing the needs with the goals of the present programs points are identified which are not sufficiently well covered up till now. The future procedure is described: the existing facilities will be used to the largest possible extent. Whenever it is necessary, upgrading and improvement will be foreseen. Studies of a Test Facility allowing the transient testing of large pin bundles should be continued. The construction of such a facility in Europe in the near future however seems premature

  1. Verification of computer code FPRETAIN with respect to RIA data from SPERT and PBF experiments

    International Nuclear Information System (INIS)

    Heo, Young-Ho; Yanagisawa, Kazuaki.

    1992-12-01

    This report presents the comparisons between calculated and measured fuel rod behavior and the analysis of stress for preirradiated LWR type fuel rods during reactivity initiated accident (RIA) conditions. For the calculations, FPRETAIN computer code which can simulate the fuel behavior under RIA conditions at extended burnup stage was used. For the experimental, data obtained from the Special Power Excursion Reactor Test (SPERT) and the Power Burst Facility (PBF) tests were used. The results of the comparisons showed that the FPRETAIN code predicted well the tendency of the fuel rod behavior during RIA. From the results of the stress analysis, it was found that the maximum hoop stress of cladding was not proportional to the energy deposition of fuel rod. Calculated cladding maximum hoop stress of failed fuel at high burnup was not lower than that of intact fresh or low burnup fuel. (author)

  2. História e psicologia em Henri Berr

    OpenAIRE

    Waeny, Maria Fernanda Costa

    2017-01-01

    O artigo aborda algumas das idéias de Henri Berr; trata de sua proposta em história, especialmente no que ela se opõe à filosofia da história e à história alemãs; e examina como esta concepção de história à la francesa introduz a psicologia nas pesquisas em história e inaugura a psicologia histórica.Palavras-chave: História da Psicologia; Psicologia Histórica; História das Ciências Humanas; História das Idéias; Annales

  3. Remote Infrared Audible Signage (RIAS) Pilot Program : evaluation report

    Science.gov (United States)

    2009-09-01

    This report presents evaluation findings on the Remote Infrared Audible Signage (RIAS) Pilot Program in the Puget Sound Region of Washington. The installation, demonstration and evaluation of RIAS were required by a provision in the Safe, Accountable...

  4. Postoperative chest physical therapy prevents respiratory complications in patients undergoing esophagectomy Fisioterapia respiratória pós-operatória previne complicações respiratórias em pacientes submetidos à esofagectomia

    Directory of Open Access Journals (Sweden)

    Adriana C. Lunardi

    2011-04-01

    Full Text Available BACKGROUND: Esophagectomy presents the highest rate of postoperative pulmonary complications among all types of upper abdominal surgery. The benefits of chest physical therapy in patients undergoing upper abdominal surgery have been shown by many studies; however, its specific effect in patients receiving esophagectomy has been seldom investigated. OBJECTIVES: This study aimed to compare the frequency of respiratory complications in patients undergoing esophagectomy receiving chest physical therapy compared to no treatment. METHODS: 70 consecutive patients were evaluated retrospectively and allocated to two groups: control group (CG=no physical therapy; n=30 and chest physical therapy group (PTG; n=40. Patients received chest physical therapy which includes lung re-expansion and airway clearance maneuvers. They were not submitted to either noninvasive ventilation or exercises with devices that generate airways positive pressure. All patients were instructed to early mobilization. Information about pre-operative and respiratory complications were collected. Statistic analysis to compare the frequency of respiratory complications was performed by the Z test. The significance level was set to 5%. RESULTS: Patients in the CG and PTG were similar in terms of age, BMI, smoking and drinking status, malignant diseases, surgical and anesthesia duration and types of esophagectomy (p>0.05. Our results show that patients received chest physical therapy after esophagectomy had a lower frequency of respiratory complications (15% vs. 37%, pCONTEXTUALIZAÇÃO: A esofagectomia apresenta a maior taxa de complicações pulmonares pós-operatórias dentre as cirurgias abdominais altas. Os benefícios da fisioterapia respiratória em pacientes submetidos à cirurgia abdominal alta convencional têm sido mostrados na literatura, porém esse efeito na esofagectomia tem sido pouco investigado. OBJETIVOS: Comparar a frequência de complicações respiratórias em dois

  5. HISTÓRIAS DE RETIRANTES: RUÍNAS LITERÁRIAS NO CINEMA

    Directory of Open Access Journals (Sweden)

    Elisabete Alfeld Rodrigues

    2009-06-01

    Full Text Available Em O caminho das nuvens, Vicente Amorim conta a história da retirada de uma família do interior nordestino para a região sudeste. Uma história que já foi muitas vezes contada, por exemplo, em Vidas Secas: primeiro, na literatura, por Graciliano Ramos e, depois, no cinema, por Nélson Pereira dos Santos. Na retirada contada por Amorim, a migração não ocorre pelos passos na aridez do sertão; ela acontece por bicicletas nas rodovias, estradas e pequenas cidades que a família – pai, mãe e cinco filhos – percorre para chegar à cidade do Rio de Janeiro. A família se desloca da Paraíba em busca de um emprego de mil reais por mês que só pode ser encontrado no sudeste do Brasil – este motivo desencadeador parte de uma história factual. O filme é uma releitura que resgata a literatura, o cinema e a história factual promovendo uma relação dialógica construída por fragmentos das várias histórias.

  6. Fabrication of irradiation capsule for IASCC irradiation tests (2). Irradiation capsule for crack propagation test (Joint research)

    International Nuclear Information System (INIS)

    Ide, Hiroshi; Matsui, Yoshinori; Kawamata, Kazuo; Taguchi, Taketoshi; Kanazawa, Yoshiharu; Onuma, Yuichi; Watanabe, Hiroyuki; Inoue, Shuichi; Izumo, Hironobu; Ishida, Takuya; Saito, Takashi; Ishitsuka, Etsuo; Kawamura, Hiroshi; Kaji, Yoshiyuki; Ugachi, Hirokazu; Tsukada, Takashi

    2008-03-01

    It is known that irradiation Assisted Stress Corrosion Cracking (IASCC) occurs when austenitic stainless steel components used for light water reactor (LWR) are irradiated for a long period. In order to evaluate the high aging of the nuclear power plant, the study of IASCC becomes the important problem. The specimens irradiated in the reactor were evaluated by post irradiation examination in the past study. For the appropriate evaluation of IASCC, it is necessary to test it under the simulated LWR conditions; temperature, water chemistry and irradiation conditions. In order to perform in-pile SCC test, saturated temperature capsule (SATCAP) was developed. There are crack growth test, crack propagation test and so on for in-pile SCC test. In this report, SATCAP for crack propagation test is reported. (author)

  7. Fabrication of irradiation capsule for IASCC irradiation tests (1). Irradiation capsule for crack growth test (Joint research)

    International Nuclear Information System (INIS)

    Ide, Hiroshi; Matsui, Yoshinori; Kawamata, Kazuo; Taguchi, Taketoshi; Kanazawa, Yoshiharu; Onuma, Yuichi; Watanabe, Hiroyuki; Inoue, Shuichi; Izumo, Hironobu; Ishida, Takuya; Saito, Takashi; Ishitsuka, Etsuo; Kawamura, Hiroshi; Kaji, Yoshiyuki; Ugachi, Hirokazu; Tsukada, Takashi

    2008-03-01

    It is known that Irradiation Assisted Stress Corrosion Cracking (IASCC) occurs when austenitic stainless steel components used for light water reactor (LWR) are irradiated for a long period. In order to evaluate the high aging of the nuclear power plant, the study of IASCC becomes the important problem. The specimens irradiated in the reactor were evaluated by post irradiation examination in the past study. For the appropriate evaluation of IASCC, it is necessary to test it under the simulated LWR conditions; temperature, water chemistry and irradiation conditions. In order to perform in-pile SCC test, saturated temperature capsule (SATCAP) was developed. There are crack growth test, crack propagation test and so on for in-pile SCC test. In this report, SATCAP for crack growth test is reported. (author)

  8. In-pile Tritium Permeation through F82H Steel with and without a Ceramic Coating of Cr2O3-SiO2 Including CrPO4

    International Nuclear Information System (INIS)

    Nakamichi, M.; Hayashi, K.; Kulsartov, T.V.; Afanasyev, S.E.; Shestakov, V.P.; Chikhray, Y.V.; Kenzhin, E.A.; Kolbaenkov, A.N.

    2006-01-01

    Development of coating on blanket structural materials with significant reduction capability of tritium permeation is highly required in order to realize a reasonable design of a tritium recovery and processing system of demonstration (DEMO) fusion reactors. An effective coating has been developed in Japan Atomic Energy Agency (JAEA) using a ceramic material of Cr 2 O 3 -SiO 2 including CrPO 4 . In previous out-of-pile deuterium permeation experiments at 600 o C [T.V. Kulsartov et al., Fusion Eng. Des. 81 (2006) 701], a significant permeation reduction factor (PFR) of about 300 was obtained for the coating on the inner-side surface of tubular diffusion cells made by ferritic steel (F82H). In the present study, in-pile experiments on tritium permeation were conducted for F82H steel with and without the same coating, using a testing reactor IGV-1M in Kazakhstan. The tritium source used was liquid lithium-lead eutectics, Pb17Li, which was poured into a space around a tubular diffusion cell (specimen) of F82H steel with or without the coating on the inner side the cell. The irradiation time was about 4 hours, which corresponds to a fast-neuron fluence of about 2x10 21 m -2 (E > 1.1 MeV). The permeation reduction factor (PRF) was obtained by comparison of kinetics curves of tritium permeation through the diffusion cell of F82H steel with and without the coating. The PRFs at 600 and 500 o C were 292 and 30, respectively. These values are close to corresponding PRF values of 307 and 45, which had been obtained at 600 and 500 o C, respectively, in the previous out-of-pile experiments [T.V. Kulsartov et al., Fusion Eng. Des. 81 (2006) 701]. (author)

  9. Avaliação da memória sob anestesia venosa total

    Directory of Open Access Journals (Sweden)

    Gulistan Aktas

    2013-06-01

    Full Text Available JUSTIFICATIVA E OBJETIVOS: Neste estudo, objetivamos avaliar a memória implícita e explícita em pacientes submetidos à cirurgia abdominal sob anestesia venosa total (AVT com propofol e remifentanil, na qual o nível de anestesia foi controlado pelo monitoramento do índice bispectral (BIS. MÉTODO: Anestesia venosa total foi administrada a 60 pacientes adultos para obter níveis de BIS de 40-60. Os pacientes foram randomicamente divididos em três grupos, de acordo com as gravações que ouviram. Os pacientes do grupo categoria (CT ouviram uma fita gravada contendo cinco nomes de animais. Os pacientes do grupo recordar palavras (RP ouviram uma fita gravada contendo cinco palavras de frequência média na língua turca, depois de adaptadas. Os pacientes do grupo controle (GC ouviram os sons do mar até o fim da cirurgia. Duas horas após a cirurgia, os testes foram administrados a cada paciente na sala de recuperação para avaliar a memória. RESULTADOS: Houve uma diferença entre os escores dos grupos CT e GC no Miniexame do Estado Mental (MMSE; todos os escores foram > 20. Os resultados dos testes de categoria e recordar palavras, aplicados para avaliar a memória implícita, não foram estatisticamente diferentes entre os grupos. Não houve evidência de memória implícita em nenhum dos pacientes. Um paciente lembrou-se de ouvir "o som de água" como uma prova de memória explícita. Onze pacientes declararam não ter sonhado. CONCLUSÕES: Apesar de não termos encontrado nenhuma evidência de memória implícita sob anestesia adequada com AVT, um paciente apresentou memória explícita. Embora a profundidade adequada da anestesia fornecida pelo monitoramento do BIS corrobore nossos resultados para a memória implícita, ela não explica os resultados para a memória explícita.

  10. Irradiation Testing of Ultrasonic Transducers

    International Nuclear Information System (INIS)

    Daw, J.; Rempe, J.; Palmer, J.; Tittmann, B.; Reinhardt, B.; Kohse, G.; Ramuhalli, P.; Montgomery, R.; Chien, H.T.; Villard, J.F.

    2013-06-01

    Ultrasonic technologies offer the potential for high accuracy and resolution in-pile measurement of numerous parameters, including geometry changes, temperature, crack initiation and growth, gas pressure and composition, and microstructural changes. Many Department of Energy-Office of Nuclear Energy (DOE-NE) programs are exploring the use of ultrasonic technologies to provide enhanced sensors for in-pile instrumentation during irradiation testing. For example, the ability of single, small diameter ultrasonic thermometers (UTs) to provide a temperature profile in candidate metallic and oxide fuel would provide much needed data for validating new fuel performance models. Other efforts include an ultrasonic technique to detect morphology changes (such as crack initiation and growth) and acoustic techniques to evaluate fission gas composition and pressure. These efforts are limited by the lack of existing knowledge of ultrasonic transducer material survivability under irradiation conditions. To address this need, the Pennsylvania State University (PSU) was awarded an Advanced Test Reactor National Scientific User Facility (ATR NSUF) project to evaluate promising magnetostrictive and piezoelectric transducer performance in the Massachusetts Institute of Technology Research Reactor (MITR) up to a fast fluence of at least 10 21 n/cm 2 (E> 0.1 MeV). This test will be an instrumented lead test; and real-time transducer performance data will be collected along with temperature and neutron and gamma flux data. By characterizing magnetostrictive and piezoelectric transducer survivability during irradiation, test results will enable the development of novel radiation tolerant ultrasonic sensors for use in Material and Test Reactors (MTRs). The current work bridges the gap between proven out-of-pile ultrasonic techniques and in-pile deployment of ultrasonic sensors by acquiring the data necessary to demonstrate the performance of ultrasonic transducers. (authors)

  11. História e memória: a soldadura da imaginação

    Directory of Open Access Journals (Sweden)

    Brum, Rosemary Fritsch

    2006-01-01

    Full Text Available Este artigo explora possibilidades em história oral, o desenvolvimento na contemporaneidade das ciências cognitivas e sua aproximação com histórias curtas. Essas direções podem ser fertilizadas pelo pesquisador nos estudos da memória, da narrativa e da oralidade

  12. Capsule development and utilization for material irradiation tests

    Energy Technology Data Exchange (ETDEWEB)

    Kang, Young Hwan; Kim, B. G.; Joo, K. N. [and others

    2000-05-01

    The development program of advanced nuclear structural and fuel materials includes the in-pile tests using the instrumented capsule at HANARO. The tests were performed in the in-core test holes of CT, IR 1 and 2 and OR 4 and 5 of HANARO. Extensive efforts have also been made to establish design and manufacturing technology for the instrumented capsule and its related system, which should be compatible with the HANARO's characteristics. Since the first instrumented capsule(97M-01K) had been designed and successfully fabricated, five tests were done to support the users and provided the economic benefits to user by generating the essential in-pile information on the performance and structural integrity of materials. This paper describes the present status and future plans of these R and D activities for the development of the instrumented capsule including in-situ material property measurement capsules and nuclear fuel test capsules.

  13. Capsule development and utilization for material irradiation tests

    International Nuclear Information System (INIS)

    Kang, Young Hwan; Kim, B. G.; Joo, K. N.

    2000-05-01

    The development program of advanced nuclear structural and fuel materials includes the in-pile tests using the instrumented capsule at HANARO. The tests were performed in the in-core test holes of CT, IR 1 and 2 and OR 4 and 5 of HANARO. Extensive efforts have also been made to establish design and manufacturing technology for the instrumented capsule and its related system, which should be compatible with the HANARO's characteristics. Since the first instrumented capsule(97M-01K) had been designed and successfully fabricated, five tests were done to support the users and provided the economic benefits to user by generating the essential in-pile information on the performance and structural integrity of materials. This paper describes the present status and future plans of these R and D activities for the development of the instrumented capsule including in-situ material property measurement capsules and nuclear fuel test capsules

  14. Capsule development and utilization for material irradiation tests

    Energy Technology Data Exchange (ETDEWEB)

    Kang, Young Hwan; Kim, B G; Joo, K N [and others

    2000-05-01

    The development program of advanced nuclear structural and fuel materials includes the in-pile tests using the instrumented capsule at HANARO. The tests were performed in the in-core test holes of CT, IR 1 and 2 and OR 4 and 5 of HANARO. Extensive efforts have also been made to establish design and manufacturing technology for the instrumented capsule and its related system, which should be compatible with the HANARO's characteristics. Since the first instrumented capsule(97M-01K) had been designed and successfully fabricated, five tests were done to support the users and provided the economic benefits to user by generating the essential in-pile information on the performance and structural integrity of materials. This paper describes the present status and future plans of these R and D activities for the development of the instrumented capsule including in-situ material property measurement capsules and nuclear fuel test capsules.

  15. Clustering high dimensional data using RIA

    Energy Technology Data Exchange (ETDEWEB)

    Aziz, Nazrina [School of Quantitative Sciences, College of Arts and Sciences, Universiti Utara Malaysia, 06010 Sintok, Kedah (Malaysia)

    2015-05-15

    Clustering may simply represent a convenient method for organizing a large data set so that it can easily be understood and information can efficiently be retrieved. However, identifying cluster in high dimensionality data sets is a difficult task because of the curse of dimensionality. Another challenge in clustering is some traditional functions cannot capture the pattern dissimilarity among objects. In this article, we used an alternative dissimilarity measurement called Robust Influence Angle (RIA) in the partitioning method. RIA is developed using eigenstructure of the covariance matrix and robust principal component score. We notice that, it can obtain cluster easily and hence avoid the curse of dimensionality. It is also manage to cluster large data sets with mixed numeric and categorical value.

  16. Melancolia, memória e subjetividade

    OpenAIRE

    Giele Rocha Dorneles

    2015-01-01

    A proposta desta tese é estabelecer, através de uma perspectiva comparatista, relações entre três temas articuladores: a melancolia, a memória e a subjetividade, de modo a constituir entrelaçamentos possíveis, além de buscar indicar o modo como essas três temáticas são apresentadas e representadas em diferentes formas de expressão das artes, partindo de obras literárias - como “A maior flor do mundo” e “As pequenas memórias”, entre outras de José Saramago, e de autores como Charles Baudelaire...

  17. Distúrbios de memória em pacientes epilépticos

    Directory of Open Access Journals (Sweden)

    STELLA FLORINDO

    1999-01-01

    Full Text Available O autor estudou distúrbios de memória em pacientes epilépticos com crises parciais complexas (CPC, com os objetivos de: 1 identificar estes distúrbios; e 2 comparar os resultados dos pacientes com os dos controles. Foram estudados 50 pacientes adultos e 20 sujeitos sem enfermidades neuropsiquiátricas. Os métodos consistiram em: 1 investigação da atividade mnemônica através do Teste de Memória de Wechsler (subtestes: Armazenamento e Recuperação, Memória Recente e Memória Imediata; e 2 comparação entre os resultados de ambos os grupos. 3 associação entre SPECT Cerebral e atividade mnemônica. Nos três subtestes, os pacientes apresentaram desempenho cognitivo significativamente inferior ao dos controles (p <0,05. Constatou-se a associação entre hipofluxo em região temporal esquerda e distúrbio da memória nos três subtestes. Concluiu-se que há associação entre CPC e distúrbios da atividade mnemônica.

  18. Microcapillary blood sampling for serological examinations by radioimmunoassay (RIA) and enzyme immunoassay (ELISA)

    Energy Technology Data Exchange (ETDEWEB)

    Rodak, L; Smid, B; Valicek, L; Jurak, E [Vyzkumny Ustav Veterinarniho Lekarstvi, Brno-Medlanky (Czechoslovakia)

    1984-01-01

    Methods were tested of sampling blood and blood serum for serological examinations on filtration paper and into heparinized glass capillaries with transfer into the dilution solution of the given composition. Samples were also examined for ACH virus antibodies. The suitability of the sampling was verified by an examination of samples using ELISA and RIA methods. The results showed the suitability of sampling using microcapillaries. The titres of virus antibodies found using the ELISA and RIA methods were identical and the sensitivity of antibody detection was not reduced even after the sample had been stored for 60 days at a temperature of 20 degC.

  19. Microcapillary blood sampling for serological examinations by radioimmunoassay (RIA) and enzyme immunoassay (ELISA)

    International Nuclear Information System (INIS)

    Rodak, L.; Smid, B.; Valicek, L.; Jurak, E.

    1984-01-01

    Methods were tested of sampling blood and blood serum for serological examinations on filtration paper and into heparinized glass capillaries with transfer into the dilution solution of the given composition. Samples were also examined for ACH virus antibodies. The suitability of the sampling was verified by an examination of samples usiOg ELISA and RIA methods. The results showed the suitability of sampling using microcapillaries. The titres of virus antibodies found using the ELISA and RIA methods were identical and the sensitivity of antibody detection was not reduced even after the sample had been stored for 60 days at a temperature of 20 degC. (B.S.)

  20. A HISTÓRIA DA APPLE COMPUTER

    OpenAIRE

    Gustavo Franco; Carlos Henrique Cirino Lacerda; Carlos Filipe de Oliveira Pedrosa; Bruno da Silva Chiriu; Antonio Marcos Pereira; Sergio Luiz; Vinícius José Andrade Silveira

    2006-01-01

    Este artigo pretende mostrar os fatos e caminhos seguidos pela empresa de computadores Apple e seus fundadores no decorrer de sua história. Tem também o objetivo de relatar os desfechos e as grandes idéias que fizeram da Apple uma das maiores empresas fabricantes de softwares e computadores pessoais, desde sua criação em 1976.

  1. RIA Beam Dynamics Comparing TRACK to IMPACT

    CERN Document Server

    Mustapha, Brahim; Ostroumov, Peter; Qiang, Ji; Ryne, Robert D

    2005-01-01

    In order to benchmark the newly developed beam dynamics code TRACK we have performed comparisons with well established existing codes. During code development, codes like TRANSPORT, COSY, GIOS and RAYTRACE were used to check TRACK's implementation of the different beam line elements. To benchmark the end-to-end simulation of the RIA driver linac, the simulation of the low-energy part (from the ion source to the entrance of the SC linac) was compared with PARMTEQ and found to agree well. For the simulation of the SC linac the code IMPACT is used. Prior to these simulations, the code IMPACT had to be updated to meet the special requirements of the RIA driver linac. Features such as multiple charge state acceleration, stripper simulation and beam collimation were added to the code. IMPACT was also modified to support new types of rf cavities and to include fringe fields for all the elements. This paper will present a comparison of the beam dynamics simulation in the RIA driver linac between the codes TRACK and I...

  2. Camptocormia secundária à polimiosite

    Directory of Open Access Journals (Sweden)

    Melina Andrade Mattar

    2013-08-01

    Full Text Available A camptocormia é uma doença postural caracterizada por flexão anormal da coluna toracolombar que surge na posição ereta, aumenta durante a caminhada e desaparece na posição supina. Na literatura, há descrição de apenas cinco casos de camptocormia secundária a miopatias inflamatórias idiopáticas. No presente relato de caso, descrevemos um paciente do sexo masculino, de 67 anos, com polimiosite há 18 anos, cursando com quadro compatível com camptocormia (estável e sem progressão do quadro clínico. A polimiosite é uma miopatia inflamatória idiopática caracterizada clinicamente por fraqueza muscular simétrica predominantemente proximal dos membros. Entretanto, sendo uma doença autoimune sistêmica, é plausível que ocorra acometimento de musculatura esquelética de forma difusa, incluindo a paravertebral, podendo manifestar-se com camptocormia.

  3. Characterization studies of prototype ISOL targets for the RIA

    International Nuclear Information System (INIS)

    Greene, John P.; Burtseva, Tatiana; Neubauer, Janelle; Nolen, Jerry A.; Villari, Antonio C.C.; Gomes, Itacil C.

    2005-01-01

    Targets employing refractory compounds are being developed for the rare isotope accelerator (RIA) facility to produce ion species far from stability. With the 100 kW beams proposed for the production targets, dissipation of heat becomes a challenging issue. In our two-step target design, neutrons are generated in a refractory primary target, inducing fission in the surrounding uranium carbide. The interplay of density, grain size, thermal conductivity and diffusion properties of the UC 2 needs to be well understood before fabrication. Thin samples of uranium carbide were prepared for thermal conductivity measurements using an electron beam to heat the sample and an optical pyrometer to observe the thermal radiation. Release efficiencies and independent thermal analysis on these samples are being undertaken at Oak Ridge National Laboratory (ORNL). An alternate target concept for RIA, the tilted slab approach promises to be simple with fast ion release and capable of withstanding high beam intensities while providing considerable yields via spallation. A proposed small business innovative research (SBIR) project will design a prototype tilted target, exploring the materials needed for fabrication and testing at an irradiation facility to address issues of heat transfer and stresses within the target

  4. Characterization studies of prototype ISOL targets for the RIA

    Science.gov (United States)

    Greene, John P.; Burtseva, Tatiana; Neubauer, Janelle; Nolen, Jerry A.; Villari, Antonio C. C.; Gomes, Itacil C.

    2005-12-01

    Targets employing refractory compounds are being developed for the rare isotope accelerator (RIA) facility to produce ion species far from stability. With the 100 kW beams proposed for the production targets, dissipation of heat becomes a challenging issue. In our two-step target design, neutrons are generated in a refractory primary target, inducing fission in the surrounding uranium carbide. The interplay of density, grain size, thermal conductivity and diffusion properties of the UC2 needs to be well understood before fabrication. Thin samples of uranium carbide were prepared for thermal conductivity measurements using an electron beam to heat the sample and an optical pyrometer to observe the thermal radiation. Release efficiencies and independent thermal analysis on these samples are being undertaken at Oak Ridge National Laboratory (ORNL). An alternate target concept for RIA, the tilted slab approach promises to be simple with fast ion release and capable of withstanding high beam intensities while providing considerable yields via spallation. A proposed small business innovative research (SBIR) project will design a prototype tilted target, exploring the materials needed for fabrication and testing at an irradiation facility to address issues of heat transfer and stresses within the target.

  5. Fundamental and clinical evaluation of osteocalcin RIA kit

    Energy Technology Data Exchange (ETDEWEB)

    Kousaka, Tadako; Yamamoto, Itsuo; Kitamura, Nobuyasu; Aoki, Jun; Uneno, Susumu; Sone, Teruki; Kasai, Ryuuichi; Torizuka, Kanji

    1987-06-01

    The laboratory performance of a double antibody radioimmunoassay (RIA) kit for measuring osteocalcin (OC) was tested for incubation, the effect of anticoagulants, serum storage, dilution, recovery, and reproducibility. Serum OC concentrations increased rapidly with the addition of 5 mM or more ethylenediamine tetraacetic acid, although they were not affected by the addition of heparin. Serum OC measurements, obtained at 2 or 3 weeks after sampling, tended to be lower. The other items, except for dilution, were reliable. Using the OC RIA kit, serum OC concentrations were measured in 161 patients with various diseases and 408 volunteers. Normal upper limit for OC was defined as 11.48 ng/ml. Serum OC concentrations were extremely high up to the age of puberty, and thereafter decreased rapidly with the constant values after the age of 20. Women had increased OC values after the latter half of their fourties. Primary hyperparathyroidism, bone metastases of malignancy, and malignant hypercalcemia were occasionally associated with increased OC values, in contrast to hypoparathyroidism showing decreased OC values. Extremely high values of OC were seen in many of the dialysis patients. (Namekawa, K.).

  6. Ocorrência de bactérias clinicamente relevantes nos resíduos de serviços de saúde em um aterro sanitário brasileiro e perfil de susceptibilidade a antimicrobianos Occurrence of clinically relevant bacteria in health service waste in a Brazilian sanitary landfill and antimicrobial susceptibility profile

    Directory of Open Access Journals (Sweden)

    Thiago César Nascimento

    2009-08-01

    Full Text Available Os resíduos de serviços de saúde suscitam polêmica quanto a importância para a saúde humana, animal e ambiental. Avaliou-se a ocorrência de bactérias clinicamente relevantes na pilha de resíduos de serviços de saúde em um aterro sanitário e seu perfil de susceptibilidade aos antimicrobianos. Alíquotas de chorume foram processadas para isolamento seletivo de Staphylococcus sp, bastonetes Gram negativos da família Enterobacteriaceae e não fermentadores. Resistência bacteriana a todos os antimicrobianos testados foi observada em todos os grupos microbianos, além de resistência a mais de uma droga. Os resultados permitem sugerir que bactérias viáveis nos resíduos de serviços de saúde representam riscos à saúde humana e animal. Além disso, a ocorrência de linhagens multirresistentes sustenta a hipótese dos resíduos de serviços de saúde atuarem como reservatórios de marcadores de resistência, com impacto ambiental. A falta de legislação regional de segregação, tratamento e destino de resíduos podem expor diferentes populações a riscos de transmissão de doenças infecciosas associadas a microrganismos multirresistentes.Health service waste gives rise to controversy regarding its importance for human, animal and environmental health. Occurrences of clinically relevant bacteria in piles of health service waste in a sanitary landfill and their antimicrobial susceptibility profile were evaluated. Aliquots of leachate were processed for selective isolation of Staphylococcus sp, Gram-negative rods of the Enterobacteriaceae family and non-fermenters. Bacterial resistance to all the antimicrobials tested was observed in all microbial groups, including resistance to more than one drug. The results make it possible to suggest that viable bacteria in health service waste represent risks to human and animal health. Furthermore, occurrences of multiresistant strains support the hypothesis that health service waste acts as a

  7. Perfis Diferenciais de Perda de Memória entre a Demência Frontotemporal e a do Tipo Alzheimer

    Directory of Open Access Journals (Sweden)

    Allegri Ricardo F.

    2001-01-01

    Full Text Available Os estados iniciais da demência tipo Alzheimer (DTA caracterizam-se classicamente por deterioração da memória enquanto que as mudanças de conduta e de personalidade aparecem nas etapas iniciais da demência frontotemporal (DFT. Entretanto, na prática clínica, o diagnóstico diferencial é difícil. O objetivo do presente trabalho foi estudar o rendimento da memória de pacientes com DTA (n= 20 e com DFT (n= 20 comparando-o com um grupo de controles (n = 20. Os pacientes, emparelhados por idade e escolaridade, foram avaliados com uma bateria neuropsicológica exaustiva. Para a avaliação da memória, examinou-se a "queixa subjetiva" de perda de memória (memória subjetiva, a aprendizagem de uma lista de palavras (memória episódica e o desempenho no teste de denominação de Boston (memória semântica. As pontuações de ambos os grupos de pacientes, na grande maioria das provas, foram significativamente inferiores às dos controles. Os pacientes com DTA mostraram uma deterioração global da memória episódica (tipo amnésia e semântica com um alto nível de queixa subjetiva. Os sujeitos com DFT, por outro lado, apresentaram um déficit de memória importante na recuperação da informação, mas com melhores capacidades de registro da informação, apesar das dificuldades de reconhecimento do seu distúrbio.

  8. Accident analysis of HANARO fuel test loop

    Energy Technology Data Exchange (ETDEWEB)

    Kim, J. Y.; Chi, D. Y

    1998-03-01

    Steady state fuel test loop will be equipped in HANARO to obtain the development and betterment of advanced fuel and materials through the irradiation tests. The HANARO fuel test loop was designed to match the CANDU and PWR fuel operating conditions. The accident analysis was performed by RELAP5/MOD3 code based on FTL system designs and determined the detail engineering specification of in-pile test section and out-pile systems. The accident analysis results of FTL system could be used for the fuel and materials designer to plan the irradiation testing programs. (author). 23 refs., 20 tabs., 178 figs.

  9. Memórias de uma história de um leitor

    Directory of Open Access Journals (Sweden)

    José Roberto Andrade Féres

    2014-07-01

    Full Text Available http://dx.doi.org/10.5007/1807-9288.2014v10n1p116 Entre histórias e estórias, entre origens e a “quimera da origem” (Michel Foucault, entre memórias e esquecimentos, entre arquivar e deletar, entre formatar e transformar, entre livros e e-books, entre leitores e leitores de e-books, entre palimpsestos e touchscreens, entre ensaio e relato, entre o que falta e o que excede, entre o que se veste com letras e o que se despe literalmente – este texto: trazendo à lembrança Peter Stallybrass (sobretudo “A vida social das coisas” e “O casaco de Marx”, palavras que buscam tratar as pessoas como coisas e as coisas como pessoas, biografando alguns leitores a partir da biografia de um leitor de e-books, e vice-versa.

  10. Filho de peixe sabe nadar: história e estórias com objetos

    Directory of Open Access Journals (Sweden)

    Ana Catarina Nunes

    2016-04-01

    Full Text Available O presente artigo apresenta e discute o projeto Filho de Peixe Sabe Nadar, desenvolvido no Museu Marítimo de Ílhavo entre 2010 e 2011, e dirigido a alunos do 4.º ano do 1.º ciclo do Ensino Básico do Município de Ílhavo. Com o objetivo de dar a conhecer a história e as memórias da pesca do bacalhau à linha em dóris de um só homem e em grandes navios de arrasto, pilar temático do Museu Marítimo de Ílhavo, o projeto visou, ainda, estreitar os laços entre gerações e entre a comunidade, procurando incentivar as crianças na procura de antepassados ligados a esta atividade. Ao longo do texto são descritas as várias etapas do projeto, assim como a contextualização teórica que as fundamentam. Através deste projeto, as crianças da comunidade local tiveram oportunidade de confrontar os conhecimentos adquiridos durante uma visita ao Museu Marítimo de Ílhavo e ao Navio Museu Santo André, com as experiências e testemunhos transmitidos pelos familiares ou amigos que entrevistaram e dos quais recolheram objetos que materializam essas vivências. Herança da comunidade ilhavense, a pesca do bacalhau pôde ser vista de forma distinta, com um contacto direto das crianças com os personagens reais da história da Grande Pesca e com os objetos que lhe estão associados. É a partir destes objetos que surgem as estórias desses mesmos personagens que, juntas constroem as memórias da pesca do bacalhau.

  11. Test

    DEFF Research Database (Denmark)

    Bendixen, Carsten

    2014-01-01

    Bidrag med en kortfattet, introducerende, perspektiverende og begrebsafklarende fremstilling af begrebet test i det pædagogiske univers.......Bidrag med en kortfattet, introducerende, perspektiverende og begrebsafklarende fremstilling af begrebet test i det pædagogiske univers....

  12. As fontes literárias no ensino de História

    Directory of Open Access Journals (Sweden)

    Joan Pagès Blanch

    2013-07-01

    Full Text Available Existem muitos recursos para levar aos alunos do ensino fundamental e médio o conhecimento e a compreensão do passado, boa parte deles são habitualmente utilizados nas salas de aula. Provavelmente um dos recursos com mais potencialidades educativas é a literatura e, em especial, o romance. Neste artigo propomos que a literatura pode contribuir para a aprendizagem do passado e qual é o valor educativo das fontes literárias no ensino de história e a sugestão de algumas ideias para o seu tratamento na prática.

  13. A Reportagem Jornalistica e a Memória - Histórias em Movimento

    Directory of Open Access Journals (Sweden)

    Jerusa de Oliveira Michel

    2016-03-01

    Full Text Available O trabalho analisa a partir de diferentes campos do conhecimento: antropologia, etnografia, etnicidade, território, história e memória em suas diversas abordagens, e o gênero jornalístico reportagem, a perspectiva de construção de conhecimento interdisciplinar, identificando os pontos de convergência entre os campos. Utiliza metodologia etnográfica/interdisciplinar, focando o trabalho da jornalista Eliane Brum à luz do referencial teórico construído.

  14. Comparison of Quick Lactose Intolerance Test in duodenal biopsies of dyspeptic patients with single nucleotide polymorphism LCT-13910C>T associated with primary hypolactasia/lactase-persistence Comparação do Teste Quick de Intolerância à Lactose em biópsias duodenais de pacientes dispépticos com polimorfismo de nucleotídeo único LCT-13910C>T associado com hipolactasia primária/lactase persistente

    Directory of Open Access Journals (Sweden)

    Rejane Mattar

    2013-01-01

    Full Text Available PURPOSE: To analyze the usefulness of Quick Lactose Intolerance Test in relation to the genetic test based on LCT-13910C>T genotypes, previously validated for clinical practice, for primary hypolactasia/lactase-persistence diagnosis. METHODS: Thirty-two dyspeptic patients that underwent upper gastrointestinal endoscopy entered the study. Two postbulbar duodenal biopsies were taken for the Quick test, and gastric antral biopsy for DNA extraction and LCT-13910C>T polymorphism analysis. DNA was also extracted from biopsies after being used in the Quick Test that was kept frozen until extraction. RESULTS: Nine patients with lactase-persistence genotype (LCT-13910CT or LCT-13910TT had normolactasia, eleven patients with hypolactasia genotype (LCT-13910CC had severe hypolactasia, and among twelve with mild hypolactasia, except for one that had LCT-13910CT genotype, all the others had hypolactasia genotype. The agreement between genetic test and quick test was high (pOBJETIVO: Analisar a aplicabilidade do Teste Quick de Intolerância à Lactose em relação ao teste genético baseado nos genótipos LCT-13910C>T, previamente validado para a prática clínica, para diagnóstico de má digestão primária de lactose/digestão de lactose. MÉTODOS: Trinta e dois pacientes dispépticos submetidos à endoscopia digestiva entraram no estudo. Duas biópsias duodenais pós-bulbares foram empregadas no Teste Quick, e biópsia do antro gástrico para extração de DNA e análise do polimorfismo LCT-13910C>T. DNA também foi extraído de biópsias depois de terem sido usadas no teste Quick, e conservadas congeladas. RESULTADOS: Nove pacientes com genótipo de lactase persistente (LCT-13910CT ou LCT-13910TT tinham normolactasia, onze pacientes com genótipo de hipolactasia (LCT-13910CC tinham hipolactasia severa, e entre doze com hipolactasia leve, com exceção de uma que tinha genótipo LCT-13910CT, todos os demais tinham genótipo de hipolactasia. A concord

  15. Effect of in-pile degradation of the meat thermal conductivity on the maximum temperature of the plate-type U-Mo dispersion fuels

    International Nuclear Information System (INIS)

    Medvedev, Pavel G.

    2009-01-01

    Effect of in-pile degradation of thermal conductivity on the maximum temperature of the plate-type research reactor fuels has been assessed using the steady-state heat conduction equation and assuming convection cooling. It was found that due to very low meat thickness, characteristic for this type of fuel, the effect of thermal conductivity degradation on the maximum fuel temperature is minor. For example, the fuel plate featuring 0.635 mm thick meat operating at heat flux of 600 W/cm2 would experience only a 20 C temperature rise if the meat thermal conductivity degrades from 0.8 W/cm-s to 0.3 W/cm-s. While degradation of meat thermal conductivity in dispersion-type U-Mo fuel can be very substantial due to formation of interaction layer between the particles and the matrix, and development of fission gas filled porosity, this simple analysis demonstrates that this phenomenon is unlikely to significantly affect the temperature-based safety margin of the fuel during normal operation.

  16. Thermal conductivity of Na3(U/sub 1-y/Pu/sub y/)O4: A preliminary in-pile determination

    International Nuclear Information System (INIS)

    Lee, M.J.; Lambert, J.D.B.; Ukai, S.; Odo, T.

    1987-01-01

    During Run-Beyond-Cladding-Breach (RBCB) operation in an oxide LMR, the performance of a breached fuel element is intimately associated with the formation of fuel-sodium reaction product (FSRP), Na 3 (U/sub 1-y/Pu/sub y/)O 4 . In-pile experiments coupled with destructive examinations of breached fuel have consistently revealed noticeable changes in fuel structure accompanying FSRP formation at the fuel surface. Previous analyses have also indicated a significant impact of FSRP on fuel centerline temperature. Successful modeling of breached fuel thermal behavior therefore requires a reasonably accurate knowledge of the thermal properties of the FSRP, especially its thermal conductivity. But laboratory investigations have been scarce and limited to the Na/UO 2 system because of the toxicity of plutonium and hygroscopicity of the FSRP. Hence, post-irradiation observations of fuel samples remain the most amenable way of deriving the thermal conductivity of the FSRP. Such work is a spin-off of the RBCB program in the Experimental Breeder Reactor-II (EBR-II), a program jointly sponsored by the US Department of Energy and the Power Reactor and Nuclear Fuel Development Corporation of Japan

  17. Regulatory research / Pesquisa regulatória

    Directory of Open Access Journals (Sweden)

    Altair Souza de Assis

    2013-05-01

    Full Text Available We present in this paper the concept, importance, and scope of research into the regulatory framework of regulation and legislation, with a particular focus on legislation related to legal metrology. This study also describes a comparative analysis of the various forms of regulation and the associated regulatory research, with the ultimate goal of better defi ning the concept and to validate the need to have research groups within a country’s regulatory bodies. Based on this work, we conclude that regulatory research is a key factor in the success of any regulatory body’s activities. Such research helps to avoid the creation of absurd or impractical regulatory barriers to a country’s technological development, or worse, to permit “orphans,” that is, technologies that are outside regulatory control, as is currently the case. Indeed, for a country to have a robust technological infrastructure, especially if it is still a developing country, strong and competent regulatory control is essential. However, this must be balanced by an atmosphere that fosters continuous and consistent technological innovation, and such development must also be self-sustainable from economic, social, and environmental viewpoints. ------------------------------------------------ Apresenta-se neste trabalho o conceito, a importância e a abrangência da pesquisa regulatória no âmbito da regulação e da regulamentação, com foco particular na regulamentação relacionada à metrologia legal. Faz-se também uma análise comparativa entre as várias formas de regular e regulamentar, e as suas pesquisas regulatórias afi ns, tendo como meta principal situar melhor o conceito e validar a necessidade de se fazer pesquisa nos órgãos e agências regulatórias do país. Com base neste trabalho, concluímos que a pesquisa regulatória é um fator chave para o sucesso de qualquer plano de ação de regulação para os agentes regulatórios do país. Ela ajuda a

  18. ENSINO DE HISTÓRIA E MEMÓRIA SOCIAL: A ARGUMENTAÇÃO COMO POSSIBILIDADE PEDAGÓGICA PARA A HISTÓRIA ENSINADA

    Directory of Open Access Journals (Sweden)

    Patricia Bastos de Azevedo

    2010-12-01

    Full Text Available Este texto é fruto da pesquisa desenvolvida no mestrado em Educação, no período de 2000 a 2003, na Universidade Federal Fluminense. Buscou-se identificar como os elementos história e memória se constituem no espaço da sala de aula e produzem, assim, a história ensinada. A teoria habermasiana da ação comunicativa é o principal alicerce teórico desta pesquisa; dessa forma, procurou-se relacionar essa teoria com a construção da memória social e seu papel no fazer pedagógico da sala de aula de história.

  19. In-Pile Assemblies for Investigation of Tritium Release from Li2TiO3 Lithium Ceramic

    International Nuclear Information System (INIS)

    Shestakov, V.; Tazhibayeva, I.; Kawamura, H.; Kenzhin, Y.; Kulsartov, T.; Chikhray, Y.; Kolbaenkov, A.; Arinkin, F.; Gizatulin, Sh.; Chakrov, P.

    2005-01-01

    The description of algorithm to design in-pipe experimental ampoule devices (IPAD) is presented here, including description of IPAD design for irradiation tests of highly enriched lithium ceramics at WWR-K reactor. The description of the system for registration of tritium release from ceramics during irradiation is presented as well. Typical curve of tritium release from the IPAD during irradiation under various temperatures of the samples is shown here

  20. Program for in-pile qualification of high density silicide dispersion fuel at IPEN/CNEN-SP

    International Nuclear Information System (INIS)

    Silva, Jose E.R. da; Silva, Antonio T. e; Terremoto, Luis A.A.; Durazzo, Michelangelo

    2009-01-01

    The development of high density nuclear fuel (U 3 Si 2 -Al) with 4,8 gU/cm 3 is on going at IPEN, at this time. This fuel has been considered to be utilized at the new Brazilian Multipurpose Reactor (RMB), planned to be constructed up to 2014. As Brazil does not have hot-cell facilities available for post-irradiation analysis, an alternative qualifying program for this fuel is proposed based on the same procedures used at IPEN since 1988 for qualifying its own U 3 O 8 -Al (1,9 and 2,3 gU/cm 3 ) and U 3 Si 2 -Al (3,0 gU/cm 3 ) dispersion fuels. The fuel miniplates and full-size fuel elements irradiations should be tested at IEA-R1 core. The fuel characterization along the irradiation time should be made by means of non-destructive methods, including periodical visual inspections with an underwater video camera system, sipping tests for fuel elements suspected of leakage, and underwater dimensional measurements for swelling evaluation, performed inside the reactor pool. This work presents the program description for the qualification of the high density nuclear fuel (U 3 Si 2 -Al) with 4,8 gU/cm 3 , and describes the IPEN fuel fabrication infrastructure and some basic features of the available systems for non-destructive tests at IEA-R1 research reactor. (author)

  1. História, estórias e memórias mineiras em Guimarães Rosa

    Directory of Open Access Journals (Sweden)

    Francis Paulina Lopes da Silva

    2005-10-01

    Full Text Available Leitura de aspectos da cultura popular, presentes no processo de construção ficcional  de Guimarães  Rosa, o “contista de contos críticos”, que confessara: "Não preciso  in venta r contos,  eles vêm até  mim”. Pela alquimia da palavra e m seu estado primitivo, a fusão do  real e ficcional com o obsessiva defesa de que "a legítima literatura  deve servida". A multiplicação do imaginário rural mineiro n a narrativa rosiana, especificamente, em contos de Tutaméia e Ave, Palavra. Historia e estória n o cotidiano do  povo  do sertão  mineiro. Pelo  jogo da memória narrativa popular, a construção da identidade cultural sertaneja e a recriação do mito: "No sertão, o homem é o eu que ainda não encontrou o tu:  por isso ali os anjos ou o diabo ainda  manuseiam a língua".

  2. Comparação entre o teste de despertar e a monitoração neurofisiológica intra-operatória com potencial evocado somato-sensitivo nas cirurgias de escoliose Comparación entre el teste de despertar y la monitorización neurofisiológica intraoperatoria con potencial evocado somato sensorial en las cirugías de escoliosis Comparison between the wake-up test and the intra-operative neurophysiologic monitoring with somato-sensitive evoked potentials in surgery for scoliosis

    Directory of Open Access Journals (Sweden)

    Eduardo Barros Puertas

    2009-03-01

    Full Text Available OBJETIVO: comparar a incidência de lesões neurológicas em cirurgias corretivas de curvas rígidas de escoliose idiopática, utilizando-se somente o teste do despertar e utilizando-se a monitoração neurofisiológica intra-operatória por meio dos Potenciais Evocados Somato-Sensitivo (PESS. MÉTODOS: foram realizadas 111 cirurgias para correção de escoliose idiopática, com curvas rígidas por meio de instrumentação e artrodese pela via posterior, no período de janeiro de 1985 a maio de 2001. Os procedimentos foram divididos em dois grupos, sendo 80 pacientes operados sem a monitoração intra-operatória, utilizando somente o teste do despertar, no período de janeiro de 1985 a janeiro de 1998. A partir de maio de 1998, as cirurgias passaram a ser monitoradas com potencial evocado somato-sensitivo (PESS, para prevenção de lesão neurológica, formando um segundo grupo de 31 pacientes. RESULTADOS: no primeiro grupo, um paciente teve lesão neurológica irreversível e quatro pacientes tiveram lesão neurológica reversível. Entre os 31 pacientes do segundo grupo, com monitoração neurofisiológica sensitiva durante a cirurgia, oito apresentaram lesão neurológica reversível constatada no intra-operatório, sem nenhuma repercussão clínica após o procedimento. CONCLUSÃO: os resultados apresentados sugerem a eficácia da monitoração intra-operatória, com o potencial evocado somato-sensitivo, para a prevenção de lesões neurológicas, nas cirurgias corretivas de curvas rígidas na escoliose idiopática.OBJETIVO: comparar la incidencia de lesiones neurológicas en cirugías correctivas de curvas rígidas de escoliosis idiopática, utilizado la prueba del despertar y la monitoración neurofisiológica intra-operatória de por medio de Potenciais Evocados Somato-Sensitivos (PESS. MÉTODOS: fueron ejecutadas 111 cirugías correctivas de escoliosis idiopática rígida, por medio de instrumentación y artrodesis por vía posterior

  3. SGSI. Mútua interuniversitària

    OpenAIRE

    Muñoz Nieto, Jordi

    2017-01-01

    Aquest Projecte planteja l'establiment de les bases per portar a terme la implementaciot d'un SGSI (Sistema de Gestió de la Seguretat de la informació), en base a la Normativa Internacional de Referència ISO/IEC 27001:2013. Aquest es vol englobar en un Sistema Integral de Gestió d'una empresa fictícia anomenada Mutua Interuniversitària. Totes les dades tant de l'empresa com del entorn fictici o ubicació de la mateixa son dades fictícies emprades per portar a terme aquest treball. ...

  4. Inferindo personalidade por meio de estórias

    Directory of Open Access Journals (Sweden)

    Guilherme Gomes Cardoso

    2014-11-01

    Full Text Available Recentemente aspectos sutis do ser humano começaram a ser estudados e utilizados por computadores, um desses é a personalidade. Existem vários estudos que analisam como estruturá-la e extraí-la computacionalmente. No entanto, um dos gargalos no seu estado da arte atual é a forma não sutil para inferir personalidade do usuário. Este trabalho tem como objetivo mostrar o relato de uma experiência que demonstra os passos iniciais e os resultados parciais de uma pesquisa em andamento sobre um método alternativo e mais sutil para inferir a personalidade do usuário. Os resultados apresentam o uso de histórias como uma abordagem promissora, entretanto demanda novos testes baseados em metodologias estatisticamente mais consistentes.

  5. Post irradiation examination of type 316 stainless steels for in-pile Oarai water loop No.2 (OWL-2)

    International Nuclear Information System (INIS)

    Shibata, Akira; Kimura, Tadashi; Nagata, Hiroshi; Aoyama, Masashi; Kanno, Masaru; Ohmi, Masao

    2010-11-01

    The Oarai water loop No.2 (OWL-2) was installed in JMTR in 1972 for the purpose of irradiation experiments of fuel element and component material for light water reactors. Type 316 stainless steels (SSs) were used for tube material of OWL-2 in the reactor. But data of mechanical properties of highly irradiated Type 316 SSs has been insufficient since OWL-2 was installed. Therefore surveillance tests of type 316 SSs which were irradiated up to 3.4x10 25 n/m 2 in fast neutron fluence (>1 MeV) were performed. Meanwhile type 316 stainless steel (SS) is widely used in JMTR such as other irradiation apparatus and irradiation capsule, and additional data of type 316 SSs irradiated higher is required. Therefore post irradiation examinations of surveillance specimens made of type 316 SSs which were irradiated up to 1.0x10 26 n/m 2 in fast neutron fluence were performed and reported in this paper. In this result of surveillance tests of type 316 SSs irradiated up to 1.0x10 26 n/m 2 , tensile strength increase with increase of Neutron fluence and total elongation decreased with increase of Neutron fluence compared to unirradiated specimens and specimens irradiated up to 3.4x10 25 n/m 2 . This tendency has good agreement with results of 10 24 - 10 25 n/m 2 in fast neutron fluence. More than 37% in total elongation was confirmed in all test conditions. It was confirmed that type 316 SS irradiated up to 1.0x10 26 n/m 2 in fast neutron fluence has enough ductility as structure material. (author)

  6. O tempo e o mundo: defesa de uma história planetária

    Directory of Open Access Journals (Sweden)

    Gustavo Velloso

    2016-12-01

    Full Text Available Resenha do livro: GRUZINSKI, Serge. As quatro partes do mundo: história de uma mundialização. Tradução de Cleonice Paes Barreto Mourão e Consuelo Fortes Santiago. Belo Horizonte: Editora UFMG; São Paulo: Edusp, 2014.

  7. FONTES PRIMÁRIAS: SABERES EM MOVIMENTO

    Directory of Open Access Journals (Sweden)

    CAMPOS Edson Nascimento

    1997-01-01

    Full Text Available Este artigo trata as fontes primárias à luz de uma epistemologia que submete a investigação e a pesquisa à ação desconstrutora dos sujeitos: as fontes, por isso, saem da posição de "ponto primacial" para a de "ponto relacional". E, aí, a linguagem se transforma em relação de intertextualidade, pois a contradição marca o sentido da interdependência e, nisso, a significação põe a força da instabilidade na relação do sujeito com o objeto. Este, aliás, aberto à abordagem múltipla do real, integra a relação de interdisciplinaridade, e, assim, vêm surgindo, por exemplo, explicações iluminadoras com as articulações de Educação, Pedagogia, Linguagem, História.

  8. A rota como memória

    Directory of Open Access Journals (Sweden)

    Patrick Fraysse

    Full Text Available No contexto de estudo do patrimônio por um ponto de vista comunicacional, este artigo permitiu-nos visualisar um objeto de comunicação por excelência « a estrada » como portador de informação a decifrar e a interpretar um documento, mas também como um repositário da memória coletiva, quer dizer um monumento. Paralelamente, a patrimonialização dos monumentos, dos conjuntos arquiteturais e sobretudo dos itinerários que os religam, dito de outra maneira, da estrada, assim como a sua documentarização (relatos de viagens, guias, bancos de dados participam de uma nova institucionalização da memória integrante também das estradas míticas como o caminho de São Tiago na França ou a famosa estrada 66 nos Estados-Unidos.

  9. A biotecnologia na agropecuária

    Directory of Open Access Journals (Sweden)

    João Lúcio de Azevedo

    1986-11-01

    Full Text Available This review reports the use of biotechnology in agriculture and animal husbandry. The main techniques and the most important products both in experimental stage or in commercial use are reported. The work intends to give a global vision to the theme, chronologically and spacely, showing the main lines of research and what has been obtained in this area. The techniques and products that are related to genetics and breeding are emphasized. Revisão Bibliográfica do emprego da biotecnologia na agropecuária, mostrando um levantamento das técnicas mais promissoras e de seus principais produtos, tanto em fase experimental como em uso comercial. Pretende-se dar uma visão global do assunto, cronológica e espacialmente, não se prendendo à detalhes, mostrando, em Unhas gerais, o que foi feito e o que se faz, atualmente, em biotecnologia. As técnicas e produtos que influenciam a área de genética e melhoramento genético na agropecuária, são enfatizadas.

  10. Risk analysis of the delayed ettringite formation in pile caps foundation in the metropolitan region of Recife - PE - Brasil

    Directory of Open Access Journals (Sweden)

    I. F. Torres

    Full Text Available ABSTRACT Currently, there is an awareness that is critical to assess the durability characteristics of concrete with as much attention as the mechanical properties. The durability of concrete structures can often be affected by chemical attacks, jeopardizing its performance and security. When concrete is subjected to high temperature at early ages, many physical and chemical changes in hardened concrete may occur. It iswidely accepted that concrete subjected to these conditions of temperature and exposed to moisture is prone to cracking due to Delayed Ettringite Formation (DEF. This work aims at providing a DEF risk analysis on foundation pile caps at the Metropolitan Region of Recife - PE. Temperature rise measurement was performed in situ at 5 different caps through datalogger and thermocouples equipments. Furthermore, the Duggan test was performed in order to assess the level of expansion of 3 cements studied: X (CP II E 40, Y (CP II F 32 and Z (CP V ARI RS. Simultaneously, the chemical compositions of these cements and their respective clinkers were quantified by analysis of X-ray fluorescence (XRF. The cement X (CP II E 40 showed the chemical characteristics favoring with more intensity DEF and, as a result, higher level of expansion in the test Duggan. It is noteworthy that incorporation of metakaolin (8% and 16% and silica fume (5% and 10% showed mitigating potential of expansions. It is important to point out that all factors related to thermal properties and chemical composition of the concrete used in the region converge to a condition of ideal susceptibility for triggering DEF. Therefore, it is essential at least minimum and basic requirements in the design specification in order to avoid high temperatures in the massive concrete elements, preventing them from delayed ettringite formation.

  11. Considerações sobre eficiência administrativa relacionado aos exames de ultra-sonografia, tomografia computadorizada e ressonância magnética nas afecções orbitárias Reasons for the administrative efficiency related to ultrassonography, computed tomography and magnetic resonance imaging tests in orbital diseases

    Directory of Open Access Journals (Sweden)

    Magno Watanabe

    2007-12-01

    Full Text Available OBJETIVOS: Enfocar os exames de ultra-sonografia (US, tomografia computadorizada (TC e ressonância magnética (RM, levantando, revisando e discutindo as seguintes medidas na melhoria da eficiência destes procedimentos na órbita: 1- Defasagem dos honorários médicos; 2- Vantagens e desvantagens dos exames; 3- Diretrizes clínicas. MÉTODOS: No período de julho de 2002 a março de 2003, realizou-se um levantamento dos valores dos exames orbitários de US, TC e RM pagos pelo Sistema Único de Saúde - SUS, operadoras de planos e seguros de saúde e particulares cobrados em três clínicas oftalmológicas e três clínicas radiológicas referenciadas. Pesquisa bibliográfica e revisão na literatura dos referidos exames e suas diretrizes clínicas nas afecções orbitárias. RESULTADOS: 1- Valores dos exames em reais (R$: US: 9,05 - SUS / 81,77 - AMB 90 / 57,01 - AMB/CIEFAS 93 / 102,00 - AMB/LPM 99 / 158,33 - particular. TC: 86,76 - SUS / 193,70 - AMB 90 / 196,30 - AMB/CIEFAS 93 / 204,12 - AMB/LPM 99 / 255,33 - particular. RM: 268,75 - SUS / 475,80 - AMB 90 e AMB/CIEFAS 93 / 472,50 - AMB/LPM 99 / 563,33 - particular; 2- Vantagens e desvantagens dos exames descritos de acordo com a revisão da literatura; 3- As doenças da órbita não têm ainda listadas suas diretrizes. CONCLUSÃO: Estes exames são os mais utilizados e consagrados pela sua eficácia no estudo da órbita. Para uma maior eficiência, devemos considerar as seguintes recomendações administrativas: 1- Modernização e atualização das tabelas de honorários com índices mínimos e mais justos na remuneração dos exames com reembolso dos insumos utilizados como filmes radiológicos e contrastes: 2- Promover e estimular a educação médica continuada, evitando o excesso de exames desnecessários ou inapropriados: 3- Elaboração e implementação de diretrizes e protocolos clínicos baseados em evidências nas principais doenças orbitárias que possam ser utilizados como refer

  12. Comparative studies of commercially available T4-RIA-kits. Pt. 2

    International Nuclear Information System (INIS)

    Schmidt, H.A.E.; Lipke, P.

    1978-01-01

    The investigation of the tested commercially available T 4 -RIA-Kits have shown that: The separation of hypo-, eu- and hyperthyroid values is better with kits a) and f) than with b), c), d) and e), though all kits give acceptable values under routine operating conditions, kit b) takes less time and work than the other tested kits, depending on the kit used, the time needed for 100 determinations varies between 1,5 and 4 hr. A general recommendation for one of the tested T 4 -RIA-Kits cannot be made since the choice of a kit depends not only on the criteria discussed but also on local circumstances. (orig.) [de

  13. Development of 3-Pin Fuel Test Loop and Utilization Technology

    International Nuclear Information System (INIS)

    Lee, Chung Young; Sim, B. S.; Lee, C. Y.

    2007-06-01

    The principal contents of this project are to design, fabricate and install the steady-state fuel test loop in HANARO for nuclear technology development. Procurement and, fabrication of main equipment, licensing and installation for fuel test loop have been performed. Following contents are described in the report. 1. Design - Design of the In-pile system and Out pile system 2. Fabrication and procurement of the equipment - Fabrication of the In-pile system and In-pool piping - Fabrication and procurement of the equipment of the out-pile system 3. Acquisition of the license - Preparation of the safety analysis report and acquisition of the license - Pre-service inspection of the facility 4. Installation and commissioning - Installation of the FTL - Development of the commissioning procedure

  14. Safety test facilities. Needs and concepts. A French evaluation

    International Nuclear Information System (INIS)

    Tretiakoff, O.; Bailly, J.

    1976-01-01

    The fuel behaviour of LMFBRs in the event of an accident has been tested in-pile in the SCARABEE program (local blockage, sudden flow reduction and pump coast-down at constant power). These tests will be carried on in the framework of an international cooperation on irradiated fuels: this is the purpose of the CABRI and SCARABEE N programs. All those studies should enable to assess safety margins between accident conditions and the technical specifications of the reactor. The paper explains how a logical set of simple observations has led to the present state of the Cadarache in-pile experimental safety program and how it may help to find the way in a dense forest of both technical and psychological difficulties

  15. Safety test facilities. Needs and concepts. A French evaluation

    International Nuclear Information System (INIS)

    Tretiakoff, O.; Bailly, J.

    1976-01-01

    The fuel behavior of LMFBRs in the event of an accident has been tested in-pile in the SCARABEE program. These tests will be carried on in the framework of an international cooperation on irradiated fuels: this is the purpose of the CABRI and SCARABEE N programs. All those studies should enable to assess safety margins between accident conditions and the technical specifications of the reactor. The purpose of this paper is to explain how a logical set of simple observations has led us to the present state of the Cadarache in-pile experimental safety program and how it may help us to find our way in a dense forest of both technical and psychological difficulties

  16. A comparison study between RIA and HI procedures for Rubella in a small laboratory practice

    International Nuclear Information System (INIS)

    Kardos, L.A.

    1983-01-01

    Two different kits of Rubella Antibody determinations were compared; one, the HI, or Hemoagglutination Inhibition, and the other, an RIA or Radioimmunoassay. Both procedures were quite accurate, adequate, and reproducible, but the RIA procedure was found to be slightly more sensitive than the HI procedure. Two hundred and fifty pregnant women were tested and classified as to origin, background, and race. There was no difference in determination results on those bases. The American Black women had a higher percentage of immunity than the American Anglo-Saxon and European background women. The Latin American patients ranged with the American Black women along with the SE Asian women as far as the percent of immunity was concerned. RIA appears to be more sensitive than HI, especially where a finer delineation is required between immune and non-immune patient results. As far as performance is concerned, the RIA procedure is less complicated and, therefore, less vulnerable to human error. The HI procedure, though quite reproducible and an excellent diagnostic tool, is more time consuming and more involved so the chance for human error in that procedure might be increased

  17. Optical Fier Based System for Multiple Thermophysical Properties for Glove Box, Hot Cell and In-Pile Application

    Energy Technology Data Exchange (ETDEWEB)

    Ban, Heng

    2017-11-30

    Thermal diffusivity of materials is of interest in nuclear applications at temperatures in excess of 2000°C. Commercial laser flash apparatus (LFA) that heats samples with a furnace typically do not reach these elevated temperatures nor are they easily adapted to a glove-box or hot cell environment. In this research, we performed work on an experimental technique using single laser surface heating, i.e. heating the disk sample only at its front surface with the continuous wave (CW) laser, to allow measurement of thermal diffusivity at very high temperatures within a small chamber. Thermal diffusivity is measured using a separate pulsed laser on the front side and IR detector on the rear side. The new way of heating provides easy operation in comparison to other heating methods. The measurement of sample reference temperature is needed for the measured thermal diffusivity. A theoretical model was developed to describe transient heat transfer across the sample due to the laser pulse, starting from the steady state temperature of the sample heated by the CW laser. The experimental setup was established with a 500W CW laser and maximum 50 Joule pulse laser irradiated at the front surface of the sample. The induced temperature rise at the rear surface, along with the steady-state temperature at the front surface, was recorded for the determination of thermal diffusivity and the sample temperature. Three samples were tested in vacuum over a wide temperature range of 500°C to 2100°C, including graphite, Inconel 600 and tungsten. The latter two samples were coated with sprayed graphite on their front surfaces in order to achieve surface absorption/emission needs, i.e. high absorptivity of the front surface against relatively low emissivity of the rear surface. Thermal diffusivity of graphite determined by our system are within a 5% difference of the commercial LFA data at temperatures below 1300°C and agree well with its trend at higher temperatures. Good agreement

  18. Heavy-ion LINAC development for the US RIA project

    Indian Academy of Sciences (India)

    The Nuclear Science Community in the Unites States has unanimously concluded that developments in both nuclear science and its supporting technologies make building a world-leading Rare-Isotope Accelerator (RIA) facility for production of radioactive beams the top priority. The RIA development effort involves several ...

  19. Computational needs for the RIA accelerator systems

    International Nuclear Information System (INIS)

    Ostroumov, P.N.; Nolen, J.A.; Mustapha, B.

    2006-01-01

    This paper discusses the computational needs for the full design and simulation of the RIA accelerator systems. Beam dynamics simulations are essential to first define and optimize the architectural design for both the driver linac and the post-accelerator. They are also important to study different design options and various off-normal modes in order to decide on the most-performing and cost-effective design. Due to the high-intensity primary beams, the beam-stripper interaction is a source of both radioactivation and beam contamination and should be carefully investigated and simulated for proper beam collimation and shielding. The targets and fragment separators area needs also very special attention in order to reduce any radiological hazards by careful shielding design. For all these simulations parallel computing is an absolute necessity

  20. Correlação entre Testes para Avaliação da Vitalidade Fetal, pH da Artéria Umbilical e os Resultados Neonatais em Gestações de Alto Risco Correlation between the Assessment of Fetal Well-being, Umbilical Artery pH at Birth and the Neonatal Results in High-risk Pregnancies

    Directory of Open Access Journals (Sweden)

    Rossana Pulcineli Vieira Francisco

    2000-09-01

    Full Text Available Objetivos: analisar a relação entre valores de pH no nascimento, testes de vitalidade fetal e resultados neonatais. Métodos: foram incluídas 1346 pacientes com gestação de alto risco atendidas no Setor de Vitalidade Fetal do HCFMUSP. Para estudo do bem-estar fetal foram realizados exames de cardiotocografia, perfil biofísico fetal e índice de líquido amniótico. Após o parto foram obtidos os seguintes parâmetros dos recém-nascidos: idade gestacional no parto, sexo e peso dos recém-nascidos, índices de Apgar de 1º e 5º minutos, pH da artéria umbilical no nascimento e a ocorrência de óbito neonatal. Para estudo destes resultados neonatais, os casos foram divididos em quatro grupos: G1 (pH ou = 7,20. Resultados: a cardiotocografia anormal relacionou-se com valores de pH inferiores a 7,20 (p = 0,001. Resultados anormais do perfil biofísico fetal (Purpose: to analyze the relationship between the values of pH at birth, fetal surveillance examinatios and neonatal results. Methods: one thousand, three hundred and forty-six high-risk pregnancies were evaluated at the Fetal Surveillance Unit. The assessment of fetal well-being included cardiotocography, fetal biophysical profile and amniotic fluid index. After birth, the perinatal results (gestational age at birth, birth weight, Apgar scores at 1st and 5th minutes, umbilical cord pH at birth were collected. To study the results, the patients were divided into four groups: G1 (pH or = 7.20. Results: the abnormal patterns of cardiotocography were associated with pH at birth inferior to 7.20 (p = 0.001. Abnormal results of the fetal biophysical profile (<=4 were related to decrease in pH values at birth (p<0.001. The adverse neonatal outcomes were associated with acidosis at birth, and they were selected to be analyzed by the logistic regression model, showing that the odds ratio of each adverse neonatal outcome increases significantly when the values of pH at birth decrease. Conclusions

  1. Em nome da memória

    Directory of Open Access Journals (Sweden)

    Maria Auxiliadora de Almeida Cunha Arantes

    Full Text Available Este texto apresenta cinco breves estórias sobre o assassinato de psicólogas e de estudantes de Psicologia que se engajaram na luta de resistência. Todas foram executadas durante a ditadura civil militar, na década de 70, e um dos casos contou com a participação da Operação Condor. As práticas extremamente cruéis de tortura, o ocultamento de provas, a simulação de morte por suicídio, o abandono de corpos em locais públicos na tentativa de desresponsabilizar os executores tornaram-se evidentes nos laudos necroscópicos posteriormente acessados e/ou em depoimentos de advogados e familiares. A intenção do texto é permitir aos psicólogos e psicólogas o acesso às histórias de jovens mulheres que também escolheram a Psicologia como profissão e que foram impedidas precocemente de viver e de realizar projetos próprios. Disponibilizar informações sobre esses fatos e oferecer esclarecimentos sobre a prática da tortura convida à participação cidadã no processo de aperfeiçoamento do Estado Democrático de Direito que avança em nosso país com a instalação da Comissão da Verdade.

  2. O PESO DA MEMÓRIA: LITERATURA E HISTÓRIA NA ACÁDIA.

    OpenAIRE

    Finney, James de

    2012-01-01

    A história está no centro da literatura e da identidade dos acadianos, uma história extremamente rica, de consonâncias míticas e bíblicas: um povo inocente é forçado a dispersar-se pelo continente americano e pela Europa, de 1755 a 1762, condenado ao exílio e à errância, antes de poder reconquistar penosamente seu direito à existência. Entretanto, a força emotiva e a coerência dessa narrativa constituem, para os acadianos, uma faca de dois gumes: numerosos autores, ao difundi-la, confinaram a...

  3. Parâmetros genéticos para a produção de leite de controles individuais de vacas da raça Gir estimados com modelos de repetibilidade e regressão aleatória Estimation of genetic parameters for test day milk records of first lactation Gyr cows using repeatability and random regression animal models

    Directory of Open Access Journals (Sweden)

    Claudio Napolis Costa

    2005-10-01

    número de estimativas negativas entre as PLC do início e fim da lactação do que a FAS. Exceto para a FAS, observou-se redução das estimativas de correlação genética próximas à unidade entre as PLC adjacentes para valores negativos entre as PLC no início e no fim da lactação. Entre os polinômios de Legendre, o de quinta ordem apresentou um melhor o ajuste das PLC. Os resultados indicam o potencial de uso de regressão aleatória, com os modelos LP5 e a FAS apresentando-se como os mais adequados para a modelagem das variâncias genética e de efeito permanente das PLC da raça Gir.Data comprising 8,183 test day records of 1,273 first lactations of Gyr cows from herds supervised by ABCZ were used to estimate variance components and genetic parameters for milk yield using repeatability and random regression animal models by REML. Genetic modelling of logarithmic (FAS, exponential (FW curves was compared to orthogonal Legendre polynomials (LP of order 3 to 5. Residual variance was assumed to be constant in all (ME=1 or some periods of lactation (ME=4. Lactation milk yield in 305-d was also adjusted by an animal model. Genetic variance, heritability and repeatability for test day milk yields estimated by a repeatability animal model were 1.74 kg2, 0.27, and 0.76, respectively. Genetic variance and heritability estimates for lactation milk yield were respectively 121,094.6 and 0.22. Heritability estimates from FAS and FW, respectively, decreased from 0,59 and 0.74 at the beginning of lactation to 0.20 at the end of the period. Except for a fifth-order LP with ME=1, heritability estimates decreased from around 0,70 at early lactation to 0,30 at the end of lactation. Residual variance estimates were slightly smaller for logarithimic than for exponential curves both for homogeneous and heterogeneous variance assumptions. Estimates of residual variance in all stages of lactation decreased as the order of LP increased and depended on the assumption about ME

  4. A PROJEÇÃO IDENTITÁRIA NO "MURAL DE HISTÓRIAS" DE MAYSA

    Directory of Open Access Journals (Sweden)

    Guilherme Moreira Fernandes

    2011-06-01

    Full Text Available Neste artigo, fazemos uma breve reflexão sobre os mecanismos de projeção e formação identitárias presentes no espaço "Mural de Histórias", do portal da minissérie Maysa: quando fala o coração, exibida em 2009 pela TV Globo. A metodologia da análise de conteúdo nos permitiu categorizar as várias facetas da cantora comentadas pelos internautas. Utilizando os estudos de Aluizio Trinta sobre os mecanismos de projeção-identificação, pudemos inferir que parcela dos internautas se dispôs a refletir sobre a identidade deles. Também percebemos que as múltiplas plataformas criadas pela emissora permitem uma aproximação maior do público e um espaço para manifestações de alegrias e angústias.

  5. Memória e história: Hannah Arendt em diálogo com Walter Benjamin

    Directory of Open Access Journals (Sweden)

    Magalhães, Marionilde Brepohl de

    2006-01-01

    Full Text Available A autora tem como proposta refletir sobre o papel da memória e da História em nossa cultura contemporânea, através de uma aproximação ao pensamento de Hannah Arendt e Walter Benjamin

  6. Feeding Supplementation And Radioimmunoassay (RIA) Technique For The Improvement Of artificial Insemination (AI) Efficiency

    International Nuclear Information System (INIS)

    Tjiptosumirat, Totti; Supandi, Dadang; Firsoni

    2002-01-01

    Recent research activities have showed that RIA techniques may be use as a tool in the improvement of dairy cattle AI in . Cisurupan district, Garut. Although already indicate in the previous research, with a small number of dairy cattle tested, a more in depth study on the utilization of RIA for the improvement of AI efficiency is still required. It is indicated from the previous experiment results that administration of feeding supplementation might improved the efficiency of reproductive performance of dairy cattle. The current Study is a continuation from the previous study with a larger number of dairy cattle and wider area covered. The experiment is aimed to monitor the impact of feeding supplementation on the reproductive performance of dairy cattle using Artificial Insemination Database Application (AIDA) and RIA technique. Result from this study indicated that feeding supplementation improved conception rate between pre-supplemented and post-supplemented dairy cattle; 25% vs 40%, respectively, therefore improve ratio of Service per Conception of 4.0 vs 2.3, respectively for pre-supplemented and post-supplemented dairy cattle. Result of this experiment also showed that RIA might be use as an effective tool in monitoring the early failure of AI compared to if just relying on the conventional method, the rectal palpation. However, due to an increase in milk production as a result of feeding supplementation, tanners tend to lengthen the lactation period from 10.20 ± 0.5 months to 11.8 ± 0.6 months, respectively in dairy cattle pre-supplemented and post-supplemented. It can be conclude from this study that supplementation feeding improve reproductive performance. However, even AIDA and RIA may be of effective tool in monitoring the reproductive performance of dairy cattle, as an holistic approach for an improvement dairy farm management is still required due to other factors play important role for AI efficiency

  7. Memória e cidadania nos acervos de história oral e mídia digital

    OpenAIRE

    Goulart, Elias Estevão; Perazzo, Priscila Ferreira; Lemos, Vilma

    2010-01-01

    Este texto tem como proposta discutir a importância da constituição de acervos de história oral, levando em consideração a difusão da memória e o exercício da cidadania a partir dela, bem como as relações de poder envolvidas nesse processo. As técnicas de história oral possibilitam a organização de um acervo de relatos de história de vida que, no seu conjunto, levam à recuperação da identidade coletiva e da memória da comunidade. São os sentimentos de pertencimento a um grupo, garantindo por ...

  8. Recidiva de urticária crônica decorrente de reinfecção por Helicobacter pylori

    Directory of Open Access Journals (Sweden)

    Dayanne Mota V. Bruscky

    2013-06-01

    Full Text Available OBJETIVO: Descrever, em uma adolescente do sexo feminino, o caso clínico de urticária crônica associado à infecção por Helicobacter pylori confirmado em dois momentos distintos, com melhora após a terapêutica antibacteriana. DESCRIÇÃO DO CASO: Paciente do sexo feminino, 13 anos, procurou atendimento médico com urticária crônica e dores epigástricas sem resposta ao tratamento medicamentoso. Os exames solicitados para investigação complementar apresentaram-se normais, exceto a endoscopia digestiva alta com biópsia, que evidenciou gastrite crônica ativa moderada associada ao Helicobacter pylori. Foi iniciado o tratamento adequado para a bactéria em questão e a paciente apresentou remissão dos sintomas. Nova endoscopia digestiva alta para controlar o tratamento após nove meses estava normal. Cinco anos depois, a paciente procurou novamente o ambulatório queixando-se de retorno do quadro de urticária e dores epigástricas. Ela se encontrava em uso de anti-histamínico, sem melhora. Foi novamente submetida a protocolo de exames para investigar urticária crônica, com resultados dentro da normalidade. Foi submetida à endoscopia digestiva alta, que apresentou teste da urease positivo. Iniciou-se então novo tratamento para Helicobacter pylori por sete dias, com desaparecimento da urticária crônica e das dores epigástricas. COMENTÁRIOS: O caso relatado sugere relação causal entre o diagnóstico positivo para o Helicobacter pylori e a ocorrência do quadro de urticária crônica, com instituição de terapêutica eficaz para tal bactéria e remissão dos sintomas. A urticária crônica é uma doença de etiopatogenia complexa e, apesar das controvérsias, as evidências do envolvimento do Helicobacter pylori com doenças extraintestinais vêm crescendo, entre elas a urticária crônica.

  9. Fishes of the Vitória-Trindade Chain: Biodiversity, Biogeography and Evolution

    OpenAIRE

    Pinheiro, Hudson Tercio

    2016-01-01

    Studies on the ecology and biogeography of seamounts and oceanic islands have advanced substantially in the last 60 years. However, few seamounts have been scientifically characterized, with basic aspects of their biodiversity still unknown and many hypotheses not empirically tested. Consequently, the role of seamounts in the evolution for marine species is still unclear. In the south Atlantic, the Vitória-Trindade Chain (VTC) extends ca. 1,200 km offshore the Brazilian coast. For a long time...

  10. Clinical relevancy of a sensitive TSH-RIA

    International Nuclear Information System (INIS)

    Seidel, C.; Ziegelitz, D.; Weber, A.; Dittmer, T.; Gerl, H.; Knappe, G.; Correns, H.J.

    1982-01-01

    Based on a sensitive TSH-RIA (measuring range 0.2-25 mU/l, 50%-intercept 2 mU/l, coefficients of between-assay-variation 5-10%) and on nearly 1200 cases, it is demonstrated that clinical results can be received by determination of basal serum TSH alone. Values above 0.5 mU TSH/l indicate positive TRH tests in a good correlation between increasing basal concentrations and pituitary TSH reserve. TSH levels below 0.3 mU/l proceed with negative TRH tests. In selected healthy subjects, we found all TSH values between 0.7 and nearly 5 mU/l (x-bar = 1.99). In euthyroid goiters TSH levels are normally in the same range, but in nodular goiters, subnormal values were found accumulated. TSH levels below 0.3 mU/l are helpful to discover non-suppressibility. Hormone treatment of goiters is successful above all in case of high-normal pretherapeutic TSH values. 'Fine-tuning' of hormone dosage (goiter treatment, postoperative prophylaxis, suppression therapy in thyroid carcinoma) as well as monitoring of thyrotoxicosis treatment is recommended to be performed by means of basal TSH determination. In pituitary disorders, thyroid hormone treatment seems to be necessary only at TSH levels below 0.5 mU/l. Combination of basal TSH and total T 3 is economical and describes nearly all functional situations in diagnosis and treatment of thyroid diseases. (author)

  11. Evaluation of the Coat-A-Count sup 125 I fentanyl RIA: Comparison of sup 12 5I RIA and GC/MS-SIM for quantification of fentanyl in case urine specimens

    Energy Technology Data Exchange (ETDEWEB)

    Watts, V.W.; Caplan, Y.H. (Mesa Police Crime Laboratory, AZ (USA))

    1990-09-01

    The Coat-A-Count solid phase {sup 125}I Fentanyl Radioimmunoassay was evaluated with respect to linearity and precision using equine urine fortified with fentanyl and then compared with a gas chromatographic/mass spectrometric method for quantification of fentanyl in urine. The RIA assay was found to be linear over the urine fentanyl concentration range of 0.25 to 7.5 ng/mL and precise with coefficients of variation (CV) ranging from 9.6 to 19.3%. The RIA calibrators, ranging in fentanyl concentrations from 0.25 to 7.5 ng/mL, and controls, at mean fentanyl concentrations of 0.46 and 1.32 ng/mL, were compared by both the RIA and GC/MS methods. The cross-reactivity with the {sup 125}I RIA test was determined for the fentanyl metabolites, norfentanyl and hydroxyfentanyl, and found to be 5% and 35%, respectively. The illicit fentanyl analogs were found to show significant cross-reactivity, ranging from 20 to 100%. The {sup 125}I RIA was compared to GC/MS quantifications of fentanyl in 35 positive and 20 negative case urine specimens.

  12. Evaluation of the Coat-A-Count 125I fentanyl RIA: Comparison of 125I RIA and GC/MS-SIM for quantification of fentanyl in case urine specimens

    International Nuclear Information System (INIS)

    Watts, V.W.; Caplan, Y.H.

    1990-01-01

    The Coat-A-Count solid phase 125 I Fentanyl Radioimmunoassay was evaluated with respect to linearity and precision using equine urine fortified with fentanyl and then compared with a gas chromatographic/mass spectrometric method for quantification of fentanyl in urine. The RIA assay was found to be linear over the urine fentanyl concentration range of 0.25 to 7.5 ng/mL and precise with coefficients of variation (CV) ranging from 9.6 to 19.3%. The RIA calibrators, ranging in fentanyl concentrations from 0.25 to 7.5 ng/mL, and controls, at mean fentanyl concentrations of 0.46 and 1.32 ng/mL, were compared by both the RIA and GC/MS methods. The cross-reactivity with the 125 I RIA test was determined for the fentanyl metabolites, norfentanyl and hydroxyfentanyl, and found to be 5% and 35%, respectively. The illicit fentanyl analogs were found to show significant cross-reactivity, ranging from 20 to 100%. The 125 I RIA was compared to GC/MS quantifications of fentanyl in 35 positive and 20 negative case urine specimens

  13. Fuel-rod response during the large-break LOCA Test LOC-6

    International Nuclear Information System (INIS)

    Vinjamuri, K.; Cook, B.A.; Hobbins, R.R.

    1981-01-01

    The large break Loss of Coolant Accident (LOCA) Test LOC-6 was conducted in the Power Burst Facility (PBF) at the Idaho National Engineering Laboratory by EG and G Idaho, Inc. The objectives of the PBF LOCA tests are to obtain in-pile cladding ballooning data under blowdown and reflood conditions and assess how well out-of-pile ballooning data represent in-pile fuel rod behavior. The primary objective of the LOC-6 test was to determine the effects of internal rod pressures and prior irradiation on the deformation behavior of fuel rods that reached cladding temperatures high in the alpha phase of zircaloy. Test LOC-6 was conducted with four rods of PWR 15 x 15 design with the exception of fuel stack length (89 cm) and enrichment (12.5 W% 235 U). Each rod was surrounded by an individual flow shroud

  14. Present state and perspectives of RIA in obstetrics and gynecology

    International Nuclear Information System (INIS)

    Talas, M.; Fingerova, H.

    1979-01-01

    A survey is presented of RIA methods introduced by the authors in their laboratory in the course of the last eight years. The results obtained by these methods in various physiological and pathological states are evaluated. The authors point to the possibilities of effective use of RIA for diagnostic purposes in obstetrics and gynecology taking into account also economic and organizational aspects. The most important trends of the use of RIA are accentuated not only in gynecological endocrinology and obstetrics but also in some other related fields, especially in the diagnosis and treatment of malignant diseases. (author)

  15. As normas de competência tributária

    OpenAIRE

    Follador, Guilherme Broto

    2013-01-01

    Resumo: O objetivo principal deste trabalho é analisar, criticamente, o conceito de competência tributária e as propostas doutrinárias de formalização das normas de competência tributária, expondo, a partir das lições colhidas sobre o tema, na Teoria Geral do Direito, os principais problemas encontrados nas tentativas de reconstruílas como típicas normas prescritivas. No primeiro capítulo, o estudo é dedicado ao exame das noções de "norma" e de "norma jurídica", e tem por principal finalidade...

  16. Present state and perspectives of RIA in obstetrics and gynecology

    Energy Technology Data Exchange (ETDEWEB)

    Talas, M; Fingerova, H [Palackeho Univ., Olomouc (Czechoslovakia). Lekarska Fakulta

    1979-01-01

    A survey is presented of RIA methods introduced by the authors in their laboratory in the course of the last eight years. The results obtained by these methods in various physiological and pathological states are evaluated. The authors point to the possibilities of effective use of RIA for diagnostic purposes in obstetrics and gynecology taking into account also economic and organizational aspects. The most important trends of the use of RIA are accentuated not only in gynecological endocrinology and obstetrics but also in some other related fields, especially in the diagnosis and treatment of malignant diseases.

  17. Dermatologia veterinária em animais de companhia

    OpenAIRE

    Pinho, Renato Martins

    2015-01-01

    Dissertação de Mestrado Integrado em Medicina Veterinária, Ciências Veterinárias A Dermatologia, em Medicina Veterinária, é uma área que representa entre 25 a 30% do total de consultas em animais de companhia, apresentando uma relação de proximidade crescente em relação à medicina humana. O presente trabalho teve como objetivos principais os seguintes estudos de caso: 1) Determinação da incidência de afeções dermatológicas e caracterização dos animais admitidos à consulta de especialida...

  18. Biblioteca universitária proativa

    Directory of Open Access Journals (Sweden)

    Maria de Fátima Pereira Raposo

    2006-07-01

    Full Text Available O trabalho visa apresentar alguns procedimentos que podem caracterizar uma postura proativa em bibliotecas universitárias. Para tanto, apresenta aspectos do conceito de proatividade em um contexto onde o uso e a aplicação das tecnologias de informação (TI constituem-se ferramentas essenciais para promover a inclusão social/digital no Brasil. O trabalho é abordado no contexto das bibliotecas do Centro Universitário da Cidade do Rio de Janeiro – UNIVER CIDADE. A adoção de procedimentos pró-ativos no Sistema de Bibliotecas da UNIVER CIDADE possibilitou um maior alcance dos problemas de informação de seus usuários, oferecendo, assim, subsídios para uma gestão eficiente da informação. Conseqüentemente, a confiança nos serviços da biblioteca e a participação nos programas instituídos cresceram proporcionalmente às ações pró-ativas adotadas pelo Sistema de Bibliotecas.

  19. RIA Analysis of Unprotected TRIGA Reactor

    Directory of Open Access Journals (Sweden)

    M.H. Altaf

    2017-07-01

    Full Text Available An RIA (reactivity initiated accident analysis has been carried out for the TRIGA Mark II research reactor considering both step and ramp reactivity ranges within 0.5 % dk/k (< $1 to 2.0 % dk/k (>$2. The insertion time was set at 10 s. Based on the fact that a reactor becomes unprotected if scram does not work at the event of danger, to define unprotected conditions, the time to actuate scram (trip was taken as close to total simulation time. In this long duration of scram inactivity, it is obtained from the present analysis that the reactor remained safe to up to 1.8 % dk/k ($2.57 for step reactivity and 1.99 % dk/k ($2.84 for ramp reactivity. In addition to negative temperature coefficient of reativity, probably the longer time of reactivity insertion keeps TRIGA safe even at larger magnitudes of reactivity during unprotected reactor transients. Coupled point kinetics, neutronics, and thermal hydraulics code EUREKA-2/R has been utilized for this work. It appears that EUREKA-2/RR predicts the sequence of unprotected transient scenario of TRIGA core with good approximation and the results will definitely be helpful for the reactor operators.

  20. Massimo Bontempelli: trajetória intelectual

    Directory of Open Access Journals (Sweden)

    Arivane Augusta Chiarelotto

    2010-11-01

    Full Text Available O italiano Massimo Bontempelli [1878-1960] é um escritor que, ao longo da carreira, conquistou uma fama controversa. Classificado de intelectual a serviço do fascismo, sua abordagem no campo literário é de natureza contestadora em relação a tradição Oitocentista. Além disso, sua trajetória resulta polêmica porque demarca a associação às vanguardas italianas insurgentes nas primeiras décadas do século XX. Tomadas as vanguardas pela sua gênese conceitual, Bontempelli esteve ligado a dois movimentos de grande impacto no contexto italiano: o futurismo e o fascismo. Neste trabalho abordaremos a sua inserção política, analisando aspectos de sua participação no cenário italiano que envolve a adesão e, posteriormente, o rompimento com o partido fascista.

  1. Tratamento cirúrgico da artéria coronária direita intra-atrial

    Directory of Open Access Journals (Sweden)

    José Carlos R. IGLÉZIAS

    1997-07-01

    Full Text Available A localização intracavitária da artéria coronária é rara. Segundo Ochsner & Mills (1, ela ocorreu com a artéria coronária direita em 0,9% e com o ramo interventricular em 0,2%. A localização da lesão e as condições patológicas relacionadas ao comprimento e diâmetro da coronária podem auxiliar na exposição da coronária intracavitária para uma revascularização apropriada. Freqüentemente os cirurgiões não estão habituados com a posição intracavitária e, durante a dissecção, podem abrir uma câmara cardíaca onde o vaso penetra. Os problemas que podem advir dai são a entrada de ar para a cavidade, a dificuldade na exposição do vaso, o sangramento e a obstrução da artéria durante o fechamento da miotomia. São relatados os casos de 3 pacientes que necessitaram de revascularização cirúrgica do miocárdio e que apresentavam a artéria coronária direita intracavitária. A localização e o comprimento da porção intracavitária da artéria auxiliam no manejo intra-operatório. A técnica utilizada para o fechamento da cavidade variou entre a anastomose na posição intracavitária com o fechamento da miotomia ao redor do enxerto (Figura 1, a liberação da artéria coronária para uma posição superficial (Figura 2, seguida da anastomose e fechamento da cavidade com sutura simples, feita subepicárdica.An intracavitary location of a coronary artery is rare in our surgical experience with revascularization. This variant has occured in the right coronary artery (0.01% and in left anterior descending coronary artery (0.2%. The location of the lesion and the pathological condition, length and size of the coronary may dictate exposure of an intracavitary coronary artery for proper revascularization; more commonly surgeons are anaware of the intracavitary position and during intramyocardial dissection of an artery will open a cardiac chamber where the vessel traverses the cavity. Problems that arise are introducion

  2. História e Memória: o caso do Ferrugem

    Directory of Open Access Journals (Sweden)

    Myrian Sepúlveda dos Santos

    2003-01-01

    Full Text Available O objetivo deste artigo é analisar o uso da memória pelas Ciências Sociais a partir da investigação de fontes orais e escritas. Ao longo do trabalho, serão consideradas cinco narrativas sobre o assassinato de um lavrador da Ilha Grande por um grupo de presos que havia fugido do Instituto Penal Cândido Mendes (IPCM. Além disso, são objetos de análise a notícia sobre o caso que aparece na imprensa e o relatório oficial sobre a fuga dos presos encaminhado pelo diretor da penitenciária ao diretor-geral do Departamento do Sistema Penitenciário (DESIPE. Em que pese a diferença entre os relatos apresentados, procurar-se-á mostrar que as memórias relacionam-se a perspectivas e códigos existentes entre grupos de pertencimento e que elas podem fornecer dados importantes sobre contextos, processos e conflitos sociais que fazem parte da vida dos diversos narradores do caso em questão.The objective of this paper is to investigate social practices developed by inmates of the Instituto Penal Cândido Mendes (IPCM as well as by those who lived in Ilha Grande, the island where the prison was settled, through the analysis of different narratives about the escape of a group of convicts. The author also analyzed the escape on the news and on the official reports. The point the author makes is that despite the different reports on the escape it is possible to relate the narrative to collective memories, that is, to common rules and perspectives, which allow us to understand social conflicts, processes and contexts inherent to the lives of the narrators.

  3. DYNREL - the reference calculation (coupled code utilization on analysis of RIA-transient)

    International Nuclear Information System (INIS)

    Strmensky, C.; Darilek, P.

    2003-01-01

    DYNREL is coupled code, comprising DYN3D and RELAP5 programs. The coupled code has been developed during four years. Now DYNREL is tested on selected RIA and thermo-hydraulic transient calculations. This material describes some results from selected RIA transient calculation (initiated by control rod movement). DYNREL modelled the whole nuclear reactors. The core is modeled as 313 or 349 independent thermo-hydraulic channels with 10 or 20 axial layers. Thermo-hydraulic part contains about 700 components that covered the six loops' model of nuclear power plant in detail. The calculated results are compared with DYN3D/M3, DYN3D/H1.1 results (Authors)

  4. Parametric study of fuel rod behaviour during the RIA using the modified FALCON code

    International Nuclear Information System (INIS)

    Khvostov, G.; Zimmermann, M.A.; Ledergerber, G.

    2010-01-01

    Presented in the paper are the results of a parametric study with the use of optimised modules of the FALCON code (FALCON-PSI) that addresses the effects of the selected characteristics of fast thermal transients (e.g., impulse width), fuel rod design (e.g., active fuel attack length) and boundary conditions (e.g., the coolant conditions) on fuel behaviour during a RIA. Specifically, the analysis of the governing processes for the fuel rod behaviour during the RIA events simulated in the experimental facility of the Nuclear Safety Research Reactor (NSRR, Japan) are in the focus of the present study. The results obtained can be useful for a better transfer of the NSRR test results in relation to the corresponding behaviour in LWRs and furthermore might also support the planning of future additional experiments. (authors)

  5. Testing and validation of methods for the diagnosis and recomendation integrated system for Signal grass Calibração do modelo e validação do sistema integrado de diagnose e recomendação para o capim - branquiária

    Directory of Open Access Journals (Sweden)

    Cristiane Prezotto Silveira

    2005-12-01

    Full Text Available The Diagnosis and Recommendation Integrated System (DRIS allows the interpretation of results of leaf analysis through relationships among nutrients, instead of the absolute and isolated concentration of each one, as it is used by the criterion of sufficiency range. The objective was to evaluate three procedures of calculation of DRIS indices, and to verify the efficiency of DRIS as interpretation method for the results of Brachiaria decumbens (Signal grass. The study was developed with the results of six experiments carried out in a greenhouse at Piracicaba, SP, with nutrient solution. Concentrations of N, P, K, Ca, Mg, S, Cu, Fe, Mn, and Zn were used in the samples of recently expanded leaf laminae of the grass. The validation of the DRIS method used results from an experiment with nitrogen and sulfur rates applied to the same grass from the Mundo Novo farm, Brotas, SP. DRIS indices were calculated according to two criteria to choose the ratio order of nutrients (F value and R value and three ways to calculate the nutrient functions (methods of Beaufils, Jones, and Elwali & Gascho. Nutritional Balance Index (NBI, calculated according to the generated norms, presented negative and significant correlation coefficients with the productivity in the combinations of methods tested and DRIS methods proposed by Beaufils, Jones and Elwali & Gascho were efficient in detecting concentrations that show nutrients deficiency or excess.O Sistema Integrado de Diagnose e Recomendação (DRIS permite a interpretação dos resultados de análise foliar, utilizando relações entre nutrientes, ao invés da concentração absoluta e isolada de cada um deles, utilizada pelo critério de faixa de suficiência. Objetivou-se avaliar três procedimentos de cálculo dos índices DRIS, bem como verificar a eficiência do DRIS como método de interpretação de resultados de análises de folhas da Brachiaria decumbens (capim-Braquiária. O estudo foi desenvolvido com os

  6. Ciclosporine A asxay: RIA or HPLC, plasma or total blood

    International Nuclear Information System (INIS)

    Lapalus, P.; Garraffo, R.; Krebs, B.; Lapalus, F.

    1985-01-01

    The two methods now in force for ciclosporine A assay are radioimmunoassay (RIA) and high pressure liquid chromatography (HPLC) in various biological media (plasma, serum, total blood). The advantages and disadvantages of the two methods are presented [fr

  7. Remote infrared audible signage (RIAS) pilot program report.

    Science.gov (United States)

    2011-07-01

    The Remote Infrared Audible Sign Model Accessibility Program (RIAS MAP) is a program funded by the Federal Transit Administration (FTA) to evaluate the effectiveness of remote infrared audible sign systems in enabling persons with visual and cognitiv...

  8. Engineering of radioimmunoassay (RIA) IP10.1

    International Nuclear Information System (INIS)

    Hari Nurcahyadi

    2010-01-01

    Engineering of Radioimmunoassay (RIA) IP10.1 is an innovative by PRPN - BATAN in 2010. Innovations made to the device IP10.1 RIA is the sample changer system, sample changer system on the device RIA IP10.1 applied 2 linear axis system (X, Z) with AC servo motor. In the RIA IP10.1 also use 5 pieces of the detector, so the enumeration process 50 (Fifty) sample is expected to be faster. Like its predecessor, The whole enumeration, data collection procedures and mechanisms operating within this system is entirely controlled by a PC via an electronic module. Electronics module consists of a high voltage module, amplifier and signal processor module, the module enumerators, low-voltage module, the module driver motor controller and a USB interface. The data acquisition and communication system using a USB port with the computer. (author)

  9. Proceedings of the topical meeting on reactivity initiated accidents (RIA)

    International Nuclear Information System (INIS)

    2003-01-01

    The topical meeting was devoted to RIA fuel acceptance criteria, in particular to the fuel fragmentation enthalpy limit and the PCMI failure enthalpy limit in relation to high burnup fuel. In total 50 participants attended. Research and industry organisations from France, Finland, Germany, Hungary, Japan, the Russian Federation, Sweden, the United Kingdom and the USA including the Swiss regulatory body, HSK, and the Halden reactor project, presented 16 papers in all. The papers covered three main areas: 'best estimate' core calculations for RIA energy deposition in high burnup fuels, the technical background of current and new RIA fuel safety criteria, and ongoing RIA experimental programmes. A number of open issues were identified, whose resolution is expected from ongoing and planned national and international experimental programmes

  10. Biotecnologia agroalimentària. Curs 2008-2009

    OpenAIRE

    Universitat de Barcelona. Facultat de Farmàcia

    2008-01-01

    Pla docent de l'assignatura Biotecnologia agroalimentària de l'Ensenyament de Ciència i Tecnologia dels Aliments. Curs acadèmic 2008-2009. Departament Productes Naturals,Biologia Vegetal i Edafologia.

  11. Internal quality control of RIA with Tonks error calculation method

    International Nuclear Information System (INIS)

    Chen Xiaodong

    1996-01-01

    According to the methodology feature of RIA, an internal quality control chart with Tonks error calculation method which is suitable for RIA is designed. The quality control chart defines the value of the allowance error with normal reference range. The method has the simplicity of its performance and directly perceived through the senses. Taking the example of determining T 3 and T 4 , the calculation of allowance error, drawing of quality control chart and the analysis of result are introduced

  12. Research ICT Africa (RIA!) - phase III | CRDI - Centre de recherches ...

    International Development Research Centre (IDRC) Digital Library (Canada)

    Research ICT Africa (RIA!) - phase III. Depuis la création du réseau RIA! en 2003, ses responsables ont mené avec succès des études portant tant sur l'offre que sur la demande afin de permettre de mieux comprendre l'accès aux TIC et leur utilisation en Afrique. Au cours des deux premières phases du projet (nos 101584 ...

  13. Study of a device for the direct measurement of the fission gas pressure inside an in-pile fuel element; Etude d'un dispositif pour la mesure directe de la pression des gaz de fission a l'interieur d'un element combustible en pile

    Energy Technology Data Exchange (ETDEWEB)

    Lavaud, B; Uschanoff, S [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

    1964-07-01

    The fission gas pressure inside a fuel element made of a refractory fuel constitutes an important limiting factor for the burn-up. Although it is possible to calculate approximately the volume of gas produced outside the fuel during its life-time; it is nevertheless very difficult to evaluate the pressure since the volume allowed to the fission gases, as well as their temperature are known only very approximately. This physical value, which is essential for the technologist, can only be known by direct in-pile measurement of the pressure. The report describes the equipment which has been developed for this test. (authors) [French] La pression des gaz de fission a l'interieur d'un element combustible a combustible refractaire constitue une des limitations importantes du taux de combustion. Si on peut approcher par calcul la determination du volume, des gaz degages hors du combustible au cours de sa vie, il est par contre tres difficile d'evaluer la pression car le volume alloue aux gaz de fission et leur temperature sont tres mal connus. Cette donnee essentielle pour le technologue ne peut etre atteinte que par une mesure directe en pile de la pression. Le rapport decrit l'appareillage qui a ete mis au point pour cet essai. (auteurs)

  14. Esquizofrenia refratária Refractory schizophrenia

    Directory of Open Access Journals (Sweden)

    Helio Elkis

    2007-10-01

    Full Text Available OBJETIVO: O propósito deste artigo é o de revisar vários aspectos da esquizofrenia refratária levando em conta questões relacionadas à definição, aspectos clínicos, correlatos psicobiológicos, tratamentos farmacológicos e não farmacológicos, assim como preditores de resposta terapêutica. MÉTODO: Pesquisa no Medline, assim como artigos dos autores. RESULTADOS E CONCLUSÕES: Pelo menos um terço dos pacientes com esquizofrenia são refratários a tratamento com antipsicóticos e as evidências apontam a clozapina em monoterapia como a principal opção nesses casos. A politerapia com antipsicóticos não tem apoio em evidências. Ensaios clínicos recentes mostraram que a potencialização da clozapina com outros antipsicóticos não é superior ao placebo.OBJECTIVE: The aim of the present paper is to review the various aspects of refractory schizophrenia regarding issues such as definitions, clinical aspects, psychobiological correlates, pharmacological and non-pharmacological treatment options and predictors of treatment response. METHOD: Medline search as well as articles of the authors. RESULTS AND CONCLUSIONS: Refractory schizophrenia affects at least one third of patients with schizophrenia and the best evidence shows that is monotherapy with clozapine remains the mainstay for the treatment of such condition. Antipsychotic polipharmacy is not supported by current evidence and recent clinical trials have shown that clozapine augmentation with antipsychotics has no benefit over placebo.

  15. Appreciation the damage of kidney function with RIA method

    International Nuclear Information System (INIS)

    Wang Haodan

    1992-01-01

    Using RIA method, the authors took 4 kinds of urine specimen from 100 normal persons which were taken in the morning 1 h after drinking voluntary and all- 24 h, and stored at 4 C deg and -30 C deg respectively, in order to detect the concentration of the urine protein Β 2 -MG, ALb, IgG and THP. The results are as follows: for 3-days-storage at 4 C deg and 2-weeks-storage at -30 C deg, P > 0.05; for the ALb, IgG and THP between voluntary urine and 24 h urine, α = 0.7565, 0.7865 and 0.7537 respectively; for Β 2 -MG, between the 1h-urine after drinking and voluntary urine, α = 0.7238. The urinary levels were measured of Β 2 -MG, ALb, IgG and THP with voluntary urine specimen in 177 cases of various types of nephropathy, urino-infection, and diabetic nephrosis, hypertesion-nephrosis, systemic lupus erythematosus. It is considered that the method of testing urine protein with voluntary urine specimen is not only accurate for collecting but also convenient for the patient. It is more accurate and sensitive than the traditional BUN and Cr for the appreciation of kidney function damage. And it gives a early stage index of kidney damage

  16. A newly development RIA for thyroid hormone autoantibodies (THAAb)

    International Nuclear Information System (INIS)

    Li Fengying; Gu Liqiong; Chen Xiayin; Jin Yan; Chen Shuxian; Zhang Qun; Qiu Hongxia; Yang Jingren; Zhao Yongju; Chen Mingdao

    2004-01-01

    Objective: To report a newly developed RIA for THAAb from this laboratory. Methods: The tested serum samples were cultured with labelled thyroid hormone analogous ( 125 I T 3 , 125 I T 4 ) for 16 hours. Antigen-antibody complex was precipitated with anti-human IgG (immune precipitation method) and radio-activity determined. Results: The mean positive rate of THAAb in healthy euthyroid controls (n=186) was only 1.07%. The mean positive rate in patients with thyroid disorders was 14.4% (mean rate 13.5% in hyperthyroid subjects, n=118 and mean rate 15.2% in hypothyroid subjects, n=72). The serum THAAb titer could be markedly lowered after adding non-labelled thyroid hormones (P 3 and FT 4 would be significantly lowered (P 3 , FT 4 levels. In patients with positive THAAb (about 14.4% in patients with all thyroid disorders), the FT 3 , FT 4 levels were best determined after PEG precipitation. (authors)

  17. Memória de longo prazo modulada pela memória de curto prazo

    Directory of Open Access Journals (Sweden)

    Viviane Moreira-Aguiar

    2008-01-01

    Full Text Available Quando um estímulo ocorre aleatoriamente à esquerda ou à direita, a resposta é mais rápida quando estímulo e resposta estão no mesmo lado (condição compatível do que em lados opostos (condição incompatível. Na tarefa de Simon, embora a resposta seja selecionada pela forma (ou cor do estímulo, a posição deste influencia o Tempo de Reação Manual (TRM. O efeito Simon corresponde à diferença entre as médias dos TRMs nas duas condições (incompatível e compatível. Neste trabalho, estudamos como uma tarefa prévia de compatibilidade realizada com um dedo indicador modula o efeito Simon. Vinte e oito voluntários realizaram uma tarefa de compatibilidade seguida pela tarefa de Simon. No grupo compatível (14 voluntários, encontramos um efeito Simon de 24 ms. No incompatível (14 voluntários, ocorreu um efeito Simon inverso de -16 ms. Estes resultados mostram uma modulação da memória de longo prazo por uma tarefa envolvendo a memória de curto prazo.

  18. Axial location of cladding failure during a slow transient overpower TREAT test

    International Nuclear Information System (INIS)

    Page, R.J.; Murphy, W.F.; Holland, J.W.

    1983-01-01

    The axial location of cladding failure following a transient overpower accident is of importance in fast reactor safety studies in that it is a determining factor in the relocation of fuel, and therefore in the possibility of inherent neutronic shutdown of the reactor. In-pile experimental data on the axial location of cladding failure of fuel in bundles of pins is sparse since, in general, the experimental fuel pin bundles are largely destroyed during the in-pile test. The post-test examination work has been completed for TREAT test J1. It was found that damage to the fuel elements during the irradiation was low enough for an accurate observation of the location of cladding failure to be made for each of the seven pins

  19. Olhar do cronista, registro da memória

    Directory of Open Access Journals (Sweden)

    Angela Maria Dutra da Silva Senra

    2016-09-01

    Full Text Available Propomos apresentar a pesquisa “Rastros da memória literária em crônicas dos jornais marianenses dos séculos XIX e XX” (PERPÉTUA, 2015, que tem como fonte um acervo de periódicos da cidade de Mariana (MG, hoje sob a guarda do Centro de Pesquisas Linguagem, Memória e Tradução do ICHS-UFOP. Dada a evidente relação desse acervo com a memória sociocultural da cidade, nossa pesquisa, em andamento, volta-se objetivamente para identificar e selecionar crônicas literárias publicadas nos periódicos, com a subsequente análise em sua correlação com a memória da região, sob as bases de um significativo material teórico sobre esse gênero. Assim, com vistas a adentrar no passado memorial da cidade de Mariana, apresentaremos o resultado parcial da nossa investigação, que tem proporcionado o conhecimento acerca da crônica; e do registro memorial dessa cidade em razão de sua importância no cenário histórico, social e cultural de Minas Gerais.

  20. In vitro susceptibility testing of dermatophytes isolated from pediatric cases in Nigeria against five antifungals Teste de susceptibilidade in vitro de dermatófitos isolados de casos pediátricos na Nigéria contra cinco antifúngicos

    Directory of Open Access Journals (Sweden)

    E.I. Nweze

    2007-10-01

    Full Text Available The antifungal activities of itraconazole, ketoconazole, fluconazole, terbinafine and griseofulvin were tested by broth microdilution methods against 71 isolates of dermatophytes isolated from Nigerian children. Most drugs were very active against all the dermatophytes and the MIC 90 ranged from 0.03 to 8.0 µg/mL. This appears to be the first documented data on the antifungal susceptibility testing of isolates of dermatophytes from Nigerian children.Atividades antifúngicas de itraconazole, ketoconazole, fluconazole, terbinafine e griseofulvina foram testadas por métodos de microdiluição em caldo contra 71 isolados de dermatófitos de crianças nigerianas. A maioria das drogas foi muito ativa contra todos os dermatófitos e o MIC 90 variou de 0,03 a 8,0 µg/mL. Estes parecem ser os primeiros dados documentados sobre os testes de susceptibilidade antifúngica de isolados de dermatófitos de crianças nigerianas.

  1. Serum specimens with double HBsAg/HBsAb (s-system) or HBeAg/HBeAb (e-system) positive markers (by ELISA) cross-checked with RIA or ECLIA--a comparison

    International Nuclear Information System (INIS)

    Tao Hongqun; Li Xiaolong; Ye Wei

    2005-01-01

    Objective: To cross-check the unusually high double positive rate of s- or e-system tested with ELISA in sera specimens from hepatitis B patients with two other methods of assay (RIA or ECLIA). Methods: Double positive s- or e-system sera specimens (tested with ELISA) were randomly selected to be cross-checked with RIA or ECLIA. Results: The double positive rate in the specimens checked with RIA was only 31.8% for s-system and 3.37% for e- system. In the case of ECLIA, the double positive rate was 17.65% and 9.09% respectively. The results obtained with both RIA and ECLIA were significantly lower than the results with ELISA (P 0.05). Conclusion: The unusually high double positive rate of s- or e- system in HBVM detection with ELISA was due to false positiveness and results from RIA were more consistent with the results from ECLIA. (authors)

  2. Radiommunoassay for triiodothyronine in serum. Development of the solid phase technic and comparison with two liquid phase RIA systems: the polyethylene glycol (PEG) and double antibody methods

    International Nuclear Information System (INIS)

    Hamada, M.M.

    1985-01-01

    A solid phase radioimmunoassay (RIA) system for triiodothyronine (T 3 ) was established by immobilizing triiodothyronine antibodies on the inner wall of reaction tubes. The antibody-coated tubes were made via reaction of antibody with glutaraldeyde residue pre coated on the inner wall of the tubes by alkaline self-polimerization. The quality of the coated tubes was tested through its performance in RIA methodology, by analysing the following RIA parameters: minimum detectable dose (MMD), nonspecific binding (NSB), X 50%, slope of the standard curve, intra and inter assay precision, accuracy of the method and figure of merit. The quality and characteristics of the reagents used in the RIA were analysed. (M.A.C.) [pt

  3. Identificação de híbridos de citros resistentes à mancha-marrom-de-alternária por meio de fAFLP e testes de patogenicidade Alternaria brown spot resistant citrus hybrid identification by means of fAFLP and pathogenicity tests

    Directory of Open Access Journals (Sweden)

    Edvan Alves Chagas

    2007-07-01

    Full Text Available O objetivo deste trabalho foi identificar híbridos, oriundos de hibridações controladas entre 'Folha Murcha' x 'Ponkan' e testá-los quanto à resistência a Alternaria alternata f. sp. citri. As plântulas foram obtidas via cultura in vitro de embriões. Utilizou-se o marcador molecular fAFLP para identificação dos híbridos e, em seguida, realizou-se o teste de patogenicidade nos híbridos com isolados de Alternaria alternata f. sp. citri, em condições de laboratório. Os pares de primers EcoRI AAG - MseI CAG e EcoRI ACC - MseI CAA foram os mais eficientes na identificação dos híbridos, os quais identificaram 48,5% de híbridos. Os híbridos F64, F108, F111, F113, F131 e F139 são potencialmente resistentes a Alternaria alternata f. sp. citri.The objective of this work was to identify hybrids obtained from controlled crossings between 'Folha Murcha' x 'Ponkan', and to check their resistance to Alternaria alternata f. sp. citri. The seedlings were obtained by in vitro embryo culture. The fAFLP marker technique was used to identify the hybrids, then laboratory pathogenicity test of the hybrids was accomplished with Alternaria alternata f. sp. citri isolates. The pairs of primers EcoRI AAG - Msel CAG and EcoRI ACC - Msel CAA were the most efficient for hybrids identification, and distinguished 48.5% of hybrids. Hybrids F64, F108, F111, F113, F131 and F139 showed potential resistance to the Alternaria alternata f. sp. citri.

  4. DN detection during SLSF tests

    International Nuclear Information System (INIS)

    Braid, T.H.; Harper, H.A.; Wilson, R.E.; Baldwin, R.D.; Gilbert, D.M.; Baxter, D.E.; Gillins, R.L.; Jeffries, G.L.

    1982-01-01

    During two tests in the Sodium Loop Safety Facility (W2 and P4), two systems were operated to detect delayed neutrons from exposed fuel. One monitored directly the sodium in the in-pile loop with a transit delay from the flux region of approx.2 seconds; the other conducted a sample stream of sodium to external detectors with a transit delay which could be varied from approx.10 to approx. 40 seconds. Detectors of a wide range of sensitivity were operated in pulse and current mode; DN signals varying from 2 recoil to many grams of molten fuel could be recorded reliably without saturation. During the W2 and P4 tests a continuous DN record was made. Massive fuel failure signals were observed during reactor transients in both tests, including events interpreted as fuel melting and exposure of large areas. The steady signal from the blockage in P4 was studied as a function of reactor power and sodium temperature

  5. Síndromes autoinflamatórias hereditárias na faixa etária pediátrica Pediatric hereditary autoinflammatory syndromes

    Directory of Open Access Journals (Sweden)

    Adriana Almeida Jesus

    2010-10-01

    Full Text Available OBJETIVO: Descrever as principais síndromes autoinflamatórias hereditárias na faixa etária pediátrica. FONTES DOS DADOS: Foi realizada uma revisão da literatura nas bases de dados PubMed e SciELO, utilizando as palavras-chave "síndromes autoinflamatórias” e "criança”, e incluindo referências bibliográficas relevantes. SÍNTESE DOS DADOS: As principais síndromes autoinflamatórias são causadas por defeitos monogênicos em proteínas da imunidade inata, sendo consideradas imunodeficiências primárias. Elas são caracterizadas clinicamente por sintomas inflamatórios sistêmicos recorrentes ou contínuos e devem ser diferenciadas das doenças infecciosas, autoimunes e outras imunodeficiências primárias. Nesta revisão, foram enfatizadas características epidemiológicas, manifestações clínicas, alterações laboratoriais, prognóstico e terapia das principais síndromes autoinflamatórias: febre familiar do Mediterrâneo; síndrome periódica associada ao receptor de fator de necrose tumoral; criopirinopatias; deficiência de mevalonato-quinase; artrite granulomatosa pediátrica; síndrome de pioderma gangrenoso, artrite piogênica e acne; síndrome de Majeed; e deficiência do antagonista do receptor de interleucina-1. As criopirinopatias discutidas foram: doença inflamatória multissistêmica de início neonatal ou síndrome neurológica, cutânea e articular crônica infantil, síndrome de Muckle-Wells e síndrome autoinflamatória familiar associada ao frio. CONCLUSÕES: É importante que o pediatra reconheça as síndromes autoinflamatórias hereditárias mais prevalentes, pois o encaminhamento ao reumatologista pediátrico pode permitir um diagnóstico precoce e uma instituição de tratamento adequado, possibilitando uma melhora da qualidade de vida dos pacientes.OBJECTIVE: To describe the most prevalent pediatric hereditary autoinflammatory syndromes. SOURCES: A review of the literature including relevant references

  6. Acuidade olfatória e qualidade de vida após a laringectomia total

    Directory of Open Access Journals (Sweden)

    Christiane Gouvêa dos Santos

    2015-12-01

    Full Text Available RESUMO: Objetivo: identificar a prevalência e os fatores associados às alterações do olfato e descrever a qualidade de vida após a laringectomia total. Métodos: estudo transversal para avaliar a acuidade olfatória e a qualidade de vida de laringectomizados totais no Instituto Nacional de Câncer por meio da aplicação do Teste de Identificação do Olfato da Universidade da Pensilvânia, do Questionário de Qualidade de Vida da Universidade de Washington e do Questionário sobre a Acuidade Olfatória Pré-Reabilitação do Olfato. Resultados: foram avaliados 48 laringectomizados totais, sendo 39 do sexo masculino e 9 do sexo feminino, com idade média de 62 anos e tempo médio de 5,6 anos desde a laringectomia total. No Teste de Identificação do Olfato a pontuação média foi de 17,9. De acordo com a classificação do olfato no teste, a maioria dos participantes apresentou algum grau de alteração, sendo que apenas 2 indivíduos tiveram o olfato considerado dentro da normalidade. No Questionário de Qualidade de vida da Universidade de Washington, o escore composto foi 80,47. Os domínios que apresentaram as médias de pontos mais baixas foram paladar, saliva e fala. No questionário sobre a acuidade olfatória pré-reabilitação do olfato, a maioria dos participantes consideraram seu olfato de ruim a razoável. 21 indivíduos relataram apresentar algum grau de dificuldade em suas atividades de vida diária em decorrência de alterações do olfato. Conclusão: os laringectomizados totais apresentaram alta prevalência de alterações do olfato, com comprometimentos relacionados às suas atividades de vida diária.

  7. Preliminary insights of the impact of steady state uncertainties on fuel rod response to an RIA

    International Nuclear Information System (INIS)

    Herranz, Luis E.; Huguet, Anne

    2013-01-01

    Nuclear fuel cycles are driven to higher burn-ups under the nowadays more demanding operational conditions. The operational safety limits that ensure the long-term core coolability are set through the analysis of the design basis accidents, RIA scenarios. These analyses are mainly performed through computer codes that encapsulate the present understanding of fuel behavior under such events. They assess safety margins and therefore their accuracy is of utmost interest. Their predictability is extended and validated through separate effect and integral experiments data. Given the complexity of working phenomena under RIA conditions, neither existing thermo-mechanical models nor rod state characterization at the moment of power pulse reflect exactly reality. So, it is essential to know how these deviations influence code predictions. This study illustrates how uncertainties related to pre-transient rod characterization affect the estimates of nuclear fuel behavior during the transient. In order to do so, the RIA scenario of the CIP0-1 test (CABRI program) has been analyzed with FRAPCON-3 (steady state irradiation) and FRAPTRAN 1.4 (transient) codes. The input uncertainties have been propagated through the codes by following a deterministic approach. This work is framed within the CSN-CIEMAT agreement on 'Thermo-Mechanical Behavior of the Nuclear Fuel at High Burnup'. (authors)

  8. Clinical experience of a sensitive immunoradiometric thyrotropin (TSH) assay kit (RIA-gnost hTSH)

    International Nuclear Information System (INIS)

    Nakamura, Saeko; Jibiki, Kazuko; Demura, Reiko; Koike, Sachiko; Kurihara, Shigeko; Odagiri, Emi; Demura, Hiroshi

    1987-01-01

    A commercially available immunoradiometric thyrotropin (TSH) assay kit (RIA-gnost hTSH) was used to study the concentration of TSH in serum in a series of 124 patients with thyroid dysfunction and 35 normal controls. Laboratory test for RIA-gnost hTSH showed a detection limit for TSH to be 0.03 μU/ml. The basal serum concentration of TSH in normal controls ranged from 0.17 to 3.21 μU/ml, with a mean of 0.74 μU/ml. It was less than 0.04 μU/ml in all 28 untreated patients with Graves' disease, indicating the discrimination between normal and hyperthyroid subjects. In the case of untreated 7 patients with hypothalamic hypopituitarism, the basal TSH concentration ranged from 0.80 to 13.5 μU/ml. There was no consistent tendency for changes in TSH levels with normalization of free thyroxine in 8 treated patients with Graves' disease. The basal serum concentration of TSH reflected the response of TSH to thyrotropin releasing hormone in 10 treated patients with Graves' disease. The use of the RIA-gnost hTSH would be of clinical significance in the diagnosis and management of patients with Graves' disease or hypopituitarism. (Namekawa, K.)

  9. Measurement of the in-pile core temperature of an EL-4 pencil element, first charge (can of type-347 stainless steel, 0.4 mm thick, UO{sub 2} fuel, 11 mm diameter). Determination of the apparent thermal conductivity integral of in-pile UO{sub 2}; Mesure de la temperature a coeur en pile d'un crayon EL-4 1er jeu (gaine acier inoxydable, nuance 347 - epaisseur 0,4 mm - combustible UO{sub 2} - diametre 11 mm). Determination de l'integrale de conductibilite thermique apparente de l'UO{sub 2} en pile

    Energy Technology Data Exchange (ETDEWEB)

    Lavaud, B; Ringot, C; Vignesoult, N [Commissariat a l' Energie Atomique, Centre d' Etudes Nucleaires de Saclay, 91 - Gif-sur-Yvette (France)

    1966-11-01

    The core temperature of a pencil fuel element depends on the thermal conductivity of the UO{sub 2}, and on the UO{sub 2}-can contact. This temperature may be known accurately only if in-pile tests using the actual geometry are carried out. The test described concerns the measurement of the core- temperature of an EL-4 fuel element, first charge, having a stainless steel can. This temperature is measured at the center of the in-pile pencil element using a high-temperature thermocouple (W-Re with Ta sheath). The element is subjected to operating conditions similar to those of EL-4, both for the specific power and the can temperature and for the pressure acting on the can. The specific power is obtained in the EL-3 reactor using a slightly higher enrichment for the UO{sub 2} than that planned for EL-4. The required can temperature and pressure are obtained using a Zircaloy-2 irradiation container filled with NaK, adapted for use in the EL-3 reactor. The core temperatures of the UO{sub 2}, and that of the can surface are measured. The power is calculated from the heat exchanges in the container calibrated in the laboratory. The temperature drop at the UO{sub 2}-can interface is deduced from laboratory measurements carried out under comparable heat flux conditions, and in a gas atmosphere corresponding to the beginning of the life-time of the fuel element. It is possible to draw an integral conductivity curve. It is also possible to check the temperature distribution in the oxide, as deduced from the thermal conductivity integral, by micro-graphic examination of the oxide structure. (authors) [French] La temperature a coeur d'un crayon combustible est fonction de la conductibilite thermique de l'UO{sub 2}, mais aussi du contact UO{sub 2}-gaine. Les essais de mesure en geometrie reelle en pile sont les seuls qui permettent d'avoir une connaissance exacte de cette valeur. L'essai dont il est question dans ce rapport a trait a la mesure de la temperature a coeur d

  10. EFEITO ANTIBIÓTICO DO PRÓPOLIS SOBRE BACTÉRIAS FITOPATOGÊNICAS

    Directory of Open Access Journals (Sweden)

    L. BIANCHINI

    1998-01-01

    Full Text Available O efeito antibiótico de extrato aquoso de própolis, em várias concentrações, foi avaliado para cinco espécies de bactérias fitopatogênicas. Agrobacterium tumefaciens, Clavibacter michiganensis subsp. michiganensis e Xanthomonas axonopodis pv. phaseoli foram completamente inibidas em meio de cultura contendo 10% de extrato de própolis. Erwinia chrysanthemi foi parcialmente inibida, enquanto Pseudomonas syringae pv. tabaci se mostrou insensível ao extrato, desenvolvendo colônias idênticas àquelas observadas em meios livres de própolis. Concentrações menores não foram suficientes para exercer um efeito antimicrobiano desejável sobre as bactérias pertencentes a todas as espécies testadas. Resultados idênticos foram obtidos quando própolis foi incorporado ao meio antes ou após a autoclavagem, demonstrando que a substância ativa presente no extrato não é termosensível. Foi demonstrado, portanto, o uso potencial do própolis como antibiótico para o controle de bactérias fitopatogênicas.The antibiotic effect of aqueous extract of propolis was evaluated in vitro against five species of bacteria. The growth of Agrobacterium tumefaciens, Clavibacter michiganensis subsp. michiganensis and Xanthomonas axonopodis pv. phaseoli was completely inhibited in a medium containing 10% of propolis. Erwinia chrysanthemi was partially inhibited and Pseudomonas syringae pv. tabaci was not affected. Lower concentration of the aqueous extract was not effective to promote a desirable antibiotic action against all bacterial species tested. The active ingredient present in the propolis was thermostable. The potential use of the propolis to control phytopathogenic bacteria was demonstrated.

  11. Agressividade tributária: um survey da literatura

    Directory of Open Access Journals (Sweden)

    Antonio Lopo Martinez

    2017-01-01

    Full Text Available Objetivo e Método: o objetivo deste artigo é revisar os estudos internacionais e no Brasil sobre a agressividade tributária, esta entendida como o comportamento de tentar evitar ou minimizar o ônus tributário explícito para a corporação. Enquanto tema de pesquisa acadêmica, o tax aggressiveness ou tax avoidance revela-se em um tópico diversificado e vasto, embora relativamente recente. Resultados e Contribuições: Entre as perguntas de pesquisa que nessa temática se desenvolvem, destaquem-se a identificação de quais seriam os determinantes da agressividade tributária da firma, apreciando: (i características das firmas; (ii atributos ambientais; (iii restrições de gatekeepers; e (iv incentivos para as firmas. Revisam-se os determinantes da agressividade tributária dos gestores e a influência da governança e estrutura de controle. Adicionalmente, identificam-se as potenciais consequências econômico-financeiras da agressividade tributária para as firmas e as proxies empíricas existentes para mensurar a agressividade tributária. O estudo se encerra com a apresentação de oportunidades futuras de pesquisa na temática.

  12. Hydrodynamic Aspects at Vitória Bay Mouth, ES

    Directory of Open Access Journals (Sweden)

    FLÁVIA A.A. GARONCE

    2014-06-01

    Full Text Available Understading the hydrodynamic behavior and suspended particulated matter (SPM transport are of great importance in port regions such as Vitória Harbor, which is located at Vitória Bay, Vitória – ES, Brazil. Vitória Bay is an estuary that has not been systematically assessed through a temporal analysis in order to identify its hydrodynamics characteristics and SPM exchange. This study aims to investigate salt and suspended particulate matter flux at the estuarine mouth of Vitória Bay by understanding the temporal variation of salinity, temperature and tidal currents within the water column and at the channel crosssection. Results showed that the estuarine mouth tended to present partial stratification periods during neap tides and little stratification in spring tides. The circulation pattern was mainly influenced by the tide, with little influence from river discharge. With regard to the SPM, the mouth of the estuary tended to show low concentrations, with the highest values occurring during the dry season. A close relationship between momentary discharge, SPM and salt fluxes was observed. Despite all the data was collected at the mouth of the estuary, the system showed an importation trend of salt in all cycles and SPM importation for three of the four studied tidal cycles. Thus, Vitoria Bay is not exporting SPM to the adjacent inner shelf.

  13. Development and application of radioimmunoassays and enzyme immunoassays in microbiological and immunological diagnosis. 2. Comparative studies for the detection of toxoplasma antibodies with ELISA, RIA and other serological methods

    Energy Technology Data Exchange (ETDEWEB)

    Mueller, W A; Struy, H; Holzwarth, F [Medizinische Akademie, Magdeburg (German Democratic Republic)

    1982-06-01

    Comparative studies of indirect immunofluorescence test (IT), complement binding reaction (CBR), enzyme- and radioimmunoassay (ELISA, RIA) for the detection of toxoplasma antibodies in sera of 513 patients are reported. The precision dependent on time, showed coefficients of variation from 3% to 12% (IFT 3%, CBR 10%, ELISA 12%, RIA 7%). The correlation of IFT and ELISA as well as RIA was relatively unfavourable (coefficient of correlation IFT/ELISA r = 0.52, IFT/RIA r = 0.54, RIA/ELISA r = 0.60). The ELISA is the most sensitive method for the detection of antibodies. The specificity of the Toxo-ELISA has to be improved by application of suitable fractions of antigens.

  14. Current status and development of mechanical test techniques in the course of irradiation in MIR, SM and RBT-6 reactors

    International Nuclear Information System (INIS)

    Burukin, A.; Izhutov, A.; Nuzhdov, A.; Palachev, P.

    2015-01-01

    The reason for development and advancement of in-pile mechanical test methods for the materials and products of nuclear power engineering is that the irradiation-induced changes of some properties cannot be explained based on the results of preirradiation and post-irradiation testing. The need for such methods grows due to strengthening the requirements to performance, reliability, safety, licensing and competitive performance of nuclear fuel. The nuclear reactor operation under the power maneuvering has become more challenging. Nowadays the nuclear fuel burnup increase is the pressing issue. The nuclear power engineering gave rise to innovative projects. The phenomena being examined called for development of models in the fame of physical and mechanical concepts which provide for methodology including a full set of in-pile test methods. The strategy of irradiation testing is targeted at demonstrating irradiation feasibility of different projects in the field of nuclear power engineering with the use of conceptual approach to the property of the material or product under examination. Such an approach provides for the following: Development of the general phenomenon concept based on the available data on its mechanism under irradiation; Development of research methodology based on the general concept providing for the similarity condition by employing RRs and test methods; In-pile testing in accordance with the research methodology; Development of the phenomenon model; Model verification with the use of data obtained in the course of irradiation testing in other RRs and examination of nuclear core components; Integration of the model into the computer code intended for demonstrating feasibility of nuclear reactor design concept. The present paper describes the in-pile test methods of mechanical properties available at JSC “SSC RIAR” and applied in research reactors MIR, SM and RBT-6. Provided here is also information on their further development and some

  15. Fuel elements and fuel element materials. Experimental facilities for fission products lift-off tests

    International Nuclear Information System (INIS)

    Blanchard, R.J.; Veyrat, J.F.

    1978-01-01

    One of the hypothetical accidents on the HTGR primary cooling circuits is the failure of a circuit resulting in a depressurization in the primary loops of the reactor. There is a risk of release of fission products in relation to the size of the failure. Experimental facilities for HTGR tests were developed: an in pile helium loop Comedie and an out of pile helium loop

  16. Feasibility study on the transient fuel test loop installation

    International Nuclear Information System (INIS)

    Kim, J. Y.; Lee, C. Y.

    1997-02-01

    The design and installation of the irradiation test facility for verification test of the fuel performance are very important in connection with maximization of the utilization of HANARO. The objective of this study is to investigate and analyze the test capsules and loops in research reactors of the other countries and to design preliminarily the eligible transient fuel test facility to be installed in HANARO. The principle subjects of this study are to analyze the contents, kinds and scopes of the irradiation test facilities for nuclear technology development. The guidances for the basic and detail design of the transient fuel test facility in the future are presented. The investigation and analysis of various kinds of test facilities that are now in operation at the research reactors of nuclear advanced countries are carried out. Based on the design data of HANARO the design materials for an eligible transient fuel test facility comprises two pacts : namely, in pile test fuel in reactor core site, and out of pile system regulates the experimental conditions in the in pile test section. Especially for power ramping and cycling selection of the eligible power variation equipment in HANARO is carried out. (author). 13 refs., 4 tabs., 46 figs

  17. The development of T3-RIA, T4-RIA and TSH-IRMA for in vitro testing of thyroid function

    International Nuclear Information System (INIS)

    Borza, V.; Neacsu, G.; Chariton, Despina

    1998-01-01

    Thyroxine (T 4 ) and triiodothyronine (T 3 ) are two principal thyroid hormones; the release of this hormones and control of different stages of their synthesis are performed by thyrotropin (TSH), secreted by pituitary gland. Also, T 3 and T 4 exert negative feed-back on the pituitary, inhibiting the release of TSH. The measurement of T 3 , T 4 content in un-extracted serum, correlated with TSH values are useful results for investigating the pituitary-thyroid axis. This paper describes radioimmunological procedures for the measurement of T 3 and T 4 using as separation method of the bound and free radiolabeled antigen, the precipitation of antigen-antibody complex by polyethyleneglycol (PEG). Antisera against T 3 , T 4 were produced by immunizing sheep with conjugates of the hormones and bovine albumin; T 3 and T 4 standards were made in horse serum free of these hormones. Binding of T 3 and T 4 to TBG in serum was inhibited by addition of 8-aniline-1-naphthalene-sulfonic acid (ANS). The separation of antigen-antibody complex was carried out using 25.5% PEG 6000. In order to develop a simple T 3 solid phase radioimmunoassay, in this paper the immobilization of anti-T 3 antibodies on polystyrene tubes is presented. The best results were obtained with an exposure time of anti-T 3 antibodies (diluted in buffer solution, pH 8.4-8.6) of 40 h at 4 o C. Also, in this study the preparation of 125 I labeled monoclonal antibody (Mab)-anti-TSH is described, which will be used as a component of a TSH-IRMA kit; this kit is to be realized in our department. 125 I - Mab anti-TSH has the following characteristics: specific activity = 20 - 24 μCi/μg and radioactive concentration ≅ 25 μCi/ml; also, the immunological properties of tracer were verified. The major results of this activity is that the total dependence on important kits will be eliminated and also, the costs will be reduced. (authors)

  18. Barbas, Helena, Madalena. História e Mito

    Directory of Open Access Journals (Sweden)

    Sidinea Pedreira

    2012-10-01

    Full Text Available É inquestionável a importância da recuperação e reconfiguração de histórias de personagens que contribuíram, ao longo dos séculos, para a criação e manutenção de estereótipos que serviram para a legitimação de papéis sociais e de comportamentos. Reescritas e reinterpretações da história – seja de relatos históricos, seja de mitos ou lendas – são possíveis e necessárias, uma vez que proporcionam espaços de discussão e de reconfiguração de papéis sociais, nomeadamente no que diz respeito às ide...

  19. Psicologia Comunitária: uma abordagem conceitual

    OpenAIRE

    Gomes, Antonio Maspoli de Araujo

    2009-01-01

    Este artigo apresenta as principais tentativas de conceituação das correntes teóricas sobre a psicologia comunitária, ligadas a psicologia social. A partir da análise dos dados obtidos podemos afirmar que a Psicologia Comunitária é um saber em construção, pragmático, derivado da Psicologia Social. Concluímos também que muitas das teorias referenciadas e das técnicas citadas pelos psicólogos que trabalham em Psicologia Comunitária são derivadas dos referenciais teóricos da Psicologia Comunitár...

  20. Development of risk-informed assessment (RIA) design methodology

    International Nuclear Information System (INIS)

    Ji, S. K.; Park, S. J.; Park, B. R.; Kim, M. R.; Choi, C. J.

    2001-01-01

    It has been assessed that the capital cost for future nuclear power plants needs to be reduced on the order of 35% to 40% for Advanced Light Water Reactors such as KNGR and System 80+. Such reduction in the capital cost will require a fundamental re-evaluation of the industry standards and regulatory basis under which nuclear plants are designed and licensed. The objective of this study is to develop the risk-informed assessment (RIA) design methodology for future nuclear power plants. In order to meet this objective, the design simplification method is developed and RIA design methodology exercised for conceptual system. For the methodology verification, simplified conceptual ECCS and feedwater system are developed, then LOCA sensitivity analyses and agressive secondary cooldown analyses for these systems are performed. In addition, the probability safety assessment (PSA) model for LOCA is developed and the validation of RIA design methodology is demonstrated

  1. The evaluation of some thermodynamic parameters by RIA method

    International Nuclear Information System (INIS)

    Dorobantu, I. I.; Cucu Delia-Irina

    2001-01-01

    The present paper evaluates some of thermodynamic parameters by using RIA (radioimmunoassay) method. The RIA systems studied were: 1) antiprogesterone antibody-progesterone- 3 H; 2) antiprogesterone antibody-progesterone- 125 I. The antigen (progesterone) was labelled with 3 H, in the first case, and 125 I in the second one (progesterone- 125 I was progesterone-6-S-CH 2 -CO-histamine- 125 I). RIA reactions were developed at two temperatures: 277 K and 296 K. Samples of antiprogesterone antibodies and labelled progesterone were incubated with different amounts of unlabeled progesterone. The immune complex was precipitated after reaching the chemical equilibrium and its radioactivity measured at γ-counter. By the radioactive measurements, the affinity constants (K S ) were estimated. The values of the affinity constants were used to estimate the thermodynamic parameters of the systems, such as: enthalpy (ΔH), Gibbs energy (ΔG) and entropy (ΔS). (authors)

  2. O Jornalismo nas Rádios Comunitárias

    OpenAIRE

    Rosembach, Cilto José

    2006-01-01

    O presente estudo analisa o jornalismo nas rádios comunitárias a partir do paradigma da comunicação popular, alternativa e da contextualização histórica das rádios comunitárias no Brasil. A programação jornalística de duas rádios comunitárias no Estado de São Paulo é analisada a partir do referencial teórico que elucida a comunicação popular e prioriza os conceitos de jornalismo popular. São analisadas a Rádio Cantareira FM 107,5, de Vila Isabel, distrito de Brasilândia, São...

  3. Kant sobre o progresso na história

    Directory of Open Access Journals (Sweden)

    Joel Thiago Klein

    2013-07-01

    Full Text Available http://dx.doi.org/10.5007/1677-2954.2013v12n1p67 O objetivo deste artigo é analisar o significado da tese central da filosofia kantiana da história: que a humanidade se encontra em um constante progresso para o melhor. Contudo, apesar de parecer a primeira vista simples, a discussão do próprio significado dessa  tese está longe de alcançar um consenso na literatura. A originalidade deste trabalho é apresentar pela primeira vez um mapeamento geral, sistemático e exaustivo das diferentes interpretações e críticas que essa tese recebeu ao longo da história. Nesse sentido, qualquer resposta que pretenda ser minimamente satisfatória precisa levar em consideração todos os argumentos e posições aqui apresentados.

  4. As teorias da história e a história ensinada no ensino fundamental

    Directory of Open Access Journals (Sweden)

    Lia Machado Fiuza Fialho

    2017-02-01

    Full Text Available Resumo: Objetiva discutir as interfaces das teorias da História e a História ensinada no ensino fundamental, com ênfase na “alfabetização histórica” no século XXI. Como metodologia de pesquisa utilizou-se grupo focal, com 21 pesquisadores e professores que atuavam no campo do Ensino de História e História da Educação. Constatou-se que o ensino no século XXI deve propiciar a aprendizagem de maneira contextualizada, relacionando a pessoa, o tempo e o espaço, em uma perspectiva de produção e transformação da sociedade, na qual o aluno é concebido como sujeito histórico inserido no âmbito dialógico-crítico, tendo o professor como um mediador. Palavras-chave: Ensino. História. Correntes teóricas.

  5. Biblioteca universitária, escolar e comunitária: o caso da biblioteca comunitária “Professora Ebe Alves da Silva” do IFMG

    Directory of Open Access Journals (Sweden)

    Helena Maria Tarchi Crivellari

    2015-12-01

    Full Text Available A Expansão da Rede Federal de Educação Profissional, Científica e Tecnológica ocorrida em 2008, pela lei 11.892, transformou diferentes instituições de ensino técnico federais em Institutos Federais de Educação, Ciência e Tecnologia, que são responsáveis pela educação profissional em diferentes modalidades de ensino, promovendo tanto a educação básica quanto a educação superior. Inseridas nesse contexto estão as bibliotecas dessas instituições, que são, concomitantemente, bibliotecas escolares e universitárias. Com o objetivo de demonstrar o papel dessas bibliotecas, motivado pelo questionamento sobre a possibilidade de convivência desses tipos de bibliotecas em um mesmo espaço, apresenta-se um estudo de caso sobre a Biblioteca Comunitária Professora Ebe Alves da Silva, do Instituto Federal de Minas Gerais que, além de escolar e universitária é também “comunitária”, pela sua própria denominação. Para a concretização do estudo de caso foram realizadas entrevistas e aplicados questionários, dirigidos a diferentes atores da comunidade interna e externa da instituição. Os resultados foram submetidos à técnica do Discurso do Sujeito Coletivo – DSC - que ilustrou a discussão, relacionando os aspectos teóricos sobre biblioteca escolar, biblioteca universitária e biblioteca comunitária à realidade da Biblioteca Comunitária Professora Ebe Alves da Silva. A pesquisa concluiu que a biblioteca estudada cumpre os três papéis, constituindo-se em uma agente propulsora da democratização da informação e contribuindo para o desenvolvimento do município.

  6. Panorama da estrutura presidiária brasileira

    Directory of Open Access Journals (Sweden)

    Renata de Oliveira Cartaxo

    2013-06-01

    Full Text Available Objetivo: Descrever, a partir do Sistema Integrado de Informações Penitenciárias – Infopen, aspectos da estrutura prisional nacional, características dos apenados e perfil dos profissionais existentes para garantir o preceito constitucional de assistência à saúde. Métodos: Estudo descritivo, de base documental, realizado a partir de dados secundários disponíveis no Sistema Integrado de Informações Penitenciárias, no qual analisaram-se a estrutura carcerária brasileira, o perfil do apenado no que tange a características pessoais e do crime cometido, e os profissionais envolvidos na assistência à saúde. Resultados: Constata-se que existem 298.275 vagas, ocupadas por 496.251 presos nos 1.857 estabelecimentos penais. No tocante ao perfil dos presos, verifica-se que 92,3% (461.444 são do sexo masculino, na faixa etária entre 18 e 24 anos (25,6% - 126.929, da cor parda (36,7% - 82.354, comensino fundamental incompleto (40,7% - 201.938, que cometeram, principalmente, o crime de tráfico de entorpecentes (23,5% - 100.648. Quanto à composição da equipe de assistência à saúde, evidencia-se um total de 5.132 profissionais registrados no sistema. Conclusão: Constata-se, a partir do sistema integrado de informações penitenciárias, que a estrutura carcerária brasileira se caracteriza por apresentar um déficit de vagas, ocasionada pelasuperlotação e/ou saturação dos estabelecimentos existentes, o que dificulta, em especial, a garantia do atendimento às necessidades de saúde dos apenados.

  7. LMFBR post accident heat removal testing needs and conceptual design of a test facility

    International Nuclear Information System (INIS)

    Kleefeldt, K.; Kuechle, M.; Royl, P.; Werle, H.; Boenisch, G.; Heinzel, V.; Mueller, R.A.; Schramm, K.; Smidt, D.

    1977-03-01

    A study has been carried out in which the needs and requirements for a test facility were derived, enabling detailed investigation of key phenomena anticipated during the post accident heat removal (PAHR) phase as a consequence of a postulated LMFBR whole core accident. Part I of the study concentrates on demonstrating the PAHR phenomena and related testing needs. Three types of experiments were identified which require in-pile testing, ranging from 10 to 70 cm test bed diameter and correspondingly, 30 to 5 W/g minimum power density in the test fuel. In part II a conceptual design for a test facility is presented, emphasizing the capability for accomodating large test beds. This is achieved by a below-reactor-vessel testing device, neutronically coupled to a 100 MWt sodium cooled fast reactor. (orig.) [de

  8. Measurement Invariance and Latent Mean Differences in the Reynolds Intellectual Assessment Scales (RIAS): Does the German Version of the RIAS Allow a Valid Assessment of Individuals with a Migration Background?

    Science.gov (United States)

    Gygi, Jasmin T.; Fux, Elodie; Grob, Alexander; Hagmann-von Arx, Priska

    2016-01-01

    This study examined measurement invariance and latent mean differences in the German version of the Reynolds Intellectual Assessment Scales (RIAS) for 316 individuals with a migration background (defined as speaking German as a second language) and 316 sex- and age-matched natives. The RIAS measures general intelligence (single-factor structure) and its two components, verbal and nonverbal intelligence (two-factor structure). Results of a multi-group confirmatory factor analysis showed scalar invariance for the two-factor and partial scalar invariance for the single-factor structure. We conclude that the two-factor structure of the RIAS is comparable across groups. Hence, verbal and nonverbal intelligence but not general intelligence should be considered when comparing RIAS test results of individuals with and without a migration background. Further, latent mean differences especially on the verbal, but also on the nonverbal intelligence index indicate language barriers for individuals with a migration background, as subtests corresponding to verbal intelligence require higher skills in German language. Moreover, cultural, environmental, and social factors that have to be taken into account when assessing individuals with a migration background are discussed. PMID:27846270

  9. Measurement Invariance and Latent Mean Differences in the Reynolds Intellectual Assessment Scales (RIAS: Does the German Version of the RIAS Allow a Valid Assessment of Individuals with a Migration Background?

    Directory of Open Access Journals (Sweden)

    Jasmin T Gygi

    Full Text Available This study examined measurement invariance and latent mean differences in the German version of the Reynolds Intellectual Assessment Scales (RIAS for 316 individuals with a migration background (defined as speaking German as a second language and 316 sex- and age-matched natives. The RIAS measures general intelligence (single-factor structure and its two components, verbal and nonverbal intelligence (two-factor structure. Results of a multi-group confirmatory factor analysis showed scalar invariance for the two-factor and partial scalar invariance for the single-factor structure. We conclude that the two-factor structure of the RIAS is comparable across groups. Hence, verbal and nonverbal intelligence but not general intelligence should be considered when comparing RIAS test results of individuals with and without a migration background. Further, latent mean differences especially on the verbal, but also on the nonverbal intelligence index indicate language barriers for individuals with a migration background, as subtests corresponding to verbal intelligence require higher skills in German language. Moreover, cultural, environmental, and social factors that have to be taken into account when assessing individuals with a migration background are discussed.

  10. História Militar do Ceará

    Directory of Open Access Journals (Sweden)

    Walter José Faustini

    1953-03-01

    Full Text Available SOUZA (Eusébio de. — História Militar do Ceará. Monografia n.o 15 da  Série História do Ceará, da Coleção Instituto do Ceará. 1950 (Obra  póstuma. (Primeiro Parágrafo do Artigo Destinada a integrar uma coleção de assuntos cearenses, a presente obra pretende historiar a evolução das instituições militares no Estado do Ceará.

  11. Teologia no Proslogion de Anselmo de Cantuária

    OpenAIRE

    Athayde, Emmanuel Roberto Leal de

    2011-01-01

    Anselmo de Cantuária é um personagem da Idade Média, considerado o pai da escolástica. Arcebispo da Catedral de Cantuária, que ficou conhecido basicamente pelo seu argumento denominado posteriormente de ontológico, que visava apresentar, valendo-se de conceitos filosóficos, um argumento único capaz de demonstrar a existência de Deus. Esse argumento único encontra-se no Proslogion, uma obra que trata da existência de um ser do qual é possível pensar nada maior , considerada uma simplificação ...

  12. As páginas de história

    Directory of Open Access Journals (Sweden)

    Höfling Maria Arlete Zülzke

    2003-01-01

    Full Text Available Produzimos um material para o estudo da localidade num Atlas Municipal Escolar, objetivando despertar a curiosidade e o gosto pelo conhecimento da história local. Destacamos nas páginas de história do Atlas de Rio Claro o processo de ocupação, povoamento, doação de sesmarias, desmembramento em fazendas, a cana-de-açúcar, o café, o escravo, o imigrante e as mudanças que ocorreram em Rio Claro até o início do século XX.

  13. Economia solidária versus economia capitalista

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    Paul Singer

    2001-12-01

    Full Text Available A economia solidária para ser competitiva no mercado capitalista não pode se furtar à concentração que incorpora progresso técnico. Experiências vêm demonstrando que cada associação ou cooperativa tem de atingir um tamanho em que ela possa resgatar seus membros da pobreza e acumular sobras que multipliquem fontes de trabalho e renda solidários. Para a economia solidária a conglomeração deve ser fácil porque a solidariedade torna natural a associação entre cooperativas.

  14. Analgesia pós-operatória

    OpenAIRE

    Bassanezi,Betina Sílvia Beozzo; Oliveira Filho,Antonio Gonçalves de

    2006-01-01

    JUSTIFICATIVAS E OBJETIVOS: A dor sempre foi uma das maiores preocupações do homem, entretanto, apesar dos progressos da ciência, ainda existem várias barreiras ao seu adequado tratamento, incluindo a falta de conhecimento por parte da equipe médica, sobre o mecanismo das diversas drogas e técnicas empregadas. O objetivo deste trabalho é abordar as principais drogas e técnicas empregadas no controle da dor pós-operatória, visando estimular o interesse sobre o assunto bem como aumentar a eficá...

  15. Incontinência urinária em mulheres que buscam exame preventivo de câncer de colo uterino: fatores sociodemográficos e comportamentais Incontinencia urinaria en mujeres que solicitan un examen preventivo de cáncer de cuello uterino: factores socio-demográficos y de comportamiento Urinary incontinence in women undergoing Pap smear test: socio-demographic and behavioral factors

    Directory of Open Access Journals (Sweden)

    Fernando Luiz Cardoso

    2013-06-01

    Full Text Available Este estudo transversal objetivou investigar a associação entre, de um lado, fatores sociodemográficos e comportamentais e, de outro, a presença de incontinência urinária referida em 784 mulheres que buscam exame preventivo de câncer de colo uterino na Grande Florianópolis, Santa Catarina, Brasil. Foram obtidos dados sociodemográficos, estado de saúde, atividade física, constipação e índice de massa corporal, sendo utilizado o International Consultation on Incontinence Questionnaire-SF. A prevalência de incontinência urinária foi de 30,7% (16,5% perdiam urina uma vez por semana ou menos e 23,8% em pequena quantidade. Na regressão de Poisson bruta, estiveram associados à incontinência urinária os seguintes fatores: baixa escolaridade, renda por pessoa da família até um salário mínimo, etnia não caucasiana, excesso de peso corporal, pior autoavaliação do estado de saúde, constipação e idade. Após ajuste, seguindo modelo hierarquizado, permaneceram associados: escolaridade, etnia, estado de saúde e idade. A alta prevalência de incontinência urinária em mulheres que buscam exame de rastreamento do câncer de colo uterino justifica abordagens preventivas nesses espaços de atuação.Este estudio transversal tuvo como objetivo investigar la asociación entre factores socio-demográficos y de comportamiento con la presencia de incontinencia urinaria, informada por 784 mujeres que solicitaron un examen preventivo de cáncer de cuello uterino en el área metropolitana de Florianópolis, Santa Catarina, Brasil. Se obtuvieron datos socio-demográficos, estado de salud, actividad física, estreñimiento e índice de masa corporal, utilizándose el International Consultation on Incontinence Questionnaire-SF. La prevalencia de incontinencia urinaria fue de un 30,7% (16,5% perdían orina una vez por semana o menos y un 23,8% en pequeña cantidad. En la regresión de Poisson bruta se asoció a la incontinencia urinaria: la

  16. Social benefits of the RIA technique in the State of Zacatecas; Beneficio social de la tecnica de RIA en el Estado de Zacatecas

    Energy Technology Data Exchange (ETDEWEB)

    Badillo R, Y.; Badillo A, V. [UAZ, Carretera a Ciudad Cuahutemoc Km. 0.5, Guadalupe, Zacatecas (Mexico)]. E-mail: yasminbadilloregis@hotmail.com

    2004-07-01

    Presently work was carried out tests of thyroid function to 159 patients with the purpose of evaluating the incidence of thyroid illnesses, being based these studies on the method of Radio immuno analysis (RIA). During this work they were studied 159 patients, men (21%) and women (79%), to which were practiced the tests of thyroid function, applying the technique of Radio immuno analysis, throwing the following results: Healthy patients (58.5%); Hyper thyroidal patients (22.6%), Hypo thyroidal patients (18.9%). The social benefit of this technique and their importance is because the patients that go to this laboratory are of scarce resources and otherwise; they would not simply be diagnose, since we have found patients that have taken until 10 years in that are diagnosed thyroid abnormalities. (Author)

  17. Spatio-temporal variability of inorganic and organic nutrients in five Galician rias (NW Spain

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    María Dolores Doval

    2013-01-01

    Full Text Available The spatial variability of inorganic (nitrate, nitrite, ammonium, phosphate and silicate and organic (dissolved organic carbon nutrients in five Galician rias (Vigo, Pontevedra, Arousa, Muros and Ares-Betanzos was assessed by considering average values for the upwelling and downwelling periods. Inner stations were significantly different from middle and outer stations, especially during the downwelling period. Spatial differences between the five rías, tested by means of a multivariate analysis, were found in both periods. The behaviour of inorganic and organic nutrient variables was also significantly different between periods with and without shellfish harvesting closures due to the occurrence of toxic phytoplankton species.

  18. Acuidade olfatória e qualidade de vida após a laringectomia total

    OpenAIRE

    Christiane Gouvêa dos Santos; Anke Bergmann; Kaliani Lima Coça; Angela Albuquerque Garcia; Tânia Cristina de Oliveira Valente

    2015-01-01

    RESUMO: Objetivo: identificar a prevalência e os fatores associados às alterações do olfato e descrever a qualidade de vida após a laringectomia total. Métodos: estudo transversal para avaliar a acuidade olfatória e a qualidade de vida de laringectomizados totais no Instituto Nacional de Câncer por meio da aplicação do Teste de Identificação do Olfato da Universidade da Pensilvânia, do Questionário de Qualidade de Vida da Universidade de Washington e do Questionário sobre a Acuidade Olfatór...

  19. Diltiazem como alternativa ao betabloqueador na angiotomografia de artérias coronárias

    Directory of Open Access Journals (Sweden)

    Carlos Eduardo Rochitte

    2012-08-01

    Full Text Available FUNDAMENTO: A redução da frequência cardíaca (FC na angiografia por tomografia das artérias coronarianas (ATCCor é fundamental para a qualidade de imagem. A eficácia dos bloqueadores de cálcio como alternativas para pacientes com contraindicações aos betabloqueadores não foi definida. OBJETIVOS: Comparar a eficácia na redução da FC e variabilidade RR do metoprolol e diltiazem na ATCCor. MÉTODOS: Estudo prospectivo, randomizado, aberto, incluiu pacientes com indicação clínica de ATCCor, em ritmo sinusal, com FC>70bpm e sem uso de agentes que interferissem com a FC. Cinquenta pacientes foram randomizados para grupos: metoprolol IV 5-15 mg ou até FC≤60 bpm(M, e diltiazem IV 0,25-0,60mg/kg ou até FC≤60 bpm (D. Pressão arterial (PA e FC foram aferidas na condição basal, 1min, 3min e 5min após agentes, na aquisição e após ATCCor. RESULTADOS: A redução da FC em valores absolutos foi maior no grupo M que no grupo D (1, 3, 5min, aquisição e pós-exame. A redução percentual da FC foi significativamente maior no grupo M apenas no 1 min e 3 min após início dos agentes. Não houve diferença no 5 min, durante a aquisição e após exame. A variabilidade RR percentual do grupo D foi estatisticamente menor do que a do grupo M durante a aquisição (variabilidade RR/ FC média da aquisição. Um único caso de BAV, 2:1 Mobitz I, revertido espontaneamente ocorreu (grupo D. CONCLUSÃO: Concluímos que o diltiazem é uma alternativa eficaz e segura aos betabloqueadores na redução da FC na realização de angiografia por tomografia computadorizada das artérias coronarianas. (Arq Bras Cardiol. 2012; [online].ahead print, PP.0-0

  20. Transiente superdifusivo em caminhadas aleatórias com perfil de memória q-exponencial

    OpenAIRE

    Moura, Thiago Rafael da Silva

    2016-01-01

    Propomos nesta pesquisa um modelo de caminhada aleatória com perfil de decaimento q-exponencial. A função q-exponencial é uma generalização da função exponencial ordinária. No limite q→1, a função q-exponencial torna-se a função exponencial ordinária. Nosso modelo apresenta um comportamento difusivo Markoviano, onde se sabe que o Teorema Central do Limite proibe superdifusão neste caso. Apesar de neste problema não ser esperado o surgimento de uma transição superdifusiva no limite assintótico...

  1. História dos modos gregos : história da estrutura dos gêneros musicais gregos

    OpenAIRE

    Lucas Fernandes de Paula

    2015-01-01

    A pesquisa que se desenvolve sobre a história da música tem por objetivos gerais, compreender, explicar, diversas medidas do objeto de análise: os modos gregos. Especificamente, os objetivos constituem narrativas historiográficas que permitam refletir, no tempo, conteúdos relacionados, e uma história da música perpetrada sob a lente dos chamados modos gregos; pensar o conceito de modos gregos em seu envolvimento com conhecimentos teóricos e práticos em Geografia, Física, Matemática, Filosofia...

  2. Memórias perdidas, identidades sem cidadania

    Directory of Open Access Journals (Sweden)

    Ungulani Ba Ka Khosa

    2015-04-01

    Full Text Available Este texto procura contribuir para o debate sobre as políticas identitárias no Moçambique contemporâneo. Contrapondo, através de vários exemplos, a diversidade identitária do tecido social do país à altivez ignorante das estruturas de poder nele presentes, o texto procura problematizar, em vários momentos históricos, a fratura cognitiva entre o projeto político nacional, conceptualizado a partir das elites que controlam o Estado, e o plurilinguismo e a polifonia que constroem o tecido social real. A partir desta dicotomia o texto explora o discurso sobre a nação a várias vozes, problematizando os sentidos das lições da história de Moçambique e os múltiplos silenciamentos que a narrativa histórica dominante vem realizando.

  3. Cutis verticis gyrata primária essencial

    Directory of Open Access Journals (Sweden)

    Schenato Letícia K.

    2002-01-01

    Full Text Available Objetivo: relatar um caso raro de uma criança portadora da forma primária essencial de Cutis verticis gyrata.Descrição: menino de 9 anos, apresenta importante hipertrofia da pele do couro cabeludo, com dobras que se assemelham aos giros cerebrais. Não apresenta retardo mental, nem alterações oftalmológicas e não há relatos semelhantes na família.Comentários: o diagnóstico de Cutis verticis gyrata primária essencial foi estabelecido pela presença de redundância da pele do couro cabeludo e ausência de alterações neurológicas e oftalmológicas, tendo-se feito o diagnóstico diferencial com as formas secundárias que incluem: nevo intradérmico cerebriforme, paquidermoperiostose, acromegalia e doenças inflamatórias do couro cabeludo. Trata-se do único relato na literatura de uma criança com esta forma de Cutis verticis gyrata.

  4. O "Programa Alfabetização Solidária": terceirização no contexto da reforma do Estado "Programa Alfabetização Solidária" literacy program and State reform in Brazil

    Directory of Open Access Journals (Sweden)

    Gladys Beatriz Barreyro

    2010-12-01

    Full Text Available O presente trabalho busca analisar o Programa Alfabetização Solidária a partir de um modelo de Estado proposto pelo governo do presidente Fernando Henrique Cardoso (1997-2002. Considera-se que a proposta de Reforma do Estado ali desenvolvida, a partir do conceito de publicização, teve sua derivação na área social-assistencial do governo na Comunidade Solidária, um ensaio de terceirização na área das políticas sociais. O Alfabetização Solidária, subprograma deste, foi a versão para a área de educação. De modo que algumas características desse Programa específico devem ser discutidas e contextualizadas à luz de um marco mais amplo, analisando conceitos como terceirização, filantropia, empregabilidade temporária, participação social e direito à educação.This article analyses the "Programa de Afabetização Solidária" Literacy Program as a product of the model of State proposed during the two presidential terms of Fernando Henrique Cardoso (1997-2002, in Brazil. I analysed the proposal of State Reform based on publicization and its counterpart in the social-assistance area of the government: the creation of the Solidarity Community ("Comunidade Solidária". This was a test of outsourcing in the social policy area and the "Programa de Afabetização Solidária"Solidarity in Literacy Program, which arose as a subproject of that one, was a laboratory that developed that State model in the educational area. For this reason, some characteristics of this Program are discussed within that frame and concepts like outsourcing, philanthropy, use of cheap and temporary labor force, participation and right to education are analyzed.

  5. Study and modelling of the in-pile densification of the UO{sub 2} and MO{sub x} nuclear oxides; Etude et modelisation de la densification en pile des oxydes nucleaires UO{sub 2} et MO{sub x}

    Energy Technology Data Exchange (ETDEWEB)

    Boulore, A

    2001-03-01

    Amongst the many phenomena which take place in the course of the irradiation of UO{sub 2} or (U, Pu)O{sub 2} nuclear fuels, one of them involves the elimination of a fraction of the as-fabricated porosity. In-pile densification or sintering can reach 2.5%, i.e. approximately half the initial volume of pores is likely to disappear. Our literature survey indicates that the amplitude and kinetics of the phenomenon are both heavily dependent on the initial fuel microstructure. Micro-structural characterisation techniques of oxide fuels have therefore been developed in conjunction with quantitative image analysis methods. The ensuing methodology enables a quantitative comparison of micro-structural features in different fuels and has been applied to ascertaining the influence of the local fission rate and temperature on in-pile densification. It is thus revealed that in-pile operation eliminates a significant fraction of pores smaller than 3 microns in diameter. The experimental data generated has been used to set up a semi-empirical and a mechanistic model. The former is based on experimental results and is not essentially predictive. The inability of this model to predict the in-pile densification of oxide fuels is illustrated by the fact that the maximum fraction of pores that disappears is proportional to an empirical function of fission rate, and temperature. The proportionality factor appears to be difficult to correlate quantitatively to any given micro-structural feature. The model has however been applied to the interpretation of an in-pile densification experiment carried out in the Halden reactor (Norway). The latter model is mechanistic, i.e. it is based on the solution to a set of equations that describe the coupled temperature and radiation induced phenomena which occur in-pile. These can broadly be broken down into three categories: the fission fragment-pore interaction, the creation of point defects as the fission fragments slow down, and the diffusion

  6. Malária grave importada: relato de caso Severe imported malaria: case report

    Directory of Open Access Journals (Sweden)

    Alessandra Alves

    2007-06-01

    Full Text Available JUSTIFICATIVA E OBJETIVOS: A malária ainda representa um problema de saúde global. A forma grave da doença é causada principalmente por P. falciparum e pode cursar com complicações cerebrais, renais, pulmonares, hematológicas, circulatórias e hepáticas. O objetivo deste estudo foi relatar um caso de paciente portador de malária grave importada. RELATO DO CASO: Paciente do sexo masculino, 30 anos, pardo, filipino, marinheiro, proveniente de embarcação vinda da Nigéria, com história de dor abdominal no hipocôndrio direito, icterícia, febre e rebaixamento do nível de consciência. Os exames laboratoriais de admissão mostraram hiperbilirrubinemia de 50 mg/dL, acidose metabólica grave, trombocitopenia, creatinina de 5,6 mg/dL, leucocitose com desvio até metamielócitos. O escore APACHE II foi de 37, com risco de óbito de 88%. Durante a internação foi diagnosticada malária por P. falciparum pelo teste de gota espessa. Mesmo com tratamento antimalárico adequado, o paciente evoluiu com insuficiência renal aguda necessitando de hemodiálise e síndrome de angústia respiratória aguda (SARA, necessitando de ventilação mecânica (VM, choque refratário tratado com aminas vasoativas, além de quadro hematológico, configurando um caso grave de disfunção de múltiplos de órgãos. Ainda apresentou pneumonia associada à VM e sepse relacionada ao uso de cateteres. Após a alta hospitalar, o paciente não apresentou seqüelas cerebral, pulmonar ou renal. CONCLUSÕES: Dos critérios definidores de malária grave descritos na literatura, o paciente preenchia: insuficiência renal aguda, síndrome da angústia respiratória aguda (SARA, acidose metabólica, alteração do nível de consciência, hemoglobinúria macroscópica, hiperparasitemia e hiperbilirrubinemia, que se relaciona a uma mortalidade maior que 10%, na dependência do tratamento precoce e dos recursos disponíveis. A malária grave exige diagnóstico e tratamento

  7. Gas Test Loop Booster Fuel Hydraulic Testing

    International Nuclear Information System (INIS)

    Gas Test Loop Hydraulic Testing Staff

    2006-01-01

    The Gas Test Loop (GTL) project is for the design of an adaptation to the Advanced Test Reactor (ATR) to create a fast-flux test space where fuels and materials for advanced reactor concepts can undergo irradiation testing. Incident to that design, it was found necessary to make use of special booster fuel to enhance the neutron flux in the reactor lobe in which the Gas Test Loop will be installed. Because the booster fuel is of a different composition and configuration from standard ATR fuel, it is necessary to qualify the booster fuel for use in the ATR. Part of that qualification is the determination that required thermal hydraulic criteria will be met under routine operation and under selected accident scenarios. The Hydraulic Testing task in the GTL project facilitates that determination by measuring flow coefficients (pressure drops) over various regions of the booster fuel over a range of primary coolant flow rates. A high-fidelity model of the NW lobe of the ATR with associated flow baffle, in-pile-tube, and below-core flow channels was designed, constructed and located in the Idaho State University Thermal Fluids Laboratory. A circulation loop was designed and constructed by the university to provide reactor-relevant water flow rates to the test system. Models of the four booster fuel elements required for GTL operation were fabricated from aluminum (no uranium or means of heating) and placed in the flow channel. One of these was instrumented with Pitot tubes to measure flow velocities in the channels between the three booster fuel plates and between the innermost and outermost plates and the side walls of the flow annulus. Flow coefficients in the range of 4 to 6.5 were determined from the measurements made for the upper and middle parts of the booster fuel elements. The flow coefficient for the lower end of the booster fuel and the sub-core flow channel was lower at 2.3

  8. Gas Test Loop Booster Fuel Hydraulic Testing

    Energy Technology Data Exchange (ETDEWEB)

    Gas Test Loop Hydraulic Testing Staff

    2006-09-01

    The Gas Test Loop (GTL) project is for the design of an adaptation to the Advanced Test Reactor (ATR) to create a fast-flux test space where fuels and materials for advanced reactor concepts can undergo irradiation testing. Incident to that design, it was found necessary to make use of special booster fuel to enhance the neutron flux in the reactor lobe in which the Gas Test Loop will be installed. Because the booster fuel is of a different composition and configuration from standard ATR fuel, it is necessary to qualify the booster fuel for use in the ATR. Part of that qualification is the determination that required thermal hydraulic criteria will be met under routine operation and under selected accident scenarios. The Hydraulic Testing task in the GTL project facilitates that determination by measuring flow coefficients (pressure drops) over various regions of the booster fuel over a range of primary coolant flow rates. A high-fidelity model of the NW lobe of the ATR with associated flow baffle, in-pile-tube, and below-core flow channels was designed, constructed and located in the Idaho State University Thermal Fluids Laboratory. A circulation loop was designed and constructed by the university to provide reactor-relevant water flow rates to the test system. Models of the four booster fuel elements required for GTL operation were fabricated from aluminum (no uranium or means of heating) and placed in the flow channel. One of these was instrumented with Pitot tubes to measure flow velocities in the channels between the three booster fuel plates and between the innermost and outermost plates and the side walls of the flow annulus. Flow coefficients in the range of 4 to 6.5 were determined from the measurements made for the upper and middle parts of the booster fuel elements. The flow coefficient for the lower end of the booster fuel and the sub-core flow channel was lower at 2.3.

  9. Aspectos actuais da hipertensão arterial pulmonar: primária e secundária

    Directory of Open Access Journals (Sweden)

    Emilia Álvares

    1997-01-01

    Full Text Available RESUMO: A situação patológica mais importante na circulação pulmonar é o desenvolvimeoto da Hipertensão Arterial Pulmonar, que pode resultar de doença parenquimatosa pulmonar, alterações da parede vascular ou da obstrução do lúmen por trombose ou embolia.Procurouse com este trabalho, fazer uma revisão actual da literatura médica acerca da hipertensão arterial pulmonar primária e secundária.Debruçãmos-nos essencialmente, sobre os seus cooceitos fisiopatológicos, critérios diagnósticos e aspectos terapêuticos mais recentes. ABSTRACT: The most important response of pulmonary blood vessels to disease is the development of increased pulmonary arterial pressure that may result from parenchymal disease of the lungs, changes in the walls of the blood vessels or obstruction to the lumen caused by thrombosis or embolization.The aim of the authors in this study, was to make a actual review of the medical literature about of primary and secondary pulmonary hypertension.We report about this entity, essentially physiopatologic concepts, diagnosis approach and therapeutics aspects, more recent. Palavras-chave: Hipertensão Pulmonar, Primária, Secundária, Classificação, Tratamento, Key-words: Pulmonary Hypertension, Primary, Secondary, Classification, Therapeutic

  10. Trajetórias identitárias e sentidos do trabalho docente para professores universitários

    Directory of Open Access Journals (Sweden)

    Tânia Regina Raitz

    2014-04-01

    Full Text Available O presente artigo é resultado de uma pesquisa que teve como objetivo compreender a trajetória identitária profissional de seis professoras universitárias e analisar os sentidos atribuídos por elas ao trabalho docente. A investigação tratou-se, metodologicamente, de uma pesquisa qualitativa. Para tanto, foram realizadas entrevistas semiestruturadas, com o uso do gravador, em que as professoras apresentaram explicações que oferecem, ao leitor, mais elementos para a compreensão de aspectos revelados sobre suas trajetórias profissionais e sobre como significam seu trabalho docente. O tratamento das informações se deu por meio da análise de conteúdo. Os resultados mostram que os sentidos do trabalho, na contemporaneidade, aparecem diversificados, entrecruzados, ambivalentes e contraditórios. Essa diversidade se caracteriza pela complexidade da própria identidade, sempre em constituição, e também em razão de o mundo estar em constante mudança, especialmente o mundo do trabalho, que acaba por afetar o trabalho docente universitário, repercutindo também numa reconfiguração da identidade profissional.

  11. Testing Testing Testing.

    Science.gov (United States)

    Deville, Craig; O'Neill, Thomas; Wright, Benjamin D.; Woodcock, Richard W.; Munoz-Sandoval, Ana; Gershon, Richard C.; Bergstrom, Betty

    1998-01-01

    Articles in this special section consider (1) flow in test taking (Craig Deville); (2) testwiseness (Thomas O'Neill); (3) test length (Benjamin Wright); (4) cross-language test equating (Richard W. Woodcock and Ana Munoz-Sandoval); (5) computer-assisted testing and testwiseness (Richard Gershon and Betty Bergstrom); and (6) Web-enhanced testing…

  12. Fisioterapia respiratória no pré-operatório de colecistectomia

    Directory of Open Access Journals (Sweden)

    Lucas Lima Ferreira

    2013-05-01

    Full Text Available Introdução: As cirurgias abdominais altas causam alterações da função pulmonar caracterizadas por redução da capacidade vital, relacionada à presença de hipoxemia e atelectasia, e pela  redução do volume expiratório forçado no primeiro segundo. Relato do caso: Paciente do sexo feminino, 29 anos, diagnóstico médico de cálculos biliares e hérnia hiatal, diagnóstico funcional de baixo desempenho cardiorrespiratório, a três meses de préoperatório de colecistectomia. Foi realizada avaliação composta por dados antropométricos, espirometria, teste de caminhada de seis minutos (TC6, mensuração das pressões respiratórias pIntrodução: As cirurgias abdominais altas causam alterações da função pulmonar caracterizadas por redução da capacidade vital, relacionada à presença de hipoxemia e atelectasia, e pela redução do volume expiratório forçado no primeiro segundo. Relato do caso: Paciente do sexo feminino, 29 anos, diagnóstico médico de cálculos biliares e hérnia hiatal, diagnóstico funcional de baixo desempenho cardiorrespiratório, a três meses de préoperatório de colecistectomia. Foi realizada avaliação composta por dados antropométricos, espirometria, teste de caminhada de seis minutos (TC6, mensuração das pressões respiratórias por meio da manovacuometria e do nível de qualidade de vida mediante o questionário SF-36. A seguir foi aplicado um protocolo de fisioterapia respiratória e reavaliação após o tratamento. Na avaliação inicial foi verificado que a paciente encontravase com sobrepeso (IMC=27,40 kg/m2, baixo desempenho cardiorrespiratório e fraqueza da musculatura respiratória. Conclusão: O protocolo aplicado mostrou-se eficaz, pois auxiliou na redução de peso corporal e melhorou o desempenho cardiorrespiratório por meio dos exercícios aeróbicos, e proporcionou ganho de força aos músculos respiratórios.

  13. COMPARAÇÃO DE TIRAS REAGENTES PARA URINÁLISE VETERINÁRIA

    Directory of Open Access Journals (Sweden)

    Rudison da Silva Florêncio

    2016-11-01

    Full Text Available No exame de urina é possível identificar parâmetros como pH, glicose, cetona, proteína, bilirrubina, urobilinogênio, densidade, hemoglobina, leucócitos, ácido ascórbico, outros e o exame do sedimento urinário. Este estudo foi desenvolvido para comparar as marcas de tiras reagentes de urina Roche Combur10 Test® UX, Labtest Uriquest Plus VET® e Inlab Uri-test11® com a marca utilizada na rotina do Laboratório de Análises Clínicas, a Labtest Uriquest Plus®. Foi observada discrepâncias entre os resultados das marcas desenvolvidas para a medicina humana com a marca desenvolvida para a medicina veterinária e entre elas, nos exames da urina de cães atendidos no Hospital Veterinário. Foi possível observar que os parâmetros de pH, densidade e proteína urinária apresentaram maiores discrepâncias entre as fitas quando comparado com padrões para dosagens da densidade por refratometria e da proteína por espectrofotometria. Há necessidade de padronização do exame de urina com tiras reagentes, pois é um valioso auxílio ao diagnóstico de doenças renais e extra-renais.

  14. Gênero, etnia e movimentos sociais na história da educação

    OpenAIRE

    Forde, Gustavo Henrique Araújo; Instituto Federal do Espírito Santo

    2013-01-01

    FRANCO, Sebastião Pimentel; SÁ, Nicanor Palhares (Org.). Gênero, etnia e movimentos sociais nahistória da educação. Vitória – ES: EDUFES, 2011.(Coleção Horizontes da pesquisa em História daEducação no Brasil, 9).

  15. Aprendizado e memória Learning and memory

    Directory of Open Access Journals (Sweden)

    Paul Lombroso

    2004-09-01

    Full Text Available A memória é dividida de duas grandes formas: explícita e implícita. O hipocampo é necessário para a formação das memórias explícitas, ao passo que várias outras regiões do cérebro, incluindo o estriado, a amígdala e o nucleus accumbens, estão envolvidos na formação das memórias implícitas. A formação de todas as memórias requer alterações morfológicas nas sinapses: novas sinapses devem ser formadas ou antigas precisam ser fortalecidas. Considera-se que essas alterações reflitam a base celular subjacente das memórias persistentes. Consideráveis avanços têm ocorrido na última década em relação a nossa compreensão sobre as bases moleculares da formação dessas memórias. Um regulador-chave da plasticidade sináptica é uma via de sinalização que inclui a proteína-quinase ativada por mitógenos (MAP. Como essa via é necessária para a memória e o aprendizado normais, não é surpreendente que as mutações nos membros dessa via levem a prejuízos no aprendizado. A neurofibromatose, a síndrome de Coffin-Lowry e a de Rubinstein-Taybi são três exemplos de transtornos de desenvolvimento que apresentam mutações em componentes-chave na via de sinalização da proteína-quinase MAP.Memory is broadly divided into declarative and nondeclarative forms of memory. The hippocampus is required for the formation of declarative memories, while a number of other brain regions including the striatum, amygdala and nucleus accumbens are involved in the formation of nondeclarative memories. The formation of all memories require morphological changes of synapses: new ones must be formed or old ones strengthened. These changes are thought to reflect the underlying cellular basis for persistent memories. Considerable advances have occurred over the last decade in our understanding of the molecular bases of how these memories are formed. A key regulator of synaptic plasticity is a signaling pathway that includes the mitogen

  16. Analysis of the LBLOCAs in the HANARO pool for the 3-pin fuel test loop

    International Nuclear Information System (INIS)

    Park, S. K.; Chi, D. Y.; Sim, B. S.; Park, K. N.; Ahn, S. H.; Lee, J. M.; Lee, C. Y.; Kim, Y. J.

    2004-12-01

    The Fuel Test Loop(FTL) has been developed to meet the increasing demand on fuel irradiation and burn up test required the development of new fuels in Korea. It is designed to provide the test conditions of high pressure and temperature like the commercial PWR and CANDU power plants. And also the FTL have the cooling capability to sufficiently remove the thermal power of the in-pile test section for normal operation, Anticipated Operational Occurrences(AOOs), and Design Basis Accidents(DBAs). This report deals with the Large Break Loss of Coolant Accidents (LBLOCAs) in HANARO pool for the 3-pin fuel test loop. The MARS code has been used for the prediction of the emergency core cooling capability of the FTL and the peak cladding temperature of the test fuels for the LBLOCAs. The location of the pipe break is assumed at the hill taps connecting the cold and hot legs in HANARO pool to the inlet and outlet nozzles of the In-Pile test Section (IPS). Double ended guillotine break is assumed for the large break loss of coolant accidents. The discharge coefficients of 0.1, 0.33, 0.67, 1.0 are investigated for the LBLOCAs. The test fuels for PWR and CANDU test modes are not heated up for the LBLOCAs caused by the double ended guillotine break in the HANARO pool. The reason is that the sufficient emergency cooling water to cool down the test fuels is supplied continuously to the in-pile test section. Therefore the PCTs for the LBLOCAs in the HANARO pool meet the design criterion of commercial PWR fuel that maximum PCT is lower than 1204 .deg. C

  17. A Recepção dos Tratados Internacionais em Matéria Tributária pelo Ordenamento Jurídico Brasileiro

    OpenAIRE

    Bianca Castellar de Faria

    2006-01-01

    A presente dissertação objetiva analisar a forma de recepção dos tratados internacionais em matéria tributária pelo ordenamento jurídico brasileiro. Para isso, é fundamental verificar a relação entre o direito internacional e o direito interno, por meio da análise das teorias monista e dualista. Apresenta-se o Direito Tributário Internacional como uma das variações do Direito Internacional Público, com o objetivo de introduzir a matéria tributária. Estudam-se os tratados como uma das principa...

  18. Avaliação pré-operatória: triagem por meio de questionário

    Directory of Open Access Journals (Sweden)

    Florentino Fernandes Mendes

    2013-08-01

    Full Text Available JUSTIFICATIVA E OBJETIVOS: Antes de cirurgia eletiva é indispensável conhecer com antecedência as condições clínicas do paciente. O objetivo deste estudo foi comparar a avaliação pré-operatória (APO por meio do preenchimento de um questionário com a consulta realizada pelo anestesiologista. MÉTODO: Antes da consulta pré-operatória, os pacientes responderam a um questionário com informações sobre idade, peso, altura, cirurgia planejada, história médica e cirúrgica pregressa, alergias, medicamentos e doses usadas, história social (drogas ilícitas, álcool, tabagismo, capacidade funcional e tolerância ao exercício. A consulta pré-operatória foi realizada por anestesiologista que não tinha acesso aos dados do questionário nem conhecimento da pesquisa. Os dados obtidos por meio do questionário foram comparados com a consulta pré-operatória por dois pesquisadores independentes, com a finalidade de responder às perguntas: 1 A avaliação pelo questionário foi suficiente - o paciente poderia ser conduzido à cirurgia sem necessidade da avaliação presencial? 2 Houve alguma informação relevante - capaz de mudar a conduta anestésica - que o questionário não aferiu, mas que a consulta presencial avaliou? 3 Houve alguma informação acrescentada pelo questionário de saúde que a consulta presencial não obteve? Para análise estatística usou-se o teste t de Student pareado para dados paramétricos e o teste Qui-quadrado para dados categóricos com P 30, baixa capacidade funcional, hipertensão arterial, diabetes mellitus, asma, insuficiência renal, hepatite e cardiopatia isquêmica. CONCLUSÕES: O uso do questionário foi efetivo para triagem de pacientes que necessitam de avaliação complementar e/ou alteração de regime terapêutico previamente ao procedimento eletivo. Além disso, o questionário acrescentou dados não contemplados pela avaliação clínica.

  19. Reactivity Insertion Accident (RIA) Capability Status in the BISON Fuel Performance Code

    Energy Technology Data Exchange (ETDEWEB)

    Williamson, Richard L. [Idaho National Lab. (INL), Idaho Falls, ID (United States); Folsom, Charles Pearson [Idaho National Lab. (INL), Idaho Falls, ID (United States); Pastore, Giovanni [Idaho National Lab. (INL), Idaho Falls, ID (United States); Veeraraghavan, Swetha [Idaho National Lab. (INL), Idaho Falls, ID (United States)

    2016-05-01

    One of the Challenge Problems being considered within CASL relates to modelling and simulation of Light Water Reactor LWR) fuel under Reactivity Insertion Accident (RIA) conditions. BISON is the fuel performance code used within CASL for LWR fuel under both normal operating and accident conditions, and thus must be capable of addressing the RIA challenge problem. This report outlines required BISON capabilities for RIAs and describes the current status of the code. Information on recent accident capability enhancements, application of BISON to a RIA benchmark exercise, and plans for validation to RIA behavior are included.

  20. EXTENSÃO UNIVERSITÁRIA: INSTITUCIONALIDADE E COMPROMISSO SOCIAL.

    OpenAIRE

    Souza, Lenilza Alves Pereira

    2013-01-01

    Esta dissertação mostra a análise da extensão universitária, no tocante à institucionalidade e ao compromisso social, o que possibilita a compreensão da extensão como prática de ações interlocutoras que integram a produção e a sistematização do conhecimento ao processo de aprendizagem, como lócus da indisssociabilidade entre ensino, pesquisa e extensão. A pesquisa identifica que a extensão no Brasil apresenta vários conceitos e concepções em sua trajetória histórica no conte...

  1. RIA of alpha-fetoprotein in serum and amniotic fluid

    International Nuclear Information System (INIS)

    Fingerova, H.; Talas, M.; Stroufova, A.

    1979-01-01

    An own modification of the double antibody radioimmunoassay for AFP using 125 I-labelled AFP as a tracer, rabbit anti-AFP obtained from SEVAC, Prague and precipitating antibodies prepared by the authors is described. The AFP levels measured in the serum and the amniotic fluid using the method were in agreement with those obtained by the means of the AFPK RIA kit by SORIN in the Institute for the Care of Mother and Child in Prague. The AFP concentrations found in the cord serum and the amniotic fluid were confirmed also by the rocket electroimmunoassay according to Laurell. The described AFP RIA seems suitable for the clinical application in prenatal screening for congenital malformations, in difficult pregnancies, in hepatology and the diagnosis and the evaluation of therapy of some human malignancies. (author)

  2. Hiperplasia fibroepitelial mamária em felinos: cinco casos

    Directory of Open Access Journals (Sweden)

    Souza Tatiana Mello de

    2002-01-01

    Full Text Available São descritos cinco casos de hiperplasia fibroepitelial mamária em gatas com idades variando entre 10 meses e 11 anos. A principal queixa por ocasião do atendimento era relacionada à tumefação das mamas com evolução clínica entre 3 e 24 semanas. Em duas das gatas, a condição desenvolveu-se após o tratamento com contraceptivos. Macroscopicamente, as tumorações na glândula mamária eram cobertas por pele, ocasionalmente ulceradas, e tinham superfície de corte brancacenta com nódulos multifocais mais pálidos de 2mm de diâmetro. Histologicamente, esses nódulos multifocais consistiam de proliferação ductal cercadas por crescimento abundante de tecido conjuntivo fibroso.

  3. Imunidade tributária : perspectivas da imunidade religiosa

    OpenAIRE

    Jackson Urquiza da Costa e Silva

    2012-01-01

    O presente trabalho tem por objetivo discutir os limites e as perspectivas da imunidade tributária religiosa prevista na Constituição da República Federativa do Brasil. Antes de discutir-se a essência dessa questão, fez-se uma breve passagem histórica da evolução da imunidade tributária, desde seu surgimento no império romano ao estado moderno; e especificamente no Brasil, desde os tempos como colônia de Portugal à Constituição de 1988. Após serem fixados os critérios informadores da ...

  4. RIA of alpha-fetoprotein in serum and amniotic fluid

    Energy Technology Data Exchange (ETDEWEB)

    Fingerova, H; Talas, M; Stroufova, A [Palackeho Univ., Olomouc (Czechoslovakia). Lekarska Fakulta; Santavy, J; Krikal, Z [Ustav pro Peci o Matku a Dite, Prague (Czechoslovakia)

    1979-01-01

    An own modification of the double antibody radioimmunoassay for AFP using /sup 125/I-labelled AFP as a tracer, rabbit anti-AFP obtained from SEVAC, Prague and precipitating antibodies prepared by the authors is described. The AFP levels measured in the serum and the amniotic fluid using the method were in agreement with those obtained by the means of the AFPK RIA kit by SORIN in the Institute for the Care of Mother and Child in Prague. The AFP concentrations found in the cord serum and the amniotic fluid were confirmed also by the rocket electroimmunoassay according to Laurell. The described AFP RIA seems suitable for the clinical application in prenatal screening for congenital malformations, in difficult pregnancies, in hepatology and the diagnosis and the evaluation of therapy of some human malignancies.

  5. Avaliação da qualidade de vida e função sexual de mulheres com e sem incontinência urinária

    Directory of Open Access Journals (Sweden)

    Kelly Faria

    2012-06-01

    Full Text Available A incontinência urinária é a queixa de perda involuntária de urina. Os objetivos do presente estudo foram mensurar e comparar a qualidade de vida e a função sexual de mulheres com e sem incontinência urinária. Foram entrevistadas setenta mulheres, com e sem incontinência urinária. Os dados foram coletados por meio dos seguintes instrumentos: WHOQOL-BREF, KHQ e FSFI. Foram realizadas análises descritivas e teste t Student pareado (p<0,05. A qualidade de vida mensurada pelo WHOQOL–BREF evidenciou que as mulheres incontinentes apresentaram média de escore menor (S=57,14 quando comparadas com as continentes (S=71,42. Na avaliação da função sexual, o grupo GI obteve média total de escore menor (S=17,17 quando comparado com o grupo GC (S=24,20. Concluiu-se que tanto na análise da qualidade de vida quanto na função sexual os menores escores foram encontrados no grupo incontinente, evidenciando assim o impacto negativo da incontinência urinária na vida dessas mulheres.

  6. Alterações do desenvolvimento de crianças prematuras nascidas de mães com malária no periodo gestacional

    OpenAIRE

    Simões, Maria da Conceição Ribeiro

    2012-01-01

    Objetivo : O estudo buscou avaliar as alterações no desenvolvimento de crianças prematuras nascidas de mães com malária no periodo gestacional, em Porto Velho, Rondônia. O objetivo principal é descrever as alterações encontradas nessas crianças aplicando um teste preditivo para alterações no desenvolvimento e compará-las à um grupo controle de crianças prematuras nascidas de mães que não apresentaram malária no periodo gestacional. Métodos : Por ser um estudo do tipo transvers...

  7. Enterobactérias isoladas de baratas (Periplaneta americana capturadas em um hospital brasileiro

    Directory of Open Access Journals (Sweden)

    Marinésia A. Prado

    2002-02-01

    Full Text Available Objetivo. Isolar e identificar microrganismos em baratas capturadas em um hospital público e determinar o seu perfil de suscetibilidade antimicrobiana. Métodos. As baratas foram capturadas nos períodos matutino e noturno, colocadas em frascos desinfetados com álcool a 70%, transferidas para um frasco estéril e levadas ao laboratório. Consideraram-se as baratas íntegras e vivas, as quais foram colocadas em solução salina estéril (0,8% e homogeneizadas. Essa solução foi semeada nos meios de cultura ágar MacConkey, caldo nutriente, infusão de cérebro e coração (ágar BHI, ágar Sabouraud e ágar manitol. As culturas foram examinadas em um estereomicroscópio para a contagem das unidades formadoras de colônias. Para a determinação do perfil de suscetibilidade antimicrobiana utilizou-se o teste de difusão de disco. Resultados. Detectou-se prevalência de 56% de enterobactérias e de 18% de estafilococos coagulase negativos. Identificaram-se 15 espécies de enterobactérias. As mais freqüentes foram Klebsiella pneumoniae (17%; Enterobacter aerogenes (14%; Serratia marcescens (13%; Hafnia alvei (12%; Enterobacter gergoviae e Enterobacter cloacae (9%; e Serratia spp. (6%. Tanto as enterobactérias quanto os estafilococos coagulase negativos apresentaram uma resistência significativa aos antimicrobianos, inclusive à oxacilina. Conclusões. A prevalência de bactérias enteropatogênicas e de estafilococos coagulase negativos isolados de baratas Periplaneta americana no hospital estudado demonstra a fragilidade das condutas adotadas tanto para o controle de vetores quanto para o uso dos antimicrobianos. Os resultados demonstram a necessidade da implementação de um programa efetivo de saneamento ambiental e do uso racional dos antimicrobianos dentro das instituições de saúde.

  8. Enterobactérias isoladas de baratas (Periplaneta americana capturadas em um hospital brasileiro

    Directory of Open Access Journals (Sweden)

    Prado Marinésia A.

    2002-01-01

    Full Text Available Objetivo. Isolar e identificar microrganismos em baratas capturadas em um hospital público e determinar o seu perfil de suscetibilidade antimicrobiana. Métodos. As baratas foram capturadas nos períodos matutino e noturno, colocadas em frascos desinfetados com álcool a 70%, transferidas para um frasco estéril e levadas ao laboratório. Consideraram-se as baratas íntegras e vivas, as quais foram colocadas em solução salina estéril (0,8% e homogeneizadas. Essa solução foi semeada nos meios de cultura ágar MacConkey, caldo nutriente, infusão de cérebro e coração (ágar BHI, ágar Sabouraud e ágar manitol. As culturas foram examinadas em um estereomicroscópio para a contagem das unidades formadoras de colônias. Para a determinação do perfil de suscetibilidade antimicrobiana utilizou-se o teste de difusão de disco. Resultados. Detectou-se prevalência de 56% de enterobactérias e de 18% de estafilococos coagulase negativos. Identificaram-se 15 espécies de enterobactérias. As mais freqüentes foram Klebsiella pneumoniae (17%; Enterobacter aerogenes (14%; Serratia marcescens (13%; Hafnia alvei (12%; Enterobacter gergoviae e Enterobacter cloacae (9%; e Serratia spp. (6%. Tanto as enterobactérias quanto os estafilococos coagulase negativos apresentaram uma resistência significativa aos antimicrobianos, inclusive à oxacilina. Conclusões. A prevalência de bactérias enteropatogênicas e de estafilococos coagulase negativos isolados de baratas Periplaneta americana no hospital estudado demonstra a fragilidade das condutas adotadas tanto para o controle de vetores quanto para o uso dos antimicrobianos. Os resultados demonstram a necessidade da implementação de um programa efetivo de saneamento ambiental e do uso racional dos antimicrobianos dentro das instituições de saúde.

  9. Ante-projeto "Memória Social Paulista"

    Directory of Open Access Journals (Sweden)

    Jaelson Bitran Trindade

    1977-09-01

    Full Text Available (parágrafo do texto Este projeto toma como preocupação básica as tarefas de preservação e valorização do patrimônio cultural do país: a "memória nacional", isto é, o conhecimento de nossa identidade, de nossa vida social. E isto diz respeito diretamente, portanto, ao homem brasi-leiro na sua integralidade.

  10. Cascas sobre o papel: memória do dilaceramento

    Directory of Open Access Journals (Sweden)

    Vera Casa Nova

    2014-08-01

    Full Text Available O ensaio tenta mostrar como o autor Georges Didi-Huberman, na obra Écorces (Cascas, nos apresenta sua experiência de rastros (W. Benjamin e sua interpretação do dilaceramento nos campos de Auschwitz Birkenau.Trata-se de uma narrativa de ruínas pela palavra e pela imagem (fotografia. Escritura que se encontra entre a pesquisa histórica e a empresa literária autobiográfica.

  11. O percurso de uma pesquisa em História

    Directory of Open Access Journals (Sweden)

    Maria Siqueira Santos

    2012-03-01

    Full Text Available Esse texto é o relato da pesquisa que empreendi quando realizava o curso de Mestrado em História Social na Universidade Estadual de Londrina. Iniciei a pesquisa estudando o romance Nove noites de Bernardo Carvalho, embrenhei-me pelo labirinto de suas vozes narrativas e envolvi-me na discussão a respeito de sua metaficcionalidade. Em seguida, analisei teses acadêmicas que focalizavam tais metaficções. Queria visualizar o discurso acadêmico acerca da literatura contemporânea, perceber se tais trabalhos poderiam ser classificados como metaficcionais. Ao ler as teses, porém, descobri António Lobo Antunes. Autor de vários romances, esse português começou sua produção literária com Memória de elefante, cuja trama se desenrola ao longo do dia de um psiquiatra que encontra na linguagem a possibilidade de transformar o mundo. Quando pensava finalmente ter encontrado minha fonte histórica, um episódio casual, o encontro com um livro, mudou a direção de minha pesquisa. Escrito pelo filósofo Peter Sloterdijk, A árvore mágica conta a história do magnetismo animal; é “uma tentativa épica com relação à filosofia da psicologia.” O presente texto, por ser um relato do percurso da pesquisa de fontes, termina no momento em que descobri esse romance e pude delimitar o assunto a ser tratado em meu texto dissertativo.

  12. RIA for the determination of serum osteocalcin level

    International Nuclear Information System (INIS)

    Lakatos, P.; Tarjan, G.; Koranyi, L.

    1989-01-01

    The antigen was separated from bovin bone and antibodies were gained by immunization of rabbits. When high titer of antibody was reached, the RIA was set up. The antigen was labelled with 125 I. The sensitivity is 1.2 ng/ml, intraassay coefficient of variation is 3.4%, interassay coefficient of variation is 8.1%, and the normal range is 6-14 ng/ml. (author) 18 refs.; 1 fig.; 1 tab

  13. A culinária na promoção da alimentação saudável: delineamento e experimentação de método educativo dirigido a adolescentes e a profissionais das redes de saúde e de educação Cooking in the promotion of a healthy diet: designing and testing an education model directed to adolescents and professionals of healthcare and education networks

    Directory of Open Access Journals (Sweden)

    Inês Rugani Ribeiro de Castro

    2007-12-01

    Full Text Available OBJETIVO: Apresentar o delineamento e a experimentação de método educativo para promoção da alimentação saudável, tendo a culinária como seu eixo estruturante. MÉTODOS: Os referenciais teóricos adotados foram: preceitos da promoção da saúde, concepção crítica de educação em saúde, direito humano à alimentação adequada e segurança alimentar e nutricional e reflexões sobre cultura alimentar no contexto da contemporaneidade. As etapas de desenvolvimento do projeto contemplaram: identificação de representantes dos grupos de interesse (merendeiras, professores de ensino fundamental, adolescentes e profissionais de saúde da atenção básica, incluindo equipes de Saúde da Família; estruturação e experimentação, na cidade do Rio de Janeiro, do modelo de ação educativa; análise dos materiais coletados e confecção de materiais educativos. RESULTADOS: O modelo proposto e experimentado consistiu em oficina educativa estruturada em: vivência culinária; debate entre os participantes; encontro denominado Temperando Conceitos, no qual foram aprofundados os temas surgidos no debate; e encontro de avaliação de todo o projeto. Foram realizadas oito oficinas educativas envolvendo 116 participantes, que avaliaram o modelo proposto como capaz de os sensibilizar sobre o tema e incentivar para mudanças em relação à sua prática profissional e pessoal. CONCLUSÃO: O modelo experimentado configura-se em inovação metodológica no campo das práticas educativas para promoção da alimentação saudável e mostrou-se factível de ser aplicado. Como forma de continuidade do estudo, está em curso projeto de pesquisa para desenvolvimento de método educativo voltado à formação de multiplicadores para a promoção da alimentação saudável, utilizando o modelo aqui apresentado como uma de suas estratégias educativas.OBJECTIVE: To present the designing and testing of an educational methodology for the promotion of a healthy

  14. Considerations on a PAHR test facility

    International Nuclear Information System (INIS)

    Boenisch, G.; Groetzbach, G.; Heinzel, V.; Kleefeld, K.; Kuechle, M.; Mueller, R.A.; Royl, P.; Schramm, K.; Smidt, D.; Werle, H.

    1976-01-01

    On the basis of a hypothetical core disruptive accident (HCDA) analysis the phenomena of the post accident phase are first identified which require experimental investigations and can only be studied in pile. Then the experimental requests for both debris bed and molten fuel pool studies are specified and grouped into three categories. For two of the categories the requests can be satisfied with loop experiments in thermal reactors. For the third category a 70 cm diameter test bed is needed and here the proposal is to use a flat core fast reactor with the test bed located below the core heated by axial leakage neutrons. Finally a conceptual design for such a reactor is presented where the test bed is loaded into an ex-vessel device and is removable on a carriage to a hot cell building. Maintenance and safety problems are briefly discussed and alternative solutions are mentioned

  15. Verification test for radiation reduction effect and material integrity on PWR primary system by zinc injection

    Energy Technology Data Exchange (ETDEWEB)

    Kawakami, H.; Nagata, T.; Yamada, M. [Nuclear Power Engineering Corp. (Japan); Kasahara, K.; Tsuruta, T.; Nishimura, T. [Mitsubishi Heavy Industries, Ltd. (Japan); Ishigure, K. [Saitama Inst. of Tech. (Japan)

    2002-07-01

    Zinc injection is known to be an effective method for the reduction of radiation source in the primary water system of a PWR. There is a need to verify the effect of Zn injection operation on radiation source reduction and materials integrity of PWR primary circuit. In order to confirm the effectiveness of Zn injection, verification test as a national program sponsored by Ministry of Economy, Trade and Industry (METI) was started in 1995 for 7-year program, and will be finished by the end of March in 2002. This program consists of irradiation test and material integrity test. Irradiation test as an In-Pile-Test managed by AEAT Plc(UK) was performed using the LVR-15 reactor of NRI Rez in Check Republic. Furthermore, Out-of-Pile-Test using film adding unit was also performed to obtain supplemental data for In-Pile-Test at Takasago Engineering Laboratory of NUPEC. Material Integrity test was planned to perform constant load test, constant strain test and corrosion test at the same time using large scale Loop and slow strain extension rate testing (SSRT) at Takasago Engineering Laboratory of NUPEC. In this paper, the results of the verification test for Zinc program at present are discussed. (authors)

  16. Imagens da cidade: memória coletiva em Londrina

    Directory of Open Access Journals (Sweden)

    Ana Cleide Chiarotti Cesário

    2004-12-01

    Full Text Available O presente artigo, além de apresentar as experiências de um projeto de pesquisa e extensão, desenvolvido por um grupo interdisciplinar de docentes e acadêmicos da Universidade Estadual de Londrina das diferentes áreas do conhecimento (Antropologia, Arquitetura, Ciência Política, História e Sociologia, discute aspectos teóricos-metodológicos importantes que envolvem as ações de política cultural, bem como os trabalhos com o Patrimônio Cultural na região norte paranaense, especialmente, na cidade de Londrina. Nesse sentido, emergem discussões importantes acerca de categorias teóricas como cultura, patrimônio, preservação, memória, representações, imaginário, identidade, aliadas à investigação de campo e à utilização de procedimentos metodológicos, que contemplam tanto o estudo do cotidiano quanto a utilização da história oral, e que estão sendo, atualmente, objetos de novas reflexões, a exemplo do Projeto de Pesquisa: "Londrina - imagens da cidade", desenvolvido pelas autoras deste trabalho.

  17. Caminhos entre a literatura e a história

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    Bosi Alfredo

    2005-01-01

    Full Text Available O ARTIGO resume o itinerário do autor como historiador da Literatura Brasileira, teórico de poesia e estudioso de nossa formação cultural. Os momentos iniciais desse percurso recebem particular atenção: o estudo da Estética de Croce, o conhecimento da filosofia marxista de Gramsci, a influência do existencialismo cristão no final dos anos de 1950 e o engajamento na política de esquerda no Brasil dos anos de 1960 e 1970. Como docente de Literatura Italiana, o autor escreveu teses sobre Pirandello e Leopardi, ambas inéditas. Trabalhando no campo da história literária, na esteira da obra de Otto Maria Carpeaux, examinou as relações dialéticas entre ideologia e poesia e ideologia e narrativa, o que lhe abriu caminho para o seu conceito de literatura como resistência. Ao elaborar a Dialética da Colonização, dedicou-se ao estudo das tensões que marcam a história das ideologias no Brasil.

  18. Tecnologia, experiência e memória

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    Aécio Amaral Jr

    2006-10-01

    Full Text Available O artigo investiga a estruturação de uma nova cultura de memória, a qual inverte a lógica metafísica com que se pensou a relação entre tecnologia e experiência nas ciências sociais. Com as recentes tecnologias da vida e da informação, a concepção do corpo humano como algo que se constitui à margem de um aparato tecnológico declina em credibilidade. Com isso, um dos principais projetos da metafísica ocidental, a saber, a estruturação de um campo de experiência e conhecimento livre de suportes técnicos, malogra em seu humanismo tecnofóbico. A partir de uma apreciação do conto Memento Mori, de Jonathan Nolan, e do filme Amnésia, de Christopher Nolan, analiso a relação entre memória e escritura, corpo e arquivo na contemporaneidade. O objetivo é perceber as tensões e oscilações implícitas na tentativa de instauração de uma mnemotécnica pretensamente pós-humana ou pós-orgânica. Palavras-chave: tecnologia; experiência; memória; humanismo; pós-humanismo.

  19. Impossibilidade de alteração de lei complementar por lei ordinária em matéria tributária

    Directory of Open Access Journals (Sweden)

    Marcelo de Lima Castro Diniz

    2000-03-01

    Full Text Available Usually the legislator controls a specific subject through a complementary law, although it can be done through a ordinary law, which is different concerning the legislative process, mainly on the quorum matter. A law with these characteristics must be considered complementary law, so that its modification is only possible by a norm on the same level. According to the principles of “more value legitimatory” and liberty of conformation of the legislator in his legislative activity.É comum que o legislador regule um determinado assunto por meio de lei complementar, embora pudesse fazê-lo através de lei ordinária, cujo processo legislativo é diferente, sobretudo pela questão do quorum. Uma lei com essas características deve ser considerada lei complementar, decorrendo daí que sua modificação apenas é possível por norma do mesmo escalão, em face dos princípios da mais valia legitimatória e da liberdade de conformação do legislador na atividade legislativa.

  20. Social benefits of the RIA technique in the State of Zacatecas

    International Nuclear Information System (INIS)

    Badillo R, Y.; Badillo A, V.

    2004-01-01

    Presently work was carried out tests of thyroid function to 159 patients with the purpose of evaluating the incidence of thyroid illnesses, being based these studies on the method of Radio immuno analysis (RIA). During this work they were studied 159 patients, men (21%) and women (79%), to which were practiced the tests of thyroid function, applying the technique of Radio immuno analysis, throwing the following results: Healthy patients (58.5%); Hyper thyroidal patients (22.6%), Hypo thyroidal patients (18.9%). The social benefit of this technique and their importance is because the patients that go to this laboratory are of scarce resources and otherwise; they would not simply be diagnose, since we have found patients that have taken until 10 years in that are diagnosed thyroid abnormalities. (Author)