WorldWideScience

Sample records for pb-versus na-cooled lmr

  1. Development of MATRA-LMR code α-version for LMR subchannel analysis

    International Nuclear Information System (INIS)

    Kim, Won Seok; Kim, Young Gyun; Kim, Young Gin

    1998-05-01

    Since the sodium boiling point is very high, maximum cladding and pin temperature are used for design limit condition in sodium cooled liquid metal reactor. It is necessary to predict accurately the core temperature distribution to increase the sodium coolant efficiency. Based on the MATRA code, which is developed for PWR analysis, MATRA-LMR is being developed for LMR. The major modification are as follows : A) The sodium properties table is implemented as subprogram in the code. B) Heat transfer coefficients are changed for LMR C) The pressure drop correlations are changed for more accurate calculations, which are Novendstern, Chiu-Rohsenow-Todreas, and Cheng-Todreas correlations. To assess the development status of MATRA-LMR code, calculations have been performed for ORNL 19 pin and EBR-II 61 pin tests. MATRA-LMR calculation results are also compared with the results obtained by the ALTHEN code, which uses more simplied thermal hydraulic model. The MATRA-LMR predictions are found to agree well to the measured values. The differences in results between MATRA-LMR and SLTHEN have occurred because SLTHEN code uses the very simplied thermal-hydraulic model to reduce computing time. MATRA-LMR can be used only for single assembly analysis, but it is planned to extend for multi-assembly calculation. (author). 18 refs., 8 tabs., 14 figs

  2. LMR steam generator blowdown with RETRAN

    International Nuclear Information System (INIS)

    Wei, T.Y.C.

    1985-01-01

    One of the transients being considered in the FSAR Chapter 15 analyses of anticipated LMR transients is the fast blowdown of a steam generator upon inadvertent actuation of the liquid metal/water reaction mitigation system. For the blowdown analysis, a stand-alone steam generator model for the IFR plant was constructed using RETRAN

  3. Development of safety analysis technology for LMR

    International Nuclear Information System (INIS)

    Hahn, Do Hee; Kwon, Y. M.; Kim, K. D.

    2000-05-01

    The analysis methodologies as well as the analysis computer code system for the transient, HCDA, and containment performance analyses, which are required for KALIMER safety analyses, have been developed. The SSC-K code has been developed based on SSC-L which is an analysis code for loop type LMR, by improving models necessary for the KALIMER system analysis, and additional models have been added to the code. In addition, HCDA analysis model has been developed and the containment performance analysis code has been also improved. The preliminary basis for the safety analysis has been established, and the preliminary safety analyses for the key design features have been performed. In addition, a state-of-art analysis for LMR PSA and overseas safety and licensing requirements have been reviewed. The design database for the systematic management of the design documents as well as design processes has been established as well

  4. Development of safety analysis technology for LMR

    Energy Technology Data Exchange (ETDEWEB)

    Hahn, Do Hee; Kwon, Y. M.; Kim, K. D. [and others

    2000-05-01

    The analysis methodologies as well as the analysis computer code system for the transient, HCDA, and containment performance analyses, which are required for KALIMER safety analyses, have been developed. The SSC-K code has been developed based on SSC-L which is an analysis code for loop type LMR, by improving models necessary for the KALIMER system analysis, and additional models have been added to the code. In addition, HCDA analysis model has been developed and the containment performance analysis code has been also improved. The preliminary basis for the safety analysis has been established, and the preliminary safety analyses for the key design features have been performed. In addition, a state-of-art analysis for LMR PSA and overseas safety and licensing requirements have been reviewed. The design database for the systematic management of the design documents as well as design processes has been established as well.

  5. Development of core design technology for LMR

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Young Jin; In, Kim Young; Kim, Young Il; Kim, Y G; Kim, S J; Song, H; Kim, T K; Kim, W S; Hwang, W; Lee, B O; Park, C K; Joo, H K; Yoo, J W; Kang, H Y; Park, W S

    2000-05-01

    For the development of KALIMER (150 MWe) core conceptual design, design evolution and optimization for improved economics and safety enhancement was performed in the uranium metallic fueled equilibrium core design which uses U-Zr binary fuel not in excess of 20 percent enrichment. Utilizing results of the uranium ,metallic fueled core design, the breeder equilibrium core design with breeding ratio being over 1.1 was developed. In addition, utilizing LMR's excellent neutron economy, various core concepts for minor actinide burnup, inherent safety, economics and non-proliferation were realized and its optimization studies were performed. A code system for the LMR core conceptual design has been established through the implementation of needed functions into the existing codes and development of codes. To improve the accuracy of the core design, a multi-dimensional nodal transport code SOLTRAN, a three-dimensional transient code analysis code STEP, MATRA-LMR and ASSY-P for T/H analysis are under development. Through the automation of design calculations for efficient core design, an input generator and several interface codes have been developed. (author)

  6. Development of core design technology for LMR

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Young Jin; Kim Young In; Kim, Young Il; Kim, Y. G.; Kim, S. J.; Song, H.; Kim, T. K.; Kim, W. S.; Hwang, W.; Lee, B. O.; Park, C. K.; Joo, H. K.; Yoo, J. W.; Kang, H. Y.; Park, W. S

    2000-05-01

    For the development of KALIMER (150 MWe) core conceptual design, design evolution and optimization for improved economics and safety enhancement was performed in the uranium metallic fueled equilibrium core design which uses U-Zr binary fuel not in excess of 20 percent enrichment. Utilizing results of the uranium ,metallic fueled core design, the breeder equilibrium core design with breeding ratio being over 1.1 was developed. In addition, utilizing LMR's excellent neutron economy, various core concepts for minor actinide burnup, inherent safety, economics and non-proliferation were realized and its optimization studies were performed. A code system for the LMR core conceptual design has been established through the implementation of needed functions into the existing codes and development of codes. To improve the accuracy of the core design, a multi-dimensional nodal transport code SOLTRAN, a three-dimensional transient code analysis code STEP, MATRA-LMR and ASSY-P for T/H analysis are under development. Through the automation of design calculations for efficient core design, an input generator and several interface codes have been developed. (author)

  7. Recent developments in the CONTAIN-LMR code

    International Nuclear Information System (INIS)

    Murata, K.K.

    1990-01-01

    Through an international collaborative effort, a special version of the CONTAIN code is being developed for integrated mechanistic analysis of the conditions in liquid metal reactor (LMR) containments during severe accidents. The capabilities of the most recent code version, CONTAIN LMR/1B-Mod.1, are discussed. These include new models for the treatment of two condensables, sodium condensation on aerosols, chemical reactions, hygroscopic aerosols, and concrete outgassing. This code version also incorporates all of the previously released LMR model enhancements. The results of an integral demonstration calculation of a sever core-melt accident scenario are given to illustrate the features of this code version. 11 refs., 7 figs., 1 tab

  8. LMR [liquid metal reactor] centrifugal pump coastdowns

    International Nuclear Information System (INIS)

    Dunn, F.E.; Malloy, D.J.

    1987-01-01

    A centrifugal pump model which describes the interrelationships of the pump discharge flowrate, pump speed, shaft torque and dynamic head has been implemented based upon existing models. Specifically, the pump model is based upon the dimensionless-homologous pump theory of Wylie and Streeter. Given data from a representative pump, homologous theory allows one to predict the transient characteristics of similarly sized pumps. This homologous pump model has been implemented into both the one-dimensional SASSYS-1 systems analysis code and the three-dimensional COMMIX-1A code. Comparisons have been made both against other pump models (CRBR) and actual pump coastdown data (EBR-II and FFTF). Agreement with this homologous pump model has been excellent. Additionally, these comparisons indicate the validity of applying the medium size pump data of Wylie and Streeter to a range of typical LMR centrifugal pumps

  9. Development of safety analysis technology for LMR

    International Nuclear Information System (INIS)

    Lee, Y. B.; Kwon, Y. M.; Suk, S. D.

    2005-03-01

    The MATRA-LMR-FB has been developed internally for the damage prevention as well as the safety assessment during a channel blockage accident and, as a the result, the quality of the code becomes comparable to that developed in the leading countries. For a code-to-code comparison, KAERI could have access to the SASSYS-1 through a bilateral collaboration between KAERI and ANL. The study could bring into the reliability improvements both on the reactivity models in the SSC-K and on the SSC-K prediction capability. It finally leads to the completion of the SSC-K version 1.3 resulting from the qualitative and quantitative code-to-code comparison. The preliminary analysis for a metal fueled LMR could also become possible with the MELT-III and the VENUS-II, which had originally been developed for the HCDA analysis with an oxidized fuel, by developing the relevant models For the development of the safety evaluation technology, the safety limits have been set up, and the analyses of the internal and external channel blockages in an assembly have also been performed. Besides, the more reliable analysis results on the key design concepts could be obtained by way of the methodology improvement resulting from the qualitative and quantitative comparison study. For an efficient and systematic control of the main project, the integration of the developed technologies and the establishment of their data base have been pursued. It has gone through the development of the process control with taking account of interfaces among the sub-projects, the overall coordination of the developed technologies, the data base for the design products, and so on

  10. Failure analysis of medical Linac (LMR-15)

    International Nuclear Information System (INIS)

    Kato, Kiyotaka; Nakamura, Katsumi; Ogihara, Kiyoshi; Takahashi, Katsuhiko; Sato, Kazuhisa.

    1994-01-01

    In August 1978, Linac (LMR-15, Z4 Toshiba) was installed at our hospital and in use for 12 years up to September 1990. Recently, we completed working and failure records on this apparatus during the 12-year period, for the purpose of their analysis in the basis of reliability engineering. The results revealed operation rate of 97.85% on the average, mean time between failures (MTBF) from 40-70 hours about the beginning of its working to 280 hours for 2 years before renewal and practically satisfactory values of mean life of parts of life such as magnetron, thyratron and electron gun; the above respective values proved to be above those reported by other literature. On the other hand, we classified, by occurring system, the contents of failures in the apparatus and determined the number of failures and the temperature and humidities in case of failures to examine the correlation between the working environment and failure. The results indicated a change in humidity to gain control of failures in the dosimetric system, especially the monitoring chamber and we could back up the strength of the above correlation from a coefficient of correlation value of 0.84. (author)

  11. Mechanical properties of LMR structural materials at high temperature

    International Nuclear Information System (INIS)

    Kim, D. W.; Kuk, I. H.; Ryu, W. S. and others

    1999-03-01

    Austenitic stainless is used for the structural material of liquid metal reactor (LMR) because of good mechanical properties at high temperature. Stainless steel having more resistant to temperature by adding minor element has been developing for operating the LMR at higher temperature. Of many elements, nitrogen is a prospective element to modify type 316L(N) stainless steel because nitrogen is the most effective element for solid solution and because nitrogen retards the precipitation of carbide at grain boundary. Ti, Nb, and V are added to improve creep properties by stabilizing the carbides through forming MC carbide. Testing techniques of tensile, fatigue, creep, and creep-fatigue at high temperature are difficult. Moreover, testing times for creep and creep-fatigue tests are very long up to several tens of thousands hours because creep and creep-fatigue phenomena are time-dependent damage mechanism. So, it is hard to acquire the material data for designing LMR systems during a limited time. In addition, the integrity of LMR structural materials at the end of LMR life has to be predicted from the laboratory data tested during the short term because there is no data tested during 40 years. Therefore, the effect of elements on mechanical properties at high temperature was reviewed in this study and many methods to predict the long-term behaviors of structural materials by simulated modelling equation is shown in this report. (author). 32 refs., 9 tabs., 38 figs

  12. Structure of the transcriptional regulator LmrR and its mechanism of multidrug recognition

    NARCIS (Netherlands)

    Madoori, Pramod Kumar; Agustiandari, Herfita; Driessen, Arnold J. M.; Thunnissen, Andy-Mark W. H.

    2009-01-01

    LmrR is a PadR-related transcriptional repressor that regulates the production of LmrCD, a major multidrug ABC transporter in Lactococcus lactis. Transcriptional regulation is presumed to follow a drug-sensitive induction mechanism involving the direct binding of transporter ligands to LmrR. Here,

  13. Novel, Integrated Reactor / Power Conversion System (LMR-AMTEC)

    Energy Technology Data Exchange (ETDEWEB)

    Pablo Rubiolo, Principal Investigator

    2003-03-21

    The main features of this project were the development of a long life (up to 10 years) Liquid Metal Reactor (LMR) and a static conversion subsystem comprising an Alkali Metal Thermal-to-Electric (AMTEC) topping cycle and a ThermoElectric (TE) Bottom cycle. Various coupling options of the LMR with the energy conversion subsystem were explored and, base in the performances found in this analysis, an Indirect Coupling (IC) between the LMR and the AMTEC/TE converters with Alkali Metal Boilers (AMB) was chosen as the reference design. The performance model of the fully integrated sodium-and potassium-AMTEC/TE converters shows that a combined conversion efficiency in excess of 30% could be achieved by the plant. (B204)

  14. Development of Core Design Technology for LMR

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Yeong Il; Hong, S. G.; Jang, J. W. (and others)

    2007-06-15

    developed and programmed. The 1st order and exact perturbation theory calculation module to use in the TRI-Z geometry model was developed. The SFR inter-assembly core thermal flow analysis code MATCOM has been developed using the sub-channel code MATRA-LMR and the porous media code COMMIX-1AR/P. The analysis model for thermal creep, irradiation creep and the creep rupture strength characteristics for the Mod. HT9 were developed based on the available experiment data. To analyze the pin power distributions considering the influence of non-fuel pin inside fuel assembly, the form function concept was introduced and the program for the pin power calculation was develop.

  15. MELCOR/CONTAIN LMR Implementation Report - FY16 Progress.

    Energy Technology Data Exchange (ETDEWEB)

    Louie, David [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Humphries, Larry L. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)

    2016-11-01

    This report describes the progress of the CONTAIN - LMR sodium physics and chemistry models to be implemented in MELCOR 2.1. In the past three years , the implementation included the addition of sodium equations of state and sodium properties from two different sources. The first source is based on the previous work done by Idaho National Laboratory by modifying MELCOR to include liquid lithium equation of state as a working fluid to model the nuclear fusion safety research. The second source uses properties generated for the SIMMER code. The implemented modeling has been tested and results are reported in this document. In addition, the CONTAIN - LMR code was derived from an early version of the CONTAIN code, and many physical models that were developed since this early version of CONTAIN are not available in this early code version. Therefore, CONTAIN 2 has been updated with the sodium models in CONTAIN - LMR as CONTAIN2 - LMR, which may be used to provide code-to-code comparison with CONTAIN - LMR and MELCOR when the sodium chemistry models from CONTAIN - LMR have been completed. Both the spray fire and pool fire chemistry routines from CONTAIN - LMR have been integrated into MELCOR 2.1, and debugging and testing are in progress. Because MELCOR only models the equation of state for liquid and gas phases of the coolant, a modeling gap still exists when dealing with experiments or accident conditions that take place when the ambient temperature is below the freezing point of sodium. An alternative method is under investigation to overcome this gap . We are no longer working on the separate branch from the main branch of MELCOR 2.1 since the major modeling of MELCOR 2.1 has been completed. At the current stage, the newly implemented sodium chemistry models will be a part of the main MELCOR release version (MELCOR 2.2). This report will discuss the accomplishments and issues relating to the implementation. Also, we will report on the planned completion of all

  16. MELCOR/CONTAIN LMR Implementation Report. FY14 Progress

    Energy Technology Data Exchange (ETDEWEB)

    Humphries, Larry L; Louie, David L.Y.

    2014-10-01

    This report describes the preliminary implementation of the sodium thermophysical properties and the design documentation for the sodium models of CONTAIN-LMR to be implemented into MELCOR 2.1. In the past year, the implementation included two separate sodium properties from two different sources. The first source is based on the previous work done by Idaho National Laboratory by modifying MELCOR to include liquid lithium equation of state as a working fluid to model the nuclear fusion safety research. To minimize the impact to MELCOR, the implementation of the fusion safety database (FSD) was done by utilizing the detection of the data input file as a way to invoking the FSD. The FSD methodology has been adapted currently for this work, but it may subject modification as the project continues. The second source uses properties generated for the SIMMER code. Preliminary testing and results from this implementation of sodium properties are given. In this year, the design document for the CONTAIN-LMR sodium models, such as the two condensable option, sodium spray fire, and sodium pool fire is being developed. This design document is intended to serve as a guide for the MELCOR implementation. In addition, CONTAIN-LMR code used was based on the earlier version of CONTAIN code. Many physical models that were developed since this early version of CONTAIN may not be captured by the code. Although CONTAIN 2, which represents the latest development of CONTAIN, contains some sodium specific models, which are not complete, the utilizing CONTAIN 2 with all sodium models implemented from CONTAIN-LMR as a comparison code for MELCOR should be done. This implementation should be completed in early next year, while sodium models from CONTAIN-LMR are being integrated into MELCOR. For testing, CONTAIN decks have been developed for verification and validation use.

  17. SAF-BRET-FMEF: a developmental LMR fuel cycle facility

    International Nuclear Information System (INIS)

    Stradley, J.G.; Yook, H.R.; Gerber, E.W.; Lerch, R.E.; Rice, L.H.

    1985-01-01

    The SAF-BRET-FMEF complex represents a versatile fuel cycle facility for processing LMR fuel. While originally conceived for processing FFTF and CRBRP fuel, it represents a facility where LMR fuel from the first generation of innovative LMRs could be processed. The cost of transporting fuel from the LMR to the Hanford site would have to be assessed when the LMR site is identified. The throughput of BRET was set at 15 MTHM/yr during conceptual design of the facility, a rate which was adequate to process all of the fuel from FFTF and fuel and blanket material from CRBRP. The design is currently being reevaluated to see if BRET could be expanded to approx.35 MTHM/yr to process fuel and blanket material from approx.1300 MWe generating capacity of the innovative LMRs. This expanded throughput is possible by designing the equipment for an instantaneous throughput of 0.2 MTHM/d, and by selected additional modifications to the facility (e.g., expansion of shipping and receiving area, and addition of a second entry tunnel transporter), and by the fact that the LMR fuel assemblies contain more fuel than the FFTF assemblies (therefore, fewer assemblies must be handled for the same throughput). The estimated cost of such an expansion is also being assessed. As stated previously, the throughput of SAF and Fuel Assembly could be made to support typical LMRs at little additional cost. The throughput could be increased to support the fuel fabrication requirements for 1300 MWe generating capacity of the innovative LMRs. This added capacity may be achieved by increasing the number of operating shifts, and is affected by variables such as fuel design, fuel enrichment, and plutonium isotopic composition

  18. Evaluation of a hanging core support concept for LMR application

    International Nuclear Information System (INIS)

    Burelbach, J.P.; Cha, B.K.; Huebotter, P.R.; Kann, W.J.; Pan, Y.C.; Saiveau, J.G.; Seidensticker, R.W.; Wu, T.S.

    1985-01-01

    The paper describes an innovative design concept for a liquid metal reactor (LMR) core support structure (CSS). A hanging core support structure is described and analyzed. The design offers inherent safety features, constructability advantages, and potential cost reductions. Some safety considerations are examined which include the in-service inspection (ISI), the backup support system and the structural behavior in a hypothetical case of a broken beam in the core support structure

  19. Liquid metal reactor development. Development of LMR design technology

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Young Cheol; Kim, Y I; Kim, Y G; Kim, E K; Song, H; Chung, H T; Sim, Y S; Min, B T; Kim, Y S; Wi, M H; Yoo, B; Lee, J H; Lee, H Y; Kim, J B; Koo, G H; Hahn, D H; Na, B C; Hwang, W; Nam, C; Ryu, W S; Lim, G S; Kim, D H; Kim, J D; Gil, C S

    1997-07-01

    This project was performed in five parts, the scope and contents of which are as follows: The nuclear data processing system was established and the KFS group constant library was improved and verified. Basic computation system was constructed by either developing or adding its function. Input/output (I/O) interface processing was developed to establish an integrated calculation system for LMR core nuclear rand thermal-hydraulic design and analysis. An experimental data analysis was performed to validate the constructed core neutronic calculation system. Using the established core calculation system and design technology, preliminary core design and performance analysis on the domestic LMR core design concept were carried out. To develop the basic technology of the LMR system analysis, LMR system behavior characteristics evaluation, thermal -fluid system analysis in the reactor pool, preliminary overall plant analysis and computer codes development have been performed. A porous model and simple one-dimensional model have been evaluated for the reactor pool analysis. The evaluation of the residual heat removal system on different design concepts has been also conducted. For the development of high temperature structural analysis, the heat transfer and thermal stress analyses were performed using finite element program with user subroutine that has been developed with an implementation of the Chaboche constitutive model for inelastic analysis capability, and the evaluation of creep-fatigue and ratcheting behavior of high temperature structure was carried out using this program. for development of the seismic isolation system and to predict the shear behavior for the laminated rubber bearing were established. And the behavior tests of isolation bearing and rubber specimens were carried out, and the seismic response tests for the isolation model structure were performed using the 30 ton shaking table. (author). 369 refs., 119 tabs., 320 figs.

  20. Liquid metal reactor development. Development of LMR design technology

    International Nuclear Information System (INIS)

    Kim, Young Cheol; Kim, Y. I.; Kim, Y. G.; Kim, E. K.; Song, H.; Chung, H. T.; Sim, Y. S.; Min, B. T.; Kim, Y. S.; Wi, M. H.; Yoo, B.; Lee, J. H.; Lee, H. Y.; Kim, J. B.; Koo, G. H.; Hahn, D. H.; Na, B. C.; Hwang, W.; Nam, C.; Ryu, W. S.; Lim, G. S.; Kim, D. H.; Kim, J. D.; Gil, C. S.

    1997-07-01

    This project was performed in five parts, the scope and contents of which are as follows: The nuclear data processing system was established and the KFS group constant library was improved and verified. Basic computation system was constructed by either developing or adding its function. Input/output (I/O) interface processing was developed to establish an integrated calculation system for LMR core nuclear rand thermal-hydraulic design and analysis. An experimental data analysis was performed to validate the constructed core neutronic calculation system. Using the established core calculation system and design technology, preliminary core design and performance analysis on the domestic LMR core design concept were carried out. To develop the basic technology of the LMR system analysis, LMR system behavior characteristics evaluation, thermal -fluid system analysis in the reactor pool, preliminary overall plant analysis and computer codes development have been performed. A porous model and simple one-dimensional model have been evaluated for the reactor pool analysis. The evaluation of the residual heat removal system on different design concepts has been also conducted. For the development of high temperature structural analysis, the heat transfer and thermal stress analyses were performed using finite element program with user subroutine that has been developed with an implementation of the Chaboche constitutive model for inelastic analysis capability, and the evaluation of creep-fatigue and ratcheting behavior of high temperature structure was carried out using this program. for development of the seismic isolation system and to predict the shear behavior for the laminated rubber bearing were established. And the behavior tests of isolation bearing and rubber specimens were carried out, and the seismic response tests for the isolation model structure were performed using the 30 ton shaking table. (author). 369 refs., 119 tabs., 320 figs

  1. MELCOR/CONTAIN LMR Implementation Report-Progress FY15

    Energy Technology Data Exchange (ETDEWEB)

    Humphries, Larry L.; Louie, David

    2016-01-01

    This report describes the progress of the CONTAIN-LMR sodium physics and chemistry models to be implemented in to MELCOR 2.1. It also describes the progress to implement these models into CONT AIN 2 as well. In the past two years, the implementation included the addition of sodium equations of state and sodium properties from two different sources. The first source is based on the previous work done by Idaho National Laborat ory by modifying MELCOR to include liquid lithium equation of state as a working fluid to mode l the nuclear fusion safety research. The second source uses properties generated for the SIMMER code. Testing and results from this implementation of sodium pr operties are given. In addition, the CONTAIN-LMR code was derived from an early version of C ONTAIN code. Many physical models that were developed sin ce this early version of CONTAIN are not captured by this early code version. Therefore, CONTAIN 2 is being updated with the sodium models in CONTAIN-LMR in or der to facilitate verification of these models with the MELCOR code. Although CONTAIN 2, which represents the latest development of CONTAIN, now contains ma ny of the sodium specific models, this work is not complete due to challenges from the lower cell architecture in CONTAIN 2, which is different from CONTAIN- LMR. This implementation should be completed in the coming year, while sodi um models from C ONTAIN-LMR are being integrated into MELCOR. For testing, CONTAIN decks have been developed for verification and validation use. In terms of implementing the sodium m odels into MELCOR, a separate sodium model branch was created for this document . Because of massive development in the main stream MELCOR 2.1 code and the require ment to merge the latest code version into this branch, the integration of the s odium models were re-directed to implement the sodium chemistry models first. This change led to delays of the actual implementation. For aid in the future implementation of sodium

  2. Overview of advanced LMR design in the US

    International Nuclear Information System (INIS)

    Wade, D.C.

    1988-01-01

    The current generation of US advanced LMR conceptual designs have resulted from a goal to address the economic and institutional issues facing the US nuclear industry in the late 70's and early 80's. They are focused technically on achieving passive safety characteristics and favorable capital and operating costs. The design strategies which have been taken were motivated as well by the coal to favorably impact the institutional and public perception regimes regarding safety, diversion, nonproliferation, and waste. The rationales and tradeoffs influencing the resulting design decisions are discussed in this paper, with a focus on core design issues. 1 fig

  3. The development of technologies of safety analysis for LMR ('03)

    International Nuclear Information System (INIS)

    Lee, Y. B.; Suk, S. D.; Chang, W. P.; Kwon, Y. M.; Jeong, H. Y.; Ha, K. W.; Heo, S.

    2004-03-01

    The developmental objectives of the project, 'The development of safety analysis techniques in LMR', are the code development for the subchannel blockage analysis, the code development for the system transient analysis, the code development for the HCDA(Hypothetical Core Disruptive Accident) analysis, the preliminary safety analysis for KALIMER-600 equipped with the components of new concepts, and the establishment of data base. The purpose of the analysis for subchannel blockage in the subassembly of LMR is to represent quantitatively that the maximum damage due to the accident is within the safety criteria. The computational program should be developed to simulate the thermal hydraulic phenomena and to verify the safety of LMR for the accident. For the purpose, the hybrid scheme has been implemented into the MATRA-LMR code based on the upwind scheme to analyze the various flow fields occurred in the subchannel blockage accident. The turbulent mixing models using the CFX code were assessed to compute more precisely the heat transfer between subchannels. Through this assessment, empirical correction factors of 1.7 for the heat conduction, 0.006 for the turbulent mixing coefficient were obtained. The distributed resistance model instead of wire forcing function has been developed to represent the more exact flow field due to wire-wrap. Other models, such as heat conductor model and various turbulent mixing model, have been implemented into the MATRA-LMR. The ORNL THORS 19-Pin FFM-5B tests have been assessed to validate above new models using the improved MATRA-LMR. The results using MATRA-LMR were well agreed with the experimental data. The subchannel blockage accidents which assumed to be occurred at the three locations for the conceptual plant of KALIMER-600 have been analysed according to blockage size using the MATRA-LMR code. The results of calculations for the design basis events which 6 subchannels were blocked showed the margins of the 290 7.dog. C up to the

  4. Functional design for the integration of BMNI/LMR

    International Nuclear Information System (INIS)

    Van Westerlaak, P.J.M.; Oldenburger, A.A.

    1995-04-01

    The aim of the Project Integration of Monitoring networks (PIM) is to realize one modular monitoring network configuration which can supply sufficient radiological data to both the National Institute of Public Health and Environment (RIVM) and the contingency organization of the Dutch Ministry of Internal Affairs. This monitoring network configuration is called the National Monitoring network Radioactivity (NMR) and is a combination of the BMNI (Internal Affairs Monitoring network Nuclear Accidents) and LMR (also translated as National Monitoring network Radioactivity). In this report only attention is paid to the coupling of the BMNI and LMR on the level of data as part of the realization of the NMR. After an overview of the existing situation the requirements for an integrated monitoring network system are outlined. Differences between NMR and BMNI and possible solutions to overcome those differences are discussed next. Subsequently the modular NMR system is described, along with a brief overview of interfaces with other information systems. Finally, attention is paid to the data structure, necessary equipment and computer programs, quality control, and the planning of the development and implementation of the monitoring system. 12 figs., 3 tabs., 19 refs

  5. A state-of-the-art report on LMR structural materials

    International Nuclear Information System (INIS)

    Ryu, Woo Seog; Kuk, I. H.; Jang, J. S.; Kim, D. W.; Lee, C. K.; Kim, S. H.; Kim, W. G.; Park, S. D.; Chung, M. G.; Han, C. H.

    1998-03-01

    This state-of-the-art report is reviewed the R and D documents for designing and constructing the Monju LMR pilot plant in Japan, that has analyzed the LMR technologies and materials. This report especially has focused on the introduction in LMR systems, components, operating conditions, environmental aspects and structural materials to help understanding LMR materials research as a guide instruction. Japan had designed the Monju reactor using their own design code for high temperature analysis of LMR integrity, based on ASME Boiler and Pressure Vessel Code and Code Case N-47. A material database has been established from the test results of Japanese materials to evaluate the structural integrity in high temperature. The improved stainless steel for LMR integrity and economy has been developed in Japan and characterized to produce a database with international co-works. Mod. 9Cr-1Mo and 9Cr-2Mo steels have been developed for the heat transfer tubes in steam generator to improve the creep rupture behavior by reducing carbon content to resist welding cracks, and adding minor elements such as Nb and V to stabilize the carbide in high temperature region. The sodium environmental effects have determined that the degree of influence on high temperature properties should not be important because of reducing environment of sodium, but the quantitative analysis of the sodium effects has been studied to evaluate the long-term structural integrity during the LMR operating life. (author). 26 refs., 9 tabs., 14 figs

  6. Preliminary validation of the MATRA-LMR-FB code for the flow blockage in a subassembly

    International Nuclear Information System (INIS)

    Jeong, H. Y.; Ha, K. S.; Kwon, Y. M.; Chang, W. P.; Lee, Y. B.; Heo, S.

    2005-01-01

    To analyze the flow blockage in a subassembly of a Liquid Metal-cooled Reactor (LMR), the MATRA-LMR-FB code has been developed and validated for the existing experimental data. Compared to the MATRA-LMR code, which had been successfully applied for the core thermal-hydraulic design of KALIMER, the MATRA-LMR-FB code includes some advanced modeling features. Firstly, the Distributed Resistance Model (DRM), which enables a very accurate description of the effects of wire-wrap and blockage in a flow path, is developed for the MATRA-LMR-FB code. Secondly, the hybrid difference method is used to minimize the numerical diffusion especially at the low flow region such as recirculating wakes after blockage. In addition, the code is equipped with various turbulent mixing models to describe the active mixing due to the turbulent motions as accurate as possible. For the validation of the MATRA-LMR-FB code the ORNL THORS test and KOS 169-pin test are analyzed. Based on the analysis results for the temperature data, the accuracy of the code is evaluated quantitatively. The MATRA-LMR-FB code predicts very accurately the exit temperatures measured in the subassembly with wire-wrap. However, the predicted temperatures for the experiment with spacer grid show some deviations from the measured. To enhance the accuracy of the MATRA-LMR-FB for the flow path with grid spacers, it is suggested to improve the models for pressure loss due to spacer grid and the modeling method for blockage itself. The developed MATRA-LMR-FB code is evaluated to be applied to the flow blockage analysis of KALIMER-600 which adopts the wire-wrapped subassemblies

  7. The role of internal and external control for mitigating or preventing LMR accidents

    International Nuclear Information System (INIS)

    Waltar, A.E.; Padilla, A.; Seeman, S.E.

    1986-01-01

    Considerable enthusiasm is building within the Liquid Metal Coolant Reactor (LMR) community that LMR's can be designed to be inherently safe. A test program is currently underway at FFTF to provide data intended to support such contentions. An equally important program is to develop computer aids for operators which are sufficiently acceptable that the inherent safety feature of the plant need not be challenged. A balanced development of these approaches to achieve safe, reliable, and economically competitive power from an LMR is the subject matter of this paper

  8. Development of mechanical structure design technology for LMR

    Energy Technology Data Exchange (ETDEWEB)

    Yoo, Bong; Lee, Jae Han; Joo, Young Sang [and others

    2000-05-01

    In this project, fundamentals for conceptual design of mechanical structure system for LMR are independently established. The research contents are as follow; at first, conceptual design for SSC, design integration of interfaces, design consistency to keep functions and interfaces by developing arrangement of reactor system and 3 dimensional concept drawings, development and revision of preliminary design requirements and structural design basis, and evaluation of structural integrity for SSC following structural design criteria to check the conceptual design to be proper, at second, development of high temperature structure design and analysis technology and establishment of high temperature structural analysis codes and scheme, development of seismic isolation design concept to reduce seismic design loads to SCC and establishment of seismic analysis codes and scheme.

  9. Development of mechanical structure design technology for LMR

    International Nuclear Information System (INIS)

    Yoo, Bong; Lee, Jae Han; Joo, Young Sang

    2000-05-01

    In this project, fundamentals for conceptual design of mechanical structure system for LMR are independently established. The research contents are as follow; at first, conceptual design for SSC, design integration of interfaces, design consistency to keep functions and interfaces by developing arrangement of reactor system and 3 dimensional concept drawings, development and revision of preliminary design requirements and structural design basis, and evaluation of structural integrity for SSC following structural design criteria to check the conceptual design to be proper, at second, development of high temperature structure design and analysis technology and establishment of high temperature structural analysis codes and scheme, development of seismic isolation design concept to reduce seismic design loads to SCC and establishment of seismic analysis codes and scheme

  10. Development of fluid I and C systems design technology for LMR

    International Nuclear Information System (INIS)

    Sim, Yoon Sub; Kim, S. O.; Kim, Y. S.

    2002-04-01

    LMR can make the utilization of the uranium resources much more efficiently and reduce the storage load of high level nuclear waste but the technology for designing the systems of LMR was not secured domestically. Based on this technical requirement, research was made for the LMR system technology and a conceptual design for the fluid and IC systems for the LMR was developed and established. Also required computer code systems for the analysis and design of the systems were developed. Design requirements for each system were revised, analysis was made for various system design features, performance, sodium-water reaction, and operation stability. The developed codes were verified against experimental data produced locally and acquired through international cooperation

  11. Structure of the transcriptional regulator LmrR and its mechanism of multidrug recognition.

    Science.gov (United States)

    Madoori, Pramod Kumar; Agustiandari, Herfita; Driessen, Arnold J M; Thunnissen, Andy-Mark W H

    2009-01-21

    LmrR is a PadR-related transcriptional repressor that regulates the production of LmrCD, a major multidrug ABC transporter in Lactococcus lactis. Transcriptional regulation is presumed to follow a drug-sensitive induction mechanism involving the direct binding of transporter ligands to LmrR. Here, we present crystal structures of LmrR in an apo state and in two drug-bound states complexed with Hoechst 33342 and daunomycin. LmrR shows a common topology containing a typical beta-winged helix-turn-helix domain with an additional C-terminal helix involved in dimerization. Its dimeric organization is highly unusual with a flat-shaped hydrophobic pore at the dimer centre serving as a multidrug-binding site. The drugs bind in a similar manner with their aromatic rings sandwiched in between the indole groups of two dimer-related tryptophan residues. Multidrug recognition is facilitated by conformational plasticity and the absence of drug-specific hydrogen bonds. Combined analyses using site-directed mutagenesis, fluorescence-based drug binding and protein-DNA gel shift assays reveal an allosteric coupling between the multidrug- and DNA-binding sites of LmrR that most likely has a function in the induction mechanism.

  12. A comparative study of MATRA-LMR/FB with CFD on a fuel assembly in PGSFR

    Energy Technology Data Exchange (ETDEWEB)

    Yoo, Jin; Chang, Won-Pyo; Jeong, Jae-Ho; Ha, Kwi-Seok; Lee, Kwi-Lim; Lee, Seung Won; Choi, Chiwoong; Ahn, Sang-Jun [KAERI, Daejeon (Korea, Republic of)

    2015-05-15

    Some of its models were modified to be eligible for the analysis of the SFR sub-channel blockage with the wire-wrapped pins. The wire-forcing-function used in the MATRA-LMR, which allocates a forced flow with an empirical correlation for the flow effect of the wire-wrap, was replaced with the Distributed Resistance Model. The Distributed Resistance Model has generally been believed to represent the effect more realistically than the wire-forcing-function. A semi-implicit numerical method was applied to resolve a flow reversal problem, which could not be handled by the former fully implicit method. A code-to-code comparison study was also performed as part of an effort to supplement the qualification. Although MATRA-LMR-FB was qualified based on available experimental data including a code-to-code comparative analysis, it was still hard to say that the level of confidence was enough to apply it to the SFR design with full satisfaction. Additional studies are therefore needed to supplement the qualification of MATRA-LMR-FB. In this study, a code-to-code comparative study was conducted as part of an effort to supplement the qualification of MATRA-LMR-FB. The comparison between MATRA-LMR-FB and the CFD code, CFX, was carried out on a 91-pin fuel assembly based on a 217 pin fuel assembly in a PGSFR to assess the MATRA-LMR-FB prediction capability.

  13. Gap and impact of LMR [Liquid Metal Reactor] piping systems and reactor components

    International Nuclear Information System (INIS)

    Ma, D.C.; Gvildys, J.; Chang, Y.W.

    1987-01-01

    Because of high operation temperature, the LMR (Liquid Metal Reactor) plant is characterized by the thin-walled piping and components. Gaps are often present to allow free thermal expansion during normal plant operation. Under dynamic loadings, such as seismic excitation, if the relative displacement between the components exceeds the gap distance, impacts will occur. Since the components and piping become brittle over their design lifetime, impact is of important concern for it may lead to fractures of components and other serious effects. This paper deals with gap and impact problems in the LMR reactor components and piping systems. Emphasis is on the impacts due to seismic motion. Eight sections are contained in this paper. The gap and impact problems in LMR piping systems are described and a parametric study is performed on the effects of gap-induced support nonlinearity on the dynamics characteristics of the LMR piping systems. Gap and impact problems in the LMR reactor components are identified and their mathematical models are illustrated, and the gap and impact problems in the seismic reactor scram are discussed. The mathematical treatments of various impact models are also described. The uncertainties in the current seismic impact analyses of LMR components and structures are presented. An impact test on a 1/10-scale LMR thermal liner is described. The test results indicated that several clusters of natural modes can be excited by the impact force. The frequency content of the excited modes depends on the duration of the impact force; the shorter the duration, the higher the frequency content

  14. Identification of an Efflux Transporter LmrB Regulating Stress Response and Extracellular Polysaccharide Synthesis in Streptococcus mutans

    Directory of Open Access Journals (Sweden)

    Jia Liu

    2017-06-01

    Full Text Available Efflux transporters have been implicated in regulating bacterial virulence properties such as resistance to antibiotics, biofilm formation and colonization. The pathogenicity of Streptococcus mutans, the primary etiologic agent of human dental caries, relies on the bacterium’s ability to form biofilms on tooth surface. However, the studies on efflux transporters in S. mutans are scare and the function of these transporters remained to be clarified. In this study, we identified an efflux transporter (LmrB in S. mutans through cloning the lmrB gene into Escherichia coli. Introducing lmrB into E. coli conferred a multidrug-resistant phenotype and resulted in higher EtBr efflux activity which could be suppressed by efflux inhibitor. To explore whether LmrB was involved in S. mutans virulence properties regulation, we constructed the lmrB inactivation mutant and examined the phenotypes of the mutant. It was found that LmrB deficiency resulted in increased IPS storage and prolonged acid production. Enhanced biofilm formation characterized by increased extracellular polysaccharides (EPS production and elevated resistance to hydrogen peroxide and antimicrobials were also observed in lmrB mutant. To gain a better understanding of the global role of LmrB, a transcriptome analysis was performed using lmrB mutant strain. The expression of 107 genes was up- or down-regulated in the lmrB mutant compared with the wild type. Notably, expression of genes in several genomic islands was differentially modulated, such as stress-related GroELS and scnRK, sugar metabolism associated glg operons and msmREFGK transporter. The results presented here indicate that LmrB plays a vital global role in the regulation of several important virulence properties in S. mutans.

  15. Effect of blanket assembly shuffling on LMR neutronic performance

    International Nuclear Information System (INIS)

    Khalil, H.; Fujita, E.K.

    1987-01-01

    Neutronic analyses of advanced liquid-metal reactors (LMRs) have generally been performed with assemblies in different batches scatter-loaded but not shuffled among the core lattice positions between cycles. While this refueling approach minimizes refueling time, significant improvements in thermal performance are believed to be achievable by blanket assembly shuffling. These improvements, attributable to mitigation of the early-life overcooling of the blankets, include reductions in peak clad temperatures and in the temperature gradients responsible for thermal striping. Here the authors summarize results of a study performed to: (1) assess whether the anticipated gains in thermal performance can be realized without sacrificing core neutronic performance, particularly the burnup reactivity swing rho/sub bu/, which determines the rod ejection worth; (2) determine the effect of various blanket shuffling operations on reactor performance; and (3) determine whether shuffling strategies developed for an equilibrium (plutonium-fueled) core can be applied during the transition from an initial uranium-fueled core as is being considered in the US advanced LMR program

  16. A study on safety measure of LMR coolant

    Energy Technology Data Exchange (ETDEWEB)

    Hwang, Sung Tai; Choi, Y D; Choi, J H; Kim, T J; Jeong, K C; Kwon, S W; Kim, B H; Jeong, J Y; Park, J H; Kim, K R; Jo, B R

    1997-08-01

    A study on safety measures of LMR coolant showed the results as follows: 1. Sodium fire characteristics. A. Sodium pool temp., gas temp., oxygen concentration calculated by flame combustion model were generally higher than those calculated by surface combustion model. B. Basic and detail designs for medium sodium fire test facility were carried out and medium sodium fire test facility was constructed. 2. Sodium/Cover gas purification technology. A. Construction and operation of calibration loop. B. Purification analysis and conceptual design of the packing for a cold trap. 3. Analysis of sodium-water reaction characteristics. We have investigated the characteristics analysis for micro and small leaks phenomena, development of the computer code for analysis of initial and quasi steady-state spike pressures to analyze large leak accident. Also, water mock-up test facility for the analysis of large leak accident phenomena was designed and manufactured. 4. Development of water leak detection technology. Detection signals were appeared when the hydrogen detector is operated to Ar-H{sub 2} gas system. The technology for the passive acoustic detection with respect to large leakage of water into sodium media was reviewed. And water mock-up test equipment and instrument system were designed and constructed. (author). 19 refs., 45 tabs., 52 figs.

  17. A study on safety measure of LMR coolant

    International Nuclear Information System (INIS)

    Hwang, Sung Tai; Choi, Y. D.; Choi, J. H.; Kim, T. J.; Jeong, K. C.; Kwon, S. W.; Kim, B. H.; Jeong, J. Y.; Park, J. H.; Kim, K. R.; Jo, B. R.

    1997-08-01

    A study on safety measures of LMR coolant showed the results as follows: 1. Sodium fire characteristics. A. Sodium pool temp., gas temp., oxygen concentration calculated by flame combustion model were generally higher than those calculated by surface combustion model. B. Basic and detail designs for medium sodium fire test facility were carried out and medium sodium fire test facility was constructed. 2. Sodium/Cover gas purification technology. A. Construction and operation of calibration loop. B. Purification analysis and conceptual design of the packing for a cold trap. 3. Analysis of sodium-water reaction characteristics. We have investigated the characteristics analysis for micro and small leaks phenomena, development of the computer code for analysis of initial and quasi steady-state spike pressures to analyze large leak accident. Also, water mock-up test facility for the analysis of large leak accident phenomena was designed and manufactured. 4. Development of water leak detection technology. Detection signals were appeared when the hydrogen detector is operated to Ar-H 2 gas system. The technology for the passive acoustic detection with respect to large leakage of water into sodium media was reviewed. And water mock-up test equipment and instrument system were designed and constructed. (author). 19 refs., 45 tabs., 52 figs

  18. Development of subchannel analysis code MATRA-LMR for KALIMER subassembly thermal-hydraulics

    International Nuclear Information System (INIS)

    Won-Seok Kim; Young-Gyun Kim

    2000-01-01

    In the sodium cooled liquid metal reactors, the design limit are imposed on the maximum temperatures of claddings and fuel pins. Thus an accurate prediction of core coolant/fuel temperature distribution is essential to the LMR core thermal-hydraulic design. The detailed subchannel thermal-hydraulic analysis code MATRA-LMR (Multichannel Analyzer for Steady States and Transients in Rod Arrays for Liquid Metal Reactors) is being developed for KALIMER core design and analysis, based on COBRA-IV-i and MATRA. The major modifications and improvements implemented into MATRA-LMR are as follows: a) nonuniform axial noding capability, b) sodium properties calculation subprogram, c) sodium coolant heat transfer correlations, and d) most recent pressure drop correlations, such as Novendstern, Chiu-Rohsenow-Todreas and Cheng-Todreas. To assess the development status of this code, the benchmark calculations were performed with the ORNL 19 pin tests and EBR-II seven-assembly SLTHEN calculation results. The calculation results of MATRA-LMR for ORNL 19-pin assembly tests and EBR-II 91-pin experiments were compared to the measurements, and to SABRE4 and SLTHEN code calculation results, respectively. In this comparison, the differences are found among the three codes because of the pressure drop and the thermal mixing modellings. Finally, the major technical results of the conceptual design for the KALIMER 98.03 core have been compared with the calculations of MATRA-LMR, SABRE4 and SLTHEN codes. (author)

  19. Thermal performance of fresh mixed-oxide fuel in a fast flux LMR [liquid metal reactor

    International Nuclear Information System (INIS)

    Ethridge, J.L.; Baker, R.B.

    1985-01-01

    A test was designed and irradiated to provide power-to-melt (heat generation rate necessary to initiate centerline fuel melting) data for fresh mixed-oxide UO 2 -PuO 2 fuel irradiated in a fast neutron flux under prototypic liquid metal reactor (LMR) conditions. The fuel pin parameters were selected to envelope allowable fabrication ranges and address mass production of LMR fuel using sintered-to-size techniques. The test included fuel pins with variations in fabrication technique, pellet density, fuel-to-cladding gap, Pu concentration, and fuel oxygen-to-metal ratios. The resulting data base has reestablished the expected power-to-melt in mixed-oxide fuels during initial reactor startup when the fuel temperatures are expected to be the highest. Calibration of heat transfer models of fuel pin performance codes with these data are providing more accurate capability for predicting steady-state thermal behavior of current and future mixed-oxide LMR fuels

  20. The development of code for the analysis of the flow blockage of rod bundles of LMR

    International Nuclear Information System (INIS)

    Ha, Q. S.; Jeong, H. Y.; Jang, W. P.; Lee, Y. B.

    2003-01-01

    A partial flow blockage within a fuel assembly in liquid metal reactor may result in localized boiling or a failure of the fuel cladding. Thus, the precise analysis for the phenomenon is required for a safe design of LMR. To take account of the effects of the surfaces of rod and wire spacer on the fluid, the distributed resistance model was implemented into the MATRA-LMR code, which is important to the analysis for flow blockage. Also central differencing scheme for the velocities is used in the flow with the lRel less than 2 and for the enthalpies with the lPel less than 2. Diffusion terms are added to the equations of momentum and energy. The validation calculation was carried out against to the experiment of FFM series tests and the results using MATRA-LMR with the distributed resistance model and above hybrid scheme well agree with the experimental data

  1. Design characteristics of metallic fuel rod on its in-LMR performance

    International Nuclear Information System (INIS)

    Hwang, Woan; Kang Hee Young; Nam, Cheol; Kim, Jong Oh

    1997-01-01

    Fuel design is a key feature to assure LMR safety goals. To date, a large effort had been devoted to develop metallic fuels at ANL's experimental breeder reactor (EBR-II). The major design and performance parameters investigated include; thermal conductivity and temperature profile; smear density; axial plenum; FCMI and cladding deformation including creep, and fission gas release. In order to evaluate the sensitivity of each parameter, in-LMR performances of metallic fuels are not only reviewed by the experiment results in literatures, but also key design characteristics according to the variation of metallic fuel rod design parameters are analyzed by using the MACSIS code which simulates in-reactor behaviors of metal fuel rod. In this study, key design characteristics and the criteria which must be considered to design fuel rod in LMR, are proposed and discussed. (author). 14 refs., 4 figs

  2. Forced-convection boiling tests performed in parallel simulated LMR fuel assemblies

    International Nuclear Information System (INIS)

    Rose, S.D.; Carbajo, J.J.; Levin, A.E.; Lloyd, D.B.; Montgomery, B.H.; Wantland, J.L.

    1985-01-01

    Forced-convection tests have been carried out using parallel simulated Liquid Metal Reactor fuel assemblies in an engineering-scale sodium loop, the Thermal-Hydraulic Out-of-Reactor Safety facility. The tests, performed under single- and two-phase conditions, have shown that for low forced-convection flow there is significant flow augmentation by thermal convection, an important phenomenon under degraded shutdown heat removal conditions in an LMR. The power and flows required for boiling and dryout to occur are much higher than decay heat levels. The experimental evidence supports analytical results that heat removal from an LMR is possible with a degraded shutdown heat removal system

  3. Develoment of pressure drop calculation modules for a wire-wrapped LMR subassembly

    International Nuclear Information System (INIS)

    Kim, Young Gyun; Lim, Hyun Jin; Kim, Won Seok; Kim, Young Il

    2000-06-01

    Pressure drop calculation modules for a wire-wrapped LMR subassembly was been developed. This report summarizes present information on pressure drop calculation modules for inlet hole, lower part and upper part of a wire-wrapped LMR subassembly which was developed using simple formulas of sudden expansion and sudden contraction. A case calculation study was done using design data of a KALIMER driver fuel subassembly. And the total pressure drop in the driver fuel subassembly, except for the bundle part, was calculated as 0.13 MPa, which is in the reasonable pressure drop range. The developed modules will be integrated in the total subassembly pressure drop calculation code with further improvements

  4. Effect of pipe insulation losses on a loss-of-heat sink accident for an LMR

    International Nuclear Information System (INIS)

    Horak, W.C.; Guppy, J.G.; Wood, P.M.

    1985-01-01

    The efficacy of pipe radiation losses as a heat sink during LOHS in a loop-type LMR plant is investigated. The Super System Code (SSC), which was modified to include pipe radiation losses, was used to simulate such an LOHS in an LMR plant. In order to enhance these losses, the pipes were assumed to be insulated by rock wool, a material whose thermal conductivity increases with increasing temperature. A transient was simulated for a total of eight days, during which the coolant temperatures peaked well below saturation conditions and then declined steadily. The coolant flow rate in the loop remained positive throughout the transient

  5. Shielding analysis of the LMR in-vessel fuel storage experiments

    International Nuclear Information System (INIS)

    Bucholz, J.A.

    1994-01-01

    The In-Vessel Fuel Storage (IVFS) experiments analyzed in this paper were conducted at the Oak Ridge National Laboratory's Tower Shielding Reactor (TSR) as part of the Japanese-American Shielding Program for Experimental Research (JASPER). These IVFS experiments were designed to study source multiplication and three-dimensional effects related to in-vessel storage of spent fuel elements in liquid metal reactor (LMR) systems. The present paper describes the 2- and 3-D calculations and results corresponding to a limited subset of those IVFS experiments in which the US LMR program had a particular interest

  6. SASSYS-1 modelling of RVACS/RACS heat removal in an LMR

    International Nuclear Information System (INIS)

    Dunn, F.E.

    1987-01-01

    The SASSYS-1 LMR systems analysis code contains a model for transient analysis of heat removal by a RVACS (Reactor Vessel Auxiliary Cooling System) or a RACS (Reactor Air Cooling System) in an LMR (Liquid Metal Reactor). This air-side RVACS/RACS model is coupled with the sodium-side primary loop thermal hydraulics model in SASSYS-1 to give a complete treatment of the problem. Application of this model to an unprotected loss-of-flow event in the PRISM rector shows that in the long run the RVACS cooling is sufficient to prevent unacceptably high system temperatures in this case

  7. In pursuit of zero risk for LMR [liquid metal reactor] accidents

    International Nuclear Information System (INIS)

    Waltar, A.E.; Armstrong, G.R.; Martin, F.J.; Muhlestein, L.D.

    1986-01-01

    LMR programs are moving towards facility designs that are inherently safe. This movement is resulting in extremely low probabilities for entering the regime of severe accidents. When these probabilities are added to the respective consequences, the resulting risk is also seen to be moving toward lower and lower values. The preliminary risk estimates being achieved by the US LMR Advanced Concepts Programs are well within US NRC guidelines and to some may be seen as approaching zero. This paper presents some aspects and results of the work being performed that supports this trend

  8. The lactococcal secondary multidrug transporter LmrP confers resistance to lincosamides, macrolides, streptogramins and tetracyclines

    NARCIS (Netherlands)

    Putman, M; van Veen, HW; Degener, JE; Konings, WN

    2001-01-01

    The active efflux of toxic compounds by (multi)drug transporters is one of the mechanisms that bacteria have developed to resist cytotoxic drugs. The authors describe the role of the lactococcal secondary multidrug transporter LmrP in the resistance to a broad range of clinically important

  9. Influence of detergents on the activity of the ABC transporter LmrA

    NARCIS (Netherlands)

    Infed, Nacera; Hanekop, Nils; Driessen, Arnold J. M.; Smits, Sander H. J.; Schmitt, Lutz

    The ABC transporter LmrA from Lactococcus lactis has been intensively studied and a role in multidrug resistance was proposed. Here, we performed a comprehensive detergent screen to analyze the impact of detergents for a successful solubilization, purification and retention of functional properties

  10. Preliminary Validation of the MATRA-LMR Code Using Existing Sodium-Cooled Experimental Data

    International Nuclear Information System (INIS)

    Choi, Sun Rock; Kim, Sangji

    2014-01-01

    The main objective of the SFR prototype plant is to verify TRU metal fuel performance, reactor operation, and transmutation ability of high-level wastes. The core thermal-hydraulic design is used to ensure the safe fuel performance during the whole plant operation. The fuel design limit is highly dependent on both the maximum cladding temperature and the uncertainties of the design parameters. Therefore, an accurate temperature calculation in each subassembly is highly important to assure a safe and reliable operation of the reactor systems. The current core thermalhydraulic design is mainly performed using the SLTHEN (Steady-State LMR Thermal-Hydraulic Analysis Code Based on ENERGY Model) code, which has been already validated using the existing sodium-cooled experimental data. In addition to the SLTHEN code, a detailed analysis is performed using the MATRA-LMR (Multichannel Analyzer for Transient and steady-state in Rod Array-Liquid Metal Reactor) code. In this work, the MATRA-LMR code is validated for a single subassembly evaluation using the previous experimental data. The MATRA-LMR code has been validated using existing sodium-cooled experimental data. The results demonstrate that the design code appropriately predicts the temperature distributions compared with the experimental values. Major differences are observed in the experiments with the large pin number due to the radial-wise mixing difference

  11. Steady state thermal hydraulic analysis of LMR core using COBRA-K code

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Eui Kwang; Kim, Young Gyun; Kim Young In; Kim Young Cheol

    1997-02-01

    A thermal hydraulics analysis code COBRA-K is being developed by the KAERI LMR core design technology development team. COBRA-K is a part of the integrated computation system for LMR core design and analysis, the K-CORE system. COBRA-K is supposed to predict the flow and temperature distributions in LMR core. COBRA-K is an extension of the previously published COBRA-IV-I code with several functional improvements. Specially COBRA-K has been improved to analyze single and multi-assembly, and whole-core in the transient condition. This report describes the overall features of COBRA-K and gives general input descriptions. The 19 pin assembly experimental data of ORNL were used to verify the accuracy of this code for the steady state analysis. The comparative results show good agreements between the calculated and the measured data. And COBRA-K can be used to predict flow and temperature distributions for the LMR core design. (author). 7 refs., 6 tabs., 13 figs.

  12. Assessment calculation of MARS-LMR using EBR-II SHRT-45R

    Energy Technology Data Exchange (ETDEWEB)

    Choi, C.; Ha, K.S.

    2016-10-15

    Highlights: • Neutronic and thermal-hydraulic behavior predicted by MARS-LMR is validated with EBR-II SHRT-45R test data. • Decay heat model of ANS-94 give better prediction of the fission power. • The core power is well predicted by reactivity feedback during initial transient, however, the predicted power after approximately 200 s is over-estimated. The study of the reactivity feedback model of the EBR-II is necessary for the better calculation of the power. • Heat transfer between inter-subassemblies is the most important parameter, especially, a low flow and power subassembly, like non-fueled subassembly. - Abstract: KAERI has designed a prototype Gen-IV SFR (PGSFR) with metallic fuel. And the safety analysis code for the PGSFR, MARS-LMR, is based on the MARS code, and supplemented with various liquid metal related features including sodium properties, heat transfer, pressure drop, and reactivity feedback models. In order to validate the newly developed MARS-LMR, KAERI has joined the International Atomic Energy Agency (IAEA) coordinated research project (CRP) on “Benchmark Analysis of an EBR-II Shutdown Heat Removal Test (SHRT)”. Argonne National Laboratory (ANL) has technically supported and participated in this program. One of benchmark analysis tests is SHRT-45R, which is an unprotected loss of flow test in an EBR-II. So, sodium natural circulation and reactivity feedbacks are major phenomena of interest. A benchmark analysis was conducted using MARS-LMR with original input data provided by ANL. MARS-LMR well predicts the core flow and power change by reactivity feedbacks in the core. Except the results of the XX10, the temperature and flow in the XX09 agreed well with the experiments. Moreover, sensitivity tests were carried out for a decay heat model, reactivity feedback model, inter-subassembly heat transfer, internal heat structures and so on, to evaluate their sensitivity and get a better prediction. The decay heat model of ANS-94 shows

  13. Assessment calculation of MARS-LMR using EBR-II SHRT-45R

    International Nuclear Information System (INIS)

    Choi, C.; Ha, K.S.

    2016-01-01

    Highlights: • Neutronic and thermal-hydraulic behavior predicted by MARS-LMR is validated with EBR-II SHRT-45R test data. • Decay heat model of ANS-94 give better prediction of the fission power. • The core power is well predicted by reactivity feedback during initial transient, however, the predicted power after approximately 200 s is over-estimated. The study of the reactivity feedback model of the EBR-II is necessary for the better calculation of the power. • Heat transfer between inter-subassemblies is the most important parameter, especially, a low flow and power subassembly, like non-fueled subassembly. - Abstract: KAERI has designed a prototype Gen-IV SFR (PGSFR) with metallic fuel. And the safety analysis code for the PGSFR, MARS-LMR, is based on the MARS code, and supplemented with various liquid metal related features including sodium properties, heat transfer, pressure drop, and reactivity feedback models. In order to validate the newly developed MARS-LMR, KAERI has joined the International Atomic Energy Agency (IAEA) coordinated research project (CRP) on “Benchmark Analysis of an EBR-II Shutdown Heat Removal Test (SHRT)”. Argonne National Laboratory (ANL) has technically supported and participated in this program. One of benchmark analysis tests is SHRT-45R, which is an unprotected loss of flow test in an EBR-II. So, sodium natural circulation and reactivity feedbacks are major phenomena of interest. A benchmark analysis was conducted using MARS-LMR with original input data provided by ANL. MARS-LMR well predicts the core flow and power change by reactivity feedbacks in the core. Except the results of the XX10, the temperature and flow in the XX09 agreed well with the experiments. Moreover, sensitivity tests were carried out for a decay heat model, reactivity feedback model, inter-subassembly heat transfer, internal heat structures and so on, to evaluate their sensitivity and get a better prediction. The decay heat model of ANS-94 shows

  14. Academic Globalization: Universality of Cross-Cultural And Cross-Disciplinary LMR Perspectives

    Directory of Open Access Journals (Sweden)

    Marta Szabo White

    2010-10-01

    Full Text Available The contribution of this paper suggests that previous research underscoring cross-cultural differences may be misleading, when in fact it is cross-professional rather than cross-cultural differences that should be emphasized. Employing the LMR framework, this paper concludes that business or non-business predisposition has a more direct impact on one's individual cultural profile than does nationality. Regardless of culture, persons involved in business are characterized primarily by linear-active modes of communication, and persons not involved in business typically employ less linear and more multi-active/hybrid modes of communication. The linkages among individual characteristics, communication styles, work behaviors, and the extent to which the LMR constructs can facilitate and predict leadership, negotiating styles, individual behaviors, etc. are central to academic globalization and preparing global business leaders.

  15. Status of LMR fuel development in the United States of America

    International Nuclear Information System (INIS)

    Leggett, R.D.; Walters, L.C.

    1993-01-01

    Three fuel systems oxide, metal, and carbide are shown to be reliable to high burnup and a fourth system, nitride, is shown to have promise for LMR applications. The excellent steady state performance of the oxide and metal driver fuels for FFTF and EBR-II, respectively, supported by the experience base on tens of thousands of test pins is provided. Achieving 300 MWd/kg in the oxide fuel system through the use of low swelling cladding and duct materials and the Integral Fast Reactor (IFR) concept that utilizes metallic fuel are described. Arguments for economic viability are presented. Responses to operational transients and severe over-power events are shown to have large safety margins and run-beyond-cladding-breach (RBCB), is shown to be non-threatening to LMR reactor system. Results from a joint U.S.-Swiss carbide test that operated successfully at high power and burnup in FFTF are also presented. (orig.)

  16. Role of FFTF in assessing structural feedbacks and inherent safety of LMR's

    International Nuclear Information System (INIS)

    Padilla, A.; Omberg, R.P.; O'Dell, L.D.; Harris, R.A.; Nguyen, D.H.; Waltar, A.E.

    1985-03-01

    The possibility of developing reactor designs with inherent safety characteristics sufficient to provide ''walk away'' safety is receiving additional emphasis in the LMR program. A key element in this effort is the recognition that LMR's possess safety characteristics above and beyond those employed in past safety review processes. Some of these additional safety characteristics are due to reactivity feedback effects caused by small structural movements during hypothetical severe design transients. The effect of these characteristics upon the behavior of the FFTF under such transients has been assessed and is discussed in this paper. The paper also presents a preliminary test matrix which might allow experimental verification of the structural reactivity feedback effects. Such experimental verification should be very useful to innovative designers seeking to optimize inherent safety. 8 refs., 1 fig., 2 tabs

  17. Status of LMR fuel development in the United States of America

    International Nuclear Information System (INIS)

    Leggett, R.D.; Walters, L.C.

    1992-01-01

    Three fuel systems - oxide, metal and carbide - are shown to be reliable to high burnup and a fourth system, nitride, is shown to have promise for LMR applications. The excellent steady state performance of the oxide and metal driver fuels for FFTF and EBR-II, respectively, as well as that of tens of thousands of test pins is provided. Achieving 300 MWd/kg in the oxide fuel system through the use of low swelling cladding and duct materials is described and arguments for economic viability are presented. Responses to operational transients and severe overpower events are shown to have large safety margins and run beyond cladding breach, RBCB, likewise, is shown to be nonthreatening to LMR reactor systems. The Integral Fast Reactor (IFR) concept that utilizes metallic fuel and the commercial viability of this concept are discussed. Results from a joint US-Swiss carbide test that operated successfully at high power and burnup in FFTF are also presented

  18. KALIMER-600-clad Core Fuel Assembly Calculation using MATRA-LMR (V2.0) Code

    International Nuclear Information System (INIS)

    Kim, Young Gyun; Kim, Young Il

    2006-12-01

    Since the sodium boiling point is very high, maximum cladding and pin temperatures are used for design limit condition in sodium cooled liquid metal reactor. It is necessary to predict accurately the temperature distribution in the core and in the subassemblies to increase the sodium coolant efficiency. Based on the MATRA code, which is developed for PWR analysis, MATRA-LMR has been developed for SFR. The major modifications are: the sodium properties table is implemented as subprogram in the code, Heat transfer coefficients are changed for SFR, te pressure drop correlations are changed for more accurate calculations, which are Novendstern, Chiu-Rohsenow-Todreas, and Cheng-Todreas correlations. This This report describes briefly code structure and equations of MATRA-LMR (Version 2.0), explains input data preparation and shows some calculation results for the KALIMER-600-clad core fuel assembly for which has been performed the conceptual design of the core in the year 2006

  19. Development of a risk-based in-service inspection program for an LMR

    International Nuclear Information System (INIS)

    King, R.W.; Buschman, H.W.

    1996-01-01

    The emerging application of risk-based assessment technology to the operation and maintenance of nuclear power plants holds considerable promise for improving efficiency and reducing operating costs. Experimental Breeder Reactor II (EBR-II) is a liquid-metal-cooled fast reactor (LMR) that operated for 30 yr before shutting down in September 1994 due to program termination. Prior to the shutdown of EBR-II, an in-service inspection (ISI) program was developed that exploited certain advantages of the LMR design. For example, it demonstrated passive response to plant upset events, low-pressure primary coolant, and compatibility of the coolant and reactor materials. This ISI program was based on work currently being done by an American Society of Mechanical Engineers (ASME) Research Task Force on Risk-Based Inspection

  20. Validation of CONTAIN-LMR code for accident analysis of sodium-cooled fast reactor containments

    Energy Technology Data Exchange (ETDEWEB)

    Gordeev, S.; Hering, W.; Schikorr, M.; Stieglitz, R. [Inst. for Neutron Physic and Reactor Technology, Karlsruhe Inst. of Technology, Campus Nord (Germany)

    2012-07-01

    CONTAIN-LMR 1 is an analytical tool for the containment performance of sodium cooled fast reactors. In this code, the modelling for the sodium fire is included: the oxygen diffusion model for the sodium pool fire, and the liquid droplet model for the sodium spray fire. CONTAIN-LMR is also able to model the interaction of liquid sodium with concrete structure. It may be applicable to different concrete compositions. Testing and validation of these models will help to qualify the simulation results. Three experiments with sodium performed in the FAUNA facility at FZK have been used for the validation of CONTAIN-LMR. For pool fire tests, calculations have been performed with two models. The first model consists of one gas cell representing the volume of the burn compartment. The volume of the second model is subdivided into 32 coupled gas cells. The agreement between calculations and experimental data is acceptable. The detailed pool fire model shows less deviation from experiments. In the spray fire, the direct heating from the sodium burning in the media is dominant. Therefore, single cell modeling is enough to describe the phenomena. Calculation results have reasonable agreement with experimental data. Limitations of the implemented spray model can cause the overestimation of predicted pressure and temperature in the cell atmosphere. The ability of the CONTAIN-LMR to simulate the sodium pool fire accompanied by sodium-concrete reactions was tested using the experimental study of sodium-concrete interactions for construction concrete as well as for shielding concrete. The model provides a reasonably good representation of chemical processes during sodium-concrete interaction. The comparison of time-temperature profiles of sodium and concrete shows, that the model requires modifications for predictions of the test results. (authors)

  1. Safety aspects of LMR [liquid metal-cooled reactor] core design

    International Nuclear Information System (INIS)

    Cahalan, J.E.

    1986-01-01

    Features contributing to increased safety margins in liquid metal-cooled reactor (LMR) design are identified. The technical basis is presented for the performance of a pool-type reactor system with an advanced metallic alloy fuel in unprotected accidents. Results are presented from analyses of anticipated transients without scram, including loss-of-flow (LOF), transient overpower (TOP), and loss-of-heat-sink (LOHS) accidents

  2. Implementation of the TDCR liquid scintillation method at CNEA-LMR, Argentina.

    Science.gov (United States)

    Arenillas, Pablo; Cassette, Philippe

    2006-01-01

    During the last two years, a triple-to-double coincidence ratio (TDCR) system was assembled and adjusted at the CNEA-LMR, Argentina. The new counting system will add complementary capabilities to the absolute measurements section of the CNEA-LMR. This work describes its implementation and validation. Several checks and a set of beta-emitting standard solutions were used in order to perform the validation experiments. In preliminary measurements, a 3H LNHB solution with reference activity concentration of (119.7+/-0.9) kBq/g on 11 November 2003 was used. The CNEA-LMR TDCR counter gave, at the same reference date, an activity concentration of (120+/-1) kBq/g. Results and improvements are presented in detail. Concerning the asymmetry of the system, the quantum efficiency of the three photomultiplier tubes was studied for different operating conditions of the focusing voltage. The counter also includes an automatic system to change the efficiency by defocusing the photomultipliers and on the other hand, it was coupled to a HPGe detector to also measure beta-gamma coincidences.

  3. Implementation of the TDCR liquid scintillation method at CNEA-LMR, Argentina

    Energy Technology Data Exchange (ETDEWEB)

    Arenillas, Pablo [Laboratorio de Metrologia de Radioisotopos, Comision Nacional de Energia Atomica (Argentina); Cassette, Philippe [Laboratoire National Henri Becquerel, LNE-LNHB, 91191, Gif sur Yvette cedex (France)

    2006-10-15

    During the last two years, a triple-to-double coincidence ratio (TDCR) system was assembled and adjusted at the CNEA-LMR, Argentina. The new counting system will add complementary capabilities to the absolute measurements section of the CNEA-LMR. This work describes its implementation and validation. Several checks and a set of beta-emitting standard solutions were used in order to perform the validation experiments. In preliminary measurements, a {sup 3}H LNHB solution with reference activity concentration of (119.7{+-}0.9) kBq/g on 11 November 2003 was used. The CNEA-LMR TDCR counter gave, at the same reference date, an activity concentration of (120{+-}1) kBq/g. Results and improvements are presented in detail. Concerning the asymmetry of the system, the quantum efficiency of the three photomultiplier tubes was studied for different operating conditions of the focusing voltage. The counter also includes an automatic system to change the efficiency by defocusing the photomultipliers and on the other hand, it was coupled to a HPGe detector to also measure beta-gamma coincidences.

  4. Implementation of the TDCR liquid scintillation method at CNEA-LMR, Argentina

    International Nuclear Information System (INIS)

    Arenillas, Pablo; Cassette, Philippe

    2006-01-01

    During the last two years, a triple-to-double coincidence ratio (TDCR) system was assembled and adjusted at the CNEA-LMR, Argentina. The new counting system will add complementary capabilities to the absolute measurements section of the CNEA-LMR. This work describes its implementation and validation. Several checks and a set of beta-emitting standard solutions were used in order to perform the validation experiments. In preliminary measurements, a 3 H LNHB solution with reference activity concentration of (119.7±0.9) kBq/g on 11 November 2003 was used. The CNEA-LMR TDCR counter gave, at the same reference date, an activity concentration of (120±1) kBq/g. Results and improvements are presented in detail. Concerning the asymmetry of the system, the quantum efficiency of the three photomultiplier tubes was studied for different operating conditions of the focusing voltage. The counter also includes an automatic system to change the efficiency by defocusing the photomultipliers and on the other hand, it was coupled to a HPGe detector to also measure beta-gamma coincidences

  5. Lichtenstein Mesh Repair (LMR) v/s Modified Bassini’s Repair (MBR) + Lichtenstein Mesh Repair of Direct Inguinal Hernias in Rural Population – A Comparative Study

    Science.gov (United States)

    Patil, Santosh M; Kumar, Ashok; Kumar, Kuthadi Sravan; Mithun, Gorre

    2016-01-01

    Introduction Lichtenstein’s tension free mesh hernioplasty is the commonly done open technique for inguinal hernias. As our hospital is in rural area, majority of patients are labourers, open hernias are commonly done. The present study was done by comparing Lichtenstein Mesh Repair (LMR) v/s Modified Bassini’s repair (MBR) + Lichtenstein mesh repair (LMR) of direct Inguinal Hernias to compare the technique of both surgeries and its outcome like postoperative complications and recurrence rate. Materials and Methods A comparative randomized study was conducted on patients reporting to MNR hospital, sangareddy with direct inguinal hernias. A total of fifty consecutive patients were included in this study of which, 25 patients were operated by LMR and 25 patients were operated by MBR+LMR and followed up for a period of two years. The outcomes of the both techniques were compared. Results Study involved 25 each of Lichtenstein’s mesh repair (LMR) and modified bassini’s repair (MBR) + LMR, over a period of 2 years. The duration of surgery for lichtenstein mesh repair is around 34.56 min compared to LMR+MBR, which is 47.56 min which was statistically significant (p-value is MBR group in POD 1, but not statistically significant (p-value is 0.0949) and from POD 7 the pain was almost similar in both groups. The recurrence rate is 2% for LMR and 0% for MBR+LMR. Conclusion LMR+MBR was comparatively better than only LMR in all direct inguinal hernias because of low recurrence rate (0%) and low postoperative complications, which showed in our present study. PMID:27042517

  6. Lichtenstein Mesh Repair (LMR) v/s Modified Bassini's Repair (MBR) + Lichtenstein Mesh Repair of Direct Inguinal Hernias in Rural Population - A Comparative Study.

    Science.gov (United States)

    Patil, Santosh M; Gurujala, Avinash; Kumar, Ashok; Kumar, Kuthadi Sravan; Mithun, Gorre

    2016-02-01

    Lichtenstein's tension free mesh hernioplasty is the commonly done open technique for inguinal hernias. As our hospital is in rural area, majority of patients are labourers, open hernias are commonly done. The present study was done by comparing Lichtenstein Mesh Repair (LMR) v/s Modified Bassini's repair (MBR) + Lichtenstein mesh repair (LMR) of direct Inguinal Hernias to compare the technique of both surgeries and its outcome like postoperative complications and recurrence rate. A comparative randomized study was conducted on patients reporting to MNR hospital, sangareddy with direct inguinal hernias. A total of fifty consecutive patients were included in this study of which, 25 patients were operated by LMR and 25 patients were operated by MBR+LMR and followed up for a period of two years. The outcomes of the both techniques were compared. Study involved 25 each of Lichtenstein's mesh repair (LMR) and modified bassini's repair (MBR) + LMR, over a period of 2 years. The duration of surgery for lichtenstein mesh repair is around 34.56 min compared to LMR+MBR, which is 47.56 min which was statistically significant (p-value is MBR group in POD 1, but not statistically significant (p-value is 0.0949) and from POD 7 the pain was almost similar in both groups. The recurrence rate is 2% for LMR and 0% for MBR+LMR. LMR+MBR was comparatively better than only LMR in all direct inguinal hernias because of low recurrence rate (0%) and low postoperative complications, which showed in our present study.

  7. Sensitivity Analysis of Uncertainty Parameter based on MARS-LMR Code on SHRT-45R of EBR II

    Energy Technology Data Exchange (ETDEWEB)

    Kang, Seok-Ju; Kang, Doo-Hyuk; Seo, Jae-Seung [System Engineering and Technology Co., Daejeon (Korea, Republic of); Bae, Sung-Won [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of); Jeong, Hae-Yong [Sejong University, Seoul (Korea, Republic of)

    2016-10-15

    In order to assess the uncertainty quantification of the MARS-LMR code, the code has been improved by modifying the source code to accommodate calculation process required for uncertainty quantification. In the present study, a transient of Unprotected Loss of Flow(ULOF) is selected as typical cases of as Anticipated Transient without Scram(ATWS) which belongs to DEC category. The MARS-LMR input generation for EBR II SHRT-45R and execution works are performed by using the PAPIRUS program. The sensitivity analysis is carried out with Uncertainty Parameter of the MARS-LMR code for EBR-II SHRT-45R. Based on the results of sensitivity analysis, dominant parameters with large sensitivity to FoM are picked out. Dominant parameters selected are closely related to the development process of ULOF event.

  8. Analysis of Phenix end-of-life natural convection test with the MARS-LMR code

    International Nuclear Information System (INIS)

    Jeong, H. Y.; Ha, K. S.; Lee, K. L.; Chang, W. P.; Kim, Y. I.

    2012-01-01

    The end-of-life test of Phenix reactor performed by the CEA provided an opportunity to have reliable and valuable test data for the validation and verification of a SFR system analysis code. KAERI joined this international program for the analysis of Phenix end-of-life natural circulation test coordinated by the IAEA from 2008. The main objectives of this study were to evaluate the capability of existing SFR system analysis code MARS-LMR and to identify any limitation of the code. The analysis was performed in three stages: pre-test analysis, blind posttest analysis, and final post-test analysis. In the pre-test analysis, the design conditions provided by the CEA were used to obtain a prediction of the test. The blind post-test analysis was based on the test conditions measured during the tests but the test results were not provided from the CEA. The final post-test analysis was performed to predict the test results as accurate as possible by improving the previous modeling of the test. Based on the pre-test analysis and blind test analysis, the modeling for heat structures in the hot pool and cold pool, steel structures in the core, heat loss from roof and vessel, and the flow path at core outlet were reinforced in the final analysis. The results of the final post-test analysis could be characterized into three different phases. In the early phase, the MARS-LMR simulated the heat-up process correctly due to the enhanced heat structure modeling. In the mid phase before the opening of SG casing, the code reproduced the decrease of core outlet temperature successfully. Finally, in the later phase the increase of heat removal by the opening of the SG opening was well predicted with the MARS-LMR code. (authors)

  9. Supervisory control in a distributed, hierarchical architecture for a multimodular LMR

    International Nuclear Information System (INIS)

    Otaduy, P.J.; Brittain, C.R.; Rovere, L.A.

    1989-01-01

    This paper describes the directions and present status of the research in supervisory control for multimodular nuclear plants being conducted at Oak Ridge National Laboratory (ORNL) as part of US Department of Energy's (DOE) Advanced Controls Program. First, the hierarchical supervisory control structure envisioned for a Power Reactor Inherently Safe Module (PRISM) multimodular LMR is discussed. Next, the architecture of the supervisory module closest to the process actuators and its implementation for demonstration in a network of CPU's are presented. 12 refs., 3 figs

  10. STEP- A three-dimensional nodal diffusion code for LMR's

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Yeong Il; Kim, Taek Kyum [Korea Atomic Energy Research Institute, Taejon (Korea)

    1999-12-01

    STEP is a three-dimensional multigroup nodal diffusion code for the neutronics analysis of the LMR core. STEP employs DIF3D and HEXNOD nodal methods. In DIF3D, one-dimensional fluxes are approximated by polynomials while HEXNOD analytically solves transverse-integrated one-dimensional diffusion equations. The nodal equations are solved using a conventional fission source iteration procedure accelerated by coarse-mesh rebalancing and asymptotic extrapolation. At each fission source iteration, the interface currents for each group are computed by solving the response matrix equations with a known group source term. These partial currents are used to updata flux moments. This solution is accomplished by inner iteration, a series of sweeps through the spatial mesh. Inner iterations are performed by sweeping the axial mesh plane in a standard red-black checkerboard ordering, i.e. the odd-numbered planes are processed during the first pass, followed by the even-numbered planes on the second pass. On each plane, the nodes are swept in the four-color checkerboard ordering. STEP accepts microscopic cross section data from the CCCC standard interface file ISOTXS currently used for the neutronics analysis of LMR's at KAERI as well as macroscopic cross section data. Material cross sections are obtained by summing the product of atom densities and microscopic cross sections over all isotopes comprising the material. Energy is released from both fission ad capture. The thermal-hydraulics model calculates average fuel and coolant temperatures. STEP takes account of feedback effects from both fuel temperature and coolant temperature changes. The thermal-hydraulics model is a conservative, single channel model where there is no heat transfer between assemblies. Thus, STEP gives conservative results which, however, are of useful information for core design and can be useful tool for neutronics analysis of LMR core design and will be used for the base program of a future

  11. Validation of intermediate heat and decay heat exchanger model in MARS-LMR with STELLA-1 and JOYO tests

    Energy Technology Data Exchange (ETDEWEB)

    Choi, Chiwoong; Ha, Kwiseok; Hong, Jonggan; Yeom, Sujin; Eoh, Jaehyuk [Sodium-cooled Fast Reactor Design Division, Korea Atomic Energy Research Institute (KAERI), 989-111, Daedeok-Daero, Yuseong-Gu, Daejeon 305-353 (Korea, Republic of); Jeong, Hae-yong, E-mail: hyjeong@sejong.ac.kr [Department of Nuclear Engineering, Sejong University, 209 Neungdong-ro, Gwangjin-gu, Seoul 143-747 (Korea, Republic of)

    2016-11-15

    Highlights: • The capability of the MARS-LMR for heat transfer through IHX and DHX is evaluated. • Prediction of heat transfer through IHXs and DHXs is essential in the SFR analysis. • Data obtained from the STELLA-1 and the JOYO test are analyzed with the MARS-LMR. • MARS-LMR adopts the Aoki’s correlation for tube side and Graber-Rieger’s for shell. • The performance of the basic models and other available correlations is evaluated. • The current models in MARS-LMR show best prediction for JOYO and STELLA-1 data. - Abstract: The MARS-LMR code has been developed by the Korea Atomic Energy Research Institute (KAERI) to analyze transients in a pool-type sodium-cooled fast reactor (SFR). Currently, KAERI is developing a prototype Gen-IV SFR (PGSFR) with metallic fuel. The decay heat exchangers (DHXs) and the intermediate heat exchangers (IHXs) were designed as a sodium-sodium counter-flow tube bundle type for decay heat removal system (DHRS) and intermediate heat transport system (IHTS), respectively. The IHX and DHX are important components for a heat removal function under normal and accident conditions, respectively. Therefore, sodium heat transfer models for the DHX and IHX heat exchangers were added in MARS-LMR. In order to validate the newly added heat transfer model, experimental data were obtained from the JOYO and STELLA-1 facilities were analyzed. JOYO has two different types of IHXs: type-A (co-axial circular arrangement) and type-B (triangular arrangement). For the code validation, 38 and 39 data points for type A and type B were selected, respectively. A DHX performance test was conducted in STELLA-1, which is the test facility for heat exchangers and primary pump in the PGSFR. The DHX test in STELLA-1 provided eight data points for a code validation. Ten nodes are used in the heat transfer region is used, based on the verification test for the heat transfer models. RMS errors for JOYO IHX type A and type B of 19.1% and 4.3% are obtained

  12. Liquid metal reactor development -Studies on safety measure of LMR coolant

    International Nuclear Information System (INIS)

    Hwang, Sung Tae; Choi, Yoon Dong; Park, Jin Hoh; Kwon, Sun Kil; Choi, Jong Hyun; Cho, Byung Ryul; Kim, Tae Joon; Kwon, Sang Woon; Jung, Kyung Chae; Kim, Byung Hoh; Hong, Soon Bok; Jung, Ji Yung

    1995-07-01

    A study on the safety measures of LMR coolant showed the results as follows; 1. LMR coolant safety measure. A. Analysis and improvement of sodium fire code. B. Analysis of sodium fire phenomena. 2. Sodium fire aerosol characteristics. It was carried out conceptual design and basic design for sodium fire facility of medium size composed of sodium supply tank, sodium reactor vessel, sodium fire aerosol filter system and scrubbing column, and drain tank etc. 3. Sodium purification technology. A. Construction of calibration loop. (1) Design of sodium loop for the calibration of the equipment. (2) Construction of sodium loop including test equipments and other components. B. Na-analysis technology. (1) Oxygen concentration determination by the wet method. (2) Cover gas purification preliminary experiment. 4. The characteristics of sodium-water reaction. A. Analysis of the micro and small leak phenomena. (1) Manufacture of the micro-leak test apparatus. B. Analysis of large leak events. (1) Development of preliminary code for analysis of initial spike pressure. (2) Sample calculation and comparison with previous works. C. Development of test facility for large leak event evaluation. (1) Conceptional and basic design for the water and sodium-water test facility. D. Technology development for water leak detection system. (1) Investigations for the characteristics of active acoustic detection system. (2) Testing of the characteristics of hydrogen leak detection system. 171 figs, 29 tabs, 3 refs. (Author)

  13. The development of technologies of safety analysis for LMR ('03)

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Y. B.; Suk, S. D.; Chang, W. P.; Kwon, Y. M.; Jeong, H. Y.; Ha, K. W.; Heo, S

    2004-03-01

    The developmental objectives of the project, 'The development of safety analysis techniques in LMR', are the code development for the subchannel blockage analysis, the code development for the system transient analysis, the code development for the HCDA(Hypothetical Core Disruptive Accident) analysis, the preliminary safety analysis for KALIMER-600 equipped with the components of new concepts, and the establishment of data base. The purpose of the analysis for subchannel blockage in the subassembly of LMR is to represent quantitatively that the maximum damage due to the accident is within the safety criteria. The computational program should be developed to simulate the thermal hydraulic phenomena and to verify the safety of LMR for the accident. For the purpose, the hybrid scheme has been implemented into the MATRA-LMR code based on the upwind scheme to analyze the various flow fields occurred in the subchannel blockage accident. The turbulent mixing models using the CFX code were assessed to compute more precisely the heat transfer between subchannels. Through this assessment, empirical correction factors of 1.7 for the heat conduction, 0.006 for the turbulent mixing coefficient were obtained. The distributed resistance model instead of wire forcing function has been developed to represent the more exact flow field due to wire-wrap. Other models, such as heat conductor model and various turbulent mixing model, have been implemented into the MATRA-LMR. The ORNL THORS 19-Pin FFM-5B tests have been assessed to validate above new models using the improved MATRA-LMR. The results using MATRA-LMR were well agreed with the experimental data. The subchannel blockage accidents which assumed to be occurred at the three locations for the conceptual plant of KALIMER-600 have been analysed according to blockage size using the MATRA-LMR code. The results of calculations for the design basis events which 6 subchannels were blocked showed the margins of the 290 7.dog. C

  14. Development of explicit solution scheme for the MATRA-LMR code and test calculation

    International Nuclear Information System (INIS)

    Jeong, H. Y.; Ha, K. S.; Chang, W. P.; Kwon, Y. M.; Jeong, K. S.

    2003-01-01

    The local blockage in a subassembly of a liquid metal reactor is of particular importance because local sodium boiling could occur at the downstream of the blockage and integrity of the fuel clad could be threatened. The explicit solution scheme of MATRA-LMR code is developed to analyze the flow blockage in a subassembly of a liquid metal cooled reactor. In the present study, the capability of the code is extended to the analysis of complete blockage of one or more subchannels. The results of the developed solution scheme shows very good agreement with the results obtained from the implicit scheme for the experiments of flow channel without any blockage. The applicability of the code is also evaluated for two typical experiments in a blocked channel. Through the sensitivity study, it is shown that the explicit scheme of MATRA-LMR predicts the flow and temperature profile after blockage reasonably if the effect of wire is suitably modeled. The simple assumption in wire-forcing function is effective for the un-blocked case or for the case of blockage with lower velocity. A different type of wire-forcing function describing the velocity reduction after blockage or an accurate distributed resistance model is required for more improved predictions

  15. Liquid metal reactor development -Studies on safety measure of LMR coolant

    Energy Technology Data Exchange (ETDEWEB)

    Hwang, Sung Tae; Choi, Yoon Dong; Park, Jin Hoh; Kwon, Sun Kil; Choi, Jong Hyun; Cho, Byung Ryul; Kim, Tae Joon; Kwon, Sang Woon; Jung, Kyung Chae; Kim, Byung Hoh; Hong, Soon Bok; Jung, Ji Yung [Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)

    1995-07-01

    A study on the safety measures of LMR coolant showed the results as follows; 1. LMR coolant safety measure. A. Analysis and improvement of sodium fire code. B. Analysis of sodium fire phenomena. 2. Sodium fire aerosol characteristics. It was carried out conceptual design and basic design for sodium fire facility of medium size composed of sodium supply tank, sodium reactor vessel, sodium fire aerosol filter system and scrubbing column, and drain tank etc. 3. Sodium purification technology. A. Construction of calibration loop. (1) Design of sodium loop for the calibration of the equipment. (2) Construction of sodium loop including test equipments and other components. B. Na-analysis technology. (1) Oxygen concentration determination by the wet method. (2) Cover gas purification preliminary experiment. 4. The characteristics of sodium-water reaction. A. Analysis of the micro and small leak phenomena. (1) Manufacture of the micro-leak test apparatus. B. Analysis of large leak events. (1) Development of preliminary code for analysis of initial spike pressure. (2) Sample calculation and comparison with previous works. C. Development of test facility for large leak event evaluation. (1) Conceptional and basic design for the water and sodium-water test facility. D. Technology development for water leak detection system. (1) Investigations for the characteristics of active acoustic detection system. (2) Testing of the characteristics of hydrogen leak detection system. 171 figs, 29 tabs, 3 refs. (Author).

  16. Blind post-test analysis of Phenix End-of-Life natural circulation test with the MARS-LMR

    International Nuclear Information System (INIS)

    Jeong, Hae Yong; Ha, Kwi Seok; Kwon, Young Min; Chang, Won Pyo; Suk, Su Dong; Lee, Kwi Lim

    2010-01-01

    KAERI is developing a system analysis code, MARS-LMR, for the application to a sodium-cooled fast reactor (SFR). This code will be used as a basic tool in the design and analysis of future SFR systems in Korea. Before wide application of a system analysis code, it is required to verify and validate the code models through analyses for appropriate experimental data or analytical results. The MARS-LMR code has been developed from MARS code which had been well verified and validated for a pressurized water reactor (PWR) system. The MARS-LMR code shares the same form of governing equations and solution schemes with MARS code, which eliminates the need of independent verification procedure. However, it is required to validate the applicability of the code to an SFR system because it adopts some dedicated heat transfer models, pressure drop models, and material properties models for a sodium system. Phenix is a medium-sized pool-type SFR successfully operated for 35 years since 1973. This reactor reached its final shutdown in February 2009. An international program of Phenix end-of-life (EOL) test was followed and some valuable information was obtained from the test, which will be useful for the validation of SFR system analysis code. In the present study, the performance of MARS-LMR code is evaluated through a blind calculation with the boundary conditions measured in the real test. The post-test analysis results are also compared with the test data generated in the test

  17. Neutronic studies of the long life core concept: Part 1, Design and performance of 1000 MWe uranium oxide fueled low power density LMR cores

    International Nuclear Information System (INIS)

    Orechwa, Y.

    1987-04-01

    The parametric behavior of some key neutronic performance parameters for low power density LMR cores fueled with uranium oxide is investigated. The results are compared to reference homogeneous and heterogeneous cores with normal fuel management and Pu fueling. It can be concluded that with respect to minimizing the initial fissile mass and thereby economizing on the inventory costs and carrying charges, the superior neutron economy of the LMR fuel cycle is best exploited through normal fuel management with Pu recycling. In the once-through mode the LMR fuel cycle has disadvantages due to a higher fissile inventory and is not competitive with the LWR fuel cycle

  18. Development of fluid and I and C system design technology for LMR('03)

    International Nuclear Information System (INIS)

    Kim, Seong O; Sim, Yoon Sub; Choi, Seok Ki; Wi, Myung Hwan; Eoh, Jae Hyuk; Kim, Eui Kwang; Hur, Seop; Kim, Dong Hoon; Seong, Sung Hwan

    2004-02-01

    Based on the system design capability developed so far, our new unique reactor design concept was developed. The features are solving of a problem which existing sodium cooled reactor had, and improvement of economy and safety. Through the work, Some results were achieved, simplicity of KALIMER-600 structures, development of passive safety concept which is applicable to large sized plant, development of unique IHTS/SG combined design concept which can remove the possibility of SWR event, and optimization method of major components. Along with these results, analysis methods and computer codes, which are necessary for new design concept reactor, were developed for the self-reliance of domestic LMR technology by developing them without foreign assistance

  19. Recent improvements in modelling fission gas release and rod deformation on metallic fuel in LMR

    International Nuclear Information System (INIS)

    Hwang, Woan; Lee, Byoung-Oon; Kim, Young Jin

    2000-01-01

    Metallic fuel design is a key feature to assure LMR core safety goals. To date, a large effort has been devoted to the development of the MACSIS code for metallic fuel rod design and the evaluation of operational limits under irradiation conditions. The updated models of fission gas release, fuel core swelling, and rod deformation are incorporated into the correspondence routines in MACSIS MOD1. The MACSIS MOD1 which is a new version of MACSIS, has been partly benchmarked on FGR, fuel swelling and rod deformation comparing with the results of U-Zr and U-Pu-Zr metal fuels irradiated in LMRs. The MACSIS MOD1 predicts, relatively well, the absolute magnitudes and trends of the gas release and rod deformations depending on burn-up, and it gives better agreement with the experimental data than the previous predictions of MACSIS and the results of the empirical model

  20. Vibration analysis for IHTS piping system of LMR conveying hot liquid sodium

    International Nuclear Information System (INIS)

    Koo, Gyeong Hoi; Lee, Hyeong Yeon; Lee, Jae Han

    2001-01-01

    In this paper, the vibration characteristics of IHTS(Intermediate Heat Transfer System) piping system of LMR(Liquid Metal Reactor) conveying hot liquid sodium are investigated to eliminate the pipe supports for economic reasons. To do this, a 3-dimensional straight pipe element and a curved pipe element conveying fluid are formulated using the dynamic stiffness method of the wave approach and coded to be applied to any complex piping system. Using this method, the dynamic characteristics including the natural frequency, the frequency response functions, and the dynamic instability due to the pipe internal flow velocity are analyzed. As one of the design parameters, the vibration energy flow is also analyzed to investigate the disturbance transmission paths for the resonant excitation and the non-resonant excitations

  1. Study of the characteristics of water into sodium leak acoustic noise in LMR steam generator

    International Nuclear Information System (INIS)

    Kim, Tae Joon; Jeong, Kyung Chai; Jeong, Ji Young; Hur, Seop; Nam, Ho Yun

    2005-01-01

    A successful time for detecting a water/steam leak into sodium in the LMR SG (steam generator) at an early phase of a leak origin depends on the fast response and sensitivity of a leak detection system. It is considered, that the acoustic system is intended for a fast detecting of a water/steam into sodium leak of an intermediate flow rate, 1∼10 g/s. This intention of an acoustic system is stipulated by a key impossibility of a fast detecting of an intermediate leak by the present nominal systems on measuring the hydrogen in the sodium and in the cover gas concentration generated at a leak. During the self-wastage of a water/steam into sodium leak in a particular instant, it is usual in 30∼40 minutes from the moment of a leak origin, there is a modification of a leak flow out regime from bubble regime to the steam jet outflow. This evolution occurs as a jump function of the self-wastage of a leak and is escorted by an increase of a leak noise power and qualitative change of a leak noise spectrum. Subject of this study is by means of two experiments, one is an acoustic leak noise analysis of the water into sodium leak results in no damage to the LMR SG tube bundle, and another is for prediction of the frequency band under a high outflow leak condition. We experimented with the Argon gas injection considered with the phenomena of secondary leaks in real

  2. Assessment of MATRA-LMR-FB with the SHRT-17 Core Subassembly Data

    Energy Technology Data Exchange (ETDEWEB)

    Chang, Won-Pyo; Yoo, Jin Yoo; Lee, Seung Won; Seong, Seung Hwan; Ahn, Sang June; Choi, Chi-Woong; Lee, Kwi Lim; Jeong, Jae-Ho; Jeong, Taekyeong; Ha, Kwi-Seok [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2015-05-15

    Since the MATRA-LMRFB code is scheduled to be applied to a partial flow blockage analysis in a PGSFR (Prototype Generation IV Sodium-cooled Fast Reactor) subassembly, code verification is an essential part for the design review. Most of its verification efforts have been devoted to local sub-channel blockages, and thus the predictions were compared to those of other codes as well as experimental data. Verifications using pin bundles with a wire-wrap spacer had to be concentrated to 19-pin bundles, because available experimental data for such a bundle were relatively affluent in world-wide literatures. Therefore, more assessments with diverse pin numbers are necessary for MATRA-LMR-FB to be a more reliable code. Thus far, MATRA-LMR-FB has been applied to a 37-pin subassembly with wire-wrap spacers at most. In this regard, the present comparative study using data produced from the SHRT-17 which was carried out in a 61-pin test subassembly (XX09) placed in the EBR-II (Experimental Breeder Reactor II) core will be a meaningful demonstration for its extensive applicability. The power operation of the EBR-II was begun by ANL (Argonne National Lab.) in 1964 and the SHRT program was carried out in EBR-II between 1984 and 1986 in order to provide not only test data for validation of the computer codes but also demonstration of a passive reactor shutdown and decay heat removal in response of the protected and unprotected transients. The EBR-II SHRT-17 test data were used to demonstrate the prediction capability of MATRA-LMRFB on a radial distribution of the subassembly outlet temperatures during the steady state.

  3. Assessment of MATRA-LMR-FB with the SHRT-17 Core Subassembly Data

    International Nuclear Information System (INIS)

    Chang, Won-Pyo; Yoo, Jin Yoo; Lee, Seung Won; Seong, Seung Hwan; Ahn, Sang June; Choi, Chi-Woong; Lee, Kwi Lim; Jeong, Jae-Ho; Jeong, Taekyeong; Ha, Kwi-Seok

    2015-01-01

    Since the MATRA-LMRFB code is scheduled to be applied to a partial flow blockage analysis in a PGSFR (Prototype Generation IV Sodium-cooled Fast Reactor) subassembly, code verification is an essential part for the design review. Most of its verification efforts have been devoted to local sub-channel blockages, and thus the predictions were compared to those of other codes as well as experimental data. Verifications using pin bundles with a wire-wrap spacer had to be concentrated to 19-pin bundles, because available experimental data for such a bundle were relatively affluent in world-wide literatures. Therefore, more assessments with diverse pin numbers are necessary for MATRA-LMR-FB to be a more reliable code. Thus far, MATRA-LMR-FB has been applied to a 37-pin subassembly with wire-wrap spacers at most. In this regard, the present comparative study using data produced from the SHRT-17 which was carried out in a 61-pin test subassembly (XX09) placed in the EBR-II (Experimental Breeder Reactor II) core will be a meaningful demonstration for its extensive applicability. The power operation of the EBR-II was begun by ANL (Argonne National Lab.) in 1964 and the SHRT program was carried out in EBR-II between 1984 and 1986 in order to provide not only test data for validation of the computer codes but also demonstration of a passive reactor shutdown and decay heat removal in response of the protected and unprotected transients. The EBR-II SHRT-17 test data were used to demonstrate the prediction capability of MATRA-LMRFB on a radial distribution of the subassembly outlet temperatures during the steady state

  4. Inactivation of a putative efflux pump (LmrB) in Streptococcus mutans results in altered biofilm structure and increased exopolysaccharide synthesis: implications for biofilm resistance.

    Science.gov (United States)

    Liu, Jia; Zhang, Jianying; Guo, Lihong; Zhao, Wei; Hu, Xiaoli; Wei, Xi

    2017-07-01

    Efflux pumps are a mechanism associated with biofilm formation and resistance. There is limited information regarding efflux pumps in Streptococcus mutans, a major pathogen in dental caries. The aim of this study was to investigate potential roles of a putative efflux pump (LmrB) in S. mutans biofilm formation and susceptibility. Upon lmrB inactivation and antimicrobial exposure, the biofilm structure and expression of other efflux pumps were examined using confocal laser scanning microscopy (CLSM) and qRT-PCR. lmrB inactivation resulted in biofilm structural changes, increased EPS formation and EPS-related gene transcription (p < 0.05), but no improvement in susceptibility was observed. The expression of most efflux pump genes increased upon lmrB inactivation when exposed to antimicrobials (p < 0.05), suggesting a feedback mechanism that activated the transcription of other efflux pumps to compensate for the loss of lmrB. These observations imply that sole inactivation of lmrB is not an effective solution to control biofilms.

  5. Effects of an LMR-based partitioning-transmutation system on US nuclear fuel cycle health risk

    International Nuclear Information System (INIS)

    Michaels, G.E.; Reich, W.J.

    1992-01-01

    Health risks for the current US nuclear fuel cycle and for an illustrative partitioning and transmutation (P-T) fuel cycle based on Liquid Metal Reactor (LMR) technology are calculated and compared. Health risks are calculated for all non-reactor fuel cycle steps, including reprocessing, transportation, and high-level waste (HLW) disposal. Uranium mining and milling health risks have been updated to include recent occupational injury and death statistics, and the radiological health risk to the general public posed by the uranium mining overburden. In addition, the radiological health risks for transportation have been updated to include latent cancer fatalities associated with both normal transport and accidents. Given the assumptions of the study, it is shown that the deployment of an LMR-based P-T system is expected to reduce overall nuclear fuel cycle health risk

  6. COMMIX analysis of four constant flow thermal upramp experiments performed in a thermal hydraulic model of an advanced LMR

    International Nuclear Information System (INIS)

    Yarlagadda, B.S.

    1989-04-01

    The three-dimensional thermal hydraulics computer code COMMIX-1AR was used to analyze four constant flow thermal upramp experiments performed in the thermal hydraulic model of an advanced LMR. An objective of these analyses was the validation of COMMIX-1AR for buoyancy affected flows. The COMMIX calculated temperature histories of some thermocouples in the model were compared with the corresponding measured data. The conclusions of this work are presented. 3 refs., 5 figs

  7. Design of the Natural Circulation Loop and Implementation of DOWTHERM A Properties into MARS-LMR Code

    Energy Technology Data Exchange (ETDEWEB)

    Shin, Yukyung; Park, Seong Dae; Kang, Sarah; Bang, In Cheol [Ulsan National Institute of Science and Technology, Ulsan (Korea, Republic of)

    2015-05-15

    Molten Salt Reactor (MSR), which is one of the generation IV reactors, has an advantage in these requirements. MSR uses a molten salt mixture as the primary coolant, or the fuel itself and it operates on high temperature, so it doesn't need pressurizing. Also, liquid state fuel has an advantage for pyro-processing with easy separation of fission products. These fission products also have relatively short half-lives compared to those of the existing reactors. With these characteristics, MSR can have inherent safety in both direct and indirect sides. Also, MSR can operate at high temperature range, so that it can have the high efficiency to produce electricity. Therefore, research of MSR is meaningful for developing advanced nuclear reactors. FLiBe which is a mixture of lithium fluoride (LiF) and beryllium fluoride (BeF{sub 2}) is used as a primary coolant in MSR and LMR (Liquid Metal cooled Reactor). It has superiority over conventional liquid metal coolant like sodium, because it doesn't react with air or water. thermos-physical properties of DOWTHERM A for MARS-LMR code were made by modifying stg file of existing one. It was based on the process of Moore using 6 output parameters such as specific volume, internal energy, thermal expansion coefficient, isothermal compressibility, specific heat and entropy. With generated stg file (stgdowa.f90) and input file, tpf file (tpfdowa) which includes fluid property tables for MARS-LMR simulation was obtained. For the verification, this tpf file with execution file will be applied to the input deck of our natural circulation design. This work will contribute to researching and developing of MSR and LMR.

  8. Development of NONSTA code for the design and analysis of LMR high temperature structure

    International Nuclear Information System (INIS)

    Kim, Jong Bum; Lee, H. Y.; Yoo, B.

    1999-02-01

    Liquid metal reactor(LMR) operates at high temperature (500-550 dg C) and structural materials undergo complex deformation behavior like diffusion, dislocation glide, and dislocation climb due to high temperature environment. And the material life reduces rapidly due to the interaction of cavities created inside structural materials and high temperature fatigue cracks. Thus the establishment of high temperature structure analysis techniques is necessary for the reliability and safety evaluation of such structures. The objectives of this study are to develop NONSTA code as the subprogram of ABAQUS code adopting constitutive equations which can predict high temperature material behavior precisely and to build the systematic analysis procedures. The developed program was applied to the example problems such as the tensile analysis using exponential creep model and the repetitive tensile-compression analysis using Chaboche unified viscoplastic model. In addition, the problem of a plate with a center hole subjected to tensile load was solved to show the applicability of the program to multiaxial problem and the time dependent stress redistribution was observed. (Author). 40 refs., 2 tabs., 24 figs

  9. The role of SASSYS-1 in LMR [Liquid Metal Reactor] safety analysis

    International Nuclear Information System (INIS)

    Dunn, F.E.; Wei, T.Y.C.

    1988-01-01

    The SASSYS-1 liquid metal reactor systems analysis computer code is currently being used as the principal tool for analysis of reactor plant transients in LMR development projects. These include the IFR and EBR-II Projects at Argonne National Laboratory, the FFTF project at Westinghouse-Hanford, the PRISM project at General Electric, the SAFR project at Rockwell International, and the LSPB project at EPRI. The SASSYS-1 code features a multiple-channel thermal-hydraulics core representation coupled with a point kinetics neutronics model with reactivity feedback, all combined with detailed one-dimensional thermal-hydraulic models of the primary and intermediate heat transport systems, including pipes, pumps, plena, valves, heat exchangers and steam generators. In addition, SASSYS-1 contains detailed models for active and passive shutdown and emergency heat rejection systems and a generalized plant control system model. With these models, SASSYS-1 provides the capability to analyze a wide range of transients, including normal operational transients, shutdown heat removal transients, and anticipated transients without scram events. 26 refs., 16 figs

  10. Integrated intra-subassembly treatment in the SASSYS-1 LMR systems analysis code

    Energy Technology Data Exchange (ETDEWEB)

    Dunn, F.

    1992-09-01

    This report discusses a hot channel treatment which has been added to the SASSYS-1 LMR systems analysis code by providing for a multiple pin treatment of each of one or more subassemblies. This is an explicit calculation of intra-subassembly effects, not a hot-channel adjustment to a calculated average channel. Thus, the code can account for effects such as transient flow redistribution, both within a subassembly and among subassemblies. The code now provides a total integrated thermal hydraulic treatment including a multiple pin treatment within subassemblies, a multi-channel treatment of the whole core, and models for the primary coolant loops, the intermediate coolant loops, the steam generators, and the balance of plant. Currently the multiple-pin option is only implemented for single-phase calculations. It is not applicable after the onset of boiling or pin disruption. The new multiple pin treatment is being verified with detailed temperature data from instrumented subassemblies in EBR-II, both steady-state and transient, with special emphasis on passive safety tests such as SHRT-45. For the SHRT-45 test, excellent agreement is obtained between code predictions and experimental measurements of coolant temperatures.

  11. Integrated intra-subassembly treatment in the SASSYS-1 LMR systems analysis code

    Energy Technology Data Exchange (ETDEWEB)

    Dunn, F.

    1992-01-01

    This report discusses a hot channel treatment which has been added to the SASSYS-1 LMR systems analysis code by providing for a multiple pin treatment of each of one or more subassemblies. This is an explicit calculation of intra-subassembly effects, not a hot-channel adjustment to a calculated average channel. Thus, the code can account for effects such as transient flow redistribution, both within a subassembly and among subassemblies. The code now provides a total integrated thermal hydraulic treatment including a multiple pin treatment within subassemblies, a multi-channel treatment of the whole core, and models for the primary coolant loops, the intermediate coolant loops, the steam generators, and the balance of plant. Currently the multiple-pin option is only implemented for single-phase calculations. It is not applicable after the onset of boiling or pin disruption. The new multiple pin treatment is being verified with detailed temperature data from instrumented subassemblies in EBR-II, both steady-state and transient, with special emphasis on passive safety tests such as SHRT-45. For the SHRT-45 test, excellent agreement is obtained between code predictions and experimental measurements of coolant temperatures.

  12. Development of MARS-LMR and Steady-state Calculation for KALIMER-600

    Energy Technology Data Exchange (ETDEWEB)

    Ha, K. S.; Jeong, H. Y.; Chang, W. P.; Lee, Y. B.; Jo, C. H

    2007-05-15

    MARS code which has been developed by coupling the RELAP and COBRA-TF in Korea Atomic Energy Research Institute has been improved in the aspects of hydraulically multi-dimensional modeling and data processing of common block using a dynamic memory allocation of FORTRAN. To use the code in the area of safety analysis of liquid metal reactor, several parts of the code have to be improved further. (1) Sodium property table including dynamic properties, such as, conductivity and viscosity, was generated to fit for the MARS code. (2) The heat transfer correlations for the liquid metal were implemented in the code. (3) The models describing the flow resistance by wire-wrap spacer in the core of LMR were applied. A MARS input data for KALIMER-600 is generated and steady-state calculation at the rated power is successfully performed. The input data can be used as a base input deck for the various transient analysis of a of PHTS, IHTS, and Tertiary system with minor revision of initial conditions and control system models.

  13. Seismic analysis of a large pool-type LMR [liquid metal reactor

    International Nuclear Information System (INIS)

    Wang, C.Y.; Gvildys, J.

    1989-01-01

    This paper describes the seismic study of a 450-MWe liquid metal reactor (LMR) under 0.3-g SSE ground excitation. Two calculations were performed using the new design configuration. They deal with the seismic response of the reactor vessel, the guard vessel and support skirt, respectively. In both calculations, the stress and displacement fields at important locations of those components are investigated. Assessments are also made on the elastic and inelastic structural capabilities for other beyond-design basis seismic loads. Results of the reactor vessel analysis reveal that the maximum equivalent stress is only about half of the material yield stress. For the guard vessel and support skirt, the stress level is very small. Regarding the analysis if inelastic structural capability, solutions of the Newmark-Hall ductility modification method show that the reactor vessel can withstand seismics with ground ZPAs ranging from 1.015 to 1.31 g, which corresponds to 3.37 to 4.37 times the basic 0.3-g SSE. Thus, the reactor vessel and guard vessel are strong enough to resist seismic loads. 4 refs., 10 figs., 5 tabs

  14. Development of LMR Coolant Technology - Development of a submersible-in-pool electromagnetic pump

    Energy Technology Data Exchange (ETDEWEB)

    Hong, Sang Hi; Kim, Hee Reyoung; Lee, Sang Don; Seo, Joon Ho [Seoul National University, Seoul (Korea, Republic of); Cho, Su Won [Kyoungki University, Suwon (Korea, Republic of)

    1997-07-15

    A submersible-in-pool type annular linear induction pumps of 60 l/min and 200 l/min, and 600 deg C has been designed with optimum geometrical and operating values found from MHD and circuit analyses reflecting the high-temperature characteristics of pump materials. Through the characteristics analyses inside the narrow flow channel of electromagnetic pump, the distribution of the time-varying flow field is calculated, and magnetic flux and force density are evaluated by end effects of linear induction electromagnetic pump and the instability analyses are carried out introducing one-dimensional linear perturbation. Testing the pump with the flow rate of 60 l/min in the suitably manufactured loop system shows a flow rate of 58 l/min at an input power of 1,377 VA with 60Hz. The design of a scaled-up pump is further taken into account LMR coolant system requiring increased capacity, and a basic analysis is carried out on the pump of 40,000 l/min for KALIMER. The present project contributes to the further design of engineering prototype electromagnetic pumps with higher capacity and to the development of liquid metal reactor with innovative simplicity. 89 refs., 8 tabs., 45 figs. (author)

  15. MARS-LMR modeling for the post-test analysis of Phenix End-of-Life natural circulation

    International Nuclear Information System (INIS)

    Jeong, Hae Yong; Ha, Kwi Seok; Chang, Won Pyo; Lee, Kwi Lim

    2011-01-01

    For a successful design and analysis of Sodium cooled Fast Reactor (SFR), it is required to have a reliable and well-proven system analysis code. To achieve this purpose, KAERI is enhancing the modeling capability of MARS code by adding the SFR-specific models such as pressure drop model, heat transfer model and reactivity feedback model. This version of MARS-LMR will be used as a basic tool in the design and analysis of future SFR systems in Korea. Before wide application of MARS-LMR code, it is required to verify and validate the code models through analyses for appropriate experimental data or analytical results. The end-of-life test of Phenix reactor performed by the CEA provided a unique opportunity to have reliable test data which is very valuable in the validation and verification of a SFR system analysis code. The KAERI joined this international program of the analysis of Phenix end-of-life natural circulation test coordinated by the IAEA from 2008. The main test of natural circulation was completed in 2009. Before the test the KAERI performed the pre-test analysis based on the design condition provided by the CEA. Then, the blind post-test analysis was also performed based on the test conditions measured during the test before the CEA provide the final test results. Finally, the final post-test analysis was performed recently to predict the test results as accurate as possible. This paper introduces the modeling approach of the MARS-LMR used in the final post-test analysis and summarizes the major results of the analysis

  16. Analysis of Phenix End-of-Life asymmetry test with multi-dimensional pool modeling of MARS-LMR code

    International Nuclear Information System (INIS)

    Jeong, H.-Y.; Ha, K.-S.; Choi, C.-W.; Park, M.-G.

    2015-01-01

    Highlights: • Pool behaviors under asymmetrical condition in an SFR were evaluated with MARS-LMR. • The Phenix asymmetry test was analyzed one-dimensionally and multi-dimensionally. • One-dimensional modeling has limitation to predict the cold pool temperature. • Multi-dimensional modeling shows improved prediction of stratification and mixing. - Abstract: The understanding of complicated pool behaviors and its modeling is essential for the design and safety analysis of a pool-type Sodium-cooled Fast Reactor. One of the remarkable recent efforts on the study of pool thermal–hydraulic behaviors is the asymmetrical test performed as a part of Phenix End-of-Life tests by the CEA. To evaluate the performance of MARS-LMR code, which is a key system analysis tool for the design of an SFR in Korea, in the prediction of thermal hydraulic behaviors during an asymmetrical condition, the Phenix asymmetry test is analyzed with MARS-LMR in the present study. Pool regions are modeled with two different approaches, one-dimensional modeling and multi-dimensional one, and the prediction results are analyzed to identify the appropriateness of each modeling method. The prediction with one-dimensional pool modeling shows a large deviation from the measured data at the early stage of the test, which suggests limitations to describe the complicated thermal–hydraulic phenomena. When the pool regions are modeled multi-dimensionally, the prediction gives improved results quite a bit. This improvement is explained by the enhanced modeling of pool mixing with the multi-dimensional modeling. On the basis of the results from the present study, it is concluded that an accurate modeling of pool thermal–hydraulics is a prerequisite for the evaluation of design performance and safety margin quantification in the future SFR developments

  17. Recent Advances on the Understanding of Structural and Composition Evolution of LMR Cathodes for Li-ion Batteries

    Energy Technology Data Exchange (ETDEWEB)

    Yan, Pengfei [Environmental Molecular Sciences Laboratory, Pacific Northwest National Laboratory, Richland, WA (United States); Zheng, Jianming; Xiao, Jie [Energy and Environment Directorate, Pacific Northwest National Laboratory, Richland, WA (United States); Wang, Chong-Min, E-mail: chongmin.wang@pnnl.gov [Environmental Molecular Sciences Laboratory, Pacific Northwest National Laboratory, Richland, WA (United States); Zhang, Ji-Guang, E-mail: chongmin.wang@pnnl.gov [Energy and Environment Directorate, Pacific Northwest National Laboratory, Richland, WA (United States)

    2015-06-08

    Lithium-and-manganese-rich (LMR) cathode materials have been regarded as very promising for lithium (Li)-ion battery applications. However, their practical application is still limited by several barriers such as their limited electrochemical stability and rate capability. In this work, we present recent progress on the understanding of structural and compositional evolution of LMR cathode materials, with an emphasis being placed on the correlation between structural/chemical evolution and electrochemical properties. In particular, using Li[Li{sub 0.2}Ni{sub 0.2}Mn{sub 0.6}]O{sub 2} as a typical example, we clearly illustrate the structural characteristics of pristine materials and their dependence on the material-processing history, cycling-induced structural degradation/chemical partition, and their correlation with electrochemical performance degradation. The fundamental understanding that resulted from this work may also guide the design and preparation of new cathode materials based on the ternary system of transitional metal oxides.

  18. Development of fast reactor containment safety analysis code, CONTAIN-LMR. (3) Improvement of sodium-concrete reaction model

    International Nuclear Information System (INIS)

    Kawaguchi, Munemichi; Doi, Daisuke; Seino, Hiroshi; Miyahara, Shinya

    2015-01-01

    A computer code, CONTAIN-LMR, is an integrated analysis tool to predict the consequence of severe accident in a liquid metal fast reactor. Because a sodium-concrete reaction behavior is one of the most important phenomena in the accident, a Sodium-Limestone Concrete Ablation Model (SLAM) has been developed and installed into the original CONTAIN code at Sandia National Laboratories (SNL) in the U.S. The SLAM treats chemical reaction kinetics between the sodium and the concrete compositions mechanistically using a three-region model, containing a pool (sodium and reaction debris) region, a dry (boundary layer (B/L) and dehydrated concrete) region, and a wet (hydrated concrete) region, the application is limited to the reaction between sodium and limestone concrete. In order to apply SLAM to the reaction between sodium and siliceous concrete which is an ordinary structural concrete in Japan, the chemical reaction kinetics model has been improved to consider the new chemical reactions between sodium and silicon dioxide. The improved model was validated to analyze a series of sodium-concrete experiments which were conducted in Japan Atomic Energy Agency (JAEA). It has been found that relatively good agreement between calculation and experimental results is obtained and the CONTAIN-LMR code has been validated with regard to the sodium-concrete reaction phenomena. (author)

  19. The ABC-Type Multidrug Resistance Transporter LmrCD Is Responsible for an Extrusion-Based Mechanism of Bile Acid Resistance in Lactococcus lactis

    NARCIS (Netherlands)

    Zaidi, Arsalan Haseeb; Bakkes, Patrick J.; Lubelski, Jacek; Agustiandari, Herfita; Kuipers, Oscar P.; Driessen, Arnold J. M.

    2008-01-01

    Upon prolonged exposure to cholate and other toxic compounds, Lactococcus lactis develops a multidrug resistance phenotype that has been attributed to an elevated expression of the heterodimeric ABC-type multidrug transporter LmrCD. To investigate the molecular basis of bile acid resistance in L.

  20. Kinetic isotope effects in the CH4 + H→CH3 + H2 system. Predictions of the LMR six-body potential-energy reaction hypersurface

    International Nuclear Information System (INIS)

    Marriott, T.D.

    1976-01-01

    Scope of Study: The purpose of this study was two-fold. First, it served to test, in part, the usefulness of the LMR six-body potential-energy surface (LMR-PES) for transition-state theory predictions of the kinetic isotope effects for both the forward and reverse reactions of CH 4 + H reversible CH 3 + H 2 . In this regard the agreement between experimental and theoretical isotope effects, assuming the former to be accurate, provides information about the accuracy of the curvature of the potential energy surface for motion both parallel and perpendicular to the reaction coordinate. Second, these isotope effects were used to assess the validity of a number of qualitative and semi-quantitative interpretations of kinetic isotope effects developed in physical organic chemistry with regard to this reaction system. The force constants and geometries obtained numerically from the LMR-PES were found to produce reasonable harmonic approximations to the reactant normal mode frequencies. Neglecting tunneling, the LMR-PES reasonably reproduces the experimental k/sub H//k/sub D/ values for the reactions CH 4 + H(D), CH 3 + HD(DH) and CD 2 + HD(DH). Since previous theoretical treatments of primary deuterium kinetic isotope effects have neglected the bending normal mode frequencies, a semi-quantitative study of the effect of neglecting bending frequencies on the VP, EXC, and ZPE elements as well as the transition-state theory kinetic isotope effects was performed. The Swain-Schaad relationship between primary deuterium and tritium kinetic isotope effects was shown to hold to a reasonable degree of accuracy for the LMR-PES reaction system. A relationship between 13-carbon and 14-carbon kinetic isotope effects similar to the Swain-Schaad relationship was derived

  1. Pre-analysis of Phenix End-of-Life Thermal-hydraulic tests with the MARS-LMR Code

    International Nuclear Information System (INIS)

    Jeong, Hae Yong; Ha, Kwi Seok; Kwon, Young Min; Chang, Won Pyo; Suk, Su Dong; Lee, Yong Bum

    2009-01-01

    A prototype SFR, PHENIX has been operated by the French Commissariat a l'energie atomique (CEA) and the Electricite de France (EdF) since 1973. Through the successful operation for 35 years, PHENIX has achieved its original objective to demonstrate a fast breeder reactor technology and also played an important role as an irradiation facility for innovative fuels and materials. Since its first operation, PHENIX has accumulated about 4,300 equivalent full power days (EFPDs) of operational experience and it reached its final shutdown in 2009. Before the decommissioning of PHENIX, the CEA started a PHENIX end-of-life (EOL) test program and opened it for international collaboration to share the valuable information from the test. The KAERI joined this program to utilize the unique opportunity to validate its SFR system analysis code, MARS-LMR which will be a basic tool in future SFR development

  2. Prognostic meaning of neutrophil to lymphocyte ratio (NLR) and lymphocyte to monocyte ration (LMR) in newly diagnosed Hodgkin lymphoma patients treated upfront with a PET-2 based strategy.

    Science.gov (United States)

    Romano, Alessandra; Parrinello, Nunziatina Laura; Vetro, Calogero; Chiarenza, Annalisa; Cerchione, Claudio; Ippolito, Massimo; Palumbo, Giuseppe Alberto; Di Raimondo, Francesco

    2018-06-01

    Recent reports identify NLR (the ratio between absolute neutrophils counts, ANC, and absolute lymphocyte count, ALC), as predictor of progression-free survival (PFS) and overall survival (OS) in cancer patients. We retrospectively tested NLR and LMR (the ratio between absolute lymphocyte and monocyte counts) in newly diagnosed Hodgkin lymphoma (HL) patients treated upfront with a PET-2 risk-adapted strategy. NLR and LMR were calculated using records obtained from the complete blood count (CBC) from 180 newly diagnosed HL patients. PFS was evaluated accordingly to Kaplan-Meier method. Higher NLR was associated to advanced stage, increased absolute counts of neutrophils and reduced count of lymphocytes, and markers of systemic inflammation. After a median follow-up of 68 months, PFS at 60 months was 86.6% versus 70.1%, respectively, in patients with NLR ≥ 6 or NLR PET-2 scan (p PET-2 was an independent predictor of PFS in multivariate analysis. Advanced-stage patients (N = 119) were treated according to a PET-2 risk-adapted protocol, with an early switch to BEACOPP regimen in case of PET-2 positivity. Despite this strategy, patients with positive PET-2 still had an inferior outcome, with PFS at 60 months of 84.7% versus 40.1% (negative and positive PET-2 patients, respectively, p PET-2 status and to a lesser extend NLR in advanced stage, while LMR maintained its significance in early stage. By focusing on PET-2 negative patients, we found that patients with NLR ≥ 6.0 or LMR PET-2 scan, NLR and LMR can result in a meaningful prognostic system that needs to be further validated in prospective series including patients treated upfront with PET-2 adapted-risk therapy.

  3. CONTAIN LMR/1B-Mod.1, A computer code for containment analysis of accidents in liquid-metal-cooled nuclear reactors

    International Nuclear Information System (INIS)

    Murata, K.K.; Carroll, D.E.; Bergeron, K.D.; Valdez, G.D.

    1993-01-01

    The CONTAIN computer code is a best-estimate, integrated analysis tool for predicting the physical, chemical, and radiological conditions inside a nuclear reactor containment building following the release of core material from the primary system. CONTAIN is supported primarily by the U. S. Nuclear Regulatory Commission (USNRC), and the official code versions produced with this support are intended primarily for the analysis of light water reactors (LWR). The present manual describes CONTAIN LMR/1B-Mod. 1, a code version designed for the analysis of reactors with liquid metal coolant. It is a variant of the official CONTAIN 1.11 LWR code version. Some of the features of CONTAIN-LMR for treating the behavior of liquid metal coolant are in fact present in the LWR code versions but are discussed here rather than in the User's Manual for the LWR versions. These features include models for sodium pool and spray fires. In addition to these models, new or substantially improved models have been installed in CONTAIN-LMR. The latter include models for treating two condensables (sodium and water) simultaneously, sodium atmosphere and pool chemistry, sodium condensation on aerosols, heat transfer from core-debris beds and to sodium pools, and sodium-concrete interactions. A detailed description of each of the above models is given, along with the code input requirements

  4. Analytical studies on the impact of using repeated-rib roughness in LMR [Liquid Metal Reactor] decay heat removal systems

    International Nuclear Information System (INIS)

    Obot, N.T.; Tessier, J.H.; Pedersen, D.R.

    1988-01-01

    A numerical study was carried out to determine the effects of roughness on the thermal performance of Liquid Metal Reactor (LMR) decay heat removal systems for a range of possible design configurations and operating conditions. The ranges covered for relative rib height (e/D/sub h/), relative pitch (p/e) and flow attack angle were 0.026--0.103, 5--20 and 0--90 degrees, successively. The heat flux was varied between 1.1 and 21.5 kW/m 2 (0.1 and 2.0 kW/ft 2 ). Calculations were made for three cases: smooth duct with no ribs, ribs on both the guard vessel and collector wall, and ribs on the collector wall only. The results indicate that significant benefits, amounting to nearly two-fold reductions in guard vessel and collector wall temperatures, can be realized by placing repeated ribs on both the guard vessel and the collector wall. The magnitudes of the reduction in the reactor vessel temperature are considerably smaller. In general, the level of improvement, be it with respect to temperature or heat flux, is only mildly affected by changes in rib height or pitch but exhibits greater sensitivity to the assumed value for the system form loss. When the ribs are placed only on the collector wall, the heat removal capability is substantially reduced

  5. SAFE: A computer code for the steady-state and transient thermal analysis of LMR fuel elements

    International Nuclear Information System (INIS)

    Hayes, S.L.

    1993-12-01

    SAFE is a computer code developed for both the steady-state and transient thermal analysis of single LMR fuel elements. The code employs a two-dimensional control-volume based finite difference methodology with fully implicit time marching to calculate the temperatures throughout a fuel element and its associated coolant channel for both the steady-state and transient events. The code makes no structural calculations or predictions whatsoever. It does, however, accept as input structural parameters within the fuel such as the distributions of porosity and fuel composition, as well as heat generation, to allow a thermal analysis to be performed on a user-specified fuel structure. The code was developed with ease of use in mind. An interactive input file generator and material property correlations internal to the code are available to expedite analyses using SAFE. This report serves as a complete design description of the code as well as a user's manual. A sample calculation made with SAFE is included to highlight some of the code's features. Complete input and output files for the sample problem are provided

  6. Summary of advanced LMR [Liquid Metal Reactor] evaluations: PRISM [Power Reactor Inherently Safe Module] and SAFR [Sodium Advanced Fast Reactor

    International Nuclear Information System (INIS)

    Van Tuyle, G.J.; Slovik, G.C.; Chan, B.C.; Kennett, R.J.; Cheng, H.S.; Kroeger, P.G.

    1989-10-01

    In support of the US Nuclear Regulatory Commission (NRC), Brookhaven National Laboratory (BNL) has performed independent analyses of two advanced Liquid Metal Reactor (LMR) concepts. The designs, sponsored by the US Department of Energy (DOE), the Power Reactor Inherently Safe Module (PRISM) [Berglund, 1987] and the Sodium Advanced Fast Reactor (SAFR) [Baumeister, 1987], were developed primarily by General Electric (GE) and Rockwell International (RI), respectively. Technical support was provided to DOE, RI, and GE, by the Argonne National Laboratory (ANL), particularly with respect to the characteristics of the metal fuels. There are several examples in both PRISM and SAFR where inherent or passive systems provide for a safe response to off-normal conditions. This is in contrast to the engineered safety systems utilized on current US Light Water Reactor (LWR) designs. One important design inherency in the LMRs is the ''inherent shutdown'', which refers to the tendency of the reactor to transition to a much lower power level whenever temperatures rise significantly. This type of behavior was demonstrated in a series of unscrammed tests at EBR-II [NED, 1986]. The second key design feature is the passive air cooling of the vessel to remove decay heat. These systems, designated RVACS in PRISM and RACS in SAFR, always operate and are believed to be able to prevent core damage in the event that no other means of heat removal is available. 27 refs., 78 figs., 3 tabs

  7. Multi-dimensional approach of MARS-LMR for the analysis of Phenix End-of-Life natural circulation test

    International Nuclear Information System (INIS)

    Jeong, Hae Yong; Ha, Kwi Seok; Chang, Won Pyo; Lee, Kwi Lim

    2012-01-01

    Phenix is one of the important prototype sodium-cooled fast reactors (SFR) in nuclear reactor development history. It had been operated successfully for 35 years by the French Commissariat a l'energie atomique (CEA) and the Electricite de France (EdF) achieving its original objectives of demonstrating a fast breeder reactor technology and of playing the role of irradiation facility for innovative fuels and materials. After its final shutdown in 2009, CEA launched the Phenix End-of-life (EOL) test program. It provided a unique opportunity to generate reliable test data which is inevitable in the validation and verification of a SFR system analysis code. KAERI joined this international collaboration program of IAEA CRP and has performed the pretest analysis and post-test analysis utilizing the one-dimensional modeling of the MARS-LMR code, which had been developed by KAERI for the transient analysis of SFR systems. Through the previous studies, it has been identified that there are some limitations in the modeling of complicated thermal-hydraulic behaviors in the large pool volumes with the one-dimensional modeling. Recently, KAERI performed the analysis of Phenix EOL natural circulation test with multi-dimensional pool modeling, which is detailed below

  8. Multi-dimensional approach of MARS-LMR for the analysis of Phenix End-of-Life natural circulation test

    Energy Technology Data Exchange (ETDEWEB)

    Jeong, Hae Yong; Ha, Kwi Seok; Chang, Won Pyo; Lee, Kwi Lim [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2012-05-15

    Phenix is one of the important prototype sodium-cooled fast reactors (SFR) in nuclear reactor development history. It had been operated successfully for 35 years by the French Commissariat a l'energie atomique (CEA) and the Electricite de France (EdF) achieving its original objectives of demonstrating a fast breeder reactor technology and of playing the role of irradiation facility for innovative fuels and materials. After its final shutdown in 2009, CEA launched the Phenix End-of-life (EOL) test program. It provided a unique opportunity to generate reliable test data which is inevitable in the validation and verification of a SFR system analysis code. KAERI joined this international collaboration program of IAEA CRP and has performed the pretest analysis and post-test analysis utilizing the one-dimensional modeling of the MARS-LMR code, which had been developed by KAERI for the transient analysis of SFR systems. Through the previous studies, it has been identified that there are some limitations in the modeling of complicated thermal-hydraulic behaviors in the large pool volumes with the one-dimensional modeling. Recently, KAERI performed the analysis of Phenix EOL natural circulation test with multi-dimensional pool modeling, which is detailed below

  9. Development of analysis model for mid and long-term effects of sodium water reaction event in LMR

    International Nuclear Information System (INIS)

    Eoh, Jae Hyuk; Sim, Yoon Sub; Kim, Seong O; Kim, Yeon Sik; Kim, Eui Kwang; Wi, Myung Hwan

    2002-04-01

    The Sodium-Water Reaction(SWR) is important in the design consideration of a LMR steam generator. To develop the analysis code for long-term effects of SWR, investigation on the characteristics of various SWR analysis code and the assessment of an analysis model for long term effects were performed. In an event of SWR, pressure spikes of wave propagation occur at its initial stage and last for a very short time, and then bulk motion of fluid and reaction products is progressed and lasts for a long time. In a case SWR occurs, a number of hydrogen bubbles produced and sodium is entrained into the bubbles through the gas-liquid bubble interfaces by evaporation or diffusion. The partial pressure of the sodium in a hydrogen bubble is determined as a function of the bubble size, temperature, and pressure, and is rapidly decreased as its size increased. From this, it can be considered that the bulk motion in the later phase of SWR is an axial motion caused by expansion of a single-phase hydrogen gas bubble produced by a reaction in the vicinity of the leak site. Through this investigation, a preliminary simple analysis model for long-term effects of SWR was set up and sensitivity study using the system design parameters such as pressure and temperature of IHTS for KALIMER was performed. Also, a simpler analysis model using the cover gas pressure change related to the production of a hydrogen bubble in a steam generator was developed from the analyses results. These simple analysis models of the reaction site and the pressure behavior with hydrogen production can be used to develop the mid and long-term analysis code for SWR in the KALIMER steam generator design

  10. A study on the characteristics of the decay heat removal capacity for a large thermal rated LMR design

    International Nuclear Information System (INIS)

    Uh, J. H.; Kim, E. K.; Kim, S. O.

    2003-01-01

    The design characteristics and the decay heat removal capacity according to the type of DHR (Decay Heat Removal) system in LMR are quantitatively analyzed, and the general relationship between the rated core thermal power and decay heat removal capacity is created in this study. Based on these analyses results, a feasibility of designing a larger thermal rating KALIMER plant is investigated in view of decay heat removal capacity, and DRC (Direct Reactor Cooling) type DHR system which rejects heat from the reactor pool to air is proper to satisfy the decay heat removal capacity for a large thermal rating plant above 1,000 MWth. Some defects, however, including the heat loss under normal plant operation and the lack of reliance associated with system operation should be resolved in order to adopt the total passive concept. Therefore, the new concept of DHR system for a larger thermal rating KALIMER design, named as PDRC (passive decay heat removal circuit), is established in this study. In the newly established concept of PDRC, the Na-Na heat exchanger is located above the sodium cold pool and is prevented from the direct sodium contact during normal operation. This total passive feature has the superiority in the aspect of the minimizing the normal heat loss and the increasing the operation reliance of DHR system by removing either any operator action or any external operation signal associated with system operation. From this study, it is confirmed that the new concept of PDRC is useful to the designing of a large thermal rating power plant of KALIMER-600 in view of decay heat removal capability

  11. LMR deactivation information exchange

    International Nuclear Information System (INIS)

    Guttenberg, S.

    1998-01-01

    This report contains vugraphs of presentations given at the meeting. The topics covered include the following: FFTF Deactivation Strategy; Sodium Drain and Disposition; Sodium Processing; and Fuel Storage and Disposition

  12. Development and Experimental Verification of the Numerical Simulation Method for the Quasi-Steady SWR Phenomena in an LMR Steam Generator

    International Nuclear Information System (INIS)

    Eoh, Jae-Hyuk; Jeong, Ji-Young; Kim, Seong-O; Hahn, Dohee; Park, Nam-Cook

    2005-01-01

    A quasi-steady system analysis of the sodium-water reaction (SWR) phenomena in a liquid-metal reactor (LMR) was performed using the Sodium-water reaction Event Later Phase System Transient Analyzer (SELPSTA) computer simulation code. The code has been formulated by implementing various physical assumptions to simplify the complex SWR phenomena, and it adopts the long-term mass and energy transfer (LMET) model developed in the present study. The LMET model is based on the hypothesis that the system transient can be described by the pressure and temperature transient of the cover gas space, and it can be applied only to the reaction period characterized by bulk motion. To evaluate the feasibility of the physical model and its assumptions, a scale-down mock-up test was carried out, and it was demonstrated that the numerical simulation using the LMET model adequately replicates the overall phenomena of the experiment with reasonable understanding. Based on the findings, as a numerical example, the long-term system transient responses during the SWR event of the Korea Advanced LIquid MEtal Reactor (KALIMER) were investigated, and it was found that the long-term dynamic responses are strongly dependent on the design parameters and operational strategies. As a result, the numerical simulation method developed in the present study is practicable; furthermore, the SELPSTA code is useful to resolve the risk for the SWR event

  13. Current and future research on corrosion and thermalhydraulic issues of HLM cooled reactors and on LMR fuels for fast reactor systems

    International Nuclear Information System (INIS)

    Knebel, J.U.; Konings, R.J.M.

    2002-01-01

    Heavy liquid metals (HLM) such as lead (Pb) or lead-bismuth eutectic (Pb-Bi) are currently investigated world-wide as coolant for nuclear power reactors and for accelerator driven systems (ADS). Besides the advantages of HLM as coolant and spallation material, e.g. high boiling point, low reactivity with water and air and a high neutron yield, some technological issues, such as high corrosion effects in contact with steels and thermalhydraulic characteristics, need further experimental investigations and physical model improvements and validations. The paper describes some typical HLM cooled reactor designs, which are currently considered, and outlines the technological challenges related to corrosion, thermalhydraulic and fuel issues. In the first part of the presentation, the status of presently operated or planned test facilities related to corrosion and thermalhydraulic questions will be discussed. First approaches to solve the corrosion problem will be given. The approach to understand and model thermalhydraulic issues such as heat transfer, turbulence, two-phase flow and instrumentation will be outlined. In the second part of the presentation, an overview will be given of the advanced fuel types that are being considered for future liquid metal reactor (LMR) systems. Advantages and disadvantages will be discussed in relation to fabrication technology and fuel cycle considerations. For the latter, special attention will be given to the partitioning and transmutation potential. Metal, oxide and nitride fuel materials will be discussed in different fuel forms and packings. For both parts of the presentation, an overview of existing co-operations and networks will be given and the needs for future research work will be identified. (authors)

  14. The Nucleotide-Free State of the Multidrug Resistance ABC Transporter LmrA: Sulfhydryl Cross-Linking Supports a Constant Contact, Head-to-Tail Configuration of the Nucleotide-Binding Domains.

    Directory of Open Access Journals (Sweden)

    Peter M Jones

    Full Text Available ABC transporters are integral membrane pumps that are responsible for the import or export of a diverse range of molecules across cell membranes. ABC transporters have been implicated in many phenomena of medical importance, including cystic fibrosis and multidrug resistance in humans. The molecular architecture of ABC transporters comprises two transmembrane domains and two ATP-binding cassettes, or nucleotide-binding domains (NBDs, which are highly conserved and contain motifs that are crucial to ATP binding and hydrolysis. Despite the improved clarity of recent structural, biophysical, and biochemical data, the seemingly simple process of ATP binding and hydrolysis remains controversial, with a major unresolved issue being whether the NBD protomers separate during the catalytic cycle. Here chemical cross-linking data is presented for the bacterial ABC multidrug resistance (MDR transporter LmrA. These indicate that in the absence of nucleotide or substrate, the NBDs come into contact to a significant extent, even at 4°C, where ATPase activity is abrogated. The data are clearly not in accord with an inward-closed conformation akin to that observed in a crystal structure of V. cholerae MsbA. Rather, they suggest a head-to-tail configuration 'sandwich' dimer similar to that observed in crystal structures of nucleotide-bound ABC NBDs. We argue the data are more readily reconciled with the notion that the NBDs are in proximity while undergoing intra-domain motions, than with an NBD 'Switch' mechanism in which the NBD monomers separate in between ATP hydrolysis cycles.

  15. Development of safety analysis technology for LMR

    International Nuclear Information System (INIS)

    Hahn, Do Hee; Kwon, Y. M.; Suk, S. D.

    2002-05-01

    In the present study, the KALIMER safety analysis has been made for the transients considered in the design concept, hypothetical core disruptive accident (HCDA), and containment performance with the establishment of the design basis. Such analyses have not been possible without the computer code improvement, and the experience attained during this research period must have greatly contributed to the achievement of the self reliance in the domestic technology establishment on the safety analysis areas of the conceptual design. The safety analysis codes have been improved to extend their applicable ranges for detailed conceptual design, and a basic computer code system has been established for HCDA analysis. A code-to-code comparison analysis has been performed as a part of code verification attempt, and the leading edge technology of JNC also has been brought for the technology upgrade. In addition, the research and development on the area of the database establishment has been made for the efficient and systematic project implementation of the conceptual design, through performances on the development of a project scheduling management, integration of the individually developed technology, establishment of the product database, and so on, taking into account coupling of the activities conducted in each specific area

  16. Development of Sodium Technology for LMR

    Energy Technology Data Exchange (ETDEWEB)

    Kim, B. H.; Nam, H. Y.; Kim, T. J. (and others)

    2007-03-15

    In the experiments to investigate the characteristics of the free surface fluctuation in a vessel, the experimental correlation was modeled to describe the free surface fluctuation in the upper plenum of a liquid metal reactor within 95% reliability and 2.4% error. The correlation was used to verify the computational model. The new conceptual flowmeters were suggested to measure the sodium flow for the reliability enhancement. The electromagnetic flowmeter with permanent magnet showed a good linearity and repeatability. For reuse of the sodium contaminated component, CO{sub 2} bubbling method was developed. Sodium in 0.3mm crevice specimen was removed completely. The optimum condition for the used sodium treatment was deduced to estimate which reaction is more safe and adequate for operation condition by analyzing the reactivity alleviation condition and the reaction rate with the control of sodium hydroxide concentration A series of tests were carried out to investigate the enlargement rate of the nozzle hole itself and the sodium-water reaction temperature associated with needle-like jets of a high-pressure water/steam into the sodium side of a steam generator. The size of the nozzle hole became larger with an increased duration of the steam injection both for the 2.25Cr-1Mo and M9Cr-1Mo steels by a self-wastage phenomenon. For developing the SWR acoustic leak detection technology, the tool prepared by the LabVIEW was installed with the system, and confirmed the performance of the on-line acoustic leak detection tool using the SWR leak signal acquired in the KAERI facility.

  17. Functioneel Ontwerp Integratie BMNI/LMR

    NARCIS (Netherlands)

    LSO

    1995-01-01

    In dit rapport wordt de meetnetconfiguratie van het Nationaal Meetnet Radioactiviteit (NMR) gepresenteerd. Het NMR zal opgebouwd worden uit de bestaande meetnetten van de Rampenbestrijdingsorganisatie van Binnenlandse Zaken, het Binnenlandse Zaken Meetnet Nucleaire Incidenten (BMNI), en van

  18. Application of advanced technology to LMR control

    International Nuclear Information System (INIS)

    Lindsay, R.W.

    1989-01-01

    Key issues must be resolved to preserve the nuclear option; including new considerations for safety, economics, waste, transportation, diversion, etc. The programs at the Experimental Breeder Reactor II (EBR-II) are now carefully focused to provide answers to the above concerns in connection with the Integral Fast Reactor program at Argonne. Safety features that are inherent in plant design, coupled with automating plant control to help achieve the above objectives are more than just an issue of installing controllers and exotic algorithms, they include the complete integration of plant design, control strategy, and information presentation. Current technology development, both at Argonne and elsewhere includes efforts relating to the use of Artificial Intelligence, sensor/signal validation in many forms, pattern recognition, optimal develop and/or adopt promising technologies, and integrate them into an operating power plant for proof of value. After they have proven useful at EBR-II, it is expected that they can be incorporated into advanced designs such as PRISM and/or included in backfit activities as well. 6 refs

  19. Transient survivability of LMR oxide fuel pins

    International Nuclear Information System (INIS)

    Weber, E.T.; Pitner, A.L.; Bard, F.E.; Culley, G.E.; Hunter, C.W.

    1986-01-01

    Fuel pin integrity during transient events must be assessed for both the core design and safety analysis phases of a reactor project. A significant increase in the experience related to limits of integrity for oxide fuel pins in transient overpower events has been realized from testing of fuel pins irradiated in FFTF and PFR. Fourteen FFTF irradiated fuel pins were tested in TREAT, representing a range of burnups, overpower ramp rates and maximum overpower conditions. Results of these tests along with similar testing in the PFR/TREAT program, provide a demonstration of significant safety margins for oxide fuel pins. Useful information applied in analytical extrapolation of fuel pin test data have been developed from laboratory transient tests on irradiated fuel cladding (FCTT) and on unirradiated fuel pellet deformation. These refinements in oxide fuel transient performance are being applied in assessment of transient capabilities of long lifetime fuel designs using ferritic cladding

  20. Application of advanced technology to LMR control

    International Nuclear Information System (INIS)

    Lindsay, R.W.

    1989-01-01

    This paper reports that key issues must be resolved to preserve the nuclear option; including new considerations for safety, economics, waste, transportation, diversion, etc. The programs at the Experimental Breeder Reactor II (EBR-II) are now carefully focused to provide answers to the above concerns in connection with the Integral Fast Reactor program at Argonne. Safety features that are inherent in plant design, coupled with automating plant control to help achieve the above objectives are more than just an issue of installing controllers and exotic algorithms, they include the complete integration of plant design, control strategy, and information presentation. Current technology development, both at Argonne and elsewhere includes efforts relating to the use of Artificial Intelligence, sensor/signal validation in many forms, pattern recognition, optimal control technologies, etc. The eBR-II effort is to identify needs, develop and/or adopt promising technologies, and integrate them into an operating power plant for proof of value. After they have proven useful at EBR-II, it is expected that they can be incorporated into advanced designs such as PRISM and/or included in backfit activities as well

  1. Coolant void effect investigation - case of a na-cooled fast reactor

    International Nuclear Information System (INIS)

    Glinatsis, G.; Gugiu, D.

    2013-01-01

    In the frame of the last EURATOM-FP7 Program, a large sized Sodium-cooled FR (SFR) has been studied. Mixed carbides fuel (U, Pu)C has been adopted for the backup core solution and important work has been also performed in order to obtain an ''optimised'' backup configuration ''close'' to the reference one, which is fueled by mixed oxides fuel (U, Pu)Ox. The peculiarity of both core designs (the reference configuration and the optimised backup configuration) is the adoption of a 60 cm Plenum zone in the upper part of each fuel assembly (FA), that is filled by coolant, in order to mitigate (when emptied) the core positive coolant void effect. This paper presents some results of a detailed study of the coolant void effect for the above SFR with mixed carbides core. Many aspects, like geometric heterogeneity, the burnup state, the operating conditions, etc., have been taken into consideration in order to obtain information about the ''propagation'' and the behaviour of the coolant void effect itself. The performed study investigates also the coolant void effect consequences on some reactivity coefficients, which are important for a safe behaviour of the reactor. The investigation consisted in the steady state simulations of the reactor on different operating conditions in Monte Carlo approach. (authors)

  2. Reduction of HLW repository environmental impact by Na-Cooled FBR

    International Nuclear Information System (INIS)

    Ahn, Joonhong; Ikegami, Tetsuo

    2005-01-01

    The present study proposes the total toxicity index of radionuclides that have accumulated in the region exterior to the repository as the environmental impact measure. The measure is quantitatively evaluated by a radionuclide transport models that incorporate the effects of canister-array configuration and the initial mass loading in the waste canister. With the measure, it is demonstrated that the environmental impact of the repository can be effectively reduced by reduction of the initial mass loading resulting from FBR deployment and change in the canister-array configuration in the repository. The rate of increase in the environmental impact with the increase in the repository size can be reduced by reducing the initial mass loading of Np and its precursors. (author)

  3. Liquid metal reactor development. Development of LMR coolant technology

    Energy Technology Data Exchange (ETDEWEB)

    Nam, H. Y.; Choi, S. K.; Hwang, J. s.; Lee, Y. B.; Choi, B. H.; Kim, J. M.; Kim, Y. G.; Kim, M. J.; Lee, S. D.; Kang, Y. H.; Maeng, Y. Y.; Kim, T. R.; Park, J. H.; Park, S. J.; Cha, J. H.; Kim, D. H.; Oh, S. K.; Park, C. G.; Hong, S. H.; Lee, K. H.; Chun, M. H.; Moon, H. T.; Chang, S. H.; Lee, D. N.

    1997-07-15

    Following studies have been performed during last three years as the 1.2 phase study of the mid and long term nuclear technology development plan. First, the small scale experiments using the sodium have been performed such as the basic turbulent mixing experiment which is related to the design of a compact reactor, the flow reversal characteristics experiment by natural circulation which is necessary for the analysis of local flow reversal when the electromagnetic pump is installed, the feasibility test of the decay heat removal by wall cooling and the operation of electromagnetic pump. Second, the technology of operation mechanism of sodium facility is developed and the technical analysis and fundamental experiments of sodium measuring technology has been performed such as differential pressure measuring experiment, local flow rate measuring experimenter, sodium void fraction measuring experiment, under sodium facility, the free surface movement experiment and the side orifice pressure drop experiment. A new bounded convection scheme was introduced to the ELBO3D thermo-hydraulic computer code designed for analysis of experimental result. A three dimensional computer code was developed for the analysis of free surface movement and the analysis model of transmission of sodium void fraction was developed. Fourth, the small scale key components are developed. The submersible-in-pool type electromagnetic pump which can be used as primary pump in the liquid metal reactor is developed. The SASS which uses the Curie-point electromagnet and the mock-up of Pantograph type IVTM were manufactured and their feasibility was evaluated. Fifth, the high temperature characteristics experiment of stainless steel which is used as a major material for liquid metal reactor and the material characteristics experiment of magnet coil were performed. (author). 126 refs., 98 tabs., 296 figs.

  4. A condensed review of the core catcher in the LMR

    International Nuclear Information System (INIS)

    Lee, Yong Bum; Hahn, Do hee

    2001-03-01

    The overwhelming emphasis in reactor safety is on the prevention of core meltdown. Moreover, although there have been several accidents that have resulted in some fuel melting, to date there have been no accidents severe enough to cause the syndrome of core collapse, reactor vessel melt-through, containment penetration, and dispersal into the ground. Nevertheless, a number of proposals have been made for the design of core catcher systems to control or stop the motion of the molten core mass should such an accident take place. Core catchers may differ in both their location within the reactor system and in the mechanism that is used to cool and control the motion of the core debris. In this report the classification, configuration and main features of the core catcher are described. And also, the core catcher provisions in constructed and planned LMRs (Liquid Metal Reactors) are summarized

  5. A review of the core catcher design in LMR

    International Nuclear Information System (INIS)

    Lee, Yong Bum; Hahn, Do Hee

    2001-08-01

    The overwhelming emphasis in reactor safety is on the prevention of core meltdown. Moreover, although there have been several accidents that have resulted in some fuel melting, to date there have been no accidents severe enough to cause the syndrome of core collapse, reactor vessel melt-through, containment penetration, and dispersal into the ground. Nevertheless, a number of proposals have been made for the design of core catcher systems to control or stop the motion of the molten core mass should such an accident take place. Core catchers may differ in both their location within the reactor system and in the mechanism that is used to cool and control the motion of the core debris. In this report the classification, configuration and main features of the core catcher are described. And also, The core catcher design technologies and processes are presented. Finally the core catcher provisions in constructed and planned LMRs (Liquid Metal Reactors) are summarized and the preliminary assessment on the core catcher installation in KALIMER is presented

  6. Evaluating advanced LMR [liquid metal reactor] reactivity feedbacks using SSC

    International Nuclear Information System (INIS)

    Slovik, G.C.; Van Tuyle, G.J.; Kennett, R.J.; Cheng, H.S.

    1988-01-01

    Analyses of the PRISM and SAFR Liquid Metal Reactors with SSC are discussed from a safety and licensing perspective. The PRISM and SAFR reactors with metal fuel are designed for inherent shutdown responses to loss-of-flow and loss-of-heat-sink events. The demonstration of this technology was performed by EBR-II during experiments in April 1986 by ANL (Planchon, et al.). Response to postulated TOPs (control rod withdrawal) are made acceptable largely by reducing reactivity swings, and therefore minimizing the size of possible ractivity insertions. Analyses by DOE and the contractors GE, RI, and ANL take credit for several reactivity feedback mechanisms during transient calculations. These feedbacks include Doppler, sodium density, and thermal expansion of the grid plates, the load pads, the fuel (axial) and the control rod which are now factored into the BNL SSC analyses. The bowing feedback mechanism is not presently modeled in the SSC due to its complexity and subsequent large uncertainty. The analysis is conservative by not taking credit for this negative feedback mechanism. Comparisons of BNL predictions with DOE contractors are provided

  7. Physics studies of higher actinide consumption in an LMR

    International Nuclear Information System (INIS)

    Hill, R.N.; Wade, D.C.; Fujita, E.K.; Khalil, H.

    1990-01-01

    The core physics aspects of the transuranic burning potential of the integral Fast Reactor (IFR) are assessed. The actinide behavior in fissile self-sufficient IFR closed cycles of 1200 MWt size is characterized, and the transuranic isotopics and risk potential of the working inventory are compared to those from a once-through LWR. The core neutronic performance effects of rare-earth impurities present in the recycled fuel are addressed. Fuel cycle strategies for burning transuranics from an external source are discussed, and specialized actinide burner designs are described

  8. Development of Mechanical Structure Design Technology for LMR

    International Nuclear Information System (INIS)

    Lee, Jae Han; Joo, Young Sang; Lee, Hyeong Yeon

    2007-03-01

    Structural integrity and design simplifications were secured on reactor core support system, upper internal structure and core catcher of KALIMER-600. The evaluation on the suitability of high temperature and seismic design of reactor structures, and the structural integrity evaluation on reactor components and high temperature pipings are performed. The interfaces between the components and ISI accessibility are checked. Lightening of reactor building by 7%, the seismic design for 0.3g seismic loads and improvement of reactor structural design concept for KALIMER-600 have been carried out. Remote inspection technique using ultrasonic wave guide sensor was acquired as a visualization method for reactor internals under opaque sodium environments. The basic guideline on high temperature structure assessment as an assessment procedure on high temperature inelastic behaviour has been completed. In high temperature creep-fatigue test, totally 500 cycles (totally 700 hold time) were carried on cylindrical test and IHTS co-axial pipe test models. The behaviors of creep-fatigue damage and creep-fatigue crack behaviour were investigated, and the DB on the structural test were established. The seismic response tests on 19-sub assembly validation test model in air and in water were carried out, and its multi-purpose characteristics and reliability on the SAC-CORE3.0 code developed for core seismic response analysis were validated

  9. Multi-dimensional Code Development for Safety Analysis of LMR

    International Nuclear Information System (INIS)

    Ha, K. S.; Jeong, H. Y.; Kwon, Y. M.; Lee, Y. B.

    2006-08-01

    A liquid metal reactor loaded a metallic fuel has the inherent safety mechanism due to the several negative reactivity feedback. Although this feature demonstrated through experiments in the EBR-II, any of the computer programs until now did not exactly analyze it because of the complexity of the reactivity feedback mechanism. A multi-dimensional detail program was developed through the International Nuclear Energy Research Initiative(INERI) from 2003 to 2005. This report includes the numerical coupling the multi-dimensional program and SSC-K code which is used to the safety analysis of liquid metal reactors in KAERI. The coupled code has been proved by comparing the analysis results using the code with the results using SAS-SASSYS code of ANL for the UTOP, ULOF, and ULOHS applied to the safety analysis for KALIMER-150

  10. SAFR: a marriage of safety and innovation in LMR design

    International Nuclear Information System (INIS)

    Lancet, R.T.; Mills, J.C.

    1985-01-01

    The Sodium Advanced Fast Reactor (SAFR) is a natural evolution of earlier designs, given the current economic and licensing environment. Stringent safety and economic goals have been established for the SAFR plant. This paper describes how these goals are being satisfied, with the primary emphasis being placed on safety. The top level safety goals are: (a) to provide inherently safe responses to all credible events (b) to minimize the potential for severe accidents, and (c) to eliminate the need for evacuation, (d) limited financial risk, (e) assured investment protection, (f) minimum development risk, (g) high capacity factor, (h) long plant life, and (i) low personnel radiation exposure

  11. Advanced 4S (super safe, small and simple) LMR

    International Nuclear Information System (INIS)

    Minato, A.; Handa, N.

    2000-01-01

    This paper describes a new nuclear power system which can be used for a greater variety of applications. The 4S liquid metal reactor has high inherent safety and passive safety characteristics. It is also easy to operate, maintain and inspect, faster to construct, more flexible in location, requires less initial investment, and is better suited to electrical grid management. The reactor offers a new route through which to expand the use of safe nuclear technology in the world. (author)

  12. Physics studies of higher actinide consumption in an LMR

    International Nuclear Information System (INIS)

    Hill, R.N.; Wade, D.C.; Fujita, E.K.; Khalil, H.S.

    1990-01-01

    The core physics aspects of the transuranic burning potential of the Integral Fast Reactor (IFR) are assessed. The actinide behavior in fissile self-sufficient IFR closed cycles of 1200 MWt size is characterized, and the transuranic isotopics and risk potential of the working inventory are compared to those from a once-through LWR. The core neutronic performance effects of rare-earth impurities present in the recycled fuel are addressed. Fuel cycle strategies for burning transuranics from an external source are discussed, and specialized actinide burner designs are described. 4 refs., 4 figs., 3 tabs

  13. Development of Fluid and I and C Systems Design Technology for LMR - Development of mechanical structure design technology for LMR

    International Nuclear Information System (INIS)

    Lee, Jae Han; Joo, Young Sang; Lee, Hueong Yeon and others

    2005-03-01

    The key research items during the fiscal years of Phase 3 of the mechanical design technology development for liquid metal reactor are described. The objective of this project is to develop the design technology for the mechanical system of 600MWe, pool type liquid metal reactor with sodium coolant, and the structural integrity evaluation technology for mechanical system of the reactor system, structures and equipments. In the design technology development for mechanical structures, the reactor internal structures, reactor head and piping system, reactor containment structures have been studied, and new structural concepts compatible with the new reactor have been proposed. The thermal protection devices of reactor vessel and the refueling system have been conceptually established and the feasibility study for 3-D seismic isolation of reactor building was performed. The structural damage detection technology for reactor internal structures has been studied and its application has been confirmed. In the structural integrity evaluation technology development, the sensitivities of material constants for inelastic analysis codes have been studied and the applicabilities of the developed codes are enhanced. The high temperature creep-fatigue structural behavior test has been conducted so that high temperature structural damage test and evaluation technology were ensured at first in domestic. The high temperature seismic buckling analysis method to evaluate the buckling of thin reactor shell structure under the transient thermal load was established. In addition, the core seismic response analysis code reflected the fluid effect of core was developed and its accuracy was confirmed with a scale-down model test

  14. Development of Fluid and I and C System Design Technology for LMR

    International Nuclear Information System (INIS)

    Kim, S. O.; Sim, Y. S.; Choi, S. K.

    2007-06-01

    The basic concept of fluid and I and C systems of KALIMER-600 was developed and the computer codes required to materialize system concept were also implemented through the R and D program. Based on the analysis results of the design characteristics for the similar reactor types developed in the foreign countries, the system design technologies with adoption of the innovative ideas were developed. With the development, expansion and reinforcement of the methodologies required according to the progress of development and design of the system and the experimental verification of the developed computer code, the excellent and innovative outcomes were produced

  15. EBR-II facility for cleaning and maintenance of LMR components

    International Nuclear Information System (INIS)

    Washburn, R.A.

    1986-01-01

    The cleaning and maintenance of EBR-II sodium wetted components is accomplished in a separate hands-on maintenance facility known as the Sodium Components Maintenance Shop (SCMS). Sodium removal is mostly done using alcohol but steam or water is used. The SCMS has three alcohol cleaning systems: one for small nonradioactive components, one for small radioactive components, and one for large radioactive components. The SCMS also has a water-wash station for the removal of sodium with steam or water. An Alcohol Recovery Facility removes radioactive contaminants from the alcohol and reclaims the alcohol for reuse. Associated with the large components cleaning system is a major component handling system

  16. Reactivity feedback components of a homogeneous U10Zr-fueled 900 MWt LMR

    International Nuclear Information System (INIS)

    Meneghetti, D.; Kucera, D.A.

    1988-01-01

    The linear and Doppler feedback components of the regional contributions of the power-reactivity-decrement (PRD) and of the temperature coefficient of reactivity for a 900 MWt homogeneous U10Zr-fueled sodium-cooled reactor are calculated. The PRD components are separated into power dependent and power-to-flow dependent parts. The values of PRD and temperature coefficient components are compared with corresponding quantities calculated for the Experimental Breeder Reactor II. The implications of these comparisons upon inherent safety characteristics of metal-fueled sodium-cooled reactors are discussed

  17. LMR design concepts for transuranic management in low sodium void worth cores

    International Nuclear Information System (INIS)

    Hill, R.N.

    1991-01-01

    The fuel cycle processing techniques and hard neuron spectrum of the Integral Fast Reactor (IFR) metal fuel cycle have favorable characteristics for the management of transuranics; and the wide range of breeding characteristics available in metal fuelled cores provides for flexibility in transuranic management strategy. Previous studies indicate that most design options which decrease the breeding ratio also show a decrease in sodium void worth; therefore, low void worths are achievable in transuranic burning (low breeding ratio) core designs. This paper describes numerous trade studies assessing various design options for a low void worth transuranic burner core. A flat annular core design appears to be a promising concept; the high leakage geometry yields a low breeding ratio and small sodium void worth. To allow flexibility in breeding characteristics, alternate design options which achieve fissile self-sufficiency are also evaluated. A self-sufficient core design which is interchangeable with the burner core and maintains a low sodium void worth is developed. 13 refs., 1 fig., 4 tabs

  18. Status of RBCB testing of LMR oxide fuel in EBR-II

    International Nuclear Information System (INIS)

    Strain, R.V.; Bottcher, J.H.; Gross, K.C.; Lambert, J.D.B.; Ukai, S.; Nomura, S.; Shikakura, S.; Katsuragawa, M.

    1991-01-01

    The status is given of the the American-Japanese collaborative program in Experimental Breeder Reactor 2 to determine the run-beyond-cladding-breach performance of (UPu)O 2 fuel pins for liquid-metal cooled reactors. Phase 1 of the collaboration involved eighteen irradiation tests over 1981--86 with 5.84-mm pins in 316 or D9 stainless steel. Emphasis in Phase 2 tests from 1989 onwards is with larger diameter (7.5mm) pins in advanced claddings. Results include delayed neutron and fission gas release data from breached pins, the impact of fuel-sodium reaction product formation on pin performance, and fuel and fission product contamination from failures. 13 refs, 1 fig., 4 tabs

  19. Analysis of Decay Heat Removal by Natural Convection in LMR with a Combined Steam Generator

    International Nuclear Information System (INIS)

    Kim, Eui Kwang; Eoh, Jae Hyuk; Han, Ji Woong; Lee, Tae Ho

    2011-01-01

    Liquid metal reactors (LMRs) conventionally employ an intermediate heat transport system (IHTS) to protect the nuclear core during a sodium-water reaction (SWR) event. However these SWR-related components increase plant construction costs. In order to eliminate the need for an IHTS, a combined steam generator, which is an integrated heat exchanger of a steam generator and intermediate heat exchanger (IHX), was proposed by the Korea Atomic Energy Research Institute (KAERI). The objective of this work is to analyze the natural circulation heat removal capability of the rector system using a combined steam generator. As a means of decay heat removal, a normal heat transport path is composed of a primary sodium system, intermediate lead-bismuth circuit combined with SG and steam/water system. This paper presents the results of the possible temperature and natural circulation flows in all circuits during a steady state for a given reactor power level varied as a function of time

  20. Realization of safety culture into a reactor plant-4S (super safe, small and simple) LMR

    International Nuclear Information System (INIS)

    Hattori, S.; Ikemoto, I.; Minato, A.

    1998-01-01

    International Nuclear Safety Advisory Group (INSAG) defines Safety Culture as the following; Safety Culture is that assembly of characteristics and attitudes in organization and individuals which establishes that, as an overriding priority, nuclear plant safety issues receive the attention warranted by their significance. While such Safety Culture is certainly a critical element of nuclear safety assurance, it is important to design nuclear power facilities as friendly to operators as possible with minimum dependence on human factors. From the viewpoint of ensuring supply in our global society, it will be necessary to have multiple approaches to further promote the use of nuclear energy worldwide despite various social and cultural restrictions. It should then be considered, as prospective options, to disperse small nuclear power plants throughout the world under technical, social and cultural conditions. Under this circumstance, we have quested for and now propose a a scheme of assuring sheer safety of nuclear power plants by implementing operator-friendly nuclear reactors virtually free from human errors. The scheme specifically includes the measures for improving reliability through fabricating more compact reactors with a continuous in-factory production system, simplify maintenance and inspection of the reactor system using passive systems and further relieving operators of burden of labors. (author)

  1. Some safety considerations in the selection of redans for pool-type LMR plants

    International Nuclear Information System (INIS)

    Pan, Y.C.; Pedersen, D.R.; Wang, C.Y.

    1985-01-01

    Three basic safety issues in the selection of the redan design for a pool type liquid metal fast breeder reactor plant are examined. The first area examined is the effect of the redan selection on the integrity of the primary system pressure boundary in normal and offset conditions. The second area is on the consequence of the hypothetical core disruptive accident. The third area is on the consequence of the loss of heat sink accident. Some general discussion and numerical results are presented which may help in the selection of an optimum redan design. 3 refs., 7 figs

  2. A new balance-of-plant model for the SASSYS-1 LMR systems analysis code

    International Nuclear Information System (INIS)

    Briggs, L.L.

    1991-01-01

    In this paper, a balance-of-plant model is developed for the SASSYS code. This model represents the balance of plant as a network of components. It interfaces with the existing SASSYS code through the water side of the steam generator. The network representation provides a discretization of the mass, momentum, and energy equations and the equation of state and allows a simultaneous solution for the changes in pressure, flow, and enthalpy throughout the waterside system. The model has been tested for several types of transients and been found to perform both accurately and efficiently

  3. Time constants and transfer functions for a homogeneous 900 MWt metallic fueled LMR

    International Nuclear Information System (INIS)

    Grimm, K.N.; Meneghetti, D.

    1988-01-01

    Nodal transfer functions are calculated for a 900 MWt U10Zr-fueled sodium cooled reactor. From the transfer functions the time constants, feedback reactivity transfer function coefficients, and power coefficients can be determined. These quantities are calculated for core fuel, upper and lower axial reflector steel, radial blanket fuel, radial reflector steel, and B 4 C rod shaft expansion effect. The quantities are compared to the analogous quantities of a 60 MWt metallic-fueled sodium cooled Experimental Breeder Reactor II configuration. 8 refs., 2 figs., 6 tabs

  4. The role of internal and external control for mitigating or preventing LMR accidents

    International Nuclear Information System (INIS)

    Waltar, A.E.; Padilla, A.; Seeman, S.E.

    1987-01-01

    For the safety assessment of LMFBRs, much effort has been devoted to the analyses of LOF accident sequences with an emphasis on initiating-phase (IP) energetics (LOF-d-TOP event). Important knowledge and experiences on the IP energetics have been accumulated through reactor studies and in-pile experiment analyses, typically for the CABRI experiments. The present paper summarises the current understanding of key phenomenology relevant to the IP energetics based on the CABRI experiment analyses and the validation study for the PAPAS-2S, SAS3D and SAS4A codes. (author)

  5. Validation of detailed thermal hydraulic models used for LMR safety and for improvement of technical specifications

    Energy Technology Data Exchange (ETDEWEB)

    Dunn, F.E.

    1995-12-31

    Detailed steady-state and transient coolant temperatures and flow rates from an operating reactor have been used to validate the multiple pin model in the SASSYS-1 liquid metal reactor systems analysis code. This multiple pin capability can be used for explicit calculations of axial and lateral temperature distributions within individual subassemblies. Thermocouples at a number of axial locations and in a number of different coolant sub-channels m the XXO9 instrumented subassembly in the EBR-II reactor provided temperature data from the Shutdown Heat Removal Test (SHRT) series. Flow meter data for XXO9 and for the overall system are also available from these tests. Results of consistent SASSYS-1 multiple pin analyses for both the SHRT-45 loss-of-flow-without-scram-test and the S14RT-17 protected loss-of-flow test agree well with the experimental data, providing validation of the SASSYS-1 code over a wide range of conditions.

  6. LMR design concepts for transuranic management in low sodium void worth cores

    International Nuclear Information System (INIS)

    Hill, R.N.

    1991-01-01

    The fuel cycle processing techniques and hard neutron spectrum of the integral Fast Reactor (IFR) metal fuel cycle have favorable characteristics for the management of transuranics; and the wide range of breeding characteristics available in metal fuelled cores provides for flexibility in transuranic management strategy. Previous studies indicate that most design options which decrease the breeding ratio also allow a decrease in sodium void worth; therefore, low void worths are achievable in transuranic burning (low breeding ratio) core designs. This paper describes numerous trade studies assessing various design options for a low void worth transuranic burner core. A flat annular core design appears to be a promising concept; the high leakage geometry yields a low breeding ratio and small sodium void worth. To allow flexibility in breeding characteristics, alternate design options which achieve fissile self-sufficiency are also evaluated. A self-sufficient core design which is interchangeable with the burner core and maintains a low sodium void worth is developed. (author)

  7. Development for LMR coolant technology - Development of a submersible-in-pool electromagnetic pump

    Energy Technology Data Exchange (ETDEWEB)

    Hong, Sang Hee; Kim, Hee Reyoung; Lee, Sang Don; Seo, Chun Ho [Seoul National University, Seoul (Korea, Republic of); Cho, Su Won [Kyungki University, Suwon (Korea, Republic of)

    1995-08-01

    The conceptual and detailed designs of an annular linear induction electromagnetic pump of small scale submersible-in-pool type are performed for the purpose of domestic development of the pumps used for the high-temperature natrium coolant transportation in liquid metal reactors. The pump drawings for and input power of 1,100 VA, an input frequency of 17 Hz, a maximum flowrate of 60 l/min and a maximum operation temperature of 600 deg C are obtained from the optimum design analyses by solving MHD and equivalent circuit equations. The characteristics of pump materials in the high temperature and neutron irradiation environment are reflected in designing the pump, and theoretical analyses for improving the pump performance and efficiency are tried through calculations of magnetic flux and temperature distributions inside the pump. The present project contributes to the further design of engineering proto-type electromagnetic pump with higher capacity and the development of liquid metal reactor with innovative simplicity. 44 refs., 4 tabs., 33 figs. (author)

  8. Identification of passive shutdown system parameters in a metal fueled LMR

    International Nuclear Information System (INIS)

    Vilim, R.B.

    1992-01-01

    This document discusses periodic testing of the passive shutdown system in a metal fueled liquid metal reactor which has been proposed as a Technical Specification requirement. In the approach to testing considered in this paper, perturbation experiments performed at normal operation are used to predict an envelope that bounds reactor response to flowrate, inlet temperature and external reactivity forcing functions. When the envelope for specific upsets lies within safety limits, one concludes that the passive shutdown system is operation properly for those upsets. Simulation results for the EBR-II reactor show that the response envelope for loss of flow and rod reactivity insertion events does indeed bound these events

  9. Techniques for computing reactivity changes caused by fuel axial expansion in LMR's

    International Nuclear Information System (INIS)

    Khalil, H.

    1988-01-01

    An evaluation is made of the accuracy of methods used to compute reactivity changes caused by axial fuel relocation in fast reactors. Results are presented to demonstrate the validity of assumptions commonly made such as linearity of reactivity with fuel elongation, additivity of local reactivity contributions, and the adequacy of standard perturbation techniques. Accurate prediction of the reactivity loss caused by axial swelling of metallic fuel is shown to require proper representation of the burnup dependence of the expansion reactivity. Some accuracy limitations in the methods used in transient analyses, which are based on the use of fuel worth tables, are identified, and efficient ways to improve accuracy are described. Implementation of these corrections produced expansion reactivity estimates within 5% of higher-order method for a metal-fueled FFTF core representation. 18 refs., 3 figs., 3 tabs

  10. Development of thermohydraulic codes for modeling liquid metal boiling in LMR fuel subassemblies

    International Nuclear Information System (INIS)

    Sorokin, G.A.; Avdeev, E.F.; Zhukov, A.V.; Bogoslovskaya, G.P.; Sorokin, A.P.

    2000-01-01

    An investigation into the reactor core accident cooling, which are associated with the power grow up or switch off circulation pumps in the event of the protective equipment comes into action, results in the problem of liquid metal boiling heat transfer. Considerable study has been given over the last 30 years to alkaline metal boiling including researches of heat transfer, boiling patterns, hydraulic resistance, crisis of heat transfer, initial heating up, boiling onset and instability of boiling. The results of these investigations have shown that the process of liquid metal boiling has substantial features in comparison with water boiling. Mathematical modeling of two phase flows in fast reactor fuel subassemblies have been developed intensively. Significant success has been achieved in formulation of two phase flow through the pin bundle and in their numerical realization. Currently a set of codes for thermohydraulic analysis of two phase flows in fast reactor subassembly have been developed with 3D macrotransfer governing equations. These codes are used for analysis of boiling onset and liquid metals boiling in fuel subassemblies during loss-of-coolant accidents, of warming up of reactor core, of blockage of some part of flow cross section in fuel subassembly. (author)

  11. Test results of sodium-water reaction testing in near prototypical LMR steam generator

    International Nuclear Information System (INIS)

    Boardman, C.E.; Hui, M.; Neely, H.H.

    1990-01-01

    An extensive test program has been performed in the United States to investigate the effects of large sodium-water reaction events in LMFBR steam generators. Tests were conducted in the Large Leak Test Rig (LLTR) located at the Energy Technology Engineering Center (ETEC). The program was divided into two phases, Series I and Series II, for the purpose of satisfying near-term and long-term needs. Series II was further subdivided into large and intermediate leak tests. This paper will emphasize the Series II intermediate leak tests and resulting conclusions for steam generator design and operation. 11 figs, 2 tabs

  12. Development of remote disassembly technology for liquid-metal reactor (LMR) fuel

    International Nuclear Information System (INIS)

    Bradley, E.C.; Evans, J.H.; Metz, C.F. III; Weil, B.S.

    1990-01-01

    A major objective of the Consolidated Fuel Reprocessing Program (CFRP) is to develop equipment and demonstrate technology to reprocess fast breeder reactor fuel. Experimental work on fuel disassembly cutting methods began in the 1970s. High-power laser cutting was selected as the preferred cutting method for fuel disassembly. Remotely operated development equipment was designed, fabricated, installed, and tested at Oak Ridge National Laboratory (ORNL). Development testing included remote automatic operation, remote maintenance testing, and laser cutting process development. This paper summarizes the development work performed at ORNL on remote fuel disassembly. 2 refs., 1 fig

  13. Verification and implications of the multiple pin treatment in the SASSYS-1 LMR systems analysis code

    International Nuclear Information System (INIS)

    Dunn, F.E.

    1994-01-01

    As part of a program to obtain realistic, as opposed to excessively conservative, analysis of reactor transients, a multiple pin treatment for the analysis of intra-subassembly thermal hydraulics has been included in the SASSYS-1 liquid metal reactor systems analysis code. This new treatment has made possible a whole new level of verification for the code. The code can now predict the steady-state and transient responses of individual thermocouples within instrumented subassemlies in a reactor, rather than just predicting average temperatures for a subassembly. Very good agreement has been achieved between code predictions and the experimental measurements of steady-state and transient temperatures and flow rates in the Shutdown Heat Removal Tests in the EBR-II Reactor. Detailed multiple pin calculations for blanket subassemblies in the EBR-II reactor demonstrate that the actual steady-state and transient peak temperatures in these subassemblies are significantly lower than those that would be calculated by simpler models

  14. Real-time LMR control parameter generation using advanced adaptive synthesis

    International Nuclear Information System (INIS)

    King, R.W.; Mott, J.E.

    1990-01-01

    The reactor ''delta T'', the difference between the average core inlet and outlet temperatures, for the liquid-sodium-cooled Experimental Breeder Reactor 2 is empirically synthesized in real time from, a multitude of examples of past reactor operation. The real-time empirical synthesis is based on reactor operation. The real-time empirical synthesis is based on system state analysis (SSA) technology embodied in software on the EBR 2 data acquisition computer. Before the real-time system is put into operation, a selection of reactor plant measurements is made which is predictable over long periods encompassing plant shutdowns, core reconfigurations, core load changes, and plant startups. A serial data link to a personal computer containing SSA software allows the rapid verification of the predictability of these plant measurements via graphical means. After the selection is made, the real-time synthesis provides a fault-tolerant estimate of the reactor delta T accurate to +/-1%. 5 refs., 7 figs

  15. Development of Fluid and I and C Systems Design Technology for LMR

    International Nuclear Information System (INIS)

    Kim, Seong O; Sim, Y. S.; Choi, S. K.; Kim, E. K.; Wi, M. H.; Eho, J. H.; Hur, S.; Seong, S. H.; Kim, S. Y.; Jeon, W. D.

    2005-03-01

    The basic concept of fluid and I and C system of KALIMER-600 was developed and the computer codes required to materialize system concept were also implemented through the R and D program. Based on the analysis results of the design characteristics for the similar reactor types developed in a foreign country, the system design technologies with adoption of the innovative ideas were developed. With the development, expansion and reinforcement of the methodologies required according to the progress of development and design of the system and the experimental verification of the developed computer code, the excellent and innovative outcomes were produced

  16. Sodium spray and jet fire model development within the CONTAIN-LMR code

    International Nuclear Information System (INIS)

    Scholtyssek, W.

    1993-01-01

    An assessment was made of the sodium spray fire model implemented in the CONTAIN code. The original droplet burn model, which was based on the NACOM code, was improved in several aspects, especially concerning evaluation of the droplet burning rate, reaction chemistry and heat balance, spray geometry and droplet motion, and consistency with CONTAIN standards of gas property evaluation. An additional droplet burning model based on a proposal by Krolikowski was made available to include the effect of the chemical equilibrium conditions at the flame temperature. The models were validated against single-droplet burn experiments as well as spray and jet fire experiments. Reasonable agreement was found between the two burn models and experimental data. When the gas temperature in the burning compartment reaches high values, the Krolikowski model seems to be preferable. Critical parameters for spray fire evaluation were found to be the spray characterization, especially the droplet size, which largely determines the burning efficiency, and heat transfer conditions at the interface between the atmosphere and structures, which controls the thermal hydraulic behavior in the burn compartment

  17. Analysis of long-term DHR System Performance for a LMR

    International Nuclear Information System (INIS)

    Burgazzi, Luciano

    2012-01-01

    Conclusions: • The demonstration of the «Non credibility» of the situation related to the long - term loss of DHR function is organized through: – Probabilistic assessment approach; – Demonstration of negligible risk; – Probabilistic goals. • Results show the inadequacy of design measures to meet the safety requirement of 10 -7 /reactor year: – System redundancies and configuration. • Results subject to the assumptions taken in the analysis: – Lack of statistically reliable data for LMRs; – Level of definition of the systems, which are not yet established; – Conservative value of the frequency of the initiator, corresponding to the normal shutdown. • Results show the relevance of CCFs; • Other provisions that could justify the “practical elimination”: – Diversification of components to cope with CCFs; – DHR function through vault cooling

  18. An analysis of multiple particle settling for LMR backup shutdown systems

    International Nuclear Information System (INIS)

    Brock, R.W.

    1992-05-01

    Backup shutdown systems proposed for future LMRs may employ discreet absorber particles to provide the negative reactivity insertion. When actuated, these systems release a dense packing of particles from an out-of-core region to settle into an in-core region. The multiple particle settling behavior is analyzed by the method of continuity waves. This method provides predictions of the dynamic response of the system including the average particle velocity and volume fraction of particles vs. time. Although hindered settling problems have been previously analyzed using continuity wave theory, this application represents an extension of the theory to conditions of unrestrained settling. Typical cases are analyzed and numerical results are calculated based on a semi-empirical drift-flux model. For 1/4-inch diameter boron-carbide particles in hot liquid sodium, the unrestrained settling problem assumes a steady-state solution when the average volume fraction of particles is 0.295 and the average particle velocity is 26.0 cm/s

  19. Multi dimensional analysis of Design Basis Events using MARS-LMR

    International Nuclear Information System (INIS)

    Woo, Seung Min; Chang, Soon Heung

    2012-01-01

    Highlights: ► The one dimensional analyzed sodium hot pool is modified to a three dimensional node system, because the one dimensional analysis cannot represent the phenomena of the inside pool of a big size pool with many compositions. ► The results of the multi-dimensional analysis compared with the one dimensional analysis results in normal operation, TOP (Transient of Over Power), LOF (Loss of Flow), and LOHS (Loss of Heat Sink) conditions. ► The difference of the sodium flow pattern due to structure effect in the hot pool and mass flow rates in the core lead the different sodium temperature and temperature history under transient condition. - Abstract: KALIMER-600 (Korea Advanced Liquid Metal Reactor), which is a pool type SFR (Sodium-cooled Fast Reactor), was developed by KAERI (Korea Atomic Energy Research Institute). DBE (Design Basis Events) for KALIMER-600 has been analyzed in the one dimension. In this study, the one dimensional analyzed sodium hot pool is modified to a three dimensional node system, because the one dimensional analysis cannot represent the phenomena of the inside pool of a big size pool with many compositions, such as UIS (Upper Internal Structure), IHX (Intermediate Heat eXchanger), DHX (Decay Heat eXchanger), and pump. The results of the multi-dimensional analysis compared with the one dimensional analysis results in normal operation, TOP (Transient of Over Power), LOF (Loss of Flow), and LOHS (Loss of Heat Sink) conditions. First, the results in normal operation condition show the good agreement between the one and multi-dimensional analysis. However, according to the sodium temperatures of the core inlet, outlet, the fuel central line, cladding and PDRC (Passive Decay heat Removal Circuit), the temperatures of the one dimensional analysis are generally higher than the multi-dimensional analysis in conditions except the normal operation state, and the PDRC operation time in the one dimensional analysis is generally longer than the multi-dimensional analysis. In particular, we can see the reverse and mixing flow phenomena in LOHS better than TOP and LOF, which affect the peak temperature in the one dimensional analysis at 330 s but is not observed in the multi-dimensional analysis. In addition, the different temperatures at the central line of fuel and cladding are shown due to different mass flow in the core. The two PDRCs show the almost same results in one and multi-dimensional analysis, respectively. However, in the comparison between the one and multi-dimension, the heat removal capability of PDRC in the multi-dimensional analysis is better than the one dimensional analysis at the beginning of calculation. The aspects change at the ending of calculation due to the different mass flow in PDRC and over flow sodium temperature. In wrap up, the sodium temperatures of the core in the one dimensional analysis are generally higher than the multidimensional analysis. The temperature peak point in the one dimensional analysis under LOHS does not show in the multi-dimensional analysis, because the reverse and mixing flow pattern between the hot pool and the core outlet region. Even thought there are some different results between the two different dimensional analyses, we can say that the KALIMER-600 system has the safety margins.

  20. A new balance-of-plant model for the SASSYS-1 LMR systems analysis code

    International Nuclear Information System (INIS)

    Briggs, L.L.

    1989-01-01

    A balance-of-plant model has been added to the SASSYS-1 liquid metal reactor systems analysis code. Until this addition, the only waterside component which SASSYS-1 could explicitly model was the water side of a steam generator, with the remainder of the water side represented by boundary conditions on the steam generator. The balance-of-plant model is based on the model used for the sodium side of the plant. It will handle subcooled liquid water, superheated steam, and saturated two-phase fluid. With the exception of heated flow paths in heaters, the model assumes adiabatic conditions along flow paths; this assumption simplifies the solution procedure while introducing very little error for a wide range of reactor plant problems. Only adiabatic flow is discussed in this report. 3 refs., 4 figs

  1. Advanced reactor development: The LMR integral fast reactor program at Argonne

    International Nuclear Information System (INIS)

    Till, C.E.

    1990-01-01

    Reactor technology for the 21st Century must develop with characteristics that can now be seen to be important for the future, quite different from the things when the fundamental materials and design choices for present reactors were made in the 1950s. Argonne National Laboratory, since 1984, has been developing the Integral Fast Reactor (IFR). This paper will describe the way in which this new reactor concept came about; the technical, public acceptance, and environmental issues that are addressed by the IFR; the technical progress that has been made; and our expectations for this program in the near term. 3 figs

  2. Safety aspects of the US advanced LMR [liquid metal reactor] design

    International Nuclear Information System (INIS)

    Pedersen, D.R.; Gyorey, G.L.; Marchaterre, J.F.; Rosen, S.

    1989-01-01

    The cornerstones of the United States Advanced Liquid Metal Cooled Reactor (ALMR) program sponsored by the Department of Energy are: the plant design program at General Electric based on the PRISM (Power Reactor Innovative Small Module) concept, and the Integral Fast Reactor program (IFR) at Argonne National Laboratory (ANL). The goal of the US program is to produce a standard, commercial ALMR, including the associated fuel cycle. This paper discusses the US regulatory framework for design of an ALMR, safety aspects of the IFR program at ANL, the IFR fuel cycle and actinide recycle, and the ALMR plant design program at GE. 6 refs., 5 figs

  3. An improved numerical model for the investigation of thermal hydraulic phenomena with applications to LMR reactor components

    International Nuclear Information System (INIS)

    Chan, B.C.; Kennett, R.J.; Van Tuyle, G.J.

    1992-01-01

    A basic limited scope, fast-running computer model is presented for the solution of single phase two-dimensional transients in thermally coupled incompressible fluid flow problems. The governing equations and the two-equation transport model (k-ε) of turbulence are reduced to a set of linear algebraic equations in an implicit finite difference scheme, based on the control volume approach. These equations are solved iteratively in a line-by-line procedure using the tri-diagonal matrix algorithm. The numerical formulation and general calculational procedure are described in detail. The calculations show good agreement when compared with experimental data and other independent analyses

  4. Software safety analysis techniques for developing safety critical software in the digital protection system of the LMR

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Jang Soo; Cheon, Se Woo; Kim, Chang Hoi; Sim, Yun Sub

    2001-02-01

    This report has described the software safety analysis techniques and the engineering guidelines for developing safety critical software to identify the state of the art in this field and to give the software safety engineer a trail map between the code and standards layer and the design methodology and documents layer. We have surveyed the management aspects of software safety activities during the software lifecycle in order to improve the safety. After identifying the conventional safety analysis techniques for systems, we have surveyed in details the software safety analysis techniques, software FMEA(Failure Mode and Effects Analysis), software HAZOP(Hazard and Operability Analysis), and software FTA(Fault Tree Analysis). We have also surveyed the state of the art in the software reliability assessment techniques. The most important results from the reliability techniques are not the specific probability numbers generated, but the insights into the risk importance of software features. To defend against potential common-mode failures, high quality, defense-in-depth, and diversity are considered to be key elements in digital I and C system design. To minimize the possibility of CMFs and thus increase the plant reliability, we have provided D-in-D and D analysis guidelines.

  5. Software safety analysis techniques for developing safety critical software in the digital protection system of the LMR

    International Nuclear Information System (INIS)

    Lee, Jang Soo; Cheon, Se Woo; Kim, Chang Hoi; Sim, Yun Sub

    2001-02-01

    This report has described the software safety analysis techniques and the engineering guidelines for developing safety critical software to identify the state of the art in this field and to give the software safety engineer a trail map between the code and standards layer and the design methodology and documents layer. We have surveyed the management aspects of software safety activities during the software lifecycle in order to improve the safety. After identifying the conventional safety analysis techniques for systems, we have surveyed in details the software safety analysis techniques, software FMEA(Failure Mode and Effects Analysis), software HAZOP(Hazard and Operability Analysis), and software FTA(Fault Tree Analysis). We have also surveyed the state of the art in the software reliability assessment techniques. The most important results from the reliability techniques are not the specific probability numbers generated, but the insights into the risk importance of software features. To defend against potential common-mode failures, high quality, defense-in-depth, and diversity are considered to be key elements in digital I and C system design. To minimize the possibility of CMFs and thus increase the plant reliability, we have provided D-in-D and D analysis guidelines

  6. Vibration and acoustic signatures of the water circulation pump in the pressurised LMR fuel element test loop at IPEN

    International Nuclear Information System (INIS)

    Holland, L.

    1985-01-01

    This report presents results of vibration and acoustic field measurements made on the water circulating pump in the IPEN - CNEN/Sao Paulo pressurised water loop. The use of such measurements to monitor the vibration of coolant circulating pumps of light water reactors is indicated. Measurements were made for defined water flows and pressures varying between 5 bar/5.22 ls sup(-1) and 40 bar/17,42ls sup(-1). Analyses of various recordings of two accelerometer signals and 1 microphone signal were made principally in the frequency range 0-5 KHz using a Nicolet 660 A Fourier analyser. Results of these analyses indicate that CPSD distributions might be more sensitive indicators of changes in pump operating conditions than the more frequently used PSD distributions. In addition, as an indicador of changing pump conditions the acoustic-vibration signal pair is perhaps a more sensitive indicator than the vibration-vibration signal pair. While coherence distributions are elearly sensitive to changing pump conditions, trends in the change of these distributions were not readily identified. It is recommended that more detailed analyses be made using pattern recognition techniques in conjunction with frequency zooming. (Author) [pt

  7. Irradiation creep and void swelling of two LMR heats of HT9 at ∝400 C and 165 dpa

    International Nuclear Information System (INIS)

    Toloczko, M.B.; Garner, F.A.

    1996-01-01

    Two nominally identical heats of HT9 ferritic-martensitic steel were produced, fabricated into pressurized tubes, and then irradiated in FFTF, using identical procedures. After reaching 165 dpa at ∝400 C, small differences in strains associated with both phase-related changes in lattice parameter and void swelling were observed in comparing the two heats. The creep strains, while different, exhibited the same functional dependence on swelling behavior. The derived creep coefficients, the one associated with creep in the absence of swelling and the one directly responsive to swelling, were essentially identical for the two heats. Even more significantly, the creep coefficients for this bcc ferritic-martensitic steel appear to be very similar and possibly identical to those routinely derived from creep experiments on fcc austenitic steels. (orig.)

  8. PERBANDINGAN APLIKASI EKSTRAK SEREH DAPUR DAN ESTRAK SEREH WANGI TERHADAP RADANG MUKOSA MULUT (Penelitian Laboratorik pada Tikus Wistar Strain LMR

    Directory of Open Access Journals (Sweden)

    Mindya Juniastuti

    2015-07-01

    Full Text Available Inflammation is one of the body's defence mechanism against irritants, infectious agents, and injury. During its process, pain, swelling, redness, and other discomforts also occur as cardinal signs of inflammation. Therefore, people seek for medicine to encounter those effects. Sereh is one of the herb plants which have anti inflammatory effect. However, effect of Sereh on inglamed oral mucosa has not been clinically examined. The aim of this research is to examine and to compare the influence of Sered Dapur (Cymbopogon citratus and Sereh Wangi (Cymbopogon winterianus lowitt extract on inflamed oral mucous induced by Hydrogen Peroxide 10%. Thirteen Wistar rats were used in this research and divided four groups, control group I (3 rats, control group II (3 rats, Sereh Dapur extract groups (4 rats and Sereh Wangi extract groups (3 rats. All rats in Sereh Dapur, Sereh Wangi and control II groups received 3x10 minutes application of Hydrogen Peroxide 10% on their vestibulum for 3 days, while rats in control gorup I received application of Aquadest. On the 4th day, all groups that received Hydrogen Peroxide 10% were application 3x5 minutes for 3 days for each substance. After rats have been killed their oral mucosa were processed and examine under microscope. Statistical result shows there are differences on oral mucous reaction between Sereh Dapur and Sereh Wangi extract with control group. Based on the research result, it can be concluded that both Sereh Dapur and Sereh Wangi can reduce oral mucous inlammation and Sereh Dapur is more effective than Sereh Wangi in reducing the oral mucous inflammation induced by Hydrogen Peroxide 10%.

  9. Development of LMR basic design technology - Development of 3-D multi-group nodal kinetics code for liquid metal reactors

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Myung Hyun [Kyunghee University, Seoul (Korea, Republic of)

    1996-07-01

    A development project of 3-dimensional kinetics code for ALMR has three level of works. In the first level, a multi-group, nodal kinetics code for the HEX-Z geometry has been developed. A code showed very good results for the static analysis as well as for the kinetics problems. At the second level, a core thermal-hydraulic analysis code was developed for the temperature feedback calculation in ALMR transients analysis. This code is coupled with kinetics code. A sodium property table was programmed and tested to the KAERI data and thermal feedback model was developed and coupled in code. Benchmarking of T/H calculation has been performed and showed fairly good results. At the third level of research work, reactivity feedback model for structure thermal expansion is developed and added to the code. At present, basic model was studied. However, code development in now on going. Benchmarking of this model developed can not be done because of lack of data. 31 refs., 17 tabs., 38 figs. (author)

  10. A new balance-of-plant model for the SASSYS-1 LMR [liquid metal reactor] systems analysis code

    International Nuclear Information System (INIS)

    Briggs, L.L.

    1989-01-01

    A balance-of-plant (BOP) model has been developed for use within the SASSYS-1 liquid-metal reactor systems analysis code. This model expands the scope of SASSYS-1 so that the code can explicitly model the waterside components of a nuclear power plant; previously, only the water side of the steam generators could be modeled, with the remainder of the water side represented by boundary conditions on the steam generator. The model represents the BOP a set of flow paths and path junctions; the mass and energy equations are solved at the junctions, and the momentum equation is solved along the flow paths. The junctions are thus mass and energy cells, and the paths are momentum cells. The various waterside component models (pumps, valves, etc.) are specialized types of energy or momentum cells, as appropriate. The solution scheme implicitly couples the energy cells through the momentum cells and solves simultaneously for pressures and enthalpies within the energy cells and for flows within the momentum cells

  11. Irradiation creep and void swelling of two LMR heat of HT9 at ∼400 degrees C and 165 dpa

    International Nuclear Information System (INIS)

    Toloczko, M.B.; Garner, F.A.

    1996-01-01

    Two nominally identical heats of HT9 ferritic-martensitic steel were produced, fabricated into pressurized tubes, and then irradiated in FFTF, using identical procedures. After reaching 165 dpa at ∼400C, small differences in strains associated with both phase-related change in lattice parameter and void swelling were observed in comparing the two heats. The creep strains, while different, exhibited the same functional relationship to the swelling behavior. The derived creep coefficients, the one associated with creep in the absence of swelling and the one directly responsive to swelling, were essentially identical for the two heats. Even more significantly, the creep coefficients for this bcc ferritic-martensitic steel appear to be very similar and possibly identical to those routinely derived from creep experiments on fcc austenitic steels

  12. Overview of the ANL advanced LMR system thermal-hydraulic test program supporting both GE/PRISM and RI/SAFR

    International Nuclear Information System (INIS)

    Oras, J.J.; Kuzay, T.M.; Kasza, K.E.

    1988-01-01

    Descriptions of the ANL thermal-hydraulic water models of both the PRISM and SAFR reactors are presented, together with results from Phases I and II of the thermal-hydraulic test program. Phenomena discovered during these tests and modeling results are presented. Overall, these efforts demonstrate the acceptable thermal-hydraulic performance of both the PRISM and SAFR concepts

  13. Development of a graphical user interface allowing use of the SASSYS LMR systems analysis code as an EBR-II interactive simulator

    International Nuclear Information System (INIS)

    Garner, P.L.; Briggs, L.L.; Gross, K.C.; Ku, J.Y.; Staffon, J.D.

    1994-01-01

    The SASSYS computer program for safety analyses of liquid-metal- cooled fast reactors has been adapted for use as the simulation engine under the graphical user interface provided by the GRAFUN and HIST programs and the Data Views software package under the X Window System on UNIX-based computer workstations to provide a high fidelity, real-time, interactive simulator of the Experimental Breeder Reactor Number II (EBR-II) plant. In addition to providing analysts with an interactive way of performing safety case studies, the simulator can be used to investigate new control room technologies and to supplement current operator training

  14. Implementation, verification, and validation of the FPIN2 metal fuel pin mechanics model in the SASSYS/SAS4A LMR transient analysis codes

    International Nuclear Information System (INIS)

    Sofu, T.; Kramer, J.M.

    1994-01-01

    The metal fuel version of the FPIN2 code which provides a validated pin mechanics model is coupled with SASSYS/SAS4A Version 3.0 for single pin calculations. In this implementation, SASSY/SAS4A provides pin temperatures, and FPIN2 performs analysis of pin deformation and predicts the time and location of cladding failure. FPIN2 results are also used for the estimates of axial expansion of fuel and associated reactivity effects. The revalidation of the integrated SAS-FPIN2 code system is performed using TREAT tests

  15. Li- and Mn-Rich Cathode Materials: Challenges to Commercialization

    Energy Technology Data Exchange (ETDEWEB)

    Zheng, Jianming [Energy and Environmental Directorate, Pacific Northwest National Laboratory, 902 Battelle Boulevard Richland WA 99354 USA; Myeong, Seungjun [School of Energy and Chemical Engineering, Green Energy Materials Development Center, Ulsan National Institute of Science and Technology (UNIST), Korea 689-798; Cho, Woongrae [School of Energy and Chemical Engineering, Green Energy Materials Development Center, Ulsan National Institute of Science and Technology (UNIST), Korea 689-798; Yan, Pengfei [Environmental Molecular Sciences Laboratory, Pacific Northwest National Laboratory, 902 Battelle Boulevard Richland WA 99354 USA; Xiao, Jie [Energy and Environmental Directorate, Pacific Northwest National Laboratory, 902 Battelle Boulevard Richland WA 99354 USA; Wang, Chongmin [Environmental Molecular Sciences Laboratory, Pacific Northwest National Laboratory, 902 Battelle Boulevard Richland WA 99354 USA; Cho, Jaephil [School of Energy and Chemical Engineering, Green Energy Materials Development Center, Ulsan National Institute of Science and Technology (UNIST), Korea 689-798; Zhang, Ji-Guang [Energy and Environmental Directorate, Pacific Northwest National Laboratory, 902 Battelle Boulevard Richland WA 99354 USA

    2016-12-14

    The lithium- and manganese-rich (LMR) layered structure cathode exhibit one of the highest specific energy (~900 Wh kg-1) among all the cathode materials. However, the practical applications of LMR cathodes are still hindered by several significant challenges including voltage fade, large initial capacity loss, poor rate capability and limited cycle life. Herein, we review the recent progresses and understandings on the application of LMR cathode materials from practical point of view. Several key parameters of LMR cathodes that affect the LMR/graphite full cell operation are systematically analysed. These factors include the first cycle capacity loss, voltage fade, powder tap density, electrode density of LMR based cathode etc. New approaches to minimize the detrimental effect of these factors are highlighted in this work. We also provided the perspectives for the future research on LMR cathode materials, focusing on addressing the fundamental problems of LMR cathodes while always keeping practical considerations in mind.

  16. 77 FR 9625 - Presentation of Final Conventional Conformance Test Criteria and Common Air Interface (CAI...

    Science.gov (United States)

    2012-02-17

    ... components of a land mobile radio (LMR) system. LMR systems are commonly used by emergency responders in portable handheld and mobile vehicle-mounted devices. Although formal standards are being developed, no process is currently in place to confirm that LMR equipment advertised as P25-compliant meets all aspects...

  17. Prognostic significance of the lymphocyte-to-monocyte ratio in patients with metastatic colorectal cancer.

    Science.gov (United States)

    Shibutani, Masatsune; Maeda, Kiyoshi; Nagahara, Hisashi; Ohtani, Hiroshi; Sakurai, Katsunobu; Yamazoe, Sadaaki; Kimura, Kenjiro; Toyokawa, Takahiro; Amano, Ryosuke; Tanaka, Hiroaki; Muguruma, Kazuya; Hirakawa, Kosei

    2015-09-14

    To evaluate the prognostic significance of the lymphocyte to monocyte ratio (LMR) in patients with unresectable metastatic colorectal cancer who received palliative chemotherapy. A total of 104 patients with unresectable metastatic colorectal cancer who underwent palliative chemotherapy were enrolled. The LMR was calculated from blood samples by dividing the absolute lymphocyte count by the absolute monocyte count. Pre-treatment LMR values were measured within one week before the initiation of chemotherapy, while post-treatment LMR values were measured eight weeks after the initiation of chemotherapy. The median pre-treatment LMR was 4.16 (range: 0.58-14.06). We set 3.38 as the cut-off level based on the receiver operating characteristic curve. Based on the cut-off level of 3.38, 66 patients were classified into the high pre-treatment LMR group and 38 patients were classified into the low pre-treatment LMR group. The low pre-treatment LMR group had a significantly worse overall survival rate (P = 0.0011). Moreover, patients who demonstrated low pre-treatment LMR and normalization after treatment exhibited a better overall survival rate than the patients with low pre-treatment and post-treatment LMR values. The lymphocyte to monocyte ratio is a useful prognostic marker in patients with unresectable metastatic colorectal cancer who receive palliative chemotherapy.

  18. Development of self-calibration techniques for on-wafer and fixtured measurements: a novel approach

    OpenAIRE

    Pradell i Cara, Lluís; Purroy Martín, Francesc; Cáceres, M.

    1992-01-01

    Network Analyzer self-calibration techniques - TRL, LMR, TAR- are developed, implemented and compared in several transmission media. A novel LMR (Line-Match-Reflect) technique based on known LINE and REFLECT Standards, is proposed and compared to conventional LMR (based on known LINE and MATCH Standards) and other techniques (TRL, TAR). They are applied to on-wafer S-parameter measurement as well as to coaxial, waveguide and microstrip media. Experimental results up to 40 GHz are presented. ...

  19. Development of fluid and I and C systems design technology

    International Nuclear Information System (INIS)

    Sim, Yoon Sub; Park, C. K.; Kim, S. O.

    2000-05-01

    LMR is the reactor type that makes utilization of uranium resource very efficiently and the necessity of construction of a LMR in 2020's has been raised. However, the design technology required for construction has not been secured domestically. To fulfill the necessity, study has been made for the LMR system design technology and conceptual design of KALIMER systems for fluid, instrumentation, control, and protection have been developed. Also the computer code systems for the design and analysis of the KALIMER fluid systems have been developed. These study results are to used as the starting point of the next phase LMR design technology development research

  20. Development of fluid and I and C systems design technology

    Energy Technology Data Exchange (ETDEWEB)

    Sim, Yoon Sub; Park, C. K.; Kim, S. O. [and others

    2000-05-01

    LMR is the reactor type that makes utilization of uranium resource very efficiently and the necessity of construction of a LMR in 2020's has been raised. However, the design technology required for construction has not been secured domestically. To fulfill the necessity, study has been made for the LMR system design technology and conceptual design of KALIMER systems for fluid, instrumentation, control, and protection have been developed. Also the computer code systems for the design and analysis of the KALIMER fluid systems have been developed. These study results are to used as the starting point of the next phase LMR design technology development research.

  1. Development of fluid and I and C systems design technology

    Energy Technology Data Exchange (ETDEWEB)

    Sim, Yoon Sub; Park, C K; Kim, S O [and others

    2000-05-01

    LMR is the reactor type that makes utilization of uranium resource very efficiently and the necessity of construction of a LMR in 2020's has been raised. However, the design technology required for construction has not been secured domestically. To fulfill the necessity, study has been made for the LMR system design technology and conceptual design of KALIMER systems for fluid, instrumentation, control, and protection have been developed. Also the computer code systems for the design and analysis of the KALIMER fluid systems have been developed. These study results are to used as the starting point of the next phase LMR design technology development research.

  2. Safety of next generation power reactors

    International Nuclear Information System (INIS)

    Anon.

    1988-01-01

    This book is organized under the following headings: Future needs of utilities regulators, government, and other energy users, PRA and reliability, LMR concepts, LWR design, Advanced reactor technology, What the industry can deliver: advanced LWRs, High temperature gas-cooled reactors, LMR whole-core experiments, Advanced LWR concepts, LWR technology, Forum: public perceptions, What the industry can deliver: LMRs and HTGRs, Criteria and licensing, LMR modeling, Light water reactor thermal-hydraulics, LMR technology, Working together to revitalize nuclear power, Appendix A, luncheon address, Appendix B, banquet address

  3. Baseline and Trend of Lymphocyte-to-Monocyte Ratio as Prognostic Factors in Epidermal Growth Factor Receptor Mutant Non-Small Cell Lung Cancer Patients Treated with First-Line Epidermal Growth Factor Receptor Tyrosine Kinase Inhibitors.

    Directory of Open Access Journals (Sweden)

    Yu-Mu Chen

    Full Text Available Patients with early-stage lung cancer who have a high baseline lymphocyte-to-monocyte ratio (LMR have a favorable prognosis. However, the prognostic significance of LMR in patients with advanced-stage EGFR-mutant non-small cell lung cancer (NSCLC receiving first-line epidermal growth factor receptor (EGFR-tyrosine kinase inhibitors (TKIs has not been established. We conducted a retrospective analysis to investigate the influence of LMR on clinical outcomes including progression-free survival (PFS and overall survival (OS in EGFR-mutant patients with NSCLC.Of 1310 lung cancer patients diagnosed between January 2011 and October 2013, 253 patients receiving first-line EGFR-TKIs for EGFR-mutant NSCLC were included. The cut-off values for baseline and the 1-month-to-baseline ratio of LMR (MBR, determined by using receiver operating characteristic curves, were 3.29 and 0.63, respectively. Patients were divided into 3 prognostic groups: high LMR and MBR, high LMR or MBR, and low LMR and MBR.The mean patient age was 65.2 years, and 41% were men. The median PFS and OS were 10.3 and 22.0 months, respectively. The PFS in patients with high LMR and MBR, high LMR or MBR, and low LMR and MBR were 15.4, 7.1, and 2.0 months, respectively (p < 0.001, whereas the OS were 32.6, 13.7, and 5.1 months, respectively (p < 0.001.A combination of baseline and trend of LMR can be used to identify patients with a high mortality risk in EGFR-mutant NSCLC patients receiving first-line EGFR-TKIs.

  4. Thermal-spectrum recriticality energetics

    International Nuclear Information System (INIS)

    Schwinkendorf, K.N.

    1993-12-01

    Large computer codes have been created in the past to predict the energy release in hypothetical core disruptive accidents (CDA), postulated to occur in liquid metal reactors (LMR). These codes, such as SIMMER, are highly specific to LMR designs. More recent attention has focused on thermal-spectrum criticality accidents, such as for fuel storage basins and waste tanks containing fissile material. This paper resents results from recent one-dimensional kinetics simulations, performed for a recriticality accident in a thermal spectrum. Reactivity insertion rates generally are smaller than in LMR CDAs, and the energetics generally are more benign. Parametric variation of input was performed, including reactivity insertion and initial temperature

  5. Local mesh refinement for incompressible fluid flow with free surfaces

    Energy Technology Data Exchange (ETDEWEB)

    Terasaka, H.; Kajiwara, H.; Ogura, K. [Tokyo Electric Power Company (Japan)] [and others

    1995-09-01

    A new local mesh refinement (LMR) technique has been developed and applied to incompressible fluid flows with free surface boundaries. The LMR method embeds patches of fine grid in arbitrary regions of interest. Hence, more accurate solutions can be obtained with a lower number of computational cells. This method is very suitable for the simulation of free surface movements because free surface flow problems generally require a finer computational grid to obtain adequate results. By using this technique, one can place finer grids only near the surfaces, and therefore greatly reduce the total number of cells and computational costs. This paper introduces LMR3D, a three-dimensional incompressible flow analysis code. Numerical examples calculated with the code demonstrate well the advantages of the LMR method.

  6. Status of fast reactor design technology development in Korea

    International Nuclear Information System (INIS)

    Dohee Hahn

    2000-01-01

    The LMR Design Technology Development Project was approved as a national long-term R and D program in 1992 by the Korea Atomic Energy Commission (KAEC) which decided to develop and construct a LMR with the goal of developing a LMR which can serve as a long term power supplier with competitive economics and enhanced safety. Based upon the KAEC decision, the Korea Atomic Energy Research Institute (KAERI) has been developing KALIMER (Korea Advanced Liquid Metal Reactor). According to the revised National Nuclear Energy Promotion Plan of June 1997, the basic design of KALIMER will be completed by 2006 and the possibility of construction will be considered sometime during the mid 2010s. Three year Phase 1 of the LMR Design Technology Development Project was completed in March 2000 and a preliminary conceptual design report has been issued. Conceptual design of KALIMER will be developed during the Phase 2 of the Project, which will last for two years. (author)

  7. Linear magnetoresistance and surface to bulk coupling in topological insulator thin films.

    Science.gov (United States)

    Singh, Sourabh; Gopal, R K; Sarkar, Jit; Pandey, Atul; Patel, Bhavesh G; Mitra, Chiranjib

    2017-12-20

    We explore the temperature dependent magnetoresistance of bulk insulating topological insulator thin films. Thin films of Bi 2 Se 2 Te and BiSbTeSe 1.6 were grown using the pulsed laser deposition technique and subjected to transport measurements. Magnetotransport measurements indicate a non-saturating linear magnetoresistance (LMR) behavior at high magnetic field values. We present a careful analysis to explain the origin of LMR taking into consideration all the existing models of LMR. Here we consider that the bulk insulating states and the metallic surface states constitute two parallel conduction channels. Invoking this, we were able to explain linear magnetoresistance behavior as a competition between these parallel channels. We observe that the cross-over field, where LMR sets in, decreases with increasing temperature. We propose that this cross-over field can be used phenomenologically to estimate the strength of surface to bulk coupling.

  8. Managing living marine resources in a dynamic environment: The role of seasonal to decadal climate forecasts

    Science.gov (United States)

    Tommasi, Desiree; Stock, Charles A.; Hobday, Alistair J.; Methot, Rick; Kaplan, Isaac C.; Eveson, J. Paige; Holsman, Kirstin; Miller, Timothy J.; Gaichas, Sarah; Gehlen, Marion; Pershing, Andrew; Vecchi, Gabriel A.; Msadek, Rym; Delworth, Tom; Eakin, C. Mark; Haltuch, Melissa A.; Séférian, Roland; Spillman, Claire M.; Hartog, Jason R.; Siedlecki, Samantha; Samhouri, Jameal F.; Muhling, Barbara; Asch, Rebecca G.; Pinsky, Malin L.; Saba, Vincent S.; Kapnick, Sarah B.; Gaitan, Carlos F.; Rykaczewski, Ryan R.; Alexander, Michael A.; Xue, Yan; Pegion, Kathleen V.; Lynch, Patrick; Payne, Mark R.; Kristiansen, Trond; Lehodey, Patrick; Werner, Francisco E.

    2017-03-01

    Recent developments in global dynamical climate prediction systems have allowed for skillful predictions of climate variables relevant to living marine resources (LMRs) at a scale useful to understanding and managing LMRs. Such predictions present opportunities for improved LMR management and industry operations, as well as new research avenues in fisheries science. LMRs respond to climate variability via changes in physiology and behavior. For species and systems where climate-fisheries links are well established, forecasted LMR responses can lead to anticipatory and more effective decisions, benefitting both managers and stakeholders. Here, we provide an overview of climate prediction systems and advances in seasonal to decadal prediction of marine-resource relevant environmental variables. We then describe a range of climate-sensitive LMR decisions that can be taken at lead-times of months to decades, before highlighting a range of pioneering case studies using climate predictions to inform LMR decisions. The success of these case studies suggests that many additional applications are possible. Progress, however, is limited by observational and modeling challenges. Priority developments include strengthening of the mechanistic linkages between climate and marine resource responses, development of LMR models able to explicitly represent such responses, integration of climate driven LMR dynamics in the multi-driver context within which marine resources exist, and improved prediction of ecosystem-relevant variables at the fine regional scales at which most marine resource decisions are made. While there are fundamental limits to predictability, continued advances in these areas have considerable potential to make LMR managers and industry decision more resilient to climate variability and help sustain valuable resources. Concerted dialog between scientists, LMR managers and industry is essential to realizing this potential.

  9. Structural design aspects of innovative designs under development in the current US Liquid Metal-Cooled Reactor program

    International Nuclear Information System (INIS)

    Seidensticker, R.W.

    1986-01-01

    The US Liquid Metal-Cooled Reactor (LMR) program has been restructured and is now focussed on the development of innovative plant designs which emphasize shorter construction times, increased use of passive, inherently safe features, cost-competitiveness with LWR plants, and minimization of safety-related systems. These changes have a considerable effect on the structural design aspects of the LMR plant. These structural problems and their solutions now under study form the main focus of this paper. (orig.)

  10. Fast Flux Test Facility: first three years of operation and future mission

    International Nuclear Information System (INIS)

    Peckinpaugh, C.L.; Newland, D.J.; Evans, E.A.

    1985-03-01

    In summary, the FFTF has proven to be a high performance, versatile test reactor. Results obtained during its first three years of operation - and those to be obtained in the coming years - are building a technology and experience base that is invaluable to future LMRs. The FFTF demonstrates proven LMR technology with a focus for the future and provides the US with international LMR technology leadership

  11. Liquid metal reactor development

    International Nuclear Information System (INIS)

    Cho, Man; Kim, Yeong Cheol; Kim, Shi Hwan; Choi, Yeong Myeong; Sho, Dong Seop; Kim, Yeong In; Park, Joo Hwan; Kim, Yeong Kyoon; Song, Hoon; Kim, Yeong In; Cho, Chang Yeon; Cho, Seok Hong; Lee, Dong Jin; Kim, Jong Sook; Jeon, Hyeong Ryeon; Kim, Jeong Do; Kim, Deok In; Lee, Ui Jin; Kil, Chung Seop; Choi, Yeong Rok; Moon, Kap Seok; Yoo, Bong; Lee, Hyeong Yeon; Seo, Uk Hwan; Lee, Jae Han; Park, Yeon Pyo; Nam, Ho Yoon; Kim, Yong Ik; Min, Byeong Tae; Choi, Seok Ki; Kim, Yoo Kon; Lee, Yong Beom; Hwang, Jong Seon; An, Do Hui; Kang, Hui Seok; Choi, Byeong Hae; Kang, Yeong Hwan; Ryoo, Uh Seok; Joo, Ki Nam; Kim, Dae Hwan; Ji, Shee Hwan; Park, Deok Keun; Kim, Seong Soo; Maeng, Wan Yeong; Park, Shee Jin; Kim, Yeong Seok; Jang, Moon Hui; Hong, Joon Hwa; Han, Jeong Ho; No, Kyee Ho; Park, Ji Yeon; Jeong, Yong Hwan; Lee, Deok Hyeon; Jeong, Chung Hwan; Cho, Shee Hyeon; Kim, Dong Hwa; Seong, Ki Ung; Lee, Ki Yeong; Kim, Ui Kwang; Hong, Sang Hee

    1993-05-01

    On this year the study was performed in two parts : The establishment of LMR development plan, and the development of LMR coolant technology 1. The establishment of LMR technologies, the domestic political and technical environment, economics and technical maturity were duly considered for comparative analysis. In this year technologies specific to LMRs and technologies common to both PWRs and LMRs were identified to understand the inter-relationships between those two categorized technologies. Including those two categories, an overall LMR technology tree was drawn up taking into consideration technologies and tasks necessary to the pool type design of the primary and secondary cooling systems. And technology options that should be thoroughly evaluated their comparative feasibilities and applicabilities in trade-off study were derived as a preliminary procedure for the selection of the reactor type. 2. The development of LMR coolant technology. Many relevant basic technologies should be developed for LMR to have the inherent safety characteristics and to be economical. Since the sodium(Na) being used as the coolant in LMR has several thermo-hydraulic characteristics differing from water, the sodium handling technique which provides the maximum utilization of the thermo-hydraulic merits of the sodium and the protection measures against its defects is one of the most important technologies for the development of LMR. In the present study many problems associated with the establishment of the technology for measuring and controlling the impurity in the Na-facility have been investigated. The conceptual design of the purity control system in the Na-facility and related purity control system have been also made. The test-run of the Na-loop facility constructed last year has been performed, which provided the technology necessary for operation and repair of the Na-facility

  12. Benchmark physics tests in the metallic-fuelled assembly ZPPR-15

    International Nuclear Information System (INIS)

    McFarlane, H.F.; Brumbach, S.B.; Carpenter, S.G.; Collins, P.J.

    1987-01-01

    In the last two years a shift in emphasis to inherent safety and economic competitiveness has led to a resurgence in US interest in metallic-alloy fuels for LMRs. Argonne National Laboratory initiated an extensive testing program for metallic-fuelled LMR technology that has included benchmark physics as one component. The tests done in the ZPPR-15 Program produced the first physics results in over 20 years for a metal-composition LMR core

  13. Patterns of fish diversity and assemblage structure and water quality in the longest Asian tropical river (Mekong)

    Science.gov (United States)

    Chea, R.; Lek, S.; Grenouillet, G.

    2016-12-01

    Although the Mekong River is one of the world's 35 biodiversity hotspots, the large-scale patterns of fish diversity and assemblage structure remain poorly addressed. The present study aimed to investigate the spatial variability of water quality in the Lower Mekong Basin and the fish distribution patterns in the Lower Mekong River (LMR) and to identify their environmental determinants. Daily fish catch data at 38 sites distributed along the LMR were related to 15 physicochemical and 19 climatic variables. As a result, four different clusters were defined according to the similarity in assemblage composition and 80 indicator species were identified. While fish species richness was highest in the Mekong delta and lowest in the upper part of the LMR, the diversity index was highest in the middle part of the LMR and lowest in the delta. We found that fish assemblages changed along the environmental gradients and that the main drivers affecting the fish assemblage structure were the seasonal variation of temperature, precipitation, dissolved oxygen, pH, and total phosphorus. Specifically, upstream assemblages were characterized by cyprinids and Pangasius catfish, well suited to low temperature, high dissolved oxygen and high pH. Fish assemblages in the delta were dominated by perch-like fish and clupeids, more tolerant to high temperatures, and high levels of nutrients (nitrates and total phosphorus) and salinity. Overall, the patterns were consistent between seasons. Our study contributes to establishing the first holistic fish community study in the LMR. Overall of the LMR water quality, we found that the water in the mainstream was less polluted than its tributaries; eutrophication and salinity could be key factors affecting water quality in LMR. Moreover, the seasonal variation of water quality seemed to be less marked than spatial variation occurring along the longitudinal gradient of Mekong River. Significant degradations were mainly associated with human

  14. Resistance to antibiotics in Lacid acid bacteria - strain Lactococcus

    Directory of Open Access Journals (Sweden)

    Filipić Brankica

    2015-01-01

    Full Text Available Lactic acid bacteria (LAB are widely used in the food industry, especially in the production of fermented dairy products and meat. The most studied species among Lis Lactococcus lactis. L. lactis strains are of great importance in the production of fermented dairy products such as yogurt, butter, fresh cheese and some kind of semi-hard cheese. Although L. lactis acquired the „Generally Regarded As Safe“ (GRAS status, many investigations indicated that lactococci may act as reservoirs of antibiotic resistance genes, which could be transferred to other bacterial species in human gastrointestinal tract includ­ing pathogens. The genome analysis of L. lactis indicated the presence of at least 40 putative drug transporter genes, and only four multidrug resistance (MDR transporters are functionally characterized: LmrA, LmrP, LmrCD i CmbT. LmrA is the first described MDR transporter in prokaryotes. LmrCD is responsible for resistance to cholate, which is an integral part of human bile and LmrCD is important for intestinal survival of lactococci that are used as probiotics. Secondary multidrug transporter LmrP confers resistance to lincosamides, macrolides, streptogramins and tetracyclines. CmbT protein has an effect on the host cell resistance to lincomycin, sulfadiazine, streptomycin, rifampicin, puromycin and sulfametox­azole. Since the food chain is an important way of transmitting resistance genes in human and animal population, it is of great importance to study the mechanisms of resistance in lactococci and other LAB, intended for the food industry. [Projekat Ministarstva nauke Republike Srbije, br. 173019: Izučavanje gena i molekularnih mehanizama u osnovi probiotičke aktivnosti bakterija mlečne kiseline izolovanih sa područja Zapadnog Balkana

  15. A wide reprogramming of histone H3 modifications during male meiosis I in rice is dependent on the Argonaute protein MEL1.

    Science.gov (United States)

    Liu, Hua; Nonomura, Ken-Ichi

    2016-10-01

    The roles of epigenetic mechanisms, including small-RNA-mediated silencing, in plant meiosis largely remain unclear, despite their importance in plant reproduction. This study unveiled that rice chromosomes are reprogrammed during the premeiosis-to-meiosis transition in pollen mother cells (PMCs). This large-scale meiotic chromosome reprogramming (LMR) continued throughout meiosis I, during which time H3K9 dimethylation (H3K9me2) was increased, and H3K9 acetylation and H3S10 phosphorylation were broadly decreased, with an accompanying immunostaining pattern shift of RNA polymerase II. LMR was dependent on the rice Argonaute protein, MEIOSIS ARRESTED AT LEPTOTENE1 (MEL1), which is specifically expressed in germ cells prior to meiosis, because LMR was severely diminished in mel1 mutant anthers. Pivotal meiotic events, such as pre-synaptic centromere association, DNA double-strand break initiation and synapsis of homologous chromosomes, were also disrupted in this mutant. Interestingly, and as opposed to the LMR loss in most chromosomal regions, aberrant meiotic protein loading and hypermethylation of H3K9 emerged on the nucleolar organizing region in the mel1 PMCs. These results suggest that MEL1 plays important roles in epigenetic LMR to promote faithful homologous recombination and synapsis during rice meiosis. © 2016. Published by The Company of Biologists Ltd.

  16. Linear Magnetoresistance in a Quasifree Two-Dimensional Electron Gas in an Ultrahigh Mobility GaAs Quantum Well.

    Science.gov (United States)

    Khouri, T; Zeitler, U; Reichl, C; Wegscheider, W; Hussey, N E; Wiedmann, S; Maan, J C

    2016-12-16

    We report a high-field magnetotransport study of an ultrahigh mobility (μ[over ¯]≈25×10^{6}  cm^{2} V^{-1} s^{-1}) n-type GaAs quantum well. We observe a strikingly large linear magnetoresistance (LMR) up to 33 T with a magnitude of order 10^{5}% onto which quantum oscillations become superimposed in the quantum Hall regime at low temperature. LMR is very often invoked as evidence for exotic quasiparticles in new materials such as the topological semimetals, though its origin remains controversial. The observation of such a LMR in the "simplest system"-with a free electronlike band structure and a nearly defect-free environment-excludes most of the possible exotic explanations for the appearance of a LMR and rather points to density fluctuations as the primary origin of the phenomenon. Both, the featureless LMR at high T and the quantum oscillations at low T follow the empirical resistance rule which states that the longitudinal conductance is directly related to the derivative of the transversal (Hall) conductance multiplied by the magnetic field and a constant factor α that remains unchanged over the entire temperature range. Only at low temperatures, small deviations from this resistance rule are observed beyond ν=1 that likely originate from a different transport mechanism for the composite fermions.

  17. Quantum and Classical Magnetoresistance in Ambipolar Topological Insulator Transistors with Gate-tunable Bulk and Surface Conduction

    Science.gov (United States)

    Tian, Jifa; Chang, Cuizu; Cao, Helin; He, Ke; Ma, Xucun; Xue, Qikun; Chen, Yong P.

    2014-01-01

    Weak antilocalization (WAL) and linear magnetoresistance (LMR) are two most commonly observed magnetoresistance (MR) phenomena in topological insulators (TIs) and often attributed to the Dirac topological surface states (TSS). However, ambiguities exist because these phenomena could also come from bulk states (often carrying significant conduction in many TIs) and are observable even in non-TI materials. Here, we demonstrate back-gated ambipolar TI field-effect transistors in (Bi0.04Sb0.96)2Te3 thin films grown by molecular beam epitaxy on SrTiO3(111), exhibiting a large carrier density tunability (by nearly 2 orders of magnitude) and a metal-insulator transition in the bulk (allowing switching off the bulk conduction). Tuning the Fermi level from bulk band to TSS strongly enhances both the WAL (increasing the number of quantum coherent channels from one to peak around two) and LMR (increasing its slope by up to 10 times). The SS-enhanced LMR is accompanied by a strongly nonlinear Hall effect, suggesting important roles of charge inhomogeneity (and a related classical LMR), although existing models of LMR cannot capture all aspects of our data. Our systematic gate and temperature dependent magnetotransport studies provide deeper insights into the nature of both MR phenomena and reveal differences between bulk and TSS transport in TI related materials. PMID:24810663

  18. Fast Flux Test Facility core system

    International Nuclear Information System (INIS)

    Ethridge, J.L.; Baker, R.B.; Leggett, R.D.; Pitner, A.L.; Waltar, A.E.

    1990-11-01

    A review of Liquid Metal Reactor (LMR) core system accomplishments provides an excellent road map through the maze of issues that faced reactor designers 10 years ago. At that time relatively large uncertainties were associated with fuel pin and fuel assembly performance, irradiation of structural materials, and performance of absorber assemblies. The extensive core systems irradiation program at the US Department of Energy's Fast Flux Test Facility (FFTF) has addressed each of these principal issues. As a result of the progress made, the attention of long-range LMR planners and designers can shift away from improving core systems and focus on reducing capital costs to ensure the LMR can compete economically in the 21st century with other nuclear reactor concepts. 3 refs., 6 figs., 1 tab

  19. Managing living marine resources in a dynamic environment: the role of seasonal to decadal climate forecasts

    DEFF Research Database (Denmark)

    Tommasi, Desiree; Stock, Charles A.; Hobday, Alistair J.

    2017-01-01

    and industry operations, as well as new research avenues in fisheries science. LMRs respond to climate variability via changes in physiology and behavior. For species and systems where climate-fisheries links are well established, forecasted LMR responses can lead to anticipatory and more effective decisions......Recent developments in global dynamical climate prediction systems have allowed for skillful predictions of climate variables relevant to living marine resources (LMRs) at a scale useful to understanding and managing LMRs. Such predictions present opportunities for improved LMR management......, benefitting both managers and stakeholders. Here, we provide an overview of climate prediction systems and advances in seasonal to decadal prediction of marine-resource relevant environmental variables. We then describe a range of climate-sensitive LMR decisions that can be taken at lead-times of months...

  20. Liquid metal reactor applications of the CONTAIN code

    International Nuclear Information System (INIS)

    Carroll, D.E.; Bergeron, K.D.; Gido, R.; Valdez, G.D.; Scholtyssek, W.

    1988-01-01

    The CONTAIN code is the NRC's best-estimate code for the evaluation of the conditions that may exist inside a reactor containment building during a severe accident. Included in the phenomena modeled are thermal-hydraulics, radiant and convective heat transfer, aerosol loading and transient response, fission product transport and heating effects, and interactions of sodium and corium with the containment atmosphere and structures. CONTAIN has been used by groups in Japan and West Germany to assess its ability to analyze accident consequences for liquid metal reactor (LMR) plants. In conjunction with this use, collaborative efforts to improve the modeling have been pursued. This paper summarizes the current state of the version of CONTAIN that has been enhanced with extra capabilities for LMR applications. A description of physical models is presented, followed by a review of validation exercises performed with CONTAIN. Some demonstration calculations of an integrated LMR application are presented

  1. Influence of a Cyclic Events Configuration on a Elevated Temperature Structural Integrity

    International Nuclear Information System (INIS)

    Park, Chang-Gyu; Koo, Gyeong-Hoi; Lee, Jae-Han

    2008-01-01

    A nuclear power plant generally undergoes the various types of operating events for a plant life time. The cyclic events for a life time may bring about a structural failure such as fatigue damage. The structures of the LMR(Liquid Metal Reactor) operated in a elevated temperature environment are seriously affected by a thermal deformation and strain. Therefore, the thermal transient condition is a key factor for ensuring the structural integrity for the LMR reactor structures. Since it is not easy to consider the entire operating events at the preliminary or conceptual design stage, the LMR structural integrity is evaluated with representative duty cycle events. In this study, the influence of the elevated temperature structural integrity evaluation per the combination and sequence of the duty cycle events is investigated

  2. Experience with lifetime limits for EBR-II core components

    International Nuclear Information System (INIS)

    Lambert, J.D.B.; Smith, R.N.; Golden, G.H.

    1987-01-01

    The Experimental Breeder Reactor No. 2 (EBR-II) is operated for the US Department of Energy by Argonne National Laboratory and is located on the Idaho National Engineering Laboratory where most types of American reactor were originally tested. EBR-II is a complete electricity-producing power plant now in its twenty-fourth year of successful operation. During this long history the reactor has had several concurrent missions, such as demonstration of a closed Liquid-Metal Reactor (LMR) fuel cycle (1964-69); as a steady-state irradiation facility for fuels and materials (1970 onwards); for investigating effects of operational transients on fuel elements (from 1981); for research into the inherent safety aspects of metal-fueled LMR's (from 1983); and, most recently, for demonstration of the Integral Fast Reactor (IFR) concept using U-Pu-Zr fuels. This paper describes experience gained at EBR-II in defining lifetime limits for LMR core components, particularly fuel elements

  3. Testing of seismic isolation bearings for advanced liquid metal reactor prism

    International Nuclear Information System (INIS)

    Tajirian, F.F.; Kelly, J.M.

    1988-01-01

    Seismic isolation can significantly mitigate earthquake loads on liquid metal reactors (LMR), thus reducing the impact of seismic loads on design. This improves plant safety margins for beyond-design basis seismic events and enhances adaptability of a standardized design to a variety of sites, with potential cost benefits. The PRISM (Power Reactor Inherently Safe Module) LMR incorporates a horizontal isolation system which consists of high damping steel laminated rubber bearings. The results of an experimental program to determine the mechanical properties of the rubber compound and the bearing performance under different loading conditions are presented. The test results demonstrate the excellent performance of the bearings and their suitability for isolating compact LMR plants

  4. Development of a MELCOR Sodium Chemistry (NAC) Package - FY17 Progress.

    Energy Technology Data Exchange (ETDEWEB)

    Louie, David [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Humphries, Larry L. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)

    2018-02-01

    This report describes the status of the development of MELCOR Sodium Chemistry (NAC) package. This development is based on the CONTAIN-LMR sodium physics and chemistry models to be implemented in MELCOR. In the past three years, the sodium equation of state as a working fluid from the nuclear fusion safety research and from the SIMMER code has been implemented into MELCOR. The chemistry models from the CONTAIN-LMR code, such as the spray and pool fire mode ls, have also been implemented into MELCOR. This report describes the implemented models and the issues encountered. Model descriptions and input descriptions are provided. Development testing of the spray and pool fire models is described, including the code-to-code comparison with CONTAIN-LMR. The report ends with an expected timeline for the remaining models to be implemented, such as the atmosphere chemistry, sodium-concrete interactions, and experimental validation tests .

  5. Structural and Chemical Evolution of Li- and Mn-rich Layered Cathode Material

    Energy Technology Data Exchange (ETDEWEB)

    Zheng, Jianming; Xu, Pinghong; Gu, Meng; Xiao, Jie; Browning, Nigel D.; Yan, Pengfei; Wang, Chong M.; Zhang, Jiguang

    2015-02-24

    Lithium (Li)- and manganese-rich (LMR) layered-structure materials are very promising cathodes for high energy density lithium-ion batteries. However, their voltage fading mechanism and its relationships with fundamental structural changes are far from being sufficiently understood. Here we report the detailed phase transformation pathway in the LMR cathode (Li[Li0.2Ni0.2Mn0.6]O2) during cycling for the samples prepared by hydro-thermal assistant method. It is found the transformation pathway of LMR cathode is closely correlated to its initial structure and preparation conditions. The results reveal that LMR cathode prepared by HA approach experiences a phase transformation from the layered structure to a LT-LiCoO2 type defect spinel-like structure (Fd-3m space group) and then to a disordered rock-salt structure (Fm-3m space group). The voltage fade can be well correlated with the Li ion insertion into octahedral sites, rather than tetrahedral sites, in both defect spinel-like structure and disordered rock-salt structure. The reversible Li insertion/removal into/from the disordered rock-salt structure is ascribed to the Li excess environment that can satisfy the Li percolating in the disordered rock-salt structure despite the increased kinetic barrier. Meanwhile, because of the presence of a great amount of oxygen vacancies, a significant decrease of Mn valence is detected in the cycled particle, which is below that anticipated for a potentially damaging Jahn-Teller distortion (+3.5). Clarification of the phase transformation pathway, cation redistribution, oxygen vacancy and Mn valence change undoubtedly provides insights into a profound understanding on the voltage fade, and capacity degradation of LMR cathode. The results also inspire us to further enhance the reversibility of LMR cathode via improving its surface structural stability.

  6. C-reactive protein-to-albumin ratio is a predictor of hepatitis B virus related decompensated cirrhosis: time-dependent receiver operating characteristics and decision curve analysis.

    Science.gov (United States)

    Huang, Si-Si; Xie, Dong-Mei; Cai, Yi-Jing; Wu, Jian-Min; Chen, Rui-Chong; Wang, Xiao-Dong; Song, Mei; Zheng, Ming-Hua; Wang, Yu-Qun; Lin, Zhuo; Shi, Ke-Qing

    2017-04-01

    Hepatitis B virus (HBV) infection remains a major health problem and HBV-related-decompensated cirrhosis (HBV-DC) usually leads to a poor prognosis. Our aim was to determine the utility of inflammatory biomarkers in predicting mortality of HBV-DC. A total of 329 HBV-DC patients were enrolled. Survival estimates for the entire study population were generated using the Kaplan-Meier method. The prognostic values for model for end-stage liver disease (MELD) score, Child-Pugh score, and inflammatory biomarkers neutrophil/lymphocyte ratio, C-reactive protein-to-albumin ratio (CAR), and lymphocyte-to-monocyte ratio (LMR) for HBV-DC were compared using time-dependent receiver operating characteristic curves and time-dependent decision curves. The survival time was 23.1±15.8 months. Multivariate analysis identified age, CAR, LMR, and platelet count as prognostic independent risk factors. Kaplan-Meier analysis indicated that CAR of at least 1.0 (hazard ratio, 7.19; 95% confidence interval, 4.69-11.03), and LMR less than 1.9 (hazard ratio, 2.40; 95% confidence interval, 1.69-3.41) were independently associated with mortality of HBV-DC. The time-dependent receiver operating characteristic indicated that CAR showed the best performance in predicting mortality of HBV-DC compared with LMR, MELD score, and Child-Pugh score. The results were also confirmed by time-dependent decision curves. CAR and LMR were associated with the prognosis of HBV-DC. CAR was superior to LMR, MELD score, and Child-Pugh score in HBV-DC mortality prediction.

  7. The clinical use of the platelet/lymphocyte ratio and lymphocyte/monocyte ratio as prognostic predictors in colorectal cancer: a meta-analysis.

    Science.gov (United States)

    Guo, Ya-Huan; Sun, Hai-Feng; Zhang, Yan-Bing; Liao, Zi-Jun; Zhao, Lei; Cui, Jie; Wu, Tao; Lu, Jian-Rong; Nan, Ke-Jun; Wang, Shu-Hong

    2017-03-21

    Conflicting evidence exists regarding the effects of platelet/lymphocyte ratio (PLR) and lymphocyte/monocyte ratio(LMR) on the prognosis of colorectal cancer (CRC) patients. This study aimed to evaluate the roles of the PLR and LMR in predicting the prognosis of CRC patients via meta-analysis. Eligible studies were retrieved from the PubMed, Embase,andChina National Knowledge Infrastructure (CNKI) databases, supplemented by a manual search of references from retrieved articles. Pooled hazard ratios (HR) with 95% confidence intervals (95% CI) were calculated using the generic inverse variance and random-effect model to evaluate the association of PLR and LMR with prognostic variables in CRC, including overall survival (OS), cancer-specific survival (CSS) and disease-free survival (DFS). Thirty-three studies containing 15,404 patients met criteria for inclusion. Pooled analysis suggested that elevated PLR was associated with poorer OS (pooled HR = 1.57, 95% CI: 1.41 - 1.75, p< 0.00001, I2=26%) and DFS (pooled HR = 1.58, 95% CI: 1.31 - 1.92, p< 0.00001, I2=66%). Conversely, high LMR correlated with more favorable OS (pooled HR = 0.59, 95% CI: 0.50 - 0.68, p< 0.00001, I2=44%), CSS (pooled HR = 0.54, 95% CI: 0.40 - 0.72, p< 0.00001, I2=11%) and DFS (pooled HR = 0.82, 95% CI: 0.71- 0.94,p=0.005, I2=29%). Elevated PLR was associated with poor prognosis, while high LMR correlated with more favorable outcomes in CRC patients. Pretreatment PLR and LMR could serve as prognostic predictors in CRC patients.

  8. The prognostic value of lymphocyte-to-monocyte ratio in retinopathy of prematurity

    Directory of Open Access Journals (Sweden)

    Yu-Xiang Hu

    2017-11-01

    Full Text Available AIM: To evaluate the associations between development of retinopathy of prematurity (ROP and serum lymphocyte-to-monocyte ratio (LMR, neutrophil-to-lymphocyte ratio (NLR, and platelet-to-lymphocyte ratio (PLR. METHODS: A retrospective cohort study was performed, involving infants who were screened for ROP from January 2015 to December 2015. Preterm newborns of ≤32 gestational weeks with ROP were enrolled as the observation group, and non-ROP infants were enrolled as the control group, whose complete blood cell were measured within the first 24h of life. The levels of NLR, LMR and PLR were determined in all groups. The data obtained were analyzed using univariate and multivariate logistic regression analysis. RESULTS: In this study, 40 cases of ROP were enrolled and 40 cases of non-ROP as controls. The LMR levels were significantly higher (P<0.001 in ROP group (3.96±1.16 compared to non-ROP group (2.85±0.79. The NLR levels were significantly lower (P=0.035 in ROP group {median [interquartile range (IQR], 0.88 (0.67-1.46} compared to non-ROP group [median (IQR, 1.20 (0.85-1.89]. The median PLR values were 61.99 (IQR, 50.23-75.98 in ROP group and 69.24 (IQR, 55.52-88.12 in non-ROP group (P=0.104. Logistic regression analysis suggested that LMR was an independent risk factor for ROP (OR: 0.275; 95% CI: 0.134-0.564; P=0.001. CONCLUSION: The findings demonstrate that higher LMR is independently and significantly associated with the development of ROP, and the LMR may be invoked as a predictive tool for identifying risk for ROP.

  9. Numerical Study for Turbulent Heat Transfer in Helical Wired Sub-channel Flow Regime of Duct-less Assembly in SFR

    International Nuclear Information System (INIS)

    You, Byunghyun; Jeong, Yong Hoon

    2014-01-01

    A fuel assembly had hexagonal structure adjacent to 6 fuel assemblies, which influence to the target fuel assembly due to elimination of duct. For calculating the influence, 6 additional channels were generated between the adjacent fuel assemblies and cross flow model was applied to the channels. The adjacent fuel assemblies were analyzed and the results were used in the additional channel as boundary condition of the target fuel assembly. To design the specifications of duct-less assembly, modified or brand-new thermal-hydraulic methodology is needed which is using MATRA-LMR and CFD codes in this study. The MATRA-LMR is a sub-channel analysis code for LMR that has been developed in Korea Atomic Energy Research Institute. It is designed to analyze a fuel assembly with wire-wrap and duct structure. However, the duct-less core is not able to be analyzed by the MATRA-LMR which doesn't consider cross flow between the fuel assemblies and effect of grid spacer. The code need improvement by editing source code to eliminate effect of duct and analyze pressure drop and mixing between the sub-channels caused by grid spacer and cross flow between the fuel assemblies. To validate reformed pressure drop model and cross flow model in MATRA-LMR, CFD analysis is performed. For verifying the results of CFD, LMR subchannel experimental data is benchmarked which is done by ORNL. The verified CFD for thermalhydraulic analysis calculated pressure drop and mixing caused by grid spacer and cross flow between fuel assemblies

  10. Evaluation of KALIMER IHTS piping using French RCC-MR code

    International Nuclear Information System (INIS)

    Lee, Hyeong Yeon; Kim, J. B.; Lee, J. H.

    2001-12-01

    In the present report, the evaluation of design integrity for the liquid metal reactor(LMR) of KALIMER IHTS(intermediate heat transport system) piping according to the French design guideline of RCC-MR RC3600 developed for secondary piping of LMR and the evaluation procedure was presented. The evaluation results showed that the results by the simple RC-3600 procedure of design by formula were more conservative than those of ASME section III subsection NH of the design by analysis for the class I structural components

  11. Physics considerations in the design of liquid metal reactors for transuranium element consumption

    International Nuclear Information System (INIS)

    Khalil, H.; Hill, R.; Fujita, E.; Wade, D.

    1992-01-01

    The management of transuranic nuclides in liquid metal reactors (LMR's) is considered based on the use of the Integral Fast Reactor (IFR) concept. Unique features of the IFR fuel cycle with respect to transuranic management are identified. These features are exploited together with the hard spectrum of LMR's to demonstrate the neutronic feasibility of a wide range of transuranic management options ranging from efficient breeding to pure consumption. Core physics aspects of the development of a low sodium void worth transuranic burner concept are described. Neutronics performance parameters and reactivity feedback characteristics estimated for this core concept are presented

  12. Failed fuel identification techniques for liquid-metal cooled reactors

    International Nuclear Information System (INIS)

    Lambert, J.D.B.; Gross, K.C.; Mikaili, R.; Frank, S.M.; Cutforth, D.C.; Angelo, P.L.

    1995-01-01

    The Experimental Breeder Reactor II (EBR-II), located in Idaho and operated for the US Department of Energy by Argonne National Laboratory, has been used as an irradiation testbed for LMR fuels and components for thirty years. During this time many endurance tests have been carried out with experimental LMR metal, oxide, carbide and nitride fuel elements, in which cladding failures were intentionally allowed to occur. This paper describes methods that have been developed for the detection, identification and verification of fuel failures

  13. Run-beyond-clad-breach oxide testing in EBR-2

    International Nuclear Information System (INIS)

    Lambert, J.D.B.; Bottcher, J.H.; Strain, R.V.; Gross, K.C.; Lee, M.J.; Webb, J.P.; Colburn, R.P.; Ukai, S.; Nomura, S.; Odo, T.; Shikakura, S.

    1990-01-01

    Fourteen tests sponsored by the US and Japan were used to study reliability of breached LMR oxide fuel pins during continued operation in EBR-II for a range of conditions and parameters. The fuel-sodium reaction product governed pin behavior. It extended primary breaches by swelling and promoted secondary failures, yet it inhibited loss of fuel and fission products and enhanced release of delayed neutrons used in monitoring breach condition. Fission gas and cesium, the main contaminants from failures, could be adequately controlled. This positive EBR-II experience suggested that limited operation with failed fuel may be feasible in commercial LMR's. 16 refs., 14 figs., 4 tabs

  14. Celiac disease biodetection using lossy-mode resonances generated in tapered single-mode optical fibers

    Science.gov (United States)

    Socorro, A. B.; Corres, J. M.; Del Villar, I.; Matias, I. R.; Arregui, F. J.

    2014-05-01

    This work presents the development and test of an anti-gliadin antibodies biosensor based on lossy mode resonances (LMRs) to detect celiac disease. Several polyelectrolites were used to perform layer-by-layer assembly processes in order to generate the LMR and to fabricate a gliadin-embedded thin-film. The LMR shifted 20 nm when immersed in a 5 ppm anti-gliadin antibodies-PBS solution, what makes this bioprobe suitable for detecting celiac disease. This is the first time, to our knowledge, that LMRs are used to detect celiac disease and these results suppose promising prospects on the use of such phenomena as biological detectors.

  15. Evaluation of postulated LOF [loss-of-flow] events in PRISM and SAFR

    International Nuclear Information System (INIS)

    Chan, B.C.; Van Tuyle, G.J.; Slovik, G.C.; Aronson, A.L.

    1987-01-01

    The PRISM and SAFR designs, as currently proposed by DOE, are designed for ''inherent'', as opposed to ''engineered'', safety. Brookhaven National Laboratory is supporting the initial NRC review of these advanced LMR concepts. A loss-of-flow (LOF) accident coupled with a failure of the reactor shutdown system is one of the major safety concerns in the advanced liquid metal reactor (LMR) evaluation effort. The analysis discussed here covers: (1) primary pipe break without pump trip, (2) primary coolant pump seizure, and (3) primary coolant pump coastdown. The analytical modelling and the calculated thermal and hydraulic behavior are described in detail

  16. Analysis of postulated unscrammed loss of flow in SAFR using SSC

    International Nuclear Information System (INIS)

    Slovik, G.C.; Van Tuyle, G.J.

    1988-01-01

    Brookhaven National Laboratory is providing technical assistance to the US Nuclear Regulatory Commission in reviewing two advanced liquid-metal reactor (LMR) designs in order to address the licensability of these innovative concepts. The designs, PRISM and SAFR are being proposed by General Electric Company and Rockwell International (RI), respectively. Brookhaven National Laboratory has utilized the super system code (SSC) to independently evaluate the LMR reactor system response during several postulated unscrammed events. This paper describes the SAFR reactor responses to a beyond-design base event where forced cooling is lost. A similar transient analysis has already been reported for PRISM

  17. Accreditation experience of radioisotope metrology laboratory of Argentina

    Energy Technology Data Exchange (ETDEWEB)

    Iglicki, A. [Laboratorio de Metrologia de Radioisotopos, Comision Nacional de Energia Atomica (Argentina)]. E-mail: iglicki@cae.cnea.gov.ar; Mila, M.I. [Laboratorio de Metrologia de Radioisotopos, Comision Nacional de Energia Atomica (Argentina)]. E-mail: mila@cae.cnea.gov.ar; Furnari, J.C. [Laboratorio de Metrologia de Radioisotopos, Comision Nacional de Energia Atomica (Argentina); Arenillas, P. [Laboratorio de Metrologia de Radioisotopos, Comision Nacional de Energia Atomica (Argentina); Cerutti, G. [Laboratorio de Metrologia de Radioisotopos, Comision Nacional de Energia Atomica (Argentina); Carballido, M. [Laboratorio de Metrologia de Radioisotopos, Comision Nacional de Energia Atomica (Argentina); Guillen, V. [Laboratorio de Metrologia de Radioisotopos, Comision Nacional de Energia Atomica (Argentina); Araya, X. [Laboratorio de Metrologia de Radioisotopos, Comision Nacional de Energia Atomica (Argentina); Bianchini, R. [Laboratorio de Metrologia de Radioisotopos, Comision Nacional de Energia Atomica (Argentina)

    2006-10-15

    This work presents the experience developed by the Radioisotope Metrology Laboratory (LMR), of the Argentine National Atomic Energy Commission (CNEA), as result of the accreditation process of the Quality System by ISO 17025 Standard. Considering the LMR as a calibration laboratory, services of secondary activity determinations and calibration of activimeters used in Nuclear Medicine were accredited. A peer review of the ({alpha}/{beta})-{gamma} coincidence system was also carried out. This work shows in detail the structure of the quality system, the results of the accrediting audit and gives the number of non-conformities detected and of observations made which have all been resolved.

  18. Accreditation experience of radioisotope metrology laboratory of Argentina

    International Nuclear Information System (INIS)

    Iglicki, A.; Mila, M.I.; Furnari, J.C.; Arenillas, P.; Cerutti, G.; Carballido, M.; Guillen, V.; Araya, X.; Bianchini, R.

    2006-01-01

    This work presents the experience developed by the Radioisotope Metrology Laboratory (LMR), of the Argentine National Atomic Energy Commission (CNEA), as result of the accreditation process of the Quality System by ISO 17025 Standard. Considering the LMR as a calibration laboratory, services of secondary activity determinations and calibration of activimeters used in Nuclear Medicine were accredited. A peer review of the (α/β)-γ coincidence system was also carried out. This work shows in detail the structure of the quality system, the results of the accrediting audit and gives the number of non-conformities detected and of observations made which have all been resolved

  19. RAP-IA code for calculus thermodinamic of the fast reactors

    International Nuclear Information System (INIS)

    Popescu, C.; Turcu, I.; Boeriu, S.; Biro, L.

    1975-01-01

    The RAP-IA code is developed in order to perform a complete calculation for a thermal channel of a Na-cooled fast reactor. Calculation may be effected for both stationary state and dynamic regime following modification of some in-put data: total thermal power, multiplication coefficient, flow-rate and in-put temperature of the thermal agent, pressure level

  20. LMFBR Ultra Long Life Cores

    International Nuclear Information System (INIS)

    Schmidt, J.E.; Doncals, R.A.; Porter, C.A.; Gundy, L.M.

    1986-01-01

    The Ultra Long Life Core is an attractive and innovative design approach with several extremely beneficial attributes. Long Life cores are applicable to the full range of LMR plant sizes resulting in lifetimes up to 30 years. Core life is somewhat limited for smaller plant sizes, however significant benefits of this approach still exist for all plant sizes. The union of long life cores and the complementary inherent safety technology offer a means of utilizing the well-proven oxide fuel in a system with unsurpassed safety capability. A further benefit is that the uranium fuel cycle can be used in long life cores, especially for initial LMR plant deployment, thereby eliminating the need for reprocessing prior to starting LMR plant construction in the U.S. Finally the long life core significantly reduces power costs. With inherent safety capability designed into an LMR and with the ULLC fuel cycle, power costs competitive with light water plants are achievable while offering improved operational flexibility derived through extending refueling intervals

  1. Post-irradiation examinations and theoretical analyses of the fuel and fuel pin behavior of innovative systems; Bestrahlungsnachuntersuchungen und modelltheoretische Analysen zum Brennstoff- und Brennstabverhalten innovativer Systeme

    Energy Technology Data Exchange (ETDEWEB)

    Ernst, W.; Freund, D.; Geithoff, D.; Heck, M.; Jacobi, O.; Steiner, H.; Weimar, P.

    1995-08-01

    For the development of LMR cladding materials an irradiation test was performed in the KNK II reactor between 1986 and 1991. It demonstrated that a temperature gradient in the cladding has no observable effect on swelling behavior. PIEs of transient experiments in the Petten HFR have shown no significant cladding deformations. (orig.)

  2. Post-irradiation examinations and theoretical analyses of the fuel and fuel pin behavior of innovative systems

    International Nuclear Information System (INIS)

    Ernst, W.; Freund, D.; Geithoff, D.; Heck, M.; Jacobi, O.; Steiner, H.; Weimar, P.

    1995-01-01

    For the development of LMR cladding materials an irradiation test was performed in the KNK II reactor between 1986 and 1991. It demonstrated that a temperature gradient in the cladding has no observable effect on swelling behavior. PIEs of transient experiments in the Petten HFR have shown no significant cladding deformations. (orig.)

  3. Tailoring properties of lossy-mode resonance optical fiber sensors with atomic layer deposition technique

    Science.gov (United States)

    Kosiel, Kamil; Koba, Marcin; Masiewicz, Marcin; Śmietana, Mateusz

    2018-06-01

    The paper shows application of atomic layer deposition (ALD) technique as a tool for tailoring sensorial properties of lossy-mode-resonance (LMR)-based optical fiber sensors. Hafnium dioxide (HfO2), zirconium dioxide (ZrO2), and tantalum oxide (TaxOy), as high-refractive-index dielectrics that are particularly convenient for LMR-sensor fabrication, were deposited by low-temperature (100 °C) ALD ensuring safe conditions for thermally vulnerable fibers. Applicability of HfO2 and ZrO2 overlays, deposited with ALD-related atomic level thickness accuracy for fabrication of LMR-sensors with controlled sensorial properties was presented. Additionally, for the first time according to our best knowledge, the double-layer overlay composed of two different materials - silicon nitride (SixNy) and TaxOy - is presented for the LMR fiber sensors. The thin films of such overlay were deposited by two different techniques - PECVD (the SixNy) and ALD (the TaxOy). Such approach ensures fast overlay fabrication and at the same time facility for resonant wavelength tuning, yielding devices with satisfactory sensorial properties.

  4. Integral Fast Reactor concept

    International Nuclear Information System (INIS)

    Till, C.E.; Chang, Y.I.

    1986-01-01

    The Integral Fast Reactor (IFR) is an innovative LMR concept, being developed at Argonne National Laboratory, that fully exploits the inherent properties of liquid metal cooling and metallic fuel to achieve breakthroughs in economics and inherent safety. This paper describes key features and potential advantages of the IFR concept, technology development status, fuel cycle economics potential, and future development path

  5. An Adaptive Classification Strategy for Reliable Locomotion Mode Recognition

    Directory of Open Access Journals (Sweden)

    Ming Liu

    2017-09-01

    Full Text Available Algorithms for locomotion mode recognition (LMR based on surface electromyography and mechanical sensors have recently been developed and could be used for the neural control of powered prosthetic legs. However, the variations in input signals, caused by physical changes at the sensor interface and human physiological changes, may threaten the reliability of these algorithms. This study aimed to investigate the effectiveness of applying adaptive pattern classifiers for LMR. Three adaptive classifiers, i.e., entropy-based adaptation (EBA, LearnIng From Testing data (LIFT, and Transductive Support Vector Machine (TSVM, were compared and offline evaluated using data collected from two able-bodied subjects and one transfemoral amputee. The offline analysis indicated that the adaptive classifier could effectively maintain or restore the performance of the LMR algorithm when gradual signal variations occurred. EBA and LIFT were recommended because of their better performance and higher computational efficiency. Finally, the EBA was implemented for real-time human-in-the-loop prosthesis control. The online evaluation showed that the applied EBA effectively adapted to changes in input signals across sessions and yielded more reliable prosthesis control over time, compared with the LMR without adaptation. The developed novel adaptive strategy may further enhance the reliability of neurally-controlled prosthetic legs.

  6. Integral Fast Reactor concept

    Energy Technology Data Exchange (ETDEWEB)

    Till, C.E.; Chang, Y.I.

    1986-01-01

    The Integral Fast Reactor (IFR) is an innovative LMR concept, being developed at Argonne National Laboratory, that fully exploits the inherent properties of liquid metal cooling and metallic fuel to achieve breakthroughs in economics and inherent safety. This paper describes key features and potential advantages of the IFR concept, technology development status, fuel cycle economics potential, and future development path.

  7. Integral Fast Reactor Program annual progress report, FY 1991

    International Nuclear Information System (INIS)

    1992-06-01

    This report summarizes highlights of the technical progress made in the Integral Fast Reactor (IFR) Program in FY 1991. Technical accomplishments are presented in the following areas of the IFR technology development activities: (1) metal fuel performance, (2) pyroprocess development, (3) safety experiments and analyses, (4) core design development, (5) fuel cycle demonstration, and (6) LMR technology R ampersand D

  8. An evaluation of the concept of transuranic burning using liquid metal reactors

    International Nuclear Information System (INIS)

    Rodwell, E.; Shaw, R.A.; Williams, R.F.

    1991-03-01

    The evaluation investigates the potential benefits to radioactive waste disposal of separating the transuranic elements from spent reactor fuel before the spent fuel is disposed of in geologic repositories. The evaluation addresses the question whether the benefits to radioactive waste disposal would justify processing the fuel to separate the transuranics, plus a liquid metal reactor (LMR) deployment program to transmute the separated transuranics. The evaluation concludes that adoption of a process-before-disposal policy for all the spent fuel from the light water reactors (LWRs) would accrue only modest benefits with respect to the accumulation of uranium mill tailings, the national inventory of transuranics and the licensing of a geologic repository. It is likely that this process-before-disposal policy would incur a large cost penalty, encounter major institutional difficulties, multiply licensing hurdles, and amplify political and public opposition to the overall nuclear power program. However, plutonium from spent LWR fuel is projected to be substantially more economic than enriched uranium, as fissile material for startup of LMRs when LMR deployment becomes economically justified. At that time, the LMR would fulfill its role as a reactor system that would protect the nation from diminishing energy resources. Development tasks towards defining and developing the most cost-effective LMR and associated fuel cycle remain very important. 29 refs., 3 figs., 18 tabs

  9. Integral Fast Reactor Program. Annual progress report, FY 1992

    Energy Technology Data Exchange (ETDEWEB)

    Chang, Y.I.; Walters, L.C.; Laidler, J.J.; Pedersen, D.R.; Wade, D.C.; Lineberry, M.J.

    1993-06-01

    This report summarizes highlights of the technical progress made in the Integral Fast Reactor (IFR) Program in FY 1992. Technical accomplishments are presented in the following areas of the IFR technology development activities: (1) metal fuel performance, (2) pyroprocess development, (3) safety experiments and analyses, (4) core design development, (5) fuel cycle demonstration, and (6) LMR technology R&D.

  10. Onderzoek naar een monsternamemethode voor de analyse van PAK's en een aantal bestrijdingsmiddelen in regenwater

    NARCIS (Netherlands)

    Baumann RA; van der Velde EG; Hoogerbrugge R; ' t Hart-de Kleijn Kleijn VM; Wammes JIJ

    1991-01-01

    The quality of analytical results obtained for polycyclic aromatic hydrocarbons (PAHs), monitored at three sites of the Dutch National Precipitation Chemistry Network (LMR) was evaluated. Also, the possibility of applying a single sampling method for analysis of both PAHs as well as a selected

  11. Heterologously expressed bacterial and human multidrug resistance proteins confer cadmium resistance to Escherichia coli

    NARCIS (Netherlands)

    Achard-Joris, M; van Saparoea, HBV; Driessen, AJM; Bourdineaud, JP; Bourdineaud, Jean-Paul

    2005-01-01

    The human MDR1 gene is induced by cadmium exposure although no resistance to this metal is observed in human cells overexpressing hMDR1. To access the role of MDR proteins in cadmium resistance, human MDR1, Lactococcus lactis lmrA, and Oenococcus oeni omrA were expressed in an Escherichia coli tolC

  12. Artificial Metalloproteins for Binding and Stabilization of a Semiquinone Radical

    NARCIS (Netherlands)

    Segaud, Nathalie; Drienovska, Ivana; Chen, Juan; Browne, Wesley R.; Roelfes, Gerard

    2017-01-01

    The interaction of a number of first-row transition-metal ions with a 2,2'-bipyridyl alanine (bpyA) unit incorporated into the lactococcal multidrug resistance regulator (LmrR) scaffold is reported. The composition of the active site is shown to influence binding affinities. In the case of Fe(II),

  13. Investigations of elementary reactions of the methyl radical with the aid of laser magnetic resonance; Untersuchungen von Elementarreaktionen des Methylradikals mit Hilfe der Laser-Magnetischen-Resonanz

    Energy Technology Data Exchange (ETDEWEB)

    Deters, R.J.

    1998-01-01

    Selected elementary reactions of CH{sub 3} radicals in an isothermal flow system in the gaseous phase were investigated by means of LMR. [Deutsch] In dieser Arbeit wurden ausgewaehlte Elementarreaktionen von CH{sub 3}-Radikalen in einem isothermen Stroemungssystem in der Gasphase mit Hilfe der Laser-Magnetischen-Resonanz untersucht. (orig.)

  14. Integral Fast Reactor Program annual progress report, FY 1994

    International Nuclear Information System (INIS)

    Chang, Y.I.; Walters, L.C.; Laidler, J.J.; Pedersen, D.R.; Wade, D.C.; Lineberry, J.J.

    1994-12-01

    This report summarizes highlights of the technical progress made in the Integral Fast Reactor (IFR) Program in FY 1994. Technical accomplishments are presented in the following areas of the IFR technology development activities: metal fuel performance; pyroprocess development; safety experiments and analyses; core design development; fuel cycle demonstration; and LMR technology R ampersand D

  15. Integral Fast Reactor Program

    International Nuclear Information System (INIS)

    Chang, Y.I.; Walters, L.C.; Laidler, J.J.; Pedersen, D.R.; Wade, D.C.; Lineberry, M.J.

    1993-06-01

    This report summarizes highlights of the technical progress made in the Integral Fast Reactor (IFR) Program in FY 1992. Technical accomplishments are presented in the following areas of the IFR technology development activities: (1) metal fuel performance, (2) pyroprocess development, (3) safety experiments and analyses, (4) core design development, (5) fuel cycle demonstration, and (6) LMR technology R ampersand D

  16. Pressure effects on the CDW transitions and magnetoresistances in NbSe3

    International Nuclear Information System (INIS)

    Yasuzuka, S.; Okajima, Y.; Tanda, S.; Yamaya, K.

    1999-01-01

    Magnetoresistance (MR) of NbSe 3 has been measured between 2 K and 150 K under high pressure including critical pressures (P c2 and P c1 ) where the lower and upper CDW phase are totally suppressed by pressure, respectively. At ambient pressure, a large MR (LMR) is observed just below T c2 , but no MR is detected above T c2 . Under high pressure, in addition to the LMR, we observe newly a MR above T c2 . Here we call it the pressure-induced MR (PIMR). The LMR always appears as long as the lower CDW phase exists, but it rapidly disappears above P c2 . Similarly, the PIMR disappears above P c1 . Furthermore, no anomalies associated with the field-induced CDW are observed within our experimental limits. From these findings, we claim that the LMR and PIMR are due to normal carriers in small pockets created by a pressure-dependent imperfect nesting of the Fermi surface in the CDW transitions. (orig.)

  17. Laser magnetic resonance spectroscopy

    International Nuclear Information System (INIS)

    Ferrari, C.A.

    1985-01-01

    The technique of laser resonance magnetic resonance allows one to study the high-resolution spectroscopy of transient paramagnetic species, viz, atoms, radicals, and molecular ions. This article is a brief exposition of the method, describing the principles, instrumentation and applicability of the IR and FIR-LMR and shows results of HF + . (Author) [pt

  18. Status of national programmes on fast reactors and accelerator driven systems in Korea

    International Nuclear Information System (INIS)

    Hahn, Dohee; Kim, Yeong Il

    2001-01-01

    The LMR (liquid metal cooled reactors) Design Technology Development Project was approved as a national long-term R and D program in 1992 by the Korea Atomic Energy Commission (KAEC). KAEC decided to develop and construct an LMR with the goal of developing an LMR that can serve as a long term power supplier with competitive economics and enhanced safety. Based upon the KAEC decision, the Korea Atomic Energy Research Institute (KAERI) has been developing KALIMER (Korea Advanced Liquid Metal Reactor). According to the revised National Nuclear Energy Promotion Plan of June 1997, the basic design of KALIMER is to be completed by 2006 and feasibility of the construction is to be examined sometime during the mid 2010s. Phase 1 of three years of the LMR Design Technology Development Project was completed in March 2000 and a preliminary conceptual design report has been issued. The conceptual design of KALIMER will be finalized during Phase 2 of the project, which was started in April 2000 and will take two years. KAERI is also carrying out research and development on an accelerator driven system, called HYPER, for the transmutation of nuclear waste and energy production through the transmutation process. The HYPER program is being performed within the framework of the national mid- and long-term nuclear research plan. KAERI aims to develop a system concept and type of roadmap by the year 2001, and to complete conceptual design of the HYPER system by the year 2007. (author)

  19. A bacterial antibiotic-resistance gene that complements the human multidrug-resistance P-glycoprotein gene

    NARCIS (Netherlands)

    van Veen, HW; Callaghan, R; Soceneantu, L; Sardini, A; Konings, WN; Higgins, CF

    1998-01-01

    Bacteria have developed many fascinating antibiotic-resistance mechanisms(1,2). A protein in Lactococcus lactis, LmrA, mediates antibiotic resistance by extruding amphiphilic compounds from the inner leaflet of the cytoplasmic membrane(3,4). Unlike other known bacterial multidrug-resistance

  20. Multidrug resistance in lactic acid bacteria : molecular mechanisms and clinical relevance

    NARCIS (Netherlands)

    van Veen, HW; Margolles, A; Putman, M; Sakamoto, K; Konings, WN

    The active extrusion of cytotoxic compounds from the cell by multidrug transporters is one of the major causes of failure of chemotherapeutic treatment of tumor cells and of infections by pathogenic microorganisms. The secondary multidrug transporter LmrP and the ATP-binding cassette (ABC) type

  1. Principles of Quantile Regression and an Application

    Science.gov (United States)

    Chen, Fang; Chalhoub-Deville, Micheline

    2014-01-01

    Newer statistical procedures are typically introduced to help address the limitations of those already in practice or to deal with emerging research needs. Quantile regression (QR) is introduced in this paper as a relatively new methodology, which is intended to overcome some of the limitations of least squares mean regression (LMR). QR is more…

  2. LWR-WIMS, a computer code for light water reactor lattice calculations

    International Nuclear Information System (INIS)

    Halsall, M.J.

    1982-06-01

    LMR-WIMS is a comprehensive scheme of computation for studying the reactor physics aspects and burnup behaviour of typical lattices of light water reactors. This report describes the physics methods that have been incorporated in the code, and the modifications that have been made since the code was issued in 1972. (U.K.)

  3. Integral Fast Reactor Program. Annual progress report, FY 1993

    Energy Technology Data Exchange (ETDEWEB)

    Chang, Y.I.; Walters, L.C.; Laidler, J.J.; Pedersen, D.R.; Wade, D.C.; Lineberry, M.J.

    1994-10-01

    This report summarizes highlights of the technical progress made in the Integral Fast Reactor (IFR) Program in FY 1993. Technical accomplishments are presented in the following areas of the IFR technology development activities: (1) metal fuel performance, (2) pyroprocess development, (3) safety experiments and analyses, (4) core design development, (5) fuel cycle demonstration, and (6) LMR technology R and D.

  4. The Integral Fast Reactor concept

    International Nuclear Information System (INIS)

    Till, C.E.; Chang, Y.I.

    1986-01-01

    The Integral Fast Reactor (IFR) is an innovative LMR concept, being developed at Argonne National Laboratory, that exploits the inherent properties of liquid metal cooling and metallic fuel to achieve breakthroughs in economics and inherent safety. This paper describes the key features and potential advantages of the IFR concept, its technology development status, fuel cycle economics potential, and its future development path

  5. Integral Fast Reactor Program. Annual progress report, FY 1993

    International Nuclear Information System (INIS)

    Chang, Y.I.; Walters, L.C.; Laidler, J.J.; Pedersen, D.R.; Wade, D.C.; Lineberry, M.J.

    1994-10-01

    This report summarizes highlights of the technical progress made in the Integral Fast Reactor (IFR) Program in FY 1993. Technical accomplishments are presented in the following areas of the IFR technology development activities: (1) metal fuel performance, (2) pyroprocess development, (3) safety experiments and analyses, (4) core design development, (5) fuel cycle demonstration, and (6) LMR technology R and D

  6. A seismic performance and cost comparison of top and bottom supported liquid metal reactor vessels

    International Nuclear Information System (INIS)

    Carlson, T.M.; Kiciman, O.K.; Petrozelli, J.F.

    1989-01-01

    It is the premise of this paper that the revision of a pool LMR from a TSRV configuration to a specific bottom supported reactor vessel (BSRV) configuration can resolve the above TSRV disadvantages related to load path length and diversity, thereby improving seismic performance and simultaneously reducing RV block costs by reducing weights. This paper demonstrates this premise by comparing a reference TSRV block with a specific BSRV block design. Recent capital cost estimates ($/kWe) for U.S. liquid metal reactor (LMR) plant designs reveal that the balance of plant costs could be reduced below that of the balance of plant costs for a comparable light water reactor plant. However, in regions of high seismicity, non-seismically isolated LMR nuclear steam supply system weights are costs per kWe are two to three times the weights and costs of light water reactor nuclear steam supply systems. While all portions of the LMR nuclear steam supply system require examination for potential cost reductions, the focus of this paper is the reactor vessel (RV) block for a large pool plant

  7. Preoperative lymphocyte-to-monocyte ratio represents a superior predictor compared with neutrophil-to-lymphocyte and platelet-to-lymphocyte ratios for colorectal liver-only metastases survival

    Directory of Open Access Journals (Sweden)

    Peng JH

    2017-07-01

    Full Text Available Jianhong Peng,1,* Hui Li,2,* Qingjian Ou,1,* Junzhong Lin,1 Xiaojun Wu,1 Zhenhai Lu,1 Yunfei Yuan,1 Desen Wan,1 Yujing Fang,1 Zhizhong Pan1 1Department of Colorectal Surgery, State Key Laboratory of Oncology in South China, Collaborative Innovation Center for Cancer Medicine, Sun Yat-sen University Cancer Center, Guangzhou, People’s Republic of China; 2Zhongshan School of Medicine, Sun Yat-sen University, Guangzhou, People’s Republic of China *These authors contributed equally to this work Abstract: Systemic inflammation was recognized as an essential factor contributing to the development of malignancies. This study aimed to investigate the prognostic value of preoperative lymphocyte-to-monocyte ratio (LMR, neutrophil-to-lymphocyte ratio (NLR, and platelet-to-lymphocyte ratio (PLR in patients with colorectal liver-only metastases (CLOM undergoing hepatectomy. We retrospectively enrolled 150 consecutive patients with CLOM between 2000 and 2012. The optimal cutoff values of continuous LMR, NLR, and PLR were determined using the receiver operating characteristic curve analysis. Recurrence-free survival (RFS and overall survival (OS related to the LMR, NLR, and PLR were analyzed using both Kaplan–Meier and multivariate Cox regression methods. Elevated LMR (≥2.82 and lower NLR (<4.63 were significantly associated with better RFS and OS in patients with CLOM after hepatectomy, instead of lower PLR (<150.17. Multivariate Cox analysis identified elevated LMR as the only independent inflammatory factor for better RFS (hazard ratio, 0.591; 95% CI, 0.32–0.844; P=0.008 and OS (hazard ratio, 0.426; 95% CI, 0.254–0.716; P=0.001. In the subgroup analysis, elevated LMR was a significant favorable factor in both 5-year RFS and OS of patients with male gender, lymph node metastases, colon cancer, liver tumor with the largest diameter <5 cm, preoperative carcinoembryonic antigen level <200 ng/mL, negative hepatitis B virus infection, non

  8. A large cohort study reveals the association of elevated peripheral blood lymphocyte-to-monocyte ratio with favorable prognosis in nasopharyngeal carcinoma.

    Directory of Open Access Journals (Sweden)

    Jing Li

    Full Text Available BACKGROUND: Nasopharyngeal carcinoma (NPC is an endemic neoplasm in southern China. Although NPC sufferers are sensitive to radiotherapy, 20-30% of patients finally progress with recurrence and metastases. Elevated lymphocyte-to-monocyte ratio (LMR has been reported to be associated with favorable prognosis in some hematology malignancies, but has not been studied in NPC. The aim of this study was to evaluate whether LMR could predict the prognosis of NPC patients. METHODS: A retrospective cohort of 1,547 non-metastatic NPC patients was recruited between January 2005 and June 2008. The counts for peripheral lymphocyte and monocyte were retrieved, and the LMR was calculated. Receiver operating characteristic curve analysis, univariate and multivariate COX proportional hazards analyses were applied to evaluate the associations of LMR with overall survival (OS, disease-free survival (DFS, distant metastasis-free survival (DMFS and loco-regional recurrence-free survival (LRRFS, respectively. RESULTS: Univariate analysis revealed that higher LMR level (≥ 5.220 was significantly associated with superior OS, DFS and DMFS (P values <0.001. The higher lymphocyte count (≥ 2.145 × 10(9/L was significantly associated with better OS (P = 0.002 and DMFS (P = 0.031, respectively, while the lower monocyte count (<0.475 × 10(9/L was associated with better OS (P = 0.012, DFS (P = 0.011 and DMFS (P = 0.003, respectively. Multivariate Cox proportional hazard analysis showed that higher LMR level was a significantly independent predictor for superior OS (hazard ratio or HR = 0.558, 95% confidence interval or 95% CI = 0.417-0.748; P<0.001, DFS (HR = 0.669, 95% CI = 0.535-0.838; P<0.001 and DMFS (HR = 0.543, 95% CI = 0.403-0.732; P<0.001, respectively. The advanced T and N stages were also independent indicators for worse OS, DFS, and DMFS, except that T stage showed borderline statistical significance for DFS (P = 0.053 and DMFS (P = 0.080. CONCLUSIONS: The

  9. Restricting youth suicide: behavioral health patients in an urban pediatric emergency department.

    Science.gov (United States)

    Rogers, Steven C; DiVietro, Susan; Borrup, Kevin; Brinkley, Ashika; Kaminer, Yifrah; Lapidus, Garry

    2014-09-01

    Suicide is the third leading cause of death among individuals age 10 years to 19 years in the United States. Adolescents with suicidal behaviors are often cared for in emergency departments (EDs)/trauma centers and are at an increased risk for subsequent suicide. Many institutions do not have standard procedures to prevent future self-harm. Lethal means restriction (LMR) counseling is an evidence-based suicide prevention strategy that informs families to restrict access to potentially fatal items and has demonstrated efficacy in preventing suicide. The objectives of this study were to examine suicidal behavior among behavioral health patients in a pediatric ED and to assess the use of LMR by hospital staff. A sample of 298 pediatric patients was randomly selected from the population of behavioral health patients treated at the ED from January 1 through December 31, 2012 (n = 2,294). Descriptive data include demographics (age, sex, race/ethnicity, etc,), chief complaint, current and past psychiatric history, primary diagnosis, disposition, alcohol/drug abuse, and documentation of any LMR counseling provided in the ED. Of the 298 patients, 52% were female, 47% were white, and 76% were in the custody of their parents. Behavior/out of control was the most common chief complaint (43%). The most common diagnoses were mood disorder (25%) and depression (20%). Thirty-four percent of the patients had suicidal ideation, 22% had a suicide plan, 32% had documented suicidal behavior, and 25% of the patients reported having access to lethal means. However, only 4% of the total patient population received any LMR counseling, and only 15% of those with access to lethal means had received LMR counseling. Providing a safe environment for adolescents at risk for suicidal behaviors should be a priority for all families/caretakers and should be encouraged by health care providers. The ED is a key point of entry into services for suicidal youth and presents an opportunity to implement

  10. The prognostic value of the systemic inflammatory score in patients with unresectable metastatic colorectal cancer.

    Science.gov (United States)

    Shibutani, Masatsune; Maeda, Kiyoshi; Nagahara, Hisashi; Fukuoka, Tatsunari; Matsutani, Shinji; Kimura, Kenjiro; Amano, Ryosuke; Hirakawa, Kosei; Ohira, Masaichi

    2018-07-01

    Inflammation has been widely recognized as a contributor to cancer progression and several inflammatory markers have been reported as associated with the clinical outcomes in patients with various types of cancer. Recently, a novel inflammatory marker, the systemic inflammatory score (SIS), which is based on a combination of the lymphocyte-to-monocyte ratio (LMR) and the serum albumin concentration has been reported as a useful prognostic marker. The aim of the present study was to assess the prognostic value of the SIS in patients with unresectable metastatic colorectal cancer (mCRC). The retrospective cohort study included 160 patients who underwent combination chemotherapy for unresectable mCRC between January 2008 and December 2016. The SIS was used to classify the patients into three groups based on their LMR and the serum albumin concentration. Patients with high-LMR and high serum albumin level were given a score of 0; patients with low-LMR or low serum albumin level were given a score of 1; patients with low-LMR and low serum albumin level were given a score of 2. There were significant differences in the overall survival among the three SIS groups and the SIS was an independent prognostic factor for the overall survival. Although the SIS was significantly associated with the overall survival rate even when using the original cut-off values, the SIS according to the new cut-off values had a more accurate prognostic value. The present study determined that the SIS was a useful biomarker for predicting the survival outcomes in patients with unresectable mCRC, although the optimum cut-off value of the SIS according to the patients' background needs to be examined in further studies.

  11. Uncertainty Evaluation of the SFR Subchannel Thermal-Hydraulic Modeling Using a Hot Channel Factors Analysis

    International Nuclear Information System (INIS)

    Choi, Sun Rock; Cho, Chung Ho; Kim, Sang Ji

    2011-01-01

    In an SFR core analysis, a hot channel factors (HCF) method is most commonly used to evaluate uncertainty. It was employed to the early design such as the CRBRP and IFR. In other ways, the improved thermal design procedure (ITDP) is able to calculate the overall uncertainty based on the Root Sum Square technique and sensitivity analyses of each design parameters. The Monte Carlo method (MCM) is also employed to estimate the uncertainties. In this method, all the input uncertainties are randomly sampled according to their probability density functions and the resulting distribution for the output quantity is analyzed. Since an uncertainty analysis is basically calculated from the temperature distribution in a subassembly, the core thermal-hydraulic modeling greatly affects the resulting uncertainty. At KAERI, the SLTHEN and MATRA-LMR codes have been utilized to analyze the SFR core thermal-hydraulics. The SLTHEN (steady-state LMR core thermal hydraulics analysis code based on the ENERGY model) code is a modified version of the SUPERENERGY2 code, which conducts a multi-assembly, steady state calculation based on a simplified ENERGY model. The detailed subchannel analysis code MATRA-LMR (Multichannel Analyzer for Steady-State and Transients in Rod Arrays for Liquid Metal Reactors), an LMR version of MATRA, was also developed specifically for the SFR core thermal-hydraulic analysis. This paper describes comparative studies for core thermal-hydraulic models. The subchannel analysis and a hot channel factors based uncertainty evaluation system is established to estimate the core thermofluidic uncertainties using the MATRA-LMR code and the results are compared to those of the SLTHEN code

  12. Graphene Oxide in Lossy Mode Resonance-Based Optical Fiber Sensors for Ethanol Detection

    Directory of Open Access Journals (Sweden)

    Miguel Hernaez

    2017-12-01

    Full Text Available The influence of graphene oxide (GO over the features of an optical fiber ethanol sensor based on lossy mode resonances (LMR has been studied in this work. Four different sensors were built with this aim, each comprising a multimode optical fiber core fragment coated with a SnO2 thin film. Layer by layer (LbL coatings made of 1, 2 and 4 bilayers of polyethyleneimine (PEI and graphene oxide were deposited onto three of these devices and their behavior as aqueous ethanol sensors was characterized and compared with the sensor without GO. The sensors with GO showed much better performance with a maximum sensitivity enhancement of 176% with respect to the sensor without GO. To our knowledge, this is the first time that GO has been used to make an optical fiber sensor based on LMR.

  13. Nuclear level mixing resonance spectroscopy

    International Nuclear Information System (INIS)

    Coussement, R.; Put, P.; Scheveneels, G.; Hardeman, F.

    1985-01-01

    The existent methods for measuring quadrupole interactions are not suited to nuclei with lifetimes in the micro-seconds to minutes region. AD/NQR, a possible candidate in this lifetime gap, has not yet succeeded in overcoming its predicted difficulties. A new resonant method, recently developed and based on the principles of level mixing (cfr atomic spectroscopy) covers this less accessible lifetime range. Many other kinds of resonances can be described according to the level mixing formalism. The particular example of NMR as a level mixing resonance (LMR) is discussed. The underlying theory of LMR and its important consequences, leading to some interesting features of the method, is briefly formulated. Two successfully performed measurements demonstrate the feasibility and the predicted characteristics of this new promising method. (orig.)

  14. Graphene Oxide in Lossy Mode Resonance-Based Optical Fiber Sensors for Ethanol Detection.

    Science.gov (United States)

    Hernaez, Miguel; Mayes, Andrew G; Melendi-Espina, Sonia

    2017-12-27

    The influence of graphene oxide (GO) over the features of an optical fiber ethanol sensor based on lossy mode resonances (LMR) has been studied in this work. Four different sensors were built with this aim, each comprising a multimode optical fiber core fragment coated with a SnO₂ thin film. Layer by layer (LbL) coatings made of 1, 2 and 4 bilayers of polyethyleneimine (PEI) and graphene oxide were deposited onto three of these devices and their behavior as aqueous ethanol sensors was characterized and compared with the sensor without GO. The sensors with GO showed much better performance with a maximum sensitivity enhancement of 176% with respect to the sensor without GO. To our knowledge, this is the first time that GO has been used to make an optical fiber sensor based on LMR.

  15. CONACS: the DOE safety analysis system

    International Nuclear Information System (INIS)

    Martin, F.J.; Armstrong, G.R.; Niccoli, L.G.

    1985-03-01

    The CONtainment Analysis Code System (CONACS) is a large, comprehensive scientific simulation system for predicting conditions in an LMR facility following the occurrence of a postulated accident. It has now been developed to a stage of completion that can be referred to as a limited operational version. This version forms a permanent portion of the ultimate system. Because CONACS was developed with change in mind, it is now possible to draw on this strength to respond to changing requirements arising from advanced design concepts. The generalized design applications in the nuclear and non-nuclear fields and the quality assurance applied to the project make those adaptations reliable. In this paper the results of prototype tests and the implications of limited version tests are presented along with a brief description of CONACS and its relationship to LMR design optimization and cost reduction

  16. The neutronic and fuel cycle performance of interchangeable 3500 MWth metal and oxide fueled LMRs

    International Nuclear Information System (INIS)

    Fujita, E.K.; Wade, D.C.

    1990-01-01

    This study summarizes the neutronic and fuel cycle analysis performed at Argonne National Laboratory for an oxide and a metal fueled 3500 MWth LMR. These reactor designs formed the basis for a joint US/European study of LMR ATWS events. The oxide and metal core designs were developed to meet reactor performance specifications that are constrained by requirements for core loading interchangeability and for a small burnup reactivity swing. Differences in the computed performance parameters of the oxide and metal cores, arising from basic differences in their neutronic characteristics, are identified and discussed. It is shown that metal and oxide cores designed to the same ground rules exhibit many similar performance characteristics; however, they differ substantially in reactivity coefficients, control strategies, and fuel cycle options. 12 refs., 2 figs., 12 tabs

  17. Verification of Remote Inspection Techniques for Reactor Internal Structures of Liquid Metal Reactor

    International Nuclear Information System (INIS)

    Joo, Young Sang; Lee, Jae Han

    2007-02-01

    The reactor internal structures and components of a liquid metal reactor (LMR) are submerged in hot sodium of reactor vessel. The division 3 of ASME code section XI specifies the visual inspection as major in-service inspection (ISI) methods of reactor internal structures and components. Reactor internals of LMR can not be visually examined due to opaque liquid sodium. The under-sodium viewing techniques using an ultrasonic wave should be applied for the visual inspection of reactor internals. Recently, an ultrasonic waveguide sensor with a strip plate has been developed for an application to the under-sodium inspection. In this study, visualization technique, ranging technique and monitoring technique have been suggested for the remote inspection of reactor internals by using the waveguide sensor. The feasibility of these remote inspection techniques using ultrasonic waveguide sensor has been evaluated by an experimental verification

  18. Irradiation behavior of metallic fast reactor fuels

    International Nuclear Information System (INIS)

    Pahl, R.G.; Porter, D.L.; Crawford, D.C.; Walters, L.C.

    1991-01-01

    Metallic fuels were the first fuels chosen for liquid metal cooled fast reactors (LMR's). In the late 1960's world-wide interest turned toward ceramic LMR fuels before the full potential of metallic fuel was realized. However, during the 1970's the performance limitations of metallic fuel were resolved in order to achieve a high plant factor at the Argonne National Laboratory's Experimental Breeder Reactor II. The 1980's spawned renewed interest in metallic fuel when the Integral Fast Reactor (IFR) concept emerged at Argonne National Laboratory. A fuel performance demonstration program was put into place to obtain the data needed for the eventual licensing of metallic fuel. This paper will summarize the results of the irradiation program carried out since 1985

  19. A low cost liquid metal reactor design

    International Nuclear Information System (INIS)

    Arnold, W.H.; Anderson, C.A.; Mangus, J.D.

    1984-01-01

    A new, compact Liquid Metal Reactor (LMR) plant arrangement designed by Westinghouse, featuring factory-fabricated modules and an integrated fuel cycle facility, has made it possible to project a commercially competitive LMR plant for the near future. This innovative liquid metal-cooled plant design will allow a combination of capital, fuel, operation and maintenance costs that could be lower than today's fossil-fueled or light water reactor plant costs, and incorporate features which enhance public safety even beyond current high standards. Following early core loadings, the plant feeds only on depleted uranium. No shipment of fuel is required. And the plant can be tailored to produce enough plutonium to meet its need or to provide fuel for other nuclear plants

  20. Human leukocyte mobilization and morphology in nickel contact allergy using a skin chamber technique

    DEFF Research Database (Denmark)

    Lerche, A; Bisgaard, H; Christensen, J D

    1981-01-01

    An improved skin chamber technique has been devised and used for quantitative evaluation of the leukocyte mobilization rate (LMR). The method was applied in 10 nickel-hypersensitive patients exposed to nickel sulphate. Each patient served as his own control and for additional control purpose, 5...... healthy individuals without nickel hypersensitivity were studied. The kinetics of the mobilized leukocytes were followed over a 48-hour period. After an initial lag phase of 2-4 hours, maximum migration was observed from the 24th to the 48th hour, with a wide interindividual variability in the number...... of mobilized cells at the time of maximum LMR response. The median cumulative leukocyte count was 1.412 x 10(6) leukocytes/cm2/48 h. In the same period a statistically significant increase in the basophils for all the nickel allergic patients was observed. In 8 out of 10 patients a statistically significant...

  1. Distributed resistance model for the analysis of wire-wrapped rod bundles

    International Nuclear Information System (INIS)

    Ha, K. S.; Jung, H. Y.; Kwon, Y. M.; Jang, W. P.; Lee, Y. B.

    2003-01-01

    A partial flow blockage within a fuel assembly in liquid metal reactor may result in localized boiling or a failure of the fuel cladding. Thus, the precise analysis for the phenomenon is required for a safe design of LMR. MATRA-LMR code developed by KAERI models the flow distribution in an assembly by using the wire forcing function to consider the effects of wire-wrap spacers, which is important to the analysis for flow blockage. However, the wire forcing function does not have the capabilities of analysis when the flow blockage is occurred. And thus this model was altered to the distributed resistance model and the validation calculation was carried out against to the experiment of FFM 2A

  2. Evaluating the efficacy of a minor actinide burner

    International Nuclear Information System (INIS)

    Dobbin, K.D.; Kessler, S.F.; Nelson, J.V.; Omberg, R.P.; Wootan, D.W.

    1993-06-01

    The efficacy of a minor actinide burner can be evaluated by comparing safety and economic parameters to the support ratio. Minor actinide mass produced per unit time in this number of Light Water Reactors (LWRs) can be burned during the same time period in one burner system. The larger the support ratio for a given set of safety and economic parameters, the better. To illustrate this concept, the support ratio for selected Liquid Metal Reactor (LMR) burner core designs was compared with corresponding coolant void worths, a fundamental safety concern following the Chernobyl accident. Results can be used to evaluate the cost in reduced burning of minor actinides caused by LMR sodium void reduction efforts or to compare with other minor actinide burner systems

  3. CONACS, the DOE safety analysis system

    International Nuclear Information System (INIS)

    Martin, F.J.; Armstrong, G.R.; Niccoli, L.G.

    1985-01-01

    The CONtainment Analysis Code System (CONACS) is a large, comprehensive scientific simulation system for predicting conditions in an LMR facility following the occurrence of a postulated accident. It has now been developed to a stage of completion that can be referred to as a limited operational version. This version forms a permanent portion of the ultimate system. Because CONACS was developed with change in mind it is now possible to draw on this strength to respond to changing requirements arising from advanced design concepts. The generalized design applications in the nuclear and non-nuclear fields and the quality assurance applied to the project make those adaptations reliable. In this paper the results of prototype tests and the implications of limited version tests are presented along with a brief description of CONACS and its relationship to LMR design optimization and cost reduction

  4. Liquid metal reactor/Pressurized water reactor plant comparison study

    International Nuclear Information System (INIS)

    Halverson, T.G.

    1986-01-01

    The selection between alternative electric power generating technologies is mainly based on their overall economics. Capital costs account for over 60% of the total busbar cost of nuclear plants. Estimates reported in the literature have shown capital cost ratios of LMRs to PWRs ranging from less than 1 to as high as 1.8. To reduce this range of uncertainty, the study selected a method for cataloging plant hardware and then performed comparisons using engineering judgment as to the anticipated and reasonable cost differences. The paper summarizes the resulting one-on-one comparisons of components, systems, and buildings and identifies the LMR-PWR similarities and differences which influence costs. The study leads to the conclusion that the capital cost of the most up-to-date large LMR design would be very close to that of the latest PWRs

  5. Hierarchical graphical-based human pose estimation via local multi-resolution convolutional neural network

    Science.gov (United States)

    Zhu, Aichun; Wang, Tian; Snoussi, Hichem

    2018-03-01

    This paper addresses the problems of the graphical-based human pose estimation in still images, including the diversity of appearances and confounding background clutter. We present a new architecture for estimating human pose using a Convolutional Neural Network (CNN). Firstly, a Relative Mixture Deformable Model (RMDM) is defined by each pair of connected parts to compute the relative spatial information in the graphical model. Secondly, a Local Multi-Resolution Convolutional Neural Network (LMR-CNN) is proposed to train and learn the multi-scale representation of each body parts by combining different levels of part context. Thirdly, a LMR-CNN based hierarchical model is defined to explore the context information of limb parts. Finally, the experimental results demonstrate the effectiveness of the proposed deep learning approach for human pose estimation.

  6. Improvement of remote monitoring on water quality in a subtropical reservoir by incorporating grammatical evolution with parallel genetic algorithms into satellite imagery.

    Science.gov (United States)

    Chen, Li; Tan, Chih-Hung; Kao, Shuh-Ji; Wang, Tai-Sheng

    2008-01-01

    Parallel GEGA was constructed by incorporating grammatical evolution (GE) into the parallel genetic algorithm (GA) to improve reservoir water quality monitoring based on remote sensing images. A cruise was conducted to ground-truth chlorophyll-a (Chl-a) concentration longitudinally along the Feitsui Reservoir, the primary water supply for Taipei City in Taiwan. Empirical functions with multiple spectral parameters from the Landsat 7 Enhanced Thematic Mapper (ETM+) data were constructed. The GE, an evolutionary automatic programming type system, automatically discovers complex nonlinear mathematical relationships among observed Chl-a concentrations and remote-sensed imageries. A GA was used afterward with GE to optimize the appropriate function type. Various parallel subpopulations were processed to enhance search efficiency during the optimization procedure with GA. Compared with a traditional linear multiple regression (LMR), the performance of parallel GEGA was found to be better than that of the traditional LMR model with lower estimating errors.

  7. Hierarchical graphical-based human pose estimation via local multi-resolution convolutional neural network

    Directory of Open Access Journals (Sweden)

    Aichun Zhu

    2018-03-01

    Full Text Available This paper addresses the problems of the graphical-based human pose estimation in still images, including the diversity of appearances and confounding background clutter. We present a new architecture for estimating human pose using a Convolutional Neural Network (CNN. Firstly, a Relative Mixture Deformable Model (RMDM is defined by each pair of connected parts to compute the relative spatial information in the graphical model. Secondly, a Local Multi-Resolution Convolutional Neural Network (LMR-CNN is proposed to train and learn the multi-scale representation of each body parts by combining different levels of part context. Thirdly, a LMR-CNN based hierarchical model is defined to explore the context information of limb parts. Finally, the experimental results demonstrate the effectiveness of the proposed deep learning approach for human pose estimation.

  8. Development of Korea advanced liquid metal reactor

    International Nuclear Information System (INIS)

    Park, C.K.

    1998-01-01

    Future nuclear power plants should not only have the features of improved safety and economic competitiveness but also provide a means to resolve spent fuel storage problems by minimizing volume of high level wastes. It is widely believed that liquid metal reactors (LMRs) have the highest potential of meeting these requirements. In this context, the LMR development program was launched as a national long-term R and D program in 1992, with a target to introduce a commercial LMR around 2030. Korea Advanced Liquid Metal Reactor (KALIMER), a 150 MWe pool-type sodium cooled prototype reactor, is currently under the conceptual design study with the target schedule to complete its construction by the mid-2010s. This paper summarizes the KALIMER development program and major technical features of the reactor system. (author)

  9. Performance and health responses of dairy calves offered different milk replacer allowances.

    Science.gov (United States)

    Bach, A; Terré, M; Pinto, A

    2013-01-01

    Eighty female Holstein calves (12±4.1 d of age and 42±4.3 kg of BW) were collected from different herds, brought to the study site, and blocked by age and assigned to either a 6 L/d maximum daily milk replacer (MR) allowance (LMR) or a maximum MR allowance of 8 L/d (HMR). Calves were kept in individual hutches until 52 d of age and then moved into pens, forming groups of 10. All calves had ad libitum access to a mash starter feed. Calves in both treatments received the MR distributed in 3 separate allotments between 1 wk after the beginning of the study and 52 d of age. Then, all calves were moved to group pens and preweaned by offering 2 L/calf of the same MR twice daily in a trough until the age of 59 d, when MR offer was further reduced to a single dose of 2 L until the age of 73 d, when all calves were completely weaned. Individual starter feed and MR consumption was recorded on a daily basis until 52 d of age, and on a group basis until weaning time. Body weight was measured at the beginning of the study and at 52 (preweaning), 73 (weaning), and 110, 160, and 228 d of age. Solid feed consumption (mean ± SE) was greater in LMR (821±42.1 g/d) than in HMR calves (462±42.1 g/d) between 42 d of age and 52 d (preweaning). As expected, as age increased, solid feed consumption increased, and LMR showed a more marked increase than HMR calves. Despite the greater solid feed intake of LMR calves, HMR grew faster than LMR calves until preweaning time, but from preweaning to weaning, LMR calves grew more than HMR calves (977 vs. 857±30.7 g/d, respectively; mean ± SE). No differences in feed efficiency were observed. While calves were individually housed, no differences were observed in the incidence of bovine respiratory disease or diarrhea between treatment groups. We concluded that, under the milk regimen, age range of calves, and weaning method used in the current study, before preweaning, HMR calves grow more than LMR calves, but between preweaning and weaning

  10. Nonlinear structural analysis methods and their application to elevated temperature design: A US perspective

    International Nuclear Information System (INIS)

    Dhalla, A.K.

    1989-01-01

    Technological advances over the last two decades have been assimilated into the routine design of Liquid Metal Reactor (LMR) structural components operating at elevated temperatures. The mature elevated temperature design technology is based upon: (a) an extensive material data base, (b) recent advances in nonlinear computational methods, and (c) conservative design criteria based upon past successful and reliable operating experiences with petrochemical and nonnuclear power plants. This survey paper provides a US perspective on the role of nonlinear analysis methods used in the design of LMR plants. The simplified and detailed nonlinear analysis methods and the level of computational effort required to qualify structural components for safe and reliable long-term operation are discussed. The paper also illustrates how a detailed nonlinear analysis can be used to resolve technical licensing issues, to understand complex nonlinear structural behavior, to identify predominant failure modes, and to guide future experimental programs

  11. A faster reactor transient analysis methodology for PCs

    International Nuclear Information System (INIS)

    Ott, K.O.

    1991-10-01

    The simplified ANL model for LMR transient analysis, in which point kinetics as well as lumped descriptions of the heat transfer equations in all components are applied, is converted from a differential into an integral formulation. All differential balance equations are implicitly solved in terms of convolution integrals. The prompt jump approximation is applied as the strong negative feedback effectively keeps the net reactivity well below prompt critical. After implicit finite differencing of the convolution integrals, the kinetics equation assumes the form of a quadratic equation, the ''quadratic dynamics equation.'' This model forms the basis for GW-BASIC program, LTC, for LMR Transient Calculation program, which can effectively be run on a PC. The GW-BASIC version of the LTC program is described in detail in Volume 2 of this report

  12. Verification of Remote Inspection Techniques for Reactor Internal Structures of Liquid Metal Reactor

    Energy Technology Data Exchange (ETDEWEB)

    Joo, Young Sang; Lee, Jae Han

    2007-02-15

    The reactor internal structures and components of a liquid metal reactor (LMR) are submerged in hot sodium of reactor vessel. The division 3 of ASME code section XI specifies the visual inspection as major in-service inspection (ISI) methods of reactor internal structures and components. Reactor internals of LMR can not be visually examined due to opaque liquid sodium. The under-sodium viewing techniques using an ultrasonic wave should be applied for the visual inspection of reactor internals. Recently, an ultrasonic waveguide sensor with a strip plate has been developed for an application to the under-sodium inspection. In this study, visualization technique, ranging technique and monitoring technique have been suggested for the remote inspection of reactor internals by using the waveguide sensor. The feasibility of these remote inspection techniques using ultrasonic waveguide sensor has been evaluated by an experimental verification.

  13. Scanning Tunneling Microscopy study and unusual transport properties of the topological semimetal a-Sn

    Science.gov (United States)

    Ruan, Jiawei

    Weyl semimetals are new states of quantum matter with topological Weyl nodes near Fermi level in the bulk and Fermi arcs at the surface, which are paid a lot attention in recently years. Here#¬we report another topological semimetal a-Sn., which is double Weyl semimetal in the magnetic field and Dirac semimetal in an appropriate in-plane strain. By combing Landau level spectroscopy and quasiparticle interference, we obtain the linear dispersion near the Dirac point within strain while quadratic band dispersion near Γpoint without strain. We also observe the negative longitudinal magnetoresistance (LMR) in both two system, which is caused by chiral anomaly. However ,the LMR profiles of strained a-Sn have a little rise and then descend while the unstrained one drop directly, which is due to the different type of Weyl semimetal and further confirm our prediction.

  14. Magnetoresistance in amorphous NdFeB/FeB compositionally modulated multilayers

    International Nuclear Information System (INIS)

    Peral, G.; Briones, F.; Vicent, J.L.

    1991-01-01

    Resistance measurements have been done in amorphous Nd 12 Fe 80 B 8 sputtered films and in amorphous sputtered Nd 26 Fe 68 B 6 /Fe 92 B 8 multilayers between 6 and 150 K with applied magnetic field parallel (LMR) and perpendicular (TMR) up to 7 T. The samples were grown by dc triode sputtering, with nominal unequal (2:1) layer thicknesses. The layered character of the samples have been tested by x-ray diffraction. Longitudinal magnetoresistance (LMR) is positive and transverse magnetoresistance (TMR) is negative. The magnetoresistance values are higher than in amorphous ferromagnets, and multilayering of these alloys produces much larger magnetoresistance values than either alloy alone and there is a strong dependence on the multilayer wavelength. The MR shows a weak temperature dependence in the temperature interval that was investigated

  15. Fast reactor of 1.000 MWt started with U-Zr

    International Nuclear Information System (INIS)

    Nascimento, J.A.; Ishiguro, Y.

    1990-01-01

    A U-Zr fueled 1000 MWt liquid metal reactor (LMR) to be used in a second step of the fast breeder reactor development program that we propose for Brazil is studied. Initially, principal technological aspects and cost trends are reviewed in order to place this type of reactors in a proper perspective regarding their application to electric power generation. Then two models are compared and one is selected for cycle-by-cycle analysis isotopic evolution and parameters of interest such as the Doppler effect, sodium void reactivity, control requirement and availability, resources consumption, and enrichment requirement. The analysed model is quite adequate for the phase for which it is considered due to its high degree of inherent safety, which should contribute to a better public acceptance of nuclear energy. In addition, its introduction with enriched uranium, available in the country, allows an autonomous development of LMR which is a better alternative to the PWR meeting for future power demand. (author)

  16. A preliminary safety analysis for the prototype Gen IV Sodium-Cooled Fast Reactor

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Kwi Lim; Ha, Kwi Seok; Jeong, Jae Ho; Choi, Chi Woong; Jeong, Tae Kyeong; Ahn, Sang June; Lee, Seung Won; Chang, Won Pyo; Kang, Seok Hun; Yoo, Jae Woon [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2016-10-15

    Korea Atomic Energy Research Institute has been developing a pool-type sodium-cooled fast reactor of the Prototype Gen-IV Sodium-cooled Fast Reactor (PGSFR). To assess the effectiveness of the inherent safety features of the PGSFR, the system transients during design basis accidents and design extended conditions are analyzed with MARS-LMR and the subchannel blockage events are analyzed with MATRA-LMR-FB. In addition, the in-vessel source term is calculated based on the super-safe, small, and simple reactor methodology. The results show that the PGSFR meets safety acceptance criteria with a sufficient margin during the events and keeps accidents from deteriorating into more severe accidents.

  17. Analytical study of sodium combustion phenomena under sodium leak accidents

    International Nuclear Information System (INIS)

    Kim, Byung Ho; Jeong, J. Y.; Jeong, K. C.; Kim, T. J.; Choi, J. H.

    2001-12-01

    The rise of temperature and pressure, the release of aerosol in the buildings as a result of sodium fire must be considered for the safety measures of LMR. Therefore for the safety of the LMR, it is necessary to understand the characteristics of sodium fire, resulting from the various type of leakage. ASSCOPS(Analysis of Simultaneous Sodium Combustion in Pool and Spray) is the computer code for the analysis of the thermal consequence of sodium leak and fire in LMR that has been developed by Japan Nuclear Cycle Development Institute(JNC) in Japan. In this study, a preliminary analysis of sodium leak and fire accidents in S/G building of KALIMER is made by using ASSCOPS code. Various phenomena of interest are spray and pool burning, peak pressure, temperature change, local structure temperature, aerosol behavior, drain system into smothering tank, ventilation characteristics at each cell with the safety venting system and nitrogen injection system. In this calculation, the dimension of the S/G building was chosen in accordance with the selected options of LMR name KALIMER(Korea). As a result of this study, it was shown that subsequent effect of sodium fire depended upon whether the sodium continued to leak from the pipe or not, whether the ventilation system was running, whether the inert gas injection system was provided, whether the sodium on floor was drained into the smothering tank or not, whether the building was sealed or not, etc. Specially the excessive rise of pressure into each cell was prevented by installing the pressure release plates on wall of the building

  18. Lyme neuroborreliosis

    DEFF Research Database (Denmark)

    Hansen, Klaus; Crone, Clarissa; Kristoferitsch, Wolfgang

    2013-01-01

    as a lymphocytic meningoradiculoneuritis (LMR). Symptoms are mainly due to a painful sensory radiculitis and a multifocal motor radiculo-neuritis. Fifty percent have cranial nerve involvement predominantly uni- or bilateral facial nerve palsies. Meningitic symptoms occur primarily in children. Nerve biopsies......, autopsies, animal models, and nerve conduction studies showed that the pathology is a lymphocytic perineuritis leading to multisegmental axonal injury of nerve roots, spinal ganglia, and distal nerve segments. Due to meningeal and root inflammation cerebrospinal fluid (CSF) shows lymphocytic inflammation...

  19. Improving DLA Aviation Engineering’s Support to its Customers and the DoD Supply Chain

    Science.gov (United States)

    2014-10-01

    Report and issued DMRD 926 under the same title. The report’s central recommendation transferred Item Management (IM) responsibilities for...3200.1 and other related functions are more appropriately addressed in a DoDI sponsored by ASD (L&MR). Currently, there is no DoDI that addresses...appropriate, of DCMA to perform in-plant quality assurance, and the option to conduct PLT when circumstances warrant, must be combined in a coherent and

  20. Improving maintenance of lost weight following a commercial liquid meal replacement program: a preliminary study.

    Science.gov (United States)

    Ames, Gretchen E; Patel, Roshni H; McMullen, Jillian S; Thomas, Colleen S; Crook, Julia E; Lynch, Scott A; Lutes, Lesley D

    2014-01-01

    Clinic-based liquid meal replacement (800kcals/day) programs produce substantial weight loss. Nevertheless, long-term maintenance remains a challenge. A limitation of maintenance programs is that they continue to promote large behavior changes that are initially required to induce weight loss which may be unsustainable long-term. The study aims were to conduct a preliminary assessment of the feasibility, acceptability, and effectiveness of a small changes maintenance intervention (SCM) for 30 patients who completed liquid meal replacement program (LMR). The 20-session SCM delivered over 52 weeks offered no preset goals for maintenance behaviors and all changes in behavior were self-selected. Participants had a median BMI of 40.9 kg/m(2) and weight of 111 kg at the start of LMR. At LMR completion, they lost 18% (21 kg) of body weight. The SCM was completed by 22 patients (73%); 19 completers (86%) attended ≥ 17 of 20 sessions with a median satisfaction rating of 9 (on a scale of 1 to 9). Completers were asked to record self-selected maintenance behaviors daily (median 351 days recorded). The most commonly reported daily behaviors were self-weighing, use of meal replacements and step counting. Median percent regain at week 52 was 14% (2.8 kg) of lost weight (range, -42 to 74%), significantly less than a median of 56% (11 kg) percent regain of lost weight (range, -78 to 110%) in a demographically similar historical control group with no maintenance intervention after LMR completion (P<0.001). Thus, SCM holds promise for improving weight maintenance. Future research should compare SCM to standard maintenance programs that promote large program-directed changes. © 2013.

  1. Evaluation of conceptual flowsheets for incorporating Light Water Reactor (LWR) fuel materials in an advanced nuclear fuel cycle

    International Nuclear Information System (INIS)

    Bell, J.T.; Burch, W.D.; Collins, E.D.; Forsberg, C.W.; Prince, B.E.; Bond, W.D.; Campbell, D.O.; Delene, J.G.; Mailen, J.C.

    1990-08-01

    A preliminary study by a group of experts at ORNL has generated and evaluated a number of aqueous and non-aqueous flowsheets for recovering transuranium actinides from LWR fuel for use as fuel in an LMR and, at the same time, for transmutation of the wastes to less hazardous materials. The need for proliferation resistance was a consideration in the flowsheets. The current state of development of the flowsheets was evaluated and recommendations for additional study were made. 3 refs., 6 figs

  2. The Experimental Characterization of the Magnetic Field Effect on a Liquid Sodium Flow

    International Nuclear Information System (INIS)

    Kim, Hee Reyoung; Kim, Jong Man; Cha, Jae Eun; Choi, Jong Hyun; Nam, Ho Yoon

    2006-01-01

    A liquid sodium coolant is used for a LMR such as KALIMER and a magnetic field is generated in the electromagnetic pump or flowmeter. The magnetic field has an effect on the electrically conducting metal flow by a generation of an electromagnetic pressure drop. Therefore, in the present study, a theoretical calculation is carried out for the effect of an external magnetic field and the magnetic field is measured over the electromagnet system manufactured for the magnetohydrodynamic experiments

  3. The Theoretical Investigation of the Magnetic Field Effect on a Liquid Sodium Flow

    International Nuclear Information System (INIS)

    Kim, Hee Reyoung; Kim, Jong Man; Cha, Jae Eun; Choi, Jong Hyun; Nam, Ho Yoon

    2005-01-01

    The liquid sodium coolant is used for LMR such as KALIMER and magnetic field is generated in the electromagnetic pump or flowmeter. The magnetic field takes an effect on the electrically conducting metal flow by the generation of the electromagnetic pressure drop. Therefore, in the present study, the theoretical calculation is carried out for an effect from the external magnetic field and the magnetic field is firstly measured over the electromagnet system manufactured for the magnetohydrodynamic experiments

  4. Uncertainty reduction requirements in cores designed for passive reactivity shutdown

    International Nuclear Information System (INIS)

    Wade, D.C.

    1988-01-01

    The first purpose of this paper is to describe the changed focus of neutronics accuracy requirements existing in the current US advanced LMR development program where passive shutdown is a major design goal. The second purpose is to provide the background and rationale which supports the selection of a formal data fitting methodology as the means for the application of critical experiment measurements to meet these accuracy needs. 6 refs., 1 fig., 2 tabs

  5. Spatial mobility fluctuation induced giant linear magnetoresistance in multilayered graphene foam

    KAUST Repository

    Li, Peng

    2016-07-05

    Giant, positive, and near-temperature-independent linear magnetoresistance (LMR), as large as 340%, was observed in graphene foam with a three-dimensional flexible network. Careful analysis of the magnetoresistance revealed that Shubnikov–de Haas (SdH) oscillations occurred at low temperatures and decayed with increasing temperature. The average classical mobility ranged from 300 (2 K) to 150 (300 K) cm2V−1s−1, which is much smaller than that required by the observed SdH oscillations. To understand the mechanism behind the observation, we performed the same measurements on the microsized graphene sheets that constitute the graphene foam. Much more pronounced SdH oscillations superimposed on the LMR background were observed in these microscaled samples, which correspond to a quantum mobility as high as 26,500cm2V−1s−1. Moreover, the spatial mobility fluctuated significantly from 64,200cm2V−1s−1 to 1370cm2V−1s−1, accompanied by a variation of magnetoresistance from near 20,000% to less than 20%. The presence of SdH oscillations actually excludes the possibility that the observed LMR originated from the extreme quantum limit, because this would demand all electrons to be in the first Landau level. Instead, we ascribe the large LMR to the second case of the classical Parish and Littlewood model, in which spatial mobility fluctuation dominates electrical transport. This is an experimental confirmation of the Parish and Littlewood model by measuring the local mobility randomly (by measuring the microsized graphene sheets) and finding the spatial mobility fluctuation.

  6. Status of liquid metal reactor development in the United States of America

    International Nuclear Information System (INIS)

    Griffith, J.D.; Horton, K.E.

    1989-01-01

    The United States has made substantial progress in achieving LMR programme objectives. A decision was made in 1988 to select the General Electric ALMR concept known as PRISM (Power Reactor Innovative Safe Module) for advanced conceptual design. A 3-year contract was awarded to General Electric in January of this year for concentrated trade-off studies and advanced design development. The strategy is to integrate those advancements that best meet programme objectives into a national ALMR system concept. (author). 8 figs

  7. Licensing issues for inherently safe fast reactors

    International Nuclear Information System (INIS)

    Kastenberg, W.E.; Lee, S.; Okrent, D.

    1986-01-01

    There has been considerable interest recently in a new generation of liquid metal reactor (LMR) concepts in the US. Some significant changes in regulatory philosophy will be required if the anticipated cost advantages of inherently safe designs are to be achieved. The defense in depth philosophy will need to be significantly re-evaluated in the context of inherently safe reactors. It is the purpose of this paper to begin such a re-evaluation of this regulatory philosophy

  8. Passive safety and the advanced liquid metal reactors

    International Nuclear Information System (INIS)

    Hill, D.J.; Pedersen, D.R.; Marchaterre, J.F.

    1988-01-01

    Advanced Liquid Metal Reactors being developed today in the USA are designed to make maximum use of passive safety features. Much of the LMR safety work at Argonne National Laboratory is concerned with demonstrating, both theoretically and experimentally, the effectiveness of the passive safety features. The characteristics that contribute to passive safety are discussed, with particular emphasis on decay heat removal systems, together with examples of Argonne's theoretical and experimental programs in this area

  9. A measurement-based method for predicting margins and uncertainties for unprotected accidents in the Integral Fast Reactor concept

    International Nuclear Information System (INIS)

    Vilim, R.B.

    1990-01-01

    A measurement-based method for predicting the response of an LMR core to unprotected accidents has been developed. The method processes plant measurements taken at normal operation to generate a stochastic model for the core dynamics. This model can be used to predict three sigma confidence intervals for the core temperature and power response. Preliminary numerical simulations performed for EBR-2 appear promising. 6 refs., 2 figs

  10. Concept Study of Multi Sensor Detection Imaging and Explosive Confirmation of Mines

    Science.gov (United States)

    1998-03-20

    surface feature removal can be achieved in LMR images. Small Business Technology Transfer (STTR) Solicitation Topic 97T006 Mufi -Sensor Detection...divided by the applied voltage. This is mathematically given by: 00 Y-I-G+jB = 1o+2E’. COS m4; m1l 1-1 = j120 72(+a) where G = the input conductance...of detector operation that are incorporated into a mathematical algorithm to convert detector impedance characteristics into recognizable indicators

  11. Improved Detection of Microsatellite Instability in Early Colorectal Lesions.

    Directory of Open Access Journals (Sweden)

    Jeffery W Bacher

    Full Text Available Microsatellite instability (MSI occurs in over 90% of Lynch syndrome cancers and is considered a hallmark of the disease. MSI is an early event in colon tumor development, but screening polyps for MSI remains controversial because of reduced sensitivity compared to more advanced neoplasms. To increase sensitivity, we investigated the use of a novel type of marker consisting of long mononucleotide repeat (LMR tracts. Adenomas from 160 patients, ranging in age from 29-55 years old, were screened for MSI using the new markers and compared with current marker panels and immunohistochemistry standards. Overall, 15 tumors were scored as MSI-High using the LMRs compared to 9 for the NCI panel and 8 for the MSI Analysis System (Promega. This difference represents at least a 1.7-fold increase in detection of MSI-High lesions over currently available markers. Moreover, the number of MSI-positive markers per sample and the size of allelic changes were significantly greater with the LMRs (p = 0.001, which increased confidence in MSI classification. The overall sensitivity and specificity of the LMR panel for detection of mismatch repair deficient lesions were 100% and 96%, respectively. In comparison, the sensitivity and specificity of the MSI Analysis System were 67% and 100%; and for the NCI panel, 75% and 97%. The difference in sensitivity between the LMR panel and the other panels was statistically significant (p<0.001. The increased sensitivity for detection of MSI-High phenotype in early colorectal lesions with the new LMR markers indicates that MSI screening for the early detection of Lynch syndrome might be feasible.

  12. An Analysis of Department Of Defense Policy and Guidance for Implementation of Performance-Based Logistics

    Science.gov (United States)

    2015-09-01

    stability to the provider’s order book and adds shareholder value . Incentives that focus on profit may not be applicable for public facilities, but... Stakeholders (from ASD (L&MR) 2011b, 17) ...............3  Figure 3.  System Life Cycle Illustration (from Secretary of Defense 2014, 2–1) ...........5...Figure 2 is provided to show the roles, relationships, responsibilities and business agreements among the various key product support stakeholders

  13. Vibrational characterization of hexagonal duct core assemblies under various support conditions

    International Nuclear Information System (INIS)

    Bartholf, L.W.; Julyk, L.J.; Ryan, J.A.

    1989-03-01

    Analysis of the dynamic response of advanced Liquid Metal Reactor (LMR) core internals to seismic excitation requires a significant number of simplifying assumptions and idealizations to economically meet the constraints of present-day computer limitations. Fluid coupling and nonlinearities associated with inter-assembly lateral support stiffness and clearances of a large cluster of core internal assemblies are some of the factors that complicate the analytical procedure (Moran, 1976). Well defined test data were needed to quantify these and other uncertainties associated with the use of analytical or numerical computer codes used in the seismic design and analysis of reactor cores. The purpose of the present experimental program was to supplement existing data, such as reported in (Sasaki and Muto, 1983), by developing vibrational characteristics of core assemblies over a range of parameters relative to LMR conceptual designs. The parameters selected for this program were variations in number and location of restraints, restraint-pad to duct-load-pad clearances, and input forcing frequency and g-level. Feature tests were conducted to characterize load pad stiffness and coefficient of restitution, and to calibrate load pads to measure inter-assembly across-flat impact loads. Simulated full-size LMR hexagonal duct core assemblies were used in vibration tests. A single assembly and a row of five assemblies were tested in air to establish modal characteristics and forced response behavior. 2 refs., 7 figs., 1 tab

  14. Optical Detection of Ketoprofen by Its Electropolymerization on an Indium Tin Oxide-Coated Optical Fiber Probe.

    Science.gov (United States)

    Bogdanowicz, Robert; Niedziałkowski, Paweł; Sobaszek, Michał; Burnat, Dariusz; Białobrzeska, Wioleta; Cebula, Zofia; Sezemsky, Petr; Koba, Marcin; Stranak, Vitezslav; Ossowski, Tadeusz; Śmietana, Mateusz

    2018-04-27

    In this work an application of optical fiber sensors for real-time optical monitoring of electrochemical deposition of ketoprofen during its anodic oxidation is discussed. The sensors were fabricated by reactive magnetron sputtering of indium tin oxide (ITO) on a 2.5 cm-long core of polymer-clad silica fibers. ITO tuned in optical properties and thickness allows for achieving a lossy-mode resonance (LMR) phenomenon and it can be simultaneously applied as an electrode in an electrochemical setup. The ITO-LMR electrode allows for optical monitoring of changes occurring at the electrode during electrochemical processing. The studies have shown that the ITO-LMR sensor’s spectral response strongly depends on electrochemical modification of its surface by ketoprofen. The effect can be applied for real-time detection of ketoprofen. The obtained sensitivities reached over 1400 nm/M (nm·mg −1 ·L) and 16,400 a.u./M (a.u.·mg −1 ·L) for resonance wavelength and transmission shifts, respectively. The proposed method is a valuable alternative for the analysis of ketoprofen within the concentration range of 0.25⁻250 μg mL −1 , and allows for its determination at therapeutic and toxic levels. The proposed novel sensing approach provides a promising strategy for both optical and electrochemical detection of electrochemical modifications of ITO or its surface by various compounds.

  15. A fast reactor transient analysis methodology for personal computers

    International Nuclear Information System (INIS)

    Ott, K.O.

    1993-01-01

    A simplified model for a liquid-metal-cooled reactor (LMR) transient analysis, in which point kinetics as well as lumped descriptions of the heat transfer equations in all components are applied, is converted from a differential into an integral formulation. All 30 differential balance equations are implicitly solved in terms of convolution integrals. The prompt jump approximation is applied as the strong negative feedback effectively keeps the net reactivity well below prompt critical. After implicit finite differencing of the convolution integrals, the kinetics equation assumes a new form, i.e., the quadratic dynamics equation. In this integral formulation, the initial value problem of typical LMR transients can be solved with large item steps (initially 1 s, later up to 256 s). This then makes transient problems amenable to a treatment on personal computer. The resulting mathematical model forms the basis for the GW-BASIC program LMR transient calculation (LTC) program. The LTC program has also been converted to QuickBASIC. The running time for a 10-h transient overpower transient is then ∼40 to 10 s, depending on the hardware version (286, 386, or 486 with math coprocessors)

  16. The feasibility study on fuel types for the KALIMER

    International Nuclear Information System (INIS)

    Hwang, W.; Nam, C.; Yim, J. S.; Na, B. C.; Hahn, D. H.; Kim, Y. I.; Kim, Y. C.; Park, C. K.

    1997-08-01

    The economics of LMR is largely dependent on the construction cost of the power plant, and the fuel cycle options usually constitute 20 to 30 % of total electricity generation cost. The choice of fuel cycle technology and the fuel type is important in order to develop a LMR with better economics, performance and safety. The LMR fuel types, whose performances have been proven up to 15 at% burnup, are MOX and IFR metal fuel. The base alloy, binary (U-10% Zr) metal fuel with HT9 is used as structural materials of KALIMER. The design concept of KALIMER fuel has been established through the investigation of technical feasibilities on the fuel and recycle systems for MOX and IFR metal fuel. According to the results of comparative analysis for MOX and metal fuel, metal fuel is better than MOX in view of safety, in-reactor performance, nuclear characteristics, economics and non-proliferation, while MOX fuels have advantages in the developmental status and technical cooperation potential. The overall performance of binary (U-10% Zr) metal fuel with HT9 cladding, which is a potential start-up fuel for KALIMER, is not only superior to that of MOX fuel, but also has enough technical feasibility in its high-burnup performance, safety and economics. (author). 54 ref., 13 tabs., 20 figs

  17. A critical prognostic analysis of neutrophil-lymphocyte ratio for patients undergoing nephroureterectomy due to upper urinary tract urothelial carcinoma.

    Science.gov (United States)

    Altan, Mesut; Haberal, Hakan Bahadır; Akdoğan, Bülent; Özen, Haluk

    2017-10-01

    To determine preoperative serum complete blood count parameters that affects survival of patients who underwent surgery for upper urinary tract urothelial cancer (UUT-UC). Since 1990, 150 patients underwent nephroureterectomy with bladder cuff excision for UUT-UC at Hacettepe University. Patients with a history of muscle-invasive bladder cancer, adjuvant chemotherapy or metastasis at the time of diagnosis were excluded. One hundred and thirteen patients without infective symptoms and with a full set of serum data were evaluated retrospectively. Effects of the neutrophil-lymphocyte ratio (NLR), lymphocyte-monocyte ratio (LMR), platelet-lymphocyte ratio (PLR), and leukocyte count on disease-free survival (DFS) and progression-free survival (PFS) were investigated. Threshold values for each parameter to predict PFS were calculated. The mean age and median follow-up were 63.7 ± 11.1 years and 34 (3-186) months, respectively. Male to female ratio was 86/27. The 5-years PFS (bladder recurrence was excluded) and DFS were 59.6 and 38.4%, respectively. In multivariate analysis, NLR was independent prognostic factor for PFS and DFS (p = 0.006 and p = 0.021, respectively) while LMR was prognostic only for PFS (p = 0.037). For UUT-UC, NLR is a prognostic factor for PFS and DFS, while LMR is a prognostic indicator for PFS in present series.

  18. The State-of-the-Art Report on the Liquid Metal Reactor

    International Nuclear Information System (INIS)

    Hahn, Do Hee; Kim, Yeong Il; Kim, Seong O; Lee, Jae Han; Lee, Yong Bum

    2006-03-01

    The status of the sodium cooled metal fuel core technology and the design methodology were described. The preliminary design concepts of the metal fuel core were established for KALIMER. A systematic study on the development fluid and I and C system has been carried out, and the conceptual design of NSSS of the 150MWe and 600MWe LMRs such as the design of PHTS, IHTS, RHRS, SGS and related technology with BOP is established together with the computational technology. The development of detection system of the sodium-water reaction, core blockage and the conceptual design of the control system of large capacity LMR are being carried. The important technological areas for mechanical structure design of LMR are high temperature thin structure design, seismic isolation design, In-Service- Inspection technology, and the economic design. The highlighted performances for the safety analysis were the developments of the containment analysis code CONTAIN-LMR-K, the safety analysis code SSC-K and the flow blockage analysis code. The safety criteria were set up, the safety analysis for the equilibrium core, the HCDA analysis, and the containment performance analysis were performed. The recent SSC-K 1.3 version turns out to be reliable after the indirect verification throughout qualitative/quantitative assessments

  19. Development of a transient calculation model for a closed sodium natural circulation loop

    International Nuclear Information System (INIS)

    Chang, Won Pyo; Ha, Kwi Seok; Jeong, Hae Yong; Heo, Sun; Lee, Yong Bum

    2003-09-01

    A natural circulation loop has usually adopted for a Liquid Metal Reactor (LMR) because of its high reliability. Up-rating of the current KALIMER capacity requires an additional PDRC to the existing PVCS to remove its decay heat under an accident. As the system analysis code currently used for LMR in Korea does not feature a stand alone capability to simulate a closed natural circulation loop, it is not eligible to be applied to PDRC. To supplement its limitation, a steady state calculation model had been developed during the first phase, and development of the transient model has successively carried out to close the present study. The developed model will then be coupled with the system analysis code, SSC-K to assess a long term cooling for the new conceptual design. The incompressibility assumption of sodium which allows the circuit to be modeled with a single loop flow, makes the model greatly simplified comparing with LWR. Some thermal-hydraulic models developed during this study can be effectively applied to other system analysis codes which require such component models, and the present development will also contribute to establishment of a code system for the LMR analysis

  20. Preservation of FFTF Data Related to Passive Safety Testing

    International Nuclear Information System (INIS)

    Wootan, David W.; Butner, R. Scott; Omberg, Ronald P.; Makenas, Bruce J.; Nielsen, Deborah L.

    2010-01-01

    One of the goals of the Fuel Cycle Research and Development Program (FCRD) is to preserve the knowledge that has been gained in the United States on Liquid Metal Reactors (LMR). A key area deserving special attention for preservation is the data relating to passive safety testing that was conducted in FFTF and EBR-II during the 1980's. Accidents at Unit 4 of the Chernobyl Station and Unit 2 at Three Mile Island changed the safety paradigm of the nuclear power industry. New emphasis was placed on assured safety based on intrinsic plant characteristics that protect not only the public, but the significant investment in the plant as well. Plants designated to perform in this manner are considered to be passively safe since no active sensor/alarm system or human intervention is required to bring the reactor to a safe shutdown condition. The liquid metal reactor (LMR) has several key characteristics needed for a passively safe reactor: reactor coolant with superior heat transfer capability and very high boiling point, low (atmospheric) system pressures, and reliable negative reactivity feedback. The credibility of the design for a passively safe LMR rests on two issues: the validity of analytic methods used to predict passive safety performance and the availability of relevant test data to calibrate design tools. Safety analysis methods used to analyze LMRs under the old safety paradigm were focused on calculating the source term for the Core Disruptive Accident. Passive safety design requires refined analysis methods for transient events because treatment of the detailed reactivity feedbacks is important in predicting the response of the reactor. Similarly, analytic tools should be calibrated against actual test experience in existing LMR facilities. The principal objectives of the combined FFTF natural circulation and Passive Safety Testing program were: (1) to verify natural circulation as a reliable means to safely remove decay heat, (2) to extend passive safety

  1. Evolution Of Lattice Structure And Chemical Composition Of The Surface Reconstruction Layer In Li1.2Ni0.2Mn0.6O2 Cathode Material For Lithium Ion Batteries

    Energy Technology Data Exchange (ETDEWEB)

    Yan, Pengfei; Nie, Anmin; Zheng, Jianming; Zhou, Yungang; Lu, Dongping; Zhang, Xiaofeng; Xu, Rui; Belharouak, Ilias; Zu, Xiaotao; Xiao, Jie; Amine, Khalil; Liu, Jun; Gao, Fei; Shahbazian-Yassar, Reza; Zhang, Jiguang; Wang, Chong M.

    2015-01-14

    Voltage and capacity fading of layer structured lithium and manganese rich (LMR) transition metal oxide is directly related to the structural and composition evolution of the material during the cycling of the battery. However, understanding such evolution at atomic level remains elusive. Based on atomic level structural imaging, elemental mapping of the pristine and cycled samples and density functional theory calculations, it is found that accompanying the hoping of Li ions is the simultaneous migration of Ni ions towards the surface from the bulk lattice, leading to the gradual depletion of Ni in the bulk lattice and thickening of a Ni enriched surface reconstruction layer (SRL). Furthermore, Ni and Mn also exhibit concentration partitions within the thin layer of SRL in the cycled samples where Ni is almost depleted at the very surface of the SRL, indicating the preferential dissolution of Ni ions in the electrolyte. Accompanying the elemental composition evolution, significant structural evolution is also observed and identified as a sequential phase transition of C2/m →I41→Spinel. For the first time, it is found that the surface facet terminated with pure cation is more stable than that with a mixture of cation and anion. These findings firmly established how the elemental species in the lattice of LMR cathode transfer from the bulk lattice to surface layer and further into the electrolyte, clarifying the long standing confusion and debate on the structure and chemistry of the surface layer and their correlation with the voltage fading and capacity decaying of LMR cathode. Therefore, this work provides critical insights for designing of cathode materials with both high capacity and voltage stability during cycling.

  2. Numerical Analyses of a single-phase natural convection system for Molten Flibe using MARS-FLIBE code

    Energy Technology Data Exchange (ETDEWEB)

    Kang, Sarah; Bang, In Cheol [Ulsan National Institute of Science and Technology, Ulsan (Korea, Republic of)

    2014-10-15

    These advantages make the MSR attractive and to be one of the six candidates for the Generation IV Reactor. Therefore, the researches related to the MSR are being conducted. To analyze the molten salt-cooled systems in the laboratory, this study generated the properties of molten salt using MARS-LMR. In this research, the implemented salts were Flibe (LiF-BeF{sub 2}) in a molar mixture that is 66% LiF and 34% BeF{sub 2}, respectively. Table 1 indicates the comparison of thermal properties of various coolants in nuclear power plants. Molten salt was added to the MARS-LMR code to support the analysis of Flibe-cooled systems. The molten salt includes LiF-BeF{sub 2} in a molar mixture that is 66% LiF and 34% BeF{sub 2}, respectively. MARS-LMR code for liquid metals uses the soft sphere model based on Monte Carlo calculations for particles interacting with pair potentials. Although MARS was originally intended for a safety analysis of light water reactor, Flibe properties were newly added to this code as so-called MARS-FLIBE which is applicable for Flibe-cooled systems. By using this thermodynamic property table file, the thermal hydraulic systems of Flibe can be simulated for numerical and parametric studies. In this study, the natural convection phenomena in the rectangular natural convection loop and IVR-ERVC in APR 1400 were simulated. Through the simulations in Flibe-cooled systems, the temperature distribution and mass flowrate of Flibe can be calculated and the heat transfer coefficients of Flibe in natural convection loop will be calculated by adding the related heat transfer correlations in the MARS-FLIBE code. MARS-FLIBE code will be used to predict and design of Flibe-cooled systems.

  3. High pressure modulated transport and signaling functions of membrane proteins in models and in vivo

    International Nuclear Information System (INIS)

    Vogel, R F; Linke, K; Teichert, H; Ehrmann, M A

    2008-01-01

    Cellular membranes serve in the separation of compartments, recognition of the environment, selective transport and signal transduction. Membrane lipids and membrane proteins play distinct roles in these processes, which are affected by environmental chemical (e. g. pH) or physical (e. g. pressure and temperature) changes. High hydrostatic pressure (HHP) affects fluidity and integrity of bacterial membranes instantly during the ramp, resulting in a loss of membrane potential and vital membrane protein functions. We have used the multiple drug transporter LmrA from Lactococcus lactis and ToxR, a membrane protein sensor from Photobacterium profundum, a deep-sea bacterium, and Vibrio cholerae to study membrane protein interaction and functionality in proteolioposomes and by the use of in vivo reporter systems, respectively. Both proteins require dimerization in the phospholipid bilayer for their functionality, which was favoured in the liquid crystalline lipid phase with ToxR and LmrA. Whereas LmrA, which resides in liposomes consisting of DMPC, DMPC/cholesterol or natural lipids, lost its ATPase activity above 20 or 40 MPa, it maintained its active dimeric structure in DOPC/DPPC/cholesterol liposomes up to 120 MPa. By using a specific indicator strain in which the dimerisation of ToxR initiates the transcription of lacZ it was demonstrated, that the amino acid sequence of the transmembrane domain influences HHP stability of ToxR dimerization in vivo. Thus, both the lipid structure and the nature of the protein affect membrane protein interaction. It is suggested that the protein structure determines basic functionality, e.g. principle ability or kinetics to dimerize to a functional complex, while the lipid environment modulates this property

  4. Organic Carbon and Trace Element Cycling in a River-Dominated Tidal Coastal Wetland System (Tampa Bay, FL, USA)

    Science.gov (United States)

    Moyer, R. P.; Smoak, J. M.; Engelhart, S. E.; Powell, C. E.; Chappel, A. R.; Gerlach, M. J.; Kemp, A.; Breithaupt, J. L.

    2016-02-01

    Tampa Bay is the largest open water, river-fed estuary in Florida (USA), and is characterized by the presence of both mangrove and salt marsh ecosystems. Both coastal wetland systems, and small rivers such as the ones draining into Tampa Bay have historically been underestimated in terms of their role in the global carbon and elemental cycles. Climate change and sea-level rise (SLR) are major threats in Tampa Bay and stand to disrupt hydrologic cycles, compromising sediment accumulation and the rate of organic carbon (OC) burial. This study evaluates organic carbon content, sediment accumulation, and carbon burial rates in salt marsh and mangrove ecosystems, along with measurements of fluxes of dissolved OC (DOC) and trace elements in the water column of the Little Manatee River (LMR) in Tampa Bay. The characterization of OC and trace elements in tidal rivers and estuaries is critical for quantitatively constraining these systems in local-to-regional scale biogeochemical budgets, and provide insight into biogeochemical processes occurring with the estuary and adjacent tidal wetlands. Material fluxes of DOC and trace elements were tied to discharge irrespective of season, and the estuarine habitats removed 15-65% of DOC prior to export to Tampa Bay and the Gulf of Mexico. Thus, material is available for cycling and burial within marsh and mangrove peats, however, LMR mangrove peats have higher OC content and burial rates than adjacent salt marsh peats. Sedimentary accretion rates in LMR marshes are not currently keeping pace with SLR, thus furthering the rapid marsh-to-mangrove conversions that have been seen in Tampa Bay over the past half-century. Additionally, wetlands in Tampa Bay tend to have a lower rate of carbon burial than other Florida tidal wetlands, demonstrating their high sensitivity to climate change and SLR.

  5. The benefits and problems of base seismic isolation for LMFBR reactor plants

    International Nuclear Information System (INIS)

    Seidensticker, R.W.

    1988-01-01

    The use of seismic isolation as an approach to aseismic design has gained increasing interest as a viable and efficient engineering solution to earthquake ground motion both within and outside of the nuclear field. Seismic isolation design is fundamentally different from conventional design practice. In the conventional approach, seismic loads are resisted by making the structures, equipment, piping, and associated supports strong enough to resist seismic loads and to provide high levels of ductility. The use of seismic isolation approaches the problem by decoupling the structure (and its contents) from the seismic input resulting from ground shaking. Because LMFBR systems operate at virtually atmospheric pressure, vessels, piping, and associated components tend to be quite thin-walled. The problem is that these thin-walled items have little inherent resistance to earthquake effects and are vulnerable to seismic load effects. As a result, earthquake loads have an even greater influence on LMR designs than they already are in LWR plants. The potential benefits of seismic isolation for an LMR plant are considerable, including minimization of high-cost commodities such as stainless steel, large reductions in internal equipment loads, increased margins of safety for beyond-design-basis loads, and enhancement of plant standardization design. There are, of course, a number of issues and concerns in the use of seismic isolation for a nuclear power plant. These issues cover a number of items such as the lack of experience in actual earthquakes, effects of long-period ground motion, effect of vertical loads, traveling waves, and other related concerns. This paper presents an evaluation of the benefits and problems in the use of seismic isolation in LMR plants. 12 refs, 7 figs

  6. An overview of the U.S. Department of Energy's program for liquid metal reactor seismic technology

    International Nuclear Information System (INIS)

    Jetter, R.I.; Seidensticker, R.W.

    1988-01-01

    During the past decade, the U.S. Department of Energy (DOE) has sponsored the development of seismic design technology in support of Liquid Metal Reactors (LMR's). This has been accomplished through 1) major projects such as the Fast Flux Test Facility (FFTF) and the Clinch River Breeder Reactor (CRBR), 2) base technology programs and 3) support to the design development of innovative LMR's, SAFR and PRISM. These developments have come in the areas of ground motion definition, soil-structure interaction, seismic isolation, fluid-structure interaction and structural analysis methods and criteria for equipment and components such as piping, reactor core and vessels. The initial developments in seismic design technology by DOE and others were directed toward ensuring that the plant, equipment and components had sufficient seismic resistance to ensure availability after an Operations Basis Earthquake (OBE) and to survive a Safe Shutdown Earthquake (SSE). During this period, the emphasis on conservative design had significant cost impacts. The current focus is directed toward a better understanding of seismic design margins and the development of methods to reduce seismic loads on plant and equipment and to enhance siting flexibility. From this perspective, the DOE is currently reassessing the needs and priorities for future seismic technology development. Coordination with University research programs and ongoing seismic technology development sponsored by other governmental agencies and institutions is an integral part of this planning process. The purpose of this paper is to highlight the current status of DOE's seismic technology program for LMR's and to provide an overview of future areas of interest. (author). 7 refs

  7. Should providers encourage realistic weight expectations and satisfaction with lost weight in commercial weight loss programs? a preliminary study.

    Science.gov (United States)

    Ames, Gretchen E; Thomas, Colleen S; Patel, Roshni H; McMullen, Jillian S; Lutes, Lesley D

    2014-01-01

    Attrition is a problem among patients who participate in commercial weight loss programs. One possible explanation is that if patients are unable to reach a weight that they expect to achieve, they may be more likely to drop out of treatment. This study investigated variables associated with attrition among 30 obese patients who completed a liquid meal replacement program (LMR) and enrolled in a 52-week Small Changes Maintenance intervention (SCM). Patients lost a median 18% of body weight during LMR and completed assessments about weight expectations and weight satisfaction pre- and post-SCM. Of the 30 patients who started SCM, 8 (27%) were lost to attrition. Odds of SCM attrition were higher in patients who lost ≤ 18.2% of pre-LMR weight (OR: 12.25, P = 0.035), had lower satisfaction (≤7) pre-SCM (OR: 10.11, P = 0.040), and who expected further weight loss of 9.1 kg or more pre-SCM (OR: 10.11, P = 0.040). SCM completers significantly increased weight loss expectations by a median of 2.3 kg from pre-SCM to post-SCM (WSR P = 0.049) that paralleled weight regained post-SCM (2.7 kg). After completion of a medically-supervised commercial weight loss program, patients with the greatest expectations for further weight loss and the lowest weight satisfaction were more likely to drop out of SCM. Failure to participate in maintenance treatment may lead to regain of greater than half of lost weight over the next year. Among SCM completers, lower expectations for further weight loss and greater weight satisfaction appeared to be associated with continued engagement in maintenance treatment.

  8. Analysis of local subassembly accident in KALIMER

    Energy Technology Data Exchange (ETDEWEB)

    Kwon, Young Min; Jeong, Kwan Seong; Hahn, Do Hee

    2000-10-01

    Subassembly Accidents (S-A) in the Liquid Metal Reactor (LMR) may cause extensive clad and fuel melting and are thus regarded as a potential whole core accident initiator. The possibility of S-A occurrence must be very low frequency by the design features, and reactor must have specific instrumentation to interrupt the S-A sequences by causing a reactor shutdown. The evaluation of the relevant initiators, the event sequences which follow them, and their detection are the essence of the safety issue. Particularly, the phenomena of flow blockage caused by foreign materials and/or the debris from the failed fuel pin have been researched world-widely. The foreign strategies for dealing with the S-A and the associated safety issues with experimental and theoretical R and D results are reviewed. This report aims at obtaining information to reasonably evaluate the thermal-hydraulic effect of S-A for a wire-wrapped LMR fuel pin bundle. The mechanism of blockage formation and growth within a pin bundle and at the subassembly entrance is reviewed in the phenomenological aspect. Knowledge about the recent LMR subassembly design and operation procedure to prevent flow blockage will be reflected for KALIMER design later. The blockage analysis method including computer codes and related analytical models are reviewed. Especially SABRE4 code is discussed in detail. Preliminary analyses of flow blockage within a 271-pin driver subassembly have been performed using the SABRE4 computer code. As a result no sodium boiling occurred for the central 24-subchannel blockage as well as 6-subchannel blockage.

  9. Electrochemical Modeling and Performance of a Lithium- and Manganese-Rich Layered Transition-Metal Oxide Positive Electrode

    Energy Technology Data Exchange (ETDEWEB)

    Dees, Dennis W.; Abraham, Daniel P; Lu, Wenquan; Gallagher, Kevin G.; Bettge, Martin; Jansen, Andrew N

    2015-01-21

    The impedance of a lithium- and manganese-rich layered transition-metal oxide (MR-NMC) positive electrode, specifically Li1.2Ni0.15Mn0.55Co0.1O2, is compared to two other transition-metal layered oxide materials, specifically LiNi0.8Co0.15Al0.05O2 (NCA) and Li1.05(Ni1/3Co1/3Mn1/3)0.95O2 (NMC). A more detailed electrochemical impedance spectroscopy (EIS) study is conducted on the LMR-NMC electrode, which includes a range of states-of-charge (SOCs) for both current directions (i.e. charge and discharge) and two relaxation times (i.e. hours and one hundred hours) before the EIS sweep. The LMR-NMC electrode EIS studies are supported by half-cell constant current and galvanostatic intermittent titration technique (GITT) studies. Two types of electrochemical models are utilized to examine the results. The first type is a lithium ion cell electrochemical model for intercalation active material electrodes that includes a complex active material/electrolyte interfacial structure. In conclusion, the other is a lithium ion half-cell electrochemical model that focuses on the unique composite structure of the bulk LMR-NMC materials.

  10. The SAFR liquid metal concept

    International Nuclear Information System (INIS)

    Baumeister, E.B.

    1987-01-01

    The Sodium Advanced Fast Reactor (SAFR) modular reactor concept is being developed by the team of Rockwell International, Combustion Engineering, and Bechtel under the U.S. Department of Energy's (DOE's) Advanced Liquid Metal Reactor (LMR) program. The SAFR plant would provide a viable alternate to light water reactors, especially for applications favoring small incremental capacity additions. SAFR is also a logical step to facilitate the later transition to LMFBRs. The SAFR plant concept employs multiple 350-MWe LMR Power Pak modules. Each Power Pak is a standardized, shop-fabricated unit that can be barge-shipped to the plant site for installation. The 350-MWe size allows SAFR to capitalize on all the inherent safety features provided by small reactors and factory fabrication, while still preserving some economy of scale. Shop fabrication minimizes nuclear-grade field fabrication and minimizes the overall plant construction schedule and capital cost. Each Power Pak consists of one reactor assembly and associated heat transfer equipment coupled to a single turbine generator. The reactor core employs mixed uranium-plutonium zirconium alloy metal fuel. The metal-alloy fuel (which has been used in EBR-II) has cost, safety, and safeguard advantages. The intrinsic properties of the sodium coolant (e.g., high boiling point, low vapor pressure, and strong natural convection), blended together with the pool-type LMR concept and the metal fuel, result in an inherently safe plant. Passive inherent features provide both public safety and plant investment protection. Refueling is carried out annually on each Power Pak, replacing one-fourth of the core over a 6-day refueling outage. A colocated pyroprocessing fuel cycle facility can be accommodated at the site such that no off-site shipments are required. (J.P.N.)

  11. Growth analysis of UV-B-irradiated cucumber seedlings as influenced by photosynthetic photon flux source and cultivar

    International Nuclear Information System (INIS)

    Krizek, D.T.; Mirecki, R.M.; Kramer, G.F.

    1994-01-01

    A growth analysis was made of ultraviolet-B (UV-B)-sensitive (Poinsett) and insensitive (Ashley) cultivars of Cucuumis satives L. grown in growth chambers at 600 μmol m −2 s −1 of photosynthetic photon flux (PPF) provided by red- and far-red-deficient metal halide (MH) or blue- and UV-A-deficient high pressure sodium/deluxe f HPS/DX) lamps. Plants were irradiated 6 h daily with 0.2 f-UV-B) or 18.2 C+UV-B) kJ m −2 day −1 of biologically effective UV-B for 8 or 15 days from time of seeding. In general, plants given supplemental UV-B for 15 days showed lower leaf area ratio (LARs, and higher specific leaf mass (SLM) mean relative growth rate (MRGR) and net assimilation rate (NAR) than that of control plants, but they showed no difference in leaf mass ratio (LMR), Plants grown under HPS/DX lamps vs MH lamps showed higher SLM and NAR. lower LAR and LMR. hut no difference in MRGR. LMR was the only growth parameter affected by cultivar: at 15 days, it was slightly greater in Poinsett than in Ashley. There were no interactive effects of UV-B. PPF source or cultivar on any of the growth parameters determined, indicating that the choice of either HPS/DX or MH lamps should not affect growth response to UV-B radiation. This was true even though leaves of UV-B-irradiated plants grown under HPS/DX lamps have been shown to have greater chlorosis than those grown under MH lamps. (author)

  12. High pressure modulated transport and signaling functions of membrane proteins in models and in vivo

    Energy Technology Data Exchange (ETDEWEB)

    Vogel, R F; Linke, K; Teichert, H; Ehrmann, M A [Technische Universitaet Muenchen, Technische Mikrobiologie, Weihenstephaner Steig 16, 85350 Freising (Germany)], E-mail: rudi.vogel@wzw.tum.de

    2008-07-15

    Cellular membranes serve in the separation of compartments, recognition of the environment, selective transport and signal transduction. Membrane lipids and membrane proteins play distinct roles in these processes, which are affected by environmental chemical (e. g. pH) or physical (e. g. pressure and temperature) changes. High hydrostatic pressure (HHP) affects fluidity and integrity of bacterial membranes instantly during the ramp, resulting in a loss of membrane potential and vital membrane protein functions. We have used the multiple drug transporter LmrA from Lactococcus lactis and ToxR, a membrane protein sensor from Photobacterium profundum, a deep-sea bacterium, and Vibrio cholerae to study membrane protein interaction and functionality in proteolioposomes and by the use of in vivo reporter systems, respectively. Both proteins require dimerization in the phospholipid bilayer for their functionality, which was favoured in the liquid crystalline lipid phase with ToxR and LmrA. Whereas LmrA, which resides in liposomes consisting of DMPC, DMPC/cholesterol or natural lipids, lost its ATPase activity above 20 or 40 MPa, it maintained its active dimeric structure in DOPC/DPPC/cholesterol liposomes up to 120 MPa. By using a specific indicator strain in which the dimerisation of ToxR initiates the transcription of lacZ it was demonstrated, that the amino acid sequence of the transmembrane domain influences HHP stability of ToxR dimerization in vivo. Thus, both the lipid structure and the nature of the protein affect membrane protein interaction. It is suggested that the protein structure determines basic functionality, e.g. principle ability or kinetics to dimerize to a functional complex, while the lipid environment modulates this property.

  13. High pressure modulated transport and signaling functions of membrane proteins in models and in vivo

    Science.gov (United States)

    Vogel, R. F.; Linke, K.; Teichert, H.; Ehrmann, M. A.

    2008-07-01

    Cellular membranes serve in the separation of compartments, recognition of the environment, selective transport and signal transduction. Membrane lipids and membrane proteins play distinct roles in these processes, which are affected by environmental chemical (e. g. pH) or physical (e. g. pressure and temperature) changes. High hydrostatic pressure (HHP) affects fluidity and integrity of bacterial membranes instantly during the ramp, resulting in a loss of membrane potential and vital membrane protein functions. We have used the multiple drug transporter LmrA from Lactococcus lactis and ToxR, a membrane protein sensor from Photobacterium profundum, a deep-sea bacterium, and Vibrio cholerae to study membrane protein interaction and functionality in proteolioposomes and by the use of in vivo reporter systems, respectively. Both proteins require dimerization in the phospholipid bilayer for their functionality, which was favoured in the liquid crystalline lipid phase with ToxR and LmrA. Whereas LmrA, which resides in liposomes consisting of DMPC, DMPC/cholesterol or natural lipids, lost its ATPase activity above 20 or 40 MPa, it maintained its active dimeric structure in DOPC/DPPC/cholesterol liposomes up to 120 MPa. By using a specific indicator strain in which the dimerisation of ToxR initiates the transcription of lacZ it was demonstrated, that the amino acid sequence of the transmembrane domain influences HHP stability of ToxR dimerization in vivo. Thus, both the lipid structure and the nature of the protein affect membrane protein interaction. It is suggested that the protein structure determines basic functionality, e.g. principle ability or kinetics to dimerize to a functional complex, while the lipid environment modulates this property.

  14. Oxide fuel pin transient performance analysis and design with the TEMECH code

    International Nuclear Information System (INIS)

    Bard, F.E.; Dutt, S.P.; Hinman, C.A.; Hunter, C.W.; Pitner, A.L.

    1986-01-01

    The TEMECH code is a fast-running, thermal-mechanical-hydraulic, analytical program used to evaluate the transient performance of LMR oxide fuel pins. The code calculates pin deformation and failure probability due to fuel-cladding differential thermal expansion, expansion of fuel upon melting, and fission gas pressurization. The mechanistic fuel model in the code accounts for fuel cracking, crack closure, porosity decrease, and the temperature dependence of fuel creep through the course of the transient. Modeling emphasis has been placed on results obtained from Fuel Cladding Transient Test (FCTT) testing, Transient Fuel Deformation (TFD) tests and TREAT integral fuel pin experiments

  15. Clinical implications of six inflammatory biomarkers as prognostic indicators in Ewing sarcoma

    Directory of Open Access Journals (Sweden)

    Li YJ

    2017-09-01

    Full Text Available Yong-Jiang Li, Xi Yang, Wen-Biao Zhang, Cheng Yi, Feng Wang, Ping Li Department of Oncology, West China Hospital, Sichuan University, Chengdu, People’s Republic of China Abstract: Cancer-related systemic inflammation responses have been correlated with cancer development and progression. The prognostic significance of several inflammatory indicators, including neutrophil–lymphocyte ratio (NLR, platelet–lymphocyte ratio (PLR, Glasgow Prognostic Score (GPS, C-reactive protein to albumin ratio (CRP/Alb ratio, lymphocyte–monocyte ratio (LMR, and neutrophil–platelet score (NPS, were found to be correlated with prognosis in several cancers. However, the prognostic role of these inflammatory biomarkers in Ewing sarcoma has not been evaluated. This study enrolled 122 Ewing patients. Receiver operating characteristic (ROC analysis was generated to determine optimal cutoff values; areas under the curves (AUCs were assessed to show the discriminatory ability of the biomarkers; Kaplan–Meier analysis was conducted to plot the survival curves; and Cox multivariate survival analysis was performed to identify independent prognostic factors. The optimal cutoff values of CRP/Alb ratio, NLR, PLR, and LMR were 0.225, 2.38, 131, and 4.41, respectively. CRP/Alb ratio had a significantly larger AUC than NLR, PLR, LMR, and NPS. Higher levels of CRP/Alb ratio (hazard ratio [HR] 2.41, P=0.005, GPS (HR 2.27, P=0.006, NLR (HR 2.07, P=0.013, and PLR (HR 1.85, P=0.032 were significantly correlated with poor prognosis. As the biomarkers had internal correlations, only the CRP/Alb ratio was involved in the multivariate Cox analysis and remained an independent prognostic indicator. The study demonstrated that CRP/Alb ratio, GPS, and NLR were effective prognostic indicators for patients with Ewing sarcoma, and the CRP/Alb ratio was the most robust prognostic indicator with a discriminatory ability superior to that of the other indicators; however, PLR, LMR, and

  16. Radioisotope measurement system

    International Nuclear Information System (INIS)

    Villanueva Ruibal, Jose

    2007-01-01

    A radioisotope measurement system installed at L.M.R. (Ezeiza Atomic Center of CNEA) allows the measurement of nuclear activity from a wide range of radioisotopes. It permits to characterize a broad range of radioisotopes at several activity levels. The measurement hardware as well as the driving software have been developed and constructed at the Dept. of Instrumentation and Control. The work outlines the system's conformation and its operating concept, describes design characteristics, construction and the error treatment, comments assay results and supplies use advices. Measuring tests carried out employing different radionuclides confirmed the system performing satisfactorily and with friendly operation. (author) [es

  17. Monitoring of radiation in the atmosphere and a food chain. Results in the Netherlands in 1994

    International Nuclear Information System (INIS)

    1995-11-01

    The programme of the RIVM/LSO includes samples of air dust and deposition taken at the RIVM premises in Bilthoven. Samples of grass and milk were taken from the surroundings of nuclear installations in the Netherlands and on Dutch territory in the vicinity of such installations situated abroad. An overall country milk sample from four milk factories in the Netherlands was also analyzed. This report also presents the data of the National Radioactivity Monitoring Network (LMR) in 1994. These data are not included in the NMP. 20 figs., 5 tabs., 23 refs., 1 appendix

  18. SWAAM code development, verification and application to steam generator design

    International Nuclear Information System (INIS)

    Shin, Y.W.; Valentin, R.A.

    1990-01-01

    This paper describes the family of SWAAM codes developed by Argonne National Laboratory to analyze the effects of sodium/water reactions on LMR steam generators. The SWAAM codes were developed as design tools for analyzing various phenomena related to steam generator leaks and to predict the resulting thermal and hydraulic effects on the steam generator and the intermediate heat transport system (IHTS). The theoretical foundations and numerical treatments on which the codes are based are discussed, followed by a description of code capabilities and limitations, verification of the codes by comparison with experiment, and applications to steam generator and IHTS design. (author). 25 refs, 14 figs

  19. SWAAM-code development and verification and application to steam generator designs

    International Nuclear Information System (INIS)

    Shin, Y.W.; Valentin, R.A.

    1990-01-01

    This paper describes the family of SWAAM codes which were developed by Argonne National Laboratory to analyze the effects of sodium-water reactions on LMR steam generators. The SWAAM codes were developed as design tools for analyzing various phenomena related to steam generator leaks and the resulting thermal and hydraulic effects on the steam generator and the intermediate heat transport system (IHTS). The paper discusses the theoretical foundations and numerical treatments on which the codes are based, followed by a description of code capabilities and limitations, verification of the codes and applications to steam generator and IHTS designs. 25 refs., 14 figs

  20. Cinética de degradación y persistencia de clorpirifós en mandarinas y naranjas del Noreste argentino (NEA

    Directory of Open Access Journals (Sweden)

    KULCZYCKI, C.1

    2012-10-01

    Full Text Available Las normativas legales sobre residuos de plaguicidas son cada vez más exigentes. Con frecuencia, hay una reducción significativa en el Límite Máximo de Residuos (LMR y en casos severos una prohibición de su uso. La estrategia de control fitosanitario debe tener en cuenta los niveles de residuos que quedan en la fruta y la cinética de disipación que disminuye los riesgos toxicológicos y comerciales. El clorpirifós es un insecticida utilizado en cítricos para el control de diversas plagas. La legislación argentina establece un LMR de 0,3 mg/kg para fruta entera y un Período de Carencia (PC de 21 días. Este valor coincide con el exigido por la Unión Europea (UE, excepto en mandarinas, y por la Federación de Rusia. En el presente trabajo se estudió la cinética de degradación y persistencia del clorpirifós en dos variedades de naranjas y tres de mandarinas.Los ensayos se realizaron con clorpirifós 48% (concentrado emulsionable en la preparación de un caldo con 120 cm3 cada 100 L de agua. Se utilizó una pulverizadora de turbina y un volumen de 2000-2500 l/ha. La degradación de residuos en frutas se estudió durante 120 días con toma de muestras periódicas. Los datos experimentales se utilizaron para establecer un modelo matemático de degradación en función del tiempo. En todos los casos, los residuos iniciales superaron el LMR y la disipación siguió un modelo logarítmico. Hasta el PC la eliminación fue rápida, con una reducción del 69 al 82% de los residuos. Luego continuó una fase de eliminación más lenta con niveles al final del ensayo entre 0,03 mg/kg y 0,01 mg/kg. En el PC se cumple con el LMR fijado por la legislación nacional y de los países compradores. La aparición de residuos en el final delensayo indica una gran persistencia del clorpirifós.

  1. Experimental and analytical studies of a passive shutdown heat removal system for advanced LMRs

    International Nuclear Information System (INIS)

    Heineman, J.; Kraimer, M.; Lottes, P.; Pedersen, D.; Stewart, R.; Tessier, J.

    1988-01-01

    A facility designed and constructed to demonstrate the viability of natural convection passive heat removal systems as a key feature of innovative LMR Shutdown Heat Removal (SHR) systems is in operation at Argonne National Laboratory (ANL). This Natural Convection Shutdown Heat Removal Test Facility (NSTF) is being used to investigate the heat transfer performance of the GE/PRISM and the RI/SAFR passive designs. This paper presents a description of the NSTF, the pretest analysis of the Radiant Reactor Vessel Auxiliary Cooling System (RVACS) in support of the GE/PRISM IFR concept, and experiment results for the RVACS simulation. Preliminary results show excellent agreement with predicted system performance

  2. Liver mortality attributable to chronic hepatitis C virus infection in Denmark and Scotland - using spontaneous resolvers as the benchmark comparator

    DEFF Research Database (Denmark)

    Innes, H; Hutchinson, S J; Obel, N

    2016-01-01

    Liver mortality among individuals with chronic hepatitis C (CHC) infection is common, but the relative contribution of CHC per se versus adverse health behaviours is uncertain. We explored data on spontaneous resolvers of hepatitis C virus (HCV) as a benchmark group, to uncover the independent...... contribution of CHC on liver mortality. Using national HCV diagnosis and mortality registers from Denmark and Scotland, we calculated the liver mortality rate (LMR) for persons diagnosed with CHC infection (LMRchronic ) and spontaneously resolved infection (LMRresolved ), according to subgroups defined by: age...

  3. Natural radioactivity in the Dutch outdoor environment. The explanation of uncomprehended variations in the background

    International Nuclear Information System (INIS)

    Blaauboer, R.O.; Smetsers, R.C.G.M.

    1996-01-01

    In the Netherlands and many other countries research in the field of natural radioactivity is focused on the prevention of radon in the indoor environment. However, also the occurrence of natural radioactivity in the outdoor environment is an interesting subject to be studied. The natural background radiation in the outdoor environment, in particular its variations, hinders the verification of radiation level standards, caused by human activities. An analysis of the data of the Dutch National Monitoring Network for Radioactivity (LMR) provided more insight into those variations. This article is a summary of the authors' thesis on the subject. 5 figs., 8 refs

  4. New biomarkers for increased intestinal permeability induced by dextran sodium sulphate and fasting in chickens.

    Science.gov (United States)

    Gilani, S; Howarth, G S; Kitessa, S M; Tran, C D; Forder, R E A; Hughes, R J

    2017-10-01

    Increased intestinal permeability (IP) can lead to compromised health in chickens. As there is limited literature on in vivo biomarkers to assess increased IP in chickens, the objective of this study was to identify a reliable biomarker of IP using DSS ingestion and fasting models. Male Ross chickens (n = 48) were reared until day 14 on the floor pen in an animal care facility, randomized into the following groups: control, DSS and fasting (each with n = 16), and then placed in metabolism cages. DSS was administered in drinking water at 0.75% from days 16 to 21, while controls and fasted groups received water. All birds had free access to feed and water except the birds in the fasting group that were denied feed for 19.5 h on day 20. On day 21, all chickens were given two separate oral gavages comprising fluorescein isothiocyanate dextran (FITC-d, 2.2 mg in 1 ml/bird) at time zero and lactulose, mannitol and rhamnose (LMR) sugars (0.25 g L, 0.05 g M and 0.05 g R in 2 ml/bird) at 60 min. Whole blood was collected from the brachial vein in a syringe 90 min post-LMR sugar gavage. Serum FITC-d and plasma LMR sugar concentrations were measured by spectrophotometry and high-performance ion chromatography respectively. Plasma concentrations of intestinal fatty acid binding protein, diamine oxidase, tight junction protein (TJP), d-lactate and faecal α-antitrypsin inhibitor concentration were also analysed by ELISA. FITC-d increased significantly (p fasting compared with control. L/M and L/R ratios for fasting and L/M ratio for DSS increased compared with control chickens (p fasting but not DSS treatment, compared with controls. Other tests did not indicate changes in IP (p > 0.05). We concluded that FITC-d and LMR sugar tests can be used in chickens to assess changes in IP. Journal of Animal Physiology and Animal Nutrition © 2016 Blackwell Verlag GmbH.

  5. Análisis de la sensibilidad de biotipos de Lolium multiflorum a herbicidas inhibidores de la enzima ALS, ACCasa y Glifosato Sensitivity analysis of Lolium multiflorum biotypes to Glyphosate, ACCase and ALS-inhibiting herbicides

    Directory of Open Access Journals (Sweden)

    P. Diez De Ulzurrun

    2012-09-01

    Full Text Available A pesar de los avances logrados en el control de las malezas con el uso de herbicidas, el manejo de las mismas no se simplificó, sino que, al contrario, surgieron nuevos desafíos, como la aparición de resistencia a herbicidas. En 2007, se reportó en Lolium multiflorum el segundo caso de resistencia a glifosato detectado en Argentina. En el sudeste de la provincia de Buenos Aires se registraron fallas de control a campo en poblaciones de Lolium multiflorum debido a su resistencia a distintos herbicidas de las familias de los inhibidores de ALS y de ACCasa y al herbicida glifosato. El objetivo de este estudio fue caracterizar el nivel de resistencia a ciertos herbicidas inhibidores de la ALS y de la ACCasa y al glifosato en una población de L. multiflorum de Lobería (Bs As, Argentina supuestamente resistente (LmR. Se realizaron bioensayos en cajas de Petri y se determinó la GR50 mediante la variación en la longitud de coleoptile. Las curvas de dosis-respuesta se obtuvieron por medio de la ecuación log-logística. El biotipo LmR presentó resistencia múltiple a herbicidas con tres modos de acción diferentes: glifosato, inhibidores de ALS y de ACCasa. Dicho ensayo demostró la aparición de un biotipo de L. multiflorum con resistencia a múltiples principios activos.Despite progress in weed control using herbicides, management has not been simplified, but new challenges such as herbicides resistance have arisen. In 2007, a Lolium multiflorum population resistant to glyphosate was reported, as the second case of glyphosate resistant weeds in Argentina. In the southeast of Buenos Aires province, control failures in populations of L. multiflorum to different families of herbicide such as ALS and ACCase inhibitors and to glyphosate at field level have been registered. The aim of this study was to characterize the level of resistance to certain herbicides inhibitors of ALS, ACCase and glyphosate in a putatively resistant (LmR population of L

  6. Sensores de fibra óptica basados en resonancias electromagnéticas

    OpenAIRE

    López Lambás, Sergio

    2011-01-01

    Este trabajo surge como continuación a los trabajos basados en LMR ya realizados con el objetivo de profundizar en el estudio y fabricación de sensores de fibra óptica basados en resonancias electromagnéticas utilizando diferentes materiales y técnicas. En concreto el proyecto perseguirá los siguientes objetivos: Desarrollar sensores de fibra óptica basados en resonancias electromagnéticas con recubrimientos metálicos y su aplicación a la detección de campo magnético. Estudiar y mejorar la fa...

  7. HEDL FACILITIES CATALOG 400 AREA

    Energy Technology Data Exchange (ETDEWEB)

    MAYANCSIK BA

    1987-03-01

    The purpose of this project is to provide a sodium-cooled fast flux test reactor designed specifically for irradiation testing of fuels and materials and for long-term testing and evaluation of plant components and systems for the Liquid Metal Reactor (LMR) Program. The FFTF includes the reactor, heat removal equipment and structures, containment, core component handling and examination, instrumentation and control, and utilities and other essential services. The complex array of buildings and equipment are arranged around the Reactor Containment Building.

  8. MIDAS: an effective tool for work management

    International Nuclear Information System (INIS)

    Ball, D.L.; Billings, M.P.; McCargar, S.B.; Talbot, M.D.; Topping, C.F.

    1985-01-01

    The computerized Master Information Data Acquisition System (MIDAS) is used to control work at facilities that support the Liquid Metal Reactor (LMR) program on the Hanford Site at Richland, Washington. Functions of this software system are to: track authorized maintenance activities, enhance operational safety, track schedule, manpower, and material constraints during work preparation, provide a management tool for quality measurement techniques, and provide an overall repository for technical and safety-related information on components at the Hanford Site 400 Area facilities. This paper describes MIDAS and how it is used as a work management tool. 1 fig

  9. Critical evaluation of the Laboratory of Radionuclide Metrology results of the Institute of Radiation Protection and Dosimetry - IRD in the international key comparisons of activity measurement of radioactive solutions

    International Nuclear Information System (INIS)

    Iwahara, A.; Tauhata, L.; Silva, C.J. da

    2014-01-01

    The Radionuclide Metrology Laboratory (LMR) of LNMRI/IRD has been participating since 1984, in international key-comparisons of activity measurement of radioactive sources organized by BIPM and the Regional Metrology Organizations as EURAMET and APMP. The measured quantity is the activity of a radioactive solution, in becquerel (Bq), containing the radionuclide involved and the of measurement methods used are 4αβ-γ coincidence/anticoincidence, coincidence sum-peak and liquid scintillation. In this paper a summary of the methods used and a performance analysis of the results obtained are presented. (author)

  10. Critical experiment tests of bowing and expansion reactivity calculations for LMRS

    International Nuclear Information System (INIS)

    Schaefer, R.W.

    1988-01-01

    Experiments done in several LMR-type critical assemblies simulated core axial expansion, core radial expansion and bowing, coolant expansion, and control driveline expansion. For the most part new experimental techniques were developed to do these experiments. Calculations of the experiments basically used design-level methods, except when it was necessary to investigate complexities peculiar to the experiments. It was found that these feedback reactivities generally are overpredicted, but the predictions are within 30% of the experimental values. 14 refs., 2 figs., 4 tabs

  11. Growth potential limits drought morphological plasticity in seedlings from six Eucalyptus provenances.

    Science.gov (United States)

    Maseda, Pablo H; Fernández, Roberto J

    2016-02-01

    Water stress modifies plant above- vs belowground biomass allocation, i.e., morphological plasticity. It is known that all species and genotypes reduce their growth rate in response to stress, but in the case of water stress it is unclear whether the magnitude of such reduction is linked to the genotype's growth potential, and whether the reduction can be largely attributed to morphological adjustments such as plant allocation and leaf and root anatomy. We subjected seedlings of six seed sources, three from each of Eucalyptus camaldulensis (potentially fast growing) and E. globulus (inherently slow growing), to three experimental water regimes. Biomass, leaf area and root length were measured in a 6-month glasshouse experiment. We then performed functional growth analysis of relative growth rate (RGR), and aboveground (leaf area ratio (LAR), specific leaf area (SLA) and leaf mass ratio (LMR)) and belowground (root length ratio (RLR), specific root length (SRL) and root mass ratio (RMR)) morphological components. Total biomass, root biomass and leaf area were reduced for all Eucalyptus provenances according to drought intensity. All populations exhibited drought plasticity, while those of greater growth potential (RGRmax) had a larger reduction in growth (discounting the effect of size). A positive correlation was observed between drought sensitivity and RGRmax. Aboveground, drought reduced LAR and LMR; under severe drought a negative correlation was found between LMR and RGRmax. Belowground, drought reduced SRL but increased RMR, resulting in no change in RLR. Under severe drought, a negative correlation was found between RLR, SRL and RGRmax. Our evidence strongly supports the classic ecophysiological trade-off between growth potential and drought tolerance for woody seedlings. It also suggests that slow growers would have a low capacity to adjust their morphology. For shoots, this constraint on plasticity was best observed in partition (i.e., LMR) whereas for

  12. Seismic analysis of liquid metal reactor piping systems

    International Nuclear Information System (INIS)

    Wang, C.Y.

    1987-01-01

    This paper describes the finite-element numerical algorithm and its applications to LMR piping under seismic excitations. A time-history analysis technique using the implicit temporal integration scheme is addressed. A 3-D pipe element is formulated which has eight degrees of freedom per node (three displacements, three rotations, one membrane displacement, and one bending rotation) to account for the hoop, flexural, rotational, and torsional modes of the piping system. Both geometric and material nonlinearities are considered. This algorithm is unconditionally stable and is particularly suited for the seismic analysis. (orig./GL)

  13. Experimental and analytical studies of a passive shutdown heat removal system for advanced LMRs

    Energy Technology Data Exchange (ETDEWEB)

    Heineman, J.; Kraimer, M.; Lottes, P.; Pedersen, D.; Stewart, R.; Tessier, J.

    1988-01-01

    A facility designed and constructed to demonstrate the viability of natural convection passive heat removal systems as a key feature of innovative LMR Shutdown Heat Removal (SHR) systems is in operation at Argonne National Laboratory (ANL). This Natural Convection Shutdown Heat Removal Test Facility (NSTF) is being used to investigate the heat transfer performance of the GE/PRISM and the RI/SAFR passive designs. This paper presents a description of the NSTF, the pretest analysis of the Radiant Reactor Vessel Auxiliary Cooling System (RVACS) in support of the GE/PRISM IFR concept, and experiment results for the RVACS simulation. Preliminary results show excellent agreement with predicted system performance.

  14. Instrumentation and control improvements at Experimental Breeder Reactor II

    International Nuclear Information System (INIS)

    Christensen, L.J.; Planchon, H.P.

    1993-01-01

    The purpose of this paper is to describe instrumentation and control (I ampersand C) system improvements at Experimental Breeder Reactor 11 (EBR-11). The improvements are focused on three objectives; to keep the reactor and balance of plant (BOP) I ampersand C systems at a high level of reliability, to provide diagnostic systems that can provide accurate information needed for analysis of fuel performance, and to provide systems that will be prototypic of I ampersand C systems of the next generation of liquid metal reactor (LMR) plants

  15. Status of ANL out-of-pile investigations of severe accident phenomena for liquid metal reactors

    International Nuclear Information System (INIS)

    Spencer, B.W.; Marchaterre, J.F.; Anderson, R.P.

    1986-01-01

    Research addressing LMFBR whole core accidents has been terminated, and there is now emphasis on quantifying reactivity feedbacks, and in particular enhancing negative feedback, so that advanced LMR designs will provide inherently safe operation. The status of recent HCDA-related laboratory research performed at ANL, up to the time that such activities were no longer needed to support CRBR licensing, is described. Included are descriptions of programs addressing sodium channel voiding, fuel sweepout, fuel dispersal and plugging, boiled-up pool, UO 2 /sodium FCI, and debris coolability. Descriptions of recent investigations involving the metal fuel/sodium system are also included

  16. IFR starts to burn up weapons-grade material

    International Nuclear Information System (INIS)

    Anon.

    1994-01-01

    With funding from different parts of the federal government, the Integral Fast Reactor (IFR) project has survived into fiscal year 1994 and is now embarking on a demonstration of how this type of liquid-metal-cooled reactor (LMR) can be used to burn fuel derived from weapons-grade plutonium. This month, an assembly made from weapons-grade material is to be loaded into Experimental Breeder Reactor-II in Idaho, which is serving as the prototype for the IFR concept. Although FY 1994 work is being funded by the DOE, this particular examination of plutonium burnup is backed by the Department of Defense

  17. Mechanical properties of martensitic alloy AISI 422

    International Nuclear Information System (INIS)

    Huang, F.H.; Hu, W.L.; Hamilton, M.L.

    1992-09-01

    HT9 is a martensitic stainless steel that has been considered for structural applications in liquid metal reactors (LMRs) as well as in fusion reactors. AISI 422 is a commercially available martensitic stainless steel that closely resembles HT9, and was studied briefly under the auspices of the US LMR program. Previously unpublished tensile, fracture toughness and charpy impact data on AISI 422 were reexamined for potential insights into the consequences of the compositional differences between the two alloys, particularly with respect to current questions concerning the origin of the radiation-induced embrittlement observed in HT9. 8 refs, 8 figs

  18. Hop Resistance in the Beer Spoilage Bacterium Lactobacillus brevis Is Mediated by the ATP-Binding Cassette Multidrug Transporter HorA

    OpenAIRE

    Sakamoto, Kanta; Margolles, Abelardo; van Veen, Hendrik W.; Konings, Wil N.

    2001-01-01

    Lactobacillus brevis is a major contaminant of spoiled beer. The organism can grow in beer in spite of the presence of antibacterial hop compounds that give the beer a bitter taste. The hop resistance in L. brevis is, at least in part, dependent on the expression of the horA gene. The deduced amino acid sequence of HorA is 53% identical to that of LmrA, an ATP-binding cassette multidrug transporter in Lactococcus lactis. To study the role of HorA in hop resistance, HorA was functionally expre...

  19. Benchmark physics tests in the metallic-fueled assembly ZPPR-15

    International Nuclear Information System (INIS)

    McFarlane, H.F.; Brumbach, S.B.; Carpenter, S.G.; Collins, P.J.

    1989-01-01

    Results of the first benchmark physics tests of a metallic-fueled, demonstration-size liquid-metal reactor (LMR) are reported. A simple, two-zone, cylindrical conventional assembly was built with three distinctly different compositions to represent the stages of the Integral Fast Reactor fuel cycle. Experiments included criticality, control, power distribution, reaction rate ratios, reactivity coefficients, shielding, kinetics, and spectrum. Analysis was done with three-dimensional nodal diffusion calculations and ENDF/B-V.2 cross sections. Predictions of the ZPPR-15 reactor physics parameters agreed sufficiently well with the measured values to justify confidence in design analyses for metallic-fueled LMRs

  20. A decade of advances in metallic fuel

    International Nuclear Information System (INIS)

    Lahm, C.E.; Pahl, R.G.; Porter, D.L.; Tsai, H.; Seidel, B.R.; Batte, G.L.; Dodds, N.E.; Hofman, G.L.; Walters, L.C.

    1991-01-01

    Significant advances in the understanding of behavior and performance of metallic fuels to high burnup have been achieved over the past four decades. Metallic fuels were the first fuels for liquid-metal-cooled fast reactors (LMR) but in the late 1960's worldwide interest turned toward ceramic fuels before the full potential of metallic fuel could be achieved. Now metallic fuels are recognized as a preferred viable option with regard to safety, integral fuel cycle, waste minimization and deployment economics. This paper reviews the key advances in the last decade and highlights the behavior and performance features which have demonstrated a much greater potential than previously expected

  1. Monitoring of radiation in the atmosphere and a food chain. Results in the Netherlands in 1995

    International Nuclear Information System (INIS)

    Drost, R.M.S.; Koolwijk, A.C.; Kwakman, P.J.M.; Koops, J.C.; Van Lunenburg, A.P.P.A.; Nissan, L.; Ockhuizen, A.; Pennders, R.M.J.; Reinen, H.A.J.M.; Tax, R.B.; Tijsmans, M.H.; De Vries, L.J.; Van Zanten, R.; Aldenkamp, F.J.; Van Tuinen, S.T.

    1996-09-01

    The NMP of the CCRX is essential for an adequate assessment of radioactivity in the biosphere. The programme of RIVM/LSO includes samples of airdust and deposition taken at the RIVM premises in Bilthoven. Samples of grass and milk were taken from the surroundings of nuclear installations in the Netherlands and on Dutch territory in the vicinity of such installations situated abroad. An overall country milk sample from four milk factories in the Netherlands was also analysed. In this report also the 1995 data of the National Radioactivity Monitoring Network (LMR) are presented. 20 figs., 4 tabs., 1 appendix, 28 refs

  2. A risk assessment of the SAFR plant

    International Nuclear Information System (INIS)

    Rutherford, P.D.; Mills, J.C.; Lancet, R.T.; Nourjah, P.

    1987-01-01

    The Sodium Advanced Fast Reactor (SAFR) is a modular, advanced concept, Liquid Metal Reactor (LMR), funded by the U.S., and designed by Rockwell International, Bechtel Corporation, and Combustion Engineering. SAFR utilizes the inherently safe features of small fast reactors, including natural convection decay heat removal systems, a self-actuated shutdown system (SASS) and inherent core response to design basis events without scram including transient overpower (TOP), loss of flow (LOF), and loss of heat sink (LOHS) events. A Level 3 probabilistic risk assessment (PRA) has been performed which demonstrates considerable reduction in plant and public risk compared to current commercial reactors. (orig./HSCH)

  3. Avaliação dos resultados do reparo artroscópico de lesões do manguito rotador em pacientes com até 50 anos de idade Evaluation of the results from arthroscopic repair on rotator cuff injuries among patients under 50 years of age

    Directory of Open Access Journals (Sweden)

    Alberto Naoki Miyazaki

    2011-01-01

    Full Text Available OBJETIVO: Avaliar o resultado do tratamento cirúrgico das lesões do manguito rotador (LMR por via artroscópica nos pacientes com até 50 anos de idade. MÉTODOS: Entre agosto de 1998 e dezembro de 2007 foram reavaliados 63 pacientes com LMR submetidos a este tratamento pelo Grupo de Ombro e Cotovelo do Departamento de Ortopedia e Traumatologia da Faculdade de Ciências Médica da Santa Casa de São Paulo - "Pavilhão Fernandinho Simonsen". Foram incluídos no estudo todos os pacientes com LMR com idade até 50 anos e com seguimento mínimo pós-operatório de 24 meses. RESULTADOS: Pelos critérios de avaliação da UCLA, 59 (92% pacientes tiveram resultados excelentes e bons; cinco (8%, regulares; e nenhum ruim. A amplitude média dos movimentos na avaliação pós-operatória foi de 145˚ na elevação, 47˚ na rotação lateral e de T10 na rotação medial. Os resultados insatisfatórios estiveram associados com o tempo prolongado da lesão, demonstrando uma relação estatisticamente significante. CONCLUSÃO: O reparo artroscópico da LMR nos pacientes jovens traz resultados bons e excelentes na maioria dos pacientes.OBJECTIVE: To assess the results from arthroscopic surgical treatment of rotator cuff injuries among patients under 50 years of age. METHODS: Sixty-three patients with rotator cuff injuries who underwent arthroscopic surgical treatment performed by the Shoulder and Elbow Group of the Department of Orthopedics and Traumatology, in the Fernandinho Simonsen wing of Santa Casa Medical School, São Paulo, between August 1998 and December 2007, were reassessed. The study included all patients with rotator cuff injuries who were under 50 years of age and had been followed up postoperatively for at least 24 months. RESULTS: According to the UCLA evaluation criteria, 59 patients (92% showed excellent and good results; five (8% showed fair results; and none showed poor results. The postoperative evaluation showed that the mean range of

  4. Advanced fabrication technology

    International Nuclear Information System (INIS)

    Sheely, W.F.

    1986-01-01

    The Fuel Cycle Plant is a multipurpose nuclear facility located on the Hanford Nuclear Reservation in eastern Washington state. The facility is part of the Hanford Engineering Development Laboratory which is operated by Westinghouse Hanford Company for the Department of Energy. The Fuel Cycle Plant is currently being prepared to support the Liquid Metal Reactors Program with fuel fabrication services for the Fast Flux Test Facility and other LMR programs. This report describes the technical innovations to be utilized in the operation of this plant

  5. The replacement of an electromagnetic primary sodium sampling pump in the Fast Flux Test Facility

    International Nuclear Information System (INIS)

    Grygiel, M.L.; McCargar, C.G.

    1985-01-01

    On November 16, 1984 a leak was discovered in one of the Fast Flux Test Facility (FFTF) Primary Sodium Sampling System electromagnetic pumps. The leak was discovered in the course of routine cell entry to investigate a shorted trace heat element. The purpose of this paper is to describe the circumstances surrounding the occurrence of the leak, the actions taken to replace the damaged pump and the additional steps which were necessary to return the plant to power. In addition, the processes involved in producing the leak are described briefly. The relative ease of recovery from this incident is indicative of the overall feasibility of the Liquid Metal Reactor (LMR) operational concept

  6. Sodium Fast Reactor Safety and Licensing Research Plan

    International Nuclear Information System (INIS)

    Denman, Matthew; Lachance, Jeff; Sofu, Tanju; Wigeland, Roald; Flanagan, George; Bari, Robert

    2013-01-01

    Conclusions: The Sodium Fast Reactor Safety and Licensing Research Plan reports conclude a multi-year expert elicitation process. All information included in the studies are publicly available and the reports are UUR. These reports are intended to guide SFR researchers in the safety and licensing arena to important and outstanding issues Two (and a half) projects have been funded based on the recommendations in this report: • Modernization of SAS4A; • Incorporation of Contain/LMR with MELCOR; • (Data recovery at INL and PNNL)

  7. Integral data for fast reactors

    International Nuclear Information System (INIS)

    Collins, P.J.; Poenitz, W.P.; McFarlane, H.F.

    1988-01-01

    Requirements at Argonne National Laboratory to establish the best estimates and uncertainties for LMR design parameters have lead to an extensive evaluation of the available critical experiment database. Emphasis has been put upon selection of a wide range of cores, including both benchmark, assemblies covering a range of spectra and compositions and power reactor mock-up assemblies with diverse measured parameters. The integral measurements have been revised, where necessary, using the most recent reference data and a covariance matrix constructed. A sensitivity database has been calculated, embracing all parameters, which enables quantification of the relevance of the integral data to parameters calculated with ENDF/B-V.2 cross sections

  8. Performance assessment modeling of pyrometallurgical process wasteforms

    International Nuclear Information System (INIS)

    Nutt, W.M.; Hill, R.N.; Bullen, D.B.

    1995-01-01

    Performance assessment analyses have been completed to estimate the behavior of high-level nuclear wasteforms generated from the pyrometallurgical processing of liquid metal reactor (LMR) and light water reactor (LWR) spent nuclear fuel. Waste emplaced in the proposed repository at Yucca Mountain is investigated as the basis for the study. The resulting cumulative actinide and fission product releases to the accessible environment within a 100,000 year period from the various pyrometallurgical process wasteforms are compared to those of directly disposed LWR spent fuel using the same total repository system model. The impact of differing radionuclide transport models on the overall release characteristics is investigated

  9. Measuring hepatic functional reserve using T1 mapping of Gd-EOB-DTPA enhanced 3T MR imaging: A preliminary study comparing with 99mTc GSA scintigraphy and signal intensity based parameters.

    Science.gov (United States)

    Nakagawa, Masataka; Namimoto, Tomohiro; Shimizu, Kie; Morita, Kosuke; Sakamoto, Fumi; Oda, Seitaro; Nakaura, Takeshi; Utsunomiya, Daisuke; Shiraishi, Shinya; Yamashita, Yasuyuki

    2017-07-01

    To determine the utility of liver T1-mapping on gadolinium-ethoxybenzyl-diethylenetriamine-pentaacetic acid (Gd-EOB-DTPA) enhanced magnetic resonance (MR) imaging for the measurement of liver functional reserve compared with the signal intensity (SI) based parameters, technetium-99m-galactosyl serum albumin ( 99m Tc-GSA) scintigraphy and indocyanine green (ICG) clearance. This retrospective study included 111 patients (Child-Pugh-A 90; -B 21) performed with both Gd-EOB-DTPA enhanced liver MR imaging and 99m Tc-GSA (76 patients with ICG). Receiver operating characteristic (ROC) curve analysis was performed to compare diagnostic performances of T1-relaxation-time parameters [pre-(T1pre) and post-contrast (T1hb) Gd-EOB-DTPA], SI based parameters [relative enhancement (RE), liver-to-muscle-ratio (LMR), liver-to-spleen-ratio (LSR)] and 99m Tc-GSA scintigraphy blood clearance index (HH15)] for Child-Pugh classification. Pearson's correlation was used for comparisons among T1-relaxation-time parameters, SI-based parameters, HH15 and ICG. A significant difference was obtained for Child-Pugh classification with T1hb, ΔT1, all SI based parameters and HH15. T1hb had the highest AUC followed by RE, LMR, LSR, ΔT1, HH15 and T1pre. The correlation coefficients with HH15 were T1pre 0.22, T1hb 0.53, ΔT1 -0.38 of T1 relaxation parameters; RE -0.44, LMR -0.45, LSR -0.43 of SI-based parameters. T1hb was highest for correlation with HH15. The correlation coefficients with ICG were T1pre 0.29, T1hb 0.64, ΔT1 -0.42 of T1 relaxation parameters; RE -0.50, LMR -0.61, LSR -0.58 of SI-based parameters; 0.64 of HH15. Both T1hb and HH15 were highest for correlation with ICG. T1 relaxation time at post-contrast of Gd-EOB-DTPA (T1hb) was strongly correlated with ICG clearance and moderately correlated HH15 with 99m Tc-GSA. T1hb has the potential to provide robust parameter of liver functional reserve. Copyright © 2017 Elsevier B.V. All rights reserved.

  10. A conceptual study of actinide transmutation system with proton accelerator, (2)

    International Nuclear Information System (INIS)

    Takizuka, T.; Takada, H.; Kanno, I.; Ogawa, T.; Nishida, T.; Kaneko, Y.

    1990-01-01

    This paper describes the thermal hydraulics of the accelerator-driven actinide incineration target system based on power distribution profiles to assess the maximum attainable power. In the case of Na cooling, the reference target operates at a thermal power of 404 MW and a beam current of 18.2 mA. The system transmutes 114 kg actinides per year, which implies that the annual actinide products from about 4.3 units of 3000 MWt pressurized water reactor (PWR) can be incinerated. The Pb-Bi cooled reference target operates at a thermal power of 163 MW and beam current of 5.4 mA. The system transmutes 42 kg actinides annually, and can serve about 1.8 units of PWR. The maximum thermal power can be increased by a factor of about 2 by introducing tungsten pins in the high flux region to flatten the power distribution. The Na cooled tungsten-loaded target operates at a thermal power of 691 MW and beam current of 22.6 mA. The system can serve about 7.6 PWRs. The tungsten-loaded target cooled by Pb-Bi operates at a thermal power of 343 MW at a 9.8 mA beam current. The system can process the actinide from about 3.8 PWRs. (N.K.)

  11. Signatures of reproductive events on blood counts and biomarkers of inflammation: Implications for chronic disease risk.

    Directory of Open Access Journals (Sweden)

    Daniel W Cramer

    Full Text Available Whether inflammation mediates how reproductive events affect chronic-disease risk is unclear. We studied inflammatory biomarkers in the context of reproductive events using National Health and Nutrition Examination Survey (NHANES data. From 15,986 eligible women from the 1999-2011 data cycles, we accessed information on reproductive events, blood counts, C-reactive protein (CRP, and total homocysteine (tHCY. We calculated blood-count ratios including: platelet-lymphocyte (PLR, lymphocyte-monocyte (LMR, platelet-monocyte (PMR, and neutrophil-monocyte (NMR. Using sampling weights per NHANES guidelines, means for counts, ratios, or biomarkers by reproductive events were compared using linear regression. We performed trend tests and calculated p-values with partial sum of squares F-tests. Higher PLR and lower LMR were associated with nulliparity. In postmenopausal women, lower PMR was associated with early age at first birth and higher NMR with later age at and shorter interval since last birth. Lower PNR and higher neutrophils and tHCY were associated with early natural menopause. In all women, the neutrophil count correlated positively with CRP; but, in premenopausal women, correlated inversely with tHCY. Reproductive events leave residual signatures on blood counts and inflammatory biomarkers that could underlie their links to chronic disease risk.

  12. The R and D issues necessary to achieve the safety design of commercialized liquid-metal cooled fast reactors

    International Nuclear Information System (INIS)

    Shoji, Kotake; Koji, Dozaki; Shigenobu, Kubo; Yoshio, Shimakawa; Hajime, Niwa; Masakazu, Ichimiya

    2002-01-01

    Within the framework of the feasibility study on commercialized fast reactor cycle systems (hereafter described as F/S), the safety design principle is investigated and several kinds of design studies are now in progress. Among the designs for liquid-metal cooled fast reactor (LMR), the advanced loop type sodium cooled fast reactor (FR) is one of the promising candidate as future commercialized LMR. In this paper, the safety related research and development (R and D) issues necessary to achieve the safety design are described along the defence-in-depth principle, taking account of not only the system characteristics of the advanced loop concepts but also design studies and R and D experiences so far. Safety issues related to the hypothetical core disruptive accidents (CDA) are emphasized both from the prevention and mitigation. A re-criticality free core concept with a special fuel assembly is pursued by performing both analytical and experimental efforts, in order to realize the rational design and to establish easy-to-understand safety logic. Sodium related issues are also given to ensure plant availability and to enhance the acceptability to the public. (authors)

  13. Evaluation of the confinement option for LMRs

    International Nuclear Information System (INIS)

    Himes, D.A.; Stepnewski, D.D.; Franz, G.R.

    1985-12-01

    The coolant in liquid metal cooled reactors operates at low pressures and therefore contains relatively little stored energy compared to LWR systems. This presents the possibility of using a more conventional building for containment coupled with a confinement system which vents the internal volume of the building through a filter/scrubber. The confinement system would be designed to keep the internal pressure in the containment near atmospheric thereby minimizing unfiltered leakage. The principal benefits of such an arrangement would be lower capital cost and less stringent leaktightness requirements permitting simpler and less disruptive testing. In conclusion, the confinement system assumed here would reduce consequences to the public of an LMR HCDA to acceptable levels. However control room doses are unacceptable due to the noble gas concentration inside the control room. A confinement system is therefore a viable design option for LMR's provided means are included for keeping noble gases out of the control room. Such means are readily available including, for example, selectable remote air intakes, an exhaust stack, or a noble gas filter. Probably the most satisfactory alternative would be a large cryogenic filter on the confinement system exhaust

  14. Seismic analysis of liquid metal reactor piping systems

    International Nuclear Information System (INIS)

    Wang, C.Y.

    1987-01-01

    To safely assess the adequacy of the LMR piping, a three-dimensional piping code, SHAPS, has been developed at Argonne National Laboratory. This code was initially intended for calculating hydrodynamic-wave propagation in a complex piping network. It has salient features for treating fluid transients of fluid-structure interactions for piping with in-line components. The code also provides excellent structural capabilities of computing stresses arising from internal pressurization and 3-D flexural motion of the piping system. As part of the development effort, the SHAPS code has been further augmented recently by introducing the capabilities of calculating piping response subjected to seismic excitations. This paper describes the finite-element numerical algorithm and its applications to LMR piping under seismic excitations. A time-history analysis technique using the implicit temporal integration scheme is addressed. A 3-D pipe element is formulated which has eight degrees of freedom per node (three displacements, three rotations, one membrane displacement, and one bending rotation) to account for the hoop, flexural, rotational, and torsional modes of the piping system. Both geometric and material nonlinearities are considered. This algorithm is unconditionally stable and is particularly suited for the seismic analysis

  15. Insights into Atlantic multidecadal variability using the Last Millennium Reanalysis framework

    Science.gov (United States)

    Singh, Hansi K. A.; Hakim, Gregory J.; Tardif, Robert; Emile-Geay, Julien; Noone, David C.

    2018-02-01

    The Last Millennium Reanalysis (LMR) employs a data assimilation approach to reconstruct climate fields from annually resolved proxy data over years 0-2000 CE. We use the LMR to examine Atlantic multidecadal variability (AMV) over the last 2 millennia and find several robust thermodynamic features associated with a positive Atlantic Multidecadal Oscillation (AMO) index that reveal a dynamically consistent pattern of variability: the Atlantic and most continents warm; sea ice thins over the Arctic and retreats over the Greenland, Iceland, and Norwegian seas; and equatorial precipitation shifts northward. The latter is consistent with anomalous southward energy transport mediated by the atmosphere. Net downward shortwave radiation increases at both the top of the atmosphere and the surface, indicating a decrease in planetary albedo, likely due to a decrease in low clouds. Heat is absorbed by the climate system and the oceans warm. Wavelet analysis of the AMO time series shows a reddening of the frequency spectrum on the 50- to 100-year timescale, but no evidence of a distinct multidecadal or centennial spectral peak. This latter result is insensitive to both the choice of prior model and the calibration dataset used in the data assimilation algorithm, suggesting that the lack of a distinct multidecadal spectral peak is a robust result.

  16. The advanced controls program at Oak Ridge National Laboratory

    International Nuclear Information System (INIS)

    Knee, H.E.; White, J.D.

    1990-01-01

    The Oak Ridge National Laboratory (ORNL), under sponsorship of the US Department of Energy (DOE), is conducting research that will lead to advanced, automated control of new liquid-metal-reactor (LMR) nuclear power plants. Although this program of research (entitled the ''Advanced Controls Program'') is focused on LMR technology, it will be capable of providing control design, test, and qualification capability for other advanced reactor designs (e.g., the advanced light water reactor [ALWR] and high temperature gas-cooled reactor [HTGR] designs), while also benefiting existing nuclear plants. The Program will also have applicability to complex, non-nuclear process control environments (e.g., petrochemical, aerospace, etc.). The Advanced Controls Program will support capabilities throughout the entire plant design life cycle, i.e., from the initial interactive first-principle dynamic model development for the process, systems, components, and instruments through advanced control room qualification. The current program involves five principal areas of research activities: (1) demonstrations of advanced control system designs, (2) development of an advanced controls design environment, (3) development of advanced control strategies, (4) research and development (R ampersand D) in human-system integration for advanced control system designs, and (5) testing and validation of advanced control system designs. Discussion of the research in these five areas forms the basis of this paper. Also included is a description of the research directions of the program. 8 refs

  17. Trends vs. reactor size of passive reactivity shutdown and control performance

    International Nuclear Information System (INIS)

    Wade, D.C.; Fujita, E.K.

    1987-01-01

    For LMR concepts, the goal of passive reactivity shutdown has been approached in the US by designing the reactors for favorable relationships among the power, power/flow, and inlet temperature coefficients of reactivity, for high internal conversion ratio (yielding small burnup control swing), and for a primary pump coastdown time appropriately matched to the delayed neutron hold back of power decay upon negative reactivity input. The use of sodium bonded metallic fuel pins has facilitated the achievement of the massive shutdown design goals as a consequence of their high thermal conductivity and high effective heavy metal density. Alternately, core designs based on derated oxide pins may be able to achieve the passive shutdown features at the cost of larger core volume and increased initial fissile inventory. For LMR concepts, the passive decay heat removal goal of inherent safety has been approached in US designs by use of pool layouts, larger surface to volume ratio of the reactor vessel with natural draft air cooling of the vessel surface, elevations and redans which promote natural circulation through the core, and thermal mass of the pool contents sufficient to absorb that initial transient decay heat which exceeds the natural draft air cooling capacity. This paper describes current US ''inherently safe'' reactor design

  18. Competition between the inter-valley scattering and the intra-valley scattering on magnetoconductivity induced by screened Coulomb disorder in Weyl semimetals

    Directory of Open Access Journals (Sweden)

    Xuan-Ting Ji

    2017-10-01

    Full Text Available Recent experiments on Weyl semimetals reveal that charged impurities may play an important role. We use a screened Coulomb disorder to model the charged impurities, and study the magneto-transport in a two-node Weyl semimetal. It is found that when the external magnetic field is applied parallel to the electric field, the calculated longitudinal magnetoconductivity shows positive in the magnetic field, which is just the negative longitudinal magnetoresistivity (LMR observed in experiments. When the two fields are perpendicular to each other, the transverse magnetoconductivities are measured. It is found that the longitudinal (transverse magnetoconductivity is suppressed (enhanced sensitively with increasing the screening length. This feature makes it hardly to observe the negative LMR in Weyl semimetals experimentally owing to a small screening length. Our findings gain insight into further understanding on recently actively debated magneto-transport behaviors in Weyl semimetals. Furthermore we studied the relative weight of the inter-valley scattering and the intra-valley scattering. It shows that the former is as important as the latter and even dominates in the case of strong magnetic fields and small screening length. We emphasize that the discussions on inter-valley scattering is out of the realm of one-node model which has been studied.

  19. Inter-subchannel heat transfer modeling for a subchannel analysis of liquid metal-cooled reactors

    International Nuclear Information System (INIS)

    Hae-Yong, Jeong; Kwi-Seok, Ha; Young-Min, Kwon; Yong-Bum, Lee; Dohee, Hahn

    2007-01-01

    In a subchannel approach, the temperature, pressure and velocity in a subchannel are averaged, and one representative thermal-hydraulic condition specifies the state of a subchannel. To enhance the predictability of a subchannel analysis code, it is required to model the inter-subchannel heat transfer between the adjacent subchannels as accurately as possible. One of the critical parameters which determine the thermal-hydraulic behavior of the coolant in subchannels is the heat conduction between two neighboring sub-channels. This portion of a heat transfer becomes more important in the design of an LMR (Liquid Metal-cooled Reactor) because of the high heat capacity of the liquid metal coolant. The other important part of heat transfer is the mixing of flow as a form of cross flow. Especially, the turbulent mixing caused by the eddy motion of fluid across the gap between the subchannels enhances the exchange of the momentum and the energy through the gap with no net transport of the mass. Major results of recent efforts on these modeling have been implemented in a subchannel analysis code MATRA-LMR-FB. The analysis shows that the accuracy of a subchannel analysis code is improved by enhancing the models describing the conduction heat transfer and the cross-flow mixing, especially at low flow rate. (authors)

  20. Determination of plateau slope and activity using filter measurement results and W. Chauvenet's criterion (Mage II and Fortran IV calculation programmes); Determination de pente de palier et d'activite a partir de resultats de mesure filtres selon le critere de W. Chauvenet (programmes de calcul en Mage II et Fortran IV)

    Energy Technology Data Exchange (ETDEWEB)

    Becker, A [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires, Departement d' Electronique Generale, Laboratoire de Metrologie de la Radioactivite

    1967-10-01

    In order to permit (at least partially) the objective comparison of plateau characteristics of gas-ionisation counters, plateaus which are obtained when each radioactive sample from normal LMR production is measured, a programme has been drawn up (on an electronic computer) comprising a processing section using least squares for obtaining the corrected plateaux and energies. With a view to an automatic operation of radio-measurement chains, the programme also comprises a preliminary section in which the statistical considerations of B. Peirce have been applied in the version better known as Chauvenet's criterion; this has been done with a view to eliminate measurement results which are dubious and even totally wrong. (author) [French] Pour rendre possibles (au moins partiellement) des comparaisons objectives entre paliers de caracteristiques de compteurs a ionisation gazeuse, paliers traces lors de la mesure de chaque etalon radioactif de la production courante du L.M.R., il a ete ecrit un programme (sur machine a calculer electronique) comportant une partie de traitement par les moindres carres en vue de la determination de pentes et d'activites corrigees. En prevision d'une exploitation automatique de cha es de radio-mesure, le programme comporte en outre une partie preliminaire dans laquelle des considerations statistiques dues a B. Peirce ont ete appliquees dans leur version plus connue sous le nom de critere de Chauvenet et ce dans le but d'une elimination des resultats de mesure suspects et meme veritablement aberrants. (auteur)

  1. Under-Sodium Inspection Techniques for Reactor Internals of KALIMER-600 using Ultrasonic Waveguide Sensor

    International Nuclear Information System (INIS)

    Joo, Young Sang; Kim, Seok Hoon; Lee, Jae Han

    2005-01-01

    KALIMER-600 is a pool type liquid metal reactor (LMR) which is operated with a sodium coolant. The reactor internals of KALIMER-600 are submerged in a liquid sodium pool. As the liquid sodium is opaque to the light, a conventional visual inspection can not be used for observing the internal structures under a sodium condition. An under-sodium viewing (USV) technique using an ultrasonic wave should be applied for the observation of the refueling maneuver and the in-service inspection of the reactor internals. Under-sodium inspection technology utilizing ultrasonic waves has been widely developed for a visualization of the reactor core and internal components of LMR. Immersion sensors and waveguide sensors have been applied to the USV inspection. The immersion sensor has a precise imaging capability, but may have high temperature restrictions and an uncertain life. The waveguide sensor has the advantages of simplicity and reliability, but limited in its movement. The new plate-type waveguide sensor has been developed as a useful alternative to immersion sensors for USV applications. In the viewing and monitoring applications, a beam steering function of a waveguide sensor might be required. A new waveguide sensor and technique are being developed to overcome the limitations of a waveguide ultrasonic sensor. In this study, the under-sodium inspection techniques using the newly developed waveguide sensor for the reactor internal structures of KALIMER-600 is proposed

  2. Changes of endocrine and ultrasound markers as ovarian aging in modifying the Stages of Reproductive Aging Workshop (STRAW) staging system with subclassification of mid reproductive age stage.

    Science.gov (United States)

    Ding, Ting; Luo, Aiyue; Jiang, Jingjing; Du, Xiaofang; Yang, Shuhong; Lai, Zhiwen; Shen, Wei; Lu, Yunping; Ma, Ding; Wang, Shixuan

    2013-01-01

    To demonstrate the changes of ovarian aging markers across the Stages of Reproductive Aging Workshop (STRAW) stages and modify it with subclassification of mid reproductive age stage (MR). Healthy females were classified according to the STRAW system. Serum basal FSH, LH, E2, and anti-Müllerian hormone (AMH) were detected, FSH/LH ratio calculated, and antral follicle counts (AFCs) determined in follicular phase. Progression through the whole STRAW stages under MR stage subdivided is associated with elevations in FSH, LH, FSH/LH ratio and decreases in E2, AMH and AFCs (p age in MR stage. 0.982 ng/ml AMH and 3 antral follicles (low level of MR 25-30 years) were set as cutoffs to distinguish MR stage into early mid reproductive age (EMR) and late mid reproductive age (LMR) stages. The women in EMR stage compared with LMR could retrieve more oocytes in IVF treatment (p stage, demonstrating disparate reproductive aging period with reduced ovarian reserve in young age across the STRAW stages.

  3. Do socio-economic disparities in dental treatment needs exist in Lithuanian adolescents?

    Science.gov (United States)

    Aleksejuniene, Jolanta; Brukiene, Vilma

    2008-01-01

    To explore disparities in needs for dental treatment which arise from individual and area-based socio-economic determinants. A cross-sectional study conducted in 22 randomly selected Lithuanian areas. In each of the pre-selected areas, one secondary school was randomly chosen. A total of 885 15-16-year-olds participated. Outcome measures. Dental treatment need was evaluated following the WHO guidelines and aQuantitative Summative Dental Treatment Needs Index (QSDTNI) was used to calculate the total burden of needs. The information about socio-economical determinants was obtained from a structured questionnaire and national statistics database. Individual socio-economic status (SES) measures were: parents' occupation, family structure, family income and affordability to have holiday used as a proxy measure for income. The area-based SES estimates were: unemployment, average household income, educational attainment, natural increase/decrease of population in an area and net migration rate. Data was analyzed by bivariate and multivariate analyses. None of significant bivariate associations between individual socio-economic variables and the QSDTNI were detected. Among area-based variables natural increase/decrease of population in an area and net migration rate were significantly related to the QSDTNI. Two individual and two area-based factors were extracted and introduced into Linear Multiple Regression Analysis (LMR). The LMR model was significant, but only one factor, i.e. area demographics, significantly contributed to this model. There are no clear social disparities in dental treatment needs in Lithuanian adolescents.

  4. Preliminary Evaluation of the Diverse Protection System in PGSFR

    International Nuclear Information System (INIS)

    Jeong, Taekyeong; Chang, Won-Pyo; Seong, Seung Hwan; Ahn, Sang June; Kang, Seok Hun; Choi, Chiwoong; Yoo, Jin; Lee, Kwi Lim; Lee, Seung Won; Jeong, Jae-Ho; Ha, Kwi-Seok

    2015-01-01

    The anticipated transient without scram (ATWS) is defined as an abnormal transient with failure of scram actuation. It is one of the “worst case” accident based on the United States Nuclear Regulatory Commission (U.S.NRC). Consideration frequently motivates the NRC to take regulatory action. An evaluation of this event is also a general requirement due to a potential safety issue that may lead to core damage under postulated condition. This paper estimated the set-points sensitivity test of the diverse protection system (DPS) related with unprotected events of the prototype generation-IV sodium cooled fast reactor (PGSFR) including unprotected transient over power (UTOP) and unprotected loss of flow (ULOF) by MARS-LMR code. The variation of the power to flow (P/Q) of UTOP and ULOF is illustrated to conduct the set-points sensitivity test of DPS. Also we estimated the effect of the DPS introduction after selecting UTOP, ULOF event as the unprotected events which are predicted to aggravate the events. This paper estimated the set-points sensitivity test of DPS related with unprotected events of PGSFR including UTOP and ULOF by MARS-LMR code. The results indicated that there is no significant difference in both RPS and DPS about the initiating time of each event. Therefore, this study found that the urgent manage for safety of the reactor when RPS failed is possible by the applying DPS

  5. Pre-treatment inflammatory indexes as predictors of survival and cetuximab efficacy in metastatic colorectal cancer patients with wild-type RAS.

    Science.gov (United States)

    Yang, Jing; Guo, Xinli; Wang, Manni; Ma, Xuelei; Ye, Xiaoyang; Lin, Panpan

    2017-12-07

    This study aims at evaluating the prognostic significance of neutrophil-to-lymphocyte ratio (NLR), platelet-to-lymphocyte ratio (PLR), lymphocyte-to-monocyte ratio (LMR), and systemic immune-inflammation indexes (SII) in metastatic colorectal cancer (mCRC) patients treated with cetuximab. Ninety-five patients receiving cetuximab for mCRC were categorized into the high or low NLR, PLR, LMR, and SII groups based on their median index values. Univariate and multivariate survival analysis were performed to identify the indexes' correlation with progression-free survival (PFS) and overall survival (OS). In the univariate analysis, ECOG performance status, neutrphil counts, lymphocyte counts, monocyte counts, NLR, PLR, and LDH were associated with survival. Multivariate analysis showed that ECOG performance status of 0 (hazard ratio [HR] 3.608, p < 0.001; HR 5.030, p < 0.001, respectively), high absolute neutrophil counts (HR 2.837, p < 0.001; HR 1.922, p = 0.026, respectively), low lymphocyte counts (HR 0.352, p < 0.001; HR 0.440, p = 0.001, respectively), elevated NLR (HR 3.837, p < 0.001; HR 2.467, p = 0.006) were independent predictors of shorter PFS and OS. In conclusion, pre-treatment inflammatory indexes, especially NLR were potential biomarkers to predict the survival of mCRC patients with cetuximab therapy.

  6. Unites States position paper on sodium fires. Design basis and testing

    International Nuclear Information System (INIS)

    Lancet, R.T.; Johnson, R.P.; Matlin, E.; Vaughan, E.U.; Fields, D.E.; Glueckler, E.; McCormack, J.D.; Miller, C.W.; Pedersen, D.R.

    1989-01-01

    This paper focuses on designs, analyses, and tests performed since the last Sodium Fires Meeting of the IAEA International Working Group on Fast Reactors in May 1982. Since the U.S. Liquid Metal Reactor (LMR) program is focused on the two advanced LMRs, SAFR and PRISM, the paper relates this work to these designs. First, the design philosophy and approach taken by these advanced pool reactors are described. This includes methods of leak detection, the design basis leaks, and passive accommodation of sodium fires. Then the small- and large-scale sodium fire tests performed in support of the Clinch River Breeder Reactor Plant (CRBRP) program, including post-accident cleanup, are presented and related to the advanced LMR designs. Next, the assessment and behavior of the aerosols generated are discussed including generation rate, behavior within structures, release and dispersal, and deposition on safety-grade equipment. Finally, the impact of these aerosols on the performance of safety-grade decay heat removal heat exchange surfaces is discussed including some test results as well as planned tests. (author)

  7. Passive safety testing at the Fast Flux Test Facility

    International Nuclear Information System (INIS)

    Lucoff, D.M.

    1989-01-01

    During 1986, the Fast Flux Test Facility (FFTF) conducted several tests designed to improve the understanding of the passive safety characteristics of an oxide-fueled liquid-metal reactor (LMR). Static and dynamic tests were performed over a broad range of power, flow, and temperature conditions that extended beyond those for normal operation. Key results of these tests are presented. Stable operation at low power with natural circulation cooling was demonstrated. A passive safety enhancement feature, the gas expansion module (GEM) was developed specifically to offset the large amount of cooldown reactivity that needs to be controlled in an oxide-fueled LMR undergoing an unprotected loss-of-flow accident. Nine GEMs were built and successfully tested in FFTF. With the reactor at 50% power (200 MW (thermal)), the main coolant pumps were turned off and the normal control rod scram response was inhibited. The GEMs and inherent core reactivity feedback mechanisms took the core subcritical with a modest peak coolant temperature transient that reached 85 degrees C above the pretransient value and always maintained a >400 degrees C margin to the sodium boiling point (910 degrees C)

  8. Operating and test experience of EBR-II

    International Nuclear Information System (INIS)

    Sackett, J.I.

    1991-01-01

    EBR-II has operated for 27 years, the longest for any Liquid Metal Reactor (LMR) power plant. During that time, much has been learned about successful LMR operation and design. The basic lesson is that conservatism in design can pay significant dividends in operating reliability. Furthermore, such conservatism need not mean high cost. The EBR-II system emphasizes simplicity, minimizing the number of valves in the heat transport system, for example, and simplifying the primary heat-transport-system layout. Another lesson is that emphasizing reliability of the steam generating system at the sodium-water interface (by using duplex tubes in the case of EBR-II) has been well worth the higher initial costs; no problems with leakage have been encountered in EBR-II's operating history. Locating spent fuel storage in the primary tank and providing for decay heat removal by natural connective flow have also been contributors to EBR-II's success. The ability to accommodate loss of forced cooling or loss of heat sink passively has resulted in benefits for simplification, primarily through less reliance on emergency power and in not requiring the secondary sodium or steam systems to be safety grade. Also, the 'piped-pool' arrangement minimizes thermal stress to the primary tank and enhances natural convective flow. These benefits have been realized through a history of operation that has seen EBR-II evolve through four major phases in its test programs, culminating in its present mission as the Integral Fast Reactor (IFR) prototype. (author)

  9. Comparison of oxide- and metal-core behavior during CRBRP [Clinch River Breeder Reactor Plant] station blackout

    International Nuclear Information System (INIS)

    Polkinghorne, S.T.; Atkinson, S.A.

    1986-01-01

    A resurrected concept that could significantly improve the inherently safe response of Liquid-Metal cooled Reactors (LMRs) during severe undercooling transients is the use of metallic fuel. Analytical studies have been reported on for the transient behavior of metal-fuel cores in innovative, inherently safe LMR designs. This paper reports on an analysis done, instead, for the Clinch River Breeder Reactor Plant (CRBRP) design with the only innovative change being the incorporation of a metal-fuel core. The SSC-L code was used to simulate a protected station blackout accident in the CRBRP with a 943 MWt Integral Fast Reactor (IFR) metal-fuel core. The results, compared with those for the oxide-fueled CRBRP, show that the margin to boiling is greater for the IFR core. However, the cooldown transient is more severe due to the faster thermal response time of metallic fuel. Some additional calculations to assess possible LMR design improvements (reduced primary system pressure losses, extended flow coastdown) are also discussed. 8 refs., 13 figs., 2 tabs

  10. The far-infrared spectrum of the OH radical

    Science.gov (United States)

    Brown, J. M.; Schubert, J. E.; Evenson, K. M.; Radford, H. E.

    1982-01-01

    It is thought likely that the study of spectral lines in the far-infrared might provide at least as much information about the physics and chemistry of the interstellar environment as radioastronomy. However, by comparison with the microwave region, the far-infrared is largely unexplored. There is a pressing need for good laboratory data to aid searches and assignments of spectra from the interstellar clouds and nebulae. Brown et al. (1981) have conducted a study of the laser magnetic resonance (LMR) spectrum of the OH radical in its ground state at far-infrared wavelengths. The present investigation is concerned with the computation of the frequencies of individual hyperfine transitions involving all rotational levels up to J = 4 1/2. The results of the calculation are presented in a table. The results are summarized in a diagram which shows the low-lying energy levels of OH. The frequencies of transitions between levels studied directly in the LMR spectrum are quite reliable.

  11. Development of a steady-state calculation model for the KALIMER PDRC(Passive Decay Heat Removal Circuit)

    International Nuclear Information System (INIS)

    Chang, Won Pyo; Ha, Kwi Seok; Jeong, Hae Yong; Kwon, Young Min; Eoh, Jae Hyuk; Lee, Yong Bum

    2003-06-01

    A sodium circuit has usually featured for a Liquid Metal Reactor(LMR) using sodium as coolant to remove the decay heat ultimately under accidental conditions because of its high reliability. Most of the system codes used for a Light Water Reactor(LWR) analysis is capable of calculating natural circulation within such circuit, but the code currently used for the LMR analysis does not feature stand alone capability to simulate the natural circulation flow inside the circuit due to its application limitation. To this end, the present study has been carried out because the natural circulation analysis for such the circuit is realistically raised for the design with a new concept. The steady state modeling is presented in this paper, development of a transient model is also followed to close the study. The incompressibility assumption of sodium which allow the circuit to be modeled with a single flow, makes the model greatly simplified. Models such as a heat exchanger developed in the study can be effectively applied to other system analysis codes which require such component models

  12. SNL/JAEA Collaborations on Sodium Fire Benchmarking.

    Energy Technology Data Exchange (ETDEWEB)

    Clark, Andrew Jordan [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Denman, Matthew R [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Takata, Takashi [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Ohshima, Hiroyuki [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)

    2017-11-01

    Two sodium spray fire experiments performed by Sandia National Laboratories (SNL) were used for a code - to - code comparison between CONTAIN - LMR and SPHINCS. Both computer codes are used for modeling sodium accidents in sodium fast reactors. The comparison between the two codes provides insights into the ability of both codes to model sodium spray fires. The SNL T3 and T4 experiments are 20 kg sodium spray fires with sodium spray temperature s of 200 deg C and 500 deg C, respe ctively. Given the relatively low sodium temperature in the SNL T3 experiment, the sodium spray experienced a period of non - combustion. The vessel in the SNL T4 experiment experienced a rapid pressurization that caused of the instrumentation ports to fail during the sodium spray. Despite these unforeseen difficulties, both codes were shown in good agreement with the experiment s . The subsequent pool fire that develops from the unburned sodium spray is a significant characteristic of the T3 experiment. SPHIN CS showed better long - term agreement with the SNL T3 experiment than CONTAIN - LMR. The unexpected port failure during the SNL T4 experiment presented modelling challenges. The time at which the port failure occurred is unknown, but is believed to have occur red at about 11 seconds into the sodium spray fire. The sensitivity analysis for the SNL T4 experiment shows that with a port failure, the sodium spray fire can still maintain elevated pressures during the spray.

  13. Safety Analysis for Key Design Features of KALIMER-600 Design Concept

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Yong Bum; Kwon, Y. M.; Kim, E. K.; Suk, S. D.; Chang, W. P.; Jeong, H. Y.; Ha, K. S

    2007-02-15

    This report contains the safety analyses of the KALIMER-600 conceptual design which KAERI has been developing under the Long-term Nuclear R and D Program. The analyses have been performed reflecting the design developments during the second year of the 4th design phase in the program. The specific presentations are the key design features with the safety principles for achieving the safety objectives, the event categorization and safety criteria, and results on the safety analyses for the DBAs and ATWS events, the containment performance, and the channel blockages. The safety analyses for both the DBAs and ATWS events have been performed using SSC-K version 1.3., and the results have shown the fulfillment of the safety criteria for DBAs with conservative assumptions. The safety margins as well as the inherent safety also have been confirmed for the ATWS events. For the containment performance analysis, ORIGEN-2.1 and CONTAIN-LMR have been used. In results, the structural integrity has been acceptable and the evaluated exposure dose rate has been complied with 10 CFR 100 and PAG limits. The analysis results for flow blockages of 6-subchannels, 24-subchannels, and 54- subchannels with the MATRA-LMR-FB code, have assured the integrity of subassemblies.

  14. Comparison of nuclear reactor types of the next generation; Komparativni prikaz novih tipova reaktorskih komercijalnih postrojenja slijedece generacije

    Energy Technology Data Exchange (ETDEWEB)

    Pavlovic, Z; Kastelan, M [NPP Krsko (Slovenia)

    1992-07-01

    The paper presents a comparison for a selected relevant set of parameters for different commercial nuclear reactor types at the next generation. This parameters overview could serve as the base for the semi-quantitative decision bases for the selection of the future nuclear strategy. The number of advanced reactor designs of the LWR, HWR, GCR and LMR type are presented. Even currently many of them are still on the drawing boards, the concepts and designs should be assessed in the sense of sensible approach for planning the possible future nuclear strategy. (author) Clanek predstavlja usporedbu odabranih bitnih parametara karakteristicnih za razlicite tipove energetskih nuklearnih postrojenja slijedece generacije. Prikazani pregled parametara omogucava osnov za polu kvantitativnu osnovu za odlucivanje u svrhu donosenja odluke oko odrednica buduce strategije uporabe nuklearne energije. Brojni koncepti naprednih nuklearnih reaktora tipa LWR, HWR, GCR i LMR su prezentirani. S obzirom na cinjenicu da se mnogi of prezentiranih nalaze jos uvijek na crtacim daskama projektanata, koncepti i projekti koji su iz njih proizasli zahtijevaju analizu u smislu kvalitativnog pristupa planiranja moguce buduce nuklearne startegije. (author)

  15. Effects of magnetic field on the pseudogap in the Kondo semiconductor CeRhAs

    International Nuclear Information System (INIS)

    Yoshii, S.; Kindo, K.; Sasakawa, T.; Suemitsu, T.; Takabatake, T.

    2004-01-01

    The magnetization and magnetoresistance of single-crystalline CeRhAs, which is the so-called Kondo semiconductor with an energygap of ∼280 K, have been measured in pulsed magnetic field up to 55 T. At 1.3 K, the slopes of the magnetization M for H parallel b and H parallel c decrease slightly at around 16 and 13 T, respectively, while M(H parallel a) shows monotonous dependence. Weak anisotropy is observed on the whole, M b (H)>M c (H)>M a (H). M b (H) reaches only to 0.07 μ B /f.u. at 55 T, which indicates the non-magnetic state being stable even in the high magnetic field. Strongly anisotropic behaviors are observed in the magnetoresistance. The longitudinal magnetoresistance (LMR) along the b- and c-axis show characteristic structures partly associated with the anomalies of the magnetizations, while the LMR along the a-axis shows only a broad maximum. The transverse magnetoresistances (TMR) for I parallel b and I parallel c follow the relation Δρ(H)/ρ(0)∝H α (α=1.5-1.7) below 5 T, whereas TMR for I parallel a exhibits only the weak field dependence. These results suggest the existence of a narrow and anisotropic structure within the wide pseudogap structure in the density of states

  16. Preliminary Evaluation of the Diverse Protection System in PGSFR

    Energy Technology Data Exchange (ETDEWEB)

    Jeong, Taekyeong; Chang, Won-Pyo; Seong, Seung Hwan; Ahn, Sang June; Kang, Seok Hun; Choi, Chiwoong; Yoo, Jin; Lee, Kwi Lim; Lee, Seung Won; Jeong, Jae-Ho; Ha, Kwi-Seok [KAERI, Daejeon (Korea, Republic of)

    2015-05-15

    The anticipated transient without scram (ATWS) is defined as an abnormal transient with failure of scram actuation. It is one of the “worst case” accident based on the United States Nuclear Regulatory Commission (U.S.NRC). Consideration frequently motivates the NRC to take regulatory action. An evaluation of this event is also a general requirement due to a potential safety issue that may lead to core damage under postulated condition. This paper estimated the set-points sensitivity test of the diverse protection system (DPS) related with unprotected events of the prototype generation-IV sodium cooled fast reactor (PGSFR) including unprotected transient over power (UTOP) and unprotected loss of flow (ULOF) by MARS-LMR code. The variation of the power to flow (P/Q) of UTOP and ULOF is illustrated to conduct the set-points sensitivity test of DPS. Also we estimated the effect of the DPS introduction after selecting UTOP, ULOF event as the unprotected events which are predicted to aggravate the events. This paper estimated the set-points sensitivity test of DPS related with unprotected events of PGSFR including UTOP and ULOF by MARS-LMR code. The results indicated that there is no significant difference in both RPS and DPS about the initiating time of each event. Therefore, this study found that the urgent manage for safety of the reactor when RPS failed is possible by the applying DPS.

  17. Safety Analysis for PHTS Integrity by the failure of the IHTS function in PGSFR

    Energy Technology Data Exchange (ETDEWEB)

    Ahn, Sang-Jun; Chang, Won-Pyo; Ha, Kwi-Seok; Kang, Seok Hun; Choi, Chi-Woong; Lee, Kwi Lim; Lee, Seung Won; Jeong, Jae-Ho; Kim, Jin Su; Jeong, Taekyeong [KAERI, Daejeon (Korea, Republic of)

    2016-05-15

    In this paper, the failure of the heat removal function of the IHTS by the SWR event is assumed. The integrity of the PHTS is analyzed by MARS-LMR code. A sodium is used as a reactor coolant to transfer the core heat to the turbine. It rigorously reacts with a water or steam in chemical and generates the high pressure waves and high temperature reaction heat. While it has an excellent characteristics as a coolant, there is an event to be necessarily considered in the sodium cooled fast reactor design. The Sodium-Water Reaction(SWR) event can be occurred due to the rupture of steam generator tubes. This event threaten the integrity of the Primary Heat Transfer System(PHTS). It is categorized to the loss of heat sink events, which are undercooling the Primary Heat Transfer System(PHTS). In PGSFR, the SWR event can be occurred in the SG. The PHTS is analyzed to the respects of the integrity of the fuel and cladding using the MARS-LMR code. From the analysis results, the peak temperature of the fuel and cladding have a sufficient margin to the safety acceptance criteria 1,237 .deg. C and 1,075 .deg. C, respectively.

  18. 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

  19. Containment Sodium Chemistry Models in MELCOR.

    Energy Technology Data Exchange (ETDEWEB)

    Louie, David [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Humphries, Larry L. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Denman, Matthew R [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)

    2017-04-01

    To meet regulatory needs for sodium fast reactors’ future development, including licensing requirements, Sandia National Laboratories is modernizing MELCOR, a severe accident analysis computer code developed for the U.S. Nuclear Regulatory Commission (NRC). Specifically, Sandia is modernizing MELCOR to include the capability to model sodium reactors. However, Sandia’s modernization effort primarily focuses on the containment response aspects of the sodium reactor accidents. Sandia began modernizing MELCOR in 2013 to allow a sodium coolant, rather than water, for conventional light water reactors. In the past three years, Sandia has been implementing the sodium chemistry containment models in CONTAIN-LMR, a legacy NRC code, into MELCOR. These chemistry models include spray fire, pool fire and atmosphere chemistry models. Only the first two chemistry models have been implemented though it is intended to implement all these models into MELCOR. A new package called “NAC” has been created to manage the sodium chemistry model more efficiently. In 2017 Sandia began validating the implemented models in MELCOR by simulating available experiments. The CONTAIN-LMR sodium models include sodium atmosphere chemistry and sodium-concrete interaction models. This paper presents sodium property models, the implemented models, implementation issues, and a path towards validation against existing experimental data.

  20. Creative design-by-analysis solutions applied to high-temperature components

    International Nuclear Information System (INIS)

    Dhalla, A.K.

    1993-01-01

    Elevated temperature design has evolved over the last two decades from design-by-formula philosophy of the ASME Boiler and Pressure Vessel Code, Sections I and VIII (Division 1), to the design-by-analysis philosophy of Section III, Code Case N-47. The benefits of design-by-analysis procedures, which were developed under a US-DOE-sponsored high-temperature structural design (HTSD) program, are illustrated in the paper through five design examples taken from two U.S. liquid metal reactor (LMR) plants. Emphasis in the paper is placed upon the use of a detailed, nonlinear finite element analysis method to understand the structural response and to suggest design optimization so as to comply with Code Case N-47 criteria. A detailed analysis is cost-effective, if selectively used, to qualify an LMR component for service when long-lead-time structural forgings, procured based upon simplified preliminary analysis, do not meet the design criteria, or the operational loads are increased after the components have been fabricated. In the future, the overall costs of a detailed analysis will be reduced even further with the availability of finite element software used on workstations or PCs

  1. Peptide microarray analysis of substrate specificity of the transmembrane Ser/Thr kinase KPI-2 reveals reactivity with cystic fibrosis transmembrane conductance regulator and phosphorylase.

    Science.gov (United States)

    Wang, Hong; Brautigan, David L

    2006-11-01

    Human lemur (Lmr) kinases are predicted to be Tyr kinases based on sequences and are related to neurotrophin receptor Trk kinases. This study used homogeneous recombinant KPI-2 (Lmr2, LMTK2, Cprk, brain-enriched protein kinase) kinase domain and a library of 1,154 peptides on a microarray to analyze substrate specificity. We found that KPI-2 is strictly a Ser/Thr kinase that reacts with Ser either preceded by or followed by Pro residues but unlike other Pro-directed kinases does not strictly require an adjacent Pro residue. The most reactive peptide in the library corresponds to Ser-737 of cystic fibrosis transmembrane conductance regulator, and the recombinant R domain of cystic fibrosis transmembrane conductance regulator was a preferred substrate. Furthermore the KPI-2 kinase phosphorylated peptides corresponding to the single site in phosphorylase and purified phosphorylase b, making this only the second known phosphorylase b kinase. Phosphorylase was used as a specific substrate to show that KPI-2 is inhibited in living cells by addition of nerve growth factor or serum. The results demonstrate the utility of the peptide library to probe specificity and discover kinase substrates and offer a specific assay that reveals hormonal regulation of the activity of this unusual transmembrane kinase.

  2. Radioisotope measurement system; Sistema de medicion de radioisotopos

    Energy Technology Data Exchange (ETDEWEB)

    Villanueva Ruibal, Jose [Comision Nacional de Energia Atomica, Ezeiza (Argentina).Centro Atomico Ezeiza

    2007-07-01

    A radioisotope measurement system installed at L.M.R. (Ezeiza Atomic Center of CNEA) allows the measurement of nuclear activity from a wide range of radioisotopes. It permits to characterize a broad range of radioisotopes at several activity levels. The measurement hardware as well as the driving software have been developed and constructed at the Dept. of Instrumentation and Control. The work outlines the system's conformation and its operating concept, describes design characteristics, construction and the error treatment, comments assay results and supplies use advices. Measuring tests carried out employing different radionuclides confirmed the system performing satisfactorily and with friendly operation. (author) [Spanish] Un sistema de instrumentacion instalado en el L.M.R. (Centro Atomico Ezeiza de la CNEA) mide en amplio rango la actividad del decaimiento nuclear de radioisotopos. Permite caracterizar una amplia gama de radioistopos de variados niveles de actividad. Tanto el hardware de medicion como el software de operacion han sido desarrollados y construidos en el Dept. Instrumentacion y Control. El trabajo esboza la conformacion del sistema y su concepto de operacion, describe caracteristicas de disenio, construccion y del tratamiento del error, comenta resultados de ensayos y provee recomendaciones de uso. Pruebas de medicion realizadas empleando diversos nucleidos comprobaron que el sistema funciona en forma satisfactoria y su operacion es amigable. (autor)

  3. Operating and test experience of EBR-II

    International Nuclear Information System (INIS)

    Sackett, J.I.

    1991-01-01

    EBR-2 has operated for 27 years, the longest for any Liquid Metal Reactor (LMR) power plant. During that time, much has been learned about successful LMR operation and design. The basic lesson is that conversatism in design can pay significant dividends in operating reliability. Furthermore, such conservatism need not mean high cost. The EBR-2 system emphasizes simplicity, minimizing the number of valves in the heat transport system, for example, and simplifying the primary heat-transport-system layout. Another lesson is that emphasizing reliability of the steam generating system at the sodium-water interface (by using duplex tubes in the case of EBR-2) has been well worth the higher initial costs; no problems with leakage have been encountered in EBR-2's operating history. Locating spent fuel storage in the primary tank and providing for decay heat removal by natural connective flow have also been contributors to EBR-2's success. The ability to accommodate loss of forced cooling or loss of heat sink passively has resulted in benefits for simplification, primarily through less reliance on emergency power and in not requiring the secondary sodium or steam systems to be safety grade. Also, the ''piped-pool '' arrangement minimizes thermal stress to the primary tank and enhances natural convective flow. These benefits have been realized through a history of operation that has seen EBR-2 evolve through four major phases in its test programs, culminating in its present mission as the Integral Fast Rector (IFR) prototype. 20 refs., 8 figs., 1 tab

  4. Remote Inspection Techniques for Reactor Internals of Liquid Metal Reactor by using Ultrasonic Waveguide Sensor

    International Nuclear Information System (INIS)

    Joo, Young Sang; Kim, Seok Hun; Lee, Jae Han

    2006-02-01

    The primary components such as a reactor core, heat exchangers, pumps and internal structures of a liquid metal reactor (LMR) are submerged in hot sodium of reactor vessel. The division 3 of ASME code section XI specifies the visual inspection and continuous monitoring as major in-service inspection (ISI) methods of reactor internal structures. Reactor core and internal structures of LMR can not be visually examined due to an opaque liquid sodium. The under-sodium viewing and remote inspection techniques by using an ultrasonic wave should be applied for the in-service inspection of reactor internals. The remote inspection techniques using ultrasonic wave have been developed and applied for the visualization and ISI of reactor internals. The under sodium viewing technique has a limitation for the application of LMR due to the high temperature and irradiation environment. In this study, an ultrasonic waveguide sensor with a strip plate has been developed for an application to the under-sodium viewing and remote inspection. The Lamb wave propagation of a waveguide sensor has been analyzed and the zero-order antisymmetric A 0 plate wave was selected as the application mode of the sensor. The A 0 plate wave can be propagated in the dispersive low frequency range by using a liquid wedge clamped to the waveguide. A new technique is presented which is capable of steering the radiation beam angle of a waveguide sensor without a mechanical movement of the sensor assembly. The steering function of the ultrasonic radiation beam can be achieved by a frequency tuning method of the excitation pulse in the dispersive range of the A 0 mode. The technique provides an opportunity to overcome the scanning limitation of a waveguide sensor. The beam steering function has been evaluated by an experimental verification. The ultrasonic C-scanning experiments are performed in water and the feasibility of the ultrasonic waveguide sensor has been verified. The various remote inspection

  5. The Last Millennium Reanalysis: Improvements to proxies and proxy modeling

    Science.gov (United States)

    Tardif, R.; Hakim, G. J.; Emile-Geay, J.; Noone, D.; Anderson, D. M.

    2017-12-01

    The Last Millennium Reanalysis (LMR) employs a paleoclimate data assimilation (PDA) approach to produce climate field reconstructions (CFRs). Here, we focus on two key factors in PDA generated CFRs: the set of assimilated proxy records and forward models (FMs) used to estimate proxies from climate model output. In the initial configuration of the LMR [Hakim et al., 2016], the proxy dataset of [PAGES2k Consortium, 2013] was used, along with univariate linear FMs calibrated against annually-averaged 20th century temperature datasets. In an updated configuration, proxy records from the recent dataset [PAGES2k Consortium, 2017] are used, while a hierarchy of statistical FMs are tested: (1) univariate calibrated on annual temperature as in the initial configuration, (2) univariate against temperature as in (1) but calibration performed using expert-derived seasonality for individual proxy records, (3) as in (2) but expert proxy seasonality replaced by seasonal averaging determined objectively as part of the calibration process, (4) linear objective seasonal FMs as in (3) but objectively selecting relationships calibrated either on temperature or precipitation, and (5) bivariate linear models calibrated on temperature and precipitation with objectively-derived seasonality. (4) and (5) specifically aim at better representing the physical drivers of tree ring width proxies. Reconstructions generated using the CCSM4 Last Millennium simulation as an uninformed prior are evaluated against various 20th century data products. Results show the benefits of using the new proxy collection, particularly on the detrended global mean temperature and spatial patterns. The positive impact of using proper seasonality and temperature/moisture sensitivities for tree ring width records is also notable. This updated configuration will be used for the first generation of LMR-generated CFRs to be publicly released. These also provide a benchmark for future efforts aimed at evaluating the

  6. Is Recent Warming Unprecedented in the Common Era? Insights from PAGES2k data and the Last Millennium Reanalysis

    Science.gov (United States)

    Erb, M. P.; Emile-Geay, J.; McKay, N.; Hakim, G. J.; Steig, E. J.; Anchukaitis, K. J.

    2017-12-01

    Paleoclimate observations provide a critical context for 20th century warming by putting recent climate change into a longer-term perspective. Previous work (e.g. IPCC AR3-5) has claimed that recent decades are exceptional in the context of past centuries, though these statements are usually accompanied by large uncertainties and little spatial detail. Here we leverage a recent multiproxy compilation (PAGES2k Consortium, 2017) to revisit this long-standing question. We do so via two complementary approaches. The first approach compares multi-decadal averages and trends in PAGES2k proxy records, which include trees, corals, ice cores, and more. Numerous proxy records reveal that late 20th century values are extreme compared to the remainder of the recorded period, although considerable variability exists in the signals preserved in individual records. The second approach uses the same PAGES2k data blended with climate model output to produce an optimal analysis: the Last Millennium Reanalysis (LMR; Hakim et al., 2016). Unlike proxy data, LMR is spatially-complete and explicitly models uncertainty in proxy records, resulting in objective error estimates. The LMR results show that for nearly every region of the world, late 20th century temperatures exceed temperatures in previous multi-decadal periods during the Common Era, and 20th century warming rates exceed rates in previous centuries. An uncertainty with the present analyses concerns the interpretation of proxy records. PAGES2k included only records that are primarily sensitive to temperature, but many proxies may be influenced by secondary non-temperature effects. Additionally, the issue of seasonality is important as, for example, many temperature-sensitive tree ring chronologies in the Northern Hemisphere respond to summer or growing season temperature rather than annual-means. These uncertainties will be further explored. References Hakim, G. J., et al., 2016: The last millennium climate reanalysis project

  7. A comparative neutronic analysis of 150MWe TRU burner according to the coolant alteration

    International Nuclear Information System (INIS)

    Yoo, J. W.; Kim, S. J.; Kim, Y. I.

    2000-01-01

    A comparative neutronic analysis has been conducted for the small TRU burner according to their coolant material. The use of Pb-Bi coolant gave a low burnup reactivity swing and negative or less positive coolant void coefficient with harder neutron spectrum. By a lower burnup reactivity swing and higher conversion ratio of Pb-Bi cooled core, the total amount of TRU consumption was found to be small compared with Na cooled core despite of the higher MA consumption ratio of Pb-Bi cooled core. However, Pb-Bi cooled reactor have a lager margin in the coolant void coefficient, so that a variable MA composition can be loaded in the core. Accordingly, even though the Pb-Bi cooled TRU burner has not effectiveness on TRU burning in the same geometry and material condition, a flexible MA loading is envisaged to result in 10 times larger MA burning amount, still preserving a low coolant void worth

  8. Model tests in RAMONA and NEPTUN

    International Nuclear Information System (INIS)

    Hoffmann, H.; Ehrhard, P.; Weinberg, D.; Carteciano, L.; Dres, K.; Frey, H.H.; Hayafune, H.; Hoelle, C.; Marten, K.; Rust, K.; Thomauske, K.

    1995-01-01

    In order to demonstrate passive decay heat removal (DHR) in an LMR such as the European Fast Reactor, the RAMONA and NEPTUN facilities, with water as a coolant medium, were used to measure transient flow data corresponding to a transition from forced convection (under normal operation) to natural convection under DHR conditions. The facilities were 1:20 and 1:5 models, respectively, of a pool-type reactor including the IHXs, pumps, and immersed coolers. Important results: The decay heat can be removed from all parts of the primary system by natural convection, even if the primary fluid circulation through the IHX is interrupted. This result could be transferred to liquid metal cooling by experiments in models with thermohydraulic similarity. (orig.)

  9. Model tests in RAMONA and NEPTUN; Modellversuche in RAMONA und NEPTUN

    Energy Technology Data Exchange (ETDEWEB)

    Hoffmann, H.; Ehrhard, P.; Weinberg, D.; Carteciano, L.; Dres, K.; Frey, H.H.; Hayafune, H.; Hoelle, C.; Marten, K.; Rust, K.; Thomauske, K.

    1995-08-01

    In order to demonstrate passive decay heat removal (DHR) in an LMR such as the European Fast Reactor, the RAMONA and NEPTUN facilities, with water as a coolant medium, were used to measure transient flow data corresponding to a transition from forced convection (under normal operation) to natural convection under DHR conditions. The facilities were 1:20 and 1:5 models, respectively, of a pool-type reactor including the IHXs, pumps, and immersed coolers. Important results: The decay heat can be removed from all parts of the primary system by natural convection, even if the primary fluid circulation through the IHX is interrupted. This result could be transferred to liquid metal cooling by experiments in models with thermohydraulic similarity. (orig.)

  10. Eddy Current Flow Measurements in the FFTF

    Energy Technology Data Exchange (ETDEWEB)

    Nielsen, Deborah L. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Polzin, David L. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Omberg, Ronald P. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Makenas, Bruce J. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States)

    2017-02-02

    The Fast Flux Test Facility (FFTF) is the most recent liquid metal reactor (LMR) to be designed, constructed, and operated by the U.S. Department of Energy (DOE). The 400-MWt sodium-cooled, fast-neutron flux reactor plant was designed for irradiation testing of nuclear reactor fuels and materials for liquid metal fast breeder reactors. Following shut down of the Clinch River Breeder Reactor Plant (CRBRP) project in 1983, FFTF continued to play a key role in providing a test bed for demonstrating performance of advanced fuel designs and demonstrating operation, maintenance, and safety of advanced liquid metal reactors. The FFTF Program provides valuable information for potential follow-on reactor projects in the areas of plant system and component design, component fabrication, fuel design and performance, prototype testing, site construction, and reactor control and operations. This report provides HEDL-TC-1344, “ECFM Flow Measurements in the FFTF Using Phase-Sensitive Detectors”, March 1979.

  11. Concept for a small, colocated fuel cycle facility for oxide breeder fuels

    International Nuclear Information System (INIS)

    Burch, W.D.; Stradley, J.G.; Lerch, R.E.

    1987-01-01

    As part of a United States Department of Energy (USDOE) program to examine innovative liquid-metal reactor (LMR) system designs over the past three years, the Oak Ridge National Laboratory (ORNL) and the Westinghouse Hanford Company (WHC) collaborated on studies of mixed oxide fuel cycle options. A principal effort was an advanced concept for a small integrated fuel cycle colocated with a 1300-MW(e) reactor station. The study provided a scoping design and a basis on which to proceed with implementation of such a facility if future plans so dictate. The facility integrated reprocessing, waste management, and refabrication functions in a single facility of nominal 35-t/year capacity utilizing the latest technology developed in fabrication programs at WHC and in reprocessing at ORNL. The concept was based on many years of work at both sites and extensive design studies of prior years

  12. Improvement of group collapsing in TRANSX code

    International Nuclear Information System (INIS)

    Jeong, Hyun Tae; Kim, Young Cheol; Kim, Young In; Kim, Young Kyun

    1996-07-01

    A cross section generating and processing computer code TRANSX version 2.15 in the K-CORE system, being developed by the KAERI LMR core design technology development team produces various cross section input files appropriated for flux calculation options from the cross section library MATXS. In this report, a group collapsing function of TRANSX has been improved to utilize the zone averaged flux file RZFLUX written in double precision as flux weighting functions. As a result, an iterative calculation system using double precision RZFLUX consisting of the cross section data library file MATXS, the effective cross section producing and processing code TRANSX, and the transport theory calculation code TWODANT has been set up and verified through a sample model calculation. 4 refs. (Author)

  13. Comparison study of inelastic analysis codes for high temperature structure

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Jong Bum; Lee, H. Y.; Park, C. K.; Geon, G. P.; Lee, J. H

    2004-02-01

    LMR high temperature structures subjected to operating and transient loadings may exhibit very complex deformation behaviors due to the use of ductile material such as 316SS and the systematic analysis technology of high temperature structure for reliable safety assessment is essential. In this project, comparative study with developed inelastic analysis program NONSTA and the existing analysis codes was performed applying various types of loading including non-proportional loading. The performance of NONSTA was confirmed and the effect of inelastic constants on the analysis result was analyzed. Also, the applicability of the inelastic analysis was enlarged as a result of applying both the developed program and the existing codes to the analyses of the enhanced creep behavior and the elastic follow-up behavior of high temperature structures and the necessary items for improvements were deduced. Further studies on the improvement of NONSTA program and the decision of the proper values of inelastic constants are necessary.

  14. Estudo radiográfico do índice acromial e sua relação com as lesões do manguito rotador Radiographic analysis of the acromion index and its association with rotator cuff tears

    Directory of Open Access Journals (Sweden)

    Alberto Naoki Miyazaki

    2010-01-01

    Full Text Available OBJETIVO: O objetivo deste estudo é avaliar a relação da projeção lateral do acrômio com as lesões do manguito rotador (LMR na população brasileira. MÉTODOS: A projeção lateral do acrômio foi mensurada por meio de radiografias de ombros em sua incidência anteroposterior realizadas com a cavidade glenoidal em seu perfil absoluto e a cabeça do úmero em rotação neutra ou medial. Foi aferido o índice acromial (IA pela razão entre a distância do plano da cavidade glenoidal ao extremo lateral do acrômio e a distância do plano da cavidade glenoidal ao extremo lateral da cabeça do úmero. Este índice foi mensurado em 83 indivíduos (idade média de 54 anos com LMR e comparados com um grupo de 28 indivíduos (idade média de 48 anos que não as apresentavam. A presença ou ausência de LMR foi evidenciada por meio de ressonância magnética. RESULTADOS: O IA médio foi de 0,7194 nos pacientes com LMR e de 0,6677 nos indivíduos que não a apresentavam na população brasileira. Essa diferença foi estatisticamente significativa com um p = 0,001. CONCLUSÃO: Pode-se estabelecer relação do IA e lesão do manguito rotador na população brasileira.OBJECTIVE: The purpose of this study is to evaluate the association between lateral extension of the acromion and rotator cuff tears (RCT in the Brazilian population. METHODS: Lateral extension of the acromion was measured using anteroposterior radiographs of the shoulders, carried out with glenoid cavity in the absolute profile and the humeral head in neutral or internal rotation. The acromion index (AI was defined by the ratio of the distance from the glenoid cavity to the lateral border of the acromion, and the distance from the glenoid cavity to the lateral border of the humeral head. This index was measured in 83 patients with (average age 54 years with RCT and compared with a group with 28 patients (average age 48 years without RCT. The presence or absence of RCT was defined by

  15. Application of consistent fluid added mass matrix to core seismic

    International Nuclear Information System (INIS)

    Koo, K. H.; Lee, J. H.

    2003-01-01

    In this paper, the application algorithm of a consistent fluid added mass matrix including the coupling terms to the core seismic analysis is developed and installed at SAC-CORE3.0 code. As an example, we assumed the 7-hexagon system of the LMR core and carried out the vibration modal analysis and the nonlinear time history seismic response analysis using SAC-CORE3.0. Used consistent fluid added mass matrix is obtained by using the finite element program of the FAMD(Fluid Added Mass and Damping) code. From the results of the vibration modal analysis, the core duct assemblies reveal strongly coupled vibration modes, which are so different from the case of in-air condition. From the results of the time history seismic analysis, it was verified that the effects of the coupled terms of the consistent fluid added mass matrix are significant in impact responses and the dynamic responses

  16. Status of Fast Reactor Technology Development in Korea

    International Nuclear Information System (INIS)

    Chang, Jinwook

    2012-01-01

    Summary: • Long-term Advanced SFR Development Plan was revised by KAEC in November 2011: – Specific design by 2017; – Specific design approval by 2020; – Construction of a prototype SFR by 2028. • Activities for development of an Advanced SFR include: – Conceptual core design from U core to MTRU core; – Conceptual design of fluid system & mechanical structure; – Development of metal fuel; – S-CO 2 Brayton cycle as an alternative option; – Under sodium viewing for in-service inspection; – STELLA for major components test and integral effect test including decay heat removal system; – Reactor physics experiment for TRU burner; – Evaluation of MARS-LMR code capability

  17. Comparison of effect of insulating blockages on metal and oxide fuel elements

    International Nuclear Information System (INIS)

    Tilbrook, R.W.; Dever, D.J.

    1988-01-01

    The safety philosophy of the new liquid metal reactor (LMR) plant designs is oriented towards inherent protection against loss of coolable geometry and other entries to core disruption. On potential entry is via propagation of local faults. Within this category is a wide range of initiators which each require assessment of their probability and consequences in order to determine their contribution to plant risk. Local faults include those initiators which cause local power/flow disturbances restricted either to a single subassembly or to a local region of the bundle. The concern is that these localized initiators may start a sequence of events in which fuel failure may propagate first within a subassembly envelope and finally cause loss of coolable geometry in adjacent. This document discusses these scenarios. 3 refs., 1 fig

  18. Failed fuel monitoring and surveillance techniques for liquid metal cooled fast reactors

    International Nuclear Information System (INIS)

    Lambert, J.D.B.; Mikaili, R.; Gross, K.C.; Strain, R.V.; Aoyama, T.; Ukai, S.; Nomura, S.; Nakae, N.

    1995-01-01

    The Experimental Breeder Reactor II (EBR-II) has been used as a facility for irradiation of LMR fuels and components for thirty years. During this time many tests of experimental fuel were continued to cladding breach in order to study modes of element failure; the methods used to identify such failures are described in a parallel paper. This paper summarizes experience of monitoring the delayed-neutron (DN) and fission-gas (FG) release behavior of a smaller number of elements that continued operation in the run-beyond-cladding-breach (RBCB) mode. The scope of RBCB testing, the methods developed to characterize failures on-line, and examples of DN/FG behavior are described

  19. Fuel-sodium reaction product formation in breached mixed-oxide fuel

    International Nuclear Information System (INIS)

    Bottcher, J.H.; Lambert, J.D.B.; Strain, R.V.; Ukai, S.; Shibahara, S.

    1988-01-01

    The run-beyond-cladding-breach (RBCB) operation of mixed-oxide LMR fuel pins has been studied for six years in the Experimental Breeder Reactor-II (EBR-II) as part of a joint program between the US Department of Energy and the Power Reactor and Nuclear Fuel Development Corporation of Japan. The formation of fuel-sodium reaction product (FSRP), Na 3 MO 4 , where M = U/sub 1-y/Pu/sub y/, in the outer fuel regions is the major phenomenon governing RBCB behavior. It increases fuel volume, decreases fuel stoichiometry, modifies fission-product distributions, and alters thermal performance of a pin. This paper describes the morphology of Na 3 MO 4 observed in 5.84-mm diameter pins covering a variety of conditions and RBCB times up to 150 EFPD's. 8 refs., 1 fig

  20. Performance of metal and oxide fuels during accidents in a large liquid metal cooled reactor

    International Nuclear Information System (INIS)

    Cahalan, J.; Wigeland, R.; Friedel, G.; Kussmaul, G.; Royl, P.; Moreau, J.; Perks, M.

    1990-01-01

    In a cooperative effort among European and US analysts, an assessment of the comparative safety performance of metal and oxide fuels during accidents in a large (3500 MWt), pool-type, liquid-metal-cooled reactor (LMR) was performed. The study focused on three accident initiators with failure to scram: the unprotected loss-of-flow (ULOF), the unprotected transient overpower (UTOP), and the unprotected loss-of-heat-sink (ULOHS). Emphasis was placed on identification of design features that provide passive, self-limiting responses to upset conditions, and quantification of relative safety margins. The analyses show that in ULOF and ULOHS sequences, metal-fueled LMRs with pool-type primary systems provide larger temperature margins to coolant boiling than oxide-fueled reactors of the same design. 3 refs., 4 figs

  1. Control Rod Withdrawal Events Analyses for the Prototype Gen-IV SFR

    Energy Technology Data Exchange (ETDEWEB)

    Choi, Chiwoong; Ha, Kwiseo; Jeong, Taekyeong; Jeong, Jaeho; Chang, Wonpyo; Lee, Seungwon; An, Sangjun; Lee, Kwilim [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2016-10-15

    To confirm the limiting condition, based on the maximum allowable reactivity insertion of 0.3 $, three cases from the end of cycle (EOC) are selected. In addition, assuming the failure of CRSS by earthquake, additional cases is defined at beginning of cycle (BOC). When the CRW occurs, the reactor can be protected by plant protection system (PPS). In this study, PPS mechanism is sequentially studied for all initiating events. For design basis accidents (DBA), the reactor can be scrammed by reactor protection system (RPS). The first and seconds RPS signals are checked during transients. When RPS is failed, so called as anticipated transient without scram (ATWS), the reactor will be protected by diverse protection system (DPS). In this study, in order to analyze various initiating events related control rod withdrawal, four kinds of operating condition is defined. TOP events are analyzed using MARS-LMR. The influence of various plant protection system such as RPS and DPS are investigated.

  2. The present status of nuclear power and prospects for fast reactors - the IAEA outlook

    International Nuclear Information System (INIS)

    Dastidar, P.; Kupitz, J.; Arkhipov, V.

    1991-01-01

    Nuclear power continues to provide a significant amount of the world's electricity supply. Based on the experience gained from about 6000 reactor years of operation, improvements are continuing to be made in the design of nuclear power plants of all types including liquid metal cooled fast reactors. Five demonstration, prototypical or semi-commercial nuclear plants with liquid metal-cooled reactors (LMR) are in operation in the world. Although the commercial deployment of fast reactors has not been seen as urgent due to the availability of adequate low-cost uranium resources there is an awareness in many countries that breeder reactors will be needed in the early decades of the next century. Adequate energy supply for all countries of the world is vital. The exploitation of all non-polluting forms of energy, of which nuclear energy is the most abundant, must be planned now to meet the growing worldwide energy demand. (author)

  3. Detection of the Mr 110,000 lung resistance-related protein LRP/MVP with monoclonal antibodies.

    Science.gov (United States)

    Schroeijers, A B; Scheffer, G L; Reurs, A W; Pijnenborg, A C; Abbondanza, C; Wiemer, E A; Scheper, R J

    2001-11-01

    The Mr 110,000 lung resistance-related protein (LRP), also termed the major vault protein (MVP), constitutes >70% of subcellular ribonucleoprotein particles called vaults. Overexpression of LRP/MVP and vaults has been linked directly to MDR in cancer cells. Clinically, LRP/MVP expression can be of value to predict response to chemotherapy and prognosis. Monoclonal antibodies (MAbs) against LRP/MVP have played a critical role in determining the relevance of this protein in clinical drug resistance. We compared the applicability of the previously described MAbs LRP-56, LMR-5, LRP, 1027, 1032, and newly isolated MAbs MVP-9, MVP-16, MVP-18, and MVP-37 for the immunodetection of LRP/MVP by immunoblotting analysis and by immunocyto- and histochemistry. The availability of a broader panel of reagents for the specific and sensitive immunodetection of LRP/MVP should greatly facilitate biological and clinical studies of vault-related MDR.

  4. Controlling Beryllium Contaminated Material And Equipment For The Building 9201-5 Legacy Material Disposition Project

    International Nuclear Information System (INIS)

    Reynolds, T.D.; Easterling, S.D.

    2010-01-01

    This position paper addresses the management of beryllium contamination on legacy waste. The goal of the beryllium management program is to protect human health and the environment by preventing the release of beryllium through controlling surface contamination. Studies have shown by controlling beryllium surface contamination, potential airborne contamination is reduced or eliminated. Although there are areas in Building 9201-5 that are contaminated with radioactive materials and mercury, only beryllium contamination is addressed in this management plan. The overall goal of this initiative is the compliant packaging and disposal of beryllium waste from the 9201-5 Legacy Material Removal (LMR) Project to ensure that beryllium surface contamination and any potential airborne release of beryllium is controlled to levels as low as practicable in accordance with 10 CFR 850.25.

  5. Analysis of the Nonlinear Density Wave Two-Phase Instability in a Steam Generator of 600MWe Liquid Metal Reactor

    International Nuclear Information System (INIS)

    Choi, Seok Ki; Kim, Seong O

    2011-01-01

    A 600 MWe demonstration reactor being developed at KAERI employs a once-through helically coiled steam generator. The helically coiled steam generator is compact and is efficient for heat transfer, however, it may suffer from the two-phase instability. It is well known that the density wave instability is the main source of instability among various types of instabilities in a helically coiled S/G in a LMR. In the present study a simple method for analysis of the density wave two phase instability in a liquid metal reactor S/G is proposed and the method is applied to the analysis of density wave instability in a S/G of 600MWe liquid metal reactor

  6. A fast reactor transient analysis methodology for PCs: Volume 3, LTC program manual of the QuickBASIC code

    International Nuclear Information System (INIS)

    Ott, K.O.; Chung, L.

    1992-06-01

    This manual augments the detailed manual of the GW-BASIC version of the LTC code for an application in QuickBASIC. As most of the GW-BASIC coding of this program for ''LMR Transient Calculations'' is compatible with QuickBASIC, this manual pertains primarily to the required changes, such as the handling of input and output. The considerable reduction in computation time achieved by this conversion is demonstrated for two sample problems, using a variety of hardware and execution options. The revised code is listed. Although the severe storage limitations of GW-BASIC no longer apply, the LOF transient path has not been completed in this QuickBASIC code. Its advantages are thus primarily in the much faster running time for TOP and LOHS transients. For the fastest PC hardware (486) and execution option the computation time is reduced by a factor of 124 compared to GW-BASIC on a 386/20

  7. Design and experimental characterization of an EM pump

    International Nuclear Information System (INIS)

    Kim, Hee Reyoung; Hong, Sang Hee

    1999-01-01

    Generally, an EM (electromagnetic) pump is been employed to circulate electrically conducting liquids by using the Lorentz force. Especially, at the liquid metal reactor (LMR), which uses liquid sodium with high electrical conductivity as a coolant, an EM pump is needed due to its advantages over a mechanical pump, such as no rotating parts, no noise, and simplicity. In this research, an EM pump of a pilot annular linear induction type with a flow rate of 200 l/min was designed by using the electrical equivalent-circuit method. The pump was designed and manufactured by considering material and environmental (high temperature and liquid sodium) requirements. The pump performance was experimentally characterized based on input currents, voltage, power, and frequency. Also, the theoretical prediction was compared with the experimental result

  8. P-Q characteristic of the electromagnetic pump with the flow rate of 60 l/min

    International Nuclear Information System (INIS)

    Kim, Hee Reyoun; KIm, Jong Man; Cha, Jae Eun; Choi, Jong Hyun; Nam, Ho Yoon

    2005-01-01

    In general, an EM pump has been employed to circulate electrically conductive liquids like molten metals by Lorentz force generated from the magnetic field and its perpendicular current. Especially, at the Liquid Metal Reactor (LMR) which uses liquid sodium with high electrical conductivity as a coolant, an EM pump is noticed due to advantages over mechanical pump such as no rotating part, no noise and simplicity. In the present study, the EM pump of a pilot annular linear induction type with the flowrate of 60 l/min is designed by using electrical equivalent circuit method that is applied to linear induction machines. The designed pump is manufactured by consideration of the requirements of material and function in high temperature and sodium environments. Experimental characterization is carried out according to input currents and frequency. And compared analyses between theoretical prediction and experimental results are performed

  9. State-of-the-art report on the development of liquid metal reactor fuel cladding materials in Japan

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Sung Ho; Kuk, Il Hiun; Ryu, Woo Seog; Jang, Jin Sung; Rhee, Chang Kyu; Kim, Dae Whan; Park, Soon Dong; Kim, Woo Gon; Chung, Man Kyo; Han, Chang Hee

    1998-01-01

    PNC 1520 and PNC-FM5 have been developed as a cladding materials for LMR in Japan. PNC 1520 has superior swelling resistance and high temperature properties to PNC 31.6. And PNC-FMS steel has shown a high rupture stress as well as good neutron irradiation performance. In addition oxide dispersed ferritic steel (PNC-ODS) and 12Cr-8Mo steel have been developed. This report will give an insight for choosing and developing the materials to be applied to the KAERI prototype liquid metal reactor which is going to be operable in 2010 by analysis of the characteristics of cladding materials developed in Japan. (author). 39 refs., 2 tabs., 23 figs

  10. Consequences of pipe ruptures in metal fueled, liquid metal cooled reactors

    International Nuclear Information System (INIS)

    Dunn, F.E.

    1990-01-01

    The capability to simulate pipe ruptures has recently been added to the SASSYS-1 LMR systems analysis code. Using this capability, the consequences of severe pipe ruptures in both loop-type and pool-type reactors using metal fuel were investigated. With metal fuel, if the control rods scram then either type of reactor can easily survive a complete double-ended break of a single pipe; although, as might be expected, the consequences are less severe for a pool-type reactor. A pool-type reactor can even survive a protected simultaneous breaking of all of its inlet pipes without boiling of the coolant or melting of the fuel or cladding. 2 refs., 16 figs., 1 tab

  11. Evaluation of buckling characteristics with respect to slenderness ratio for thin cylinderical structures

    International Nuclear Information System (INIS)

    Kim, D. H.; Ko, K. H.; Lee, J. H.

    2002-01-01

    This work was done as one of the pre-research of buckling behavior for LMR reactor vessel. For the reduced scale buckling test, the three types of test specimen(slenderness ratio 1.0, 2.0, 4.8) was selected. Using the buckling formulae by Okada and the elastic-plastic finite element method, the buckling characteristics are investigated. From the results of buckling load evaluations, as the slenderness ratio decreases, the buckling load increases and a deflection shape approaches shear buckling mode. As the slenderness increases, the deflection approaches bending buckling mode. In comparison of buckling loads, the calculated buckling loads by the elastic-plastic finite element method are in good agreement with those of the evaluation formulae considering with plastic effect

  12. A decade of advances in metallic fuel

    International Nuclear Information System (INIS)

    Seidel, B.R.; Batte, G.L.; Dodds, N.E.; Hofman, G.L.; Lahm, C.E.; Pahl, R.G.; Porter, D.L.; Tsai, H.; Walters, L.C.

    1990-01-01

    Significant advances in the understanding of behavior and performance of metallic fuels to high burnup have been achieved over the past four decades. Metallic fuels were the first fuels for liquid-metal-cooled fast reactors (LMR) but in the late 1960s worldwide interest turned toward ceramic fuels before the full potential of metallic fuel could be achieved. Now metallic fuels are recognized as a preferred viable option with regard to safety, integral fuel cycle, waste minimization and deployment economics. This paper reviews the key advances in the last decade and highlights the behavior and performance features which have demonstrated a much greater potential than previously expected. 28 refs., 2 figs., 1 tab

  13. Comparison of the SASSYS/SAS4A radial core expansion reactivity feedback model and the empirical correlation for FFTF

    International Nuclear Information System (INIS)

    Wigeland, R.A.

    1987-01-01

    The present emphasis on inherent safety for LMR designs has resulted in a need to represent the various reactivity feedback mechanisms as accurately as possible. The dominant negative reactivity feedback has been found to result from radial expansion of the core for most postulated ATWS events. For this reason, a more detailed model for calculating the reactivity feedback from radial core expansion has been recently developed for use with the SASSYS/SAS4A Code System. The purpose of this summary is to present an extension to the model so that it is more suitable for handling a core restraint design as used in FFTF, and to compare the SASSYS/SAS4A results using this model to the empirical correlation presently being used to account for radial core expansion reactivity feedback to FFTF

  14. Demonstration of passive safety features in EBR-II

    International Nuclear Information System (INIS)

    Planchon, H.P. Jr.; Golden, G.H.; Sackett, J.I.

    1987-01-01

    Two tests of great importance to the design of future commercial nuclear power plants were carried out in the Experimental Breeder Reactor-II on April 3, 1986. These tests, (viewed by about 60 visitors, including 13 foreign LMR specialists) were a loss of flow without scram and a loss of heat sink without scram, both from 100% initial power. In these tests, inherent feedback shut the reactor down without damage to the fuel or other reactor components. This resulted primarily from advantageous characteristics of the metal driver fuel used in EBR-II. Work is currently underway at EBR-II to develop a control strategy that promotes inherent safety characteristics, including survivability of transient overpower accidents. In parallel, work is underway at EBR-II on the development of state-of-the-art plant diagnostic techniques

  15. Level II Probabilistic Safety Analysis Methodology for the Application to GEN-IV Sodium-cooled Fast Reactor

    International Nuclear Information System (INIS)

    Park, S. Y.; Kim, T. W.; Han, S. H.; Jeong, H. Y.

    2010-03-01

    The Korea Atomic Energy Research Institute (KAERI) has been developing liquid metal reactor (LMR) design technologies under a National Nuclear R and D Program. Nevertheless, there is no experience of the probabilistic safety assessment (PSA) domestically for a fast reactor with the metal fuel. Therefore, the objective of this study is to establish the methodologies of risk assessment for the reference design of GEN-IV sodium fast reactor (SFR). An applicability of the PSA methodology of U. S. NRC and PRISM plant to the domestic GEN-IV SFR has been studied. The study contains a plant damage state analysis, a containment event tree analysis, and a source-term release category binning process

  16. Overview of fast reactor safety research and development in the USA

    International Nuclear Information System (INIS)

    Neuhold, R.J.; Avery, R.; Marchaterre, J.F.

    1986-01-01

    The liquid metal reactor (LMR) safety R and D program in the U.S. is presently focused on support of two modular innovative reactor concepts: PRISM - the General Electric Power Reactor Inherently Safe Module and SAFR - the Rockwell International Sodium Advanced Fast Reactor. These reactor plant concepts accommodate the use of either oxide fuel or the metal fuel which is under development in the Argonne National Laboratory (ANL) Integral Fast Reactor (IFR) program. Both concepts emphasize prevention of accidents through enhancement of inherent and passive safety characteristics. Enhancement of these characteristics is expected to be a major factor in establishing new and improved safety criteria and licensing arrangements with regulatory authorities for advanced reactors. Limited work is also continuing on the Large Scale Prototype Breeder (LSPB), a large pool plant design. Major elements of the current and restructured safety program are discussed. (author)

  17. Concept for a small, colocated fuel cycle facility for oxide breeder fuels

    International Nuclear Information System (INIS)

    Burch, W.D.; Lerch, R.E.; Stradley, J.G.

    1987-01-01

    As part of a United States Department of Energy (USDOE) program to examine innovative liquid-metal reactor (LMR) system designs over the past three years, the Oak Ridge National Laboratory (ORNL) and the Westinghouse Hanford Company (WHC) collaborated on studies of mixed oxide fuel cycle options. A principal effort was an advanced concept for a small integrated fuel cycle colocated with a 1300-MW(e) reactor station. The study provided a scoping design, capital and operating cost estimates, and a basis on which to proceed with implementation of such a facility if future plans so dictate. The facility integrated reprocessing, waste management, and refabrication functions in a single facility of nominal 35-t/year capacity utilizing the latest technology developed in fabrication programs at WHC and in reprocessing at ORNL. The concept was based on many years of work at both sites and extensive design studies of prior years

  18. Influence of Temperature and Mechanical Scratch on the Recorded Magnetization Stability of Longitudinal and Perpendicular Recording Media

    International Nuclear Information System (INIS)

    Nagano, Katsumasa; Tobari, Kousuke; Futamoto, Masaaki

    2011-01-01

    Stability of recorded magnetization of hard disk drive (HDD) is influenced by external environments, such as temperature and magnetic field. Small scratches are frequently formed on HDD medium surface upon contacts with the magnetic head. The influences of temperature and mechanical scratch on the magnetization structure stability are investigated for longitudinal and perpendicular recording media by using a magnetic force microscope. PMR media remained almost unchanged up to about 300 deg. C for the area with no scratches, whereas the areas near and under mechanical scratches started to change around 250 deg. C. The magnetization structure of LMR media started to change at about 100 degrees lower temperature under mechanical scratches when compared with no scratch areas. A quantitative analysis of magnetization structure variation is carried out by measuring the recorded magnetization strength difference estimated from the MFM images observed for a same sample area before and after exposing the sample to different temperatures.

  19. Secure Retrieval of FFTF Testing, Design, and Operating Information

    International Nuclear Information System (INIS)

    Butner, R. Scott; Wootan, David W.; Omberg, Ronald P.; Makenas, Bruce J.; Nielsen, Deborah

    2009-01-01

    One of the goals of the Advanced Fuel Cycle Initiative (AFCI) is to preserve the knowledge that has been gained in the United States on Liquid Metal Reactors (LMR). In addition, preserving LMR information and knowledge is part of a larger international collaborative activity conducted under the auspices of the International Atomic Energy Agency (IAEA). A similar program is being conducted for EBR-II at the Idaho Nuclear Laboratory (INL) and international programs are also in progress. Knowledge preservation at the FFTF is focused on the areas of design, construction, startup, and operation of the reactor. As the primary function of the FFTF was testing, the focus is also on preserving information obtained from irradiation testing of fuels and materials. This information will be invaluable when, at a later date, international decisions are made to pursue new LMRs. In the interim, this information may be of potential use for international exchanges with other LMR programs around the world. At least as important in the United States, which is emphasizing large-scale computer simulation and modeling, this information provides the basis for creating benchmarks for validating and testing these large scale computer programs. Although the preservation activity with respect to FFTF information as discussed below is still underway, the team of authors above is currently retrieving and providing experimental and design information to the LMR modeling and simulation efforts for use in validating their computer models. On the Hanford Site, the FFTF reactor plant is one of the facilities intended for decontamination and decommissioning consistent with the cleanup mission on this site. The reactor facility has been deactivated and is being maintained in a cold and dark minimal surveillance and maintenance mode until final decommissioning is pursued. In order to ensure protection of information at risk, the program to date has focused on sequestering and secure retrieval

  20. Clinical introduction of simultaneous radiohyperthermotherapy

    International Nuclear Information System (INIS)

    Kuroda, Masahiro; Asaumi, Junichi; Hiraki, Yoshio; Inamura, Keiji; Tahara, Seiji; Mimura, Seiichi; Mikami, Yasutaka; Kawasaki, Shoji.

    1992-01-01

    Simultaneous radiohyperthermotherapy (SRH) is a combined hyperthermia-radiation therapy in which radiation is given during heating. Mutual interference between the high energy radiotherapy system (Toshiba LMR-15A) and the 13.56 MHz capacitive heating system (Omron HEH-500C) was examined using phantoms prior to clinical trials. Phantoms were irradiated and heated simultaneously at right angles. The energy and flatness of irradiation were measured using films and were not affected by the heating system within the range of clinical use. The temperature increase was measured with a thermocouple thermometer, and the temperature distribution was determined by liquid crystal thermometer. The high energy radiotherapy system did not affect the heating device set power, the temperature increase and distribution during simultaneous treatment. This study clarified that these apparatuses work simultaneously without clinically significant mutual interference. SRH using these apparatuses can be safely applied to clinical study. (author)

  1. Analysis and evaluation of ZPPR critical experiments for a 100 kilowatt-electric space reactor

    International Nuclear Information System (INIS)

    McFarlane, H.F.; Collins, P.J.; Carpenter, S.G.; Olsen, D.N.; Smith, D.M.; Schaefer, R.W.; Doncals, R.A.; Andre, S.V.; Porter, C.A.; Cowan, C.L.; Stewart, S.L.; Protsik, R.

    1990-01-01

    ZPPR critical experiments were used for physics testing the reactor design of the SP-100, a 100-kW thermoelectric LMR that is being developed to provide electrical power for space applications. These tests validated all key physics characteristics of the design, including the ultimate safety in the event of a launch or re-entry accident. Both the experiments and the analysis required the use of techniques not previously needed for fast reactor designs. A few significant discrepancies between the experimental and calculated results leave opportunities for further reductions in the mass of the SP-100. An initial investigation has been made into application of the ZPPR-20 results, along with those of other relevant integral data, to the SP-100 design

  2. Reliability and extended-life potential of EBR-II

    International Nuclear Information System (INIS)

    King, R.W.

    1985-01-01

    Although the longlife potential of liquid-metal-cooled reactors (LMRs) has been only partially demonstrated, many factors point to the potential for exceptionally long life. EBR-II has the opportunity to become the first LMR to achieve an operational lifetime of 30 years or more. In 1984 a study of the extended-life potential of EBR-II identified the factors that contribute to the continued successful operation of EBR-II as a power reactor and experimental facility. Also identified were factors that could cause disruptions in the useful life of the facility. Although no factors were found that would inherently limit the life of EBR-II, measures were identified that could help ensure continued plant availability. These measures include the implementation of more effective surveillance, diagnostic, and control systems to complement the inherent safety and reliability features of EBR-II. An operating lifetime of well beyond 30 years is certainly feasible

  3. Liquid metal reactor head designs in the USA - heat and mass transfer considerations

    International Nuclear Information System (INIS)

    Burke, T.M.

    1986-01-01

    Development of liquid metal reactor plants in the United States over the past 30 years has resulted in an evolution of reactor head designs as reflected in the SRE, Hallam, EBR-II and FFTF plants. This evolution has probably been affected to some extent by the fact that, in contrast to most other countries, there is no single organization in the United States which has been responsible for the design of liquid metal reactor plants. The current U.S. LMR design efforts involve two innovative design consortiums (guided by the US Department of Energy) and a joint industry venture on the Large Scale Prototype Breeder. It is therefore somewhat difficult to provide a statement on the philosophy of the reactor head design in the U.S. This paper however briefly describes the existing and proposed U.S. liquid metal reactor head designs and in the process, attempt to provide some insight on the basis for those designs

  4. Luna B. Leopold--pioneer setting the stage for modern hydrology

    Science.gov (United States)

    Hunt, Randall J.; Meine, Curt

    2012-01-01

    In 1986, during the first year of graduate school, the lead author was sampling the water from a pitcher pump in front of “The Shack,” the setting of the opening essays in Aldo Leopold's renowned book A Sand County Almanac. The sampling was part of my Master's work that included quarterly monitoring of water quality on the Leopold Memorial Reserve (LMR) near Baraboo, Wisconsin. The Shack was already a well-known landmark, and it was common to come upon visitors and hikers there. As such, I took no special note of the man who approached me as I was filling sample bottles and asked, as was typical, “What are you doing?”

  5. Estimação do período de carência de medicamento veterinário em produtos comestíveis (tecidos) de origem animal por modelos de regressão

    OpenAIRE

    Simone Cristina Rosa

    2016-01-01

    Resíduos de medicamento veterinário podem estar presentes em produtos comestíveis de origem animal, tais como carne, leite, ovos e mel. Para assegurar que a concentração de tais resíduos não excede um limite considerado seguro (Limite Máximo de Resíduo - LMR) deve ser estabelecido o período de carência, que é o tempo que deve ser respeitado para que um animal possa ser enviado para o abate após ter recebido um dado medicamento veterinário. A estimação do período de carência usualmente é feita...

  6. Irradiation of a 19 pin subassembly with mixed carbide fuel in KNK II

    Science.gov (United States)

    Geithoff, D.; Mühling, G.; Richter, K.

    1992-06-01

    The presentation deals with the fabrication, irradiation and nondestructive postirradiation examinations of LMR fuel pins with mixed (U, Pu)-carbide fuels. The mixed carbide fuel was fabricated by the European Institute of Transuranium Elements using various fabrication procedures. Fuel composition varied therefore in a wide range of tolerances with respect to oxygen and phase content and microstructure. The 19 carbide pins were irradiated in the fast neutron flux of the KNK II reactor to a burn-up of about 7 at% without any failure in the centre of a KNK "carrier element" at a maximum linear rating of 800 W/cm. After dismantling in the Hot Cells of KfK nondestructive examinations were carried out comprising dimensional controls, radiography, γ-scanning and eddy-current testing. The results indicate differences in fuel behaviour with respect to composition of the fuel.

  7. Advanced light-water reactors

    International Nuclear Information System (INIS)

    Golay, M.W.; Todreas, N.E.

    1990-01-01

    Environmental concerns, economics and the earth's finite store of fossil fuels argue for a resuscitation of nuclear power. The authors think improved light-water reactors incorporating passive safety features can be both safe and profitable, but only if attention is paid to economics, effective management and rigorous training methods. The experience of nearly four decades has winnowed out designs for four basic types of reactor: the heavy-water reactor (HWR), the gas-cooled rector (GCR), the liquid-metal-cooled reactor (LMR) and the light-water reactor (LWR). Each design is briefly described before the paper discusses the passive safety features of the AP-600 rector, so-called because it employs an advanced pressurized water design and generates 600 MW of power

  8. Performance assessment modeling of high level nuclear wasteforms from the pyroprocess fuel cycle

    International Nuclear Information System (INIS)

    Nutt, W.M.; Hill, R.N.; Bullen, D.B.

    1995-01-01

    Several performance assessment (PA) analyses have been completed to estimate the release to the accessible environment of radionuclides from spent light water reactor (LWR) fuel emplaced in the proposed Yucca Mountain repository. Probabilistic methods were utilized based on the complexity of the repository system. Recent investigations have been conducted to identify the merits of a pyroprocess fuel cycle. This cycle utilizes high temperature molten salts and metals to partially separate actinides and fission products. In a closed liquid metal reactor (LMR) fuel cycle, this allows recycling of nearly all of the actinides. In a once-through cycle, this isolates the actinides for storage into a wasteform which can be specifically tailored for their retention. With appropriate front-end treatment, this Process can also be used to treat LWR spent fuel

  9. ASCENDE-RT: An Analysis of Treatment-Related Morbidity for a Randomized Trial Comparing a Low-Dose-Rate Brachytherapy Boost with a Dose-Escalated External Beam Boost for High- and Intermediate-Risk Prostate Cancer

    International Nuclear Information System (INIS)

    Rodda, Sree; Tyldesley, Scott; Morris, W. James; Keyes, Mira; Halperin, Ross; Pai, Howard; McKenzie, Michael; Duncan, Graeme; Morton, Gerard; Hamm, Jeremy; Murray, Nevin

    2017-01-01

    Purpose: To report the genitourinary (GU) and gastrointestinal (GI) morbidity and erectile dysfunction in a randomized trial comparing 2 methods of dose escalation for high- and intermediate-risk prostate cancer. Methods and Materials: ASCENDE-RT (Androgen Suppression Combined with Elective Nodal and Dose Escalated Radiation Therapy) enrolled 398 men, median age 68 years, who were then randomized to either a standard arm that included 12 months of androgen deprivation therapy and pelvic irradiation to 46 Gy followed by a dose-escalated external beam radiation therapy (DE-EBRT) boost to 78 Gy, or an experimental arm that substituted a low-dose-rate prostate brachytherapy (LDR-PB) boost. At clinic visits, investigators recorded GU and GI morbidity and information on urinary continence, catheter use, and erectile function. Exclusion of 15 who received nonprotocol treatment and correction of 14 crossover events left 195 men who actually received a DE-EBRT boost and 188, an LDR-PB boost. Median follow-up was 6.5 years. Results: The LDR-PB boost increased the risk of needing temporary catheterization and/or requiring incontinence pads. At 5 years the cumulative incidence of grade 3 GU events was 18.4% for LDR-PB, versus 5.2% for DE-EBRT (P<.001). Compared with the cumulative incidence, the 5-year prevalence of grade 3 GU morbidity was substantially lower for both arms (8.6% vs 2.2%, P=.058). The 5-year cumulative incidence of grade 3 GI events was 8.1% for LDR-PB, versus 3.2% for DE-EBRT (P=.124). The 5-year prevalence of grade 3 GI toxicity was lower than the cumulative incidence for both arms (1.0% vs 2.2%, respectively). Among men reporting adequate baseline erections, 45% of LDR-PB patients reported similar erectile function at 5 years, versus 37% after DE-EBRT (P=.30). Conclusions: The incidence of acute and late GU morbidity was higher after LDR-PB boost, and there was a nonsignificant trend for worse GI morbidity. No differences in the frequency of

  10. ASCENDE-RT: An Analysis of Treatment-Related Morbidity for a Randomized Trial Comparing a Low-Dose-Rate Brachytherapy Boost with a Dose-Escalated External Beam Boost for High- and Intermediate-Risk Prostate Cancer

    Energy Technology Data Exchange (ETDEWEB)

    Rodda, Sree [British Columbia (BC) Cancer Agency, Vancouver Centre, Vancouver, British Columbia (Canada); Tyldesley, Scott [British Columbia (BC) Cancer Agency, Vancouver Centre, Vancouver, British Columbia (Canada); Department of Surgery, University of British Columbia, Vancouver, British Columbia (Canada); Morris, W. James, E-mail: jmorris@bccancer.bc.ca [British Columbia (BC) Cancer Agency, Vancouver Centre, Vancouver, British Columbia (Canada); Department of Surgery, University of British Columbia, Vancouver, British Columbia (Canada); Keyes, Mira [British Columbia (BC) Cancer Agency, Vancouver Centre, Vancouver, British Columbia (Canada); Department of Surgery, University of British Columbia, Vancouver, British Columbia (Canada); Halperin, Ross [Department of Surgery, University of British Columbia, Vancouver, British Columbia (Canada); BC Cancer Agency, Centre for the Southern Interior, Kelowna, British Columbia (Canada); Pai, Howard [Department of Surgery, University of British Columbia, Vancouver, British Columbia (Canada); BC Cancer Agency, Vancouver Island Centre, Victoria, British Columbia (Canada); McKenzie, Michael; Duncan, Graeme [British Columbia (BC) Cancer Agency, Vancouver Centre, Vancouver, British Columbia (Canada); Department of Surgery, University of British Columbia, Vancouver, British Columbia (Canada); Morton, Gerard [Sunnybrook Health Sciences Centre, Toronto, Ontario (Canada); Department of Radiation Oncology, University of Toronto, Toronto, Ontario (Canada); Hamm, Jeremy [Department of Population Oncology, BC Cancer Agency, Vancouver, British Columbia (Canada); Murray, Nevin [British Columbia (BC) Cancer Agency, Vancouver Centre, Vancouver, British Columbia (Canada); Department of Medicine, University of British Columbia, Vancouver, British Columbia (Canada)

    2017-06-01

    Purpose: To report the genitourinary (GU) and gastrointestinal (GI) morbidity and erectile dysfunction in a randomized trial comparing 2 methods of dose escalation for high- and intermediate-risk prostate cancer. Methods and Materials: ASCENDE-RT (Androgen Suppression Combined with Elective Nodal and Dose Escalated Radiation Therapy) enrolled 398 men, median age 68 years, who were then randomized to either a standard arm that included 12 months of androgen deprivation therapy and pelvic irradiation to 46 Gy followed by a dose-escalated external beam radiation therapy (DE-EBRT) boost to 78 Gy, or an experimental arm that substituted a low-dose-rate prostate brachytherapy (LDR-PB) boost. At clinic visits, investigators recorded GU and GI morbidity and information on urinary continence, catheter use, and erectile function. Exclusion of 15 who received nonprotocol treatment and correction of 14 crossover events left 195 men who actually received a DE-EBRT boost and 188, an LDR-PB boost. Median follow-up was 6.5 years. Results: The LDR-PB boost increased the risk of needing temporary catheterization and/or requiring incontinence pads. At 5 years the cumulative incidence of grade 3 GU events was 18.4% for LDR-PB, versus 5.2% for DE-EBRT (P<.001). Compared with the cumulative incidence, the 5-year prevalence of grade 3 GU morbidity was substantially lower for both arms (8.6% vs 2.2%, P=.058). The 5-year cumulative incidence of grade 3 GI events was 8.1% for LDR-PB, versus 3.2% for DE-EBRT (P=.124). The 5-year prevalence of grade 3 GI toxicity was lower than the cumulative incidence for both arms (1.0% vs 2.2%, respectively). Among men reporting adequate baseline erections, 45% of LDR-PB patients reported similar erectile function at 5 years, versus 37% after DE-EBRT (P=.30). Conclusions: The incidence of acute and late GU morbidity was higher after LDR-PB boost, and there was a nonsignificant trend for worse GI morbidity. No differences in the frequency of

  11. Observation Of Electron-beam-induced Phase Evolution Mimicking The Effect Of Charge-discharge Cycle In Li-rich Layered Cathode Materials Used For Li-ion Batteries

    Energy Technology Data Exchange (ETDEWEB)

    Lu, Ping; Yan, Pengfei; Romero, Eric; Spoerke, Erik D.; Zhang, Jiguang; Wang, Chong M.

    2015-02-24

    Capacity loss, and voltage fade upon electrochemical charge-discharge cycling observed in lithium-rich layered cathode oxides (Li[LixMnyTM1-x-y]O2 , TM = Ni, Co or Fe) have recently been identified to be correlated to the gradual phase transformation, featuring the formation of a surface reconstructed layer (SRL) that evolves from a thin (<2 nm), defect spinel layer upon the first charge, to a relatively thick (~5 nm), spinel or rock-salt layer upon continuous charge-discharge cycling. Here we report observations of a SRL and structural evolution of the SRL on the Li[Li0.2Ni0.2Mn0.6]O2 (LMR) particles, which are identical to those reported due to the charge-discharge cycle but are a result of electron-beam irradiation during scanning transmission electron microscopy (STEM) imaging. Sensitivity of the lithium-rich layered oxides to high-energy electrons leads to the formation of thin, defect spinel layer on surfaces of the particles when exposed to a 200 kV electron beam for as little as 30 seconds under normal high-resolution STEM imaging conditions. Further electron irradiation produces a thicker layer of the spinel phase, ultimately producing a rock-salt layer at a higher electron exposure. Atomic-scale chemical mapping by energy dispersive X-ray spectroscopy in STEM indicates the electron-beam-induced SRL formation on LMR is accomplished by migration of the transition metal ions to the Li sites without breaking down the lattice. This study provides an insight for understanding the mechanism of forming the SRL and also possibly a mean to study structural evolution in the Li-rich layered oxides without involving the electrochemistry.

  12. Material and Energy Flows in the Production of Cathode and Anode Materials for Lithium Ion Batteries

    Energy Technology Data Exchange (ETDEWEB)

    Dunn, Jennifer B. [Argonne National Lab. (ANL), Argonne, IL (United States). Energy Systems Division; James, Christine [Michigan State Univ., East Lansing, MI (United States). Chemical Engineering and Materials Science Dept.; Gaines, Linda G. [Argonne National Lab. (ANL), Argonne, IL (United States). Energy Systems Division; Gallagher, Kevin [Argonne National Lab. (ANL), Argonne, IL (United States). Chemical Sciences and Engineering Division

    2014-09-30

    The Greenhouse gases, Regulated Emissions and Energy use in Transportation (GREET) model has been expanded to include four new cathode materials that can be used in the analysis of battery-powered vehicles: lithium nickel cobalt manganese oxide (LiNi0.4Co0.2Mn0.4O2 [NMC]), lithium iron phosphate (LiFePO4 [LFP]), lithium cobalt oxide (LiCoO2 [LCO]), and an advanced lithium cathode (0.5Li2MnO3∙0.5LiNi0.44Co0.25Mn0.31O2 [LMR-NMC]). In GREET, these cathode materials are incorporated into batteries with graphite anodes. In the case of the LMR-NMC cathode, the anode is either graphite or a graphite-silicon blend. This report documents the material and energy flows of producing each of these cathode and anode materials from raw material extraction through the preparation stage. For some cathode materials, we considered solid state and hydrothermal preparation methods. Further, we used Argonne National Laboratory’s Battery Performance and Cost (BatPaC) model to determine battery composition (e.g., masses of cathode, anode, electrolyte, housing materials) when different cathode materials were used in the battery. Our analysis concluded that cobalt- and nickel-containing compounds are the most energy intensive to produce.

  13. Subclinical Inflammation and Simple Blood Parameters in Pregnant with Familial Mediterranean Fever

    Directory of Open Access Journals (Sweden)

    Korkut Daglar

    2016-09-01

    Full Text Available Aim: Familial Mediterranean Fever (FMF is the most common hereditary monogenic auto-inflammatory disease. Studies suggest that inflammation persists even in attack-free periods in FMF patients. In this study, we aim to investigate the potential of simple blood parameters including neutrophil to lymphocyte ratio (NLR, platelet to lymphocyte ratio (PLR, lymphocyte/monocyte ratio (LMR, mean platelet volume (MPV, and platelet distributed width (PDW as emerging inflammatory markers to identify chronic inflammations during symptom-free periods in a group of pregnant patients with FMF. Material and Method: A total of consecutive 65 singleton pregnancies, 33 with FMF and the other 32 healthy women, were followed from the first trimester to the end of the pregnancies. Blood samples for biochemical analyses (C-reactive protein, fibrinogen and a complete blood count were obtained at 11-13 weeks and at 16-19 weeks following a detailed examination. Results: While the mean, NLR, PLR, PDW, fibrinogen, and LMR values were comparable between the groups, the mean hs-CRP levels were significantly higher and MPV values were significantly lower in the FMF group compared with the control group at both the first and second trimester. There was a significant negative correlation between hs-CRP levels with MPV at second trimester (r= -0.375 p=0.003. Discussion: Since all of our FMF patients had already been on regular colchicine therapy on admission, we admit, at least theoretically, that the anti-inflammatory and potential effects of colchicine on platelets could have altered our results. Otherwise, MPV may be used as a negative acute-phase reactant in pregnant patients with FMF.

  14. Consolidated fuel reprocessing programme: Analysis of various options for the breeder fuel cycle in the USA

    International Nuclear Information System (INIS)

    Stradley, J.G.; Burch, W.D.; Yook, H.R.

    1986-01-01

    The United States Department of Energy (DOE) has established a programme to develop innovative liquid metal reactor (LMR) designs to assist in developing future U.S. reactor strategy. The paper describes studies in progress to examine various fuel cycle strategies that relate to the reactor strategy. Three potential fuel cycle options that focus on supporting an initial 1300 MW(e) reactor station have been defined: (1) Completion and utilization of the Breeder Reprocessing Engineering Test/Secure Automated Fabrication (BRET/SAF) in the Fuels and Materials Examination Facility (FMEF) at Hanford, Washington; (2) a co-located fuel cycle facility; and (3) delayed closure of the fuel cycle for five to ten years. The BRET, designed as a development facility, has sufficient capacity to service the needs of an initial module at an LMR station. It appears feasible to increase this capacity and to utilize SAF in the FMEF to accommodate the projected output (up to 35 MtHM/year) from the 1300 MW(e) liquid-metal concepts under study. Plans developed within the United States Consolidated Management Office for an initial reactor project have envisioned that cost savings could be realized by delaying the closure of the fuel cycle as long as supplies of plutonium could be obtained relatively inexpensively. This might prove to be only five to ten years, but even that period might be long enough for the fuel cycle costs to be spread over more than one reactor rather than loaded on the initial project. This concept is being explored as is the question of the future coupling of a light water reactor reprocessing industry for plutonium supply to breeder recycle

  15. Genome wide adaptations of Plasmodium falciparum in response to lumefantrine selective drug pressure.

    Directory of Open Access Journals (Sweden)

    Leah Mwai

    Full Text Available The combination therapy of the Artemisinin-derivative Artemether (ART with Lumefantrine (LM (Coartem® is an important malaria treatment regimen in many endemic countries. Resistance to Artemisinin has already been reported, and it is feared that LM resistance (LMR could also evolve quickly. Therefore molecular markers which can be used to track Coartem® efficacy are urgently needed. Often, stable resistance arises from initial, unstable phenotypes that can be identified in vitro. Here we have used the Plasmodium falciparum multidrug resistant reference strain V1S to induce LMR in vitro by culturing the parasite under continuous drug pressure for 16 months. The initial IC(50 (inhibitory concentration that kills 50% of the parasite population was 24 nM. The resulting resistant strain V1S(LM, obtained after culture for an estimated 166 cycles under LM pressure, grew steadily in 378 nM of LM, corresponding to 15 times the IC(50 of the parental strain. However, after two weeks of culturing V1S(LM in drug-free medium, the IC(50 returned to that of the initial, parental strain V1S. This transient drug tolerance was associated with major changes in gene expression profiles: using the PFSANGER Affymetrix custom array, we identified 184 differentially expressed genes in V1S(LM. Among those are 18 known and putative transporters including the multidrug resistance gene 1 (pfmdr1, the multidrug resistance associated protein and the V-type H+ pumping pyrophosphatase 2 (pfvp2 as well as genes associated with fatty acid metabolism. In addition we detected a clear selective advantage provided by two genomic loci in parasites grown under LM drug pressure, suggesting that all, or some of those genes contribute to development of LM tolerance--they may prove useful as molecular markers to monitor P. falciparum LM susceptibility.

  16. Material and Energy Flows in the Production of Cathode and Anode Materials for Lithium Ion Batteries

    Energy Technology Data Exchange (ETDEWEB)

    Dunn, Jennifer B. [Argonne National Lab. (ANL), Argonne, IL (United States); James, Christine [Michigan State Univ., East Lansing, MI (United States); Gaines, Linda [Argonne National Lab. (ANL), Argonne, IL (United States); Gallagher, Kevin [Argonne National Lab. (ANL), Argonne, IL (United States); Dai, Qiang [Argonne National Lab. (ANL), Argonne, IL (United States); Kelly, Jarod C. [Argonne National Lab. (ANL), Argonne, IL (United States)

    2015-09-01

    The Greenhouse gases, Regulated Emissions and Energy use in Transportation (GREET) model has been expanded to include four new cathode materials that can be used in the analysis of battery-powered vehicles: lithium nickel cobalt manganese oxide (LiNi0.4Co0.2Mn0.4O2 [NMC]), lithium iron phosphate (LiFePO4 [LFP]), lithium cobalt oxide (LiCoO2 [LCO]), and an advanced lithium cathode (0.5Li2MnO3∙0.5LiNi0.44Co0.25Mn0.31O2 [LMR-NMC]). In GREET, these cathode materials are incorporated into batteries with graphite anodes. In the case of the LMR-NMC cathode, the anode is either graphite or a graphite-silicon blend. Lithium metal is also an emerging anode material. This report documents the material and energy flows of producing each of these cathode and anode materials from raw material extraction through the preparation stage. For some cathode materials, we considered solid state and hydrothermal preparation methods. Further, we used Argonne National Laboratory’s Battery Performance and Cost (BatPaC) model to determine battery composition (e.g., masses of cathode, anode, electrolyte, housing materials) when different cathode materials were used in the battery. Our analysis concluded that cobalt- and nickel-containing compounds are the most energy intensive to produce.

  17. Characterization of liquid metal reactor materials

    International Nuclear Information System (INIS)

    Kuk, I. H.; Ryu, W. S.; Kim, H. H. and others

    1999-03-01

    The objectives of this report were to assess the material requirements for LMR environment, to select the optimum candidates for KALIMER components, to characterize the performance for establishing a database of the structural materials for KALIMER, and to develop the basic material technologies for the localization of the advanced materials. Stainless steel ingots were melted by VIM and hot-rolled to plate with the thickness of 15mm. The plate was solution-treated for 1 hr at 1100 deg C and then water-quenched. Specimens were taken parallel to the rolling direction of the plate. The effects of nitrogen and phosphorus were analyzed on the high temperature mechanical properties of 316MRP (Liquid Metal Reactor, Primary candidate material) stainless steels with the different nitrogen content from 0.04 to 0.15% and with the different phosphorus content from 0.002 to 0.02%. Heat treatment was performed to investigate the changes in microstructure and mechanical properties of Cr-Mo steels for LMR heat transfer tube materials and core materials. The Cr-Mo steels were normalized at the temperatures between 900 deg C and 1200 deg C for 1hrs and tempered at the temperatures between 500 deg C and 800 deg C for 2hrs. Conventional optical and electron micrographic studies were carried out to investigate the martensite lath structure, carbide indentification and carbide shape. Vickers microhardness was measured at room temperature using 10g load. Tensile properties were tested at high temperature. Charpy V-notch impact tests were also carried out at temperature between -120 deg C and +180 deg C. (author). 72 refs., 28 tabs., 244 figs

  18. An inflammation-based cumulative prognostic score system in patients with diffuse large B cell lymphoma in rituximab era.

    Science.gov (United States)

    Sun, Feifei; Zhu, Jia; Lu, Suying; Zhen, Zijun; Wang, Juan; Huang, Junting; Ding, Zonghui; Zeng, Musheng; Sun, Xiaofei

    2018-01-02

    Systemic inflammatory parameters are associated with poor outcomes in malignant patients. Several inflammation-based cumulative prognostic score systems were established for various solid tumors. However, there is few inflammation based cumulative prognostic score system for patients with diffuse large B cell lymphoma (DLBCL). We retrospectively reviewed 564 adult DLBCL patients who had received rituximab, cyclophosphamide, doxorubicin, vincristine and prednisolone (R-CHOP) therapy between Nov 1 2006 and Dec 30 2013 and assessed the prognostic significance of six systemic inflammatory parameters evaluated in previous studies by univariate and multivariate analysis:C-reactive protein(CRP), albumin levels, the lymphocyte-monocyte ratio (LMR), the neutrophil-lymphocyte ratio(NLR), the platelet-lymphocyte ratio(PLR)and fibrinogen levels. Multivariate analysis identified CRP, albumin levels and the LMR are three independent prognostic parameters for overall survival (OS). Based on these three factors, we constructed a novel inflammation-based cumulative prognostic score (ICPS) system. Four risk groups were formed: group ICPS = 0, ICPS = 1, ICPS = 2 and ICPS = 3. Advanced multivariate analysis indicated that the ICPS model is a prognostic score system independent of International Prognostic Index (IPI) for both progression-free survival (PFS) (p systemic inflammatory status was associated with clinical outcomes of patients with DLBCL in rituximab era. The ICPS model was shown to classify risk groups more accurately than any single inflammatory prognostic parameters. These findings may be useful for identifying candidates for further inflammation-related mechanism research or novel anti-inflammation target therapies.

  19. Urinary p-cresol diagnosis using nanocomposite of ZnO/MoS2 and molecular imprinted polymer on optical fiber based lossy mode resonance sensor.

    Science.gov (United States)

    Usha, Sruthi P; Gupta, Banshi D

    2018-03-15

    A lossy mode resonance (LMR) based sensor for urinary p-cresol testing on optical fiber substrate is developed. The sensor probe fabrication includes dip coating of nanocomposite layer of zinc oxide and molybdenum sulphide (ZnO/MoS 2 ) over unclad core of optical fiber as the transducer layer followed by the layer of molecular imprinted polymer (MIP) as the recognition medium. The addition of molybdenum sulphide in the transducer layer increases the absorption of light in the medium which enhances the LMR properties of zinc oxide thereby increasing the conductivity and hence the sensitivity of the sensor. The sensor probe is characterized for p-cresol concentration range from 0µM (reference sample) to 1000µM in artificially prepared urine. Optimizations of various probe fabrication parameters are carried to bring out the sensor's optimal performance with a sensitivity of 11.86nm/µM and 28nM as the limit of detection (LOD). A two-order improvement in LOD is obtained as compared to the recently reported p-cresol sensor. The proposed sensor possesses a response time of 15s which is 8 times better than that reported in the literature utilizing electrochemical method. Its response time is also better than the p-cresol sensor currently available in the market for the medical field. Thus, with a fast response, significant stability and repeatability, the proposed sensor holds practical implementation possibilities in the medical field. Further, the realization of sensor probe over optical fiber substrate adds remote sensing and online monitoring feasibilities. Copyright © 2017 Elsevier B.V. All rights reserved.

  20. Analyses of Design Extended Condition Events for the Prototype Gen-IV SFR

    International Nuclear Information System (INIS)

    Choi, Chiwoong; Jeong, Taekyung; Lee, Kwilim; Jeong, Jaeho; Ha, Kwiseok

    2015-01-01

    In this study, the sensitivity tests are conducted. In the case of the UTOP event, a sensitivity test for the reactivity insertion amount and rate were conducted. This analysis can give a requirement for margin of control rod stop system (CRSS). For example, the CRSS in the PRISM designed based on the 0.4 $ reactivity insertion, which is analyzed with safety analysis of UTOP event. Moreover, the sensitivity tests for weighting factor in the core radial expansion reactivity feedback model were also carried out for all ATWS events. Currently, the reactivity feedback model for the PGSFR is not validated yet. However, the reactivity feedback models in the MARS-LMR are validating with various plant-based data including EBR-II SHRT. The ATWS events for the PGSFR classified in the design extended condition including UTOP, ULOF, and ULOHS are analyzed with MARS-LMR. In this study, the sensitivity tests for reactivity insertion amount and rate in the UTOP event are conducted. The reactivity insertion amount is obviously an influential parameter. The reactivity insertion amount can give a requirement for design of the CRSS, therefore, this sensitivity result is very important to the CRSS. In addition, sensitivity tests for the weighting factor in the radial expansion reactivity model are carried out. The weighting factor for a grid plate, W GP , which means contribution of feedback in the grid plate is changed for all unprotected events. The grid plate expansion is governed by a core inlet temperature. As the W GP is increased, the power in the UTOP and the ULOF is increased, however, the power in the ULOHS is decreased. The higher power during transient means lower reactivity feedback and smaller expansion. Thus, the core outlet temperature rise is dominant in the UTOP and ULOF events, however, the core inlet temperature rise is dominant in the ULOHS. Therefore, the grid plate expansion in the ULOHS is predominant

  1. The Climate Response to Explosive Volcanism in the Last Millennium Reanalysis

    Science.gov (United States)

    Emile-Geay, J.; Erb, M. P.; Hakim, G. J.; Anchukaitis, K. J.; Toohey, M.; Steig, E. J.

    2017-12-01

    Explosive volcanism substantially affects the climate system via the direct effect of radiative forcing anomalies and ensuing influences on, and feedback to, major modes of ocean-atmosphere variability. Eruptions therefore offer unparalleled natural experiments with which to study the climate response to stratospheric aerosol loading. While the instrumental record provides a few, modest examples of such eruptions, the Common Era provides a much larger sample with more dramatic instances [Sigl et al, Nature, 2015]. Here we leverage the Last Millennium Reanalysis (LMR, Hakim et al [JGR-Atm, 2016]), to probe the climate response to explosive volcanism. LMR fuses information from general circulation models and a recent multiproxy compilation [PAGES 2k Consortium, Sci Data, 2017] to depict Common Era climate: surface temperature, 500mb geopotential height, precipitation and drought indices are reconstructed at annual resolution over the past 2,000 years, with error estimates. Using forcing estimates from Toohey & Sigl [ESDD, 2017], the reconstructions shows a 0.2K cooling following the 20 largest eruptions since 750, with maximum impacts over Northern Eurasia and western North America. Comparison to the N-TREND temperature reconstruction [Anchukaitis et al, QSR 2017], which uses a completely independent methodology, shows remarkable agreement in the magnitude and spatial patterns. Surprisingly, reconstructed temperature recovers slowly (10-15y) after major eruptions, a result at odds with conventional wisdom [Robock, Rev. Geophys. 2000] but consistent with modeling results [Pausata et al, PNAS, 2015], and suggestive of an active role for ocean dynamics. Preliminary results show a marginally significant, El Niño-like sea-surface temperature response immediately after the eruption, accompanied by a significant weakening of the Walker circulation and a southward shift of the Intertropical Convergence Zone. A comparison to PMIP3 simulations shows greater magnitudes of

  2. Comparison of the prognostic values of preoperative inflammation-based parameters in patients with breast cancer.

    Directory of Open Access Journals (Sweden)

    Hideya Takeuchi

    Full Text Available Peripheral blood-derived inflammation-based markers, including C-reactive protein (CRP, neutrophil-to-lymphocyte ratio (NLR, lymphocyte-to-monocyte ratio (LMR, and platelet-to-lymphocyte ratio (PLR are indicators of prognosis in various malignant tumors. The present study aimed to identify the inflammation-based parameters that are most suitable for predicting outcomes in patients with breast cancer. Two hundred ninety-six patients who underwent surgery for localized breast cancer were reviewed retrospectively. The association between clinicopathological factors and inflammation-based parameters were investigated. Univariate and multivariate Cox regression analyses were performed to identify independent prognostic indicators associated with disease-free survival (DFS. The NLR level correlated significantly with tumor size (P<0.05. The PLR level correlated with the expression of estrogen receptor and lymph node involvement (P<0.05. Univariate analysis revealed that lower CRP and PLR values as well as tumor size, lymph node involvement, and nuclear grade were significantly associated with superior DFS (CRP: P<0.01; PLR, tumor size, lymph node involvement, and nuclear grade: P<0.05. On multivariate analysis, CRP (hazard ratio [HR]: 2.85, 95% confidence interval [CI]: 1.03-7.88, P<0.05, PLR (HR: 2.61, 95% CI: 1.07-6.36, P<0.05 and nuclear grade (HR: 3.066, 95% CI: 1.26-7.49, P<0.05 were significant prognostic indicators of DFS in patients with breast cancer. Neither LMR nor NLR significantly predicted DFS. Both preoperative CRP and PLR values were independently associated with poor prognosis in patients with breast carcinoma; these were superior to other inflammation-based scores in terms of prognostic ability.

  3. Safety analysis for key design features of KALIMER-600 design concept

    International Nuclear Information System (INIS)

    Lee, Yong-Bum; Kwon, Y. M.; Kim, E. K.; Suk, S. D.; Chang, W. P.; Joeng, H. Y.; Ha, K. S.; Heo, S.

    2005-03-01

    KAERI is developing the conceptual design of a Liquid Metal Reactor, KALIMER-600 (Korea Advanced LIquid MEtal Reactor) under the Long-term Nuclear R and D Program. KALIMER-600 addresses key issues regarding future nuclear power plants such as plant safety, economics, proliferation, and waste. In this report, key safety design features are described and safety analyses results for typical ATWS accidents, containment design basis accidents, and flow blockages in the KALIMER design are presented. First, the basic approach to achieve the safety goal and main design features of KALIMER-600 are introduced in Chapter 1, and the event categorization and acceptance criteria for the KALIMER-600 safety analysis are described in Chapter 2, In Chapter 3, results of inherent safety evaluations for the KALIMER-600 conceptual design are presented. The KALIMER-600 core and plant system are designed to assure benign performance during a selected set of events without either reactor control or protection system intervention. Safety analyses for the postulated anticipated transient without scram (ATWS) have been performed using the SSC-K code to investigate the KALIMER-600 system response to the events. The objectives of Chapter 4, are to assess the response of KALIMER-600 containment to the design basis accidents and to evaluate whether the consequences are acceptable or not in the aspect of structural integrity and the exposure dose rate. In Chapter 5, the analysis of flow blockage for KALIMER-600 with the MATRA-LMR-FB code, which has been developed for the internal flow blockage in a LMR subassembly, are described. The cases with a blockage of 6-subchannel, 24-subchannel, and 54-subchannel are analyzed

  4. Application of Mycobacterium Leprae-specific cellular and serological tests for the differential diagnosis of leprosy from confounding dermatoses.

    Science.gov (United States)

    Freitas, Aline Araújo; Hungria, Emerith Mayra; Costa, Maurício Barcelos; Sousa, Ana Lúcia Osório Maroccolo; Castilho, Mirian Lane Oliveira; Gonçalves, Heitor Sá; Pontes, Maria Araci Andrade; Duthie, Malcolm S; Stefani, Mariane Martins Araújo

    2016-10-01

    Mycobacterium leprae-specific serological and cell-mediated-immunity/CMI test were evaluated for the differential diagnosis of multibacillary/MB, and paucibacillary/PB leprosy from other dermatoses. Whole-blood assay/WBA/IFNγ stimulated with LID-1 antigen and ELISA tests for IgG to LID-1 and IgM to PGL-I were performed. WBA/LID-1/IFNγ production was observed in 72% PB, 11% MB leprosy, 38% dermatoses, 40% healthy endemic controls/EC. The receiver operating curve/ROC for WBA/LID-1 in PB versus other dermatoses showed 72.5% sensitivity, 61.5% specificity and an area-under-the-curve/AUC=0.75; 74% positive predictive value/PPV, 59% negative predictive value/NPV. Anti PGL-I serology was positive in 67% MB, 8% PB leprosy, 6% of other dermatoses; its sensitivity for MB=66%, specificity=93%, AUC=0.89; PPV=91%, NPV=72%. Anti-LID-1 serology was positive in 87% MB, 7% PB leprosy, all other participants were seronegative; 87.5% sensitivity for MB, 100% specificity, AUC=0.97; PPV=100%, NPV=88%. In highly endemic areas anti-LID-1/PGL-I serology and WBA/LID-1-represent useful tools for the differential diagnosis of leprosy from other confounding dermatoses. Copyright © 2016 Elsevier Inc. All rights reserved.

  5. Maintenance energy requirements of beef cows and relationship with cow and calf performance, metabolic hormones, and functional proteins.

    Science.gov (United States)

    Cooper-Prado, M J; Long, N M; Davis, M P; Wright, E C; Madden, R D; Dilwith, J W; Bailey, C L; Spicer, L J; Wettemann, R P

    2014-08-01

    Gestating Angus, nonlactating, spring-calving cows were used to determine variation in maintenance energy requirements (MR); to evaluate the relationship among MR and cow and calf performance, plasma concentrations of IGF-I, T4, glucose, insulin, and ruminal temperature; and to describe the LM proteome and evaluate protein abundance in cows with different MR. Cows (4 to 7 yr of age) with a BCS of 5.0 ± 0.2 and BW of 582 ± 37 kg in the second to third trimester of gestation were studied in 3 trials (trial 1, n = 23; trial 2, n = 32; trial 3, n = 38). Cows were individually fed a complete diet in amounts to meet predicted MR (Level 1 Model of NRC), and feed intake was adjusted weekly until constant BW was achieved for at least 21 d (maintenance). Cows were classified on the basis of MR as low (>0.5 SD less than mean, LMR), moderate (±0.5 SD of mean, MMR), or high (>0.5 SD more than mean, HMR) MR. Blood samples were taken at maintenance and at 2 mo postpartum in trial 2. Muscle biopsies were taken from LMR and HMR after cows consumed actual MR for 28 d (trial 2) or 21 d (trial 3). Proteins from LM were separated by 2-dimensional difference gel electrophoresis and were identified, and abundance was quantified and compared. The greatest differences in MR between cows were 29%, 24%, and 25% in trials 1, 2, and 3, respectively. Daily MR (NEm, kcal·BW(-0.75)·d(-1)) averaged 89.2 ± 6.3, 93.0 ± 4.9, and 90.4 ± 4.6 in trials 1, 2, and 3, respectively. Postpartum BW and BCS, calf birth and weaning weights, postpartum luteal activity, and ruminal temperature were not influenced by MR of the cows. Concentrations of IGF-I were greater (P = 0.001) in plasma of MMR compared with LMR cows consuming predicted MR diets, and MR was negatively correlated with concentrations of IGF-I in plasma (r = -0.38; P = 0.05) at 2 mo postpartum. A total of 103 proteins were isolated from LM; 52 gene products were identified. Abundance of specific proteins in the LM was not influenced (P > 0

  6. Quasiparticle Excitations with Berry Curvature in Insulating Magnets and Weyl Semimetals

    Science.gov (United States)

    Hirschberger, Maximilian Anton

    half-Heusler material GdPtBi. A careful doping study of the negative longitudinal magnetoresistance (LMR) establishes GdPtBi as a new material platform to study the physical properties of a simple Weyl metal with only two Weyl points (for magnetic field along the crystallographic 〈111〉 direction). The negative LMR is associated with the theory of the chiral anomaly in solids, and a direct consequence of the nonzero Berry curvature of the energy band structure of a Weyl semimetal. We compare our results to detailed calculations of the electronic band structure. Moving beyond the negative LMR, we report for the first time the effect of the chiral anomaly on the longitudinal thermopower in a Weyl semimetal.

  7. Subchannel analysis of a small ultra-long cycle fast reactor core

    International Nuclear Information System (INIS)

    Seo, Han; Kim, Ji Hyun; Bang, In Cheol

    2014-01-01

    Highlights: • The UCFR-100 is small-sized one of 60 years long-life nuclear reactors without refueling. • The design safety limits of the UCFR-100 are evaluated using MATRA-LMR. • The subchannel results are below the safety limits of general SFR design criteria. - Abstract: Thermal-hydraulic evaluation of a small ultra-long cycle fast reactor (UCFR) core is performed based on existing safety regulations. The UCFR is an innovative reactor newly designed with long-life core based on the breed-and-burn strategy and has a target electric power of 100 MWe (UCFR-100). Low enriched uranium (LEU) located at the bottom region of the core play the role of igniter to operate the UCFR for 60 years without refueling. A metallic form is selected as a burning fuel region material after the LEU location. HT-9 and sodium are used as cladding and coolant materials, respectively. In the present study, MATRA-LMR, subchannel analysis code, is used for evaluating the safety design limit of the UCFR-100 in terms of fuel, cladding, and coolant temperature distributions in the core as design criteria of a general fast reactor. The start-up period (0 year of operation), the middle of operating period (30 years of operation), and the end of operating cycle (60 years of operation) are analyzed and evaluated. The maximum cladding surface temperature (MCST) at the BOC (beginning of core life) is 498 °C on average and 551 °C when considering peaking factor, while the MCST at the MOC (middle of core life) is 498 °C on average and 548 °C in the hot channel, respectively, and the MCST at the EOC (end of core life) is 499 °C on average and 538 °C in the hot channel, respectively. The maximum cladding surface temperature over the long cycle is found at the BOC due to its high peaking factor. It is found that all results including fuel rods, cladding, and coolant exit temperature are below the safety limit of general SFR design criteria

  8. X-ray backscatter imaging for radiography by selective detection and snapshot: Evolution, development, and optimization

    Science.gov (United States)

    Shedlock, Daniel

    Compton backscatter imaging (CBI) is a single-sided imaging technique that uses the penetrating power of radiation and unique interaction properties of radiation with matter to image subsurface features. CBI has a variety of applications that include non-destructive interrogation, medical imaging, security and military applications. Radiography by selective detection (RSD), lateral migration radiography (LMR) and shadow aperture backscatter radiography (SABR) are different CBI techniques that are being optimized and developed. Radiography by selective detection (RSD) is a pencil beam Compton backscatter imaging technique that falls between highly collimated and uncollimated techniques. Radiography by selective detection uses a combination of single- and multiple-scatter photons from a projected area below a collimation plane to generate an image. As a result, the image has a combination of first- and multiple-scatter components. RSD techniques offer greater subsurface resolution than uncollimated techniques, at speeds at least an order of magnitude faster than highly collimated techniques. RSD scanning systems have evolved from a prototype into near market-ready scanning devices for use in a variety of single-sided imaging applications. The design has changed to incorporate state-of-the-art detectors and electronics optimized for backscatter imaging with an emphasis on versatility, efficiency and speed. The RSD system has become more stable, about 4 times faster, and 60% lighter while maintaining or improving image quality and contrast over the past 3 years. A new snapshot backscatter radiography (SBR) CBI technique, shadow aperture backscatter radiography (SABR), has been developed from concept and proof-of-principle to a functional laboratory prototype. SABR radiography uses digital detection media and shaded aperture configurations to generate near-surface Compton backscatter images without scanning, similar to how transmission radiographs are taken. Finally, a

  9. SSC-K code user's manual

    Energy Technology Data Exchange (ETDEWEB)

    Kwon, Y.M.; Lee, Y.B.; Chang, W.P.; Hahn, D

    2000-07-01

    The Supper System Code of KAERI (SSC-K) is a best-estimate system code for analyzing a variety of off-normal or accidents in the heat transport system of a pool type LMR design. It is being developed at Korea Atomic Energy Research Inititution (KAERI) on the basis of SSC-L, originally developed at BNL to analyze loop-type LMR transients. SSC-K can handle both designs of loop and pool type LMRs. SSC-K contains detailed mechanistic models of transient thermal, hydraulic, neutronic, and mechanical phenomena to describe the response of the reactor core, coolant, fuel elements, and structures to accident conditions. This report provides an overview of recent model developmentsvfor the SSC-K computer code, focusing on phenomenological model descriptions for new thermal, hydraulic, neutronic, and mechnaical modules. A comprehensive description of the models for pool-type reactor is given in Chapters 2 and 3; the steady-state plant characterization, prior to the initiation of transient is described in Chapter 2 and their transient counterparts are discussed in Chapter 3. In Chapter 4, a discussion on the intermediate heat exchanger (IHX) is presented. The IHX model of SSC-K is similar to that used in the SSC-L, except for some changes required for the pool-type configuration of reactor vessel. In Chapter 5, an electromagnetic (EM) pump is modeled as a component. There are two pump choices available in SSC-K; a centrifugal pump which was originally imbedded into the SSC-L, and an EM pump which was introduced for the KALIMER design. In Chapter 6, a model of passive safety decay heat removal system(PSDRS) is discussed, which removes decay heat through the reactor and containment vessel walls to the ambient air heat sink. In Chapter 7, models for various reactivity feedback effects are discussed. Reactivity effects of importance in fast reactor include the Doppler effect, effects of sodium density changes, effects of dimensional changes in core geometry. Finally in Chapter 8

  10. SSC-K code users manual (rev.1)

    International Nuclear Information System (INIS)

    Kwon, Y. M.; Lee, Y. B.; Chang, W. P.; Hahn, D.

    2002-01-01

    The Supper System Code of KAERI (SSC-K) is a best-estimate system code for analyzing a variety of off-normal or accidents in the heat transport system of a pool type LMR design. It is being developed at Korea Atomic Energy Research Institution (KAERI) on the basis of SSC-L, originally developed at BNL to analyze loop-type LMR transients. SSC-K can handle both designs of loop and pool type LMRs. SSC-K contains detailed mechanistic models of transient thermal, hydraulic, neutronic, and mechanical phenomena to describe the response of the reactor core, coolant, fuel elements, and structures to accident conditions. This report provides a revised User's Manual (rev.1) of the SSC-K computer code, focusing on phenomenological model descriptions for new thermal, hydraulic, neutronic, and mechanical modules. A comprehensive description of the models for pool-type reactor is given in Chapters 2 and 3; the steady-state plant characterization, prior to the initiation of transient is described in Chapter 2 and their transient counterparts are discussed in Chapter 3. Discussions on the intermediate heat exchanger (IHX) and the electromagnetic (EM) pump are described in Chapter 4 and 5, respectively. A model of passive safety decay heat removal system (PSDRS) is discussed in Chapter 6, and models for various reactivity feedback effects are discussed in Chapter 7. In Chapter 8, constitutive laws and correlations required to execute the SSC-K are described. New models developed for SSC-K rev.1 are two dimensional hot pool model in Chapter 9, and long term cooling model in Chapter 10. Finally, a brief description of MINET code adopted to simulate BOP is presented in Chapter 11. Based on test runs for typical LMFBR accident analyses, it was found that the present version of SSC-K would be used for the safety analysis of KALIMER. However, the further validation of SSC-K is required for real applications. It is noted that the user's manual of SSC-K will be revised later with the

  11. Cuantificación de plaguicidas residuales en granos de maíz (Zea mays L. aplicando técnicas de evaluación residual

    Directory of Open Access Journals (Sweden)

    Dante Rojas

    2014-07-01

    Full Text Available El empleo de plaguicidas en la producción agrícola ha tomado marcada importancia para muchos sectores de la sociedad. Los productores agropecuarios necesitan realizar un tratamiento fitoterapeútico efectivo y la utilización de estos agroquímicos es una alternativa rentable. Sin embargo, la toxicidad de estas sustancias presenta un riesgo para la salud humana durante su fabricación y empleo. El objetivo del presente trabajo fue obtener información de los niveles y frecuencia de los principales residuos de pesticidas presentes en granos de maíz aplicando técnicas de evaluación multiresidual. El muestreo (basado en la Norma ISO 950:1979 fue realizado en cintas de embarque y terminales portuarias del Río Paraná y del sur de la Provincia de Buenos Aires (Argentina, dado que manejan más del 80 % de las exportaciones del país (Ingeniero White, Rosario/General San Martín/San Lorenzo, Villa Constitución y Quequén. Sobre un total de 192 muestras, 94 presentaron residuos de plaguicidas, siendo el orden de frecuencia de aparición de los mismos: fenitrotión (n = 40 > cipermetrina (n = 31 > pirimifós metil (n = 27 > deltametrina (n = 24 > clorpirifós metil (n = 23 > diclorvós (n = 18 > permetrina (n = 15 > clorpirifós etil (n = 12 > fenvalerato (n = 3 > malatión (n = 2 > endosulfán (n = 0; suma de alfa endosulfán, beta endosulfán y endosulfán sulfato. No se hallaron organoclorados. Considerando la legislación Argentina, solo 4 muestras presentaron niveles superiores a los Límites Máximos de Residuos (LMR, siendo cipermetrina el plaguicida involucrado. Sin embargo, según los LMR del Codex Alimentarius, todas las muestras presentaron niveles permitidos.

  12. Cuantificación de plaguicidas residuales en granos de maíz (Zea mays L. aplicando técnicas de evaluación residual

    Directory of Open Access Journals (Sweden)

    Dante Rojas

    2014-06-01

    Full Text Available El empleo de plaguicidas en la producción agrícola ha tomado marcada importancia para muchos sectores de la sociedad. Los productores agropecuarios necesitan realizar un tratamiento fitoterapeútico efectivo y la utilización de estos agroquímicos es una alternativa rentable. Sin embargo, la toxicidad de estas sustancias presenta un riesgo para la salud humana durante su fabricación y empleo. El objetivo del presente trabajo fue obtener información de los niveles y frecuencia de los principales residuos de pesticidas presentes en granos de maíz aplicando técnicas de evaluación multiresidual. El muestreo (basado en la Norma ISO 950:1979 fue realizado en cintas de embarque y terminales portuarias del Río Paraná y del sur de la Provincia de Buenos Aires (Argentina, dado que manejan más del 80 % de las exportaciones del país (Ingeniero White, Rosario/General San Martín/San Lorenzo, Villa Constitución y Quequén. Sobre un total de 192 muestras, 94 presentaron residuos de plaguicidas, siendo el orden de frecuencia de aparición de los mismos: fenitrotión (n = 40 > cipermetrina (n = 31 > pirimifós metil (n = 27 > deltametrina (n = 24 > clorpirifós metil (n = 23 > diclorvós (n = 18 > permetrina (n = 15 > clorpirifós etil (n = 12 > fenvalerato (n = 3 > malatión (n = 2 > endosulfán (n = 0; suma de alfa endosulfán, beta endosulfán y endosulfán sulfato. No se hallaron organoclorados. Considerando la legislación Argentina, solo 4 muestras presentaron niveles superiores a los Límites Máximos de Residuos (LMR, siendo cipermetrina el plaguicida involucrado. Sin embargo, según los LMR del Codex Alimentarius, todas las muestras presentaron niveles permitidos.

  13. Academic Globalization And Ice: Cross-Cultural Research And Transnational Education

    Directory of Open Access Journals (Sweden)

    Marta Szabo White

    2012-10-01

    Full Text Available As the Lion said to the Man, "There are many statues of men slaying lions, but if only the lions were sculptors there might be quite a different set of statues." - Aesop Commensurate with Aesop's message of the sculptor matters, so does the communicator, the language and surprisingly, business context. The evolution from the experientially-based Cultureactive to the theoretically-based ICE, from first-generation to second-generation, this paper underscores the marriage of cross-cultural research and transnational education. Both Cultureactive and ICE serve at the pleasure of Globalization, and more importantly, Academic Globalization and Transnational Education. The impetus for this paper derives from two pivotal questions: Does one's professional lens create similarities more dominant than culture; and does English evoke responses significantly different from those of one's native language. ICE emerged from Cultureactive when validity and reliability research issues became noteworthy. Known as the ABC research team, Adair, Buchan and Chen [1] and [2] capitalized upon both Hall's low context/high context communication tool and Triandis' model of subjective culture to result in the theoretical underpinnings for ICE. This conceptual reconfiguration is also grounded in the works of Trompenaars, Holtgraves, Hampden-Turner, Thomas and Kilman, Yamagishi, and Bearden, Money and Nevins [3], [11], [20], [22] and [24]. ICE implementation strategies include the employment of Myers Briggs typologies. The contribution of this paper is the celebration of the first year of ICE [InterCultural Edge], and its far-reaching ramifications. Previous research streams have underscored global similarities and differences among cultures, and a previous paper [23] established that cross-professional rather than cross-cultural differences are more paramount in assessing communication differences. This study employs Cultureactive and the LMR model, noting that business

  14. Development of basic key technologies for Gen IV SFR

    International Nuclear Information System (INIS)

    Kim, Yeongil; Kim, Sungoh; Choi, Sukgi

    2012-04-01

    The advanced concepts, for the breakeven reactor(1,200MWe) and TRU burner(600MWe), were defined to satisfy the technology goals of Generation IV nuclear systems. Based on the advanced design concepts, a conceptual design of the demonstration SFR has been developed using the available licensing technology. The conceptual core design has been developed for the TRU burner in which an initial core is fueled with less than 20wt% enriched U235, and finally transformed to a self-recycled TRU core. The passive decay heat removal circuit ensuring reactor safety even in case of loss of emergency power has been developed and minimization of a reactor vessel and simplification of reactor internals have been conducted in the conceptual design. For development of advanced technologies, control logics for various power levels and the optimal design concept of heat exchanger applicable to supercritical CO 2 Brayton cycle as an energy conversion system was developed. A novel under-sodium waveguide sensor and a prototype under-sodium inspection system have been developed for under-sodium viewing of in-vessel structures submerged in an opaque liquid sodium. The fabrication technology of fuel slugs using the advanced fuel slug casting system was developed, and U-Zr alloy fuel rods were fabricated and examined. And a HT 9 cladding tube was manufactured using the developed cladding tube fabrication technology. For development of basic technologies, the cross section adjustment code ATCROSS and the MATRA-LMR code with HCFs have been developed to reduce core design uncertainties. The SIE ASME-NH computer program to evaluate high temperature structural design for 60 years design life, and the safety analysis code MARS-LMR with thermal-hydraulic and reactivity feedback models have been developed and validated. In addition, the sodium impurity measurement and control technology, the sodium water reaction event propagation model to predict the sodium leak propagation in a steam generator, and

  15. Monitoring of radiation in the atmosphere and a food chain. Results in the Netherlands in 1993

    International Nuclear Information System (INIS)

    Aldenkamp, F.J.

    1994-12-01

    Samples of grass and milk were taken from the surroundings of nuclear installations in the Netherlands and on Dutch territory in the vicinity of such installations. An overall country milk sample from four milk factories in the Netherlands was also analyzed. This report also presents the data of the National Radioactivity Monitoring Network (LMR) in 1993. In 1993, the yearly average gross α- and gross β-activity concentration of airdust was 0.09 ±0.01 (SD 0.04) and 0.55 ±0.04 (SD 0.37) mBq.m -3 , respectively. These values were significantly higher than those of previous years. This effect is explained by a change in the procedures for sampling. The γ-spectrometric analysis was performed on airdust sampled with a high volume sampler. For 7 Be, 137 Cs and 2l0 Pb the yearly average of the activity concentrations were 3600 ±50 (SD 1300), 1.7 ±0.1 (SD 1.3) and 530 ±10 (SD 500) μBq.m -3 , respectively (well detector results). The yearly total gross α- and gross β-activity of the deposition in Bilthoven was 54.3 ±0.7 and 87.9 ±0.8 Bq.m -2 , respectively, and the deposition of 3 H was 1310 ±30 Bqm -2 . The total activity of 137 Cs in deposition was 0.80 ±0.03 Bq m -2 , of 210 Pb 105 ±2 Bq.m -2 and 2l0 Po 6.0 ±0.6 Bq.m -( α-spectroscopy). These activities are comparable to those of previous years. The yearly average concentrations of 137 Cs and 90 Sr in consumer milk from a nationwide sample mix was 0.09 ±0.02 and 0.04 ±0.01 Bq.L -l , respectively, which are about equal to that of the previous year. For the gross α-activity concentration, as measured by the aerosol monitors of the LMR, values in the range of 0.3-12.1 Bq m -3 were found, with an average value across the country of 2.6 Bq.m -3 . This value corresponds to the value of 2.4 Bq.m -3 in 1992. 20 figs., 5 tabs., 29 refs., 1 appendix

  16. Relationship between biomarkers of inflammation, oxidative stress and endothelial/microcirculatory function in successful aging versus healthy youth: a transversal study.

    Science.gov (United States)

    Bottino, Daniel Alexandre; Lopes, Flávia Gomes; de Oliveira, Francisco José; Mecenas, Anete de Souza; Clapauch, Ruth; Bouskela, Eliete

    2015-04-08

    There is a functional decline of endothelial- dependent vasodilatation in the aging process. The aims of this study were to investigate if various microcirculatory parameters could correlate to anthropometrical variables, oxidative stress and inflammatory biomarkers in successful aging and compare the results to young healthy controls. Healthy elderly women (HE, 74.0 ± 8.7 years, n = 11) and young controls (YC, 23.1 ± 3.6 years, n = 24) were evaluated through nailfold videocapillaroscopy (NVC), venous occlusion plethysmography (VOP) and laboratorial analysis. Functional capillary density (FCD) and diameters, maximum red blood cell velocity (RBCVmax) during the reactive hyperemia response/RBCVbaseline after 1 min arterial occlusion at the finger base, time to reach RBCVmax were determined by NVC, peak increment of forearm blood flow (FBF) during the reactive hyperemia response (%Hyper) and after 0.4 mg sublingual nitroglycerin (%Nitro) by VOP and lipidogram, fibrinogen, fasting and postload glucose, oxidized LDL-cholesterol (oxLDL), sICAM, sVCAM, sE-Selectin, interleukines 1 and 6 and TNF-α by laboratorial analysis. Correlations and linear multiple regression (LMR) between %Hyper, %Nitro, microcirculatory parameters, oxidative stress and inflammatory biomarkers were investigated. sVCAM, sE-Selectin and oxLDL were higher and RBCVmax/RBCVbaseline and %Hyper lower in HE, while %Nitro and FCD remained unchanged. Fibrinogen, LDL-cholesterol, oxLDL correlated negatively to %Hyper while sVCAM correlated negatively to %Hyper and RBCVmax/RBCVbaseline. Healthy aged women presented dilated capillaries with sustained perfusion and endothelial dysfunction with preserved vascular smooth muscle reactivity. Fibrinogen, LDL-cholesterol, oxidized-LDL and sVCAM correlated negatively to endothelial function but not to microcirculatory parameters. Oxidized-LDL and sVCAM could determine %Hyper through LMR. Oxidized-LDL and sVCAM might be used as endothelial

  17. CALIDAD DEL AGUA DEL REFUGIO MATA REDONDA Y LOS ARROZALES COLINDANTES, GUANACASTE, COSTA RICA

    Directory of Open Access Journals (Sweden)

    Ana Gabriela P\\u00E9rez-Castillo

    2013-01-01

    Full Text Available El objetivo de este trabajo fue evaluar si el agua de la laguna Mata Redonda (LMR y de la actividad arrocera en el sector San Lázaro (SSL de Nicoya, es apropiada para el sostenimiento de la biodiversidad y el desarrollo de la vida acuática. El análisis de la calidad fisicoquímica del agua se llevó a cabo mediante el índice de calidad de agua para el manejo de lagunas de inundación (ICA-L a partir de datos de temperatura, pH, porcentaje de saturación de oxígeno, conductividad eléctrica, demanda bioquímica de oxígeno, sólidos suspendidos, nitratos y fósforo total. El ICA-L promedio del agua que drenó de los arrozales por el canal principal, (ICA-Lp fue 42, correspondiente a la categoría “mala” (no apta para el sostenimiento de la biodiversidad de lagunas de inundación. En la LMR (ICA-Lp 80 y en la salida de la laguna (ICA-Lp 81 la calidad del agua se clasificó como “buena”. No obstante incrementos en la concentración de fósforo total y en la demanda biológica de oxígeno (DBO conducirían a un deterioro del ecosistema. El nivel de riesgo de los plaguicidas aplicados a los arrozales durante el período en estudio, bajo las condiciones del SSL, fue estimado mediante el Pesticide Index Rating Impact (PIRI; los resultados mostraron que la deltametrina, esfenvalerato, permetrina y butaclor, por su alta toxicidad y movilidad, serían los menos apropiados de aplicar. En tanto que, imidapropid, bispiribac-Na, triazofos, glifosato, acefato, clomazone y tricopyr, resultarían poco peligrosos bajo prácticas de aplicación apropiadas.

  18. Sensitivity Tests for the Unprotected Events of the Prototype Gen-IV SFR

    Energy Technology Data Exchange (ETDEWEB)

    Choi, Chiwoong; Lee, Kwilim; Jeong, Jaeho; Yu, Jin; An, Sangjun; Lee, Seung Won; Chang, Wonpyo; Ha, Kwiseok [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2014-10-15

    Unprotected Transient Over Power, (UTOP), Unprotected Loss Of Flow (ULOF), and Unprotected Loss Of Heat Sink (ULOHS) are selected as ATWS events. Among these accidents, the ULOF event shows the lowest clad temperature. However, the ULOHS event showed the highest peak clad temperature, due to the positive CRDL/RV expansion reactivity feedback and insufficient DHRS capacity. In this study, the sensitivity tests are conducted. In the case of the UTOP event, a sensitivity test for the reactivity insertion amount and rate were conducted. This analysis can give a requirement for margin of control rod stop system (CRSS). Currently, the reactivity feedback model for the PGSFR is not validated yet. However, the reactivity feedback models in the MARS-LMR are validating with various plant-based data including EBR-II SHRT. The ATWS events for the PGSFR classified in the design extended condition including UTOP, ULOF, and ULOHS are analyzed with MARS-LMR. In this study, the sensitivity tests for reactivity insertion amount and rate in the UTOP event are conducted. The reactivity insertion amount is obviously an influential parameter. The reactivity insertion amount can give a requirement for design of the CRSS, therefore, this sensitivity result is very important to the CRSS. In addition, sensitivity tests for the weighting factor in the radial expansion reactivity model are carried out. The weighting factor for a grid plate, W{sub GP}, which means contribution of feedback in the grid plate is changed for all unprotected events. The grid plate expansion is governed by a core inlet temperature. As the W{sub GP} is increased, the power in the UTOP and the ULOF is increased, however, the power in the ULOHS is decreased. The higher power during transient means lower reactivity feedback and smaller expansion. Thus, the core outlet temperature rise is dominant in the UTOP and ULOF events, however, the core inlet temperature rise is dominant in the ULOHS. Therefore, the grid plate

  19. SSC-K code user's manual

    Energy Technology Data Exchange (ETDEWEB)

    Kwon, Y M; Lee, Y B; Chang, W P; Hahn, D

    2000-07-01

    The Supper System Code of KAERI (SSC-K) is a best-estimate system code for analyzing a variety of off-normal or accidents in the heat transport system of a pool type LMR design. It is being developed at Korea Atomic Energy Research Inititution (KAERI) on the basis of SSC-L, originally developed at BNL to analyze loop-type LMR transients. SSC-K can handle both designs of loop and pool type LMRs. SSC-K contains detailed mechanistic models of transient thermal, hydraulic, neutronic, and mechanical phenomena to describe the response of the reactor core, coolant, fuel elements, and structures to accident conditions. This report provides an overview of recent model developmentsvfor the SSC-K computer code, focusing on phenomenological model descriptions for new thermal, hydraulic, neutronic, and mechnaical modules. A comprehensive description of the models for pool-type reactor is given in Chapters 2 and 3; the steady-state plant characterization, prior to the initiation of transient is described in Chapter 2 and their transient counterparts are discussed in Chapter 3. In Chapter 4, a discussion on the intermediate heat exchanger (IHX) is presented. The IHX model of SSC-K is similar to that used in the SSC-L, except for some changes required for the pool-type configuration of reactor vessel. In Chapter 5, an electromagnetic (EM) pump is modeled as a component. There are two pump choices available in SSC-K; a centrifugal pump which was originally imbedded into the SSC-L, and an EM pump which was introduced for the KALIMER design. In Chapter 6, a model of passive safety decay heat removal system(PSDRS) is discussed, which removes decay heat through the reactor and containment vessel walls to the ambient air heat sink. In Chapter 7, models for various reactivity feedback effects are discussed. Reactivity effects of importance in fast reactor include the Doppler effect, effects of sodium density changes, effects of dimensional changes in core geometry. Finally in Chapter 8

  20. Crystal structures of two transcriptional regulators from Bacillus cereus define the conserved structural features of a PadR subfamily.

    Directory of Open Access Journals (Sweden)

    Guntur Fibriansah

    Full Text Available PadR-like transcriptional regulators form a structurally-related family of proteins that control the expression of genes associated with detoxification, virulence and multi-drug resistance in bacteria. Only a few members of this family have been studied by genetic, biochemical and biophysical methods, and their structure/function relationships are still largely undefined. Here, we report the crystal structures of two PadR-like proteins from Bacillus cereus, which we named bcPadR1 and bcPadR2 (products of gene loci BC4206 and BCE3449 in strains ATCC 14579 and ATCC 10987, respectively. BC4206, together with its neighboring gene BC4207, was previously shown to become significantly upregulated in presence of the bacteriocin AS-48. DNA mobility shift assays reveal that bcPadR1 binds to a 250 bp intergenic region containing the putative BC4206-BC4207 promoter sequence, while in-situ expression of bcPadR1 decreases bacteriocin tolerance, together suggesting a role for bcPadR1 as repressor of BC4206-BC4207 transcription. The function of bcPadR2 (48% identical in sequence to bcPadR1 is unknown, but the location of its gene just upstream from genes encoding a putative antibiotic ABC efflux pump, suggests a role in regulating antibiotic resistance. The bcPadR proteins are structurally similar to LmrR, a PadR-like transcription regulator in Lactococcus lactis that controls expression of a multidrug ABC transporter via a mechanism of multidrug binding and induction. Together these proteins define a subfamily of conserved, relatively small PadR proteins characterized by a single C-terminal helix for dimerization. Unlike LmrR, bcPadR1 and bcPadR2 lack a central pore for ligand binding, making it unclear whether the transcriptional regulatory roles of bcPadR1 and bcPadR2 involve direct ligand recognition and induction.

  1. Trajectories of change and long-term outcomes in a randomised controlled trial of internet-based insomnia treatment to prevent depression.

    Science.gov (United States)

    Batterham, Philip J; Christensen, Helen; Mackinnon, Andrew J; Gosling, John A; Thorndike, Frances P; Ritterband, Lee M; Glozier, Nick; Griffiths, Kathleen M

    2017-09-01

    Insomnia treatment using an internet-based cognitive-behavioural therapy for insomnia (CBT-I) program reduces depression symptoms, anxiety symptoms and suicidal ideation. However, the speed, longevity and consistency of these effects are unknown. To test the following: whether the efficacy of online CBT-I was sustained over 18 months; how rapidly the effects of CBT-I emerged; evidence for distinct trajectories of change in depressive symptoms; and predictors of these trajectories. A randomised controlled trial compared the 6-week Sleep Healthy Using the Internet (SHUTi) CBT-I program to an attention control program. Adults ( N =1149) with clinical insomnia and subclinical depression symptoms were recruited online from the Australian community. Depression, anxiety and insomnia decreased significantly by week 4 of the intervention period and remained significantly lower relative to control for >18 months (between-group Cohen's d =0.63, 0.47, 0.55, respectively, at 18 months). Effects on suicidal ideation were only short term. Two depression trajectories were identified using growth mixture models: improving (95%) and stable/deteriorating (5%) symptoms. More severe baseline depression, younger age and limited comfort with the internet were associated with reduced odds of improvement. Online CBT-I produced rapid and long-term symptom reduction in people with subclinical depressive symptoms, although the initial effect on suicidal ideation was not sustained. P.J.B. has received grants from the National Health and Medical Research Council (NHMRC) during the conduct of the study. H.C. has received grants from the NHMRC and the Australian Research Council during the conduct of the study. L.M.R. receives research funding from the National Institutes of Health (NIH) that, in part, focuses on insomnia. F.P.T. and L.M.R. have equity ownership in BeHealth Solutions (Charlottesville, VA, USA), a company that develops and makes available products related to the research reported

  2. Lead isotopic characterization of respirable urban aerosols and related sources, Santiago-Chile

    International Nuclear Information System (INIS)

    Diaz, M; Kawashita, K; Antinao, J.L

    2001-01-01

    Santiago de Chile is located in a poorly ventilated valley at 33 o 30' latitude south at an altitude of 550m. Local climate is semi-arid with mean annual rainfall below 350mm. The atmospheric particles constitute one of the main factors of urban air pollution in the city. Morphological characterization of airborne particles of Santiago done by Scanning Electron Microscopy showed the presence of three groups of particles: crystalline. spherical and agglomerate particles. The crystalline shapes originated in geologic sources have perfectly defined crystallographic parameters. The agglomerated shapes are formed by organic material and submicrometrical mineral particles derived from combustion of fossil fuel and the spherical shapes are products of metallurgical activities. Some of them could been associated with the wear of motorcars. Samples of aerosols. sediments and leaded petrol of different distributors were collected. Aerosols were sampled in two sites of Santiago: the Movil monitoring station, at east of the city, and Parque O'Higgins monitoring station in downtown. These two monitoring stations belong to the MACAM network. Sediments of Mapocho, Maipo, San Francisco and Zanjon de la Aguada rivers and two samples from Disputada and Merceditas ores were studied. All the samples have been measured for their 206 Pb/ 204 Pb, 207 Pb/ 204 Pb and 208 Pb/ 204 Pb ratios. The experimental chemical procedures of sample dissolution and Pb separation by anion exchange chromatography were developed in the Sernageomin clean laboratory of Santiago de Chile. The isotopic measurements were made using a VG-Sector isotope ratio mass spectrometer fitted with a thermal ion source, multi Faraday collector and Daly collector of the Isotopic Geology Laboratory in the Universidade Federal de Rio Grande do Sul, Brazil. The measurements were corrected using NBS 981 and 982 standards. Isotopic results plotted in a 208 Pb/ 204 Pb versus 206 Pb/ 204 Pb diagram and in a 207 Pb/ 204 Pb versus

  3. Comparison of bacillary index on slit skin smear with bacillary index of granuloma in leprosy and its relevance to present therapeutic regimens

    Directory of Open Access Journals (Sweden)

    Sendhil M Kumaran

    2015-01-01

    Full Text Available Background: As the world moves toward elimination of leprosy, persistence of infective cases in endemic pockets remains a significant problem. The use of clinical criteria to decide the paucibacillary (PB versus multibacillary (MB regimens has greatly simplified therapy at the field setting. However, a small but significant risk of under-treatment of so-called "PB" cases which actually have significant bacillary load exists. This study was undertaken to assess this risk and compare two methods of assessment of bacillary load, namely bacillary index on slit skin smear (BIS versus bacillary index of granuloma (BIG. Aims: To compare BIS with BIG on skin biopsy in consecutive untreated cases of leprosy. Materials and Methods: This prospective study was conducted over a period of 12 months, wherein new untreated patients with leprosy were consecutively recruited. After a thorough clinical examination, each patient underwent slit skin smear (SSS where the BIS was calculated. The same patient also underwent a skin biopsy from a clinical lesion where, the BIG was calculated. SSS and skin biopsy for BIS and BIG respectively were repeated for all patients at the end of therapy for comparison. All patients received therapy according to World Health Organization-Multidrug Therapy Guidelines. Results: The BIG was positive in all cases where the BIS was positive. Significantly, BIG was positive in three cases of borderline tuberculoid leprosy with <5 lesions who received PB regimen, whereas the BIS was negative in all three cases. Conclusion: This study suggests that BIG may be a better indicator of the true bacillary load in leprosy as compared to BIS. Its role in management is significant, at least in tertiary care centers to prevent "under-treatment" of so called PB cases, which may actually warrant MB regimens.

  4. MENDL2 and IEAF-2001 nuclide production yields data bases verification at intermediate energies.

    Energy Technology Data Exchange (ETDEWEB)

    Titarenko, Y. E. (Yury E.); Batyaev, V. F. (Vyacheslav F.); Zhivun, V. M. (Valery M.); Mulambetov, R. D. (Ruslan D.); Mulambetova, S. V.; Zaitsev, S. L.; Lipatov, K. A.; Mashnik, S. G. (Stepan G.); Prael, R. E. (Richard E.)

    2004-01-01

    The work presents the results of computer simulation of two experiments which aim was measuring the threshold activation reaction rates in {sup 12}C, {sup 19}F, {sup 27}Al, {sup 59}Co, {sup 63}Cu, {sup 65}Cu, {sup 64}Zn, {sup 93}Nb, {sup 115}In, {sup 169}Tm, {sup 181}Ta, {sup 197}Au, and {sup 209}Bi thin samples placed inside and outside the 0.8-GeV proton-irradiated 4-cm thick W target and 92-cm thick W-Na composite target of 15-cm diameter both. In total, more than 1000 values of activation reaction were determined in the both experiments. The measured reaction rates were compared with the rates simulated by the LAHET code with the use of several nuclear databases for the respective excitation functions, namely, MENDL2/2P for neutron/proton cross sections up to 100 MeV, and recently developed IEAF-2001 that provides neutron cross sections up to 150 MeV. The comparison between the simulation-to-experiment agreements obtained via the MENDL2 and IEAF-2001 is presented. The agreement between simulation and experiment has been found generally satisfactory for both of the databases. The high-energy threshold excitation functions to be used in the activation-based unfolding of neutron spectra inside the Accelerator Driven Systems (ADS), particularly with Na-cooled W targets, can be inferred from the results.

  5. Summary report of the 7th reduced-moderation water reactor workshop

    International Nuclear Information System (INIS)

    Akie, Hiroshi; Nabeshima, Kunihiko; Uchikawa, Sadao

    2005-08-01

    As a research on the future innovative water reactor, the development of Reduced-Moderation Water Reactors (RMWRs) has been performed in Japan Atomic Energy Research Institute (JAERI). The workshop on RMWRs is aiming at information exchange between JAERI and other organizations such as universities, laboratories, utilities and vendors, and has been held every year since 1998. The 7th workshop was held on March 5, 2004 under the joint auspices of JAERI and North Kanto branch of Atomic Energy Society of Japan. The program of the workshop was composed of 5 lectures and an overall discussion time. The workshop started with the lecture by JAERI on the status and future program of PMWR research and development, followed by the two presentations by JAERI and Japan Nuclear Cycle Development Institute, respectively, on the investigation and evaluation of water cooled reactor in Feasibility Study Program on Commercialized Fast Reactor Systems. The lectures were also made on the Japan's nuclear fuel cycle and scenarios for RMWRs deployment by JAERI, and on the next generation reactor development activity by Hitachi, Ltd. The main subjects of the overall discussion time were Na cooled fast reactor, deployment effects of RMWRs and the future plan of the RMWR research and development. This report includes the original papers presented at the workshop and summaries of the questions and answers for each lecture, as well as of the discussion time. In addition in the Appendices, there are included presentation handouts of each lecture, program of the workshop and the participants list. (author)

  6. Investigation of molten salt fast reactor

    International Nuclear Information System (INIS)

    Kubota, Kenichi; Konomura, Mamoru

    2002-01-01

    On survey research for practicability strategy of fast reactor (FR) (phase 1), to extract future practicability image candidates of FR from wide options, in addition to their survey and investigation objects of not only solid fuel reactors of conventional research object but also molten salt reactor as a flowing fuel reactor, investigation on concept of molten salt FR plant was carried out. As a part of the first step of the survey research for practicability strategy, a basic concept on plant centered at nuclear reactor facility using chloride molten salt reactor capable of carrying out U-Pu cycle was examined, to perform a base construction to evaluate economical potential for a practical FBR. As a result, a result could be obtained that because of inferior fuel inventory and heat transmission to those in Na cooling reactor in present knowledge, mass of reactor vessel and intermediate heat exchanger were to widely increased to expect reduction of power generation unit price even on considering cheapness of its fuel cycle cost. Therefore, at present step further investigation on concept design of the chloride molten salt reactor plant system is too early in time, and it is at a condition where basic and elementary researches aiming at upgrading of economical efficiency such as wide reduction of fuel inventory, a measure expectable for remarkable rationalization effect of reprocessing system integrating a reactor to a processing facility, and so on. (G.K.)

  7. Development of an innovative PWR for low cost fuel recycle and waste reduction

    International Nuclear Information System (INIS)

    Kanagawa, Takashi; Onoue, Masaaki

    2001-01-01

    In order to bear long-term and stable energy supply, it is important for nuclear power generation to realize establishment of energy security controlling dependence on natural resources and reduction of long-life radioactive wastes such as minor actinide elements (MA) and so on. For this, establishment of fast breeder reproducible on its fuel and of fuel recycling is essential and construction of the fuel recycling capable of repeatedly recycling of plutonium (Pu) and MA with low cost is required. Here were proposed a fuel recycling system combining recycling type PWR with advanced recycling system under development for Na cooling fast breeder reactor as a candidate filling such conditions, to show its characteristics and effects after its introduction. By this system, some facilities to realize flexible and low cost fuel recycling, to reduce longer-life radioactive wastes due to recycling burning of Pu and MA, and to realize an electric power supplying system independent on natural resources due to fuel breeding feature, were shown. (G.K.)

  8. Design and analysis of an axial bypass compressor blade in a supercritical CO2 gas turbine

    International Nuclear Information System (INIS)

    Ishizuka, Takao; Muto, Yasushi; Aritomi, Masanori; Tsuzuki, Nobuyoshi; Kikura, Hiroshige

    2010-01-01

    A supercritical carbon dioxide gas turbine can generate power at a high cycle thermal efficiency, even at modest temperatures of 500-550degC. Consequently, a more reliable and economically advantageous power generation system is achieved by coupling with a Na-cooled fast reactor. This paper mainly describes the bypass compressor (a key component) design and thermal hydraulic analysis using CFD (with FLUENT code). Fluid conditions of the bypass compressor are determined by the cycle calculation of this system. Aerodynamic design was conducted using the loss model described by Cohen et al., which enables the use of several stages while providing total adiabatic efficiency of 21 and 87%, respectively. Blade shapes were prepared based on flow angles and chord length obtained for the aerodynamic design. In the CFD analysis, the calculated value of the mass flow rate for each stage was adjusted to that of the design. The value of the design outlet pressure was reached at stage No. 16, which is fewer stages than that for design, No. 21. The difference between these stage numbers is attributed to the three-dimensional effect in design. If these effects are eliminated, then the design calculation yields an almost identical number of stages. Therefore, it was concluded that the existing design method is applicable to the supercritical CO 2 bypass compressor. Furthermore, CFD analysis appears to be an effective aerodynamic design tool, but these conclusions should be verified experimentally. (author)

  9. Adaptability of Brayton cycle conversion systems to fast, epithermal and thermal spectrum space nuclear reactors

    International Nuclear Information System (INIS)

    Tilliette, Z.P.

    1988-01-01

    The two French Government Agencies C.N.E.S. (Centre National d'Etudes Spatiales) and C.E.A. (Commissariat a l'Energie Atomique) are carrying out joint preliminary studies on space nuclear power systems for future ARIANE 5 launch vehicle applications. The Brayton cycle is the reference conversion system, whether the heat source is a liquid metal-cooled (NaK, Na or Li) reactor or a gas-cooled direct cycle concept. The search for an adequate utilization of this energy conversion means has prompted additional evaluations featuring the definition of satisfactory cycle conditions for these various kinds of reactor concepts. In addition to firstly studied fast and epithermal spectrum ones, thermal spectrum reactors can offer an opportunity of bringing out some distinctive features of the Brayton cycle, in particular for the temperature conditioning of the efficient metal hydrides (ZrH, Li/sub 7/H) moderators. One of the purposes of the paper is to confirm the potential of long lifetime ZrH moderated reactors associated with a gas cycle and to assess the thermodynamical consequences for both Nak(Na)-cooled or gas-cooled nuclear heat sources. This investigation is complemented by the definition of appropriate reactor arrangements which could be presented on a further occasion

  10. Development of inflatable seals for the rotatable plugs of sodium cooled fast breeder reactors. Pt. II. R and D necessities and development across the world. A review

    International Nuclear Information System (INIS)

    Sinha, Nilay K.; Raj, Baldev

    2013-01-01

    Identification of development areas and their implementation for rotatable plug (RP) inflatable seals of Na cooled, 500 Mw (e) Prototype Fast Breeder Reactor (PFBR) and 40 MW (t) Fast Breeder Test Reactor (FBTR) are described, largely based on a late 1990s survey of cover gas seal development (1950s - early 1990s) which defined a set of shortlisted design options and developmental strategy to minimize effort, cost and time. Comparative study of top shield sealing and evolving FBR designs suggest suitability of inflatable seal as primary barrier in RPs. International experience identified choice and qualification of seal elastomer under synergistic degrading environment of reactor as the prime element of development. The low pressure, non-reinforced, unbeaded, PFBR inflatable seal (made of 50/50 blend of Viton registered GBL 200S/600S) developed for 10 y life provides a unification scheme for nuclear elastomeric sealing based on 5 peroxide cured fluoroelastomer blend formulations, 1 finite element analysis approach, 1 Teflon-like plasma coating technique and 2 manufacturing processes promising significant gains in standardization, economy and safety. Uniqueness was ab initio development in the absence of established industry or readymade supply. R and D necessities for inflatable seals and their development across the world are given closer look in Part II of the review in continuation of Part I. (orig.)

  11. Analysis of the laser photoelectron spectrum of CH-2

    International Nuclear Information System (INIS)

    Bunker, P.R.; Sears, T.J.

    1985-01-01

    We have simulated the photoelectron spectrum of CH - 2 using the model described previously [Sears and Bunker, J. Chem. Phys. 79, 5265 (1983)]. The optimization of the fit of the simulated spectrum to the recently observed spectrum of Lineberger and co-workers [J. Chem. Phys. 81, 1048 (1984) and preceding paper] has enabled us to determine the rotation-bending energy levels of triplet CH 2 over an energy range of more than 1 eV. It has also enabled us to determine that the rotational temperature of the CH - 2 in the experiment is 220 K and that, for v 2 = 1, the vibrational temperature is 680 K. For CH - 2 we determine that a/sub e/ = 103 0 and that ν 2 = 1230 cm -1 . The singlet--triplet splitting in methylene is determined to be 3150 +- 30 cm -1 (0.3905 +- 0.004 eV, 9.01 +- 0.09 kcal/mol) from the photoelectron spectrum, in excellent agreement with the more accurate value previously obtained from LMR spectroscopy [McKellar et al., J. Chem. Phys. 79, 5251 (1983)] of 3165 +- 20 cm -1 (0.3924 +- 0.0025 eV, 9.05 +- 0.06 kcal/mol), and the electron affinity of triplet CH 2 is determined to be 0.652 +- 0.006 eV

  12. Studies on the dose distribution and treatment technique of high energy electron beams

    International Nuclear Information System (INIS)

    Lee, D.H.; Chu, S.S.

    1978-01-01

    Some important properties of high energy electron beams from the linear accelerator, LMR-13, installed in the Yonsei Cancer Center were studied. The results of experimental studies on the problems associated with the 8, 10, and 12 MeV electron beam therapy were as followings; The ionization type dosemeters calibrated by 90 Sr standard source were suitable to the measurements of the outputs and the obsorbed doses in accuracy point of view, and dose measurements using ionization chambers were difficult when measuring doses in small field size and the regions of rapid fall off. The electron energies were measured precisely with an energy spectrometer, and the practical electron energy was calculated within 5% error in the maximum range of the high energy electron beam in water. The correcting factors of perturbated dose distributions owing to radiation field, energy, and materials of the treatment cone were checked and described systematically and thus the variation of dose distributions due to the non-homogeneities of tissues and slopping skin surfaces were completely compensated. The electron beams were adequately diffused using the scatterers, and minimized the bremsstrahlung, irradiation field size, and materials of scatterers. Thus, the therapeutic capacity with the limited electron energy could be extended by improving the dose distributions. (author)

  13. Dominant seismic sloshing mode in a pool-type reactor tank

    International Nuclear Information System (INIS)

    Ma, D.C.; Gvildys, J.; Chang, Y.W.

    1987-01-01

    Large-diameter LMR (Liquid Metal Reactor) tanks contain a large volume of sodium coolant and many in-tank components. A reactor tank of 70 ft. in diameter contains 5,000,000 of sodium coolant. Under seismic events, the sloshing wave may easily reach several feet. If sufficient free board is not provided to accommodate the wave height, several safety problems may occur such as damage to tank cover due to sloshing impact and thermal shocks due to hot sodium, etc. Therefore, the sloshing response should be properly considered in the reactor design. This paper presents the results of the sloshing analysis of a pool-type reactor tank with a diameter of 39 ft. The results of the fluid-structure interaction analysis are presented in a companion paper. Five sections are contained in this paper. The reactor system and mathematical model are described. The dominant sloshing mode and the calculated maximum wave heights are presented. The sloshing pressures and sloshing forces acting on the submerged components are described. The conclusions are given

  14. Functioning mechanism of AlF3 coating on the Li- and Mn-rich cathode materials

    Energy Technology Data Exchange (ETDEWEB)

    Zheng, Jianming; Gu, Meng; Xiao, Jie; Polzin, Bryant; Yan, Pengfei; Chen, Xilin; Wang, Chong M.; Zhang, Jiguang

    2014-11-25

    Li- and Mn-rich (LMR) material is a very promising cathode for lithium ion batteries because of their high theoretical energy density (~900 Wh kg-1) and low cost. However, their poor long-term cycling stability, voltage fade, and low rate capability are significant barriers hindered their practical applications. Surface coating, e.g. AlF3 coating, can significantly improve the capacity retention and enhance the rate capability. However, the fundamental mechanism of this improvement and the microstructural evolution related to the surface coating is still not well understood. Here, we report systematic studies of the microstructural changes of uncoated and AlF3-coated materials before and after cycling using aberration-corrected scanning/transmission electron microscopy and electron energy loss spectroscopy. The results reveal that surface coating can reduce the oxidation of electrolyte at high voltage, thus suppressing the accumulation of SEI layer on electrode particle surface. Surface coating also enhances structural stability of the surface region (especially the electrochemically transformed spinel-like phase), and protects the electrode from severe etching/corrosion by the acidic species in the electrolyte, therefore limiting the degradation of the material. Moreover, surface coating can alleviate the undesirable voltage fade by minimize layered-spinel phase transformation in the bulk region of the materials. These fundamental findings may also be widely applied to explain the functioning mechanism of other surface coatings used in a broad range of electrode materials.

  15. Ni And Co Segregations On Selective Surface Facets And Rational Design Of Layered Lithium Transition-metal Oxide Cathodes

    Energy Technology Data Exchange (ETDEWEB)

    Yan, Pengfei; Zheng, Jianming; Zheng, Jiaxin; Wang, Zhiguo; Teng, Gaofeng; Kuppan, Saravanan; Xiao, Jie; Chen, Guoying; Zhang, Jiguang; Wang, Chong M.; Pan, Feng

    2016-05-05

    The chemical processes occurring on the surface of cathode materials during battery cycling play a crucial role in determining battery’s performance. However, our understanding on such surface chemistry is far from clear due to the complexity of redox chemistry during battery charge/discharge. In this work, through intensive aberration corrected STEM investigation on eight layered oxide cathode materials, we report two important findings on the pristine oxides. First, Ni and Co show strong plane selectivity when building up their respective surface segregation layers (SSL). Specifically, Ni-SSL is exclusively developed on (200)m facet in Li-Mn-rich oxides (monoclinic C2/m symmetry) and (012)h facet in Mn-Ni equally rich oxides (hexagonal R-3m symmetry), while Co-SSL has a strong preference to (20-2)m plane with minimal Co-SSL also developed on some other planes in LMR cathodes. Structurally, Ni-SSLs tend to form spinel-like lattice while Co-SSLs are in a rock-salt-like structure. Secondly, by increasing Ni concentration in these layered oxides, Ni and Co SSLs can be suppressed and even eliminated. Our findings indicate that Ni and Co SSLs are tunable through controlling particle morphology and oxide composition, which opens up a new way for future rational design and synthesis of cathode materials.

  16. Probing the Degradation Mechanism of Li2MnO3 Cathode for Li-Ion Batteries

    Energy Technology Data Exchange (ETDEWEB)

    Yan, Pengfei; Xiao, Liang; Zheng, Jianming; Zhou, Yungang; He, Yang; Zu, Xiaotao; Mao, Scott X.; Xiao, Jie; Gao, Fei; Zhang, Jiguang; Wang, Chong M.

    2015-02-10

    Capacity and voltage fading of Li2MnO3 is a major challenge for the application of this category of material, which is believed to be associated with the structural and chemical evolution of the materials. This paper reports the detailed structural and chemical evolutions of Li2MnO3 cathode captured by using aberration corrected scanning/transmission electron microscope (S/TEM) after certain numbers of charge-discharge cycling of the batteries. It is found that structural degradation occurs from the very first cycle and is spatially initiated from the surface of the particle and propagates towards the inner bulk as cyclic number increase, featuring the formation of the surface phase transformation layer and gradual thickening of this layer. The structure degradation is found to follow a sequential phase transformation: monoclinic C2/m → tetragonal I41 → cubic spinel, which is consistently supported by the decreasing lattice formation energy based on DFT calculations. For the first time, high spatial resolution quantitative chemical analysis reveals that 20% oxygen in the surface phase transformation layer is removed and such newly developed surface layer is a Li-depleted layer with reduced Mn cations. This work demonstrates a direct correlation between structural degradation and cell’s electrochemical degradation, which enhances our understanding of Li-Mn-rich (LMR) cathode materials.

  17. Functioning Mechanism of AlF 3 Coating on the Li- and Mn-Rich Cathode Materials

    Energy Technology Data Exchange (ETDEWEB)

    Zheng, Jianming; Gu, Meng; Xiao, Jie; Polzin, Bryant J.; Yan, Pengfei; Chen, Xilin; Wang, Chongmin; Zhang, Ji-Guang

    2014-11-25

    We report systematic studies of the microstructural changes of uncoated and AlF3-coated Li-rich Mn-rich (LMR) cathode materials (Li1.2Ni0.15Co0.10Mn0.55O2) before and after cycling using a combination of aberration-corrected scanning/transmission electron microscopy (S/TEM) and electron energy loss spectroscopy (EELS). TEM coupled with EELS provides detailed information about the crystallographic and electronic structure changes that occur after cycling, thus revealing the fundamental improvement mechanism of surface coating. The results demonstrate that the surface coating reduces oxidation of the electrolyte at high voltage, suppressing the accumulation of a thick solid electrolyte interface (SEI) layer on electrode particle surface. Surface coating significantly enhances the stability of the surface structure and protects the electrode from severe etching/corrosion by the acidic species in the electrolyte, reducing the formation of etched surfaces and corrosion pits. Moreover, surface coating alleviates the undesirable voltage fade by mitigating layered to spinel-like phase transformation in the bulk region of the material. These fundamental findings may also be widely applied to explain the functioning mechanisms of other surface coatings used in a broad range of electrode materials.

  18. Global warming---The role for nuclear power

    International Nuclear Information System (INIS)

    Jones, J.E. Jr.; Fulkerson, W.

    1989-01-01

    Nuclear power is currently making an important contribution to our energy requirements. It provides 17% of the world's electricity today --- almost 20% in the US. Reducing the emissions of carbon dioxide over the next 30 to 50 years sufficiently to address the issue of global warming can only be accomplished by a combination of much improved energy efficiency, substantial growth in use of nuclear power, and substantial growth in use of renewable energy. This paper discusses new initiatives in the major nuclear technologies (LWR, HTGR, LMR) which are emerging from a fundamental reexamination of nuclear power in response to the challenges and opportunities in the 21st century. To fulfill its role, nuclear power must gain worldwide acceptance as a viable energy option. The use of modern technology and ''passive'' safety features in next-generation nuclear power plants offers the potential to simplify their design and operation, enhance their safety, and reduce the cost of electricity. With such improvements, we believe nuclear power can regain public confidence and make a significant contribution to our energy future. 24 refs., 2 figs., 1 tab

  19. Academic Globalization: Cultureactive to Ice- the Cross-Cultural, Crossdisciplinary and Cross-Epistemological Transformation

    Directory of Open Access Journals (Sweden)

    Marta Szabo White

    2010-12-01

    Full Text Available Commensurate with the concept of Academic Globalization, coupled with the foray of Globalization, this paper underscores the cross-cultural, cross-disciplinary and cross-epistemological transformation from the first-generation Cultureactive to the second-generation InterCultural Edge [ICE]. The former is embedded in the experiential works of cross-cultural consultant. Richard Lewis and the latter is grounded in established theoretical frameworks. Both serve to underscore the impact of the Globalization Phenomenon, as manifested in and enabled by the acceleration of academic and practitioner cross-cultural activities. The contribution of this paper is the celebration of the longawaited arrival of ICE [InterCultural Edge]. While previous research streams have underscored global similarities and differences among cultures, a previous paper [19] established that cross-professional rather than cross-cultural differences are more paramount. Employing Cultureactive and the LMR framework, it was noted that business versus non-business predisposition had a more direct impact on one's individual cultural profile than did nationality. Regardless of culture, persons involved in business are characterized primarily by linear-active modes of communication, and persons involved in non-business activities typically employ more multiactive/hybrid and less linear modes of communication. The pivotal question is this: Now that we have a new and improved tool, are we in a better position to assess and predict leadership, negotiating styles, individual behaviors, etc., which are central to academic globalization and preparing global business leaders?

  20. Development of severe accident evaluation technology (level 2 PSA) for sodium-cooled fast reactors. (5) Identification of dominant factors in ex-vessel accident sequences

    International Nuclear Information System (INIS)

    Ohno, Shuji; Seino, Hiroshi; Miyahara, Shinya

    2009-01-01

    The evaluation of accident progression outside of a reactor vessel (ex-vessel) and subsequent transfer behavior of radioactive materials is of great importance from the viewpoint of Level 2 PSA. Hence typical ex-vessel accident sequences in the JAEA Sodium-cooled Fast Reactor are qualitatively discussed in this paper and dominant behaviors or factors in the sequences are investigated through parametric calculations using the CONTAIN/LMR code. Scenarios to be focused on are, 1) sodium vapor leakage from the reactor vessel and 2) sodium-concrete reaction, which are both to be considered in the accident category of LOHRS (loss of heat removal system) and might be followed by an early containment failure due to the thermal effect of sodium combustion and hydrogen burning respectively. The calculated results clarify that the sodium vapor leak rate and the scale of sodium-concrete reaction are the important factors to dominate the ex-vessel accident progression. In addition to the understandings of the dominant factors, the analyzed results also provide the specific information such as pressure loading value to the containment and the timing of pressurization, which is indispensable as technical base in Level 2 PSA for developing event trees and for quantifying the accident consequences. (author)

  1. Development of UO2/PuO2 dispersed in uranium matrix CERMET fuel system for fast reactors

    Science.gov (United States)

    Sinha, V. P.; Hegde, P. V.; Prasad, G. J.; Pal, S.; Mishra, G. P.

    2012-08-01

    CERMET fuel with either PuO2 or enriched UO2 dispersed in uranium metal matrix has a strong potential of becoming a fuel for the liquid metal cooled fast breeder reactors (LMR's). In fact it may act as a bridge between the advantages and disadvantages associated with the two extremes of fuel systems (i.e. ceramic fuel and metallic fuel) for fast reactors. At Bhabha Atomic Research Centre (BARC), R & D efforts are on to develop this CERMET fuel by powder metallurgy route. This paper describes the development of flow sheet for preparation of UO2 dispersed in uranium metal matrix pellets for three different compositions i.e. U-20 wt%UO2, U-25 wt%UO2 and U-30 wt%UO2. It was found that the sintered pellets were having excellent integrity and their linear mass was higher than that of carbide fuel pellets used in Fast Breeder Test Reactor programme (FBTR) in India. The pellets were characterized by X-ray diffraction (XRD) technique for phase analysis and lattice parameter determination. The optical microstructures were developed and reported for all the three different U-UO2 compositions.

  2. Review of the critical heat flux correlations for liquid metals

    International Nuclear Information System (INIS)

    Lee, Yong Bum; Han, H. D.; Chang, W. P.; Kwon, Y. M.

    1999-09-01

    The CHF phenomenon in the two-phase convective flows has been an important issue in the fields of design and safety analysis of light water reactor (LWR) as well as sodium cooled liquid metal reactor (LMR). Especially in the LWR application, many physical aspects of the CHF phenomenon are understood and reliable correlations and mechanistic models to predict the CHF condition have been proposed over the past three decades. Most of the existing CHF correlations have been developed for light water reactor core applications. Compared with water, liquid metals show a divergent picture of boiling pattern. This can be attributed to the consequence that special CHF conditions obtained from investigations with water cannot be applied to liquid metals. Numerous liquid metal boiling heat transfer and two-phase flow studies have put emphasis on development of models and understanding of the mechanism for improving the CHF predictions. Thus far, no overall analytical solution method has been obtained and the reliable prediction method has remained empirical. The principal objectives of the present report are to review the state of the art in connection with liquid metal critical heat flux under low pressure and low flow conditions and to discuss the basic mechanisms. (author)

  3. Analysis of ZPPR experiments supporting production of 60Co in FFTF

    International Nuclear Information System (INIS)

    Wootan, D.W.; Carter, L.L.; Rawlins, J.A.; Schaefer, R.W.; Maddison, D.W.

    1987-01-01

    An effort to expand the irradiation mission of the Fast Flux Test Facility (FFTF) beyond testing fuels and materials for the liquid-metal reactor (LMR) program included a study of the feasibility of producing commercial quantities of 60 Co. The 60 Co would be produced by neutron capture in assemblies containing an array of natural cobalt pins and hydrogen-bearing moderator pins located at the periphery of the FFTF core. Adding hydrogenous material to the assemblies enhances 60 Co production by slowing neutrons into energy ranges where the 59 Co capture cross section is higher. Some of the moderated neutrons leak from the moderated region to adjacent fuel regions, increasing local fission rates. In order to validate calculated fission rates and establish calculational biases and uncertainties, experiments were conducted in the zero-power plutonium reactor (ZPPR) to measure fission rates in fuel regions adjacent to a mock-up of a cobalt production assembly. The ZPPR experiment and analyses provided the technical basis for irradiating hydride-moderated assemblies in FFTF and a cobalt production cycle of FFTF with generally good agreement between measured and predicted reactivity worth and outlet temperatures in adjacent fuel assemblies. This experiment provides a benchmark configuration of a hydrogenous assembly in a fast reactor, with emphasis on the effect of the hydrogen on adjacent fuel. It is anticipated there will be other applications of hydride moderation in the development of future isotope production missions in FFTF

  4. Validation of the metal fuel version of the SAS4A accident analysis code

    International Nuclear Information System (INIS)

    Tentner, A.M.

    1991-01-01

    This paper describes recent work directed towards the validation of the metal fuel version of the SAS4A accident analysis code. The SAS4A code system has been developed at Argonne National Laboratory for the simulation of hypothetical severe accidents in Liquid Metal-Cooled Reactors (LMR), designed to operate in a fast neutron spectrum. SAS4A was initially developed for the analysis of oxide-fueled liquid metal-cooled reactors and has played an important role in the simulation and assessment of the energetics potential for postulated severe accidents in these reactors. Due to the current interest in the metal-fueled liquid metal-cooled reactors, a metal fuel version of the SAS4A accident analysis code is being developed in the Integral Fast Reactor program at Argonne. During such postulated accident scenarios as the unprotected (i.e. without scram) loss-of-flow and transient overpower events, a large number of interrelated physical phenomena occur during a relatively short time. These phenomena include transient heat transfer and hydrodynamic events, coolant boiling, and fuel and cladding melting and relocation. Due to strong neutronic feedbacks these events can significantly influence the reactor power history in the accident progression. The paper presents the results of a recent SAS4A simulation of the M7 TREAT experiment. 6 refs., 5 figs

  5. On the evaluation of elastic follow-up of a high temperature discontinuous structure

    International Nuclear Information System (INIS)

    Lee, J. M.; Kim, J. B.; Lee, H. Y.; Lee, J. H.

    2003-01-01

    While high temperature structures of LMR experience inelastic deformation such as plasticity and creep due to high temperature operating temperature of 530∼550 .deg. C, geometric nonlinear structures may undergo elastic follow-up behavior due to the interaction between stiff region and weak region. Thus, careful consideration should be given to the design and analysis of high temperature geometric nonlinear structure. In this study, the elastic follow-up behavior of geometric nonlinear structure has been investigated and the current status of design method implemented in the ASME-NH, Japanese BDS, French RCC-MR, and UK R-5 codes to consider elastic follow-up behavior has been reviewed. It has been shown that the ratio of the stiff region and the weak region and the type of loading affect the elastic follow-up behavior greatly from the detailed inelastic analyses of two bar model and L-shaped structure subjected to various loading situation. The applicability and the conservatism of simplified analysis methods implemented among various design codes need to be studied further

  6. Quadrupole moments measured by nuclear orientation

    International Nuclear Information System (INIS)

    Bouchta, H.

    1985-01-01

    Quadrupole interactions between the nuclei and solids have been studied with the low temperature nuclear orientation technique. The first series of measurements have been effected on the orientation of 195H g m and 197 Hg m , long lived daughter states in the 195 Au and 197 Au decay. The lifetimes of these states are of the same order as the spin-lattice relaxation time. The reorientation of the intermediate states has been taken into account extending the dipole relaxation mechanism to non-equidistant relaxing substates. The experimental nuclear quadrupole moments, thus deduced are slightly different from theoretical estimations. A new high precision method accessible to levels with 100 ns to 1 m lifetimes, the level mixing resonance on oriented nuclei (LMR/ON) has been elaborated in collaboration with LEUVEN university (Belgium). In this technique the nucleus is subject to a non colinear electric plus magnetic combined interaction. The quadrupole interaction of Ag[7/2, = 40 s] isomer with the electric field gradient in zinc has been established to better than 1% observing its level mixing resonances; and also the ratio of electric field gradients of silver in zinc to cadmium. The electric quadrupole moments of 106 Ag m , 107 Ag m and 109 Ag m have been established combining the level mixing resonances with classical low temperature quadrupole alignment measurements. The experimental values are in good agreement with theoretical calculations based on a semi-microscopical model using Yukawa potential [fr

  7. Rapid Purification and Procoagulant and Platelet Aggregating Activities of Rhombeobin: A Thrombin-Like/Gyroxin-Like Enzyme from Lachesis muta rhombeata Snake Venom

    Science.gov (United States)

    Torres-Huaco, Frank Denis; Werneck, Cláudio C.; Vicente, Cristina Pontes; Vassequi-Silva, Talita; Nery-Diez, Ana Cláudia Coelho; Mendes, Camila B.; Antunes, Edson; Marangoni, Sérgio; Damico, Daniela C. S.

    2013-01-01

    We report a rapid purification method using one-step chromatography of SVSP Rhombeobin (LMR-47) from Lachesis muta rhombeata venom and its procoagulant activities and effects on platelet aggregation. The venom was fractionated by a single chromatographic step in RP-HPLC on a C8 Discovery BIO Wide Pore, showing high degree of molecular homogeneity with molecular mass of 47035.49 Da. Rhombeobin showed amidolytic activity upon BAρNA, with a broad optimum pH (7–10) and was stable in solution up to 60°C. The amidolytic activity was inhibited by serine proteinase inhibitors and reducing agents, but not chelating agents. Rhombeobin showed high coagulant activity on mice plasma and bovine fibrinogen. The deduced amino acid sequence of Rhombeobin showed homology with other SVSPs, especially with LM-TL (L. m. muta) and Gyroxin (C. d. terrificus). Rhombeobin acts, in vitro, as a strong procoagulant enzyme on mice citrated plasma, shortening the APTT and PT tests in adose-dependent manner. The protein showed, “ex vivo”, a strong defibrinogenating effect with 1 µg/animal. Lower doses activated the intrinsic and extrinsic coagulation pathways and impaired the platelet aggregation induced by ADP. Thus, this is the first report of a venom component that produces a venom-induced consumptive coagulopathy (VICC). PMID:24058917

  8. Breached fuel pin contamination from Run Beyond Cladding Breach (RBCB) tests in EBR-II

    International Nuclear Information System (INIS)

    Colburn, R.P.; Strain, R.V.; Lambert, J.D.B.; Ukai, S.; Shibahara, I.

    1988-09-01

    Studies indicate there may be a large economic incentive to permit some continued reactor operation with breached fuel pin cladding. A major concern for this type of operation is the potential spread of contamination in the primary coolant system and its impact on plant maintenance. A study of the release and transport of contamination from naturally breached mixed oxide Liquid Metal Reactor (LMR) fuel pins was performed as part of the US Department of Energy/Power Reactor and Nuclear Fuel Development Corporation (DOE/PNC) Run Beyond Cladding Breach (RBCB) Program at EBR-II. The measurements were made using the Breached Fuel Test Facility (BFTF) at EBR-II with replaceable deposition samplers located approximately 1.5 meters from the breached fuel test assemblies. The effluent from the test assemblies containing the breached fuel pins was routed up through the samplers and past dedicated instrumentation in the BFTF before mixing with the main coolant flow stream. This paper discusses the first three contamination tests in this program. 2 refs., 5 figs., 2 tabs

  9. Korea-NEA Research Project for the Construction of Worldwide Reactor Physics Experiments Database and the Foundation of Sustainable Collaboration Environment

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Sang Ji; Jang, Jin Wook

    2004-07-15

    740 documents on PWR, LMR and VHTR related critical experiments are procured by participating in the IRPhE Project under the auspices of the OECD/NEA Data Bank. These documents were reviewed in detail for classification, measurement technique study. Among the database, the SNEAK-7 critical benchmarks were selected for further analysis by modern analysis tool, which requires minimum amount of correction for the raw calculated value. The SNEAK-7A and 7B were selected due to their spectrum similarity with KALIMER-600. Core eigenvalue, spectral indices, central material worths were evaluated and compared with the measurement. JEF-2.2 predict core eigenvalues pretty well, while the conversion ratio was underestimated by about 3%. ENDF/B-VI overestimates core eigenvalue by about 500 pcm while the conversion ratio was underestimated by about 4%. Through the sensitivity analysis of core eigenvalue to the partial cross section, a problem in {sup 238}U capture cross section was identified and a necessity arose to reduce the measurement uncertainty of {sup 239}Pu due to the high high sensitivity of core eigenvalue to {sup 239}Pu fission cross section.

  10. Containment Performance Evaluation of a Sodium Fire Event Due to Air Ingress into the Cover Gas Region of the Reactor Vessel in the PGSFR

    International Nuclear Information System (INIS)

    Ahn, Sang June; Chang, Won-Pyo; Kang, Seok Hun; Choi, Chi-Woong; Yoo, Jin; Lee, Kwi Lim; Jeong, Jae-Ho; Lee, Seung Won; Jeong, Taekyeong; Ha, Kwi-Seok

    2015-01-01

    Comparing with the light water reactor, sodium as a reactor coolant violently reacts with oxygen in the containment atmosphere. Due to this chemical reaction, heat generated from the combustion heat increases the temperature and pressure in the containment atmosphere. The structural integrity of the containment building which is a final radiological defense barrier is threaten. A sodium fire event in the containment due to air ingress into the cover gas region in the reactor vessel is classified as one of the design basis events in the PGSFR. This event comes from a leak or crack on the reactor upper closure header surface. It accompanys an event of the radiological fission products release to the inside the containment. In this paper, evaluation for the sodium fire and radiological influence due to air ingress into the cover gas region of the reactor vessel is described. To evaluate this event, the CONTAIN-LMR, MACCS-II and OR-IGEN-II codes are used. For the sodium pool fire event in the containment, the performance evaluation and radiological influence are carried out. In the thermal hydraulic aspects, the 1 cell containment yields the most conservative result. In this event, the maximum temperature and pressure in the containment are calculated 0.185 MPa, 280.0 .deg. C, respectively. The radiological dose at the EAB and LPZ are below the acceptance criteria specified in the 10CFR100

  11. Radiological release analysis for the EFR project

    International Nuclear Information System (INIS)

    Carluec, B.; Dechelette, S.; Balard, F.

    1996-01-01

    Tile safety approach of the European Fast Reactor project (EFR) requires to deal with certain hypothetical CDA and therefore to enhance the containment structure in order to mitigate the consequences. The analyses are performed in order to design a containment taking advantages of die inherent characteristics of the liquid metal fast reactor. Adequate computer codes describing the sequences which follow the core disruptive accident, are used. One of the main tool is the computer code CONTAIN-LMR. The goal of these analyses is to identify the most sensitive phenomena such as the overpressure due to sodium fire, to assess the involvement of some design parameters such as the leaktightness of the structures, the arrangement of the ventilation system- the effects of the implementation of filters or a retention chamber. The results of the calculations allow to propose a robust containment for EFR, and to verify that the radiological releases in the environment can be limited. The paper presents the safety approach of EFR adopted with regard to the accidents leading to a radiological source term, and the main design options retained for the containment of EFR. Then, the methods used to describe the phenomena and some representative calculations, will be presented. The main useful information and knowledge which derive from these studies for the designers conclude the paper. (author)

  12. UK contribution to CEGB-EPRI-CRIEPI program on seismic isolation

    International Nuclear Information System (INIS)

    Austin, N.M.; Hattori, S.; Rodwell, E.; Womack, G.J.

    1989-01-01

    Over the last decade the concept of seismic isolation applied to nuclear power plants has generated a great deal of interest worldwide and a number of comprehensive reviews on the topic have been published. Understandably, most of the design and research and development (R and D) effort on seismic isolation has come from countries where larger magnitude earthquakes are an ever-present problem; e.g., Japan, USA, etc. In some areas of these countries seismic isolation may in fact present the only feasible design solution for potential sites of Liquid-Metal-Cooled Reactors (LMR's). This paper summarizes the test results obtained from a small scale seismic isolation system consisting of a laminated steel/natural rubber bearing and a viscodamper. Dynamic characteristics of the system; e.g., stiffness and damping, were measured for a variety of loading conditions. The results are suitable for developing a mathematical model of the isolation system and providing data for use in the design of larger scale bearings and viscodampers

  13. Uncertainty correlation in stochastic safety analysis of natural circulation decay heat removal of liquid metal reactor

    International Nuclear Information System (INIS)

    Takata, Takashi; Yamaguchi, Akira

    2009-01-01

    Since various uncertainties of input variables are involved and nonlinearly-correlated in the Best Estimate (BE) plant dynamics code, it is of importance to evaluate the importance of input uncertainty to the computational results and to estimate the accuracy of the confidence level of the results. In order to estimate the importance and the accuracy, the authors have applied the stochastic safety analysis procedure using the Latin Hypercube sampling method to Liquid Metal Reactor (LMR) natural circulation Decay Heat Removal (DHR) phenomenon in the present paper. 17 input variables are chosen for the analyses and 5 influential variables, which affect the maximum coolant temperature at the core in a short period of time (several tens seconds), are selected to investigate the importance by comparing with the full-scope parametric analysis. As a result, it has been demonstrated that a comparative small number of samples is sufficient enough to estimate the dominant input variable and the confidence level. Furthermore, the influence of the sampling method on the accuracy of the upper tolerance limit (confidence level of 95%) has been examined based on the Wilks' formula. (author)

  14. 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

  15. A state-of-the-art report on the development of liquid metal reactor materials

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Yung Suk; Noh, Kye Hoh; Han, Jung Hoh; Park, Jee Yun; Lee, Duk Hyun; Suh, Jung Hoon; Park, Kee Sung; Jung, Choong Hwan [Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)

    1993-09-01

    A state-of-the are survey on the LMR materials - core and structural materials and the others - has been conducted. For core materials, ferritic steels with superior swelling resistance such as HT-9 or PNC-FMS and the ODS steels are found to be one of the best candidates for the cladding and wrapper tubes, respectively. As boron carbide presently used for a neutron absorber also needs to extend its life time, much attention is now being paid to the development of a coated pellets and a kind of cermet made of boron carbide and metal in order to eliminate the control rod failure. As structural materials for pressure vessel, pipe and steam generator, the 316 MN SS with lower carbon and medium nitrogen compared to the 316 SS and 9Cr-1Mo ferritic steels are well recommended, respectively. The inelastic analytical model and the evaluation methodology to predict creep fatigue life time have been reviewed. On the other hand, a state of the art survey on the EMP coil/insulator materials has been conducted and the feasibility of the functionally gradient materials such as ZrO2-304 SS has also been investigated. 89 figs., 34 tabs., 131 refs. (Author).

  16. A development report on the inelastic analysis program for the high temperature structures

    International Nuclear Information System (INIS)

    Kim, Jong Bum; Lee, H. Y.; Lee, J. H.

    2001-04-01

    LMR high temperature structures such as reactor vessel and reactor internal structures are subject to high temperature operating loads thus they can undergo damage due to creep, creep-fatigue, and ratcheting behavior. In this project, NONSTA-EP program implementing combined isotropic and kinematic hardening behavior and NONSTA-VP program implementing Chaboche model, which is so called viscoplasticity model, have been developed and have been continuously improved. In the year of 2000, NONSTA-OW program implementing Ohno-Wang model which can simulate progressive plasticity (that is ratcheting) more precisely compared to other models. One of the characteristics of inelastic constitutive equations is to have various numbers of material parameters to simulate complex material behaviors realistically and it is very important to obtain these material parameters. In this project, the improved method to obtain these material parameters has been studied with the optimal technique and by conducting material characteristic tests under high temperature conditions. The feasibility of the developed program with Ohno-Wang model, which contains 9 isotropic constitutive equations, has been studied through the example problem

  17. Enhancement of antibiotic productions by engineered nitrate utilization in actinomycetes.

    Science.gov (United States)

    Meng, Sitong; Wu, Hang; Wang, Lei; Zhang, Buchang; Bai, Linquan

    2017-07-01

    Nitrate is necessary for primary and secondary metabolism of actinomycetes and stimulates the production of a few antibiotics, such as lincomycin and rifamycin. However, the mechanism of this nitrate-stimulating effect was not fully understood. Two putative ABC-type nitrate transporters were identified in Streptomyces lincolnensis NRRL2936 and verified to be involved in lincomycin biosynthesis. With nitrate supplementation, the transcription of nitrogen assimilation genes, nitrate-specific ABC1 transporter genes, and lincomycin exporter gene lmrA was found to be enhanced and positively regulated by the global regulator GlnR, whose expression was also improved. Moreover, heterologous expression of ABC2 transporter genes in Streptomyces coelicolor M145 resulted in an increased actinorhodin production. Further incorporation of a nitrite-specific transporter gene nirC, as in nirC-ABC2 cassette, led to an even higher actinorhodin production. Similarly, the titers of salinomycin, ansamitocin, lincomycin, and geldanamycin were increased with the integration of this cassette to Streptomyces albus BK3-25, Actinosynnema pretiosum ATCC31280, S. lincolnensis LC-G, and Streptomyces hygroscopicus XM201, respectively. Our work expanded the nitrate-stimulating effect to many antibiotic producers by utilizing the nirC-ABC2 cassette for enhanced nitrate utilization, which could become a general tool for titer increase of antibiotics in actinomycetes.

  18. MIDAS [Master Information and Data Acquisition System

    International Nuclear Information System (INIS)

    Ball, D.L.

    1986-01-01

    The Master Information and Data Acquisition System (MIDAS) is a computerized work control system that provides 24-hour, real-time access to plant equipment information and work package status. It is used in the 400 Area of the Department of Energy (DOE) Hanford Site in Richland, Washington. MIDAS was originally created to aid in the release and control of work at the Fast Flux Test Facility (FFTF), which is operated by the Westinghouse Hanford Company for the DOE. After MIDAS performed that function at FFTF successfully for over two years, its role was expanded to provide similar functions for other facilities supporting the LMR mission. Through its ability to provide online, accurate information on plant components, safety criteria, and work package status, MIDAS reinforces Operations functions and the control and authorization of maintenance activities in the FFTF plant and in other related facilities. Thus, MIDAS enhances the operational safety, as well as the planning and scheduling process for these facilities. MIDAS consists of three parts: The Plant Tracking System (PTS), the Work Control Log (WCL), and the MIDAS Component Indices

  19. An Inter-Disciplinary Language for Inter-Disciplinary Communication: Academic Globalization, Ethos, Pathos, and Logos

    Directory of Open Access Journals (Sweden)

    Marta Szabo White

    2014-08-01

    Full Text Available Inspired by the intersection of character, emotions, and logic, much like a Hungarian Rhapsody which is beautifully sad; this paper explores ethos, pathos, and logos in the context of Academic Globalization. As students of the world, an inter-disciplinary language is pivotal for inter-disciplinary communication. Given that the current state of the world stems primarily from miscommunications, it is imperative to launch a cognitive language tool which underscores global commonalities and mitigates cultural differences. Such a platform would foster interdisciplinary research, education, and communication. New paradigms would evolve, grounded in ethos, pathos, and logos. Like yin and yang, these states are interrelated, interacting, and interchanging learning spheres. Just as day and night blend at some point; just as the Parthenon epitomized Greek thought, celebrated the birthplace of democracy, and for the first time, depicted everyday citizens in friezes- underscoring their impactful role- ethos, pathos, and logos represent cross-disciplinary communication devices which synergistically transform and ignite academic globalization. The Literature Review links the concepts of ethos, pathos, and logos with the seminal work Lewis and his LMR framework, which has given birth to Cultureactive and subsequently to ICE [InterCultural Edge]. http://www.fuqua.duke.edu/ciber/programs/we_organize/ice/ Accessed February 14, 2014

  20. Nuclear design and analysis report for KALIMER breakeven core conceptual design

    International Nuclear Information System (INIS)

    Kim, Sang Ji; Song, Hoon; Lee, Ki Bog; Chang, Jin Wook; Hong, Ser Gi; Kim, Young Gyun; Kim, Yeong Il

    2002-04-01

    During the phase 2 of LMR design technology development project, the breakeven core configuration was developed with the aim of the KALIMER self-sustaining with regard to the fissile material. The excess fissile material production is limited only to the extent of its own requirement for sustaining its planned power operation. The average breeding ratio is estimated to be 1.05 for the equilibrium core and the fissile plutonium gain per cycle is 13.9 kg. The nuclear performance characteristics as well as the reactivity coefficients have been analyzed so that the design evaluation in other activity areas can be made. In order to find out a realistic heavy metal flow evolution and investigate cycle-dependent nuclear performance parameter behaviors, the startup and transition cycle loading strategies are developed, followed by the startup core physics analysis. Driver fuel and blankets are assumed to be shuffled at the time of each reload. The startup core physics analysis has shown that the burnup reactivity swing, effective delayed neutron fraction, conversion ratio and peak linear heat generation rate at the startup core lead to an extreme of bounding physics data for safety analysis. As an outcome of this study, a whole spectrum of reactor life is first analyzed in detail for the KALIMER core. It is experienced that the startup core analysis deserves more attention than the current design practice, before the core configuration is finalized based on the equilibrium cycle analysis alone.