WorldWideScience

Sample records for npp seismic design

  1. Seismic site evaluation practice and seismic design guide for NPP in Continent of China

    Energy Technology Data Exchange (ETDEWEB)

    Hu Yuxian [State Seismological Bureau, Beijing, BJ (China). Inst. of Geophysics

    1997-03-01

    Energy resources, seismicity, NPP and related regulations of the Continent of China are briefly introduced in the beginning and two codes related to the seismic design of NPP, one on siting and another on design, are discussed in some detail. The one on siting is an official code of the State Seismological Bureau, which specifies the seismic safety evaluation requirements of various kinds of structures, from the most critic and important structures such as NPP to ordinary buildings, and including also engineering works in big cities. The one on seismic design of NPP is a draft subjected to publication now, which will be an official national code. The first one is somewhat unique but the second one is quite similar to those in the world. (author)

  2. Investigation on seismic characteristic in Muria Peninsula to asses the NPP seismic design

    Energy Technology Data Exchange (ETDEWEB)

    Kusnowo, A. [National Atomic Energy Agency, Jakarta (Indonesia)

    1997-03-01

    A feasibility study on first nuclear power plant was conducted during 4,5 years started on 22 November 1991. This study consists of two parts. First, the non site study, Second part is the site and environmental study. The scope of non site studies are economic financing, technical and safety aspect as well as fuel cycle and waste management aspect. The site and environmental studied consist of site conditions and qualification, seismological, environmental condition as well as social economic and cultural impact. In the first step of site study (step 1), the result come up to the three candidates named Ujung Lemahabang, Ujung Watu and Ujung Grenggengan. Further study on geology, topography, oceanography, geophysics, hydrology, seismology, vulcanology, man induced event, etc was done on those three candidates (named as step 2). The results come up with Ujung Lemahabang as the best candidates. It is important to know basic, characteristic of seismicity of nuclear power plant sitting region for seismic hazard assessment this was done as step 3. This paper describe the results of step 3. (J.P.N.)

  3. Considerations on Improving Seismic Design at NPP Emergency Response Center after Fukushima Daiichi NPP Accident%福岛核事故后对我国核电厂应急控制中心抗震设防的思考

    Institute of Scientific and Technical Information of China (English)

    付强; 陈晓秋; 岳会国; 潘蓉

    2011-01-01

    结合福岛核事故后对我国核电厂进行的核安全检查,分析了我国核安全法规关于核电厂应急控制中心的要求以及福岛核事故的经验教训,提出目前我国核电厂应急控制中心采用民用抗震设防标准进行抗震设防,无法保证在由地震引发的应急事故工况下应急控制中心的功能,应该适当提高其抗震设防级别。%Based on the nuclear safety impections at NPPs carried out in China in the aftermash of Fukushima Daiichi NPP accident, the requirements for NPP emergency response centers in the nuclear safety regulations and the lessons of the Fukushima Daiichi NPP accident are analylzed. The seismic design of the current NPP emergency response centers in China, based on the civil building seismic design code, is considered to be unable to ensure the function of emergency response centers in emergency accident conditions caused by earthquake, except as otherwise impporved.

  4. Seismic response analysis of Wolsung NPP structure and equipment subjected to scenario earthquakes

    Energy Technology Data Exchange (ETDEWEB)

    Choi, In Kil; Ahn, Seong Moon; Choun, Young Sun; Seo, Jeong Moon

    2005-03-15

    The standard response spectrum proposed by US NRC has been used as a design earthquake for the design of Korean nuclear power plant structures. However, it does not reflect the characteristic of seismological and geological of Korea. In this study, the seismic response analysis of Wolsung NPP structure and equipment were performed. Three types of input motions, artificial time histories that envelop the US NRC Regulatory Guide 1.60 spectrum and the probability based scenario earthquake spectra developed for the Korean NPP site and a typical near-fault earthquake recorded at thirty sites, were used as input motions. The acceleration, displacement and shear force responses of Wolsung containment structure due to the design earthquake were larger than those due to the other input earthquakes. But, considering displacement response increases abruptly as Wolsung NPP structure does nonlinear behavior, the reassessment of the seismic safety margin based on the displacement is necessary if the structure does nonlinear behavior; although it has adequate the seismic safety margin within elastic limit. Among the main safety-related devices, electrical cabinet and pump showed the large responses on the scenario earthquake which has the high frequency characteristic. This has great effects of the seismic capacity of the main devices installed inside of the building. This means that the design earthquake is not so conservative for the safety of the safety related nuclear power plant equipments.

  5. OVERVIEW ON BNL ASSESSMENT OF SEISMIC ANALYSIS METHODS FOR DEEPLY EMBEDDED NPP STRUCTURES.

    Energy Technology Data Exchange (ETDEWEB)

    XU,J.; COSTANTINO, C.; HOFMAYER, C.; GRAVES, H.

    2007-04-01

    A study was performed by Brookhaven National Laboratory (BNL) under the sponsorship of the U. S. Nuclear Regulatory Commission (USNRC), to determine the applicability of established soil-structure interaction analysis methods and computer programs to deeply embedded and/or buried (DEB) nuclear power plant (NPP) structures. This paper provides an overview of the BNL study including a description and discussions of analyses performed to assess relative performance of various SSI analysis methods typically applied to NPP structures, as well as the importance of interface modeling for DEB structures. There are four main elements contained in the BNL study: (1) Review and evaluation of existing seismic design practice, (2) Assessment of simplified vs. detailed methods for SSI in-structure response spectrum analysis of DEB structures, (3) Assessment of methods for computing seismic induced earth pressures on DEB structures, and (4) Development of the criteria for benchmark problems which could be used for validating computer programs for computing seismic responses of DEB NPP structures. The BNL study concluded that the equivalent linear SSI methods, including both simplified and detailed approaches, can be extended to DEB structures and produce acceptable SSI response calculations, provided that the SSI response induced by the ground motion is very much within the linear regime or the non-linear effect is not anticipated to control the SSI response parameters. The BNL study also revealed that the response calculation is sensitive to the modeling assumptions made for the soil/structure interface and application of a particular material model for the soil.

  6. Checking of seismic and tsunami hazard for coastal NPP of Chinese continent after Fukushima nuclear accident

    Institute of Scientific and Technical Information of China (English)

    Chang Xiangdong; Zhou Bengang; Zhao Lianda

    2013-01-01

    A checking on seismic and tsunami hazard for coastal nuclear power plant (NPP) of Chinese continent has been made after Japanese Fukushima nuclear accident caused by earthquake tsunami.The results of the checking are introduced briefly in this paper,including the evaluations of seismic and tsunami hazard in NPP siting period,checking results on seismic and tsunami hazard.Because Chinese coastal area belongs to the continental shelf and far from the boundary of plate collision,the tsunami hazard is not significant for coastal area of Chinese continent.However,the effect from tsunami still can' t be excluded absolutely since calculated result of Manila trench tsunami source although the tsunami wave is lower than water level from storm surge.The research about earthquake tsunami will continue in future.The tsunami warning system and emergency program of NPP will be established based on principle of defense in depth in China.

  7. Upgrading of seismic design of nuclear power plant building

    Energy Technology Data Exchange (ETDEWEB)

    Akiyama, Hiroshi [Tokyo Univ. (Japan). Faculty of Engineering; Kitada, Yoshio

    1997-03-01

    In Japan seismic design methodology of nuclear power plant (NPP) structures has been established as introduced in the previous session. And yet efforts have been continued to date to upgrade the methodology, because of conservative nature given to the methodology in regard to unknown phenomena and technically-limited modeling involved in design analyses. The conservative nature tends to produce excessive safety margins, and inevitably send NPP construction cost up. Moreover, excessive seismic design can increase the burden on normal plant operation, though not necessarily contributing to overall plant safety. Therefore, seismic engineering has put to many tests and simulation analyses in hopes to rationalize seismic design and enhance reliability of seismic safety of NPPs. In this paper, we describe some studies on structural seismic design of NPP underway as part of Japan`s effort to upgrade existing seismic design methodology. Most studies described here are carried out by NUPEC (Nuclear Power Engineering Company) funded by MITI (the Ministry of International Trade and Industry Japan), though, similar studies with the same motive are also carrying out by nuclear industries such as utilities, NPP equipment and system manufacturers and building constructors. This paper consists of three sections, each introducing studies relating to NPP structural seismic design, new siting technology, and upgrading of the methodology of structural design analyses. (J.P.N.)

  8. Probabilistic Seismic Hazard Assessment for a NPP in the Upper Rhine Graben, France

    Science.gov (United States)

    Clément, Christophe; Chartier, Thomas; Jomard, Hervé; Baize, Stéphane; Scotti, Oona; Cushing, Edward

    2015-04-01

    The southern part of the Upper Rhine Graben (URG) straddling the border between eastern France and western Germany, presents a relatively important seismic activity for an intraplate area. A magnitude 5 or greater shakes the URG every 25 years and in 1356 a magnitude greater than 6.5 struck the city of Basel. Several potentially active faults have been identified in the area and documented in the French Active Fault Database (web site in construction). These faults are located along the Graben boundaries and also inside the Graben itself, beneath heavily populated areas and critical facilities (including the Fessenheim Nuclear Power Plant). These faults are prone to produce earthquakes with magnitude 6 and above. Published regional models and preliminary geomorphological investigations provided provisional assessment of slip rates for the individual faults (0.1-0.001 mm/a) resulting in recurrence time of 10 000 years or greater for magnitude 6+ earthquakes. Using a fault model, ground motion response spectra are calculated for annual frequencies of exceedance (AFE) ranging from 10-4 to 10-8 per year, typical for design basis and probabilistic safety analyses of NPPs. A logic tree is implemented to evaluate uncertainties in seismic hazard assessment. The choice of ground motion prediction equations (GMPEs) and range of slip rate uncertainty are the main sources of seismic hazard variability at the NPP site. In fact, the hazard for AFE lower than 10-4 is mostly controlled by the potentially active nearby Rhine River fault. Compared with areal source zone models, a fault model localizes the hazard around the active faults and changes the shape of the Uniform Hazard Spectrum at the site. Seismic hazard deaggregations are performed to identify the earthquake scenarios (including magnitude, distance and the number of standard deviations from the median ground motion as predicted by GMPEs) that contribute to the exceedance of spectral acceleration for the different AFE

  9. Seismic response analysis of a piping system subjected to multiple support excitations in a base isolated NPP building

    Energy Technology Data Exchange (ETDEWEB)

    Surh, Han-Bum [School of Mechanical Engineering, Sungkyunkwan University, 2066 Seobu-ro, Jangan-gu, Suwon 440-746 (Korea, Republic of); Korea Atomic Energy Research Institute, 989-111 Daedeok-daero, Yuseong-gu, Daejeon 305-353 (Korea, Republic of); Ryu, Tae-Young; Park, Jin-Sung [School of Mechanical Engineering, Sungkyunkwan University, 2066 Seobu-ro, Jangan-gu, Suwon 440-746 (Korea, Republic of); Ahn, Eun-Woo; Choi, Chul-Sun [Korea Electric Power Corporation Engineering & Construction Company, Inc., 2354 Yonggu-daero, Giheung-gu, Yongin 446-713 (Korea, Republic of); Koo, Ja Choon [School of Mechanical Engineering, Sungkyunkwan University, 2066 Seobu-ro, Jangan-gu, Suwon 440-746 (Korea, Republic of); Choi, Jae-Boong [School of Mechanical Engineering, Sungkyunkwan University, 2066 Seobu-ro, Jangan-gu, Suwon 440-746 (Korea, Republic of); SKKU Advanced Institute of Nanotechnology, Sungkyunkwan University, 2066 Seobu-ro, Jangan-gu, Suwon 440-746 (Korea, Republic of); Kim, Moon Ki, E-mail: mkkim@me.skku.ac.kr [School of Mechanical Engineering, Sungkyunkwan University, 2066 Seobu-ro, Jangan-gu, Suwon 440-746 (Korea, Republic of); SKKU Advanced Institute of Nanotechnology, Sungkyunkwan University, 2066 Seobu-ro, Jangan-gu, Suwon 440-746 (Korea, Republic of)

    2015-10-15

    Highlights: • Piping system in the APR 1400 NPP with a base isolation design is studied. • Seismic response of piping system in base isolated building are investigated. • Stress classification method is examined for piping subjected to seismic loading. • Primary stress of piping is reduced due to base isolation design. • Substantial secondary stress is observed in the main steam piping. - Abstract: In this study, the stress response of the piping system in the advanced power reactor 1400 (APR 1400) with a base isolation design subjected to seismic loading is addressed. The piping system located between the auxiliary building with base isolation and the turbine building with a fixed base is considered since it can be subjected to substantial relative support movement during seismic events. First, the support responses with respect to the base characteristic are investigated to perform seismic analysis for multiple support excitations. Finite element analyses are performed to predict the piping stress response through various analysis methods such as the response spectrum, seismic support movement and time history method. To separately evaluate the inertial effect and support movement effect on the piping stress, the stress is decomposed into a primary and secondary stress using the proposed method. Finally, influences of the base isolation design on the piping system in the APR 1400 are addressed. The primary stress based on the inertial loading is effectively reduced in a base isolation design, whereas a considerable amount of secondary stress is generated in the piping system connecting a base isolated building with a fixed base building. It is also confirmed that both the response spectrum analysis and seismic support movement analysis provide more conservative estimations of the piping stress compared to the time history analysis.

  10. Development of seismic safety reevaluation procedure considering the ageing of NPP facilities

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Myoung Kue [Jeonju Univ., Cheonju (Korea, Republic of); Kim, J. M. [Cheonnam National Univ., Gwangju (Korea, Republic of); Kim, Y. S.; Cheong, S. H.; Kim, I. S.; Lee, M. G.; Kim, D. O. [Andong National Univ., Andong (Korea, Republic of); Lee, G. H. [Mokpo National Maritime Univ., Mokpo (Korea, Republic of)

    2003-03-15

    There are three of Nuclear Power Plants subject to the USI A-46 in Korea, including Kori No 1 and No 2 and Wolsung No 1. For the sake of resolution of the issue the possibility of adopting the GIP developed by the SQUG in USA is very high. In relation to the issue, this study addresses some technical improvements of the GIP including sloshing analysis based on multiple modes, seismic retrofit of cabinet for reduction of ICRS and modification of IRS depending on damping ratio. Dominant degradation factor and its affects NPP concrete elements are reviewed : chloride induced corrosion, carbonation of concrete elements, freezing and thawing of concrete elements, chemical and biological process, crack affect on concrete degradation. Various technical reports and papers about age-related degradation are reviewed for identification of degradation properties of NPP structures and components and degradation trend in NPP structures and components. This report summarizes numerical model for concrete degradation and development procedure of numerical models for concrete degradation. This report proposes the research necessity for performance evaluation of degraded concrete structure and selection of element for further study.

  11. Seismic dynamic analysis of Heat Exchangers inside of the Auxiliary Buildings in AP1000{sup T}M NPP

    Energy Technology Data Exchange (ETDEWEB)

    Di Fonzo, M.; Aragon, J.; Moraleda, F.; Palazuelos, M.; San vicente, J. L.

    2011-07-01

    Seismic dynamic analysis was carried out for the Heat Exchangers (RNS-HR) located inside of the Auxiliary Building in AP 1000{sup T}M NPP. The main function of the RNS-HX is to provide shutdown reactor cooling. These equipment's are safety-related. So the seismic analysis was done using the methodology for Seismic Category I (SCI) structures. The most important topic is that the RNS-HX shall withstand the effects of the Safe Shutdown Earthquake (SSE) and maintain the specified design functions. for the analysis, two finite element models (FEM) were built in order to investigate the structural response of the couple system of building and equipment. The response spectra method was used. The floor response spectra (FRS) at the slab-wall connection were used as input Lateral seismic restrain was necessary to added in order to achieve the natural frequency of 33 Hz. The global structural response was obtained by means of the modal combination method indicated in the Regulatory Guide 1.92.

  12. Seismic design and analysis of nuclear power plant structures

    Institute of Scientific and Technical Information of China (English)

    Pentti Varpasuo

    2013-01-01

    The seismic design and analysis of nuclear power plant (NPP) begin with the seismic hazard assessment and design ground motion development for the site.The following steps are needed for the seismic hazard assessment and design ground motion development:a.the development of regional seismo-tectonic model with seismic source areas within 500 km radius centered to the site; b.the development of strong motion prediction equations;c.logic three development for taking into account uncertainties and seismic hazard quantification; d.the development of uniform hazard response spectra for ground motion at the site; e.simulation of acceleration time histories compatible with uniform hazard response spectra.The following phase two in seismic design of NPP structures is the analysis of structural response for the design ground motion.This second phase of the process consists of the following steps:a.development of structural models of the plant buildings; b.development of the soil model underneath the plant buildings for soil-structure interaction response analysis; c.determination of in-structure response spectra for the plant buildings for the equipment response analysis.In the third phase of the seismic design and analysis the equipment is analyzed on the basis of in-structure response spectra.For this purpose the structural models of the mechanical components and piping in the plant are set up.In large 3D-structural models used today the heaviest equipment of the primary coolant circuit is included in the structural model of the reactor building.In the fourth phase the electrical equipment and automation and control equipment are seismically qualified with the aid of the in-structure spectra developed in the phase two using large three-axial shaking tables.For this purpose the smoothed envelope spectra for calculated in-structure spectra are constructed and acceleration time is fitted to these smoothed envelope spectra.

  13. A seismic design of nuclear reactor building structures applying seismic isolation system in a seismicity region-a feasibility case study in Japan

    Energy Technology Data Exchange (ETDEWEB)

    Kubo, Tetsuo [The University of Tokyo, Tokyo (Japan); Yamamoto, Tomofumi; Sato, Kunihiko [Mitsubishi Heavy Industries, Ltd., Kobe (Japan); Jimbo, Masakazu [Toshiba Corporation, Yokohama (Japan); Imaoka, Tetsuo [Hitachi-GE Nuclear Energy, Ltd., Hitachi (Japan); Umeki, Yoshito [Chubu Electric Power Co. Inc., Nagoya (Japan)

    2014-10-15

    A feasibility study on the seismic design of nuclear reactor buildings with application of a seismic isolation system is introduced. After the Hyogo-ken Nanbu earthquake in Japan of 1995, seismic isolation technologies have been widely employed for commercial buildings. Having become a mature technology, seismic isolation systems can be applied to NPP facilities in areas of high seismicity. Two reactor buildings are discussed, representing the PWR and BWR buildings in Japan, and the application of seismic isolation systems is discussed. The isolation system employing rubber bearings with a lead plug positioned (LRB) is examined. Through a series of seismic response analyses using the so-named standard design earthquake motions covering the design basis earthquake motions obtained for NPP sites in Japan, the responses of the seismic isolated reactor buildings are evaluated. It is revealed that for the building structures examined herein: (1) the responses of both isolated buildings and isolating LRBs fulfill the specified design criteria; (2) the responses obtained for the isolating LRBs first reach the ultimate condition when intensity of motion is 2.0 to 2.5 times as large as that of the design-basis; and (3) the responses of isolated reactor building fall below the range of the prescribed criteria.

  14. Floor response spectra for seismic qualification of Kozloduy VVER 440-230 NPP

    Energy Technology Data Exchange (ETDEWEB)

    Kostov, M.K. [Bulgarian Academy of Sciences, Sofia (BG). Central Lab. for Seismic Mechanics and Earthquake Engineering; Ma, D.C. [Argonne National Lab., IL (United States); Prato, C.A. [Univ. of Cordoba (AR); Stevenson, J.D. [Stevenson and Associates, Cleveland, OH (US)

    1993-08-01

    In this paper the floor response spectra generation methodology for Kozloduy NPP, Unit 1-2 of VVER 440-230 is presented. The 2D coupled soil-structure interaction models are used combined with a simplified correction of the final results for accounting of torsional effects. Both time history and direct approach for in-structure spectra generation are used and discussion of results is made.

  15. Condenser Design for the Proposed AM600 NPP

    Energy Technology Data Exchange (ETDEWEB)

    Rahman, Md. Mizanur; Abdallah, Khaled Atya Ahmed; Field, Robert M. [KEPCO International Nuclear Graduate School, Ulsan (Korea, Republic of)

    2015-10-15

    The design goals are to make the condenser more robust and compact with a reduced component count. The AM600 condenser design also has new features as described below. Considering that the minimum heat sink temperature for potentially emergent nuclear countries is on the order of 21.deg. C or higher, a turbine design with a single low pressure rotor can be considered without sacrificing thermal efficiency. The condenser back pressure range for the considered markets is on the order of 2 to 3 in-HgA. With these boundary conditions, the AM600 condenser duty can be met with a single pressure zone design with a total of eight (8) titanium tube bundles (four (4) per pass) divided into four isolable sections. Due to the compact design (i.e., accepting exhaust from only one low pressure cylinder), both axial ends of the condenser are unobstructed and available for attachment of extended flash chambers, diverting inflows away from the tube bundles. The single shell design of this condenser then allows for an innovative design feature, namely the extended flash chambers. This permits the routing of dump, drain, vent, and bypass flows directly to these chambers, bypassing the condenser shell. Within the condenser shell, this design eliminates impingement plates, impingement boxes, and spargers. Failure of these components represents an ongoing source of condenser tube damage in operating nuclear units, requiring significant resources for outage inspections. The extended flash chamber approach also has a number of other advantages as delineated above.

  16. Seismic qualification tests of fans of the NPP of Laguna Verde U-1 and U-2; Pruebas de calificacion sismica de ventiladores de la Central Laguna Verde U1 and U2

    Energy Technology Data Exchange (ETDEWEB)

    Jarvio C, G.; Garcia H, E. E.; Arguelles F, R.; Vela H, A. [ININ, Carretera Mexico-Toluca s/n, 52750 Ocoyoacac, Estado de Mexico (Mexico); Naranjo U, J. L., E-mail: gilberto.jarvio@inin.gob.mx [Comision Federal de Electricidad, Gerencia de Centrales Nucleoelectricas, Subgerencia de Ingenieria, Carretera Veracruz-Medellin Km 7.5, Dos Bocas, Veracruz (Mexico)

    2013-10-15

    This work presents the results of the seismic qualification tests applied to the fans that will be installed in the control panels of the three divisions of the diesel generators of the nuclear power plant (NPP) of Laguna Verde, Unit-1 and Unit-2. This seismic qualification process of the fans was carried out using two specimens that were tested in the seismic table (vibrating) of the Engineering Institute of Universidad Nacional Autonoma de Mexico (UNAM), in accordance with the requirements of the standard IEEE 344-1975, to satisfy the established requirements of seismic qualification in the technical specifications and normative documents required by the nuclear standards, in order to demonstrate its application in the diesel generators Divisions I, II and III of the NPP. The seismic qualification tests were developed on specimens that were retired of the NPP of Laguna Verde recently with a service life of 7.75 years. (Author)

  17. DISPLACEMENT BASED SEISMIC DESIGN CRITERIA

    Energy Technology Data Exchange (ETDEWEB)

    HOFMAYER,C.H.

    1999-03-29

    The USNRC has initiated a project to determine if any of the likely revisions to traditional earthquake engineering practice are relevant to seismic design of the specialized structures, systems and components of nuclear power plants and of such significance to suggest that a change in design practice might be warranted. As part of the initial phase of this study, a literature survey was conducted on the recent changes in seismic design codes/standards, on-going activities of code-writing organizations/communities, and published documents on displacement-based design methods. This paper provides a summary of recent changes in building codes and on-going activities for future codes. It also discusses some technical issues for further consideration.

  18. Displacement Based Seismic Design Criteria

    Energy Technology Data Exchange (ETDEWEB)

    Costello, J.F.; Hofmayer, C.; Park, Y.J.

    1999-03-29

    The USNRC has initiated a project to determine if any of the likely revisions to traditional earthquake engineering practice are relevant to seismic design of the specialized structures, systems and components of nuclear power plants and of such significance to suggest that a change in design practice might be warranted. As part of the initial phase of this study, a literature survey was conducted on the recent changes in seismic design codes/standards, on-going activities of code-writing organizations/communities, and published documents on displacement-based design methods. This paper provides a summary of recent changes in building codes and on-going activities for future codes. It also discusses some technical issues for further consideration.

  19. Reassessment of Seismic Design and Noise Simulation using Finite Element Calculation of the Condensate Storage Tank of Cofrentes NPP according to standard API-650 11th Ed; Reevaluacion del diseno Sismico mediante Simulacion de Fluidos y Calculo por Elementos Finitos del Deposito del Almacenamiento de Condensado de Central Nuclear de Cofrentes conforme a la norma API-650 11th Ed

    Energy Technology Data Exchange (ETDEWEB)

    Sarti Fernandez, F.; Gavilan Moreno, C.; Paez Ortega, E.

    2012-07-01

    There have been several dynamic simulations in which I analyzed: fluid-structure interaction effect of the wave, studying stress, vibration modes and possible effects of structural instability. After this process to make the changes in the tank to comply with the new rules and updated seismic conditions were designed. were performed.

  20. Establishing seismic design criteria to achieve an acceptable seismic margin

    Energy Technology Data Exchange (ETDEWEB)

    Kennedy, R.P. [RPK Structural Mechanics Consulting, Inc., Yorba Linda, CA (United States)

    1997-01-01

    In order to develop a risk based seismic design criteria the following four issues must be addressed: (1) What target annual probability of seismic induced unacceptable performance is acceptable? (2). What minimum seismic margin is acceptable? (3) Given the decisions made under Issues 1 and 2, at what annual frequency of exceedance should the Safe Shutdown Earthquake ground motion be defined? (4) What seismic design criteria should be established to reasonably achieve the seismic margin defined under Issue 2? The first issue is purely a policy decision and is not addressed in this paper. Each of the other three issues are addressed. Issues 2 and 3 are integrally tied together so that a very large number of possible combinations of responses to these two issues can be used to achieve the target goal defined under Issue 1. Section 2 lays out a combined approach to these two issues and presents three potentially attractive combined resolutions of these two issues which reasonably achieves the target goal. The remainder of the paper discusses an approach which can be used to develop seismic design criteria aimed at achieving the desired seismic margin defined in resolution of Issue 2. Suggestions for revising existing seismic design criteria to more consistently achieve the desired seismic margin are presented.

  1. Seismic design of industrial facilities

    Science.gov (United States)

    Arze, E.

    1993-02-01

    The design philosophy, codes, practice and experience of Chile are described and compared with other countries, mainly the USA, New Zealand and the (former) USSR. It is shown that, even though the design methods of the four countries are similar, the results in six important earthquakes since 1960 are better in Chile and the US than in New Zealand and the USSR. It is proposed that the reason for this lies in the methodology used to enforce the application of codes and specifications rather than in the design. It is finally concluded that there is a need in most countries to prepare seismic codes for industrial facilities and structures and to stress in them the requirements for compulsory design review and construction inspection.

  2. DISPLACEMENT BASED SEISMIC DESIGN METHODS.

    Energy Technology Data Exchange (ETDEWEB)

    HOFMAYER,C.MILLER,C.WANG,Y.COSTELLO,J.

    2003-07-15

    A research effort was undertaken to determine the need for any changes to USNRC's seismic regulatory practice to reflect the move, in the earthquake engineering community, toward using expected displacement rather than force (or stress) as the basis for assessing design adequacy. The research explored the extent to which displacement based seismic design methods, such as given in FEMA 273, could be useful for reviewing nuclear power stations. Two structures common to nuclear power plants were chosen to compare the results of the analysis models used. The first structure is a four-story frame structure with shear walls providing the primary lateral load system, referred herein as the shear wall model. The second structure is the turbine building of the Diablo Canyon nuclear power plant. The models were analyzed using both displacement based (pushover) analysis and nonlinear dynamic analysis. In addition, for the shear wall model an elastic analysis with ductility factors applied was also performed. The objectives of the work were to compare the results between the analyses, and to develop insights regarding the work that would be needed before the displacement based analysis methodology could be considered applicable to facilities licensed by the NRC. A summary of the research results, which were published in NUREGICR-6719 in July 2001, is presented in this paper.

  3. Seismic design of reactors in NUCEF

    Energy Technology Data Exchange (ETDEWEB)

    Kurosaki, Akira [Mitsui Shipbuilding and Engineering Co. Ltd., Tokyo (Japan); Kuchiya, Masao; Yasuda, Naomitsu; Kitanaka, Tsutomu; Ogawa, Kazuhiko; Sakuraba, Koichi; Izawa, Naoki; Takeshita, Isao

    1997-03-01

    Basic concept and calculation method for the seismic design of the main equipment of the reactors in NUCEF (Nuclear Fuel Cycle Safety Engineering Research Facility) are described with actual calculation examples. The present paper is published to help the seismic design of the equipment and application of the authorization for the design and constructing of facilities. (author)

  4. Seismic Design Guidelines For Port Structures

    DEFF Research Database (Denmark)

    Burcharth, H. F.; Bernal, Alberto; Blazquez, Rafael

    -balance approach, in which structures are designed to resist a prescribed level of seismic force specified as a fraction of gravity. These methodologies have contributed to the acceptable seismic performance of port structures, particularly when the earthquake motions are more or less within the prescribed design...

  5. Update of the tectonic model for the Pannonian basin: a contribution to the seismic hazard reassessment of the Paks NPP (Hungary)

    Science.gov (United States)

    Horváth, Ferenc; Tóth, Tamás; Wórum, Géza; Koroknai, Balázs; Kádi, Zoltán; Kovács, Gábor; Balázs, Attila; Visnovitz, Ferenc

    2015-04-01

    The planned construction of two new units at the site of the Paks NPP requires a comprehensive site investigation including complete reassessment of the seismic hazard according to the Hungarian as well as international standards. Following the regulations of the Specific Safety Guide no. 9 (IAEA 2010), the approved Hungarian Geological Investigation Program (HGIP) includes integrated geological-geophysical studies at different scales. The regional study aims at to elaborate a new synthesis of all published data for the whole Pannonian basin. This task is nearly completed and the main outcomes have already been published (Horváth et al. 2015). The near regional study is in progress and addresses the construction of a new tectonic model for the circular area with 50 km radius around the NPP using a wealth of unpublished oil company seismic and borehole data. The site vicinity study has also been started with a core activity of 300 km² 3D seismic data acquisition, processing and interpretation assisted by a series of additional geophysical surveys, new drillings and geological mapping. This lecture will present a few important results of the near regional study, which sheds new light on the intricate tectonic evolution of the Mid-Hungarian Fault Zone (MHFZ), which is a strongly deformed belt between the Alcapa and Tisza-Dacia megatectonic units. The nuclear power plant is located at the margin of the Tisza unit near to the southern edge of the MHFZ. Reassessment of seismic hazard at the site of the NPP requires better understanding of the Miocene to Recent tectonic evolution of this region in the central part of the Pannonian basin. Early to Middle Miocene was a period of rifting with formation of 1 to 3 km deep half-grabens filled with terrestrial to marine deposits and large amount of rift-related volcanic material. Graben fill became strongly deformed as a consequence of juxtaposition of the two megatectonic units leading to strong compression and development of

  6. Environmental qualification design for NPP refurbishment to comply with revised licensing requirements

    Energy Technology Data Exchange (ETDEWEB)

    MacBeth, M. J.; Hemmings, R. L. [Canatom-NPM, Ontario (Canada)

    2002-04-15

    Recent Canadian Nuclear Regulatory decisions have imposed Environmental Qualification (EQ) requirements for twenty-four Reactor Building (RB) airlocks at the four-unit Pickering Nuclear Generating Station-B (PNGS-B) facility. This paper describes the EQ modification design work completed by CANATOM-NPM for the problematic aspects for such projects. The airlocks allow RB access while providing a containment boundary and are designed to prevent a potential breach of containment for all analysed station conditions. Each PNGS-B unit has three large equipment airlocks and three smaller personnel airlocks. The airlocks must function under postulated worst-case design basis accident(DBA) conditions for assigned mission durations. The design must ensure that accident conditions cannot spuriously initiate an un-requested door opening. CANATOM-NPM reviewed site data to specify the necessary EQ modifications required to satisfy licensing requirements while providing a correct and complete as-found record of the existing airlock installation. The design team assessed the installed airlocks configuration against environmental qualification requirements to finalize the list of necessary modifications. A comprehensive, cross-discipline review of proposed design changes was completed to identify any further changes required to satisfy the final EQ licensing goal. The design team also conducted a design review of the EQ modification installation strategy to integrate the design deliverables with the installation team requirements while attempting to minimize necessary outage time for EQ modification installations. This project was completed on schedule and within the cost limitations required by the client with comprehensive, high quality final design packages. Overall improvements were realized for OPG system drawings and the electronic documentation of design data. The EQ modifications designed by CANATOM-NPM will ensure the continued operation of the PNGS-B NPP past December 31

  7. Seismic capacity of a reinforced concrete frame structure without seismic detailing and limited ductility seismic design in moderate seismicity

    Energy Technology Data Exchange (ETDEWEB)

    Kim, J. K.; Kim, I. H. [Seoul National Univ., Seoul (Korea, Republic of)

    1999-10-01

    A four-story reinforced concrete frame building model is designed for the gravity loads only. Static nonlinear pushover analyses are performed in two orthogonal horizontal directions. The overall capacity curves are converted into ADRS spectra and compared with demand spectra. At several points the deformed shape, moment and shear distribution are calculated. Based on these results limited ductility seismic design concept is proposed as an alternative seismic design approach in moderate seismicity resign.

  8. Seismic design verification of LMFBR structures

    Energy Technology Data Exchange (ETDEWEB)

    1977-07-01

    The report provides an assessment of the seismic design verification procedures currently used for nuclear power plant structures, a comparison of dynamic test methods available, and conclusions and recommendations for future LMFB structures.

  9. Simplified seismic performance assessment and implications for seismic design

    Science.gov (United States)

    Sullivan, Timothy J.; Welch, David P.; Calvi, Gian Michele

    2014-08-01

    The last decade or so has seen the development of refined performance-based earthquake engineering (PBEE) approaches that now provide a framework for estimation of a range of important decision variables, such as repair costs, repair time and number of casualties. This paper reviews current tools for PBEE, including the PACT software, and examines the possibility of extending the innovative displacement-based assessment approach as a simplified structural analysis option for performance assessment. Details of the displacement-based s+eismic assessment method are reviewed and a simple means of quickly assessing multiple hazard levels is proposed. Furthermore, proposals for a simple definition of collapse fragility and relations between equivalent single-degree-of-freedom characteristics and multi-degree-of-freedom story drift and floor acceleration demands are discussed, highlighting needs for future research. To illustrate the potential of the methodology, performance measures obtained from the simplified method are compared with those computed using the results of incremental dynamic analyses within the PEER performance-based earthquake engineering framework, applied to a benchmark building. The comparison illustrates that the simplified method could be a very effective conceptual seismic design tool. The advantages and disadvantages of the simplified approach are discussed and potential implications of advanced seismic performance assessments for conceptual seismic design are highlighted through examination of different case study scenarios including different structural configurations.

  10. Structural concepts and details for seismic design

    Energy Technology Data Exchange (ETDEWEB)

    1991-09-01

    This manual discusses building and building component behavior during earthquakes, and provides suggested details for seismic resistance which have shown by experience to provide adequate performance during earthquakes. Special design and construction practices are also described which, although they might be common in some high-seismic regions, may not be common in low and moderate seismic-hazard regions of the United States. Special attention is given to describing the level of detailing appropriate for each seismic region. The UBC seismic criteria for all seismic zones is carefully examined, and many examples of connection details are given. The general scope of discussion is limited to materials and construction types common to Department of Energy (DOE) sites. Although the manual is primarily written for professional engineers engaged in performing seismic-resistant design for DOE facilities, the first two chapters, plus the introductory sections of succeeding chapters, contain descriptions which are also directed toward project engineers who authorize, review, or supervise the design and construction of DOE facilities. 88 refs., 188 figs.

  11. Summary of the historical development of seismic design of nuclear power plants in Japan and the U.S

    Energy Technology Data Exchange (ETDEWEB)

    Stevenson, John D., E-mail: jstevenson4@earthlink.net

    2014-04-01

    Over the past 50 years seismic design of nuclear power plants in Japan and the U.S. have undergone very significant changes in the three activities associated with design: • Quantification of seismic load and other applicable loads and specification of their load combinations to be considered in design. • Analysis methods and procedures necessary to convert input earthquake motions and loads normally expressed in the form of acceleration to resultant seismic dynamic or equivalent static forces, moments or stresses, fms in structures, systems and components, SSC. • Codes or standards acceptance criteria used to evaluate resultant forces, moments or stresses, fms in nuclear safety SSC to determine design adequacy. These applications to the historical development of Nuclear Power Plant, NPP designs in Japan and U.S. are summarized.

  12. Seismic Design Guidelines For Port Structures

    DEFF Research Database (Denmark)

    Burcharth, H. F.; Bernal, Alberto; Blazquez, Rafael

    In order to mitigate hazards and losses due to earthquakes, seismic design methodologies have been developed and implemented in design practice in many regions since the early twentieth century, often in the form of codes and standards. Most of these methodologies are based on a force-balance app...

  13. Conceptual Design of Portable Filtered Air Suction Systems For Prevention of Released Radioactive Gas under Severe Accidents of NPP

    Energy Technology Data Exchange (ETDEWEB)

    Gu, Beom W.; Choi, Su Y.; Yim, Man S.; Rim, Chun T. [Korea Advanced Institute of Science and Technology, Daejeon (Korea, Republic of)

    2014-05-15

    It becomes evident that severe accidents may occur by unexpected disasters such as tsunami, heavy flood, or terror. Once radioactive material is released from NPP through severe accidents, there are no ways to prevent the released radioactive gas spreading in the air. As a remedy for this problem, the idea on the portable filtered air suction system (PoFASS) for the prevention of released radioactive gas under severe accidents was proposed. In this paper, the conceptual design of a PoFASS focusing on the number of robot fingers and robot arm rods are proposed. In order to design a flexible robot suction nozzle, mathematical models for the gaps which represent the lifted heights of extensible covers for given convex shapes of pipes and for the covered areas are developed. In addition, the system requirements for the design of the robot arms of PoFASS are proposed, which determine the accessible range of leakage points of released radioactive gas. In this paper, the conceptual designs of the flexible robot suction nozzle and robot arm have been conducted. As a result, the minimum number of robot fingers and robot arm rods are defined to be four and three, respectively. For further works, extensible cover designs on the flexible robot suction nozzle and the application of the PoFASS to the inside of NPP should be studied because the radioactive gas may be released from connection pipes between the containment building and auxiliary buildings.

  14. The challenge of the global management of plant design modifications. example of the new EJ system at Vandellos NPP

    Energy Technology Data Exchange (ETDEWEB)

    Ortega, Fernando; Valdivia, Carlos; Fernandez Illobre, Luis; Trueba, Pedro [Control Rooms and Simulation, Tecnatom, Avda. Montes de Oca, 1 - 28703 San Sebastian de los Reyes. Madrid (Spain)

    2010-07-01

    One of the most challenging areas in the operation of nuclear power plants (NPP) is related to the management of plant design modifications. Plant modifications can be made to improve reliability, facilitate operation, improve safety or get better results. In any of these situations, plant modifications imply many different activities that have to be done in a coordinated manner. NUREG-0711 (Human Factors Engineering Program Review Model) shows a global approach to manage most of these activities. Although this approach is mainly focused on the design and construction of new plants, it can also be applied to plant modification management. Successful global management will require performing every activity in a specific order, taking advantage of the output coming from some tasks as input for others and finalizing every task when necessary. This will provide the best results in terms of quality, time required for implementation, safe and reliable operation and maintenance, and cost. Tecnatom is involved in most of the activities related to the operational areas and has applied a global approach to get advantages in terms of quality and cost, which is outlined in this paper. As an example of this approach, the Vandellos NPP experience is shown in this presentation. Vandellos NPP carried out an important design modification that consists of replacing an old essential service water system with a new one. This was a three-year project that implied the construction of new reservoirs, new buildings, the implementation of new equipment, and new panels in the main control room. This paper shows the way in which all of these activities were performed. (authors)

  15. Earthquake Hazards Program: U.S. Seismic Design Maps

    Data.gov (United States)

    U.S. Geological Survey, Department of the Interior — The USGS collaborates with organizations (such as the Building Seismic Safety Council) that develop model building and bridge design codes to make seismic design...

  16. Conceptual Design of Hybrid Safety Features for NPP by Utilizing Solar Updraft Tower

    Energy Technology Data Exchange (ETDEWEB)

    Song, Sub Lee [Handong Global University, Pohang (Korea, Republic of); Choi, Young Jae; Kim, Yong Jin [KAIST, Daejeon (Korea, Republic of); Park, Hyo Chan; Park, Youn Won [BEES, Daejeon (Korea, Republic of)

    2016-05-15

    In this study, hybrid safety features for NPP with solar updraft tower (SUT) is conceptually suggested to cope with loss of ultimate heat sink accident. The hybrid safety features utilizing SUT target NPPs in seashore of Arabian Gulf. Usually NPPs are constructed near seashore to utilize sea water as an ultimate heat sink. Residual heat or decay heat of nuclear reactor will diffuse into the ocean through the condenser. NPPs in Middle East are expected to be placed in seashore of Arabian Gulf. The NPP site of Barakah is an actual example. For NPPs in seashore of Arabian Gulf, an additional safety concern should be considered. Arabian Gulf is the largest oil transporting route in the world. The oil spill risk in Arabian Gulf will be the largest simultaneously. Unfortunately, not like other oceans, Arabian Gulf is a kind of closed ocean which does not have strong ocean currents connected to out of the gulf. If once oil spill is occurred, its influence can be propagated more than our expectation. The spilled oil also can affect to NPPs in seashore by covering surfaces of condenser. It will directly cause loss of ultimate heat sink. The hybrid safety features of SUT system are expected to aid normal operation of safety system and mitigate consequence of severe accident. Detail analysis and technology development is ongoing now.

  17. Seismic hazard in the design of oil and gas pipelines

    OpenAIRE

    Zdravković Slavko; Mladenović Biljana; Zlatkov Dragan

    2011-01-01

    Criteria that are adopted in earthquake resistant design of pipelines and gas lines have to take into account seismic movements and seismic generated forces that are of significantly high probability level of appearance along the length of pipeline. A choice of criteria has to include an acceptable level of seismic hazard, while design criteria should be calculated. Seismic hazard is defined as a part of natural hazard and means probability of appearance of earthquake of corresponding c...

  18. Research on performance-based seismic design criteria

    Institute of Scientific and Technical Information of China (English)

    谢礼立; 马玉宏

    2002-01-01

    The seismic design criterion adopted in the existing seismic design codes is reviewed. It is pointed out that the presently used seismic design criterion is not satisfied with the requirements of nowadays social and economic development. A new performance-based seismic design criterion that is composed of three components is presented in this paper. It can not only effectively control the economic losses and casualty, but also ensure the building(s function in proper operation during earthquakes. The three components are: classification of seismic design for buildings, determination of seismic design intensity and/or seismic design ground motion for controlling seismic economic losses and casualties, and determination of the importance factors in terms of service periods of buildings. For controlling the seismic human losses, the idea of socially acceptable casualty level is presented and the (Optimal Economic Decision Model( and (Optimal Safe Decision Model( are established. Finally, a new method is recommended for calculating the importance factors of structures by adjusting structures service period on the base of more important structure with longer service period than the conventional ones. Therefore, the more important structure with longer service periods will be designed for higher seismic loads, in case the exceedance probability of seismic hazard in different service period is same.

  19. Beyond designed functional margins in CANDU type NPP. Radioactive nuclei assessment in an LOCA type accident

    Directory of Open Access Journals (Sweden)

    Budu Andrei Razvan

    2015-01-01

    Full Text Available European Union's energy roadmap up to year 2050 states that in order to have an efficient and sustainable economy, with minimum or decreasing greenhouse gas emissions, along with use of renewable resources, each constituent state has the option for nuclear energy production as one desirable option. Every scenario considered for tackling climate change issues, along with security of supply positions the nuclear energy as a recommended option, an option that is highly competitive with respect to others. Nuclear energy, along with other renewable power sources are considered to be the main pillars in the energy sector for greenhouse gas emission mitigation at European level. European Union considers that nuclear energy must be treated as a highly recommended option since it can contribute to security of energy supply. Romania showed excellent track-records in operating in a safe and economically sound manner of Cernavoda NPP Units 1&2. Both Units are in top 10 worldwide in terms of capacity factor. Due to Romania's need to ensure the security of electricity supply, to meet the environmental targets and to move to low carbon generation technologies, Cernavoda Units 3&4 Project appears as a must. This Project was started in 2010 and it is expected to have the Units running by 2025. Cost effective and safety operation of a Nuclear Power Plant is made taking into consideration functional limits of its equipment. As common practice, every nuclear reactor type (technology used is tested according to the worse credible accident or equipment failure that can occur. For CANDU type reactor, this is a Loss of Cooling Accident (LOCA. In a LOCA type accident in a CANDU NPP, using RELAP/SCDAP code for fuel bundle damage assessment the radioactive nuclei are to be quantified. Recently, CANDU type NPP accidents are studied using the RELAP/SCDAP code only. The code formerly developed for PWR type reactors was adapted for the CANDU geometry and can assess the

  20. Tritium glovebox stripper system seismic design evaluation

    Energy Technology Data Exchange (ETDEWEB)

    Grinnell, J. J. [Savannah River Site (SRS), Aiken, SC (United States); Klein, J. E. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL)

    2015-09-01

    The use of glovebox confinement at US Department of Energy (DOE) tritium facilities has been discussed in numerous publications. Glovebox confinement protects the workers from radioactive material (especially tritium oxide), provides an inert atmosphere for prevention of flammable gas mixtures and deflagrations, and allows recovery of tritium released from the process into the glovebox when a glovebox stripper system (GBSS) is part of the design. Tritium recovery from the glovebox atmosphere reduces emissions from the facility and the radiological dose to the public. Location of US DOE defense programs facilities away from public boundaries also aids in reducing radiological doses to the public. This is a study based upon design concepts to identify issues and considerations for design of a Seismic GBSS. Safety requirements and analysis should be considered preliminary. Safety requirements for design of GBSS should be developed and finalized as a part of the final design process.

  1. Dynamic responses of base isolated NPPs under seismic excitations and aircraft crashes

    Energy Technology Data Exchange (ETDEWEB)

    Noh, Sang Hoon; Kim, Hyun Uk; Joo, Kwang Ho [KHNP, Daejeon (Korea, Republic of)

    2012-10-15

    Seismic isolation (SI) is a type of seismic design that is based on the concept of reducing the seismic demand rather than increasing the resistance capacity of the structure and related systems. Applying this technology leads to improved performance of structures that will remain essentially elastic during a design basis earthquake. In the application of the system to a nuclear power plant (NPP) structure to gain seismic resistance advantages, other safety issues should also be considered. One of those issues is the safety of an NPP against an aircraft crash (ACC). In this study, responses of a seismically isolated structure, such as acceleration and displacement, were obtained from a time domain non linear analysis to check the performance of SI system under seismic excitation. In addition, the dynamic responses of NPP structures with or without SI against an ACC were compared and other considerations are discussed.

  2. Rigid-plastic seismic design of reinforced concrete structures

    DEFF Research Database (Denmark)

    Costa, Joao Domingues; Bento, R.; Levtchitch, V.

    2007-01-01

    In this paper a new seismic design procedure for Reinforced Concrete (R/C) structures is proposed-the Rigid-Plastic Seismic Design (RPSD) method. This is a design procedure based on Non-Linear Time-History Analysis (NLTHA) for systems expected to perform in the non-linear range during a lifetime...

  3. Comparative study of codes for the seismic design of structures

    Directory of Open Access Journals (Sweden)

    S. H. C. Santos

    Full Text Available A general evaluation of some points of the South American seismic codes is presented herein, comparing them among themselves and with the American Standard ASCE/SEI 7/10 and with the European Standard Eurocode 8. The study is focused in design criteria for buildings. The Western border of South America is one of the most seismically active regions of the World. It corresponds to the confluence of the South American and Nazca plates. This region corresponds roughly to the vicinity of the Andes Mountains. This seismicity diminishes in the direction of the comparatively seismically quieter Eastern South American areas. The South American countries located in its Western Border possess standards for seismic design since some decades ago, being the Brazilian Standard for seismic design only recently published. This study is focused in some critical topics: definition of the recurrence periods for establishing the seismic input; definition of the seismic zonation and design ground motion values; definition of the shape of the design response spectra; consideration of soil amplification, soil liquefaction and soil-structure interaction; classification of the structures in different importance levels; definition of the seismic force-resisting systems and respective response modification coefficients; consideration of structural irregularities and definition of the allowable procedures for the seismic analyses. A simple building structure is analyzed considering the criteria of the several standards and obtained results are compared.

  4. Structural Analysis and Seismic Design for Cold Neutron Laboratory Building

    Energy Technology Data Exchange (ETDEWEB)

    Wu, Sangik; Kim, Y. K.; Kim, H. R

    2007-05-15

    This report describes all the major results of the dynamic structural analysis and seismic design for the Cold Neutron Laboratory Building which is classified in seismic class II. The results are summarized of the ground response spectrum as seismic input loads, mechanical properties of subsoil, the buoyancy stability due to ground water, the maximum displacement of the main frame under the seismic load and the member design. This report will be used as a basic design report to maintenance its structural integrity in future.

  5. The seismic design of axial blower using Ansys

    Energy Technology Data Exchange (ETDEWEB)

    Im, Hyung Bin; Kim, Kang Sung; Heo, Jin Wook; Chung, Jin Tai [Hanyang Univ., Seoul (Korea, Republic of)

    2001-07-01

    The seismic design for an axial blower is the procedure in which the Required Response Spectrum(RRS) is computed by using the Floor Response Spectrum(FRS). The seismic design is very important to reduce severe damages from an earthquake; therefore, the seismic design has been a great concern in engineering society. In this study, after finite element modeling is established by using Ansys, the modal data are obtained such as the natural frequencies, the participation factor, and so on. With these data, the RRS is acquired by a numerical approach. The seismic safety of the axial blower is evaluated.

  6. Assessment of seismic design response factors of concrete wall buildings

    Science.gov (United States)

    Mwafy, Aman

    2011-03-01

    To verify the seismic design response factors of high-rise buildings, five reference structures, varying in height from 20- to 60-stories, were selected and designed according to modern design codes to represent a wide range of concrete wall structures. Verified fiber-based analytical models for inelastic simulation were developed, considering the geometric nonlinearity and material inelasticity of the structural members. The ground motion uncertainty was accounted for by employing 20 earthquake records representing two seismic scenarios, consistent with the latest understanding of the tectonic setting and seismicity of the selected reference region (UAE). A large number of Inelastic Pushover Analyses (IPAs) and Incremental Dynamic Collapse Analyses (IDCAs) were deployed for the reference structures to estimate the seismic design response factors. It is concluded that the factors adopted by the design code are adequately conservative. The results of this systematic assessment of seismic design response factors apply to a wide variety of contemporary concrete wall buildings with various characteristics.

  7. Optimizing the NPP refurbishment environmental qualification design process for an in-service installation

    Energy Technology Data Exchange (ETDEWEB)

    MacBeth, M.J.; Hemmings, R.L. [Canatom-NPM, Oakville, Ontario (Canada)

    2002-07-01

    This paper describes the Environmental Qualification (EQ) modification design work required to upgrade the Reactor Building (RB) airlocks at the Pickering Nuclear Generating Station B Facility. The RB airlocks provide a containment boundary function and are designed to prevent a breach of containment from occurring for all analysed station conditions. Recent, more stringent, Canadian Nuclear Regulatory actions have imposed EQ requirements for the RB airlocks in Canadian Nuclear Generating Stations. The airlocks are required to function under the worst-case design basis accident (DBA) conditions for the assigned mission duration and the design must demonstrate that a spurious door opening cannot be initiated by any accident conditions. This paper reviews key project design activities while providing detailed insights to the potential solution or elimination of some problematic aspects of these types of design activities. General recommendations for optimal technical management of such project implementation issues are presented. (author)

  8. Understanding seismic design criteria for Japanese Nuclear Power Plants

    Energy Technology Data Exchange (ETDEWEB)

    Park, Y.J.; Hofmayer, C.H. [Brookhaven National Lab., Upton, NY (United States); Costello, J.F. [Nuclear Regulatory Commission, Washington, DC (United States)

    1995-04-01

    This paper summarizes the results of recent survey studies on the seismic design practice for nuclear power plants in Japan. The seismic design codes and standards for both nuclear as well as non-nuclear structures have been reviewed and summarized. Some key documents for understanding Japanese seismic design criteria are also listed with brief descriptions. The paper highlights the design criteria to determine the seismic demand and component capacity in comparison with U.S. criteria, the background studies which have led to the current Japanese design criteria, and a survey of current research activities. More detailed technical descriptions are presented on the development of Japanese shear wall equations, design requirements for containment structures, and ductility requirements.

  9. A Conceptual Design of Light-weighted Mobile Robot for the Integrity of SG Tubes in NPP

    Energy Technology Data Exchange (ETDEWEB)

    Seo, Yong Chil; Jeong, Kyung Min; Shin, Ho Chul; Lee, Sung Uk; Cho, Jae Wan; Choi, Young Soo; Kim, Seung Ho [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of); Shin, Chun Sup; Park, Ki Tae [Korea Plant Serviceand Engineering, Busan (Korea, Republic of)

    2010-10-15

    Steam generators (SG) are among the most critical components of pressurized water Nuclear Power Plants (NPP). SG tubes must provide a reliable pressure boundary between the primary and secondary cooling water. It is because that any leakage from tube defects could result in the release of radioactivity to the environment. Thus degradations of steam generators tubes should be monitored and inspected periodically under nuclear regulatory. In-service inspections of SG tubes are carried out using eddy current test (ECT) and the defected tubes are usually plugged. Because the radioactivity in the internal of SG chambers limits free access of human worker, remote manipulators are required. In South Korea, Manipulators such as the Zetec SM series and the Westinghouse ROSA series have been used. Such manipulators are rigidly mounted to manways or tube sheets of SG. Confusions for the inspected tubes may occur from deflection of the manipulators. To reduce the deflections of the manipulators for covering the large working areas of tube sheets, sufficient rigidity is required and it leads to the increase of the weight. Such weight increase results in some difficulties for handling and more radiation exposure of human workers. Recently light-weighed mobile robots have been introduced by Westinghouse and Zetec. The robots can move keeping in contact with the tube sheets using devices which are commonly called cam-locks. They are easier to handle and provide no confusion for the position of the inspected tubes. But when the clamping forces are loosed accidently, they can be fall down and light repair works can be performed. This paper provides the design results for a light weighted mobile robot which is recently being developed in cooperation of our institutes

  10. Nuclear fuel performance in embalse NPP, design optimizations and manufacturing improvements

    Energy Technology Data Exchange (ETDEWEB)

    Alvarez, L.A.; Casario, J.A.; Valesi, J.; Olezza, R. [Unidad Proyectos Especiales Suministros Nucleares, Comision Nacional de Energia Atomica, Buenos Aires (Argentina)

    1997-07-01

    Fuel performance in Embalse Nuclear Power Plant since the beginning of the operation of the commercial fuel manufacturing plant has been encouraging. Failure rates because of manufacturing flaws during the last 3 years is discussed. The total manufacturing failure rate is strongly affected by some 'defect excursions'. The first part of this paper presents the evolution of the failure rate and describes the most important excursions. Despite the good performance of the fuel, new trends in the energy market require more economic fuels. Domestic fuel design optimizations towards this objective are discussed. These changes are mainly referred to an increment of the uranium content in the fuel. Another design changes that are directed to reduce the fuel manufacturing cost are also described. This modifications are in progress and under a qualification program. New manufacturing equipments have been incorporated to reduce the cost of the fuel and to increase the fuel reliability. Some of them have been completely qualified and are fully operational. (author)

  11. Seismic Data Gathering and Validation

    Energy Technology Data Exchange (ETDEWEB)

    Coleman, Justin [Idaho National Lab. (INL), Idaho Falls, ID (United States)

    2015-02-01

    Three recent earthquakes in the last seven years have exceeded their design basis earthquake values (so it is implied that damage to SSC’s should have occurred). These seismic events were recorded at North Anna (August 2011, detailed information provided in [Virginia Electric and Power Company Memo]), Fukushima Daichii and Daini (March 2011 [TEPCO 1]), and Kaswazaki-Kariwa (2007, [TEPCO 2]). However, seismic walk downs at some of these plants indicate that very little damage occurred to safety class systems and components due to the seismic motion. This report presents seismic data gathered for two of the three events mentioned above and recommends a path for using that data for two purposes. One purpose is to determine what margins exist in current industry standard seismic soil-structure interaction (SSI) tools. The second purpose is the use the data to validated seismic site response tools and SSI tools. The gathered data represents free field soil and in-structure acceleration time histories data. Gathered data also includes elastic and dynamic soil properties and structural drawings. Gathering data and comparing with existing models has potential to identify areas of uncertainty that should be removed from current seismic analysis and SPRA approaches. Removing uncertainty (to the extent possible) from SPRA’s will allow NPP owners to make decisions on where to reduce risk. Once a realistic understanding of seismic response is established for a nuclear power plant (NPP) then decisions on needed protective measures, such as SI, can be made.

  12. Investigation of techniques for the development of seismic design basis using the probabilistic seismic hazard analysis

    Energy Technology Data Exchange (ETDEWEB)

    Bernreuter, D.L.; Boissonnade, A.C.; Short, C.M.

    1998-04-01

    The Nuclear Regulatory Commission asked Lawrence Livermore National Laboratory to form a group of experts to assist them in revising the seismic and geologic siting criteria for nuclear power plants, Appendix A to 10 CFR Part 100. This document describes a deterministic approach for determining a Safe Shutdown Earthquake (SSE) Ground Motion for a nuclear power plant site. One disadvantage of this approach is the difficulty of integrating differences of opinions and differing interpretations into seismic hazard characterization. In answer to this, probabilistic seismic hazard assessment methodologies incorporate differences of opinion and interpretations among earth science experts. For this reason, probabilistic hazard methods were selected for determining SSEs for the revised regulation, 10 CFR Part 100.23. However, because these methodologies provide a composite analysis of all possible earthquakes that may occur, they do not provide the familiar link between seismic design loading requirements and engineering design practice. Therefore, approaches used to characterize seismic events (magnitude and distance) which best represent the ground motion level determined with the probabilistic hazard analysis were investigated. This report summarizes investigations conducted at 69 nuclear reactor sites in the central and eastern U.S. for determining SSEs using probabilistic analyses. Alternative techniques are presented along with justification for key choices. 16 refs., 32 figs., 60 tabs.

  13. Determination of Design Basis Earthquake ground motion

    Energy Technology Data Exchange (ETDEWEB)

    Kato, Muneaki [Japan Atomic Power Co., Tokyo (Japan)

    1997-03-01

    This paper describes principle of determining of Design Basis Earthquake following the Examination Guide, some examples on actual sites including earthquake sources to be considered, earthquake response spectrum and simulated seismic waves. In sppendix of this paper, furthermore, seismic safety review for N.P.P designed before publication of the Examination Guide was summarized with Check Basis Earthquake. (J.P.N.)

  14. Seismic fragility assessment of RC frame structure designed according to modern Chinese code for seismic design of buildings

    Science.gov (United States)

    Wu, D.; Tesfamariam, S.; Stiemer, S. F.; Qin, D.

    2012-09-01

    Following several damaging earthquakes in China, research has been devoted to find the causes of the collapse of reinforced concrete (RC) building sand studying the vulnerability of existing buildings. The Chinese Code for Seismic Design of Buildings (CCSDB) has evolved over time, however, there is still reported earthquake induced damage of newly designed RC buildings. Thus, to investigate modern Chinese seismic design code, three low-, mid- and high-rise RC frames were designed according to the 2010 CCSDB and the corresponding vulnerability curves were derived by computing a probabilistic seismic demand model (PSDM).The PSDM was computed by carrying out nonlinear time history analysis using thirty ground motions obtained from the Pacific Earthquake Engineering Research Center. Finally, the PSDM was used to generate fragility curves for immediate occupancy, significant damage, and collapse prevention damage levels. Results of the vulnerability assessment indicate that the seismic demands on the three different frames designed according to the 2010 CCSDB meet the seismic requirements and are almost in the same safety level.

  15. Development of tools to manage the operational monitoring and pre-design of the NPP-LV cycle; Desarrollo de herramientas para administrar el seguimiento operativo y el pre-diseno del ciclo de la CLV

    Energy Technology Data Exchange (ETDEWEB)

    Perusquia, R.; Arredondo S, C.; Hernandez M, J. L.; Montes T, J. L.; Castillo M, A.; Ortiz S, J. J., E-mail: raul.perusquia@inin.gob.mx [ININ, Carretera Mexico-Toluca s/n, 52750 Ocoyoacac, Estado de Mexico (Mexico)

    2015-09-15

    This paper presents the development of tools to facilitate the management so much, the operational monitoring of boiling water reactors (BWR) of the nuclear power plant of Laguna Verde (NPP-LV) through independent codes, and how to carry out the static calculations corresponding to process of optimized pre-design of the reference cycle next to current cycle. The progress and preliminary results obtained with the program SACal, developed at Instituto Nacional de Investigaciones Nucleares (ININ), central tool to achieve provide a management platform of the operational monitoring and pre-design of NPP-LV cycle are also described. The reached preliminary advances directed to get an Analysis center and automated design of fuel assembly cells are also presented, which together with centers or similar modules related with the fuel reloads form the key part to meet the targets set for the realization of a Management Platform of Nuclear Fuel of the NPP-LV. (Author)

  16. Considerations on Seismic Design of Installations using Natural Gas Fuel

    Directory of Open Access Journals (Sweden)

    Adriana Tokar

    2016-10-01

    Full Text Available The paper presents issues relating to existing standards underlying seismic design restrictions for non-structural components (NSC related to constructions. Are presented measures that can be implemented to maintain a high level of safety in case of earthquake, natural gas plants, which due to the flammability of fuel, carry some risk of fire or explosion. The purpose of this paper is to highlight the need for seismic design of facilities using natural gas fuel for new buildings but also to review the existing installations in buildings by taking mandatory measures.

  17. Department of Energy seismic siting and design decisions: Consistent use of probabilistic seismic hazard analysis

    Energy Technology Data Exchange (ETDEWEB)

    Kimball, J.K.; Chander, H.

    1997-02-01

    The Department of Energy (DOE) requires that all nuclear or non-nuclear facilities shall be designed, constructed and operated so that the public, the workers, and the environment are protected from the adverse impacts of Natural Phenomena Hazards including earthquakes. The design and evaluation of DOE facilities to accommodate earthquakes shall be based on an assessment of the likelihood of future earthquakes occurrences commensurate with a graded approach which depends on the potential risk posed by the DOE facility. DOE has developed Standards for site characterization and hazards assessments to ensure that a consistent use of probabilistic seismic hazard is implemented at each DOE site. The criteria included in the DOE Standards are described, and compared to those criteria being promoted by the staff of the Nuclear Regulatory Commission (NRC) for commercial nuclear reactors. In addition to a general description of the DOE requirements and criteria, the most recent probabilistic seismic hazard results for a number of DOE sites are presented. Based on the work completed to develop the probabilistic seismic hazard results, a summary of important application issues are described with recommendations for future improvements in the development and use of probabilistic seismic hazard criteria for design of DOE facilities.

  18. Next generation seismic fragility curves for California bridges incorporating the evolution in seismic design philosophy

    Science.gov (United States)

    Ramanathan, Karthik Narayan

    Quantitative and qualitative assessment of the seismic risk to highway bridges is crucial in pre-earthquake planning, and post-earthquake response of transportation systems. Such assessments provide valuable knowledge about a number of principal effects of earthquakes such as traffic disruption of the overall highway system, impact on the regions’ economy and post-earthquake response and recovery, and more recently serve as measures to quantify resilience. Unlike previous work, this study captures unique bridge design attributes specific to California bridge classes along with their evolution over three significant design eras, separated by the historic 1971 San Fernando and 1989 Loma Prieta earthquakes (these events affected changes in bridge seismic design philosophy). This research developed next-generation fragility curves for four multispan concrete bridge classes by synthesizing new knowledge and emerging modeling capabilities, and by closely coordinating new and ongoing national research initiatives with expertise from bridge designers. A multi-phase framework was developed for generating fragility curves, which provides decision makers with essential tools for emergency response, design, planning, policy support, and maximizing investments in bridge retrofit. This framework encompasses generational changes in bridge design and construction details. Parameterized high-fidelity three-dimensional nonlinear analytical models are developed for the portfolios of bridge classes within different design eras. These models incorporate a wide range of geometric and material uncertainties, and their responses are characterized under seismic loadings. Fragility curves were then developed considering the vulnerability of multiple components and thereby help to quantify the performance of highway bridge networks and to study the impact of seismic design principles on the performance within a bridge class. This not only leads to the development of fragility relations

  19. Preventing Undesirable Seismic Behaviour of Infill Walls in Design Process

    Directory of Open Access Journals (Sweden)

    Azadeh Noorifard

    2017-03-01

    Full Text Available Dividing walls are usually considered as non-structural elements, but experiences of past earthquakes show that some buildings designed and constructed by engineers have been damaged during earthquakes because of disregarding the negative effects of walls. Apart from the poor quality of construction and materials, inattention in design process is the main reason for undesirable seismic behaviour of walls.The main aim of this paper is to investigate the measures taken in different stages of architectural and structural design for improving the seismic behaviour of infilled concrete structures. As a general principle, with the further progress of project from basic architectural design to detailed structural design, there is a need to reduce designer authority and increase obligation, furthermore the cost of project increases too. The conclusion of this study implies that, in order to achieve the desirable seismic behaviour of walls, close collaboration between architects and structural engineers is required from the early stages of design. The results of this study are presented in a check list for designing reinforced concrete (RC moment resisting frame and RC shear wall.

  20. Review of seismicity and ground motion studies related to development of seismic design at SRS

    Energy Technology Data Exchange (ETDEWEB)

    Stephenson, D.E. [Westinghouse Savannah River Co., Aiken, SC (United States); Acree, J.R. [Westinghouse Environmental and Geotechnical Services, Inc., Columbia, SC (United States)

    1992-08-01

    The NRC response spectra developed in Reg. Guide 1.60 is being used in the studies related to restarting of the existing Savannah River Site (SRS) reactors. Because it envelopes all the other site specific spectra which have been developed for SRS, it provides significant conservatism in the design and analysis of the reactor systems for ground motions of this value or with these probability levels. This spectral shape is also the shape used for the design of the recently licensed Vogtle Nuclear Station, located south of the Savannah River from the SRS. This report provides a summary of the data base used to develop the design basis earthquake. This includes the seismicity, rates of occurrence, magnitudes, and attenuation relationships. A summary is provided for the studies performed and methodologies used to establish the design basis earthquake for SRS. The ground motion response spectra developed from the various studies are also summarized. The seismic hazard and PGA`s developed for other critical facilities in the region are discussed, and the SRS seismic instrumentation is presented. The programs for resolving outstanding issues are discussed and conclusions are presented.

  1. Integrated ageing management of Atucha NPP

    Energy Technology Data Exchange (ETDEWEB)

    Ranalli, Juan M.; Marchena, Martin H.; Zorrilla, Jorge R.; Antonaccio, Elvio E.; Brenna, Pablo; Yllanez, Daniela; Cruz, Gerardo Vera de la; Luraschi, Carlos, E-mail: ranalli@cnea.gov.ar [Gerencia Coordinacion Proyectos CNEA-NASA, Comision Nacional de Energia Atomica, Buenos Aires (Argentina); Sabransky, Mario, E-mail: msabransky@na-sa.com.ar [Departamento Gestion de Envejecimiento, Central Nuclear Atucha I-II Nucleoelectrica Argentina S.A., Provincia de Buenos Aires (Argentina)

    2013-07-01

    Atucha NPP is a two PHWR unit site located in Lima, Province of Buenos Aires, 120 km north of Buenos Aires, Argentina. Until recent, the site was split in Atucha I NPP, a 350 MW pressure vessel heavy water reactor in operation since 1974; and Atucha II, a similar design reactor, twice as big as Atucha I finishing a delayed construction. With the start-up of Atucha II and aiming to integrate the management of the plants, the Utility (Nucleolectrica Argentina Sociedad Anonima - NASA) has reorganized its operation units. Within this reorganization, an Ageing Management Department has been created to cope with all ageing issues of both Atucha I and II units. The Atomic Energy Commission of Argentina (Comision Nacional de Energia Atomica - CNEA) is a state-owned R and D organization that; among other functions such as designing and building research reactors, developing uranium mining and supplying radioisotopes to the medical market; is in charge of providing support and technological update to all Argentinean NPPs. The Ageing Management Department of Atucha NPP and the Ageing Management Division of CNEA has formed a joint working group in order to set up an Integrated Ageing Management Program for Atucha NPP following IAEA guidelines. In the present work a summary of the activities, documental structure and first outputs of the Integrated Ageing Management Program of Atucha NPP is presented. (author)

  2. Simplified seismic risk analysis

    Energy Technology Data Exchange (ETDEWEB)

    Pellissetti, Manuel; Klapp, Ulrich [AREVA NP GmbH, Erlangen (Germany)

    2011-07-01

    Within the context of probabilistic safety analysis (PSA) for nuclear power plants (NPP's), seismic risk assessment has the purpose to demonstrate that the contribution of seismic events to overall risk is not excessive. The most suitable vehicle for seismic risk assessment is a full scope seismic PSA (SPSA), in which the frequency of core damage due to seismic events is estimated. An alternative method is represented by seismic margin assessment (SMA), which aims at showing sufficient margin between the site-specific safe shutdown earthquake (SSE) and the actual capacity of the plant. Both methods are based on system analysis (fault-trees and event-trees) and hence require fragility estimates for safety relevant systems, structures and components (SSC's). If the seismic conditions at a specific site of a plant are not very demanding, then it is reasonable to expect that the risk due to seismic events is low. In such cases, the cost-benefit ratio for performing a full scale, site-specific SPSA or SMA will be excessive, considering the ultimate objective of seismic risk analysis. Rather, it will be more rational to rely on a less comprehensive analysis, used as a basis for demonstrating that the risk due to seismic events is not excessive. The present paper addresses such a simplified approach to seismic risk assessment which is used in AREVA to: - estimate seismic risk in early design stages, - identify needs to extend the design basis, - define a reasonable level of seismic risk analysis Starting from a conservative estimate of the overall plant capacity, in terms of the HCLPF (High Confidence of Low Probability of Failure), and utilizing a generic value for the variability, the seismic risk is estimated by convolution of the hazard and the fragility curve. Critical importance is attached to the selection of the plant capacity in terms of the HCLPF, without performing extensive fragility calculations of seismically relevant SSC's. A suitable basis

  3. Integrated seismic design of structure and control systems

    CERN Document Server

    Castaldo, Paolo

    2014-01-01

    The structural optimization procedure presented in this book makes it possible to achieve seismic protection through integrated structural/control system design. In particular, it is explained how slender structural systems with a high seismic performance can be achieved through inclusion of viscous and viscoelastic dampers as an integral part of the system. Readers are provided with essential introductory information on passive structural control and passive energy dissipation systems. Dynamic analyses of both single and multiple degree of freedom systems are performed in order to verify the achievement of pre-assigned performance targets, and it is explained how the optimal integrated design methodology, also relevant to retrofitting of existing buildings, should be applied. The book illustrates how structural control research is opening up new possibilities in structural forms and configurations without compromising structural performance.

  4. Seismic design of earth-retaining structures and foundations

    OpenAIRE

    Choudhury, Deepankar; Sitharam, TG; Rao, Subba KS

    2004-01-01

    Earthquake-resistant design of earth retaining structures like retaining walls, earth dams and foundations are very important problems to minimize the devastating effect of earthquake hazards. In this paper a comprehensive review for different methods to calculate seismic earth pressures and their point of applications is shown. Numerical example shows the merit of a displacement-based analysis over force-based analysis by considering a permissible displacement of the wall.Modification of IS ...

  5. Development of a seismic design procedure for metal building systems

    OpenAIRE

    2007-01-01

    Metal building systems are widely used in low-rise (1- or 2-story) building construction for economic reasons. Maximum cost efficiency is usually achieved through optimization of steel weight and the fabrication process by adopting web-tapered members and bolted end-plate connections. However, the cyclic behavior of this kind of system has not been investigated, and no specific seismic design guidelines are available in the United States. Based on both experimental and analytical studies, thi...

  6. Evaluation of seismic design spectrum based on UHS implementing fourth-generation seismic hazard maps of Canada

    Science.gov (United States)

    Ahmed, Ali; Hasan, Rafiq; Pekau, Oscar A.

    2016-12-01

    Two recent developments have come into the forefront with reference to updating the seismic design provisions for codes: (1) publication of new seismic hazard maps for Canada by the Geological Survey of Canada, and (2) emergence of the concept of new spectral format outdating the conventional standardized spectral format. The fourth -generation seismic hazard maps are based on enriched seismic data, enhanced knowledge of regional seismicity and improved seismic hazard modeling techniques. Therefore, the new maps are more accurate and need to incorporate into the Canadian Highway Bridge Design Code (CHBDC) for its next edition similar to its building counterpart National Building Code of Canada (NBCC). In fact, the code writers expressed similar intentions with comments in the commentary of CHBCD 2006. During the process of updating codes, NBCC, and AASHTO Guide Specifications for LRFD Seismic Bridge Design, American Association of State Highway and Transportation Officials, Washington (2009) lowered the probability level from 10 to 2% and 10 to 5%, respectively. This study has brought five sets of hazard maps corresponding to 2%, 5% and 10% probability of exceedance in 50 years developed by the GSC under investigation. To have a sound statistical inference, 389 Canadian cities are selected. This study shows the implications of the changes of new hazard maps on the design process (i.e., extent of magnification or reduction of the design forces).

  7. Seismic design of RC buildings theory and practice

    CERN Document Server

    Manohar, Sharad

    2015-01-01

    This book is intended to serve as a textbook for engineering courses on earthquake resistant design. The book covers important attributes for seismic design such as material properties, damping, ductility, stiffness and strength. The subject coverage commences with simple concepts and proceeds right up to nonlinear analysis and push-over method for checking building adequacy. The book also provides an insight into the design of base isolators highlighting their merits and demerits. Apart from the theoretical approach to design of multi-storey buildings, the book highlights the care required in practical design and construction of various building components. It covers modal analysis in depth including the important missing mass method of analysis and tension shift in shear walls and beams. These have important bearing on reinforcement detailing. Detailed design and construction features are covered for earthquake resistant design of reinforced concrete as well as confined and reinforced masonry structures. Th...

  8. Seismic design technology for Breeder Reactor structures. Volume 3: special topics in reactor structures

    Energy Technology Data Exchange (ETDEWEB)

    Reddy, D.P. (ed)

    1983-04-01

    This volume is divided into six chapters: analysis techniques, equivalent damping values, probabilistic design factors, design verifications, equivalent response cycles for fatigue analysis, and seismic isolation. (JDB)

  9. Fast Bayesian optimal experimental design for seismic source inversion

    KAUST Repository

    Long, Quan

    2015-07-01

    We develop a fast method for optimally designing experiments in the context of statistical seismic source inversion. In particular, we efficiently compute the optimal number and locations of the receivers or seismographs. The seismic source is modeled by a point moment tensor multiplied by a time-dependent function. The parameters include the source location, moment tensor components, and start time and frequency in the time function. The forward problem is modeled by elastodynamic wave equations. We show that the Hessian of the cost functional, which is usually defined as the square of the weighted L2 norm of the difference between the experimental data and the simulated data, is proportional to the measurement time and the number of receivers. Consequently, the posterior distribution of the parameters, in a Bayesian setting, concentrates around the "true" parameters, and we can employ Laplace approximation and speed up the estimation of the expected Kullback-Leibler divergence (expected information gain), the optimality criterion in the experimental design procedure. Since the source parameters span several magnitudes, we use a scaling matrix for efficient control of the condition number of the original Hessian matrix. We use a second-order accurate finite difference method to compute the Hessian matrix and either sparse quadrature or Monte Carlo sampling to carry out numerical integration. We demonstrate the efficiency, accuracy, and applicability of our method on a two-dimensional seismic source inversion problem. © 2015 Elsevier B.V.

  10. Fast Bayesian Optimal Experimental Design for Seismic Source Inversion

    KAUST Repository

    Long, Quan

    2016-01-06

    We develop a fast method for optimally designing experiments [1] in the context of statistical seismic source inversion [2]. In particular, we efficiently compute the optimal number and locations of the receivers or seismographs. The seismic source is modeled by a point moment tensor multiplied by a time-dependent function. The parameters include the source location, moment tensor components, and start time and frequency in the time function. The forward problem is modeled by the elastic wave equations. We show that the Hessian of the cost functional, which is usually defined as the square of the weighted L2 norm of the difference between the experimental data and the simulated data, is proportional to the measurement time and the number of receivers. Consequently, the posterior distribution of the parameters, in a Bayesian setting, concentrates around the true parameters, and we can employ Laplace approximation and speed up the estimation of the expected Kullback-Leibler divergence (expected information gain), the optimality criterion in the experimental design procedure. Since the source parameters span several magnitudes, we use a scaling matrix for efficient control of the condition number of the original Hessian matrix. We use a second-order accurate finite difference method to compute the Hessian matrix and either sparse quadrature or Monte Carlo sampling to carry out numerical integration. We demonstrate the efficiency, accuracy, and applicability of our method on a two-dimensional seismic source inversion problem.

  11. Design response spectra-compliant real and synthetic GMS for seismic analysis of seismically isolated nuclear reactor containment building

    Energy Technology Data Exchange (ETDEWEB)

    Ali, Ahmer [ENVICO Consultants Co. Ltd., Seoul (Korea, Republic of); Abu-Hayah, Nadin; Kim, Doo Kie [Civil and Environmental Engineering, Kunsan National University, Gunsan (Korea, Republic of); Cho, Sung Gook [Innose Tech Co., Ltd., Incheon (Korea, Republic of)

    2017-06-15

    Due to the severe impacts of recent earthquakes, the use of seismic isolation is paramount for the safety of nuclear structures. The diversity observed in seismic events demands ongoing research to analyze the devastating attributes involved, and hence to enhance the sustainability of base-isolated nuclear power plants. This study reports the seismic performance of a seismically-isolated nuclear reactor containment building (NRCB) under strong short-period ground motions (SPGMs) and long-period ground motions (LPGMs). The United States Nuclear Regulatory Commission-based design response spectrum for the seismic design of nuclear power plants is stipulated as the reference spectrum for ground motion selection. Within the period range(s) of interest, the spectral matching of selected records with the target spectrum is ensured using the spectral-compatibility approach. NRC-compliant SPGMs and LPGMs from the mega-thrust Tohoku earthquake are used to obtain the structural response of the base-isolated NRCB. To account for the lack of earthquakes in low-to-moderate seismicity zones and the gap in the artificial synthesis of long-period records, wavelet-decomposition based autoregressive moving average modeling for artificial generation of real ground motions is performed. Based on analysis results from real and simulated SPGMs versus LPGMs, the performance of NRCBs is discussed with suggestions for future research and seismic provisions.

  12. Highway bridge seismic design: summary of FHWA/MCEER project on seismic vulnerability of new highway construction

    Institute of Scientific and Technical Information of China (English)

    2002-01-01

    The Federal Highway Administration (FHWA) sponsored a large, multi-year project conducted by theMultidisciplinary Center for Earthquake Engineering Research (MCEER) titled "Seismic Vulnerability of New HighwayConstruction" (MCEER Project 112), which was completed in 1998. MCEER coordinated the work of many researchers, whoperformed studies on the seismic design and vulnerability analysis of highway bridges, tunnels, and retaining structures.Extensive research was conducted to provide revisions and improvements to current design and detailing approaches andnational design specifications for highway bridges. The program included both analytical and experimental studies, andaddressed seismic hazard exposure and ground motion input for the U.S. highway system; foundation design and soil behavior;structural importance, analysis, and response; structural design issues and details; and structural design criteria.

  13. Final report of the cooperative study on seismic isolation design. The second stage

    Energy Technology Data Exchange (ETDEWEB)

    Uryu, Mitsuru; Terada, Syuji; Shioya, Tsutomu (and others)

    1999-05-01

    The applicability of the seismic isolation design onto the nuclear fuel facilities, which must clear severe criteria of integrity, has been examined. Following the first stage of the cooperative study, conducted from 1988 to 1991, the second stage included critical vibration testing, seismic observation of seismic isolation building and founded buildings of non-isolation, with the objectives of clarifying the policies on critical design of seismic isolation building. Integrity of the seismic isolation piping system was tested by means of static deformation test, with variable inner water pressure and relative deformation. (Yamamoto, A.)

  14. Study of seismic design bases and site conditions for nuclear power plants

    Energy Technology Data Exchange (ETDEWEB)

    1980-04-01

    This report presents the results of an investigation of four topics pertinent to the seismic design of nuclear power plants: Design accelerations by regions of the continental United States; review and compilation of design-basis seismic levels and soil conditions for existing nuclear power plants; regional distribution of shear wave velocity of foundation materials at nuclear power plant sites; and technical review of surface-founded seismic analysis versus embedded approaches.

  15. Design of engineered cementitious composites for ductile seismic resistant elements

    Science.gov (United States)

    Kanda, Tetsushi

    This dissertation focuses on designing Engineered Cementitious Composite (ECC) to achieve high performance seismic resistant elements. To attain this goal, three major tasks have been accomplished. Task 1 aims at achieving new ECCs involving low cost fiber, which often involve fiber rupture in crack bridging, thus named as "Fiber Rupture Type ECC". Achieving the new ECC requires a new practical and comprehensive composite design theory. For this theory, single fiber behavior was first investigated. Specifically, fiber rupture in composite and chemical bond in fiber/matrix interface were experimentally examined and mathematically modeled. Then this model for single fiber behavior was implemented into a proposed bridging law, a theoretical model for relationship between fiber bridging stress of composite and Crack Opening Displacement (COD). This new bridging law was finally employed to establish a new composite design theory. Task 2 was initiated to facilitate structural interpretation of ECC's material behavior investigated in Task 1. For this purpose, uniaxial tensile behavior, one of the most important ECC's properties, was theoretically characterized with stress-strain relation from micromechanics view point. As a result, a theory is proposed to express ECC's tensile stress-strain relation in terms of micromechanics parameters of composites, such as bond strengths. Task 3 primarily demonstrates an integrated design scheme for ductile seismic elements that covers from micromechanics in single fiber level to structural design tool, such as with non-linear FEM analysis. The significance of this design scheme is that the influences of ECC's microstructure on element's structural performance is quantitatively captured. This means that a powerful tool is obtained for tailoring constitutive micromechanics parameters in order to maximize structural performance of elements. While the tool is still preliminary, completing this tool in future studies will enable one to

  16. Study of rationalized safety design based on the seismic PSA for an LMFBR

    Energy Technology Data Exchange (ETDEWEB)

    Nakai, Ryodai; Yamaguchi, Akira

    1998-12-01

    Seismic PSA was carried out for a typical liquid metal cooled fast breeder reactor (LMFBR) in order to study the rationalized seismic design, maintaining and/or improving safety during seismic event. The seismic sequence quantification identifies the dominant structures, systems and components (SSCs) to the seismic core damage frequency (CDF). The sensitivity analyses by reducing or increasing the seismic capacity for SSCs are used to examine the optimized seismic design in view of safety and economical aspects. The LMFBR-specific risk-significant SSCs are reactor coolant boundary, decay heat removal coolant path and reactor control rod, which are different from those of light water reactors (LWRs). The electrical power supply system has a minor contribution to the seismic CDF. The sensitivity study shows that passive safety features of LMFBRs are important to maintain and/or enhance seismic capacity. The passive safety includes the decay heat removal capability via natural circulation and safety measures without depending on the support systems such as alternating current (AC) electrical power, for example. On the course of seismic sequence quantification, a methodology to evaluate the probability of seismic-induced multiple failure has been developed and applied to the decay heat removal function. The results suggest the multiplicity of the triply redundant system is to be considered for the significant components such as the decay heat removal path when one considers the difference in the seismic response.

  17. NSR&D Program Fiscal Year (FY) 2015 Call for Proposals Mitigation of Seismic Risk at Nuclear Facilities using Seismic Isolation

    Energy Technology Data Exchange (ETDEWEB)

    Coleman, Justin [Idaho National Lab. (INL), Idaho Falls, ID (United States)

    2015-02-01

    Seismic isolation (SI) has the potential to drastically reduce seismic response of structures, systems, or components (SSCs) and therefore the risk associated with large seismic events (large seismic event could be defined as the design basis earthquake (DBE) and/or the beyond design basis earthquake (BDBE) depending on the site location). This would correspond to a potential increase in nuclear safety by minimizing the structural response and thus minimizing the risk of material release during large seismic events that have uncertainty associated with their magnitude and frequency. The national consensus standard America Society of Civil Engineers (ASCE) Standard 4, Seismic Analysis of Safety Related Nuclear Structures recently incorporated language and commentary for seismically isolating a large light water reactor or similar large nuclear structure. Some potential benefits of SI are: 1) substantially decoupling the SSC from the earthquake hazard thus decreasing risk of material release during large earthquakes, 2) cost savings for the facility and/or equipment, and 3) applicability to both nuclear (current and next generation) and high hazard non-nuclear facilities. Issue: To date no one has evaluated how the benefit of seismic risk reduction reduces cost to construct a nuclear facility. Objective: Use seismic probabilistic risk assessment (SPRA) to evaluate the reduction in seismic risk and estimate potential cost savings of seismic isolation of a generic nuclear facility. This project would leverage ongoing Idaho National Laboratory (INL) activities that are developing advanced (SPRA) methods using Nonlinear Soil-Structure Interaction (NLSSI) analysis. Technical Approach: The proposed study is intended to obtain an estimate on the reduction in seismic risk and construction cost that might be achieved by seismically isolating a nuclear facility. The nuclear facility is a representative pressurized water reactor building nuclear power plant (NPP) structure

  18. Suomi Npp Products Performance

    Science.gov (United States)

    Zhou, L.

    2014-12-01

    A suite of Sensor Data Records (SDRs) and Environment Data Records (EDRs) is generated from the Joint Polar Satellite System (JPSS) operational environmental satellite system. The products include atmospheric, ocean, land surface and cryospheric products from the Visible Infrared Imaging Radiometer Suite (VIIRS); atmospheric sounding products from the Cross-track Infrared Sounder (CrIS) and the Advance Technology Microwave Sounder (ATMS); and ozone products from the Ozone Mapping and Profiler Suite (OMPS). These EDRs undergo a rigorous validation process and algorithm updates to achieve a product maturity needed for end user applications. Since the successful launch of Suomi National Polar Partnership (SNPP) satellite in October 2011, significant progresses have been made on calibration and validation of the SNPP data products. By far all products were publicly available and most products were ready for operational evaluation. Most products also are expected to meet requirements and work is underway to reach validated maturity status and fully operational use. Further developments and improvements of the algorithms for J1 have been planned based on the JPSS requirements and lessons learned from SNPP. Sensitivity and impact studies are performed as sensor test data become available. For the majority of data products, no significant changes in sensor input and corresponding sensor degradation are expected. However, the J1 products will undergo the same rigorous calibration and validation process as the S-NPP products once the on-orbit data are available. The schedule for the maturity of the J1 data products however is expected to be accelerated compared to that for S-NPP as lessons learned from the S-NPP mission will be applied to the J1 satellite data. In the presentation, we will provide an overview of the latest SNPP data products' quality status and the plan forward for JPSS-1 algorithm updates.

  19. Performance-Based Seismic Design of Bitlis River Viaduct Based on Damage Control Using Seismic Isolation and Energy Dissipation Devices

    Science.gov (United States)

    Dicleli, Murat; Salem Milani, Ali

    2017-06-01

    This paper presents a sample application of seismic isolation techniques in performance-based design of a major viaduct. The Bitlis River viaduct is located in a seismically active region. The targeted performance goal required no damage at 475-year return period earthquake and repairable damage at 2475-year return period earthquake. The bridge is designed with a seismic isolation system composed of spherical bearings and MRSD (Multidirectional Re-centering steel Damper) hysteretic dampers. The MRSD is a recently-developed hysteretic damper with a controllable post-elastic stiffness. To keep the dampers from being activated during the thermal displacements, the attachment of the dampers to the deck are made through elongated holes oriented in the longitudinal direction of the bridge. The gaps are sized based on the amount of expected maximum thermal displacement in each pier. The gap length is thus different for different piers. This means that the number of the dampers to be engaged during an earthquake will depend on the intensity of the displacements. The distinct feature in this design is how it achieves double purpose: (i)preventing the dampers from engagement during service life as a result of thermal displacements and (ii) sequential engagement of the dampers depending on the level of seismically-induced displacements. The paper presents the basic design features of this seismically isolated bridge designed based on performance-based principles, a brief description of the newly-developed damper and a summary of analyses results.

  20. Seismic resistance design of nuclear power plant building structures in Japan

    Energy Technology Data Exchange (ETDEWEB)

    Kitano, Takehito [Kansai Electric Power Co., Inc., Osaka (Japan)

    1997-03-01

    Japan is one of the countries where earthquakes occur most frequently in the world and has incurred a lot of disasters in the past. Therefore, the seismic resistance design of a nuclear power plant plays a very important role in Japan. This report describes the general method of seismic resistance design of a nuclear power plant giving examples of PWR and BWR type reactor buildings in Japan. Nuclear facilities are classified into three seismic classes and is designed according to the corresponding seismic class in Japan. Concerning reactor buildings, the short-term allowable stress design is applied for the S1 seismic load and it is confirmed that the structures have a safety margin against the S2 seismic load. (J.P.N.)

  1. U.S. Seismic Design Maps Web Application

    Science.gov (United States)

    Martinez, E.; Fee, J.

    2015-12-01

    The application computes earthquake ground motion design parameters compatible with the International Building Code and other seismic design provisions. It is the primary method for design engineers to obtain ground motion parameters for multiple building codes across the country. When designing new buildings and other structures, engineers around the country use the application. Users specify the design code of interest, location, and other parameters to obtain necessary ground motion information consisting of a high-level executive summary as well as detailed information including maps, data, and graphs. Results are formatted such that they can be directly included in a final engineering report. In addition to single-site analysis, the application supports a batch mode for simultaneous consideration of multiple locations. Finally, an application programming interface (API) is available which allows other application developers to integrate this application's results into larger applications for additional processing. Development on the application has proceeded in an iterative manner working with engineers through email, meetings, and workshops. Each iteration provided new features, improved performance, and usability enhancements. This development approach positioned the application to be integral to the structural design process and is now used to produce over 1800 reports daily. Recent efforts have enhanced the application to be a data-driven, mobile-first, responsive web application. Development is ongoing, and source code has recently been published into the open-source community on GitHub. Open-sourcing the code facilitates improved incorporation of user feedback to add new features ensuring the application's continued success.

  2. Analysis and selection of high pressure heaters design for a new generation of NPP with BN-1200 reactor plant

    Science.gov (United States)

    Yurchenko, A. Yu.; Sukhorukov, Yu. G.; Trifonov, N. N.; Grigor'eva, E. B.; Esin, S. B.; Svyatkin, F. A.; Nikolaenkova, E. K.; Prikhod'ko, P. Yu.; Nazarov, V. V.

    2016-09-01

    In the development of advanced high-power steam-turbine plants (STP), special attention is placed on the design of reliable and economical high-pressure heater (HPH) capable to maintain the specified thermal hydraulic performance during the entire service life. Comparative analysis of the known designs of HPH, such as the spiral-collector HPH, the collector-coiled HPH, the collector-platen HPH, modular HPH, and the chamber HPH, was carried out. The advantages and disadvantages of each design were pointed. For better comparison, the heaters are separated into two groups—horizontal and vertical ones. The weight and dimension characteristics, the materials and features of the basic elements, and operating features of variety HPH are presented. At operating the spiral-collector HPH used in the majority of regenerative schemes of high-pressure STP of thermal and nuclear power plants, the disadvantages reducing the economy and reliability of their operation were revealed. The recommendations directed to the reliability growth of HPH, the decrease of subcooling the feed water, the increase of compactness are stated. Some of these were developed by the specialists of OAO NPO TsKTI and are successfully implemented on the thermal power plants and nuclear power plants. Technical solutions to reduce the cost of regeneration system and the weight of chamber HPH, reduce the thickness of the tube plate of HPH, and reliability assurance of the cooler of steam and condensate built in the HPH casing under all operating conditions were proposed. Three types of feed water chambers for vertical and horizontal chamber HPH are considered in detail, the constructive solutions that have been implemented in HPH of the regeneration system of turbines of 1000 and 1200 MW capacity with water-moderated water-cooled power reactor (WMWCPR) are described. The optimal design of HPH for the regeneration system of high-pressure turbine plant with BN-1200 reactor was selected.

  3. Seismic design of equipment and piping systems for nuclear power plants in Japan

    Energy Technology Data Exchange (ETDEWEB)

    Minematsu, Akiyoshi [Tokyo Electric Power Co., Inc. (Japan)

    1997-03-01

    The philosophy of seismic design for nuclear power plant facilities in Japan is based on `Examination Guide for Seismic Design of Nuclear Power Reactor Facilities: Nuclear Power Safety Committee, July 20, 1981` (referred to as `Examination Guide` hereinafter) and the present design criteria have been established based on the survey of governmental improvement and standardization program. The detailed design implementation procedure is further described in `Technical Guidelines for Aseismic Design of Nuclear Power Plants, JEAG4601-1987: Japan Electric Association`. This report describes the principles and design procedure of the seismic design of equipment/piping systems for nuclear power plant in Japan. (J.P.N.)

  4. Seismic behavior and design of wall-EDD-frame systems

    Directory of Open Access Journals (Sweden)

    Oren eLavan

    2015-06-01

    Full Text Available Walls and frames have different deflection lines and, depending on the seismic mass they support, may often poses different natural periods. In many cases, wall-frame structures present an advantageous behavior. In these structures the walls and the frames are rigidly connected. Nevertheless, if the walls and the frames were not rigidly connected, an opportunity for an efficient passive control strategy would arise: Connecting the two systems by energy dissipation devices (EDDs to result in wall-EDD-frame systems. This, depending on the parameters of the system, is expected to lead to an efficient energy dissipation mechanism.This paper studies the seismic behavior of wall-EDD-frame systems in the context of retrofitting existing frame structures. The controlling non-dimensional parameters of such systems are first identified. This is followed by a rigorous and extensive parametric study that reveals the pros and cons of the new system versus wall-frame systems. The effect of the controlling parameters on the behavior of the new system are analyzed and discussed. Finally, tools are given for initial design of such retrofitting schemes. These enable both choosing the most appropriate retrofitting alternative and selecting initial values for its parameters.

  5. Structural seismic upgrading of NPPs in Czech and Slovak republics

    Energy Technology Data Exchange (ETDEWEB)

    David, M. [DAVID Consulting, Engineering and Design Office, Prague (Czech Republic)

    1997-03-01

    Several Nuclear Power Plants of the VVER type has been constructed during the past years in former Czechoslovak Republic. Some of them has been already put in operation and some of them are under construction. Nuclear Power Plants V1(2 units of VVER 440/230), V2(2 units of VVER 440/213) in Slovak and NPP Dukovany (4 units of VVER 440/213) in Czech republic are in operation. NPP Mochovce (4 units of VVER 440/213) in Slovak and NPP Temelin (4 units reduced now to 2 units VVER 1000) have been already almost completed, but still under construction. All above cited NPPs have not been either explicitly designed against earthquake or the design against earthquake or its input data must be upgraded to be compatible with present requirements. The upgrading of seismic input as well the seismic upgrading of all structures and technological equipments for so many NPPs has involved a lot of comprehensive work in Czech as well as in Slovak republics. The upgrading cannot be completed in a short time and as a rule the seismic upgrading has been usually performed in several steps, beginning with the most important arrangements against seismic hazard. The basic principles and requirements for seismic upgrading has been defined in accordance with the international and particularly with the IAEA recommendations. About the requirements for seismic upgrading of NPPs in Czech and Slovak republics will be reported in other contribution. This contribution is dealing with the problems of seismic upgrading of NNPs civil engineering structures. The aim of this contribution is to point out some specific problems connected firstly with very complicated concept of Versa structures and secondly with the difficult task to increase the structural capacity to the required seismic level. (J.P.N.)

  6. Evaluation of fatigue vessel in the Sta. M Garona NPP : real transients and design transients; Evaluacion de la fatiga en la vasija de CN Santa M de Garona: transitorios reales frente a transitorios de diseno

    Energy Technology Data Exchange (ETDEWEB)

    Martin, J.; Gorrochategui, I.

    2005-07-01

    The number of transient that control the fatigue of its reactor pressure vessel is included in the Sta. M Garona NPP Technical Specifications, being the different transients described in the design specification of the corresponding component. In this work, on the one hand, the description of the design transients with their corresponding real ones is compared and, on the other hand, the number of occurrences and the number of transients originally estimated is also compared. In both cases the influence of the difference between design and reality in the fatigue usage is discussed. (Author)

  7. Seismic soil–structure interaction analysis of a nuclear power plant building founded on soil and in degraded concrete stiffness condition

    Energy Technology Data Exchange (ETDEWEB)

    Farahani, Reza V., E-mail: reza.farahani@rizzoassoc.com; Dessalegn, Tewodros M., E-mail: tewodros.dessalegn@rizzoassoc.com; Vaidya, Nishikant R., E-mail: nish.vaidya@rizzoassoc.com; Bazan-Zurita, Enrique, E-mail: enrique.bazanz@rizzoassoc.com

    2016-02-15

    . Therefore, it is important to consider SSI parameter variability in the seismic design or evaluation of NPP buildings that bear on soil.

  8. Report of the US Nuclear Regulatory Commission Piping Review Committee. Volume 2. Evaluation of seismic designs: a review of seismic design requirements for Nuclear Power Plant Piping

    Energy Technology Data Exchange (ETDEWEB)

    1985-04-01

    This document reports the position and recommendations of the NRC Piping Review Committee, Task Group on Seismic Design. The Task Group considered overlapping conservation in the various steps of seismic design, the effects of using two levels of earthquake as a design criterion, and current industry practices. Issues such as damping values, spectra modification, multiple response spectra methods, nozzle and support design, design margins, inelastic piping response, and the use of snubbers are addressed. Effects of current regulatory requirements for piping design are evaluated, and recommendations for immediate licensing action, changes in existing requirements, and research programs are presented. Additional background information and suggestions given by consultants are also presented.

  9. Report of the US Nuclear Regulatory Commission Piping Review Committee. Volume 2. Evaluation of seismic designs: a review of seismic design requirements for Nuclear Power Plant Piping

    Energy Technology Data Exchange (ETDEWEB)

    1985-04-01

    This document reports the position and recommendations of the NRC Piping Review Committee, Task Group on Seismic Design. The Task Group considered overlapping conservation in the various steps of seismic design, the effects of using two levels of earthquake as a design criterion, and current industry practices. Issues such as damping values, spectra modification, multiple response spectra methods, nozzle and support design, design margins, inelastic piping response, and the use of snubbers are addressed. Effects of current regulatory requirements for piping design are evaluated, and recommendations for immediate licensing action, changes in existing requirements, and research programs are presented. Additional background information and suggestions given by consultants are also presented.

  10. Hydrodynamic model of Fukushima-Daiichi NPP Industrial site flooding

    CERN Document Server

    Vaschenko, V N; Gerasimenko, T V; Vachev, B

    2014-01-01

    While the Fukushima-Daiichi was designed and constructed the maximal tsunami height estimate was about 3 m based on analysis of statistical data including Chile earthquake in 1960. The NPP project industrial site height was 10 m. The further deterministic estimates TPCO-JSCE confirmed the impossibility of the industrial site flooding by a tsunami and therefore confirmed ecological safety of the NPP. However, as a result of beyond design earthquake of 11 March 2011 the tsunami height at the shore near the Fukushima-Daiichi NPP reached 15 m. This led to flooding and severe emergencies having catastrophic environmental consequences. This paper proposes hydrodynamic model of tsunami emerging and traveling based on conservative assumptions. The possibility of a tsunami wave reaching 15 m height at the Fukushima-Daiichi NPP shore was confirmed for deduced hydrodynamic resistance coefficient of 1.8. According to the model developed a possibility of flooding is determined not only by the industrial site height, magni...

  11. Towards Improved Considerations of Risk in Seismic Design (Plinius Medal Lecture)

    Science.gov (United States)

    Sullivan, T. J.

    2012-04-01

    The aftermath of recent earthquakes is a reminder that seismic risk is a very relevant issue for our communities. Implicit within the seismic design standards currently in place around the world is that minimum acceptable levels of seismic risk will be ensured through design in accordance with the codes. All the same, none of the design standards specify what the minimum acceptable level of seismic risk actually is. Instead, a series of deterministic limit states are set which engineers then demonstrate are satisfied for their structure, typically through the use of elastic dynamic analyses adjusted to account for non-linear response using a set of empirical correction factors. From the early nineties the seismic engineering community has begun to recognise numerous fundamental shortcomings with such seismic design procedures in modern codes. Deficiencies include the use of elastic dynamic analysis for the prediction of inelastic force distributions, the assignment of uniform behaviour factors for structural typologies irrespective of the structural proportions and expected deformation demands, and the assumption that hysteretic properties of a structure do not affect the seismic displacement demands, amongst other things. In light of this a number of possibilities have emerged for improved control of risk through seismic design, with several innovative displacement-based seismic design methods now well developed. For a specific seismic design intensity, such methods provide a more rational means of controlling the response of a structure to satisfy performance limit states. While the development of such methodologies does mark a significant step forward for the control of seismic risk, they do not, on their own, identify the seismic risk of a newly designed structure. In the U.S. a rather elaborate performance-based earthquake engineering (PBEE) framework is under development, with the aim of providing seismic loss estimates for new buildings. The PBEE framework

  12. Yield Frequency Spectra and seismic design of code-compatible RC structures: an illustrative example

    DEFF Research Database (Denmark)

    Katsanos, Evangelos; Vamvatsikos, Dimitrios

    2017-01-01

    to redesign the resulting structure working backwards from the desired MAF of response (rather than intensity) to estimate an appropriate value of seismic intensity for use within a typical engineering design process. For this high-seismicity and high-importance midrise building, a stiffer system with higher...

  13. Life cycle and performance based seismic design of major bridges in China

    Institute of Scientific and Technical Information of China (English)

    FAN Lichu

    2007-01-01

    The idea of life cycle and performance based seismic design of major bridges is introduced.Based on the key components and non-key components of a bridge and the consideration of the inspectability,replaceability,reparability,controllability and retrofitability of the bridge components,different seismic design levels and expected performance objectives are suggested for the major bridges in China.The vulnerability analysis and progressive collapse analysis,as well as risk assessment,are also proposed to be the important issues to study in order to guide the seismic design of major bridges in the future.

  14. STATE OF THE ART OF SEISMIC DESIGN OF RC PRECAST FARM BUILDINGS

    Directory of Open Access Journals (Sweden)

    Patrizia Tassinari

    2008-06-01

    Full Text Available Structural design of rural buildings deals with several requirements, among which seismic resistance. In this study the state of the art of Italian seismic zoning and its possible consequences over the design of rural buildings are analyzed. Study cases are proposed referring to a municipality of Emilia-Romagna region, regarding precast concrete structures, that are widely employed in farms. Linear and non linear criteria are adopted for modelling seismic-resistant elements. Pushover analyses are performed to verify the designed structures. Results are expressed in terms of parameters quantifying structural reliability and construction costs.

  15. Seismic Analysis Issues in Design Certification Applications for New Reactors

    Energy Technology Data Exchange (ETDEWEB)

    Miranda, M.; Morante, R.; Xu, J.

    2011-07-17

    The licensing framework established by the U.S. Nuclear Regulatory Commission under Title 10 of the Code of Federal Regulations (10 CFR) Part 52, “Licenses, Certifications, and Approvals for Nuclear Power Plants,” provides requirements for standard design certifications (DCs) and combined license (COL) applications. The intent of this process is the early reso- lution of safety issues at the DC application stage. Subsequent COL applications may incorporate a DC by reference. Thus, the COL review will not reconsider safety issues resolved during the DC process. However, a COL application that incorporates a DC by reference must demonstrate that relevant site-specific de- sign parameters are within the bounds postulated by the DC, and any departures from the DC need to be justified. This paper provides an overview of several seismic analysis issues encountered during a review of recent DC applications under the 10 CFR Part 52 process, in which the authors have participated as part of the safety review effort.

  16. Suomi NPP Ground System Performance

    Science.gov (United States)

    Grant, K. D.; Bergeron, C.

    2013-12-01

    The National Oceanic and Atmospheric Administration (NOAA) and National Aeronautics and Space Administration (NASA) are jointly acquiring the next-generation civilian weather and environmental satellite system: the Joint Polar Satellite System (JPSS). JPSS will replace the afternoon orbit component and ground processing system of the current Polar-orbiting Operational Environmental Satellites (POES) managed by NOAA. The JPSS satellites will carry a suite of sensors designed to collect meteorological, oceanographic, climatological and geophysical observations of the Earth. The first satellite in the JPSS constellation, known as the Suomi National Polar-orbiting Partnership (Suomi NPP) satellite, was launched on 28 October 2011, and is currently undergoing product calibration and validation activities. As products reach a beta level of maturity, they are made available to the community through NOAA's Comprehensive Large Array-data Stewardship System (CLASS). CGS's data processing capability processes the satellite data from the Joint Polar Satellite System satellites to provide environmental data products (including Sensor Data Records (SDRs) and Environmental Data Records (EDRs)) to NOAA and Department of Defense (DoD) processing centers operated by the United States government. CGS is currently processing and delivering SDRs and EDRs for Suomi NPP and will continue through the lifetime of the Joint Polar Satellite System programs. Following the launch and sensor activation phase of the Suomi NPP mission, full volume data traffic is now flowing from the satellite through CGS's C3, data processing, and data delivery systems. Ground system performance is critical for this operational system. As part of early system checkout, Raytheon measured all aspects of data acquisition, routing, processing, and delivery to ensure operational performance requirements are met, and will continue to be met throughout the mission. Raytheon developed a tool to measure, categorize, and

  17. Design and development of digital seismic amplifier recorder

    Energy Technology Data Exchange (ETDEWEB)

    Samsidar, Siti Alaa; Afuar, Waldy; Handayani, Gunawan, E-mail: gunawanhandayani@gmail.com [Department of Physics, ITB (Indonesia)

    2015-04-16

    A digital seismic recording is a recording technique of seismic data in digital systems. This method is more convenient because it is more accurate than other methods of seismic recorders. To improve the quality of the results of seismic measurements, the signal needs to be amplified to obtain better subsurface images. The purpose of this study is to improve the accuracy of measurement by amplifying the input signal. We use seismic sensors/geophones with a frequency of 4.5 Hz. The signal is amplified by means of 12 units of non-inverting amplifier. The non-inverting amplifier using IC 741 with the resistor values 1KΩ and 1MΩ. The amplification results were 1,000 times. The results of signal amplification converted into digital by using the Analog Digital Converter (ADC). Quantitative analysis in this study was performed using the software Lab VIEW 8.6. The Lab VIEW 8.6 program was used to control the ADC. The results of qualitative analysis showed that the seismic conditioning can produce a large output, so that the data obtained is better than conventional data. This application can be used for geophysical methods that have low input voltage such as microtremor application.

  18. Design and development of digital seismic amplifier recorder

    Science.gov (United States)

    Samsidar, Siti Alaa; Afuar, Waldy; Handayani, Gunawan

    2015-04-01

    A digital seismic recording is a recording technique of seismic data in digital systems. This method is more convenient because it is more accurate than other methods of seismic recorders. To improve the quality of the results of seismic measurements, the signal needs to be amplified to obtain better subsurface images. The purpose of this study is to improve the accuracy of measurement by amplifying the input signal. We use seismic sensors/geophones with a frequency of 4.5 Hz. The signal is amplified by means of 12 units of non-inverting amplifier. The non-inverting amplifier using IC 741 with the resistor values 1KΩ and 1MΩ. The amplification results were 1,000 times. The results of signal amplification converted into digital by using the Analog Digital Converter (ADC). Quantitative analysis in this study was performed using the software Lab VIEW 8.6. The Lab VIEW 8.6 program was used to control the ADC. The results of qualitative analysis showed that the seismic conditioning can produce a large output, so that the data obtained is better than conventional data. This application can be used for geophysical methods that have low input voltage such as microtremor application.

  19. Overcoming barriers to high performance seismic design using lessons learned from the green building industry

    Science.gov (United States)

    Glezil, Dorothy

    NEHRP's Provisions today currently governing conventional seismic resistant design. These provisions, though they ensure the life-safety of building occupants, extensive damage and economic losses may still occur in the structures. This minimum performance can be enhanced using the Performance-Based Earthquake Engineering methodology and passive control systems like base isolation and energy dissipation systems. Even though these technologies and the PBEE methodology are effective reducing economic losses and fatalities during earthquakes, getting them implemented into seismic resistant design has been challenging. One of the many barriers to their implementation has been their upfront costs. The green building community has faced some of the same challenges that the high performance seismic design community currently faces. The goal of this thesis is to draw on the success of the green building industry to provide recommendations that may be used overcome the barriers that high performance seismic design (HPSD) is currently facing.

  20. Probabilistic seismic safety assessment of a CANDU 6 nuclear power plant including ambient vibration tests: Case study

    Energy Technology Data Exchange (ETDEWEB)

    Nour, Ali [Hydro Québec, Montréal, Québec H2L4P5 (Canada); École Polytechnique de Montréal, Montréal, Québec H3C3A7 (Canada); Cherfaoui, Abdelhalim; Gocevski, Vladimir [Hydro Québec, Montréal, Québec H2L4P5 (Canada); Léger, Pierre [École Polytechnique de Montréal, Montréal, Québec H3C3A7 (Canada)

    2016-08-01

    Highlights: • In this case study, the seismic PSA methodology adopted for a CANDU 6 is presented. • Ambient vibrations testing to calibrate a 3D FEM and to reduce uncertainties is performed. • Procedure for the development of FRS for the RB considering wave incoherency effect is proposed. • Seismic fragility analysis for the RB is presented. - Abstract: Following the 2011 Fukushima Daiichi nuclear accident in Japan there is a worldwide interest in reducing uncertainties in seismic safety assessment of existing nuclear power plant (NPP). Within the scope of a Canadian refurbishment project of a CANDU 6 (NPP) put in service in 1983, structures and equipment must sustain a new seismic demand characterised by the uniform hazard spectrum (UHS) obtained from a site specific study defined for a return period of 1/10,000 years. This UHS exhibits larger spectral ordinates in the high-frequency range than those used in design. To reduce modeling uncertainties as part of a seismic probabilistic safety assessment (PSA), Hydro-Québec developed a procedure using ambient vibrations testing to calibrate a detailed 3D finite element model (FEM) of the containment and reactor building (RB). This calibrated FE model is then used for generating floor response spectra (FRS) based on ground motion time histories compatible with the UHS. Seismic fragility analyses of the reactor building (RB) and structural components are also performed in the context of a case study. Because the RB is founded on a large circular raft, it is possible to consider the effect of the seismic wave incoherency to filter out the high-frequency content, mainly above 10 Hz, using the incoherency transfer function (ITF) method. This allows reducing significantly the non-necessary conservatism in resulting FRS, an important issue for an existing NPP. The proposed case study, and related methodology using ambient vibration testing, is particularly useful to engineers involved in seismic re-evaluation of

  1. Evaluating some Reliability Analysis Methodologies in Seismic Design

    Directory of Open Access Journals (Sweden)

    A. E. Ghoulbzouri

    2011-01-01

    Full Text Available Problem statement: Accounting for uncertainties that are present in geometric and material data of reinforced concrete buildings is performed in this study within the context of performance based seismic engineering design. Approach: Reliability of the expected performance state is assessed by using various methodologies based on finite element nonlinear static pushover analysis and specialized reliability software package. Reliability approaches that were considered included full coupling with an external finite element code and surface response based methods in conjunction with either first order reliability method or importance sampling method. Various types of probability distribution functions that model parameters uncertainties were introduced. Results: The probability of failure according to the used reliability analysis method and to the selected distribution of probabilities was obtained. Convergence analysis of the importance sampling method was performed. The required duration of analysis as function of the used reliability method was evaluated. Conclusion/Recommendations: It was found that reliability results are sensitive to the used reliability analysis method and to the selected distribution of probabilities. Durations of analysis for coupling methods were found to be higher than those associated to surface response based methods; one should however include time needed to derive these lasts. For the reinforced concrete building considered in this study, it was found that significant variations exist between all the considered reliability methodologies. The full coupled importance sampling method is recommended, but the first order reliability method applied on a surface response model can be used with good accuracy. Finally, the distributions of probabilities should be carefully identified since giving the mean and the standard deviation were found to be insufficient.

  2. Seismic hazard mitigation for nuclear power plant

    Institute of Scientific and Technical Information of China (English)

    Frieder Seible

    2013-01-01

    The seismic safety of nuclear power plant(NPP) has always been a major consideration in the site selection,design,operation,and more recently recertification of existing installations.In addition to the actual NPP and all their operational and safety related support systems,the storage of spent fuel in temporary or permanent storage facilities also poses a seismic risk.This seismic risk is typically assessed with state-of-the-art modeling and analytical tools that capture everything from the ground rupture or source of the earthquake to the site specific ground shaking,taking geotechnical parameters and soil-foundation-structure-interaction (SFSI) into account to the non-linear structural response of the reactor core,the containment structure,the core cooling system and the emergency cooling system(s),to support systems,piping systems and non-structural components,and finally the performance of spent fuel storage in the probabilistically determined operational basis earthquake (OBE) or the safe shutdown earthquake (SSE) scenario.The best and most meaningful validation and verification of these advanced analytical tools is in the form of full or very large scale experimental testing,designed and conducted in direct support of model and analysis tool calibration.This paper outlines the principles under which such calibration testing should be conducted and illustrates with examples the kind of testing and parameter evaluation required.

  3. The Ductile Design Concept for Seismic Actions in Miscellaneous Design Codes

    Directory of Open Access Journals (Sweden)

    M. Budescu

    2009-01-01

    Full Text Available The concept of ductility estimates the capacity of the structural system and its components to deform prior to collapse, without a substantial loss of strength, but with an important energy amount dissipated. Consistent with the „Applied Technology Council” (ATC-34, from 1995, it was agreed that the reduction seismic response factor to decrease the design force. The purpose of this factor is to transpose the nonlinear behaviour of the structure and the energy dissipation capacity in a simplified form that can be used in the design stage. Depending on the particular structural model and the design standard the used values are different. The paper presents the characteristics of the ductility concept for the structural system. Along with this the general way of computing the reserve factor with the necessary explanations for the parameters that determine the behaviour factor are described. The purpose of this paper is to make a comparison between different international norms for the values and the distribution of the behaviour factor. The norms from the following countries are taken into consideration: the United States of America, New Zealand, Japan, Romania and the European general seismic code.

  4. Re-evaluation of seismic design for JOYO buildings and equipments

    Energy Technology Data Exchange (ETDEWEB)

    Isozaki, K.; Tomita, N. [Power Reactor and Nuclear Fuel Development Corp., Oarai, Ibaraki (Japan). Oarai Engineering Center

    1997-07-01

    Hyougo-ken southern earthquake broke out in 1997/01/17. The Atomic Energy Safety Commission considered reasonable of the design guide for seismic design. And the Science and Technology Agency (STA) required reevaluation of atomic power facilities built by old design guide according to the new seismic design guide. JOYO obtained the construction license in 1970/02. Heat transport system and buildings of JOYO was re-evaluated by the new seismic design guide for the MK-III project. So, JOYO was not required re-evaluation by STA. But, this evaluation of MK-III was limited to reconstruction area, and the seismic design was reevaluated extensively to confirm earthquake proof characteristics. The structural integrity of buildings and equipments was confirmed by the result of reevaluation by the new seismic design guide. The analysis model conditions were established according to the 1987 and 1991 version of JEAG. This was done by ground investigation result and buildings vibration test. It was made clear that the analysis model conditions were reasonable and conservative from a technical view point. (author)

  5. SEISMIC DESIGN OF TWO STOREY REINFORCED CONCRETE BUILDING IN MALAYSIA WITH LOW CLASS DUCTILITY

    Directory of Open Access Journals (Sweden)

    MOHD IRWAN ADIYANTO

    2014-02-01

    Full Text Available Since Malaysia is not located in active seismic fault zones, majority of buildings in Malaysia had been designed according to BS8110, which not specify any seismic provision. After experienced several tremors originating from neighbouring countries especially from Sumatra, Indonesia, the Malaysian start to ask questions on integrity of existing structures in Malaysia to withstand the earthquake load. The question also arises regarding the economical effect in term of cost of construction if seismic design has to be implemented in Malaysian construction industry. If the cost is increasing, how much the increment and is it affordable? This paper investigated the difference of steel reinforcement and concrete volume required when seismic provision is considered in reinforced concrete design of 2 storey general office building. The regular office building which designed based on BS8110 had been redesigned according to Eurocode 2 with various level of reference peak ground acceleration, agR reflecting Malaysian seismic hazard for ductility class low. Then, the all frames had been evaluated using a total of 800 nonlinear time history analyses considering single and repeated earthquakes to simulate the real earthquake event. It is observed that the level of reference peak ground acceleration, agR and behaviour factor, q strongly influence the increment of total cost. For 2 storey RC buildings built on Soil Type D with seismic consideration, the total cost of material is expected to increase around 6 to 270%, depend on seismic region. In term of seismic performance, the repeated earthquake tends to cause increasing in interstorey drift ratio around 8 to 29% higher compared to single earthquake.

  6. Seismic analysis and design of a spent nuclear fuel dry storage system

    Energy Technology Data Exchange (ETDEWEB)

    Choi, Kyu-Sup; Jeong, In-Su; Kim, Kap-Sun; Kim, Jong-Soo [KONES Corporation, Seoul (Korea, Republic of); Yoon, Jeong-Hyoun; Kang, Young-Gon; Cho, Chun-Hyung; Lee, Heung-Young [Nuclear Environment Technology Institute, Daejeon (Korea, Republic of)

    2005-11-15

    A comprehensive seismic analysis has been conducted in this paper by using the computer programs, SHAKE and SASSI, for a consolidated dry storage module named MACSTOR/KN-400, which will be constructed in Wolsung CANDU Nuclear Power Plant site. Especially seismic soil-structure interaction effects have been investigated in terms of transfer functions, maximum floor acceleration and floor response spectrum, and finally those effects are to be incorporated in the detailed structure design.

  7. Revision of seismic design codes corresponding to building damages in the ``5.12'' Wenchuan earthquake

    Science.gov (United States)

    Wang, Yayong

    2010-06-01

    A large number of buildings were seriously damaged or collapsed in the “5.12” Wenchuan earthquake. Based on field surveys and studies of damage to different types of buildings, seismic design codes have been updated. This paper briefly summarizes some of the major revisions that have been incorporated into the “Standard for classification of seismic protection of building constructions GB50223-2008” and “Code for Seismic Design of Buildings GB50011-2001.” The definition of seismic fortification class for buildings has been revisited, and as a result, the seismic classifications for schools, hospitals and other buildings that hold large populations such as evacuation shelters and information centers have been upgraded in the GB50223-2008 Code. The main aspects of the revised GB50011-2001 code include: (a) modification of the seismic intensity specified for the Provinces of Sichuan, Shanxi and Gansu; (b) basic conceptual design for retaining walls and building foundations in mountainous areas; (c) regularity of building configuration; (d) integration of masonry structures and pre-cast RC floors; (e) requirements for calculating and detailing stair shafts; and (f) limiting the use of single-bay RC frame structures. Some significant examples of damage in the epicenter areas are provided as a reference in the discussion on the consequences of collapse, the importance of duplicate structural systems, and the integration of RC and masonry structures.

  8. Seismic design factors for RC special moment resisting frames in Dubai, UAE

    Science.gov (United States)

    Alhamaydeh, Mohammad; Abdullah, Sulayman; Hamid, Ahmed; Mustapha, Abdilwahhab

    2011-12-01

    This study investigates the seismic design factors for three reinforced concrete (RC) framed buildings with 4, 16 and 32-stories in Dubai, UAE utilizing nonlinear analysis. The buildings are designed according to the response spectrum procedure defined in the 2009 International Building Code (IBC'09). Two ensembles of ground motion records with 10% and 2% probability of exceedance in 50 years (10/50 and 2/50, respectively) are used. The nonlinear dynamic responses to the earthquake records are computed using IDARC-2D. Key seismic design parameters are evaluated; namely, response modification factor ( R), deflection amplification factor ( C d), system overstrength factor ( Ω o), and response modification factor for ductility ( R d ) in addition to inelastic interstory drift. The evaluated seismic design factors are found to significantly depend on the considered ground motion (10/50 versus 2/50). Consequently, resolution to the controversy of Dubai seismicity is urged. The seismic design factors for the 2/50 records show an increase over their counterparts for the 10/50 records in the range of 200%-400%, except for the Ω o factor, which shows a mere 30% increase. Based on the observed trends, perioddependent R and C d factors are recommended if consistent collapse probability (or collapse prevention performance) in moment frames with varying heights is to be expected.

  9. Seismic margin analysis technique for nuclear power plant structures

    Energy Technology Data Exchange (ETDEWEB)

    Seo, Jeong Moon; Choi, In Kil

    2001-04-01

    In general, the Seismic Probabilistic Risk Assessment (SPRA) and the Seismic Margin Assessment(SAM) are used for the evaluation of realistic seismic capacity of nuclear power plant structures. Seismic PRA is a systematic process to evaluate the seismic safety of nuclear power plant. In our country, SPRA has been used to perform the probabilistic safety assessment for the earthquake event. SMA is a simple and cost effective manner to quantify the seismic margin of individual structural elements. This study was performed to improve the reliability of SMA results and to confirm the assessment procedure. To achieve this goal, review for the current status of the techniques and procedures was performed. Two methodologies, CDFM (Conservative Deterministic Failure Margin) sponsored by NRC and FA (Fragility Analysis) sponsored by EPRI, were developed for the seismic margin review of NPP structures. FA method was originally developed for Seismic PRA. CDFM approach is more amenable to use by experienced design engineers including utility staff design engineers. In this study, detailed review on the procedures of CDFM and FA methodology was performed.

  10. Performance-Based Seismic Design of Steel Frames Utilizing Colliding Bodies Algorithm

    Directory of Open Access Journals (Sweden)

    H. Veladi

    2014-01-01

    Full Text Available A pushover analysis method based on semirigid connection concept is developed and the colliding bodies optimization algorithm is employed to find optimum seismic design of frame structures. Two numerical examples from the literature are studied. The results of the new algorithm are compared to the conventional design methods to show the power or weakness of the algorithm.

  11. Evaluation of collapse resistance of RC frame structures for Chinese schools in seismic design categories B and C

    Science.gov (United States)

    Tang, Baoxin; Lu, Xinzheng; Ye, Lieping; Shi, Wei

    2011-09-01

    According to the Code for Seismic Design of Buildings (GB50011-2001), ten typical reinforced concrete (RC) frame structures, used as school classroom buildings, are designed with different seismic fortification intensities (SFIs) (SFI=6 to 8.5) and different seismic design categories (SDCs) (SDC=B and C). The collapse resistance of the frames with SDC=B and C in terms of collapse fragility curves are quantitatively evaluated and compared via incremental dynamic analysis (IDA). The results show that the collapse resistance of structures should be evaluated based on both the absolute seismic resistance and the corresponding design seismic intensity. For the frames with SFI from 6 to 7.5, because they have relatively low absolute seismic resistance, their collapse resistance is insufficient even when their corresponding SDCs are upgraded from B to C. Thus, further measures are needed to enhance these structures, and some suggestions are proposed.

  12. Deaggregation of seismic safety in the design of the reinforced concrete building

    OpenAIRE

    Žižmond, Jure

    2012-01-01

    Design of earthquake-resistant buildings according to Eurocode 8 is not based on the concept of acceptable probability of failure since standard introduces fundamental non-collapse and damage limitation requirements, which are associated with the design seismic action. It is foreseen that the non-collapse requirement is satisfied when the regular buildings are designed to withstand design earthquake, which corresponds to a return period of 475 years and thus to probability of occu...

  13. Base Isolation for Seismic Retrofitting of a Multiple Building Structure: Design, Construction, and Assessment

    Directory of Open Access Journals (Sweden)

    Massimiliano Ferraioli

    2017-01-01

    Full Text Available The paper deals with the seismic retrofit of a multiple building structure belonging to the Hospital Centre of Avellino (Italy. At first, the paper presents the preliminary investigations, the in situ measurements and laboratory tests, and the seismic assessment of the existing fixed-base structures. Having studied different strategies, base isolation proved to be the more appropriate, also for the possibility offered by the geometry of the building to easily create an isolation interface at the ground level. The paper presents the design project, the construction process, and the details of the isolation intervention. Some specific issues of base isolation for seismic retrofitting of multiple building structures were lightened. Finally, the seismic assessment of the base-isolated building was carried out. The seismic response was evaluated through nonlinear time-history analysis, using the well-known Bouc-Wen model as the constitutive law of the isolation bearings. For reliable dynamic analyses, a suite of natural accelerograms compatible with acceleration spectra of Italian Code was first selected and then applied along both horizontal directions. The results were finally used to address some of the critical issues of the seismic response of the base-isolated multiple building structure: accidental torsional effects and potential poundings during strong earthquakes.

  14. Analysis and Design of One Dimensional Periodic Foundations for Seismic Base Isolation of Structures

    Directory of Open Access Journals (Sweden)

    Witarto Witarto

    2016-01-01

    Full Text Available Periodic foundationis a new type of seismic base isolation system. It is inspired by the periodic material crystal lattice in the solid state physics. This kind of material has a unique property, which is termed as frequency band gap that is capable of blocking incoming waves having frequencies falling within the band gap. Consequently, seismic waves having frequencies falling within the frequency band gap are blocked by the periodic foundation. The ability to block the seismic waveshas put this kind of foundation as a prosperous next generation of seismic base isolators. This paper provides analytical study on the one dimensional (1D type periodic foundations to investigate their seismic performance. The general idea of basic theory of one dimensional (1D periodic foundations is first presented.Then, the parametric studies considering infinite and finite boundary conditions are discussed. The effect of superstructure on the frequency band gap is investigated as well. Based on the analytical study, a set of equations is proposed for the design guidelines of 1D periodic foundations for seismic base isolation of structures.

  15. Comparison of seismic actions and structural design requirements in Chinese Code GB 50011 and International Standard ISO 3010

    Institute of Scientific and Technical Information of China (English)

    王亚勇

    2004-01-01

    This paper presents a comparison between the Chinese Code GB50011-2001 and the International Standard ISO3010: 2001(E), emphasizing the similarities and differences related to design requirements, seismic actions and analytical approaches. Similarities include: earthquake return period, conceptual design, site classification, structural strength and ductility requirements, deformation limits, response spectra, seismic analysis procedures, isolation and energy dissipation,and nonstructural elements. Differences exist in the following areas: seismic levels, earthquake loading, mode damping factors and structural control.

  16. Estimation of cyclic interstory drift capacity of steel framed structures and future applications for seismic design.

    Science.gov (United States)

    Bojórquez, Edén; Reyes-Salazar, Alfredo; Ruiz, Sonia E; Terán-Gilmore, Amador

    2014-01-01

    Several studies have been devoted to calibrate damage indices for steel and reinforced concrete members with the purpose of overcoming some of the shortcomings of the parameters currently used during seismic design. Nevertheless, there is a challenge to study and calibrate the use of such indices for the practical structural evaluation of complex structures. In this paper, an energy-based damage model for multidegree-of-freedom (MDOF) steel framed structures that accounts explicitly for the effects of cumulative plastic deformation demands is used to estimate the cyclic drift capacity of steel structures. To achieve this, seismic hazard curves are used to discuss the limitations of the maximum interstory drift demand as a performance parameter to achieve adequate damage control. Then the concept of cyclic drift capacity, which incorporates information of the influence of cumulative plastic deformation demands, is introduced as an alternative for future applications of seismic design of structures subjected to long duration ground motions.

  17. Estimation of Cyclic Interstory Drift Capacity of Steel Framed Structures and Future Applications for Seismic Design

    Directory of Open Access Journals (Sweden)

    Edén Bojórquez

    2014-01-01

    Full Text Available Several studies have been devoted to calibrate damage indices for steel and reinforced concrete members with the purpose of overcoming some of the shortcomings of the parameters currently used during seismic design. Nevertheless, there is a challenge to study and calibrate the use of such indices for the practical structural evaluation of complex structures. In this paper, an energy-based damage model for multidegree-of-freedom (MDOF steel framed structures that accounts explicitly for the effects of cumulative plastic deformation demands is used to estimate the cyclic drift capacity of steel structures. To achieve this, seismic hazard curves are used to discuss the limitations of the maximum interstory drift demand as a performance parameter to achieve adequate damage control. Then the concept of cyclic drift capacity, which incorporates information of the influence of cumulative plastic deformation demands, is introduced as an alternative for future applications of seismic design of structures subjected to long duration ground motions.

  18. Analytical Study on the Beyond Design Seismic Capacity of Reinforced Concrete Shear Walls

    Energy Technology Data Exchange (ETDEWEB)

    Nugroho, Tino Sawaldi Adi [Korea Advanced Institute of Science and Technology, Daejeon (Korea, Republic of); Chi, Ho-Seok [Korea Institute of Nuclear Safety, Daejeon (Korea, Republic of)

    2015-10-15

    The OECD-NEA has organized an international benchmarking program to better understand this critical issue. The benchmark program provides test specimen geometry, test setup, material properties, loading conditions, recorded measures, and observations of the test specimens. The main objective of this research is to assess the beyond design seismic capacity of the reinforced concrete shear walls tested at the European Laboratory for Structural Assessment between 1997 and 1998 through participation in the OECD-NEA benchmark program. In this study, assessing the beyond design seismic capacity of reinforced concrete shear walls is performed analytically by comparing numerical results with experimental results. The seismic shear capacity of the reinforced concrete shear wall was predicted reasonably well using ABAQUS program. However, the proper calibration of the concrete material model was necessary for better prediction of the behavior of the reinforced concrete shear walls since the response was influenced significantly by the material constitutive model.

  19. Local network deployed around the Kozloduy NPP - a useful tool for seismological monitoring

    Science.gov (United States)

    Solakov, Dimcho; Simeonova, Stela; Dimitrova, Liliya; Slavcheva, Krasimira; Raykova, Plamena; Popova, Maria; Georgiev, Ivan

    2015-04-01

    Radiation risks may transcend national borders, and international cooperation serves to promote and enhance safety globally by exchanging experience and by improving capabilities to control hazards, to prevent accidents, to respond to emergencies and to mitigate any harmful consequences. International safety standards provide support for states in meeting their obligations under general principles of international law, such as those relating to environmental protection. Seismic safety is a key element of NPP safe operation. Safety and security measures have in common the aim of protecting human life and health and the environment. The Kozloduy NPP site is located in the stable part of the Moesian platform (area of about 50000 km2). From seismological point of view the Moesian platform is the most quite area on the territory of Bulgaria. There are neither historical nor instrumental earthquakes with M>4.5 occurred within the platform. The near region (area with radial extent of 30 km) of the NPP site is characterized with very low seismic activity. The strongest recorded quake is the 1987 earthquake МS=3.6, localized 22 km northwest of the Kozloduy NPP site on the territory of Romania. In line with international practice, the geological, geophysical and seismological characteristics of the region around the site have been investigated for the purpose of evaluating the seismic hazards at the NPP site. A local network (LSN) of sensitive seismographs having a recording capability for micro-earthquakes have been installed around Kozloduy NPP and operated since 1997. The operation and data processing, data interpretation, and reporting of the local micro-earthquake network are linked to the national seismic network (NOTSSI). A real-time data transfer from stations to National Data Center (in Sofia) was implemented using the VPN and MAN networks of the Bulgarian Telecommunication. Real-time and interactive data processing are performed by the Seismic Network Data

  20. Development of a seismic design method based on response spectra for building structures

    Institute of Scientific and Technical Information of China (English)

    ZHOU Xiyuan; YU Ruifang

    2007-01-01

    The assumption and problem of the mode-superposition response spectrum method in seismic design code is discussed based on a brief review of the development of the seismic design method for building structures. The scope of application for the classical damping theory is ana- lyzed and the necessity of the research on mode-superposition method for non-classical damping is presented. The pro- gresses on the mode superposition response spectrum theory are discussed. This includes: 1) the complex mode superposi- tion method (in real form) for the non-classically damped linear system and the general calculation formula for the application of code; 2) the complex complete quadratic com- bination (CCQC) method for the non-classically damped linear system, which is based on the same assumptions as in deducing the complete quadratic combination (CQC) method which is popularly used in seismic design codes of many countries; 3) the complex complete quadratic combination with three components (CCQC3) method, which is a general- ization of the CCQC method to the case of multi-components and multiple-support seismic excitations and deducing cor- responding method; 4) the approach for calculation of seismic response of the non-classically damped system with over- critical damping and the calculation method of seismic response for the linear system with multiple eigenvalues; 5) the time-dependent CCQC(t) algorithm considering non- stationary earthquake ground motion; 6) an applied and effec- tive method to solve the low order complex vector basis for the large linear non-classically damped system, which can be expediently used in practice to avoid the unknown errors coming from the forced uncoupling method; 7) bringing for- ward the concept of partial quadratic combination in order to reduce the calculation amount of CQC and CCQC methods, and studying the primary estimation-criterion. The reason- ability and applicable scope of these methods are also briefly discussed in this

  1. Response spectrum of seismic design code for zones lack of near-fault strong earthquake records

    Institute of Scientific and Technical Information of China (English)

    LI Xin-le; DOU Hui-juan; ZHU Xi; SUN Jian-gang

    2007-01-01

    It was shown from the study on the recently near-fault earthquake ground motions that the near-fault effects were seldom considered in the existing Chinese seismic code. Referring to the UBC97 design concept for near-fault factors, based on the collected world-widely free-site records of near-fault earthquakes ground motions classified by earthquake magnitude and site condition, the attenuation relationship expressions of the acceleration spectrum demand at the key points within the long period and moderate period were established in term of the earthquake magnitude and the site condition. Furthermore, the near-fault factors' expressions about the earthquake magnitude and the fault distance were deduced for the area lack of near-fault strong earthquake records. Based on the current Chinese Building Seismic Design Code, the near-fault effect factors and the modified design spectral curves, which were valuable for the seismic design, were proposed to analyze the seismic response of structures.

  2. Risk-Targeted versus Current Seismic Design Maps for the Conterminous United States

    Science.gov (United States)

    Luco, Nicolas; Ellingwood, Bruce R.; Hamburger, Ronald O.; Hooper, John D.; Kimball, Jeffrey K.; Kircher, Charles A.

    2007-01-01

    The probabilistic portions of the seismic design maps in the NEHRP Provisions (FEMA, 2003/2000/1997), and in the International Building Code (ICC, 2006/2003/2000) and ASCE Standard 7-05 (ASCE, 2005a), provide ground motion values from the USGS that have a 2% probability of being exceeded in 50 years. Under the assumption that the capacity against collapse of structures designed for these "uniformhazard" ground motions is equal to, without uncertainty, the corresponding mapped value at the location of the structure, the probability of its collapse in 50 years is also uniform. This is not the case however, when it is recognized that there is, in fact, uncertainty in the structural capacity. In that case, siteto-site variability in the shape of ground motion hazard curves results in a lack of uniformity. This paper explains the basis for proposed adjustments to the uniform-hazard portions of the seismic design maps currently in the NEHRP Provisions that result in uniform estimated collapse probability. For seismic design of nuclear facilities, analogous but specialized adjustments have recently been defined in ASCE Standard 43-05 (ASCE, 2005b). In support of the 2009 update of the NEHRP Provisions currently being conducted by the Building Seismic Safety Council (BSSC), herein we provide examples of the adjusted ground motions for a selected target collapse probability (or target risk). Relative to the probabilistic MCE ground motions currently in the NEHRP Provisions, the risk-targeted ground motions for design are smaller (by as much as about 30%) in the New Madrid Seismic Zone, near Charleston, South Carolina, and in the coastal region of Oregon, with relatively little (<15%) change almost everywhere else in the conterminous U.S.

  3. Displacement-Based Seismic Design Procedure for Framed Buildings with Dissipative Braces Part I: Theoretical formulation

    Science.gov (United States)

    Mazza, Fabio; Vulcano, Alfonso

    2008-07-01

    The insertion of steel braces equipped with dissipative devices proves to be very effective in order to enhance the performance of a framed building under horizontal seismic loads. Multi-level design criteria were proposed according to the Performance-Based Design, in order to get, for a specific level of the seismic intensity, a designated performance objective of the building (e.g., an assigned damage level of either the framed structure or non-structural elements). In this paper a design procedure aiming to proportion braces with hysteretic dampers in order to attain, for a specific level of the seismic intensity, a designated performance level of the building is proposed. Exactly, a proportional stiffness criterion, which assumes the elastic lateral storey-stiffness due to the braces proportional to that of the unbraced frame, is combined with the Direct Displacement-Based Design, in which the design starts from target deformations. A computer code has been prepared for the nonlinear static and dynamic analyses, using a step-by-step procedure. Frame members and hysteretic dampers are idealized by bilinear models.

  4. A new design strategy based on a deterministic definition of the seismic input to overcome the limits of design procedures based on probabilistic approaches

    CERN Document Server

    Fasan, Marco; Noè, Salavore; Panza, Giuliano; Magrin, Andrea; Romanelli, Fabio; Vaccari, Franco

    2015-01-01

    In this paper, a new seismic Performance Based Design (PBD) process based on a deterministic definition of the seismic input is presented. The proposed procedure aims to address the following considerations, arisen from the analysis of seismic phenomena, which cannot be taken in account using standard probabilistic seismic input (PSHA): a) any structure at a given location, regardless of its importance, is subject to the same shaking as a result of a given earthquake, b) it is impossible to determine when a future earthquake of a given intensity/magnitude will occur, c) insufficient data are available to develop reliable statistics with regards to earthquakes. On the basis of these considerations, the seismic input at a given site - determined on the basis of the seismic history, the seismogenic zones and the seismogenic nodes - is defined using the Neo Deterministic Seismic Hazard Assessment (NDSHA). Two different analysis are carried out at different levels of detail. The first one (RSA) provides the Maximu...

  5. An improved pseudo-static method for seismic resistant design of underground structures

    Institute of Scientific and Technical Information of China (English)

    Liu Rushan; Shi Hongbin

    2006-01-01

    This paper describes a commonly used pseudo-static method in seismic resistant design of the cross section of underground structures. Based on dynamic theory and the vibration characteristics of underground structures, the sources of errors when using this method are analyzed. The traditional seismic motion loading approach is replaced by a method in which a one-dimensional soil layer response stress is differentiated and then converted into seismic live loads. To validate the improved method, a comparison of analytical results is conducted for internal forces under earthquake shaking of a typical shallow embedded box-shaped subway station structure using four methods: the response displacement method,finite element response acceleration method, the finite element dynamic analysis method and the improved pseudo-static calculation method. It is shown that the improved finite element pseudo-static method proposed in this paper provides an effective tool for the seismic design of underground structures. The evaluation yields results close to those obtained by the finite element dynamic analysis method, and shows that the improved finite element pseudo-static method provides a higher degree of precision.

  6. New Zealand Advances in Performance-Based Seismic Design

    Institute of Scientific and Technical Information of China (English)

    Andrew King; Roger Shelton

    2009-01-01

    This paper provides a summary of the objectives and principles which underpin the 2004 edition of the New Zealand earthquake design standard, AS/NZS 1170 Part 5. As with many modern earthquake design standards, the New Zealand earthquake design standard recognizes that earthquake resistant design that only addresses life safety goals without addressing both operational continuity of essential facilities and damage control, falls short of public expectations. Such standards not longer meet societal expectations. The paper outlines how these issues have been addressed within New Zealand, and some of the issues addressed when preparing appendices to the standard to provide guidance for materials standard writers to ensure consistency with the proposed approach. Recognizing the significance of non-structural components and parts of buildings in both damage control and operational continuity has been an important step forward in attaining the performance levels required.

  7. Problems of NPP construction project standardization and operational safety increase in the USA

    Energy Technology Data Exchange (ETDEWEB)

    Gudkov, Yu.V.

    1980-01-01

    Main causes of slackening paces of the USA nuclear power engineering development are considered using the experience of the USA NPP design, construction and operation. Data on increase in capital investments for the NPP construction and variation of their structure to enhancing waste of capital are given. Problems of improvement of operational safety of water-cooled and water-moderated reactors as well as NPP separate assemblies are considered. Ways for reducing periods of NPP design realization are described taking as an example the USA leading power, construction and reactor construction companies. It is shown that the optimization of existing methods for designing NPPs and nuclear reactor structures, systems for construction management and control as well as complex standartization of equipment, construction methods and operational procedures for NPPs are main factors.

  8. Former Soviet Regulations for seismic design of NPPs and comparison with current international practice

    Energy Technology Data Exchange (ETDEWEB)

    Kostarev, V.; Schukin, A.; Berkovski, A. [CKTI-Vibroseism Co. Ltd. (Cape Verde)

    1997-03-01

    This paper presents a summary of current earthquake design criteria used in former Soviet Regulations for equipment and piping systems of nuclear power plants in light of those used in United States and Japan. The detailed comparative seismic analysis of PWR (WWER) Primary Coolant Loop System (PCLS) according to Former Soviet (Russian) PNAE Code and ASME BPV Code with some comments regarding to Japan Code JEAG - 4601 was undertaken for better understanding of the differences and coincidences of seismic design criteria and requirements. The selection of these three guides for the study has very simple explanation: according to ASME BVPC, JEAG and PNAE the huge majority of existing NPPs has been designed. (J.P.N.)

  9. The method of design for seismic data database system based on tree structure

    Institute of Scientific and Technical Information of China (English)

    王喜珍; 滕云田; 高孟潭; 陈步云; 姜慧

    2005-01-01

    With the massive growth of the seismic data, it is required a new method to manage them. In this paper, the design method will be reported about relational database based on tree structure. Comparing with other designs, it is not only simpler and easier to organize data, but also can simplify the design process of the database. This method has been used to design database of the earthquake monitor center station of the earthquake monitoring system for the Yangtze River Three Gorges Project and has shown good results.

  10. Some considerations for establishing seismic design criteria for nuclear plant piping

    Energy Technology Data Exchange (ETDEWEB)

    Chen, W.P. [Energy Technology Engineering Center, Canoga Park, CA (United States); Chokshi, N.C. [Nuclear Regulatory Commission, Washington, DC (United States)

    1997-01-01

    The Energy Technology Engineering Center (ETEC) is providing assistance to the U.S. NRC in developing regulatory positions on the seismic analysis of piping. As part of this effort, ETEC previously performed reviews of the ASME Code, Section III piping seismic design criteria as revised by the 1994 Addenda. These revised criteria were based on evaluations by the ASME Special Task Group on Integrated Piping Criteria (STGIPC) and the Technical Core Group (TCG) of the Advanced Reactor Corporation (ARC) of the earlier joint Electric Power Research Institute (EPRI)/NRC Piping & Fitting Dynamic Reliability (PFDR) program. Previous ETEC evaluations reported at the 23rd WRSM of seismic margins associated with the revised criteria are reviewed. These evaluations had concluded, in part, that although margins for the timed PFDR tests appeared acceptable (>2), margins in detuned tests could be unacceptable (<1). This conclusion was based primarily on margin reduction factors (MRFs) developed by the ASME STGIPC and ARC/TCG from realistic analyses of PFDR test 36. This paper reports more recent results including: (1) an approach developed for establishing appropriate seismic margins based on PRA considerations, (2) independent assessments of frequency effects on margins, (3) the development of margins based on failure mode considerations, and (4) the implications of Code Section III rules for Section XI.

  11. EPC projects for EPR Flamanville 3 NPP

    Energy Technology Data Exchange (ETDEWEB)

    Diaz, J.I.; Polo, J.; Aymerich, E.; Cubian, B. [Nuclear Generation Department, Iberdrola Ingenieria y Construccion, Avda. Manoteras 20, 28050 Madrid (Spain)

    2010-07-01

    IBERDROLA Ingenieria y Construccion is carrying out a handful of activities in the EPR Flamanville 3 -FA3 NPP- context since 2007 matching oriented to position the company in the emerging marketplace of new nuclear power plants Generation III+, whose expectation for the next years is highly promising. IBERDROLA Ingenieria y Construccion leads 5 EPC -Engineering, Procurement and Commissioning- projects for FA3 NPP from the Nuclear Island till Sea Water Pumping Station as follows: - Design, procurement. fabrication, installation and testing of 21 shell and tubes heat-exchangers for the nuclear island. 12 out of these 17 HXs are conventional and will be designed according to ASME BPV code Section VIII and have to comply with PED 97/23/CE and ESPN. The remaining 5 HXs are nuclear and will be designed according to ASME BPV code Section III and have also to comply with PED and ESPN. - Design, procurement, fabrication and assembly of 9 demineralizers for different plant systems. Three of these Important To Safety (IPS) equipments have been manufactured according with ASME VIII codes and six of them with EN 13445 code plus additional requirements to comply with PED and final client requirements for nuclear island. - Design, fabrication and installation of qualified travelling water screening filters. The equipments furnished will be two nuclear safety qualified filters and associated equipment (cleaning water system and control system). Additionally some auxiliary devices such as grids, automatic trash rakes and stop gates are included in the contract. - Engineering, procurement, fabrication, erection and commissioning for the condensate treatment plant. This system includes a demineralizer tank, 5 filters, reactive injection mixer, pneumatic and manual valves, piping and instrumentation and control systems. - Engineering, procurement erection and commissioning for the electro-chlorination plant to protect the IPS piping for Condensate Water System for FA3. This system

  12. Modifications to risk-targeted seismic design maps for subduction and near-fault hazards

    Science.gov (United States)

    Liel, Abbie B.; Luco, Nicolas; Raghunandan, Meera; Champion, C.; Haukaas, Terje

    2015-01-01

    ASCE 7-10 introduced new seismic design maps that define risk-targeted ground motions such that buildings designed according to these maps will have 1% chance of collapse in 50 years. These maps were developed by iterative risk calculation, wherein a generic building collapse fragility curve is convolved with the U.S. Geological Survey hazard curve until target risk criteria are met. Recent research shows that this current approach may be unconservative at locations where the tectonic environment is much different than that used to develop the generic fragility curve. This study illustrates how risk-targeted ground motions at selected sites would change if generic building fragility curve and hazard assessment were modified to account for seismic risk from subduction earthquakes and near-fault pulses. The paper also explores the difficulties in implementing these changes.

  13. Seismic design technology for breeder reactor structures. Volume 1. Special topics in earthquake ground motion

    Energy Technology Data Exchange (ETDEWEB)

    Reddy, D.P.

    1983-04-01

    This report is divided into twelve chapters: seismic hazard analysis procedures, statistical and probabilistic considerations, vertical ground motion characteristics, vertical ground response spectrum shapes, effects of inclined rock strata on site response, correlation of ground response spectra with intensity, intensity attenuation relationships, peak ground acceleration in the very mean field, statistical analysis of response spectral amplitudes, contributions of body and surface waves, evaluation of ground motion characteristics, and design earthquake motions. (DLC)

  14. Probabilistic seismic hazard characterization and design parameters for the Pantex Plant

    Energy Technology Data Exchange (ETDEWEB)

    Bernreuter, D. L.; Foxall, W.; Savy, J. B.

    1998-10-19

    The Hazards Mitigation Center at Lawrence Livermore National Laboratory (LLNL) updated the seismic hazard and design parameters at the Pantex Plant. The probabilistic seismic hazard (PSH) estimates were first updated using the latest available data and knowledge from LLNL (1993, 1998), Frankel et al. (1996), and other relevant recent studies from several consulting companies. Special attention was given to account for the local seismicity and for the system of potentially active faults associated with the Amarillo-Wichita uplift. Aleatory (random) uncertainty was estimated from the available data and the epistemic (knowledge) uncertainty was taken from results of similar studies. Special attention was given to soil amplification factors for the site. Horizontal Peak Ground Acceleration (PGA) and 5% damped uniform hazard spectra were calculated for six return periods (100 yr., 500 yr., 1000 yr., 2000 yr., 10,000 yr., and 100,000 yr.). The design parameters were calculated following DOE standards (DOE-STD-1022 to 1024). Response spectra for design or evaluation of Performance Category 1 through 4 structures, systems, and components are presented.

  15. Does climate directly influence NPP globally?

    Science.gov (United States)

    Chu, Chengjin; Bartlett, Megan; Wang, Youshi; He, Fangliang; Weiner, Jacob; Chave, Jérôme; Sack, Lawren

    2016-01-01

    The need for rigorous analyses of climate impacts has never been more crucial. Current textbooks state that climate directly influences ecosystem annual net primary productivity (NPP), emphasizing the urgent need to monitor the impacts of climate change. A recent paper challenged this consensus, arguing, based on an analysis of NPP for 1247 woody plant communities across global climate gradients, that temperature and precipitation have negligible direct effects on NPP and only perhaps have indirect effects by constraining total stand biomass (Mtot ) and stand age (a). The authors of that study concluded that the length of the growing season (lgs ) might have a minor influence on NPP, an effect they considered not to be directly related to climate. In this article, we describe flaws that affected that study's conclusions and present novel analyses to disentangle the effects of stand variables and climate in determining NPP. We re-analyzed the same database to partition the direct and indirect effects of climate on NPP, using three approaches: maximum-likelihood model selection, independent-effects analysis, and structural equation modeling. These new analyses showed that about half of the global variation in NPP could be explained by Mtot combined with climate variables and supported strong and direct influences of climate independently of Mtot , both for NPP and for net biomass change averaged across the known lifetime of the stands (ABC = average biomass change). We show that lgs is an important climate variable, intrinsically correlated with, and contributing to mean annual temperature and precipitation (Tann and Pann ), all important climatic drivers of NPP. Our analyses provide guidance for statistical and mechanistic analyses of climate drivers of ecosystem processes for predictive modeling and provide novel evidence supporting the strong, direct role of climate in determining vegetation productivity at the global scale.

  16. Improvements of seismic design of nuclear power plant equipment

    Energy Technology Data Exchange (ETDEWEB)

    Suzuki, Kohei [Tokyo Metropolitan Univ., Hachioji (Japan). Faculty of Technology; Takayama, Yoshihiro

    1997-03-01

    A brief survey and overview of the current research and development in Japan was presented. Particularly, several kinds of new dampers and isolators were developed and those effectiveness were examined by caring out the large-scale vibration test and so on. The evaluation of the energy absorption of these damping devices at the earthquake appeared to be significant. In addition, it must be necessary to investigate the design margin and the failure mode and limit problem to these devices and the nuclear structures and piping supported by those. Mutual exchange of the information related to these technology and research has to be put forward and cooperative works including the international conference on those issues should be promoted. (J.P.N.)

  17. Metallography and Microanalysis of Qinshan PhaseⅠ NPP Spent Fuel Rods

    Institute of Scientific and Technical Information of China (English)

    QIAN; Jin; BIAN; Wei; GUO; Li-na; GUO; Yi-fan; CHU; Feng-min; LIANG; Zheng-qiang

    2015-01-01

    Qinshan PhaseⅠNPP is a first domestic commercial PWR and its fuel rods and fuel assembly were designed and manufactured by China.In order to assess the irradiation properties of the fuel rods,8spent fuel rods which were drew out from 3fuel assemblies were transferred to CIAE hot cells for post irradiation examination(PIE)in 2014.The cladding material of the fuel

  18. IMPLEMENTATION OF THE SEISMIC DESIGN CRITERIA OF DOE-STD-1189-2008 APPENDIX A [FULL PAPER

    Energy Technology Data Exchange (ETDEWEB)

    OMBERG SK

    2008-05-14

    This paper describes the approach taken by two Fluor Hanford projects for implementing of the seismic design criteria from DOE-STD-1189-2008, Appendix A. The existing seismic design criteria and the new seismic design criteria is described, and an assessment of the primary differences provided. The gaps within the new system of seismic design criteria, which necessitate conduct of portions of work to the existing technical standards pending availability of applicable industry standards, is discussed. Two Hanford Site projects currently in the Control Decision (CD)-1 phase of design have developed an approach to implementation of the new criteria. Calculations have been performed to determine the seismic design category for one project, based on information available in early CD-1. The potential effects of DOE-STD-1189-2008, Appendix A seismic design criteria on the process of project alternatives analysis is discussed. Present of this work is expected to benefit others in the DOE Complex that may be implementing DOE-STD-1189-2008.

  19. Effects of Moat Wall Impact on the Seismic Response of Base Isolated Nuclear Power Plants

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Min Kyu; Kim, Jung Han [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of); Mosqueda, Gilberto; Sarebanhab, Alireza [University of California, San Diego (United States)

    2015-10-15

    Implementation of the moat wall as a hard stop for isolated NPP is able to decrease the displacement demand. However, since the NPP is relatively heavy structure designed to remain elastic during a seismic event, the moat wall and backfill soil flexibility result in a significant penetration into the wall. As a result, isolators undergo displacements exceeding design considerations based on the clearance to hard stop. Isolators should be tested beyond the hard stop to ensure functionality in the case of an extreme earthquake.

  20. Feed water distribution pipe replacement at Loviisa NPP

    Energy Technology Data Exchange (ETDEWEB)

    Savolainen, S.; Elsing, B. [Imatran Voima Loviisa NPP (Finland)

    1995-12-31

    Imatran Voima Oy operates two WWER-440 reactors. Unit 1 has been operating since 1977 and unit 2 since 1981. First damages of feed water distribution (FWD) pipe were observed in 1989. The FWD-pipe T-connection had suffered from severe erosion corrosion damages. Similar damages have been been found also in other WWER-440 type NPPs. In 1989 the nozzles of the steam generator YB11 were inspected. No signs of the damages or signs of erosion were detected. The first damaged nozzles were found in 1992 in steam generators of both units. In 1992 it was started studying different possibilities to either repair or replace the damaged FWD-pipes. Due to the difficult conditions for repairing the damaged nozzles it was decided to study different FWD-pipe constructions. In 1991 two new feedwater distributors had been implemented at Dukovany NPP designed by Vitckovice company. Additionally OKB Gidropress had presented their design for new collector. In spring 1994 all the six steam generators of Rovno NPP unit 1 were replaced with FWD-pipes designed by OKB Gidropress. After the implementation an experimental program with the new systems was carried out. Due to the successful experiments at Rovno NPP Unit 1 it was decided to implement `Gidropress solution` during 1994 refueling outage into the steam generator YB52 at Loviisa 2. The object of this paper is to discuss the new FWD-pipe and its effects on the plant safety during normal and accident conditions. (orig.).

  1. Seismic analysis and design of ventilation duct at the battery room

    Energy Technology Data Exchange (ETDEWEB)

    Ryu, Jeong Soo [Korea Atomic Energy Research Institute, Taejon (Korea)

    1998-06-01

    Ventilation duct located at the battery room in the 2nd floor, reactor building was classified into the seismic category II. In this report the seismic analysis and design of the duct subjected to SSE were performed. Static, modal and response spectrum analysis were carried out using the structural analysis program, ADINA. The structural integrity on the main frame duct, supports, revets and bolts were evaluated. From the results of the above analysis the support at the concrete wall opening near louver was redesigned and reinforced. Finally the analysis results for the redesigned duct satisfied the code requirements. Therefore the structural integrity on the redesigned ventilation duct was proved. (author). 12 refs., 9 figs., 8 tabs.

  2. Decision making with epistemic uncertainty under safety constraints: An application to seismic design

    Science.gov (United States)

    Veneziano, D.; Agarwal, A.; Karaca, E.

    2009-01-01

    The problem of accounting for epistemic uncertainty in risk management decisions is conceptually straightforward, but is riddled with practical difficulties. Simple approximations are often used whereby future variations in epistemic uncertainty are ignored or worst-case scenarios are postulated. These strategies tend to produce sub-optimal decisions. We develop a general framework based on Bayesian decision theory and exemplify it for the case of seismic design of buildings. When temporal fluctuations of the epistemic uncertainties and regulatory safety constraints are included, the optimal level of seismic protection exceeds the normative level at the time of construction. Optimal Bayesian decisions do not depend on the aleatory or epistemic nature of the uncertainties, but only on the total (epistemic plus aleatory) uncertainty and how that total uncertainty varies randomly during the lifetime of the project. ?? 2009 Elsevier Ltd. All rights reserved.

  3. Seismic design repair and retrofit strategies for steel roof deck diaphragms

    Science.gov (United States)

    Franquet, John-Edward

    Structural engineers will often rely on the roof diaphragm to transfer lateral seismic loads to the bracing system of single-storey structures. The implementation of capacity-based design in the NBCC 2005 has caused an increase in the diaphragm design load due to the need to use the probable capacity of the bracing system, thus resulting in thicker decks, closer connector patterns and higher construction costs. Previous studies have shown that accounting for the in-plane flexibility of the diaphragm when calculating the overall building period can result in lower seismic forces and a more cost-efficient design. However, recent studies estimating the fundamental period of single storey structures using ambient vibration testing showed that the in-situ approximation was much shorter than that obtained using analytical means. The difference lies partially in the diaphragm stiffness characteristics which have been shown to decrease under increasing excitation amplitude. Using the diaphragm as the energy-dissipating element in the seismic force resisting system has also been investigated as this would take advantage of the diaphragm's ductility and limited overstrength; thus, lower capacity based seismic forces would result. An experimental program on 21.0m by 7.31m diaphragm test specimens was carried out so as to investigate the dynamic properties of diaphragms including the stiffness, ductility and capacity. The specimens consisted of 20 and 22 gauge panels with nailed frame fasteners and screwed sidelap connections as well a welded and button-punch specimen. Repair strategies for diaphragms that have previously undergone inelastic deformations were devised in an attempt to restitute the original stiffness and strength and were then experimentally evaluated. Strength and stiffness experimental estimations are compared with those predicted with the Steel Deck Institute (SDI) method. A building design comparative study was also completed. This study looks at the

  4. Optimum Performance-Based Seismic Design Using a Hybrid Optimization Algorithm

    Directory of Open Access Journals (Sweden)

    S. Talatahari

    2014-01-01

    Full Text Available A hybrid optimization method is presented to optimum seismic design of steel frames considering four performance levels. These performance levels are considered to determine the optimum design of structures to reduce the structural cost. A pushover analysis of steel building frameworks subject to equivalent-static earthquake loading is utilized. The algorithm is based on the concepts of the charged system search in which each agent is affected by local and global best positions stored in the charged memory considering the governing laws of electrical physics. Comparison of the results of the hybrid algorithm with those of other metaheuristic algorithms shows the efficiency of the hybrid algorithm.

  5. Development of NPP Monitoring and Operation Support Technology

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Jung Woon; Park, Jae Chang; Lee, Yong Hee [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)] (and others)

    2008-04-15

    During the first stage (2001.7.1-2004.6.30), we developed general human factors design guidelines VDU-based workstations, PMAS alarm display design guidelines, PMAS SPADES display design guidelines, and the revision of KHNP HFE guidelines (HF-010), which have been applied to domestic NPP designs. We also supported other KNICS projects by performing RPS COM design reviews, development of RPS COM Style Guide, and a review of CEDMCS cabinet operator module display design. We developed the ADIOS prototype, NPP performance analysis systems for YGN No.1, 2 plants and Kori No. 2 plant, alarm cause tracking systems for Kori No. 2 plant and OPR1000, and signal fault detection and diagnosis methods for deaerators and steam generators. During the second stage(2004.7.1-2008.4.30), we supported other KNICS projects by reviewing RPS COM display designs three times, developing ESF-CCS COM style guides and reviewing ESF-CCS COM display design, reviewing CRCS LOM and PCS MTP display designs, and developing requirements for DCS GUI components. We also developed integrated style guide for I and C cabinet operator module display designs. In cooperative research with KOPEC-AE, we developed basic technologies for advanced HSI design including task analysis methods, an information and control requirements database, display design criteria, a HSI prototype with its evaluation, and methods for human factors engineering verification and validation.

  6. Application of consequence-based design criteria in regions of moderate seismicity

    Institute of Scientific and Technical Information of China (English)

    胡聿贤

    2003-01-01

    Current design criteria and principles of earthquake engineering design are reviewed, including safety factors, probabilistic approach, and two-level and multi-level functional design ideas. The modern multi-functional idea is discussed in greater details. When designing a structure, its resistance to and the intensity of the earthquake action are considered. The consequence of failure of the structure is considered only through a rough and empirical factor of importance, ranging usually from 1.0 to 1.5. This paper suggests a method of "consequence-based design," which considers the consequences of malfunctioning instead of simply an importance factor. The main argument for this method is that damage to a structure located in different types of societies may have very different consequences, which are dependant on its value and usefulness to the society and the seismicity in the region.

  7. NPP VIIRS Geometric Performance Status

    Science.gov (United States)

    Lin, Guoqing; Wolfe, Robert E.; Nishihama, Masahiro

    2011-01-01

    Visible Infrared Imager Radiometer Suite (VIIRS) instrument on-board the National Polar-orbiting Operational Environmental Satellite System (NPOESS) Preparatory Project (NPP) satellite is scheduled for launch in October, 2011. It is to provide satellite measured radiance/reflectance data for both weather and climate applications. Along with radiometric calibration, geometric characterization and calibration of Sensor Data Records (SDRs) are crucial to the VIIRS Environmental Data Record (EDR) algorithms and products which are used in numerical weather prediction (NWP). The instrument geometric performance includes: 1) sensor (detector) spatial response, parameterized by the dynamic field of view (DFOV) in the scan direction and instantaneous FOV (IFOV) in the track direction, modulation transfer function (MTF) for the 17 moderate resolution bands (M-bands), and horizontal spatial resolution (HSR) for the five imagery bands (I-bands); 2) matrices of band-to-band co-registration (BBR) from the corresponding detectors in all band pairs; and 3) pointing knowledge and stability characteristics that includes scan plane tilt, scan rate and scan start position variations, and thermally induced variations in pointing with respect to orbital position. They have been calibrated and characterized through ground testing under ambient and thermal vacuum conditions, numerical modeling and analysis. This paper summarizes the results, which are in general compliance with specifications, along with anomaly investigations, and describes paths forward for characterizing on-orbit BBR and spatial response, and for improving instrument on-orbit performance in pointing and geolocation.

  8. Decommissioning Study of Oskarshamn NPP

    Energy Technology Data Exchange (ETDEWEB)

    Larsson, Helena; Anunti, Aake; Edelborg, Mathias [Westinghouse Electric Sweden AB, Vaesteraas (Sweden)

    2013-06-15

    By Swedish law it is the obligation of the nuclear power utilities to satisfactorily demonstrate how a nuclear power plant can be safely decommissioned and dismantled when it is no longer in service as well as calculate the estimated cost of decommissioning of the nuclear power plant. Svensk Kaernbraenslehantering AB (SKB) has been commissioned by the Swedish nuclear power utilities to meet the requirements of current legislation by studying and reporting on suitable technologies and by estimating the costs of decommissioning and dismantling of the Swedish nuclear power plants. The present report is an overview, containing the necessary information to meet the above needs, for Oskarshamn NPP. Information is given for the plant about the inventory of materials and radioactivity at the time for final shutdown. A feasible technique for dismantling is presented and the waste management is described and the resulting waste quantities are estimated. Finally a schedule for the decommissioning phase is given and the costs associated are estimated as a basis for funding.

  9. Decommissioning study of Forsmark NPP

    Energy Technology Data Exchange (ETDEWEB)

    Anunti, Aake; Larsson, Helena; Edelborg, Mathias [Westinghouse Electric Sweden AB, Vaesteraas (Sweden)

    2013-06-15

    By Swedish law it is the obligation of the nuclear power utilities to satisfactorily demonstrate how a nuclear power plant can be safely decommissioned and dismantled when it is no longer in service as well as calculate the estimated cost of decommissioning of the nuclear power plant. Svensk Kaernbraenslehantering AB (SKB) has been commissioned by the Swedish nuclear power utilities to meet the requirements of current legislation by studying and reporting on suitable technologies and by estimating the costs of decommissioning and dismantling of the Swedish nuclear power plants. The present report is an overview, containing the necessary information to meet the above needs, for the Forsmark NPP. Information is given for the plant about the inventory of materials and radioactivity at the time for final shutdown. A feasible technique for dismantling is presented and the waste management is described and the resulting waste quantities are estimated. Finally a schedule for the decommissioning phase is given and the costs associated are estimated as a basis for funding.

  10. Seismic Design Value Evaluation Based on Checking Records and Site Geological Conditions Using Artificial Neural Networks

    Directory of Open Access Journals (Sweden)

    Tienfuan Kerh

    2013-01-01

    Full Text Available This study proposes an improved computational neural network model that uses three seismic parameters (i.e., local magnitude, epicentral distance, and epicenter depth and two geological conditions (i.e., shear wave velocity and standard penetration test value as the inputs for predicting peak ground acceleration—the key element for evaluating earthquake response. Initial comparison results show that a neural network model with three neurons in the hidden layer can achieve relatively better performance based on the evaluation index of correlation coefficient or mean square error. This study further develops a new weight-based neural network model for estimating peak ground acceleration at unchecked sites. Four locations identified to have higher estimated peak ground accelerations than that of the seismic design value in the 24 subdivision zones are investigated in Taiwan. Finally, this study develops a new equation for the relationship of horizontal peak ground acceleration and focal distance by the curve fitting method. This equation represents seismic characteristics in Taiwan region more reliably and reasonably. The results of this study provide an insight into this type of nonlinear problem, and the proposed method may be applicable to other areas of interest around the world.

  11. Sensitivity Analysis of Evacuation Speed in Hypothetical NPP Accident by Earthquake

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Sung-yeop; Lim, Ho-Gon [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2016-10-15

    Effective emergency response in emergency situation of nuclear power plant (NPP) can make consequences be different therefore it is regarded important when establishing an emergency response plan and assessing the risk of hypothetical NPP accident. Situation of emergency response can be totally changed when NPP accident caused by earthquake or tsunami is considered due to the failure of roads and buildings by the disaster. In this study evacuation speed has been focused among above various factors and reasonable evacuation speed in earthquake scenario has been investigated. Finally, sensitivity analysis of evacuation speed in hypothetical NPP accident by earthquake has been performed in this study. Evacuation scenario can be entirely different in the situation of seismic hazard and the sensitivity analysis of evacuation speed in hypothetical NPP accident by earthquake has been performed in this study. Various references were investigated and earthquake evacuation model has been developed considering that evacuees may convert their evacuation method from using a vehicle to walking when they face the difficulty of using a vehicle due to intense traffic jam, failure of buildings and roads, and etc. The population dose within 5 km / 30 km have been found to be increased in earthquake situation due to decreased evacuation speed and become 1.5 - 2 times in the severest earthquake evacuation scenario set up in this study. It is not agreed that using same emergency response model which is used for normal evacuation situations when performing level 3 probabilistic safety assessment for earthquake and tsunami event. Investigation of data and sensitivity analysis for constructing differentiated emergency response model in the event of seismic hazard has been carried out in this study.

  12. Displacement-based seismic design of flat slab-shear wall buildings

    Science.gov (United States)

    Sen, Subhajit; Singh, Yogendra

    2016-06-01

    Flat slab system is becoming widely popular for multistory buildings due to its several advantages. However, the performance of flat slab buildings under earthquake loading is unsatisfactory due to their vulnerability to punching shear failure. Several national design codes provide guidelines for designing flat slab system under gravity load only. Nevertheless, flat slab buildings are also being constructed in high seismicity regions. In this paper, performance of flat slab buildings of various heights, designed for gravity load alone according to code, is evaluated under earthquake loading as per ASCE/SEI 41 methodology. Continuity of slab bottom reinforcement through column cage improves the performance of flat slab buildings to some extent, but it is observed that these flat slab systems are not adequate in high seismicity areas and need additional primary lateral load resisting systems such as shear walls. A displacement-based method is proposed to proportion shear walls as primary lateral load resisting elements to ensure satisfactory performance. The methodology is validated using design examples of flat slab buildings with various heights.

  13. SRS BEDROCK PROBABILISTIC SEISMIC HAZARD ANALYSIS (PSHA) DESIGN BASIS JUSTIFICATION (U)

    Energy Technology Data Exchange (ETDEWEB)

    (NOEMAIL), R

    2005-12-14

    This represents an assessment of the available Savannah River Site (SRS) hard-rock probabilistic seismic hazard assessments (PSHAs), including PSHAs recently completed, for incorporation in the SRS seismic hazard update. The prior assessment of the SRS seismic design basis (WSRC, 1997) incorporated the results from two PSHAs that were published in 1988 and 1993. Because of the vintage of these studies, an assessment is necessary to establish the value of these PSHAs considering more recently collected data affecting seismic hazards and the availability of more recent PSHAs. This task is consistent with the Department of Energy (DOE) order, DOE O 420.1B and DOE guidance document DOE G 420.1-2. Following DOE guidance, the National Map Hazard was reviewed and incorporated in this assessment. In addition to the National Map hazard, alternative ground motion attenuation models (GMAMs) are used with the National Map source model to produce alternate hazard assessments for the SRS. These hazard assessments are the basis for the updated hard-rock hazard recommendation made in this report. The development and comparison of hazard based on the National Map models and PSHAs completed using alternate GMAMs provides increased confidence in this hazard recommendation. The alternate GMAMs are the EPRI (2004), USGS (2002) and a regional specific model (Silva et al., 2004). Weights of 0.6, 0.3 and 0.1 are recommended for EPRI (2004), USGS (2002) and Silva et al. (2004) respectively. This weighting gives cluster weights of .39, .29, .15, .17 for the 1-corner, 2-corner, hybrid, and Greens-function models, respectively. This assessment is judged to be conservative as compared to WSRC (1997) and incorporates the range of prevailing expert opinion pertinent to the development of seismic hazard at the SRS. The corresponding SRS hard-rock uniform hazard spectra are greater than the design spectra developed in WSRC (1997) that were based on the LLNL (1993) and EPRI (1988) PSHAs. The

  14. Inelastic seismic behavior of post-installed anchors for nuclear safety related structures: Generation of experimental database

    Energy Technology Data Exchange (ETDEWEB)

    Mahadik, Vinay, E-mail: vinay.mahadik@iwb.uni-stuttgart.de; Sharma, Akanshu; Hofmann, Jan

    2016-02-15

    Highlights: • Experiments for evaluating seismic behavior of anchors were performed. • Two undercut anchor products in use in nuclear facilities were considered. • Monotonic tension, shear and cycling tension tests at different crack widths. • Crack cycling tests at constant, in-phase and out-of phase tension loads. • Characteristics for the two anchors as a function of crack width were identified. - Abstract: Post installed (PI) anchors are often employed for connections between concrete structure and components or systems in nuclear power plants (NPP) and related facilities. Standardized practices for nuclear related structures demand stringent criteria, which an anchor has to satisfy in order to qualify for use in NPP related structures. In NPP and related facilities, the structure–component interaction in the event of an earthquake depends on the inelastic behavior of the concrete structure, the component system and also the anchorage system that connects them. For analysis, anchorages are usually assumed to be rigid. Under seismic actions, however, it is known that anchors may undergo significant plastic displacement and strength degradation. Analysis of structure–component interaction under seismic loads calls for numerical models simulating inelastic behavior of anchorage systems. A testing program covering different seismic loading scenarios in a reasonably conservative manner is required to establish a basis for generating numerical models of anchorage systems. Currently there is a general lack of modeling techniques to consider the inelastic behavior of anchorages in structure–component interaction under seismic loads. In this work, in view of establishing a basis for development of numerical models simulating the inelastic behavior of anchors, seismic tests on two different undercut anchors qualified for their use in NPP related structures were carried out. The test program was primarily based on the DIBt-KKW-Leitfaden (2010) guidelines

  15. Exploratory Shaft Seismic Design Basis Working Group report; Yucca Mountain Project

    Energy Technology Data Exchange (ETDEWEB)

    Subramanian, C.V. [Sandia National Labs., Albuquerque, NM (USA); King, J.L. [Science Applications International Corp., Las Vegas, NV (USA); Perkins, D.M. [Geological Survey, Denver, CO (USA); Mudd, R.W. [Fenix and Scisson, Inc., Tulsa, OK (USA); Richardson, A.M. [Parsons, Brinckerhoff, Quade and Douglas, Inc., San Francisco, CA (USA); Calovini, J.C. [Holmes and Narver, Inc., Las Vegas, NV (USA); Van Eeckhout, E. [Los Alamos National Lab., NM (USA); Emerson, D.O. [Lawrence Livermore National Lab., CA (USA)

    1990-08-01

    This report was prepared for the Yucca Mountain Project (YMP), which is managed by the US Department of Energy. The participants in the YMP are investigating the suitability of a site at Yucca Mountain, Nevada, for construction of a repository for high-level radioactive waste. An exploratory shaft facility (ESF) will be constructed to permit site characterization. The major components of the ESF are two shafts that will be used to provide access to the underground test areas for men, utilities, and ventilation. If a repository is constructed at the site, the exploratory shafts will be converted for use as intake ventilation shafts. In the context of both underground nuclear explosions (conducted at the nearby Nevada Test Site) and earthquakes, the report contains discussions of faulting potential at the site, control motions at depth, material properties of the different rock layers relevant to seismic design, the strain tensor for each of the waveforms along the shaft liners, and the method for combining the different strain components along the shaft liners. The report also describes analytic methods, assumptions used to ensure conservatism, and uncertainties in the data. The analyses show that none of the shafts` structures, systems, or components are important to public radiological safety; therefore, the shafts need only be designed to ensure worker safety, and the report recommends seismic design parameters appropriate for this purpose. 31 refs., 5 figs., 6 tabs.

  16. Application of 'Six Sigma{sup TM}' and 'Design of Experiment' for Cementation - Recipe Development for Evaporator Concentrate for NPP Ling AO, Phase II (China) - 12555

    Energy Technology Data Exchange (ETDEWEB)

    Fehrmann, Henning [Westinghouse Electric Germany GmbH (Germany); Perdue, Robert [Westinghouse Electric Company (United States)

    2012-07-01

    Cementation of radioactive waste is a common technology. The waste is mixed with cement and water and forms a stable, solid block. The physical properties like compression strength or low leach ability depends strongly on the cement recipe. Due to the fact that this waste cement mixture has to fulfill special requirements, a recipe development is necessary. The Six Sigma{sup TM}' DMAIC methodology, together with the Design of experiment (DoE) approach, was employed to optimize the process of a recipe development for cementation at the Ling Ao nuclear power plant (NPP) in China. The DMAIC offers a structured, systematical and traceable process to derive test parameters. The DoE test plans and statistical analysis is efficient regarding the amount of test runs and the benefit gain by getting a transfer function. A transfer function enables simulation which is useful to optimize the later process and being responsive to changes. The DoE method was successfully applied for developing a cementation recipe for both evaporator concentrate and resin waste in the plant. The key input parameters were determined, evaluated and the control of these parameters were included into the design. The applied Six Sigma{sup TM} tools can help to organize the thinking during the engineering process. Data are organized and clearly presented. Various variables can be limited to the most important ones. The Six Sigma{sup TM} tools help to make the thinking and decision process trace able. The tools can help to make data driven decisions (e.g. C and E Matrix). But the tools are not the only golden way. Results from scoring tools like the C and E Matrix need close review before using them. The DoE is an effective tool for generating test plans. DoE can be used with a small number of tests runs, but gives a valuable result from an engineering perspective in terms of a transfer function. The DoE prediction results, however, are only valid in the tested area. So a careful selection of

  17. Spent fuel management of Jose Cabrera NPP

    Energy Technology Data Exchange (ETDEWEB)

    Blanco Zurro, J.E.; Garcia Costilla, M. [Area de Generacion - Unidad Nuclear, Gas Natural Fenosa, Avda. de San Luis, 77, 28033 Madrid (Spain); Lavara Sanz, A. [Division Nuclear, SOCOIN, P. del Club Deportivo, 1 - Edificio 5, 28223 Pozuelo de Alarcon, Madrid (Spain); Martinez Abad, J.E. [Departamento de Residuos de Alta Actividad, ENRESA, C/ Emilio Vargas, 7, 28043 Madrid (Spain)

    2010-07-01

    The definitive shutdown of Jose Cabrera Nuclear Power Plant took place on 30. of April 2006. From this moment, cooperation agreements between ENRESA and GAS NATURAL FENOSA were established to reach, among others objectives, its decommissioning, 3 years after the shutdown of the reactor. In order to accomplish the Spanish nuclear regulation, a spent fuel management plan was developed. This plan determined that the fuel assemblies placed in the spent fuel pool would be managed by means of their storage in an interim installation. For this reason, an Independent Spent Fuel Storage Installation (ISFSI) was built at plant site, pioneer in Spain by its characteristics of design. Different administrative authorizations from the point of view of nuclear safety as well as from the environmental were required for ISFSI licensing process. The transference and storage of spent fuel was carried out using the HI-STORM 100Z Dry Storage System, developed by HOLTEC INTERNATIONAL. This system, designed for the spent fuel storage in casks, supports abnormal and very hard accident conditions. The system has three main components: Storage Cask (HI-STORM), Transfer Cask (HI-TRAC) and Multipurpose Canister (MPC). In addition to this, the system has a specific Transport Cask (HI-STAR) for the future transport out of the Plant. More than 30 Design Modifications to the system and plant were implemented to solve structural problems and to include safety and ALARA improvements. The transfer of the spent fuel and its emplacement in the ISFSI began on January 2009 and finished on September of that year allowing starting the decommissioning process, three years and a half after Jose Cabrera NPP shutdown. (authors)

  18. AP1000{sup R} design robustness against extreme external events - Seismic, flooding, and aircraft crash

    Energy Technology Data Exchange (ETDEWEB)

    Pfister, A.; Goossen, C.; Coogler, K.; Gorgemans, J. [Westinghouse Electric Company LLC, 1000 Westinghouse Drive, Cranberry Township, PA 16066 (United States)

    2012-07-01

    Both the International Atomic Energy Agency (IAEA) and the U.S. Nuclear Regulatory Commission (NRC) require existing and new nuclear power plants to conduct plant assessments to demonstrate the unit's ability to withstand external hazards. The events that occurred at the Fukushima-Dai-ichi nuclear power station demonstrated the importance of designing a nuclear power plant with the ability to protect the plant against extreme external hazards. The innovative design of the AP1000{sup R} nuclear power plant provides unparalleled protection against catastrophic external events which can lead to extensive infrastructure damage and place the plant in an extended abnormal situation. The AP1000 plant is an 1100-MWe pressurized water reactor with passive safety features and extensive plant simplifications that enhance construction, operation, maintenance and safety. The plant's compact safety related footprint and protection provided by its robust nuclear island structures prevent significant damage to systems, structures, and components required to safely shutdown the plant and maintain core and spent fuel pool cooling and containment integrity following extreme external events. The AP1000 nuclear power plant has been extensively analyzed and reviewed to demonstrate that it's nuclear island design and plant layout provide protection against both design basis and extreme beyond design basis external hazards such as extreme seismic events, external flooding that exceeds the maximum probable flood limit, and malicious aircraft impact. The AP1000 nuclear power plant uses fail safe passive features to mitigate design basis accidents. The passive safety systems are designed to function without safety-grade support systems (such as AC power, component cooling water, service water, compressed air or HVAC). The plant has been designed to protect systems, structures, and components critical to placing the reactor in a safe shutdown condition within the steel

  19. The thinking on engineering seismic design%工程抗震设计思考

    Institute of Scientific and Technical Information of China (English)

    黄龙生; 黄勇

    2011-01-01

    Seismic design codes are generalized from theory research and practice of earthquake engineering, meanwhile they should be improved with the deepening on the earthquake engineering research and science progress. Some views and opinions about seismic design, such as aseismic concepts, requirement for fortification earthquake, structural analysis, constructional measure for earthquake resistance, are proposed. The meanings of earthquake intensity should be understood according to its different application conditions. It is tried for the seismic design to put probability into the earthquake intensity, but no easy to its application. The goals of earthquake fortification are to reduce the damage of building, avoid human casualties and alleviate economic loss. The object of the earthquake fortification in a zone should be earthquake fortification intensity. The site condition should be considered into the fortification intensity of engineering seismic design. It is reasonable to put the importance modified coefficient and structural coefficient into seismic design based on elastic response spectrum. The importance modified coefficient and structural coefficient are not generally relative to earthquake arose probability. It is no necessary to add many earthquake time histories to structural analysis under frequently occurred earthquake. The accurate of earthquake action is limited, so it is necessary to adopt constructional measure for the earthquake resistance besides structural a-nalysis. The earthquake over the fortification intensity is a risk problem.%抗震设计规范主要是理论研究与地震工程实践经验的概括和总结.而且它还将随着地震认识的深化和科学的进步,与时俱进,不断地修改、完善.因此,文中就一些理论概念、设防要求、结构分析、抗震措施等问题阐释我们的体会和看法.明确指出,地震烈度的意义应依据应用的不同状况给出合理解释;将地震烈度附上概率的概念

  20. 3-D seismic acquisition geometry design and analysis: Investigation of the requirements to include illumination from all multiples

    NARCIS (Netherlands)

    Kumar, A.

    2015-01-01

    A seismic survey should be designed such that imaging of the acquired data leads to a sufficiently accurate subsurface image. For that purpose, methods for acquisition geometry analysis and design are available. These methods are used to judge whether an acquisition geometry is suited for the specif

  1. Forest NPP estimation based on MODIS data under cloudless condition

    Institute of Scientific and Technical Information of China (English)

    CHEN LiangFu; GAO YanHua; LI Li; LIU QinHuo; GU XingFa

    2008-01-01

    Based on light-use efficiency model, an MODIS-derived daily net primary production (NPP) model was developed. In this model, a new model for the fraction of photosynthetically active radiation absorbed by vegetation (FPAR) is developed based on leaf area index (LAI) and albedo parameters, and a photosynthetically active radiation (PAR) is calculated from the combination of Bird's model with aerosol optical thickness and water vapor derived from cloud free MODIS images. These two models are integrated into our predicted NPP model, whose most parameters are retrieved from MODIS data. In order to validate our NPP model, the observed NPP in the Qianyanzhou station and the Changbai Mountains station are used to compare with our predicted NPP, showing that they are in good agreement. The NASA NPP products also have been downloaded and compared with the measurements, which shows that the NASA NPP products underestimated NPP in the Qianyanzhou station but overestimated in the Changbai Mountains station in 2004.

  2. Design Guidelines of a Spring-Damper System for Emergency Diesel Generator Sets

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Min Kyu; Choun, Young Sun; Seo, Jeong Moon

    2007-05-15

    This guidelines described about the procedure of isolation system design for Emergency Diesel Generator (EDG) of Nuclear Power Plant (NPP). First of all, a vibration concept including the ground vibration was described and vibration control system and seismic isolation system were considered. The behavior characteristics and design consideration of coil spring-viscose damper system were summarized. The material properties of foundation of EDG system and the ground were considered. A design load and seismic load for isolation system design were described and an analysis method was explained. Finally, a design example for an EDG in Yonggwang Nuclear Unit 5 and 6 was attached of Appendix. First of all, this design guideline can apply to design of a vibration and seismic isolation system for EDG system and the design example present a design procedure practically. Moreover, this design guideline can be used for isolation design of other rotational machines and other isolation system except spring-damper system.

  3. Spatial correlation analysis of seismic noise for STAR X-ray infrastructure design

    Science.gov (United States)

    D'Alessandro, Antonino; Agostino, Raffaele; Festa, Lorenzo; Gervasi, Anna; Guerra, Ignazio; Palmer, Dennis T.; Serafini, Luca

    2014-05-01

    The Italian PON MaTeRiA project is focused on the creation of a research infrastructure open to users based on an innovative and evolutionary X-ray source. This source, named STAR (Southern Europe TBS for Applied Research), exploits the Thomson backscattering process of a laser radiation by fast-electron beams (Thomson Back Scattering - TBS). Its main performances are: X-ray photon flux 109-1010 ph/s, Angular divergence variable between 2 and 10 mrad, X-ray energy continuously variable between 8 keV and 150 keV, Bandwidth ΔE/E variable between 1 and 10%, ps time resolved structure. In order to achieve this performances, bunches of electrons produced by a photo-injector are accelerated to relativistic velocities by a linear accelerator section. The electron beam, few hundreds of micrometer wide, is driven by magnetic fields to the interaction point along a 15 m transport line where it is focused in a 10 micrometer-wide area. In the same area, the laser beam is focused after being transported along a 12 m structure. Ground vibrations could greatly affect the collision probability and thus the emittance by deviating the paths of the beams during their travel in the STAR source. Therefore, the study program to measure ground vibrations in the STAR site can be used for site characterization in relation to accelerator design. The environmental and facility noise may affect the X-ray operation especially if the predominant wavelengths in the microtremor wavefield are much smaller than the size of the linear accelerator. For wavelength much greater, all the accelerator parts move in phase, and therefore also large displacements cannot generate any significant effect. On the other hand, for wavelengths equal or less than half the accelerator size several parts could move in phase opposition and therefore small displacements could affect its proper functioning. Thereafter, it is important to characterize the microtremor wavefield in both frequencies and wavelengths domains

  4. Development of DUPIC fuel cycle technology - Assessment of Wolsong NPP fuel handling system for DUPIC fuel

    Energy Technology Data Exchange (ETDEWEB)

    Na, Bok Gyun; Nam, Gung Ihn [Korea Power Engineering Company, Taejon (Korea)

    2000-04-01

    The DUPIC fuel loading and discharge path of Wolsong NPP is studied assuming that DUPIC fuel is used at Wolsong NPP. Spent DUPIC fuel discharge path is irrelevant, since it uses the same spent fuel discharge path. Number of factors such as safety, economics of design change, radiation exposure to operators, easy of operation and maintenance, etc, are considered in the evaluation of path. A more detailed analysis of cost estimation of the selected path is also carried out. The study shows that DUPIC fuel loading path following through Spent Fuel Storage Bay and Spent Fuel Discharge Port in reverse direction will minimize the design change and additional equipment and radiation exposure to operators. The estimated total cost of using DUPIC fuel in Wolsong NPP based on price index of year 2000 is around 4.5 billion won. 4 refs., 30 figs., 13 tabs. (Author)

  5. Displacement-Based Seismic Design Procedure for Framed Buildings with Dissipative Braces Part II: Numerical Results

    Science.gov (United States)

    Mazza, Fabio; Vulcano, Alfonso

    2008-07-01

    For a widespread application of dissipative braces to protect framed buildings against seismic loads, practical and reliable design procedures are needed. In this paper a design procedure based on the Direct Displacement-Based Design approach is adopted, assuming the elastic lateral storey-stiffness of the damped braces proportional to that of the unbraced frame. To check the effectiveness of the design procedure, presented in an associate paper, a six-storey reinforced concrete plane frame, representative of a medium-rise symmetric framed building, is considered as primary test structure; this structure, designed in a medium-risk region, is supposed to be retrofitted as in a high-risk region, by insertion of diagonal braces equipped with hysteretic dampers. A numerical investigation is carried out to study the nonlinear static and dynamic responses of the primary and the damped braced test structures, using step-by-step procedures described in the associate paper mentioned above; the behaviour of frame members and hysteretic dampers is idealized by bilinear models. Real and artificial accelerograms, matching EC8 response spectrum for a medium soil class, are considered for dynamic analyses.

  6. Development of Information Datasheets of Nuclear Power Plant (NPP) Equipment using cfiXLM schema

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Jaiho; Song, Eunhye [KHNP-Central Research Institute, Daejeon (Korea, Republic of)

    2014-05-15

    In 2009, EPRI (Electrical Power Research Institute) published a new NPP information handover guide to provide NPP owners and operators with data handover templates in consistent format for effective delivery of information during all stages of the handover process. Another difficult concern for NPP data information management is to exchange the data information among many organizations such as NPP owners, operators, engineering companies, suppliers, and vendors. As a matter of fact, the improperly formatted handover of information sometimes occurs due to the discrepancy of data format (e. g., data description language type). This improper delivery can make negative effects on NPP integrity and safety. Thus, the lack of proper exchange for different data information systems of organizations should be resolved by using an international standard data format. The standard data format can reduce the cost and time for data exchange in each phase for design, procurement, delivery, installation, operation and maintenance of equipment. The AEX(automating equipment information exchange) pilot implementation project team under EPRI advanced nuclear technology (ANT) program has been conducted a research for the use of XML equipment schemas for electronic data exchange(EDE). They applied XML equipment schema for the design, selection, quotation, purchase and mock install of a safety injection centrifugal pump using EDE standard HI(hydraulic institute) 50.7. For data exchange, FIATECH, an industry consortium, has equally developed library of templates and reference data for ISO-15926, which is an international standard capable of reducing data-error and delivery time for exchanging data among different organizations. KHNP as an only owner/operator company has not experienced much difficulty in data interoperability with other organizations, but continued its unremitting exertions to develop a robust system capable of managing data information generated in all the stages of NPP

  7. Damage investigation of girder bridges under the Wenchuan earthquake and corresponding seismic design recommendations

    Institute of Scientific and Technical Information of China (English)

    Li Jianzhong; Peng Tianbo; Xu yan

    2008-01-01

    An investigation of girder bridges on National Highway 213 and the Doujiangyan-Wenchuan expressway after the Wenchuan earthquake showed that typical types of damage included:span collapses due to unseating at expansion joints;shear key failure;and damage of the expansion joint due to the slide-induced large relative displacement between the bottom of the girder and the top of the laminated-rubber bearing.This slide,however,can actually act as a form of isolation for the substructure,and as a result,the piers and foundation of most of the bridges on state route 213 suffered minor damage.The exception was the Baihua Bridge,which suffered severe damage.Corresponding seismic design recommendations are presented based on this investigation.

  8. On the Computation of H/V and its Application to Microzonation and Seismic Design

    Science.gov (United States)

    Perton, M.; Martínez, J. A.; Lermo, J. F.; Sanchez-Sesma, F. J.

    2014-12-01

    The H/V ratio is the square root of the ratio of horizontal to vertical energies of ground motion. It has been observed that the frequency of the main peak is well suited for the characterization of site effects and had been widely used for micro-zonation and seismic structural design. Historically that ratio was made from the average of individual H/V ratios obtained from noise autocorrelations. Nevertheless, it has been recently pointed out that the H/V ratio should be calculated differently as the ratio of the average of H over the average of V. This calculation is based on the relation between the directional energies (the imaginary part of Green's function) and the noise autocorrelations. In general, the average of ratios is different from the ratio of averages. Although the frequency of the main response was correctly obtained, the associated amplification factor has generally been badly predicted, having little matching with the amplification observed during strong earthquakes. The unexpected decay behavior of such ratios at high frequency and the lack of stability and reproducibility of the H/V ratios are other problems that face the method. These problems are addressed here from the point of view of normalization of noise correlations. In fact, several normalization techniques have already been proposed in order to correctly retrieve the Green's function. Some of them are well suited for the retrieval of the surface wave contribution, while others are more appropriate for bulk wave incidence. Since the H/V ratio may be used for various purposes like surface wave tomography, micro-zonation or seismic design, different normalizations are discussed in functions of the objectives. The H/V obtained from local historical earthquakes on top or far away from the subduction zone are also discussed. ACKNOWLEDGEMENT This research has been partially supported by DGAPA-UNAM under Project IN104712 and the AXA Research Fund.

  9. Enhancement of Seismic Performance Using Shear Link Braces in a Building Designed Only for Gravity Loads

    Science.gov (United States)

    Maniyar, S. U.; Paul, D. K.

    2012-02-01

    The present work attempts to study the behaviour of building designed for gravity loads only under the effect of lateral seismic load. Such a building is generally deficient against lateral forces and need to be retrofitted against lateral earthquake forces. A retrofitting scheme by providing aluminium shear link with chevron braces is suggested to improve its performance. Past earthquakes have shown a great deal of damages to the deficient RC frame buildings designed without any consideration to the lateral earthquake forces. Chevron braces with the aluminium shear link can be implemented as an effective retrofit measure. A comparison of the performance of building initially designed for gravity load only with the retrofitted building using chevron braces with the aluminium shear link is presented in this paper. The behaviour of building is worked out by performing nonlinear static pushover analysis and nonlinear time history analyses. A parametric study has also been carried out to study the effect of shear link and braces on the retrofitted building. The performance of RC building designed for gravity loads only as evaluated from the nonlinear static pushover analysis lies in life safety and collapse prevention range for DBE and MCE level of earthquakes respectively. The same building when retrofitted by using chevron braces with aluminium shear link show improved performance. This device is very simple, economic, effective and can be placed in a building very easily. The dissipation of damaging energy/damage is localised in shear link which can be replaced after a major earthquake.

  10. Problems and their solutions in practical application of Eurocodes in seismic design of RC structures

    Directory of Open Access Journals (Sweden)

    Milev Jordan

    2016-01-01

    Full Text Available The main purpose of the paper is to present practical application of Eurocodes in the field of RC structures design. The selected examples represent the main problems in practical application of Eurocodes for seismic analysis and design of RC Structures in Bulgarian construction practice. The analysis is focused on some structural and economic problems as well as on some contradictions in Eurocode 8 itself. Special attention is paid to the practical solution of the following problems: recognition of torsionally flexible systems, stiffness reduction of RC elements for linear analysis dimensions and detailing of confined boundary areas of shear walls, detailing of wall structures, etc. Those problems appear during the practical design of some buildings in Bulgaria. Several proposals for solving some problems defined in the paper are presented through some practical examples. Some conclusions are made for further application of Eurocode 8 in the design and construction practice. The importance of some rules and procedures in Eurocode 8 is supported by the examples of damaged RC members during the past earthquakes. The problems of Eurocode 8 and their solutions are illustrated through the experience of Bulgarian construction practice.

  11. Analysis list: npp-13 [Chip-atlas[Archive

    Lifescience Database Archive (English)

    Full Text Available npp-13 Embryo + ce10 http://dbarchive.biosciencedbc.jp/kyushu-u/ce10/target/npp-13....1.tsv http://dbarchive.biosciencedbc.jp/kyushu-u/ce10/target/npp-13.5.tsv http://dbarchive.biosciencedbc.jp/kyushu-u/ce10/target/npp...-13.10.tsv http://dbarchive.biosciencedbc.jp/kyushu-u/ce10/colo/npp-13.Embryo.tsv http://dbarchive.biosciencedbc.jp/kyushu-u/ce10/colo/Embryo.gml ...

  12. Analysis list: npp-3 [Chip-atlas[Archive

    Lifescience Database Archive (English)

    Full Text Available npp-3 Embryo + ce10 http://dbarchive.biosciencedbc.jp/kyushu-u/ce10/target/npp-3.1....tsv http://dbarchive.biosciencedbc.jp/kyushu-u/ce10/target/npp-3.5.tsv http://dbarchive.biosciencedbc.jp/kyushu-u/ce10/target/npp...-3.10.tsv http://dbarchive.biosciencedbc.jp/kyushu-u/ce10/colo/npp-3.Embryo.tsv http://dbarchive.biosciencedbc.jp/kyushu-u/ce10/colo/Embryo.gml ...

  13. The development of stochastic process modeling through risk analysis derived from scheduling of NPP project

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Kwang Ho; Roh, Myung Sub [KEPCO International Nuclear Graduate School, Ulsan (Korea, Republic of)

    2013-10-15

    There are so many different factors to consider when constructing a nuclear power plant successfully from planning to decommissioning. According to PMBOK, all projects have nine domains from a holistic project management perspective. They are equally important to all projects, however, this study focuses mostly on the processes required to manage timely completion of the project and conduct risk management. The overall objective of this study is to let you know what the risk analysis derived from scheduling of NPP project is, and understand how to implement the stochastic process modeling through risk management. Building the Nuclear Power Plant is required a great deal of time and fundamental knowledge related to all engineering. That means that integrated project scheduling management with so many activities is necessary and very important. Simulation techniques for scheduling of NPP project using Open Plan program, Crystal Ball program, and Minitab program can be useful tools for designing optimal schedule planning. Thus far, Open Plan and Monte Carlo programs have been used to calculate the critical path for scheduling network analysis. And also, Minitab program has been applied to monitor the scheduling risk. This approach to stochastic modeling through risk analysis of project activities is very useful for optimizing the schedules of activities using Critical Path Method and managing the scheduling control of NPP project. This study has shown new approach to optimal scheduling of NPP project, however, this does not consider the characteristic of activities according to the NPP site conditions. Hence, this study needs more research considering those factors.

  14. Influence of Uncertainty of Rock Properties on Seismic Responses of Reactor Buildings

    Institute of Scientific and Technical Information of China (English)

    2006-01-01

    The influence of the dispersion and uncertainty of the dynamic shear wave velocity and Poisson's ratio of soil in a hard rock site was investigated on the seismic response of reactor building structure. The analysis is performed by considering the soil-structure interaction effects and based on the model of the reactor building in a typical pressurized water reactor nuclear power plant (NPP). The numerical results show that for the typical floor selected, while the relative increment ratio of the dynamic shear wave velocity varies from -30% to 30% compared to the basis of 1 930 m/s, the relative variation of the horizontal response spectra peak value lies in the scope of ±10% for the internal structure, and the relative variation of the frequency corresponding to the spectra peak is 0.0% in most cases. The relative variation of the vertical response spectra peak value lies in the scope of - 10% to 22%, and the relative variation of the frequency corresponding to the spectra peak lies in the scope of -22% to 4%. The analysis indicates that the dynamic shear wave velocity and the Poisson's ratio of the rock would affect the seismic response of structure and the soil-structure interaction effects should be considered in seismic analysis and design of NPP even for a hard rock site.

  15. A probabilistic seismic risk assessment procedure for nuclear power plants: (II) Application

    Science.gov (United States)

    Huang, Y.-N.; Whittaker, A.S.; Luco, N.

    2011-01-01

    This paper presents the procedures and results of intensity- and time-based seismic risk assessments of a sample nuclear power plant (NPP) to demonstrate the risk-assessment methodology proposed in its companion paper. The intensity-based assessments include three sets of sensitivity studies to identify the impact of the following factors on the seismic vulnerability of the sample NPP, namely: (1) the description of fragility curves for primary and secondary components of NPPs, (2) the number of simulations of NPP response required for risk assessment, and (3) the correlation in responses between NPP components. The time-based assessment is performed as a series of intensity-based assessments. The studies illustrate the utility of the response-based fragility curves and the inclusion of the correlation in the responses of NPP components directly in the risk computation. ?? 2011 Published by Elsevier B.V.

  16. GA-based optimum design of a shape memory alloy device for seismic response mitigation

    Science.gov (United States)

    Ozbulut, O. E.; Roschke, P. N.; Y Lin, P.; Loh, C. H.

    2010-06-01

    Damping systems discussed in this work are optimized so that a three-story steel frame structure and its shape memory alloy (SMA) bracing system minimize response metrics due to a custom-tailored earthquake excitation. Multiple-objective numerical optimization that simultaneously minimizes displacements and accelerations of the structure is carried out with a genetic algorithm (GA) in order to optimize SMA bracing elements within the structure. After design of an optimal SMA damping system is complete, full-scale experimental shake table tests are conducted on a large-scale steel frame that is equipped with the optimal SMA devices. A fuzzy inference system is developed from data collected during the testing to simulate the dynamic material response of the SMA bracing subcomponents. Finally, nonlinear analyses of a three-story braced frame are carried out to evaluate the performance of comparable SMA and commonly used steel braces under dynamic loading conditions and to assess the effectiveness of GA-optimized SMA bracing design as compared to alternative designs of SMA braces. It is shown that peak displacement of a structure can be reduced without causing significant acceleration response amplification through a judicious selection of physical characteristics of the SMA devices. Also, SMA devices provide a recentering mechanism for the structure to return to its original position after a seismic event.

  17. A new methodology for energy-based seismic design of steel moment frames

    Science.gov (United States)

    Mezgebo, Mebrahtom Gebrekirstos; Lui, Eric M.

    2017-01-01

    A procedure is proposed whereby input and hysteretic energy spectra developed for single-degree-of-freedom (SDOF) systems are applied to multi-degree-of-freedom (MDOF) steel moment resisting frames. The proposed procedure is verified using four frames, viz., frame with three-, five-, seven- and nine-stories, each of which is subjected to the fault-normal and fault-parallel components of three actual earthquakes. A very good estimate for the three- and five-story frames, and a reasonably acceptable estimate for the seven-, and nine-story frames, have been obtained. A method for distributing the hysteretic energy over the frame height is also proposed. This distribution scheme allows for the determination of the energy demand component of a proposed energy-based seismic design (EBSD) procedure for each story. To address the capacity component of EBSD, a story-wise optimization design procedure is developed by utilizing the energy dissipating capacity from plastic hinge formation/rotation for these moment frames. The proposed EBSD procedure is demonstrated in the design of a three-story one-bay steel moment frame.

  18. Seismicity in pipeline design; Consideraciones sismicas en el diseno de tuberias

    Energy Technology Data Exchange (ETDEWEB)

    Flores Berrones, Raul; Vassilev, Vanguel H. [Instituto Mexicano de Tecnologia del Agua, Jiutepec, Morelos (Mexico)

    1999-08-01

    The design of buried pipelines should include the effect of seismic vibrations. This review covers the basic practices recommended in Japan and the USA based on their extensive research, applications and field experiences. The factors that affect the forces acting along the soil-pipeline interface are presented first, focussing on the response of the continuous and segmented lines to the seismic wave-induced soil movement. This step-by-step procedure estimates the unit deformations in continuous pipelines and compares them with the permitted values. For segmented pipelines, both a simplified procedure and a more sophisticated finite element method are presented; the latter calculates the forces and deformations in each segment, and the expansion and contraction at each joint. [Spanish] Se hace una revision de la forma como se ha tomado en cuenta, para fines de diseno, el efecto de las vibraciones sismicas en el comportamiento de las tuberias enterradas. La revision comprende fundamentalmente la practica recomendada en Japon y en los Estados Unidos de America, ya que es en esos paises donde mayor investigacion, aplicacion y registro de campo existen sobre el tema. Se presenta primeramente los factores que influyen en las fuerzas ejercidas a lo largo de la superficie donde interactua el suelo con la tuberia; en particular, se considera la respuesta de una tuberia al movimiento del suelo causado por las ondas sismicas, tanto para el caso de las tuberias continuas como para el de las tuberias segmentadas. Se presenta un procedimiento que muestra paso a paso la manera como se estiman las deformaciones unitarias en las tuberias continuas y su comparacion con las deformaciones permisibles. Para el caso de las tuberias segmentadas, se presentan un metodo simplificado y un procedimiento mas sofisticado utilizando el metodo del elemento finito; este ultimo permite determinar, ademas de los esfuerzos y deformaciones correspondientes a cada tubo, la expansiones o contracciones

  19. Application of Robotic System for Emergency Response in NPP

    Energy Technology Data Exchange (ETDEWEB)

    Jeong, Kyung Min; Seo, Yong Chil; Shin, Ho Chul; Lee, Sung Uk; Cho, Jae Wan; Choi, Young Soo; Kim, Chang Hoi; Kim, Seung Ho [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2010-10-15

    Increasing energy demand and concerns over climate change make increasing use of nuclear power plant in worldwide. Even though the probability of accident is greatly reduced, safety is the highest priority issue in the nuclear energy industry. Applying highly reliable and conservative 'defense in depth' concepts with the design and construction of NPP, there are very little possibilities with which accidents are occur and radioactive materials are released to environments in NPP. But NPP have prepared with the emergency response procedures and conduct exercises for post-accident circumstance according to the procedures. The application of robots for emergency response task for post-accident in nuclear facilities is not a new concept. Robots have been sent to recover the damaged reactor at Chernobyl where human workers could receive a lifetime dose of radiation in minutes. Based on NRC's TMI-2 Cleanup Program, several robots were built in the 1980s to help gather information and remove debris from a reactor at the Three Mile Island nuclear power plant that partially melted down in 1979. The first robot was lowered into the basement through a hatch and human operators monitoring in a control room drove it through mud, water and debris, capturing the initial post-accident images of the reactor's basement. It was used for several years equipped with various tools allowing it to scour surfaces, scoop samples and vacuum sludge. A second version carried a core sampler to determine the intensity and depth of the radiation that had permeated into the walls. To perform cleanup tasks, they built Workhorse that featured system redundancy and had a boom extendable to reach high places, but it was never used because it had too many complexities and to clean and fix. While remote robotics technology has proven to remove the human from the radioactive environment, it is also difficult to make it useful because it may requires skill about remote control and

  20. Seismic design technology for breeder reactor structures. Volume 4. Special topics in piping and equipment

    Energy Technology Data Exchange (ETDEWEB)

    Reddy, D.P.

    1983-04-01

    This volume is divided into five chapters: experimental verification of piping systems, analytical verification of piping restraint systems, seismic analysis techniques for piping systems with multisupport input, development of floor spectra from input response spectra, and seismic analysis procedures for in-core components. (DLC)

  1. Seismic design technology for breeder reactor structures. Volume 4. Special topics in piping and equipment

    Energy Technology Data Exchange (ETDEWEB)

    Reddy, D.P.

    1983-04-01

    This volume is divided into five chapters: experimental verification of piping systems, analytical verification of piping restraint systems, seismic analysis techniques for piping systems with multisupport input, development of floor spectra from input response spectra, and seismic analysis procedures for in-core components. (DLC)

  2. Constant-ductility strength demand spectra for seismic design of structures

    Institute of Scientific and Technical Information of China (English)

    Zhai Changhai; Xie Lili

    2005-01-01

    In displacement-based seismic design, constant-ductility strength demand spectra (CDSDS) are very useful for preliminary design of new structures where the global displacement ductility capacity is known. The CDSDS can provide the required inelastic lateral strength of new structures from the required elastic lateral strength. Based on a statistical study of nonlinear time-history for an SDOF system, the mean CDSDS corresponding to four site conditions are presented and approximate expressions of the inelastic spectra are proposed, which are functions of the structural period and ductility level.The effects of site conditions, structural period, level of ductility, damping and post-yield stiffness of structures on CDSDS are also investigated. It is concluded that site conditions, ductility level and structural period have important effects on the CDSDS and damping, post-yield stiffness effects are rather complex and of minor importance. The damping, post-yield stiffness effects depend on both the level of ductility and the natural period of structures.

  3. Highly Deformable Energy-Dissipating Reinforced Concrete Elements in Seismic Design of Reinforced Concrete Structures

    Directory of Open Access Journals (Sweden)

    Momoh Emmanuel Owoichoechi

    2017-06-01

    Full Text Available Incorporating scrap tyre rubber particles as partial replacement for aggregates has been found to produce concrete with improved ductility, deformability and damping which are desired characteristics of a viable material for enhancing structural response to earthquake vibrations. An analytical study using Drain-2dX was carried out to investigate the response of 4-storey, 3-bay reinforced concrete frames on innovative rubberised concrete deformable foundation models to simulated earthquake scaled to 5 different peak ground accelerations. Stress-strain properties of 3-layers aramid fibre-reinforced polymer (FRP-confinement for concrete incorporating waste rubber from scrap vehicle tyres were used to model the elements of this foundation models. With a partial decoupling of the superstructure from the direct earthquake force, the models showed up to 70% reduction in base shear, an improved overall q-factor of 7.1, and an estimated frame acceleration of 0.11g for an earthquake peak ground acceleration of 0.44g. This implies that a non-seismically designed reinforced concrete frame on the proposed rubberised concrete deformable foundation system would provide a simple, affordable and equally efficient alternative to the conventional and usually expensive earthquake resistant concrete frames. A supplementary Arrest System (SAS was proposed to anchor the frame from the resulting soft storey at the rubberised concrete foundation. A further research is recommended for the design of concrete hinges with rubberised concrete as used in the model with the most impressive response.

  4. Knowledge management in the NPP domain

    Energy Technology Data Exchange (ETDEWEB)

    Nilsen, Svein; Bisio, Rossella; Ludvigsen, Jan Tore

    2004-03-15

    This report gives an outlook on Knowledge Management (KM) activities within NPP related establishments as of today. There may be less activity in the NPP world as compared to many other industrial sectors. Still there is an awakening within the NPP industry demanding that KM should be attended to at a larger scale. The most notable reason for this is maybe an imminent increase in the number of people going into retirement. The types of establishments involved cover the major kinds such as utilities, research institutes and worldwide nuclear organizations. The report sums up a few of those efforts that are presently being implemented. Moreover the report looks at general advancements within the field of knowledge management. Simply stated the endeavours belong to either one of two classes. The first class emphasize the use of technology to solve knowledge management problems. The second class regard knowledge management as a problem pertaining to human factors and organizational issues. This report maintain that knowledge management initiatives should make due considerations to both perspectives. This report also sums up the Halden Reactor Project short term KM initiative. (Author)

  5. Development of requirements tracking and verification technology for the NPP software

    Energy Technology Data Exchange (ETDEWEB)

    Jung, Chul Hwan; Kim, Jang Yeol; Lee, Jang Soo; Song, Soon Ja; Lee, Dong Young; Kwon, Kee Choon

    1998-12-30

    Searched and analyzed the technology of requirements engineering in the areas of aerospace and defense industry, medical industry and nuclear industry. Summarized the status of tools for the software design and requirements management. Analyzed the software design methodology for the safety software of NPP. Development of the design requirements for the requirements tracking and verification system. Development of the background technology to design the prototype tool for the requirements tracking and verification.

  6. Site study plan for EDBH (Engineering Design Boreholes) seismic surveys, Deaf Smith County site, Texas: Revision 1

    Energy Technology Data Exchange (ETDEWEB)

    Hume, H.

    1987-12-01

    This site study plan describes seismic reflection surveys to run north-south and east-west across the Deaf Smith County site, and intersecting near the Engineering Design Boreholes (EDBH). Both conventional and shallow high-resolution surveys will be run. The field program has been designed to acquire subsurface geologic and stratigraphic data to address information/data needs resulting from Federal and State regulations and Repository program requirements. The data acquired by the conventional surveys will be common-depth- point, seismic reflection data optimized for reflection events that indicate geologic structure near the repository horizon. The data will also resolve the basement structure and shallow reflection events up to about the top of the evaporite sequence. Field acquisition includes a testing phase to check/select parameters and a production phase. The field data will be subjected immediately to conventional data processing and interpretation to determine if there are any anamolous structural for stratigraphic conditions that could affect the choice of the EDBH sites. After the EDBH's have been drilled and logged, including vertical seismic profiling, the data will be reprocessed and reinterpreted for detailed structural and stratigraphic information to guide shaft development. The shallow high-resulition seismic reflection lines will be run along the same alignments, but the lines will be shorter and limited to immediate vicinity of the EDBH sites. These lines are planned to detect faults or thick channel sands that may be present at the EDBH sites. 23 refs. , 7 figs., 5 tabs.

  7. Numerical computation of fragility curves for NPP equipment

    Energy Technology Data Exchange (ETDEWEB)

    Zentner, I., E-mail: irmela.zentner@edf.f [LaMSID, Laboratory for the Mechanics of Aging Industrial Structures, UMR EDF/CNRS, 1, av. du General de Gaulle, 92141 Clamart (France)

    2010-06-15

    The seismic probabilistic risk assessment (PRA) methodology is a popular approach for evaluating the risk of failure of engineering structures due to earthquake. In this framework, fragility curves express the conditional probability of failure of a structure or component for a given seismic input motion parameter A, such as peak ground acceleration (PGA) or spectral acceleration. The failure probability due to a seismic event is obtained by convolution of fragility curves with seismic hazard curves. In general, a log-normal model is used in order to estimate fragilities. In nuclear engineering practice, these fragilities are determined using safety factors with respect to design earthquake. This approach allows to determine fragility curves based on design study but largely draws on expert judgement and simplifying assumptions. When a more realistic assessment of seismic fragility is needed, simulation-based statistical estimation of fragility curves is more appropriate. In this paper, we will discuss statistical estimation of parameters of fragility curves and present results obtained for a reactor coolant system of nuclear power plant. We have performed non-linear dynamic response analyses using artificially generated strong motion time histories. Uncertainties due to seismic loads as well as model uncertainties are taken into account and propagated using Monte Carlo simulation.

  8. Design of Seismic Test Rig for Control Rod Drive Mechanism of Jordan Research and Training Reactor

    Energy Technology Data Exchange (ETDEWEB)

    Sun, Jongoh; Kim, Gyeongho; Yoo, Yeonsik; Cho, Yeonggarp; Kim, Jong In [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2014-05-15

    The reactor assembly is submerged in a reactor pool filled with water and its reactivity is controlled by locations of four control absorber rods(CARs) inside the reactor assembly. Each CAR is driven by a stepping motor installed at the top of the reactor pool and they are connected to each other by a tie rod and an electromagnet. The CARs scram the reactor by de-energizing the electromagnet in the event of a safe shutdown earthquake(SSE). Therefore, the safety function of the control rod drive mechanism(CRDM) which consists of a drive assembly, tie rod and CARs is to drop the CAR into the core within an appropriate time in case of the SSE. As well known, the operability for complex equipment such as the CRDM during an earthquake is very hard to be demonstrated by analysis and should be verified through tests. One of them simulates the reactor assembly and the guide tube of the CAR, and the other one does the pool wall where the drive assembly is installed. In this paper, design of the latter test rig and how the test is performed are presented. Initial design of the seismic test rig and excitation table had its first natural frequency at 16.3Hz and could not represent the environment where the CRDM was installed. Therefore, experimental modal analyses were performed and an FE model for the test rig and table was obtained and tuned based on the experimental results. Using the FE model, the design of the test rig and table was modified in order to have higher natural frequency than the cutoff frequency. The goal was achieved by changing its center of gravity and the stiffness of its sliding bearings.

  9. Design and experimental verification of a new multi-functional bridge seismic isolation bearing

    Institute of Scientific and Technical Information of China (English)

    Chen-xi XING; Hao WANG; Ai-qun LI; Ji-rong WU

    2012-01-01

    A new multi-functional bridge seismic isolation bearing (MFBSIB) is designed and its mechanical model is developed in this paper.Combining an upper sliding device and a lower energy dispassion isolation device effectively,the new MFBSIB can adjust the deformation caused by temperature,vehicle breaks,and concrete creep,etc.,in addition to dissipating energy.The switch of ‘slide-isolation' is achieved and the efficiency of both upper and lower parts is validated through experiment with a model.The shear performance curve established in this paper is verified to be efficient in describing the mechanical characteristics of the bearing through experiment.It is proved through both numerical calculation and experimental analysis that the new MFBSIB is endowed with enough vertical rigidity,good energy dissipation ability,stable overall performance,and good realization in expected goals.Its performance is slightly influenced by shear stress,while affected by vertical pressure,loading frequency,slide limit,etc.,diversely.The results could provide reference for study and application of the new MFBSIB.

  10. Application of seismic refraction tomography for tunnel design in Santa Clara Mountain, San Juan, Argentina Application of seismic refraction tomography for tunnel design in Santa Clara Mountain, San Juan, Argentina

    Directory of Open Access Journals (Sweden)

    Imhof Armando Luis

    2011-12-01

    Full Text Available

    A geophysical survey involving seismic refraction tomography (SRT for mapping 'P' waves was carried out in Sierra Santa Clara, San Juan Province, Argentina in July 2009. The purpose of the geophysical survey was to determine the degree of fracturing and the rigidity of the rock mass through which it is planned to build a 290 m long road tunnel traversing the mountain almost perpendicular to the axis thereof, at around 100 m depth from the summit.

    Several difficulties arose from the operational point of view which made it almost impossible to conduct fieldwork in normal circumstances. Firstly, the topography had almost 45° slopes and 100 m research depths which would have involved having had to use explosives to generate seismic waves reaching sensors which had sufficient signal-to-noise ratio for distinguishing them. Legal restrictions regarding the use of explosives on the one hand and insufficient power when using hammer blows on the other made it necessary to design and build a gas-powered gun to achieve the minimum energy (2 kJ required for detecting seismic signals.

    Secondly, using conventional interpretation methods involving layered models was inoperable in such geological structures; seismic tomography methods were thus used which make use of the velocity gradient concept (both lateral and in-depth. This allowed mapping subsurface velocity variations in the form of velocity contour lines.

    The methodology used with the new seismic waves' source generator, as well as SRT application in this type of geological structure, demonstrated that satisfactory results could be obtained for this kind of geophysical study for geotechnical purposes.

    A geophysical survey involving seismic refraction tomography (SRT for mapping 'P' waves was

  11. Simplified seismic collapse capacity-based evaluation and design of frame buildings with and without supplemental damping systems

    Science.gov (United States)

    Hamidia, Mohammad Javad

    A simplified procedure is developed for estimating the seismic sidesway collapse capacity of frame building structures. The procedure is then extended to quantify the seismic collapse capacity of buildings incorporating supplemental damping systems. The proposed procedure is based on a robust database of seismic peak displacement responses of viscously damped nonlinear single-degree-of-freedom systems for various seismic intensities and uses nonlinear static (pushover) analysis without the need for nonlinear time history dynamic analysis. The proposed procedure is assessed by comparing its collapse capacity predictions on 1470 different building models with those obtained from incremental nonlinear dynamic analyses. A straightforward unifying collapse capacity based design procedure aimed at achieving a pre-determined probability of collapse under maximum considered earthquake event is also introduced for structures equipped with viscous dampers (linear and nonlinear) and hysteretic dampers. The proposed simplified procedure offers a simple, yet efficient, computational/analytical tool that is capable of predicting collapse capacities with acceptable accuracy for a wide variety of frame building structures incorporate several types of supplemental damping systems.

  12. Performance Based Plastic Design of Concentrically Braced Frame attuned with Indian Standard code and its Seismic Performance Evaluation

    Directory of Open Access Journals (Sweden)

    Sejal Purvang Dalal

    2015-12-01

    Full Text Available In the Performance Based Plastic design method, the failure is predetermined; making it famous throughout the world. But due to lack of proper guidelines and simple stepwise methodology, it is not quite popular in India. In this paper, stepwise design procedure of Performance Based Plastic Design of Concentrically Braced frame attuned with the Indian Standard code has been presented. The comparative seismic performance evaluation of a six storey concentrically braced frame designed using the displacement based Performance Based Plastic Design (PBPD method and currently used force based Limit State Design (LSD method has also been carried out by nonlinear static pushover analysis and time history analysis under three different ground motions. Results show that Performance Based Plastic Design method is superior to the current design in terms of displacement and acceleration response. Also total collapse of the frame is prevented in the PBPD frame.

  13. Structural design of active seismic isolation floor with a charging function

    Science.gov (United States)

    Nakakoji, Hayato; Miura, Nanako

    2016-04-01

    This study shows an optimum structure of a seismic isolation floor against horizontal ground motions. Although a seismic isolation floor is effective with vibration reduction, the response of the floor becomes larger when excited by long-period ground motions. It is shown that caster equipment move and suffer damage in a seismic isolation structure by an experiment. Moreover, the permissible displacement of the floor is limited. Therefore, the focus is on an active seismic isolation. About active control, the system cannot operate without power supply. To solve these problems an energy regeneration is considered in our previous study. These studies only analyze simple model and did not choose the suitable structure for active control and energy regeneration. This research propose a new structure which has regenerated energy exceeds the energy required for the active control by numerical simulation.

  14. On the Seismic Safety of Nuclear Power Plant Sites in South Korea

    Science.gov (United States)

    Choi, H.; Park, S.; Yang, J.; Shim, T.; Im, C. B.

    2016-12-01

    The Korean Peninsula is located at the far eastern part of Eurasian Plate, and within the intra-plate region several hundred km away from the nearest plate boundary. The earthquakes around the Korean Peninsula show the typical characteristics of intra-plate earthquakes. So to speak, those are low seismicity, relatively smaller magnitude than that of inter-plate earthquakes, and spatially irregular epicenters. There are 24 nuclear power plants (NPPs) in operation, 4 NPPs in completion of construction, and 4 NPPs in preparation of construction in South Korea. Even though the seismicity of the Korean Peninsula is known as relatively low, but because there are more than 30 NPPs within not so large territory, thorough the preparedness of NPPs' safety against earthquakes is required. The earthquake preparedness of NPPs in South Korea is composed of 4 stages: site election, design, construction and operation. Since regulatory codes and standards are strictly applied in each stage, the NPPs in South Korea are believed to be safe enough against the maximum potential earthquake ground motion. Through data analysis on geological and seismological characteristics of the region within a radius of 320 km from the site and the detailed geological survey of the area within a radius of 8 km from the site, the design earthquake ground motion of NPPs in South Korea is determined to be 0.2g (in case of newly constructed NPPs is 0.3g) considering the maximum potential earthquake ground motion and some safety margin. The ground motions and surface deformation caused by capable faults are also considered in the seismic design of NPPs. In addition, the Korea Institute of Nuclear Safety as a regulatory technical expert organization, has been operating independent real time earthquake monitoring network as a part of securing the seismic safety of NPP sites in South Korea since late 1990's. If earthquakes with more than magnitude 3.0 are occurred in the Korean Peninsula or the peak ground

  15. Conceptual Design and Architecture of Mars Exploration Rover (MER) for Seismic Experiments Over Martian Surfaces

    Science.gov (United States)

    Garg, Akshay; Singh, Amit

    2012-07-01

    Keywords: MER, Mars, Rover, Seismometer Mars has been a subject of human interest for exploration missions for quite some time now. Both rover as well as orbiter missions have been employed to suit mission objectives. Rovers have been preferentially deployed for close range reconnaissance and detailed experimentation with highest accuracy. However, it is essential to strike a balance between the chosen science objectives and the rover operations as a whole. The objective of this proposed mechanism is to design a vehicle (MER) to carry out seismic studies over Martian surface. The conceptual design consists of three units i.e. Mother Rover as a Surrogate (Carrier) and Baby Rovers (two) as seeders for several MEMS-based accelerometer / seismometer units (Nodes). Mother Rover can carry these Baby Rovers, having individual power supply with solar cells and with individual data transmission capabilities, to suitable sites such as Chasma associated with Valles Marineris, Craters or Sand Dunes. Mother rover deploys these rovers in two opposite direction and these rovers follow a triangulation pattern to study shock waves generated through firing tungsten carbide shells into the ground. Till the time of active experiments Mother Rover would act as a guiding unit to control spatial spread of detection instruments. After active shock experimentation, the babies can still act as passive seismometer units to study and record passive shocks from thermal quakes, impact cratering & landslides. Further other experiments / payloads (XPS / GAP / APXS) can also be carried by Mother Rover. Secondary power system consisting of batteries can also be utilized for carrying out further experiments over shallow valley surfaces. The whole arrangement is conceptually expected to increase the accuracy of measurements (through concurrent readings) and prolong life cycle of overall experimentation. The proposed rover can be customised according to the associated scientific objectives and further

  16. Three-dimensional seismic survey planning based on the newest data acquisition design technique; Saishin no data shutoku design ni motozuku sanjigen jishin tansa keikaku

    Energy Technology Data Exchange (ETDEWEB)

    Minehara, M.; Nakagami, K.; Tanaka, H. [Japan National Oil Corp., Tokyo (Japan). Technology Research Center

    1996-10-01

    Theory of parameter setting for data acquisition is arranged, mainly as to the seismic generating and receiving geometry. This paper also introduces an example of survey planning for three-dimensional land seismic exploration in progress. For the design of data acquisition, fundamental parameters are firstly determined on the basis of the characteristics of reflection records at a given district, and then, the layout of survey is determined. In this study, information through modeling based on the existing interpretation of geologic structures is also utilized, to reflect them for survey specifications. Land three-dimensional seismic survey was designed. Ground surface of the surveyed area consists of rice fields and hilly regions. The target was a nose-shaped structure in the depth about 2,500 m underground. A survey area of 4km{times}5km was set. Records in the shallow layers could not obtained when near offset was not ensured. Quality control of this distribution was important for grasping the shallow structure required. In this survey, the seismic generating point could be ensured more certainly than initially expected, which resulted in the sufficient security of near offset. 2 refs., 2 figs.

  17. Application of Moessbauer spectroscopy on corrosion products of NPP

    Energy Technology Data Exchange (ETDEWEB)

    Dekan, J., E-mail: julius.dekan@stuba.sk; Lipka, J.; Slugen, V. [Institute of Nuclear and Physical Engineering, Faculty of Electrical Engineering and Information Technology, SUT (Slovakia)

    2013-04-15

    Steam generator (SG) is generally one of the most important components at all nuclear power plants (NPP) with close impact to safe and long-term operation. Material degradation and corrosion/erosion processes are serious risks for long-term reliable operation. Steam generators of four VVER-440 units at nuclear power plants V-1 and V-2 in Jaslovske Bohunice (Slovakia) were gradually changed by new original 'Bohunice' design in period 1994-1998, in order to improve corrosion resistance of SGs. Corrosion processes before and after these design and material changes in Bohunice secondary circuit were studied using Moessbauer spectroscopy during last 25 years. Innovations in the feed water pipeline design as well as material composition improvements were evaluated positively. Moessbauer spectroscopy studies of phase composition of corrosion products were performed on real specimens scrapped from water pipelines or in form of filters deposits. Newest results in our long-term corrosion study confirm good operational experiences and suitable chemical regimes (reduction environment) which results mostly in creation of magnetite (on the level 70 % or higher) and small portions of hematite, goethite or hydrooxides. Regular observation of corrosion/erosion processes is essential for keeping NPP operation on high safety level. The output from performed material analyses influences the optimisation of operating chemical regimes and it can be used in optimisation of regimes at decontamination and passivation of pipelines or secondary circuit components. It can be concluded that a longer passivation time leads more to magnetite fraction in the corrosion products composition.

  18. Assessment the Behavior of Seismic Designed Steel Moment Frames Subjected to Progressive Collapse

    Directory of Open Access Journals (Sweden)

    Azlan Bin Adnan

    2014-02-01

    Full Text Available Recent investigations reveal that progressive collapse phenomenon is dominant behavior in the majority of steel structures. Although the design of buildings is based on the fact that they need to withstand all the loads exerted on the structure, failure occurs as a result of inadequate design and modeling techniques, particularly for abnormal and extreme loading conditions. Once one or more load bearing member is eliminated from the structure, progressive collapse, mainly in columns, will commence. By the time a column is eliminated from the structure as a result of a sudden motor vehicle strike or earthquake or fire or any other internal or external factor that could take one column out of the system, the weight of the building (gravity load will be distributed among other columns within the structure. Failure commences in the part of the structure that has lost a column unless other columns are designed appropriately against gravity loads and are capable of redistribution of additional loads imposed on them. Failure of vertical load bearing elements will continue until the stabilization of extra loading. Hence, this could lead to serious damage and collapse of the building which will lead to higher damage to the building than the primary damage. This research is based on the regulations conforming to the specifications of UFC guidelines and the structures have been modeled using SAP2000 (2012. In order to study the effects of the progressive collapse on the seismic design of special steel moment frames, SMRF, two 5-story and 15-storystructures are modeled in SAP2000 (2012. In order to have a better understanding of progressive collapse and obtain reliable results, Linear Static (LS, Nonlinear Static (NLS and Nonlinear Dynamic analyses (NLD procedure for single and 2 adjacent columns removal have been implemented in this study. Having a good perception of the possibility of progressive collapse involves incorporation of demand capacity ratio

  19. Seismic Studies

    Energy Technology Data Exchange (ETDEWEB)

    R. Quittmeyer

    2006-09-25

    This technical work plan (TWP) describes the efforts to develop and confirm seismic ground motion inputs used for preclosure design and probabilistic safety 'analyses and to assess the postclosure performance of a repository at Yucca Mountain, Nevada. As part of the effort to develop seismic inputs, the TWP covers testing and analyses that provide the technical basis for inputs to the seismic ground-motion site-response model. The TWP also addresses preparation of a seismic methodology report for submission to the U.S. Nuclear Regulatory Commission (NRC). The activities discussed in this TWP are planned for fiscal years (FY) 2006 through 2008. Some of the work enhances the technical basis for previously developed seismic inputs and reduces uncertainties and conservatism used in previous analyses and modeling. These activities support the defense of a license application. Other activities provide new results that will support development of the preclosure, safety case; these results directly support and will be included in the license application. Table 1 indicates which activities support the license application and which support licensing defense. The activities are listed in Section 1.2; the methods and approaches used to implement them are discussed in more detail in Section 2.2. Technical and performance objectives of this work scope are: (1) For annual ground motion exceedance probabilities appropriate for preclosure design analyses, provide site-specific seismic design acceleration response spectra for a range of damping values; strain-compatible soil properties; peak motions, strains, and curvatures as a function of depth; and time histories (acceleration, velocity, and displacement). Provide seismic design inputs for the waste emplacement level and for surface sites. Results should be consistent with the probabilistic seismic hazard analysis (PSHA) for Yucca Mountain and reflect, as appropriate, available knowledge on the limits to extreme ground

  20. Degradation and Failure Characteristics of NPP Containment Protective Coating Systems

    Energy Technology Data Exchange (ETDEWEB)

    Sindelar, R.L.

    2001-02-22

    A research program to investigate the performance and potential for debris formation of Service Level I coating systems used in nuclear power plant containment is being performed at the Savannah River Technology Center. The research activities are aligned to address phenomena important to cause coating disbondment as identified by the Industry Coatings Expert Panel. The period of interest for performance covers the time from application of the coating through 40 years of service, followed by a medium-to-large break loss-of-coolant accident scenario, which is a design basis accident (DBA) scenario. The interactive program elements are described in this report and the application of these elements to evaluate the performance of the specific coating system of Phenoline 305 epoxy-phenolic topcoat over Carbozinc 11 primer on a steel substrate. This system is one of the predominant coating systems present on steel substrates in NPP containment.

  1. Post-Launch Calibration Support for VIIRS Onboard NASA NPP Spacecraft

    Science.gov (United States)

    Xiong, Xiaoxion; Chiang, Kwo-Fu; McIntire, Jeffrey; Schwaller, Matthew; Butler, James

    2011-01-01

    The NPP Instrument Calibration Support Element (NICSE) is one of the elements within the NASA NPP Science Data Segment (SDS). The primary responsibility of NICSE is to independently monitor and evaluate on-orbit radiometric and geometric performance of the Visible Infrared Imaging Radiometer Suite (VIIRS) instrument and to validate its Sensor Data Record (SDR) [1]. The NICSE interacts and works closely with other SDS Product Evaluation and Analysis Tools Elements (PEATE) and the NPP Science Team (ST) and supports their on-orbit data product calibration and validation efforts. The NICSE also works closely with the NPP Instrument Calibration Support Team (NICST) during sensor pre-launch testing in ambient and thermal vacuum environment [2]. This paper provides an overview of NICSE VIIRS sensor post-launch calibration support with a focus on the use of sensor on-board calibrators (OBC) for the radiometric calibration and characterization. It presents the current status of NICSE post-launch radiometric calibration tool development effort based on its design requirements

  2. Forward alliance. AREVA's initiative for NPP's LTO projects

    Energy Technology Data Exchange (ETDEWEB)

    Bergholz, Steffen; Heinz, Benedikt; Rudolph, Juergen [AREVA GmbH, Erlangen (Germany); Quist, Perry [EPZ - Elektriciteits-Productiemaatschappij Zuid-Nederland N.V., Borssele (Netherlands)

    2014-08-15

    Nowadays, the abbreviation LTO (Long Term Operation) is well known in the NPP's world. No other kind of projects can ensure the actual economic and environmental questions of the world of energy production with this high efficiency. Two-thirds of the actual international NPP fleet in operation has reached an age of more than 25 years. The former NPP's design life of normally 40 years has changed to 60 years for new plants. Furthermore, the existing fleet is nominally prepared for an operational period of more the 40 years. AREVA had launched the Forward Alliance initiative which offers different activities to ensure a support of customer's LTO projects. This article will give an overview on the Forward Alliance initiative followed by a technical example how the AREVA Fatigue Concept (AFC) can fulfill the fatigue monitoring topic within potential LTO projects. The successfully realized LTO project for NPP Borssele (Netherlands) shows as a customer example how the Forward Alliance blocks can work.

  3. Design and implementation of a low-cost multichannel seismic noise recorder for array measurements

    Science.gov (United States)

    Soler-Llorens, Juan Luis; Juan Giner-Caturla, Jose; Molina-Palacios, Sergio; Galiana-Merino, Juan Jose; Rosa-Herranz, Julio; Agea-Medina, Noelia

    2017-04-01

    Soil characterization is the starting point for seismic hazard studies. Currently, the methods based on ambient noise measurements are very used because they are non-invasive methods and relatively easy to implement in urban areas. Among these methods, the analysis of array measurements provides the dispersion curve and subsequently the shear-wave velocity profile associated to the site under study. In this case, we need several sensors recording simultaneously and a data acquisition system with one channel by sensor, what can become the complete equipment unaffordable for small research groups. In this work, we have designed and implemented a low-cost multichannel ambient noise recorder for array measurements. The complete system is based on Arduino, an open source electronic development platform, which allows recording 12 differential input channels simultaneously. Besides, it is complemented with a conditioning circuit that includes an anti-aliasing filter and a selectable gain between 0 and 40dB. The data acquisition is set up through a user-friendly graphical user interface. It is important to note that the electronic scheme as well as the programming code are open hardware and software, respectively, so it allows other researchers to suite the system to their particular requirements. The developed equipment has been tested at several sites around the province of Alicante (southeast of Spain), where the soil characteristics are well-known from previous studies. Array measurements have been taken and after that, the recorded data have been analysed using the frequency-wavenumber (f-k) and the extended spatial autocorrelation (ESAC) methods. The comparison of the obtained dispersion curves with the ones obtained in previous studies shows the suitability of the implemented low-cost system for array measurements.

  4. Seismic design and evaluation guidelines for the Department of Energy High-Level Waste Storage Tanks and Appurtenances

    Energy Technology Data Exchange (ETDEWEB)

    Bandyopadhyay, K.; Cornell, A.; Costantino, C.; Kennedy, R.; Miller, C.; Veletsos, A.

    1995-10-01

    This document provides seismic design and evaluation guidelines for underground high-level waste storage tanks. The guidelines reflect the knowledge acquired in the last two decades in defining seismic ground motion and calculating hydrodynamic loads, dynamic soil pressures and other loads for underground tank structures, piping and equipment. The application of the guidelines is illustrated with examples. The guidelines are developed for a specific design of underground storage tanks, namely double-shell structures. However, the methodology discussed is applicable for other types of tank structures as well. The application of these and of suitably adjusted versions of these concepts to other structural types will be addressed in a future version of this document. The original version of this document was published in January 1993. Since then, additional studies have been performed in several areas and the results are included in this revision. Comments received from the users are also addressed. Fundamental concepts supporting the basic seismic criteria contained in the original version have since then been incorporated and published in DOE-STD-1020-94 and its technical basis documents. This information has been deleted in the current revision.

  5. Displacement based seismic design of symmetric single-storey wood-frame buildings with the aid of N2 method

    Directory of Open Access Journals (Sweden)

    Panagiotis eMergos

    2015-07-01

    Full Text Available This paper presents a new methodology for the displacement-based seismic design of symmetric single-storey wood-frame buildings. Previous displacement-based design efforts were based on the direct displacement-based design (DDBD approach, which uses a substitute linear system with an appropriate stiffness and viscous damping combination. Despite the fact that this method has shown to produce promising results for wood structures, it does not fit into the framework of the Eurocode 8 (EC8 provisions. The methodology presented herein is based on the N2 method, which is incorporated in EC8 and combines the non-linear pushover analysis with the response spectrum method. The N2 method has been mostly applied to reinforced concrete and steel structures. In order to properly implement the N2 method for the case of wood-frame buildings new behavior factor – displacement ductility relationships are proposed. These relationships were derived from inelastic time history analyses of 35 SDOF systems subjected to 80 different ground motion records. Furthermore, the validity of the N2 method is examined for the case of a timber shear wall tested on a shake table and satisfactory predictions are obtained. Last, the proposed design methodology is applied to the displacement-based seismic design of a realistic symmetric single-storey wood-frame building in order to meet the performance objectives of EC8. It is concluded that the simplicity and computational efficiency of the adopted methodology make it a valuable tool for the seismic design of this category of wood-frame buildings, while the need for extending the method to more complex wood-frame buildings is also highlighted.

  6. Forest NPP estimation based on MODIS data under cloudless condition

    Institute of Scientific and Technical Information of China (English)

    2008-01-01

    Based on light-use efficiency model, an MODIS-derived daily net primary production (NPP) model was developed. In this model, a new model for the fraction of photosynthetically active radiation absorbed by vegetation (FPAR) is developed based on leaf area index (LAI) and albedo parameters, and a pho- tosynthetically active radiation (PAR) is calculated from the combination of Bird’s model with aerosol optical thickness and water vapor derived from cloud free MODIS images. These two models are inte- grated into our predicted NPP model, whose most parameters are retrieved from MODIS data. In order to validate our NPP model, the observed NPP in the Qianyanzhou station and the Changbai Mountains station are used to compare with our predicted NPP, showing that they are in good agreement. The NASA NPP products also have been downloaded and compared with the measurements, which shows that the NASA NPP products underestimated NPP in the Qianyanzhou station but overestimated in the Changbai Mountains station in 2004.

  7. Seismic design of steel structures with lead-extrusion dampers as knee braces

    Science.gov (United States)

    monir, Habib Saeed; Naser, Ali

    2008-07-01

    One of the effective methods in decreasing the seismic response of structure against dynamic loads due to earthquake is using energy dissipating systems. Lead-extrusion dampers (LED)are one of these systems that dissipate energy in to one lead sleeve because of steel rod movement. Hysteresis loops of these dampers are approximately rectangular and acts independent from velocity in frequencies that are in the seismic frequency rang. In this paper lead dampers are considered as knee brace in steel frames and are studied in an economical view. Considering that lead dampers don't clog structural panels, so this characteristic can solve brace problems from architectural view. The behavior of these dampers is compared with the other kind of dampers such as XADAS and TADAS. The results indicate that lead dampers act properly in absorbing the induced energy due to earthquake and good function in controlling seismic movements of multi-story structures

  8. Lessons learned from the "5.12" Wenchuan Earthquake: evaluation of earthquake performance objectives and the importance of seismic conceptual design principles

    Institute of Scientific and Technical Information of China (English)

    Wang Yayong

    2008-01-01

    Many different types of buildings were severely damaged or collapsed during the May 12, 2008 Great Wenchuan Earthquake. Based on survey data collected in regions that were subjected to moderate to severe earthquake intensities, a comparison between the observed building damage, and the three earthquake performance objectives and seismic conceptual design principles specified by the national "Code for Seismic Design of Buildings GB50011-2001," was carried out. Actual damage and predicted damage for a given earthquake level for different types of structures is compared. Discussions on seismic conceptual design principles, with respect to multiple defense lines, strong column-weak beam, link beam of shear walls, ductility detailing of masonry structures, exits and staircases, and nonstructural elements, etc. Are carried out. Suggestions for improving the seismic design of structures are also proposed. It is concluded that the seismic performance objectives for three earthquake levels, I.e., "no failure under minor earthquake level, ""repairable damage under moderate earthquake level" and "no collapse under major earthquake level" can be achieved if seismic design principles are carried out by strictly following the code requirements and ensuring construction quality.

  9. Prioritization of Delay Factors for NPP Construction Risk in International Project by Using AHP Methodology

    Energy Technology Data Exchange (ETDEWEB)

    Hossen, Muhammed Mufazzal; Kang, Sunkoo; Kim, Jonghyun [KEPCO International Nuclear Graduate School, Ulsan (Korea, Republic of)

    2014-10-15

    construction delay of NPP. The main contribution of the work was the identification of main cause of NPP construction schedule delay for turnkey contractual approached international project in different level. The second contribution was a development of a multi-criteria decision making model for the prioritization of NPP construction delay risk factors. Finally, prioritization of delay factors in different levels of NPP construction delay risk factors were accomplished. The model is developed by using the AHP methodology. This study has produced results and insights that involve one of the most vital aspect which is the quantitative weights and ranking of factors that affect delay in NPP construction. Undoubtedly, it is a necessity in the NPP construction industry for the use of quantitative terms when it comes to schedule delay risk. The outcomes of this study confirm that the model is capable to support decision-makers to examine the strengths and weaknesses of factors in different level of the NPP construction phase. Decision makers of nuclear industry can understand the significance of different factors on NPP construction phase and they can apply risk informed decision making to avoid unexpected construction delay of NPP. This study finds the different party's importance in behind the construction schedule delay of NPP which constitutes main contractor (28.4%), regulatory authority (27.3%), Financial and Country Factor (23.5%), and utility (20.8%).The results show that the top most important 5 sub factors according to global weight in level 2 are delayed regulatory approval, country factor, inadequate completion of design before start of construction, slow procurement, manufacturing of equipment and delivery to the site for installation, and financial matters. This study finds top most important 10 sub-sub factors in the lowest level which are uncompromising regulatory criteria and conflicting licensing documents with existing regulations, robust design documents

  10. Seismic damage assessment of reinforced concrete structure and its seismic design%框架结构地震损伤评估与抗震设计

    Institute of Scientific and Technical Information of China (English)

    章永乐; 蒋建群; 刘加进; 王振宇

    2011-01-01

    针对现行的结构抗震设计规范没有考虑双震中地震动对结构性能的影响问题,引入同时反映位移超越及能量耗散影响的双参数损伤模型进行结构损伤评估,可以更好地反映结构构件在不同类型地震动作用下的损伤发展规律.比较4种构件的双参数损伤模型,并对其中一种模型进行改进.对汶川地震中一典型的9层框架结构进行三维非线性地震响应分析,研究结构损伤规律.分析结果表明,结构主要的损伤积累发生在第一次主震中.结合现行抗震设计规范,提出一种直接基于目标损伤指标的结构抗震设计方法,通过一简单算例验证了该方法对大震作用下结构抗震设计的适用性.%The obvious dual-epicenter was not considered in the present seismic design code. An appropriate damage model should take both the damage caused by dissipated energy and displacement overpass into consideration in order to evaluate the progress of structural damage. Four damage models were described, and one of which was improved. Comparisons of the damage models were made in three-dimensional nonlinear dynamic analysis of a 9-storey reinforced concrete structure subjected to a real Wenchuan earthquake excitation. Results showed that damage in the structural members increased mainly in the first shock. A performance-based approach based on target damage index was proposed and verified in conjunction with present seismic design method for high level earthquake.

  11. South Ukraine NPP: Safety improvements through Plant Computer upgrade

    Energy Technology Data Exchange (ETDEWEB)

    Brenman, O. [Westinghouse Electric Company, 4350 Northern Pike, Monroeville, PA 15146 (United States); Chernyshov, M. A. [Westron, LLC, 1 Acad. Proskura St., Kharkiv 61070 (Ukraine); Denning, R. S. [Battelle, 505 King Ave, Columbus, OH 43201 (United States); Kolesov, S. A. [NAEK Energoatom, 3 Vetrov Str., Kiev, 01032 (Ukraine); Balakan, H. H.; Bilyk, B. I.; Kuznetsov, V. I. [PO South Ukraine NPP, NAEK Energoatom, Mylolayv Region, 55000 (Ukraine); Trosman, G. [US Dept. of Energy, International Nuclear Safety Program, Washington, DC 20585 (United States)

    2006-07-01

    This paper summarizes some results of the Plant Computer upgrade at the Units 2 and 3 of South Ukraine Nuclear Power Plant (NPP). A Plant Computer, which is also called the Computer Information System (CIS), is one of the key safety-related systems at VVER-1000 nuclear plants. The main function of the CIS is information support for the plant operators during normal and emergency operational modes. Before this upgrade, South Ukraine NPP operated out-of-date and obsolete systems. This upgrade project wax founded by the U.S. DOE in the framework of the International Nuclear Safety Program (INSP). The most efficient way to improve the quality and reliability of information provided to the plant operator is to upgrade the Human-System Interface (HSI), which is the Upper Level (UL) CIS. The upgrade of the CIS data-acquisition system (DAS), which is the Lower Level (LL) CIS, would have less effect on the unit safety. Generally speaking, the lifetime of the LL CIS is much higher than one of the UL CIS. Unlike Plant Computers at the Western-designed plants, the functionality of the WER-1000 CISs includes a control function (Centralized Protection Testing) and a number of the plant equipment monitoring functions, for example, Protection and Interlock Monitoring and Turbo-Generator Temperature Monitoring. The new system is consistent with a historical migration of the format by which information is presented to the operator away from the traditional graphic displays, for example, Piping and Instrument Diagrams (P and ID's), toward Integral Data displays. The cognitive approach to information presentation is currently limited by some licensing issues, but is adapted to a greater degree with each new system. The paper provides some lessons learned on the management of the international team. (authors)

  12. The influence of micro-regionalization in the seismic conditions of project; La influencia de la micro-regionalizacion en el ambiente sismico de proyecto

    Energy Technology Data Exchange (ETDEWEB)

    Alcaide Echegoyen, Y.; Rueda Aramburu, D. de; Aguilar Rodriguez, J. A.; Garcia-Monge Fernandez, J.

    2011-07-01

    This paper presents a methodology for analyzing the behavior of seismic waves through the stratigraphic column. As an example applies to the dynamic characteristics of the stratigraphic column of the site of ASCO NPP.

  13. Probabilistic Seismic Hazard Characterization and Design Parameters for the Sites of the Nuclear Power Plants of Ukraine

    Energy Technology Data Exchange (ETDEWEB)

    Savy, J.B.; Foxall, W.

    2000-01-26

    The U.S. Department of Energy (US DOE), under the auspices of the International Nuclear Safety Program (INSP) is supporting in-depth safety assessments (ISA) of nuclear power plants in Eastern Europe and the former Soviet Union for the purpose of evaluating the safety and upgrades necessary to the stock of nuclear power plants in Ukraine. For this purpose the Hazards Mitigation Center at Lawrence Livermore National Laboratory (LLNL) has been asked to assess the seismic hazard and design parameters at the sites of the nuclear power plants in Ukraine. The probabilistic seismic hazard (PSH) estimates were updated using the latest available data and knowledge from LLNL, the U.S. Geological Survey, and other relevant recent studies from several consulting companies. Special attention was given to account for the local seismicity, the deep focused earthquakes of the Vrancea zone, in Romania, the region around Crimea and for the system of potentially active faults associated with the Pripyat Dniepro Donnetts rift. Aleatory (random) uncertainty was estimated from the available data and the epistemic (knowledge) uncertainty was estimated by considering the existing models in the literature and the interpretations of a small group of experts elicited during a workshop conducted in Kiev, Ukraine, on February 2-4, 1999.

  14. Seismic Effects on the Design of Geosynthetic-Reinforced Earth Retaining Structures

    Science.gov (United States)

    1998-07-01

    geosynthetics and are subjected to cyclic motion such as that caused by earthquakes. It will examine some case studies of the performance of... geosynthetic reinforced earth retaining structures (GSRW) and review some time tested concepts dealing with both geosynthetics and seismic earth pressures

  15. Principle and Program of Evaluating Diffuse Seismicity

    Institute of Scientific and Technical Information of China (English)

    Chang Xiangdong

    2001-01-01

    Concept and origin of the term "the diffuse seismicity" are illustrated. Some different viewpoints regarding the diffuse seismicity and the influence characteristics on determining seismic design basis of engineering from the seismicity are analyzed. Principle and program for evaluating diffuse seismicity are studied and discussed base on over contents.

  16. Seismic Design of Japanese Portal Frame Bridge%日本单跨门式刚架桥的抗震设计

    Institute of Scientific and Technical Information of China (English)

    张春轶; 施立鑫; 李岩

    2011-01-01

    简要介绍日本单跨门式刚架桥的特点,通过抗震性能,解析方法,解析步骤,设计水平震度,地震土压系数等几方面对抗震设计进行了阐述.最后介绍了单跨门式刚架桥的适用条件.%This paper introduces the characteristics of Japanese portal frame bridge, and seismic design of bridge are described by the seismic performance, analytical methods and procedures, the design level of seismic intensity, seismic pressure coefficient. Finally, it introduces application conditions of portal frame bridge.

  17. Recent development of seismic evaluation for Swedish NPPs

    Energy Technology Data Exchange (ETDEWEB)

    Bennemo, L. [Vattenfall Energisystem, Stockholm (Sweden)

    1997-03-01

    In Scandinavia seismic activity is generally low. Only a few incidents have been registered in historic time, which might have damaged an industrial plant of today. There has been no earthquakes in Sweden strong enough to affect a NPP during our nuclear era (and not for very long time before either). So the risk for an nuclear accident i Sweden, caused by an earthquake, may thus be considered to be low. The basis and the methodology used in the design of Forsmark 3 and Oskarshamn 3 with respect to seismic safety is not in all parts suited to be employed for the older reactors. The methods implies a number of simplifications which may be a practical approach in connection with a new design but which might cause too conservative judgements of existing designs. The development of methods is therefore a vital part in the analysis. The Swedish nuclear Power Inspectorate (SKI), Vattenfall AB, Sydkraft AB and Oskarshams Kraftgrupp AB (OKG) have performed such a development of methods in a joint research program: `Project Seismic Safety`. The aim of the project was to develop methods for calculating the ground response to be used in the safety analysis of nuclear power plants in Sweden, as well as to demonstrate its application to the power plants at Ringhals and Barseback. The study also included a survey of geological and seismological conditions in the regions around the power plants studied. Since the large scale geological and seismological conditions around the individual nuclear plant sites are not very different as regards their expected effects on the seismic ground motion, the results obtained for the `typical hard rock site` can be taken as a basis for the characterization of the ground motions at the individual sites, after appropriate transformations to account for specific load conditions, seismological as well as geological. (J.P.N.)

  18. N-16 monitors: Almaraz NPP experience

    Energy Technology Data Exchange (ETDEWEB)

    Adrada, J. [Almaraz NPP, Madrid (Spain)

    1997-02-01

    Almaraz Nuclear Power Plant has installed N-16 monitors - one per steam generator - to control the leakage rate through the steam generator tubes after the application of leak before break (LBB) criteria for the top tube sheet (TTS). After several years of operation with the N-16 monitors, Almaraz NPP experience may be summarized as follows: N-16 monitors are very useful to follow the steam generator leak rate trend and to detect an incipient tube rupture; but they do not provide an exact absolute leak rate value, mainly when there are small leaks. The evolution of the measured N-16 leak rates varies along the fuel cycle, with the same trend for the 3 steam generators. This behaviour is associated with the primary water chemistry evolution along the cycle.

  19. Application of Correlation and Coherency Methods to Naqu Seismic Array Design

    Institute of Scientific and Technical Information of China (English)

    Hao Chunyue; Zheng Zhong

    2006-01-01

    The waveform data recorded during the site survey of the Naqu seismic array in Aug. 2004 were processed by the author. According to the relativity of site pairs in time and frequency domains, the reference values of the inner ring and outer ring were determined. The author evaluated the array deployed for site survey as the primary array, and the results show that the resolution of the primary array is high enough to locate earthquakes precisely.

  20. Post-PKS tailoring steps of a disaccharide-containing polyene NPP in Pseudonocardia autotrophica.

    Directory of Open Access Journals (Sweden)

    Hye-Jin Kim

    Full Text Available A novel polyene compound NPP identified in a rare actinomycetes, Pseudonocardia autotrophica KCTC9441, was shown to contain an aglycone identical to nystatin but to harbor a unique di-sugar moiety, mycosaminyl-(α1-4-N-acetyl-glucosamine, which led to higher solubility and reduced hemolytic activity. Although the nppDI was proved to be responsible for the transfer of first polyene sugar, mycosamine in NPP biosynthesis, the gene responsible for the second sugar extending glycosyltransferase (GT as well as NPP post-PKS tailoring mechanism remained unknown. Here, we identified a NPP-specific second sugar extending GT gene named nppY, located at the edge of the NPP biosynthetic gene cluster. Targeted nppY gene deletion and its complementation proved that nppY is indeed responsible for the transfer of second sugar, N-acetyl-glucosamine in NPP biosynthesis. Site-directed mutagenesis on nppY also revealed several amino acid residues critical for NppY GT function. Moreover, a combination of deletions and complementations of two GT genes (nppDI and nppY and one P450 hydroxylase gene (nppL involved in the NPP post-PKS biosynthesis revealed that NPP aglycone is sequentially modified by the two different GTs encoded by nppDI and nppY, respectively, followed by the nppL-driven regio-specific hydroxylation at the NPP C10 position. These results set the stage for the biotechnological application of sugar diversification for the biosynthesis of novel polyene compounds in actinomycetes.

  1. Nonlinear Time Domain Seismic Soil-Structure Interaction (SSI) Deep Soil Site Methodology Development

    Energy Technology Data Exchange (ETDEWEB)

    Spears, Robert Edward [Idaho National Lab. (INL), Idaho Falls, ID (United States); Coleman, Justin Leigh [Idaho National Lab. (INL), Idaho Falls, ID (United States)

    2015-09-01

    methodology will be known as, NonLinear Soil-Structure Interaction (NLSSI). In general NLSSI analysis should provide a more accurate representation of the seismic demands on nuclear facilities their systems and components. INL, in collaboration with a Nuclear Power Plant Vender (NPP-V), will develop a generic Nuclear Power Plant (NPP) structural design to be used in development of the methodology and for comparison with SASSI. This generic NPP design has been evaluated for the INL soil site because of the ease of access and quality of the site specific data. It is now being evaluated for a second site at Vogtle which is located approximately 15 miles East-Northeast of Waynesboro, Georgia and adjacent to Savanna River. The Vogtle site consists of many soil layers spanning down to a depth of 1058 feet. The reason that two soil sites are chosen is to demonstrate the methodology across multiple soil sites. The project will drive the models (soil and structure) using successively increasing acceleration time histories with amplitudes. The models will be run in time domain codes such as ABAQUS, LS-DYNA, and/or ESSI and compared with the same models run in SASSI. The project is focused on developing and documenting a method for performing time domain, non-linear seismic soil structure interaction (SSI) analysis. Development of this method will provide the Department of Energy (DOE) and industry with another tool to perform seismic SSI analysis.

  2. The Terrestrial NPP Simulation in China since 6ka BP

    Institute of Scientific and Technical Information of China (English)

    HE Yong; DONG Wenjie; JI Jinjun; DAN Li

    2005-01-01

    A better understanding of the long-term global carbon cycle required estimate of the changes in terrestrial carbon storage after the last glacial period. The results of simulation at mid-Holocene (MH) from PMIP (Paleoclimate Modeling Intercomparison Project) and the modern data from CRU (Climate Research Unit,East Anglia University, UK) allow us to use the Atmosphere-Vegetation Interaction Model (AVIM) to simulate the Chinese terrestrial net primary productivity (NPP) at 6ka BP and present time. The change of NPP and total NPP in China from now to mid-Holocene are about 54 g m-2yr-1 and 0.63 Pg yr-1,respectively, mainly due to the build-up of temperate forest and tropical rainforest. Chinese terrestrial NPP variation from MH to now is closely related to the variation in intensity of Asian monsoon, which controlled the climate-vegetation pattern change.

  3. Stade NPP. Dismantling of the reactor pool

    Energy Technology Data Exchange (ETDEWEB)

    Scharf, Daniel; Dziwis, Joachim [E.ON Anlagenservice GmbH Nukleartechnik, Gelsenkirchen (Germany); Kemp, Lutz-Hagen [KKW Stade GmbH und Co. oHG, Stade (Germany)

    2012-11-01

    Within the scope of the 4{sup th} partial decommissioning permission of Stade NPP the activated and contaminated structures of the reactor pool had to be dismantled in order to gain a completely non-radioactive reactor pool area for the subsequent clearance measurement of the reactor building. In order to achieve the aim it was intended to remove the activated pool liner sheets, its activated framework and several contaminated ventilation channels made of stainless steel, the concrete walls of the reactor pool entirely or in parts depending on their activation level, as well as the remaining activated carbon steel structures of the reactor pool bottom. Embedded in the concrete walls there were several highly contaminated excore tubes and the contaminated pool top edge, which were intended to be removed to its full extent. The contract of the Stade NPP initiated reactor pool dismantling project had been awarded to E.ON Anlagenservice GmbH (EAS) and its subsupplier sat. Kerntechnik GmbH for the concrete dismantling works and was performed as follows. In order to minimize the radiation level in the main working area in accordance with the ALARA principle, the liner sheets and middle parts of its framework were removed by means of angle grinders first, as they were the most dose rate relevant parts. As a result the primary average radiation level in the reactor pool (measured in a distance of 500 mm from the walls) was lowered from 40 {mu}Sv/h to less than 2 {mu}Sv/h. After the minimization of the radiation level in the working area the main dismantling step started with the cutting of the reactor pool walls in blocks by means of diamond rope cutters. Once a concrete block was cut out, it was transported into the fuel pool by means of a crane and crane fork, examined radiologically, marked area by area and segmented to debris by means of an electrical excavator with a hydraulic chisel. Afterwards the debris and carbon steel parts were fractioned and packed for further

  4. A comparative study between China and U.S. on seismic design philosophy and practice of a long span arch bridge

    Institute of Scientific and Technical Information of China (English)

    Xu Yan; George C Lee; Fan Lichu; Hu Shide

    2006-01-01

    This paper presents the first of a series of case studies on the seismic design of long span bridges (cablestayed bridges, suspension bridges and arch bridges) under a cooperative research project on seismic behavior and design of highway bridges between the State Key Laboratory for Disaster Reduction in Civil Engineering, Tongji University and the Multidisciplinary Center for Earthquake Engineering Research, University at Buffalo. The objective of this series of case studies is to examine the differences and similarities on the seismic design practice of long span bridges in China and the U.S., to identify research needs and to develop design guidelines beneficial to bridge engineers in both countries. Unlike short to medium span bridges, long span bridges are not included in most seismic design specifications, mainly because they are location dependent and structurally unique. In this paper, an available model of a steel tied half through arch bridge with a main span of 550m in China is discussed. Analysis is focused on comparisons of the seismic responses due to different ground motions. Seismic design criteria and seismic performance requirements for long span bridges in both countries were first introduced and compared, and then three near field earthquake records with large vertical components were selected as the excitations to examine the seismic behavior and seismic vulnerability of the bridge. Results show that (1) the selected near field ground motions cause larger responses to key components (critical sections) of the bridge (such as arch rib ends) with a maximum increase of more than twice those caused by the site specific ground motions; (2) piers, longitudinal girders and arch crowns are more vulnerable to vertical motions, especially their axial forces; and (3) large vertical components of near field ground motions may not significantly affect the bridge's internal forces provided that their peak acceleration spectra ordinates only appear at periods

  5. Seismic design and evaluation guidelines for the Department of Energy high-level waste storage tanks and appurtenances

    Energy Technology Data Exchange (ETDEWEB)

    Bandyopadhyay, K.; Cornell, A.; Costantino, C.; Kennedy, R.; Miller, C.; Veletsos, A.

    1993-01-01

    This document provides guidelines for the design and evaluation of underground high-level waste storage tanks due to seismic loads. Attempts were made to reflect the knowledge acquired in the last two decades in the areas of defining the ground motion and calculating hydrodynamic loads and dynamic soil pressures for underground tank structures. The application of the analysis approach is illustrated with an example. The guidelines are developed for specific design of underground storage tanks, namely double-shell structures. However, the methodology discussed is applicable for other types of tank structures as well. The application of these and of suitably adjusted versions of these concepts to other structural types will be addressed in a future version of this document.

  6. 自动喷水灭火系统的抗震设计%Sprinkler systems for the seismic design

    Institute of Scientific and Technical Information of China (English)

    张明

    2011-01-01

    自动喷水灭火系统的抗震措施应在设计和安装时予以考虑,以确保在地震发生次生火灾时能正常发挥作用,保护财产安全.自动喷水灭火系统抗震设计的方式主要有抗震支撑、柔性连接及设置间隙三种方式.%The aseismic measures of automatic sprinkler system should be taken into consideration in the design and installation. It assures that the system can cperate mormally to protect the property and the fire safety during the secondary fire of earthquake. The main methods of seismic design are earthquake support, flexonics and setting of gap.

  7. Seismic energy dissipation study of linear fluid viscous dampers in steel structure design

    Directory of Open Access Journals (Sweden)

    A. Ras

    2016-09-01

    Full Text Available Energy dissipation systems in civil engineering structures are sought when it comes to removing unwanted energy such as earthquake and wind. Among these systems, there is combination of structural steel frames with passive energy dissipation provided by Fluid Viscous Dampers (FVD. This device is increasingly used to provide better seismic protection for existing as well as new buildings and bridges. A 3D numerical investigation is done considering the seismic response of a twelve-storey steel building moment frame with diagonal FVD that have linear force versus velocity behaviour. Nonlinear time history, which is being calculated by Fast nonlinear analysis (FNA, of Boumerdes earthquake (Algeria, May 2003 is considered for the analysis and carried out using the SAP2000 software and comparisons between unbraced, braced and damped structure are shown in a tabulated and graphical format. The results of the various systems are studied to compare the structural response with and without this device of the energy dissipation thus obtained. The conclusions showed the formidable potential of the FVD to improve the dissipative capacities of the structure without increasing its rigidity. It is contributing significantly to reduce the quantity of steel necessary for its general stability.

  8. A design method for high performance seismic data acquisition based on oversampling delta-sigma modulation

    Science.gov (United States)

    Gao, Shanghua; Xue, Bing

    2017-04-01

    The dynamic range of the currently most widely used 24-bit seismic data acquisition devices is 10-20 dB lower than that of broadband seismometers, and this can affect the completeness of seismic waveform recordings under certain conditions. However, this problem is not easy to solve because of the lack of analog to digital converter (ADC) chips with more than 24 bits in the market. So the key difficulties for higher-resolution data acquisition devices lie in achieving more than 24-bit ADC circuit. In the paper, we propose a method in which an adder, an integrator, a digital to analog converter chip, a field-programmable gate array, and an existing low-resolution ADC chip are used to build a third-order 16-bit oversampling delta-sigma modulator. This modulator is equipped with a digital decimation filter, thus forming a complete analog to digital converting circuit. Experimental results show that, within the 0.1-40 Hz frequency range, the circuit board's dynamic range reaches 158.2 dB, its resolution reaches 25.99 dB, and its linearity error is below 2.5 ppm, which is better than what is achieved by the commercial 24-bit ADC chips ADS1281 and CS5371. This demonstrates that the proposed method may alleviate or even solve the amplitude-limitation problem that broadband observation systems so commonly have to face during strong earthquakes.

  9. Effect of Seismic Zone and Story Height on Response Reduction Factor for SMRF Designed According to IS 1893(Part-1):2002

    Science.gov (United States)

    Rao, P. Pravin Venkat; Gupta, L. M.

    2016-12-01

    Indian seismic code design procedure, which permit the estimation of inelastic deformation capacity of lateral force resisting systems, has been questioned since no coherence exists for determining the values of response reduction factor tabulated in code. Indian code at present does not give any deterministic values of ductility reduction factor and overstrength factor to be used in the design, because of the inadequacy of research results currently available. Hence, this study focuses on the variation of overstrength and ductility factors in steel moment resisting frame with different seismic zones and number of story. A total of 12 steel moment resisting frames were analyzed and designed. Response reduction factor has been determined by performing the non-linear static pushover analysis. The result shows that overstrength and ductility factors varies with number of story and seismic zones. It is also observed that for different seismic zones and story, ductility reduction factor is found to be different from overall structural ductility. It is observed that three buildings of different heights had an average overstrength of 63% higher in Zone-II as compared to Zone-V. These observations are extremely significant for building seismic provision codes, that at present not taking into consideration the variation of response reduction factor.

  10. Impact of thicker cladding on the nuclear parameters of the NPP Krsko fuel

    Energy Technology Data Exchange (ETDEWEB)

    Kromar, Marjan, E-mail: marjan.kromar@ijs.s [Jozef Stefan Institute, Reactor Physics Department, Jamova 39, 1001 Ljubljana (Slovenia); Kurincic, Bojan [Nuclear Power Plant Krsko, Engineering Division, Nuclear Fuel and Reactor Core, Vrbina 12, 8270 Krsko (Slovenia)

    2011-04-15

    To make fuel rods more resistant to grid-to-rod fretting or other cladding penetration failures, the cladding thickness could be increased or strengthened. Implementation of thicker fuel rod cladding was evaluated for the NPP Krsko that uses 16 x 16 fuel design. Cladding thickness of the Westinghouse standard fuel design (STD) and optimized fuel design (OFA) is increased. The reactivity effect during the fuel burnup is determined. To obtain a complete realistic view of the fuel behaviour a typical, near equilibrium, 18-month fuel cycle is investigated. The most important nuclear core parameters such as critical boron concentrations, isothermal temperature coefficient and rod worth are determined and compared.

  11. Methodology and measures for preventing unacceptable flow-accelerated corrosion thinning of pipelines and equipment of NPP power generating units

    Science.gov (United States)

    Tomarov, G. V.; Shipkov, A. A.; Lovchev, V. N.; Gutsev, D. F.

    2016-10-01

    Problems of metal flow-accelerated corrosion (FAC) in the pipelines and equipment of the condensate- feeding and wet-steam paths of NPP power-generating units (PGU) are examined. Goals, objectives, and main principles of the methodology for the implementation of an integrated program of AO Concern Rosenergoatom for the prevention of unacceptable FAC thinning and for increasing operational flow-accelerated corrosion resistance of NPP EaP are worded (further the Program). A role is determined and potentialities are shown for the use of Russian software packages in the evaluation and prediction of FAC rate upon solving practical problems for the timely detection of unacceptable FAC thinning in the elements of pipelines and equipment (EaP) of the secondary circuit of NPP PGU. Information is given concerning the structure, properties, and functions of the software systems for plant personnel support in the monitoring and planning of the inservice inspection of FAC thinning elements of pipelines and equipment of the secondary circuit of NPP PGUs, which are created and implemented at some Russian NPPs equipped with VVER-1000, VVER-440, and BN-600 reactors. It is noted that one of the most important practical results of software packages for supporting NPP personnel concerning the issue of flow-accelerated corrosion consists in revealing elements under a hazard of intense local FAC thinning. Examples are given for successful practice at some Russian NPP concerning the use of software systems for supporting the personnel in early detection of secondary-circuit pipeline elements with FAC thinning close to an unacceptable level. Intermediate results of working on the Program are presented and new tasks set in 2012 as a part of the updated program are denoted. The prospects of the developed methods and tools in the scope of the Program measures at the stages of design and construction of NPP PGU are discussed. The main directions of the work on solving the problems of flow

  12. Handling of damaged spent fuel at Ignalina NPP

    Energy Technology Data Exchange (ETDEWEB)

    Ziehm, Ronny [NUKEM Technologies GmbH (Germany); Bechtel, Sascha [Hoefer und Bechtel GmbH (Germany)

    2012-11-01

    The Ignalina Nuclear Power Plant (INPP) is situated in the north-eastern part of Lithuania close to the borders with Latvia and Belarus and on the shore of Lake Druksiai. It is approximately 120 km from the capital city Vilnius. The power plant has two RMBK type water cooled graphite moderated pressure tube reactors each of design capacity 1500MW(e). The start of operation of the Unit 1 was in 1983 and of the Unit 2 in 1987. In the period 1987 - 1991 (i.e. Soviet period) a small proportion of the existing spent nuclear fuel suffered minor to major damages. In the frame of decommissioning of INPP it is necessary that this damaged fuel is retrieved from the storage pools and stored in an interim spent fuel store. NUKEM Technologies GmbH (Germany) as part of a consortium with GNS mbH (Germany) was awarded the contract for an Interim Spent Fuel Storage Facility (B1- ISFSF). This contract includes the design, procurement, manufacturing, supply and installation of a damaged fuel handling system (DFHS). Objective of this DFHS is the safe handling of spent nuclear fuel with major damages, which result in rupture of the cladding and potential loss of fuel pellets from within the cladding. Typical damages are bent fuel bundle skeletons, broken fuel rods, missing or damaged end plugs, very small gaps between fuel bundles, bent central rods between fuel bundles. The presented concept is designed for Ignalina NPP. However, the design is developed more generally to solve these problems with damaged fuel at other nuclear power plants applying these proven techniques. (orig.)

  13. Seismic analysis and evaluation of the base isolation system in AP1000 NI under SSE loading

    Energy Technology Data Exchange (ETDEWEB)

    Chen, Jianyun; Zhao, Chunfeng, E-mail: zhaowindy@126.com; Xu, Qiang; Yuan, Chenyang

    2014-10-15

    Graphical abstract: - Highlights: • The feasibility of base isolation technique in NI is evaluated. • A comparison of structural response highlighted the effectiveness of isolation system. • DAR was proposed to validate the effectiveness of base isolation under SSE. • Connection of pipes, seismic gap and fail safety system are also considered. - Abstract: Safety and integrity of NPP must be ensured during the plant life in any design conditions, particularly, in the event of a severe earthquake. Base isolation as a popular and powerful technology can drastically reduce the seismic response of the structure and prevent the structure from damage. The objective of this paper is to numerically investigate the dynamic response of the AP1000 Nuclear Island (NI) building with and without isolators under a typical safe shutdown earthquake (SSE). By the help of a sophisticated detailed three-dimensional finite element model of the Nuclear Island, the different design solutions are compared in terms of acceleration and relative displacement. The decreasing amplitude ratio (DAR) obtained in the calculations highlights the effectiveness of the isolation system in mitigating the seismic response of the nuclear island of AP1000. Acceleration floor response spectra (carried out from both isolated and non-isolated seismic analysis) are herein also presented and compared in order to validate the isolation technology effectiveness. The obtained numerical results highlight the drastic reduction of considered floor accelerations as the base isolation major effect. The connection of pipelines and design criteria of isolators presently recommended for the stability of isolated building are also validated and verified to highlight the feasibility and safety of the base isolation system. In addition, seismic gap, expansion joint and horizontal fail safe system are also recommended to apply in the isolated structure.

  14. Evaluation of Seismic Performance of Long Span Continuous Girder Bridges Based on Seismic Isolation Design%基于减隔震设计的大跨度连续梁桥抗震性能评价

    Institute of Scientific and Technical Information of China (English)

    李贞新; 刘高

    2011-01-01

    Nonlinear time history analysis method is adopted to analyze dynamic characteristics and seismic performance based on long span continuous girder bridges with spans of 89 m, 170 m and 89 m in high intensity region. The good hysteretic, energy-dissipation characteristics and self-restoring ability of double curvature seismic isolation bearings are simulated as well as the friction energy-dissipation characteristics of sliding bearing and damping energy-dissipation characteristics of dampers. Analytical results indicate that seismic performance can basically meet the expected design goal; seismic isolation device of double curvature spherical supports and dampers can adjust dynamic characteristics, reduce seismic response, dissipate earthquake energy and guarantee the safety of the structure.%基于高烈度区的某大跨度连续梁桥(89 m+170 m+89 m),采用非线性时程分析法进行结构动力特性及抗震性能分析.全桥均采用三维梁单元建立空间模型,对于双曲面球形减隔震支座的滞回耗能特性和自恢复功能,活动支座的摩擦耗能以及固定销剪断后的效应进行了模拟,同时模拟了阻尼器的阻尼耗能作用.研究结果表明:采用双曲面球形减隔震支座及桥台处纵向阻尼器后,结构的反应得到了很好的控制,确保了高烈度区结构的抗震安全性.

  15. Robustness of timber structures in seismic areas

    OpenAIRE

    Neves, Luís A.C.; Branco, Jorge M.

    2011-01-01

    Major similarities between robustness assessment and seismic design exist, and significant information can be brought from seismic design to robustness design. As will be discussed, although some methods and limitations considered in seismic design can improve robustness, the capacity of the structure to sustain limited damage without disproportionate effects is significantly more complex. In fact, seismic design can either improve or reduce the resistance of structures to unfo...

  16. CONCIDERATION OF FOUNDATION AND SEISMIC CONDITIONS OF AREA IN ANALYSIS OF SEISMIC RESISTANCE OF REACTOR COMPARTMENT

    Directory of Open Access Journals (Sweden)

    SEDIN V. L.

    2015-11-01

    Full Text Available Problem statement. Providing of safe exploitation of nuclear power plants, as well as a safety of staff and environment is a very important problem. A distinct feature of this problem is a necessity to provide not only a strength of structures, but also a safe functioning of all systems that control nuclear process. In particular, the influence of earthquake should be considered on constructions of buildings and structures of nuclear and thermal power plant, taking into account soil-structure interaction. According to IAEA’s SSD-9 recommendations, a risk of vibration of soil should be analyzed for each NPP connected with earthquakes soil that means researches, including general, detailed and microseismic zoning of the area works. One of the distinctive features of the considered problem is an evaluation of the seismicity of area and getting the response spectrum on the free surface. Purpose. Determination of seismic resistance of buildings of high category of safety with the example of the reactor compartment of Zaporoghskaya NPP including the soil structure interaction. Conclusion The seismicity assessment of the area and obtaining of response specters on free surface was made during research and analysis of seismic resistance of buildings of high category of safety including the effects of foundation and structures. The method of modeling of the equivalent dynamic characteristics of the base was considered during the research in seismic impacts.

  17. Procedure and method of Equipment Qualification(EQ) for EPA in NPP

    Energy Technology Data Exchange (ETDEWEB)

    Jeong, Sun Chul; Bhang, Keug Jin; Kang, Pil Sun [KHNP Central Research Institute, Daejeon (Korea, Republic of)

    2012-10-15

    The Electric Penetration Assemblies(EPAs) for NPP are usually used for medium voltage power, low voltage power, low voltage control and instrumentation. Field cables either interface with the EPAs using electrical connectors or are terminated to penetration lead wires using splices or terminal blocks. These EPAs provide two critical and distinct functions, which are the electrical continuity, insulation and the containment pressure integrity. EPAs insulation resistance or impedance characteristics may be critical in instrument applications. The following design shows a typical modular unit design. In this paper, we analyze the codes and procedures of the equipment qualification test and propose test items, conditions, and acceptance criteria more specifically.

  18. Seismic hazard analyses for Taipei city including deaggregation, design spectra, and time history with excel applications

    Science.gov (United States)

    Wang, Jui-Pin; Huang, Duruo; Cheng, Chin-Tung; Shao, Kuo-Shin; Wu, Yuan-Chieh; Chang, Chih-Wei

    2013-03-01

    Given the difficulty of earthquake forecast, Probabilistic Seismic Hazard Analysis (PSHA) has been a method to best estimate site-specific ground motion or response spectra in earthquake engineering and engineering seismology. In this paper, the first in-depth PSHA study for Taipei, the economic center of Taiwan with a six-million population, was carried out. Unlike the very recent PSHA study for Taiwan, this study includes the follow-up hazard deaggregation, response spectra, and the earthquake motion recommendations. Hazard deaggregation results show that moderate-size and near-source earthquakes are the most probable scenario for this city. Moreover, similar to the findings in a few recent studies, the earthquake risk for Taipei should be relatively high and considering this city's importance, the high risk should not be overlooked and a potential revision of the local technical reference would be needed. In addition to the case study, some innovative Excel applications to PSHA are introduced in this paper. Such spreadsheet applications are applicable to geosciences research as those developed for data reduction or quantitative analysis with Excel's user-friendly nature and wide accessibility.

  19. Optimizing the design of vertical seismic profiling (VSP) for imaging fracture zones over hardrock basement geothermal environments

    Science.gov (United States)

    Reiser, Fabienne; Schmelzbach, Cedric; Maurer, Hansruedi; Greenhalgh, Stewart; Hellwig, Olaf

    2017-04-01

    A primary focus of geothermal seismic imaging is to map dipping faults and fracture zones that control rock permeability and fluid flow. Vertical seismic profiling (VSP) is therefore a most valuable means to image the immediate surroundings of an existing borehole to guide, for example, the placing of new boreholes to optimize production from known faults and fractures. We simulated 2D and 3D acoustic synthetic seismic data and processed it through to pre-stack depth migration to optimize VSP survey layouts for mapping moderately to steeply dipping fracture zones within possible basement geothermal reservoirs. Our VSP survey optimization procedure for sequentially selecting source locations to define the area where source points are best located for optimal imaging makes use of a cross-correlation statistic, by which a subset of migrated shot gathers is compared with a target or reference image from a comprehensive set of source gathers. In geothermal exploration at established sites, it is reasonable to assume that sufficient à priori information is available to construct such a target image. We generally obtained good results with a relatively small number of optimally chosen source positions distributed over an ideal source location area for different fracture zone scenarios (different dips, azimuths, and distances from the surveying borehole). Adding further sources outside the optimal source area did not necessarily improve the results, but rather resulted in image distortions. It was found that fracture zones located at borehole-receiver depths and laterally offset from the borehole by 300 m can be imaged reliably for a range of the different dips, but more source positions and large offsets between sources and the borehole are required for imaging steeply dipping interfaces. When such features cross-cut the borehole, they are particularly difficult to image. For fracture zones with different azimuths, 3D effects are observed. Far offset source positions

  20. Land 3D-Seismic Data: Preprocessing Quality Control Utilizing Survey Design Specifications, Noise Properties, Normal Moveout, First Breaks, and Offset

    Institute of Scientific and Technical Information of China (English)

    Abdelmoneam Raef

    2009-01-01

    The recent proliferation of the 3D reflection seismic method into the near-surface area of geophysical applications, especially in response to the emergence of the need to comprehensively characterize and monitor near-surface carbon dioxide sequestration in shallow saline aquifers around the world, Justifies the emphasis on cost-effective and robust quality control and assurance (QC/QA) workflow of 3D seismic data preprocessing that is suitable for near-surface applications. The main purpose of our seismic data preprocessing QC is to enable the use of appropriate header information, data that are free of noise-dominated traces, and/or flawed vertical stacking in subsequent processing steps. In this article, I provide an account of utilizing survey design specifications, noise properties, first breaks, and normal moveout for rapid and thorough graphical QC/QA diagnostics, which are easy to apply and efficient in the diagnosis of inconsistencies. A correlated vibroseis time-lapse 3D-seismic data set from n CO2-flood monitoring survey is used for demonstrating QC dlagnostles. An Important by-product of the QC workflow is establishing the number of layers for n refraction statics model in a data-driven graphical manner that capitalizes on the spatial coverage of the 3D seismic data.

  1. Land 3D-seismic data: Preprocessing quality control utilizing survey design specifications, noise properties, normal moveout, first breaks, and offset

    Science.gov (United States)

    Raef, A.

    2009-01-01

    The recent proliferation of the 3D reflection seismic method into the near-surface area of geophysical applications, especially in response to the emergence of the need to comprehensively characterize and monitor near-surface carbon dioxide sequestration in shallow saline aquifers around the world, justifies the emphasis on cost-effective and robust quality control and assurance (QC/QA) workflow of 3D seismic data preprocessing that is suitable for near-surface applications. The main purpose of our seismic data preprocessing QC is to enable the use of appropriate header information, data that are free of noise-dominated traces, and/or flawed vertical stacking in subsequent processing steps. In this article, I provide an account of utilizing survey design specifications, noise properties, first breaks, and normal moveout for rapid and thorough graphical QC/QA diagnostics, which are easy to apply and efficient in the diagnosis of inconsistencies. A correlated vibroseis time-lapse 3D-seismic data set from a CO2-flood monitoring survey is used for demonstrating QC diagnostics. An important by-product of the QC workflow is establishing the number of layers for a refraction statics model in a data-driven graphical manner that capitalizes on the spatial coverage of the 3D seismic data. ?? China University of Geosciences (Wuhan) and Springer-Verlag GmbH 2009.

  2. Construction prospects of new power units at Khmelnitskij NPP site

    Energy Technology Data Exchange (ETDEWEB)

    Zenyuk, Denys [NNEGC ' Energoatom' , 01032 Vetrova, 3, Kiev (Ukraine)

    2008-07-01

    According to the Energy Strategy of Ukraine for a period up to 2030 it is planned to put into operation power units 3 and 4 of Khmelnitskij NPP by year 2016. In this work considerations are presented on the possible options while selecting reactor unit type for Khmelnitskij NPP power units 3 and 4, which is the main determinant of the cost, construction and commissioning time, and utilization of the existent civil structures. To optimize Khmelnitskij-3 and 4 construction, a survey of the data has been conducted with regard to the possibility of construction of new power units of PWR/VVER type at Khmelnitskij NPP site. The multivariable analysis has been performed based on the projects technical and cost data, construction time and conditions, as well as their compliance with the IAEA and EUR safety requirements for new power units. (author)

  3. Validation of MCNP NPP Activation Simulations for Decommissioning Studies by Analysis of NPP Neutron Activation Foil Measurement Campaigns

    Directory of Open Access Journals (Sweden)

    Volmert Ben

    2016-01-01

    Full Text Available In this paper, an overview of the Swiss Nuclear Power Plant (NPP activation methodology is presented and the work towards its validation by in-situ NPP foil irradiation campaigns is outlined. Nuclear Research and consultancy Group (NRG in The Netherlands has been given the task of performing the corresponding neutron metrology. For this purpose, small Aluminium boxes containing a set of circular-shaped neutron activation foils have been prepared. After being irradiated for one complete reactor cycle, the sets have been successfully retrieved, followed by gamma-spectrometric measurements of the individual foils at NRG. Along with the individual activities of the foils, the reaction rates and thermal, intermediate and fast neutron fluence rates at the foil locations have been determined. These determinations include appropriate corrections for gamma self-absorption and neutron self-shielding as well as corresponding measurement uncertainties. The comparison of the NPP Monte Carlo calculations with the results of the foil measurements is done by using an individual generic MCNP model functioning as an interface and allowing the simulation of individual foil activation by predetermined neutron spectra. To summarize, the comparison between calculation and measurement serve as a sound validation of the Swiss NPP activation methodology by demonstrating a satisfying agreement between measurement and calculation. Finally, the validation offers a chance for further improvements of the existing NPP models by ensuing calibration and/or modelling optimizations for key components and structures.

  4. EFFECTS OF PARAMETRIC VARIATIONS ON SEISMIC ANALYSIS METHODS FOR NON-CLASSICALLY DAMPED COUPLED SYSTEMS

    Energy Technology Data Exchange (ETDEWEB)

    XU,J.; DEGRASSI,G.

    2000-04-02

    A comprehensive benchmark program was developed by Brookhaven National Laboratory (BNL) to perform an evaluation of state-of-the-art methods and computer programs for performing seismic analyses of coupled systems with non-classical damping. The program, which was sponsored by the US Nuclear Regulatory Commission (NRC), was designed to address various aspects of application and limitations of these state-of-the-art analysis methods to typical coupled nuclear power plant (NPP) structures with non-classical damping, and was carried out through analyses of a set of representative benchmark problems. One objective was to examine the applicability of various analysis methods to problems with different dynamic characteristics unique to coupled systems. The examination was performed using parametric variations for three simple benchmark models. This paper presents the comparisons and evaluation of the program participants' results to the BNL exact solutions for the applicable ranges of modeling dynamic characteristic parameters.

  5. PROBABILISTIC SEISMIC ASSESSMENT OF BASE-ISOLATED NPPS SUBJECTED TO STRONG GROUND MOTIONS OF TOHOKU EARTHQUAKE

    Directory of Open Access Journals (Sweden)

    AHMER ALI

    2014-10-01

    Full Text Available The probabilistic seismic performance of a standard Korean nuclear power plant (NPP with an idealized isolation is investigated in the present work. A probabilistic seismic hazard analysis (PSHA of the Wolsong site on the Korean peninsula is performed by considering peak ground acceleration (PGA as an earthquake intensity measure. A procedure is reported on the categorization and selection of two sets of ground motions of the Tohoku earthquake, i.e. long-period and common as Set A and Set B respectively, for the nonlinear time history response analysis of the base-isolated NPP. Limit state values as multiples of the displacement responses of the NPP base isolation are considered for the fragility estimation. The seismic risk of the NPP is further assessed by incorporation of the rate of frequency exceedance and conditional failure probability curves. Furthermore, this framework attempts to show the unacceptable performance of the isolated NPP in terms of the probabilistic distribution and annual probability of limit states. The comparative results for long and common ground motions are discussed to contribute to the future safety of nuclear facilities against drastic events like Tohoku.

  6. Seismic hazard assessment: Issues and alternatives

    Science.gov (United States)

    Wang, Z.

    2011-01-01

    Seismic hazard and risk are two very important concepts in engineering design and other policy considerations. Although seismic hazard and risk have often been used inter-changeably, they are fundamentally different. Furthermore, seismic risk is more important in engineering design and other policy considerations. Seismic hazard assessment is an effort by earth scientists to quantify seismic hazard and its associated uncertainty in time and space and to provide seismic hazard estimates for seismic risk assessment and other applications. Although seismic hazard assessment is more a scientific issue, it deserves special attention because of its significant implication to society. Two approaches, probabilistic seismic hazard analysis (PSHA) and deterministic seismic hazard analysis (DSHA), are commonly used for seismic hazard assessment. Although PSHA has been pro-claimed as the best approach for seismic hazard assessment, it is scientifically flawed (i.e., the physics and mathematics that PSHA is based on are not valid). Use of PSHA could lead to either unsafe or overly conservative engineering design or public policy, each of which has dire consequences to society. On the other hand, DSHA is a viable approach for seismic hazard assessment even though it has been labeled as unreliable. The biggest drawback of DSHA is that the temporal characteristics (i.e., earthquake frequency of occurrence and the associated uncertainty) are often neglected. An alternative, seismic hazard analysis (SHA), utilizes earthquake science and statistics directly and provides a seismic hazard estimate that can be readily used for seismic risk assessment and other applications. ?? 2010 Springer Basel AG.

  7. 最小二乘法分段拟合标定反应谱方法%Sectional least square fitting method for calibrating seismic design response spectrum

    Institute of Scientific and Technical Information of China (English)

    郭晓云; 薄景山; 巴文辉; 田启文; 李平

    2012-01-01

    The method of calibrating seismic design response spectrum is related directly to the determination of the characteristic parameters of response spectrum, and seismic design response spectrum based on logical calibrating method can express the real characteristic of earthquake strong motion. So calibration of seismic design response spectrum is the important chain of structures' seismic input determination. This paper advances least square fitting method of calibrating seismic design response spectrum based on coordinate transformation. By calculating the characteristic parameters of typical Wenchuan earthquake strong motion records and comparing different calibrating methods and analyzing the error of different methods, it points out that sectional least square fitting method is a simple and reasonable calibrating method.%反应谱的标定方法直接关系到反应谱特征参数的确定,合理的反应谱标定方法得到的设计反应谱能够真实地表达地震动的特性,是确定地震动输入的重要环节.提出了基于坐标变换的最小二乘法分段拟合方法,通过对汶川大地震不同场地典型强震记录反应谱的标定,对比了反应谱不同的标定方法,根据反应谱标定图形的对比及误差分析认为,最小二乘法分段拟合方法是操作简便且标定结果合理的反应谱标定方法.

  8. Comprehensive radiation survey and public health assessment in the vicinity of NPP

    Directory of Open Access Journals (Sweden)

    Samoilov A.S.

    2015-12-01

    health indicators of the public living around the NPP, general state of the adult and children public is healthy. There is no impact of the NPP on negative trends in some changing indicators of the adult and children public health.

  9. The development of robotic system for inspecting and repairing NPP primary coolant system of high-level radioactive environment

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Seung Ho; Kim, Ki Ho; Jung, Seung Ho; Kim, Byung Soo; Hwang, Suk Yeoung; Kim, Chang Hoi; Seo, Yong Chil; Lee, Young Kwang; Lee, Yong Bum; Cho, Jai Wan; Lee, Jae Kyung; Lee, Yong Deok

    1997-07-01

    This project aims at developing a robotic system to automatically handle inspection and maintenance of NPP safety-related facilities in high-level radioactive environment. This robotic system under development comprises two robots depending on application fields - a mobile robot and multi-functional robot. The mobile robot is designed to be used in the area of primary coolant system during the operation of NPP. This robot enables to overcome obstacles and perform specified tasks in unstructured environment. The multi-functional robot is designed for performing inspection and maintenance tasks of steam generator and nuclear reactor vessel during the overhaul periods of NPP. Nuclear facilities can be inspected and repaired all the time by use of both the mobile robot and the multi-functional robot. Human operator, by teleoperation, monitors the movements of such robots located at remote task environment via video cameras and controls those remotely generating desired commands via master manipulator. We summarize the technology relating to the application of the mobile robot to primary coolant system environment, the applicability of the mobile robot through 3D graphic simulation, the design of the mobile robot, the design of its radiation-hardened controller. We also describe the mechanical design, modeling, and control system of the multi-functional robot. Finally, we present the design of the force-reflecting master and the modeling of virtual task environment for a training simulator. (author). 47 refs., 16 tabs., 43 figs.

  10. Preclosure seismic design methodology for a geologic repository at Yucca Mountain. Topical report YMP/TR-003-NP

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1996-10-01

    This topical report describes the methodology and criteria that the U.S. Department of Energy (DOE) proposes to use for preclosure seismic design of structures, systems, and components (SSCs) of the proposed geologic repository operations area that are important to safety. Title 10 of the Code of Federal Regulations, Part 60 (10 CFR 60), Disposal of High-Level Radioactive Wastes in Geologic Repositories, states that for a license to be issued for operation of a high-level waste repository, the U.S. Nuclear Regulatory Commission (NRC) must find that the facility will not constitute an unreasonable risk to the health and safety of the public. Section 60.131 (b)(1) requires that SSCs important to safety be designed so that natural phenomena and environmental conditions anticipated at the geologic repository operations area will not interfere with necessary safety functions. Among the natural phenomena specifically identified in the regulation as requiring safety consideration are the hazards of ground shaking and fault displacement due to earthquakes.

  11. Development of seismic analysis model of LMFBR and seismic time history response analysis

    Energy Technology Data Exchange (ETDEWEB)

    Koo, K. H.; Lee, J. H.; Yoo, B. [KAERI, Taejon (Korea, Republic of)

    2001-05-01

    The main objective of this paper is to develop the seismic analysis model of KALIMER reactor structures including the primary coolant of sodium and to evaulate the seismic responses of the maximum peak acceleration and the relative displacements by the time history seismic response analysis. The seismic time history response analyses were carried out for both cases of the seismic isolation design and the non-isolation one to verify the seismic isolation performance. From the results of seismic response analysis using the developed seismic analysis model, it is clearly verified that the seismic isolation design gives very significantly reduced seismic responses compared with the non-isolation design. All design criteria for the relative displacement repsonse were satisfied for KALIMER reactor structures.

  12. 拉美抗震设计规范与中、美规范相关内容的对比研究%Comparison of Latin- American Seismic Design Codes with Chinese and US Seismic Design Codes

    Institute of Scientific and Technical Information of China (English)

    任广杰; 邱兆山

    2013-01-01

    Among the Latin-American countries, seismic design codes of Cuba, Colombia and Mexico (MOC) are very typi-cal;this paper introduces the methods to set up spectral acceleration of Design Earthquakes and these methods are compared with relevant contents in the Chinese and US codes. The simplicity of the Cuban code is close to the Chinese code and 1997 UBC code;the Colombian code has referred to the concepts of US codes of different periods;and the Mexican MOC code (manual) has very special application methods. Other relevant comparative points are also summarized in the paper. The pa-per thus helps people understand the relevant design codes of Latin-American countries.%在拉美国家中,古巴、哥伦比亚、墨西哥MOC抗震规范比较典型。文中介绍了其中建立设计地震加速度反应谱的方法,并与中、美国家规范相关内容进行了对比。古巴规范简化的程度与中国规范及1997UBC规范相近;哥伦比亚规范混合采用了不同时期美国规范中的概念;墨西哥MOC规范应用形式上很特殊。文中还总结了与各个规范相关的其它对比要点。为理解拉美国家相关规范提供借鉴。

  13. Modification of the Decontamination Facility at the Kruemmel NPP - 13451

    Energy Technology Data Exchange (ETDEWEB)

    Klute, Stefan; Kupke, Peter [Siempelkamp Nukleartechnik GmbH Am Taubenfeld 25/1, 69123 Heidelberg (Germany)

    2013-07-01

    In February 2009, Siempelkamp Nukleartechnik GmbH was awarded the contract for the design, manufacture, delivery and construction of a new Decontamination Facility in the controlled area for Kruemmel NPP. The new decontamination equipment has been installed according to the state of art of Kruemmel NPP. The existing space required the following modification, retrofitting and reconstruction works: - Demounting of the existing installation: to create space for the new facility it was necessary to dismantle the old facility. The concrete walls and ceilings were cut into sizes of no more than 400 kg for ease of handling. This enabled decontamination so largest possible amount could be released for recycling. All steel parts were cut into sizes fitting for iron-barred boxes, respecting the requirement to render the parts decontaminable and releasable. - Reconstructing a decontamination facility: Reconstruction of a decontamination box with separate air lock as access area for the decontamination of components and assemblies was conducted using pressurized air with abrasives (glass beads or steel shots). The walls were equipped with sound protection, the inner walls were welded gap-free to prevent the emergence of interstices and were equipped with changeable wear and tear curtains. Abrasive processing unit positioned underneath the dry blasting box adjacent to the two discharge hoppers. A switch has been installed for the separation of the glass beads and the steel shot. The glass beads are directed into a 200 l drum for the disposal. The steel shot was cleaned using a separator. The cleaned steel shot was routed via transportation devices to the storage container, making it available for further blasting operations. A decontamination box with separate air lock as access area for the decontamination of components and assemblies using high pressure water technology was provided by new construction. Water pressures between 160 bar and 800 bar can be selected. The inner

  14. Seismic isolation of nuclear power plants using elastomeric bearings

    Science.gov (United States)

    Kumar, Manish

    Seismic isolation using low damping rubber (LDR) and lead-rubber (LR) bearings is a viable strategy for mitigating the effects of extreme earthquake shaking on safety-related nuclear structures. Although seismic isolation has been deployed in nuclear structures in France and South Africa, it has not seen widespread use because of limited new build nuclear construction in the past 30 years and a lack of guidelines, codes and standards for the analysis, design and construction of isolation systems specific to nuclear structures. The nuclear accident at Fukushima Daiichi in March 2011 has led the nuclear community to consider seismic isolation for new large light water and small modular reactors to withstand the effects of extreme earthquakes. The mechanical properties of LDR and LR bearings are not expected to change substantially in design basis shaking. However, under shaking more intense than design basis, the properties of the lead cores in lead-rubber bearings may degrade due to heating associated with energy dissipation, some bearings in an isolation system may experience net tension, and the compression and tension stiffness may be affected by the horizontal displacement of the isolation system. The effects of intra-earthquake changes in mechanical properties on the response of base-isolated nuclear power plants (NPPs) were investigated using an advanced numerical model of a lead-rubber bearing that has been verified and validated, and implemented in OpenSees and ABAQUS. A series of experiments were conducted at University at Buffalo to characterize the behavior of elastomeric bearings in tension. The test data was used to validate a phenomenological model of an elastomeric bearing in tension. The value of three times the shear modulus of rubber in elastomeric bearing was found to be a reasonable estimate of the cavitation stress of a bearing. The sequence of loading did not change the behavior of an elastomeric bearing under cyclic tension, and there was no

  15. Suomi-NPP VIIRS Solar Diffuser Stability Monitor Performance

    Science.gov (United States)

    Fulbright, Jon; Lei, Ning; Efremova, Boryana; Xiong, Xiaoxiong

    2015-01-01

    When illuminated by the Sun, the onboard solar diffuser (SD) panel provides a known spectral radiance source to calibrate the reflective solar bands of the Visible Infrared Imaging Radiometer Suite on the Suomi-NPP satellite. The SD bidirectional reflectance distribution function (BRDF) degrades over time due to solar exposure, and this degradation is measured using the SD stability monitor (SDSM). The SDSM acts as a ratioing radiometer, comparing solar irradiance measurements off the SD panel to those from a direct Sun view. We discuss the design and operations of the SDSM, the SDSM data analysis, including improvements incorporated since launch, and present the results through 1000 days after launch. After 1000 days, the band-dependent H-factors, a quantity describing the relative degradation of the BRDF of the SD panel since launch, range from 0.716 at 412 nanometers to 0.989 at 926 nanometers. The random uncertainty of these H-factors is about 0.1 percent, which is confirmed by the similar standard deviation values computed from the residuals of quadratic exponential fits to the H-factor time trends. The SDSM detector gains have temperature sensitivity of up to about 0.36 percent per kelvin, but this does not affect the derived H-factors. An initial error in the solar vector caused a seasonal bias to the H-factors of up to 0.5 percent. The total exposure of the SD panel to UV light after 1000 orbits is equivalent to about 100 hours of direct sunlight illumination perpendicular to the SD panel surface.

  16. Load Distribution Patterns for Displacement-based Seismic Design of RC Framed Buildings

    Science.gov (United States)

    Varughese, Jiji Anna; Menon, Devdas; Meher Prasad, A.

    2014-12-01

    The behaviour of tall frames is characterized by the influence of higher modes in addition to the fundamental mode and thus the design procedures for Displacement-based Design (DBD) adopt several measures to control higher mode effects. The performances of 4, 9 and 15-storeyed frames, designed by DBD were verified using non-linear time history analyses. Higher values of inter-storey drift and damage index were seen near the top of tall frames, which shows the inefficiency of the design method in accounting for higher mode effect. As the principle of damage-limiting aseismic design is to get uniform damage along the height of the frame, several load distribution patterns were examined and the storey shear distributions were compared to identify the best pattern to get uniform damage. The Chao load distribution was found to give higher storey shear at top and thus the frames were redesigned using this load distribution. The efficiency of Chao load distribution in reducing higher mode effects is demonstrated using non-linear time history analyses.

  17. Nuclear Power Plant Module, NPP-1: Nuclear Power Cost Analysis.

    Science.gov (United States)

    Whitelaw, Robert L.

    The purpose of the Nuclear Power Plant Modules, NPP-1, is to determine the total cost of electricity from a nuclear power plant in terms of all the components contributing to cost. The plan of analysis is in five parts: (1) general formulation of the cost equation; (2) capital cost and fixed charges thereon; (3) operational cost for labor,…

  18. Improvement of waste release control in French NPP

    Energy Technology Data Exchange (ETDEWEB)

    Samson, T.; Lucquin, E.; Dupin, M. [EDF/GDL (France); Florence, D. [EDF/GENV (France); Grisot, M. [EDF/CNPE Saint Laurent (France)

    2002-07-01

    The new waste release control in French NPP is more restrictive than the old one and needs heavy investment to bring plants to compliance with it. The great evolutions are a chemical follow up on more chemicals with a higher measurement frequency and with lower maximum concentrations and a specific measurement of carbon 14. Regarding radioactive releases, a new counting has been settled and activity of carbon 14 release is now measured and no longer calculated. The evolution of the French regulation leads to develop specific procedures and analytical techniques in chemistry and in radiochemistry (UV spectrometric methods, carbon 14 measurements,..) EDF NPP operators have launched a voluntarist process to reduce their releases since the beginning and before the evolution of the regulation. EDF priorities in terms of environment care lead henceforth to implement a global optimisation of the impact for a better control of releases. The new regulation will help EDF to reach its goals because it covers all the aspects in one administrative document: it is seen as a real simplification and a clarification towards public. In addition, this new regulation fits in with international practices which will allow an easier comparison of results between EDF and foreign NPP. These big environmental concerns lead EDF to create a national dedicated laboratory (LAMEN) in charge of developing specific measurement procedures to be implemented either by NPP or by sub-contractor laboratories. (authors)

  19. Evaluation of MODIS NPP and GPP products across multiple biomes.

    Science.gov (United States)

    David P. Turner; William D. Ritts; Warren B. Cohen; Stith T. Gower; Steve W. Running; Maosheng Zhao; Marcos H. Costa; Al A. Kirschbaum; Jay M. Ham; Scott R. Saleska; Douglas E. Ahl

    2006-01-01

    Estimates of daily gross primary production (GPP) and annual net primary production (NPP) at the 1 km spatial resolution are now produced operationally for the global terrestrial surface using imagery from the MODIS (Moderate Resolution Imaging Spectroradiometer) sensor. Ecosystem-level measurements of GPP at eddy covariance flux towers and plot-level measurements of...

  20. Study on the Design Improvements of NPP Based on the Risk -informed Regulation%基于风险指引的核电厂设计改进评价研究

    Institute of Scientific and Technical Information of China (English)

    倪曼; 肖军; 宫宇

    2016-01-01

    核电厂概率安全评价(PSA )可以论证核电厂的风险满足安全目标,也是对运行核电厂进行风险管理的有效工具,例如核电厂的在役检查、安全分级、技术规格书优化等。核电厂的风险指引管理是在确定论的基础上,充分利用概率安全评价的结果进行风险影响评价,以此来论证决策的合理性。核电厂的重要设计改进通常基于传统的工程分析结果,没有分析其对核电厂整体风险的影响。重点探讨风险指引决策的基本原则以及方法,以核电厂设计改进实例探讨如何在分析时引入风险指引方法,并提出相关建议。%The probabilistic safety analysis (PSA)can demonstrate that if the risk of nuclear power plant satisfies the safety goals ,and also can be used in the risk management of nuclear power plant to improve in -service test ,classification of e-quipment and maintenance etc .The risk-informed management of nuclear power plant is the combination of determinate methodology and probabilistic methodology .In the comprehensive decision ,the PSA results should be used to evaluate the risk and demonstrate the rationality .The design improvements of nuclear power plant are usually based on the traditional en-gineering analysis ,and the influences for the overall risk are not considered .This paper specially introduces the basic prin-ciples and methods of risk -informed management and discusses how to use the risk -informed method to analyse the design improvement of nuclear power plant and put forward related suggestions .

  1. Seismic design or retrofit of buildings with metallic structural fuses by the damage-reduction spectrum

    Science.gov (United States)

    Li, Gang; Jiang, Yi; Zhang, Shuchuan; Zeng, Yan; Li, Qiang

    2015-03-01

    Recently, the structural fuse has become an important issue in the field of earthquake engineering. Due to the trilinearity of the pushover curve of buildings with metallic structural fuses, the mechanism of the structural fuse is investigated through the ductility equation of a single-degree-of-freedom system, and the corresponding damage-reduction spectrum is proposed to design and retrofit buildings. Furthermore, the controlling parameters, the stiffness ratio between the main frame and structural fuse and the ductility factor of the main frame, are parametrically studied, and it is shown that the structural fuse concept can be achieved by specific combinations of the controlling parameters based on the proposed damage-reduction spectrum. Finally, a design example and a retrofit example, variations of real engineering projects after the 2008 Wenchuan earthquake, are provided to demonstrate the effectiveness of the proposed design procedures using buckling restrained braces as the structural fuses.

  2. The Effect of Seismic Design on Structural Progressive Collapse%抗震设计对结构抗连续倒塌的影响分析

    Institute of Scientific and Technical Information of China (English)

    于述强; 肖光辉

    2012-01-01

    地震作用是影响结构连续倒塌的重要因素,首先分析了地震作用的特点,比较了抗震设计和抗连续倒塌设计的要求及方法,进而为考虑抗震设防烈度对结构抗连续倒塌能力的影响,建立了非抗震和抗震设防烈度分别为6度(0.05g)、7度(0.1g)、8度(0.2g)的4个典型四层框架,依据GSA准则采用静力线性方法分析了结构在底层柱破坏下的抗连续倒塌能力.计算结果表明,6度和7度抗震设防结构抗连续倒塌能力相对非抗震结构提高不大,8度设防结构的抗连续倒塌能力较好.%Earthquake action is an important factor that affects structural progressive collapse, first, the characteristics of the earthquake action are analyzed, the seismic design and collapse-resistance design are compared, in order to consider the effect of seismic intensity on the structure, non-seismic and seismic intensity of 6 (0. 05 g) , 7(0. 1 g) , 8 (0.2 g) of four typical four-layer frameworks were established. According to GSA guidelines, using the linear static analysis the frameworks' collapse-resistance capacity were analyzed. The results show the collapse capacity of 6 and 7 degree improved less than non-seismic structure; the collapse capacity of 8 degree is better.

  3. Seismic performance analysis and design suggestion for frame buildings with cast-in-place staircases

    Science.gov (United States)

    Feng, Yuan; Wu, Xiaobin; Xiong, Yaoqing; Li, Congchun; Yang, Wen

    2013-06-01

    Many staircases in reinforced concrete (RC) frame structures suffered severe damage during the Wenchuan earthquake. Elastic analyses for 18 RC structure models with and without staircases are conducted and compared to study the influence of the staircase on the stiffness, displacements and internal forces of the structures. To capture the yielding development and damage mechanism of frame structures, elasto-plastic analysis is carried out for one of the 18 models. Based on the features observed in the analyses, a new type of staircase design i.e., isolating them from the master structure to eliminate the effect of K-type struts, is proposed and discussed. It is concluded that the proposed method of staircase isolation is effective and feasible for engineering design, and does not significantly increase the construction cost.

  4. Seismic performance evaluation of existing RC buildings designed as per past codes of practice

    Indian Academy of Sciences (India)

    K Rama Raju; A Cinitha; Nagesh R Iyer

    2012-04-01

    Assessing the capacity of existing building as per the present codes of practice is an important task in performance-based evaluation. In order to enhance the performance of existing buildings to the present level of ductile design prescribed by present codes and find the retrofit or design a rehabilitation system, there is an urgent need to assess accurately the actual lateral load resistance and the potential failure modes. In this paper, a typical 6-storey reinforced concrete (RC) building frame is designed for four design cases as per the provisions in three revisions of IS: 1893 and IS: 456 and it is analysed using user-defined (UD) nonlinear hinge properties or default-hinge (DF) properties, given in SAP 2000 based on the FEMA-356 and ATC-40 guidelines. An analytical procedure is developed to evaluate the yield, plastic and ultimate rotation capacities of RC elements of the framed buildings and these details are used to define user-defined inelastic effect of hinge for columns as P-M-M and for beams as M3 curves. A simplified three parameter model is used to find the stress–strain curves of RC elements beyond the post yield region of confined concrete. Building performance of structural components in terms of target building performance levels are studied with the nonlinear static analysis. The possible differences in the results of pushover analysis due to default- and user-defined nonlinear component properties at different performance levels of the building are studied.

  5. Effects of charge design features on parameters of acoustic and seismic waves and cratering, for SMR chemical surface explosions

    Science.gov (United States)

    Gitterman, Y.

    2012-04-01

    A series of experimental on-surface shots was designed and conducted by the Geophysical Institute of Israel at Sayarim Military Range (SMR) in Negev desert, including two large calibration explosions: about 82 tons of strong IMI explosives in August 2009, and about 100 tons of ANFO explosives in January 2011. It was a collaborative effort between Israel, CTBTO, USA and several European countries, with the main goal to provide fully controlled ground truth (GT0) infrasound sources in different weather/wind conditions, for calibration of IMS infrasound stations in Europe, Middle East and Asia. Strong boosters and the upward charge detonation scheme were applied to provide a reduced energy release to the ground and an enlarged energy radiation to the atmosphere, producing enhanced infrasound signals, for better observation at far-regional stations. The following observations and results indicate on the required explosives energy partition for this charge design: 1) crater size and local seismic (duration) magnitudes were found smaller than expected for these large surface explosions; 2) small test shots of the same charge (1 ton) conducted at SMR with different detonation directions showed clearly lower seismic amplitudes/energy and smaller crater size for the upward detonation; 3) many infrasound stations at local and regional distances showed higher than expected peak amplitudes, even after application of a wind-correction procedure. For the large-scale explosions, high-pressure gauges were deployed at 100-600 m to record air-blast properties, evaluate the efficiency of the charge design and energy generation, and provide a reliable estimation of the charge yield. Empirical relations for air-blast parameters - peak pressure, impulse and the Secondary Shock (SS) time delay - depending on distance, were developed and analyzed. The parameters, scaled by the cubic root of estimated TNT equivalent charges, were found consistent for all analyzed explosions, except of SS

  6. Seismic design and engineering research at the U.S. Geological Survey

    Science.gov (United States)

    1988-01-01

    The Engineering Seismology Element of the USGS Earthquake Hazards Reduction Program is responsible for the coordination and operation of the National Strong Motion Network to collect, process, and disseminate earthquake strong-motion data; and, the development of improved methodologies to estimate and predict earthquake ground motion.  Instrumental observations of strong ground shaking induced by damaging earthquakes and the corresponding response of man-made structures provide the basis for estimating the severity of shaking from future earthquakes, for earthquake-resistant design, and for understanding the physics of seismologic failure in the Earth's crust.

  7. Observation and modeling of NPP for Pinus elliottii plantation in subtropical China

    Institute of Scientific and Technical Information of China (English)

    MA ZeQing; LIU QiJing; WANG HuiMin; LI XuanRan; ZENG HuiQing; XU WenJia

    2008-01-01

    Based on the stem analysis of 59 individuals of Pinus elliottii in combination with tree biomass models,we calculated annual biomass increment of forest plots at Qianyanzhou Ecological Station,Chinese Academy of Sciences in subtropical China. In addition,canopy layer and community NPP were calculated based on 12 years' litter fall data. NPP of the 21-year-old forest was estimated by using the BIOME BGC model; and both measured NPP and estimated NPP were compared with flux data. Community lation between annual litter fall and annual biomass increment; and the litter fall was 1.19 times the biomass increment of living trees. From 1985 to 2005,average NPP and GPP values based on BGC simulated tree layer NPP values. NPP accounted for 30.2% (25.6%-32.9%) of GPP,while NEP accounted for 57.5% (48.1%-66.5%) of tree-layer NPP and 41.74% (37%-52%) of stand NPP. Soil respiration accounted for 77.0% of measured tree NPP and 55.9% of the measured stand NPP. NEE based on eddy covariance method was 12.97% higher than the observed NEP.

  8. SOAR Telescope seismic performance II: seismic mitigation

    Science.gov (United States)

    Elias, Jonathan H.; Muñoz, Freddy; Warner, Michael; Rivera, Rossano; Martínez, Manuel

    2016-07-01

    We describe design modifications to the SOAR telescope intended to reduce the impact of future major earthquakes, based on the facility's experience during recent events, most notably the September 2015 Illapel earthquake. Specific modifications include a redesign of the encoder systems for both azimuth and elevation, seismic trigger for the emergency stop system, and additional protections for the telescope secondary mirror system. The secondary mirror protection may combine measures to reduce amplification of seismic vibration and "fail-safe" components within the assembly. The status of these upgrades is presented.

  9. Why CAREM? Bias towards smaller sized NPP

    Energy Technology Data Exchange (ETDEWEB)

    Mazzi, R.O. [INVAP, Bariloche (Argentina)], E-mail: mazzi@invap.com.ar

    2009-07-01

    Presented on March 1984 in an international conference for the first time, 'CAREM Concept' focused on engineering solutions from early stages of the design that minimize requirements to safety and safeguards systems being the product simpler, highly reliable and cost effective. The overall idea was widely adopted by worldwide designers, originated a new category of small a medium size nuclear power plants frequently know as 'integrated reactor' and/or 'Advanced-passive safety-reactor'. This paper describes the main design features, progress and prospects of the CAREM project as well as proliferation resistant conditions applicable to the desig000.

  10. Mapping and analysing cropland use intensity from a NPP perspective

    Science.gov (United States)

    Niedertscheider, Maria; Kastner, Thomas; Fetzel, Tamara; Haberl, Helmut; Kroisleitner, Christine; Plutzar, Christoph; Erb, Karl-Heinz

    2016-01-01

    Meeting expected surges in global biomass demand while protecting pristine ecosystems likely requires intensification of current croplands. Yet many uncertainties relate to the potentials for cropland intensification, mainly because conceptualizing and measuring land use intensity is intricate, particularly at the global scale. We present a spatially explicit analysis of global cropland use intensity, following an ecological energy flow perspective. We analyze (a) changes of net primary production (NPP) from the potential system (i.e. assuming undisturbed vegetation) to croplands around 2000 and relate these changes to (b) inputs of (N) fertilizer and irrigation and (c) to biomass outputs, allowing for a three dimensional focus on intensification. Globally the actual NPP of croplands, expressed as per cent of their potential NPP (NPPact%), amounts to 77%. A mix of socio-economic and natural factors explains the high spatial variation which ranges from 22.6% to 416.0% within the inner 95 percentiles. NPPact% is well below NPPpot in many developing, (Sub-) Tropical regions, while it massively surpasses NPPpot on irrigated drylands and in many industrialized temperate regions. The interrelations of NPP losses (i.e. the difference between NPPact and NPPpot), agricultural inputs and biomass harvest differ substantially between biogeographical regions. Maintaining NPPpot was particularly N-intensive in forest biomes, as compared to cropland in natural grassland biomes. However, much higher levels of biomass harvest occur in forest biomes. We show that fertilization loads correlate with NPPact% linearly, but the relation gets increasingly blurred beyond a level of 125 kgN ha-1. Thus, large potentials exist to improve N-efficiency at the global scale, as only 10% of global croplands are above this level. Reallocating surplus N could substantially reduce NPP losses by up to 80% below current levels and at the same time increase biomass harvest by almost 30%. However, we

  11. The status of nuclear waste from NPP in Romania

    Energy Technology Data Exchange (ETDEWEB)

    Mauna, T. [Romanian Nuclear Energy Association Council, Asociatia Romana Energia Nucleara AREN, Bucharest (Romania)]. E-mail: tmauna@nuclearelectrica.ro

    2006-07-01

    AREN founded in 1990 is a Romanian NGO focused to sustain its employees or corporate members to develop all kinds of nuclear activities in connection with environmental protection as a scientific organization, having as the first objective activities with respect to Cernavoda NPP. As the only CANDU type reactor equipped Nuclear Power Plant (NPP) in Europe, we pay very much attention to all aspects regarding implementation of this concept in our country and the consequences of this implementation. From July 1996 the first unit in operation supplied into the grid around 40 TWh electric power and around 400 Tcal of thermal power for district heating until September 2004. The second unit is still under construction managed also by the Canadian project team, having a finalization target year of 2007. The temporary LILW, and spent fuel dry storage facilities are also on Cernavoda NPP site inside the safety exclusion area boundary of the first unit. The capacity of temporary LILW warehouse concrete building, practically located into the security plant fence, is around 2,400 m{sup 3}. T he occupied capacity is estimated as 140 m{sup 3} until the end of 2004. The spent fuel dry storage MACSTOR type (a Canadian solution for spent fuel storage) with about 12,000 spent fuel bundles capacity is in operation on Cernavoda NPP site, since May 2003. Nuclearelectrica as the owner implemented all the projects based on the licenses and permits granted by the National Commission for Nuclear Activities Control (CNCAN) for each step: the sitting, construction, commissioning and operation. According to the specific Romanian regulations, every project on the site, like the interim dry storage facility, was also subject to the licensing process by the Environmental and Public Health authorities. The public acceptance has been an important step of the licensing procedure. Cernavoda NPP used different legal procedures for public debate including announcements in local and national newspapers

  12. Ageing management of french NPP civil work structures

    Science.gov (United States)

    Gallitre, E.; Dauffer, D.

    2011-04-01

    This paper presents EDF practice about concrete structure ageing management, from the mechanisms analysis to the formal procedure which allows the French company to increase 900 MWe NPP lifetime until 40 years; it will also introduce its action plan for 60 years lifetime extension. This practice is based on a methodology which identifies every ageing mechanism; both plants feedback and state of the art are screened and conclusions are drawn up into an "ageing analysis data sheet". That leads at first to a collection of 57 data sheets which give the mechanism identification, the components that are concerned and an analysis grid which is designed to assess the safety risk. This analysis screens the reference documents describing the mechanism, the design lifetime hypotheses, the associated regulation or codification, the feedback experiences, the accessibility, the maintenance actions, the repair possibility and so one. This analysis has to lead to a conclusion about the risk taking into account monitoring and maintenance. If the data sheet conclusion is not clear enough, then a more detailed report is launched. The technical document which is needed, is a formal detailed report which summarizes every theoretical knowledge and monitoring data: its objective is to propose a solution for ageing management: this solution can include more inspections or specific research development, or additional maintenance. After a first stage on the 900 MWe units, only two generic ageing management detailed reports have been needed for the civil engineering part: one about reactor building containment, and one about other structures which focuses on concrete inflating reactions. The second stage consists on deriving this generic analysis (ageing mechanism and detailed reports) to every plant where a complete ageing report is required (one report for all equipments and structures of the plant, but specific for each reactor). This ageing management is a continuous process because the

  13. Material properties of CSG for the seismic design of trapezoid-shaped CSG dam

    Energy Technology Data Exchange (ETDEWEB)

    Fujisawa, T. [Japan Dam Engineering Center, Tokyo (Japan); Nakamura, A.; Kawasaki, H.; Hirayama, D. [National Institute for Land and Infrastructure Management, Tsukuba City (Japan); Yamaguchi, Y.; Sasaki, T. [Public Works Research Institute, Tsukuba (Japan)

    2004-07-01

    Cemented Sand and Gravel (CSG) is a relatively new material in dam construction, and its physical properties are affected by gradation curves of raw material, unit water content and cement content. This paper presents an examination of the dynamic properties of CSG during cyclic loading tests simulating earthquake activity. Stress-strain curves obtained by uniaxial compression tests were confirmed as non-linear, with maximum compressive stress not exceeding the linear range of CSG. It was concluded that compared with a conventional concrete dam, stress generated in a dam body of a trapezoid-shaped CSG dam is small. In the event of an earthquake, brittle failure was presented as unlikely, due the wide range of plasticity in CSG. In a basic design of trapezoid-shaped CSG dams, the strength and modulus of elasticity in a linear range should be used as material properties of CSG. It was concluded that trapezoid-shaped CSG had a high enough safety margin against severe earthquakes. 2 refs., 2 tabs., 23 figs.

  14. A New Energy-Based Structural Design Optimization Concept under Seismic Actions

    Directory of Open Access Journals (Sweden)

    George Papazafeiropoulos

    2017-07-01

    Full Text Available A new optimization concept is introduced which involves the optimization of non-linear planar shear buildings by using gradients based on equivalent linear structures, instead of the traditional practice of calculating the gradients from the non-linear objective function. The optimization problem is formulated as an equivalent linear system of equations in which a target fundamental eigenfrequency and equal dissipated energy distribution within the storeys of the building are the components of the objective function. The concept is applied in a modified Newton–Raphson algorithm in order to find the optimum stiffness distribution of two representative linear or non-linear MDOF shear buildings, so that the distribution of viscously damped and hysteretically dissipated energy, respectively, over the structural height is uniform. A number of optimization results are presented in which the effect of the earthquake excitation, the critical modal damping ratio, and the normalized yield inter-storey drift limit on the optimum stiffness distributions is studied. Structural design based on the proposed approach is more rational and technically feasible compared to other optimization strategies (e.g., uniform ductility concept, whereas it is expected to provide increased protection against global collapse and loss of life during strong earthquake events. Finally, it is proven that the new optimization concept not only reduces running times by as much as 91% compared to the classical optimization algorithms but also can be applied in other optimization algorithms which use gradient information to proceed to the optimum point.

  15. Project equipment HVAC chilled with R22 in the NPP Asco; Proyecto de sustitucion de equipos HVAC refrigerados con R22 en la C.N. Asco

    Energy Technology Data Exchange (ETDEWEB)

    Jaimot Jimenez, J. J.; Imbert, J. J.

    2013-07-01

    This paper describes the project of changing units of air conditioning in the Asco NPP currently used R22 as coolant. The project has a powerful, affecting 37 units, of which more than half are Clase1E. The document describes the process of sizing, scope of change and solutions adopted for this change of design.

  16. Comparison of seismic sources for shallow seismic: sledgehammer and pyrotechnics

    Directory of Open Access Journals (Sweden)

    Brom Aleksander

    2015-10-01

    Full Text Available The pyrotechnic materials are one of the types of the explosives materials which produce thermal, luminous or sound effects, gas, smoke and their combination as a result of a self-sustaining chemical reaction. Therefore, pyrotechnics can be used as a seismic source that is designed to release accumulated energy in a form of seismic wave recorded by tremor sensors (geophones after its passage through the rock mass. The aim of this paper was to determine the utility of pyrotechnics for shallow seismic engineering. The work presented comparing the conventional method of seismic wave excitation for seismic refraction method like plate and hammer and activating of firecrackers on the surface. The energy released by various sources and frequency spectra was compared for the two types of sources. The obtained results did not determine which sources gave the better results but showed very interesting aspects of using pyrotechnics in seismic measurements for example the use of pyrotechnic materials in MASW.

  17. Seismic new PCI system for C.N. Almaraz. Design, installation and testing; Nuevo sistema de PCI Sismico para C. N. Almaraz. diseno, montaje y pruebas

    Energy Technology Data Exchange (ETDEWEB)

    Eugenio Poza, J. M. de; Arguello Tara, A.; Galan Herranz, D.

    2014-07-01

    Through an important design modification has been installed in the Almaraz nuclear power plant a new system capable of meeting PCI the requirements of paragraph 3.6.4. the NFPA-805. This new system is capable of covering all areas of fire of the station with equipment necessary for the safe stop with a water supply of functional fire protection after an earthquake of stop secure (SSE). In addition, this new seismic PCI system is capable of replacing the volume lost by evaporation of pools of storage of spent fuel to events beyond the design basis. (Author)

  18. Integrated tool for NPP lifetime management in Spain

    Energy Technology Data Exchange (ETDEWEB)

    Francia, L. [UNESA, Madrid (Spain); Lopez de Santa Maria, J. [ASCO-Vandellos 2 NPPs l' Hospitalet de l' Infant, Tarragona (Spain); Cardoso, A. [Tecnatom SA, Madrid (Spain)

    2001-07-01

    The project for the Integrated Nuclear Power Plant Lifetime Management System SIGEVI (Sistema Integrado de GEstion de VIda de Centrales Nucleares) was initiated in April 1998 and finalized in December 2000, the main objective of the project being to develop a computer application facilitating the assessment of the condition and lifetime of nuclear power plant components. This constituted the second phase of a further-reaching project on NPP Lifetime Management. During the first phase of this project, carried out between 1992 and 1995, the methodology and strategy for the lifetime management of the Spanish NPP's were developed. Among others, degradation phenomena were assessed and the most adequate methods for their monitoring were defined. The SIGEVI Project has been performed under the management of UNESA (Spanish Electricity Association) and with the collaboration of different engineering firms and research institutes (Tecnatom, Empresarios Agrupados, Ufisa, Initec and IIT), with Vandellos II as the pilot plant. The rest of the Spanish NPP's have also actively participated through the Project Steering Committee. The following sections describe the scope, the structure and the main functionalities of the system SIGEVI. (authors)

  19. Robot dispatching Scenario for Accident Condition Monitoring of NPP

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Jongseog [Central Research Institute of Korea Hydro and Nuclear Power Co., Daejeon (Korea, Republic of)

    2013-05-15

    In March of 2011, unanticipated big size of tsunami attacks Fukushima NPP, this accident results in explosion of containment building. Tokyo electric power of Japan couldn't dispatch a robot for monitoring of containment inside. USA Packbot robot used for desert war in Iraq was supplied to Fukushima NPP for monitoring of high radiation area. Packbot also couldn't reach deep inside of Fukushima NPP due to short length of power cable. Japanese robot 'Queens' also failed to complete a mission due to communication problem between robot and operator. I think major reason of these robot failures is absence of robot dispatching scenario. If there was a scenario and a rehearsal for monitoring during or after accident, these unanticipated obstacles could be overcome. Robot dispatching scenario studied for accident of nuclear power plant was described herein. Study on scenario of robot dispatching is performed. Flying robot is regarded as good choice for accident monitoring. Walking robot with arm equipped is good for emergency valve close. Short time work and shift work by several robots can be a solution for high radiation area. Thin and soft cable with rolling reel can be a good solution for long time work and good communication.

  20. Preparation for Early Termination of Ignalina NPP Operation

    Energy Technology Data Exchange (ETDEWEB)

    Poskas, P.; Poskas, R.

    2003-02-26

    Seimas (Parliament of Lithuania) approved updated National Energy strategy where it is indicated that first Unit will be shutdown before the year 2005 and second Unit in 2009 if funding for decommissioning is available from EU and other donors. In accordance to Ignalina NPP Unit 1 Closure Law the Government of Lithuania approved the Ignalina NPP Unit 1 Decommissioning Program until year 2005. For enforcement of this program, the plan of measures for implementation of the program was prepared and approved by the Minister of Economy. The plan consists of two parts, namely technical- environmental and social-economic. Technical-environmental measures are mostly oriented to the safe management of spent nuclear fuel and operational radioactive waste stored at the plant and preparation of licensing documents for Unit 1 decommissioning. Social-economic measures are oriented to mitigate negative social and economic impact on Lithuania, inhabitants of the region, and, particularly, o n the staff of Ignalina NPP by means of creating favorable conditions for a balanced social and economic development of the region. In this paper analysis of planned activities, licensing requirements for decommissioning, progress in preparation of the Final Decommissioning Plan is discussed.

  1. Modeling the critical safety functions status tree of a NPP using FPGA

    Energy Technology Data Exchange (ETDEWEB)

    Farias, Marcos Santana; Oliveira, Mauro Vitor de; Jaime, Guilherme Dutra Gonzaga; Almeida, Jose Carlos Soares de; Augusto, Silas Cordeiro, E-mail: msantana@ien.gov.br, E-mail: mvitor@ien.gov.br, E-mail: gdjaime@ien.gov.br, E-mail: jcsa@ien.gov.br, E-mail: silas@ien.gov.br [Instituto de Engenharia Nuclear (IEN/CNEN-RJ), Rio de Janeiro, RJ (Brazil). Divisao de Engenharia Nuclear

    2013-07-01

    Field Programmable Gate Arrays (FPGAs) based systems and equipment are beginning to appear in new plants I and C applications, as well as in retrofits for operating plants, in particular for safety applications due to their capability to face the systems obsolescence since they are circuit independent. The circuits implemented can be portable to different FPGAs architectures. Moreover, they reduce complexity for regulatory approval as compared to conventional microprocessor-based systems. Critical safety function (CSF) is the most significant design concept for prioritize operator actions for NPP based on the potential threat to the three barriers (fuel cladding, primary coolant system boundary, and containment) and allows the operator to respond to these threats prior to event diagnosis. CSF has a hierarchical information structure that organizes the system variables affecting the plant safety in terms of goal-means relations. This paper describes the application of FPGA in the implementation of the CSFs status tree logic for a Westinghouse 3-loops NPP simulator. (author)

  2. Modelling the current and future spatial distribution of NPP in a Mediterranean watershed

    Science.gov (United States)

    Donmez, Cenk; Berberoglu, Suha; Curran, Paul J.

    2011-06-01

    The aim of this study is to use full spatial resolution Envisat MERIS data to drive an ecosystem productivity model for pine forests along the Mediterranean coast of Turkey. The Carnegie, Ames, Stanford Approach (CASA) terrestrial biogeochemical model, designed to simulate the terrestrial carbon cycle using satellite sensor and meteorological data, was used to estimate annual regional fluxes in terrestrial net primary productivity (NPP). At its core this model is based on light-use efficiency, influenced by temperature, rainfall and solar radiation. Present climate data was generated from 50 climate stations within the watershed using co-kriging. Regional scale pseudo-warming data for year 2070 were derived using a Regional Climate Model (RCM) these data were used to downscale the GCM General Circulation Model for the research area as part of an international research project called Impact of Climate Changes on Agricultural Production Systems in Arid Areas (ICCAP). Outputs of climate data can be moderated using the four variables of percent tree cover, land cover, soil texture and NDVI. This study employed 47 MERIS images recorded between March 2003 and September 2005 to derive percent tree cover, land cover and NDVI. Envisat MERIS data hold great potential for estimating NPP with the CASA model because of the appropriateness of both its spatial and its spectral resolution.

  3. Neural networks in seismic discrimination

    Energy Technology Data Exchange (ETDEWEB)

    Dowla, F.U.

    1995-01-01

    Neural networks are powerful and elegant computational tools that can be used in the analysis of geophysical signals. At Lawrence Livermore National Laboratory, we have developed neural networks to solve problems in seismic discrimination, event classification, and seismic and hydrodynamic yield estimation. Other researchers have used neural networks for seismic phase identification. We are currently developing neural networks to estimate depths of seismic events using regional seismograms. In this paper different types of network architecture and representation techniques are discussed. We address the important problem of designing neural networks with good generalization capabilities. Examples of neural networks for treaty verification applications are also described.

  4. Key Features of the Deployed NPP/NPOESS Ground System

    Science.gov (United States)

    Heckmann, G.; Grant, K. D.; Mulligan, J. E.

    2010-12-01

    The National Oceanic & Atmospheric Administration (NOAA), Department of Defense (DoD), and National Aeronautics & Space Administration (NASA) are jointly acquiring the next-generation weather/environmental satellite system; the National Polar-orbiting Operational Environmental Satellite System (NPOESS). NPOESS replaces the current NOAA Polar-orbiting Operational Environmental Satellites (POES) and DoD Defense Meteorological Satellite Program (DMSP). NPOESS satellites carry sensors to collect meteorological, oceanographic, climatological, and solar-geophysical data of the earth, atmosphere, and space. The ground data processing segment is the Interface Data Processing Segment (IDPS), developed by Raytheon Intelligence & Information Systems (IIS). The IDPS processes NPOESS Preparatory Project (NPP)/NPOESS satellite data to provide environmental data products/records (EDRs) to NOAA and DoD processing centers operated by the US government. The IDPS will process EDRs beginning with NPP and continuing through the lifetime of the NPOESS system. The command & telemetry segment is the Command, Control & Communications Segment (C3S), also developed by Raytheon IIS. C3S is responsible for managing the overall NPP/NPOESS missions from control & status of the space and ground assets to ensuring delivery of timely, high quality data from the Space Segment to IDPS for processing. In addition, the C3S provides the globally-distributed ground assets needed to collect and transport mission, telemetry, and command data between the satellites and processing locations. The C3S provides all functions required for day-to-day satellite commanding & state-of-health monitoring, and delivery of Stored Mission Data to each Central IDP for data products development and transfer to system subscribers. The C3S also monitors and reports system-wide health & status and data communications with external systems and between the segments. The C3S & IDPS segments were delivered & transitioned to

  5. Discuss on Seismic Resistance Capability Analysis and Design of High-rise Building Structure%高层建筑结构抗震分析和设计的探讨

    Institute of Scientific and Technical Information of China (English)

    刘忠昊; 郭鹏昊

    2014-01-01

    This paper mainly introduces the seismic resistance capability of high-rise building structure, il ustrates the exi-sting problems in the seismic resistance capability design of high-rise building structure in China, and then analyzes the seismic resistance capability analysis methods of high-rise building structure.%文章主要对高层建筑结构抗震进行了介绍,说明了我国高层建筑结构抗震设计存在的问题,继而分析了高层建筑结构抗震分析方法。

  6. Analysis on anti-seismic identification and reinforcement design of current existing architectural structure%现有建筑结构抗震鉴定及加固设计分析

    Institute of Scientific and Technical Information of China (English)

    2015-01-01

    The paper introduces anti-seismic identification status of domestic architectural structures. Based on structural anti-seismic design de-mands,it analyzes anti-seismic identification contents and methods. Combining with engineering reinforcement theories,it discusses current com-mon reinforcement design concepts and measures,with a view to reduce seismic loss as much as possible.%介绍了国内对于建筑结构进行抗震鉴定的现状,基于结构抗震设计要求,分析了抗震鉴定的内容与主要方法,并结合工程加固理论,论述了当前比较常见的加固设计思路与措施,以最大限度的减少震害损失。

  7. Design and Implementation of a Wireless Sensor Network of GPS-enabled Seismic Sensors for the Study of Glaciers and Ice Sheets

    Science.gov (United States)

    Bilen, S. G.; Anandakrishnan, S.; Urbina, J. V.

    2012-12-01

    In an effort to provide new and improved geophysical sensing capabilities for the study of ice sheets in Antarctica and Greenland, or to study mountain glaciers, we are developing a network of wirelessly interconnected seismic and GPS sensor nodes (called "geoPebbles"), with the primary objective of making such instruments more capable and cost effective. We describe our design methodology, which has enabled us to develop these state-of-the art sensors using commercial-off-the-shelf hardware combined with custom-designed hardware and software. Each geoPebble is a self-contained, wirelessly connected sensor for collecting seismic measurements and position information. Each node is built around a three-component seismic recorder, which includes an amplifier, filter, and 24-bit analog-to-digital card that can sample up to 10 kHz. Each unit also includes a microphone channel to record the ground-coupled airwave. The timing for each node is available through a carrier-phase measurement of the L1 GPS signal at an absolute accuracy of better than a microsecond. Each geoPebble includes 16 GB of solid-state storage, wireless communications capability to a central supervisory unit, and auxiliary measurements capability (up to eight 10-bit channels at low sample rates). We will report on current efforts to test this new instrument and how we are addressing the challenges imposed by the extreme weather conditions on the Antarctic continent. After fully validating its operational conditions, the geoPebble system will be available for NSF-sponsored glaciology research projects. Geophysical experiments in the polar region are logistically difficult. With the geoPebble system, the cost of doing today's experiments (low-resolution, 2D) will be significantly reduced, and the cost and feasibility of doing tomorrow's experiments (integrated seismic, positioning, 3D, etc.) will be reasonable. Sketch of an experiment with geoPebbles scattered on the surface of the ice sheet. The seismic

  8. Seismic fragility analysis of seismically isolated nuclear power plants piping system

    Energy Technology Data Exchange (ETDEWEB)

    Salimi Firoozabad, Ehsan, E-mail: e.salimi@pusan.ac.kr [Department of Civil and Environmental Engineering, Pusan National University, 30 Jangjeon-dong, Geumjeong-gu, Busan 609-735 (Korea, Republic of); Jeon, Bub-Gyu, E-mail: bkjeon79@pusan.ac.kr [KOCED Seismic Simulation Test Center, Pusan National University, Yangsan Campus Mulgeum, Yangsan, Kyungsangnam (Korea, Republic of); Choi, Hyoung-Suk, E-mail: engineer@pusan.ac.kr [KOCED Seismic Simulation Test Center, Pusan National University, Yangsan Campus Mulgeum, Yangsan, Kyungsangnam (Korea, Republic of); Kim, Nam-Sik, E-mail: nskim@pusan.ac.kr [Department of Civil and Environmental Engineering, Pusan National University, 30 Jangjeon-dong, Geumjeong-gu, Busan 609-735 (Korea, Republic of)

    2015-04-01

    Highlights: • The critical points of a seismically isolated NPP piping system are identified. • The simulation results are validated through a monotonic and cyclic test of the critical points. • The conditional mean spectrum method is used to scale the selected records. • The fragility curves of the NPP piping system are estimated. • Computation of the fragility parameters is addressed. - Abstract: Nuclear power plants are high risk facilities due to the possibility of sudden seismic events, because any possible failure could initiate catastrophic radioactive contamination. The seismic fragility analysis of NPPs and related equipments (such as piping systems) is a proven method to determine their performance against any possible earthquake. In this study the Brookhaven National laboratory benchmark model of a piping system was considered for the fragility analysis. A tensile test was conducted to define the material properties. An initial seismic analysis of the piping system is performed to indicate the critical sections of the piping system. Numerical analysis was validated through a monotonic and cyclic loading experiment of two identified critical points of the piping system. The tests were conducted at the Korea Construction Engineering Development (KOCED) Seismic Simulation Test Center, Pusan National University, Korea. Fragility curves were expressed for critical points of the system as a function of the spectral acceleration of the records and the maximum relative displacement. The standard deviation of the response and capacity were calculated using mathematical formulas, assuming that those follow a log-normal distribution. We determined that the fragility curve of a pipe elbow must be derived for both the opening and closing mode, regarding the difference between the capacities of the elbow on those modes. The high confidence of low probability of failure for the considered fragility functions in a straight section in any direction is

  9. Procedures for computing site seismicity

    Science.gov (United States)

    Ferritto, John

    1994-02-01

    This report was prepared as part of the Navy's Seismic Hazard Mitigation Program. The Navy has numerous bases located in seismically active regions throughout the world. Safe effective design of waterfront structures requires determining expected earthquake ground motion. The Navy's problem is further complicated by the presence of soft saturated marginal soils that can significantly amplify the levels of seismic shaking as evidenced in the 1989 Loma Prieta earthquake. The Naval Facilities Engineering Command's seismic design manual, NAVFAC P355.l, requires a probabilistic assessment of ground motion for design of essential structures. This report presents the basis for the Navy's Seismic Hazard Analysis procedure that was developed and is intended to be used with the Seismic Hazard Analysis computer program and user's manual. This report also presents data on geology and seismology to establish the background for the seismic hazard model developed. The procedure uses the historical epicenter data base and available geologic data, together with source models, recurrence models, and attenuation relationships to compute the probability distribution of site acceleration and an appropriate spectra. This report discusses the developed stochastic model for seismic hazard evaluation and the associated research.

  10. Comparing global models of terrestrial net primary productivity (NPP): Global pattern and differentiation by major biomes

    Science.gov (United States)

    Kicklighter, D.W.; Bondeau, A.; Schloss, A.L.; Kaduk, J.; McGuire, A.D.

    1999-01-01

    Annual and seasonal net primary productivity estimates (NPP) of 15 global models across latitudinal zones and biomes are compared. The models simulated NPP for contemporary climate using common, spatially explicit data sets for climate, soil texture, and normalized difference vegetation index (NDVI). Differences among NPP estimates varied over space and time. The largest differences occur during the summer months in boreal forests (50??to 60??N) and during the dry seasons of tropical evergreen forests. Differences in NPP estimates are related to model assumptions about vegetation structure, model parameterizations, and input data sets.

  11. Modelling Active Faults in Probabilistic Seismic Hazard Analysis (PSHA) with OpenQuake: Definition, Design and Experience

    Science.gov (United States)

    Weatherill, Graeme; Garcia, Julio; Poggi, Valerio; Chen, Yen-Shin; Pagani, Marco

    2016-04-01

    The Global Earthquake Model (GEM) has, since its inception in 2009, made many contributions to the practice of seismic hazard modeling in different regions of the globe. The OpenQuake-engine (hereafter referred to simply as OpenQuake), GEM's open-source software for calculation of earthquake hazard and risk, has found application in many countries, spanning a diversity of tectonic environments. GEM itself has produced a database of national and regional seismic hazard models, harmonizing into OpenQuake's own definition the varied seismogenic sources found therein. The characterization of active faults in probabilistic seismic hazard analysis (PSHA) is at the centre of this process, motivating many of the developments in OpenQuake and presenting hazard modellers with the challenge of reconciling seismological, geological and geodetic information for the different regions of the world. Faced with these challenges, and from the experience gained in the process of harmonizing existing models of seismic hazard, four critical issues are addressed. The challenge GEM has faced in the development of software is how to define a representation of an active fault (both in terms of geometry and earthquake behaviour) that is sufficiently flexible to adapt to different tectonic conditions and levels of data completeness. By exploring the different fault typologies supported by OpenQuake we illustrate how seismic hazard calculations can, and do, take into account complexities such as geometrical irregularity of faults in the prediction of ground motion, highlighting some of the potential pitfalls and inconsistencies that can arise. This exploration leads to the second main challenge in active fault modeling, what elements of the fault source model impact most upon the hazard at a site, and when does this matter? Through a series of sensitivity studies we show how different configurations of fault geometry, and the corresponding characterisation of near-fault phenomena (including

  12. Seismic Creep

    Data.gov (United States)

    National Oceanic and Atmospheric Administration, Department of Commerce — Seismic creep is the constant or periodic movement on a fault as contrasted with the sudden erupture associated with an earthquake. It is a usually slow deformation...

  13. Seismic seiches

    Science.gov (United States)

    McGarr, Arthur; Gupta, Harsh K.

    2011-01-01

    Seismic seiche is a term first used by Kvale (1955) to discuss oscillations of lake levels in Norway and England caused by the Assam earthquake of August 15, 1950. This definition has since been generalized to apply to standing waves set up in closed, or partially closed, bodies of water including rivers, shipping channels, lakes, swimming pools and tanks due to the passage of seismic waves from an earthquake.

  14. Korea-Japan Joint Research on Development of Seismic Capacity Evaluation and Enhancement Technology Considering Near-Fault Effect

    Energy Technology Data Exchange (ETDEWEB)

    Choun, Young Sun; Choi, In Kil; Kim, Min Kyu [KAERI, Daejon (Korea, Republic of); Ohtori, Yasuki; Shiba, Yoshiaki; Nakajima, Masato [Central Research Institute of Electric Power Industry, Tokyo (Japan)

    2005-12-15

    Several recent improved methods for the EGFM are introduced in order to avoid artificial holes seen in the synthetic acceleration spectrum. Furthermore evaluation of input ground motions at Wolsung NPP are performed by varying the source parameters that may control the high-frequency wave radiation and the deviation of the synthetic motions are revealed. The PSHA case studies for four NPP sites (Wolsung, Kori, Uljin, Younggwang) are performed. In the analysis, site-specific attenuation equations developed for Korean NPP sites are employed, and the seismic hazards for the target sites are evaluated in the case where the four kind of seismic source models are considered. Moreover, the PSHA for Wolsung and Younggwang are conducted by using the site-specific attenuation equation with the index of response spectra and the uniform hazard spectra are evaluated for the two sites. The supporting tool for seismic response analysis and the evaluation tool for evaluating annual probability of failure were integrated in the frame of the seismic risk assessment system. Then, the tools were applied to the seismic risk assessment of the conventional EDG and isolated EDG. General information such as earthquake parameters and regional distribution of seismic intensity is summarized on the 2005 West Off Fukuoka earthquake. Then, the observed strong motion records in Japan and Korea sites are compiled, and regional distribution of peak accelerations are represented. Moreover, the peak accelerations of the records are compared with the values estimated from the existing attenuation equations.

  15. Impact of lateral force-resisting system and design/construction practices on seismic performance and cost of tall buildings in Dubai, UAE

    Science.gov (United States)

    AlHamaydeh, Mohammad; Galal, Khaled; Yehia, Sherif

    2013-09-01

    The local design and construction practices in the United Arab Emirates (UAE), together with Dubai's unique rate of development, warrant special attention to the selection of Lateral Force-Resisting Systems (LFRS). This research proposes four different feasible solutions for the selection of the LFRS for tall buildings and quantifies the impact of these selections on seismic performance and cost. The systems considered are: Steel Special Moment-Resisting Frame (SMRF), Concrete SMRF, Steel Dual System (SMRF with Special Steel Plates Shear Wall, SPSW), and Concrete Dual System (SMRF with Special Concrete Shear Wall, SCSW). The LFRS selection is driven by seismic setup as well as the adopted design and construction practices in Dubai. It is found that the concrete design alternatives are consistently less expensive than their steel counterparts. The steel dual system is expected to have the least damage based on its relatively lesser interstory drifts. However, this preferred performance comes at a higher initial construction cost. Conversely, the steel SMRF system is expected to have the most damage and associated repair cost due to its excessive flexibility. The two concrete alternatives are expected to have relatively moderate damage and repair costs in addition to their lesser initial construction cost.

  16. Application of Mössbauer spectroscopy on corrosion products of NPP

    Science.gov (United States)

    Dekan, J.; Lipka, J.; Slugeň, V.

    2013-04-01

    Steam generator (SG) is generally one of the most important components at all nuclear power plants (NPP) with close impact to safe and long-term operation. Material degradation and corrosion/erosion processes are serious risks for long-term reliable operation. Steam generators of four VVER-440 units at nuclear power plants V-1 and V-2 in Jaslovske Bohunice (Slovakia) were gradually changed by new original "Bohunice" design in period 1994-1998, in order to improve corrosion resistance of SGs. Corrosion processes before and after these design and material changes in Bohunice secondary circuit were studied using Mössbauer spectroscopy during last 25 years. Innovations in the feed water pipeline design as well as material composition improvements were evaluated positively. Mössbauer spectroscopy studies of phase composition of corrosion products were performed on real specimens scrapped from water pipelines or in form of filters deposits. Newest results in our long-term corrosion study confirm good operational experiences and suitable chemical regimes (reduction environment) which results mostly in creation of magnetite (on the level 70 % or higher) and small portions of hematite, goethite or hydrooxides. Regular observation of corrosion/erosion processes is essential for keeping NPP operation on high safety level. The output from performed material analyses influences the optimisation of operating chemical regimes and it can be used in optimisation of regimes at decontamination and passivation of pipelines or secondary circuit components. It can be concluded that a longer passivation time leads more to magnetite fraction in the corrosion products composition.

  17. Characterization of neutron field in a NPP workplace.

    Science.gov (United States)

    Breznik, B; Pochat, J L; Muller, H; Asselineau, B; Pavlin, M

    2007-01-01

    At the Krsko Nuclear Power Plant (NPP), albedo dosimeters are used for personal neutron dosimetry. Spectrometric measurements allow determination of reference dosimetric values of realistic neutron fields to be used for calibration of albedo dosimeters. The Laboratory for Neutron Metrology and Dosimetry from the Institute for Radiological Protection and Nuclear Safety (IRSN) was in charge of characterising neutron fields in the plant at two representative points with high neutron and gamma dose rate. Calibration of the dosimeters in the workplace used to be performed only by a spherical survey meter. Based on the reference dosimetric values, the Plant Dosimetry Laboratory has verified the response of albedo dosimeters.

  18. Status of steam generator tubing integrity at Jaslovske Bohunice NPP

    Energy Technology Data Exchange (ETDEWEB)

    Cepcek, S. [Nuclear Regulatory Authority of the Slovak Republic, Trnava (Slovakia)

    1997-02-01

    Steam generator represents one of the most important component of nuclear power plants. Especially, loss of tubing integrity of steam generators can lead to the primary coolant leak to secondary circuit and in worse cases to the unit shut down or to the PTS events occurrence. Therefore, to ensure the steam generator tubing integrity and the current knowledge about tube degradation propagation and development is of the highest importance. In this paper the present status of steam generator tubing integrity in operated NPP in Slovak Republic is presented.

  19. Multi-Hazard Advanced Seismic Probabilistic Risk Assessment Tools and Applications

    Energy Technology Data Exchange (ETDEWEB)

    Coleman, Justin L. [Idaho National Lab. (INL), Idaho Falls, ID (United States); Bolisetti, Chandu [Idaho National Lab. (INL), Idaho Falls, ID (United States); Veeraraghavan, Swetha [Idaho National Lab. (INL), Idaho Falls, ID (United States); Parisi, Carlo [Idaho National Lab. (INL), Idaho Falls, ID (United States); Prescott, Steven R. [Idaho National Lab. (INL), Idaho Falls, ID (United States); Gupta, Abhinav [Idaho National Lab. (INL), Idaho Falls, ID (United States)

    2016-09-01

    Design of nuclear power plant (NPP) facilities to resist natural hazards has been a part of the regulatory process from the beginning of the NPP industry in the United States (US), but has evolved substantially over time. The original set of approaches and methods was entirely deterministic in nature and focused on a traditional engineering margins-based approach. However, over time probabilistic and risk-informed approaches were also developed and implemented in US Nuclear Regulatory Commission (NRC) guidance and regulation. A defense-in-depth framework has also been incorporated into US regulatory guidance over time. As a result, today, the US regulatory framework incorporates deterministic and probabilistic approaches for a range of different applications and for a range of natural hazard considerations. This framework will continue to evolve as a result of improved knowledge and newly identified regulatory needs and objectives, most notably in response to the NRC activities developed in response to the 2011 Fukushima accident in Japan. Although the US regulatory framework has continued to evolve over time, the tools, methods and data available to the US nuclear industry to meet the changing requirements have not kept pace. Notably, there is significant room for improvement in the tools and methods available for external event probabilistic risk assessment (PRA), which is the principal assessment approach used in risk-informed regulations and risk-informed decision-making applied to natural hazard assessment and design. This is particularly true if PRA is applied to natural hazards other than seismic loading. Development of a new set of tools and methods that incorporate current knowledge, modern best practice, and state-of-the-art computational resources would lead to more reliable assessment of facility risk and risk insights (e.g., the SSCs and accident sequences that are most risk-significant), with less uncertainty and reduced conservatisms.

  20. Experience Practices on Decontamination Activity in NPP Decommissioning

    Energy Technology Data Exchange (ETDEWEB)

    Yoon, Suk Bon; Kim, Jeongju; Sohn, Wook [Korea Hydro and Nuclear Power Co., Daejeon (Korea, Republic of)

    2016-10-15

    Decommissioning of a nuclear power plant (NPP) involves various technical and administrative activities for a utility to terminate its license, which allows the plant site to be released from the regulatory control (site release). Decontamination activity in NPP decommissioning is one of the main technical activities to be performed during the decommissioning. The decontamination at decommissioning sites is usually performed due to several reasons such as reducing personnel dose and disposal costs, and cleanup to meet license termination requirements by using physical or chemical removal techniques proven through the previous experience practices. This paper introduces the best and worst practices for the decontamination activities collected from the decommissioning operational experiences through the implementation of nuclear decommissioning projects around the world. Review of the experiences of decontamination shows that it is important to conduct an advanced planning for optimized implementation of decontamination taking into considering site specific conditions such as operating time, reactor type, system, and so on. Also, a review of newer decontamination methods is necessary to safely and economically decommission the nuclear facility.

  1. Suomi NPP VIIRS Reflective Solar Bands Operational Calibration Reprocessing

    Directory of Open Access Journals (Sweden)

    Slawomir Blonski

    2015-12-01

    Full Text Available Radiometric calibration coefficients for the VIIRS (Visible Infrared Imaging Radiometer Suite reflective solar bands have been reprocessed from the beginning of the Suomi NPP (National Polar-orbiting Partnership mission until present. An automated calibration procedure, implemented in the NOAA (National Oceanic and Atmospheric Administration JPSS (Joint Polar Satellite System operational data production system, was applied to reprocess onboard solar calibration data and solar diffuser degradation measurements. The latest processing parameters from the operational system were used to include corrected solar vectors, optimized directional dependence of attenuation screens transmittance and solar diffuser reflectance, updated prelaunch calibration coefficients without an offset term, and optimized Robust Holt-Winters filter parameters. The parameters were consistently used to generate a complete set of the radiometric calibration coefficients for the entire duration of the Suomi NPP mission. The reprocessing has demonstrated that the automated calibration procedure can be successfully applied to all solar measurements acquired from the beginning of the mission until the full deployment of the automated procedure in the operational processing system. The reprocessed calibration coefficients can be further used to reprocess VIIRS SDR (Sensor Data Record and other data products. The reprocessing has also demonstrated how the automated calibration procedure can be used during activation of the VIIRS instruments on the future JPSS satellites.

  2. Modernization and power upgrading of the Loviisa NPP

    Energy Technology Data Exchange (ETDEWEB)

    Keskinen, A. [IVO Power Engineering Ltd., Vantaa (Finland)

    1997-12-31

    In 1995, Imatran Voima Oy (IVO) started a project for modernization and power upgrading of the Loviisa NPP. The main objectives of the project are to ensure plant safety, to increase electricity production and to improve the expertise of the IVO staff. The total electricity output of Loviisa 1 and 2 units is planned to be increased by about 100 MW. This will be achieved through renovation of the steam turbines and through gradual increase in the thermal reactor power up to 1,500 MW from the present level of 1,375 MW. The Loviisa NPP Final Safety Analysis Report has been revised to a great extent in connection with the licensing process of the reactor power upgrading. The project also includes certain improvements in the primary and safety systems to ensure plant safety. The total cost estimate of the project is around 200 million FIM. The project implementation started in 1995 and in accordance with the plans in 2000 after several phases the last measures at power plant will be completed. (orig.). 4 refs.

  3. Land and Cryosphere Products from Suomi NPP VIIRS: Overview and Status

    Science.gov (United States)

    Roman, M. O.; Justice, C. O.; Csiszar, I. A.; Vermote, E.; Wolfe, R. E.; Hook, S. J.; Friedl, M. A.; Schaaf, C.; Wang, Z.; Miura, T.; Tschudi, M. A.; Riggs, G. A.; Hall, D. K.; Lyapustin, A.; Devadiga, S.; Davidson, C.; Masuoka, E. J.

    2013-12-01

    The Visible Infrared Imaging Radiometer Suite (VIIRS) instrument was launched in October 2011 as part of the Suomi National Polar-orbiting Partnership (S-NPP). The VIIRS instrument was designed to improve upon the capabilities of the operational Advanced Very High Resolution Radiometer (AVHRR) and provide observation continuity with NASA's Earth Observing System's (EOS) Moderate Resolution Imaging Spectroradiometer (MODIS). Since the VIIRS first-light images were received in November 2011, NASA and NOAA funded scientists have been working to evaluate the instrument performance and generate land and cryosphere products which would meet the needs of the NOAA operational users and the NASA science community. NOAA's focus has been on refining a suite of operational products known as Environmental Data Records (EDRs), which were developed according to project specifications under the National Polar-orbiting Environmental Satellite System (NPOESS). The NASA S-NPP Science Team has focused on evaluating the EDRs for science use and developing and testing additional products to meet science data needs and provide MODIS data product continuity. This paper will present the findings to-date of the NASA Science Team's evaluation of the VIIRS Land and Cryosphere EDRs, specifically Surface Reflectance, Land Surface Temperature, Surface Albedo, Vegetation Indices, Surface Type, Active Fires, Snow Cover, Ice Surface Temperature, and Sea Ice Characterization. To achieve the stated goal of MODIS data continuity and the establishment of long-term data records through VIIRS, it is important to start now to use S-NPP to establish a pathway to science use of VIIRS data in the JPSS era. One year after launch, initial instrument and operational product evaluations are now ending and the next step is to build on the success of the MODIS Adaptive Processing System (MODAPS) and the Land Product Evaluation and Analysis Tool Element (PEATE) data processing and generate and distribute high

  4. Nonvascular contribution to ecosystem NPP in a subarctic heath during early and late growing season

    DEFF Research Database (Denmark)

    Campioli, Matteo; Samson, Roeland; Michelsen, Anders

    2009-01-01

    Bryophytes and lichens abound in many arctic ecosystems and can contribute substantially to the ecosystem net primary production (NPP). Because of their growth seasonality and their potential for growth out of the growing season peak, bryophyte and lichen contribution to NPP may be particularly...

  5. 7 CFR 1792.104 - Seismic acknowledgments.

    Science.gov (United States)

    2010-01-01

    ... registered architect or engineer responsible for the building design stating that seismic provisions pursuant to § 1792.103 of this subpart will be used in the design of the building. (a) For projects in which... include the identification and date of the model code or standard that is used in the seismic design...

  6. Seismic evaluation methods for existing buildings

    Energy Technology Data Exchange (ETDEWEB)

    Hsieh, B.J.

    1995-07-01

    Recent US Department of Energy natural phenomena hazards mitigation directives require the earthquake reassessment of existing hazardous facilities and general use structures. This applies also to structures located in accordance with the Uniform Building Code in Seismic Zone 0 where usually no consideration is given to seismic design, but where DOE specifies seismic hazard levels. An economical approach for performing such a seismic evaluation, which relies heavily on the use of preexistent structural analysis results is outlined below. Specifically, three different methods are used to estimate the seismic capacity of a building, which is a unit of a building complex located on a site considered low risk to earthquakes. For structures originally not seismically designed, which may not have or be able to prove sufficient capacity to meet new arbitrarily high seismic design requirement and which are located on low-seismicity sites, it may be very cost effective to perform detailed site-specific seismic hazard studies in order to establish the true seismic threat. This is particularly beneficial, to sites with many buildings and facilities to be seismically evaluated.

  7. Seismic Fragility Analysis of a Degraded Condensate Storage Tank

    Energy Technology Data Exchange (ETDEWEB)

    Nie, J.; Braverman, J.; Hofmayer, C.; Choun, Y-S.; Kim, M.K.; Choi, I-K.

    2011-05-16

    The Korea Atomic Energy Research Institute (KAERI) and Brookhaven National Laboratory are conducting a collaborative research project to develop seismic capability evaluation technology for degraded structures and components in nuclear power plants (NPPs). One of the goals of this collaboration endeavor is to develop seismic fragility analysis methods that consider the potential effects of age-related degradation of structures, systems, and components (SSCs). The essential part of this collaboration is aimed at achieving a better understanding of the effects of aging on the performance of SSCs and ultimately on the safety of NPPs. A recent search of the degradation occurrences of structures and passive components (SPCs) showed that the rate of aging related degradation in NPPs was not significantly large but increasing, as the plants get older. The slow but increasing rate of degradation of SPCs can potentially affect the safety of the older plants and become an important factor in decision making in the current trend of extending the operating license period of the plants (e.g., in the U.S. from 40 years to 60 years, and even potentially to 80 years). The condition and performance of major aged NPP structures such as the containment contributes to the life span of a plant. A frequent misconception of such low degradation rate of SPCs is that such degradation may not pose significant risk to plant safety. However, under low probability high consequence initiating events, such as large earthquakes, SPCs that have slowly degraded over many years could potentially affect plant safety and these effects need to be better understood. As part of the KAERI-BNL collaboration, a condensate storage tank (CST) was analyzed to estimate its seismic fragility capacities under various postulated degradation scenarios. CSTs were shown to have a significant impact on the seismic core damage frequency of a nuclear power plant. The seismic fragility capacity of the CST was developed

  8. Teacher Directed Design: Content Knowledge, Pedagogy and Assessment under the Nevada K-12 Real-Time Seismic Network

    Science.gov (United States)

    Cantrell, P.; Ewing-Taylor, J.; Crippen, K. J.; Smith, K. D.; Snelson, C. M.

    2004-12-01

    Education professionals and seismologists under the emerging SUN (Shaking Up Nevada) program are leveraging the existing infrastructure of the real-time Nevada K-12 Seismic Network to provide a unique inquiry based science experience for teachers. The concept and effort are driven by teacher needs and emphasize rigorous content knowledge acquisition coupled with the translation of that knowledge into an integrated seismology based earth sciences curriculum development process. We are developing a pedagogical framework, graduate level coursework, and materials to initiate the SUN model for teacher professional development in an effort to integrate the research benefits of real-time seismic data with science education needs in Nevada. A component of SUN is to evaluate teacher acquisition of qualified seismological and earth science information and pedagogy both in workshops and in the classroom and to assess the impact on student achievement. SUN's mission is to positively impact earth science education practices. With the upcoming EarthScope initiative, the program is timely and will incorporate EarthScope real-time seismic data (USArray) and educational materials in graduate course materials and teacher development programs. A number of schools in Nevada are contributing real-time data from both inexpensive and high-quality seismographs that are integrated with Nevada regional seismic network operations as well as the IRIS DMC. A powerful and unique component of the Nevada technology model is that schools can receive "stable" continuous live data feeds from 100's seismograph stations in Nevada, California and world (including live data from Earthworm systems and the IRIS DMC BUD - Buffer of Uniform Data). Students and teachers see their own networked seismograph station within a global context, as participants in regional and global monitoring. The robust real-time Internet communications protocols invoked in the Nevada network provide for local data acquisition

  9. Comparative analysis of NPP changes in global tropical forests from 2001 to 2013

    Science.gov (United States)

    Yin, S.; Li, X.; Wu, W.

    2017-02-01

    Net primary production (NPP) is the difference between total photosynthesis (gross primary production, GPP) and total plant respiration in an ecosystem. NPP is a key component of the terrestrial carbon cycle and is important in global climate research. Tropical forests, distributed mainly in Central Africa, Central and South America, and Southeast Asia, are among the most important ecosystems on earth. They are very important to analyses of the global carbon budget and to the projection of future climatic changes. In this study, we analyzed and compared the temporal and spatial changes of NPP within the three dominant areas of tropical forest from 2001 to 2013 by using data from the Moderate Resolution Imaging Spectroradiometer (MODIS). We found that Central and South America has the highest annual mean NPP, statistically, while the average NPP shows an increasing trend both in Central and South America and Central Africa but a decreasing trend in Southeast Asia.

  10. Seismic imaging of sandbox experiments – laboratory hardware setup and first reflection seismic sections

    OpenAIRE

    Kukowski, N.; Oncken, O.; M.-L. Buddensiek; C. M. Krawczyk

    2012-01-01

    With the study and technical development introduced here, we combine analogue sandbox simulation techniques with seismic physical modelling of sandbox models. For that purpose, we designed and developed a new mini-seismic facility for laboratory use, comprising a seismic tank, a PC-driven control unit, a positioning system, and piezo-electric transducers used here the first time in an array mode. To assess the possibilities and limits of seismic imaging of small-scale structures in sandbox mo...

  11. Seismic imaging of sandbox experiments – laboratory hardware setup and first reflection seismic sections

    OpenAIRE

    C. M. Krawczyk; Buddensiek, M.-L.; Oncken, O.; Kukowski, N.

    2013-01-01

    With the study and technical development introduced here, we combine analogue sandbox simulation techniques with seismic physical modelling of sandbox models. For that purpose, we designed and developed a new mini-seismic facility for laboratory use, comprising a seismic tank, a PC-driven control unit, a positioning system, and piezoelectric transducers used here for the first time in an array mode. To assess the possibilities and limits of seismic imaging of small-scale str...

  12. Simulation of Thermopower Influence on Fuel Core of Power Rod in Nuclear Power Plant (NPP Active Zone

    Directory of Open Access Journals (Sweden)

    I. S. Kulikov

    2010-01-01

    Full Text Available The paper considers problems of modern methods for  calculation of designs and materials of nuclear power. A model of numerical analysis for stress-strain state of fuel pins in the NPP active zone is proposed in the paper. The paper contains simulation concerning a fuel core section of a nuclear reactor heat-generating element with subsequent solution of a temperature and thermoelastic problem in computer program complex FEA ANSYS Workbench 11.0. All the obtained results have passed through checking procedure.

  13. The Role of Suomi NPP VIIRS Data in Land Science and Applications.

    Science.gov (United States)

    Justice, C. O.; Csiszar, I. A.; Roman, M. O.; Vermote, E.

    2014-12-01

    The current Suomi-NPP mission was designed as a bridging mission to the Joint Polar Satellite System (JPSS) next-generation, operational satellites. The VIIRS instrument on-board Suomi-NPP provides continuity with NASA's Earth Observing System Moderate-resolution Imaging Spectroradiometer (MODIS) observations and a much-needed replacement of the long-serving, operational NOAA Advanced Very High Resolution Radiometer (AVHRR) system, to meet the expanding needs of Earth Science and Applications of Societal Benefit. Post-launch evaluation has proven the instrument to be excellent for land observations and capable of providing measurement continuity with MODIS. This provides a critical contribution to the scientific study of global change. Several regions of the World are undergoing rapid land transformations, driven by economic development and population growth. In addition, changes in climate conditions are resulting in ecosystem responses and changes in land cover and land use. Long-term, systematic observations of the global land surface at coarse resolution enable detection, monitoring and characterization of such changes to the land surface. A suite of Land environmental data records (EDRs) from the VIIRS, are being developed by NOAA to meet operational data needs, primarily for the National Weather Service (e.g., Albedo, Land Surface Temperature, Fractional Vegetation Cover, Surface Type, Snow and Ice Monitoring). Scientists funded by NOAA and NASA, have been evaluating and validating these products. Based on these evaluations, NASA is embarking on a program to develop enhanced and additional products to provide continuity with MODIS to meet the needs of the global change science community. In addition, and as with MODIS, data from the VIIRS can be used as input to a number of practical applications of societal benefit and the associated decision support systems. For example, progress with VIIRS data is being made in the areas of fire and agricultural monitoring

  14. Design of a seismic energy dissipator for an interruptor type 3AS2-45; Diseno de un disipador de energia sismica para un interruptor tipo 3AS2-45

    Energy Technology Data Exchange (ETDEWEB)

    Castro Felix, Jaime

    2004-02-15

    With the aid of the theory behind seismically isolated structures and the bi-linear behavior of an isolated system of Multiple Degrees of Freedom (MDOF), the information obtained on the spectral analysis is complemented with the purpose of simulating one itself for the design of a dissipator of seismic energy. The seismicity in the world is briefly explained, (in Mexico in special for the Geothermal Field of Cerro Prieto), the types of earthquakes, etc., to give way to a documentation of the state-of-the-art in advanced seismic resistant systems and to a procedure to establish the level of seismic qualification of electrical equipment from the level of seismic performance for the Mexican Republic. [Spanish] Con la ayuda de la teoria detras de estructuras aisladas sismicamente y el comportamiento bilineal de un sistema de aislamiento de Multiples Grados de Libertad (MDOF), se complementa la informacion recabada sobre el analisis espectral con el fin de simular uno propio para el diseno de un disipador de energia sismica. Se explica brevemente la sismicidad en el mundo, en Mexico, en especial el Campo Geotermico de Cerro Prieto, los tipos de sismos, etc., para dar paso a una documentacion del estado del arte en sistemas sismorresistentes avanzados y a un procedimiento para establecer el nivel de calificacion sismica de equipos electricos a partir del Nivel de desempeno sismico para la Republica Mexicana.

  15. Construction scheduled delay risk assessment by using combined AHP-RII methodology for an international NPP project

    Energy Technology Data Exchange (ETDEWEB)

    Hossen, Mufazal Muhammed; Kang, Sun Koo; Kim, Jong Hyun [KEPCO International Nuclear Graduate School (KINGS), Ulsan (Korea, Republic of)

    2015-04-15

    In this study, Nuclear Power Plant (NPP) construction schedule delay risk assessment methodology is developed and the construction delay risk is assessed for turnkey international NPP projects. Three levels of delay factors were selected through literature review and discussions with nuclear industry experts. A questionnaire survey was conducted on the basis of an analytic hierarchy process (AHP) and Relative Importance Index (RII) methods and the schedule delay risk is assessed qualitatively and quantitatively by severity and frequency of occurrence of delay factors. This study assigns four main delay factors to the first level: main contractor, utility, regulatory authority, and financial and country factor. The second and the third levels are designed with 12 sub-factors and 32 sub-sub-factors, respectively. This study finds the top five most important sub-sub-factors, which are as follows: policy changes, political instability and public intervention; uncompromising regulatory criteria and licensing documents conflicting with existing regulations; robust design document review procedures; redesign due to errors in design and design changes; and worldwide shortage of qualified and experienced nuclear specific equipment manufacturers. The proposed combined AHP-RII methodology is capable of assessing delay risk effectively and efficiently. Decision makers can apply risk informed decision making to avoid unexpected construction delays of NPPs.

  16. Integrated system for seismic evaluations

    Energy Technology Data Exchange (ETDEWEB)

    Xu, J.; Philippacopoulos, A.J.; Miller, C.A.; Costantino, C.J.; Graves, H.

    1989-01-01

    This paper describes the various features of the Seismic Module of the CARES system (Computer Analysis for Rapid Evaluation of Structures). This system was developed by Brookhaven National Laboratory (BNL) for the US Nuclear Regulatory Commission to perform rapid evaluations of structural behavior and capability of nuclear power plant facilities. The CARES is structured in a modular format. Each module performs a specific type of analysis i.e., static or dynamic, linear or nonlinear, etc. This paper describes the features of the Seismic Module in particular. The development of the Seismic Module of the CARES system is based on an approach which incorporates all major aspects of seismic analysis currently employed by the industry into an integrated system that allows for carrying out interactively computations of structural response to seismic motions. The code operates on a PC computer system and has multi-graphics capabilities. It has been designed with user friendly features and it allows for interactive manipulation of various analysis phases during the seismic design process. The capabilities of the seismic module include (a) generation of artificial time histories compatible with given design ground response spectra, (b) development of Power Spectral Density (PSD) functions associated with the seismic input, (c) deconvolution analysis using vertically propagating shear waves through a given soil profile, and (d) development of in-structure response spectra or corresponding PSD's. It should be pointed out that these types of analyses can also be performed individually by using available computer codes such as FLUSH, SAP, etc. The uniqueness of the CARES, however, lies on its ability to perform all required phases of the seismic analysis in an integrated manner. 5 refs., 6 figs.

  17. Development of Earthquake Ground Motion Input for Preclosure Seismic Design and Postclosure Performance Assessment of a Geologic Repository at Yucca Mountain, NV

    Energy Technology Data Exchange (ETDEWEB)

    I. Wong

    2004-11-05

    This report describes a site-response model and its implementation for developing earthquake ground motion input for preclosure seismic design and postclosure assessment of the proposed geologic repository at Yucca Mountain, Nevada. The model implements a random-vibration theory (RVT), one-dimensional (1D) equivalent-linear approach to calculate site response effects on ground motions. The model provides results in terms of spectral acceleration including peak ground acceleration, peak ground velocity, and dynamically-induced strains as a function of depth. In addition to documenting and validating this model for use in the Yucca Mountain Project, this report also describes the development of model inputs, implementation of the model, its results, and the development of earthquake time history inputs based on the model results. The purpose of the site-response ground motion model is to incorporate the effects on earthquake ground motions of (1) the approximately 300 m of rock above the emplacement levels beneath Yucca Mountain and (2) soil and rock beneath the site of the Surface Facilities Area. A previously performed probabilistic seismic hazard analysis (PSHA) (CRWMS M&O 1998a [DIRS 103731]) estimated ground motions at a reference rock outcrop for the Yucca Mountain site (Point A), but those results do not include these site response effects. Thus, the additional step of applying the site-response ground motion model is required to develop ground motion inputs that are used for preclosure and postclosure purposes.

  18. Consideration of hazardous and especially hazardous hydrometeorological impacts in design of buildings and structures of nuclear power plants

    Directory of Open Access Journals (Sweden)

    Bryukhan Fedor

    2016-01-01

    Full Text Available External impacts of the hydrometeorological origin have a significant influence on the safety level of objects of use of atomic energy (OUAE, including nuclear power plants (NPP. Therefore, the existing NPP-related safety regulations demand to consider such impacts at all stages of the NPP life cycle. It is important to make decisions on considering or ignoring certain external impacts while designing NPP buildings and structures. The main criterion for such decisions is the probability of a non-project accident associated with the release of radionuclides into the environment when an extreme phenomena occurs. The aim of this study is to develop a concept for refinement regulatory requirements, considering hydrometeorological factors in organization of NPP engineering protection. Criteria for consideration of hazardous and especially hazardous hydrometeorological impacts for design of NPP buildings and structures were analyzed, and recommendations for refinement of regulatory requirements, considering hydrometeorological factors in organization of NPP engineering protection, were developed.

  19. Seismic Symphonies

    Science.gov (United States)

    Strinna, Elisa; Ferrari, Graziano

    2015-04-01

    The project started in 2008 as a sound installation, a collaboration between an artist, a barrel organ builder and a seismologist. The work differs from other attempts of sound transposition of seismic records. In this case seismic frequencies are not converted automatically into the "sound of the earthquake." However, it has been studied a musical translation system that, based on the organ tonal scale, generates a totally unexpected sequence of sounds which is intended to evoke the emotions aroused by the earthquake. The symphonies proposed in the project have somewhat peculiar origins: they in fact come to life from the translation of graphic tracks into a sound track. The graphic tracks in question are made up by copies of seismograms recorded during some earthquakes that have taken place around the world. Seismograms are translated into music by a sculpture-instrument, half a seismograph and half a barrel organ. The organ plays through holes practiced on paper. Adapting the documents to the instrument score, holes have been drilled on the waves' peaks. The organ covers about three tonal scales, starting from heavy and deep sounds it reaches up to high and jarring notes. The translation of the seismic records is based on a criterion that does match the highest sounds to larger amplitudes with lower ones to minors. Translating the seismogram in the organ score, the larger the amplitude of recorded waves, the more the seismogram covers the full tonal scale played by the barrel organ and the notes arouse an intense emotional response in the listener. Elisa Strinna's Seismic Symphonies installation becomes an unprecedented tool for emotional involvement, through which can be revived the memory of the greatest disasters of over a century of seismic history of the Earth. A bridge between art and science. Seismic Symphonies is also a symbolic inversion: the instrument of the organ is most commonly used in churches, and its sounds are derived from the heavens and

  20. Near Real Time Processing Chain for Suomi NPP Satellite Data

    Science.gov (United States)

    Monsorno, Roberto; Cuozzo, Giovanni; Costa, Armin; Mateescu, Gabriel; Ventura, Bartolomeo; Zebisch, Marc

    2014-05-01

    Since 2009, the EURAC satellite receiving station, located at Corno del Renon, in a free obstacle site at 2260 m a.s.l., has been acquiring data from Aqua and Terra NASA satellites equipped with Moderate Resolution Imaging Spectroradiometer (MODIS) sensors. The experience gained with this local ground segmenthas given the opportunity of adapting and modifying the processing chain for MODIS data to the Suomi NPP, the natural successor to Terra and Aqua satellites. The processing chain, initially implemented by mean of a proprietary system supplied by Seaspace and Advanced Computer System, was further developed by EURAC's Institute for Applied Remote Sensing engineers. Several algorithms have been developed using MODIS and Visible Infrared Imaging Radiometer Suite (VIIRS) data to produce Snow Cover, Particulate Matter estimation and Meteo maps. These products are implemented on a common processor structure based on the use of configuration files and a generic processor. Data and products have then automatically delivered to the customers such as the Autonomous Province of Bolzano-Civil Protection office. For the processing phase we defined two goals: i) the adaptation and implementation of the products already available for MODIS (and possibly new ones) to VIIRS, that is one of the sensors onboard Suomi NPP; ii) the use of an open source processing chain in order to process NPP data in Near Real Time, exploiting the knowledge we acquired on parallel computing. In order to achieve the second goal, the S-NPP data received and ingested are sent as input to RT-STPS (Real-time Software Telemetry Processing System) software developed by the NASA Direct Readout Laboratory 1 (DRL) that gives as output RDR files (Raw Data Record) for VIIRS, ATMS (Advanced Technology Micorwave Sounder) and CrIS (Cross-track Infrared Sounder)sensors. RDR are then transferred to a server equipped with CSPP2 (Community Satellite Processing Package) software developed by the University of

  1. NPP VIIRS Early On-Orbit Geometric Performance

    Science.gov (United States)

    Wolfe, Robert E.; Lin, Guoqing; Nishihama, Masahiro; Tewari, Krishna; Montano, Enrique

    2012-01-01

    The NASA/NOAA Visible Infrared Imager Radiometer Suite (VIIRS) instrument on-board the Suomi National Polar-orbiting Partnership (NPP) satellite was launched in October, 2011. The instrument geometric performance includes sensor spatial response, band-to-band co-registration (BBR), and geolocation accuracy and precision. The geometric performance is an important aspect of sensor data record (SDR) calibration and validation. In this paper we will discuss geometric performance parameter characterization using the first seven-month of VIIRS' earth and lunar data, and compare with the at-launch performance using ground testing data and analysis of numerical modeling results as the first step in on-orbit geometric calibration and validation.

  2. Development of NPP personnel training system in Ukraine

    Energy Technology Data Exchange (ETDEWEB)

    Tarykin, V. [Operation Personnel Training Department, Khmelnitsky NPP, Training Center, Neteshin 30100, Khmelnitsky region (Ukraine)]. E-mail: tarykinv@ukr.net

    2005-07-01

    Modern personnel training and retraining system is a guarantee of NPPs safe reliable operation. Since the time when independence of Ukraine was proclaimed personnel training system was created directly at NPPs. This system is based on the latest legislation framework, developed subject to IAEA recommendations, gained international experience in the field of personnel training in view of increased demands to personnel qualification. Training Centers, formed at each plant, form one of the main components of NPP personnel training. Personnel training at Training Centers is performed in accordance with standard programmes. Simulator training base was created by joint efforts of specialists from the USA, Russia and Ukraine. Establishing manager training system and replacement reserves for National Nuclear Energy Generating Company 'ENERGOATOM' (NNEGC 'ENERGOATOM') managerial personnel, including training programme and training materials development, teacher selection and training, is under way. (author)

  3. MORE: Management of Requirements in NPP Modernisation Projects, final report

    Energy Technology Data Exchange (ETDEWEB)

    Fredriksen, R.; Katta, V.; Raspotnig, C. (Inst. for energiteknikk (IFE) (Norway)); Valkonen, J. (Technical Research Centre of Finland (VTT) (Finland))

    2008-09-15

    This report documents the work and related activities of the MORE (Management of Requirements in NPP Modernisation Projects) (NKS-R project number NKS-R-2005-47) project. This report also provides a summary of the project activities and deliverables, and discusses possible application areas. The project has aimed at the industrial utilisation of the results from the TACO: (Traceability and Communication of Requirements in Digital I and C Systems Development) (NKS-R project number NKS-R-2002-16, completed June, 2005) project, and practical application of improved approaches and methods for requirements engineering and change management. Finally, the report provides a brief description of the extended industrial network and disseminations of the results in Nordic and NKS related events such as seminars and workshops. (author)

  4. Reasonable Seleetion for Design Seheme in Composite Seismic-insolated Structure of Masonry%砌体复合隔震结构设计方案的合理选择

    Institute of Scientific and Technical Information of China (English)

    杨树标; 周书敬

    2001-01-01

    Based on the discussion for the design scheme of one seismic-isolated building,reasonably selecting the design scheme of composite seismic-isolated masonry structure is studied.At the same time,the main factors affecting composite seismic-isolated scheme of masonry and the principles of reasonably selecting seimsic-isolated scheme are discussed.%通过对一砌体隔震建筑设计方案的讨论,研究了砌体复合隔震设计方案的合理选择问题。论述了影响砌体复合隔震方案的主要因素及选择合理隔震方案的原则。

  5. COMPARISON OF NOVORONEZH UNIT 5 NPP AND SOUTH UKRAINE UNIT 1 NPP LEVEL I PRA RESULTS.

    Energy Technology Data Exchange (ETDEWEB)

    MUSICKI,Z.; GINSBERG,T.

    2002-04-18

    This paper describes a study undertaken to explain the risk profile differences in the results of PRAs of two similar WER-1000 nuclear power plants. The risk profile differences are particularly significant in the area of small steam/feedwater line breaks, small-small LOCAs, support system initiators and containment bypass initiators. A top level (limited depth) approach was used in which we studied design differences, major assumptions, data differences, and also compared the two PRA analyses on an element-by-element basis in order to discern the major causative factors for the risk profile differences. We conclude that the major risk profile differences are due to differences in assumptions and engineering judgment (possibly combined with some design and data differences) involved in treatment of uncertain physical phenomena (primarily sump plugging in LOCAs and turbine building steaming effects in secondary system breaks). Additional major differences are attributable to support system characteristics.

  6. Korea-Japan joint research on development of seismic capacity evaluation and enhancement technology considering near-fault effect (annual report 2004)

    Energy Technology Data Exchange (ETDEWEB)

    Choun, Young Sun; Choi, In Kil; Kim, Min Kyu [KAERI, Taejon (Korea, Republic of); Ohtori, Yasuki; Shiba, Yoshiaki; Nakajima, Masato [CRIEPI (Japan)

    2004-12-01

    In Chapter 2 the evaluation methods of input ground motions for seismic design are summarized and especially the empirical and/or stochastic Green's function method is introduced in order to calculate the broadband strong motions based on the physically reliable fault model. Then the evaluation procedure is applied to the Ulsan fault system near which Wolsung nuclear power plant is located. In chapter3, the PSHA case studies for Wolsung NPP site are performed, in which multi attenuation equations of earthquake motions are adopted. Moreover, the results of seismic hazard evaluation for eight sites in Korea are shown. In addition, the contents of two literatures on seismic hazard evaluation are introduced. In chapter 4, isolation devices for emergency diesel generator have been studied. The models for friction-pendulum system, high damping rubber bearing and natural rubber bearing are developed and implemented in the TDAP-III. Then, the rubber bearings as the isolation system for EDG were designed. As a result of draft design, it was found that multi-stage isolation system, of which 4 isolators are mounted at each stage, has much potential more than conventional (single-stage) isolation system. In chapter 5, the seismic PSA of conventional and isolated EDG was evaluated at major Korean cities. The fragility curves and HCLPF (High Confidence Low Probability of Failure) capacity were selected as the measures of comparisons. The response acceleration at the center of gravity of EDG, and deformation of isolation system were compared. From the evaluation it was found that the isolation system has a possibility to improve HCLPF capacity.

  7. 框架结构中楼梯的抗震设计分析%On anti-seismic design analysis of stairs in frame structure

    Institute of Scientific and Technical Information of China (English)

    王大斌; 张莉

    2012-01-01

    The paper undertakes the anti-seismic analysis of four stair forms of some frame structure, explores the changes at the stairs, the peri- od, the displacement, and the stress of the structure under the small earthquake, the middle and large earthquake, so as to provide the helpful reference for the stair design for the frame structure.%对某框架结构的四种不同楼梯形式进行了抗震分析,探讨了其在小震、中震及大震作用下楼梯及结构的周期、位移、受力等变化情况,为框架结构的楼梯设计提供了有益的参考。

  8. The International Cooperation and Partnership, Keystones for Engineering and Procurement for Cernavoda NPP Unit 2

    Energy Technology Data Exchange (ETDEWEB)

    Stiopol, Mihaela; Vatamanu, Mariana; Bucur, Cristina [Nuclearelectrica SA, 65 Polona Street, 010494 Bucharest (Romania)

    2008-07-01

    Romania is starting the second year as a MS of the EU, and is crossing a crucial year in implementing the national energy strategy. The EC documents from last year, as an energy policy for Europe or the nuclear illustrative programme provided the guidelines for the new Romanian energy strategy, based on the principles of security of supply, competitiveness, environment protection and optimization of the use of domestic natural resources. In the line with the right of each European state to choose the proper energy mix, in order to face the predicted deployment of natural gas and oil resources, Romania has to redirect its strategy to improve the energy efficiency, develop the renewable energies and to extend the use of nuclear. Romania has developed the national infrastructure for implementation, management and supervision of the nuclear power projects, including the environment protection aspects. The Ministry of Economy and Finance is responsible for the national strategy in the energy field, including NPP projects implementation and operation. Other important actors are the Ministry of the Environment, the Nuclear Agency, the Nuclear Regulatory Body - CNCAN and the National Agency for Radioactive Waste - ANDRAD. For Romania, the nuclear energy represents an obvious reality, strongly proved by good performances registered by Cernavoda NPP Unit 1 during over 12 years of commercial operation: High quality of the nuclear fuel produced by Nuclear Fuel Plant in Pitesti - as demonstrated by the 7 consecutive years of operation of Cernavoda Unit 1 without detecting a single fuel bundle with nuclear defect, the very good quality of heavy water produced in Romania based on Romanian concept and technology and, by the most recently success of the Romanian nuclear industry: commissioning of the second Unit at Cernavoda NPP on October 5. 2007. All those represent achievements of entire Romanian society for which the education, research, design engineering and operation of

  9. Suggestion of a Framework to Analyze Failure Modes and Effect of Cyber Attacks in NPP

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Chan Young; Seong, Poong Hyun [KAIST, Daejeon (Korea, Republic of)

    2016-05-15

    The cyber security issue on NPP is inevitable issue. Unlike general cyber security, cyber-physical system like NPP can induce serious consequences such as core damage by cyber-attack. So in this paper, to find how hacker can attack the NPP, (1) PSA results were utilized to find the relationship between physical system and cyber-attack and (2) vulnerabilities on digital control systems were investigated to find how hacker can implement the possible attack. It is expected that these steps are utilized when establishing penetration test plans or cyber security drill plans.

  10. Information theory-based approach for modeling the cognitive behavior of NPP operators

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Jong Hyun; Seong, Poong Hyun [KAIST, Taejon (Korea, Republic of)

    2001-10-01

    An NPP system consists of three important components: the machine system, operators, and MMI. Through the MMI, operators monitor and control the plant system. The cognitive model of NPP operators has become a target of modeling by cognitive engineers due to their work environment: complex, uncertain, and safe critical. We suggested the contextual model for the cognitive behavior of NPP operator and the mathematical fundamentals based on information theory which can quantify the model. The demerit of the methodology using the information theory is that it cannot evaluate the correctness and quality of information. Therefore, the validation through the experiment is needed.

  11. Porcine ecto-nucleotide pyrophosphatase/phosphodiesterase 1 (NPP1/CD203a)

    DEFF Research Database (Denmark)

    Petersen, Cathrine Bie; Hillig, Ann-Britt Nygaard; Viuff, Birgitte;

    2007-01-01

    /phosphodiesterase 1 (NPP1/CD203a). The porcine NPP1/CD203a encoding gene was mapped to chromosome 1 using a radiation hybrid panel, and transcription was investigated by RT-PCR analysis of several tissues. The cDNA was cloned and introduced into COS7 cells resulting in expression of functionally active enzyme...... and verification of the specificity of an SWC9 reacting monoclonal antibody. The antibody was used for immunohistochemical examination of various porcine tissues. Most prominent expression of NPP1/CD203a was found in lung macrophages and liver sinusoids....

  12. Advanced Seismic While Drilling System

    Energy Technology Data Exchange (ETDEWEB)

    Robert Radtke; John Fontenot; David Glowka; Robert Stokes; Jeffery Sutherland; Ron Evans; Jim Musser

    2008-06-30

    A breakthrough has been discovered for controlling seismic sources to generate selectable low frequencies. Conventional seismic sources, including sparkers, rotary mechanical, hydraulic, air guns, and explosives, by their very nature produce high-frequencies. This is counter to the need for long signal transmission through rock. The patent pending SeismicPULSER{trademark} methodology has been developed for controlling otherwise high-frequency seismic sources to generate selectable low-frequency peak spectra applicable to many seismic applications. Specifically, we have demonstrated the application of a low-frequency sparker source which can be incorporated into a drill bit for Drill Bit Seismic While Drilling (SWD). To create the methodology of a controllable low-frequency sparker seismic source, it was necessary to learn how to maximize sparker efficiencies to couple to, and transmit through, rock with the study of sparker designs and mechanisms for (a) coupling the sparker-generated gas bubble expansion and contraction to the rock, (b) the effects of fluid properties and dynamics, (c) linear and non-linear acoustics, and (d) imparted force directionality. After extensive seismic modeling, the design of high-efficiency sparkers, laboratory high frequency sparker testing, and field tests were performed at the University of Texas Devine seismic test site. The conclusion of the field test was that extremely high power levels would be required to have the range required for deep, 15,000+ ft, high-temperature, high-pressure (HTHP) wells. Thereafter, more modeling and laboratory testing led to the discovery of a method to control a sparker that could generate low frequencies required for deep wells. The low frequency sparker was successfully tested at the Department of Energy Rocky Mountain Oilfield Test Center (DOE RMOTC) field test site in Casper, Wyoming. An 8-in diameter by 26-ft long SeismicPULSER{trademark} drill string tool was designed and manufactured by TII

  13. Midget Seismic in Sandbox Models

    Science.gov (United States)

    Krawczyk, C. M.; Buddensiek, M. L.; Philipp, J.; Kukowski, N.; Oncken, O.

    2008-12-01

    Analog sandbox simulation has been applied to study geological processes to provide qualitative and quantitative insights into specific geological problems. In nature, the structures, which are simulated in those sandbox models, are often inferred from seismic data. With the study introduced here, we want to combine the analog sandbox simulation techniques with seismic physical modeling of those sandbox models. The long-term objectives of this approach are (1) imaging of seismic and seismological events of actively deforming and static 3D analogue models, and (2) assessment of the transferability of the model data to field data in order to improve field data acquisition and interpretation according to the addressed geological problem. To achieve this objective, a new midget-seismic facility for laboratory use was designed and developed, comprising a seismic tank, a PC control unit including piezo-electric transducers, and a positioning system. The first experiments are aimed at studying the wave field properties of the piezo- transducers in order to investigate their feasibility for seismic profiling. The properties investigated are their directionality and the change of waveform due to their size (5-12 mm) compared to the wavelengths (material properties and the effects of wave propagation in an-/isotropic media by physical studies, before we finally start using different seismic imaging and processing techniques on static and actively deforming 3D analog models.

  14. Study on design of thrust blocks of large-scale ball mills with seismic loadings%地震载荷作用下大型球磨机止推块的抗震设计研究

    Institute of Scientific and Technical Information of China (English)

    刘普林; 郭勤涛; 姬建刚; 陈剑

    2011-01-01

    In order to study the anti-seismic performance of large-scale ball mills, the paper firstly establishes a finite element model of overall system composed of the ball mill barrel and the foundation. Then it finds the most dangerous conditions of earthquake, and respectively uses current national anti-seismic design code and Australian anti-seismic standards as the input stimulus to obtain the acceleration peak response of ball mills with seismic loadings in the finite element analysis software Nastran. In addition, the paper uses the peak response as the input loadings, establishes the finite element sub-model of the most dangerous parts of the ball mill, and further analyzes the contact strength of the dangerous parts. The analysis provides a theoretical basis for the anti-seismic structural design of large-scale ball mills and the overall anti-seismic design.%为了研究大型球磨机的抗震性能,首先建立了球磨机回转体和地基基础的整体系统有限元模型;寻找地震作用最危险工况,分别以我国现行抗震设计规范和澳大利亚抗震标准作为输入激励,在有限元分析软件Nastran中得到球磨机地震加速度峰值响应;然后,以该峰值响应作为输入载荷,建立了球磨机最危险部位的有限元子模型,进一步分析该危险部位的接触强度.该分析为大型球磨机抗震结构设计及整体抗震设计提供了理论依据.

  15. Thermodynamic analysis of SCW NPP cycles with thermo-chemical co-generation of hydrogen

    Energy Technology Data Exchange (ETDEWEB)

    Naidin, N.; Mokry, S.; Monichan, R.; Chophla, K.; Pioro, I. [Faculty of Energy Systems and Nuclear Science, Univ. of Ontario Inst. of Technology, Oshawa, Ontario (Canada)], E-mail: Maria.Naidin@mycampus.uoit.ca, Sarah.Mokry@mycampus.uoit.ca, Romson.Monichan@uoit.ca, Karan.Chophla@mycampus.uoit.ca, Igor.Pioro@uoit.ca; Naterer, G.; Gabriel, K. [Faculty of Engineering and Applied Science, Univ. of Ontario Inst. of Technology, Oshawa, Ontario (Canada)], E-mail: Greg.Naterer@uoit.ca, Kamiel.Gabriel@uoit.ca

    2009-07-01

    Research activities are currently conducted worldwide to develop Generation IV nuclear reactor concepts with the objective of improving thermal efficiency and increasing economic competitiveness of Generation IV Nuclear Power Plants (NPPs) compared to modern thermal power plants. The Super-Critical Water-cooled Reactor (SCWR) concept is one of the six Generation IV options chosen for further investigation and development in several countries including Canada and Russia. Water-cooled reactors operating at subcritical pressures (10 - 16 MPa) have provided a significant amount of electricity production for the past 50 years. However, the thermal efficiency of the current NPPs is not very high (30 - 35%). As such, more competitive designs, with higher thermal efficiencies, which will be close to that of modern thermal power plants (45 - 50%), need to be developed and implemented. Super-Critical Water (SCW) NPPs will have much higher operating parameters compared to current NPPs (i.e., steam pressures of about 25 MPa and steam outlet temperatures up to 625{sup o}C). Furthermore, SCWRs operating at higher temperatures can facilitate an economical co-generation of hydrogen through thermochemical cycles (particularly, the copper-chlorine cycle) or direct high-temperature electrolysis. The two SCW NPP cycles proposed by this paper are based on direct, regenerative, no-reheat and single-reheat configurations. As such, the main parameters and performance in terms of thermal efficiency of the SCW NPP concepts mentioned above are being analyzed. The cycles are generally comprised of: an SCWR, a SC turbine, one deaerator, ten feedwater heaters, and pumps. The SC turbine of the no-reheat cycle consists of one High-Pressure (HP) cylinder and two Low-Pressure (LP) cylinders. Alternatively, the SC turbine for the single-reheat cycle is comprised of one High-Pressure (HP) cylinder, one Intermediate-Pressure (IP) cylinder and two Low-Pressure (LP) cylinders. Since the single

  16. 优化设计输入和分析方法以提高核电厂抗震安全性%Optimize the design input and analysis methods to improve the seismic safety of nuclear power plants

    Institute of Scientific and Technical Information of China (English)

    张超琦; 杨建华

    2013-01-01

      日本福岛事故后核电厂抵御极端自然灾害能力受到广泛关注,世界上各个国家都积极开展相关研究,而地震一直是核电厂工程安全问题的主要威胁之一,因此核电厂的抗震安全性更是成为业界分析研究的重点。楼层反应谱作为核电厂系统、结构和部件抗震设计的输入,其计算分析是核电厂抗震分析的重要环节,其结果对于核电厂的抗震安全水平起着举足轻重的作用。本文以中国核电工程有限公司自主研发的三代机型ACP1000标准设计为例,通过介绍楼层反应谱的输入、分析过程和方法,来阐述合理确定符合国情的地震输入、采用先进的建模和分析方法,对完善核电厂的抗震设计、提高核电厂的抗震安全性具有重要意义。%The competence of resisting nature extreme disaster is widely concerned after Fukushima nu-clear incident in Japan. Many countries carry through investigation actively. The seismic is one of primary threat-ens for nuclear power plant safety. Therefore the seismic ability of nuclear power plants becomes the investiga-tive emphasis. The floor response spectra is the input of the seismic design for nuclear plant systems,structures and components,and the important part of the seismic design,which is holding the balance in nuclear plant seis-mic safety. In this paper we use the third generation nuclear power plant example that is ACP1000 normal design excogitated by the China Nuclear Power Engineering Co.,LTD. themselves to expatiate the reasonable seismic input and the advanced analysis method for China. Through introducing the input,the analysis process and the method about the ACP1000 floor response spectra are calculated. Then it has significant effect for improving the nuclear power plant seismic design and seismic safety.

  17. Development of Highly Survivable Power and Communication System for NPP Instruments under Severe Accident

    Energy Technology Data Exchange (ETDEWEB)

    Yoo, Seung J.; Gu, Beom W.; Nguyen, Duy T.; Choi, Bo H.; Rim, Chun T. [KAIST, Daejeon (Korea, Republic of); Lee, So I. [KHNP CRI, Daejeon (Korea, Republic of)

    2014-10-15

    According to the detail report from the Fukushima nuclear accident, the failure of conventional instruments is mainly due to the following reasons. 1) Insufficient backup battery capacity after the station black out (SBO) 2) The malfunction or damage of instruments due to the extremely harsh ambient condition after the severe accident 3) The cut-off of power and communication cable due to the physical shocks of hydrogen explosion after the severe accident Since the current equipment qualification (EQ) for the NPP instruments is based on the design basis accident such as loss of coolant accident (LOCA), conventional instruments, which are examined under EQ condition, cannot guarantee their normal operation during the severe accident. A 7m-long-distance wireless power transfer and a radio frequency (RF) communication were introduced with conventional wired system to increase a redundancy. A heat isolation box and a harness are adopted to provide a protection from the expected physical shocks such as missiles and drastic increase of ambient temperature and pressure. A detail design principle of the highly survivable power and communication system, which has 4 sub-systems of a DCRS wireless power transfer, a Zigbee wireless communication, a GFRP harness, and a passive type router with a fly back regulator, has been presented in this paper. Each sub-system has been designed to have a robust operation characteristic regardless of the estimated physical shocks after the severe accident.

  18. Designing a low-cost effective network for monitoring large scale regional seismicity in a soft-soil region (Alsace, France)

    Science.gov (United States)

    Bès de Berc, M.; Doubre, C.; Wodling, H.; Jund, H.; Hernandez, A.; Blumentritt, H.

    2015-12-01

    The Seismological Observatory of the North-East of France (ObSNEF) is developing its monitoring network within the framework of several projects. Among these project, RESIF (Réseau sismologique et géodésique français) allows the instrumentation of broad-band seismic stations, separated by 50-100 km. With the recent and future development of geothermal industrial projects in the Alsace region, the ObSNEF is responsible for designing, building and operating a dense regional seismic network in order to detect and localize earthquakes with both a completeness magnitude of 1.5 and no clipping for M6.0. The realization of the project has to be done prior to the summer 2016Several complex technical and financial constraints constitute such a projet. First, most of the Alsace Région (150x150 km2), particularly the whole Upper Rhine Graben, is a soft-soil plain where seismic signals are dominated by a high frequency noise level. Second, all the signals have to be transmitted in near real-time. And finally, the total cost of the project must not exceed $450,000.Regarding the noise level in Alsace, in order to make a reduction of 40 dB for frequencies above 1Hz, we program to instrument into 50m deep well with post-hole sensor for 5 stations out of 8 plane new stations. The 3 remaining would be located on bedrock along the Vosges piedmont. In order to be sensitive to low-magnitude regional events, we plan to install a low-noise short-period post-hole velocimeter. In order to avoid saturation for high potentiel local events (M6.0 at 10km), this velocimeter will be coupled with a surface strong-motion sensor. Regarding the connectivity, these stations will have no wired network, which reduces linking costs and delays. We will therefore use solar panels and a 3G/GPRS network. The infrastructure will be minimal and reduced to an outdoor box on a secured parcel of land. In addition to the data-logger, we will use a 12V ruggedized computer, hosting a seed-link server for near

  19. VIIRS Climate Raw Data Record (C-RDR) from Suomi NPP, Version 1

    Data.gov (United States)

    National Oceanic and Atmospheric Administration, Department of Commerce — The Suomi NPP Climate Raw Data Record (C-RDR) developed at the NOAA NCDC is an intermediate product processing level (NOAA Level 1b) between a Raw Data Record (RDR)...

  20. Assessment of NPP VIIRS Ocean Color Data Products: Hope and Risk

    Science.gov (United States)

    Turpie, Kevin R.; Meister, Gerhard; Eplee, Gene; Barnes, Robert A.; Franz, Bryan; Patt, Frederick S.; Robinson, Wayne d.; McClain, Charles R.

    2010-01-01

    For several years, the NASA/Goddard Space Flight Center (GSFC) NPP VIIRS Ocean Science Team (VOST) provided substantial scientific input to the NPP project regarding the use of Visible Infrared Imaging Radiometer Suite (VIIRS) to create science quality ocean color data products. This work has culminated into an assessment of the NPP project and the VIIRS instrument's capability to produce science quality Ocean Color data products. The VOST concluded that many characteristics were similar to earlier instruments, including SeaWiFS or MODIS Aqua. Though instrument performance and calibration risks do exist, it was concluded that programmatic and algorithm issues dominate concerns. Keywords: NPP, VIIRS, Ocean Color, satellite remote sensing, climate data record.

  1. The kinetics of aerosol particle formation and removal in NPP severe accidents

    Science.gov (United States)

    Zatevakhin, Mikhail A.; Arefiev, Valentin K.; Semashko, Sergey E.; Dolganov, Rostislav A.

    2016-06-01

    Severe Nuclear Power Plant (NPP) accidents are accompanied by release of a massive amount of energy, radioactive products and hydrogen into the atmosphere of the NPP containment. A valid estimation of consequences of such accidents can only be carried out through the use of the integrated codes comprising a description of the basic processes which determine the consequences. A brief description of a coupled aerosol and thermal-hydraulic code to be used for the calculation of the aerosol kinetics within the NPP containment in case of a severe accident is given. The code comprises a KIN aerosol unit integrated into the KUPOL-M thermal-hydraulic code. Some features of aerosol behavior in severe NPP accidents are briefly described.

  2. Design of an UML conceptual model and implementation of a GIS with metadata information for a seismic hazard assessment cooperative project.

    Science.gov (United States)

    Torres, Y.; Escalante, M. P.

    2009-04-01

    This work illustrates the advantages of using a Geographic Information System in a cooperative project with researchers of different countries, such as the RESIS II project (financed by the Norwegian Government and managed by CEPREDENAC) for seismic hazard assessment of Central America. As input data present different formats, cover distinct geographical areas and are subjected to different interpretations, data inconsistencies may appear and their management get complicated. To achieve data homogenization and to integrate them in a GIS, it is required previously to develop a conceptual model. This is accomplished in two phases: requirements analysis and conceptualization. The Unified Modeling Language (UML) is used to compose the conceptual model of the GIS. UML complies with ISO 19100 norms and allows the designer defining model architecture and interoperability. The GIS provides a frame for the combination of large geographic-based data volumes, with an uniform geographic reference and avoiding duplications. All this information contains its own metadata following ISO 19115 normative. In this work, the integration in the same environment of active faults and subduction slabs geometries, combined with the epicentres location, has facilitated the definition of seismogenetic regions. This is a great support for national specialists of different countries to make easier their teamwork. The GIS capacity for making queries (by location and by attributes) and geostatistical analyses is used to interpolate discrete data resulting from seismic hazard calculations and to create continuous maps as well as to check and validate partial results of the study. GIS-based products, such as complete, homogenised databases and thematic cartography of the region, are distributed to all researchers, facilitating cross-national communication, the project execution and results dissemination.

  3. Observation and modeling of NPP for Pinus elliottii plantation in subtropical China

    Institute of Scientific and Technical Information of China (English)

    2008-01-01

    Based on the stem analysis of 59 individuals of Pinus elliottii in combination with tree biomass models, we calculated annual biomass increment of forest plots at Qianyanzhou Ecological Station, Chinese Academy of Sciences in subtropical China. In addition, canopy layer and community NPP were calcu- lated based on 12 years’ litter fall data. NPP of the 21-year-old forest was estimated by using the BIOME BGC model; and both measured NPP and estimated NPP were compared with flux data. Community biomass was 10574 g·m-2; its distribution patterns in tree layer, shrub layer, herbaceous layer, tree root, herbaceous and shrub roots and fine roots were 7542, 480, 239, 1810, 230, 274 and 239 g·m-2, respectively. From 1999 to 2004, the average annual growth rate and litter fall were 741 g·m-2·a-1 (381.31 gC·m-2·a-1) and 849 g·m?2·a?1 (463 gC·m-2·a-1), respectively. There was a significant corre- lation between annual litter fall and annual biomass increment; and the litter fall was 1.19 times the biomass increment of living trees. From 1985 to 2005, average NPP and GPP values based on BGC modeling were 630.88 (343.31 - 906.42 gC·m-2·a-1) and 1 800 gC·m-2·a-1 (1351.62 - 2318.26 gC·m-2·a-1). Regression analysis showed a linear relationship (R2=0.48) between the measured and simulated tree layer NPP values. NPP accounted for 30.2% (25.6%-32.9%) of GPP, while NEP ac- counted for 57.5% (48.1%-66.5%) of tree-layer NPP and 41.74% (37%-52%) of stand NPP. Soil respi- ration accounted for 77.0% of measured tree NPP and 55.9% of the measured stand NPP. NEE based on eddy covariance method was 12.97% higher than the observed NEP.

  4. Monitoring Bio-Optical Processes Using NPP-VIIRS and MODIS-Aqua Ocean Color Products

    Science.gov (United States)

    2013-01-01

    Same day ocean color products from the S-NPP and MODIS provide for a new capability to monitor changes in the bio - optical processes occurring in...coastal waters. The combined use of multiple looks per day from several sensors can be used to follow the water mass changes of bio -optical properties...day to resolve bio - optical processes. We examine how these changes in bio -optical properties can be monitored using the NPP and MODIS ocean color

  5. Seismic isolation for Advanced LIGO

    CERN Document Server

    Abbott, R; Allen, G; Cowley, S; Daw, E; Debra, D; Giaime, J; Hammond, G; Hammond, M; Hardham, C; How, J; Hua, W; Johnson, W; Lantz, B; Mason, K; Mittleman, R; Nichol, J; Richman, S; Rollins, J; Shoemaker, D; Stapfer, G; Stebbins, R

    2002-01-01

    The baseline design concept for a seismic isolation component of the proposed 'Advanced LIGO' detector upgrade has been developed with proof-of-principle experiments and computer models. It consists of a two-stage in-vacuum active isolation platform that is supported by an external hydraulic actuation stage. Construction is underway for prototype testing of a full-scale preliminary design.

  6. 弹塑性钢减隔震支座在桥梁抗震设计中的应用%Application of Elasto-Plastic Steel Seismic Isolators to Bridge Anti-Seismic Design

    Institute of Scientific and Technical Information of China (English)

    高山; 彭泽友; 史春娟; 王永祥

    2015-01-01

    为了给桥梁抗震设计提供参考,以减轻桥梁结构在地震中遭受的损伤,介绍一种弹塑性钢减隔震支座(NDQZ)的结构特点及其减隔震原理,并以(83+140+83) m双塔双索面预应力混凝土斜拉桥为实例进行减隔震分析。采用有限元分析软件SAP2000建立全桥有限元模型,在E2地震状态下分别进行非减隔震支座桥梁和NDQZ支座桥梁地震动力时程分析。结果表明:NDQZ支座可实现全桥协同抗震,减隔震效果良好;采用NDQZ支座后,桥梁前3阶自振周期平均延长133%,在顺桥向和横桥向墩底弯矩分别减小了40%和83%,墩底剪力分别减小了39%和70%;承台底弯矩分别减小了39%和74%,承台底剪力分别减小了34%和60%;弯矩和剪力分布均匀。%To provide reference for bridge anti‐seismic design and reduce the damage that bridge suffers in earthquakes ,the structural features and principles of vibration mitigation and iso‐lation of a kind of elasto‐plastic steel seismic isolators (NDQZ)is introduced .A two‐pylon pres‐tressed concrete cable‐stayed bridge with span arrangement of (83+140+83) m and with double cable planes is cited as an example to conduct vibration mitigation and isolation analysis .T he finite element software SAP2000 was used to establish the finite element model of the whole bridge ,to carry out time‐history analysis of the bridge with bearings incapable of vibration mitigation and iso‐lation effect and the bridge with NDQZ under the E2 earthquake condition respectively .The re‐sults of the analysis indicate that the NDQZ bearings can realize the effect of the w hole‐bridge col‐laborative vibration resistance ,displaying sound vibration mitigation and isolation effect .When the NDQZ bearings are used ,the first three orders of bridge natural vibration period averagely ex‐tends 133% .The bending moments in the base of the piers along the bridge length

  7. Development of NPP Safety Requirements into Kenya's Grid Codes

    Energy Technology Data Exchange (ETDEWEB)

    Ndirangu, Nguni James; Koo, Chang Choong [KEPCO International Nuclear Graduate School, Ulsan (Korea, Republic of)

    2015-10-15

    As presently drafted, Kenya's grid codes do not contain any NPP requirements. Through case studies of selected grid codes, this paper will study frequency, voltage and fault ride through requirements for NPP connection and operation, and offer recommendation of how these requirements can be incorporated in the Kenya's grid codes. Voltage and frequency excursions in Kenya's grid are notably frequently outside the generic requirement and the values observed by the German and UK grid codes. Kenya's grid codes require continuous operation for ±10% of nominal voltage and 45.0 to 52Hz on the grid which poses safety issues for an NPP. Considering stringent NPP connection to grid and operational safety requirements, and the importance of the TSO to NPP safety, more elaborate requirements need to be documented in the Kenya's grid codes. UK and Germany have a history of meeting high standards of nuclear safety and it is therefore recommended that format like the one in Table 1 to 3 should be adopted. Kenya's Grid code considering NPP should have: • Strict rules for voltage variation, that is, -5% to +10% of the nominal voltage • Strict rules for frequency variation, that is, 48Hz to 52Hz of the nominal frequencyand.

  8. Westinghouse Fuel Assemblies Performance after Operation in South-Ukraine NPP Mixed Core

    Energy Technology Data Exchange (ETDEWEB)

    Abdullayev, A. M.; Kulish, G. V.; Slyeptsov, O.; Slyeptsov, S.; Aleshin, Y.; Sparrow, S.; Lashevych, P.; Sokolov, D.; Latorre, Richard

    2013-09-14

    The evaluation of WWER-1000 Westinghouse fuel performance was done using the results of post–irradiation examinations of six LTAs and the WFA reload batches that have operated normally in mixed cores at South-Ukraine NPP, Unit-3 and Unit-2. The data on WFA/LTA elongation, FR growth and bow, WFA bow and twist, RCCA drag force and drag work, RCCA drop time, FR cladding integrity as well as the visual observation of fuel assemblies obtained during the 2006-2012 outages was utilized. The analysis of the measured data showed that assembly growth, FR bow, irradiation growth, and Zr-1%Nb grid and ZIRLO cladding corrosion lies within the design limits. The RCCA drop time measured for the LTA/WFA is about 1.9 s at BOC and practically does not change at EOC. The measured WFA bow and twist, and data of drag work on RCCA insertion showed that the WFA deformation in the mixed core is mostly controlled by the distortion of Russian FAs (TVSA) having the higher lateral stiffness. The visual inspection of WFAs carried out during the 2012 outages revealed some damage to the Zr-1%Nb grid outer strap for some WFAs during the loading sequence. The performed fundamental investigations allowed identifying the root cause of grid outer strap deformation and proposing the WFA design modifications for preventing damage to SG at a 225 kg handling trip limit.

  9. Analysis of Steam Generators Corrosion Products from Slovak NPP Bohunice

    Directory of Open Access Journals (Sweden)

    Jarmila Degmová

    2012-01-01

    Full Text Available One of the main goals of the nuclear industry is to increase the nuclear safety and reliability of nuclear power plants (NPPs. As the steam generator (SG is the most corrosion sensitive component of NPPs, it is important to analyze the corrosion process and optimize its construction materials to avoid damages like corrosion cracking. For this purpose two different kinds of SGs and its feed water distributing systems from the NPP Jaslovske Bohunice were studied by nondestructive Mössbauer spectroscopy. The samples were scraped from the surface and analyzed in transmission geometry. Magnetite and hematite were found to be the main components in the corrosion layers of both SGs. Dependant of the material the SG consisted of, and the location in the system where the samples were taken, the ratios between magnetite and hematite and the paramagnetic components were different. The obtained results can be used to improve corrosion safety of the VVER-440 secondary circuit as well as to optimize its water chemistry regime.

  10. Derived Land Surface Emissivity From Suomi NPP CrIS

    Science.gov (United States)

    Zhou, Daniel K.; Larar, Allen M.; Liu, Xu

    2012-01-01

    Presented here is the land surface IR spectral emissivity retrieved from the Cross-track Infrared Sounder (CrIS) measurements. The CrIS is aboard the Suomi National Polar-orbiting Partnership (NPP) satellite launched on October 28, 2011. We describe the retrieval algorithm, demonstrate the surface emissivity retrieved with CrIS measurements, and inter-comparison with the Infrared Atmospheric Sounding Interferometer (IASI) emissivity. We also demonstrate that surface emissivity from satellite measurements can be used in assistance of monitoring global surface climate change, as a long-term measurement of IASI and CrIS will be provided by the series of EUMETSAT MetOp and US Joint Polar Satellite System (JPSS) satellites. Monthly mean surface properties are produced using last 5-year IASI measurements. A temporal variation indicates seasonal diversity and El Nino/La Nina effects not only shown on the water but also on the land. Surface spectral emissivity and skin temperature from current and future operational satellites can be utilized as a means of long-term monitoring of the Earth's environment. CrIS spectral emissivity are retrieved and compared with IASI. The difference is small and could be within expected retrieval error; however it is under investigation.

  11. Complexity in Design-Driven Innovation: A Case Study of Knowledge Transfer Flow in Subsea Seismic Sensor Technology and Design Education

    Science.gov (United States)

    Pavel, Nenad; Berg, Arild

    2015-01-01

    To the extent previously claimed, concept exploration is not the key to product innovation. However, companies that are design-focused are twice as innovative as those that are not. To study design-driven innovation and its occurrence in design education, two case studies are conducted. The first is an example of design practice which includes…

  12. Seismic Isolation Working Meeting Gap Analysis Report

    Energy Technology Data Exchange (ETDEWEB)

    Coleman, Justin [Idaho National Lab. (INL), Idaho Falls, ID (United States); Sabharwall, Piyush [Idaho National Lab. (INL), Idaho Falls, ID (United States)

    2014-09-01

    The ultimate goal in nuclear facility and nuclear power plant operations is operating safety during normal operations and maintaining core cooling capabilities during off-normal events including external hazards. Understanding the impact external hazards, such as flooding and earthquakes, have on nuclear facilities and NPPs is critical to deciding how to manage these hazards to expectable levels of risk. From a seismic risk perspective the goal is to manage seismic risk. Seismic risk is determined by convolving the seismic hazard with seismic fragilities (capacity of systems, structures, and components (SSCs)). There are large uncertainties associated with evolving nature of the seismic hazard curves. Additionally there are requirements within DOE and potential requirements within NRC to reconsider updated seismic hazard curves every 10 years. Therefore opportunity exists for engineered solutions to manage this seismic uncertainty. One engineered solution is seismic isolation. Current seismic isolation (SI) designs (used in commercial industry) reduce horizontal earthquake loads and protect critical infrastructure from the potentially destructive effects of large earthquakes. The benefit of SI application in the nuclear industry is being recognized and SI systems have been proposed, in the American Society of Civil Engineers (ASCE) 4 standard, to be released in 2014, for Light Water Reactors (LWR) facilities using commercially available technology. However, there is a lack of industry application to the nuclear industry and uncertainty with implementing the procedures outlined in ASCE-4. Opportunity exists to determine barriers associated with implementation of current ASCE-4 standard language.

  13. Infrasound Generation from the HH Seismic Hammer.

    Energy Technology Data Exchange (ETDEWEB)

    Jones, Kyle Richard

    2014-10-01

    The HH Seismic hammer is a large, "weight-drop" source for active source seismic experiments. This system provides a repetitive source that can be stacked for subsurface imaging and exploration studies. Although the seismic hammer was designed for seismological studies it was surmised that it might produce energy in the infrasonic frequency range due to the ground motion generated by the 13 metric ton drop mass. This study demonstrates that the seismic hammer generates a consistent acoustic source that could be used for in-situ sensor characterization, array evaluation and surface-air coupling studies for source characterization.

  14. Issues on the seismic performance of embankments

    DEFF Research Database (Denmark)

    Zania, Varvara; Tsompanakis, Y.; Psarropoulos, P.N.

    2011-01-01

    Seismic vulnerability of embankments with reinforcement at their base is strongly related to the slip displacements, which may accumulate along the interface between soil and geosynthetic. The inertial accelerations within the embankment, due to the propagation of seismic waves and the subsequent...... performed. The stability of the soil mass was estimated in terms of seismic slip deformations along low-shear-strength interfaces, while the response of the embankment is assessed through the acceleration time histories at the top surface of the soil. This investigation presents also the effect of the most......’t be neglected during the seismic design of embankments....

  15. Infrasound Generation from the HH Seismic Hammer.

    Energy Technology Data Exchange (ETDEWEB)

    Jones, Kyle Richard

    2014-10-01

    The HH Seismic hammer is a large, "weight-drop" source for active source seismic experiments. This system provides a repetitive source that can be stacked for subsurface imaging and exploration studies. Although the seismic hammer was designed for seismological studies it was surmised that it might produce energy in the infrasonic frequency range due to the ground motion generated by the 13 metric ton drop mass. This study demonstrates that the seismic hammer generates a consistent acoustic source that could be used for in-situ sensor characterization, array evaluation and surface-air coupling studies for source characterization.

  16. Load Calculation for Wind Turbines Under the Condition of Anti-seismic Design%抗震设计条件下的风电机组载荷计算

    Institute of Scientific and Technical Information of China (English)

    李声茂; 赵伟

    2013-01-01

      按照GB50011-2010建筑抗震设计规范的要求,对有抗震设计要求的风场所用的风电机组进行地震载荷计算。根据中国风场的地质条件,用GB2010规范生成设计目标反应谱,再利用三角级数法将之合成为地震动加速度时程,考虑双向水平地震作用并进行时域分析。结合工程实例,借助Bladed软件对项目所用风电机组进行地震载荷计算,对比设计载荷和地震载荷,结果表明,地震时风电机组载荷大幅增大,但没有超过风电机组设计极限载荷,项目所用风电机组安全可靠。%According to the requirement of GB50011-2010, the seismic load calculation was carried out for the wind turbines which request for anti-seismic design. Based on the special geological conditions of wind farms in China and the requirements of GB50011-2010, the aim design acceleration response spectrum was generated, and then transformed to seismic acceleration time history using trigonometric series method. e domain analysis was carried on considering the bi-directional seismic action. A project, and the so ware Bladed was used to simulate the seismic of wind turbines, the design and seismic load of wind turbines were compared nally. e results showed that the seismic load of wind turbines was increased, but didn' t exceed the limit of design load of wind turbines. therefore, the wind turbine in this project was safe and reliable.

  17. Final Report: Seismic Hazard Assessment at the PGDP

    Energy Technology Data Exchange (ETDEWEB)

    Wang, Zhinmeng [KY Geological Survey, Univ of KY

    2007-06-01

    Selecting a level of seismic hazard at the Paducah Gaseous Diffusion Plant for policy considerations and engineering design is not an easy task because it not only depends on seismic hazard, but also on seismic risk and other related environmental, social, and economic issues. Seismic hazard is the main focus. There is no question that there are seismic hazards at the Paducah Gaseous Diffusion Plant because of its proximity to several known seismic zones, particularly the New Madrid Seismic Zone. The issues in estimating seismic hazard are (1) the methods being used and (2) difficulty in characterizing the uncertainties of seismic sources, earthquake occurrence frequencies, and ground-motion attenuation relationships. This report summarizes how input data were derived, which methodologies were used, and what the hazard estimates at the Paducah Gaseous Diffusion Plant are.

  18. SEISMIC GEOLOGY

    Institute of Scientific and Technical Information of China (English)

    2009-01-01

    <正>20091465 Cai Xuelin(College of Earth Sciences,Chengdu University of Technology,Chengdu 610059,China);Cao Jiamin Preliminary Study on the 3-D Crust Structure for the Longmen Lithosphere and the Genesis of the Huge Wenchuan Earthquake,Sichuan Province,China(Journal of Chengdu University of Technology,ISSN1671-9727,CN51-1634/N,35(4),2008,p.357-365,8 illus.,39 refs.)Key words:deep-seated structures,large earthquakes,Longmenshan Fracture ZoneBased on a structural analysis of many seismic sounding profiles,there are two fault systems in Longmen collisional orogenic belt,Sichuan Province,China.They are both different obviously and correlative closely.One is shallow fault system composed mainly of brittle shear zones in surface crust,and the other is deep fault system composed mainly of crust-mantle ductile shear zones cutting Moho discontinuity.Based on the result of researching geological structure and seismic sounding profiles,

  19. 基于两水平设防的连续梁桥抗震性能分析%Seismic Performance Analysis of Continuous Girder Bridge Based on Two-level Design Approach

    Institute of Scientific and Technical Information of China (English)

    邓小伟

    2012-01-01

    According to the new ideas and new methods by guidelines for seismic design of highway bridges (JTG / T B02-01-2008) , with the background of a continuous girder bridge in the area of 7 degree earthquake intensity, an elastic-plastic finite element model is established for dynamic characteristics analysis, seismic response spectrum analysis and nonlinear time history analysis, to reveal the force and deformation under earthquake action of two levels. Furthermore, the seismic performance is evaluated to provide a reference for seismic design of bridges.%根据《公路桥梁抗震设计细则》(JTG/T B02—01—2008)中的抗震设防新理念和新方法,以Ⅶ度区某连续梁桥为工程背景,建立了弹塑性有限元模型,依次进行了动力特性分析、地震反应谱分析和非线性时程分析,揭示了两级地震作用下桥梁的受力及变形情况,并对桥梁的抗震性能进行了评价,可供桥梁抗震设计参考.

  20. Seismic risk perception in Italy

    Science.gov (United States)

    Crescimbene, Massimo; La Longa, Federica; Camassi, Romano; Pino, Nicola Alessandro; Peruzza, Laura

    2014-05-01

    Risk perception is a fundamental element in the definition and the adoption of preventive counter-measures. In order to develop effective information and risk communication strategies, the perception of risks and the influencing factors should be known. This paper presents results of a survey on seismic risk perception in Italy conducted from January 2013 to present . The research design combines a psychometric and a cultural theoretic approach. More than 7,000 on-line tests have been compiled. The data collected show that in Italy seismic risk perception is strongly underestimated; 86 on 100 Italian citizens, living in the most dangerous zone (namely Zone 1), do not have a correct perception of seismic hazard. From these observations we deem that extremely urgent measures are required in Italy to reach an effective way to communicate seismic risk. Finally, the research presents a comparison between groups on seismic risk perception: a group involved in campaigns of information and education on seismic risk and a control group.

  1. The development on seismic design and evaluation of CGNPC after Fukushima accident%福岛核事故后中国广东核电集团核电厂抗震设计和评估进展

    Institute of Scientific and Technical Information of China (English)

    毛庆; 吴应喜; 张健; 孟阿军; 张涛; 杨春菊; 刘芳

    2013-01-01

      本文介绍了核电站抗震设计要求、在建和运行核电站的抗震设计情况以及运行核电站遭遇地震灾害的情况,简述了福岛核事故后世界各国核电站在抗震方面采取的措施,针对中国广东核电集团在福岛核事故后的行动进行了详细介绍,并提出了新建核电厂在抗震设计和评估方面的策略,以期通过技术手段持续提升核电站的抗震能力。%This paper introduced the seismic design requirements of nuclear power plant,the seismic de-sign situation of the unit in construction or in service,and the serious consequence impacted by earthquake. Then,it described in brief the measures on seismic analysis taken by countries who own nuclear power plants in the world after the Fukushima nuclear accident,and gave a particular introduction about the improvement taken by China Guangdong Nuclear Power Holding Co. Ltd. Finally,this paper presented some steps for the new nucle-ar power plants at the seismic design and evaluation to enhance the seismic capacity of nuclear power plants through technical means.

  2. Fukushima Daiichi accident as a stress test for the national system for the protection of the public in event of severe accident at NPP

    Directory of Open Access Journals (Sweden)

    V.A. Kutkov

    2017-03-01

    Full Text Available It is proposed that the circumstances of the Fukushima Daiichi nuclear accident on 11 March 2011 in Japan should be used as the framework for the stress test of the national system for the protection of public in the beyond design extension conditions at NPP. Stress tests of the public protection strategy show to what extent the national system is stable under the most unfavorable NPP conditions and give an understanding of the potential vulnerabilities and the ways to resolve them. A definition of the Fukushima stress test model has been provided, and the actions undertaken by Japanese authorities under the conditions of the Fukushima Daiichi accident have been considered as the response to this stress test. The stress test has revealed major vulnerabilities in the strategy for the protection of public in the event of an accident at an NPP, which was successfully proven many times by over a hundred exercises at different levels. The stress test showed that the principal vulnerability of protection strategy being in use in Japan in 2011 was the reliance on computer systems in the assessment of the emergency exposure for decision-making during the emergency response phase. It is proposed, that the Fukushima stress test should be used to identify the vulnerabilities in the Russian Federation's strategy for the protection of public in the event of a nuclear accident and to use the lessons learnt from the test results to perfect this strategy.

  3. Nitrogen Limitation is Reducing the Enhancement of NPP by Elevated CO2 in a Deciduous Forest

    Energy Technology Data Exchange (ETDEWEB)

    Norby, Richard J [ORNL; Warren, Jeffrey [ORNL; Iversen, Colleen M [ORNL; Medlyn, Belinda [Macquarie University; McMurtrie, Ross [University of New South Wales; Hoffman, Forrest M [ORNL

    2008-01-01

    Accurate model representation of the long-term response of forested ecosystems to elevated atmospheric CO2 concentrations (eCO2) is important for predictions of future concentrations of CO2. For biogeochemical models that predict the response of net primary productivity (NPP) to eCO2, free-air CO2 enrichment (FACE) experiments provide the only source of data for comparison. A synthesis of forest FACE experiments reported a 23% increase in NPP in eCO2, and this result has been used as a model benchmark. Here, we provide new evidence from a FACE experiment in a deciduous forest in Tennessee that N limitation has significantly reduced the stimulation of NPP by eCO2, consistent with predictions from ecosystem and global models that incorporate N feedbacks. The Liquidambar styraciflua stand has been exposed to current ambient atmospheric CO2 or air enriched with CO2 to 550 ppm since 1998. Results from the first 6 years of the experiment indicated that NPP was significantly enhanced by eCO2 and that this was a consistent and sustained response. Now, with 10 years of data, our analysis must be revised. The response of NPP to eCO2 has declined from 24% in 2001-2003 to 9% in 2007. The diminishing response to eCO2 since 2004 coincides with declining NPP in ambient CO2 plots. Productivity of this forest stand is limited by N availability, and the steady decline in forest NPP is closely related to changes in the N economy, as evidenced by declining foliar N concentrations. There is a strong linear relationship between foliar [N] and NPP, and the steeper slope in eCO2 indicates that the NPP response to eCO2 should diminish as foliar N declines. Increased fine-root production and root proliferation deeper in the soil have sustained N uptake, but not to an extent sufficient to benefit aboveground production. The mechanistic basis of the N effect on NPP resides in the photosynthetic machinery. The linear relationships between Jmax and Vcmax with foliar [N] did not change from 1998

  4. Nitrogen Limitation is Reducing the Enhancement of NPP by Elevated CO2 in a Deciduous Forest

    Science.gov (United States)

    Norby, R. J.; Warren, J. M.; Iversen, C. M.; Medlyn, B. E.; McMurtrie, R. E.; Hoffman, F. M.

    2008-12-01

    Accurate model representation of the long-term response of forested ecosystems to elevated atmospheric CO2 concentrations (eCO2) is important for predictions of future concentrations of CO2. For biogeochemical models that predict the response of net primary productivity (NPP) to eCO2, free-air CO2 enrichment (FACE) experiments provide the only source of data for comparison. A synthesis of forest FACE experiments reported a 23% increase in NPP in eCO2, and this result has been used as a model benchmark. Here, we provide new evidence from a FACE experiment in a deciduous forest in Tennessee that N limitation has significantly reduced the stimulation of NPP by eCO2, consistent with predictions from ecosystem and global models that incorporate N feedbacks. The Liquidambar styraciflua stand has been exposed to current ambient atmospheric CO2 or air enriched with CO2 to 550 ppm since 1998. Results from the first 6 years of the experiment indicated that NPP was significantly enhanced by eCO2 and that this was a consistent and sustained response. Now, with 10 years of data, our analysis must be revised. The response of NPP to eCO2 has declined from 24% in 2001-2003 to 9% in 2007. The diminishing response to eCO2 since 2004 coincides with declining NPP in ambient CO2 plots. Productivity of this forest stand is limited by N availability, and the steady decline in forest NPP is closely related to changes in the N economy, as evidenced by declining foliar N concentrations. There is a strong linear relationship between foliar [N] and NPP, and the steeper slope in eCO2 indicates that the NPP response to eCO2 should diminish as foliar N declines. Increased fine-root production and root proliferation deeper in the soil have sustained N uptake, but not to an extent sufficient to benefit aboveground production. The mechanistic basis of the N effect on NPP resides in the photosynthetic machinery. The linear relationships between Jmax and Vcmax with foliar [N] did not change from 1998

  5. Romanian Educational Seismic Network Project

    Science.gov (United States)

    Tataru, Dragos; Ionescu, Constantin; Zaharia, Bogdan; Grecu, Bogdan; Tibu, Speranta; Popa, Mihaela; Borleanu, Felix; Toma, Dragos; Brisan, Nicoleta; Georgescu, Emil-Sever; Dobre, Daniela; Dragomir, Claudiu-Sorin

    2013-04-01

    Romania is one of the most active seismic countries in Europe, with more than 500 earthquakes occurring every year. The seismic hazard of Romania is relatively high and thus understanding the earthquake phenomena and their effects at the earth surface represents an important step toward the education of population in earthquake affected regions of the country and aims to raise the awareness about the earthquake risk and possible mitigation actions. In this direction, the first national educational project in the field of seismology has recently started in Romania: the ROmanian EDUcational SEISmic NETwork (ROEDUSEIS-NET) project. It involves four partners: the National Institute for Earth Physics as coordinator, the National Institute for Research and Development in Construction, Urban Planning and Sustainable Spatial Development " URBAN - INCERC" Bucharest, the Babeş-Bolyai University (Faculty of Environmental Sciences and Engineering) and the software firm "BETA Software". The project has many educational, scientific and social goals. The main educational objectives are: training students and teachers in the analysis and interpretation of seismological data, preparing of several comprehensive educational materials, designing and testing didactic activities using informatics and web-oriented tools. The scientific objective is to introduce into schools the use of advanced instruments and experimental methods that are usually restricted to research laboratories, with the main product being the creation of an earthquake waveform archive. Thus a large amount of such data will be used by students and teachers for educational purposes. For the social objectives, the project represents an effective instrument for informing and creating an awareness of the seismic risk, for experimentation into the efficacy of scientific communication, and for an increase in the direct involvement of schools and the general public. A network of nine seismic stations with SEP seismometers

  6. Validation of S-NPP VIIRS Sea Surface Temperature Retrieved from NAVO

    Directory of Open Access Journals (Sweden)

    Qianguang Tu

    2015-12-01

    Full Text Available The validation of sea surface temperature (SST retrieved from the new sensor Visible Infrared Imaging Radiometer Suite (VIIRS onboard the Suomi National Polar-Orbiting Partnership (S-NPP Satellite is essential for the interpretation, use, and improvement of the new generation SST product. In this study, the magnitude and characteristics of uncertainties in S-NPP VIIRS SST produced by the Naval Oceanographic Office (NAVO are investigated. The NAVO S-NPP VIIRS SST and eight types of quality-controlled in situ SST from the National Oceanic and Atmospheric Administration in situ Quality Monitor (iQuam are condensed into a Taylor diagram. Considering these comparisons and their spatial coverage, the NAVO S-NPP VIIRS SST is then validated using collocated drifters measured SST via a three-way error analysis which also includes SST derived from Moderate Resolution Imaging Spectro-radiometer (MODIS onboard AQUA. The analysis shows that the NAVO S-NPP VIIRS SST is of high accuracy, which lies between the drifters measured SST and AQUA MODIS SST. The histogram of NAVO S-NPP VIIRS SST root-mean-square error (RMSE shows normality in the range of 0–0.6 °C with a median of ~0.31 °C. Global distribution of NAVO VIIRS SST shows pronounced warm biases up to 0.5 °C in the Southern Hemisphere at high latitudes with respect to the drifters measured SST, while near-zero biases are observed in AQUA MODIS. It means that these biases may be caused by the NAVO S-NPP VIIRS SST retrieval algorithm rather than the nature of the SST. The reasons and correction for this bias need to be further studied.

  7. Length Effect on the Thermal Performance of a Heat Pipe for NPP Decay Heat Removal

    Energy Technology Data Exchange (ETDEWEB)

    Seo, Joseph; Lee, Jae Young [Handong Global University, Pohang (Korea, Republic of)

    2015-10-15

    After Fukushima accident, importance and necessity of passive safety for nuclear power plant have been emphasized. Due to its passive characteristic, heat pipe is seriously considered as an alternative device of the active safety system for removing decay heat from the reactor core. Among many possible applications of heat pipe in NPP, we considered the application to the control rod. In the situation of SBO(Station Black Out) due to BDBA(Beyond Design Basis Accident) in a PWR, control rods are dropped in to nuclear reactor core automatically. Thus, it is expected that applying heat pipe function to control rod can enhance reactor safety by removing decay heat of fuel assembly. Considering the height of the control rod, L/D of the heat pipe would be larger than 400 if the given diameter is assumed to be similar to the diameter of the control rod. Thus, it may not be the matter for small heat pipes, it is necessary to consider the effects of L/D for the large L/D heat pipes. There for, length effect on the thermal performance of heat pipe for decay heat removal was experimentally investigated in this study. Through this study, the L/D effect on the thermal performance of the large L/D heat pipe for nuclear reactor has been studied.

  8. Systems engineering approach for the reuse of metallic waste from NPP decommissioning and dose evaluation

    Energy Technology Data Exchange (ETDEWEB)

    Seo, Hyung Woo; Kim, Chang Lak [KEPCO International Nuclear Graduate School, Ulsan (Korea, Republic of)

    2017-03-15

    The oldest commercial reactor in South Korea, Kori-1 Nuclear Power Plant (NPP), will be shut down in 2017. Proper treatment for decommissioning wastes is one of the key factors to decommission a plant successfully. Particularly important is the recycling of clearance level or very low level radioactively contaminated metallic wastes, which contributes to waste minimization and the reduction of disposal volume. The aim of this study is to introduce a conceptual design of a recycle system and to evaluate the doses incurred through defined work flows. The various architecture diagrams were organized to define operational procedures and tasks. Potential exposure scenarios were selected in accordance with the recycle system, and the doses were evaluated with the RESRAD-RECYCLE computer code. By using this tool, the important scenarios and radionuclides as well as impacts of radionuclide characteristics and partitioning factors are analyzed. Moreover, dose analysis can be used to provide information on the necessary decontamination, radiation protection process, and allowable concentration limits for exposure scenarios.

  9. An overview of Suomi NPP VIIRS calibration maneuvers

    Science.gov (United States)

    Butler, James J.; Xiong, Xiaoxiong; Barnes, Robert A.; Patt, Frederick S.; Sun, Junqiang; Chiang, Kwofu

    2012-09-01

    The first Visible Infrared Imager Radiometer Suite (VIIRS) instrument was successfully launched on-board the Suomi National Polar-orbiting Partnership (SNPP) spacecraft on October 28, 2011. Suomi NPP VIIRS observations are made in 22 spectral bands, from the visible (VIS) to the long-wave infrared (LWIR), and are used to produce 22 Environmental Data Records (EDRs) with a broad range of scientific applications. The quality of these VIIRS EDRs strongly depends on the quality of its calibrated and geo-located Sensor Date Records (SDRs). Built with a strong heritage to the NASA's EOS MODerate resolution Imaging Spectroradiometer (MODIS) instrument, the VIIRS is calibrated on-orbit using a similar set of on-board calibrators (OBC), including a solar diffuser (SD) and solar diffuser stability monitor (SDSM) system for the reflective solar bands (RSB) and a blackbody (BB) for the thermal emissive bands (TEB). Onorbit maneuvers of the SNPP spacecraft provide additional calibration and characterization data from the VIIRS instrument which cannot be obtained pre-launch and are required to produce the highest quality SDRs. These include multiorbit yaw maneuvers for the characterization of SD and SDSM screen transmission, quasi-monthly roll maneuvers to acquire lunar observations to track sensor degradation in the visible through shortwave infrared, and a driven pitch-over maneuver to acquire multiple scans of deep space to determine TEB response versus scan angle (RVS). This paper provides an overview of these three SNPP calibration maneuvers. Discussions are focused on their potential calibration and science benefits, pre-launch planning activities, and on-orbit scheduling and implementation strategies. Results from calibration maneuvers performed during the Intensive Calibration and Validation (ICV) period for the VIIRS sensor are illustrated. Also presented in this paper are lessons learned regarding the implementation of calibration spacecraft maneuvers on follow

  10. An initial assessment of Suomi NPP VIIRS vegetation index EDR

    Science.gov (United States)

    Vargas, M.; Miura, T.; Shabanov, N.; Kato, A.

    2013-11-01

    The Suomi National Polar-orbiting Partnership (S-NPP) satellite with Visible/Infrared Imager/Radiometer Suite (VIIRS) onboard was launched in October 2011. VIIRS is the primary instrument for a suite of Environmental Data Records (EDR), including Vegetation Index (VI) EDR, for weather forecasting and climate research. The VIIRS VI EDR operational product consists of the Top of the Atmosphere (TOA) Normalized Difference Vegetation Index (NDVI), the Top of the Canopy (TOC) Enhanced Vegetation Index (EVI), and per-pixel product quality information. In this paper, we report results of our assessment of the early VIIRS VI EDR (beta quality) using Aqua MODIS and NOAA-18 AVHRR/3 as a reference for May 2012 to March 2013. We conducted two types of analyses focused on an assessment of physical (global scale) and radiometric (regional scale) performances of VIIRS VI EDR. Both TOA NDVI and TOC EVI of VIIRS showed spatial and temporal trends consistent with the MODIS counterparts, whereas VIIRS TOA NDVI was systematically higher than that of AVHRR. Performance of the early VIIRS VI EDR was limited by a lack of adequate per-pixel quality information, commission/omission errors of the cloud mask, and uncertainties associated with the surface reflectance retrievals. A number of enhancements to the VI EDR are planned, including: (1) implementation of a TOC EVI back-up algorithm, (2) addition of more detailed quality flags on aerosols, clouds, and snow cover, and (3) implementation of gridding and temporal compositing. A web-based, product quality monitoring tool has been developed and automated product validation protocols are being prototyped.

  11. Seismic design optimization of IHP cooling baffle in nuclear power plant%核电厂IHP通风围板的抗震设计优化

    Institute of Scientific and Technical Information of China (English)

    徐峰

    2012-01-01

    核电厂一体化堆顶组件(IHP)通风围板为驱动机构磁轭线圈的冷却提供了间隙均匀的通道.为了优化IHP通风围板的设计,根据ANSI/AISC N690分析了当前设计的通风围板的关键结构件在D级使用限制下的应力和变形并对关键结构件进行了初步设计优化,然后对IHP通风围板进行了有限元分析并对通风围板进行了最终设计改进.经过抗震设计优化通风围板的最大应力值分布趋于均匀.本文对抗震类设备的设计优化具有一定的参考价值.%Integrated head package (IHP) cooling baffle supplies uniform gap cooling channel for control rod drive mechanism coil stack. For optimizing design of IHP cooling baffle, stress and deformation of cooling baffle key parts were analyzed at Level D service limit according to ANSI/AISC 690, and primary optimization of key parts was processed. Then the cooling baffle was analyzed using finite element method, and final design improvement of baffle was made. The result shows better maximum stress distribution is obtained after optimization. This paper could be referenced for design optimization of seismic components.

  12. Experimental Evaluation of the Failure of a Seismic Design Category - B Precast Concrete Beam-Column Connection System

    Science.gov (United States)

    2014-12-01

    specimen to examine the specimen, but not inside the reaction frame . 8. The load will removed from the stub column, and the specimen will be braced to...experiment to test a precast concrete beam-column system to failure. This experiment was designed to evaluate the performance of precast frame ...54  Figure 81. Strains in top lateral steel brace beam

  13. Korea-Japan Joint Research on Development of Seismic Capacity Evaluation and Enhancement Technology Considering Near-Fault Effect (Final Report)

    Energy Technology Data Exchange (ETDEWEB)

    Choun, Young Sun; Choi, In Kil; Kim, Min Kyu [KAERI, Daejeon (Korea, Republic of); Ohtori, Yasuki; Shiba, Yoshiaki; Nakajima, Masato [Central Research Institute of Electric Power Industry, Tokyo (Japan)

    2006-12-15

    We compiled the results of the source analysis obtained under the collaboration research. Recent construction scheme for source modeling adopted in Japan is described, and strong-motion prediction is performed assuming the scenario earthquakes occurring in the Ulsan fault system, Korea. Finally Qs values beneath the Korean inland crust are estimated using strong-motion records in Korea from the 2005 Off West Fukuoka earthquake (M7.0). Probabilistic seismic hazard for four NPP sites in Korea are evaluated, in which the site specific attenuation equations with Index SA developed for NPP sites are adopted. Furthermore, the uniform hazard spectra for the four NPP sites in Korea are obtained by conducting the PSHA by using the attenuation equations with the index of response spectra and seismic source model cases with maximum weights. The supporting tools for seismic response analysis, the evaluation tool for evaluating annual probability of failure, and system analysis program were developed for the collaboration. The tools were verified with theoretical results, the results written in the reference document of EQESRA, and so forth. The system analysis program was applied for the investigation of the effect of improving the seismic capacity of equipment. We evaluated the annual probability of failure of isolated and non-isolated EDG at Younggwang NPP site as the results of the collaboration. The input ground motion for generating the seismic fragility curve was determined based on the seismic hazard analysis. It was found that the annual probability of failure of isolated EDG is lower than that of non-isolated EDG.

  14. 高层钢结构基于均匀损伤设计的整体抗震能力提高方法%A method for increasing the integral seismic capacity of tall steel buildings based on uniform-damage seismic design

    Institute of Scientific and Technical Information of China (English)

    孙爱伏; 侯爽; 欧进萍

    2012-01-01

    The paper mainly study how to increase the integral seismic capacity of the tall steel buildings by reasonable design. Firstly, the structural nonlinear calculation model is given. Secondly, the criterion of collapse failure modes of tall steel buildings under strong earthquake motion is established. Thirdly, by modal pushover analysis, damage law of tall steel buildings under horizongtal earthquake action is studied. Finally, the method for increasing the integral seismic capacity of tall steel buildings is studied mainly. The uniform-damage design method is proposed to increase the integral seismic capacity of tall steel buildings by eliminating the structural weakest stories. Two 20-story steel frame structures are designed on the basis of conventional philosophy and the uniform damage design method are used for limit state time history analysis and limit state pushover analysis to verify the proposed method in the paper. The results demonstrate that the uniform-damage design method is effective for increasing the integral seismic capacity. The research in the paper will give a reference to the design for preventing the seismic collapse of tall steel buildings.%本文主要研究如何通过合理设计来提高高层钢结构的整体抗震能力.首先,给出了高层钢结构的非线性计算模型;其次,建立了高层钢结构在强地震动作用下的倒塌失效模式的极限状态判别准则;然后,通过模态pushover分析,研究了高层钢结构在水平地震作用下的损伤规律;最后,重点研究了高层钢结构的整体抗震能力的提高方法,提出了均匀损伤的设计方法,该方法通过消除结构的薄弱层,来达到提高高层钢结构的整体抗震能力的目的.通过对两栋20层的高层钢框架结构进行极限时程分析和极限pushover分析,验证了文中提出的均匀损伤的设计方法的可行性.本文的工作可为高层钢结构的抗地震倒塌设计提供参考依据.

  15. Variations and trends of terrestrial NPP and its relation to climate change in the 10 CMIP5 models

    Indian Academy of Sciences (India)

    Suosuo Li; Shihua Lü; Yuanpu Liu; Yanhong Gao; Yinhuan Ao

    2015-03-01

    Using global terrestrial ecosystem net primary productivity (NPP) data, we validated the simulated multi-model ensemble (MME) NPP, analyzed the spatial distribution of global NPP and explored the relationship between NPP and climate variations in historical scenarios of 10 CMIP5 models. The results show that the global spatial pattern of simulated terrestrial ecosystem NPP, is consistent with IGBP NPP, but the values have some differences and there is a huge uncertainty. Considering global climate change, near surface temperature is the major factor affecting the terrestrial ecosystem, followed by the precipitation. This means terrestrial ecosystem NPP is more closely related to near surface temperature than precipitation. Between 1976 and 2005, NPP shows an obvious increasing temporal trend, indicating the terrestrial ecosystem has had a positive response to climate change. MME NPP has increased 3.647PgC during historical period, which shows an increasing temporal trend of 3.9 gCm−2∙100 yr−2 in the past 150 years, also indicating that the terrestrial ecosystem has shown a positive response to climate change in past 150 years.

  16. Large, moderate, small earthquakes and seismic fortification criterion

    Institute of Scientific and Technical Information of China (English)

    沈建文; 石树中

    2004-01-01

    This paper discusses the relation between two-step seismic design and the standard of probability of exceedance, and the relation of three-levels seismic ground motion parameters given by probability method and comprehensive probability method. The relative size relations of the ground motions with 2%, 10%, 63% probability of exceedance in 50 years, namely "large earthquake","moderate earthquake", and "small earthquake", are discussed through a practical example of seismic hazard analysis. The methods to determine seismic fortification criterion are discussed.

  17. Simplified design method and seismic performance of space trusses with consideration of the influence of the stiffness of their lower supporting columns

    Science.gov (United States)

    Fan, Feng; Sun, Menghan; Zhi, Xudong

    2016-06-01

    Static and dynamic force performance of two types of space truss structures i.e. square pyramid space truss (SPST) and diagonal on square pyramid space truss (DSPST), are studied to determine the effect of stiffness of their lower supporting members. A simplified model for the supporting columns and the equivalent spring mass system are presented. Furthermore, the feasibility of the simplified model is demonstrated through theoretical analysis and examples of comparative analysis of the simplified model with the entire model. Meanwhile, from the elastic analysis under frequently occurring earthquakes and elasto-plastic analysis under seldom occurring earthquakes subjected to TAFT and EL-Centro seismic oscillation it is shown that the simplified method can be encompassed in the results from the normal model. It also showed good agreement between the two methods, as well as greatly improved the computational efficiency. This study verified that the dynamic effect of the supporting structures was under considered in space truss design in the past. The method proposed in the paper has important significance for other space truss structures.

  18. Quantitative Seismic Amplitude Analysis

    OpenAIRE

    Dey, A. K.

    2011-01-01

    The Seismic Value Chain quantifies the cyclic interaction between seismic acquisition, imaging and reservoir characterization. Modern seismic innovation to address the global imbalance in hydrocarbon supply and demand requires such cyclic interaction of both feed-forward and feed-back processes. Currently, the seismic value chain paradigm is in a feed-forward mode. Modern seismic data now have the potential to yield the best images in terms of spatial resolution, amplitude accuracy, and incre...

  19. Seismic analysis of nuclear power plant structures

    Science.gov (United States)

    Go, J. C.

    1973-01-01

    Primary structures for nuclear power plants are designed to resist expected earthquakes of the site. Two intensities are referred to as Operating Basis Earthquake and Design Basis Earthquake. These structures are required to accommodate these seismic loadings without loss of their functional integrity. Thus, no plastic yield is allowed. The application of NASTRAN in analyzing some of these seismic induced structural dynamic problems is described. NASTRAN, with some modifications, can be used to analyze most structures that are subjected to seismic loads. A brief review of the formulation of seismic-induced structural dynamics is also presented. Two typical structural problems were selected to illustrate the application of the various methods of seismic structural analysis by the NASTRAN system.

  20. Brief talk on application of flat beam on building anti-seismic design%浅谈宽扁梁在建筑抗震设计中的应用

    Institute of Scientific and Technical Information of China (English)

    田华

    2009-01-01

    Combining with the development situation of Chinese high rise building, the author introduces into the concept of the flat beam, introduces some attention problems and structural requirements in the flat beam anti-seismic design, and points out that the ductility and deforming capacity of the flat beam is good, if the design and structure measure is proper, it has good anti-seismic performance.%结合我国高层建筑的发展情况,引入了宽扁梁的概念,介绍了宽扁梁抗震设计中一些需要注意的问题及构造要求,指出宽扁梁的延性和变形能力较好,只要设计、构造措施得当,也具有良好的抗震性能.

  1. Seismic displacement of gravity retaining walls

    Directory of Open Access Journals (Sweden)

    Kamal Mohamed Hafez Ismail Ibrahim

    2015-08-01

    Full Text Available Seismic displacement of gravity walls had been studied using conventional static methods for controlled displacement design. In this study plain strain numerical analysis is performed using Plaxis dynamic program where prescribed displacement is applied at the bottom boundary of the soil to simulate the applied seismic load. Constrained absorbent side boundaries are introduced to prevent any wave reflection. The studied soil is chosen dense granular sand and modeled as elasto-plastic material according to Mohr–Column criteria while the gravity wall is assumed elastic. By comparing the resulted seismic wall displacements calculated by numerical analysis for six historical ground motions with that calculated by the pseudo-static method, it is found that numerical seismic displacements are either equal to or greater than corresponding pseudo-static values. Permissible seismic wall displacement calculated by AASHTO can be used for empirical estimation of seismic displacement. It is also found that seismic wall displacement is directly proportional with the positive angle of inclination of the back surface of the wall, soil flexibility and with the earthquake maximum ground acceleration. Seismic wall sliding is dominant and rotation is negligible for rigid walls when the ratio between the wall height and the foundation width is less than 1.4, while for greater ratios the wall becomes more flexible and rotation (rocking increases till the ratio reaches 1.8 where overturning is susceptible to take place. Cumulative seismic wall rotation increases with dynamic time and tends to be constant at the end of earthquake.

  2. Application of bounding spectra to seismic design of piping based on the performance of above ground piping in power plants subjected to strong motion earthquakes

    Energy Technology Data Exchange (ETDEWEB)

    Stevenson, J.D. [Stevenson and Associates, Cleveland, OH (United States)

    1995-02-01

    This report extends the potential application of Bounding Spectra evaluation procedures, developed as part of the A-46 Unresolved Safety Issue applicable to seismic verification of in-situ electrical and mechanical equipment, to in-situ safety related piping in nuclear power plants. The report presents a summary of earthquake experience data which define the behavior of typical U.S. power plant piping subject to strong motion earthquakes. The report defines those piping system caveats which would assure the seismic adequacy of the piping systems which meet those caveats and whose seismic demand are within the bounding spectra input. Based on the observed behavior of piping in strong motion earthquakes, the report describes the capabilities of the piping system to carry seismic loads as a function of the type of connection (i.e. threaded versus welded). This report also discusses in some detail the basic causes and mechanisms for earthquake damages and failures to power plant piping systems.

  3. LANL seismic screening method for existing buildings

    Energy Technology Data Exchange (ETDEWEB)

    Dickson, S.L.; Feller, K.C.; Fritz de la Orta, G.O. [and others

    1997-01-01

    The purpose of the Los Alamos National Laboratory (LANL) Seismic Screening Method is to provide a comprehensive, rational, and inexpensive method for evaluating the relative seismic integrity of a large building inventory using substantial life-safety as the minimum goal. The substantial life-safety goal is deemed to be satisfied if the extent of structural damage or nonstructural component damage does not pose a significant risk to human life. The screening is limited to Performance Category (PC) -0, -1, and -2 buildings and structures. Because of their higher performance objectives, PC-3 and PC-4 buildings automatically fail the LANL Seismic Screening Method and will be subject to a more detailed seismic analysis. The Laboratory has also designated that PC-0, PC-1, and PC-2 unreinforced masonry bearing wall and masonry infill shear wall buildings fail the LANL Seismic Screening Method because of their historically poor seismic performance or complex behavior. These building types are also recommended for a more detailed seismic analysis. The results of the LANL Seismic Screening Method are expressed in terms of separate scores for potential configuration or physical hazards (Phase One) and calculated capacity/demand ratios (Phase Two). This two-phase method allows the user to quickly identify buildings that have adequate seismic characteristics and structural capacity and screen them out from further evaluation. The resulting scores also provide a ranking of those buildings found to be inadequate. Thus, buildings not passing the screening can be rationally prioritized for further evaluation. For the purpose of complying with Executive Order 12941, the buildings failing the LANL Seismic Screening Method are deemed to have seismic deficiencies, and cost estimates for mitigation must be prepared. Mitigation techniques and cost-estimate guidelines are not included in the LANL Seismic Screening Method.

  4. 罕遇地震下上海中心超高层的性能化抗震设计%Performance-based Seismic Design of Shanghai Tower Under Rare Earthquake

    Institute of Scientific and Technical Information of China (English)

    罗永峰; 王磊; 李海锋; 陈文辉

    2011-01-01

    Based on CECS160 and ASCF41, performance design levels and objects of Shanghai Tower are proposed. A computational strategy for dynamic analysis of seismic behavior of the building is put forward,in which the nonlinear stress-strain relationship of structural materials is directly adopted rather than concentrated plastic hinge. The corresponding performance-hased seismic design objects of primary members are determined. The suitable finite elements and a reliable nonlinear dynamics analysis technique are selected to accomplish the performance evaluation of Shanghai Tower. Valuable suggestions about the performance seismic design are proposed for the structure. The results provide useful hackground materials for further study of the performance-based seismic design of similar buildings.%参照CECS160()和ASCE41(),研究确定拟建的上海中心超高层建筑结构的性能化抗震设计目标,提出了直接用于该结构的基于材料本构关系的性能化抗震设计方法,以及基于位移的性能化抗震设计控制指标,选取合适的结构单元模型与合适的非线性动力分析技术相结合的方法,对上海中心超高层结构进行整体抗震性能评估.为该结构设计提供了有益的建议,并为基于位移的性能化抗震设计方法积累了资料.

  5. Temporal variability of the NPP-GPP ratio at seasonal and interannual time scales in a temperate beech forest

    Directory of Open Access Journals (Sweden)

    M. Campioli

    2011-09-01

    Full Text Available The allocation of carbon (C taken up by the tree canopy for respiration and production of tree organs with different construction and maintenance costs, life span and decomposition rate, crucially affects the residence time of C in forests and their C cycling rate. The carbon-use efficiency, or ratio between net primary production (NPP and gross primary production (GPP, represents a convenient way to analyse the C allocation at the stand level. In this study, we extend the current knowledge on the NPP-GPP ratio in forests by assessing the temporal variability of the NPP-GPP ratio at interannual (for 8 years and seasonal (for 1 year scales for a young temperate beech stand, reporting dynamics for both leaves and woody organs, in particular stems. NPP was determined with biometric methods/litter traps, whereas the GPP was estimated via the eddy covariance micrometeorological technique.

    The interannual variability of the proportion of C allocated to leaf NPP, wood NPP and leaf plus wood NPP (on average 11% yr−1, 29% yr−1 and 39% yr−1, respectively was significant among years with up to 12% yr−1 variation in NPP-GPP ratio. Studies focusing on the comparison of NPP-GPP ratio among forests and models using fixed allocation schemes should take into account the possibility of such relevant interannual variability. Multiple linear regressions indicated that the NPP-GPP ratio of leaves and wood significantly correlated with environmental conditions. Previous year drought and air temperature explained about half of the NPP-GPP variability of leaves and wood, respectively, whereas the NPP-GPP ratio was not decreased by severe drought, with large NPP-GPP ratio on 2003 due mainly to low GPP. During the period between early May and mid June, the majority of GPP was allocated to leaf and stem NPP, whereas these sinks were of little importance later on. Improved estimation of seasonal GPP and of the

  6. Seismic behavior of buried pipelines constructed by design criteria and construction specifications of both Korea and the US

    Directory of Open Access Journals (Sweden)

    S.-S. Jeon

    2013-03-01

    Full Text Available Lifeline damage induced by earthquake loading not only causes structure damage but also communication problems resulting from the interruption of various energy utilities such as electric power, gas, and water resources. Earthquake loss estimation systems in the US, for example HAZUS (Hazard in US, have been established for the purpose of prevention and efficient response to earthquake hazards. Sufficient damage records obtained from earthquakes are required to establish these systems, however, in Korea, insufficient data sets of damage records are currently available. In this study, according to the design criteria and construction specifications of pipelines in Korea and the US, the behavior of both brittle and ductile pipelines embedded in dense sand overlying various in-situ soils, such as clay, sand, and gravel, were examined and compared with respect to the mechanical characteristics of pipelines under various earthquake loadings.

  7. Performance of the Clouds and the Earth's Radiant Energy System (CERES) Flight Model 5 (FM5) instrument on NPP mission

    Science.gov (United States)

    Thomas, Susan; Priestley, Kory J.; Hess, Phillip C.; Wilson, Robert S.; Smith, Nathaniel P.; Timcoe, Mark G.; Shankar, Mohan; Walikainen, Dale R.

    2012-09-01

    Clouds and the Earth's Radiant Energy System (CERES) instrument was designed to provide accurate measurements for the long-term monitoring of Earth's radiation energy budget. Flight Model 5, the sixth of the CERES instrument was launched aboard the NPP spacecraft on October 2011 and it has started the Earth-viewing measurements on January 26, 2012. The CERES instrument with the three scanning sensors measure radiances in 0.3 to 5.0 micron region with Shortwave sensor, 0.3 to elevation offset in the sensor measurement will be determined from the spacecraft pitch manuveur activity viewing the deep space. This paper covers the early-orbit checkout activities and the overall performance of the CERES-FM5 instrument. The postlaunch calibration and the validation results from the instrument are presented.

  8. 多层生态复合墙结构基于位移的抗震设计方法研究%STUDY OF METHOD OF DISPLACEMENT-BASED SEISMIC DESIGN OF MULTI-LAYER ECOLOGICAL COMPOSITE WALL STRUCTURE

    Institute of Scientific and Technical Information of China (English)

    黄炜; 张敏; 张程华; 蒋小平; 侯莉娜

    2014-01-01

    目前生态复合墙结构体系采用的“两阶段三水准”抗震设计方法已无法满足业主对建筑结构性能目标的个性化要求。将结构特有的三道抗震防线与基于性能的抗震设计理论框架相结合,分别以三道抗震防线的屈服位移值对结构的性能水准进行量化。以倒三角形水平分布荷载等截面剪切型悬臂柱的侧移曲线作为结构的初始侧移模式,结合位移反应谱提出其基于位移设计的具体步骤,并对实例进行了三个性能目标下的设计计算。算例表明:提出的多层生态复合墙结构基于位移的抗震设计方法能够针对不同性能水平进行设计计算,简单实用。%Now the “two-phase and three-level” seismic design method , which has been used in the calculation of ecological composite-wall structure system , has failed to meet the modern owner ’ s personalized requirement of building structure performance target .Combining three special seismic defence lines of ecological composite-wall structure with the theoretical framework of seismic design based on performance , and based on yield displacement value of the three seismic defence lines , the performance level of structure was quantified .Applying the inverted triangular distribution of lateral force to the cantilever column of constant section , and the displaced shape of the column was regarded as the initial mode of lateral displacement;combining with the displacement response spectrum , the specific steps of the displacement-based design method were put forward and three performance targets design of a example were calculated .Example shows that the proposed multiple ecological composite wall structure displacement -based seismic design method is simple and practical , which can be designed and calculated according to different performance levels .

  9. Electrical Grid Conditioning For First NPP Integration, a Systems Engineering Approach Incorporating Quality Function Deployment

    Energy Technology Data Exchange (ETDEWEB)

    Pwani, Henry; James, J. [KEPCO International Nuclear Graduate School, Ulsan (Korea, Republic of)

    2013-10-15

    Nuclear power plant has a high potential to cause serious harm to environment as evidenced by effects of Fukushima and Chernobyl accidents. A reliable electrical power is required for a NPP to facilitate cooling after a shutdown. Failure of electrical power supply during shutdown increases core damage probability. Research shows that a total of 39% of LOOP related events in US are electrical grid centered. In Korea, 38% and 29% of all events that led to NPP shutdown at Hanul units 3-6 and at Hanbit units 3-6 respectively were electrical related. Electric grids for both operating and new NPPs must therefore be examined and upgraded for reliability improvement in order to enhance NPP safety.

  10. Operating and mathematical representation of resonances between flow parameters oscillations and structure vibrations of NPP

    Energy Technology Data Exchange (ETDEWEB)

    Proskuryakov, K.N.; Yang Shan Afshar, E.; Polyakov, N.I. [Nuclear Power Plant Department of Moscow Power Engineering Institute Technical Univ., Moscow (Russian Federation)

    2007-07-01

    The experimental data that have been obtained from the measurements of noise signals in primary circuit of NPP with reactor of WWER-1000 are presented. The causes of resonant interaction between Eigen-Frequencies of Oscillations of the Coolant Pressure (EFOCP) and structure vibrations are discussed. An application-oriented approach to the problem of identification of abnormal phenomena of thermal-hydraulic parameters is proposed. Logarithmic Decrement {delta} is determined. The bigger damping ratio {zeta} provides bigger {delta} and correspondingly smaller values of Q-factor and amplitude X(t)max. All experimental units intended for NPP severe accident investigation must satisfy to the NPP Q-factor criterion of similarity. (authors)

  11. Seismic behaviour of geotechnical structures

    Directory of Open Access Journals (Sweden)

    F. Vinale

    2002-06-01

    Full Text Available This paper deals with some fundamental considerations regarding the behaviour of geotechnical structures under seismic loading. First a complete definition of the earthquake disaster risk is provided, followed by the importance of performing site-specific hazard analysis. Then some suggestions are provided in regard to adequate assessment of soil parameters, a crucial point to properly analyze the seismic behaviour of geotechnical structures. The core of the paper is centered on a critical review of the analysis methods available for studying geotechnical structures under seismic loadings. All of the available methods can be classified into three main classes, including the pseudo-static, pseudo-dynamic and dynamic approaches, each of which is reviewed for applicability. A more advanced analysis procedure, suitable for a so-called performance-based design approach, is also described in the paper. Finally, the seismic behaviour of the El Infiernillo Dam was investigated. It was shown that coupled elastoplastic dynamic analyses disclose some of the important features of dam behaviour under seismic loading, confirmed by comparing analytical computation and experimental measurements on the dam body during and after a past earthquake.

  12. Comparing the impacts of 2003 and 2010 heatwaves in NPP over Europe

    Directory of Open Access Journals (Sweden)

    A. Bastos

    2013-10-01

    Full Text Available In the last decade, Europe was stricken by two outstanding heatwaves, the 2003 event in Western Europe and the recent 2010 episode over Russia. Both extreme events were characterised by record-breaking temperatures, and widespread socio-economic impacts, including significant increments on mortality rates, decreases in crop production and in hydroelectric production. This work aims to assess the influence of both mega-heatwaves on vegetation carbon uptake, using yearly Net Primary Production (NPP and monthly Net Photosynthesis (PsN data derived from satellite imagery obtained from MODIS for the period 2000–2011. In 2010, markedly low productivity was observed over a very large area in Russia, at monthly, seasonal and yearly scales, falling below 50% of average NPP. This decrease in NPP in 2010 was far more intense than the one affecting Western Europe in 2003, which corresponded to 20–30% of the average, and affected a~much larger extent. Total NPP anomalies reached −19 Tg C for the selected regions in France during 2003 and −94 Tg C for western Russia in 2010, which corresponds almost to the magnitude of total NPP anomaly during 2010 for the whole Europe. Overall, the widespread negative PsN anomalies in both regions match the patterns of very high temperature values preceded by a long period of below-average precipitation, leading to strong soil moisture deficits, stressing the role of soil-atmosphere coupling. In the case of 2003 heatwave, results indicate a strong influence of moisture deficits coupled with high temperatures in the response of vegetation, while for the 2010 event very high temperatures appear to be the main driver of very low NPP.

  13. Counter-regulatory phosphatases TNAP and NPP1 temporally regulate tooth root cementogenesis

    Institute of Scientific and Technical Information of China (English)

    Laura E Zweifler; Mudita K Patel; Francisco H Nociti Jr; Helen F Wimer; Jose L Milla n; Martha J Somerman; Brian L Foster

    2015-01-01

    Cementum is critical for anchoring the insertion of periodontal ligament fibers to the tooth root. Several aspects of cementogenesis remain unclear, including differences between acellular cementum and cellular cementum, and between cementum and bone. Biomineralization is regulated by the ratio of inorganic phosphate (Pi) to mineral inhibitor pyrophosphate (PPi), where local Pi and PPi concentrations are controlled by phosphatases including tissue-nonspecific alkaline phosphatase (TNAP) and ectonucleotide pyrophosphatase/phosphodiesterase 1 (NPP1). The focus of this study was to define the roles of these phosphatases in cementogenesis. TNAP was associated with earliest cementoblasts near forming acellular and cellular cementum. With loss of TNAP in the Alpl null mouse, acellular cementum was inhibited, while cellular cementum production increased, albeit as hypomineralized cementoid. In contrast, NPP1 was detected in cementoblasts after acellular cementum formation, and at low levels around cellular cementum. Loss of NPP1 in the Enpp1 null mouse increased acellular cementum, with little effect on cellular cementum. Developmental patterns were recapitulated in a mouse model for acellular cementum regeneration, with early TNAP expression and later NPP1 expression. In vitro, cementoblasts expressed Alpl gene/protein early, whereas Enpp1 gene/protein expression was significantly induced only under mineralization conditions. These patterns were confirmed in human teeth, including widespread TNAP, and NPP1 restricted to cementoblasts lining acellular cementum. These studies suggest that early TNAP expression creates a low PPi environment promoting acellular cementum initiation, while later NPP1 expression increases PPi, restricting acellular cementum apposition. Alterations in PPi have little effect on cellular cementum formation, though matrix mineralization is affected.

  14. Seismic behavior of buried pipelines constructed by design criteria and construction specifications of both Korea and the US

    Directory of Open Access Journals (Sweden)

    S.-S. Jeon

    2013-09-01

    Full Text Available Earthquake loss estimation systems in the US, for example HAZUS (Hazard in US, have been established based on sufficient damage records for the purpose of prevention and efficient response to earthquake hazards; however, in Korea, insufficient data sets of earthquakes and damage records are currently available. In this study, the earthquake damages to pipelines in Korea using the pipeline repair rate (RR recommended in HAZUS was reevaluated with the degree of confidence when RR is used without modification for the damage estimation of pipelines in Korea. The numerical analyses using a commercial finite element model, ABAQUS, were carried out to compare stresses and strains mobilized in both brittle and ductile pipelines constructed by the design criteria and construction specifications of both Korea and the US. These pipelines were embedded in dense sand overlying three different in situ soils (clay, sand, and gravel subjected to earthquake excitations with peak ground accelerations (PGAs of 0.2 to 1.2 g and 1994 Northridge and 1999 Chi-Chi earthquake loadings. The numerical results show that differences in the stress and strain rates are less than 10%. This implies that RR in HAZUS can be used for earthquake damage estimation of pipelines with a 90% confidence level in Korea.

  15. Studies on seismic waves

    Institute of Scientific and Technical Information of China (English)

    张海明; 陈晓非

    2003-01-01

    The development of seismic wave study in China in the past four years is reviewed. The discussion is divided into several aspects, including seismic wave propagation in laterally homogeneous media, laterally heterogeneous media, anisotropic and porous media, surface wave and seismic wave inversion, and seismic wave study in prospecting and logging problems. Important projects in the current studies on seismic wave is suggested as the development of high efficient numerical methods, and applying them to the studies of excitation and propagation of seismic waves in complex media and strong ground motion, which will form a foundation for refined earthquake hazard analysis and prediction.

  16. Robustness of timber structures in seismic areas

    OpenAIRE

    Branco, J. M.

    2011-01-01

    Some of the properties sought in seismic design of buildings are also considered fundamental to guarantee structural robustness. Moreover, some key concepts are common to both seismic and robustness design. In fact, both analyses consider events with a very small probability of occurrence, and consequently, a significant level of damage is admissible. As very rare events,in both cases, the actions are extremely hard to quantify. The acceptance of limited damage requires a system based anal...

  17. An information theory-based approach to modeling the information processing of NPP operators

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Jong Hyun; Seong, Poong Hyun [Korea Advanced Institute, Taejon (Korea, Republic of)

    2002-08-01

    This paper proposes a quantitative approach to modeling the information processing of NPP operators. The aim of this work is to derive the amount of the information processed during a certain control task. The focus will be on i) developing a model for information processing of NPP operators and ii) quantifying the model. To resolve the problems of the previous approaches based on the information theory, i.e. the problems of single channel approaches, we primarily develop the information processing model having multiple stages, which contains information flows. Then the uncertainty of the information is quantified using the Conant's model, a kind of information theory.

  18. MODIS GPP/NPP for complex land use area: a case study of comparison between MODIS GPP/NPP and ground-based measurements over Korea

    Science.gov (United States)

    Shim, C.

    2013-12-01

    The Moderate Resolution Imaging Radiometer (MODIS) Gross Primary Productivity (GPP)/Net Primary Productivity (NPP) has been widely used for the study on global terrestrial ecosystem and carbon cycle. The current MODIS product with ~ 1 km spatial resolution, however, has limitation on the information on local scale environment (Pinus densiflora) agreed well with -0.2% of bias (1.6 gCm-2yr-1). The fairly comparable values of the MODIS here however, cannot assure the quality of the MOD17 over the complex vegetation area of Korea since the ground measurements except the eddy covariance tower flux measurements are highly inconsistent. Therefore, the comprehensive experiments to represents GPP/NPP over diverse vegetation types for a comparable scale of MODIS with a consistent measurement technique are necessary in order to evaluate the MODIS vegetation productivity data over Korea, which contains a large portion of highly heterogeneous vegetation area.

  19. 长富金茂大厦结构设计及抗震性能研究%Structural design and seismic performance of Changfu Jinmao Building

    Institute of Scientific and Technical Information of China (English)

    王兴法; 林超伟; 陈勤; 李瑞; 郑明华; 李开伦

    2011-01-01

    Changfu Jinmao Building is 295 meters high with a structural system of composite frame-core-outrigger.ETABS and SATWE softwares were used to achieve structural elastic analysis, and the results coincide with each other and meet with the relevant requirements.Elastic time-history analysis was carried out, and the larger values in time-history and spectrum response were used in structural design.Results from wind-tunnel test show that the peak acceleration in the top of the main building is met with human camfort requirements in the office.Structural safety in construction was checked in the simulation of construction stage.ABAQUS was used in the analysis of elastic-plastic time-history response and seismic performance evaluation in rare earthquakes.Finally, some aseismic measures were introduced on the basis of the specific characteristics of the project.%长富金茂大厦结构主体高度295m,为组合框架-核心筒-伸臂结构.用ETABS和SATWE软件进行结构弹性分析,计算结果吻合较好,各项指标满足规范要求.此外还进行了结构的弹性时程分析,将其结果和反应谱结果中的较大值用于结构设计.风洞试验表明主楼顶层加速度峰值满足人体舒适度要求,同时验算了施工过程中的结构安全性.采用ABAQUS对结构进行大震弹塑性时程反应分析及抗震性能评价,最后介绍了采取的抗震措施.

  20. On influence of seismic disasters on structural design and its reference%地震灾害对结构设计的影响及借鉴意义

    Institute of Scientific and Technical Information of China (English)

    苏志章

    2015-01-01

    The paper surveys the magnitude and seismic features for the sites and structures of the earthquakes in China, and points out some sug-gestions for the architectural structural design according to the investigation and analysis of the common reasons for the collapses and damages of the architectural structures, so as to improve the anti-seismic performance for the architectural structure in China.%对近年来我国大地震的震级、场地与结构震害特点进行了概述,通过调查与分析建筑结构倒塌破坏的共性原因,提出了一些建筑结构设计的建议,以提高我国建筑结构的抗震性能。

  1. Seismic surveying for coal mine planning

    Energy Technology Data Exchange (ETDEWEB)

    Zhou, B. [CMTE/CSIRO Exploration and Mining, Kenmore, Qld. (Australia)

    2002-07-01

    More and more coal in Australia is extracted by underground mining methods especially by longwall mining. These methods can be particularly sensitive to relatively small-scale structural discontinuities and variations in roof and floor rock character. Traditionally, information on these features has been obtained through drilling. However, this is an expensive process and its relevance is limited to the immediate neighbourhood of the boreholes. Seismic surveying, especially by 3D seismic, is an alternative tool for geological structure delineation. It is one of the most effective geophysical methods available for identification of geological structures such as faults, folds, washouts, seam splits and thickness changes which are normally associated with potential mining hazards. Seismic data even can be used for stratigraphic identification. The information extracted from seismic data can be integrated into mine planning and design. In this paper, computer aided interpretation techniques for maximising the information from seismic data are demonstrated and the ability of seismic reflection methods to resolve localised geological features illustrated. Both synthetic and real seismic data obtained in recent 2D and 3D seismic surveys from Australian coal mines are used. 7 refs., 9 figs.

  2. Vegetation NPP Distribution Based on MODIS Data and CASA Model——A Case Study of Northern Hebei Province

    Institute of Scientific and Technical Information of China (English)

    YUAN Jinguo; NIU Zheng; WANG Chenli

    2006-01-01

    Net Primary Productivity (NPP) is one of the important biophysical variables of vegetation activity, and it plays an important role in studying global carbon cycle, carbon source and sink of ecosystem, and spatial and temporal distribution of CO2. Remote sensing can provide broad view quickly, timely and multi-temporally, which makes it an attractive and powerful tool for studying ecosystem primary productivity, at scales ranging from local to global. This paper aims to use Moderate Resolution Imaging Spectroradiometer (MODIS) data to estimate and analyze spatial and temporal distribution of NPP of the northern Hebei Province in 2001 based on Carnegie-Ames-Stanford Approach (CASA) model.The spatial distribution of Absorbed Photosynthetically Active Radiation (APAR) of vegetation and light use efficiency in three geographical subregions, that is, Bashang Plateau Region, Basin Region in the northwestern Hebei Province and Yanshan Mountainous Region in the Northern Hebei Province were analyzed, and total NPP spatial distribution of the study area in 2001 was discussed. Based on 16-day MODIS Fraction of Photosynthetically Active Radiation absorbed by vegetation (FPAR) product, 16-day composite NPP dynamics were calculated using CASA model; the seasonal dyamics of vegetation NPP in three subregions were also analyzed. Result reveals that the total NPP of the study area in 2001 was 25.1877×106 gC/(m2·a), and NPP in 2001 ranged from 2 to 608 gC/(m2·a), with an average of 337.516 gC/(m2·a). NPP of the study area in 2001 accumulated mainly from May to September (DOY 129-272), high NPP values appeared from June to August (DOY 177-204), and the maximum NPP appeared from late July to mid-August (DOY 209-224).

  3. Study on spectra and spectral damping reduction factors in Chinese seismic design codes%我国抗震设计规范设计反应谱及谱阻尼折减系数研究

    Institute of Scientific and Technical Information of China (English)

    曹加良; 施卫星; 汪洋; 蒋湘闽

    2011-01-01

    The determination of the damping reduction factors of acceleration spectra that match the statistical characteristics of strong ground motions,based on the normalized acceleration spectra specified in the seismic codes,is a practical method to construct the design response spectra for long-period structures with damping ratios higher than 0.05.Statistical characteristics of earthquake response spectra were summarized first.Then qualitative investigations on the rationality of the seismic design spectra and spectral damping reduction factors in various Chinese seismic design codes including the codes for buildings,special structures,nuclear power plants,highway bridges and electrical facilities in industrial plants were performed.In addition,rationality of the improved seismic code spectra and spectral damping reduction factors was also discussed.The results show that values of both relative displacement spectra and relative velocity spectra will decrease along with the increase of the damping ratio.Values of absolute acceleration spectra will either decrease or increase along with the increase of the damping ratio.There are still no appropriate evaluation expressions for the damping reduction factors in the Chinese seismic design codes.The pseudo relative displacement spectra obtained from converting acceleration spectra in Chinese seismic design codes or modified acceleration spectra proposed by some researchers are only suitable for the seismic design of short-period structures with lower damping ratios.%在标准加速度反应谱基础上,研究并建立符合强震反应谱统计特征的谱阻尼折减系数是建立长周期、大阻尼比反应谱的一种实用方法。首先研究总结强震反应谱的统计特征,据此对我国建筑物、构筑物、核电厂、公路桥梁、工业企业电气设备等结构的抗震设计规范反应谱及谱阻尼折减系数的合理性进行定性研究,对已有改进抗震规范谱方案的合理性进行

  4. Seismic fragility analysis of a nuclear building based on probabilistic seismic hazard assessment and soil-structure interaction analysis

    Energy Technology Data Exchange (ETDEWEB)

    Gonzalez, R.; Ni, S.; Chen, R.; Han, X.M. [CANDU Energy Inc, Mississauga, Ontario (Canada); Mullin, D. [New Brunswick Power, Point Lepreau, New Brunswick (Canada)

    2016-09-15

    Seismic fragility analyses are conducted as part of seismic probabilistic safety assessment (SPSA) for nuclear facilities. Probabilistic seismic hazard assessment (PSHA) has been undertaken for a nuclear power plant in eastern Canada. Uniform Hazard Spectra (UHS), obtained from the PSHA, is characterized by high frequency content which differs from the original plant design basis earthquake spectral shape. Seismic fragility calculations for the service building of a CANDU 6 nuclear power plant suggests that the high frequency effects of the UHS can be mitigated through site response analysis with site specific geological conditions and state-of-the-art soil-structure interaction analysis. In this paper, it is shown that by performing a detailed seismic analysis using the latest technology, the conservatism embedded in the original seismic design can be quantified and the seismic capacity of the building in terms of High Confidence of Low Probability of Failure (HCLPF) can be improved. (author)

  5. Widespread use of best estimate codes in Atucha II NPP simulator; Uso extendido de codigos Best estimate en el sumulador de Atucha II

    Energy Technology Data Exchange (ETDEWEB)

    Dieguez, G. L.; Garde, D.; Ruiz, J. A.; Exposito, A.

    2016-08-01

    Since the best estimate codes were first used in training simulators in the 90s, the computing power has increased dramatically and today the computing cost has become insignificant in these project. This allows using state of the art process simulation codes, both on detailed design models and also on the simulation of all the potentially biphasic plant systems. The Atucha II NPP simulator sets a good example. The quality of the results has enabled to proactively support the plant start-up, verifying the planned maneuvers and featuring reference behavior. It has also helped to understand unexpected phenomena and optimize the control loops. (Author)

  6. Radiometric Inter-Calibration between Himawari-8 AHI and S-NPP VIIRS for the Solar Reflective Bands

    Directory of Open Access Journals (Sweden)

    Fangfang Yu

    2016-02-01

    Full Text Available The Advanced Himawari Imager (AHI on-board Himawari-8, which was launched on 7 October 2014, is the first geostationary instrument housed with a solar diffuser to provide accurate onboard calibrated data for the visible and near-infrared (VNIR bands. In this study, the Ray-matching and collocated Deep Convective Cloud (DCC methods, both of which are based on incidently collocated homogeneous pairs between AHI and Suomi NPP (S-NPP Visible Infrared Imaging Radiometer Suite (VIIRS, are used to evaluate the calibration difference between these two instruments. While the Ray-matching method is used to examine the reflectance difference over the all-sky collocations with similar viewing and illumination geometries, the near lambertian collocated DCC pxiels are used to examine the difference for the median or high reflectance scenes. Strong linear relationships between AHI and VIIRS can be found at all the paired AHI and VIIRS bands. Results of both methods indicate that AHI radiometric calibration accuracy agrees well with VIIRS data within 5% for B1-4 and B6 at mid and high reflectance scenes, while AHI B5 is generally brighter than VIIRS by ~6%–8%. No apparent East-West viewing angle dependent calibration difference can be found at all the VNIR bands. Compared to the Ray-matching method, the collocated DCC method provides less uncertainty of inter-calibration results at near-infrared (NIR bands. As AHI has similar optics and calibration designs to the GOES-R Advanced Baseline Imager (ABI, which is currently scheduled to launch in fall 2016, the on-orbit AHI data provides a unique opportunity to develop, test and examine the cal/val tools developed for ABI.

  7. Quantitative Seismic Amplitude Analysis

    NARCIS (Netherlands)

    Dey, A.K.

    2011-01-01

    The Seismic Value Chain quantifies the cyclic interaction between seismic acquisition, imaging and reservoir characterization. Modern seismic innovation to address the global imbalance in hydrocarbon supply and demand requires such cyclic interaction of both feed-forward and feed-back processes.

  8. Quantitative Seismic Amplitude Analysis

    NARCIS (Netherlands)

    Dey, A.K.

    2011-01-01

    The Seismic Value Chain quantifies the cyclic interaction between seismic acquisition, imaging and reservoir characterization. Modern seismic innovation to address the global imbalance in hydrocarbon supply and demand requires such cyclic interaction of both feed-forward and feed-back processes. Cur

  9. Robotization in Seismic Acquisition

    NARCIS (Netherlands)

    Blacquière, G.; Berkhout, A.J.

    2013-01-01

    The amount of sources and detectors in the seismic method follows "Moore’s Law of seismic data acquisition", i.e., it increases approximately by a factor of 10 every 10 years. Therefore automation is unavoidable, leading to robotization of seismic data acquisition. Recently, we introduced a new

  10. Advanced Seismic While Drilling System

    Energy Technology Data Exchange (ETDEWEB)

    Robert Radtke; John Fontenot; David Glowka; Robert Stokes; Jeffery Sutherland; Ron Evans; Jim Musser

    2008-06-30

    A breakthrough has been discovered for controlling seismic sources to generate selectable low frequencies. Conventional seismic sources, including sparkers, rotary mechanical, hydraulic, air guns, and explosives, by their very nature produce high-frequencies. This is counter to the need for long signal transmission through rock. The patent pending SeismicPULSER{trademark} methodology has been developed for controlling otherwise high-frequency seismic sources to generate selectable low-frequency peak spectra applicable to many seismic applications. Specifically, we have demonstrated the application of a low-frequency sparker source which can be incorporated into a drill bit for Drill Bit Seismic While Drilling (SWD). To create the methodology of a controllable low-frequency sparker seismic source, it was necessary to learn how to maximize sparker efficiencies to couple to, and transmit through, rock with the study of sparker designs and mechanisms for (a) coupling the sparker-generated gas bubble expansion and contraction to the rock, (b) the effects of fluid properties and dynamics, (c) linear and non-linear acoustics, and (d) imparted force directionality. After extensive seismic modeling, the design of high-efficiency sparkers, laboratory high frequency sparker testing, and field tests were performed at the University of Texas Devine seismic test site. The conclusion of the field test was that extremely high power levels would be required to have the range required for deep, 15,000+ ft, high-temperature, high-pressure (HTHP) wells. Thereafter, more modeling and laboratory testing led to the discovery of a method to control a sparker that could generate low frequencies required for deep wells. The low frequency sparker was successfully tested at the Department of Energy Rocky Mountain Oilfield Test Center (DOE RMOTC) field test site in Casper, Wyoming. An 8-in diameter by 26-ft long SeismicPULSER{trademark} drill string tool was designed and manufactured by TII

  11. Development of a light weighted mobile robot for SG tube inspection in NPP

    Energy Technology Data Exchange (ETDEWEB)

    Seo, Yong Chil; Jeong, Kyung Min; Shin, Hochul; Gweng, Jung Ju; Lee, Sung Uk; Jeong, Seung Ho; Choi, Young Soo; Kim, Seung Ho [KAERI, Daejeon (Korea, Republic of); Shin, Chun Sup; Park, Ki Tae [Korea Plant Service and Engineering, Busan (Korea, Republic of)

    2012-10-15

    Steam generators (SG) are among the most critical components of pressurized water Nuclear Power Plants (NPP). SG tubes must provide a reliable pressure boundary between the primary and secondary cooling water, because any leakage from tube defects could result in the release of radioactivity to the environment. Thus degradations of steam generators tubes should be monitored and inspected periodically under nuclear regulation. In service inspections of SG tubes are carried out using eddy current test (ECT) and the defected tubes are usually plugged. Because the radioactivity in the internal SG chambers limits free access of human workers, remote manipulators are required. In South Korea, Manipulators such as the Zet ec SM series and the Westinghouse ROSA series have bee used. Such manipulators are rigidly mounted to man ways or tube sheets of SG. Confusions of the inspected tubes may occur from deflection of the manipulators. To reduce the deflections of the manipulators for covering the large working areas of tube sheets, sufficient rigidity is required and that leads to an increase of the weight. Such weight increase results in some difficulties for handling and more radiation exposure of human workers. Recently light weighed mobile robots have been introduced by Westinghouse and Zet ec. The robots can move keeping in contact with the tube sheets using devices which are commonly called cam locks. They are easier to handle and provide no confusion for the position of the inspected tubes. But when the clamping forces are loosed accidentally, they can be fall down and light repair works can be performed. This paper provides the design results for a lightweight mobile robot which is being developed in cooperation of our institutes.

  12. Development of regulatory guide for review of aging management of the operating NPP

    Energy Technology Data Exchange (ETDEWEB)

    Shin, Tae Myung; Lee, Jae Kyung [Cheongju Univ., Cheongju (Korea, Republic of); Kim, Young Ryul [Korea Advanced Institute of Science and Technology, Taejon (Korea, Republic of)

    2001-03-15

    This is the final report of the second year study. Based on the first year study, proposal of revised guidelines, analysis of revised or newly issued IAEA safety guides and reference guidelines of developed countries, and proposal of detailed guidelines of aging management in PSR have been performed in the second year study. The summary of results in the study so far can be summarized as below, overall view on PSR and idea of effective domestic application were leaded through additional investigation and comparison of legal basis, experiences and current status of PSR implementation among the countries having operating NPPs including Korea. Strategies of adequate application of PSR are roughly reevaluated and totally reestablished in summary from the analysis in factor by factor basis of PSR implementation experience in foreign countries and background of IAEA guidelines. Models and draft framework of PSR report in the first year study were summarized and reevaluated, and structure and outline options of PSR guidelines for judging the PSR report are newly proposed with comparison of their strengths and weaknesses based on the first year study. Among the opt ions, guidelines framework equivalent to the PSR report was picked up as the best. For the judgement of aging management, the most appropriate one was chosen for the detailed judgement of aging management review in our PSR being based on the Standard Review Plan for License Renewal (SRP-LR) in United States considering potential future usage in the judgement for continued operation of old NPP at the time of expiration of its design life. A draft PSR guidelines is prepared and attached by revision of basic guidelines issued in 2000, considering the issues discussed for the draft revision of IAEA PSR guide, the draft IAEA document about 'experience of PSR implementation of member states', and the characteristics of Hungarian PSR Guidelines.

  13. USGS National Seismic Hazard Maps

    Science.gov (United States)

    Frankel, A.D.; Mueller, C.S.; Barnhard, T.P.; Leyendecker, E.V.; Wesson, R.L.; Harmsen, S.C.; Klein, F.W.; Perkins, D.M.; Dickman, N.C.; Hanson, S.L.; Hopper, M.G.

    2000-01-01

    The U.S. Geological Survey (USGS) recently completed new probabilistic seismic hazard maps for the United States, including Alaska and Hawaii. These hazard maps form the basis of the probabilistic component of the design maps used in the 1997 edition of the NEHRP Recommended Provisions for Seismic Regulations for New Buildings and Other Structures, prepared by the Building Seismic Safety Council arid published by FEMA. The hazard maps depict peak horizontal ground acceleration and spectral response at 0.2, 0.3, and 1.0 sec periods, with 10%, 5%, and 2% probabilities of exceedance in 50 years, corresponding to return times of about 500, 1000, and 2500 years, respectively. In this paper we outline the methodology used to construct the hazard maps. There are three basic components to the maps. First, we use spatially smoothed historic seismicity as one portion of the hazard calculation. In this model, we apply the general observation that moderate and large earthquakes tend to occur near areas of previous small or moderate events, with some notable exceptions. Second, we consider large background source zones based on broad geologic criteria to quantify hazard in areas with little or no historic seismicity, but with the potential for generating large events. Third, we include the hazard from specific fault sources. We use about 450 faults in the western United States (WUS) and derive recurrence times from either geologic slip rates or the dating of pre-historic earthquakes from trenching of faults or other paleoseismic methods. Recurrence estimates for large earthquakes in New Madrid and Charleston, South Carolina, were taken from recent paleoliquefaction studies. We used logic trees to incorporate different seismicity models, fault recurrence models, Cascadia great earthquake scenarios, and ground-motion attenuation relations. We present disaggregation plots showing the contribution to hazard at four cities from potential earthquakes with various magnitudes and

  14. An Analysis of Cyber-Attack on NPP Considering Physical Impact

    Energy Technology Data Exchange (ETDEWEB)

    Lee, In Hyo; Kang, Hyun Gook [KAIST, Daejeon (Korea, Republic of); Son, Han Seong [Joonbu University, Geumsan (Korea, Republic of)

    2016-05-15

    Some research teams performed related works on cyber-physical system which is a system that cyber-attack can lead to serious consequences including product loss, damage, injury and death when it is attacked. They investigated the physical impact on cyber-physical system due to the cyber-attack. But it is hard to find the research about NPP cyber security considering the physical impact or safety. In this paper, to investigate the relationship between physical impact and cyber-attack, level 1 PSA results are utilized in chapter 2 and cyber-attack analysis is performed in chapter 3. The cyber security issue on NPP is inevitable issue. Unlike general cyber security, cyber-physical system like NPP can induce serious consequences such as core damage by cyber-attack. So in this paper, to find how hacker can attack the NPP, (1) PSA results were utilized to find the relationship between physical system and cyber-attack and (2) vulnerabilities on digital control systems were investigated to find how hacker can implement the possible attack. It is expected that these steps are utilized when establishing penetration test plans or cyber security drill plans.

  15. Filtration Algorithms of Untrustworthy Analogous Information in APCS at TPP and NPP

    Directory of Open Access Journals (Sweden)

    V. Nazarov

    2012-01-01

    Full Text Available The paper considers filtration algorithms of untrustworthy analogous information in APCS at TTP and NPP that make it possible to identify credibility of information transmitted through communication channels in the form of signals and which are continuously changeable in the regime of real time.

  16. Assessing deposition levels of 55Fe, 60Co and 63Ni in the Ignalina NPP environment

    DEFF Research Database (Denmark)

    Gudelis, A.; Druteikienė, R.; Lukšienė, B.

    2010-01-01

    Two RBMK-1500 reactor units operated in Lithuania in the 1987–2004 period (one of them was stopped for decommissioning in 2004). This study presents a preliminary investigation of surface deposition density levels of 55Fe and 63Ni in moss samples collected in the close vicinity of the Ignalina NPP...

  17. Activity level of gross α and gross β in airborne aerosol samples around the Qinshan NPP

    Institute of Scientific and Technical Information of China (English)

    CHEN Bin; YE Jida; CHEN Qianyuan; WU Xiaofei; SONG Weili; WANG Hongfeng

    2007-01-01

    The monitoring results of gross α and gross β activity from 2001 to 2005 for environmental airborne aerosol samples around the Qinshan NPP base are presented in this paper. A total of 170 aerosol samples were collected from monitoring sites of Caichenmen village, Qinlian village, Xiajiawan village and Yangliucun village around the Qinshan NPP base. The measured specific activity of gross α and gross β are in the range of 0.02 ~ 0.38 mBq/m3 and 0.10 ~ 1.81 mBq/m3, respectively, with an average of 0.11 mBq/m3 and 0.45mBq/m3, respectively. They are lower than the average of 0.15 mBq/m3 and 0.52mBq/m3, of reference site at Hangzhou City. It is indicated that the specific activity of gross α and gross β for environmental aerosol samples around the Qinshan NPP base had not been increased in normal operating conditions of the NPP.

  18. Replacement of battery in Asco NPP Chargers; Sustitucion de cargadores de baterias en C. N. Asco

    Energy Technology Data Exchange (ETDEWEB)

    Montero Lansanc, J.

    2013-07-01

    The purpose of this paper is to present the project to replace battery chargers at NPP Asco. It describes the reasons for the replacement, the project approach, the development to date and current status of the project, the economics, and some lessons learned during the process.

  19. [Specific Features of Scots Pine Seeds Formation in the Remote Period after the Chernobyl NPP Accident].

    Science.gov (United States)

    Geras'kin, S A; Vasiliev, D V; Kuzmenkov, A G

    2015-01-01

    The results of long-term (2007-2011) observations on the quality of seed progeny in Scots pine populations inhabiting the sites within the Bryansk region contaminated as a result of the Chernobyl NPP accident are presented. Formed under the chronic exposure seeds are characterized by a high interannual variability, which is largely determined by weather conditions.

  20. Effect of dietary NPP level and phytase supplementation on the laying performance over one year period

    Directory of Open Access Journals (Sweden)

    Annamaria Tischler

    2015-06-01

    Full Text Available Our trial was aimed to study the effect of different dietary non-phytin phosphorus (NPP levels with and without phytase enzyme supplementation on laying performance and eggshell quality of Tetra SL-LL in the last 25 weeks of the long-term (17 months egg production. A total of 69 Tetra SL-LL layers were allocated into 3 dietary treatments. Two diets with different levels of NPP (2.45 or 2.15 g/kg, HP and LP, respectively were formulated, and 0 or 300 FTU/kg phytase enzyme was added to low NPP feed (LP and LP+E, respectively. Dietary Ca was uniformly adjusted (38.2 g/kg to feed in each treatment. In the course of the trial, intensity of egg production (%, egg weight (g/egg, number of the broken eggs and feed intake (g/d/bird were recorded. Every 2 weeks 20 eggs per treatment were broken to determine the shell strength and thickness. Our results show that low NPP diet had detrimental effect on the intensity of egg production (P<0.05 and phytase added to the LP diet resulted the lowest number of broken eggs (P<0.05. In conclusion, NPP content of the layer diet can be reduced from 2.45 to 2.15 g/kg in the last 25 weeks of the elongated laying term (12-17 month of laying, if supplemented with 300 FTU/kg phytase enzyme without compromising the egg production, and in the same time it can improve eggshell quality and reduce the number of broken eggs.

  1. The Contribution of Paleoseismology to Seismic Hazard Assessment in Site Evaluation for Nuclear Installations

    Science.gov (United States)

    Decker, Kurt; Guerrieri, Luca; Fukushima, Yoshimitsu

    2015-04-01

    In the framework of site evaluation/re-evaluation procedures for nuclear power plants (NPP), paleoseismology plays an essential role not only for Fault Displacement Hazard Assessment (FDHA) but also for Seismic Hazard Assessment (SHA). The relevance of paleoseismology is recommended in the reference IAEA Safety Guide (IAEA SSG-9) and has been dramatically confirmed in recent time especially after the accident at the Fukushima Daiichi NPP caused by the disastrous great Tohoku earthquake and tsunami occurred on 11 March 2011. After this event, the IAEA International Seismic Safety Center promoted a technical document aimed at encouraging and supporting Member States, especially from newcomer countries, to include paleoseismic investigations into the geologic database, highlighting the value of earthquake geology studies and paleoseismology for nuclear safety and providing standard methodologies to perform such investigations. In detail, paleoseismic investigations in the context of site evaluation of nuclear installations have the following main objectives: i) identification of seismogenic structures based on the recognition of effects of past earthquakes in the regional area; ii) improvement of the completeness of earthquake catalogs, through the identification and dating of ancient moderate to large earthquakes, whose trace has been preserved in the geologic records; iii) estimation of the maximum seismic potential associated with an identified seismogenic structure/source, typically on the basis of the amount of displacement per event (evaluable in paleoseismic trenches), as well as of the geomorphic and stratigraphic features interpretable as the cumulative effect of repeated large seismic events (concept of "seismic landscape"); iv) rough calibration of probabilistic seismic hazard assessment (PSHA), by using the recurrence interval of large earthquakes detectable by paleoseismic investigations, and providing a "reality check" based on direct observations of

  2. 平西府车辆段与综合基地(运用库)高位隔震设计分析%High-position seismic isolation design of the Pingxifu vehicle depot and comprehensive base structures

    Institute of Scientific and Technical Information of China (English)

    黄跃斌; 杨铮; 万红宇; 冯慧君; 朱兴刚

    2011-01-01

    基于高位隔震结构的动力特性及影响高位隔震结构隔震效果的主要参数——频率比、质量比,介绍了地震波的选取及输入方式和高位隔震结构隔震层、隔震层以上结构、隔震层以下结构的抗震性能目标,以及振型分解反应谱法中隔震支座等效刚度的计算方法。采用ETABS软件对高位隔震结构进行计算分析,采用ETABS中Link单元模拟隔震支座,进行了非线性时程法及振型分解反应谱法分析,同时采用了PKPM等效剪切刚度的计算方法。经过分析,高位隔震结构隔震层以上结构可按降低一度进行设计,隔震层、隔震层以下结构能够达到预期抗震设防目标,并验证了PKPM简化计算方法的可行性。%The high-position seismic-isolated structure characteristic and the main parameters:frequency ratio and mass ratios are discussed which effect the isolated structure.The design method is introduced,such as the selection of the earthquake wave and its input methods,the anti-seismic aims of the isolation layer of structure and the structure above/below the layer,the rubber bearings equivalent stiffness calculation for response spectrum method.The high-position seismic-isolation structure was analyzed by ETABS program,in which simulates rubber bearings by unit Link,and was studied by the nonlinear time-history method and response spectrum method,and the equivalent shear stiffness of PKPM calculation method was also used.The structure above the isolation layer of the high-position seismic-isolation structure can reduce one degree to design.The isolation layer and the below structure can meet the expected anti-seismic goals.The correctness of the simplified calculation method of PKPM software is veified.

  3. Review of the seismic risk in the design of civil engineering of nuclear installations excepted the long term storage of radioactive wastes; Prise en compte du risque sismique a la conception des ouvrages de genie civil d'installations nucleaires de base a l'exception des stockages a long terme des dechets radioactifs

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2006-07-01

    This guide aims to define, for the nuclear installations excepted the long term storage of radioactive wastes, from site data, the design specifications of earthquake resistant civil engineering and the possible methods for: the determination of the seismic response of the buildings, taking into account the interactions with the materials and the evaluation of the associated strains to size the installation; the determination of seismic displacements to be considered to size the materials. (A.L.B.)

  4. The use of simulators for the training of the NPP licensed personnel; El uso de los simuladores de adiestramiento como apoyo para el ajuste de sistemas de instrumentacion y control

    Energy Technology Data Exchange (ETDEWEB)

    Ortega, F.; Ruiz, J. A.

    2005-07-01

    The full scope simulators used for the training of the NPP licensed personnel, are characterised by the integration of models of all the systems of the plant, so that a real time integrated response with a high degree of physical and functional fidelity may be provided. Due to these features, these simulators have showed high capabilities in the engineering field where they can support with effectiveness the design and tuning of I and C plant modifications. (Author)

  5. Study on Seismic Zoning of Sino-Mongolia Arc Areas

    Science.gov (United States)

    Xu, G.

    2015-12-01

    According to the agreement of Cooperation on seismic zoning between Institute of Geophysics, China Earthquake Administration and Research Center of Astronomy and Geophysics, Mongolian Academy of Science, the data of geotectonics, active faults, seismicity and geophysical field were collected and analyzed, then field investigation proceeded for Bolnay Faults, Ar Hutul Faults and Gobi Altay Faults, and a uniform earthquake catalogue of Mongolia and North China were established for the seismic hazard study in Sino-Mongolia arc areas. Furthermore the active faults and epicenters were mapped and 2 seismic belts and their 54 potential seismic sources are determined. Based on the data and results above mentioned the seismicity parameters for the two seismic belts and their potential sources were studied. Finally, the seismic zoning with different probability in Sino-Mongolia arc areas was carried out using China probabilistic hazard analysis method. By analyzing the data and results, we draw the following main conclusions. Firstly, the origin of tectonic stress field in the study areas is the collision and pressure of the India Plate to Eurasian Plate, passing from the Qinghai-Tibet Plateau. This is the reason why the seismicity is higher in the west than in the east, and all of earthquakes with magnitude 8 or greater occurred in the west. Secondly, the determination of the 2 arc seismic belts, Altay seismic belt and Bolnay-Baikal seismic belt, are reasonable in terms of their geotectonic location, geodynamic origin and seismicity characteristics. Finally, there are some differences between our results and the Mongolia Intensity Zoning map published in 1985 in terms of shape of seismic zoning map, especially in the areas near Ulaanbaatar. We argue that our relsults are reasonable if we take into account the data use of recent study of active faults and their parameters, so it can be used as a reference for seismic design.

  6. Measurement of the stressed state of welded joints in the NPP process components and circulation pipelines based on acoustoelasticity theory

    Directory of Open Access Journals (Sweden)

    A.I. Trofimov

    2016-09-01

    Full Text Available The paper presents the results of a theoretical justification and an experimental research for a method to measure the stressed state of welded joints in the nuclear power plant (NPP process components and circulation pipelines based on acoustoelasticity theory, as well as for ways to implement them technically. Devices for measuring the stressed state of welded joints in the NPP process components and circulation pipelines based on acoustoelasticity theory allow online measurement of residual stresses along the weld height and detection of crack formation points. The use of such devices will enable early crack detection in welded joints for an increased safety of the NPP operation.

  7. Design of a Technical Consulting System on Seismic Safety of Rural Buildings%农居地震安全技术咨询系统的设计

    Institute of Scientific and Technical Information of China (English)

    袁中夏; 贾冠华; 夏坤; 蔡宗文

    2013-01-01

    Easily understood and practical technology consulting on earthquake safety can help rural residents improve the seismic safety of their homes on one hand and promote awareness on seismic safety in rural areas on the other.This paper discussed the main idea and algorithm of "web-based consultation system for technology consulting on seismic safety of rural buildings".This system includes consultation inquiry,seismic safety assessment and consultation results output.The system combined earthquake investigation data,relevant standard and input information to provide recommendations on general terms such as building structure,geological hazard,foundation treatment and infrastructure construction.This study makes a new effort in providing necessary seismic safety information service for improving seismic safety of rural houses.%提供简易实用的农居地震安全技术咨询,既可以使农民得到农居地震安全方面的技术帮助,也有利于提高农民对地震安全的认识.本文讨论了基于网络环境的农居地震安全技术咨询系统的技术思路和主要算法.该系统主要由咨询条件输入、地震安全信息预处理及地震安全分析计算和咨询结果输出3部分构成.系统合理利用震害经验总结及相关规范,通过输入信息,提供农居基本的结构选型、场地灾害、地基处理和基础施工方面的信息.然后根据各项条件对农居地震安全的影响,提供基于网络的农居地震安全技术咨询.本项工作是农村震害防御信息服务方面的新尝试.

  8. 大容量机组空冷支架结构抗震设计方法研究%STUDY OF THE SEISMIC DESIGN METHOD OF AIR COOLED CONDENSER SUPPORT STRUCTURE SYSTEM IN HIGH-CAPACITY THERMAL POWER PLANT

    Institute of Scientific and Technical Information of China (English)

    刘林; 白国良; 薛群虎; 代慧娟

    2014-01-01

    大容量机组空冷支架结构属质量和刚度沿竖向分布不均匀的竖向混合结构,结构的扭转效应明显,地震作用复杂。大直径钢筋混凝土薄壁管柱为结构的主要抗侧力构件和耗能构件,结构抗震防线过于单一。强烈地震作用下,混凝土管柱底部及柱顶钢桁架连接部位为抗震设计的关键部位。目前,对大容量机组空冷支架结构抗震设计缺乏系统研究,国家相关规范对这方面内容很少涉及。为了确保空冷支架结构的安全,在模型抗震性能试验和大直径薄壁管柱承载力试验的基础上,提出了大容量机组空冷支架结构抗震设计方法和抗震构造措施。%Support structure of air cooled condenser is a typical vertical hybrid structure whose stiffness and mass are non-uniform at vertical direction; torsion effect of the structure is obvious , earthquake response of the structure is complex.Research results show that the large-diameter and thin-walled reinforced concrete pipe columns are main lateral force resisting members in the structure , the damage of the structure is mainly concentrated on the bottom of the columns, structure’s earthquake resistance fortification is simplex .For lacking of systematic study on the seismic design method of this kind of structure , and little of its design cortents is involved in the national standards .In order to guarantee the safety of the support structure and equipment under earthquake action , based on the seismic behavior test of model structure and bearing capacity test of large-diameter and thin-walled reinforced concrete pipe columns , seismic design method and seismic measure are put forward to design support structure of air cooled condenser .

  9. Angola Seismicity MAP

    Science.gov (United States)

    Neto, F. A. P.; Franca, G.

    2014-12-01

    The purpose of this job was to study and document the Angola natural seismicity, establishment of the first database seismic data to facilitate consultation and search for information on seismic activity in the country. The study was conducted based on query reports produced by National Institute of Meteorology and Geophysics (INAMET) 1968 to 2014 with emphasis to the work presented by Moreira (1968), that defined six seismogenic zones from macro seismic data, with highlighting is Zone of Sá da Bandeira (Lubango)-Chibemba-Oncócua-Iona. This is the most important of Angola seismic zone, covering the epicentral Quihita and Iona regions, geologically characterized by transcontinental structure tectono-magmatic activation of the Mesozoic with the installation of a wide variety of intrusive rocks of ultrabasic-alkaline composition, basic and alkaline, kimberlites and carbonatites, strongly marked by intense tectonism, presenting with several faults and fractures (locally called corredor de Lucapa). The earthquake of May 9, 1948 reached intensity VI on the Mercalli-Sieberg scale (MCS) in the locality of Quihita, and seismic active of Iona January 15, 1964, the main shock hit the grade VI-VII. Although not having significant seismicity rate can not be neglected, the other five zone are: Cassongue-Ganda-Massano de Amorim; Lola-Quilengues-Caluquembe; Gago Coutinho-zone; Cuima-Cachingues-Cambândua; The Upper Zambezi zone. We also analyzed technical reports on the seismicity of the middle Kwanza produced by Hidroproekt (GAMEK) region as well as international seismic bulletins of the International Seismological Centre (ISC), United States Geological Survey (USGS), and these data served for instrumental location of the epicenters. All compiled information made possible the creation of the First datbase of seismic data for Angola, preparing the map of seismicity with the reconfirmation of the main seismic zones defined by Moreira (1968) and the identification of a new seismic

  10. Seismic margins and calibration of piping systems

    Energy Technology Data Exchange (ETDEWEB)

    Shieh, L.C.; Tsai, N.C.; Yang, M.S.; Wong, W.L.

    1985-01-01

    The Seismic Safety Margins Research Program (SSMRP) is a US Nuclear Regulatory Commission-funded, multiyear program conducted by Lawrence Livermore National Laboratory (LLNL). Its objective is to develop a complete, fully coupled analysis procedure for estimating the risk of earthquake-induced radioactive release from a commercial nuclear power plant and to determine major contributors to the state-of-the-art seismic and systems analysis process and explicitly includes the uncertainties in such a process. The results will be used to improve seismic licensing requirements for nuclear power plants. In Phase I of SSMRP, the overall seismic risk assessment methodology was developed and assembled. The application of this methodology to the seismic PRA (Probabilistic Risk Assessment) at the Zion Nuclear Power Plant has been documented. This report documents the method deriving response factors. The response factors, which relate design calculated responses to best estimate values, were used in the seismic response determination of piping systems for a simplified seismic probablistic risk assessment. 13 references, 31 figures, 25 tables.

  11. Seismic base isolation technologies for Korea advanced liquid metal reactor

    Energy Technology Data Exchange (ETDEWEB)

    Yoo, B.; Lee, J.-H.; Koo, G.-H.; Lee, H.-Y.; Kim, J.-B. [Korea Atomic Energy Research Inst., Taejon (Korea, Republic of)

    2000-06-01

    This paper describes the status and prospects of the seismic base isolation technologies for Korea Advanced Liquid Metal Reactor (KALIMER). The research and development program on the seismic base isolation for KALIMER began in 1993 by KAERI under the national long-term R and D program. The objective of this program is to enhance the seismic safety, to accomplish the economic design, and to standardize the plant design through the establishment of technologies on seismic base isolation for liquid metal reactors. In this paper, tests and analyses performed in the program are presented. (orig.)

  12. Development of seismic force requirements for buildings in Taiwan

    Science.gov (United States)

    Chai, Juin-Fu; Teng, Tsung-Jen; Tsai, Keh-Chyuan

    2009-09-01

    This paper describes static and dynamic procedures to calculate seismic demand specified by the current seismic design code for buildings in Taiwan, which was issued in 2005. For design levels with a return period of 475 years, the design spectral response acceleration can be developed for general sites, near-fault sites and Taipei Basin. In addition, in order to prevent building collapse during extremely large earthquakes and yielding of structural components and elements during frequent small earthquakes, the required seismic demands at the maximum considered earthquake level (MCE, 2%/50 years) and operational level are also included in the new seismic design code. For dynamic analysis procedures, both the response spectrum method and time history method are specified in the new seismic design code. Finally, procedures to generate spectrum compatible ground motions for time history analysis are illustrated in this paper.

  13. Development of seismic force requirements for buildings in Taiwan

    Institute of Scientific and Technical Information of China (English)

    Juin-Fu Chai; Tsung-Jen Teng; Keh-Chyuan Tsai

    2009-01-01

    This paper describes static and dynamic procedures to calculate seismic demand specified by the current seismic design code for buildings in Taiwan, which was issued in 2005. For design levels with a return period of 475 years, the design spectral response acceleration can be developed for general sites, near-fault sites and Taipei Basin. In addition, in order to prevent building collapse during extremely large earthquakes and yielding of structural components and elements during frequent small earthquakes, the required seismic demands at the maximum considered earthquake level (MCE, 2%/50 years) and operational level are also included in the new seismic design code.'For dynamic analysis procedures, both the response spectrum method and time history method are specified in the new seismic design code. Finally, procedures to generate spectrum compatible ground motions for time history analysis are illustrated in this paper.

  14. Seismic hazard map of the western hemisphere

    Science.gov (United States)

    Shedlock, K.M.; Tanner, J.G.

    1999-01-01

    Vulnerability to natural disasters increases with urbanization and development of associated support systems (reservoirs, power plants, etc.). Catastrophic earthquakes account for 60% of worldwide casualties associated with natural disasters. Economic damage from earthquakes is increasing, even in technologically advanced countries with some level of seismic zonation, as shown by the 1989 Loma Prieta, CA ($6 billion), 1994 Northridge, CA ($ 25 billion), and 1995 Kobe, Japan (> $ 100 billion) earthquakes. The growth of megacities in seismically active regions around the world often includes the construction of seismically unsafe buildings and infrastructures, due to an insufficient knowledge of existing seismic hazard. Minimization of the loss of life, property damage, and social and economic disruption due to earthquakes depends on reliable estimates of seismic hazard. National, state, and local governments, decision makers, engineers, planners, emergency response organizations, builders, universities, and the general public require seismic hazard estimates for land use planning, improved building design and construction (including adoption of building construction codes), emergency response preparedness plans, economic forecasts, housing and employment decisions, and many more types of risk mitigation. The seismic hazard map of the Americas is the concatenation of various national and regional maps, involving a suite of approaches. The combined maps and documentation provide a useful global seismic hazard framework and serve as a resource for any national or regional agency for further detailed studies applicable to their needs. This seismic hazard map depicts Peak Ground Acceleration (PGA) with a 10% chance of exceedance in 50 years for the western hemisphere. PGA, a short-period ground motion parameter that is proportional to force, is the most commonly mapped ground motion parameter because current building codes that include seismic provisions specify the

  15. Seismic hazard map of the western hemisphere

    Directory of Open Access Journals (Sweden)

    J. G. Tanner

    1999-06-01

    Full Text Available Vulnerability to natural disasters increases with urbanization and development of associated support systems (reservoirs, power plants, etc.. Catastrophic earthquakes account for 60% of worldwide casualties associated with natural disasters. Economic damage from earthquakes is increasing, even in technologically advanced countries with some level of seismic zonation, as shown by the 1989 Loma Prieta, CA ($ 6 billion, 1994 Northridge, CA ($ 25 billion, and 1995 Kobe, Japan (> $ 100 billion earthquakes. The growth of megacities in seismically active regions around the world often includes the construction of seismically unsafe buildings and infrastructures, due to an insufficient knowledge of existing seismic hazard. Minimization of the loss of life, property damage, and social and economic disruption due to earthquakes depends on reliable estimates of seismic hazard. National, state, and local governments, decision makers, engineers, planners, emergency response organizations, builders, universities, and the general public require seismic hazard estimates for land use planning, improved building design and construction (including adoption of building construction codes, emergency response preparedness plans, economic forecasts, housing and employment decisions, and many more types of risk mitigation. The seismic hazard map of the Americas is the concatenation of various national and regional maps, involving a suite of approaches. The combined maps and documentation provide a useful global seismic hazard framework and serve as a resource for any national or regional agency for further detailed studies applicable to their needs. This seismic hazard map depicts Peak Ground Acceleration (PGA with a 10% chance of exceedance in 50 years for the western hemisphere. PGA, a short-period ground motion parameter that is proportional to force, is the most commonly mapped ground motion parameter because current building codes that include seismic provisions

  16. Necessity and Design for Seismic Experiment of China Future Manned Moon Landing Missions%中国未来载人登月月震实验必要性和方案设计

    Institute of Scientific and Technical Information of China (English)

    赵娜; 朱培民; 袁悦锋; 金丹

    2012-01-01

    Since Apollo passive seismic network just covers a relatively limited area on the lunar nearside, the internal structure of whole Moon can not be detected accurately. It is necessary to perform seismic experiments in future Chinese manned Moon landing missions. According to technological condition of space investigation and the future missions of manned Moon landing in our country, we design two schemes of lunar seismic network. The first is a basic scheme which can basically meet the demand for detecting the internal structure. The second is an optimizing scheme which can obtain high-resolution internal structure of the Moon. Both seismic networks cover nearside, farside, south and north poles, which can detect internal structure of the whole Moon. In addition, this paper also provides possible technological parameters, instruments and appropriate sites for deployment of seismic experiments.%Apollo被动月震台站仅覆盖了月球正面有限的面积,不能对全月球的内部结构进行精细分析,因此在我国未来的载人登月中继续开展月震探测是非常必要的.基于我国现有的空间探测技术条件,并针对未来载人登月的探测任务,设计了两种月震观测网络方案:一是基本方案,可以基本满足对月球内部结构进行探测的要求;二是优化方案,可满足较高分辨率的月球内部结构探测.两种方案中的月震仪网络在月球正面、背面和南北极均有覆盖,可对全月球的内部结构进行探测.最后对月震观测的基本技术参数、设备及布置地点提出了相应的要求.

  17. Considerations related to housing and seismic risk

    Directory of Open Access Journals (Sweden)

    Oana Luca

    2016-06-01

    Full Text Available The paper aims to present the main problems related to the seismic risk and housing in urban settlements in Romania, with special focus on Bucharest, which is the most exposed city. The paper emphasizes the framework related to evolution of technical regulations and seismic safety of residential buildings, highlighting the main dysfunctions in the National Program for Seismic Retrofitting. At the same time, because the collapse of a single residential building may have major negative effects on the surrounding area (buildings, streets, utilities etc., the paper is proposing a methodology for evaluation of damages which may appear in such a case. The article is also suggesting several solutions for improving the design and expertise process and also for the seismic retrofitting of vulnerable buildings, especially housing.

  18. NPP-VIIRS DNB-based reallocating subpopulations to mercury in Urumqi city cluster, central Asia

    Science.gov (United States)

    Zhou, X.; Feng, X. B.; Dai, W.; Li, P.; Ju, C. Y.; Bao, Z. D.; Han, Y. L.

    2017-02-01

    Accurate and update assignment of population-related environmental matters onto fine grid cells in oasis cities of arid areas remains challenging. We present the approach based on Suomi National Polar-orbiting Partnership (S-NPP) -Visible Infrared Imaging Radiometer Suite (VIIRS) Day/Night Band (DNB) to reallocate population onto a regular finer surface. The number of potential population to the mercury were reallocated onto 0.1x0.1 km reference grid in Urumqi city cluster of China’s Xinjiang, central Asia. The result of Monte Carlo modelling indicated that the range of 0.5 to 2.4 million people was reliable. The study highlights that the NPP-VIIRS DNB-based multi-layered, dasymetric, spatial method enhances our abilities to remotely estimate the distribution and size of target population at the street-level scale and has the potential to transform control strategies for epidemiology, public policy and other socioeconomic fields.

  19. A comprehensive Aging Management Program of a German NPP

    Energy Technology Data Exchange (ETDEWEB)

    Wildner, U.

    2014-07-01

    The majority of System, Structure and Components (SSC) in a nuclear power plants are designed to experience a service life, which is far above the intended design life. In most cases, only a small percentage of SSCs are subject to significant aging effects, which may affect the integrity or the function of the component. The process of aging management (AM) has the objective to monitor and control degradation effects which may compromise safety functions of the plant. And furthermore, to ensure, that testing and maintenance programs sufficiently provide preventive measures to control degradation effects. (Author)

  20. Seismic base isolation in practice: The California experience

    Energy Technology Data Exchange (ETDEWEB)

    Naeim, F. [John A. Martin and Associates, Inc., Los Angeles, CA (United States); Lew, M. [Law/Crandall, Inc., Los Angeles, CA (United States)

    1995-12-01

    Seismic base isolation systems of various forms and features have been implemented in design of many new buildings and in rehabilitation of several existing structures. Currently, at least in California, the seismic isolation option is seriously considered at the onset of design of any hospital or health care facility project. While the design and implementation of seismic isolation systems seem to have been successful, there exist a multitude of problems which need to be addressed during each of the design, manufacturing, and construction processes to ensure a satisfactory end-result. The authors have been involved as structural and geotechnical engineers, as well as peer reviewers and plan checkers for many of the landmark California seismic isolated structures. This paper will provide a summary of state-of-the-practice and its problems for seismic isolated building structures.

  1. RADIATION HYGIENIC CONSEQUENCES OF THE ACCIDENT AT THE CHERNOBYL NPP AND THE TASKS OF THEIR MINIMIZATION

    Directory of Open Access Journals (Sweden)

    G. G. Onischenko

    2009-01-01

    Full Text Available The paper presents data on the role and results of activities of Rospotrebnadzor bodies and institutions in the field of ensuring population radiation protection during various periods since accident at the Chernobyl NPP. Radiation hygienic characterization of territories affected by radioactive contamination from the accident, population exposure dose range, issues of ensuring radiological well-being of population and ways of their solution are being presented in the paper.

  2. Optimization of the energy complex “NPP-accumulator” in case of force majeure

    Science.gov (United States)

    Zaluzhnaya, G.; Zagrebaev, A.

    2017-01-01

    We consider a problem of optimization of NPP with accumulator operation mode in case of force majeure. A mathematical formulation and solving of problem of energy output’s time behavior is provided. A mathematical formulation and solving of problem of energy’s optimum allocation to consumers with different priorities. Mathematically, the problem reduces to linear programming problem. We received that optimal time behavior is uniform energy output, and one should start with consumer with highest priority.

  3. Deterministic and Probabilistic Analysis of NPP Communication Bridge Resistance Due to Extreme Loads

    Directory of Open Access Journals (Sweden)

    Králik Juraj

    2014-12-01

    Full Text Available This paper presents the experiences from the deterministic and probability analysis of the reliability of communication bridge structure resistance due to extreme loads - wind and earthquake. On the example of the steel bridge between two NPP buildings is considered the efficiency of the bracing systems. The advantages and disadvantages of the deterministic and probabilistic analysis of the structure resistance are discussed. The advantages of the utilization the LHS method to analyze the safety and reliability of the structures is presented

  4. Computer modeling and simulators as part of university training for NPP operating personnel

    Science.gov (United States)

    Volman, M.

    2017-01-01

    This paper considers aspects of a program for training future nuclear power plant personnel developed by the NPP Department of Ivanovo State Power Engineering University. Computer modeling is used for numerical experiments on the kinetics of nuclear reactors in Mathcad. Simulation modeling is carried out on the computer and full-scale simulator of water-cooled power reactor for the simulation of neutron-physical reactor measurements and the start-up - shutdown process.

  5. Retrofitting Design of Single-span Multi-story Concrete Frame Teaching Buildings With Seismic Reduction%单跨多层混凝土框架教学楼减震加固设计

    Institute of Scientific and Technical Information of China (English)

    高向宇; 徐帅; 郭运勇

    2015-01-01

    为了解决既有单跨多层混凝土框架存在的结构体系不合理、抗震能力差等问题,以某典型单跨多层混凝土框架为背景,采用防屈曲支撑( buckling-restrained brace,BRB)消能减震加固技术对其进行加固。梳理应用该技术的工程技术条件、减震加固方案的设计流程以及BRB加固连接方式的工程应用条件等,对某单跨教学楼进行直连式减震加固改造,进行非线性推覆分析和时程分析,完成节点构造抗震加固设计。研究结果表明:利用该技术加固单跨框架可行,且能达到较高的抗震设防目标要求。%In order to solve the problems of the existing single-span multi-story concrete frame buildings that the structural system is unreasonable and the seismic capacity is poor, and so on, a typical single-span multi-story concrete frame with energy dissipation and seismic reduction technique by using buckling-restrained braces(BRB) was strengthened. The technical conditions of the technique and the design flow of the strengthening scheme, and the technical applying conditions of the BRB reinforcement methods, etc. was summarized. Then a single-span teaching building was strengthed with the proposed technique of which the BRB was directly connected with the original frame, and the nonlinear pushover analysis and nonlinear time history analysis were made, and the joint seismic strengthening design was completed. It shows that the proposed correlative technique is practicable to strengthen single-span concrete buildings and able to achieve the requirements of higher seismic fortification goal.

  6. Estimation of Net Primary Production (NPP) of Inner Mongolia in China

    Science.gov (United States)

    Park, J.; Kwak, Y.; Yasuda, Y.

    2009-12-01

    1. Introduction In the latter part of 1970's, the need for more precise calculation of the fixed-quantity of global land vegetation was emphasized. This data is necessary for estimating carbon income and expenditure at a global level. Research at the Mauna Loa volcano has clearly shown that the density of CO2 in the atmosphere is increasing. This increase is caused mainly by changes in human activities and the respiration of plants and animals. At present, however, the value of CO2 income and expenditure as calculated for human activities does not agree with the value thought to be contained in the marine and terrestrial carbon sinks. Clearly the value of primary production needs to be measured more precisely on a global scale. The use of satellite data immediately enables application at a global level, leading to higher precision of estimation when analyzing ecosystem models. In this study, we analyzed and compared Hohhot and Naiman, two regions in Inner Mongolia. In situ observation data (biomass and reflection data for each type of vegetation) was collected from 1999 to 2002. The results of these ground observations were then compared to the results from wide area measurement of vegetation index utilizing Terra/MODIS data 2. Application to satellite data The MODIS Surface Reflectance product (MOD09), with resolution of 250m, was utilized from April to November of 2002. MOD09 did atmosphere correction and geometric correction. Bands 1 (RED : 620-670nm) and 2 (NIR : 841-876nm) from MOD09 were used to produce a NDVI image. In addition, to remove the influence of cloud cover, monthly vegetation index images for May to September were generated using the Temporal Window Operation method (TWO : Park et al.1999), with the mid day of each month designated as a representative day. 3. Conclusion In this study, we estimate Net Primary Production (NPP) for a semiarid region of northern China using satellite data. An area in which pasturage is prohibited was studied in 1999

  7. Integrated risk assessment for multi-unit NPP sites—A comparison

    Energy Technology Data Exchange (ETDEWEB)

    Kumar, C. Senthil, E-mail: cskumar@igcar.gov.in [AERB-Safety Research Institute, Kalpakkam (India); Hassija, Varun; Velusamy, K. [Reactor Design Group, Indira Gandhi Centre for Atomic Research, Kalpakkam (India); Balasubramaniyan, V. [AERB-Safety Research Institute, Kalpakkam (India)

    2015-11-15

    Highlights: • Framework for integrated risk assessment for multi-unit NPP sites. • Categorization of external and internal events. • Modelling of key issues: mission time, cliff-edge, common cause failures, etc. • Safety goals for multi-unit NPP sites. • Comparison of site core damage frequency in one, two, three and four unit sites. - Abstract: Most of the nuclear power producing sites in the world houses multiple units. Such sites are faced with hazards generated from external events: earthquake, tsunami, flood, etc. and can threaten the safety of nuclear power plants. Further, risk from a multiple unit site and its impact on the public and environment was evident during the Fukushima nuclear disaster in March 2011. It is therefore important to evolve a methodology to systematically assess the risk from multi-unit site. For a single unit site, probabilistic risk assessment technique identifies the potential accident scenarios, their consequences, and estimates the core damage frequency that arise due to internal and external hazards. This challenging task becomes even more complex for a multiple unit site, especially when the external hazards that has the potential to generate one or more correlated hazards or a combination of non-correlated hazards are to be modelled. This paper presents an approach to evaluate risk for multiple NPP sites and also compare the risk for sites housing single, double and multiple nuclear plants.

  8. The Fukushima Dai-ichi NPP accident crisis and its influence on energy policy in Japan

    Energy Technology Data Exchange (ETDEWEB)

    Uchida, Shunsuke; Naitoh, Masanori; Okada, Hidetoshi; Suzuki, Hiroaki [Institute of Applied Energy, Tokyo (Japan)

    2011-10-15

    Fossil fuel power plants (FPPs) and nuclear power plants (NPPs) along the northern Pacific coast of Japan experienced a mega earthquake and resulting tsunamis on March 11, 2011, which resulted in serious damage. More than half of the FPPs have returned to supplying electricity, while all NPPs are still shut down. In particular, Fukushima Dai-ichi Nuclear Power Plant (NPP) of the Tokyo Electric Power Co. experienced a nuclear accident crisis unprecedented in both scale and timeframe. This paper gives a brief overview of the events and their propagation based on the International Atomic Energy Agency (IAEA) report and the authors' studies on accident analysis, and offers considerations on root causes of the propagation, e.g., problems in hardware, software and accident management, by comparing the responses of Fukushima Dai-ichi NPP with those of other reactors at the Fukushima Dai-ni, Tokai, Onagawa and Higashidori NPPs, where cold shutdowns were successfully maintained even though they had also been affected by the earthquake and tsunamis. Future technical subjects for safe NPP operation and the influence of the events on Japanese energy policy are presented. (orig.)

  9. Evaluation of radiation safety for storage o high integrity container in Yonggwang NPP

    Energy Technology Data Exchange (ETDEWEB)

    Kwak, Sang Soo; Park, Seung Chil; Ha, Jong Hyun; Kim, Byung Tae [Nuclear Environment Technology Institute, KEPCO, Taejon (Korea, Republic of)

    1999-07-01

    In order to reduce the generation of radioactive waste in Yonggwang NPP, the spent resin dry system(SRDS) will be used for treatment of spent resin. According to operation of SRD, a different container will be required for containment of spent resin instead of DOT-17H drum. Therefore, the high integrity container (HIC) which is manufactured for disposal will be used for containment of spent resin generated from SRDS. Because the HIC contained with spent resin as high radioactivity and high radiation dose rate, a special attention in handling of HIC and storage of HIC in radioactive waste storage building should be paid. Accordingly, it is necessary to prepare the program for safe storage of HIC. Several options on storage of HIC into the radioactive waste storage building in Yonggwang NPP were established. Depending on the field conditions, it can be of help to the choice of pertinent method for safe and effective storage of HIC. In this report, the radiation safety of each option on the storage of HIC was evaluated and it shows that any option can be adapted as an effective storage method for Younggwang NPP if some problems appeared through the radiation safety evaluation are resolved. (author)

  10. Numerical Methods for an Analysis of Hydrogen Behaviors Coupled with Thermal Hydraulics in a NPP Containment

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Jongtae; Park, Rae-Joon; Hong, Seong-Wan; Kim, Gun-Hong [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2016-10-15

    In a containment safety analysis, multi-dimensional characteristics in thermal hydraulics are very important because the flow paths are not confined in a large free volume of the containment. The analysis is difficult because of a difference in length scales between a characteristic length of the flow and representative length of the containment. In order to simulate hydrogen and steam behaviors in a containment during postulated severe accidents, the GASFLOW code as a multi-dimensional analysis tool for NPP containment has been used for years because of its computational efficiency. Though GASFLOW is well developed for a real NPP containment analysis, there exist shortcomings in nodalization, two-phase and turbulence models. It is based on a Cartesian or cylindrical coordinate mesh, so it is impractical to refine a mesh locally in a region with a physical or geometrical complication. In this paper, the importance of the hydrogen safety in an NPP containment and requirements of the analysis tool was described. And physical models necessary for the hydrogen safety analysis code were listed. As a member of international collaborative project HYMERES for containment thermal hydraulics, KAERI is actively participating in an analytic working group. As an analysis tool for blind benchmarkes, the analysis code described in this paper was used. From the blind benchmark analyses, it was found that the code is very promising for hydrogen safety analysis. Currently, it is proposed to develop the code collaboratively in a hydrogen safety community based on an open-source strategy.

  11. Conformity Between LR0 Mock-Ups and Vvers Npp Rpv Neutron Flux Attenuation

    Science.gov (United States)

    Belousov, Sergey; Ilieva, Krassimira; Kirilova, Desislava

    2009-08-01

    The conformity of the mock-up results and those for reactor pressure vessel (RPV) of nuclear power plants (NPP) has been evaluated in order to qualify if the mock-ups data could be used for benchmark's purpose only, or/and for simulating of the NPP irradiation conditions. Neutron transport through the vessel has been calculated by the three-dimensional discrete ordinate code TORT with problem oriented multigroup energy neutron cross-section library BGL. Neutron flux/fluence and spectrum shape represented by normalized group neutron fluxes in the multigroup energy structure, for neutrons with energy above 0.5 MeV, have been used for conformity analysis. It has been demonstrated that the relative difference of the attenuation factor as well as the group neutron fluxes did not exceed 10% at all considered positions for VVER-440. For VVER-1000, it has been obtained the same consistency, except for the location behind the RPV. The neutron flux attenuation behind the RPV is 18% higher than the mock-up attenuation. It has been shown that this difference arises from the dissimilarity of the biological shielding. The obtained results have demonstrated that the VVERs' mock-ups are appropriate for simulating the NPP irradiation conditions. The mock-up results for VVER-1000 have to be applied more carefully i.e. taking into account the existing peculiarity of the biological shielding and RPV attenuation azimuthal dependence.

  12. Seismic Catalogue and Seismic Network in Haiti

    Science.gov (United States)

    Belizaire, D.; Benito, B.; Carreño, E.; Meneses, C.; Huerfano, V.; Polanco, E.; McCormack, D.

    2013-05-01

    The destructive earthquake occurred on January 10, 2010 in Haiti, highlighted the lack of preparedness of the country to address seismic phenomena. At the moment of the earthquake, there was no seismic network operating in the country, and only a partial control of the past seismicity was possible, due to the absence of a national catalogue. After the 2010 earthquake, some advances began towards the installation of a national network and the elaboration of a seismic catalogue providing the necessary input for seismic Hazard Studies. This paper presents the state of the works carried out covering both aspects. First, a seismic catalogue has been built, compiling data of historical and instrumental events occurred in the Hispaniola Island and surroundings, in the frame of the SISMO-HAITI project, supported by the Technical University of Madrid (UPM) and Developed in cooperation with the Observatoire National de l'Environnement et de la Vulnérabilité of Haiti (ONEV). Data from different agencies all over the world were gathered, being relevant the role of the Dominican Republic and Puerto Rico seismological services which provides local data of their national networks. Almost 30000 events recorded in the area from 1551 till 2011 were compiled in a first catalogue, among them 7700 events with Mw ranges between 4.0 and 8.3. Since different magnitude scale were given by the different agencies (Ms, mb, MD, ML), this first catalogue was affected by important heterogeneity in the size parameter. Then it was homogenized to moment magnitude Mw using the empirical equations developed by Bonzoni et al (2011) for the eastern Caribbean. At present, this is the most exhaustive catalogue of the country, although it is difficult to assess its degree of completeness. Regarding the seismic network, 3 stations were installed just after the 2010 earthquake by the Canadian Government. The data were sent by telemetry thought the Canadian System CARINA. In 2012, the Spanish IGN together

  13. Atucha II NPP full scope simulator modelling with the thermal hydraulic code TRAC{sub R}T

    Energy Technology Data Exchange (ETDEWEB)

    Alonso, Pablo Rey; Ruiz, Jose Antonio; Rivero, Norberto, E-mail: prey@tecnatom.e, E-mail: jaruiz@tecnatom.e, E-mail: nrivero@tecnatom.e [Tecnatom S.A., Madrid (Spain)

    2011-07-01

    In February 2010 NA-SA (Nucleoelectrica Argentina S.A.) awarded Tecnatom the Atucha II full scope simulator project. NA-SA is a public company owner of the Argentinean nuclear power plants. Atucha II is due to enter in operation shortly. Atucha II NPP is a PHWR type plant cooled by the water of the Parana River and has the same design as the Atucha I unit, doubling its power capacity. Atucha II will produce 745 MWe utilizing heavy water as coolant and moderator, and natural uranium as fuel. A plant singular feature is the permanent core refueling. TRAC{sub R}T is the first real time thermal hydraulic six-equations code used in the training simulation industry for NSSS modeling. It is the result from adapting to real time the best estimate code TRACG. TRAC{sub R}T is based on first principle conservation equations for mass, energy and momentum for liquid and steam phases, with two phase flows under non homogeneous and non equilibrium conditions. At present, it has been successfully implemented in twelve full scope replica simulators in different training centers throughout the world. To ease the modeling task, TRAC{sub R}T includes a graphical pre-processing tool designed to optimize this process and alleviate the burden of entering alpha numerical data in an input file. (author)

  14. An economical educational seismic system

    Science.gov (United States)

    Lehman, J. D.

    1980-01-01

    There is a considerable interest in seismology from the nonprofessional or amateur standpoint. The operation of a seismic system can be satisfying and educational, especially when you have built and operated the system yourself. A long-period indoor-type sensor and recording system that works extremely well has been developed in the James Madison University Physics Deparment. The system can be built quite economically, and any educational institution that cannot commit themselves to a professional installation need not be without first-hand seismic information. The system design approach has been selected by college students working a project or senior thesis, several elementary and secondary science teachers, as well as the more ambitious tinkerer or hobbyist at home 

  15. Experience gained from the development and results from tests of the equipment of the Kalinin NPP Unit 4 regeneration and intermediate steam separation and reheating system

    Science.gov (United States)

    Trifonov, N. N.; Sukhorukov, Yu. G.; Ermolov, V. F.; Svyatkin, F. A.; Nikolaenkova, E. K.; Sintsova, T. G.; Grigor'eva, E. B.; Esin, S. B.; Ukhanova, M. G.; Golubev, E. A.; Bik, S. P.; Tren'kin, V. B.

    2014-06-01

    The equipment of the Kalinin NPP Unit 4 regeneration, intermediate separation, and steam reheating (ISSR) systems is described and the results of their static and dynamic tests are presented. It was shown from an analysis of test results that the equipment of the regeneration and ISSR systems produce the design thermal and hydraulic characteristics in static and dynamic modes of its operation. Specialists of the Central boiler-Turbine Institute Research and Production Association have developed procedures and computer programs for calculating the system of direct-contact horizontal low-pressure heaters (connected according to the gravity circuit arrangement jointly with the second-stage electrically-driven condensate pumps) and the ISSR system, the results of which are in satisfactory agreement with experimental data. The drawbacks of the layout solutions due to which cavitation failure of the pumps may occur are considered. Technical solutions aimed at securing stable operation of the equipment of regeneration and ISSR systems are proposed. The process arrangement for heating the chamber-type high-pressure heaters adopted at the Kalinin NPP is analyzed. The version of this circuit developed at the Central Boiler-Turbine Institute Research and Production Association that allows the heating rate equal to 1°C/min to be obtained is proposed.

  16. Seismic Risk Perception compared with seismic Risk Factors

    Science.gov (United States)

    Crescimbene, Massimo; La Longa, Federica; Pessina, Vera; Pino, Nicola Alessandro; Peruzza, Laura

    2016-04-01

    The communication of natural hazards and their consequences is one of the more relevant ethical issues faced by scientists. In the last years, social studies have provided evidence that risk communication is strongly influenced by the risk perception of people. In order to develop effective information and risk communication strategies, the perception of risks and the influencing factors should be known. A theory that offers an integrative approach to understanding and explaining risk perception is still missing. To explain risk perception, it is necessary to consider several perspectives: social, psychological and cultural perspectives and their interactions. This paper presents the results of the CATI survey on seismic risk perception in Italy, conducted by INGV researchers on funding by the DPC. We built a questionnaire to assess seismic risk perception, with a particular attention to compare hazard, vulnerability and exposure perception with the real data of the same factors. The Seismic Risk Perception Questionnaire (SRP-Q) is designed by semantic differential method, using opposite terms on a Likert scale to seven points. The questionnaire allows to obtain the scores of five risk indicators: Hazard, Exposure, Vulnerability, People and Community, Earthquake Phenomenon. The questionnaire was administered by telephone interview (C.A.T.I.) on a statistical sample at national level of over 4,000 people, in the period January -February 2015. Results show that risk perception seems be underestimated for all indicators considered. In particular scores of seismic Vulnerability factor are extremely low compared with house information data of the respondents. Other data collected by the questionnaire regard Earthquake information level, Sources of information, Earthquake occurrence with respect to other natural hazards, participation at risk reduction activities and level of involvement. Research on risk perception aims to aid risk analysis and policy-making by

  17. Seismic Design on High Transfer of A High-rise Building beyond the Code Limit%某高位转换超限高层建筑结构抗震设计

    Institute of Scientific and Technical Information of China (English)

    陈达锋

    2013-01-01

    介绍了某商厦和酒店综合体超限高层建筑的结构设计和抗震性能分析,采用两种不同的力学模型分析软件,对该结构的整体及关键构件进行了模拟仿真分析,并对计算结果进行了有效分析比较.结果表明,该结构设计方案是安全可行的.%The seismic performance and the structural design of commercial building which is a high-rise building beyond the code limit are presented in this paper.The structure and main components are simulated with software of SATWE and ETABS,and the results are compared.It is concluded that the design is safety and reliability.

  18. Studies on the Needs of Seismic Base Isolation Concept and its Standardization

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Min-Seok; Kim, Jong-Hae [Korea Electric Association, Seoul (Korea, Republic of)

    2015-05-15

    In the late 1970s, seismic resistance design was introduced as a new design concept through the construction of nuclear power plants. Before this, lateral forces other than wind loads, such as seismic forces, were not taken into consideration in the structural design process. However, in response to the building of increasingly large and heavy structures such as nuclear power plants, a consensus began to form in society regarding the importance of seismic resistance design to avoid a largescale calamity. Since then, Korea has reinforced the relevant regulations, and there has been some progress. At the same time, the seismic base isolation concept was introduced to encourage active research activities related to building safety issues. It has lately been applied for the purpose of reducing construction costs. In 1980s, seismic base isolation design was applied for 'Cruas' plant in France and 'Koeberg' plant in South Africa. Those two are the few cases in which the seismic base isolation design was applied; for the rest, seismic resistance design was applied in most nuclear power plants that are in operation and in construction in the world. Rather than welcoming innovative technology on a trial basis, nuclear power plant design makes use only of proven technologies, which explains the application of seismic resistance design. As seismic base isolation design has become more accepted for use in the building of domestic general bridges, which has, thereby, confirmed its safety, it has been accepted for nuclear power plant design and has even been actively applied. So far, most structures of nuclear facility have been constructed with seismic resistance design and engineering methods. However, seismic force prediction is not perfect in reality; nor is it financially beneficial to apply the system for gradually increasing seismic resistance design loads. Therefore, it is necessary to apply a seismic base isolation system as a way to help secure the

  19. Imaging seismic reflections

    NARCIS (Netherlands)

    Op 't Root, Timotheus Johannes Petrus Maria

    2011-01-01

    The goal of reflection seismic imaging is making images of the Earth subsurface using surface measurements of reflected seismic waves. Besides the position and orientation of subsurface reflecting interfaces it is a challenge to recover the size or amplitude of the discontinuities. We investigate tw

  20. Information and training for outside radiation workers at Krsko NPP

    Energy Technology Data Exchange (ETDEWEB)

    Breznik, Borut [Krsko Nuclear Power Plant, SI-8270 (Slovenia)

    2004-07-01

    According to the basic safety standards the undertaking shall inform exposed workers about the health risks involved in their work, general radiation protection procedures and precautions to be taken in the controlled area. Using available information and knowledge based on international recommendations related to radiation protection, nuclear energy and specific plant design and procedures, the topics of interest have been selected and prepared for computer presentation or film. The paper presents the requirements, suggestions and facts included in this information, such as radiation protection practice in general and nuclear power plant specific information. The presentation will provide a useful example on how to inform and train periodically radiation workers from outside undertakings. (author)

  1. 考虑残余位移影响的梁式桥基于性能的抗震设计%Study on performance-based seismic design for beam bridges considering residual displacement

    Institute of Scientific and Technical Information of China (English)

    李宇; 车艳阳; 王森

    2015-01-01

    According to the current Chinese code of bridge seismic design,320 strong motion records of four sites are selected to establish elastic-plastic displacement spectra,residual displacement spectra. Normalized parameters of cumulative dissipation energy are improved and equivalent ductility coefficients based on damage indexes are obtained. Furthermore,developed seismic damage models are discussed. Performance-based seismic design for bridges considering residual displacement is proposed and specific examples are provided to show the detailed design procedures. The nonlinear time-history analysis results show that both deformation capacity and energy dissipation capacity of bridge can be considered by the proposed method and the maximal displacement, plastic cumulative damage and residual displacement can be controlled well. The proposed method can be applied in design of low and medium-height piers with short natural period and low ductility.%以我国现行的桥梁抗震设计规范为依据,合理地选取4类场地320条强震记录,统计出适用于我国梁式桥抗震设计的弹塑性位移谱和残余位移谱,并改进正规化累积耗能参数,得到基于损伤性能指标的等效位移延性系数,并以此对桥梁的地震损伤模型进行探讨。在此基础上,提出考虑残余位移影响的梁式桥基于性能的抗震设计方法,并给出具体算例,其非线性时程分析的结果表明:该方法综合考虑了结构的变形和耗能能力,可有效地控制桥墩的首超破坏、塑性累积损伤以及震后残余位移,适用于我国短周期、低延性的一般规则梁式桥的中、低矮桥墩的抗震设计。

  2. 基于滞回耗能谱的钢板剪力墙结构性态设计方法%Performance based seismic design of steel plate shear walls using hysteretic energy spectrum

    Institute of Scientific and Technical Information of China (English)

    孙国华; 顾强; 何若全; 方有珍

    2011-01-01

    The damages of buildings under earthquakes are related to cumulative effects of the ground motion.In order to reflect the ground motion effect,an energy-based seismic design method of steel plate shear wall,based on the normalized hysteretic energy spectrum and accumulated ductility spectrum,was proposed.The computation methods for accumulated hysteretic energy of steel beam,steel column,and steel plate infill wall were constructed.The different hysteretic behavior of steel components was taken into consideration by pinching parameters.Capacity design method was used to determine the sections of steel components,and to ensure that SPSW could produce the favorite failure mode under rare earthquakes.A ten-story,three-span SPSW was designed based on this new design method.The seismic behavior was evaluated by nonlinear time history method.The maximum average story drift of the example SPSW structure can meet the requirement of the Chinese seismic code.The reliability of this method is proved.%结构在地震作用下的损伤往往与地面运动的加速度循环特征密切相关,为反映这种地面运动特征,引入了累积延性比,并结合标准化的滞回耗能谱,提出了钢板剪力墙(SPSW)结构基于能量的性态抗震设计方法。该方法给出了SPSW结构中钢梁、钢柱、剪力墙板累积滞回耗能的计算方法,引入捏缩系数来反映构件的滞回特性,采用能力设计方法确定剪力墙板周边的梁、柱截面,确保SPSW结构在罕遇地震作用下出现理想的塑性机构。通过对1榀10层3跨的SPSW结构算例分析,采用弹塑性时程分析对所设计结构进行了验证。计算结果表明:结构最大楼层侧移平均值满足我国现行抗震规范的要求,与设计假定的目标侧移基本一致,验证了建议方法的合理性。

  3. 浅议福岛核电事故对我国核电发展的影响及借鉴%Lessons from Fukushima Dai-ichi NPP Accident and Effect on NPP Development in China

    Institute of Scientific and Technical Information of China (English)

    潘金钊

    2012-01-01

    Although the Fukushima NPP accident caused no serious environmental problem in China, but it does have great effect on the future NPP development in China. The NPP development plan in China is so uniquely huge in the world energy field that great challenge has already arisen to the Chinese NPP constructors and operators. This paper analyzes the sequence of the Fukushima NPP, which can be referred to in the improvement of the NPP development plan and the NPP accident emergency plan.%日本福岛核电事故虽然未对我国的环境造成严重影响,但是该事故的发生对我国后续核电的发展必然产生重大影响.我国庞大、密集的核电发展规划在世界能源发展领域是绝无仅有的,无论是在技术路线、标准制订还是在建造、运行的组织管理上,我国核电建设者和管理者都将面临巨大考验.通过分析和借鉴本次日本福岛核电事故的发生、处理过程,将对我国核电发展在多方面提供重要参考,从而促进我国核电规划及核电事故应急体系的持续完善.

  4. METHODOLOGY OF SYSTEM APPROACHE TO SEISMIC RISK ASSESSMENT AND REDUCTION

    Directory of Open Access Journals (Sweden)

    A. D. Abakarov

    2016-01-01

    Full Text Available Abstract. Ensuring of urban areas seismic safety is a task which do not require delay. But it cannot be solved by separate parts. It is essential that all components of the seismic hazard must be grouped together in one problem based on the system approach. In the present paper is presented not only the main flowchart of systems approach to ensuring the territory seismic safety but also the flowcharts of components of each main unit. They cover the whole package of measures for a full assessment of territory seismic hazard, seismic risk and its reduction.The proposed methodology can be carried out for design and implementation of regional territory seismic safety programs. 

  5. Seismic texture classification. Final report

    Energy Technology Data Exchange (ETDEWEB)

    Vinther, R.

    1997-12-31

    The seismic texture classification method, is a seismic attribute that can both recognize the general reflectivity styles and locate variations from these. The seismic texture classification performs a statistic analysis for the seismic section (or volume) aiming at describing the reflectivity. Based on a set of reference reflectivities the seismic textures are classified. The result of the seismic texture classification is a display of seismic texture categories showing both the styles of reflectivity from the reference set and interpolations and extrapolations from these. The display is interpreted as statistical variations in the seismic data. The seismic texture classification is applied to seismic sections and volumes from the Danish North Sea representing both horizontal stratifications and salt diapers. The attribute succeeded in recognizing both general structure of successions and variations from these. Also, the seismic texture classification is not only able to display variations in prospective areas (1-7 sec. TWT) but can also be applied to deep seismic sections. The seismic texture classification is tested on a deep reflection seismic section (13-18 sec. TWT) from the Baltic Sea. Applied to this section the seismic texture classification succeeded in locating the Moho, which could not be located using conventional interpretation tools. The seismic texture classification is a seismic attribute which can display general reflectivity styles and deviations from these and enhance variations not found by conventional interpretation tools. (LN)

  6. Large scale mechanical metamaterials as seismic shields

    Science.gov (United States)

    Miniaci, Marco; Krushynska, Anastasiia; Bosia, Federico; Pugno, Nicola M.

    2016-08-01

    Earthquakes represent one of the most catastrophic natural events affecting mankind. At present, a universally accepted risk mitigation strategy for seismic events remains to be proposed. Most approaches are based on vibration isolation of structures rather than on the remote shielding of incoming waves. In this work, we propose a novel approach to the problem and discuss the feasibility of a passive isolation strategy for seismic waves based on large-scale mechanical metamaterials, including for the first time numerical analysis of both surface and guided waves, soil dissipation effects, and adopting a full 3D simulations. The study focuses on realistic structures that can be effective in frequency ranges of interest for seismic waves, and optimal design criteria are provided, exploring different metamaterial configurations, combining phononic crystals and locally resonant structures and different ranges of mechanical properties. Dispersion analysis and full-scale 3D transient wave transmission simulations are carried out on finite size systems to assess the seismic wave amplitude attenuation in realistic conditions. Results reveal that both surface and bulk seismic waves can be considerably attenuated, making this strategy viable for the protection of civil structures against seismic risk. The proposed remote shielding approach could open up new perspectives in the field of seismology and in related areas of low-frequency vibration damping or blast protection.

  7. VERONA V6.22 – An enhanced reactor analysis tool applied for continuous core parameter monitoring at Paks NPP

    Energy Technology Data Exchange (ETDEWEB)

    Végh, J., E-mail: janos.vegh@ec.europa.eu [Institute for Energy and Transport of the Joint Research Centre of the European Commission, Postbus 2, NL-1755 ZG Petten (Netherlands); Pós, I., E-mail: pos@npp.hu [Paks Nuclear Power Plant Ltd., H-7031 Paks, P.O. Box 71 (Hungary); Horváth, Cs., E-mail: csaba.horvath@energia.mta.hu [Centre for Energy Research, Hungarian Academy of Sciences, H-1525 Budapest 114, P.O. Box 49 (Hungary); Kálya, Z., E-mail: kalyaz@npp.hu [Paks Nuclear Power Plant Ltd., H-7031 Paks, P.O. Box 71 (Hungary); Parkó, T., E-mail: parkot@npp.hu [Paks Nuclear Power Plant Ltd., H-7031 Paks, P.O. Box 71 (Hungary); Ignits, M., E-mail: ignits@npp.hu [Paks Nuclear Power Plant Ltd., H-7031 Paks, P.O. Box 71 (Hungary)

    2015-10-15

    Between 2003 and 2007 the Hungarian Paks NPP performed a large modernization project to upgrade its VERONA core monitoring system. The modernization work resulted in a state-of-the-art system that was able to support the reactor thermal power increase to 108% by more accurate and more frequent core analysis. Details of the new system are given in Végh et al. (2008), the most important improvements were as follows: complete replacement of the hardware and the local area network; application of a new operating system and porting a large fraction of the original application software to the new environment; implementation of a new human-system interface; and last but not least, introduction of new reactor physics calculations. Basic novelty of the modernized core analysis was the introduction of an on-line core-follow module based on the standard Paks NPP core design code HELIOS/C-PORCA. New calculations also provided much finer spatial resolution, both in terms of axial node numbers and within the fuel assemblies. The new system was able to calculate the fuel applied during the first phase of power increase accurately, but it was not tailored to determine the effects of burnable absorbers as gadolinium. However, in the second phase of the power increase process the application of fuel assemblies containing three fuel rods with gadolinium content was intended (in order to optimize fuel economy), therefore off-line and on-line VERONA reactor physics models had to be further modified, to be able to handle the new fuel according to the accuracy requirements. In the present paper first a brief overview of the system version (V6.0) commissioned after the first modernization step is outlined; then details of the modified off-line and on-line reactor physics calculations are described. Validation results for new modules are treated extensively, in order to illustrate the extent and complexity of the V&V procedure associated with the development and licensing of the new

  8. Automating Shallow Seismic Imaging

    Energy Technology Data Exchange (ETDEWEB)

    Steeples, Don W.

    2004-12-09

    -access environments, this device could make SSR surveying considerably more efficient and less expensive, particularly when geophone intervals of 25 cm or less are required. The most recent research analyzed the difference in seismic response of the geophones with variable geophone spike length and geophones attached to various steel media. Experiments investigated the azimuthal dependence of the quality of data relative to the orientation of the rigidly attached geophones. Other experiments designed to test the hypothesis that the data are being amplified in much the same way that an organ pipe amplifies sound have so far proved inconclusive. Taken together, the positive results show that SSR imaging within a few meters of the earth's surface is possible if the geology is suitable, that SSR imaging can complement GPR imaging, and that SSR imaging could be made significantly more cost effective, at least in areas where the topography and the geology are favorable. Increased knowledge of the Earth's shallow subsurface through non-intrusive techniques is of potential benefit to management of DOE facilities. Among the most significant problems facing hydrologists today is the delineation of preferential permeability paths in sufficient detail to make a quantitative analysis possible. Aquifer systems dominated by fracture flow have a reputation of being particularly difficult to characterize and model. At chemically contaminated sites, including U.S. Department of Energy (DOE) facilities and others at Department of Defense (DOD) installations worldwide, establishing the spatial extent of the contamination, along with the fate of the contaminants and their transport-flow directions, is essential to the development of effective cleanup strategies. Detailed characterization of the shallow subsurface is important not only in environmental, groundwater, and geotechnical engineering applications, but also in neotectonics, mining geology, and the analysis of petroleum reservoir

  9. Atmospheric-Seismic Effect of Chelyabinsk Meteoroid

    Science.gov (United States)

    Chernogor, L. F.

    2017-06-01

    Purpose: The parameters of the shock-wave source in the atmosphere and seismic oscillations that this source caused are investigated Design/methodology/approach: The atmospheric and seismic processes caused by the passage and explosion of Chelyabinsk meteoroid on February 15, 2013 have been modelled. The model results are compared with the observation results obtained at several seismic stations. Findings: The shock-wave impact duration is shown to be equal to approximately 97 s, and the time delays of the shockwave at the sites of destruction relative to its generation time at altitudes of 23÷53 km are shown to be equal to 77÷295 s in the distance range interval of 23÷84 km. The length of the area destructed by the shock with the access pressure of no less than 0.7 kPa is determined to be equal to 125÷130 km, and its width to 16÷60 km at various parts of the meteoroid path. The regression relation between the duration of the seismic signal and the length of the seismic wave path has been determined. The characteristic scale time of seismic source impact is equal to approximately 40 s. In the 20÷50 -s period range of seismic oscillations, the dependence of the group speed on period is established. The attenuation depth of seismic waves is estimated to be approximately 10÷20 Mm in the frequency range of 0.25÷3.0 Hz, and the Earth’s crust speed to 5.7÷7.0 μm/s. Conclusions: The model and estimation results are in good agreement with the observations.

  10. Evaluation and assessment of nuclear power plant seismic methodology

    Energy Technology Data Exchange (ETDEWEB)

    Bernreuter, D.; Tokarz, F.; Wight, L.; Smith, P.; Wells, J.; Barlow, R.

    1977-03-01

    The major emphasis of this study is to develop a methodology that can be used to assess the current methods used for assuring the seismic safety of nuclear power plants. The proposed methodology makes use of system-analysis techniques and Monte Carlo schemes. Also, in this study, we evaluate previous assessments of the current seismic-design methodology.

  11. Feasibility of a seismic gap in southeastern Sicily

    Energy Technology Data Exchange (ETDEWEB)

    Mulargia, F.; Baldi, P.; Achilli, V.; Broccio, F.

    1985-01-16

    A major seismic gap has been recently suggested for southeastern Sicily. The present note analyses the feasibility of such a gap on the basis of the available historic seismicity data and in light of the results of a levelling campaign which was specially designed for this purpose.

  12. Degradation and failure characteristics of NPP containment protective coating systems

    Energy Technology Data Exchange (ETDEWEB)

    Sindelar, R.L.

    2000-03-30

    A research program to investigate the performance and potential for failure of Service Level 1 coating systems used in nuclear power plant containment is in progress. The research activities are aligned to address phenomena important to cause failure as identified by the industry coatings expert panel. The period of interest for performance covers the time from application of the coating through 40 years of service, followed by a medium-to-large break loss-of-coolant accident scenario, which is a design basis accident (DBA) scenario. The interactive program elements are discussed in this report and the application of these elements to the System 5 coating system (polyamide epoxy primer, carbon steel substrate) is used to evaluate performance.

  13. Degradation and Failure Characteristics of NPP Containment Protective Coating Systems

    Energy Technology Data Exchange (ETDEWEB)

    Sindelar, R.L.

    2001-04-10

    Nuclear power plants (NPPs) must ensure that the emergency core cooling system (ECCS) or safety-related containment spray system (CSS) remains capable of performing its design safety function throughout the life of the plant. This requires ensuring that long-term core cooling can be maintained following a postulated loss-of-coolant accident (LOCA). Adequate safety operation can be impaired if the protective coatings which have been applied to the concrete and steel structures within the primary containment fail, producing transportable debris which could then accumulate on BWR ECCS suction strainers or PWR ECCS sump debris screens located within the containment. This document will present the data collected during the investigation of coating specimens from plants.

  14. Comparison of French and German NPP water chemistry programs

    Energy Technology Data Exchange (ETDEWEB)

    Staudt, U. [VGB Powertech (Germany); Odar, S. [Framatome ANP GmbH (Germany); Stutzmann, A. [EDF/GDL (France)

    2002-07-01

    PWRs in the western hemisphere obey basically the same rules concerning design, choice of material and operational mode. In spite of these basic similarities, the manufacturers of PWRs in different countries developed different solutions in respect to single components in the steam/water cycle. Looking specifically at France and Germany, the difference in the tubing material of the steam generators (Inconel 600/690 chosen by Framatome and Incoloy 800 chosen by the former Siemens KWU) led to specific differences in the respective chemistry programs and in some respect to different 'philosophies' in operating the water/steam cycle. Compared to this, basic differences in operating the reactor coolant system cannot be observed. Nevertheless specific solutions as zinc injection and the use of enriched B-10 are applied in German PWRs. The application of such measures arises from a specific dose rate situation in older PWRs (zinc injection) or from economic reasons mainly (B-10). (authors)

  15. Packaging, Transportation and Recycling of NPP Condenser Modules - 12262

    Energy Technology Data Exchange (ETDEWEB)

    Polley, G.M. [Perma-Fix Environmental Services, 575 Oak Ridge Turnpike, Oak Ridge, TN 37830 (United States)

    2012-07-01

    Perma-Fix was awarded contract from Energy Northwest for the packaging, transportation and disposition of the condenser modules, water boxes and miscellaneous metal, combustibles and water generated during the 2011 condenser replacement outage at the Columbia Generating Station. The work scope was to package the water boxes and condenser modules as they were removed from the facility and transfer them to the Perma-Fix Northwest facility for processing, recycle of metals and disposition. The condenser components were oversized and overweight (the condenser modules weighed ∼102,058 kg [225,000 lb]) which required special equipment for loading and transport. Additional debris waste was packaged in inter-modals and IP-1 boxes for transport. A waste management plan was developed to minimize the generation of virtually any waste requiring landfill disposal. The Perma-Fix Northwest facility was modified to accommodate the ∼15 m [50-ft] long condenser modules and equipment was designed and manufactured to complete the disassembly, decontamination and release survey. The condenser modules are currently undergoing processing for free release to a local metal recycler. Over three millions pounds of metal will be recycled and over 95% of the waste generated during this outage will not require land disposal. There were several elements of this project that needed to be addressed during the preparation for this outage and the subsequent packaging, transportation and processing. - Staffing the project to support 24/7 generation of large components and other wastes. - The design and manufacture of the soft-sided shipping containers for the condenser modules that measured ∼15 m X 4 m X 3 m [50 ft X 13 ft X 10 ft] and weighed ∼102,058 kg [225,000 lbs] - Developing a methodology for loading the modules into the shipping containers. - Obtaining a transport vehicle for the modules. - Designing and modifying the processing facility. - Movement of the modules at the processing

  16. Station Blackout Initiated Event Chronology in LWR/HWR NPP

    Energy Technology Data Exchange (ETDEWEB)

    Park, Soo Yong; Ahn, Kwang Il [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2011-10-15

    Since the crisis at Fukushima nuclear power plants, a severe accident progression has been recognized as a very important area for an accident management and emergency planning. The purpose of this study is to investigate the comparative characteristics of a severe accident progression among the typical pressurized water reactor (PWR), boiling water reactor (BWR) and pressurized heavy water reactor (PHWR). The OPR 1000-like (ABB-CE type PWR), Peach Bottom-like (BWR/4 RCS with a MARK I Containment), and Wolsong1-like (CANDU6 type) plants are selected as reference plants of typical 1000 MWe PWR, 1140MWe BWR, and 600 MWe PHWR, respectively. The design parameters of these plants are quite different. Some of the major different design features of CANDU6 plant from other light water reactors, in terms of a severe accident, are that the plant adopts a duel primary heat transport system and has an additional amount of cooling water in the calandria vessel (calandria tank, CT) and calandria vault (CV). Another feature is that the CT is always submerged in water because the CV is flooded during normal operation. The containment (reactor building, R/B) failure pressure of the CANDU6 plant is considerably lower than that of the typical PWR or BWR4/MARK-I. The containment vessel free volume of MARK-I is much smaller than that of the PWR or CANDU6 plant. Since there is no steam generator (SG) or passive cooling system, the amount of cooling water inventory in BWR4 is relatively less than other plants. Meanwhile the minimum available time of battery power against station blackout (SBO) accident is different among plant types: six hours for BWR4 and four hours for 1000MWe PWR. Therefore, plant responses against the severe core damage scenarios like Fukushima accident are expected to be much different. By identifying plant response signatures, the appropriate correction actions can be developed as part of severe accident management. A SBO scenario, where all off-site power is lost

  17. Assessment Impacts of Weather and Land Use/Land Cover (LULC Change on Urban Vegetation Net Primary Productivity (NPP: A Case Study in Guangzhou, China

    Directory of Open Access Journals (Sweden)

    Xiantie Zeng

    2013-08-01

    Full Text Available Net primary productivity (NPP can indicate vegetation ecosystem services ability and reflect variation response to climate change and human activities. This study applied MODIS-1 km NPP products to investigate the NPP variation from 2001 to 2006, a fast urban expansion and adjustment period in Guangzhou, China, and quantify the impacts of weather and land use/land cover (LULC changes, respectively. The results showed that the NPP mean value increased at a rate of 11.6 g∙C∙m−2∙yr−1 during the initial three years and decreased at an accelerated rate of 31.0 g∙C∙m−2∙yr−1 during the final three years, resulting in a total NPP loss of approximately 167 × 106 g∙C. The spatiotemporal of NPP varied obviously in the central area, suburb and exurb of Guangzhou driven by three patterns of weather and LULC changes. By the interactive effects and the weather variation dominated effects, NPP of most areas changed slightly with dynamic index less than 5% of NPP mean value in the central area and the suburb. The LULC change dominated effects caused obvious NPP reduction, by more than 15% of the NPP mean value, which occurred in some areas of the suburb and extended to the exurb with the outward urban sprawl. Importantly, conversion from wood grassland, shrublands and even forests to croplands occupied by urban landscapes proved to be a main process in the conversion from high-NPP coverage to low-NPP coverage, thereby leading to the rapid degradation of urban carbon stock capacity in urban fringe areas. It is helpful for government to monitor urban ecological health and safety and make relevant policies.

  18. 多层钢框架性态抗震设计——屈服点谱法%Performance-based Seismic Design of Steel Moment Frames Using YPS

    Institute of Scientific and Technical Information of China (English)

    周磊; 顾强

    2011-01-01

    Yield Point Spectra is a new response to the displaceme