WorldWideScience

Sample records for nuclear containment building

  1. Integrity assessment of grouted posttensioning cables and reinforced concrete of a nuclear containment building

    OpenAIRE

    Shenton B.; Philipose K.

    2011-01-01

    The Containment Buildings of CANDU Nuclear Generating Stations were designed to house nuclear reactors and process equipment and also to provide confinement of releases from a potential nuclear accident such as a Loss Of Coolant Accident (LOCA). To meet this design requirement, a post-tensioning system was designed to induce compressive stresses in the structure to counteract the internal design pressure. The CANDU reactor building at Gentilly-1 (G-1), Quebec, Canada (250 MWe) was built in th...

  2. Integrity assessment of grouted posttensioning cables and reinforced concrete of a nuclear containment building

    Directory of Open Access Journals (Sweden)

    Shenton B.

    2011-04-01

    Full Text Available The Containment Buildings of CANDU Nuclear Generating Stations were designed to house nuclear reactors and process equipment and also to provide confinement of releases from a potential nuclear accident such as a Loss Of Coolant Accident (LOCA. To meet this design requirement, a post-tensioning system was designed to induce compressive stresses in the structure to counteract the internal design pressure. The CANDU reactor building at Gentilly-1 (G-1, Quebec, Canada (250 MWe was built in the early 1970s and is currently in a decommissioned state. The structure at present is under surveillance and monitoring. In the year 2000, a field investigation was conducted as part of a condition assessment and corrosion was detected in some of the grouted post-tension cable strands. However, no further work was done at that time to determine the cause, nature, impact and extent of the corrosion. An investigation of the Gentilly-1 containment building is currently underway to assess the condition of grouted post-tensioning cables and reinforced concrete. At two selected locations, concrete and steel reinforcements were removed from the containment building wall to expose horizontal cables. Individual cable strands and reinforcement bars were instrumented and measurements were taken in-situ before removing them for forensic examination and destructive testing to determine the impact of ageing and corrosion. Concrete samples were also removed and tested in a laboratory. The purpose of the field investigation and laboratory testing, using this structure as a test bed, was also to collect material ageing data and to develop potential Nondestructive Examination (NDE methods to monitor Containment Building Integrity. The paper describes the field work conducted and the test results obtained for concrete, reinforcement and post-tensioning cables.

  3. Improvement of impact-resistance of a nuclear containment building using fiber reinforced concrete

    Energy Technology Data Exchange (ETDEWEB)

    Jeon, Se-Jin, E-mail: conc@ajou.ac.kr [Ajou University, 206, World cup-ro, Yeongtong-gu, Suwon-si, Gyeonggi-do 16499 (Korea, Republic of); Jin, Byeong-Moo [DAEWOO E& C, Institute of Construction Technology, 20, Suil-ro 123beon-gil, Jangan-gu, Suwon-si, Gyeonggi-do 16297 (Korea, Republic of)

    2016-08-01

    Highlights: • Impact-resistance of a structure can be improved by fiber reinforced concrete (FRC). • Material modeling of FRC is incorporated into finite element analysis of a structure. • A new index for impact-resistance is proposed based on plastic dissipation energy. • A nuclear power plant made of FRC shows improved resistance against aircraft crashes. - Abstract: Since the act of terrorism that occurred in the USA on September 11, 2001, the protection of nuclear power plants against large commercial aircraft crashes has been an emerging issue. Besides the verification of the safety of nuclear power plants in operation or in design, efficient methods for improving the impact-resistance of these structures have been investigated. Fiber reinforced concrete (FRC) has been generally accepted as an effective material for this purpose. In particular, FRC has been developed to improve the tensile behavior of concrete such as tensile strength, ductility and toughness. One of the main fields of application of FRC can be found in blast-protective or blast-resistant concrete structures. It is expected, therefore, that safety-related structures in a nuclear power plant can also be effectively protected from external blast, aircraft crash, etc. by applying FRC. In order to analytically verify the effect on structural behavior of applying FRC, the particular material properties of FRC should be incorporated into the material modeling of a structural analysis program. This study investigates the mathematical modeling of FRC, which represents various aspects of material behavior. Two numerical examples are provided to show the improved impact-resistance of a nuclear containment building that is expected when applying FRC in comparison with ordinary concrete. The analysis results show that the displacement decreases by 43–67% while the impact-resistance increases by 40–82%, depending on a fiber type.

  4. Structural response of nuclear containment shield buildings with unanticipated construction openings

    Science.gov (United States)

    Mac Namara, Sinead Caitriona

    As Nuclear Power Plants age many require steam generator replacement. There is a nickel alloy in the steam generator tubes that is susceptible to stress cracking and although these cracks can be sealed the generator becomes uneconomical without 10%-15% of the tubes. The steam generator in a typical nuclear power plant is housed in the containment structure next to the reactor. The equipment hatch is not big enough to facilitate steam generator replacement, thus construction openings in the dome of the containment structure are required. To date the structural consequences of construction openings in the dome have not been examined. This thesis examines the effects of such openings. The prototype concrete dome is made up of a 2 ft thick dome atop 3 ft thick and 170 ft high cylindrical walls (radius 65.5 ft) with a tension ring 15 ft high and 8 ft thick in between. The dome of the building is cast in two layers; a lower 9 inch layer that serves as the formwork for an upper 15 inch layer. The weight of the dome is carried in axial compression along the hoops and meridians of the dome. The first finite element model uses shell elements and considers two limiting load cases; where the two layers act as one, and where the lower layer carries the weight of both. The openings interrupt the hoops and meridians and the weight of the dome must be redistributed around the openings. Without openings, the stresses due to dead load in the structure are very low when compared to the material strength. The impact of the openings is increased compression stresses near the opening. The maximum stresses are approximately four times larger than in the original structure. These results are confirmed by the second model which is made from layers of solid elements. This model shows a significant difference between the compression on the top surface of the dome, in the affected areas, and that on the bottom surface, leading to shear stresses. These shear stresses are largest around the

  5. 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.

  6. Comparison of test and earthquake response modeling of a nuclear power plant containment building

    Energy Technology Data Exchange (ETDEWEB)

    Srinivasan, M.G.; Kot, C.A.; Hsieh, B.J.

    1985-01-01

    The reactor building of a BWR plant was subjected to dynamic testing, a minor earthquake, and a strong earthquake at different times. Analytical models simulating each of these events were devised by previous investigators. A comparison of the characteristics of these models is made in this paper. The different modeling assumptions involved in the different simulation analyses restrict the validity of the models for general use and also narrow the comparison down to only a few modes. The dynamic tests successfully identified the first mode of the soil-structure system.

  7. A Monte Carlo program to calculate the exposure rate from airborne radioactive gases inside a nuclear reactor containment building.

    Science.gov (United States)

    Sherbini, S; Tamasanis, D; Sykes, J; Porter, S W

    1986-12-01

    A program was developed to calculate the exposure rate resulting from airborne gases inside a reactor containment building. The calculations were performed at the location of a wall-mounted area radiation monitor. The program uses Monte Carlo techniques and accounts for both the direct and scattered components of the radiation field at the detector. The scattered component was found to contribute about 30% of the total exposure rate at 50 keV and dropped to about 7% at 2000 keV. The results of the calculations were normalized to unit activity per unit volume of air in the containment. This allows the exposure rate readings of the area monitor to be used to estimate the airborne activity in containment in the early phases of an accident. Such estimates, coupled with containment leak rates, provide a method to obtain a release rate for use in offsite dose projection calculations.

  8. Development of 3D models of buildings for containment of the nuclear power plant of Almaraz and of the Trillo Nuclear with the GOTHIC 8.0 code; Desarrollo de modelos 3D de los edificios de conten cion de la Central Nuclear de Almaraz y de la Central Nuclear de Trillo con el codigo GOTHIC 8.0

    Energy Technology Data Exchange (ETDEWEB)

    Jimenez, G.; Bocanegra Melian, R.; Fernandez Cosils, K.; Barreira Pereira, P.; Rey Peinado, L.; Posada Barral, J. M.

    2014-07-01

    The objective of the first phase of the research of CNAT and the UPM project is the construction of several three-dimensional models detailed GOTHIC 8.0 code of containment of a buildings plant type PWR-W and KWU, corresponding to the Central Nuclear de Almaraz (CNA) and Trillo (CNT) respectively. (Author)

  9. Building a secondary containment system

    Energy Technology Data Exchange (ETDEWEB)

    Broder, M.F.

    1994-10-01

    Retail fertilizer and pesticide dealers across the United States are installing secondary containment at their facilities or are seriously considering it. Much of this work is in response to new state regulations; however, many dealers not facing new regulations are upgrading their facilities to reduce their liability, lower their insurance costs, or comply with anticipated regulations. The Tennessee Valley Authority`s (TVA) National Fertilizer and Environmental Research Center (NFERC) has assisted dealers in 22 states in retrofitting containment to their facilities. Simultaneous improvements in the operational efficiency of the facilities have been achieved at many of the sites. This paper is based on experience gained in that work and details the rationale used in planning secondary containment and facility modifications.

  10. Replacement of the feedwater pipe system in reactor building outside containment at the nuclear power plant Philippsburg; Austausch der Speisewasserleitung im Reaktorgebaeude ausserhalb SHB im Kernkraftwerk Philippsburg I

    Energy Technology Data Exchange (ETDEWEB)

    Kessler, A. [Energie-Versorgung Schwaben AG, Stuttgart (Germany); Labes, M. [Siemens AG Unternehmensbereich KWU, Offenbach am Main (Germany); Schwenk, B. [Kernkraftwerk Philippsburg GmbH (Germany)

    1998-11-01

    After full replacement of the feedwater pipe system during the inspection period in 1997, combined with a modern materials, manufacturing and analysis concept, the entire pipe system of the water/steam cycle in the reactor building of KKP 1 now consists of high-toughness materials. The safety level of the entire plant has been increased by leaving aside postulation of F2 breaks in the reactor building and providing for protection against 0.1 leaks. Based on fluid-dynamic calculations for the cases of pump failure and pipe break, as well as pipe system calculations in 5 extensive calculation cycles, about 130 documents were filed for inspection and approval (excluding preliminary test documents on restraints). Points of main interest for safety analysis in this context were the optimised closing performance of the 3rd check valves and the integrity of the nozzle region at the RPV. (oirg./CB) [Deutsch] Durch den Restaustausch der Speisewasserleitungen in der Revision 1997, verbunden mit einem modernen Werkstoff-, Fertigungs- und Nachweiskonzept, sind im Reaktorgebaeude von KKP 1 in den Hauptleitungen des Wasser-Dampf-Kreislaufes nur noch hochzaehe Werkstoffe eingesetzt. Durch den Verzicht auf das Postulat von 2F-Bruechen im Reaktorgebaeude und durch die Auslegung gegen 0,1F-Lecks wird das Sicherheitsniveau der Anlage insgesamt gesteigert. Ausgehend von fluiddynamischen Berechnungen fuer Pumpenausfall und Rohrbruch sowie Rohrsystem-Berechnungen in 5 umfangreichen Berechnungskreisen wurden fuer die Genehmigung und Begutachtung ca. 130 Unterlagen (ohne Halterungs-Vorpruefunterlagen) eingereicht und vom Gutachter geprueft. Schwerpunkte der Nachweisfuehrung waren die Optimierung des Schliessverhaltens der 3. Rueckschlagarmaturen sowie der Integritaetsnachweis des RDB-Anschlusses. (orig./MM)

  11. Information for Owners and Managers of Buildings that Contain Asbestos

    Science.gov (United States)

    Federal requirements for the renovation and demolition of buildings and guidance on developing and maintaining an operations and maintenance program to manage asbestos-containing materials in buildings.

  12. Predicting the Lifetimes of Nuclear Waste Containers

    Science.gov (United States)

    King, Fraser

    2014-03-01

    As for many aspects of the disposal of nuclear waste, the greatest challenge we have in the study of container materials is the prediction of the long-term performance over periods of tens to hundreds of thousands of years. Various methods have been used for predicting the lifetime of containers for the disposal of high-level waste or spent fuel in deep geological repositories. Both mechanical and corrosion-related failure mechanisms need to be considered, although until recently the interactions of mechanical and corrosion degradation modes have not been considered in detail. Failure from mechanical degradation modes has tended to be treated through suitable container design. In comparison, the inevitable loss of container integrity due to corrosion has been treated by developing specific corrosion models. The most important aspect, however, is to be able to justify the long-term predictions by demonstrating a mechanistic understanding of the various degradation modes.

  13. Hydrogen behavior at a subcomparment in the containment building

    Energy Technology Data Exchange (ETDEWEB)

    Lee, U. J.; Park, G. C. [Seoul National University, Seoul (Korea, Republic of)

    1997-12-31

    For hydrogen management in severe accidents with degraded nuclear core of PWR`s, several experiments have been performed in the SNU hydrogen mixing facility. The objectives are understanding the extent of hydrogen mixing and analyzing the effects of factors which dominate uniform or non-uniform mixing at compartments in the containment building. The facility represents on a 1/11th linearly scaled model of the YGN unit 3 and 4, hydrogen was simulated by helium. Because there are the gaps between safety injection tank and compartment layers in the containment, the test facility was constructed in three dimensional mode for analyzing of mixture behaviour through the gaps. >From the experimental results we could conclude that overall hydrogen concentration distributed uniformly in the free volume of the test compartment, but fluctuated in the gaps. This paper is focused on experimental result from several experiments. 5 refs., 4 figs. (Author)

  14. Nanoporous Glasses for Nuclear Waste Containment

    Directory of Open Access Journals (Sweden)

    Thierry Woignier

    2016-01-01

    Full Text Available Research is in progress to incorporate nuclear waste in new matrices with high structural stability, resistance to thermal shock, and high chemical durability. Interactions with water are important for materials used as a containment matrix for the radio nuclides. It is indispensable to improve their chemical durability to limit the possible release of radioactive chemical species, if the glass structure is attacked by corrosion. By associating high structural stability and high chemical durability, silica glass optimizes the properties of a suitable host matrix. According to an easy sintering stage, nanoporous glasses such as xerogels, aerogels, and composite gels are alternative ways to synthesize silica glass at relatively low temperatures (≈1,000–1,200°C. Nuclear wastes exist as aqueous salt solutions and we propose using the open pore structure of the nanoporous glass to enable migration of the solution throughout the solid volume. The loaded material is then sintered, thereby trapping the radioactive chemical species. The structure of the sintered materials (glass ceramics is that of nanocomposites: actinide phases (~100 nm embedded in a vitreous silica matrix. Our results showed a large improvement in the chemical durability of glass ceramic over conventional nuclear glass.

  15. Inspection of Nuclear Power Plant Containment Structures

    Energy Technology Data Exchange (ETDEWEB)

    Graves, H.L.; Naus, D.J.; Norris, W.E.

    1998-12-01

    Safety-related nuclear power plant (NPP) structures are designed to withstand loadings from a number of low-probability external and interval events, such as earthquakes, tornadoes, and loss-of-coolant accidents. Loadings incurred during normal plant operation therefore generally are not significant enough to cause appreciable degradation. However, these structures are susceptible to aging by various processes depending on the operating environment and service conditions. The effects of these processes may accumulate within these structures over time to cause failure under design conditions, or lead to costly repair. In the late 1980s and early 1990s several occurrences of degradation of NPP structures were discovered at various facilities (e.g., corrosion of pressure boundary components, freeze- thaw damage of concrete, and larger than anticipated loss of prestressing force). Despite these degradation occurrences and a trend for an increasing rate of occurrence, in-service inspection of the safety-related structures continued to be performed in a somewhat cursory manner. Starting in 1991, the U.S. Nuclear Regulatory Commission (USNRC) published the first of several new requirements to help ensure that adequate in-service inspection of these structures is performed. Current regulatory in-service inspection requirements are reviewed and a summary of degradation experience presented. Nondestructive examination techniques commonly used to inspect the NPP steel and concrete structures to identify and quantify the amount of damage present are reviewed. Finally, areas where nondestructive evaluation techniques require development (i.e., inaccessible portions of the containment pressure boundary, and thick heavily reinforced concrete sections are discussed.

  16. Spent Nuclear Fuel Project Canister Storage Building Functions and Requirements

    Energy Technology Data Exchange (ETDEWEB)

    KLEM, M.J.

    2000-10-18

    In 1998, a major change in the technical strategy for managing Multi Canister Overpacks (MCO) while stored within the Canister Storage Building (CSB) occurred. The technical strategy is documented in Baseline Change Request (BCR) No. SNF-98-006, Simplified SNF Project Baseline (MCO Sealing) (FDH 1998). This BCR deleted the hot conditioning process initially adopted for the Spent Nuclear Fuel Project (SNF Project) as documented in WHC-SD-SNF-SP-005, Integrated Process Strategy for K Basins Spent Nuclear Fuel (WHC 199.5). In summary, MCOs containing Spent Nuclear Fuel (SNF) from K Basins would be placed in interim storage following processing through the Cold Vacuum Drying (CVD) facility. With this change, the needs for the Hot Conditioning System (HCS) and inerting/pressure retaining capabilities of the CSB storage tubes and the MCO Handling Machine (MHM) were eliminated. Mechanical seals will be used on the MCOs prior to transport to the CSB. Covers will be welded on the MCOs for the final seal at the CSB. Approval of BCR No. SNF-98-006, imposed the need to review and update the CSB functions and requirements baseline documented herein including changing the document title to ''Spent Nuclear Fuel Project Canister Storage Building Functions and Requirements.'' This revision aligns the functions and requirements baseline with the CSB Simplified SNF Project Baseline (MCO Sealing). This document represents the Canister Storage Building (CSB) Subproject technical baseline. It establishes the functions and requirements baseline for the implementation of the CSB Subproject. The document is organized in eight sections. Sections 1.0 Introduction and 2.0 Overview provide brief introductions to the document and the CSB Subproject. Sections 3.0 Functions, 4.0 Requirements, 5.0 Architecture, and 6.0 Interfaces provide the data described by their titles. Section 7.0 Glossary lists the acronyms and defines the terms used in this document. Section 8

  17. Detailed thermal-hydraulic computation into a containment building

    Energy Technology Data Exchange (ETDEWEB)

    Caruso. A.; Flour, I.; Simonin, O. [EDF/LNH, Chatou (France); Cherbonnel, C [EDF/SEPTEN, Villeurbanne (France)

    1995-09-01

    This paper deals with numerical predictions of the influence of water sprays upon stratifications into a containment building using a two-dimensional two-phase flow code. Basic equations and closure assumptions are briefly presented. A test case in a situation involving spray evaporation is first detailed to illustrate the validation step. Then results are presented for a compressible recirculating flow into a containment building with condensation phenomena.

  18. Building a Universal Nuclear Energy Density Functional

    Energy Technology Data Exchange (ETDEWEB)

    Carlson, Joe A. [Michigan State Univ., East Lansing, MI (United States); Furnstahl, Dick; Horoi, Mihai; Lust, Rusty; Nazaewicc, Witek; Ng, Esmond; Thompson, Ian; Vary, James

    2012-12-30

    During the period of Dec. 1 2006 – Jun. 30, 2012, the UNEDF collaboration carried out a comprehensive study of all nuclei, based on the most accurate knowledge of the strong nuclear interaction, the most reliable theoretical approaches, the most advanced algorithms, and extensive computational resources, with a view towards scaling to the petaflop platforms and beyond. The long-term vision initiated with UNEDF is to arrive at a comprehensive, quantitative, and unified description of nuclei and their reactions, grounded in the fundamental interactions between the constituent nucleons. We seek to replace current phenomenological models of nuclear structure and reactions with a well-founded microscopic theory that delivers maximum predictive power with well-quantified uncertainties. Specifically, the mission of this project has been three-fold: First, to find an optimal energy density functional (EDF) using all our knowledge of the nucleonic Hamiltonian and basic nuclear properties; Second, to apply the EDF theory and its extensions to validate the functional using all the available relevant nuclear structure and reaction data; Third, to apply the validated theory to properties of interest that cannot be measured, in particular the properties needed for reaction theory.

  19. Building a Universal Nuclear Energy Density Functional

    Energy Technology Data Exchange (ETDEWEB)

    Carlson, Joe A. [Michigan State University; Furnstahl, Dick; Horoi, Mihai; Lust, Rusty; Nazaewicc, Witek; Ng, Esmond; Thompson, Ian; Vary, James

    2012-12-30

    During the period of Dec. 1 2006 – Jun. 30, 2012, the UNEDF collaboration carried out a comprehensive study of all nuclei, based on the most accurate knowledge of the strong nuclear interaction, the most reliable theoretical approaches, the most advanced algorithms, and extensive computational resources, with a view towards scaling to the petaflop platforms and beyond. The long-term vision initiated with UNEDF is to arrive at a comprehensive, quantitative, and unified description of nuclei and their reactions, grounded in the fundamental interactions between the constituent nucleons. We seek to replace current phenomenological models of nuclear structure and reactions with a well-founded microscopic theory that delivers maximum predictive power with well-quantified uncertainties. Specifically, the mission of this project has been three-fold:  First, to find an optimal energy density functional (EDF) using all our knowledge of the nucleonic Hamiltonian and basic nuclear properties;  Second, to apply the EDF theory and its extensions to validate the functional using all the available relevant nuclear structure and reaction data;  Third, to apply the validated theory to properties of interest that cannot be measured, in particular the properties needed for reaction theory.

  20. Numerical analyses of an aircraft crash on containment building

    Energy Technology Data Exchange (ETDEWEB)

    Sim, Jae Min; Kim, Seung Hyun; Chang, Yoon Suk [Kyunghee University, Yongin (Korea, Republic of)

    2016-05-15

    The containment building is responsible to isolate and protect internal devices against external conditions like earthquake, hurricane and impact loading. It has also to protect leakage of radioactivity, like LOCA (Loss Of Coolant Accident), when severe accidents occurred. Meanwhile, social awareness such as terrorism has been increased globally after international aircraft crashes at World Trade Center and Pentagon. In this paper, FE (Finite Element) analyses according to variation of crash locations and speeds were carried out to examine the aircraft crash impact on a domestic containment building. In this paper, numerical analyses of aircraft crash on NPP's containment building were performed taking into account different locations and aircraft speeds. (1) Amounts of concrete failure were dependent on the crash locations and the connector was the most delicate location comparing to the dome and wall part. (2) Maximum stress values generated at the liner plate and rebars did not exceed their UTS values.

  1. Analysis of flammability in the attached buildings to containment under severe accident conditions

    Energy Technology Data Exchange (ETDEWEB)

    Rosa, J.C. de la, E-mail: juan-carlos.de-la-rosa-blul@ec.europa.eu [European Commission Joint Research Centre (Netherlands); Fornós, Joan, E-mail: jfornosh@anacnv.com [Asociación Nuclear Ascó-Vandellós (Spain)

    2016-11-15

    Highlights: • Analysis of flammability conditions in buildings outside containment. • Stepwise approach easily applicable for any kind of containment and attached buildings layout. • Detailed application for real plant conditions has been included. - Abstract: Right after the events unfolded in Fukushima Daiichi, the European Union countries agreed in subjecting Nuclear Power Plants to Stress Tests as developed by WENRA and ENSREG organizations. One of the results as implemented in many European countries derived from such tests consisted of mandatory technical instructions issued by nuclear regulatory bodies on the analysis of potential risk of flammable gases in attached buildings to containment. The current study addresses the key aspects of the analysis of flammable gases leaking to auxiliary buildings attached to Westinghouse large-dry PWR containment for the specific situation where mitigating systems to prevent flammable gases to grow up inside containment are available, and containment integrity is preserved – hence avoiding isolation system failure. It also provides a full practical exercise where lessons learned derived from the current study – hence limited to the imposed boundary conditions – are applied. The leakage of gas from the containment to the support buildings is based on separate calculations using the EPRI-owned Modular Accident Analysis Program, MAAP4.07. The FATE™ code (facility Flow, Aerosol, Thermal, and Explosion) was used to model the transport and distribution of leaked flammable gas (H{sub 2} and CO) in the penetration buildings. FATE models the significant mixing (dilution) which occurs as the released buoyant gas rises and entrains air. Also, FATE accounts for the condensation of steam on room surfaces, an effect which acts to concentrate flammable gas. The results of the analysis show that during a severe accident, flammable conditions are unlikely to occur in compartmentalized buildings such as the one used in the

  2. Spent nuclear fuel canister storage building conceptual design report

    Energy Technology Data Exchange (ETDEWEB)

    Swenson, C.E. [Westinghouse Hanford Co., Richland, WA (United States)

    1996-01-01

    This Conceptual Design Report provides the technical basis for the Spent Nuclear Fuels Project, Canister Storage Building, and as amended by letter (correspondence number 9555700, M.E. Witherspoon to E.B. Sellers, ``Technical Baseline and Updated Cost Estimate for the Canister Storage Building``, dated October 24, 1995), includes the project cost baseline and Criteria to be used as the basis for starting detailed design in fiscal year 1995.

  3. Innovative Nuclear Power Plant Building Arrangement in Consideration of Decommissioning

    Directory of Open Access Journals (Sweden)

    Won-Jun Choi

    2017-04-01

    Full Text Available A new concept termed the Innovative Nuclear Power Plant Building Arrangement (INBA strategy is a new nuclear power plant building arrangement method which encompasses upfront consideration of more efficient decommissioning. Although existing decommissioning strategies such as immediate dismantling and differed dismantling has the advantage of either early site restoration or radioactive decommissioning waste reduction, the INBA strategy has the advantages of both strategies. In this research paper, the concept and the implementation method of the INBA strategy will be described. Two primary benefits will be further described: (1 early site restoration; and (2 radioactive waste reduction. Several other potential benefits will also be identified. For the estimation of economic benefit, the INBA strategy, with two primary benefits, will be compared with the immediate dismantling strategy. The effect of a short life cycle nuclear power plant in combination with the INBA strategy will be reviewed. Finally, some of the major impediments to the realization of this strategy will be discussed.

  4. Innovative nuclear power plant building arragement in consideration of decommissioning

    Energy Technology Data Exchange (ETDEWEB)

    Choi, Won Jun; Roh, Myung Sub; Kim, Chang Lak [Dept. of Nuclear Power Plant Engineering, KEPCO International Nuclear Graduate School, Ulsan (Korea, Republic of)

    2017-04-15

    A new concept termed the Innovative Nuclear Power Plant Building Arrangement (INBA) strategy is a new nuclear power plant building arrangement method which encompasses upfront consideration of more efficient decommissioning. Although existing decommissioning strategies such as immediate dismantling and differed dismantling has the advantage of either early site restoration or radioactive decommissioning waste reduction, the INBA strategy has the advantages of both strategies. In this research paper, the concept and the implementation method of the INBA strategy will be described. Two primary benefits will be further described: (1) early site restoration; and (2) radioactive waste reduction. Several other potential benefits will also be identified. For the estimation of economic benefit, the INBA strategy, with two primary benefits, will be compared with the immediate dismantling strategy. The effect of a short life cycle nuclear power plant in combination with the INBA strategy will be reviewed. Finally, some of the major impediments to the realization of this strategy will be discussed.

  5. Influence of heat transfer on walls due to aerosol decomposition rate in the containment building of nuclear power plants during heavy incidents; Einfluss des Waermeuebergangs an Waenden auf die Aerosolabbaurate im Sicherheitsbehaelter von Kernkraftwerken bei schweren Stoerfaellen

    Energy Technology Data Exchange (ETDEWEB)

    Braun, T.

    2004-07-01

    Today, German nuclear power plants are leading in safety standards worldwide. Increasing potentials arise continuously along with improvements in technology. One of these potentials is the best-estimate simulation of fission product transport in case of a severe accident. A main part of the fission products is allocated on aerosols. Therefore, the aerosol behavior before containment leakage is important for the radioactive source term to the environment. Having a good knowledge about the main aerosol phenomena, it is possible to simulate them numerically. This enables to develop and test safety measures to limit damages before accidents occur. Within this study, the main aerosol phenomena have been ascertained and accordingly classified into formation, transport and reduction. On this basis, simulations of one- and multi-component aerosol experiments of the KAEVER series have been performed with the COCOSYS code. Due to an overprediction of the computed volume condensation rate, the results showed an overestimation of the reduction rate of insoluble aerosols. The reason was found to be the underestimation of the wall condensation rate. Based on an additional plain thermal hydraulic multi compartment experiment, these uncertainties in the wall heat transfer correlations were investigated in detail. The results show a strong dependency between the wall condensation rate and the convective heat transfer, resp. the characteristic length. In case of mainly forced convection, correct values for the characteristic length led to an underestimation of the calculated heat transfer coefficients. The analysis of the heat transfer models show an inconsistency in the coupling of free and forced convection. Therefore, an improved and consistent convection model has been developed and implemented. Both models have been tested on different experiments. Although the new model shows only minor improvements, it could be proven that the influence for forced convection is significant

  6. Structural analyses of the storage container for heavy element facility, building-251

    Energy Technology Data Exchange (ETDEWEB)

    Ng, D S

    1999-01-01

    The Heavy Element Facility, Building 251, contains a series of underground storage vaults which are used for long term storage of nuclear materials. A storage rack with shelves is suspended from the top of each storage vault. The stainless steel containers enclosing the nuclear materials are stored on the shelves. A Hazard & Accident assessment analyzed the vulnerability of this storage system to assaults resulting from natural phenomena and accidents within the building. The assessment considered all racks and their containers to be stored underground and secured in their static, long-term configuration. Moving beyond the static, long-term hazard assessment, the structural analyses were performed to evaluate the storage container against a rare, short duration event. An accidental free drop of a container may occur in a combination of two events: a rare, short-duration earthquake concurrent with an operation of raising the storage rack to a maximum height that the crane is capable of. This hypothetical free drop may occur only to the container in the uppermost shelf of the storage rack. The analyses were the structural evaluation of the storage container to determine the material containment integrity of the storage container after the accident. The evaluation was performed simulating a free drop from the storage rack, with a maximum load in the container, striking/an unyielding surface in the worst orientation. The analyses revealed that, in the very unlikely event of a container drop, the integrity of the hermetic seal of the storage container could be compromised due to plastic deformation of the lid and mating flange. Simple engineering and administrative controls can prevent that from occurring.

  7. Damage assessment of nuclear containment against aircraft crash

    Energy Technology Data Exchange (ETDEWEB)

    Iqbal, Mohd Ashraf, E-mail: iqbal_ashraf@rediffmail.com; Sadique, Md. Rehan, E-mail: rehan.sadique@gmail.com; Bhargava, Pradeep, E-mail: bhpdpfce@iitr.ac.in; Bhandari, N.M., E-mail: nmbcefce@iitr.ac.in

    2014-10-15

    Highlights: • Damage assessment of nuclear containment is studied against aircraft crash. • Four impact locations have been identified at the outer containment shell. • The mid of the total height has been found to be most vulnerable location. • The crown of dome has been found to be the strongest location. • Phantom F4 caused more localized and severe damage compared to other aircrafts. - Abstract: The behavior of nuclear containment structure has been studied against aircraft crash with an emphasis on the influence of strike location. The impact locations identified on the BWR Mark III type nuclear containment structure are mid-height, junction of dome and cylinder, crown of dome and arc of dome. The containment at each of the above locations has been impacted normally by Phantom F-4, Boeing 707-320 and Airbus A320 aircrafts. The loading of the aircraft has been assigned through the corresponding reaction-time response curve. ABAQUS/Explicit finite element code has been used to carry out the three-dimensional numerical simulations. The concrete damaged plasticity model was used to simulate the behavior of concrete while the behavior of steel reinforcement was incorporated using the Johnson–Cook elasto-viscoplastic material model. The mid-height of containment has been found to experience most severe deformation against each aircraft. Phantom F4 has been found to be most disastrous at each location. The results have been compared with those of the available studies with respect to the containment deformation.

  8. Impact of risk analysis on ITER nuclear buildings layout

    Energy Technology Data Exchange (ETDEWEB)

    Sabathe, Laurent [AREVA NP SAS, 10 rue Juliette Recamier, 69456 Lyon Cedex 06 (France)], E-mail: laurent.sabathe@areva.com; Lignini, Franck [AREVA NP SAS, 10 rue Juliette Recamier, 69456 Lyon Cedex 06 (France)], E-mail: franck.lignini@areva.com; Rodriguez-Rodrigo, Lina [EFDA-CSU Barcelona and Asociacion EURATOM-CIEMAT para Fusion, 08019 Barcelona (Spain); Uzan-Elbez, Joelle [Agence ITER-France, Cadarache, St Paul Lez Durance F-13108 (France); Girard, Jean-Philippe [ITER-JWS, Cadarache, St Paul Lez Durance F-13108 (France)

    2007-10-15

    The internal layout of ITER nuclear buildings (Tokamak, Tritium, Hot cell and Radwaste buildings) is the result of an iterative process. Notwithstanding civil engineering requirements, technical and functional requirements for the processes housed in the buildings, the internal layout must also take into account safety requirements and workers protection requirements in normal, incidental and accidental conditions. Potential hazards and constraints result in the definition of various zonings. Each room is classified depending on the level of the risks induced by normal and incidental or accidental conditions: - radiological exposure to tritium, and activated products {yields} radiological zoning; - exposure to beryllium (vacuum vessel blankets) {yields} beryllium zoning; - exposure to electromagnetic fields during plasma shots {yields} electromagnetic zoning; - fire hazard: fire compartmentalization; {center_dot}explosion hazard: anti-blast zoning; - waste treatment {yields} waste zoning. Prevention of common mode failure due to internal hazards (fire, flooding, load drop...) for redundant safety important components is also taken into account by geographical separation or by installation of protections between components (either in the same room or preferably when possible by segregation in different rooms). The designer has also taken into account access requirements to equipments and circulation rules for personal, material and substances in ITER nuclear buildings. Risk analyses are performed in the Preliminary Safety Report in order to demonstrate that the layout of ITER nuclear buildings allows meeting the safety objectives and takes into account the requirements associated with the zonings classifications and complies with the regulation. When necessary, modifications are implemented in the design. For example, recent layout modifications are been studied in the tritium building: utility rooms (electrical supply) were transferred outside the radiological

  9. Overview of nuclear new build projects and global perspective

    Energy Technology Data Exchange (ETDEWEB)

    Poncelet, Jean-Pol [FORATOM, Brussels (Belgium)

    2017-05-15

    Nuclear power is an important source for electricity production in Europe: today 131 reactors are operated in 14 EU Member States, delivering 28 % of the European power and one half of its low-carbon electricity. The turnover of the sector is about 70 billion Euro and there are about 800,000 high qualified jobs. Worldwide the capacities of nuclear power are extending. New build activities are moving to the Eastern countries. Today, the whole electricity market in Europe is characterised by uncertainties for all investments due to political market interventions. A common European energy policy does not appear to exist.

  10. Preliminary CFD Analysis for HVAC System Design of a Containment Building

    Energy Technology Data Exchange (ETDEWEB)

    Son, Sung Man; Choi, Choengryul [ELSOLTEC, Yongin (Korea, Republic of); Choo, Jae Ho; Hong, Moonpyo; Kim, Hyungseok [KEPCO Engineering and Construction, Gimcheon (Korea, Republic of)

    2016-10-15

    HVAC (Heating, Ventilation, Air Conditioning) system has been mainly designed based on overall heat balance and averaging concepts, which is simple and useful for designing overall system. However, such a method has the disadvantage that cannot predict the local flow and temperature distributions in a containment building. In this study, a CFD (Computational Fluid Dynamics) preliminary analysis is carried out to obtain detailed flow and temperature distributions in a containment building and to ensure that such information can be obtained via CFD analysis. This approach can be useful for hydrogen analysis in an accident related to hydrogen released into a containment building. In this study, CFD preliminary analysis has been performed to obtain the detailed information of the reactor containment building by using the CFD analysis techniques and to ensure that such information can be obtained via CFD analysis. We confirmed that CFD analysis can offer enough detailed information about flow patterns and temperature field and that CFD technique is a useful tool for HVAC design of nuclear power plants.

  11. A Wireless Monitoring System for Cracks on the Surface of Reactor Containment Buildings.

    Science.gov (United States)

    Zhou, Jianguo; Xu, Yaming; Zhang, Tao

    2016-06-14

    Structural health monitoring with wireless sensor networks has been increasingly popular in recent years because of the convenience. In this paper, a real-time monitoring system for cracks on the surface of reactor containment buildings is presented. Customized wireless sensor networks platforms are designed and implemented with sensors especially for crack monitoring, which include crackmeters and temperature detectors. Software protocols like route discovery, time synchronization and data transfer are developed to satisfy the requirements of the monitoring system and stay simple at the same time. Simulation tests have been made to evaluate the performance of the system before full scale deployment. The real-life deployment of the crack monitoring system is carried out on the surface of reactor containment building in Daya Bay Nuclear Power Station during the in-service pressure test with 30 wireless sensor nodes.

  12. International nuclear fuel cycle fact book. [Contains glossary

    Energy Technology Data Exchange (ETDEWEB)

    Leigh, I.W.; Lakey, L.T.; Schneider, K.J.; Silviera, D.J.

    1987-01-01

    As the US Department of Energy (DOE) and DOE contractors have become increasingly involved with other nations in nuclear fuel cycle and waste management cooperative activities, a need has developed for a ready source of information concerning foreign fuel cycle programs, facilities, and personnel. This Fact Book was compiled to meet that need. The information contained has been obtained from nuclear trade journals and newsletters; reports of foreign visits and visitors; CEC, IAEA, and OECD/NEA activities reports; proceedings of conferences and workshops; and so forth. Sources do not agree completely with each other, and the data listed herein does not reflect any one single source but frequently is a consolidation/combination of information. Lack of space as well as the intent and purpose of the Fact Book limit the given information to that pertaining to the Nuclear Fuel Cycle and to data considered of primary interest or most helpful to the majority of users.

  13. Nuclear containment steel liner corrosion workshop : final summary and recommendation report.

    Energy Technology Data Exchange (ETDEWEB)

    Erler, Bryan A. (Erler Engineering Ltd., Chicago, IL); Weyers, Richard E. (Virginia Tech University, Blacksburg, VA); Sagues, Alberto (University of South Florida, Tampa, FL); Petti, Jason P.; Berke, Neal Steven (Tourney Consulting Group, LLC, Kalamazoo, MI); Naus, Dan J. (Oak Ridge National Laboratory, Oak Ridge, TN)

    2011-07-01

    This report documents the proceedings of an expert panel workshop conducted to evaluate the mechanisms of corrosion for the steel liner in nuclear containment buildings. The U.S. Nuclear Regulatory Commission (NRC) sponsored this work which was conducted by Sandia National Laboratories. A workshop was conducted at the NRC Headquarters in Rockville, Maryland on September 2 and 3, 2010. Due to the safety function performed by the liner, the expert panel was assembled in order to address the full range of issues that may contribute to liner corrosion. This report is focused on corrosion that initiates from the outer surface of the liner, the surface that is in contact with the concrete containment building wall. Liner corrosion initiating on the outer diameter (OD) surface has been identified at several nuclear power plants, always associated with foreign material left embedded in the concrete. The potential contributing factors to liner corrosion were broken into five areas for discussion during the workshop. Those include nuclear power plant design and operation, corrosion of steel in contact with concrete, concrete aging and degradation, concrete/steel non-destructive examination (NDE), and concrete repair and corrosion mitigation. This report also includes the expert panel member's recommendations for future research.

  14. Evaluation of a hydrogen sensor for nuclear reactor containment monitoring

    Energy Technology Data Exchange (ETDEWEB)

    Hoffheins, B.S.; McKnight, T.E.; Lauf, R.J.; Smith, R.R. [Oak Ridge National Lab., TN (United States); James, R.E. [Electric Power Research Inst., Palo Alto, CA (United States)

    1997-02-01

    Measurement of hydrogen concentration in containment atmospheres in nuclear plants is a key safety capability. Current technologies require extensive sampling systems and subsequent maintenance and calibration costs can be very expensive. A new hydrogen sensor has been developed that is small and potentially inexpensive to install and maintain. Its size and low power requirement make it suitable in distributed systems for pinpointing hydrogen buildup. This paper will address the first phase of a testing program conducted to evaluate this sensor for operation in reactor containments.

  15. Analysis of impact of large commercial aircraft on a prestressed containment building

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Kyoungsoo, E-mail: kylee@pvamu.edu [Center for Energy and Environmental Sustainability, Prairie View A and M University, Prairie view, TX, 77446 (United States); Han, Sang Eul, E-mail: hsang@inha.ac.kr [Department of Architectural Engineering, School of Architecture, Inha University, 253 Yonghyundong Nam-gu, Incheon, 402-751 (Korea, Republic of); Hong, Jung-Wuk, E-mail: j.hong@kaist.ac.kr [Department of Civil and Environmental Engineering, KAIST, 373-1 Guseon-dong, Yuseong-gu, Daejeon, 305-701 (Korea, Republic of)

    2013-12-15

    Highlights: • Aircraft impact analyses are performed using the missile–target interaction method. • A large commercial B747 aircraft is considered with erosion effect. • The rigid wall impact test shows the validity of the developed aircraft model. • The parametric studies on the fictitious containment building are performed. • The plastic failure of the target is governed by the impulse of aircraft at the first momentum peak. - Abstract: In this paper, the results of nonlinear dynamic analyses of a concrete containment building under extreme loads are presented. The impact of a large commercial B747 airliner is investigated as the extreme load, and a rigid wall impact test is performed using commercial nonlinear finite element codes. The impact forces exerted by the aircraft are verified compared with the time-dependent impact force provided by OECD/NEA (2002), which was calculated based on the so-called Riera method. The rigid wall impact analysis shows that the finite element model of a B747 is appropriate for the purpose of the aircraft crash analysis exposed to the external hazard of “Beyond Design-Basis Events” defined by U.S. Nuclear Regulatory Commission. Finally, the applicability of this methodology is further studied and verified by conducting parametric studies on the critical infrastructures of nuclear power plant containment structures.

  16. Los Alamos National Laboratory standard nuclear material container

    Energy Technology Data Exchange (ETDEWEB)

    Stone, Timothy A [Los Alamos National Laboratory

    2009-01-01

    The shut down of United States (U.S.) nuclear-weapons production activities in the early 1990s left large quantities of nuclear materials throughout the U.S. Department of Energy (DOE) complex in forms not intended for long-term storage. In May 1994, the Defense Nuclear Facilities Safety Board (DNFSB) issued Recommendation 94-1, which called for the stabilization and disposition of 'thousands of containers of plutonium-bearing liquids and solids' in the DOE complex, including LANL in the nuclear-weapons-manufacturing pipeline when manufacturing ended. This resulted in the development of the 3013 standard with container requirements for long term storage (up to 50 years). A follow on was the Criteria For Interim Storage of Plutonium Bearing Materials, Charles B. Curtis, in 1996 to address storage other than the 3013 standard for shorter time frames. In January 2000, the DNFSB issued Recommendation 2000-1, which stated the need for LANL to repackage 'about one ton of plutonium metal and oxide,' declared excess to Defense Program (DP) needs. The DNFSB recommended that LANL 'stabilize and seal within welded containers with an inert atmosphere the plutonium oxides ... which are not yet in states conforming to the long-term storage envisaged by DOE-STD-3013,' and that they '... enclose existing and newly-generated legacy plutonium metal in sealed containers with an inert atmosphere,' and 'remediate and/or safely store the various residues.' Recommendation 2000-1, while adding to the number of items needing remediation, also reiterated the need to address remaining items from 1994-1 in a timely fashion. Since timetables slipped, the DNFSB recommended that the Complex 'prioritize and schedule tasks according to the consideration of risks.' In March 2005, the DNFSB issued Recommendation 2005-1. This recommendation addresses the need for a consistent set of criteria across the DOE complex for the interim storage of

  17. Uncanistered Spent Nuclear fuel Disposal Container System Description Document

    Energy Technology Data Exchange (ETDEWEB)

    N. E. Pettit

    2001-07-13

    The Uncanistered Spent Nuclear Fuel (SNF) Disposal Container System supports the confinement and isolation of waste within the Engineered Barrier System of the Monitored Geologic Repository (MGR). Disposal containers are loaded with intact uncanistered assemblies and/or individually canistered SNF assemblies and sealed in the surface waste handling facilities, transferred to the underground through the access drifts, and emplaced in emplacement drifts. The Uncanistered SNF Disposal Container provides long-term confinement of the commercial SNF placed inside, and withstands the loading, transfer, emplacement, and retrieval loads and environments. The Uncanistered SNF Disposal Container System provides containment of waste for a designated period of time, and limits radionuclide release. The disposal container maintains the waste in a designated configuration, withstands maximum handling and rockfall loads, limits the individual SNF assembly temperatures after emplacement, limits the introduction of moderator into the disposal container during the criticality control period, resists corrosion in the expected handling and repository environments, and provides containment of waste in the event of an accident.

  18. Nuclear emergency buildings of Asco and Vandellos II nuclear power plants; Centros alternativos de emergencias de las centrales nucleares de Asco y Vandellos II

    Energy Technology Data Exchange (ETDEWEB)

    Massuet, J.; Sabater, J.; Mirallas Esteban, S.

    2016-08-01

    The Nuclear Emergency Buildings sited at Asco and Vandellos II Nuclear Power Plants (NPP) are designed to safety manage emergencies in extreme situations, beyond the design basis of the Nuclear Power Plants. Designed in accordance with the requirements of the Spanish Nuclear Regulator (Consejo de Seguridad Nuclear-CSN) these buildings are ready to operate over a period of 72 hours without external assistance and ensure habitability for crews of 120 and 70 people respectively. This article describes the architectural conception, features and major systems of the Nuclear Emergency Buildings sited at Asco and Vandellos II. (Author)

  19. Nuclear containment structure subjected to commercial and fighter aircraft crash

    Energy Technology Data Exchange (ETDEWEB)

    Sadique, M.R., E-mail: rehan.sadique@gmail.com; Iqbal, M.A., E-mail: iqbalfce@iitr.ernet.in; Bhargava, P., E-mail: bhpdpfce@iitr.ernet.in

    2013-07-15

    Highlights: • Nuclear containment response has been studied against aircraft crash. • Concrete damaged plasticity and Johnson–Cook elasto-viscoplastic models were employed. • Boeing 747-400 and Boeing 767-400 aircrafts caused global failure of containment. • Airbus A320 and Boeing 707-320 aircrafts caused local damage. • Tension damage of concrete was found more prominent compared to compression damage. -- Abstract: The response of a boiling water reactor (BWR) nuclear containment vessel has been studied against commercial and fighter aircraft crash using a nonlinear finite element code ABAQUS. The aircrafts employed were Boeing 747-400, Boeing 767-400, Airbus A-320, Boeing 707-320 and Phantom F4. The containment was modeled as a three-dimensional deformable reinforced concrete structure while the loading of aircraft was assigned using the respective reaction–time curve. The location of strike was considered near the junction of dome and cylinder, and the angle of incidence, normal to the containment surface. The material behavior of the concrete was incorporated using the damaged plasticity model while that of the reinforcement, the Johnson–Cook elasto-viscoplastic model. The containment could not sustain the impact of Boeing 747-400 and Boeing 767-400 aircrafts and suffered rupture of concrete around the impact region leading to global failure. On the other hand, the maximum local deformation at the point of impact was found to be 0.998 m, 0.099 m, 0.092 m, 0.089 m, and 0.074 m against Boeing 747-400, Phantom F4, Boeing 767, Boeing 707-320 and Airbus A-320 aircrafts respectively. The results of the present study were compared with those of the previous analytical and numerical investigations with respect to the maximum deformation and overall behavior of the containment.

  20. Output-Only Modal Identification of a Containment Building from Ambient Vibration Measurements

    Energy Technology Data Exchange (ETDEWEB)

    Park, Soo-Yong; Shin, Yung-Moo; Kim, Ha-Yeon [Korea Maritime University, Pusan (Korea, Republic of); Choi, Sang-Hyun; Kim, Dae-Hyuk [Korea National Railroad College, Uiwang (Korea, Republic of); Hyun, Chang-Hun; Kim, Moon-Soo; Kim, Sang-Yun [Korea Institute of Nuclear Safety, Daejeon (Korea, Republic of)

    2008-10-15

    Ensuring and maintaining the structural integrity of the containment building (CB) in nuclear power plants is essential in preserving the nuclear reactor and other safety related systems from man-made as well as natural disasters, and protecting plant workers and publics from hazardous radioactive materials. To date, the structural integrity of the CB has been evaluated periodically via visual inspections, chemical tests, nondestructive strength tests, etc. However, these methods can only provide the local information on the structural condition and require considerable time and cost to estimate overall structural integrity. In this paper, the possibility of monitoring the structural integrity of a CB utilizing ambient vibration measurement (AVM) is explored. The ambient vibration testing has gained attention which can avoid the interruption of normal operation of civil structures. To fulfill the objective, the ambient vibration of the CB of the Ulchin 5th unit was measured, and the modal parameters, resonant frequencies and corresponding mode shapes, were extracted.

  1. Insights into the behavior of nuclear power plant containments during severe accidents

    Energy Technology Data Exchange (ETDEWEB)

    Horschel, D.S.; Ludwigsen, J.S.; Parks, M.B.; Lambert, L.D. [Sandia National Labs., Albuquerque, NM (United States); Dameron, R.A.; Rashid, Y.R. [ANATECH Research Corp., San Diego, CA (United States)

    1993-06-01

    The containment building surrounding a nuclear reactor offers the last barrier to the release of radioactive materials from a severe accident into the environment. The loading environment of the containment under severe accident conditions may include much greater than design pressures and temperatures. Investigations into the performance of containments subject to ultimate or failure pressure and temperature conditions have been performed over the last several years through a program administered by the Nuclear Regulatory Commission (NRC). These NRC sponsored investigations are subsequently discussed. Reviewed are the results of large scale experiments on reinforced concrete, prestressed concrete, and steel containment models pressurized to failure. In conjunction with these major tests, the results of separate effect testing on many of the critical containment components; that is, aged and unaged seals, a personnel air lock and electrical penetration assemblies subjected to elevated temperature and pressure have been performed. An objective of the NRC program is to gain an understanding of the behavior of typical existing and planned containment designs subject to postulated severe accident conditions. This understanding has led to the development of experimentally verified analytical tools that can be applied to accurately predict their ultimate capacities useful in developing severe accident mitigation schemes. Finally, speculation on the response of containments subjected to severe accident conditions is presented.

  2. Analysis of Potential Risk Caused by Hydrogen and Carbon Monoxide in Buildings Attached to Containment for Asco 1 and 2 and Vandellos II NPPs

    Energy Technology Data Exchange (ETDEWEB)

    Nos, V.; Rosa, C. de la; Lee, S. J.; Burelbach, J.; Plys, M.; Fornos, J.

    2014-07-01

    The Consejo de Seguridad Nuclear (CSN) of Spain issued a Technical Instruction encouraging nuclear power plant s to analyze the potential risk of hydrogen in the buildings attached to containment [1]. According to the Technical Instruction, the analysis should assume that all severe accident mitigation features are available, including those that are planned but not yet in place. (Author)

  3. Characterization of nuclear reactor containment penetrations. Preliminary report

    Energy Technology Data Exchange (ETDEWEB)

    Bump, T.R.; Seidensticker, R.W.; Shackelford, M.A.; Gambhir, V.K.; McLennan, G.L.

    1984-06-01

    This report summarizes the survey work conducted by Argonne National Laboratory on the design and details of major penetrations in 22 nuclear power plants. The survey includes all containment types and materials in current use. It also includes details of all types of penetrations (except for electrical penetration assemblies and valves) and the seals and gaskets used in them. The report provides a test matrix for testing major penetrations and for testing seals and gaskets in order to evaluate their leakage potential under severe accident conditions.

  4. 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.)

  5. Nuclear shielding of openings in ITER Tokamak building

    Energy Technology Data Exchange (ETDEWEB)

    Dammann, A., E-mail: alexis.dammann@iter.org [ITER Organization, Route de Vinon sur Verdon, 13115 Saint Paul Lez Durance (France); Arumugam, A.P.; Beaudoin, V.; Beltran, D.; Benchikhoune, M.; Berruyer, F.; Cortes, P.; Gandini, F. [ITER Organization, Route de Vinon sur Verdon, 13115 Saint Paul Lez Durance (France); Ghirelli, N. [ASSYSTEM E.O.S, ZAC Saint Martin, 23, rue Benjamin Franklin, 84120 Pertuis (France); Gray, A.; Hurzlmeier, H.; Le Page, M. [ITER Organization, Route de Vinon sur Verdon, 13115 Saint Paul Lez Durance (France); Lemée, A. [SOGETI High Tech, 180 Rue René Descartes, 13851 Aix en Provence (France); Lentini, G.; Loughlin, M.; Mita, Y.; Patisson, L.; Rigoni, G.; Rathi, D.; Song, I. [ITER Organization, Route de Vinon sur Verdon, 13115 Saint Paul Lez Durance (France)

    2013-10-15

    Highlights: ► Establishment of a methodology to design shielded opening in external wall of the Tokamak building. ► Analysis of the shielding requirement, case by case, depending on the localization and the context. ► Implementation of an integrated solution for shielded opening. -- Abstract: The external walls of the Tokamak building, made of thick concrete, provide the nuclear shielding for operators working in adjacent buildings and for the environment. There are a series of openings to these external walls, devoted to ducts or pipes for ventilation, waveguides and transmission lines for heating systems and diagnostics, cooling pipes, cable trays or busbars. The shielding properties of the wall shall be preserved by adequate design of the openings in order not to affect the radiological zoning in adjacent areas. For some of them, shielding properties of the wall are not affected because the size of the network is quite small or the source is far from the opening. But for most of the openings, specific features shall be considered. Even if the approach is the same and the ways to shield can be standardized, specific analysis is requested in any case because the constraints are different.

  6. Physical modeling of spent-nuclear-fuel container

    Directory of Open Access Journals (Sweden)

    Wang Liping

    2012-11-01

    Full Text Available A new physical simulation model was developed to simulate the casting process of the ductile iron heavy section spent-nuclear-fuel container. In this physical simulation model, a heating unit with DR24 Fe-Cr-Al heating wires was used to compensate the heat loss across the non-natural surfaces of the sample, and a precise and reliable casting temperature controlling/monitoring system was employed to ensure the thermal behavior of the simulated casting to be similar to the actual casting. Also, a mould system was designed, in which changeable mould materials can be used for both the outside and inside moulds for different applications. The casting test was carried out with the designed mould and the cooling curves of central and edge points at different isothermal planes of the casting were obtained. Results show that for most isothermal planes, the temperature control system can keep the temperature differences within 6 ℃ between the edge points and the corresponding center points, indicating that this new physical simulation model has high simulation accuracy, and the mould developed can be used for optimization of casting parameters of spent-nuclear-fuel container, such as composition of ductile iron, the pouring temperature, the selection of mould material and design of cooling system. In addition, to maintain the spheroidalization of the ductile iron, the force-chilling should be used for the current physical simulation to ensure the solidification of casting in less than 2 h.

  7. A Hydrogen Containment Process For Nuclear Thermal Engine Ground Testing

    Science.gov (United States)

    Wang, Ten-See; Stewart, Eric; Canabal, Francisco

    2016-01-01

    A hydrogen containment process was proposed for ground testing of a nuclear thermal engine. The hydrogen exhaust from the engine is contained in two unit operations: an oxygen-rich burner and a tubular heat exchanger. The burner burns off the majority of the hydrogen, and the remaining hydrogen is removed in the tubular heat exchanger through the species recombination mechanism. A multi-dimensional, pressure-based multiphase computational fluid dynamics methodology was used to conceptually sizing the oxygen-rich burner, while a one-dimensional thermal analysis methodology was used to conceptually sizing the heat exchanger. Subsequently, a steady-state operation of the entire hydrogen containment process, from pressure vessel, through nozzle, diffuser, burner and heat exchanger, was simulated numerically, with the afore-mentioned computational fluid dynamics methodology. The computational results show that 99% of hydrogen reduction is achieved at the end of the burner, and the rest of the hydrogen is removed to a trivial level in the heat exchanger. The computed flammability at the exit of the heat exchanger is less than the lower flammability limit, confirming the hydrogen containment capability of the proposed process.

  8. Thermal analysis of a building brick containing phase change material

    Energy Technology Data Exchange (ETDEWEB)

    Alawadhi, E.M. [Kuwait Univ., Safat (Kuwait). Dept. of Mechanical Engineering

    2008-07-01

    This paper presents the thermal analysis of a building brick containing phase change material (PCM) to be used in hot climates. The objective of using the PCM is to utilize its high latent heat of fusion to reduce the heat gain by absorbing the heat in the bricks through the melting process before it reaches the indoor space. The considered model consists of bricks with cylindrical holes filled with PCM. The problem is solved in a two-dimensional space using the finite element method. The thermal effectiveness of the proposed brick-PCM system is evaluated by comparing the heat flux at the indoor surface to a wall without the PCM during typical working hours. A paramedic study is conducted to assess the effect of different design parameters, such as the PCM's quantity, type, and location in the brick. The results indicate that the heat gain is significantly reduced when the PCM is incorporated into the brick, and increasing the quantity of the PCM has a positive effect. PCM cylinders located at the centerline of the bricks shows the best performance. (author)

  9. Prediction of prestressing losses for long term operation of nuclear reactor buildings

    Directory of Open Access Journals (Sweden)

    Thillard G.

    2011-04-01

    Full Text Available Prestressed concrete is used in nuclear reactor buildings to guarantee containment and structural integrity in case of an accident. Monitoring and operating experience over 40 years has shown that prestressing losses can be much greater than the design estimation based on the usual standard laws. A method was developed to determine the realistic residual prestress level in structures, in particular for those where no embedded instrumentation was installed, taking into account in situ measurement results rather than design characteristics. The results can enable the owner to justify extending the lifespan while guaranteeing adequate safety and to define and plan adequate maintenance actions.

  10. Evaluation of prestress losses in nuclear reactor containments

    Energy Technology Data Exchange (ETDEWEB)

    Lundqvist, Peter, E-mail: peter.lundqvist@kstr.lth.s [Div. of Structural Engineering, Lund University, Lund (Sweden); Nilsson, Lars-Olof [Div. of Building Materials, Lund University, Lund (Sweden)

    2011-01-15

    Research highlights: Prestress losses in reactor containments were estimated using prediction models. The predicted prestress losses were compared to long-term measurements. The accuracy of the models was improved by considering actual drying conditions. Predictions by CEB/FIP MC 1999 and ACI 209 were closest to the measured losses. - Abstract: The most critical safety barrier in a nuclear power plant, the concrete containment, is prestressed by hundreds of tendons, both horizontally and vertically. The main purpose of the containment is to prevent radioactive discharge to the environment in the case of a serious internal accident. Due to creep and shrinkage of concrete and relaxation of the prestressing steel, tendon forces decrease with time. These forces are thus measured in Swedish containments with unbonded tendons at regular in-service inspections. In this paper, the prestress losses obtained from these in-service inspections are compared to losses estimated using several prediction models for creep, shrinkage and relaxation. In an attempt to increase the accuracy of these models, existing expressions for the development of shrinkage were modified using previous findings on the humidity and temperature inside two Swedish containments. The models which were used and modified for predicting creep and shrinkage were CEB-FIP Model Codes 1990 and 1999, ACI 209, Model B3 and GL2000. Eurocode 2 was used for the prediction of relaxation. The results show that the most accurate of the models were CEB/FIP MC 99 and ACI 209. Depending on the model, the accuracy of the prediction models was increased by 0.5-1.2 percentage points of prestress losses when using the modified development of shrinkage. Furthermore, it was found that the differences between the different models depend mainly on the prediction of creep. Possible explanations for the deviation between the calculated and measured models can be the influence of reinforcement on creep and shrinkage of concrete and

  11. ANSYS 3-D analysis of nuclear steel containment

    Energy Technology Data Exchange (ETDEWEB)

    Fanous, F.; Greimann, L.; Rogers, J. (Iowa State Univ. of Science and Technology, Ames, IA (USA))

    1990-10-01

    Considerable analytical and experimental research has been devoted recently to containment building performance under severe accident loadings. Among other potential leakage paths, the containment shell may fail in highly strained regions and release radioactive material into the surrounding environment. After testing 1:32-scale and 1:8-scale steel models, the researchers at Sandia National Laboratories have suggested that the rupture of a steel containment will occur when the equivalent membrane strain reaches the ultimate strain of the material with some allowance for higher strain for bending. The actual containment geometry must be analysed when these criteria are applied. The objective of this paper is to demonstrate the capabilities of the ANSYS finite element program to predict a containment failure pressure utilising the Sandia failure criteria. This was accomplished by analysing a portion of the as-built 1:8-scale model. The overall size of the model was determined from Saint-Venant type considerations of the stress field around the model equipment hatch. Geometric and material nonlinear behaviours were included. Triangular shell (STIF48 in the ANSYS element library) elements were used in the finite element model. The model was loaded in steps up to a pressure of 165 psi (1.138 MPa). At this pressure, a strain of 19.7 percent was induced into the intersection between the shell ring stiffener and the equipment hatch-formed stiffener. The ANSYS large deflection, small-strain analysis results agreed well with the Sandia experimental results and with those predicted by the large deflection, large strain analysis option available in MARC finite element code. (author).

  12. Gamma radiation induced changes in nuclear waste glass containing Eu

    Science.gov (United States)

    Mohapatra, M.; Kadam, R. M.; Mishra, R. K.; Kaushik, C. P.; Tomar, B. S.; Godbole, S. V.

    2011-10-01

    Gamma radiation induced changes were investigated in sodium-barium borosilicate glasses containing Eu. The glass composition was similar to that of nuclear waste glasses used for vitrifying Trombay research reactor nuclear waste at Bhabha Atomic Research Centre, India. Photoluminescence (PL) and electron paramagnetic resonance (EPR) techniques were used to study the speciation of the rare earth (RE) ion in the matrix before and after gamma irradiation. Judd-Ofelt ( J- O) analyses of the emission spectra were done before and after irradiation. The spin counting technique was employed to quantify the number of defect centres formed in the glass at the highest gamma dose studied. PL data suggested the stabilisation of the trivalent RE ion in the borosilicate glass matrix both before and after irradiation. It was also observed that, the RE ion distributes itself in two different environments in the irradiated glass. From the EPR data it was observed that, boron oxygen hole centre based radicals are the predominant defect centres produced in the glass after irradiation along with small amount of E’ centres. From the spin counting studies the concentration of defect centres in the glass was calculated to be 350 ppm at 900 kGy. This indicated the fact that bulk of the glass remained unaffected after gamma irradiation up to 900 kGy.

  13. Code manual for CONTAIN 2.0: A computer code for nuclear reactor containment analysis

    Energy Technology Data Exchange (ETDEWEB)

    Murata, K.K.; Williams, D.C.; Griffith, R.O.; Gido, R.G.; Tadios, E.L.; Davis, F.J.; Martinez, G.M.; Washington, K.E. [Sandia National Labs., Albuquerque, NM (United States); Tills, J. [J. Tills and Associates, Inc., Sandia Park, NM (United States)

    1997-12-01

    The CONTAIN 2.0 computer code is an integrated analysis tool used for predicting the physical conditions, chemical compositions, and distributions of radiological materials inside a containment building following the release of material from the primary system in a light-water reactor accident. It can also predict the source term to the environment. CONTAIN 2.0 is intended to replace the earlier CONTAIN 1.12, which was released in 1991. The purpose of this Code Manual is to provide full documentation of the features and models in CONTAIN 2.0. Besides complete descriptions of the models, this Code Manual provides a complete description of the input and output from the code. CONTAIN 2.0 is a highly flexible and modular code that can run problems that are either quite simple or highly complex. An important aspect of CONTAIN is that the interactions among thermal-hydraulic phenomena, aerosol behavior, and fission product behavior are taken into account. The code includes atmospheric models for steam/air thermodynamics, intercell flows, condensation/evaporation on structures and aerosols, aerosol behavior, and gas combustion. It also includes models for reactor cavity phenomena such as core-concrete interactions and coolant pool boiling. Heat conduction in structures, fission product decay and transport, radioactive decay heating, and the thermal-hydraulic and fission product decontamination effects of engineered safety features are also modeled. To the extent possible, the best available models for severe accident phenomena have been incorporated into CONTAIN, but it is intrinsic to the nature of accident analysis that significant uncertainty exists regarding numerous phenomena. In those cases, sensitivity studies can be performed with CONTAIN by means of user-specified input parameters. Thus, the code can be viewed as a tool designed to assist the knowledge reactor safety analyst in evaluating the consequences of specific modeling assumptions.

  14. Experimental results from pressure testing a 1:6-scale nuclear power plant containment

    Energy Technology Data Exchange (ETDEWEB)

    Horschel, D.S. [Sandia National Labs., Albuquerque, NM (United States)

    1992-01-01

    This report discusses the testing of a 1:6-scale, reinforced-concrete containment building at Sandia National Laboratories, in Albuquerque, New Mexico. The scale-model, Light Water Reactor (LWR) containment building was designed and built to the American Society of Mechanical Engineers (ASME) code by United Engineers and Constructors, Inc., and was instrumented with over 1200 transducers to prepare for the test. The containment model was tested to failure to determine its response to static internal overpressurization. As part of the US Nuclear Regulatory Commission`s program on containment integrity, the test results will be used to assess the capability of analytical methods to predict the performance of containments under severe-accident loads. The scaled dimensions of the cylindrical wall and hemispherical dome were typical of a full-size containment. Other typical features included in the heavily reinforced model were equipment hatches, personnel air locks, several small piping penetrations, and a ihin steel liner that was attached to the concrete by headed studs. In addition to the transducers attached to the model, an acoustic detection system and several video and still cameras were used during testing to gather data and to aid in the conduct of the test. The model and its instrumentation are briefly discussed, and is followed by the testing procedures and measured response of the containment model. A summary discussion is included to aid in understanding the significance of the test as it applies to real world reinforced concrete containment structures. The data gathered during SIT and overpressure testing are included as an appendix.

  15. Guidelines for Assessment and Abatement of Asbestos-Containing Materials in Buildings.

    Science.gov (United States)

    Pielert, James H.; Mathey, Robert G.

    This report presents guidelines, based on available information, for the assessment and abatement of asbestos-containing materials in buildings. Section 1 provides background information on the history and use of asbestos-containing products in buildings, the characteristics of asbestos fibers, products and materials containing asbestos, and…

  16. In-Place Filter Tester Instrument for Nuclear Material Containers.

    Science.gov (United States)

    Brown, Austin D; Moore, Murray E; Runnels, Joel T; Reeves, Kirk

    2016-05-01

    A portable instrument was developed to determine filter clogging and container leakage of in-place nuclear material storage canisters. This paper describes the development of an in-place filter tester for determining the "as found" condition of unopened canisters. The U.S. Department of Energy uses several thousand canisters for nuclear material storage, and air filters in the canister lids allow gases to escape while maintaining an equilibrated pressure without release of radioactive contamination. Diagnosing the filter condition and canister integrity is important for ensuring worker and public safety. Customized canister interfaces were developed for suction clamping (during tests) to two of the canister types in use at Los Alamos National Laboratory. Experimental leakage scenarios included: O-rings fouled with dust, cracked O-rings, and loose canister lids. The prototype tester has a measurement range for air leakage rates from 8.2 × 10 mL s up to 3.0 × 10 mL s. This is sufficient to measure a leak rate of 3.4 × 10 mL s, which is the Los Alamos helium leak criterion for post-drop tested canisters. The In-Place-Filter-Tester cannot measure to the lower value of the helium leak criterion for pre-drop tested canisters (1.0 × 10 mL s). However, helium leak testing requires canister disassembly, while the new in-place filter tester is able to assess the assembled condition of as-found and in-situ canisters.

  17. Building a Single Atom Microscope for Nuclear Astrophysics

    Science.gov (United States)

    Frisbie, Dustin; Johnson, Maegan; Parzuchowski, Kristen; Wenzl, Jennifer; Singh, Jaideep

    2017-01-01

    The primary research goal of this project is to develop a new technique of optical single atom detection to measure rare nuclear reactions at low energies. The 22Ne(α, n)25Mg reaction is of particular interest, as it is thought to be a primary source of neutrons in the s-process of massive stars. Nuclear reaction products are captured in a cryogenically frozen film of noble gas, which can contain a variety of guest atoms. These solids are ideal to use because they are optically transparent and simple to grow and purify. The sample is illuminated by laser light and imaged to identify fluorescing atoms. The atomic transitions of captured atoms indicate which atoms are present; only atoms which are excited at the laser wavelength will fluoresce. This offers high selectivity during experiments. We began development with Yb, a very bright guest atom, being embedded in a host of solid neon in order to study the optical properties necessary for single atom detection. In addition, we study background effects from the laser exciting contaminants in our substrates. We present data that indicates the efficiency with which we can excite and collect fluorescence light with our apparatus, and use it to propose a strategy for the development of Mg single atom detection. This work is generously supported by Michigan State University.

  18. Consideration on hydrogen explosion scenario in APR 1400 containment building during small breakup loss of coolant accident

    Energy Technology Data Exchange (ETDEWEB)

    Park, Kweonha, E-mail: khpark@kmou.ac.kr [Division of Mechanical & Energy Systems Engineering, Korea Maritime University, Dongsam-dong, Yeongdo-gu, Busan 606-791 (Korea, Republic of); Khor, Chong Lee, E-mail: itachi_829@hotmail.com [Department of Mechanical Engineering, Korea Maritime University, Dongsam-dong, Yeongdo-gu, Busan 606-791 (Korea, Republic of)

    2015-11-15

    Highlights: • Hydrogen behavior in the containment building of APR1400 nuclear plant up to 15 h after the failure happened. • The risk of hydrogen explosion largely depends on the combination of air, hydrogen and steam in the containment. • Hydrogen explosion risk at different locations in the containment was analyzed. - Abstract: This paper describes the analytical result of the potential risk of hydrogen gas up to 15 h after the failure takes place. The major cause of the disaster occurred in Fukushima Daiichi nuclear reactor was the detonation of accumulated hydrogen in the containment by highly increased reactor core temperatures after the failure of the emergency cooling system. The hydrogen risk should be considered in severe accident strategies in current and future NPPs. A hydrogen explosion scenario is proposed. Hydrogen is accumulated on top of the dome during the hydrogen release period. At this point, there are no risk of explosion due to the steam that resides in upper part of the dome. As the hydrogen concentration increase, substantial amount of steams are released. Subsequently, hydrogen is forced into the lower part of the building with high air density—small explosion and dormant steam condensation phase are possible. The light hydrogen rises up slowly with air, gathering on top of the building with high air density. Massive hydrogen explosion is anticipated upon ignition at this stage.

  19. Proceedings of the 25th Seismic Research Review -- Nuclear Explosion Monitoring: Building the Knowledge Base

    Energy Technology Data Exchange (ETDEWEB)

    Chavez, Francesca C. [Editor; Mendius, E. Louise [Editor

    2003-09-23

    These proceedings contain papers prepared for the 25th Seismic Research Review -- Nuclear Explosion Monitoring: Building the Knowledge Base, held 23-25 September, 2003 in Tucson, Arizona. These papers represent the combined research related to ground-based nuclear explosion monitoring funded by the National Nuclear Security Administration (NNSA), Defense Threat Reduction Agency (DTRA), Air Force Research Laboratory (AFRL), US Army Space and Missile Defense Command, and other invited sponsors. The scientific objectives of the research are to improve the United States capability to detect, locate, and identify nuclear explosions. The purpose of the meeting is to provide the sponsoring agencies, as well as potential users, an opportunity to review research accomplished during the preceding year and to discuss areas of investigation for the coming year. For the researchers, it provides a forum for the exchange of scientific information toward achieving program goals, and an opportunity to discuss results and future plans. Paper topics include: seismic regionalization and calibration; detection and location of sources; wave propagation from source to receiver; the nature of seismic sources, including mining practices; hydroacoustic, infrasound, and radionuclide methods; on-site inspection; and data processing.

  20. Numerical simulation of aircraft crash on nuclear containment structure

    Energy Technology Data Exchange (ETDEWEB)

    Iqbal, M.A., E-mail: iqbalfce@iitr.ernet.in [Department of Civil Engineering, Indian Institute of Technology Roorkee, Roorkee 247667 (India); Rai, S.; Sadique, M.R.; Bhargava, P. [Department of Civil Engineering, Indian Institute of Technology Roorkee, Roorkee 247667 (India)

    2012-02-15

    Highlights: Black-Right-Pointing-Pointer The deformation was more localised at the center of cylindrical portion. Black-Right-Pointing-Pointer The peak deflection at the junction of dome and cylinder was found to be 67 mm. Black-Right-Pointing-Pointer The peak deflection at midpoint of the cylindrical portion was found to be 88.9 mm. Black-Right-Pointing-Pointer The strain rate was found to be an important parameter to effect the deformation. Black-Right-Pointing-Pointer The model without strain rate and 290 s{sup -1} strain rate predicted very high deformations. - Abstract: Numerical simulations were carried with ABAQUS/Explicit finite element code in order to predict the response of BWR Mark III type nuclear containment against Boeing 707-320 aircraft crash. The load of the aircraft was applied using and force history curve. The damaged plasticity model was used to predict the behavior of concrete while the Johnson-Cook elasto-viscoplastic material model was used to incorporate the behavior of steel reinforcement. The crash was considered to occur at two different locations i.e., the midpoint of the cylindrical portion and the junction of dome and cylinder. The midpoint of the cylindrical portion experienced more deformation. The strain rate in the material model was varied and found to have a significant effect on the response of containment. The results of the present investigation were compared with those of the studies available in literature and a close agreement with the previous results was found in terms of maximum target deformation.

  1. Air leakage analysis of research reactor HANARO building in typhoon condition for the nuclear emergency preparedness

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Goany Up; Lee, Hae Cho; Kim, Bong Seok; Kim, Jong Soo; Choi, Pyung Kyu [Dept. of Emergency Preparedness, Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2016-12-15

    To find out the leak characteristic of research reactor 'HANARO' building in a typhoon condition MELCOR code which normally is used to simulate severe accident behavior in a nuclear power plant was used to simulate the leak rate of air and fission products from reactor hall after the shutdown of the ventilation system of HANARO reactor building. For the simulation, HANARO building was designed by MELCOR code and typhoon condition passed through Daejeon in 2012 was applied. It was found that the leak rate is 0.1%·day{sup -1} of air, 0.004%·day{sup -1} of noble gas and 3.7×10{sup -5}%·day{sup -1} of aerosol during typhoon passing. The air leak rate of 0.1%·day can be converted into 1.36 m{sup 3}·hr{sup -1} , but the design leak rate in HANARO safety analysis report was considered as 600 m3·hr{sup -1} under the condition of 20 m·sec{sup -1} wind speed outside of the building by typhoon. Most of fission products during the maximum hypothesis accident at HANARO reactor will be contained in the reactor hall, so the direct radiation by remained fission products in the reactor hall will be the most important factor in designing emergency preparedness for HANARO reactor.

  2. Nanostructured sensors containing immobilized nuclear receptors for thyroid hormone detection.

    Science.gov (United States)

    Bendo, Luana; Casanova, Monise; Figueira, Ana Carolina M; Polikarpov, Igor; Zucolotto, Valtencir

    2014-05-01

    Thyroid hormone receptors (TRs) are members of the nuclear receptors (NRs) superfamily, being encoded by two genes: TRa and TRbeta. In this paper, the ligand-binding domain (LBD) of the TRbeta1 isoform was immobilized on the surface of nanostructured electrodes for TR detection. The platforms containing TRbeta1-LBD were applied to the detection of specific ligand agonists, including the natural hormones T3 (triiodothyronine) and T4 (thyroxine), and the synthetic agonists TRIAC (3,5,3'-triiodothyroacetic acid) and GC-1 [3,5-dimethyl-4-(4'-hydroxy-3'-isopropylbenzyl phenoxy) acetic acid]. Detection was performed via impedance spectroscopy. The biosensors were capable of distinguishing between the thyroid hormones T3 and T4, and/or the analogues TRIAC and GC-1 at concentrations as low as 50 nM. The detection and separation of thyroid hormones and analogue ligands by impedance techniques represents an innovative tool in the field of nanomedicine because it allows the design of inexpensive devices for the rapid and real-time detection of distinct ligand/receptor systems.

  3. Safety assessment of a nuclear power plant building subjected to an aircraft crash

    Energy Technology Data Exchange (ETDEWEB)

    Thai, Duc-Kien; Kim, Seung-Eock, E-mail: sekim@sejong.ac.kr

    2015-11-15

    Highlights: • Numerical analysis of a nuclear auxiliary building under aircraft crash is conducted. • The analysis result of impact force is verified using the Riera function. • The safety assessment is performed with regard to different impact scenarios. • Discussions and conclusions on safety of the nuclear building are presented. - Abstract: This paper presents a safety assessment of a nuclear building subjected to an aircraft crash using numerical analysis. For impact simulation, the reinforced concrete (RC) Primary Auxiliary Building (PAB) of the Korea Standard Nuclear Power Plant (KSNP) is fully modeled and an aircraft model of a Boeing 767-400 is used. The Riera function is used to verify the analysis result of impact force–time history. The IRIS test is used to verify the structural behavior of the RC wall under impact loading. The safety assessment of the building is performed with regard to different impact scenarios. The safety of the nuclear building under aircraft crash, including (1) global structural safety, (2) local structural safety, and (3) vibration safety are evaluated and discussed. The results show that the global and local structural safety of the PAB is ensured in all impact scenarios. However, the vibration safety of the building is not ensured. In accordance, the regulatory guide of United States Nuclear Regulatory Commission (U.S. NRC), shutdown of the nuclear power plant is required.

  4. Probabilistic Internal Pressure Capacity Evaluation of Prestressed Concrete Containment Buildings using Bonded Tendons

    Energy Technology Data Exchange (ETDEWEB)

    Hahm, Dea Gi; Choi, In Kil; Seo, Jeong Moon; Chon, Young Sun; Kim, Min Kyu [KAERI, Daejeon (Korea, Republic of)

    2010-12-15

    In this research, an assessment method of the internal pressure fragility of the CANDU type containment buildings is developed. The uncertainties of the performance of the containment buildings, material properties and tendon characteristics are referred from the in-service inspection reports of Wolsung Unit 1. The containment buildings are modeled as a three-dimensional finite elements with considering the major opening and penetrations. A new method to evaluate the probabilistic fragility of the massive structural system is proposed. The fragility curves of the target containment building are presented with respect to the failure modes and reliability levels. The center of wall is reveled as the most weak structural component of the containment building in the sense of the rupture and catastrophic rupture failure modes

  5. North Korea’s 2009 Nuclear Test: Containment, Monitoring, Implications

    Science.gov (United States)

    2010-04-02

    50 years of the nuclear weapons era, radiochemistry techniques were developed and used to determine the characteristics (such as yield, materials...meet national needs. Similarly, Congress, in P.L. 111-140, Nuclear Forensics and Attribution Act, found, “The number of radiochemistry programs and

  6. Lift-based up-ender and methods using same to manipulate a shipping container containing unirradiated nuclear fuel

    Energy Technology Data Exchange (ETDEWEB)

    Nilles, Michael J.

    2017-08-01

    A shipping container containing an unirradiated nuclear fuel assembly is lifted off the ground by operating a crane to raise a lifting tool comprising a winch. The lifting tool is connected with the shipping container by a rigging line connecting with the shipping container at a lifting point located on the shipping container between the top and bottom of the shipping container, and by winch cabling connecting with the shipping container at the top of the shipping container. The shipping container is reoriented by operating the winch to adjust the length of the winch cabling so as to rotate the shipping container about the lifting point. Shortening the winch cabling rotates the shipping container about the lifting point from a horizontal orientation to a vertical orientation, while lengthening the winch cabling rotates the shipping container about the lifting point from the vertical orientation to the horizontal orientation.

  7. Deccan Traps-associated obsidian glass: a nuclear waste containment

    National Research Council Canada - National Science Library

    Nishi Rani; J. P. Shrivastava; R. K. Bajpai

    2013-01-01

    Alteration of obsidian collected from Osham Hill, Gujarat after treatment under hydrothermal-like conditions is compared with the naturally altered obsidian for its assessment as a nuclear waste glass...

  8. A study on the functional assessment of the prestressed system and main structural elements in life extended containment building

    Energy Technology Data Exchange (ETDEWEB)

    Cheong, C. H.; Kim, S. W.; Choi, J. G. [DAEWOO E and C Institute of Costruction Technology, Suwon (Korea, Republic of)] (and others)

    2001-10-15

    The design life of KNGR (Korean Next Generation Reactor) containment buildings is extended from 40 years to 60 years. However, nuclear reactor buildings are passive structures that are impossible to be exchanged in the case of degradation by the deterioration and so on when extending the design life of structures. Therefore, it is necessary to consider the long-term safety endurance in the design and construction of KNGR. Also, ti is judged that choice of the material and various test methods should be prescribed clearly. In this study, the reduction schemes of deterioration and the safety-ensuring schemes are drawn for the expected performance to be maintained from the beginning of the service to the required period together with ensuring the safety and serviceability of KNGR which will be constructed with the design life of 60 years, taking into account the dimensions, selection of material and construction methods in the design and construction stages. Also, the validity is to be examined for the estimation method of long-term losses of stress introduced to KNGR whose design life is increased to 60 years. The durability enhancement scheme on the design and construction for the design life extension of nuclear containment buildings is to be drawn through these studies. These results are utilized as the basic data for the safety inspection and examination guides of KNGR and finally the additional investigations are proposed for the items which require long-term studies.

  9. Sources of evaluation of nuclear and renewable energy contained in the local press

    OpenAIRE

    1987-01-01

    Examined the sources of evaluative coverage concerning nuclear power and renewable alternatives contained in local UK daily press coverage. 10 categories of source were defined for their relevance to the nuclear debate and energy issues. Out of these, only pronuclear industries and national government produced more positive than negative appraisals of nuclear power. However, detractors of nuclear power were more varied, the most prolific category being the general public. Alternative technolo...

  10. Two Nations Underground: Building Schools to Survive Nuclear War and Desegregation in the 1960s

    Science.gov (United States)

    Preston, John

    2017-01-01

    In the 1960s federal agencies in the US encouraged the building of protected schools designed to survive a nuclear attack. A number of designs, including underground schools, were constructed. In order to promote the building of protected schools, the US government produced a number of propaganda films for school boards and governors. In addition…

  11. Two Nations Underground: Building Schools to Survive Nuclear War and Desegregation in the 1960s

    Science.gov (United States)

    Preston, John

    2017-01-01

    In the 1960s federal agencies in the US encouraged the building of protected schools designed to survive a nuclear attack. A number of designs, including underground schools, were constructed. In order to promote the building of protected schools, the US government produced a number of propaganda films for school boards and governors. In addition…

  12. Carolinas' Nuclear Cluster: building competency through collaboration

    Energy Technology Data Exchange (ETDEWEB)

    Little, J. [Carolinas' Nuclear Cluster (United States)

    2013-07-01

    This presentation discusses the Carolinas Nuclear Cluster that was built with collaboration amongst interested parties. The challenge facing the participants were availability of qualified & experienced workforce; retiring expertise; competition for resources within nuclear and other technology sectors; competition for skills and leadership; competing priorities in a changing environment such as slow growth in new nuclear in the U.S.; speedup in existing plant upgrades & retrofits and international project development. The established principles were collaboration amongst players, no competition, no borders, business driven focus on job creation, think as a global business, be willing to invest actively with money, talent, time and focus on results and not activities.

  13. Corrosion issues in high-level nuclear waste containers

    Science.gov (United States)

    Asl, Samin Sharifi

    In this dissertation different aspects of corrosion and electrochemistry of copper, candidate canister material in Scandinavian high-level nuclear waste disposal program, including the thermodynamics and kinetics of the reactions that are predicted to occur in the practical system have been studied. A comprehensive thermodynamic study of copper in contact with granitic groundwater of the type and composition that is expected in the Forsmark repository in Sweden has been performed. Our primary objective was to ascertain whether copper would exist in the thermodynamically immune state in the repository, in which case corrosion could not occur and the issue of corrosion in the assessment of the storage technology would be moot. In spite of the fact that metallic copper has been found to exist for geological times in granitic geological formations, copper is well-known to be activated from the immune state to corrode by specific species that may exist in the environment. The principal activator of copper is known to be sulfur in its various forms, including sulfide (H2S, HS-, S2-), polysulfide (H2Sx, HSx -, Sx 2-), poly sulfur thiosulfate ( SxO3 2-), and polythionates (SxO6 2-). A comprehensive study of this aspect of copper chemistry has never been reported, and yet an understanding of this issue is vital for assessing whether copper is a suitable material for fabricating canisters for the disposal of HLNW. Our study identifies and explores those species that activate copper; these species include sulfur-containing entities as well as other, non-sulfur species that may be present in the repository. The effects of temperature, solution pH, and hydrogen pressure on the kinetics of the hydrogen electrode reaction (HER) on copper in borate buffer solution have been studied by means of steady-state polarization measurements, including electrochemical impedance spectroscopy (EIS). In order to obtain electrokinetic parameters, such as the exchange current density and the

  14. BUILDING A UNIVERSAL NUCLEAR ENERGY DENSITY FUNCTIONAL (UNEDF)

    Energy Technology Data Exchange (ETDEWEB)

    Nazarewicz, Witold

    2012-07-01

    The long-term vision initiated with UNEDF is to arrive at a comprehensive, quantitative, and unified description of nuclei and their reactions, grounded in the fundamental interactions between the constituent nucleons. We seek to replace current phenomenological models of nuclear structure and reactions with a well-founded microscopic theory that delivers maximum predictive power with well-quantified uncertainties. Specifically, the mission of this project has been three-fold: First, to find an optimal energy density functional (EDF) using all our knowledge of the nucleonic Hamiltonian and basic nuclear properties. Second, to apply the EDF theory and its extensions to validate the functional using all the available relevant nuclear structure and reaction data. Third, to apply the validated theory to properties of interest that cannot be measured, in particular the properties needed for reaction theory.

  15. Steam explosions-induced containment failure studies for Swiss nuclear power plants

    Energy Technology Data Exchange (ETDEWEB)

    Zuchuat, O.; Schmocker, U. [Swiss Federal Nuclear Safety Inspectorate, Villigen (Switzerland); Esmaili, H.; Khatib-Rahbar, M.

    1998-01-01

    The assessment of the consequences of both in-vessel and ex-vessel energetic fuel-coolant interaction for Beznau (a Westinghouse pressurized water reactor with a large, dry containment), Goesgen (a Siemens/KWU pressurized water reactor with a large, dry containment) and Leibstadt (a General Electric boiling water reactor-6 with a free standing steel, MARK-III containment) nuclear power plants is presented in this paper. The Conditional Containment Failure Probability of the steel containment of these Swiss nuclear power plants is determined based on different probabilistic approaches. (author)

  16. Development of finite element models for the study of ageing effects in CANDU 6 concrete containment buildings

    Energy Technology Data Exchange (ETDEWEB)

    Ding, Y.; Jaffer, S., E-mail: Yuqing.Ding@cnl.ca [Canadian Nuclear Laboratories, Chalk River, Ontario (Canada)

    2016-06-15

    In nuclear power plants (NPPs), concrete containment buildings (CCBs) provide the final physical barrier against the release of radioactive materials into the environment and protect the nuclear structures housed within the containment building. CCBs have to be maintained to ensure leak tightness and sound structural integrity for the safe operation throughout the life of NPPs. However, the integrity of CCBs may be affected by the ageing of its concrete, post-tensioning cables and reinforcing bars (rebars). Finite element models (FEMs) of CANDU 6 CCBs have been developed using 2 independent finite element programs for the study of the effect of ageing of CCBs. These FEMs have been validated using multiple-source data and have been used for preliminary analyses of the effect of thermal load and ageing degradation on the concrete structure. The modelling assumptions and simplifications, approach, and validation are discussed in this paper. The preliminary analyses for temperature effects and potential applications to the study of ageing degradation in CCBs using the FEMs are briefly introduced. (author)

  17. 40 CFR 267.1103 - What additional design and operating standards apply if liquids will be in my containment building?

    Science.gov (United States)

    2010-07-01

    ... containment building and of sufficient strength and thickness to prevent collapse under the pressure exerted... standards apply if liquids will be in my containment building? 267.1103 Section 267.1103 Protection of... OPERATORS OF HAZARDOUS WASTE FACILITIES OPERATING UNDER A STANDARDIZED PERMIT Containment buildings § 267...

  18. Building A Universal Nuclear Energy Density Functional (UNEDF)

    Energy Technology Data Exchange (ETDEWEB)

    Carlson, Joe [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Furnstahl, Dick [The Ohio State Univ., Columbus, OH (United States); Horoi, Mihai [Central Michigan Univ., Mount Pleasant, MI (United States); Lusk, Rusty [Argonne National Lab. (ANL), Argonne, IL (United States); Nazarewicz, Witek [Univ. of Tennessee, Knoxville, TN (United States); Ng, Esmond [Lawrence Berkeley National Lab. (LBNL), Berkeley, CA (United States); Thompson, Ian [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Vary, James [Iowa State Univ., Ames, IA (United States)

    2012-09-30

    During the period of Dec. 1 2006 - Jun. 30, 2012, the UNEDF collaboration carried out a comprehensive study of all nuclei, based on the most accurate knowledge of the strong nuclear interaction, the most reliable theoretical approaches, the most advanced algorithms, and extensive computational resources, with a view towards scaling to the petaflop platforms and beyond. The long-term vision initiated with UNEDF is to arrive at a comprehensive, quantitative, and unified description of nuclei and their reactions, grounded in the fundamental interactions between the constituent nucleons. We seek to replace current phenomenological models of nuclear structure and reactions with a well-founded microscopic theory that delivers maximum predictive power with well-quantified uncertainties. Specifically, the mission of this project has been three-fold: first, to find an optimal energy density functional (EDF) using all our knowledge of the nucleonic Hamiltonian and basic nuclear properties; second, to apply the EDF theory and its extensions to validate the functional using all the available relevant nuclear structure and reaction data; third, to apply the validated theory to properties of interest that cannot be measured, in particular the properties needed for reaction theory. The main physics areas of UNEDF, defined at the beginning of the project, were: ab initio structure; ab initio functionals; DFT applications; DFT extensions; reactions.

  19. 40 CFR 267.1101 - What design and operating standards must my containment building meet?

    Science.gov (United States)

    2010-07-01

    ... containment building must be completely enclosed with a floor, walls, and a roof to prevent exposure to the elements, (e.g., precipitation, wind, run-on), and to assure containment of managed wastes. (b) The floor...) Physical contact with the hazardous wastes to which they are exposed. (iii) Climatic conditions....

  20. Sources of evaluation of nuclear and renewable energy contained in the local press

    NARCIS (Netherlands)

    van der Pligt, J.; Spears, R.; Eiser, J.R.

    1987-01-01

    Examined the sources of evaluative coverage concerning nuclear power and renewable alternatives contained in local UK daily press coverage. 10 categories of source were defined for their relevance to the nuclear debate and energy issues. Out of these, only pronuclear industries and national

  1. Sources of evaluation of nuclear and renewable energy contained in the local press

    NARCIS (Netherlands)

    van der Pligt, J.; Spears, R.; Eiser, J.R.

    1987-01-01

    Examined the sources of evaluative coverage concerning nuclear power and renewable alternatives contained in local UK daily press coverage. 10 categories of source were defined for their relevance to the nuclear debate and energy issues. Out of these, only pronuclear industries and national governme

  2. Monitoring the Durability Performance of Concrete in Nuclear Waste Containment. Technical Progress Report No. 3

    Energy Technology Data Exchange (ETDEWEB)

    Ulm, Franz-Josef

    2000-03-31

    OAK-B135 Monitoring the Durability Performance of Concrete in Nuclear Waste Containment. Technical Progress Report No. 3(NOTE: Part II A item 1 indicates ''PAPER'', but a report is attached electronically)

  3. A Hydrogen Containment Process for Nuclear Thermal Engine Ground testing

    Science.gov (United States)

    Wang, Ten-See; Stewart, Eric; Canabal, Francisco

    2016-01-01

    The objective of this study is to propose a new total hydrogen containment process to enable the testing required for NTP engine development. This H2 removal process comprises of two unit operations: an oxygen-rich burner and a shell-and-tube type of heat exchanger. This new process is demonstrated by simulation of the steady state operation of the engine firing at nominal conditions.

  4. Long-term reliability evaluation of nuclear containments with tendon force degradation

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Sang-Hyo, E-mail: sanghyo@yonsei.ac.kr; Choi, Moon-Seock, E-mail: ms50000@yonsei.ac.kr; Joung, Jung-Yeun, E-mail: jjoong@yonsei.ac.kr; Kim, Kun-Soo, E-mail: kun-soo_kim@yonsei.ac.kr

    2013-12-15

    Highlights: • A probabilistic model on long-term degradation of tendon force is developed. • By using the model, we performed reliability evaluation of nuclear containment. • The analysis is also performed for the case with the strict maintenance programme. • We showed how to satisfy the target safety in the containments facing life extension. - Abstract: The long-term reliability of nuclear containment is important for operating nuclear power plants. In particular, long-term reliability should be clarified when the service life of nuclear containment is being extended. This study focuses not only on determining the reliability of nuclear containment but also presenting the reliability improvement by strengthening the containment itself or by running a strict maintenance programme. The degradation characteristics of tendon force are estimated from the data recorded during in-service inspection of containments. A reliability analysis is conducted for a limit state of through-wall cracking, which is conservative, but most crucial limit state. The results of this analysis indicate that reliability is the lowest at 3/4 height of the containment wall. Therefore, this location is the most vulnerable for the specific limit state considered in this analysis. Furthermore, changes in structural reliability owing to an increase in the number of inspecting tendons are analysed for verifying the effect of the maintenance program's intensity on expected containment reliability. In the last part of this study, an example of obtaining target reliability of nuclear containment by strengthening its structural resistance is presented. A case study is conducted for exemplifying the effect of strengthening work on containment reliability, especially during extended service life.

  5. Building Foundations for Nuclear Security Enterprise Analysis Utilizing Nuclear Weapon Data.

    Energy Technology Data Exchange (ETDEWEB)

    Josserand, Terry Michael; Young, Leone; Chamberlin, Edwin Phillip,

    2017-10-01

    T he Nuclear Security Enterprise , managed by the National Nuclear Security Administration - a semiautonomous agency within the Department of Energy - has been associated with numerous assessments with respect to the estimating, management capabilities, and practices pertaining to nuclear weapon modernization efforts. This report identifies challenges in estimating and analyzing the N uclear S ecurity E nterprise through an analysis of analogous timeframe conditions utilizing two types of nuclear weapon data - (1) a measure of effort and (2) a function of time. The analysis of analogous timeframe conditions that utilizes only two types of nuclear weapon d ata yields four summary observations that estimators and analysts of the N uclear S ecurity E nterprise will find useful. This Page Intentionally Left Blank

  6. 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.)

  7. Asbestos-containing materials and airborne asbestos levels in industrial buildings in Korea.

    Science.gov (United States)

    Choi, Sangjun; Suk, Mee-Hee; Paik, Nam Won

    2010-03-01

    Recently in Korea, the treatment of asbestos-containing materials (ACM) in building has emerged as one of the most important environmental health issues. This study was conducted to identify the distribution and characteristics of ACM and airborne asbestos concentrations in industrial buildings in Korea. A total of 1285 presumed asbestos-containing material (PACM) samples were collected from 80 workplaces across the nation, and 40% of the PACMs contained more than 1% of asbestos. Overall, 94% of the surveyed workplaces contained ACM. The distribution of ACM did not show a significant difference by region, employment size, or industry. The total ACM area in the buildings surveyed was 436,710 m2. Ceiling tile ACM accounted for 61% (267,093 m2) of the total ACM area, followed by roof ACM (32%), surfacing ACM (6.1%), and thermal system insulation (TSI). In terms of asbestos type, 98% of total ACM was chrysotile, while crocidolite was not detected. A comparison of building material types showed that the material with the highest priority for regular management is ceiling tile, followed by roof, TSI, and surfacing material. The average airborne concentration of asbestos sampled without disturbing in-place ACM was 0.0028 fibers/cc by PCM, with all measurements below the standard of recommendation for indoor air quality in Korea (0.01 fibers/cc).

  8. Sequential insertion of three different organometallics into a versatile building block containing a PNA backbone.

    Science.gov (United States)

    Patra, Malay; Gasser, Gilles; Bobukhov, Dmytro; Merz, Klaus; Shtemenko, Alexander V; Metzler-Nolte, Nils

    2010-06-28

    In the view of developing a synthetic route for the controlled insertion of distinct organometallic moieties into peptide nucleic acid (PNA) oligomers, a proof-of-principle study of the chemoselective insertion of three different organometallics into a building block containing both a PNA backbone and an alkyne side-chain is presented in this study.

  9. Asbestos-Containing Materials in School Buildings: A Guidance Document. Part 2.

    Science.gov (United States)

    Sawyer, Robert N.; Spooner, Charles M.

    Part 2 of the Environmental Protection Agency (EPA) guidance manuals consists of more detailed information on asbestos identification and control methods. Available information on sprayed asbestos-containing materials in buildings is summarized. Guidelines are presented for the detection and monitoring, removal or encapsulation, and disposal of…

  10. Asbestos-Containing Materials in School Buildings: A Guidance Document. Part 1.

    Science.gov (United States)

    Environmental Protection Agency, Washington, DC. Office of Toxic Substances.

    The Environmental Protection Agency (EPA) has worked with the states to develop a program for accurate information and guidance to deal with the problem of school buildings constructed with asbestos-containing materials. This is the first of two guidance manuals that are a major part of this program and are being mailed to all public school…

  11. Detection of explosives, shielded nuclear materials and other hazardous substances in cargo containers

    Science.gov (United States)

    Kuznetsov, Andrey; Evsenin, Alexey; Vakhtin, Dmitry; Gorshkov, Igor; Osetrov, Oleg; Kalinin, Valery

    2006-05-01

    Nanosecond Neutron Analysis / Associated Particles Technique (NNA/APT) has been used to create devices for detection of explosives, radioactive and heavily shielded nuclear materials in cargo containers. Explosives and other hazardous materials are detected by analyzing secondary high-energy gamma-rays form reactions of fast neutrons with the materials inside the container. Depending on the dimensions of the inspected containers, the detecting system consists of one or several detection modules, each of which contains a small neutron generator with built-in position sensitive detector of associated alpha-particles and several scintillator-based gamma-ray detectors. The same gamma-ray detectors are used to detect unshielded radioactive and nuclear materials. Array of several detectors of fast neutrons is used to detect neutrons from spontaneous and induced fission of nuclear materials. These neutrons can penetrate thick layers of lead shielding, which can be used to conceal gamma-radioactivity from nuclear materials. Coincidence and timing analysis allows one to discriminate between fission neutrons and scattered probing neutrons. Mathematical modeling by MCNP5 code was used to estimate the sensitivity of the device and its optimal configuration. Capability of the device to detect 1 kg of explosive imitator inside container filled with suitcases and other baggage items has been confirmed experimentally. First experiments with heavily shielded nuclear materials have been carried out.

  12. Development of deterioration models and tests of structural materials for nuclear containment structures(III)

    Energy Technology Data Exchange (ETDEWEB)

    Oh, Byung Hwan [Seoul National University, Seoul (Korea)

    2002-03-01

    The nuclear containment structures are very important infrastructures which require much cost for construction and maintenance. If these structures lose their functions and do not ensure their safety, great losses of human lives and properties will result. Therefore, the nuclear containment structures should secure appropriate safety and functions during these service lives. The nuclear concrete structures start to experience deterioration due to severe environmental condition, even though the concrete structures exhibit generally superior durability. It is, therefore, necessary to take appropriate actions at each stage of planning, design and construction to secure safety and functionability. Thorough examination of deterioration mechanism and comprehensive tests have been conducted to explore the durability characteristics of nuclear concrete structures. 88 refs., 70 figs., 12 tabs. (Author)

  13. A Study on Nuclear Blast Overpressure on Buildings and other infrastructures using Geospatial Technology

    Directory of Open Access Journals (Sweden)

    D. Thirumalaivasan

    2012-01-01

    Full Text Available An Improvised Nuclear Device or nuclear bomb of yield 10 kiloton to 20 kiloton explodes in any major city due to terrorism or any other reason can cause catastrophic damages on the building's and other infrastructures and also shutting down of critical life-safety systems.. The explosion may produce blast overpressure, thermal radiation and harmful instant and delayed nuclear radiations. The buildings and other Civil Engineering structures may be highly vulnerabke due to the blast overpressure from the explosion and thermal radiation. In this present study Remote Sensing and Geographical Information System is effectively utilized to model the blast affected zone from the ground Zero of the study area. This study also introduces different emperical methods to estimate blast loads and structural response. The purpose is to describe the blast effects of a nuclear explosion, thereby informing people of the real dangers posed by nuclear weapons. Therefore, as a case study, we consider a hypothetical City as a target for detonation. Due to security reasons the data for existing City is not used for this study purpose. The study area is hypothetically detonated with a 15 kiloton yield nuclear explosion as surface blast and wind spped is assumed as 5 meters per second.

  14. Evaluation of Shear Resisting Capacity of a Prestressed Concrete Containment Building with Steel or Polyamide Fiber Reinforcement

    Energy Technology Data Exchange (ETDEWEB)

    Choun, Youngsun; Park, Junhee [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2014-05-15

    Conventional reinforced concrete (RC) members generally show a rapid deterioration in shear resisting mechanisms under a reversed cyclic load. However, the use of high-performance fiber-reinforced cement composites provides excellent damage tolerance under large displacement reversals compared with regular concrete. Previous experimental studies have indicated that the use of fibers in conventional RC can enhance the structural and functional performance of prestressed concrete containment buildings (PCCBs) in nuclear power plants. This study evaluates the shear resisting capacity for a PCCB constructed using steel fiber reinforced concrete (SFRC) or polyamide fiber reinforced concrete (PFRC). The effects of steel and polyamide fibers on the shear performance of a PCCB were investigated. It was revealed that steel fibers are more effective to enhance the shear resisting capacity of a PCCB than polyamide fibers. The ductility and energy dissipation increase significantly in fiber reinforced PCCBs.

  15. Microwave assisted regioselective synthesis of novel pyrazoles and pyrazolopyridazines via fluorine containing building blocks

    Science.gov (United States)

    Althagafi, Ismail I.; Shaaban, Mohamed R.

    2017-08-01

    A facile regioselective synthesis of novel pyrazole derivatives containing a fluorophenyl moiety via the 1,3-dipolar cycloaddition of nitrileimines and enamines using conventional as well as microwave irradiation conditions have been achieved. Fluorine-containing building blocks methodology was used in order to access the targeted fluorinated compounds. The structures of the synthesized products were confirmed by 1H NMR, FT-IR, mass spectrometry, and elemental analyses. Furthermore, the synthesized pyrazoles have been used in the synthesis of some new pyrazolo pyidazines containing pendent to fluorophenyl moiety. An unambiguous structural assignment of the obtained pyrazole regioisomers was determined using the 1H NMR analysis as a valuable tool.

  16. Turning Points in Containment of Lawrence Livermore National Laboratory Underground Nuclear Tests

    Energy Technology Data Exchange (ETDEWEB)

    Hudson, B C; Rambo, J T; Pawloski, G A; Burkhard, N R

    2006-11-21

    Sometime in 1987 Billy Hudson, a long-time LLNL Containment Scientist and the Task Leader for Containment Diagnostics, put together a presentation entitled ''Turning Points in Containment''. This presentation identifies challenges, lessons learned, and changes made in containment practice over a 20-year period, from 1967-1987. Besides providing a significant historical summary, the presentation is valuable as we maintain a position of readiness 14 years after the last underground nuclear detonation. It is particularly valuable to personnel who are new to the program and have no first-hand experience in implementing underground nuclear test containment for actual tests. We now view this material as a unique containment summary with timeless importance. We envision this report to be particularly useful to new Containment Program members and anyone interested in the history of underground nuclear test containment practices. We believe that the Barnwell test, detonated in 1989, would have been added to this summary if Billy Hudson had the opportunity to update the presentation. We have chosen to add a few slides to the end of the original presentation to describe the issues and lessons learned from Barnwell.

  17. Why do states build nuclear weapons? Three models in search of a bomb

    Energy Technology Data Exchange (ETDEWEB)

    Sagan, S.D.

    1996-12-31

    The central purpose of this article is to challenge conventional wisdom about nuclear proliferation. The author argues that the consensus view, focusing on national security considerations as the cause of proliferation, is dangerously inadequate because nuclear weapons programs also serve other, more parochial and less obvious objectives. Nuclear weapons, like other weapons, are more than tools of national security; they are political objects of considerable importance in domestic debates and internal bureaucratic struggles and can also serve as international normative symbols of modernity and identity. The body of this article examines three alternate theoretical frameworks - called {open_quotes}models{close_quotes} in the very informal sense of the term - about why states decide to build or refrain from developing nuclear weapons: {open_quotes}the security model,{close_quotes} according to which states build nuclear weapons to increase national security against foreign threats, especially nuclear threats; {open_quotes}the domestic politics model,{close_quotes} which envisions nuclear weapons as political tools used to advance parochial domestic and bureaucratic interests; and {open_quotes}the norms model,{close_quotes} under which nuclear weapons decisions are made because weapons acquisition, or restraint in weapons development, provides an important normative symbol of a state`s modernity and identity. Although many of the ideas underlying these models exist in the vast case-study and proliferation-policy literatures, they have not been adequately analyzed, nor placed in a comparative theoretical framework, nor properly evaluated against empirical evidence. Models are compared to their theoretical conceptions of the causes of weapons development, present alternative interpretations of the history of some major proliferation decisions, and contrast the models` implications for nonproliferation policy. 71 refs.

  18. Optimal Protection of Reactor Hall Under Nuclear Fuel Container Drop Using Simulation Methods

    Directory of Open Access Journals (Sweden)

    Králik Juraj

    2014-12-01

    Full Text Available This paper presents of the optimal design of the damping devices cover of reactor hall under impact of nuclear fuel container drop of type TK C30. The finite element idealization of nuclear power plant structure is used in software ANSYS. The steel pipe damper system is proposed for dissipation of the kinetic energy of the container free fall in comparison with the experimental results. The probabilistic and sensitivity analysis of the damping devices was considered on the base of the simulation methods in program AntHill using the Monte Carlo method.

  19. Source term and radiation dose estimates for postulated damage to the 102 Building at the General Electric Vallecitos Nuclear Center

    Energy Technology Data Exchange (ETDEWEB)

    Mishima, J.; McPherson, R.B.; Schwendiman, L.C.; Watson, E.C.; Ayer, J.E.

    1979-02-01

    Three scenarios representing significant levels of containment loss due to moderate, substantial, and major damage to the 102 Building at the Vallecitos Nuclear Center are postulated, and the potential radiation doses to the general population as a result of the airborne releases of radionuclides are estimated. The damage scenarios are not correlated to any specific level of seismic activity. The three scenarios are: (1) Moderate damage scenario--perforation of the enclosures in and the structure comprising the Plutonium Analytical Laboratory. (2) Substantial damage scenario--complete loss of containment of the Plutonium Analytical Laboratory and loss of the filters sealing the inlet to the Radioactive Materials Laboratory hot cells. (3) Major damage scenario--the damage outlined in (2) plus the perforation of enclosures holding significant inventories of dispersible plutonium in and the structure comprising the Advanced Fuels Laboratory.

  20. A survey of repair practices for nuclear power plant containment metallic pressure boundaries

    Energy Technology Data Exchange (ETDEWEB)

    Oland, C.B.; Naus, D.J. [Oak Ridge National Lab., TN (United States)

    1998-05-01

    The Nuclear Regulatory Commission has initiated a program at the Oak Ridge National Laboratory to provide assistance in their assessment of the effects of potential degradation on the structural integrity and leaktightness of metal containment vessels and steel liners of concrete containments in nuclear power plants. One of the program objectives is to identify repair practices for restoring metallic containment pressure boundary components that have been damaged or degraded in service. This report presents issues associated with inservice condition assessments and continued service evaluations and identifies the rules and requirements for the repair and replacement of nonconforming containment pressure boundary components by welding or metal removal. Discussion topics include base and welding materials, welding procedure and performance qualifications, inspection techniques, testing methods, acceptance criteria, and documentation requirements necessary for making acceptable repairs and replacements so that the plant can be returned to a safe operating condition.

  1. Nuclear power plant containment metallic pressure boundary materials and plans for collecting and presenting their properties

    Energy Technology Data Exchange (ETDEWEB)

    Oland, C.B.

    1995-04-01

    A program is being conducted at the Oak Ridge National Laboratory (ORNL to assist the Nuclear Regulatory Commission (NRC)) in their assessment of the effects of degradation (primarily corrosion) on the structural capacity and leaktight integrity of metal containments and steel liners of reinforced concrete structures in nuclear power plants. One of the program objectives is to characterize and quantify manifestations of corrosion on the properties of steels used to construct containment pressure boundary components. This report describes a plan for use in collecting and presenting data and information on ferrous alloys permitted for use in construction of pressure retaining components in concrete and metal containments. Discussions about various degradation mechanisms that could potentially affect the mechanical properties of these materials are also included. Conclusions and recommendations presented in this report will be used to guide the collection of data and information that will be used to prepare a material properties data base for containment steels.

  2. Development of damage detection methods in containment building using system identification

    Energy Technology Data Exchange (ETDEWEB)

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

    2001-05-01

    This study presents an SI-based damage detection schemes using minimization of an error function. The singular value decomposition is utilized to investigate the instability of the SI. The Tikhonov regularization scheme is introduced to alleviate oscillations in the solutions of the SI. The optimal regularization factor is determined by the GMS and the GGMS. The characteristics of measurement error are investigated. The regularization effect is estimated by the concept of the error level and the resolution limit. The statistical approach is employed for reliable damage detection. The Monte-Carlo simulation is performed by the artificially perturbed data. The statistical distribution of system parameters obtained by the Monte-Carlo simulation is utilized in the hypothesis test for the damage detection. The validity and effectiveness of the proposed method is demonstrated through three types of numerical examples identification of an inclusion in a plate, determination of prestress losses in a containment building and damage detection in a containment building.

  3. Experimental and numerical characterization of wind-induced pressure coefficients on nuclear buildings and chimney exhausts

    Energy Technology Data Exchange (ETDEWEB)

    Ricciardi, Laurent, E-mail: laurent.ricciardi@irsn.fr; Gélain, Thomas; Soares, Sandrine

    2015-10-15

    Highlights: • Experiments on scale models of nuclear buildings and chimney exhausts were performed. • Pressure coefficient fields on buildings are shown for various wind directions. • Evolution of pressure coefficient vs U/W ratio is given for various chimney exhausts. • RANS simulations using SST k–ω turbulence model were performed on most studied cases. • A good agreement is overall observed, with Root Mean Square Deviation lower than 0.15. - Abstract: Wind creates pressure effects on different surfaces of buildings according to their exposure to the wind, in particular at external communications. In nuclear facilities, these effects can change contamination transfers inside the building and can even lead to contamination release into the environment, especially in damaged (ventilation stopped) or accidental situations. The diversity of geometries of facilities requires the use of a validated code for predicting pressure coefficients, which characterize the wind effect on the building walls and the interaction between the wind and chimney exhaust. The first aim of a research program launched by the French Institut de Radioprotection et de Sûreté Nucléaire (IRSN), was therefore to acquire experimental data of the mean pressure coefficients for different geometries of buildings and chimneys through wind tunnel tests and then to validate a CFD code (ANSYS CFX) from these experimental results. The simulations were performed using a steady RANS approach and a two-equation SST k–ω turbulence model. After a mesh sensitivity study for one configuration of building and chimney, a comparison was carried out between the numerical and experimental values for other studied configurations. This comparison was generally satisfactory, averaged over all measurement points, with values of Root Mean Square Deviations lower than 0.15 for most cases.

  4. LEAF: a computer program to calculate fission product release from a reactor containment building for arbitrary radioactive decay chains

    Energy Technology Data Exchange (ETDEWEB)

    Lee, C.E.; Apperson, C.E. Jr.; Foley, J.E.

    1976-10-01

    The report describes an analytic containment building model that is used for calculating the leakage into the environment of each isotope of an arbitrary radioactive decay chain. The model accounts for the source, the buildup, the decay, the cleanup, and the leakage of isotopes that are gas-borne inside the containment building.

  5. Fabrication and closure development of nuclear waste containers for storage at the Yucca Mountain, Nevada repository

    Energy Technology Data Exchange (ETDEWEB)

    Russell, E.W.; Nelson, T.A. [Lawrence Livermore National Lab., CA (USA); Domian, H.A.; LaCount, D.F.; Robitz, E.S.; Stein, K.O. [Babcock and Wilcox Co., New Orleans, LA (USA)

    1989-04-01

    US Congress and the President have determined that the Yucca Mountain site in Nevada is to be characterized to determine its suitability for construction of the first US high-level nuclear waste repository. Work in connection with this site is carried out within the Yucca Mountain Project (YMP). Lawrence Livermore National Laboratory (LLNL) has the responsibility for designing, developing, and projecting the performance of the waste package for the permanent storage of high-level nuclear waste. Babcock & Wilcox (B & W) is involved with the YMP as a subcontractor to LLNL. B & W`s role is to recommend and demonstrate a method for fabricating the metallic waste container and a method for performing the final closure of the container after it has been filled with waste. Various fabrication and closure methods are under consideration for the production of containers. This paper presents progress to date in identifying and evaluating the candidate manufacturing processes. 2 refs., 1 fig., 7 tabs.

  6. Proving test on the seismic reliability of nuclear power plant: PWR reactor containment vessel

    Energy Technology Data Exchange (ETDEWEB)

    Akiyama, Hiroshi; Yoshikawa, Teiichi; Ohno, Tokue; Yoshikawa, Eiji.

    1989-01-01

    Seismic reliability proving tests of nuclear power plant facilities are carried out by the Nuclear Power Engineering Test Center, using the large-scale, high-performance vibration table of Tadotsu Engineering Laboratory, and sponsored by the Ministry of International Trade and Industry. In 1982, the seismic reliability proving test of a PWR containment vessel was conducted using a test component of reduced scale 1/3.7. As a result of this test, the test component proved to have structural soundness against earthquakes, and at the same time its stable function was proved by leak tests which were carried out before and after the vibration test. In 1983, the detailed analysis and evaluation of these test results were carried out, and the analysis methods for evaluating strength against earthquakes were established. The seismic analysis and evaluation on the actual containment vessel were then performed using these analysis methods, and the safety and reliability of the PWR reactor containment vessel were confirmed.

  7. Concept study of a hydrogen containment process during nuclear thermal engine ground testing

    Science.gov (United States)

    Wang, Ten-See; Stewart, Eric T.; Canabal, Francisco

    A new hydrogen containment process was proposed for ground testing of a nuclear thermal engine. It utilizes two thermophysical steps to contain the hydrogen exhaust. First, the decomposition of hydrogen through oxygen-rich combustion at higher temperature; second, the recombination of remaining hydrogen with radicals at low temperature. This is achieved with two unit operations: an oxygen-rich burner and a tubular heat exchanger. A computational fluid dynamics methodology was used to analyze the entire process on a three-dimensional domain. The computed flammability at the exit of the heat exchanger was less than the lower flammability limit, confirming the hydrogen containment capability of the proposed process.

  8. Review of Corrosion Modes for Alloy 22 Regarding Lifetime Expectancy of Nuclear Waste Containers

    Energy Technology Data Exchange (ETDEWEB)

    Rebak, R B; Estill, J C

    2002-11-15

    Alloy 22 (UNS N06022) was selected to fabricate the corrosion resistant outer barrier of a two-layer waste package container for nuclear waste at the designated repository site in Yucca Mountain in Nevada (USA). A testing program is underway to characterize and quantify three main modes of corrosion that may occur at the site. Current results show that the containers would perform well under general corrosion, localized corrosion and environmentally assisted cracking (EAC). For example, the general corrosion rate is expected to be below 100 nm/year and the container is predicted to be outside the range of potential for localized corrosion and environmentally assisted cracking.

  9. In-Containment Signal Conditioning and Transmission via Power Lines within High Dose Rate Areas of Nuclear Power Plants

    Energy Technology Data Exchange (ETDEWEB)

    Mueller, Steffen; Weigel, Robert; Koelpin, Alexander [Institute for Electronics Engineering, University of Erlangen-Nuremberg, Cauerstr. 9, 91058 Erlangen (Germany); Dennerlein, Juergen; Janke, Iryna; Weber, Johannes [AREVA GmbH, Paul-Gossen-Str. 100, 91052 Erlangen (Germany)

    2015-07-01

    Signal conditioning and transmission for sensor systems and networks within the containment of nuclear power plants (NPPs) still poses a challenge to engineers, particularly in the case of equipment upgrades for existing plants, temporary measurements, decommissioning of plants, but also for new builds. This paper presents an innovative method for efficient and cost-effective instrumentation within high dose rate areas inside the containment. A transmitter-receiver topology is proposed that allows simultaneous, unidirectional point-to-point transmission of multiple sensor signals by superimposing them on existing AC or DC power supply cables using power line communication (PLC) technology. Thereby the need for costly installation of additional cables and containment penetrations is eliminated. Based on commercial off-the-shelf (COTS) electronic parts, a radiation hard transmitter is designed to operate in harsh environment within the containment during full plant operation. Hardware modularity of the transmitter allows application specific tradeoffs between redundancy and channel bandwidth. At receiver side in non-radiated areas, signals are extracted from the power line, demodulated, and provided either in analog or digital output format. Laboratory qualification tests and field test results within a boiling water reactor (BWR) are validating the proof of concept of the proposed system. (authors)

  10. Building tomorrow's nuclear power plants with 4{sup +}D VR technology

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Il S.; Yoon, Sang H.; Shim, Kyu W.; Yu, Yong H.; Suh, Kune Y. [PhiloSOPhIA, Inc., Seoul (Korea, Republic of)

    2002-04-15

    There continues to be an increasing demand of electricity around the globe to fuel the industrial growth and to promote the human welfare. The economic activities have brought about richness in our material and cultural lives, in which process the electric power has been at the heart of the versatile energy sources. In order to timely and competitively respond to rapidly changing energy environment in the twenty-first century there is a growing need to build the advanced nuclear power plants in the unlimited workspace of virtual reality (VR) prior to commissioning. One can then realistically evaluate their construction time and cost per varying methods and options available from the leading-edge technology. In particular a great deal of efforts have yet to be made for time- and cost-dependent plant simulation and dynamically coupled database construction in the VR space. The operator training and personnel education may also benefit from the VR technology. The present work is being proposed in the three-dimensional space and time plus cost coordinates, i. e. four plus dimensional (4{sup +}D) coordinates. The 4{sup +}D VR application will enable the nuclear industry to narrow the technological gap from the other leading industries that have long since been employing the VR engineering. The 4{sup +}D technology will help nurture public understanding of the special discipline of nuclear power plants. The technology will also facilitate public access to the knowledge on the nuclear science and engineering which has so far been monopolized by the academia, national laboratories and the heavy industry. The 4{sup +}D virtual design and construction will open up the new horizon for revitalization of the nuclear industry over the globe in the foreseeable future. Considering the long construction and operation time for the nuclear power plants, the preliminary VR simulation capability for the plants will supply the vital information not only for the actual design and

  11. Conditions inside Water Pooled in a Failed Nuclear Waste Container and its Effect on Radionuclide Release

    Science.gov (United States)

    Hamdan, L. K.; Walton, J. C.; Woocay, A.

    2009-12-01

    Nuclear power use is expected to expand in the future, as part of the global clean energy initiative, to meet the world’s surging energy demand, and attenuate greenhouse gas emissions, which are mainly caused by fossil fuels. As a result, it is estimated that hundreds of thousands of metric tons of spent nuclear fuel (SNF) will accumulate. SNF disposal has major environmental (radiation exposure) and security (nuclear proliferation) concerns. Storage in unsaturated zone geological repositories is a reasonable solution for dealing with SNF. One of the key factors that determine the performance of the geological repository is the release of radionuclides from the engineered barrier system. Over time, the nuclear waste containers are expected to fail gradually due to general and localized corrosions and eventually infiltrating water will have access to the nuclear waste. Once radionuclides are released, they will be transported by water, and make their way to the accessible environment. Physical and chemical disturbances in the environment over the container will lead to different corrosion rates, causing different times and locations of penetration. One possible scenario for waste packages failure is the bathtub model, where penetrations occur on the top of the waste package and water pools inside it. In this paper the bathtub-type failed waste container is considered. We shed some light on chemical and physical processes that take place in the pooled water inside a partially failed waste container (bathtub category), and the effects of these processes on radionuclide release. Our study considers two possibilities: temperature stratification of the pooled water versus mixing process. Our calculations show that temperature stratification of the pooled water is expected when the waste package is half (or less) filled with water. On the other hand, when the waste package is fully filled (or above half) there will be mixing in the upper part of water. The effect of

  12. The effects of age on nuclear power plant containment cooling systems

    Energy Technology Data Exchange (ETDEWEB)

    Lofaro, R.; Subudhi, M.; Travis, R.; DiBiasio, A.; Azarm, A. [Brookhaven National Lab., Upton, NY (United States); Davis, J. [Science Applications International Corp., New York, NY (United States)

    1994-04-01

    A study was performed to assess the effects of aging on the performance and availability of containment cooling systems in US commercial nuclear power plants. This study is part of the Nuclear Plant Aging Research (NPAR) program sponsored by the US Nuclear Regulatory Commission. The objectives of this program are to provide an understanding of the aging process and how it affects plant safety so that it can be properly managed. This is one of a number of studies performed under the NPAR program which provide a technical basis for the identification and evaluation of degradation caused by age. The effects of age were characterized for the containment cooling system by reviewing and analyzing failure data from national databases, as well as plant-specific data. The predominant failure causes and aging mechanisms were identified, along with the components that failed most frequently. Current inspection, surveillance, and monitoring practices were also examined. A containment cooling system unavailability analysis was performed to examine the potential effects of aging by increasing failure rates for selected components. A commonly found containment spray system design and a commonly found fan cooler system design were modeled. Parametric failure rates for those components in each system that could be subject to aging were accounted for in the model to simulate the time-dependent effects of aging degradation, assuming no provisions are made to properly manage it. System unavailability as a function of increasing component failure rates was then calculated.

  13. Effluent Containment System for space thermal nuclear propulsion ground test facilities

    Science.gov (United States)

    1995-08-01

    This report presents the research and development study work performed for the Space Reactor Power System Division of the U.S. Department of Energy on an innovative effluent containment system (ECS) that would be used during ground testing of a space nuclear thermal rocket engine. A significant portion of the ground test facilities for a space nuclear thermal propulsion engine are the effluent treatment and containment systems. The proposed ECS configuration developed recycles all engine coolant media and does not impact the environment by venting radioactive material. All coolant media, hydrogen and water, are collected, treated for removal of radioactive particulates, and recycled for use in subsequent tests until the end of the facility life. Radioactive materials removed by the treatment systems are recovered, stored for decay of short-lived isotopes, or packaged for disposal as waste. At the end of the useful life, the facility will be decontaminated and dismantled for disposal.

  14. The nuclear receptor gene family in the Pacific oyster, Crassostrea gigas, contains a novel subfamily group.

    Science.gov (United States)

    Vogeler, Susanne; Galloway, Tamara S; Lyons, Brett P; Bean, Tim P

    2014-05-15

    Nuclear receptors are a superfamily of transcription factors important in key biological, developmental and reproductive processes. Several of these receptors are ligand- activated and through their ability to bind endogenous and exogenous ligands, are potentially vulnerable to xenobiotics. Molluscs are key ecological species in defining aquatic and terrestrial habitats and are sensitive to xenobiotic compounds in the environment. However, the understanding of nuclear receptor presence, function and xenobiotic disruption in the phylum Mollusca is limited. Here, forty-three nuclear receptor sequences were mined from the genome of the Pacific oyster, Crassostrea gigas. They include members of NR0-NR5 subfamilies, notably lacking any NR6 members. Phylogenetic analyses of the oyster nuclear receptors have been conducted showing the presence of a large novel subfamily group not previously reported, which is named NR1P. Homologues to all previous identified nuclear receptors in other mollusc species have also been determined including the putative heterodimer partner retinoid X receptor, estrogen receptor and estrogen related receptor. C. gigas contains a highly diverse set of nuclear receptors including a novel NR1 group, which provides important information on presence and evolution of this transcription factor superfamily in invertebrates. The Pacific oyster possesses two members of NR3, the sex steroid hormone receptor analogues, of which there are 9 in humans. This provides increasing evidence that steroid ligand specific expansion of this family is deuterostome specific. This new knowledge on divergence and emergence of nuclear receptors in C. gigas provides essential information for studying regulation of molluscan gene expression and the potential effects of xenobiotics.

  15. The little brown bat nuclear genome contains an entire mitochondrial genome: Real or artifact?

    Science.gov (United States)

    Shi, Huizhen; Xing, Yutong; Mao, Xiuguang

    2017-09-20

    Nuclear mitochondrial DNA sequences (NUMTs) have been documented in almost all eukaryotic genomes studied. Recently, with the number of sequenced genomes increasing, extremely large NUMTs, even a nearly entire mitochondrial genome, have been reported in some plants and animals. However, few such studies provided strong experimental evidences for these important discoveries. In this study using a computer-based search method an entire mitochondrial genome (NUMT-1) was found in the nuclear genome of a bat species (Myotis lucifugus). This super-large NUMT shared a same scaffold with a 754bp nuclear genomic sequence and a second NUMT (NUMT-2, 3292bp). If NUMT-1 was real, it will be the largest NUMT found in animals and this finding will provide valuable insights into the mode of generation of NUMTs in the nuclear genome. Unfortunately, although the initial sequencing technology of the published M. lucifugus genome makes the possibility of artifact less likely, our results from both the PCR amplification followed by Sanger sequencing and mapping method based on the whole-genome resequencing datasets suggested that the scaffold containing the entire mitochondrial genome was artifact possibly due to a misassembly of mitochondrial and the nuclear DNA sequences. Our current study highlights the necessity to validate the authenticity of extremely large NUMTs identified in previous searches on whole-genome sequence assemblies. Copyright © 2017 Elsevier B.V. All rights reserved.

  16. Nonlinear seismic behavior of a CANDU containment building subjected to near-field ground motions

    Energy Technology Data Exchange (ETDEWEB)

    Choi, In Kil; Ahn, Seong Moon; Choun, Young Sun; Seo, Jeong Moon [Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)

    2004-07-01

    The standard response spectrum proposed by US NRC has been used as a design earthquake for the design of Korean nuclear power plant structures. A survey on some of the Quaternary fault segments near Korean nuclear power plants is ongoing. It is likely that these faults will be identified as active ones. If the faults are confirmed as active ones, it will be necessary to reevaluate the seismic safety of the nuclear power plants located near the fault. Near-fault ground motions are the ground motions that occur near an earthquake fault. In general, the near-fault ground motion records exhibit a distinctive long period pulse like time history with very high peak velocities. These features are induced by the slip of the earthquake fault. Near-fault ground motions, which have caused much of the damage in recent major earthquakes, can be characterized by a pulse-like motion that exposes the structure to a high input energy at the beginning of the motion. In this study, nonlinear dynamic time-history analyses were performed to investigate the seismic behavior of a CANDU containment structure subjected to various earthquake ground motions including the near-field ground motions.

  17. Pyrometallurgical separation processes of radionuclides contained in the irradiated nuclear fuel

    Energy Technology Data Exchange (ETDEWEB)

    De Cordoba, Guadalupe; Caravaca, Concha; Quinones, Javier; Gonzalez de la Huebra, Angel

    2005-01-01

    Faced with the new options for the high level waste management, the ''Partitioning and Transmutation (P and T)'' of the radio nuclides contained in the irradiated nuclear fuel appear as a promising option from different points of view, such as environmental risk, radiotoxic inventory reduction, economic, etc.. The present work is part of a research project called ''PYROREP'' of the 5th FWP of the EU that studied the feasibility of the actinide separation from the rest of fission products contained in the irradiated nuclear fuel by pyrometallurgical processes with the aim of their transmutation. In order to design these processes it is necessary to determine basic thermodynamic and kinetic data of the radionuclides contained in the nuclear fuel in molten salt media. The electrochemical study of uranium, samarium and molybdenum in the eutectic melt LiCl - KCl has been performed at a tungsten electrode in the temperature range of 450 - 600 deg C in order to obtain these basic properties. (Author)

  18. Demonstrating Structural Adequacy of Nuclear Power Plant Containment Structures for Beyond Design-Basis Pressure Loadings

    Energy Technology Data Exchange (ETDEWEB)

    Braverman, J.I.; Morante, R.

    2010-07-18

    ABSTRACT Demonstrating the structural integrity of U.S. nuclear power plant (NPP) containment structures, for beyond design-basis internal pressure loadings, is necessary to satisfy Nuclear Regulatory Commission (NRC) requirements and performance goals. This paper discusses methods for demonstrating the structural adequacy of the containment for beyond design-basis pressure loadings. Three distinct evaluations are addressed: (1) estimating the ultimate pressure capacity of the containment structure (10 CFR 50 and US NRC Standard Review Plan, Section 3.8) ; (2) demonstrating the structural adequacy of the containment subjected to pressure loadings associated with combustible gas generation (10 CFR 52 and 10 CFR 50); and (3) demonstrating the containment structural integrity for severe accidents (10 CFR 52 as well as SECY 90-016, SECY 93-087, and related NRC staff requirements memoranda (SRMs)). The paper describes the technical basis for specific aspects of the methods presented. It also presents examples of past issues identified in licensing activities related to these evaluations.

  19. Influences of nuclear containment radius on the aircraft impact force based on the Riera function

    Energy Technology Data Exchange (ETDEWEB)

    Zhang, T.; Wu, H., E-mail: abrahamhao@126.com; Fang, Q.; Gong, Z.M.

    2015-11-15

    Highlights: • A fine aircraft model of A320 was built and verified by available limited prototype impacting tests. • The influences of aircraft longitudinal crushing strength on the impact process were analyzed. • The influences of NPP containment radius on the impact force were numerically studied. • The Riera function was modified by considering the radius effect of NPP containment. - Abstract: The aircraft impact force directly influences the local failure and global response of the nuclear power plant (NPP) containment, while the existing theoretical models and the field tests were almost based on the flat target. In order to analyze the radius effect of the circular sectional containment on the impact force, a fine FE model of the commercial aircraft A320 was established and validated by the available limited full-scale F-4 Phantom impact experiment. In order to determine the force to crush the A320 FE model, the influences of aircraft longitudinal crushing strength on the impact process were analyzed based on the Riera function. Considering the containment decaying effect to aircraft impact velocity, the impact impulse was theoretically calculated, while the influences of the losses of mass and energy were not included. The numerical simulations of A320 aircrafts impacting on simplified NPP containments with different radii were conducted, which could well reproduce the airframe crushing and debris scattering. By comparison of the simulated impact impulses and the calculation values by the Riera function, the coefficients corresponding to different containment radii are derived and a fitting formula is obtained. Finally, an improved Riera function dependent on the dimensionless ratio of nuclear containment radius and aircraft wingspan is proposed.

  20. Subsoil exploration of the estimated building site for nuclear fuel development and fabrication facility

    Energy Technology Data Exchange (ETDEWEB)

    Song, In Taek [Korea Atomic Energy Research Institute, Taejeon (Korea)

    2000-01-01

    The objective of this report, as the result of subsoil exploration, is to provide basic design data of structural plan for nuclear fuel development and fabrication facility that is builded on Duckjin 150, Yusong, Taejeon, Korea, and provide basic data for execution of work. The soft rock level of estimated building site is deep(18.0m:BH-1, 20.5m:BH-2, 25.5m:BH-3) and the hard rock level of it is very deep (33.0m:BH-1, 46.0m:BH-2, 34.5m:BH-3) , for structural design, the hard rock shall be the bottom of foundation. 9 figs., 19 tabs. (Author)

  1. Subsoil exploration of the estimated building site for nuclear fuel development and fabrication facility

    Energy Technology Data Exchange (ETDEWEB)

    Song, In Taek [Korea Atomic Energy Research Institute, Taejeon (Korea)

    2000-01-01

    The objective of this report, as the result of subsoil exploration, is to provide basic design data of structural plan for nuclear fuel development and fabrication facility that is builded on Duckjin 150, Yusong, Taejeon, Korea, and provide basic data for execution of work. The soft rock level of estimated building site is deep(18.0m:BH-1, 20.5m:BH-2, 25.5m:BH-3) and the hard rock level of it is very deep (33.0m:BH-1, 46.0m:BH-2, 34.5m:BH-3) , for structural design, the hard rock shall be the bottom of foundation. 9 figs., 19 tabs. (Author)

  2. Foundation requirements for the buildings of the Paks nuclear power plant, Hungary

    Energy Technology Data Exchange (ETDEWEB)

    Vago, I. (Paksi Atomeroemue Vallalat (Hungary))

    1983-01-01

    Prior to the construction of the Paks nuclear plant buildings, the soil mechanics had to be taken into consideration. The investigations needed for the foundation of the power plant are discussed. The strata of the soil under the site were explored. The load bearing capability and the solidity of the soil was investigated using a dynamic probe technique with /sup 137/Cs isotope. The groundwater level was also studied. It was found that the stratification is uniform, the ground subsidence conditions are acceptable and the strata are well loadable. The packing of the grained strata is difficult but the landfilling was constructed to form a dense ground.

  3. Design Verification Report Spent Nuclear Fuel (SNF) Project Canister Storage Building (CSB)

    Energy Technology Data Exchange (ETDEWEB)

    PICKETT, W.W.

    2000-09-22

    The Sub-project W379, ''Spent Nuclear Fuel Canister Storage Building (CSB),'' was established as part of the Spent Nuclear Fuel (SNF) Project. The primary mission of the CSB is to safely store spent nuclear fuel removed from the K Basins in dry storage until such time that it can be transferred to the national geological repository at Yucca Mountain Nevada. This sub-project was initiated in late 1994 by a series of studies and conceptual designs. These studies determined that the partially constructed storage building, originally built as part of the Hanford Waste Vitrification Plant (HWVP) Project, could be redesigned to safely store the spent nuclear fuel. The scope of the CSB facility initially included a receiving station, a hot conditioning system, a storage vault, and a Multi-Canister Overpack (MCO) Handling Machine (MHM). Because of evolution of the project technical strategy, the hot conditioning system was deleted from the scope and MCO welding and sampling stations were added in its place. This report outlines the methods, procedures, and outputs developed by Project W379 to verify that the provided Structures, Systems, and Components (SSCs): satisfy the design requirements and acceptance criteria; perform their intended function; ensure that failure modes and hazards have been addressed in the design; and ensure that the SSCs as installed will not adversely impact other SSCs. Because this sub-project is still in the construction/start-up phase, all verification activities have not yet been performed (e.g., canister cover cap and welding fixture system verification, MCO Internal Gas Sampling equipment verification, and As-built verification.). The verification activities identified in this report that still are to be performed will be added to the start-up punchlist and tracked to closure.

  4. A containment analysis for SBLOCA without ECI in the refurbished Wolsong-1 Nuclear Power Plant

    Energy Technology Data Exchange (ETDEWEB)

    Kim, T.M.; Moon, B.J.; Bae, C.J.; Lee, S.H.; Choi, C.J.; Lee, D.S. [NSSS, Korea Power Engineering Company, Inc., Daejeon (Korea, Republic of); Kim, S.M. [NETEC, Korea Hydro and Nuclear Power Company, Inc., Daejeon (Korea, Republic of)

    2010-07-01

    A small break leading to loss of coolant accident (SBLOCA), being one of the topic accidents in the nuclear plant diagnosis in recent years, has been analyzed and evaluated for the refurbished Wolsong-1 Nuclear Power Plant (NPP). The industry standard toolset (IST) codes developed by CANDU Owners Group and updated models including design change parameters are applied to the event analyses. GOTHIC code has been used for the containment analysis of Wolsong-1. Also, SMART-IST code fitted in the Iodine Chemistry (IMOD-2) model has been used to predict nuclide behavior within the containment considering various aspects. IMOD-2 was incorporated into SMART-IST as a module dealing the chemical transformations and mass transfer of iodine species in containment. IMOD-2 model is very sensitive to paint and chemicals. The parameter studies for IMOD-2 model are performed to decide the analysis value set. The developed methodology and the results of SBLOCA without ECI are presented herein. Under the most heat-up conditions, the radionuclide release from the failed fuel into the containment and subsequently to the environment is such that the radioactive doses to the public are below the acceptable limits. (author)

  5. Aseismic safety analysis of a prestressed concrete containment vessel for CPR1000 nuclear power plant

    Science.gov (United States)

    Yi, Ping; Wang, Qingkang; Kong, Xianjing

    2017-01-01

    The containment vessel of a nuclear power plant is the last barrier to prevent nuclear reactor radiation. Aseismic safety analysis is the key to appropriate containment vessel design. A prestressed concrete containment vessel (PCCV) model with a semi-infinite elastic foundation and practical arrangement of tendons has been established to analyze the aseismic ability of the CPR1000 PCCV structure under seismic loads and internal pressure. A method to model the prestressing tendon and its interaction with concrete was proposed and the axial force of the prestressing tendons showed that the simulation was reasonable and accurate. The numerical results show that for the concrete structure, the location of the cylinder wall bottom around the equipment hatch and near the ring beam are critical locations with large principal stress. The concrete cracks occurred at the bottom of the PCCV cylinder wall under the peak earthquake motion of 0.50 g, however the PCCV was still basically in an elastic state. Furthermore, the concrete cracks occurred around the equipment hatch under the design internal pressure of 0.4MPa, but the steel liner was still in the elastic stage and its leak-proof function soundness was verified. The results provide the basis for analysis and design of containment vessels.

  6. Structural integrity analysis of the degraded drywell containment at the Oyster Creek Nuclear generating station.

    Energy Technology Data Exchange (ETDEWEB)

    Petti, Jason P.

    2007-01-01

    This study examines the effects of the degradation experienced in the steel drywell containment at the Oyster Creek Nuclear Generating Station. Specifically, the structural integrity of the containment shell is examined in terms of the stress limits using the ASME Boiler and Pressure Vessel (B&PV) Code, Section III, Division I, Subsection NE, and examined in terms of buckling (stability) using the ASME B&PV Code Case N-284. Degradation of the steel containment shell (drywell) at Oyster Creek was first observed during an outage in the mid-1980s. Subsequent inspections discovered reductions in the shell thickness due to corrosion throughout the containment. Specifically, significant corrosion occurred in the sandbed region of the lower sphere. Since the presence of the wet sand provided an environment which supported corrosion, a series of analyses were conducted by GE Nuclear Energy in the early 1990s. These analyses examined the effects of the degradation on the structural integrity. The current study adopts many of the same assumptions and data used in the previous GE study. However, the additional computational recourses available today enable the construction of a larger and more sophisticated structural model.

  7. Device for Detection of Explosives, Nuclear and Other Hazardous Materials in Luggage and Cargo Containers

    Science.gov (United States)

    Kuznetsov, Andrey; Evsenin, Alexey; Gorshkov, Igor; Osetrov, Oleg; Vakhtin, Dmitry

    2009-12-01

    Device for detection of explosives, radioactive and heavily shielded nuclear materials in luggage and cargo containers based on Nanosecond Neutron Analysis/Associated Particles Technique (NNA/APT) is under construction. Detection module consists of a small neutron generator with built-in position-sensitive detector of associated alpha-particles, and several scintillator-based gamma-ray detectors. Explosives and other hazardous chemicals are detected by analyzing secondary high-energy gamma-rays from reactions of fast neutrons with materials inside a container. The same gamma-ray detectors are used to detect unshielded radioactive and nuclear materials. An array of several neutron detectors is used to detect fast neutrons from induced fission of nuclear materials. Coincidence and timing analysis allows one to discriminate between fission neutrons and scattered probing neutrons. Mathematical modeling by MCNP5 and MCNP-PoliMi codes was used to estimate the sensitivity of the device and its optimal configuration. Comparison of the features of three gamma detector types—based on BGO, NaI and LaBr3 crystals is presented.

  8. Los Alamos National Laboratory new generation standard nuclear material storage container - the SAVY4000 design

    Energy Technology Data Exchange (ETDEWEB)

    Stone, Timothy Amos [Los Alamos National Laboratory

    2010-01-01

    Incidents involving release of nuclear materials stored in containers of convenience such as food pack cans, slip lid taped cans, paint cans, etc. has resulted in defense board concerns over the lack of prescriptive performance requirements for interim storage of nuclear materials. Los Alamos National Laboratory (LANL) has shared in these incidents and in response proactively moved into developing a performance based standard involving storage of nuclear material (RD003). This RD003 requirements document has sense been updated to reflect requirements as identified with recently issued DOE M 441.1-1 'Nuclear Material Packaging Manual'. The new packaging manual was issued at the encouragement of the Defense Nuclear Facilities Safety Board with a clear directive for protecting the worker from exposure due to loss of containment of stored materials. The Manual specifies a detailed and all inclusive approach to achieve a high level of protection; from package design & performance requirements, design life determinations of limited life components, authorized contents evaluations, and surveillance/maintenance to ensure in use package integrity over time. Materials in scope involve those stored outside an approved engineered-contamination barrier that would result in a worker exposure of in excess of 5 rem Committed Effective Does Equivalent (CEDE). Key aspects of meeting the challenge as developed around the SAVY-3000 vented storage container design will be discussed. Design performance and acceptance criteria against the manual, bounding conditions as established that the user must ensure are met to authorize contents in the package (based upon the activity of heat-source plutonium (90% Pu-238) oxide, which bounds the requirements for weapons-grade plutonium oxide), interface as a safety class system within the facility under the LANL plutonium facility DSA, design life determinations for limited life components, and a sense of design specific surveillance

  9. Corrosion of copper containers prior to saturation of a nuclear fuel waste disposal vault

    Energy Technology Data Exchange (ETDEWEB)

    King, F.; Kolar, M

    1997-12-01

    The buffer material surrounding the containers in a Canadian nuclear fuel waste disposal vault will partially desiccate as a result of the elevated temperature at the container surface. This will lead to a period of corrosion in a moist air atmosphere. Corrosion will either take the form of slow oxidation if the container surface remains dry or aqueous electrochemical corrosion if the surface is wetted by a thin liquid film. The relevant literature is reviewed, from which it is concluded that corrosion should be uniform in nature, except if the surface is wetted, in which case localized corrosion is a possibility. A quantitative analysis of the extent and rate of uniform corrosion during the unsaturated period is presented. Two bounding cases are considered: first, the case of slow oxidation in moist air following either logarithmic or parabolic oxide-growth kinetics and, second, the case of electrochemically based corrosion occurring in a thin liquid film uninhibited by the growth of corrosion products. (author)

  10. Research on the additives to reduce radioactive pollutants in the building materials containing fly ash.

    Science.gov (United States)

    He, Deng-liang; Yin, Guang-fu; Dong, Fa-qin; Liu, Lai-bao; Luo, Ya-jun

    2010-05-15

    Several kinds of functional additives such as barite, zeolite, ferric oxide, gypsum, and high alumina cement were introduced to prepare a low-radiation cement-based composite to reduce radioactive pollutants contained in fly ash. The effect of content and granularity of the functional additives on the release of radioactive pollutants were investigated. Composites were characterized by X-ray diffraction, Scan electron microscopy. The results indicate that the radioactive pollutants contained in the fly ash can be reduced by adding a proper amount of zeolite, ferric oxide, gypsum, and high alumina cement. The release of radon from fly ash decreases with a decrease in the granularity of additives. Compared with traditional cement-based composite containing fly ash, the release of radon can be reduced 64.8% in these composites, and the release of gamma-ray is decreased 45%. Based on the microstructure and phase analysis, we think that by added functional additives, there are favorable to form self-absorption of radioactivity in the interior composites. This cement-based composite will conducive to fly ash are large-scale applied in the field of building materials.

  11. Toward a common nuclear safety culture. From knowledge creation to competence building in Euratom programs

    Energy Technology Data Exchange (ETDEWEB)

    Goethem, Georges van [EC DG Research J2 / Euratom (Fission), Brussels (Belgium). Innovation in Nuclear Systems, and Education and Training

    2010-11-15

    One of the main goals of the Euratom research and training programs is to contribute to the sustainability of nuclear energy by providing resources, in particular, for research and innovation in Generations II, IIII and IV (knowledge creation). Euratom training programs contribute most notably to competence building while facilitating the mutual recognition of experts and thereby continuously improving the nuclear safety culture. The Sustainable Nuclear Energy Technology Platform (SNE-TP), composed of all stakeholders of nuclear fission and radiation protection (over 75 organizations), is a driving force therein. The emphasis in this paper is on nuclear competence building under the current 7-th Euratom Framework Programme (2007 - 2013). The employers (in particular, the nuclear industry and the technical safety organisations) are naturally involved in this process. According to the IAEA definition, competence means the ability to apply knowledge, skills and attitudes so as to perform a job in an effective and efficient manner and to an established standard (S.S.S. No. RS-G-1.4 / 2001). Knowledge is usually created in higher education institutions (e.g., universities) and in (private and public) research organizations. Skills and attitudes are usually the result of specific training and on-the-job experience throughout professional life. Euratom training activities are traditionally addressed to scientists and experts with higher education. Special attention is devoted to the continuous improvement of their competencies through borderless mobility and lifelong learning in synergy with the main stakeholders. The Euratom training strategy is based on 3 objectives: 1. Analysis of the needs of society and industry with regard to a common nuclear safety culture. This issue raises important questions, for examples: What should be added to existing training schemes? How could Continuous Professional Development (CPD) be improved? Is mobility and mutual recognition of

  12. Synthesis,characterization and catalytic properties of mesoporous MCM-48 containing zeolite secondary building units

    Institute of Scientific and Technical Information of China (English)

    LI Qiang; DOU Tao; ZHANG Ying; LI Yuping; WANG Shan; SUN Famin

    2007-01-01

    Mesoporous aluminosilicate MCM-48 containing zeolite secondary building units in the pore wall has been synthesized in alkaline media with a two-step procedure.The aluminosilicate precursors comprising zeolite secondary building units were first synthesized by carefully controlling reaction conditions and then were assembled using cotemplates of geminisurfactant [C18H37N(CH3)2(CH2)3-N(CH3)2C18H37]2+ (18-3-18) and triethanolamine (TEA).X-ray Diffraction (XRD) patterns of the as-made samples indicated that highly ordered mesostmctured MCM-48 was formed.Transmission Electron Microscopy (TEM) images further verified the formation of MCM-48 with uniform cubic pore channel system having the pore opening diameter of about 25 A.Compared with the conventionally synthesized MCM-48,the as-synthesized MCM-48 sample showed an adsorption band at 520-600 cm-1 in its FT-IR spectrum,which was assigned to five-membered ring vibration from zeolite structure.This suggested the presence of zeolite building units in the pore wall.N2 adsorption data showed that the material had a much higher specific surface area (1 200 m2/g)than the conventional MCM-48(1 100 m2/g).Finally,the catalytic performance of the as-made MCM-48 was evaluated by hydrogenation dealkylation reaction of heavy aromatic hydrocarbons.Catalytic results showed that the as-made MCM-48 catalyst exhibited higher conversion than the conventional MCM-48 catalyst.The as-made mesostructured MCM-48 may have a potential catalytic application in the conversion of bulky molecules.

  13. Heterogeneity within a Mesoporous Metal-Organic Framework with Three Distinct Metal-Containing Building Units.

    Science.gov (United States)

    Tu, Binbin; Pang, Qingqing; Ning, Erlong; Yan, Wenqing; Qi, Yi; Wu, Doufeng; Li, Qiaowei

    2015-10-28

    Materials built from multiple constituents have revealed emerging properties that are beyond linear integration of those from single components. We report a mesoporous metal-organic framework made from three geometrically distinct metal-containing secondary building units (SBUs) as a result of topological induction. The combinations of the Cu-based triangular, Zn-based octahedral, and Zn-based square pyramidal SBUs have created four types of cages in the network, despite that only one organic linker pyrazolecarboxylate was used. The longest distance for molecules maneuvering inside the largest cage is 5.2 nm. Furthermore, the complex and diversified pore environments allow the installation of various new functionalities in the framework as well as the expedited Ag nanoparticle formation in the pores. As presented in the molecule movement diagram, the crystal has provided specific arrangements of cages and apertures with distinct chemical features for guests transporting between the pores.

  14. Nuclear power plant life extension: How aging affects performance of containments & other structures

    Institute of Scientific and Technical Information of China (English)

    Robert A Dameron; Sun Junling

    2013-01-01

    This paper focuses on how aging can affect performance of safety-related structures in nuclear power plant (NPP).Knowledge and assessment of impacts of aging on structures are essential to plant life extension analysis,especially performance to severe loadings such as loss-of-coolant-accidents or major seismic events.Plant life extension issues are of keen interest in countries (like the United States) which have a large,aging fleet of NPPs.This paper addresses the overlap and relationship of structure aging to severe loading performance,with particular emphasis on containment structures.

  15. Building

    OpenAIRE

    Seavy, Ryan

    2014-01-01

    Building for concrete is temporary. The building of wood and steel stands against the concrete to give form and then gives way, leaving a trace of its existence behind. Concrete is not a building material. One does not build with concrete. One builds for concrete. MARCH

  16. Probabilistic finite element investigation of prestressing loss in nuclear containment wall segments

    Energy Technology Data Exchange (ETDEWEB)

    Balomenos, Georgios P., E-mail: gbalomen@uwaterloo.ca; Pandey, Mahesh D., E-mail: mdpandey@uwaterloo.ca

    2017-01-15

    Highlights: • Probabilistic finite element framework for assessing concrete strain distribution. • Investigation of prestressing loss based on concrete strain distribution. • Application to 3D nuclear containment wall segments. • Use of ABAQUS with python programing for Monte Carlo simulation. - Abstract: The main function of the concrete containment structures is to prevent radioactive leakage to the environment in case of a loss of coolant accident (LOCA). The Canadian Standard CSA N287.6 (2011) proposes periodic inspections, i.e., pressure testing, in order to assess the strength and design criteria of the containment (proof test) and the leak tightness of the containment boundary (leakage rate test). During these tests, the concrete strains are measured and are expected to have a distribution due to several uncertainties. Therefore, this study aims to propose a probabilistic finite element analysis framework. Then, investigates the relationship between the concrete strains and the prestressing loss, in order to examine the possibility of estimating the average prestressing loss during pressure testing inspections. The results indicate that the concrete strain measurements during the leakage rate test may provide information with respect to the prestressing loss of the bonded system. In addition, the demonstrated framework can be further used for the probabilistic finite element analysis of real scale containments.

  17. Safety analysis of nuclear containment vessels subjected to strong earthquakes and subsequent tsunamis

    Directory of Open Access Journals (Sweden)

    Feng Lin

    2017-08-01

    Full Text Available Nuclear power plants under expansion and under construction in China are mostly located in coastal areas, which means they are at risk of suffering strong earthquakes and subsequent tsunamis. This paper presents a safety analysis for a new reinforced concrete containment vessel in such events. A finite element method-based model was built, verified, and first used to understand the seismic performance of the containment vessel under earthquakes with increased intensities. Then, the model was used to assess the safety performance of the containment vessel subject to an earthquake with peak ground acceleration (PGA of 0.56g and subsequent tsunamis with increased inundation depths, similar to the 2011 Great East earthquake and tsunami in Japan. Results indicated that the containment vessel reached Limit State I (concrete cracking and Limit State II (concrete crushing when the PGAs were in a range of 0.8–1.1g and 1.2–1.7g, respectively. The containment vessel reached Limit State I with a tsunami inundation depth of 10 m after suffering an earthquake with a PGA of 0.56g. A site-specific hazard assessment was conducted to consider the likelihood of tsunami sources.

  18. Tus, an E. coli protein, contains mammalian nuclear targeting and exporting signals.

    Science.gov (United States)

    Kaczmarczyk, Stanislaw J; Sitaraman, Kalavathy; Hill, Thomas; Hartley, James L; Chatterjee, Deb K

    2010-01-26

    Shuttling of proteins between nucleus and cytoplasm in mammalian cells is facilitated by the presence of nuclear localization signals (NLS) and nuclear export signals (NES), respectively. However, we have found that Tus, an E. coli replication fork arresting protein, contains separate sequences that function efficiently as NLS and NES in mammalian cell lines, as judged by cellular location of GFP-fusion proteins. The NLS was localized to a short stretch of 9 amino acids in the carboxy-terminus of Tus protein. Alterations of any of these basic amino acids almost completely abolished the nuclear targeting. The NES comprises a cluster of leucine/hydrophobic residues located within 21 amino acids at the amino terminus of Tus. Finally, we have shown that purified GFP-Tus fusion protein or GFP-Tus NLS fusion protein, when added to the culture media, was internalized very efficiently into mammalian cells. Thus, Tus is perhaps the first reported bacterial protein to possess both NLS and NES, and has the capability to transduce protein into mammalian cells.

  19. Monitoring the Durability Performance of Concrete in Nuclear Waste Containment. Technical Progress Report No. 4

    Energy Technology Data Exchange (ETDEWEB)

    Ulm, Franz-Josef

    2000-06-30

    OAK-B135 Monitoring the Durability Performance of Concrete in Nuclear Waste Containment. Technical Progress Report No. 4. The analysis of the effect of cracks on the acceleration of the calcium leaching process of cement-based materials has been pursued. During the last period (Technical Progress Report No 3), we have introduced a modeling accounting for the high diffusivity of fractures in comparison with the weak solid material diffusivity. It has been shown through dimensional and asymptotic analysis that small fractures do not significantly accelerate the material aging process. This important result for the overall structural aging kinetics of containment structure has been developed in a paper submitted to the international journal ''Transport in Porous Media''.

  20. [GnRH analogues containing SV-40 virus T-antigen nuclear localization sequence].

    Science.gov (United States)

    Burov, S V; Iablokova, T V; Dorosh, M Iu; Kriviziuk, E V; Efremov, A M; Orlov, S V

    2010-01-01

    To improve the efficiency of anticancer drugs due to their delivery to intracellular targets a set of GnRH analogues containing nuclear localization signal (NLS) of SV-40 virus large T-antigen have been synthesized. NLS was attached to the parent molecule via ε-amino group of D-Lysine in position 1 or 6 of peptide sequence using orthogonal protection strategy. The biological activity studies revealed that incorporation of NLS moiety significantly increases cytotoxic activity of palmitoyl-containing GnRH analogues in vitro. The influence of tested peptides on tumor cells does not accompanied by the destruction of cell membrane, as confirmed in experiments with normal fibroblasts, used as a control.

  1. The effect of friction on simulated containment of underground nuclear explosions

    Energy Technology Data Exchange (ETDEWEB)

    Attia, A.V.

    1990-11-01

    The strength of the residual stress field is used as an important indicator in assessing the containment of underground nuclear explosions. Containment analysis using the COTTAGE geology shows considerable cracking in the hard Paleozoic layer, just below the cavity. The coefficient of friction is the ratio of total shear stress applied to a closed fracture surface to normal applied compressive total stress. Without any friction, the Paleozoic residual stress field is weakest. As the friction coefficient is increased from 0 to 0.5, the Paleozoic residual stress field is strengthened. A further increase of the friction coefficient from 0.5 to 0.8 shows strengthened where cracks are closed and weakening where cracks remain open. 4 refs., 4 figs., 1 tab.

  2. Solid state 31phosphorus nuclear magnetic resonance of iron-, manganese-, and copper-containing synthetic hydroxyapatites

    Science.gov (United States)

    Sutter, B.; Taylor, R. E.; Hossner, L. R.; Ming, D. W.

    2002-01-01

    The incorporation of micronutrients into synthetic hydroxyapatite (SHA) is proposed for slow release of these nutrients to crops in the National Aeronautics and Space Administration's (NASA's) Advanced Life Support (ALS) program for Lunar or Martian outposts. Solid state 31P nuclear magnetic resonance (NMR) was utilized to examine the paramagnetic effects of Fe3+, Mn2+, and Cu2+ to determine if they were incorporated into the SHA structure. Separate Fe3+, Mn2+, and Cu2+ containing SHA materials along with a transition metal free SHA (pure-SHA) were synthesized using a precipitation method. The proximity (concentrations were incorporated in the SHA structure. Iron-, Mn-, and Cu-containing SHA are potential slow release sources of Fe, Mn, and Cu in the ALS cropping system.

  3. Design Verification Report Spent Nuclear Fuel (SNF) Project Canister Storage Building (CSB)

    Energy Technology Data Exchange (ETDEWEB)

    BAZINET, G.D.

    2000-11-03

    The Sub-project W379, ''Spent Nuclear Fuel Canister Storage Building (CSB),'' was established as part of the Spent Nuclear Fuel (SNF) Project. The primary mission of the CSB is to safely store spent nuclear fuel removed from the K Basins in dry storage until such time that it can be transferred to the national geological repository at Yucca Mountain Nevada. This sub-project was initiated in late 1994 by a series of studies and conceptual designs. These studies determined that the partially constructed storage building, originally built as part of the Hanford Waste Vitrification Plant (HWVP) Project, could be redesigned to safely store the spent nuclear fuel. The scope of the CSB facility initially included a receiving station, a hot conditioning system, a storage vault, and a Multi-Canister Overpack (MCO) Handling Machine (MHM). Because of evolution of the project technical strategy, the hot conditioning system was deleted from the scope and MCO welding and sampling stations were added in its place. This report outlines the methods, procedures, and outputs developed by Project W379 to verify that the provided Structures, Systems, and Components (SSCs): satisfy the design requirements and acceptance criteria; perform their intended function; ensure that failure modes and hazards have been addressed in the design; and ensure that the SSCs as installed will not adversely impact other SSCs. The original version of this document was prepared by Vista Engineering for the SNF Project. The purpose of this revision is to document completion of verification actions that were pending at the time the initial report was prepared. Verification activities for the installed and operational SSCs have been completed. Verification of future additions to the CSB related to the canister cover cap and welding fixture system and MCO Internal Gas Sampling equipment will be completed as appropriate for those components. The open items related to verification of those

  4. Nuclear power plant Olkiluoto 3. Containment leakage test under extreme conditions

    Energy Technology Data Exchange (ETDEWEB)

    Fleckenstein, Tobias [TUEV SUED Industrie Service GmbH, Munich (Germany). Measaruement Technology Dept.

    2015-01-15

    Modern nuclear power plants place high demands on the design and execution of safety checks. TUEV SUED supported the containment leakage test for the largest- capacity third generation nuclear power plant in the world - Olkiluoto 3 in Finland. The experts successfully met the challenges presented by exceptional parameters of the project. The containment of Olkiluoto 3 is unique in that the vessel's volume is 80,000 m{sup 3} while measurements were carried out over a period of ten days. To execute the test, 75 temperature and 15 humidity sensors had to be installed and correctly interlinked by more than ten kilometres of cable. These instruments also needed to withstand an absolute pressure of 6 bar, ambient temperatures of 30 C and high levels of humidity. These conditions required comprehensive preparation and a high amount of qualification tests. Parts of the qualifications were carried out at the autoclave system of the Technical University in Munich, Germany, where the project test conditions could be simulated. The software required to determine the tests was developed by TUEV SUED and verified by German's national accreditation body DAkkS under ISO 17025. TUEV SUED enabled the test schedule to continue without delay by analysing all recorded data continuously on site, including pressure, temperature, humidity and leakage mass flow curves. With the comprehensive preparation, data acquisition system recording measurements continuously and the on-time result calculation, all components of the leak-tightness assessment were successfully completed in accordance with requirements.

  5. Nuclear Containment Inspection Using AN Array of Guided Wave Sensors for Damage Localization

    Science.gov (United States)

    Cobb, A. C.; Fisher, J. L.

    2010-02-01

    Nuclear power plant containments are typically both the last line of defense against the release of radioactivity to the environment and the first line of defense to protect against intrusion from external objects. As such, it is important to be able to locate any damage that would limit the integrity of the containment itself. Typically, a portion of the containment consists of a metallic pressure boundary that encloses the reactor primary circuit. It is made of thick steel plates welded together, lined with concrete and partially buried, limiting areas that can be visually inspected for corrosion damage. This study presents a strategy using low frequency (corrosion-like damage several meters from the probe in a mock-up of the containment vessel. A magnetostrictive sensor (MsS) is scanned across the width of the vessel, acquiring waveforms at a fixed interval. A beam forming strategy is used to localize the defects. Experimental results are presented for a variety of damage configurations, demonstrating the efficacy of this technique for detecting damage smaller than the ultrasonic wavelength.

  6. Effects of reinforcement ratio and arrangement on the structural behavior of a nuclear building under aircraft impact

    Energy Technology Data Exchange (ETDEWEB)

    Thai, Duc-Kien; Kim, Seung-Eock, E-mail: sekim@sejong.ac.kr; Lee, Hyuk-Kee

    2014-09-15

    Highlights: • Numerical analysis of RC nuclear building model under aircraft impact was conducted. • The analysis result shows similar behavior as compared to the Riera function. • The effects of reinforcement ratio and arrangement were enumerated. • The appropriate number of layer of longitudinal rebar was recommended. - Abstract: This study presents the effectiveness of the rebar ratio and the arrangement of reinforced concrete (RC) structures on the structural behavior of nuclear buildings under aircraft impact using a finite element (FE) approach. A simplified model of a fictitious nuclear building using RC structures was fully modeled. The aircraft model of a Boeing 767-400 was used for impact simulation and was developed and verified with a conventional impact force–time history curve. The IRIS Punching test was used to validate the damage prediction capabilities of the RC wall under impact loading. With regard to the different rebar ratios and rebar arrangements of a nuclear RC building, the structural behavior of a building under aircraft impact was investigated. The structural behavior investigated included plastic deformation, displacement, energy dissipation, perforation/penetration depth and scabbing area. The results showed that the rebar ratio has a significant effect on withstanding aircraft impact and reducing local damage. With four layers of rebar, the RC wall absorbed and dissipated the impact energy more than once with only two layers of rebar for the same rebar ratio.

  7. Radiation dose reduction efficiency of buildings after the accident at the Fukushima Daiichi Nuclear Power Station.

    Directory of Open Access Journals (Sweden)

    Satoru Monzen

    Full Text Available Numerous radionuclides were released from the Fukushima Daiichi Nuclear Power Station (F1-NPS in Japan following the magnitude 9.0 earthquake and tsunami on March 11, 2011. Local residents have been eager to calculate their individual radiation exposure. Thus, absorbed dose rates in the indoor and outdoor air at evacuation sites in the Fukushima Prefecture were measured using a gamma-ray measuring devices, and individual radiation exposure was calculated by assessing the radiation dose reduction efficiency (defined as the ratio of absorbed dose rate in the indoor air to the absorbed dose rate in the outdoor air of wood, aluminum, and reinforced concrete buildings. Between March 2011 and July 2011, dose reduction efficiencies of wood, aluminum, and reinforced concrete buildings were 0.55 ± 0.04, 0.15 ± 0.02, and 0.19 ± 0.04, respectively. The reduction efficiency of wood structures was 1.4 times higher than that reported by the International Atomic Energy Agency. The efficiency of reinforced concrete was similar to previously reported values, whereas that of aluminum structures has not been previously reported. Dose reduction efficiency increased in proportion to the distance from F1-NPS at 8 of the 18 evacuation sites. Time variations did not reflect dose reduction efficiencies at evacuation sites although absorbed dose rates in the outdoor air decreased. These data suggest that dose reduction efficiency depends on structure types, levels of contamination, and evacuee behaviors at evacuation sites.

  8. Ultrasonic Fingerprinting of Structural Materials: Spent Nuclear Fuel Containers Case-Study

    Science.gov (United States)

    Sednev, D.; Lider, A.; Demyanuk, D.; Kroening, M.; Salchak, Y.

    Nowadays, NDT is mainly focused on safety purposes, but it seems possible to apply those methods to provide national and IAEA safeguards. The containment of spent fuel in storage casks could be dramatically improved in case of development of so-called "smart" spent fuel storage and transfer casks. Such casks would have tamper indicating and monitoring/tracking features integrated directly into the cask design. The microstructure of the containers material as well as of the dedicated weld seam is applied to the lid and the cask body and provides a unique fingerprint of the full container, which can be reproducibly scanned by using an appropriate technique. The echo-sounder technique, which is the most commonly used method for material inspection, was chosen for this project. The main measuring parameter is acoustic noise, reflected from material's artefacts. The purpose is to obtain structural fingerprinting. Reference measurement and additional measurement results were compared. Obtained results have verified the appliance of structural fingerprint and the chosen control method. The successful authentication demonstrates the levels of the feature points' compliance exceeding the given threshold which differs considerably from the percentage of the concurrent points during authentication from other points. Since reproduction or doubling of the proposed unique identification characteristics is impossible at the current state science and technology, application of this technique is considered to identify the interference into the nuclear materials displacement with high accuracy.

  9. Passive 3D imaging of nuclear waste containers with Muon Scattering Tomography

    Science.gov (United States)

    Thomay, C.; Velthuis, J.; Poffley, T.; Baesso, P.; Cussans, D.; Frazão, L.

    2016-03-01

    The non-invasive imaging of dense objects is of particular interest in the context of nuclear waste management, where it is important to know the contents of waste containers without opening them. Using Muon Scattering Tomography (MST), it is possible to obtain a detailed 3D image of the contents of a waste container on reasonable timescales, showing both the high and low density materials inside. We show the performance of such a method on a Monte Carlo simulation of a dummy waste drum object containing objects of different shapes and materials. The simulation has been tuned with our MST prototype detector performance. In particular, we show that both a tungsten penny of 2 cm radius and 1 cm thickness, and a uranium sheet of 0.5 cm thickness can be clearly identified. We also show the performance of a novel edge finding technique, by which the edges of embedded objects can be identified more precisely than by solely using the imaging method.

  10. Standard practice for sampling special nuclear materials in multi-container lots

    CERN Document Server

    American Society for Testing and Materials. Philadelphia

    1987-01-01

    1.1 This practice provides an aid in designing a sampling and analysis plan for the purpose of minimizing random error in the measurement of the amount of nuclear material in a lot consisting of several containers. The problem addressed is the selection of the number of containers to be sampled, the number of samples to be taken from each sampled container, and the number of aliquot analyses to be performed on each sample. 1.2 This practice provides examples for application as well as the necessary development for understanding the statistics involved. The uniqueness of most situations does not allow presentation of step-by-step procedures for designing sampling plans. It is recommended that a statistician experienced in materials sampling be consulted when developing such plans. 1.3 The values stated in SI units are to be regarded as the standard. 1.4 This standard does not purport to address all of the safety problems, if any, associated with its use. It is the responsibility of the user of this standar...

  11. Pressure and temperature analyses using GOTHIC for Mark I containment of the Chinshan Nuclear Power Plant

    Energy Technology Data Exchange (ETDEWEB)

    Chen, Yen-Shu, E-mail: yschen@iner.org.t [Nuclear Engineering Division, Institute of Nuclear Energy Research, 1000, Wenhua Rd., Jiaan Village, Longtan Township, Taoyuan County 32546, Taiwan (China); Yuann, Yng-Ruey; Dai, Liang-Che; Lin, Yon-Pon [Nuclear Engineering Division, Institute of Nuclear Energy Research, 1000, Wenhua Rd., Jiaan Village, Longtan Township, Taoyuan County 32546, Taiwan (China)

    2011-05-15

    Research highlights: The Chinshan Mark I containment pressure-temperature responses are analyzed. GOTHIC is used to calculate the containment responses under three pipe break events. This study is used to support the Chinshan Stretch Power Uprate (SPU) program. The calculated peak pressure and temperature are still below the design values. The Chinshan containment integrity can be maintained under SPU condition. - Abstract: Chinshan Nuclear Power Plant in Taiwan is a GE-designed twin-unit BWR/4 plant with original licensed thermal power (OLTP) of 1775 MWt for each unit. Recently, the Stretch Power Uprate (SPU) program for the Chinshan plant is being conducted to uprate the core thermal power to 1858 MWt (104.66% OLTP). In this study, the Chinshan Mark I containment pressure/temperature responses during LOCA at 105% OLTP (104.66% OLTP + 0.34% OLTP power uncertainty = 105% OLTP) are analyzed using the containment thermal-hydraulic program GOTHIC. Three kinds of LOCA (Loss of Coolant Accident) scenarios are investigated: Recirculation Line Break (RCLB), Main Steam Line Break (MSLB), and Feedwater Line Break (FWLB). In the short-term analyses, blowdown data generated by RELAP5 transient analyses are provided as boundary conditions to the GOTHIC containment model. The calculated peak drywell pressure and temperature in the RCLB event are 217.2 kPaG and 137.1 {sup o}C, respectively, which are close to the original FSAR results (219.2 kPaG and 138.4 {sup o}C). Additionally, the peak drywell temperature of 155.3 {sup o}C calculated by MSLB is presented in this study. To obtain the peak suppression pool temperature, a long-term RCLB analysis is performed using a simplified RPV (Reactor Pressure Vessel) volume to calculate blowdown flow rate. One RHR (Residual Heat Removal) heat exchanger is assumed to be inoperable for suppression pool cooling mode. The calculated peak suppression pool temperature is 93.2 {sup o}C, which is below the pool temperature used for evaluating the

  12. Geotechnical studies relevant to the containment of underground nuclear explosions at the Nevada Test Site

    Energy Technology Data Exchange (ETDEWEB)

    Heuze, F.E.

    1982-05-01

    The Department of Energy and the Department of Defense are actively pursuing a program of nuclear weapons testing by underground explosions at the Nevada Test Site (NTS). Over the past 11 years, scores of tests have been conducted and the safety record is very good. In the short run, emphasis is put on preventing the release of radioactive materials into the atmosphere. In the long run, the subsidence and collapse of the ground above the nuclear cavities also are matters of interest. Currently, estimation of containment is based mostly on empiricism derived from extensive experience and on a combination of physical/mechanical testing and numerical modeling. When measured directly, the mechanical material properties are obtained from short-term laboratory tests on small, conventional samples. This practice does not determine the large effects of scale and time on measured stiffnesses and strengths of geological materials. Because of the limited data base of properties and in situ conditions, the input to otherwise fairly sophisticated computer programs is subject to several simplifying assumptions; some of them can have a nonconservative impact on the calculated results. As for the long-term, subsidence and collapse phenomena simply have not been studied to any significant degree. This report examines the geomechanical aspects of procedures currently used to estimate containment of undergroung explosions at NTS. Based on this examination, it is concluded that state-of-the-art geological engineering practice in the areas of field testing, large scale laboratory measurements, and numerical modeling can be drawn upon to complement the current approach.

  13. Blastocele fluid from in vitro- and in vivo-produced equine embryos contains nuclear DNA.

    Science.gov (United States)

    Herrera, C; Morikawa, M I; Castex, C Baca; Pinto, M R; Ortega, N; Fanti, T; Garaguso, R; Franco, M J; Castañares, M; Castañeira, C; Losinno, L; Miragaya, M H; Mutto, A A

    2015-02-01

    Normal mammalian early embryonic development involves apoptosis of blastomeres as a remodeling process during differentiation, starting at the blastocyst stage. Genomic DNA has been recently detected in the blastocele fluid of human embryos and has been amplified by real-time polymerase chain reaction (PCR) to diagnose the sex of in vitro-produced human embryos. This new approach varies from conventional preimplantation genetic diagnosis in that no cells are extracted from the embryo and only the blastocele fluid is aspirated and used as a DNA sample for diagnosis. In the present work, we investigated whether the blastocele fluid of equine preimplantation embryos contains nuclear DNA and whether this DNA could be used to diagnose the sex of the embryos by conventional PCR, using specific primers that target the TSPY and AMEL equine genes. The sex of 11 of 13 in vivo-produced embryos and of four of five in vitro-produced embryos was successfully diagnosed. The PCR amplification product was analyzed using genetic sequencing reporting that the DNA present in blastocele fluid was genomic. Additionally, after polyacrylamide gel electrophoresis and silver staining, the blastocele fluid from three different embryos produced a ladder pattern characteristic of DNA fragmented during apoptosis. Therefore, the results presented in this work report that blastocele fluid from in vivo- and in vitro-produced equine embryos contains nuclear DNA which is probably originated by apoptosis of embryonic cells, and this DNA could be used to diagnose the sex of preimlpantation embryos by conventional PCR.

  14. In-Containment Signal Acquisition and Data Transmission via Power Lines within High Dose Areas of Nuclear Power Plants

    Energy Technology Data Exchange (ETDEWEB)

    Mueller Steffen; Wibbing Sascha; Weigel Robert; Koelpin Alexander [Institute for Electronics Engineering, University of Erlangen-Nuremberg (Germany); Dennerlein, Juergen; Janke, Iryna; Weber, Johannes [AREVA GmbH, Paul-Gossen-Str. 100, 91052 Erlangen (Germany)

    2015-07-01

    Signal acquisition and data transmission for innovative sensor systems and networks inside the containment of nuclear power plants (NPPs) is still a challenge with respect to safety, performance, reliability, availability, and costs. This especially applies to equipment upgrades for existing plants, special measurements, but also for new builds. This paper presents a novel method for efficient and cost-effective sensor signal acquisition and data transmission via power lines, in order to cope with the disadvantages of common system architectures that often suffer from poor signal integrity due to raw data transmissions via long cables, huge efforts and costs for installation, and low flexibility with respect to maintenance and upgrades. A transmitter-receiver architecture is proposed that allows multiplexing of multiple sensor inputs for unidirectional point-to-point transmission by superimposing information signals on existing AC or DC supply lines, but also on active and inactive sensor wires, or spare cables, using power line communication (PLC) technology. Based on commercial off-the-shelf (COTS) electronic parts, a radiation hard transmitter hardware is designed to operate in harsh environment within the containment during full plant operation. The system's modular approach allows application specific trade-offs between redundancy and throughput regarding data transmission, as well as various sensor input front-ends which are compatible with state of the art systems. PLC technology eliminates the need for costly installation of additional cables and wall penetrations, while providing a complementary and diverse communication technology for upgrades of existing systems. At the receiver side in low dose areas, signals are extracted from the power line, demodulated, and de-multiplexed, in order to regain the original sensor signal information and provide it either in analog or digital output format. Successful laboratory qualification tests, field trails

  15. Joseph A. Burton Forum Award Lecture: Managing Nuclear and Biological Risks: Building Resilience through International Cooperation

    Science.gov (United States)

    Pregenzer, Arian

    2012-03-01

    International technical cooperation has long been an important nonproliferation strategy, especially since the 1990s when cooperative threat reduction (CTR) to prevent theft or illicit transfer of nuclear weapons, material and expertise in the former Soviet Union became a keystone of U.S. policy. The CTR approach expanded to include engagement with scientists and engineers with expertise relevant to biological and chemical weapons, and continued in the 2000s with efforts in Iraq and Libya, and cooperation with a wide range of countries on export control and nuclear and biological security. In general, the goal of such efforts has been to prevent proliferation or WMD terrorism. In most cases, the United States (or the West) defines the threat, and then funds partner countries to implement solutions. This presentation will argue that the future requires a new approach. Nuclear capabilities are more widely available than ever before, repercussions of the A.Q. Khan network continue to unfurl, and countries such as the DPRK engage in illicit cooperation. In addition, there has been a global boom in biotechnology with many nations, particularly across South and East Asia, investing in the biotech industry as a source of fuels, food, and materials for their rapidly expanding populations. Compared to the 1990s, today's threat is more diffuse, and the line between legitimate and illegitimate technical capability is no longer so clear. In addition, the West has many fewer resources to invest due to the global economic downturn. In this environment, full commitment of all countries that benefit from nuclear and biological advances will be required to assure the safety and security of all. Technical cooperation can continue to play an important role, but with some significant changes: First, challenges should be defined from a local perspective to ensure full commitment and participation. Second, the goal of cooperation should shift from preventing specific threats to building

  16. Non-destructive evaluation of containment walls in nuclear power plants

    Science.gov (United States)

    Garnier, V.; Payan, C.; Lott, M.; Ranaivomanana, N.; Balayssac, J. P.; Verdier, J.; Larose, E.; Zhang, Y.; Saliba, J.; Boniface, A.; Sbartai, Z. M.; Piwakowski, B.; Ciccarone, C.; Hafid, H.; Henault, J. M.; Buffet, F. Ouvrier

    2017-02-01

    Two functions are regularly tested on containment walls in order to anticipate a possible accident. The first is mechanical to resist a possible internal over-pressure and the second is to prevent leakage. The AAPR reference accident is the rupture of a pipe in the primary circuit of a nuclear plant. In this case, the pressure and temperature can reach 5 bar and 180°C in 20 seconds. The national project `Non-destructive testing of the containment structures of nuclear plants' aims at studying the non-destructive techniques capable to evaluate the concrete properties and its damaging and cracks. This 4-year-project is segmented into two parts. The first consists in developing and selecting the most relevant NDEs in the laboratory to reach these goals. These evaluations are developed in conditions representing the real conditions of the stresses generated during ten-yearly visits of the plants or those related to an accident. The second part consists in applying the selected techniques to two containment structures under pressure. The first structure is proposed by ONERA and the second is a mockup of a containment wall on a 1/3 scale made by EDF within the VeRCoRs project. Communication is focused on the part of the project that concerns the damage and crack process characterization by means of NDT. The tests are done in 3 or 4 points bending in order to study the cracks' generation, their propagation, as well as their opening and closing. The main ultrasonic techniques developed concern linear or non-linear acoustic: acoustic emission [1], Locadiff [2], energy diffusion, surface wave's velocity and attenuation, DAET [3]. The recorded data contribute to providing the mapping of the investigated parameters, either in volume, in surface or globally. Digital image correlation is an important additional asset to validate the coherence of the data. The spatial normalization of the data in the specimen space allows proposing algorithms on the combination of the

  17. 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)

  18. Tripartite Motif-Containing Protein 22 Interacts with Class II Transactivator and Orchestrates Its Recruitment in Nuclear Bodies Containing TRIM19/PML and Cyclin T1

    Directory of Open Access Journals (Sweden)

    Greta Forlani

    2017-05-01

    Full Text Available Among interferon (IFN inducible antiviral factors both tripartite motif-containing protein 22 (TRIM22 and class II transactivator (CIITA share the capacity of repressing human immunodeficiency virus type 1 (HIV-1 proviral transcription. TRIM22 is constitutively expressed in a subset of U937 cell clones poorly permissive to HIV-1 replication, whereas CIITA has been shown to inhibit virus multiplication in both T lymphocytic and myeloid cells, including poorly HIV-1 permissive U937 cells, by suppressing Tat-mediated transactivation of HIV-1 transcription. Therefore, we tested whether TRIM22 and CIITA could form a nuclear complex potentially endowed with HIV-1 repressive functions. Indeed, we observed that TRIM22, independent of its E3 ubiquitin ligase domain, interacts with CIITA and promotes its recruitment into nuclear bodies. Importantly, TRIM19/promyelocytic leukemia (PML protein, another repressor of HIV-1 transcription also acting before proviral integration, colocalize in these nuclear bodies upon TRIM22 expression induced by IFN-γ. Finally, tTRIM22 nuclear bodies also contained CyclinT1, a crucial elongation factor of HIV-1 primary transcripts. These findings show that TRIM22 nuclear bodies are a site of recruitment of factors crucial for the regulation of HIV-1 transcription and highlight the potential existence of a concerted action between TRIM22, CIITA, and TRIM19/PML to maintain a state of proviral latency, at least in myeloid cells.

  19. In the O&C Building, the P3 truss, an ISS segment, is revealed inside its shipping container

    Science.gov (United States)

    1999-01-01

    Inside the Operations and Checkout Building, cranes lift the top of the shipping container containing the port-side P3 truss, a segment of the International Space Station (ISS). The truss is scheduled to be added to the ISS on mission STS-115 in 2002 aboard Space Shuttle Atlantis. The second port truss segment, P3 will be attached to the first port truss segment (P1).

  20. Corrosion of steel drums containing cemented ion-exchange resins as intermediate level nuclear waste

    Energy Technology Data Exchange (ETDEWEB)

    Duffó, G.S. [Departamento de Materiales, Comisión Nacional de Energía Atómica, Av. Gral. Paz 1499, 1650 Buenos Aires (Argentina); Universidad Nacional de San Martín, Av. Gral. Paz 1499, 1650 Buenos Aires (Argentina); Consejo Nacional de Investigaciones Científicas y Tecnológicas – CONICET, Av. Gral. Paz 1499, 1650 Buenos Aires (Argentina); Farina, S.B., E-mail: farina@cnea.gov.ar [Departamento de Materiales, Comisión Nacional de Energía Atómica, Av. Gral. Paz 1499, 1650 Buenos Aires (Argentina); Universidad Nacional de San Martín, Av. Gral. Paz 1499, 1650 Buenos Aires (Argentina); Consejo Nacional de Investigaciones Científicas y Tecnológicas – CONICET, Av. Gral. Paz 1499, 1650 Buenos Aires (Argentina); Schulz, F.M. [Consejo Nacional de Investigaciones Científicas y Tecnológicas – CONICET, Av. Gral. Paz 1499, 1650 Buenos Aires (Argentina)

    2013-07-15

    Highlights: • There are no works related to the corrosion of drums containing radioactive waste. • Chloride induces high corrosion rate and after 1 year it drops abruptly. • Decrease in the corrosion rate is due to the lack of water to sustain the process. • Cementated ion-exchange resins do not pose risks of corrosion of the steel drums. -- Abstract: Exhausted ion-exchange resins used in nuclear reactors are immobilized by cementation before being stored. They are contained in steel drums that may undergo internal corrosion depending on the presence of certain contaminants. The objective of this work is to evaluate the corrosion susceptibility of steel drums in contact with cemented ion-exchange resins with different aggressive species. The corrosion potential and the corrosion rate of the steel, and the electrical resistivity of the matrix were monitored for 900 days. Results show that the cementation of ion-exchange resins seems not to pose special risks regarding the corrosion of the steel drums.

  1. Method for Non-Intrusively Identifying a Contained Material Utilizing Uncollided Nuclear Transmission Measurements

    Energy Technology Data Exchange (ETDEWEB)

    Morrison, John L.; Stephens, Alan G.; Grover Blaine S.

    1999-02-26

    An improved nuclear diagnostic method identifies a contained target material by measuring on-axis, mono-energetic uncollided particle radiation transmitted through a target material for two penetrating radiation beam energies, and applying specially developed algorithms to estimate a ratio of macroscopic neutron cross-sections for the uncollided particle radiation at the two energies, where the penetrating radiation is a neutron beam, or a ratio of linear attenuation coefficients for the uncollided particle radiation at the two energies, where the penetrating radiation is a gamma-ray beam. Alternatively, the measurements are used to derive a minimization formula based on the macroscopic neutron cross-sections for the uncollided particle radiation at the two neutron beam energies, or the linear attenuation coefficients for the uncollided particle radiation at the two gamma-ray beam energies. A candidate target material database, including known macroscopic neutron cross-sections or linear attenuation coefficients for target materials at the selected neutron or gamma-ray beam energies, is used to approximate the estimated ratio or to solve the minimization formula, such that the identity of the contained target material is discovered.

  2. Cooperative Monitoring Center Occasional Paper/12: ENTNEA: A Concept for Enhancing Nuclear Transparency for Confidence Building in Northeast Asia

    Energy Technology Data Exchange (ETDEWEB)

    Nam, Man-Kwon; Shin, Sung-Tack

    1999-06-01

    Nuclear energy continues to be a strong and growing component of economic development in Northeast Asia. A broad range of nuclear energy systems already exists across the region and vigorous growth is projected. Associated with these capabilities and plans are various concerns about operational safety, environmental protection, and accumulation of spent fuel and other nuclear materials. We consider cooperative measures that might address these concerns. The confidence building measures suggested here center on the sharing of information to lessen concerns about nuclear activities or to solve technical problems. These activities are encompassed by an Enhanced Nuclear Transparency in Northeast Asia (ENTNEA) concept that would be composed of near-term, information-sharing activities and an eventual regional institution. The near-term activities would address specific concerns and build a tradition of cooperation; examples include radiation measurements for public safety and emergency response, demonstration of safe operations at facilities and in transportation, and material security in the back end of the fuel cycle. Linkages to existing efforts and organizations would be sought to maximize the benefits of cooperation. In the longer term, the new cooperative tradition might evolve into an ENTNEA institution. In institutional form, ENTNEA could combine the near-term activities and new cooperative activities, which might require an institutional basis, for the mutual benefit and security of regional parties.

  3. Properties and solubility of chrome in iron alumina phosphate glasses containing high level nuclear waste

    Energy Technology Data Exchange (ETDEWEB)

    Huang, W. [School of Materials Science and Engineering, Tongji Univ., Shanghai, SH (China); Day, D.E.; Ray, C.S.; Kim, C.W.; Reis, S.T.D. [Univ. of Missouri-Rolla (United States). Graduate Center for Materials Research

    2004-10-01

    Chemical durability, glass formation tendency, and other properties of iron alumina phosphate glasses containing 70 wt% of a simulated high level nuclear waste (HLW), doped with different amounts of Cr{sub 2}O{sub 3}, have been investigated. All of the iron alumina phosphate glasses had an outstanding chemical durability as measured by their small dissolution rate (1 . 10{sup -9} g/(cm{sup 2} . min)) in deionized water at 90 C for 128 d, their low normalized mass release as determined by the product consistency test (PCT) and a barely measurable corrosion rate of <0.1 g/(m{sup 2} . d) after 7 d at 200 C by the vapor hydration test (VHT). The solubility limit for Cr{sub 2}O{sub 3} in the iron phosphate melts was estimated at 4.1 wt%, but all of the as-annealed melts contained a few percent of crystalline Cr{sub 2}O{sub 3} that had no apparent effect on the chemical durability. The chemical durability was unchanged after deliberate crystallization, 48 h at 650 C. These iron phosphate waste forms, with a waste loading of at least 70 wt%, can be readily melted in commercial refractory crucibles at 1250 C for 2 to 4 h, are resistant to crystallization, meet all current US Department of Energy requirements for chemical durability, and have a solubility limit for Cr{sub 2}O{sub 3} which is at least three times larger than that for borosilicate glasses. (orig.)

  4. Turbulent jet erosion of a stably stratified gas layer in a nuclear reactor test containment

    Energy Technology Data Exchange (ETDEWEB)

    Ishay, Liel [Department of Mechanical Engineering, Ben-Gurion University of the Negev, Beer-Sheva 84105 (Israel); Bieder, Ulrich [Commissariat à l’énergie atomique et aux énergies alternatives, Centre de SACLAY DEN/SAC/DANS/DM2S/STMF/LMSF, F-91191 Gif-sur-Yvette (France); Ziskind, Gennady [Department of Mechanical Engineering, Ben-Gurion University of the Negev, Beer-Sheva 84105 (Israel); Rashkovan, Alex, E-mail: rashbgu@gmail.com [Physics Department, Nuclear Research Center Negev (NRCN), PO Box 9001, Beer-Sheva 84190 (Israel)

    2015-10-15

    Highlights: • We model stably stratified layer erosion by vertical turbulent round jet. • Separate effect studies are performed as a platform for choosing modeling approach. • A test performed in MISTRA facility, CEA, Saclay is modeled using Fluent and Trio-U codes. • The proposed modeling approach showed good agreement with the MISTRA facility LOWMA-3 test. - Abstract: A number of integral and separate effect experiments were performed in the last two decades for validation of containment computational tools. The main goal of these benchmark experiments was to assess the ability of turbulence models and computational fluid dynamics codes to predict hydrogen concentration distribution and steam condensation rate in a nuclear reactor containment in the course of severe accidents. It appears from the published literature that the predictive capability of the existing computational tools still needs to be improved. This work examines numerically the temporal evolution of helium concentration in the experiment called LOWMA-3, performed in the MISTRA facility of CEA-Saclay, France. In the experiment, helium is used to mimic hydrogen of a real-case accident. The aim of this separate effect experiment, where steam condensation was not involved, is to predict helium concentration field. The conditions of the experiment are such that both the momentum transport and molecular diffusion contributions to the mixing process are of the same order of magnitude (Fr ∼ 1). A commercial CFD code, Fluent, and a CEA in-house code, Trio-U, are used for flow and helium concentration fields temporal evolution prediction in the present study. The preliminary separate effect studies provide guidance to an optimal modeling approach for the LOWMA-3 experiment. Temporal evolution of helium concentration in the stratification layer is shown, and a comparison to the experiment is discussed. It is shown that correct modeling of the round jet flowfield is essential for a reliable

  5. Measurement and modelling of reactive transport in geological barriers for nuclear waste containment.

    Science.gov (United States)

    Xiong, Qingrong; Joseph, Claudia; Schmeide, Katja; Jivkov, Andrey P

    2015-11-11

    Compacted clays are considered as excellent candidates for barriers to radionuclide transport in future repositories for nuclear waste due to their very low hydraulic permeability. Diffusion is the dominant transport mechanism, controlled by a nano-scale pore system. Assessment of the clays' long-term containment function requires adequate modelling of such pore systems and their evolution. Existing characterisation techniques do not provide complete pore space information for effective modelling, such as pore and throat size distributions and connectivity. Special network models for reactive transport are proposed here using the complimentary character of the pore space and the solid phase. This balances the insufficient characterisation information and provides the means for future mechanical-physical-chemical coupling. The anisotropy and heterogeneity of clays is represented using different length parameters and percentage of pores in different directions. Resulting networks are described as mathematical graphs with efficient discrete calculus formulation of transport. Opalinus Clay (OPA) is chosen as an example. Experimental data for the tritiated water (HTO) and U(vi) diffusion through OPA are presented. Calculated diffusion coefficients of HTO and uranium species are within the ranges of the experimentally determined data in different clay directions. This verifies the proposed pore network model and validates that uranium complexes are diffusing as neutral species in OPA. In the case of U(vi) diffusion the method is extended to account for sorption and convection. Rather than changing pore radii by coarse grained mathematical formula, physical sorption is simulated in each pore, which is more accurate and realistic.

  6. The aftermath of the Fukushima nuclear accident: Measures to contain groundwater contamination.

    Science.gov (United States)

    Gallardo, Adrian H; Marui, Atsunao

    2016-03-15

    Several measures are being implemented to control groundwater contamination at the Fukushima Daiichi Nuclear Plant. This paper presents an overview of work undertaken to contain the spread of radionuclides, and to mitigate releases to the ocean via hydrological pathways. As a first response, contaminated water is being held in tanks while awaiting treatment. Limited storage capacity and the risk of leakage make the measure unsustainable in the long term. Thus, an impervious barrier has been combined with a drain system to minimize the discharge of groundwater offshore. Caesium in seawater at the plant port has largely dropped, although some elevated concentrations are occasionally recorded. Moreover, a dissimilar decline of the radioactivity in fish could indicate additional sources of radionuclides intake. An underground frozen shield is also being constructed around the reactors. This structure would reduce inflows to the reactors and limit the interaction between fresh and contaminated waters. Additional strategies include groundwater abstraction and paving of surfaces to lower water levels and further restrict the mobilisation of radionuclides. Technical difficulties and public distrust pose an unprecedented challenge to the site remediation. Nevertheless, the knowledge acquired during the initial work offers opportunities for better planning and more rigorous decisions in the future.

  7. Dynamic localization of tripartite motif-containing 22 in nuclear and nucleolar bodies

    Energy Technology Data Exchange (ETDEWEB)

    Sivaramakrishnan, Gayathri; Sun, Yang; Tan, Si Kee [School of Biological Sciences, Nanyang Technological University, 60 Nanyang Drive, Singapore 637551 (Singapore); Lin, Valerie C.L., E-mail: cllin@ntu.edu.sg [School of Biological Sciences, Nanyang Technological University, 60 Nanyang Drive, Singapore 637551 (Singapore)

    2009-05-01

    Tripartite motif-containing 22 (TRIM22) exhibits antiviral and growth inhibitory properties, but there has been no study on the localization and dynamics of the endogenous TRIM22 protein. We report here that TRIM22 is dramatically induced by progesterone in MDA-MB-231-derived ABC28 cells and T47D cells. This induction was associated with an increase in TRIM22 nuclear bodies (NB), and an even more prominent increase in nucleolar TRIM22 bodies. Distinct endogenous TRIM22 NB were also demonstrated in several other cell lines including MCF7 and HeLa cells. These TRIM22 NB resemble Cajal bodies, co-localized with these structures and co-immunoprecipitated with p80-coilin. However, IFN{gamma}-induced TRIM22 in HeLa and MCF7 cells did not form NB, implying the forms and distribution of TRIM22 are regulated by specific cellular signals. This notion is also supported by the observation that TRIM22 NB undergoes dynamic cell-cycle dependent changes in distribution such that TRIM22 NB started to form in early G0/G1 but became dispersed in the S-phase. In light of its potential antiviral and antitumor properties, the findings here provide an interesting gateway to study the relationship between the different forms and functions of TRIM22.

  8. Evaluation of polymer inclusion membranes containing crown ethers for selective cesium separation from nuclear waste solution.

    Science.gov (United States)

    Mohapatra, P K; Lakshmi, D S; Bhattacharyya, A; Manchanda, V K

    2009-09-30

    Transport behaviour of (137)Cs from nitric acid feed was investigated using cellulose triacetate plasticized polymer inclusion membrane (PIM) containing several crown ether carriers viz. di-benzo-18-crown-6 (DB18C6), di-benzo-21-crown-7 (DB21C7) and di-tert-butylbenzo-18-crown-6 (DTBB18C6). The PIM was prepared from cellulose triacetate (CTA) with various crown ethers and plasticizers. DTBB18C6 and tri-n-butyl phosphate (TBP) were found to give higher transport rate for (137)Cs as compared to other carriers and plasticizers. Effect of crown ether concentration, nitric acid concentration, plasticizer and CTA concentration on the transport rate of Cs was also studied. The Cs selectivity with respect to various fission products obtained from an irradiated natural uranium target was found to be heavily dependent on the nature of the plasticizer. The present work shows that by choosing a proper plasticizer, one can get either good transport efficiency or selectivity. Though TBP plasticized membranes showed good transport efficiency, it displayed poor selectivities. On the other hand, an entirely opposite separation behaviour was observed with 2-nitrophenyloctylether (NPOE) plasticized membranes suggesting the possible application of the later membranes for the removal of bulk (137)Cs from the nuclear waste. The stability of the membrane was tested by carrying out transport runs for nearly 25 days.

  9. Separate effects testing and analyses to investigate liner tearing of the 1:6-scale reinforced concrete containment building

    Energy Technology Data Exchange (ETDEWEB)

    Spletzer, B.L.; Lambert, L.D.; Bergman, V.L. [Sandia National Labs., Albuquerque, NM (United States)] [and others

    1995-06-01

    The overpressurization of a 1:6-scale reinforced concrete containment building demonstrated that liner tearing is a plausible failure mode in such structures under severe accident conditions. A combined experimental and analytical program was developed to determine the important parameters which affect liner tearing and to develop reasonably simple analytical methods for predicting when tearing will occur. Three sets of test specimens were designed to allow individual control over and investigation of the mechanisms believed to be important in causing failure of the liner plate. The series of tests investigated the effect on liner tearing produced by the anchorage system, the loading conditions, and the transition in thickness from the liner to the insert plate. Before testing, the specimens were analyzed using two- and three-dimensional finite element models. Based on the analysis, the failure mode and corresponding load conditions were predicted for each specimen. Test data and post-test examination of test specimens show mixed agreement with the analytical predictions with regard to failure mode and specimen response for most tests. Many similarities were also observed between the response of the liner in the 1:6-scale reinforced concrete containment model and the response of the test specimens. This work illustrates the fact that the failure mechanism of a reinforced concrete containment building can be greatly influenced by details of liner and anchorage system design. Further, it significantly increases the understanding of containment building response under severe conditions.

  10. A robotized surface workstation for manipulation, filling and closing of packaging containers for spent nuclear fuel

    Energy Technology Data Exchange (ETDEWEB)

    Bartos, Pavel [FITE a.s., Ostrava-Marianske Hory (Czech Republic); Haladova, Petra [Robotsystem, LLC/Moravian Research, LLC, Ostrava-Moravska (Czech Republic); Otcenasek, Petr

    2016-01-15

    Options for the handling of spent nuclear fuel are described and a packaging cask for an underground repository is presented as also a robotic surface workplace for the repository. The potential for the closing the nuclear fuel cycle is discussed. Currently, a team of Czech experts is developing a project of fully robotic technology for manipulation and storage of packaging casks for spent nuclear fuel in host rock of underground repository.

  11. Nuclear geyser model of the origin of life: Driving force to promote the synthesis of building blocks of life

    Directory of Open Access Journals (Sweden)

    Toshikazu Ebisuzaki

    2017-03-01

    Full Text Available We propose the nuclear geyser model to elucidate an optimal site to bear the first life. Our model overcomes the difficulties that previously proposed models have encountered. Nuclear geyser is a geyser driven by a natural nuclear reactor, which was likely common in the Hadean Earth, because of a much higher abundance of 235U as nuclear fuel. The nuclear geyser supplies the following: (1 high-density ionizing radiation to promote chemical chain reactions that even tar can be used for intermediate material to restart chemical reactions, (2 a system to maintain the circulation of material and energy, which includes cyclic environmental conditions (warm/cool, dry/wet, etc. to enable to produce complex organic compounds, (3 a lower temperature than 100 °C as not to break down macromolecular organic compounds, (4 a locally reductive environment depending on rock types exposed along the geyser wall, and (5 a container to confine and accumulate volatile chemicals. These five factors are the necessary conditions that the birth place of life must satisfy. Only the nuclear geyser can meet all five, in contrast to the previously proposed birth sites, such as tidal flat, submarine hydrothermal vent, and outer space. The nuclear reactor and associated geyser, which maintain the circulations of material and energy with its surrounding environment, are regarded as the nuclear geyser system that enables numerous kinds of chemical reactions to synthesize complex organic compounds, and where the most primitive metabolism could be generated.

  12. Estimating the Additional Greenhouse Gas Emissions in Korea: Focused on Demolition of Asbestos Containing Materials in Building.

    Science.gov (United States)

    Kim, Young-Chan; Hong, Won-Hwa; Zhang, Yuan-Long; Son, Byeung-Hun; Seo, Youn-Kyu; Choi, Jun-Ho

    2016-09-12

    When asbestos containing materials (ACM) must be removed from the building before demolition, additional greenhouse gas (GHG) emissions are generated. However, precedent studies have not considered the removal of ACM from the building. The present study aimed to develop a model for estimating GHG emissions created by the ACM removal processes, specifically the removal of asbestos cement slates (ACS). The second objective was to use the new model to predict the total GHG emission produced by ACM removal in the entire country of Korea. First, an input-equipment inventory was established for each step of the ACS removal process. Second, an energy consumption database for each equipment type was established. Third, the total GHG emission contributed by each step of the process was calculated. The GHG emissions generated from the 1,142,688 ACS-containing buildings in Korea was estimated to total 23,778 tonCO₂eq to 132,141 tonCO₂eq. This study was meaningful in that the emissions generated by ACS removal have not been studied before. Furthermore, the study deals with additional problems that can be triggered by the presence of asbestos in building materials. The method provided in this study is expected to contribute greatly to the calculation of GHG emissions caused by ACM worldwide.

  13. Estimating the Additional Greenhouse Gas Emissions in Korea: Focused on Demolition of Asbestos Containing Materials in Building

    Directory of Open Access Journals (Sweden)

    Young-Chan Kim

    2016-09-01

    Full Text Available When asbestos containing materials (ACM must be removed from the building before demolition, additional greenhouse gas (GHG emissions are generated. However, precedent studies have not considered the removal of ACM from the building. The present study aimed to develop a model for estimating GHG emissions created by the ACM removal processes, specifically the removal of asbestos cement slates (ACS. The second objective was to use the new model to predict the total GHG emission produced by ACM removal in the entire country of Korea. First, an input-equipment inventory was established for each step of the ACS removal process. Second, an energy consumption database for each equipment type was established. Third, the total GHG emission contributed by each step of the process was calculated. The GHG emissions generated from the 1,142,688 ACS-containing buildings in Korea was estimated to total 23,778 tonCO2eq to 132,141 tonCO2eq. This study was meaningful in that the emissions generated by ACS removal have not been studied before. Furthermore, the study deals with additional problems that can be triggered by the presence of asbestos in building materials. The method provided in this study is expected to contribute greatly to the calculation of GHG emissions caused by ACM worldwide.

  14. Bilberry xyloglucan - novel building blocks containing ß-xylose within a complex structure

    NARCIS (Netherlands)

    Hilz, H.; Jong, de L.E.; Kabel, M.A.; Verhoef, R.P.; Schols, H.A.; Voragen, A.G.J.

    2007-01-01

    Bilberries are known to have one of the most complex xyloglucan structures described in the plant kingdom until now. To characterise this structure, xyloglucans were enzymatically degraded and the oligosaccharides obtained were analysed. More than 20 different building blocks were found to make up t

  15. Investigation of active interrogation techniques to detect special nuclear material in maritime environments: Boarded search of a cargo container ship

    Energy Technology Data Exchange (ETDEWEB)

    Grogan, Brandon R., E-mail: groganbr@ornl.gov; Henkel, James J.; Johnson, Jeffrey O.; Mihalczo, John T.; Miller, Thomas M.; Patton, Bruce W.

    2013-12-01

    The detonation of a terrorist nuclear weapon in the United States would result in the massive loss of life and grave economic damage. Even if a device was not detonated, its known or suspected presence aboard a cargo container ship in a U.S. port would have major economic and political consequences. One possible means to prevent this threat would be to board a ship at sea and search for the device before it reaches port. The scenario considered here involves a small Coast Guard team with strong intelligence boarding a container ship to search for a nuclear device. Using active interrogation, the team would nonintrusively search a block of shipping containers to locate the fissile material. Potential interrogation source and detector technologies for the team are discussed. The methodology of the scan is presented along with a technique for calculating the required interrogation source strength using computer simulations. MCNPX was used to construct a computer model of a container ship, and several search scenarios were simulated. The results of the simulations are presented in terms of the source strength required for each interrogation scenario. Validation measurements were performed in order to scale these simulation results to expected performance. Interrogations through the short (2.4 m) axis of a standardized shipping container appear to be feasible given the entire range of container loadings tested. Interrogations through several containers at once or a single container through its long (12.2 m) axis do not appear to be viable with a portable interrogation system.

  16. The aftermath of the Fukushima nuclear accident: Measures to contain groundwater contamination

    Energy Technology Data Exchange (ETDEWEB)

    Gallardo, Adrian H., E-mail: adgallardo@geowater.com.au [CONICET (Argentina National Scientific and Technical Research Council), San Luis National University, FCFMyN, Department of Geology, San Luis 5700 (Argentina); Marui, Atsunao [AIST Geological Survey of Japan, Geo-Resources and Environment Institute, Groundwater Research Group, Ibaraki-ken, Tsukuba 305-8567 (Japan)

    2016-03-15

    Several measures are being implemented to control groundwater contamination at the Fukushima Daiichi Nuclear Plant. This paper presents an overview of work undertaken to contain the spread of radionuclides, and to mitigate releases to the ocean via hydrological pathways. As a first response, contaminated water is being held in tanks while awaiting treatment. Limited storage capacity and the risk of leakage make the measure unsustainable in the long term. Thus, an impervious barrier has been combined with a drain system to minimize the discharge of groundwater offshore. Caesium in seawater at the plant port has largely dropped, although some elevated concentrations are occasionally recorded. Moreover, a dissimilar decline of the radioactivity in fish could indicate additional sources of radionuclides intake. An underground frozen shield is also being constructed around the reactors. This structure would reduce inflows to the reactors and limit the interaction between fresh and contaminated waters. Additional strategies include groundwater abstraction and paving of surfaces to lower water levels and further restrict the mobilisation of radionuclides. Technical difficulties and public distrust pose an unprecedented challenge to the site remediation. Nevertheless, the knowledge acquired during the initial work offers opportunities for better planning and more rigorous decisions in the future. - Highlights: • Measures are being undertaken to manage groundwater contamination in Fukushima. • Methods focus on isolating the source and controlling the radionuclides migration. • Wastewater is being temporarily held in tanks for treatment. • Impervious walls inhibit the transport of contaminants toward the ocean. • Paving and pumping further mitigate the dispersion of pollutants by water.

  17. Characterization of the Corrosion Behavior of Alloy 22 Regarding its Lifetime Performance as a Potential Nuclear Waste Container Material

    Energy Technology Data Exchange (ETDEWEB)

    Rebak, R B; McCright, D

    2002-06-04

    Alloy 22 (UNS N06022) was proposed for the corrosion resistant outer barrier of a two-layer waste package container for nuclear waste at the potential repository site at Yucca Mountain in Nevada (USA). A testing program is underway to characterize and quantify three main modes of corrosion that may occur at the site. Current results show that the containers would perform well under general corrosion, localized corrosion and environmentally assisted cracking (EAC). For example, the general corrosion rate is expected to be below 100 nm/year and the container is predicted to be outside the range of potential for localized corrosion and environmentally assisted cracking.

  18. Assessment of the feasibility of indefinite containment of canadian nuclear fuel wastes; Evaluation de la faisabilite du confinement illimite des dechets de combustible nucleaire canadiens

    Energy Technology Data Exchange (ETDEWEB)

    Shoesmith, D.W.; King, F.; Ikeda, B.M.

    1995-05-01

    This report presents an analysis of the expected corrosion behavior of nuclear fuel waste containers in a conceptual Canadian disposal vault. The container materials considered are dilute Ti alloys (Grades-2, -12 and -16) and oxygen-free copper.

  19. Force Reduction Factors for the Structural Design and Evaluation of Facilities Containing Nuclear and Hazardous Materials

    Energy Technology Data Exchange (ETDEWEB)

    Mertz, G.E.

    2001-07-26

    This report examines significant contributions to inelastic behavior of common building systems and develops frequency dependent force reduction factors that may be used with the results from linear elastic analyses models.

  20. Force Reduction Factors for the Structural Design and Evaluation of Facilities Containing Nuclear and Hazardous Materials

    Energy Technology Data Exchange (ETDEWEB)

    Mertz, G.E.

    2001-07-26

    This report examines significant contributions to inelastic behavior of common building systems and develops frequency dependent force reduction factors that may be used with the results from linear elastic analyses models.

  1. Reduction of 68Ge activity containing liquid waste from 68Ga PET chemistry in nuclear medicine and radiopharmacy by solidification

    NARCIS (Netherlands)

    E. de Blois (Erik); H.S. Chan; K. Roy (Kamalika); E.P. Krenning (Eric); W.A.P. Breeman (Wouter)

    2011-01-01

    textabstractPET with68Ga from the TiO2- or SnO2- based68Ge/68Ga generators is of increasing interest for PET imaging in nuclear medicine. In general, radionuclidic purity (68Ge vs.68Ga activity) of the eluate of these generators varies between 0.01 and 0.001%. Liquid waste containing low amounts of6

  2. Experiments to investigate direct containment heating phenomena with scaled models of the Zion Nuclear Power Plant in the Surtsey Test Facility

    Energy Technology Data Exchange (ETDEWEB)

    Allen, M.D.; Pilch, M.M.; Blanchat, T.K.; Griffith, R.O. [Sandia National Labs., Albuquerque, NM (United States); Nichols, R.T. [Ktech Corp., Albuquerque, NM (United States)

    1994-05-01

    The Surtsey Facility at Sandia National Laboratories (SNL) is used to perform scaled experiments that simulate hypothetical high-pressure melt ejection (HPME) accidents in a nuclear power plant (NPP). These experiments are designed to investigate the effect of specific phenomena associated with direct containment heating (DCH) on the containment load, such as the effect of physical scale, prototypic subcompartment structures, water in the cavity, and hydrogen generation and combustion. In the Integral Effects Test (IET) series, 1:10 linear scale models of the Zion NPP structures were constructed in the Surtsey vessel. The RPV was modeled with a steel pressure vessel that had a hemispherical bottom head, which had a 4-cm hole in the bottom head that simulated the final ablated hole that would be formed by ejection of an instrument guide tube in a severe NPP accident. Iron/alumina/chromium thermite was used to simulate molten corium that would accumulate on the bottom head of an actual RPV. The chemically reactive melt simulant was ejected by high-pressure steam from the RPV model into the scaled reactor cavity. Debris was then entrained through the instrument tunnel into the subcompartment structures and the upper dome of the simulated reactor containment building. The results of the IET experiments are given in this report.

  3. The Al-containing wastes technology of recycling for alumina, coagulants and building materials production

    Institute of Scientific and Technical Information of China (English)

    Lainer; U.; A.; Tuzhilin; A.; S.; Perekhoda; S.; P.; Vetchinkina; T.; N.; Samoilov; E.; N.

    2005-01-01

    The Al-containing wastes are generated by a row of industrial plants as hydroalumocarbonate residuum, underwastes water, foundry slag, mud, catalysts, mineral part of coals and others. These wastes is cycling in technological processes that cause to extra energy costs, processes stages difficulties and negatively affecting to environment.……

  4. The Al-containing wastes technology of recycling for alumina, coagulants and building materials production

    Institute of Scientific and Technical Information of China (English)

    2005-01-01

    @@ The Al-containing wastes are generated by a row of industrial plants as hydroalumocarbonate residuum, underwastes water, foundry slag, mud, catalysts, mineral part of coals and others. These wastes is cycling in technological processes that cause to extra energy costs, processes stages difficulties and negatively affecting to environment.

  5. Dual-Functional Hydrazide-Reactive and Anhydride-Containing Oligomeric Hydrogel Building Blocks.

    Science.gov (United States)

    Kascholke, Christian; Loth, Tina; Kohn-Polster, Caroline; Möller, Stephanie; Bellstedt, Peter; Schulz-Siegmund, Michaela; Schnabelrauch, Matthias; Hacker, Michael C

    2017-02-08

    Biomimetic hydrogels are advanced biomaterials that have been developed following different synthetic routes. Covalent postfabrication functionalization is a promising strategy to achieve efficient matrix modification decoupled of general material properties. To this end, dual-functional macromers were synthesized by free radical polymerization of maleic anhydride with diacetone acrylamide (N-(1,1-dimethyl-3-oxobutyl)acrylamide) and pentaerythritol diacrylate monostearate. Amphiphilic oligomers (Mn 40%). Efficient hydrazide/hydrazine immobilization depending on solution pH, hydrogel ketone content as well as ligand concentration for bioconjugation was shown and reversibility of hydrazone formation was indicated by physiologically relevant hydrazide release over 7 days. Proof-of-concept experiments with hydrazido-functionalized hyaluronan demonstrated potential for covalent aECM immobilization. The presented dual-functional macromers have perspective as reactive hydrogel building blocks for various biomedical applications.

  6. 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.

  7. Analysis of preliminary design concept of stainless steel container for disposal of spent nuclear fuel

    Energy Technology Data Exchange (ETDEWEB)

    Chun, K.S.; Ku, J.H.; Park, J.H.; Choi, J.W. [Korea Atomic Energy Research Institute, Taejon (Korea)

    1999-02-01

    This report represents the structural, thermal and radiation shielding analysis of the basic concepts of the disposal container, that could accommodate PWR and CANDU fuels of which physical dimensions and shapes are quite different each other, with respect to the emplacement modes. Basic concepts of the disposal containers for the vertical horehole and the drift emplacement modes are proposed with their maximum allowable thermal loading. Appropriate thickness of the container to withstand the expected external pressure in the underground repository system was delivered by the structural analyses. The thermal analysis of the container containing spent fuels showed that the internal maximum temperatures of all container concepts did not reach the constraint values. Radiation dose rate from the container with 10cm thickness wall were also less than the established constraint value. (author). 9 refs., 33 figs., 12 tabs.

  8. Nuclear Magnetic Resonance and Elastic Wave Velocity of Chalk Saturated with Brines Containing Divalent Ions

    DEFF Research Database (Denmark)

    Katika, Konstantina; Alam, Mohammad Monzurul; Fabricius, Ida Lykke

    Nuclear magnetic resonance (NMR) has proven a good technique for measuring pore size distribution in reservoir rocks. The use of low field NMR together with sonic and electrical resistivity measurements, can contribute to illustrate the effect of adsorbing ions on chalk elasticity. NMR is useful...

  9. Discovery of a new RNA-containing nuclear structure in UVC-induced apoptotic cells by integrated laser electron microscopy.

    Science.gov (United States)

    Karreman, Matthia A; Agronskaia, Alexandra V; Verkleij, Arie J; Cremers, Fons F M; Gerritsen, Hans C; Humbel, Bruno M

    2009-05-01

    Treatment of cells with UVC radiation leads to the formation of DNA cross-links which, if not repaired, can lead to apoptosis. gamma-H2AX and cleaved caspase 3 are proteins formed during UVC-induced DNA damage and apoptosis respectively. The present study sets out to identify early morphological markers of apoptosis using a new method of correlative microscopy, ILEM (integrated laser electron microscopy). Cleaved caspase 3 and gamma-H2AX were immunofluorescently labelled to mark the cells of interest. These cells were subsequently searched in the fluorescence mode of the ILEM and further analysed at high resolution with TEM (transmission electron microscopy). Following the treatment of HUVECs (human umbilical vein endothelial cells) with UVC radiation, in the majority of the cells gamma-H2AX was formed, whereas only in a subset of cells caspase 3 was activated. In severely damaged cells with high levels of gamma-H2AX a round, electron-dense nuclear structure was found, which was hitherto not identified in UV-stressed cells. This structure exists only in nuclei of cells containing cleaved caspase 3 and is present during all stages of the apoptotic process. Energy-loss imaging showed that the nuclear structure accumulates phosphorus, indicating that it is rich in nucleic acids. Because the nuclear structure did not label for DNA and was not affected by regressive EDTA treatment, it is suggested that the UV-induced nuclear structure contains a high amount of RNA. Because the UV-induced nuclear structure was only found in cells labelled for cleaved caspase 3 it is proposed as an electron microscopic marker for all stages of apoptosis. Such a marker will especially facilitate the screening for early apoptotic cells, which lack the well-known hallmarks of apoptosis within a cell population. It also raises new questions on the mechanisms involved in the UV-induced apoptotic pathway.

  10. Radon diffusion studies in some building materials using solid state nuclear track detectors

    CERN Document Server

    Singh, S; Singh, B; Singh, J

    1999-01-01

    LR-115 plastic track detector has been used to study radon diffusion through some building materials, viz. cement, soil, marble chips, sand and lime as well as air. Diffusion constant and diffusion length is calculated for all these materials.

  11. Proceedings of the seventh symposium on containment of underground nuclear explosions. Volume 1

    Energy Technology Data Exchange (ETDEWEB)

    Olsen, C.W. [ed.

    1993-12-31

    This is Volume 1 of two unclassified volumes of a meeting of workers at all levels in the science and technology of containment. Papers on containment and related geological, geophysical, engineering, chemical, and computational topics were included. Particular topics included in this volume are: General containment,tunnel and LOS topics, cavity conditions, and LYNER and chemical kiloton. Individual papers are indexed separately on the data base.

  12. Computational Fluid Dynamics Modeling of Steam Condensation on Nuclear Containment Wall Surfaces Based on Semiempirical Generalized Correlations

    Directory of Open Access Journals (Sweden)

    Pavan K. Sharma

    2012-01-01

    Full Text Available In water-cooled nuclear power reactors, significant quantities of steam and hydrogen could be produced within the primary containment following the postulated design basis accidents (DBA or beyond design basis accidents (BDBA. For accurate calculation of the temperature/pressure rise and hydrogen transport calculation in nuclear reactor containment due to such scenarios, wall condensation heat transfer coefficient (HTC is used. In the present work, the adaptation of a commercial CFD code with the implementation of models for steam condensation on wall surfaces in presence of noncondensable gases is explained. Steam condensation has been modeled using the empirical average HTC, which was originally developed to be used for “lumped-parameter” (volume-averaged modeling of steam condensation in the presence of noncondensable gases. The present paper suggests a generalized HTC based on curve fitting of most of the reported semiempirical condensation models, which are valid for specific wall conditions. The present methodology has been validated against limited reported experimental data from the COPAIN experimental facility. This is the first step towards the CFD-based generalized analysis procedure for condensation modeling applicable for containment wall surfaces that is being evolved further for specific wall surfaces within the multicompartment containment atmosphere.

  13. Building a Universal Nuclear Energy Density Functional (UNEDF): SciDAC-2 Project

    Energy Technology Data Exchange (ETDEWEB)

    Carlson, Joe; Furnstahl, Dick; Lusk, Rusty; Nazarewicz, Witek; Ng, Esmond; Thompson, Ian; Vary, James

    2012-06-30

    An understanding of the properties of atomic nuclei is crucial for a complete nuclear theory, for element formation, for properties of stars, and for present and future energy and defense applications. During the period of Dec. 1, 2006 - Jun. 30, 2012, the UNEDF collaboration carried out a comprehensive study of all nuclei based on the most accurate knowledge of the strong nuclear interaction, the most reliable theoretical approaches, the most advanced algorithms, and extensive computational resources, with a view towards scaling to the petaflop platforms and beyond. The long-term vision initiated with UNEDF is to arrive at a comprehensive, quantitative, and unified description of nuclei and their reactions, grounded in the fundamental interactions between the constituent nucleons. We seek to replace current phenomenological models of nuclear structure and reactions with a well-founded microscopic theory that delivers maximum predictive power with well-quantified uncertainties. Specifically, the mission of this project has been three-fold: first, to find an optimal energy density functional (EDF) using all our knowledge of the nucleonic Hamiltonian and basic nuclear properties; second, to apply the EDF theory and its extensions to validate the functional using all the available relevant nuclear structure and reaction data; and third, to apply the validated theory to properties of interest that cannot be measured, in particular the properties needed for reaction theory.

  14. Accelerated development of Zr-containing new generation ferritic steels for advanced nuclear reactors

    Energy Technology Data Exchange (ETDEWEB)

    Tan, Lizhen [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Yang, Ying [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Sridharan, K. [Univ. of Wisconsin, Madison, WI (United States)

    2015-12-01

    The mission of the Nuclear Energy Enabling Technologies (NEET) program is to develop crosscutting technologies for nuclear energy applications. Advanced structural materials with superior performance at elevated temperatures are always desired for nuclear reactors, which can improve reactor economics, safety margins, and design flexibility. They benefit not only new reactors, including advanced light water reactors (LWRs) and fast reactors such as the sodium-cooled fast reactor (SFR) that is primarily designed for management of high-level wastes, but also life extension of the existing fleet when component exchange is needed. Developing and utilizing the modern materials science tools (experimental, theoretical, and computational tools) is an important path to more efficient alloy development and process optimization. The ultimate goal of this project is, with the aid of computational modeling tools, to accelerate the development of Zr-bearing ferritic alloys that can be fabricated using conventional steelmaking methods. The new alloys are expected to have superior high-temperature creep performance and excellent radiation resistance as compared to Grade 91. The designed alloys were fabricated using arc-melting and drop-casting, followed by hot rolling and conventional heat treatments. Comprehensive experimental studies have been conducted on the developed alloys to evaluate their hardness, tensile properties, creep resistance, Charpy impact toughness, and aging resistance, as well as resistance to proton and heavy ion (Fe2+) irradiation.

  15. Deterministic and probabilistic analysis of damping device resistance under impact loads from nuclear fuel container drop

    Science.gov (United States)

    Kala, J.; Bajer, M.; Barnat, J.; Smutný, J.

    2010-12-01

    Pedestrian-induced vibrations are a criterion for serviceability. This loading is significant for light-weight footbridge structures, but was established as a basic loading for the ceilings of various ordinary buildings. Wide variations of this action exist. To verify the different conclusions of various authors, vertical pressure measurements invoked during walking were performed. In the article the approaches of different design codes are also shown.

  16. CFA-1: the first chiral metal-organic framework containing Kuratowski-type secondary building units.

    Science.gov (United States)

    Schmieder, Phillip; Denysenko, Dmytro; Grzywa, Maciej; Baumgärtner, Benjamin; Senkovska, Irena; Kaskel, Stefan; Sastre, German; van Wüllen, Leo; Volkmer, Dirk

    2013-08-14

    The novel homochiral metal-organic framework CFA-1 (Coordination Framework Augsburg-1), [Zn5(OAc)4(bibta)3], containing the achiral linker {H2-bibta = 1H,1'H-5,5'-bibenzo[d][1,2,3]triazole}, has been synthesised. The reaction of H2-bibta and Zn(OAc)2·2H2O in N-methylformamide (NMF) (90 °C, 3 d) yields CFA-1 as trigonal prismatic single crystals. CFA-1 serves as a convenient precursor for the synthesis of isostructural frameworks with redox-active metal centres, which is demonstrated by the postsynthetic exchange of Zn(2+) by Co(2+) ions. The framework is robust to solvent removal and has been structurally characterized by synchrotron single-crystal X-ray diffraction and solid state NMR measurements ((13)C MAS- and (1)H MAS-NMR at 10 kHz). Results from MAS-NMR and IR spectroscopy studies are corroborated by cluster and periodic DFT calculations performed on CFA-1 cluster fragments.

  17. Proceedings of the seventh symposium on containment of underground nuclear explosions. Volume 2

    Energy Technology Data Exchange (ETDEWEB)

    Olsen, C.W. [ed.

    1993-12-31

    This is Volume 2 of two unclassified volumes of a meeting of workers at all levels in the science and technology of containment. Papers on containment and related geological, geophysical, engineering, chemical, and computational topics were included. Particular topics in this volume include: Low-yield test beds, modeling and residual stress, material properties, collapse phenomena and shock diagnostics, stemming practices and performance, geophysics, and geosciences and weapons destruction. Individual papers are indexed separately on the data base.

  18. A four-scale homogenization analysis of creep of a nuclear containment structure

    Energy Technology Data Exchange (ETDEWEB)

    Tran, A.B. [Université Paris-Est, Laboratoire Modélisation et Simulation Multi Échelle, MSME UMR 8208 CNRS, 5 bd Descartes, F-77454 Marne-la-Vallée (France); EDF R and D – Département MMC Site des Renardières – Avenue des Renardières - Ecuelles, 77818 Moret sur Loing Cedex (France); Department of Applied Informatics in Construction, National University of Civil Engineering, 55 Giai Phong Road, Hai Ba Trung District, Hanoi (Viet Nam); Yvonnet, J., E-mail: julien.yvonnet@univ-paris-est.fr [Université Paris-Est, Laboratoire Modélisation et Simulation Multi Échelle, MSME UMR 8208 CNRS, 5 bd Descartes, F-77454 Marne-la-Vallée (France); He, Q.-C. [Université Paris-Est, Laboratoire Modélisation et Simulation Multi Échelle, MSME UMR 8208 CNRS, 5 bd Descartes, F-77454 Marne-la-Vallée (France); Toulemonde, C.; Sanahuja, J. [EDF R and D – Département MMC Site des Renardières – Avenue des Renardières - Ecuelles, 77818 Moret sur Loing Cedex (France)

    2013-12-15

    A four-scale approach is proposed to predict the creep behavior of a concrete structure. The behavior of concrete is modeled through a numerical multiscale methodology, by successively homogenizing the viscoelastic behavior at different scales, starting from the cement paste. The homogenization is carried out by numerically constructing an effective relaxation tensor at each scale. In this framework, the impact of modifying the microstructural parameters can be directly observed on the structure response, like the interaction of the creep of concrete with the prestressing tendons network, and the effects of an internal pressure which might occur during a nuclear accident.

  19. Nuclear Magnetic Resonance and Elastic Wave Velocity of Chalk Saturated with Brines Containing Divalent Ions

    DEFF Research Database (Denmark)

    Katika, Konstantina; Alam, Mohammad Monzurul; Fabricius, Ida Lykke

    Nuclear magnetic resonance (NMR) has proven a good technique for measuring pore size distribution in reservoir rocks. The use of low field NMR together with sonic and electrical resistivity measurements, can contribute to illustrate the effect of adsorbing ions on chalk elasticity. NMR is useful...... of the relaxation time. Core samples saturated with calcium chloride solution relaxed slower and those saturated with magnesium chloride solution relaxed faster than the rest of the samples. Along with the changes in relaxation the samples experienced smaller velocities of elastic waves when saturated with MgCl2...

  20. Short-term pressure and temperature MSLB response analyses for large dry containment of the Maanshan nuclear power station

    Energy Technology Data Exchange (ETDEWEB)

    Dai, Liang-Che, E-mail: lcdai@iner.gov.tw; Chen, Yen-Shu; Yuann, Yng-Ruey

    2014-12-15

    Highlights: • The GOTHIC code is used for the PWR dry containment pressure and temperature analysis. • Boundary conditions are hot standby and 102% power main steam line break accidents. • Containment pressure and temperature responses of GOTHIC are similar with FSAR. • The capability of the developed model to perform licensing calculation is assessed. - Abstract: Units 1 and 2 of the Maanshan nuclear power station are the typical Westinghouse three-loop PWR (pressurized water reactor) with large dry containments. In this study, the containment analysis program GOTHIC is adopted for the dry containment pressure and temperature analysis. Free air space and sump of the PWR dry containment are individually modeled as control volumes. The containment spray system and fan cooler unit are also considered in the GOTHIC model. The blowdown mass and energy data of the main steam line break (hot standby condition and various reactor thermal power levels) are tabulated in the Maanshan Final Safety Analysis Report (FSAR) 6.2 which could be used as the boundary conditions for the containment model. The calculated containment pressure and temperature behaviors of the selected cases are in good agreement with the FSAR results. In this study, hot standby and 102% reactor thermal power main steam line break accidents are selected. The calculated peak containment pressure is 323.50 kPag (46.92 psig) for hot standby MSLB, which is a little higher than the FSAR value of 311.92 kPag (45.24 psig). But it is still below the design value of 413.69 kPag (60 psig). The calculated peak vapor temperature inside the containment is 187.0 °C (368.59 F) for 102% reactor thermal power MSLB, which is lower than the FSAR result of 194.42 °C (381.95 F). The effects of the containment spray system and fan cooler units could be clearly observed in the GOTHIC analysis. The calculated containment pressure and temperature behaviors of the selected cases are in good agreement with the FSAR

  1. V-Model based Configuration Management Program for New-Build Nuclear Power Plant

    Energy Technology Data Exchange (ETDEWEB)

    An, Kyungik [PartDB Co. Ltd., Daejeon (Korea, Republic of); Cho, Yoon Sang [KHNP Co. Ltd., Daejeon (Korea, Republic of); Freeland, Kent R. [Industrial Analysts Incorporated, New Hampshire (United States)

    2014-05-15

    As NPP operators undertook design basis reconstitution efforts, they began to realize that the design basis is a foundation for Configuration Management (CM). This realization was made evident in the magnitude of the problems that were being observed. This experience also raised serious questions about how the information being developed to produce the design basis documents would be kept up to date in the future. A process to reconstitute the design basis is likely to be ineffective if CM controls are not in place. The right IT solution for CM depends upon a number of factors, including the nuclear power plant culture, budget, target technology, and the nuclear power plant owner/operator's standards, requirements and limitations for its generating fleet. Comprehensive CM Program for NPP is the single greatest strategy to meet the commitment to nuclear excellence. The safety and viability of nuclear power, particularly at the fleet level, depends upon the development of positive design control and design basis to better understanding plant operating dynamics and margin management, along with technology to control the realization of such design in the physical plant. However the most of plant facilities are modified many times, often without suitable support needed to confirm with their design base and to update their engineering data, maintenance rules and operating procedures. This lack of equilibrium between the requirements, design information and physical plant still remains a important issue. This study focuses on how to manage the configuration information of NPP using systems engineering V-model approach, and proposes data model to manage the configuration information in relation to manage their life cycle. Comprehensive CM Program and IMS for NPP life cycle support is the greatest strategy to meet the commitment to nuclear safety.

  2. Building the strategic national stockpile through the NIAID Radiation Nuclear Countermeasures Program.

    Science.gov (United States)

    Rios, Carmen I; Cassatt, David R; Dicarlo, Andrea L; Macchiarini, Francesca; Ramakrishnan, Narayani; Norman, Mai-Kim; Maidment, Bert W

    2014-02-01

    The possibility of a public health radiological or nuclear emergency in the United States remains a concern. Media attention focused on lost radioactive sources and international nuclear threats, as well as the potential for accidents in nuclear power facilities (e.g., Windscale, Three Mile Island, Chernobyl, and Fukushima) highlight the need to address this critical national security issue. To date, no drugs have been licensed to mitigate/treat the acute and long-term radiation injuries that would result in the event of large-scale, radiation, or nuclear public health emergency. However, recent evaluation of several candidate radiation medical countermeasures (MCMs) has provided initial proof-of-concept of efficacy. The goal of the Radiation Nuclear Countermeasures Program (RNCP) of the National Institute of Allergy and Infectious Diseases (National Institutes of Health) is to help ensure the government stockpiling of safe and efficacious MCMs to treat radiation injuries, including, but not limited to, hematopoietic, gastrointestinal, pulmonary, cutaneous, renal, cardiovascular, and central nervous systems. In addition to supporting research in these areas, the RNCP continues to fund research and development of decorporation agents targeting internal radionuclide contamination, and biodosimetry platforms (e.g., biomarkers and devices) to assess the levels of an individual's radiation exposure, capabilities that would be critical in a mass casualty scenario. New areas of research within the program include a focus on special populations, especially pediatric and geriatric civilians, as well as combination studies, in which drugs are tested within the context of expected medical care management (e.g., antibiotics and growth factors). Moving forward, challenges facing the RNCP, as well as the entire radiation research field, include further advancement and qualification of animal models, dose conversion from animal models to humans, biomarker identification, and

  3. Building and Querying RDF/OWL Database of Semantically Annotated Nuclear Medicine Images.

    Science.gov (United States)

    Hwang, Kyung Hoon; Lee, Haejun; Koh, Geon; Willrett, Debra; Rubin, Daniel L

    2017-02-01

    As the use of positron emission tomography-computed tomography (PET-CT) has increased rapidly, there is a need to retrieve relevant medical images that can assist image interpretation. However, the images themselves lack the explicit information needed for query. We constructed a semantically structured database of nuclear medicine images using the Annotation and Image Markup (AIM) format and evaluated the ability the AIM annotations to improve image search. We created AIM annotation templates specific to the nuclear medicine domain and used them to annotate 100 nuclear medicine PET-CT studies in AIM format using controlled vocabulary. We evaluated image retrieval from 20 specific clinical queries. As the gold standard, two nuclear medicine physicians manually retrieved the relevant images from the image database using free text search of radiology reports for the same queries. We compared query results with the manually retrieved results obtained by the physicians. The query performance indicated a 98 % recall for simple queries and a 89 % recall for complex queries. In total, the queries provided 95 % (75 of 79 images) recall, 100 % precision, and an F1 score of 0.97 for the 20 clinical queries. Three of the four images missed by the queries required reasoning for successful retrieval. Nuclear medicine images augmented using semantic annotations in AIM enabled high recall and precision for simple queries, helping physicians to retrieve the relevant images. Further study using a larger data set and the implementation of an inference engine may improve query results for more complex queries.

  4. 某核电厂生产办公楼的建筑设计%Production office building design of nuclear power plant

    Institute of Scientific and Technical Information of China (English)

    车新路; 赵书娴

    2016-01-01

    Combining with the general horizontal layout scheme of the production office building of the nuclear power plant,introduces its spatial composite features,describes matters needing attention in the production office building design of the nuclear power plant from aspects of the of-fice building design demands,the relationship between the nuclear power plant production office building and the nuclear power plant workshop, office building space features,with a view to realize the office building serving targets of “convenient management and safe production”.%结合某核电厂生产办公楼的总平面布局方案,介绍了其平面空间组合特点,并从办公楼的设计要求、办公楼与厂区关系、办公空间特质等方面,阐述了核电厂生产办公楼设计的注意要点,旨在实现办公楼“便于管理、安全生产”的服务目标。

  5. Evaluation of Ultimate Pressure Capacity of a Prestressed Concrete Containment Building with Steel or Polyamide Fiber Reinforcement

    Energy Technology Data Exchange (ETDEWEB)

    Choun, Youngsun; Hahm, Daegi [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2014-05-15

    Fiber reinforced concrete (FRC) includes thousands of small fibers that are distributed randomly in the concrete. Fibers resist the growth of cracks in concrete through their bridging at the cracks. Therefore, FRC fails in tension only when the fibers break or are pulled out of the cement matrix. For this reason, the addition of fibers in concrete mixing increases the tensile toughness of concrete and enhances the post-cracking behavior. A prevention of through-wall cracks and an increase of the post-cracking ductility will improve the ultimate internal pressure capacity of a prestressed concrete containment building (PCCB). In this study, the effects of steel or polyamide fiber reinforcement on the ultimate pressure capacity of a PCCB are evaluated. When R-SFRC contains hooked steel fibers in a volume fraction of 1.0%, the ultimate pressure capacity of a PCCB can be improved by 17%. When R-PFRC contains polyamide fibers in a volume fraction of 1.5%, the ultimate pressure capacity of a PCCB can be enhanced by 10%. Further studies are needed to determine the strain limits acceptable for PCCBs reinforced with fibers.

  6. PROVING EXPERIMENTS AND ANALYSIS OF ROOFTOP HEAT SHIELD EXPERIMENT WITH WATER CONTAIN CONCRETE BOAD THAT USES ELEMENTARY SCHOOL BUILDING

    Science.gov (United States)

    Yamada, Hiroyuki; Tanaka, Akinori; 日根, 隆夫; Okuda, Yoshio; Koyama, Hiroyuki; Hada, Yuuichi

    In this study, the reduction effect of the heat inflow on the rooftop and the indoor thermal environment was measured by using the elementary school building, the rooftop of the bilding was covered with the water contain concrete boards. And, conserve energy effect and effectiveness for the indoor thermal environment improvement were evaluated. The effect of the decrease of the surface temperature and the slab side temperature at water contain concrete boad plot remarkably from the measurement result during the July-September of 2010, the temperatures decrease 22°C at the surface, 15°C at the waterproof layer surface that was caused compared with the gravel covered roof. The water contain concrete boards plot always drove the ceiling side temperature and the indoor temperature low as a result of comparing with the indoor condition of the control plot. The temperature fluctuate was small at time that opened the window and ventilated, and ventilation was discontinued, it became big temperatures fluctuate. The effect of the decrease of 0.5°C in PMV and 0.5 in WBGT was caused while the room had sealed up, and the effect of the decrease of 0.3 in WBGT was caused while the ventilated state.

  7. A Prototype Scintillating-Fibre Tracker for the Cosmic-ray Muon Tomography of Legacy Nuclear Waste Containers

    Directory of Open Access Journals (Sweden)

    Kaiser R.

    2014-03-01

    Full Text Available Cosmic-ray muons are highly-penetrative charged particles observed at sea level with a flux of approximately 1 cm−2 min−1. They interact with matter primarily through Coulomb scattering which can be exploited in muon tomography to image objects within industrial nuclear waste containers. This paper presents the prototype scintillating-fibre detector developed for this application at the University of Glasgow. Experimental results taken with test objects are shown in comparison to results from GEANT4 simulations. These results verify the simulation and show discrimination between the low, medium and high-Z materials imaged.

  8. Compatibility of Space Nuclear Power Plant Materials in an Inert He/Xe Working Gas Containing Reactive Impurities

    Energy Technology Data Exchange (ETDEWEB)

    MM Hall

    2006-01-31

    A major materials selection and qualification issue identified in the Space Materials Plan is the potential for creating materials compatibility problems by combining dissimilar reactor core, Brayton Unit and other power conversion plant materials in a recirculating, inert He/Xe gas loop containing reactive impurity gases. Reported here are results of equilibrium thermochemical analyses that address the compatibility of space nuclear power plant (SNPP) materials in high temperature impure He gas environments. These studies provide early information regarding the constraints that exist for SNPP materials selection and provide guidance for establishing test objectives and environments for SNPP materials qualification testing.

  9. A Prototype Scintillating-Fibre Tracker for the Cosmic-ray Muon Tomography of Legacy Nuclear Waste Containers

    Science.gov (United States)

    Kaiser, R.; Clarkson, A.; Hamilton, D. J.; Hoek, M.; Ireland, D. G.; Johnston, J. R.; Keri, T.; Lumsden, S.; Mahon, D. F.; McKinnon, B.; Murray, M.; Nutbeam-Tuffs, S.; Shearer, C.; Staines, C.; Yang, G.; Zimmerman, C.

    2014-03-01

    Cosmic-ray muons are highly-penetrative charged particles observed at sea level with a flux of approximately 1 cm-2 min-1. They interact with matter primarily through Coulomb scattering which can be exploited in muon tomography to image objects within industrial nuclear waste containers. This paper presents the prototype scintillating-fibre detector developed for this application at the University of Glasgow. Experimental results taken with test objects are shown in comparison to results from GEANT4 simulations. These results verify the simulation and show discrimination between the low, medium and high-Z materials imaged.

  10. Experimental study on the heat transfer characteristics of a nuclear reactor containment wall cooled by gravitationally falling water

    Science.gov (United States)

    Pasek, Ari D.; Umar, Efrison; Suwono, Aryadi; Manalu, Reinhard E. E.

    2012-06-01

    Gravitationally falling water cooling is one of mechanism utilized by a modern nuclear Pressurized Water Reactor (PWR) for its Passive Containment Cooling System (PCCS). Since the cooling is closely related to the safety, water film cooling characteristics of the PCCS should be studied. This paper deals with the experimental study of laminar water film cooling on the containment model wall. The influences of water mass flow rate and wall heat rate on the heat transfer characteristic were studied. This research was started with design and assembly of a containment model equipped with the water cooling system, and calibration of all measurement devices. The containment model is a scaled down model of AP 1000 reactor. Below the containment steam is generated using electrical heaters. The steam heated the containment wall, and then the temperatures of the wall in several positions were measure transiently using thermocouples and data acquisition. The containment was then cooled by falling water sprayed from the top of the containment. The experiments were done for various wall heat rate and cooling water flow rate. The objective of the research is to find the temperature profile along the wall before and after the water cooling applied, prediction of the water film characteristic such as means velocity, thickness and their influence to the heat transfer coefficient. The result of the experiments shows that the wall temperatures significantly drop after being sprayed with water. The thickness of water film increases with increasing water flow rate and remained constant with increasing wall heat rate. The heat transfer coefficient decreases as film mass flow rate increase due to the increases of the film thickness which causes the increasing of the thermal resistance. The heat transfer coefficient increases slightly as the wall heat rate increases. The experimental results were then compared with previous theoretical studied.

  11. Spent nuclear fuel project detonation phenomena of hydrogen/oxygen in spent fuel containers

    Energy Technology Data Exchange (ETDEWEB)

    Cooper, T.D.

    1996-09-30

    Movement of Spent N Reactor fuels from the Hanford K Basins near the Columbia River to Dry interim storage facility on the Hanford plateau will require repackaging the fuel in the basins into multi-canister overpacks (MCOs), drying of the fuel, transporting the contained fuel, hot conditioning, and finally interim storage. Each of these functions will be accomplished while the fuel is contained in the MCOs by several mechanisms. The principal source of hydrogenand oxygen within the MCOs is residual water from the vacuum drying and hot conditioning operations. This document assesses the detonation phenomena of hydrogen and oxygen in the spent fuel containers. Several process scenarios have been identified that could generate detonation pressures that exceed the nominal 10 atmosphere design limit ofthe MCOS. Only 42 grams of radiolized water are required to establish this condition.

  12. e-Cluster Building and Using for Nuclear Industry Human Resources

    Energy Technology Data Exchange (ETDEWEB)

    Hur, Jung Hoon; Suh, Jang Soo [Nuclear Power Education Institute, KHNP, Ulsan (Korea, Republic of)

    2009-10-15

    In line with its industry support policy, KHNP provides training courses for small and medium sized companies within the nuclear sector. The courses cover three main areas; technical development, market expansion and human resource and finance. They are provided in traditional classroom settings and on-line. Employees from small and medium sized companies can take any of the available courses according to company and individual training and development requirements. While the training and development opportunities serve a role in the growth and development of skills and capabilities industry-wide, KHNP also sees the involvement of a wide range of nuclear industry participants in the program as a means of developing a safety consensus that addresses both operational and social safety concerns. The purpose of this paper is to outline the successes of the KHNP industry training support program to date and to propose the development of an e-Cluster model. This model envisages the development of a nuclear industry. It will provide a means for sharing information and developing and maintaining industry-wide technical, management and safety standards.

  13. Building a Universal Nuclear Energy Density Functional (UNEDF). SciDAC-2 Project

    Energy Technology Data Exchange (ETDEWEB)

    Vary, James P. [Iowa State University, Ames, IA (United States); Carlson, Joe; Furnstahl, Dick; Horoi, Mihai; Lusk, Rusty; Nazarewicz, Witek; Ng, Esmond; Thompson, Ian

    2012-09-29

    An understanding of the properties of atomic nuclei is crucial for a complete nuclear theory, for element formation, for properties of stars, and for present and future energy and defense applications. During the period of Dec. 1 2006 – Jun. 30, 2012, the UNEDF collaboration carried out a comprehensive study of all nuclei, based on the most accurate knowledge of the strong nuclear interaction, the most reliable theoretical approaches, the most advanced algorithms, and extensive computational resources, with a view towards scaling to the petaflop platforms and beyond. Until recently such an undertaking was hard to imagine, and even at the present time such an ambitious endeavor would be far beyond what a single researcher or a traditional research group could carry out. The UNEDF SciDAC project has developed several key computational codes and algorithms for reaching the goal of solving the nuclear quantum many-body problem throughout the chart of nuclei. Without such developments, scientific progress would not be possible. In addition the UNEDF SciDAC successfully applied these developments to solve many forefront research problems.

  14. Building up the nucleus: nuclear organization in the establishment of totipotency and pluripotency during mammalian development

    Science.gov (United States)

    Borsos, Máté; Torres-Padilla, Maria-Elena

    2016-01-01

    In mammals, epigenetic reprogramming, the acquisition and loss of totipotency, and the first cell fate decision all occur within a 3-d window after fertilization from the one-cell zygote to the formation of the blastocyst. These processes are poorly understood in molecular detail, yet this is an essential prerequisite to uncover principles of stem cells, chromatin biology, and thus regenerative medicine. A unique feature of preimplantation development is the drastic genome-wide changes occurring to nuclear architecture. From studying somatic and in vitro cultured embryonic stem cells (ESCs) it is becoming increasingly established that the three-dimensional (3D) positions of genomic loci relative to each other and to specific compartments of the nucleus can act on the regulation of gene expression, potentially driving cell fate. However, the functionality, mechanisms, and molecular characteristics of the changes in nuclear organization during preimplantation development are only now beginning to be unraveled. Here, we discuss the peculiarities of nuclear compartments and chromatin organization during mammalian preimplantation development in the context of the transition from totipotency to pluripotency. PMID:26980186

  15. STABILIZING GLASS BONDED WASTE FORMS CONTAINING FISSION PRODUCTS SEPARATED FROM SPENT NUCLEAR FUEL

    Energy Technology Data Exchange (ETDEWEB)

    Kenneth J. Bateman; Charles W. Solbrig

    2008-07-01

    A model has been developed to represent the stresses developed when a molten, glass-bonded brittle cylinder (used to store nuclear material) is cooled from high temperature to working temperature. Large diameter solid cylinders are formed by heating glass or glass-bonded mixtures (mixed with nuclear waste) to high temperature (915°C). These cylinders must be cooled as the final step in preparing them for storage. Fast cooling time is desirable for production; however, if cooling is too fast, the cylinder can crack into many pieces. To demonstrate the capability of the model, cooling rate cracking data were obtained on small diameter (7.8 cm diameter) glass-only cylinders. The model and experimental data were combined to determine the critical cooling rate which separates the non-cracking stable glass region from the cracked, non-stable glass regime. Although the data have been obtained so far only on small glass-only cylinders, the data and model were used to extrapolate the critical-cooling rates for large diameter ceramic waste form (CWF) cylinders. The extrapolation estimates long term cooling requirements. While a 52-cm diameter cylinder (EBR-II-waste size) can be cooled to 100°C in 70 hours without cracking, a 181.5-cm diameter cylinder (LWR waste size) requires 35 days to cool to 100°C. These cooling times are long enough that verification of these estimates are required so additional experiments are planned on both glass only and CWF material.

  16. Evaluation of nitrogen containing reducing agents for the corrosion control of materials relevant to nuclear reactors

    Energy Technology Data Exchange (ETDEWEB)

    Kumar, Padma S. [Water and Steam Chemistry Division, BARC Facilities, Kalpakkam, Tamilnadu (India); Mohan, D. [Department of Chemistry, Anna University, Chennai, Tamilnadu (India); Chandran, Sinu; Rajesh, Puspalata; Rangarajan, S. [Water and Steam Chemistry Division, BARC Facilities, Kalpakkam, Tamilnadu (India); Velmurugan, S., E-mail: svelu@igcar.gov.in [Water and Steam Chemistry Division, BARC Facilities, Kalpakkam, Tamilnadu (India)

    2017-02-01

    Materials undergo enhanced corrosion in the presence of oxidants in aqueous media. Usually, hydrogen gas or water soluble reducing agents are used for inhibiting corrosion. In the present study, the feasibility of using alternate reducing agents such as hydrazine, aqueous ammonia, and hydroxylamine that can stay in the liquid phase was investigated. A comparative study of corrosion behavior of the structural materials of the nuclear reactor viz. carbon steel (CS), stainless steel (SS-304 LN), monel-400 and incoloy-800 in the oxidizing and reducing conditions was also made. In nuclear industry, the presence of radiation field adds to the corrosion problems. The radiolysis products of water such as oxygen and hydrogen peroxide create an oxidizing environment that enhances the corrosion. Electrochemical studies at 90 °C showed that the reducing agents investigated were efficient in controlling corrosion processes in the presence of oxygen and hydrogen peroxide. Evaluation of thermal stability of hydrazine and its effect on corrosion potential of SS-304 LN were also investigated in the temperature range of 200–280 °C. The results showed that the thermal decomposition of hydrazine followed a first order kinetics. Besides, a change in electrochemical corrosion potential (ECP) was observed from −0.4 V (Vs SHE) to −0.67 V (Vs SHE) on addition of 5 ppm of hydrazine at 240 °C. Investigations were also made to understand the distribution behavior of hydrogen peroxide and hydrazine in water-steam phases and it was found that both the phases showed identical behavior. - Highlights: • Hydrazine was found to be a promising reducing agent for oxidant control. • In presence of hydrazine corrosion potential of SS304 LN was well below −230 mV. • SS304LN could be protected from IGSCC by hydrazine addition. • Thermal and radiation stability of hydrazine at 285 °C was found satisfactory.

  17. STUDIES OF MAIN CHAIN DYNAMICS OF FLUORINE-CONTAINING IONOMERS BY CARBON-13 NUCLEAR MAGNETIC RELAXATION

    Institute of Scientific and Technical Information of China (English)

    YANG Yanwu; WANG Dehua; QIU Jianqing; QIAN Baogong; WANG Hongzuo

    1992-01-01

    The carbon-13 spin-spin relaxation times of fluorine-containing ionomers are measured and motional correlation times τ0 and τd are calculated by using VJGM model. The results show that the motions of polymer main chain in ionomers become more difficult with increasing of ionization degree and contents of functional group, and depend on the fine structures and stability of ionic microdomains.

  18. Challenges in Nuclear Structure Theory

    CERN Document Server

    Nazarewicz, Witold

    2016-01-01

    The goal of nuclear structure theory is to build a comprehensive microscopic framework in which properties of nuclei and extended nuclear matter, and nuclear reactions and decays can all be consistently described. Due to novel theoretical concepts, breakthroughs in the experimentation with rare isotopes, increased exchange of ideas across different research areas, and the progress in computer technologies and numerical algorithms, nuclear theorists have been quite successful in solving various bits and pieces of the nuclear many-body puzzle and the prospects are exciting. This article contains a brief, personal perspective on the status of the field.

  19. Prediction of hydrogen concentration in nuclear power plant containment under severe accidents using cascaded fuzzy neural networks

    Energy Technology Data Exchange (ETDEWEB)

    Choi, Geon Pil; Kim, Dong Yeong; Yoo, Kwae Hwan; Na, Man Gyun, E-mail: magyna@chosun.ac.kr

    2016-04-15

    Highlights: • We present a hydrogen-concentration prediction method in an NPP containment. • The cascaded fuzzy neural network (CFNN) is used in this prediction model. • The CFNN model is much better than the existing FNN model. • This prediction can help prevent severe accidents in NPP due to hydrogen explosion. - Abstract: Recently, severe accidents in nuclear power plants (NPPs) have attracted worldwide interest since the Fukushima accident. If the hydrogen concentration in an NPP containment is increased above 4% in atmospheric pressure, hydrogen combustion will likely occur. Therefore, the hydrogen concentration must be kept below 4%. This study presents the prediction of hydrogen concentration using cascaded fuzzy neural network (CFNN). The CFNN model repeatedly applies FNN modules that are serially connected. The CFNN model was developed using data on severe accidents in NPPs. The data were obtained by numerically simulating the accident scenarios using the MAAP4 code for optimized power reactor 1000 (OPR1000) because real severe accident data cannot be obtained from actual NPP accidents. The root-mean-square error level predicted by the CFNN model is below approximately 5%. It was confirmed that the CFNN model could accurately predict the hydrogen concentration in the containment. If NPP operators can predict the hydrogen concentration in the containment using the CFNN model, this prediction can assist them in preventing a hydrogen explosion.

  20. Experiments to investigate direct containment heating phenomena with scaled models of the Calvert Cliffs Nuclear Power Plant

    Energy Technology Data Exchange (ETDEWEB)

    Blanchat, T.K.; Pilch, M.M.; Allen, M.D.

    1997-02-01

    The Surtsey Test Facility is used to perform scaled experiments simulating High Pressure Melt Ejection accidents in a nuclear power plant (NPP). The experiments investigate the effects of direct containment heating (DCH) on the containment load. The results from Zion and Surry experiments can be extrapolated to other Westinghouse plants, but predicted containment loads cannot be generalized to all Combustion Engineering (CE) plants. Five CE plants have melt dispersal flow paths which circumvent the main mitigation of containment compartmentalization in most Westinghouse PWRs. Calvert Cliff-like plant geometries and the impact of codispersed water were addressed as part of the DCH issue resolution. Integral effects tests were performed with a scale model of the Calvert Cliffs NPP inside the Surtsey test vessel. The experiments investigated the effects of codispersal of water, steam, and molten core stimulant materials on DCH loads under prototypic accident conditions and plant configurations. The results indicated that large amounts of coejected water reduced the DCH load by a small amount. Large amounts of debris were dispersed from the cavity to the upper dome (via the annular gap). 22 refs., 84 figs., 30 tabs.

  1. [Analysis of fragments of intergenome spacers of human body observed in chromosomes containing no nuclear organization].

    Science.gov (United States)

    Kupriyanova, N S; Nechvolodov, K K; Korsunenko, A V

    2014-01-01

    Tandem repetitions of rDNA provide so-called nuclear organizations (NOR). On the other hand, rDNA-structures are observed in some NOR chromosomes. It was demonstrated that, in addition to ribosome biogenesis, nucleoli provided a number of functions: cell cycle regulation, stress-induced response, transcription regulation, which often induced cell cascades. The mechanisms of the induction of rDNA segments in NOR chromosomes are obscure and require further research. About 1/3 repetitions are associated with nucleoli and SINE/Alu repetitions, homogeneous repetition, and tandem repetition. Perhaps, relative position of nucleoli and chromosomes may facilitate/prevent interaction of chromosomes with rDNA clusters. The variability of two larger repetitions in the central part of rMGS, LR1, and LR2 similar by -90% and separated by several hundred pairs of bases from each other was studied in our previous works. This work was devoted to the search for the LR1-LR2 segments in other chromosomes, characterization of their terminal tips at rupture points and genome areas of incorporation of the LR1-LR2 segments.

  2. An ARGONAUTE4-containing nuclear processing center colocalized with Cajal bodies in Arabidopsis thaliana.

    Science.gov (United States)

    Li, Carey Fei; Pontes, Olga; El-Shami, Mahmoud; Henderson, Ian R; Bernatavichute, Yana V; Chan, Simon W-L; Lagrange, Thierry; Pikaard, Craig S; Jacobsen, Steven E

    2006-07-14

    ARGONAUTE4 (AGO4) and RNA polymerase IV (Pol IV) are required for DNA methylation guided by 24 nucleotide small interfering RNAs (siRNAs) in Arabidopsis thaliana. Here we show that AGO4 localizes to nucleolus-associated bodies along with the Pol IV subunit NRPD1b; the small nuclear RNA (snRNA) binding protein SmD3; and two markers of Cajal bodies, trimethylguanosine-capped snRNAs and the U2 snRNA binding protein U2B''. AGO4 interacts with the C-terminal domain of NRPD1b, and AGO4 protein stability depends on upstream factors that synthesize siRNAs. AGO4 is also found, along with the DNA methyltransferase DRM2, throughout the nucleus at presumed DNA methylation target sites. Cajal bodies are conserved sites for the maturation of ribonucleoprotein complexes. Our results suggest a function for Cajal bodies as a center for the assembly of an AGO4/NRPD1b/siRNA complex, facilitating its function in RNA-directed gene silencing at target loci.

  3. Microwave assisted regioselective synthesis and 2D-NMR studies of novel azoles and azoloazines utilizing fluorine-containing building blocks

    Science.gov (United States)

    Al-Bogami, Abdullah S.; Saleh, Tamer S.; Mekky, Ahmed E. M.; Shaaban, Mohamed R.

    2016-10-01

    An efficient regioselective synthesis of novel azoles containing a trifluoromethyl moiety via the 1,3-dipolar cycloaddition reaction under microwave irradiation, using fluorine-containing building blocks methodology was achieved. Furthermore, these novel azoles scaffolds have been employed as the starting material in the synthesis of new azoloazines containing a trifluoromethyl group. An unambiguous structural assignment of the obtained regioisomers was determined using the 2D HMBC NMR techniques as a valuable tool.

  4. A concept map aiding the knowledge management to build the collective knowledge in a nuclear organization - a case study: IEN

    Energy Technology Data Exchange (ETDEWEB)

    Cussa, Adriana L.D. [Instituto de Engenharia Nuclear (IEN), Rio de Janeiro, RJ (Brazil). Coordenacao de Transferencia de Tecnologia e Inovacao], e-mail: adriana@ien.gov.br; Fonseca, Marcus Vinicius de A. [Universidade Federal do Rio de Janeiro (UFRJ), RJ (Brazil). Programa de Engenharia de Producao], e-mail: vfonseca@iq.ufrj.br

    2009-07-01

    This paper's proposition is to build and apply a tool to aid the knowledge management based in the intellectual capital as a value and competitiveness aggregator for a science, technology and innovation public organization in the Brazilian's nuclear area - the 'Instituto de Engenharia Nuclear - IEN'. It will be presented the hole survey of the finalistic activities and what has been considered the intellectual capital to be developed and strategically validated in its decision making practices. It was also surveyed the inter relations between the stakeholders, hereby the maintainer (CNEN), federal government, support foundations, public employees and contributors, in many different aspects focusing the continuity of research and development (R and D) activities and its results. As it is going to be detailed, the tool has been designed based in the concept map methodology using the Cmap tools software. The hole cognitive basis used here was constructed under disclosed and recognized knowledge models about knowledge, knowledge management, knowledge transference and intellectual capital. (author)

  5. Nuclear Criticality Safety of the DOT 9975 Container for237NpO2Storage, Handling, and Transport

    Energy Technology Data Exchange (ETDEWEB)

    Reed, D.A.

    2003-08-29

    Nuclear criticality safety considerations are presented to address use of the DOT 9975 shipping container for {sup 237}NpO{sub 2}. The DOT 9975 container will be used by multiple DOE sites and contractors. Various of site- and activity-specific NCS and facility safety documents are yet to be developed. For these reasons, an overall assessment of criticality safety of {sup 237}NpO{sub 2}-loaded DOT 9975 containers is considered useful to personnel involved in generating, reviewing, or approving these various documents. It is concluded that inherent container features, the loading per container (maximum of 6 kg {sup 237}Np), and the nuclear physics properties of {sup 237}NpO{sub 2} combine to preclude the potential for a nuclear criticality accident. This conclusion applies to storage, handling, and transport operations involving closed DOT 9975 packages, including credible off-normal conditions that may result in damage to packages during those operations.

  6. Detection of Special Nuclear Material in Cargo Containers Using Neutron Interrogation

    Energy Technology Data Exchange (ETDEWEB)

    Slaughter, D; Accatino, M; Bernstein, A; Candy, J; Dougan, A; Hall, J; Loshak, A; Manatt, D; Meyer, A; Pohl, B; Prussin, S; Walling, R; Weirup, D

    2003-08-01

    The goal of the work reported here is to develop a concept for an active neutron interrogation system that can detect small targets of SNM contraband in cargo containers, roughly 5 kg HEU or 1 kg Pu, even when well shielded by a thick cargo. It is essential that the concept be reliable and have low false-positive and false-negative error rates. It also must be rapid to avoid interruption of commerce, completing the analysis in minutes. A new radiation signature unique to SNM has been identified that utilizes high-energy (E{sub {gamma}} = 3-7 MeV) fission product {gamma}-ray emission. Fortunately, this high-energy {gamma}-ray signature is robust in that it is very distinct compared to normal background radiation where there is no comparable high-energy {gamma}-ray radiation. Equally important, it has a factor of 10 higher yield than delayed neutrons that are the basis of classical interrogation technique normally used on small unshielded specimens of SNM. And it readily penetrates two meters of low-Z and high-Z cargo at the expected density of {approx} 0.5 gm/cm{sup 3}. Consequently, we expect that in most cases the signature flux at the container wall is at least 2-3 decades more intense than delayed neutron signals used historically and facilitates the detection of SNM even when shielded by thick cargo. Experiments have verified this signature and its predicted characteristics. However, they revealed an important interference due to the activation of {sup 16}O by the {sup 16}O(n,p){sup 16}N reaction that produces a 6 MeV {gamma}-ray following a 7-sec {beta}-decay of the {sup 16}N. This interference is important when irradiating with 14 MeV neutrons but is eliminated when lower energy neutron sources are utilized since the reaction threshold for {sup 16}O(n,p){sup 16}N is 10 MeV. The signature {gamma}-ray fluxes exiting a thick cargo can be detected in large arrays of scintillation detectors to produce useful signal count rates of 2-4 x 10{sup 4} cps. That is high

  7. POTENTIAL FOR STRESS CORROSION CRACKING OF A537 CARBON STEEL NUCLEAR WASTE TANKS CONTAINING HIGHLY CAUSTIC SOLUTIONS

    Energy Technology Data Exchange (ETDEWEB)

    Lam, P.; Stripling, C.; Fisher, D.; Elder, J.

    2010-04-26

    The evaporator recycle streams of nuclear waste tanks may contain waste in a chemistry and temperature regime that exceeds the current corrosion control program, which imposes temperature limits to mitigate caustic stress corrosion cracking (CSCC). A review of the recent service history found that two of these A537 carbon steel tanks were operated in highly concentrated hydroxide solution at high temperature. Visual inspections, experimental testing, and a review of the tank service history have shown that CSCC has occurred in uncooled/un-stress relieved tanks of similar construction. Therefore, it appears that the efficacy of stress relief of welding residual stress is the primary corrosion-limiting mechanism. The objective of this experimental program is to test A537 carbon steel small scale welded U-bend specimens and large welded plates (30.48 x 30.38 x 2.54 cm) in a caustic solution with upper bound chemistry (12 M hydroxide and 1 M each of nitrate, nitrite, and aluminate) and temperature (125 C). These conditions simulate worst-case situations in these nuclear waste tanks. Both as-welded and stress-relieved specimens have been tested. No evidence of stress corrosion cracking was found in the U-bend specimens after 21 days of testing. The large plate test was completed after 12 weeks of immersion in a similar solution at 125 C except that the aluminate concentration was reduced to 0.3 M. Visual inspection of the plate revealed that stress corrosion cracking had not initiated from the machined crack tips in the weld or in the heat affected zone. NDE ultrasonic testing also confirmed subsurface cracking did not occur. Based on these results, it can be concluded that the environmental condition of these tests was unable to develop stress corrosion cracking within the test periods for the small welded U-bends and for the large plates, which were welded with an identical procedure as used in the construction of the actual nuclear waste tanks in the 1960s. The

  8. Do nuclear bodies in oocytes of Tenebrio molitor (Coleoptera: Polyphaga, Tenebrionidae) contain two forms of RNA polymerase II?

    Science.gov (United States)

    Bogolyubov, D; Parfenov, V

    2004-02-01

    Late vitellogenic oocytes of the mealworm beetle, Tenebrio molitor, which are transcriptionally inert, contain numerous fibrogranular nuclear bodies (NBs). Previously, we have shown that these NBs contain both unphosphorylated and phosphorylated forms of RNA polymerase II (pol II) [Tissue Cell 33 (2001) 549]. The conclusion on the presence of phosphorylated pol II was based on our immunoelectron experiments with monoclonal antibody (mAb) H5 against the phosphorylated serine-2 of the carboxy-terminal domain (CTD) of pol II. Because the specificity of mAb H5 was recently questioned by demonstration of its cross-reaction with SR-proteins [J. Struct. Biol. 140 (2002) 154], we re-examined here the occurence of pol II in T. molitor oocyte NBs using other appropriate antibodies. We confirm the presence of phosphorylated pol II in NBs using the affinity-purified polyclonal antibody against the phosphorylated CTD. Using double immunogold labeling with this antibody plus mAb 8WG16 against the unphosphorylated CTD, we confirm the presence of two forms of pol II in NBs. Additionally, the presence of pol II in NBs was verified here using mAb ARNA3 against the epitope outside CTD. We suggest that at the transcriptionally inactive stage, T. molitor oocyte NBs represent storage domains for pol II disengaged from the transcription.

  9. Nuclear Magnetic Resonance Structure of a Novel Globular Domain in RBM10 Containing OCRE, the Octamer Repeat Sequence Motif.

    Science.gov (United States)

    Martin, Bryan T; Serrano, Pedro; Geralt, Michael; Wüthrich, Kurt

    2016-01-01

    The OCtamer REpeat (OCRE) has been annotated as a 42-residue sequence motif with 12 tyrosine residues in the spliceosome trans-regulatory elements RBM5 and RBM10 (RBM [RNA-binding motif]), which are known to regulate alternative splicing of Fas and Bcl-x pre-mRNA transcripts. Nuclear magnetic resonance structure determination showed that the RBM10 OCRE sequence motif is part of a 55-residue globular domain containing 16 aromatic amino acids, which consists of an anti-parallel arrangement of six β strands, with the first five strands containing complete or incomplete Tyr triplets. This OCRE globular domain is a distinctive component of RBM10 and is more widely conserved in RBM10s across the animal kingdom than the ubiquitous RNA recognition components. It is also found in the functionally related RBM5. Thus, it appears that the three-dimensional structure of the globular OCRE domain, rather than the 42-residue OCRE sequence motif alone, confers specificity on RBM10 intermolecular interactions in the spliceosome.

  10. A prototype scintillating-fibre tracker for the cosmic-ray muon tomography of legacy nuclear waste containers

    Energy Technology Data Exchange (ETDEWEB)

    Mahon, D.F., E-mail: David.Mahon@Glasgow.ac.uk [Nuclear Physics Group, University of Glasgow, Kelvin Building, University Avenue, Glasgow, G12 8QQ Scotland (United Kingdom); Clarkson, A.; Hamilton, D.J.; Hoek, M.; Ireland, D.G. [Nuclear Physics Group, University of Glasgow, Kelvin Building, University Avenue, Glasgow, G12 8QQ Scotland (United Kingdom); Johnstone, J.R. [National Nuclear Laboratory, Central Laboratory, Sellafield, Seascale, Cumbria, CA20 1PG England (United Kingdom); Kaiser, R.; Keri, T.; Lumsden, S.; McKinnon, B.; Murray, M.; Nutbeam-Tuffs, S. [Nuclear Physics Group, University of Glasgow, Kelvin Building, University Avenue, Glasgow, G12 8QQ Scotland (United Kingdom); Shearer, C.; Staines, C. [National Nuclear Laboratory, Central Laboratory, Sellafield, Seascale, Cumbria, CA20 1PG England (United Kingdom); Yang, G. [Nuclear Physics Group, University of Glasgow, Kelvin Building, University Avenue, Glasgow, G12 8QQ Scotland (United Kingdom); Zimmerman, C. [National Nuclear Laboratory, Central Laboratory, Sellafield, Seascale, Cumbria, CA20 1PG England (United Kingdom)

    2013-12-21

    Cosmic-ray muons are highly penetrative charged particles observed at sea level with a flux of approximately 1 cm{sup −2} min{sup −1}. They interact with matter primarily through Coulomb scattering which can be exploited in muon tomography to image objects within industrial nuclear waste containers. A prototype scintillating-fibre detector has been developed for this application, consisting of two tracking modules above and below the volume to be assayed. Each module comprises two orthogonal planes of 2 mm fibres. The modular configuration allows the reconstruction of the initial and scattered muon trajectories which enable the container content, with respect to atomic number Z, to be determined. Fibre signals are read out by Hamamatsu H8500 MAPMTs with two fibres coupled to each pixel via dedicated pairing schemes developed to avoid space point ambiguities and retain the high spatial resolution of the fibres. A likelihood-based image reconstruction algorithm was developed and tested using a GEANT4 simulation of the prototype system. Images reconstructed from this simulation are presented in comparison with experimental results taken with test objects. These results verify the simulation and show discrimination between the low, medium and high-Z materials imaged.

  11. 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.

  12. Reduction of (68)Ge activity containing liquid waste from (68)Ga PET chemistry in nuclear medicine and radiopharmacy by solidification.

    Science.gov (United States)

    de Blois, Erik; Chan, Ho Sze; Roy, Kamalika; Krenning, Eric P; Breeman, Wouter A P

    PET with (68)Ga from the TiO2- or SnO2- based (68)Ge/(68)Ga generators is of increasing interest for PET imaging in nuclear medicine. In general, radionuclidic purity ((68)Ge vs. (68)Ga activity) of the eluate of these generators varies between 0.01 and 0.001%. Liquid waste containing low amounts of (68)Ge activity is produced by eluting the (68)Ge/(68)Ga generators and residues from PET chemistry. Since clearance level of (68)Ge activity in waste may not exceed 10 Bq/g, as stated by European Directive 96/29/EURATOM, our purpose was to reduce (68)Ge activity in solution from >10 kBq/g to waste. Most efficient method to reduce the (68)Ge activity is by sorption of TiO2 or Fe2O3 and subsequent centrifugation. The required 10 Bq per mL level of (68)Ge activity in waste was reached by Fe2O3 logarithmically, whereas with TiO2 asymptotically. The procedure with Fe2O3 eliminates ≥90% of the (68)Ge activity per treatment. Eventually, to simplify the processing a recirculation system was used to investigate (68)Ge activity sorption on TiO2, Fe2O3 or Zeolite. Zeolite was introduced for its high sorption at low pH, therefore (68)Ge activity containing waste could directly be used without further interventions. (68)Ge activity containing liquid waste at different HCl concentrations (0.05-1.0 M HCl), was recirculated at 1 mL/min. With Zeolite in the recirculation system, (68)Ge activity showed highest sorption.

  13. Between German phase-out and Chinese new-build rally. The situation of the nuclear industry worldwide five years after Fukushima

    Energy Technology Data Exchange (ETDEWEB)

    Stoll, Uwe [AREVA GmbH, Erlangen (Germany). Engineering and Projects

    2016-07-01

    Fukushima was a turning point for the nuclear industry, especially in Japan and in Germany, but also in other European countries and worldwide. Plants were shut down in Japan and Germany, new-build projects were postponed, and stress tests were carried out in most of the countries operating nuclear power plants. Five years later, the time has come to draw a picture of the impact of Fukushima on the nuclear industry. Japan has started to bring its nuclear capacity back online after implementing a comprehensive retrofit program. In most of the international markets, lifetime extensions of up to 60 years are on the agenda while the US is even starting to discuss operational lifetimes of 80 years. This trend brings a need for more upgrade projects.

  14. Simulations and imaging algorithm development for a cosmic ray muon tomography system for the detection of special nuclear material in transport containers

    Energy Technology Data Exchange (ETDEWEB)

    Jewett, C.; Anghel, V.N.P. [Atomic Energy of Canada Limited, Chalk River, Ontario (Canada); Armitage, J.; Boudjemline, K.; Botte, J. [Carleton Univ., Dept. of Physics, Ottawa, Ontario (Canada); Bryman, D. [Advanced Applied Physics Solutions, Vancouver, British Columbia (Canada); Univ. of British Columbia, Vancouver, British Columbia (Canada); Bueno, J. [Advanced Applied Physics Solutions, Vancouver, British Columbia (Canada); Charles, E. [Canada Border Services Agency, Ottawa, Ontario (Canada); Cousins, T. [International Safety Research, Ottawa, Ontario (Canada); Didsbury, R. [Atomic Energy of Canada Limited, Chalk River, Ontario (Canada); Erhardt, L. [Defence Research and Development Canada, Ottawa, Ontario (Canada); Erlandson, A. [Carleton Univ., Dept. of Physics, Ottawa, Ontario (Canada); Gallant, G. [Canada Border Services Agency, Ottawa, Ontario (Canada); Jason, A. [Los Alamos National Laboratory, Los Alamos (United States); Jonkmans, G. [Atomic Energy of Canada Limited, Chalk River, Ontario (Canada); Liu, Z. [Advanced Applied Physics Solutions, Vancouver, British Columbia (Canada); Univ. of British Columbia, Vancouver, British Columbia (Canada); McCall, M.; Noel, S. [International Safety Research, Ottawa, Ontario (Canada); Oakham, F.G. [Carleton Univ., Dept. of Physics, Ottawa, Ontario (Canada); TRIUMF, Vancouver, British Columbia, (Canada); Ong, D.; Stocki, T. [Health Canada, Ottawa, Ontario (Canada); Thompson, M. [Atomic Energy of Canada Limited, Chalk River, Ontario (Canada); Waller, D. [Defence Research and Development Canada, Ottawa, Ontario (Canada)

    2011-07-01

    The Cosmic Ray Inspection and Passive Tomography (CRIPT) collaboration is developing a cosmic ray muon tomography system to identify Special Nuclear Materials (SNM) in cargo containers. In order to gauge the viability of the technique, and to determine the best detector type, GEANT4 was used to simulate the passage of cosmic ray muons through a cargo container. The scattering density estimation (SDE) algorithm was developed and tested with data from these simulations to determine how well it could reconstruct the interior of a container. The simulation results revealed the ability of cosmic ray muon tomography techniques to image spheres of lead-shielded Special Nuclear Materials (SNM), such as uranium or plutonium, in a cargo container, containing a cargo of granite slabs. (author)

  15. ‘Geo’chemical research: A key building block for nuclear waste disposal safety cases

    Science.gov (United States)

    Altmann, Scott

    2008-12-01

    Disposal of high level radioactive waste in deep underground repositories has been chosen as solution by several countries. Because of the special status this type waste has in the public mind, national implementation programs typically mobilize massive R&D efforts, last decades and are subject to extremely detailed and critical social-political scrutiny. The culminating argument of each program is a 'Safety Case' for a specific disposal concept containing, among other elements, the results of performance assessment simulations whose object is to model the release of radionuclides to the biosphere. Public and political confidence in performance assessment results (which generally show that radionuclide release will always be at acceptable levels) is based on their confidence in the quality of the scientific understanding in the processes included in the performance assessment model, in particular those governing radionuclide speciation and mass transport in the geological host formation. Geochemistry constitutes a core area of research in this regard. Clay-mineral rich formations are the subjects of advanced radwaste programs in several countries (France, Belgium, Switzerland…), principally because of their very low permeabilities and demonstrated capacities to retard by sorption most radionuclides. Among the key processes which must be represented in performance assessment models are (i) radioelement speciation (redox state, speciation, reactions determining radionuclide solid-solution partitioning) and (ii) diffusion-driven transport. The safety case must therefore demonstrate a detailed understanding of the physical-chemical phenomena governing the effects of these two aspects, for each radionuclide, within the geological barrier system. A wide range of coordinated (and internationally collaborated) research has been, and is being, carried out in order to gain the detailed scientific understanding needed for constructing those parts of the Safety Case

  16. 'Geo'chemical research: a key building block for nuclear waste disposal safety cases.

    Science.gov (United States)

    Altmann, Scott

    2008-12-12

    Disposal of high level radioactive waste in deep underground repositories has been chosen as solution by several countries. Because of the special status this type waste has in the public mind, national implementation programs typically mobilize massive R&D efforts, last decades and are subject to extremely detailed and critical social-political scrutiny. The culminating argument of each program is a 'Safety Case' for a specific disposal concept containing, among other elements, the results of performance assessment simulations whose object is to model the release of radionuclides to the biosphere. Public and political confidence in performance assessment results (which generally show that radionuclide release will always be at acceptable levels) is based on their confidence in the quality of the scientific understanding in the processes included in the performance assessment model, in particular those governing radionuclide speciation and mass transport in the geological host formation. Geochemistry constitutes a core area of research in this regard. Clay-mineral rich formations are the subjects of advanced radwaste programs in several countries (France, Belgium, Switzerland...), principally because of their very low permeabilities and demonstrated capacities to retard by sorption most radionuclides. Among the key processes which must be represented in performance assessment models are (i) radioelement speciation (redox state, speciation, reactions determining radionuclide solid-solution partitioning) and (ii) diffusion-driven transport. The safety case must therefore demonstrate a detailed understanding of the physical-chemical phenomena governing the effects of these two aspects, for each radionuclide, within the geological barrier system. A wide range of coordinated (and internationally collaborated) research has been, and is being, carried out in order to gain the detailed scientific understanding needed for constructing those parts of the Safety Case

  17. 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

    Highlights: • Three dimensional finite element modeling of a Nuclear Power Plant (NPP) building founded on soil is described. • A simplified technique to consider degraded stiffness of concrete members in seismic analysis of NPP buildings is presented. • The effect of subsurface profiles on the seismic response of a NPP building is investigated. - Abstract: This study describes three-dimensional (3-D) finite element (FE) modeling and seismic Soil-Structure Interaction (SSI) analysis of a Nuclear Power Plant (NPP) Diesel Generator Building (DGB) that is founded on soil in degraded concrete stiffness condition. A new technique is presented that uses two horizontal and vertical FE models to consider the concrete stiffness reduction of NPP buildings subjected to orthogonal ground motion excitations, in which appropriate stiffness reduction factors, based on the input motion orientation, are applied. Seismic SSI analysis is performed for each model separately, and dynamic responses are calculated in the three global directions. The results of the analysis for the two FE models are then combined, using the square-root-of-the-sum-of-squares (SRSS) combination rule. A sensitivity analysis is also performed to investigate the subsurface profile effect on the In-Structure (acceleration) Response Spectra (ISRS) of the building when subjected to site-specific Foundation Input Response Spectra (FIRS) that exhibit high spectral amplifications in the high-frequency range. The sensitivity analysis considers three strain-compatible subsurface profiles that represent Lower-Bound (LB), Best-Estimate (BE), and Upper-Bound (UB) conditions at the DGB site. The sensitivity analysis results indicate that the seismic response of the DGB founded on soil highly depends on the subsurface profile; i.e., each of the LB, BE, and UB subsurface profiles can maximize building seismic response when subjected to FIRS that exhibit high spectral amplifications in the high-frequency range

  18. Nuclear Magnetic Resonance Structure Shows that the Severe Acute Respiratory Syndrome Coronavirus-Unique Domain Contains a Macrodomain Fold▿

    Science.gov (United States)

    Chatterjee, Amarnath; Johnson, Margaret A.; Serrano, Pedro; Pedrini, Bill; Joseph, Jeremiah S.; Neuman, Benjamin W.; Saikatendu, Kumar; Buchmeier, Michael J.; Kuhn, Peter; Wüthrich, Kurt

    2009-01-01

    The nuclear magnetic resonance (NMR) structure of a central segment of the previously annotated severe acute respiratory syndrome (SARS)-unique domain (SUD-M, for “middle of the SARS-unique domain”) in SARS coronavirus (SARS-CoV) nonstructural protein 3 (nsp3) has been determined. SUD-M(513-651) exhibits a macrodomain fold containing the nsp3 residues 528 to 648, and there is a flexibly extended N-terminal tail with the residues 513 to 527 and a C-terminal flexible tail of residues 649 to 651. As a follow-up to this initial result, we also solved the structure of a construct representing only the globular domain of residues 527 to 651 [SUD-M(527-651)]. NMR chemical shift perturbation experiments showed that SUD-M(527-651) binds single-stranded poly(A) and identified the contact area with this RNA on the protein surface, and electrophoretic mobility shift assays then confirmed that SUD-M has higher affinity for purine bases than for pyrimidine bases. In a further search for clues to the function, we found that SUD-M(527-651) has the closest three-dimensional structure homology with another domain of nsp3, the ADP-ribose-1"-phosphatase nsp3b, although the two proteins share only 5% sequence identity in the homologous sequence regions. SUD-M(527-651) also shows three-dimensional structure homology with several helicases and nucleoside triphosphate-binding proteins, but it does not contain the motifs of catalytic residues found in these structural homologues. The combined results from NMR screening of potential substrates and the structure-based homology studies now form a basis for more focused investigations on the role of the SARS-unique domain in viral infection. PMID:19052085

  19. The Drosophila Mitochondrial Translation Elongation Factor G1 Contains a Nuclear Localization Signal and Inhibits Growth and DPP Signaling

    Science.gov (United States)

    Trivigno, Catherine; Haerry, Theodor E.

    2011-01-01

    Mutations in the human mitochondrial elongation factor G1 (EF-G1) are recessive lethal and cause death shortly after birth. We have isolated mutations in iconoclast (ico), which encodes the highly conserved Drosophila orthologue of EF-G1. We find that EF-G1 is essential during fly development, but its function is not required in every tissue. In contrast to null mutations, missense mutations exhibit stronger, possibly neomorphic phenotypes that lead to premature death during embryogenesis. Our experiments show that EF-G1 contains a secondary C-terminal nuclear localization signal. Expression of missense mutant forms of EF-G1 can accumulate in the nucleus and cause growth and patterning defects and animal lethality. We find that transgenes that encode mutant human EF-G1 proteins can rescue ico mutants, indicating that the underlying problem of the human disease is not just the loss of enzymatic activity. Our results are consistent with a model where EF-G1 acts as a retrograde signal from mitochondria to the nucleus to slow down cell proliferation if mitochondrial energy output is low. PMID:21364917

  20. In-situ removal and characterisation of uranium-containing particles from sediments surrounding the Fukushima Daiichi Nuclear Power Plant

    Science.gov (United States)

    Martin, P. G.; Griffiths, I.; Jones, C. P.; Stitt, C. A.; Davies-Milner, M.; Mosselmans, J. F. W.; Yamashiki, Y.; Richards, D. A.; Scott, T. B.

    2016-03-01

    Traditional methods to locate and subsequently study radioactive fallout particles have focused heavily on autoradiography coupled with in-situ analytical techniques. Presented here is the application of a Variable Pressure Scanning Electron Microscope with both backscattered electron and energy dispersive spectroscopy detectors, along with a micromanipulator setup and electron-hardening adhesive to isolate and remove individual particles before synchrotron radiation analysis. This system allows for a greater range of new and existing analytical techniques, at increased detail and speed, to be applied to the material. Using this method, it was possible to erform detailed energy dispersive spectroscopy and synchrotron radiation characterisation of material likely ejected from the Fukushima Daiichi Nuclear Power Plant found within a sediment sample collected from the edge of the 30 km exclusion zone. Particulate material sub-micron in maximum dimension examined during this work via energy dispersive spectroscopy was observed to contain uranium at levels between 19.68 and 28.35 weight percent, with the application of synchrotron radiation spectroscopy confirming its presence as a major constituent. With great effort and cost being devoted to the remediation of significant areas of eastern Japan affected by the incident, it is crucial to gain the greatest possible understanding of the nature of this contamination in order to inform the most appropriate clean-up response.

  1. Development and validation of a new TRNSYS type for the simulation of external building walls containing PCM

    OpenAIRE

    Kuznik, F.; Virgone, J.; Johannes, K.

    2010-01-01

    International audience; In building construction, the use of phase change materials (PCMs) allows the storage/release of energy from the solar radiation and/or internal loads. The application of such materials for lightweight construction (e.g., a wood house) makes it possible to improve thermal comfort and reduce energy consumption. However, in order to assess and optimize phase change materials included in building wall, numerical simulation is mandatory. For that purpose, a new TRNSYS Type...

  2. Land Use and Land Cover, Impervious Surface - contains polygons that represent houses, buildings, roads, driveways, sidewalks, pools, patios, parking lots, pavements, Published in 2008, 1:2400 (1in=200ft) scale, Effingham County Government.

    Data.gov (United States)

    NSGIC Local Govt | GIS Inventory — Land Use and Land Cover dataset current as of 2008. Impervious Surface - contains polygons that represent houses, buildings, roads, driveways, sidewalks, pools,...

  3. An investigation of the feasibility of building a harbor on the West coast of South America using explosive power of nuclear weapons, a preliminary report

    Energy Technology Data Exchange (ETDEWEB)

    Zodtner, H. H.

    1971-12-31

    There is an interest in discovering the various peace time uses of nuclear explosives. One of the proposals is the building of harbors. There are several ports along the west coast of South America where lighterage is necessary. This implies a need for expanded harbor facilities. The problem is to find a good location for creating a harbor, and the feasibility of accomplishing this with the use of nuclear force. Feasibility includes blast effects, radiation hazards, the number of weapons needed, and economic considerations. Economic considerations include the cost of treating a harbor of sufficient depth and area, the building of harbor facilities, and the estimated savings and advantages of the new harbor. Several meetings were held with naval personnel of the Military Liaison group at UCRL to discuss the general problems of harbors. Thirty-three different ports were given a preliminary investigation.

  4. eEF1A Mediates the Nuclear Export of SNAG-Containing Proteins via the Exportin5-Aminoacyl-tRNA Complex

    Directory of Open Access Journals (Sweden)

    José Manuel Mingot

    2013-11-01

    Full Text Available Exportin5 mediates the nuclear export of double-stranded RNAs, including pre-microRNAs, adenoviral RNAs, and tRNAs. When tRNAs are aminoacylated, the Exportin5-aminoacyl (aa-tRNA complex recruits and coexports the translation elongation factor eEF1A. Here, we show that eEF1A binds to Snail transcription factors when bound to their main target, the E-cadherin promoter, facilitating their export to the cytoplasm in association with the aa-tRNA-Exportin5 complex. Snail binds to eEF1A through the SNAG domain, a protein nuclear export signal present in several transcription factor families, and this binding is regulated by phosphorylation. Thus, we describe a nuclear role for eEF1A and provide a mechanism for protein nuclear export that attenuates the activity of SNAG-containing transcription factors.

  5. eEF1A mediates the nuclear export of SNAG-containing proteins via the Exportin5-aminoacyl-tRNA complex.

    Science.gov (United States)

    Mingot, José Manuel; Vega, Sonia; Cano, Amparo; Portillo, Francisco; Nieto, M Angela

    2013-11-14

    Exportin5 mediates the nuclear export of double-stranded RNAs, including pre-microRNAs, adenoviral RNAs, and tRNAs. When tRNAs are aminoacylated, the Exportin5-aminoacyl (aa)-tRNA complex recruits and coexports the translation elongation factor eEF1A. Here, we show that eEF1A binds to Snail transcription factors when bound to their main target, the E-cadherin promoter, facilitating their export to the cytoplasm in association with the aa-tRNA-Exportin5 complex. Snail binds to eEF1A through the SNAG domain, a protein nuclear export signal present in several transcription factor families, and this binding is regulated by phosphorylation. Thus, we describe a nuclear role for eEF1A and provide a mechanism for protein nuclear export that attenuates the activity of SNAG-containing transcription factors.

  6. Evolution of a novel subfamily of nuclear receptors with members that each contain two DNA binding domains

    Directory of Open Access Journals (Sweden)

    Hirai Hirohisa

    2007-02-01

    Full Text Available Abstract Background Nuclear receptors (NRs are important transcriptional modulators in metazoans which regulate transcription through binding to the promoter region of their target gene by the DNA binding domain (DBD and activation or repression of mRNA synthesis through co-regulators bound to the ligand binding domain (LBD. NRs typically have a single DBD with a LBD. Results Three nuclear receptors named 2DBD-NRs, were identified from the flatworm Schistosoma mansoni that each possess a novel set of two DBDs in tandem with a LBD. They represent a novel NR modular structure: A/B-DBD-DBD-hinge-LBD. The 2DBD-NRs form a new subfamily of NRs, VII. By database mining, 2DBD-NR genes from other flatworm species (Schmidtea mediterranea and Dugesia japonica, from Mollusks (Lottia gigantean and from arthropods (Daphnia pulex were also identified. All 2DBD-NRs possess a P-box sequence of CEACKK in the first DBD, which is unique to 2DBD-NRs, and a P-box sequence of CEGCKG in the second DBD. Phylogenetic analyses of both DBD and ligand binding domain sequences showed that 2DBD-NR genes originate from a common two DBD-containing ancestor gene. A single 2DBD-NR orthologue was found in Arthropoda, Platyhelminths and Mollusca. Subsequent 2DBD-NR gene evolution in Mollusks and Platyhelminths involved gene duplication. Chromosome localization of S. mansoni 2DBD-NR genes by Fluorescent in situ hybridization (FISH suggests that 2DBD-NR genes duplicated on different chromosomes in the Platyhelminths. Dimerization of Sm2DBDα indicates that 2DBD-NRs may act as homodimers, suggesting either that two repeats of a half-site are necessary for each DBD of 2DBD-NRs to bind to its target gene, or that each 2DBD-NR can recognize multiple sites. Conclusion 2DBD-NRs share a common ancestor gene which possessed an extra DBD that likely resulted from a recombination event. After the split of the Arthropods, Mollusks and Platyhelminths, 2DBD-NR underwent a recent duplication in a

  7. Nuclear Ambitions

    Institute of Scientific and Technical Information of China (English)

    2008-01-01

    China will begin to build the world’s first third-generation nuclear power plant at the Sanmen Nuclear Power Project in Sanmen City, coastal Zhejiang Province, in March 2009, accord-ing to the State Nuclear Power Technology Corp.

  8. Model of the containment building of Almaraz NPP and the system of recombiners PARs, with the GOTHIC code, for the study of the diffusion of combustible gases; Modelo del edificio de contencion de C.N. Almaraz y del sistema de recombinadores PARs, con el codigo GOTHIC, para el estudio de la difusion de gases combustibles

    Energy Technology Data Exchange (ETDEWEB)

    Garcia Gonzalez, M.; Huelamo, E.; Mazrtinez, M.; Perez, J. R.

    2014-07-01

    This paper presents the analysis of distribution of gases within the containment building carried out a simulation model with the code Thermo hydraulic GOTHIC, which has been evaluated based on passive autocatalytic recombiners gas control system. The model considers scenarios of severe accident with specific conditions that produce the most hydrogen generation rates. Intended to verify the effectiveness of the control system of gas expected to be installed in the Almaraz Nuclear power plant so that the number and location of recombiners equipment meets its function of preventing the formation of explosive atmospheres which impairs the integrity of the containment, reducing and limiting the concentration of combustible gases during the postulated accident. (Author)

  9. Participation of C.N. Vandellos II as a pilot plant in the PWROG PA-ASC-1084 project about analysis and distribution of hydrogen in the containment buildings annexes; Participacion de C. N. Vandellos II como planta piloto en el proyecto del PWROG PA-ASC-1084 sobre analisis y distribucion del hidrogeno en edificios anexos a la Contencion

    Energy Technology Data Exchange (ETDEWEB)

    Fornos Herrando, J.

    2013-07-01

    Fukushima accident has demonstrated that hydrogen outside the Containment building, due to its potential combustion or explosion, may result in loss of mitigation equipment, thus hindering the recovery of the plant. This reality has been treated in the framework of Stress Tests that are being developed at European level, and the Spanish nuclear power plants should evaluate this potential risk according to the specific design of each plant. The aim of this paper is to introduce this hydrogen problem and to present the main developments of the Vandellos II NPP experience as pilot plant in the project that PWROG is developing to analyze the potential risk of hydrogen in the Containment outbuildings.

  10. Development and validation of a new TRNSYS type for the simulation of external building walls containing PCM

    Energy Technology Data Exchange (ETDEWEB)

    Kuznik, Frederic; Virgone, Joseph; Johannes, Kevyn [Universite de Lyon, CNRS, INSA de Lyon, CETHIL, UMR 5008, F-69621 Villeurbanne, France Universite Lyon 1, F-69622 (France)

    2010-07-15

    In building construction, the use of phase change materials (PCMs) allows the storage/release of energy from the solar radiation and/or internal loads. The application of such materials for lightweight construction (e.g., a wood house) makes it possible to improve thermal comfort and reduce energy consumption. However, in order to assess and optimize phase change materials included in building wall, numerical simulation is mandatory. For that purpose, a new TRNSYS Type, named Type 260, is developed to model the thermal behavior of an external wall with PCM. This model is presented in this paper and validated using experimental data from the literature. (author)

  11. Identification of low molecular weight nuclear complexes containing integrase during the early stages of HIV-1 infection.

    Science.gov (United States)

    Gérard, Annabelle; Soler, Nicolas; Ségéral, Emmanuel; Belshan, Michael; Emiliani, Stéphane

    2013-02-01

    HIV-1 replication requires integration of its reverse transcribed viral cDNA into a host cell chromosome. The DNA cutting and joining reactions associated to this key step are catalyzed by the viral protein integrase (IN). In infected cells, IN binds the viral cDNA, together with viral and cellular proteins, to form large nucleoprotein complexes. However, the dynamics of IN complexes formation is still poorly understood. Here, we characterized IN complexes during the early stages of T-lymphocyte infection. We found that following viral entry into the host cell, IN was rapidly targeted to proteasome-mediated degradation. Interactions between IN and cellular cofactors LEDGF/p75 and TNPO3 were detected as early as 6 h post-infection. Size exclusion chromatography of infected cell extracts revealed distinct IN complexes in vivo. While at 2 h post-infection the majority of IN eluted within a high molecular weight complex competent for integration (IN complex I), IN was also detected in a low molecular weight complex devoid of full-length viral cDNA (IN complex II, ~440 KDa). At 6 h post-infection the relative proportion of IN complex II increased. Inhibition of reverse transcription or integration did not alter the elution profile of IN complex II in infected cells. However, in cells depleted for LEDGF/p75 IN complex II shifted to a lower molecular weight complex (IN complex III, ~150 KDa) containing multimers of IN. Notably, cell fractionation experiments indicated that both IN complex II and III were exclusively nuclear. Finally, IN complex II was not detected in cells infected with a virus harboring a mutated IN defective for LEDGF/p75 interaction and tetramerization. Our findings indicate that, shortly after viral entry, a significant portion of DNA-free IN that is distinct from active pre-integration complexes accumulates in the nucleus.

  12. Identification of low molecular weight nuclear complexes containing integrase during the early stages of HIV-1 infection

    Directory of Open Access Journals (Sweden)

    Gérard Annabelle

    2013-02-01

    Full Text Available Abstract Background HIV-1 replication requires integration of its reverse transcribed viral cDNA into a host cell chromosome. The DNA cutting and joining reactions associated to this key step are catalyzed by the viral protein integrase (IN. In infected cells, IN binds the viral cDNA, together with viral and cellular proteins, to form large nucleoprotein complexes. However, the dynamics of IN complexes formation is still poorly understood. Results Here, we characterized IN complexes during the early stages of T-lymphocyte infection. We found that following viral entry into the host cell, IN was rapidly targeted to proteasome-mediated degradation. Interactions between IN and cellular cofactors LEDGF/p75 and TNPO3 were detected as early as 6 h post-infection. Size exclusion chromatography of infected cell extracts revealed distinct IN complexes in vivo. While at 2 h post-infection the majority of IN eluted within a high molecular weight complex competent for integration (IN complex I, IN was also detected in a low molecular weight complex devoid of full-length viral cDNA (IN complex II, ~440 KDa. At 6 h post-infection the relative proportion of IN complex II increased. Inhibition of reverse transcription or integration did not alter the elution profile of IN complex II in infected cells. However, in cells depleted for LEDGF/p75 IN complex II shifted to a lower molecular weight complex (IN complex III, ~150 KDa containing multimers of IN. Notably, cell fractionation experiments indicated that both IN complex II and III were exclusively nuclear. Finally, IN complex II was not detected in cells infected with a virus harboring a mutated IN defective for LEDGF/p75 interaction and tetramerization. Conclusions Our findings indicate that, shortly after viral entry, a significant portion of DNA–free IN that is distinct from active pre-integration complexes accumulates in the nucleus.

  13. Three-dimensional all-speed CFD code for safety analysis of nuclear reactor containment: Status of GASFLOW parallelization, model development, validation and application

    Energy Technology Data Exchange (ETDEWEB)

    Xiao, Jianjun, E-mail: jianjun.xiao@kit.edu [Institute of Nuclear and Energy Technologies, Karlsruhe Institute of Technology, P.O. Box 3640, 76021 Karlsruhe (Germany); Travis, John R., E-mail: jack_travis@comcast.com [Engineering and Scientific Software Inc., 3010 Old Pecos Trail, Santa Fe, NM 87505 (United States); Royl, Peter, E-mail: peter.royl@partner.kit.edu [Institute of Nuclear and Energy Technologies, Karlsruhe Institute of Technology, P.O. Box 3640, 76021 Karlsruhe (Germany); Necker, Gottfried, E-mail: gottfried.necker@partner.kit.edu [Institute of Nuclear and Energy Technologies, Karlsruhe Institute of Technology, P.O. Box 3640, 76021 Karlsruhe (Germany); Svishchev, Anatoly, E-mail: anatoly.svishchev@kit.edu [Institute of Nuclear and Energy Technologies, Karlsruhe Institute of Technology, P.O. Box 3640, 76021 Karlsruhe (Germany); Jordan, Thomas, E-mail: thomas.jordan@kit.edu [Institute of Nuclear and Energy Technologies, Karlsruhe Institute of Technology, P.O. Box 3640, 76021 Karlsruhe (Germany)

    2016-05-15

    Highlights: • 3-D scalable semi-implicit pressure-based CFD code for containment safety analysis. • Robust solution algorithm valid for all-speed flows. • Well validated and widely used CFD code for hydrogen safety analysis. • Code applied in various types of nuclear reactor containments. • Parallelization enables high-fidelity models in large scale containment simulations. - Abstract: GASFLOW is a three dimensional semi-implicit all-speed CFD code which can be used to predict fluid dynamics, chemical kinetics, heat and mass transfer, aerosol transportation and other related phenomena involved in postulated accidents in nuclear reactor containments. The main purpose of the paper is to give a brief review on recent GASFLOW code development, validations and applications in the field of nuclear safety. GASFLOW code has been well validated by international experimental benchmarks, and has been widely applied to hydrogen safety analysis in various types of nuclear power plants in European and Asian countries, which have been summarized in this paper. Furthermore, four benchmark tests of a lid-driven cavity flow, low Mach number jet flow, 1-D shock tube and supersonic flow over a forward-facing step are presented in order to demonstrate the accuracy and wide-ranging capability of ICE’d ALE solution algorithm for all-speed flows. GASFLOW has been successfully parallelized using the paradigms of Message Passing Interface (MPI) and domain decomposition. The parallel version, GASFLOW-MPI, adds great value to large scale containment simulations by enabling high-fidelity models, including more geometric details and more complex physics. It will be helpful for the nuclear safety engineers to better understand the hydrogen safety related physical phenomena during the severe accident, to optimize the design of the hydrogen risk mitigation systems and to fulfill the licensing requirements by the nuclear regulatory authorities. GASFLOW-MPI is targeting a high

  14. Managing Asbestos in Place: A Building Owner's Guide to Operations and Maintenance Programs for Asbestos-Containing Materials.

    Science.gov (United States)

    Environmental Protection Agency, Washington, DC.

    Instructions for building owners on the selection and application of appropriate asbestos control and abatement actions are presented in this guidebook. Chapter 1 offers background information on the asbestos problem. Chapter 2 describes the purpose and scope of an operations and maintenance (O&M) program. The third chapter discusses planning…

  15. 340 Facility secondary containment and leak detection

    Energy Technology Data Exchange (ETDEWEB)

    Bendixsen, R.B.

    1995-01-31

    This document presents a preliminary safety evaluation for the 340 Facility Secondary Containment and Leak Containment system, Project W-302. Project W-302 will construct Building 340-C which has been designed to replace the current 340 Building and vault tank system for collection of liquid wastes from the Pacific Northwest Laboratory buildings in the 300 Area. This new nuclear facility is Hazard Category 3. The vault tank and related monitoring and control equipment are Safety Class 2 with the remainder of the structure, systems and components as Safety Class 3 or 4.

  16. Analysis of Dust Samples Collected from an Unused Spent Nuclear Fuel Interim Storage Container at Hope Creek, Delaware.

    Energy Technology Data Exchange (ETDEWEB)

    Bryan, Charles R. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Enos, David [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)

    2015-03-01

    In July, 2014, the Electric Power Research Institute and industry partners sampled dust on the surface of an unused canister that had been stored in an overpack at the Hope Creek Nuclear Generating Station for approximately one year. The foreign material exclusion (FME) cover that had been on the top of the canister during storage, and a second recently - removed FME cover, were also sampled. This report summarizes the results of analyses of dust samples collected from the unused Hope Creek canister and the FME covers. Both wet and dry samples of the dust/salts were collected, using SaltSmart(TM) sensors and Scotch - Brite(TM) abrasive pads, respectively. The SaltSmart(TM) samples were leached and the leachate analyzed chemically to determine the composition and surface load per unit area of soluble salts present on the canister surface. The dry pad samples were analyzed by X-ray fluorescence and by scanning electron microscopy to determine dust texture and mineralogy; and by leaching and chemical analysis to deter mine soluble salt compositions. The analyses showed that the dominant particles on the canister surface were stainless steel particles, generated during manufacturing of the canister. Sparse environmentally - derived silicates and aluminosilicates were also present. Salt phases were sparse, and consisted of mostly of sulfates with rare nitrates and chlorides. On the FME covers, the dusts were mostly silicates/aluminosilicates; the soluble salts were consistent with those on the canister surface, and were dominantly sulfates. It should be noted that the FME covers were w ashed by rain prior to sampling, which had an unknown effect of the measured salt loads and compositions. Sulfate salts dominated the assemblages on the canister and FME surfaces, and in cluded Ca - SO4 , but also Na - SO4 , K - SO4 , and Na - Al - SO4 . It is likely that these salts were formed by particle - gas conversion reactions, either

  17. Detection of collagen triple helix repeat containing-1 and nuclear factor (erythroid-derived 2-like 3 in colorectal cancer

    Directory of Open Access Journals (Sweden)

    Palma Marco

    2012-02-01

    Full Text Available Abstract Background Collagen Triple Helix Repeat Containing-1 (CTHRC1 and Nuclear factor (erythroid-derived 2-like 3 (NFE2L3 may be useful biomarker candidates for the diagnosis of colorectal cancer (CRC since they have shown an increase messenger RNA transcripts (mRNA expression level in adenomas and colorectal tumours when compared to normal tissues. Methods To evaluate CTHRC1 and NFE2L3 as cancer biomarkers, it was generated and characterised several novel specific polyclonal antibodies (PAb, monoclonal antibodies (MAbs and soluble Fab fragments (sFabs against recombinant CTHRC1 and NFE2L3 proteins, which were obtained from different sources, including a human antibody library and immunised animals. The antibodies and Fab fragments were tested for recognition of native CTHRC1 and NFE2L3 proteins by immunoblotting analysis and enzyme-linked immunosorbent assay (ELISA in colorectal cell lines derived from tumour and cancer tissues. Results Both, antibodies and a Fab fragment showed high specificity since they recognised only their corresponding recombinant antigens, but not a panel of different unrelated- and related proteins. In Western blot analysis of CTHRC1, a monoclonal antibody designated CH21D7 was able to detect a band of the apparent molecular weight of a full-length CTHRC1 in the human colon adenocarcinoma cell line HT29. This result was confirmed by a double antibody sandwich enzyme-linked immunosorbent assay (DAS-ELISA with the monoclonal antibodies CH21D7 and CH24G2, detecting CTHRC1 in HT29 and in the colon adenocarcinoma cell line SW620. Similar experiments were performed with PAb, MAbs, and sFab against NFE2L3. The immunoblot analysis showed that the monoclonal antibody 41HF8 recognised NFE2L3 in HT29, and leukocytes. These results were verified by DAS-ELISA assay using the pairs PAb/sFab E5 and MAb 41HF8/sFab E5. Furthermore, an immunoassay for simultaneous detection of the two cancer biomarkers was developed using a

  18. Experimental study on the shrinkage properties and cracking potential of high strength concrete containing industrial by-products for nuclear power plant concrete

    Energy Technology Data Exchange (ETDEWEB)

    KIm, Baek Joong; Yi, Chong Ku [School of Civil, Environmental and Architectural Engineering, Korea University, Seoul (Korea, Republic of)

    2017-02-15

    In Korea, attempts have been made to develop high strength concrete for the safety and design life improvement of nuclear power plants. In this study, the cracking potentials of nuclear power plant-high strength concretes (NPP-HSCs) containing industrial by-products with W/B 0.34 and W/B 0.28, which are being reviewed for their application in the construction of containment structures, were evaluated through autogenous shrinkage, unrestrained drying shrinkage, and restrained drying shrinkage experiments. The cracking potentials of the NPP-HSCs with W/B 0.34 and W/B 0.28 were in the order of 0.34FA25 > 0.34FA25BFS25 > 0.34BFS50 > 0.34BFS65SF5 and 0.28FA25SF5 >> 0.28BFS65SF5 > 0.28BFS45SF5 > 0.28 FA20BFS25SF5, respectively. The cracking potentials of the seven mix proportions excluding 0.28FA25SF5 were lower than that of the existing nuclear power plant concrete; thus, the durability of a nuclear power plant against shrinkage cracking could be improved by applying the seven mix proportions with low cracking potentials.

  19. Nuclear inclusions mimicking poly(A)-binding protein nuclear 1 inclusions in a case of inclusion body myopathy associated with Paget disease of bone and frontotemporal dementia with a novel mutation in the valosin-containing protein gene.

    Science.gov (United States)

    Matsubara, Shiro; Shimizu, Toshio; Komori, Takashi; Mori-Yoshimura, Madoka; Minami, Narihiro; Hayashi, Yukiko K

    2016-07-01

    A middle-aged Japanese man presented with slowly progressive asymmetric weakness of legs and arm but had neither ptosis nor dysphagia. He had a family history of similar condition suggestive of autosomal dominant inheritance. A muscle biopsy showed mixture of neurogenic atrophy and myopathy with rimmed vacuoles. Furthermore we found intranuclear inclusions that had a fine structure mimicking that of inclusions reported in oculopharyngeal muscular dystrophy (OPMD). Immunohistochemical staining for polyadenylate-binding nuclear protein 1, which is identified within the nuclear inclusions of OPMD, demonstrated nuclear positivity in this case. However, OPMD was thought unlikely based on the clinical features and results of genetic analyses. Instead, a novel mutation in valosin-containing protein, c.376A>T (p.Ile126Phe), was revealed. A diagnosis of inclusion body myopathy associated with Paget disease of bone and frontotemporal dementia was made. This is the first report of polyadenylate-binding nuclear protein 1-positive nuclear inclusions in the muscle of this condition.

  20. Dynamic analysis of steel-concrete structure of TVO power plant containment building; Olkiluodon ydinvoimalaitoksen suojarakennuksen teraesbetonirakenteiden dynaaminen analyysi

    Energy Technology Data Exchange (ETDEWEB)

    Hakala, M. [Saanio and Riekkola Consulting Engineers, Helsinki (Finland); Karjunen, T. [Finnish Centre for Radiation and Nuclear Safety, Helsinki (Finland)

    1996-08-01

    The report presents results from a study concerning the ability of the containment to withstand the loads caused by steams explosions which are possible during a severe accident at TVO plant (BWR). In the first phase, the suitability of the engineering mechanics code (FLAC) for modelling the dynamic response of damaging steel-concrete structures was tested by post-calculating a small scale test. As a result, a new dynamic material model taking account the fracture orientation was developed. In containment calculations both the developed and the best generally accepted material model were used. The loads against the containment were obtained from a simple model for steam explosions, which allowed the impulse of the pressure load to be fixed by tuning a few parameters. The ability of the containment to withstand the pressure pulses was analysed with loads of 5, 1 0, 20, 40, 60, and 80 kPa s impulse. As a results, the area and magnitude of permanent damage together with time histories of displacement and stress at critical points are presented. The estimations on the consequences of the observed structural damages as far as the containment leak tightness and stability are concerned and presented as conclusions. (9 refs.).

  1. Generic approach for designing and implementing a passive autocatalytic recombiner PAR-system in nuclear power plant containments

    Energy Technology Data Exchange (ETDEWEB)

    Bachellerie, E. E-mail: bachelle@tecatom.fr; Arnould, F.; Auglaire, M.; Boeck, B. de; Braillard, O.; Eckardt, B.; Ferroni, F.; Moffett, R

    2003-04-01

    PARSOAR project is one of the scientific projects on hydrogen risk in nuclear power plants co-sponsored by the European Commission in the Fifth Euratom Framework Program and the Swiss government. It is one of the components of the 'Safety Accident Management' (SAM) cluster that is focusing on review of severe accident risks and on development of countermeasures for defence-in-depth. The first objective is to carry out a state-of-the-art on passive autocatalytic recombiners (PAR) to constitute a database helpful for the PAR-designers, nuclear power plant designers and utilities, and safety authorities. The second objective is to elaborate a handbook guide that defines an approach for implementing catalytic recombiners in nuclear power plants, and that proposes recommended practices to support the detailed implementation by individual nuclear actors. The third objective is to identify the needs in terms of complementary experimental qualification or computer code developments about the hydrogen risk in nuclear power plants. It is also recommended that future experimental tests and numerical modelling should concentrate on the remaining issues of (a) lowering of existing uncertainties about hydrogen sources as core reflood or the reactions between boron carbide and steam or uranium and steam, (b) completing the experimental qualification of catalytic recombiners for existing and future nuclear power plant applications, and (c) performing well-qualified couplings between computational fluid dynamics computer codes and numerical models simulating PAR-behaviour (thanks to some global and well-instrumented experiments reproducing a complete reference accident sequence in presence of catalytic recombiners). Such areas to be considered for future work could be integrated in the scope of a European hydrogen network of excellence, in the framework of the Sixth Euratom Framework Program (2002-2006)

  2. The Design and Performance of a Scintillating-Fibre Tracker for the Cosmic-ray Muon Tomography of Legacy Nuclear Waste Containers

    CERN Document Server

    Clarkson, Anthony; Hoek, Matthias; Ireland, David G; Johnstone, Russell; Kaiser, Ralf; Keri, Tibor; Lumsden, Scott; Mahon, David F; McKinnon, Bryan; Murray, Morgan; Nutbeam-Tuffs, Sian; Shearer, Craig; Staines, Cassie; Yang, Guangliang; Zimmerman, Colin

    2013-01-01

    Tomographic imaging techniques using the Coulomb scattering of cosmic-ray muons are increasingly being exploited for the non-destructive assay of shielded containers in a wide range of applications. One such application is the characterisation of legacy nuclear waste materials stored within industrial containers. The design, assembly and performance of a prototype muon tomography system developed for this purpose are detailed in this work. This muon tracker comprises four detection modules, each containing orthogonal layers of Saint-Gobain BCF-10 2mm-pitch plastic scintillating fibres. Identification of the two struck fibres per module allows the reconstruction of the incoming and Coulomb-scattered muon trajectories. These allow the container content, with respect to the atomic number Z of the scattering material, to be determined through reconstruction of the scattering location and magnitude. On each detection layer, the light emitted by the fibre is detected by a single Hamamatsu H8500 MAPMT with two fibre...

  3. A resin composite material containing an eugenol derivative for intracanal post cementation and core build-up restoration.

    Science.gov (United States)

    Almaroof, A; Rojo, L; Mannocci, F; Deb, S

    2016-02-01

    To formulate and evaluate new dual cured resin composite based on the inclusion of eugenyl methacrylate monomer (EgMA) with Bis-GMA/TEGDMA resin systems for intracanal post cementation and core build-up restoration of endodontically treated teeth. EgMA was synthesized and incorporated at 5% (BTEg5) or 10% (BTEg10) into dual-cure formulations. Curing properties, viscosity, Tg, radiopacity, static and dynamic mechanical properties of the composites were determined and compared with Clearfil™DC Core-Plus, a commercial dual-cure, two-component composite. Statistical analysis of the data was performed with ANOVA and the Tukey's post-hoc test. The experimental composites were successfully prepared, which exhibited excellent curing depths of 4.9, 4.7 and 4.2 mm for BTEg0, BTEg5 and BTEg10 respectively, which were significantly higher than Clearfil™DC. However, the inclusion of EgMA initially led to a lower degree of cure, which increased when measured at 24 h with values comparable to formulations without EgMA, indicating post-curing. The inclusion of EgMA also lowered the polymerization exotherm thereby reducing the potential of thermal damage to host tissue. Both thermal and viscoelastic analyses confirmed the ability of the monomer to reduce the stiffness of the composites by forming a branched network. The compressive strength of BTEg5 was significantly higher than the control whilst flexural strength increased significantly from 95.9 to 114.8 MPa (BTEg5) and 121.9 MPa (BTEg10). Radiopacity of the composites was equivalent to ∼3 mm Al allowing efficient diagnosis. The incorporation of EgMA within polymerizable formulations provides a novel approach to prepare reinforced resin composite material for intracanal post cementation and core build-up and the potential to impart antibacterial properties of eugenol to endodontic restorations. Copyright © 2015 Academy of Dental Materials. Published by Elsevier Ltd. All rights reserved.

  4. Advanced Borobond™ Shields for Nuclear Materials Containment and Borobond™ Immobilization of Volatile Fission Products - Final CRADA Report

    Energy Technology Data Exchange (ETDEWEB)

    Wagh, Arun S. [Argonne National Lab. (ANL), Argonne, IL (United States)

    2016-05-19

    Borobond is a company-proprietary material developed by the CRADA partner in collaboration with Argonne, and is based on Argonne's Ceramicrete technology. It is being used by DOE for nuclear materials safe storage, and Boron Products, LLC is the manufacturer and supplier of Borobond.

  5. Proceedings of the second US Department of Energy environmental control symposium. Volume 2. Nuclear energy, conservation, and solar energy

    Energy Technology Data Exchange (ETDEWEB)

    None

    1980-06-01

    These proceedings document the presentations given at the Second Environmental Control Symposium. Symposium presentations highlighted environmental control activities which span the entire DOE. Volume II contains papers relating to: environmental control aspects of nuclear energy use and development; nuclear waste management; renewable energy sources; transportation and building conservation (fuel economy, gasohol, building standards, and industry); and geothermal energy, power transmission, and energy storage. (DMC)

  6. Direct containment heating models in the CONTAIN code

    Energy Technology Data Exchange (ETDEWEB)

    Washington, K.E.; Williams, D.C.

    1995-08-01

    The potential exists in a nuclear reactor core melt severe accident for molten core debris to be dispersed under high pressure into the containment building. If this occurs, the set of phenomena that result in the transfer of energy to the containment atmosphere and its surroundings is referred to as direct containment heating (DCH). Because of the potential for DCH to lead to early containment failure, the U.S. Nuclear Regulatory Commission (USNRC) has sponsored an extensive research program consisting of experimental, analytical, and risk integration components. An important element of the analytical research has been the development and assessment of direct containment heating models in the CONTAIN code. This report documents the DCH models in the CONTAIN code. DCH models in CONTAIN for representing debris transport, trapping, chemical reactions, and heat transfer from debris to the containment atmosphere and surroundings are described. The descriptions include the governing equations and input instructions in CONTAIN unique to performing DCH calculations. Modifications made to the combustion models in CONTAIN for representing the combustion of DCH-produced and pre-existing hydrogen under DCH conditions are also described. Input table options for representing the discharge of debris from the RPV and the entrainment phase of the DCH process are also described. A sample calculation is presented to demonstrate the functionality of the models. The results show that reasonable behavior is obtained when the models are used to predict the sixth Zion geometry integral effects test at 1/10th scale.

  7. Purification and characterization of a simple ribonucleoprotein particle containing small nucleoplasmic RNAs (snRNP) as a subset of RNP containing heterogenous nuclear RNA (hnRNP) from HeLa cells.

    Science.gov (United States)

    Brunel, C; Widada, J S; Lelay, M N; Jeanteur, P; Liautard, J P

    1981-02-25

    A ribonucleoprotein complex whose RNA complement consists exclusively of small nuclear RNA species (snRNA) has been purified from particles containing heterogenous nuclear RNA (hnRNP) from HeLa cells. This was accomplished by taking advantage of their ability to band at a density of about 1.43 g/cm3 in plain cesium chloride as well as in cesium chloride gradients containing 0.5% sarkosyl without prior aldehyde fixation. After these two steps of equilibrium density centrifugation, these snRNPs were still largely contaminated by free proteins (and especially phosphoproteins). A final step of purification by velocity sedimentation in a sucrose gradient containing 0.5 M cesium chloride and 0.5% sarkosyl was efficient in completely eliminating all free proteins. U1, U2, U4, U5 and U6 species according to the nomenclature of Lerner et al. (Nature, (1980) 283, 220-224) were found in these purified snRNPs, while a significant part of U6 and a small amount of U2 were found in the bottom fraction. 5S species behaved entirely as free RNA and is presumably a contaminant of cytoplasmic origin. Electrophoresis of proteins from snRNP labeled in vivo with (35S) methionine, revealed four bands with migrations corresponding to molecular weights ranging between 10,000 and 14,000 daltons.

  8. CLASSIFICATION OF SYSTEMS FOR PASSIVE AFTERHEAT REMOVAL FROM REACTOR CONTAINMENT OF NUCLEAR POWER PLANT WITH WATER-COOLED POWER REACTOR

    Directory of Open Access Journals (Sweden)

    N. Khaled

    2014-01-01

    Full Text Available A classification on systems for passive afterheat removal from reactor containment has been developed in the paper.  The classification permits to make a detailed analysis of various concepts pertaining to systems for passive afterheat removal from reactor containment of new generation. The paper considers main classification features of the given systems.

  9. Unmanned Mobile Monitoring for Nuclear Emergency Response

    Energy Technology Data Exchange (ETDEWEB)

    Choi, YoungSoo; Park, JongWon; Kim, TaeWon; Jeong, KyungMin [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2016-10-15

    Severe accidents at nuclear power plant have led to significant consequences to the people, the environment or the facility. Therefore, the appropriate response is required for the mitigation of the accidents. In the past, most of responses were performed by human beings, but it was dangerous and risky. In this paper, we proposed unmanned mobile system for the monitoring of nuclear accident in order to response effectively. For the integrity of reactor cooling and containment building, reactor cooling pipe and hydrogen distribution monitoring with unmanned ground vehicle was designed. And, for the safety of workers, radiation distribution monitoring with unmanned aerial vehicle was designed. Unmanned mobile monitoring system was proposed to respond nuclear accidents effectively. Concept of reinforcing the integrity of RCS and containment building, and radiation distribution monitoring were described. RCS flow measuring, hydrogen distribution measuring and radiation monitoring deployed at unmanned vehicle were proposed. These systems could be a method for the preparedness of effective response of nuclear accidents.

  10. Nuclear industry practice for clearance of materials, facilities and buildings as well as land. Tutorial; Kaerntekniska industrins praxis foer friklassning av material, lokaler och byggnader samt mark. Handledning

    Energy Technology Data Exchange (ETDEWEB)

    2011-12-15

    This handbook comprises the common practices of the Swedish nuclear industry for the clearance of material, rooms, buildings and soil in order to be exempted from the Swedish Nuclear Activities Act and the Swedish Radiation Protection Act. After clearance the management/usage of material, rooms, buildings and soil is permitted without any control from the radiation protection point of view. Clearance is practiced to reduce the amount radioactive waste. Cleared material can be reused according to its original form, recycled or, if these two possibilities are not available, disposed as conventional waste. The working procedures described in this handbook are mainly based on the regulation SSMFS 2011:2 from the Swedish Radiation Safety Authority: 'Regulations concerning clearance of material, rooms, buildings and soil from activities with ionising radiation'. The purpose of this handbook is to serve as a tool and guidance for generating specific routines and instructions for clearance. It describes the principles, processes and routines that should be followed under a clearance procedure. The intention is to accomplish the current regulation by following the routines and principles described in this manual. This handbook spans over a large number of conditions towards clearance, such as facility specific conditions and different types of objects. Because not all the conceivable conditions and objects can be included here, the purpose has been to cover the most common types of clearance practices. The practices comprise: - Description of regulations and recommendations, Swedish and international, that represent the basis of the requirements in this handbook. - Presentation of the processes for clearance of material, rooms, buildings and soil. Those which cannot be cleared are considered as radioactive waste. A proposal for the decision-making process is presented. - Illustration for radiological surveys to systems and components, buildings and soil in regard

  11. Screening evaluation of radionuclide groundwater concentrations for the end state basement fill model Zion Nuclear Power Station decommissioning project

    Energy Technology Data Exchange (ETDEWEB)

    Sullivan T.

    2014-06-09

    ZionSolutions is in the process of decommissioning the Zion Nuclear Power Plant. The site contains two reactor Containment Buildings, a Fuel Building, an Auxiliary Building, and a Turbine Building that may be contaminated. The current decommissioning plan involves removing all above grade structures to a depth of 3 feet below grade. The remaining underground structures will be backfilled with clean material. The final selection of fill material has not been made.

  12. Understanding the Risk of Chloride Induced Stress Corrosion Cracking of Interim Storage Containers for the Dry Storage of Spent Nuclear Fuel: Evolution of Brine Chemistry on the Container Surface.

    Energy Technology Data Exchange (ETDEWEB)

    Enos, David; Bryan, Charles R.

    2015-10-01

    Although the susceptibility of austenitic stainless steels to chloride-induced stress corrosion cracking is well known, uncertainties exist in terms of the environmental conditions that exist on the surface of the storage containers. While a diversity of salts is present in atmospheric aerosols, many of these are not stable when placed onto a heated surface. Given that the surface temperature of any container storing spent nuclear fuel will be well above ambient, it is likely that salts deposited on its surface may decompose or degas. To characterize this effect, relevant single and multi-salt mixtures are being evaluated as a function of temperature and relative humidity to establish the rates of degassing, as well as the likely final salt and brine chemistries that will remain on the canister surface.

  13. Synthesis and Crystal Structure of a Novel Hetero-six-nuclear Copper-iron Cluster Containing Ferroceylphenyl Groups

    Institute of Scientific and Technical Information of China (English)

    Yan XU; Hai Xian WANG; Yong FU; Mao Ping SONG; Yang Jie WU

    2005-01-01

    A new hetero-six-nuclear cluster was synthesized and determined by X-ray diffraction technique. The four-carboxylate groups are bound to the Cu(Ⅱ) atoms to form Cu(OR)4Cu paddle-wheel-type cage between two DMF as the basis for the cluster. The distance of two copper(Ⅱ) atoms is 2.642A, and they are bridged by the carboxylate groups. A huge system plane was auto-assembled by four host molecules and two Cu (Ⅱ) ions, which was observed in the crystal structure.

  14. The phylogenetic position of red algae revealed by multiple nuclear genes from mitochondria-containing eukaryotes and an alternative hypothesis on the origin of plastids.

    Science.gov (United States)

    Nozaki, Hisayoshi; Matsuzaki, Motomichi; Takahara, Manabu; Misumi, Osami; Kuroiwa, Haruko; Hasegawa, Masami; Shin-i, Tadasu; Kohara, Yuji; Ogasawara, Naotake; Kuroiwa, Tsuneyoshi

    2003-04-01

    Red algae are one of the main photosynthetic eukaryotic lineages and are characterized by primitive features, such as a lack of flagella and the presence of phycobiliproteins in the chloroplast. Recent molecular phylogenetic studies using nuclear gene sequences suggest two conflicting hypotheses (monophyly versus non-monophyly) regarding the relationships between red algae and green plants. Although kingdom-level phylogenetic analyses using multiple nuclear genes from a wide-range of eukaryotic lineages were very recently carried out, they used highly divergent gene sequences of the cryptomonad nucleomorph (as the red algal taxon) or incomplete red algal gene sequences. In addition, previous eukaryotic phylogenies based on nuclear genes generally included very distant archaebacterial sequences (designated as the outgroup) and/or amitochondrial organisms, which may carry unusual gene substitutions due to parasitism or the absence of mitochondria. Here, we carried out phylogenetic analyses of various lineages of mitochondria-containing eukaryotic organisms using nuclear multigene sequences, including the complete sequences from the primitive red alga Cyanidioschyzon merolae. Amino acid sequence data for two concatenated paralogous genes (alpha- and beta-tubulin) from mitochondria-containing organisms robustly resolved the basal position of the cellular slime molds, which were designated as the outgroup in our phylogenetic analyses. Phylogenetic analyses of 53 operational taxonomic units (OTUs) based on a 1525-amino-acid sequence of four concatenated nuclear genes (actin, elongation factor-1alpha, alpha-tubulin, and beta-tubulin) reliably resolved the phylogeny only in the maximum parsimonious (MP) analysis, which indicated the presence of two large robust monophyletic groups (Groups A and B) and the basal eukaryotic lineages (red algae, true slime molds, and amoebae). Group A corresponded to the Opisthokonta (Metazoa and Fungi), whereas Group B included various

  15. Recombinant Sj16 from Schistosoma japonicum contains a functional N-terminal nuclear localization signal necessary for nuclear translocation in dendritic cells and interleukin-10 production.

    Science.gov (United States)

    Sun, Xi; Yang, Fan; Shen, Jia; Liu, Zhen; Liang, Jinyi; Zheng, Huanqin; Fung, Mingchiu; Wu, Zhongdao

    2016-12-01

    Sj16 is a Schistosoma japonicum-derived protein (16 kDa in molecular weight) that has been identified as an immune modulation molecule, but the mechanisms of modulation of immune responses are not known. In this report, we aimed to investigate the host immune regulation mechanism by recombinant Sj16 (rSj16) and thus illuminate the molecular mechanism of immune evasion by S. japonicum. The effect of rSj16 and rSj16 mutants on the biology of dendritic cells (DCs) was assessed by examining DC maturation, cytokine production, and expression of surface markers by flow cytometry and enzyme-linked immunosorbent assay. We found that rSj16 significantly stimulated interleukin (IL)-10 production and inhibited LPS-induced bone marrow-derived dendrite cell (BMDC) maturation in a dose-dependent manner. By using antibody neutralization experiments and IL-10-deficient (knockout) mice, we confirmed that the inhibitory effect of rSj16 on LPS-induced BMDCs is due to its induction of IL-10 production. To understand how rSj16 induces the production of IL-10, we analyzed the protein sequence and revealed two potential nuclear localization signals (NLS) in Sj16. The N-terminal NLS (NLS1) is both necessary and sufficient for translocation of rSj16 to the nucleus of BMDCs and is important for subsequent induction of IL-10 production and the inhibition of BMDC maturation by rSj16. The results of our study concluded that the ability of rSj16 to inhibit DC functions is IL-10 dependent which is operated by IL-10R signal pathway. This study also confirmed that NLS is an important domain associated with increased production of IL-10. Our findings will extend the current understanding on host-schistosome relationship and provide insight about bottleneck of parasitic control.

  16. Building flexibility into the design of a pilot plant for the immobilisation of Pu containing residues and wastes

    Energy Technology Data Exchange (ETDEWEB)

    Scales, C R; Maddrell, E R [NNL, Havelock Rd, Workington, CA14 3YQ (United Kingdom); Hobbs, J; Stephen, R [Sellafield Ltd, Sellafield, CA20 1 PG (United Kingdom); Moricca, S; Stewart, M W A [ANSTO, New Illawara Road, Lucas Heights 2234 (Australia)

    2013-07-01

    NNL and ANSTO on behalf of Sellafield Ltd have developed a process for the immobilisation of a range of Pu containing wastes and residues. Following the inactive demonstration of the technology the project is now focusing on the design of an active pilot plant capable of validating the technology and ultimately immobilising a waste inventory containing around 100 kg plutonium. The diverse wastes from which it is uneconomic to recover Pu, require a flexible process with a wide product envelope capable of producing a wasteform suitable for disposal in a UK repository. Ceramics, glass ceramics and metal encapsulated waste-forms can be delivered by the process line which incorporates size reduction and heat treatment techniques with the aim of feeding a hot isostatic pressing process designed to deliver the highly durable waste-forms. Following a demonstration of feasibility, flowsheet development is progressing to support the design which has the aim of a fully flexible facility based in NNL's Central Laboratory on the Sellafield site. Optimisation of the size reduction, mixing and blending operations is being carried out using UO{sub 2} as a surrogate for PuO{sub 2}. This work is supporting the potential of using an enhanced glass ceramic formulation in place of the full ceramic with the aim of simplifying glove box operations. Heat treatment and subsequent HIPing strategies are being explored in order to eliminate any carbon from the feeds without increasing the valence state of the uranium present in some of the inventory which can result in an unwanted increase in wasteform volumes. The HIP and ancillary systems are being specifically designed to meet the requirements of the Sellafield site and within the constraints of the NNL Central Laboratory. The HIP is being configured to produce consolidated product cans consistent with the requirements of ongoing storage and disposal. With the aim of one cycle per day, the facility will deliver its mission of

  17. A nuclear criticality safety assessment of the loss of moderation control in 2 1/2 and 10-ton cylinders containing enriched UF{sub 6}

    Energy Technology Data Exchange (ETDEWEB)

    Newvahner, R.L. [Martin Marietta Energy Systems, Inc., Piketon, OH (United States); Pryor, W.A. [PAI Corp., Oak Ridge, TN (United States)

    1991-12-31

    Moderation control for maintaining nuclear criticality safety in 2 {1/2}-ton, 10-ton, and 14-ton cylinders containing enriched uranium hexafluoride (UF{sub 6}) has been used safely within the nuclear industry for over thirty years, and is dependent on cylinder integrity and containment. This assessment evaluates the loss of moderation control by the breaching of containment and entry of water into the cylinders. The first objective of this study was to estimate the required amounts of water entering these large UF{sub 6} cylinders to react with, and to moderate the uranium compounds sufficiently to cause criticality. Hypothetical accident situations were modeled as a uranyl fluoride (UO{sub 2}F{sub 2}) slab above a UF{sub 6} hemicylinder, and a UO{sub 2}F{sub 2} sphere centered within a UF{sub 6} hemicylinder. These situations were investigated by computational analyses utilizing the KENO V.a Monte Carlo Computer Code. The results were used to estimate both the masses of water required for criticality, and the limiting masses of water that could be considered safe. The second objective of the assessment was to calculate the time available for emergency control actions before a criticality would occur, i.e., a {open_quotes}safetime{close_quotes}, for various sources of water and different size openings in a breached cylinder. In the situations considered, except the case for a fire hose, the safetime appears adequate for emergency control actions. The assessment shows that current practices for handling moderation controlled cylinders of low enriched UF{sub 6}, along with the continuation of established personnel training programs, ensure nuclear criticality safety for routine and emergency operations.

  18. Laboratory Building

    Energy Technology Data Exchange (ETDEWEB)

    Herrera, Joshua M. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)

    2015-03-01

    This report is an analysis of the means of egress and life safety requirements for the laboratory building. The building is located at Sandia National Laboratories (SNL) in Albuquerque, NM. The report includes a prescriptive-based analysis as well as a performance-based analysis. Following the analysis are appendices which contain maps of the laboratory building used throughout the analysis. The top of all the maps is assumed to be north.

  19. Laboratory Building.

    Energy Technology Data Exchange (ETDEWEB)

    Herrera, Joshua M. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)

    2015-03-01

    This report is an analysis of the means of egress and life safety requirements for the laboratory building. The building is located at Sandia National Laboratories (SNL) in Albuquerque, NM. The report includes a prescriptive-based analysis as well as a performance-based analysis. Following the analysis are appendices which contain maps of the laboratory building used throughout the analysis. The top of all the maps is assumed to be north.

  20. Nuclear Safety Review for Qualification of Class 1E Motor inside Containment for Nuclear Power Stations%1E级安全壳内用电动机鉴定的核安全审查

    Institute of Scientific and Technical Information of China (English)

    李世欣; 毋琦; 张云波; 吴彩霞

    2013-01-01

    In nuclear power plants with pressurized water reactors,the review for class 1E motor inside containment qualification process and documents is an important aspect of nuclear safety equipment review,and the reviewers should make evaluations for the qualification test results in terms of the compliance with standard and regulation,and the consistency with inside containment environment.Firstly,this paper introduces the qualification test of class 1E motor inside containment for nuclear power generating stations,such as aging test and design-basis-event test.Second,there is a discussion about typical problems of review.At last,comparison of IEEE334 with RCC-E is conducted and explored.%对压水堆核电厂1E级安全壳内电动机的鉴定过程和鉴定文件进行审查,要求对鉴定试验结果与标准法规的符合性以及与安全壳内环境要求的一致性做出评价.首先介绍1E级安全壳内用电动机的老化试验、设计基准事故试验等主要鉴定试验,对随后审查过程中遇到的典型问题进行分析,并将IEEE 334与RCC-E两套标准进行对比探讨.

  1. Building Data

    Data.gov (United States)

    Town of Cary, North Carolina — Explore real estate information about buildings in the Town of Cary.This file is created by the Town of Cary GIS Group. It contains data from both the Wake, Chatham...

  2. Advanced Non-Destructive Assessment Technology to Determine the Aging of Silicon Containing Materials for Generation IV Nuclear Reactors

    Science.gov (United States)

    Koenig, T. W.; Olson, D. L.; Mishra, B.; King, J. C.; Fletcher, J.; Gerstenberger, L.; Lawrence, S.; Martin, A.; Mejia, C.; Meyer, M. K.; Kennedy, R.; Hu, L.; Kohse, G.; Terry, J.

    2011-06-01

    To create an in-situ, real-time method of monitoring neutron damage within a nuclear reactor core, irradiated silicon carbide samples are examined to correlate measurable variations in the material properties with neutron fluence levels experienced by the silicon carbide (SiC) during the irradiation process. The reaction by which phosphorus doping via thermal neutrons occurs in the silicon carbide samples is known to increase electron carrier density. A number of techniques are used to probe the properties of the SiC, including ultrasonic and Hall coefficient measurements, as well as high frequency impedance analysis. Gamma spectroscopy is also used to examine residual radioactivity resulting from irradiation activation of elements in the samples. Hall coefficient measurements produce the expected trend of increasing carrier concentration with higher fluence levels, while high frequency impedance analysis shows an increase in sample impedance with increasing fluence.

  3. GEANT4 Simulation of a Scintillating-Fibre Tracker for the Cosmic-ray Muon Tomography of Legacy Nuclear Waste Containers

    CERN Document Server

    Clarkson, Anthony; Hoek, Matthias; Ireland, David G; Johnstone, Russell; Kaiser, Ralf; Keri, Tibor; Lumsden, Scott; Mahon, David F; McKinnon, Bryan; Murray, Morgan; Nutbeam-Tuffs, Sian; Shearer, Craig; Staines, Cassie; Yang, Guangliang; Zimmerman, Colin

    2013-01-01

    Cosmic-ray muons are highly penetrative charged particles that are observed at sea level with a flux of approximately one per square centimetre per minute. They interact with matter primarily through Coulomb scattering, which is exploited in the field of muon tomography to image shielded objects in a wide range of applications. In this paper, simulation studies are presented that assess the feasibility of a scintillating-fibre tracker system for use in the identification and characterisation of nuclear materials stored within industrial legacy waste containers. A system consisting of a pair of tracking modules above and a pair below the volume to be assayed is simulated within the GEANT4 framework using a range of potential fibre pitches and module separations. Each module comprises two orthogonal planes of fibres that allow the reconstruction of the initial and Coulomb-scattered muon trajectories. A likelihood-based image reconstruction algorithm has been developed that allows the container content to be det...

  4. Nuclear law in the EU and beyond. Proceedings

    Energy Technology Data Exchange (ETDEWEB)

    Raetzke, Christian (ed.) [CONLAR Consulting on Nuclear Law and Regulation, Leipzig (Germany)

    2014-11-01

    This volume contains the proceedings of the 13{sup th} Regional Conference of the German Branch of the Association Internationale du Droit Nucleaire / International Nuclear Law Association (AIDN/INLA) held in Leipzig in June 2013. German and international experts explain the most recent developments in nuclear law in the EU, in Germany and worldwide. The topics include nuclear safety, nuclear liability, nuclear new build and phase-out legislation. Current EU legislation projects, particularly concerning nuclear safety, are explained and their impact is analysed. Worldwide developments are discussed, such as the quest for a global nuclear liability regime. Fitting to the international character of the conference, the language of all papers, including those from German authors, is English, with the exception of four papers dealing with issues of German nuclear law. For everyone who wants to keep up-to-date on important developments of nuclear law, this volume is an obvious choice.

  5. Application and Exploration of Container Building in Urban Farm:Take Kunming Maple Valley Urban Farm Container Building as the Case%集装箱建筑在都市农庄中的应用与探索--以昆明金殿后山枫叶谷都市农庄集装箱建筑为例

    Institute of Scientific and Technical Information of China (English)

    张濒予; 翟辉

    2016-01-01

    The rise of a large number of container buildings in the world makes it become a regular branch of architecture. Based on Kunming Maple Valley Urban Farm container architectural design, this paper explores the advantages of using containers as the main building material compared to general material, and analyzes the value of container construction and the practice summary, which provides inspiration for architectural design of urban farm.%集装箱建筑在世界范围内大量的兴起使其被作为一个常规建筑学的分支。以昆明枫叶谷都市农庄集装箱建筑设计为依托,探讨用集装箱作为建筑主要材料时与一般性材料的优势的比较,并浅析集装箱建筑存在的价值及实践总结,为都市农庄中建筑设计的创作提供思路和启发。

  6. A Metal-Organic Framework Containing Unusual Eight-Connected Zr–-Oxo Secondary Building Units and Orthogonal Carboxylic Acids for Ultra-sensitive Metal Detection

    Energy Technology Data Exchange (ETDEWEB)

    Carboni, Michaël; Lin, Zekai; Abney, Carter W.; Zhang, Teng; Lin, Wenbin (UC)

    2015-08-21

    Two metal-organic frameworks (MOFs) with Zr-oxo secondary building units (SBUs) were prepared by using p,p'-terphenyldicarboxylate (TPDC) bridging ligands pre-functionalized with orthogonal succinic acid (MOF-1) and maleic acid groups (MOF-2). Single-crystal X-ray structure analysis of MOF-1 provides the first direct evidence for eight-connected SBUs in UiO-type MOFs. In contrast, MOF-2 contains twelve-connected SBUs as seen in the traditional UiO MOF topology. These structural assignments were confirmed by extended X-ray absorption fine structure (EXAFS) analysis. The highly porous MOF-1 is an excellent fluorescence sensor for metal ions with the detection limit of <0.5 ppb for Mn2+ and three to four orders of magnitude greater sensitivity for metal ions than previously reported luminescent MOFs.

  7. The influence of modified water chemistries on metal oxide films, activity build-up and stress corrosion cracking of structural materials in nuclear power plants

    Energy Technology Data Exchange (ETDEWEB)

    Maekelae, K.; Laitinen, T.; Bojinov, M. [VTT Manufacturing Technology, Espoo (Finland)

    1999-03-01

    The primary coolant oxidises the surfaces of construction materials in nuclear power plants. The properties of the oxide films influence significantly the extent of incorporation of actuated corrosion products into the primary circuit surfaces, which may cause additional occupational doses for the maintenance personnel. The physical and chemical properties of the oxide films play also an important role in different forms of corrosion observed in power plants. This report gives a short overview of the factors influencing activity build-up and corrosion phenomena in nuclear power plants. Furthermore, the most recent modifications in the water chemistry to decrease these risks are discussed. A special focus is put on zinc water chemistry, and a preliminary discussion on the mechanism via which zinc influences activity build-up is presented. Even though the exact mechanisms by which zinc acts are not yet known, it is assumed that Zn may block the diffusion paths within the oxide film. This reduces ion transport through the oxide films leading to a reduced rate of oxide growth. Simultaneously the number of available adsorption sites for {sup 60}Co is also reduced. The current models for stress corrosion cracking assume that the anodic and the respective cathodic reactions contributing to crack growth occur partly on or in the oxide films. The rates of these reactions may control the crack propagation rate and therefore, the properties of the oxide films play a crucial role in determining the susceptibility of the material to stress corrosion cracking. Finally, attention is paid also on the novel techniques which can be used to mitigate the susceptibility of construction materials to stress corrosion cracking. (orig.) 127 refs.

  8. BEACON/MOD2A: a computer program for subcompartment analysis of nuclear reactor containment. A user's manual. [PWR

    Energy Technology Data Exchange (ETDEWEB)

    Wells, R. A.

    1979-03-01

    The BEACON code is a Best Estimate Advanced Containment code which being developed by EG and G, Idaho, Inc., at the Idaho National Engineering Laboratory. The program is designed to perform a best estimate analysis of the flow of a mixture of air, water, and steam in a nuclear reactor containment system under loss-of-coolant accident conditions. The code can simulate two-component, two-phase fluid flow in complex geometries using a combination of two-dimensional, one-dimensional, and lumped-parameter representations for the various parts of the system. The current version of BEACON, which is designated BEACON/MOD2A, contains mass and heat transfer models for wall film and for wall conduction. It is suitable for the evaluation of short term transients in PWR dry containment systems. This manual describes the models employed in BEACON/MOD2A and specifies code implementation requirements. It provides application information for input data preparation and for output data interpretation.

  9. Analysis of dust samples collected from spent nuclear fuel interim storage containers at Hope Creek, Delaware, and Diablo Canyon, California

    Energy Technology Data Exchange (ETDEWEB)

    Bryan, Charles R. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Enos, David George [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)

    2014-07-01

    Potentially corrosive environments may form on the surface of spent nuclear fuel dry storage canisters by deliquescence of deposited dusts. To assess this, samples of dust were collected from in-service dry storage canisters at two near-marine sites, the Hope Creek and Diablo Canyon storage installations, and have been characterized with respect to mineralogy, chemistry, and texture. At both sites, terrestrially-derived silicate minerals, including quartz, feldspars, micas, and clays, comprise the largest fraction of the dust. Also significant at both sites were particles of iron and iron-chromium metal and oxides generated by the manufacturing process. Soluble salt phases were minor component of the Hope Creek dusts, and were compositionally similar to inland salt aerosols, rich in calcium, sulfate, and nitrate. At Diablo Canyon, however, sea-salt aerosols, occurring as aggregates of NaCl and Mg-sulfate, were a major component of the dust samples. The seasalt aerosols commonly occurred as hollow spheres, which may have formed by evaporation of suspended aerosol seawater droplets, possibly while rising through the heated annulus between the canister and the overpack. The differences in salt composition and abundance for the two sites are attributed to differences in proximity to the open ocean and wave action. The Diablo Canyon facility is on the shores of the Pacific Ocean, while the Hope Creek facility is on the shores of the Delaware River, several miles from the open ocean.

  10. Closure development for high-level nuclear waste containers for the tuff repository; Phase 1, Final report

    Energy Technology Data Exchange (ETDEWEB)

    Robitz, E.S. Jr.; McAninch, M.D. Jr.; Edmonds, D.P. [Babcock and Wilcox Co., Lynchburg, VA (USA). Nuclear Power Div.]|[Babcock and Wilcox Co., Alliance, OH (USA). Research and Development Div.

    1990-09-01

    This report summarizes Phase 1 activities for closure development of the high-level nuclear waste package task for the tuff repository. Work was conducted under U.S. Department of Energy (DOE) Contract 9172105, administered through the Lawrence Livermore National Laboratory (LLNL), as part of the Yucca Mountain Project (YMP), funded through the DOE Office of Civilian Radioactive Waste Management (OCRWM). The goal of this phase was to select five closure processes for further evaluation in later phases of the program. A decision tree methodology was utilized to perform an objective evaluation of 15 potential closure processes. Information was gathered via a literature survey, industrial contacts, and discussions with project team members, other experts in the field, and the LLNL waste package task staff. The five processes selected were friction welding, electron beam welding, laser beam welding, gas tungsten arc welding, and plasma arc welding. These are felt to represent the best combination of weldment material properties and process performance in a remote, radioactive environment. Conceptual designs have been generated for these processes to illustrate how they would be implemented in practice. Homopolar resistance welding was included in the Phase 1 analysis, and developments in this process will be monitored via literature in Phases 2 and 3. Work was conducted in accordance with the YMP Quality Assurance Program. 223 refs., 20 figs., 9 tabs.

  11. Analysis of dust samples collected from spent nuclear fuel interim storage containers at Hope Creek, Delaware, and Diablo Canyon, California.

    Energy Technology Data Exchange (ETDEWEB)

    Bryan, Charles R.; Enos, David George

    2014-07-01

    Potentially corrosive environments may form on the surface of spent nuclear fuel dry storage canisters by deliquescence of deposited dusts. To assess this, samples of dust were collected from in-service dry storage canisters at two near-marine sites, the Hope Creek and Diablo Canyon storage installations, and have been characterized with respect to mineralogy, chemistry, and texture. At both sites, terrestrially-derived silicate minerals, including quartz, feldspars, micas, and clays, comprise the largest fraction of the dust. Also significant at both sites were particles of iron and iron-chromium metal and oxides generated by the manufacturing process. Soluble salt phases were minor component of the Hope Creek dusts, and were compositionally similar to inland salt aerosols, rich in calcium, sulfate, and nitrate. At Diablo Canyon, however, sea-salt aerosols, occurring as aggregates of NaCl and Mg-sulfate, were a major component of the dust samples. The seasalt aerosols commonly occurred as hollow spheres, which may have formed by evaporation of suspended aerosol seawater droplets, possibly while rising through the heated annulus between the canister and the overpack. The differences in salt composition and abundance for the two sites are attributed to differences in proximity to the open ocean and wave action. The Diablo Canyon facility is on the shores of the Pacific Ocean, while the Hope Creek facility is on the shores of the Delaware River, several miles from the open ocean.

  12. Gene suppression via U1 small nuclear RNA interference (U1i) machinery using oligonucleotides containing 2'-modified-4'-thionucleosides.

    Science.gov (United States)

    Kikuchi, Yusaku; Yamazaki, Naoshi; Tarashima, Noriko; Furukawa, Kazuhiro; Takiguchi, Yoshiharu; Itoh, Kohji; Minakawa, Noriaki

    2013-09-01

    Gene suppression via U1 small nuclear RNA interference (U1i) is considered to be one of the most attractive approaches, and takes the place of general antisense, RNA interference (RNAi), and anti-micro RNA machineries. Since the U1i can be induced by short oligonucleotides (ONs), namely U1 adaptors consisting of a 'target domain' and a 'U1 domain', we prepared adaptor ONs using 2'-modified-4'-thionucleosides developed by our group, and evaluated their U1i activity. As a result, the desired gene suppression via U1i was observed in ONs prepared as a combination of 2'-fluoro-4'-thionucleoside and 2'-fluoronucleoside units as well as only 2'-fluoronucleoside units, while those prepared as combination of 2'-OMe nucleoside/2'-OMe-4'-thionucleoside and 2'-fluoronucleoside units did not show significant activity. Measurement of Tm values indicated that a higher hybridization ability of adaptor ONs with complementary RNA is one of the important factors to show potent U1i activity.

  13. Inter-organisational knowledge transfer: building and sustaining the sources of innovation in nuclear safety and security

    Energy Technology Data Exchange (ETDEWEB)

    Staude, Fabio, E-mail: fstaude@cnen.gov.br [Comissao Nacional de Energia Nuclear (CNEN-RJ), Rio de Janeiro, RJ (Brazil); Ramirez, Matias, E-mail: matias.ramirez@sussex.ac.uk [University of Sussex (SPRU/US), Brighton (United Kingdom). Science and Technology Policy Research

    2013-07-01

    The current complexity of innovation processes has led to an understanding that the models of innovation have changed from linear model to a model characterised by multiple interactions and complex networks. Within this more multifaceted environment, has emerged a new set of actors, generally termed as intermediaries, performing a variety of tasks in the innovation process. The innovation literature has recognised various important supporting activities performed by intermediaries, by linking and facilitating the movement of information and knowledge between actors within an innovation system, in order to fill information gaps. Complementary, we make the assumption that the intermediary can assume a more central role in the innovation process, performing activities beyond to filling information gaps, since they intervene to create, prioritise, and articulate meaning to practices. Under this argument, this paper explores how intermediaries work in making innovation happen in the Brazilian nuclear safety and security area, demonstrating the influence of intermediary organisations in improving nuclear regulatory activities. We make sense of these processes by analyzing intermediary roles in the recent regulatory activities improvements, specifically those related to the practices involving radiation sources in medicine. Thus, through an empirical case study, this paper examines the issue of intermediation in a wide sense, including strategic activities preformed by intermediaries, associated with accessing, diffusing, coordinating and enabling knowledge activities. (author)

  14. Consolidation: Thwarting Nuclear Theft

    OpenAIRE

    Bunn, Matthew G.; Harrell, Eben

    2013-01-01

    At the first nuclear security summit in April 2010, the assembled leaders agreed on the goal of securing all vulnerable nuclear material worldwide within four years, including consolidating plutonium and highly enriched uranium (HEU) to fewer locations and minimizing the use of HEU “where technically and economically feasible.†Reducing the number of buildings and sites where nuclear weapons and weapons-usable nuclear material exist is a key element of preventing nuclear theft and nuclear ...

  15. The meganuclease I-SceI containing nuclear localization signal (NLS-I-SceI efficiently mediated mammalian germline transgenesis via embryo cytoplasmic microinjection.

    Directory of Open Access Journals (Sweden)

    Yong Wang

    Full Text Available The meganuclease I-SceI has been effectively used to facilitate transgenesis in fish eggs for nearly a decade. I-SceI-mediated transgenesis is simply via embryo cytoplasmic microinjection and only involves plasmid vectors containing I-SceI recognition sequences, therefore regarding the transgenesis process and application of resulted transgenic organisms, I-SceI-mediated transgenesis is of minimal bio-safety concerns. However, currently no transgenic mammals derived from I-SceI-mediated transgenesis have been reported. In this work, we found that the native I-SceI molecule was not capable of facilitating transgenesis in mammalian embryos via cytoplasmic microinjection as it did in fish eggs. In contrast, the I-SceI molecule containing mammalian nuclear localization signal (NLS-I-SceI was shown to be capable of transferring DNA fragments from cytoplasm into nuclear in porcine embryos, and cytoplasmic microinjection with NLS-I-SceI mRNA and circular I-SceI recognition sequence-containing transgene plasmids resulted in transgene expression in both mouse and porcine embryos. Besides, transfer of the cytoplasmically microinjected mouse and porcine embryos into synchronized recipient females both efficiently resulted in transgenic founders with germline transmission competence. These results provided a novel method to facilitate mammalian transgenesis using I-SceI, and using the NLS-I-SceI molecule, a simple, efficient and species-neutral transgenesis technology based on embryo cytoplasmic microinjection with minimal bio-safety concerns can be established for mammalian species. As far as we know, this is the first report for transgenic mammals derived from I-SceI-mediated transgenesis via embryo cytoplasmic microinjection.

  16. The meganuclease I-SceI containing nuclear localization signal (NLS-I-SceI) efficiently mediated mammalian germline transgenesis via embryo cytoplasmic microinjection.

    Science.gov (United States)

    Wang, Yong; Zhou, Xiao-Yang; Xiang, Peng-Ying; Wang, Lu-Lu; Tang, Huan; Xie, Fei; Li, Liang; Wei, Hong

    2014-01-01

    The meganuclease I-SceI has been effectively used to facilitate transgenesis in fish eggs for nearly a decade. I-SceI-mediated transgenesis is simply via embryo cytoplasmic microinjection and only involves plasmid vectors containing I-SceI recognition sequences, therefore regarding the transgenesis process and application of resulted transgenic organisms, I-SceI-mediated transgenesis is of minimal bio-safety concerns. However, currently no transgenic mammals derived from I-SceI-mediated transgenesis have been reported. In this work, we found that the native I-SceI molecule was not capable of facilitating transgenesis in mammalian embryos via cytoplasmic microinjection as it did in fish eggs. In contrast, the I-SceI molecule containing mammalian nuclear localization signal (NLS-I-SceI) was shown to be capable of transferring DNA fragments from cytoplasm into nuclear in porcine embryos, and cytoplasmic microinjection with NLS-I-SceI mRNA and circular I-SceI recognition sequence-containing transgene plasmids resulted in transgene expression in both mouse and porcine embryos. Besides, transfer of the cytoplasmically microinjected mouse and porcine embryos into synchronized recipient females both efficiently resulted in transgenic founders with germline transmission competence. These results provided a novel method to facilitate mammalian transgenesis using I-SceI, and using the NLS-I-SceI molecule, a simple, efficient and species-neutral transgenesis technology based on embryo cytoplasmic microinjection with minimal bio-safety concerns can be established for mammalian species. As far as we know, this is the first report for transgenic mammals derived from I-SceI-mediated transgenesis via embryo cytoplasmic microinjection.

  17. A Probabilistic Performance Assessment Model for General Corrosion of Alloy 22 for High Level Nuclear Waste Disposal Container

    Energy Technology Data Exchange (ETDEWEB)

    J. H. Lee; H. A. Elayat

    2003-12-11

    Alloy 22 (UNS N06022) is the candidate material for the corrosion barrier of the double-wall waste package (WP) for the disposal of high-Gel nuclear waste at the proposed Yucca Mountain repository. A probabilistic temperature-dependent general corrosion model for the WP outer barrier (WPOB) was developed based on the 5-year weight-loss measurements of Alloy 22 crevice samples. The 5-year corrosion rate distribution is represented by a Weibull distribution, with scale factors = 8.88, shape factor b = 1.62, and location factor l = 0. The temperature-dependence of the general corrosion rate was modeled using an Arrhenius relation. An activation energy of 25.91 {+-} 2.46 kJ/mol was determined from the corrosion rates obtained from the short-term polarization resistance data for Alloy 22 specimens tested for a wide range of sample configurations, metallurgical conditions, and exposure conditions (temperature and water chemistry). Analysis of the data from the current study and the literature indicates that the activation energies of general corrosion rate of highly corrosion resistant Ni-Cr-Mo alloys including Alloy 22 are similar and do not change significantly, as the general corrosion rate decreases with the exposure time. The 5-year corrosion rates were conservatively selected for extrapolation over the repository time scale. Because of very low general corrosion rates of the WPOB for the conditions expected in the proposed repository, the WP performance will not be limited by general corrosion for the repository regulatory time period. The current conservative approach for the constant (time-independent) general corrosion rate at a given temperature provides an additional confidence for the general corrosion model.

  18. The improvements on reactor building liner plate erection work

    Energy Technology Data Exchange (ETDEWEB)

    Roh, Myungsub; Choi, Sangmoo [Ulchin Nuclear Division, KHNP, Seoul (Korea, Republic of)

    2002-04-15

    The pressurized water reactor, with its primary cooling circuit and steam generators, is housed in a cylindrical building. This 'containment' building is 44m in diameter and 80m high, and has a hemispherical or dome roof. A 6mm steel plate lines the entire interior of this containment building. This steel lining covers the floors, walls, dome and is made gas tight. There are more than 160 penetrations in the containment building for: equipment and personnel access, piping and electrical services. There are also over 370 field welded embedments fixed to the steel liner plate. Reducing construction costs of commercial nuclear power plants is essential in order to expand the future use of nuclear energy. One of the major components of reducing construction costs is the continuous improvement in construction technology. This is also essential in order to increase the nuclear culture in Quality Assurance of nuclear power plants. These improvements can make up for shortages in skilled craft labor necessary during site construction. In this paper, a number of improvements for the containment building steel liner plate fabrication and erection work will be described; adoption of flux core arc welding process, welding improvement in thickened liner plates, prefabrication of reactor cavity wall liner plates in the yard and optimization of the number of field welded embedments. Eventually these improvements may provide cost reduction and may allow reduction in the critical path schedule.

  19. Supplement analysis for a container system for the management of DOE spent nuclear fuel located at the INEEL

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1999-03-12

    The Council on Environmental Quality (CEQ) regulations for implementing the NEPA, 40 CFR 1502.9 (c), directs federal agencies to prepare a supplement to an environmental impact statement when an agency makes substantial changes in the Proposed Action that are relevant to environmental concerns, or there are significant new circumstances or information relevant to environmental concerns and bearing on the Proposed Action or impacts. When it is unclear whether a supplemental environmental impact statement is required, DOE regulations (10 CFR 1021.314) direct the preparation of a supplement analysis to assist in making that determination. This supplement analysis evaluates the impacts of employing dual-purpose canisters (DPCs) to prepare DOE SNF located at the INEEL for interim onsite storage and transport outside the State of Idaho. Impacts associated with DPC manufacturing, loading and storage of DOE-ID SNF into DPCs, transport of loaded DPCs outside Idaho, and the cumulative impacts are compared with the impacts previously analyzed in the SNF and INEL EIS and the Navy Container System EIS. This SA provides information to determine whether: (1) an existing EIS should be supplemented; (2) a new EIS should be prepared; or (3) no further NEPA documentation is required.

  20. Conducting water chemistry of the secondary coolant circuit of VVER-based nuclear power plant units constructed without using copper containing alloys

    Science.gov (United States)

    Tyapkov, V. F.

    2014-07-01

    The secondary coolant circuit water chemistry with metering amines began to be put in use in Russia in 2005, and all nuclear power plant units equipped with VVER-1000 reactors have been shifted to operate with this water chemistry for the past seven years. Owing to the use of water chemistry with metering amines, the amount of products from corrosion of structural materials entering into the volume of steam generators has been reduced, and the flow-accelerated corrosion rate of pipelines and equipment has been slowed down. The article presents data on conducting water chemistry in nuclear power plant units with VVER-1000 reactors for the secondary coolant system equipment made without using copper-containing alloys. Statistical data are presented on conducting ammonia-morpholine and ammonia-ethanolamine water chemistries in new-generation operating power units with VVER-1000 reactors with an increased level of pH. The values of cooling water leaks in turbine condensers the tube system of which is made of stainless steel or titanium alloy are given.

  1. Determination of the melon chloroplast and mitochondrial genome sequences reveals that the largest reported mitochondrial genome in plants contains a significant amount of DNA having a nuclear origin

    Science.gov (United States)

    2011-01-01

    Background The melon belongs to the Cucurbitaceae family, whose economic importance among vegetable crops is second only to Solanaceae. The melon has a small genome size (454 Mb), which makes it suitable for molecular and genetic studies. Despite similar nuclear and chloroplast genome sizes, cucurbits show great variation when their mitochondrial genomes are compared. The melon possesses the largest plant mitochondrial genome, as much as eight times larger than that of other cucurbits. Results The nucleotide sequences of the melon chloroplast and mitochondrial genomes were determined. The chloroplast genome (156,017 bp) included 132 genes, with 98 single-copy genes dispersed between the small (SSC) and large (LSC) single-copy regions and 17 duplicated genes in the inverted repeat regions (IRa and IRb). A comparison of the cucumber and melon chloroplast genomes showed differences in only approximately 5% of nucleotides, mainly due to short indels and SNPs. Additionally, 2.74 Mb of mitochondrial sequence, accounting for 95% of the estimated mitochondrial genome size, were assembled into five scaffolds and four additional unscaffolded contigs. An 84% of the mitochondrial genome is contained in a single scaffold. The gene-coding region accounted for 1.7% (45,926 bp) of the total sequence, including 51 protein-coding genes, 4 conserved ORFs, 3 rRNA genes and 24 tRNA genes. Despite the differences observed in the mitochondrial genome sizes of cucurbit species, Citrullus lanatus (379 kb), Cucurbita pepo (983 kb) and Cucumis melo (2,740 kb) share 120 kb of sequence, including the predicted protein-coding regions. Nevertheless, melon contained a high number of repetitive sequences and a high content of DNA of nuclear origin, which represented 42% and 47% of the total sequence, respectively. Conclusions Whereas the size and gene organisation of chloroplast genomes are similar among the cucurbit species, mitochondrial genomes show a wide variety of sizes, with a non

  2. The design and performance of a scintillating-fibre tracker for the cosmic-ray muon tomography of legacy nuclear waste containers

    Science.gov (United States)

    Clarkson, A.; Hamilton, D. J.; Hoek, M.; Ireland, D. G.; Johnstone, J. R.; Kaiser, R.; Keri, T.; Lumsden, S.; Mahon, D. F.; McKinnon, B.; Murray, M.; Nutbeam-Tuffs, S.; Shearer, C.; Staines, C.; Yang, G.; Zimmerman, C.

    2014-05-01

    Tomographic imaging techniques using the Coulomb scattering of cosmic-ray muons are increasingly being exploited for the non-destructive assay of shielded containers in a wide range of applications. One such application is the characterisation of legacy nuclear waste materials stored within industrial containers. The design, assembly and performance of a prototype muon tomography system developed for this purpose are detailed in this work. This muon tracker comprises four detection modules, each containing orthogonal layers of Saint-Gobain BCF-10 2 mm-pitch plastic scintillating fibres. Identification of the two struck fibres per module allows the reconstruction of a space point, and subsequently, the incoming and Coulomb-scattered muon trajectories. These allow the container content, with respect to the atomic number Z of the scattering material, to be determined through reconstruction of the scattering location and magnitude. On each detection layer, the light emitted by the fibre is detected by a single Hamamatsu H8500 MAPMT with two fibres coupled to each pixel via dedicated pairing schemes developed to ensure the identification of the struck fibre. The PMT signals are read out to standard charge-to-digital converters and interpreted via custom data acquisition and analysis software. The design and assembly of the detector system are detailed and presented alongside results from performance studies with data collected after construction. These results reveal high stability during extended collection periods with detection efficiencies in the region of 80% per layer. Minor misalignments of millimetre order have been identified and corrected in software. A first image reconstructed from a test configuration of materials has been obtained using software based on the Maximum Likelihood Expectation Maximisation algorithm. The results highlight the high spatial resolution provided by the detector system. Clear discrimination between the low, medium and high

  3. Applications of polymer coatings for the fabrication of copper-based containers for the ultimate disposal of Canada's spent nuclear fuel

    Science.gov (United States)

    Mortley, Aba

    Oxygen-free, phosphorous doped copper containers have been proposed for the storage of the used nuclear fuel bundles as a part of Canada's multi-barrier, adaptive phased management procedure for long term storage of spent nuclear fuel bundles. The spent nuclear fuel disposal system proposed for Canada has been engineered based on the multi-barrier approach intended to minimize the risk that the radioactive materials enter the biosphere. Copper is known to be susceptible to corrosion and it is thought that the simultaneous exposure to aggressive ionizing radiation field and residual heat produced by the spent nuclear fuel and the surrounding groundwater would all challenge the container's integrity. The goal of the present work is to reduce the impact of corrosion in the early stages of emplacement with the addition of a protective coating. Specifically, castor oil based polyurethanes were assessed as coatings and their ability to act as an additional physical barrier in the multi-barrier system mentioned previously. The novelty of this work stems from the use of a naturally derived non-petroleum based material in the form of castor oil as the polyol component. Two types of castor oil polyurethanes were investigated, one based on an aliphatic hexamethylene diisocyanate (HMDI), and the other based on an aromatic 2,4-toluene diisocyanate (TDI). Radiation and saturation tests were conducted using varying conditions. Mixed field ionizing radiation was provided by a SLOWPOKE-2 pool-type nuclear research reactor, up to accumulated doses of 6 MGy at dose rates of 37 kGy h-1 and 55.5 kGy h-1. Weight gain immersion studies, at temperatures of 25° C, 50° C, 70° C, were used to determine the mass uptake of several different solutions. The solutions utilized in the present work included hydrochloric acids of varying pHs, distilled water, and buffered solutions, which simulated chloride and sulphide rich calcium-sodium bicarbonate waters. After being exposed to radiation and

  4. Final Report: Part 1. In-Place Filter Testing Instrument for Nuclear Material Containers. Part 2. Canister Filter Test Standards for Aerosol Capture Rates.

    Energy Technology Data Exchange (ETDEWEB)

    Brown, Austin Douglas [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Runnels, Joel T. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Moore, Murray E. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Reeves, Kirk Patrick [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

    2014-11-02

    A portable instrument has been developed to assess the functionality of filter sand o-rings on nuclear material storage canisters, without requiring removal of the canister lid. Additionally, a set of fifteen filter standards were procured for verifying aerosol leakage and pressure drop measurements in the Los Alamos Filter Test System. The US Department of Energy uses several thousand canisters for storing nuclear material in different chemical and physical forms. Specialized filters are installed into canister lids to allow gases to escape, and to maintain an internal ambient pressure while containing radioactive contaminants. Diagnosing the condition of container filters and canister integrity is important to ensure worker and public safety and for determining the handling requirements of legacy apparatus. This report describes the In-Place-Filter-Tester, the Instrument Development Plan and the Instrument Operating Method that were developed at the Los Alamos National Laboratory to determine the “as found” condition of unopened storage canisters. The Instrument Operating Method provides instructions for future evaluations of as-found canisters packaged with nuclear material. Customized stainless steel canister interfaces were developed for pressure-port access and to apply a suction clamping force for the interface. These are compatible with selected Hagan-style and SAVY-4000 storage canisters that were purchased from NFT (Nuclear Filter Technology, Golden, CO). Two instruments were developed for this effort: an initial Los Alamos POC (Proof-of-Concept) unit and the final Los Alamos IPFT system. The Los Alamos POC was used to create the Instrument Development Plan: (1) to determine the air flow and pressure characteristics associated with canister filter clogging, and (2) to test simulated configurations that mimicked canister leakage paths. The canister leakage scenarios included quantifying: (A) air leakage due to foreign material (i.e. dust and hair

  5. Regulation of nuclear-cytoplasmic shuttling and function of Family with sequence similarity 13, member A (Fam13a), by B56-containing PP2As and Akt.

    Science.gov (United States)

    Jin, Zhigang; Chung, Jin Wei; Mei, Wenyan; Strack, Stefan; He, Chunyan; Lau, Gee W; Yang, Jing

    2015-03-15

    Recent genome-wide association studies reveal that the FAM13A gene is associated with human lung function and a variety of lung diseases, including chronic obstructive pulmonary disease, asthma, lung cancer, and pulmonary fibrosis. The biological functions of Fam13a, however, have not been studied. In an effort to identify novel substrates of B56-containing PP2As, we found that B56-containing PP2As and Akt act antagonistically to control reversible phosphorylation of Fam13a on Ser-322. We show that Ser-322 phosphorylation acts as a molecular switch to control the subcellular distribution of Fam13a. Fam13a shuttles between the nucleus and cytoplasm. When Ser-322 is phosphorylated by Akt, the binding between Fam13a and 14-3-3 is enhanced, leading to cytoplasmic sequestration of Fam13a. B56-containing PP2As dephosphorylate phospho-Ser-322 and promote nuclear localization of Fam13a. We generated Fam13a-knockout mice. Fam13a-mutant mice are viable and healthy, indicating that Fam13a is dispensable for embryonic development and physiological functions in adult animals. Intriguingly, Fam13a has the ability to activate the Wnt pathway. Although Wnt signaling remains largely normal in Fam13a-knockout lungs, depletion of Fam13a in human lung cancer cells causes an obvious reduction in Wnt signaling activity. Our work provides important clues to elucidating the mechanism by which Fam13a may contribute to human lung diseases. © 2015 Jin, Chung, et al. This article is distributed by The American Society for Cell Biology under license from the author(s). Two months after publication it is available to the public under an Attribution–Noncommercial–Share Alike 3.0 Unported Creative Commons License (http://creativecommons.org/licenses/by-nc-sa/3.0).

  6. GEANT4 simulation of a scintillating-fibre tracker for the cosmic-ray muon tomography of legacy nuclear waste containers

    Science.gov (United States)

    Clarkson, A.; Hamilton, D. J.; Hoek, M.; Ireland, D. G.; Johnstone, J. R.; Kaiser, R.; Keri, T.; Lumsden, S.; Mahon, D. F.; McKinnon, B.; Murray, M.; Nutbeam-Tuffs, S.; Shearer, C.; Staines, C.; Yang, G.; Zimmerman, C.

    2014-05-01

    Cosmic-ray muons are highly penetrative charged particles that are observed at the sea level with a flux of approximately one per square centimetre per minute. They interact with matter primarily through Coulomb scattering, which is exploited in the field of muon tomography to image shielded objects in a wide range of applications. In this paper, simulation studies are presented that assess the feasibility of a scintillating-fibre tracker system for use in the identification and characterisation of nuclear materials stored within industrial legacy waste containers. A system consisting of a pair of tracking modules above and a pair below the volume to be assayed is simulated within the GEANT4 framework using a range of potential fibre pitches and module separations. Each module comprises two orthogonal planes of fibres that allow the reconstruction of the initial and Coulomb-scattered muon trajectories. A likelihood-based image reconstruction algorithm has been developed that allows the container content to be determined with respect to the scattering density λ, a parameter which is related to the atomic number Z of the scattering material. Images reconstructed from this simulation are presented for a range of anticipated scenarios that highlight the expected image resolution and the potential of this system for the identification of high-Z materials within a shielded, concrete-filled container. First results from a constructed prototype system are presented in comparison with those from a detailed simulation. Excellent agreement between experimental data and simulation is observed showing clear discrimination between the different materials assayed throughout.

  7. GEANT4 simulation of a scintillating-fibre tracker for the cosmic-ray muon tomography of legacy nuclear waste containers

    Energy Technology Data Exchange (ETDEWEB)

    Clarkson, A.; Hamilton, D.J.; Hoek, M.; Ireland, D.G. [SUPA, School of Physics and Astronomy, University of Glasgow, Kelvin Building, University Avenue, Glasgow G12 8QQ, Scotland (United Kingdom); Johnstone, J.R. [National Nuclear Laboratory, Central Laboratory, Sellafield, Seascale, Cumbria CA20 1PG, England (United Kingdom); Kaiser, R.; Keri, T.; Lumsden, S. [SUPA, School of Physics and Astronomy, University of Glasgow, Kelvin Building, University Avenue, Glasgow G12 8QQ, Scotland (United Kingdom); Mahon, D.F., E-mail: David.Mahon@Glasgow.ac.uk [SUPA, School of Physics and Astronomy, University of Glasgow, Kelvin Building, University Avenue, Glasgow G12 8QQ, Scotland (United Kingdom); McKinnon, B.; Murray, M.; Nutbeam-Tuffs, S. [SUPA, School of Physics and Astronomy, University of Glasgow, Kelvin Building, University Avenue, Glasgow G12 8QQ, Scotland (United Kingdom); Shearer, C.; Staines, C. [National Nuclear Laboratory, Central Laboratory, Sellafield, Seascale, Cumbria CA20 1PG, England (United Kingdom); Yang, G. [SUPA, School of Physics and Astronomy, University of Glasgow, Kelvin Building, University Avenue, Glasgow G12 8QQ, Scotland (United Kingdom); Zimmerman, C. [National Nuclear Laboratory, Central Laboratory, Sellafield, Seascale, Cumbria CA20 1PG, England (United Kingdom)

    2014-05-11

    Cosmic-ray muons are highly penetrative charged particles that are observed at the sea level with a flux of approximately one per square centimetre per minute. They interact with matter primarily through Coulomb scattering, which is exploited in the field of muon tomography to image shielded objects in a wide range of applications. In this paper, simulation studies are presented that assess the feasibility of a scintillating-fibre tracker system for use in the identification and characterisation of nuclear materials stored within industrial legacy waste containers. A system consisting of a pair of tracking modules above and a pair below the volume to be assayed is simulated within the GEANT4 framework using a range of potential fibre pitches and module separations. Each module comprises two orthogonal planes of fibres that allow the reconstruction of the initial and Coulomb-scattered muon trajectories. A likelihood-based image reconstruction algorithm has been developed that allows the container content to be determined with respect to the scattering density λ, a parameter which is related to the atomic number Z of the scattering material. Images reconstructed from this simulation are presented for a range of anticipated scenarios that highlight the expected image resolution and the potential of this system for the identification of high-Z materials within a shielded, concrete-filled container. First results from a constructed prototype system are presented in comparison with those from a detailed simulation. Excellent agreement between experimental data and simulation is observed showing clear discrimination between the different materials assayed throughout.

  8. Nuclear Assessment

    Institute of Scientific and Technical Information of China (English)

    CHARLES; K.; EBINGER; JOHN; P.; BANKS

    2010-01-01

    The United States needs a comprehensive policy and market-based solutions to address the challenges and demands of energy provision in President Barack Obama’s State of the Union address in January 2009, he called for the building of "a new generation of safe, clean nuclear power plants." This was followed by his high- profile speech in Prague in April 2009,

  9. Production of transgenic cashmere goat embryos expressing red fluorescent protein and containing IGF1 hair-follicle-cell specific expression cassette by somatic cell nuclear transfer

    Institute of Scientific and Technical Information of China (English)

    BOU; ShorGan

    2009-01-01

    In the present study, cashmere goat fetal fibroblasts were transfected with pCDsR-KI, a hair-follicle-cell specific expression vector for insulin-like growth factor 1 (IGF1) that contains two markers for selection (red fluorescent protein gene and neomycin resistant gene). The transgenic fibroblasts cell lines were obtained after G418 selection. Prior to the somatic cell nuclear transfer (SCNT), the maturation rate of caprine cumulus oocytes complexes (COCs) was optimized to an in vitro maturation time of 18 h. Parthenogenetic ooctyes were used as a model to investigate the effect of two activation methods, one with calcium ionophore IA23187 plus 6-DMAP and the other with ethanol plus 6-DMAP. The cleavage rates after 48 h were respectively 88.7% and 86.4%, with no significant difference (P>0.05). There was no significant difference between the cleavage rate and the blastocyst rate in two different media (SO- Faa and CR1aa; 86.3% vs 83.9%, P>0.05 and 23.1% vs 17.2%,P>0.05). The fusion rate of a 190 V/mm group (62.4%) was significantly higher than 130 V/mm (32.8%) and 200 V/mm (42.9%), groups (P<0.05). After transgenic somatic cell nuclear transfer (TSCNT) manipulation, 203 reconstructed embryos were obtained in which the cleavage rate after in vitro development (IVD) for 48 h was 79.3% (161/203). The blastocyst rate after IVD for 7 to 9 d was 15.3% (31/203). There were 17 embryos out of 31 strongly ex- pressing red fluorescence. Two of the red fluorescent blastocysts were randomly selected to identify transgene by polymerase chain reaction. Both were positive. These results showed that: (i) RFP and Neor genes were correctly expressed indicating that transgenic somatic cell lines and positive trans- genic embryos were obtained; (ii) one more selection at the blastocyst stage was necessary although the donor cells were transgenic positive, because only partially transgenic embryos expressing red fluorescence were obtained; and (iii) through TSCNT manipulation and

  10. Production of transgenic cashmere goat embryos expressing red fluorescent protein and containing IGF1 hair-follicle-cell specific expression cassette by somatic cell nuclear transfer

    Institute of Scientific and Technical Information of China (English)

    GUO XuDong; YANG DongShan; Ao XuDong; WU Xia; LI GuangPeng; WANG LingLing; BAO MingTao; XUE Lian; BOU ShorGan

    2009-01-01

    In the present study, cashmere goat fetal flbroblasta were transfected with pCDsR-KI, a hair-follicle-cell specific expression vector for insulin-like growth factor 1(IGF1) that contains two markers for selection (red fluorescent protein gene and neomycin resistant gene). The transgenic fibroblasta cell lines were obtained after G418 selection. Prior to the somatic cell nuclear transfer (SCNT), the maturation rate of caprine cumulus oocytes complexes (COCs) was optimized to an in vitro maturation time of 18 h.Parthenogenetic ooctyes were used as a model to Investigate the effect of two activation methods, one with calcium ionophore IA23187 plus 6-DMAP and the other with ethanol plus 6-DMAP. The cleavage rates after 48 h were respectively 88.7% and 86.4%, with no significant difference (P>0.05). There was no significant difference between the cleavage rate and the blastocyst rate in two different media (SO-Faa and CR1aa; 86.3% va 83.9%, P>0.05 and 23.1% vs 17.2%, P>0.05). The fusion rate of a 190 V/mm group (62.4%) was significantly higher than 130 V/mm (32.8%) and 200 V/mm (42.9%), groups (P<0.05).After transgenic somatic cell nuclear transfer (TSCNT) manipulation, 203 reconstructed embryos were obtained in which the cleavage rate after in vitro development (IVD) for 48 h was 79.3% (161/203). The blastocyst rate after IVD for 7 to 9 d was 15.3% (31/203). There were 17 embryos out of 31 strongly ex-pressing red fluorescence. Two of the red fluorescent blastocysta were randomly selected to identify transgene by polymeraee chain reaction. Both were positive. These results showed that: (i) RFP and Neo genes were correctly expressed indicating that transgenlc somatic cell lines and positive trans-genic embryos were obtained; (ii) one more selection at the blastocyst stage was necessary although the donor cells were transgenic positive, because only partially transgenic embryos expressing red fluorescence were obtained; and (iii) through TSCNT manipulation and

  11. Editorial Board Indexed in Current Issue Coming Issue Archives Submission » Contact Us Incorporation of Nuclear Wastes in LIP and Uranium Containing LIP Glasses.

    Directory of Open Access Journals (Sweden)

    A. Ghosh

    2014-03-01

    Full Text Available Glasses in lead-iron phosphate (LIP system loaded with simulated nuclear waste, were melted in the temperature range750-950oC. Some of the LIP glasses were mixed with uranium salt. The pH determinations of the leachate solution at normal temperature show some interesting trends. Leaching study of these glasses with a maximum time period of 300 hrs. were conducted under Soxhlet distillation condition with distilled water. Weight losses and residual activities by ‘Radiotracer technique’ were followed with respect to cumulative time period of leaching. For some LIP-glass samples containing uranium the leach rates as calculated from BET surface area measurements. They were in the range 8.2 x 10–4 to 1.8 x 10–3 g.m-2.hr-1 at 90°C. DTA endotherms occur at ~400oC and ~900oC for the LIP glasses. FTIR studies show absorptions at ~532, ~1025, ~1620-1640, ~2365 and ~3440-3490 cm–1. SEM of some selected glasses was reported. The variation of different properties was explained in terms of the changes in the ionic potentials of the different modifier ions. The model structure of glasses has been considered taking the dual role of and as glass formers/ modifiers which ultimately has an effect on the chemical durability of these glasses.

  12. A review of the Generic Design Assessment (GDA) Public Dialogue Pilot (2015) for new nuclear build in the UK: lessons for engagement theory and practice.

    Science.gov (United States)

    Whitton, John; Parry, Ioan; Grundy, Colette; Lillycrop, Annabelle; Ross, David

    2016-06-01

    We have discussed previously that a community-based, asset-based approach is required to achieve any sense of how social sustainability can be defined in a community setting within the context of energy developments. Our approach aims to initiate a lasting change within 'energy' communities through building social capital; focusing on community assets not deficits to define their social priorities. Through deliberation, we develop an understanding of social sustainability so that a community is well placed to enter discussions with government and industry regarding large energy developments that will directly affect them. We review the 2015 Generic Design Assessment (GDA) Public Dialogue Pilot process for potential new nuclear reactors in the UK. We examine the aims of the dialogue, giving particular attention to a comparison between the national sampling of citizens for the GDA and the local community-based, deliberative approach we have proposed previously. We find an ongoing tension between 'national' engagement processes (such as the GDA Public Dialogue Pilot process) and the specific requirements of those energy communities that live adjacent or close to energy infrastructure, manifested here by a conflict between the requirements of the convenor and those of participants regarding priority issues for discussion. We also reveal a paradox; despite participant preference for a remote, internet-based engagement process, they agreed that face to face contact is a priority to encourage trust building between participants and the convenor of the process-a desired outcome of the process. The GDA Public Dialogue Pilot process has demonstrated that stakeholders are willing to engage with and be more directly involved in local energy-related decisions that affect them directly, provided there is opportunity to discuss locally-relevant and site-specific issues in addition to those of a broader nature. There exists a disparity and conflict between 'national' engagement

  13. Event classification related to overflow of solvent containing uranium according to the INES scale (International Nuclear and Radiological Event Scale); Classificacao do evento de transbordamento de solvente contendo uranio segundo a escala INES (International Nuclear and Radiological Event Scale)

    Energy Technology Data Exchange (ETDEWEB)

    Dourado, Eneida R.G.; Assis, Juliana T. de; Lage, Ricardo F., E-mail: cneida@inb.gov.br, E-mail: julianateixeira@inb.gov.br, E-mail: rlage@inb.gov.br [lndustrias Nucleares do Brasil S/A (CLISE.P/INB), Rio de Janeiro, RJ (Brazil). Coordenacao de Licenciamento Nuclear e Ambiental, Saude e Seguranca; Lopes, Karina B., E-mail: karina@inb.gov.br [lndustrias Nucleares do Brasil S/A (CPRAD/INB), Rio de Janeiro, RJ (Brazil). Coordenacao de Protecao Radiologica

    2013-11-01

    This paper aims to frame the event overflow organic solvent rich in uranium, from a decanter of ore beneficiation plant, caused by the fall in the supply of electricity, according to the criteria established by the International Nuclear Event Scale and radiological (INES), facilitating the understanding of the occurrence and communication with the public regarding the radiation safety aspects involved. With the fall of electricity, routine procedures in situations of installation stop were performed, however, due to operational failure, the valve on the transfer line liquor was not closed. Thus, the mixer continued being fed with liquor, that led the consequent leakage of solvent loaded with uranium. It reached the drainage system, and the box of rainwater harvesting of the plant. However, immediately after the detection of the event, corrective actions were initiated and the overflow was contained. Regulatory agencies followed the removal of the solvent and on the results of the analysis of environmental monitoring, found that the event did not provide exposure to workers or any other impact. Therefore, comparing the characteristics of the event and the guidelines proposed by the INES scale, it is concluded that the classification of the event is below scale/level 0, confirming the absence of risk to the local population, workers and the environment.

  14. Nuclear questions

    Energy Technology Data Exchange (ETDEWEB)

    Durrani, M. [Physics World (United Kingdom)

    2006-01-01

    The future of nuclear power has returned to centre stage. Freezing weather on both sides of the Atlantic and last month's climate-change talks in Montreal have helped to put energy and the future of nuclear power right back on the political agenda. The issue is particularly pressing for those countries where existing nuclear stations are reaching the end of their lives. In the UK, prime minister Tony Blair has commissioned a review of energy, with a view to deciding later this year whether to build new nuclear power plants. The review comes just four years after the Labour government published a White Paper on energy that said the country should keep the nuclear option open but did not follow this up with any concrete action. In Germany, new chancellor and former physicist Angela Merkel is a fan of nuclear energy and had said she would extend the lifetime of its nuclear plants beyond 2020, when they are due to close. However, that commitment has had to be abandoned, at least for the time being, following negotiations with her left-wing coalition partners. The arguments in favour of nuclear power will be familiar to all physicists - it emits almost no carbon dioxide and can play a vital role in maintaining a diverse energy supply. To over-rely on imported supplies of oil and gas can leave a nation hostage to fortune. The arguments against are equally easy to list - the public is scared of nuclear power, it generates dangerous waste with potentially huge clean-up costs, and it is not necessarily cheap. Nuclear plants could also be a target for terrorist attacks. Given political will, many of these problems can be resolved, or at least tackled. China certainly sees the benefits of nuclear power, as does Finland, which is building a new 1600 MW station - the world's most powerful - that is set to open in 2009. Physicists, of course, are essential to such developments. They play a vital role in ensuring the safety of such plants and developing new types of

  15. Tox21Challenge to build predictive models of nuclear receptor and stress response pathways as mediated by exposure to environmental chemicals and drugs

    Directory of Open Access Journals (Sweden)

    Ruili eHuang

    2016-01-01

    Full Text Available Tens of thousands of chemicals with poorly understood biological properties are released into the environment each day. High-throughput screening (HTS is potentially a more efficient and cost-effective alternative to traditional toxicity tests. Using HTS, one can profile chemicals for potential adverse effects and prioritize a manageable number for more in-depth testing. Importantly, it can provide clues to mechanism of toxicity. The Tox21 program has generated >50 million quantitative high-throughput screening (qHTS data points. A library of several thousands of compounds, including environmental chemicals and drugs, is screened against a panel of nuclear receptor and stress response pathway assays. The National Center for Advancing Translational Sciences (NCATS has organized an International data challenge in order to crowd-source data and build predictive toxicity models. This Challenge asks a crowd of researchers to use these data to elucidate the extent to which the interference of biochemical and cellular pathways by compounds can be inferred from chemical structure data. The data generated against the Tox21 library served as the training set for this modeling Challenge. The competition attracted participants from 18 different countries to develop computational models aimed at better predicting chemical toxicity. The winning models from nearly 400 model submissions all achieved >80% accuracy. Several models exceeded 90% accuracy, which was measured by area under the receiver operating characteristic curve (AUC-ROC. Combining the winning models with the knowledge already gained from Tox21 screening data are expected to improve the community’s ability to prioritize novel chemicals with respect to potential human health concern.

  16. Recommended values for the distribution coefficient (Kd) to be used in dose assessments for decommissioning the Zion Nuclear Power Plant

    Energy Technology Data Exchange (ETDEWEB)

    Sullivan T.

    2014-06-09

    ZionSolutions is in the process of decommissioning the Zion Nuclear Power Plant. The site contains two reactor Containment Buildings, a Fuel Building, an Auxiliary Building, and a Turbine Building that may be contaminated. The current decommissioning plan involves removing all above grade structures to a depth of 3 feet below grade. The remaining underground structures will be backfilled. The remaining underground structures will contain low amounts of residual licensed radioactive material. An important component of the decommissioning process is the demonstration that any remaining activity will not cause a hypothetical individual to receive a dose in excess of 25 mrem/y as specified in 10CFR20 SubpartE.

  17. Recommended values for the distribution coefficient (Kd) to be used in dose assessments for decommissioning the Zion Nuclear Power Plant

    Energy Technology Data Exchange (ETDEWEB)

    Sullivan, T. [Brookhaven National Lab. (BNL), Upton, NY (United States)

    2014-09-24

    ZionSolutions is in the process of decommissioning the Zion Nuclear Power Plant. The site contains two reactor Containment Buildings, a Fuel Building, an Auxiliary Building, and a Turbine Building that may be contaminated. The current decommissioning plan involves removing all above grade structures to a depth of 3 feet below grade. The remaining underground structures will be backfilled. The remaining underground structures will contain low amounts of residual licensed radioactive material. An important component of the decommissioning process is the demonstration that any remaining activity will not cause a hypothetical individual to receive a dose in excess of 25 mrem/y as specified in 10CFR20 SubpartE.

  18. Building Protection Against External Ionizing Fallout Radiation

    Energy Technology Data Exchange (ETDEWEB)

    Dillon, Michael B. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Homann, Steven G. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States)

    2016-12-01

    A nuclear explosion has the potential to injure or kill tens to hundreds of thousands of people through exposure to fallout (external gamma) radiation. Existing buildings can protect their occupants (reducing external radiation exposures) by placing material and distance between fallout particles and indoor individuals. This protection is not well captured in current fallout risk assessment models and so the US Department of Defense is implementing the Regional Shelter Analysis methodology to improve the ability of the Hazard Prediction and Assessment Capability (HPAC) model to account for building protection. This report supports the HPAC improvement effort by identifying a set of building attributes (next page) that, when collectively specified, are sufficient to calculate reasonably accurate, i.e., within a factor of 2, fallout shelter quality estimates for many individual buildings. The set of building attributes were determined by first identifying the key physics controlling building protection from fallout radiation and then assessing which building attributes are relevant to the identified physics. This approach was evaluated by developing a screening model (PFscreen) based on the identified physics and comparing the screening model results against the set of existing independent experimental, theoretical, and modeled building protection estimates. In the interests of transparency, we have developed a benchmark dataset containing (a) most of the relevant primary experimental data published by prior generations of fallout protection scientists as well as (b) the screening model results.

  19. Enhanced expression of WD repeat-containing protein 35 via nuclear factor-kappa B activation in bupivacaine-treated Neuro2a cells.

    Directory of Open Access Journals (Sweden)

    Lei Huang

    Full Text Available The family of WD repeat proteins comprises a large number of proteins and is involved in a wide variety of cellular processes such as signal transduction, cell growth, proliferation, and apoptosis. Bupivacaine is a sodium channel blocker administered for local infiltration, nerve block, epidural, and intrathecal anesthesia. Recently, we reported that bupivacaine induces reactive oxygen species (ROS generation and p38 mitogen-activated protein kinase (MAPK activation, resulting in an increase in the expression of WD repeat-containing protein 35 (WDR35 in mouse neuroblastoma Neuro2a cells. It has been shown that ROS activate MAPK through phosphorylation, followed by activation of nuclear factor-kappa B (NF-κB and activator protein 1 (AP-1. The present study was undertaken to test whether NF-κB and c-Jun/AP-1 are involved in bupivacaine-induced WDR35 expression in Neuro2a cells. Bupivacaine activated both NF-κB and c-Jun in Neuro2a cells. APDC, an NF-κB inhibitor, attenuated the increase in NF-κB activity and WDR35 protein expression in bupivacaine-treated Neuro2a cells. GW9662, a selective peroxisome proliferator-activated receptor-γ antagonist, enhanced the increase in NF-κB activity and WDR35 protein expression in bupivacaine-treated Neuro2a cells. In contrast, c-Jun siRNA did not inhibit the bupivacaine-induced increase in WDR35 mRNA expression. These results indicate that bupivacaine induces the activation of transcription factors NF-κB and c-Jun/AP-1 in Neuro2a cells, while activation of NF-κB is involved in bupivacaine-induced increases in WDR35 expression.

  20. Nuclear Assessment

    Institute of Scientific and Technical Information of China (English)

    CHARLES K.EBINGER; JOHN P.BANKS

    2010-01-01

    @@ In President Barack Obama's State of the Union address in January 2009,he called for the building of "a new generation of safe,clean nuclear power plants" This was followed by his highprofile speech in Prague in April 2009,in which he noted the need "to harness the power of nuclear energy on behalf of our efforts to combat climate change."In December 2009 in Copenhagen,he pledged the United States will reduce carbon dioxide (CO2) emissions 17 percent from 2005 levels by 2020.

  1. Theoretical and Experimental Thermal Performance Analysis of Building Shell Components Containing Blown Fiber Glass Insulation Enhanced with Phase Change Material (PCM)

    Energy Technology Data Exchange (ETDEWEB)

    Miller, William A [ORNL; Kosny, Jan [ORNL; Yarbrough, David W [ORNL; Childs, Phillip W [ORNL; Shrestha, Som S [ORNL; Atchley, Jerald Allen [ORNL; Bianchi, Marcus V [ORNL; Smith, John B [ORNL; Fellinger, Thomas [ORNL; Kossecka, Elizabeth [Institute of Fundamental Technological Research, Polish Academy of Sciences; Lee, Edwin S [ORNL

    2010-01-01

    Different types of Phase Change Materials (PCMs) have been tested as dynamic components in buildings during the last 4 decades. Most historical studies have found that PCMs enhance building energy performance. Some PCM-enhanced building materials, like PCM-gypsum boards or PCM-impregnated concretes have already found their limited applications in different countries. Today, continued improvements in building envelope technologies suggest that throughout Southern and Central US climates, residences may soon be routinely constructed with PCM in order to maximize insulation effectiveness and maintain low heating and cooling loads. The proposed paper presents experimental and numerical results from thermal performance studies. These studies focus on blown fiber glass insulation modified with a novel spray-applied microencapsulated PCM. Experimental results are reported for both laboratory-scale and full-size building elements tested in the field. In order to confirm theoretical predictions, PCM enhanced fiber glass insulation was evaluated in a guarded hot box facility to demonstrate heat flow reductions when one side of a test wall is subjected to a temperature increase. The laboratory work showed reductions in heat flow of 30% due to the presence of approximately 20 wt % PCM in the insulation. Field testing of residential attics insulated with blown fiber glass and PCM was completed in Oak Ridge, Tennessee. Experimental work was followed by detailed whole building EnergyPlus simulations in order to generate energy performance data for different US climates. In addition, a series of numerical simulations and field experiments demonstrated a potential for application of a novel PCM fiber glass insulation as enabling technology to be utilized during the attic thermal renovations.

  2. Nuclear energy data 2011

    CERN Document Server

    2011-01-01

     . Nuclear Energy Data, the OECD Nuclear Energy Agency's annual compilation of statistics and country reports on nuclear energy, contains official information provided by OECD member country governments on plans for new nuclear plant construction, nuclear fuel cycle developments as well as current and projected nuclear generating capacity to 2035. For the first time, it includes data for Chile, Estonia, Israel and Slovenia, which recently became OECD members. Key elements of this edition show a 2% increase in nuclear and total electricity production and a 0.5% increase in nuclear generating ca

  3. Disposal of high level nuclear wastes: Thermodynamic equilibrium and environment ethics

    Institute of Scientific and Technical Information of China (English)

    RANA Mukhtar Ahmed

    2009-01-01

    Contamination of soil, water or air, due to a failure of containment or disposal of high level nuclear wastes, can potentially cause serious hazards to the environment or human health. Essential elements of the environment and radioactivity dangers to it are illustrated. Issues of high level nuclear waste disposal are discussed with a focus on thermodynamic equilibrium and environment ethics. Major aspects of the issues are analyzed and described briefly to build a perception of risks involved and ethical implications. Nuclear waste containment repository should be as close as possible to thermodynamic equilibrium. A clear demonstration about safety aspects of nuclear waste management is required in gaining public and political confidence in any possible scheme of permanent disposal. Disposal of high level nuclear waste offers a spectrum of environment connected challenges and a long term future of nuclear power depends on the environment friendly solution of the problem of nuclear wastes.

  4. Technical evaluation of the electrical, instrumentation, and control design aspects of the override of containment purge valve isolation and other engineered safety feature signals for the Fort Calhoun Nuclear Power Plant

    Energy Technology Data Exchange (ETDEWEB)

    Hackett, D.B.

    1980-01-01

    This report documents the technical evaluation of the electrical, instrumentation, and control design aspects of the override of containment purge valve isolation and other engineered safety feature signals for the Fort Calhoun nuclear power plant. The review criteria are based on IEEE Std-279-1971 requirements for the safety signals to all purge and ventilation isolation valves. This report is supplied as part of the Selected Electrical, Instrumentation, and Control Systems Issues Program being conducted for the US Nuclear Regulatory Commission by Lawrence Livermore Laboratory.

  5. Triangle Universities Nuclear Laboratory

    Energy Technology Data Exchange (ETDEWEB)

    1991-01-01

    This report contains brief papers that discusses the following topics: Fundamental Symmetries in the Nucleus; Internucleon Interactions; Dynamics of Very Light Nuclei; Facets of the Nuclear Many-Body Problem; and Nuclear Instruments and Methods.

  6. Report on design and technical standard planning of vibration controlling structure on the buildings, in the Tokai Reprocessing Facility, Power Reactor and Nuclear Fuel Development Corporation

    Energy Technology Data Exchange (ETDEWEB)

    Uryu, Mitsuru; Terada, Shuji; Shinohara, Takaharu; Yamazaki, Toshihiko; Nakayama, Kazuhiko [Power Reactor and Nuclear Fuel Development Corp., Tokai, Ibaraki (Japan). Tokai Works; Kondo, Toshinari; Hosoya, Hisashi

    1997-10-01

    The Tokai reprocessing facility buildings are constituted by a lower foundation, vibration controlling layers, and upper structure. At the vibration controlling layer, a laminated rubber aiming support of the building load and extension of the eigenfrequency and a damper aiming absorption of earthquake energy are provided. Of course, the facility buildings are directly supported at the arenaceous shale (Taga Layer) of the Miocene in the Neogene confirmed to the stablest ground, as well the buildings with high vibration resistant importance in Japan. This report shows that when the vibration controlling structure is adopted for the reprocessing facility buildings where such high vibration resistance is required, reduction of input acceleration for equipments and pipings can be achieved and the earthquake resistant safety can also be maintained with sufficient tolerance and reliability. (G.K.)

  7. Report on design and technical standard planning of vibration controlling structure on the buildings, in the Tokai Reprocessing Facility, Power Reactor and Nuclear Fuel Development Corporation

    Energy Technology Data Exchange (ETDEWEB)

    Uryu, Mitsuru; Terada, Shuji; Shinohara, Takaharu; Yamazaki, Toshihiko; Nakayama, Kazuhiko [Power Reactor and Nuclear Fuel Development Corp., Tokai, Ibaraki (Japan). Tokai Works; Kondo, Toshinari; Hosoya, Hisashi

    1997-10-01

    The Tokai reprocessing facility buildings are constituted by a lower foundation, vibration controlling layers, and upper structure. At the vibration controlling layer, a laminated rubber aiming support of the building load and extension of the eigenfrequency and a damper aiming absorption of earthquake energy are provided. Of course, the facility buildings are directly supported at the arenaceous shale (Taga Layer) of the Miocene in the Neogene confirmed to the stablest ground, as well the buildings with high vibration resistant importance in Japan. This report shows that when the vibration controlling structure is adopted for the reprocessing facility buildings where such high vibration resistance is required, reduction of input acceleration for equipments and pipings can be achieved and the earthquake resistant safety can also be maintained with sufficient tolerance and reliability. (G.K.)

  8. Technology Roadmaps: Nuclear Energy

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2010-07-01

    This nuclear energy roadmap has been prepared jointly by the IEA and the OECD Nuclear Energy Agency (NEA). Unlike most other low-carbon energy sources, nuclear energy is a mature technology that has been in use for more than 50 years. The latest designs for nuclear power plants build on this experience to offer enhanced safety and performance, and are ready for wider deployment over the next few years. Several countries are reactivating dormant nuclear programmes, while others are considering nuclear for the first time. China in particular is already embarking on a rapid nuclear expansion. In the longer term, there is great potential for new developments in nuclear energy technology to enhance nuclear's role in a sustainable energy future.

  9. Regulation of cell proliferation by ERK and signal-dependent nuclear translocation of ERK is dependent on Tm5NM1-containing actin filaments.

    Science.gov (United States)

    Schevzov, Galina; Kee, Anthony J; Wang, Bin; Sequeira, Vanessa B; Hook, Jeff; Coombes, Jason D; Lucas, Christine A; Stehn, Justine R; Musgrove, Elizabeth A; Cretu, Alexandra; Assoian, Richard; Fath, Thomas; Hanoch, Tamar; Seger, Rony; Pleines, Irina; Kile, Benjamin T; Hardeman, Edna C; Gunning, Peter W

    2015-07-01

    ERK-regulated cell proliferation requires multiple phosphorylation events catalyzed first by MEK and then by casein kinase 2 (CK2), followed by interaction with importin7 and subsequent nuclear translocation of pERK. We report that genetic manipulation of a core component of the actin filaments of cancer cells, the tropomyosin Tm5NM1, regulates the proliferation of normal cells both in vitro and in vivo. Mouse embryo fibroblasts (MEFs) lacking Tm5NM1, which have reduced proliferative capacity, are insensitive to inhibition of ERK by peptide and small-molecule inhibitors, indicating that ERK is unable to regulate proliferation of these knockout (KO) cells. Treatment of wild-type MEFs with a CK2 inhibitor to block phosphorylation of the nuclear translocation signal in pERK resulted in greatly decreased cell proliferation and a significant reduction in the nuclear translocation of pERK. In contrast, Tm5NM1 KO MEFs, which show reduced nuclear translocation of pERK, were unaffected by inhibition of CK2. This suggested that it is nuclear translocation of CK2-phosphorylated pERK that regulates cell proliferation and this capacity is absent in Tm5NM1 KO cells. Proximity ligation assays confirmed a growth factor-stimulated interaction of pERK with Tm5NM1 and that the interaction of pERK with importin7 is greatly reduced in the Tm5NM1 KO cells.

  10. Diversidade de criadouros e tipos de imóveis freqüentados por Aedes albopictus e Aedes aegypti Diversity of oviposition containers and buildings where Aedes albopictus and Aedes aegypti can be found

    Directory of Open Access Journals (Sweden)

    Vanderlei C da Silva

    2006-12-01

    Full Text Available OBJETIVOS: Verificar a diversidade de criadouros e tipos de imóveis freqüentados por fêmeas de Aedes albopictus e Aedes aegypti. MÉTODOS: O estudo foi realizado nos anos de 2002 e 2003 no bairro de Campo Grande, Rio de Janeiro, RJ. Realizou-se pesquisa larvária em diferentes tipos de imóveis. As larvas encontradas foram identificadas em laboratório. A freqüência de larvas dessas duas espécies foi computada nos diversos criadouros disponíveis. Foram calculados os índices de infestação predial e de Breteau, as diferenças foram testadas pelo qui-quadrado. RESULTADOS: Os tipos de imóveis positivos para os aedinos foram: residências (83,9% do total; igrejas, escolas, clubes (6,8%; terrenos baldios (6,4%; e comércios (2,8%. Das 9.153 larvas, 12,0% eram de Aedes albopictus e 88,0% de Aedes aegypti. Para aquela espécie, os recipientes onde foram mais encontradas foram ralos (25,4%, latas, garrafas, vasilhames (23,9% e vasos com plantas (16,2%. Aedes aegypti mostrou-se mais freqüente nos criadouros que Aedes albopictus (chi2=145,067, pOBJECTIVE: To assess the diversity of oviposition containers and buildings where females of Aedes albopictus and Aedes aegypti can be found. METHODS: A study was carried out in the city of Rio de Janeiro, Southern Brazil, between 2002 and 2003. Larvae in different types of buildings were investigated, and immature forms found were then sent to the laboratory for identification. The larval frequency for both mosquitoes was estimated in the oviposition containers available. The Breteau index and the building infestation index were calculated and differences were tested using the Chi-square test. RESULTS: The types of buildings that were positive for Aedes albopictus and Aedes aegypti were: dwellings (83.9%; churches, schools, clubs (6.8%; vacant land (6.4%; and businesses (2.8%. Of 9,153 larvae collected, 12.0% were Aedes albopictus and 88.0% were Aedes aegypti. Aedes albopictus were mostly found in drains

  11. Nuclear disarmament verification

    Energy Technology Data Exchange (ETDEWEB)

    DeVolpi, A.

    1993-12-31

    Arms control treaties, unilateral actions, and cooperative activities -- reflecting the defusing of East-West tensions -- are causing nuclear weapons to be disarmed and dismantled worldwide. In order to provide for future reductions and to build confidence in the permanency of this disarmament, verification procedures and technologies would play an important role. This paper outlines arms-control objectives, treaty organization, and actions that could be undertaken. For the purposes of this Workshop on Verification, nuclear disarmament has been divided into five topical subareas: Converting nuclear-weapons production complexes, Eliminating and monitoring nuclear-weapons delivery systems, Disabling and destroying nuclear warheads, Demilitarizing or non-military utilization of special nuclear materials, and Inhibiting nuclear arms in non-nuclear-weapons states. This paper concludes with an overview of potential methods for verification.

  12. Sensitivity of Sump Water Temperature to Containment Integrity

    Energy Technology Data Exchange (ETDEWEB)

    Jang, Misuk; Kim, Seoung Rae [Nuclear Engineering Service and Solution, Daejeon (Korea, Republic of)

    2014-05-15

    This paper is focused on the containment behavior analysis in the above described cases using GOTHIC-IST (generation of thermal-hydraulic information for containments, industry standard toolset). GOTHIC-IST version 7.2a is an integrated, general purpose thermal-hydraulics software package for design, licensing, safety and operating analysis of nuclear power plant containments and other confinement buildings. In this study, we perform the sensitivity the sump water temperature to containment integrity. For 35% RIH break accident with the malfunction of spray system, local air coolers, ECC(emergency core cooling) pump and heat exchanger, the peak pressure at boiler room do not exceed the design pressure 124kPa(g) of the containment and containment integrity is secured. If accompanied the malfunction of heat exchanger or pump in the time of low pressure safety injection, of ECCS, it will be one of the aggravating factors to the integrity of core and containment.

  13. Chinese Nuclear Science Basic Data Base (CNSBDB)

    Institute of Scientific and Technical Information of China (English)

    2002-01-01

    A new research project on "Development of the Chinese Nuclear Science Basic Database (CNSBDB)for Fundamental Researches of Nuclear Physics and Interrelated Subjects, and Requirements of NuclearPower and Nuclear Technologies Application" has been commenced. The CNSBDB contains thefollowing eight segments: 1) Information on Nuclear Science (INFO); 2) Nuclear Structure Data Base(NSDB); 3) Nuclear Decay Data Base (NDDB); 4) Nuclear Reaction Data Base (NRDB); 5) Nuclear

  14. Coat proteins of Rice tungro bacilliform virus and Mungbean yellow mosaic virus contain multiple nuclear-localization signals and interact with importin alpha.

    Science.gov (United States)

    Guerra-Peraza, O; Kirk, D; Seltzer, V; Veluthambi, K; Schmit, A C; Hohn, T; Herzog, E

    2005-06-01

    Transport of the viral genome into the nucleus is an obligatory step in the replication cycle of plant pararetro- and geminiviruses. In both these virus types, the multifunctional coat protein (CP) is thought to be involved in this process. Here, a green fluorescent protein tagging approach was used to demonstrate nuclear import of the CPs of Rice tungro bacilliform virus (RTBV) and Mungbean yellow mosaic virus--Vigna (MYMV) in Nicotiana plumbaginifolia protoplasts. In both cases, at least two nuclear localization signals (NLSs) were identified and characterized. The NLSs of RTBV CP are located within both N- and C-terminal regions (residues 479KRPK/497KRK and 744KRK/758RRK), and those of MYMV CP within the N-terminal part (residues 3KR and 41KRRR). The MYMV and RTBV CP NLSs resemble classic mono- and bipartite NLSs, respectively. However, the N-terminal MYMV CP NLS and both RTBV CP NLSs show peculiarities in the number and position of basic residues. In vitro pull-down assays revealed interaction of RTBV and MYMV CPs with the nuclear import factor importin alpha, suggesting that both CPs are imported into the nucleus via an importin alpha-dependent pathway. The possibility that this pathway could serve for docking of virions to the nucleus is discussed.

  15. mer-[Fe(pcq)(CN)3]-: a novel cyanide-containing building block and its application to assembling cyanide-bridged trinuclear FeIII2MnII complexes [pcq- = 8-(pyridine-2-carboxamido)quinoline anion].

    Science.gov (United States)

    Ni, Zhong-Hai; Kou, Hui-Zhong; Zhang, Li-Fang; Ni, Wei-Wei; Jiang, Yun-Bo; Cui, Ai-Li; Ribas, Joan; Sato, Osamu

    2005-12-26

    A new cyanide-containing building block K[Fe(pcq)(CN)(3)] [1; pcq(-) = 8-(pyridine-2-carboxamido)quinoline anion] containing a low-spin Fe(III) center with three cyanide groups in a meridional arrangement has been successfully designed and synthesized. Three cyanide-bridged trinuclear Fe(III)(2)Mn(II) complexes, [Fe(pcq)(CN)(3)](2)[Mn(CH(3)OH)(2)(H(2)O)(2)].2H(2)O (2), [Fe(pcq)(CN)(3)](2)[Mn(bipy)(2)].CH(3)OH.2H(2)O (3), and [Fe(pcq)(CN)(3)](2)[Mn(phen)(2)].CH(3)OH.2H(2)O (4), have been synthesized and structurally characterized. The magnetic susceptibilities of the three heterometallic complexes have been investigated.

  16. Phylogeny of nuclear-encoded plastid-targeted GAPDH gene supports separate origins for the peridinin- and the fucoxanthin derivative-containing plastids of dinoflagellates.

    Science.gov (United States)

    Takishita, Kiyotaka; Ishida, Ken-Ichiro; Maruyama, Tadashi

    2004-12-01

    Although most photosynthetic dinoflagellates have plastids with peridinin, the three dinoflagellate genera Karenia, Karlodinium, and Takayama possess anomalously pigmented plastids that contain fucoxanthin and its derivatives (19'-hexanoyloxy-fucoxanthin and 19'-butanoyloxy-fucoxanthin) instead of the peridinin. This pigment composition is similar to that of haptophytes. All peridinin-containing dinoflagellates investigated so far have at least two types of glyceraldehyde-3-phosphate dehydrogenase (GAPDH): cytosolic and plastid-targeted forms. In the present study, we cloned and sequenced genes encoding cytosolic and plastid-targeted GAPDH proteins from three species of the fucoxanthin derivative-containing dinoflagellates. Based on the molecular phylogeny, the plastid-targeted GAPDH genes of the fucoxanthin derivative-containing dinoflagellates were closely related to those of haptophyte algae rather than to the peridinin-containing dinoflagellates, while one of several cytosolic versions from the peridinin- and the fucoxanthin derivative-containing dinoflagellates are closely related to each other. Considering a previously reported theory that the plastid-targeted GAPDH from the peridinin-containing dinoflagellates originated by a gene duplication of the cytosolic form before the splitting of the dinoflagellate lineage, it is highly likely that the plastid-targeted GAPDH gene of the peridinin-containing dinoflagellates is original in this algal group and that in the fucoxanthin-containing dinoflagellates, the original plastid-targeted GAPDH was replaced by that of a haptophyte endosymbiont during a tertiary endosymbiosis. The present results strongly support the hypothesis that the plastids of the peridinin- and the fucoxanthin derivative-containing dinoflagellates are of separate origin.

  17. SEISMIC PERFORMANCE ANALYSIS OF WATER INTAKE BUILDING IN A NUCLEAR POWER STATION%核电站取水口建筑物的抗震性能分析

    Institute of Scientific and Technical Information of China (English)

    薛志成; 王振清; 裴强; 吴爽

    2012-01-01

    Based on dynamic time-history response analysis, seismic performance analysis of water intake building in the million-kilowatt nuclear power plant was carried out. Considering rock properties and structural characteristics of water intake building, many combinations with different design water levels, operation and maintenance conditions, wave pressure, ice loadings, static and dynamic water pressure, earth pressure and seismic action were considered. The internal force of each section of the structure was obtained by secondary development of ANSYS and the results could provide theoretic evidences for the structural design of water intake building.%针对某百万千瓦级核电厂,运用动力时程反应分析法对取水口建筑物进行抗震分析。结合取水口建筑物场地岩性和结构特点,分别考虑运行和检修情况、波浪、冰块冲击、水压、土压和地震等作用的组合工况,对结构进行抗震性能分析,得到结构构件各个截面内力包络图,对取水LI建筑物设计提供理论依据。

  18. Selection of candidate container materials for the conceptual waste package design for a potential high level nuclear waste repository at Yucca Mountain

    Energy Technology Data Exchange (ETDEWEB)

    Van Konynenburg, R.A.; Halsey, W.G.; McCright, R.D.; Clarke, W.L. Jr. [Lawrence Livermore National Lab., CA (United States); Gdowski, G.E. [KMI, Inc., Albuquerque, NM (United States)

    1993-02-01

    Preliminary selection criteria have been developed, peer-reviewed, and applied to a field of 41 candidate materials to choose three alloys for further consideration during the advanced conceptual design phase of waste package development for a potential high level nuclear waste repository at Yucca Mountain, Nevada. These three alloys are titanium grade 12, Alloy C-4, and Alloy 825. These selections are specific to the particular conceptual design outlined in the Site Characterization Plan. Other design concepts that may be considered in the advanced conceptual design phase may favor other materials choices.

  19. 核电厂安全壳极限抗压承载力及影响因素分析%Ultimate Capacity and Influenced Factors Analysis of Nuclear RC Containment Subj ected to Internal Pressure

    Institute of Scientific and Technical Information of China (English)

    宋辰宁; 侯钢领; 周国良

    2014-01-01

    Ultimate compressive bearing capacity,influenced factors and its rules of nuclear RC containment are key problems of safety assessment,accident treatment and structure design,etc.Ultimate compressive bearing capacity of nuclear RC containment is shown by concrete damaged plasticity model and steel double liner model of ABAQUS.The study shows that the concrete of nuclear RC containment cylinder wall becomes plastic when the internal pressure is up to 0.87 MPa,the maximum tensile strain of steel liner exceeds 3000 × 106 and nuclear RC containment reaches ultimate status when the internal pressure is up to 1.02 MPa.The result shows that nuclear RC containment is in elastic condition under the design internal pressure and the bearing capacity meets requirement.Prestress and steel liner play key parts in the ultimate internal pressure and failure mode of nuclear RC containment.The study results have value for the analysis of ultimate compressive bearing capacity,structure design and safety assessment.%核电厂安全壳极限抗压承载力、影响因素及其规律是核电结构安全评估、事故处理和结构设计的关键问题。本文以某安全壳为例,采用损伤塑性模型模拟混凝土的力学性能,双线形应力-应变模型模拟钢衬里和预应力钢束的材料非线性,基于 ABAQUS软件系统地分析了核安全壳极限抗压承载力,并给出了结构自重、预应力、钢衬里等因素的影响规律。研究表明,当内压增大到0��87 MP a 时,安全壳筒壁上部混凝土开始进入塑性;当内压增大到1��02 MPa时,钢衬里最大拉应变超过限值3000×10-6,安全壳达到极限状态。在各种影响因素中,预应力和钢衬里对安全壳的极限内压和破坏形式起着关键作用。本文研究结果对核安全壳极限承载能力分析、结构设计和安全评定等方面具有一定的参考价值。

  20. Allegheny County Building Footprint Locations

    Data.gov (United States)

    Allegheny County / City of Pittsburgh / Western PA Regional Data Center — This dataset contains photogrammetrically compiled roof outlines of buildings. All near orthogonal corners are square. Buildings that are less than 400 square feet...

  1. Allegheny County Building Footprint Locations

    Data.gov (United States)

    Allegheny County / City of Pittsburgh / Western PA Regional Data Center — This dataset contains photogrammetrically compiled roof outlines of buildings. All near orthogonal corners are square. Buildings that are less than 400 square feet...

  2. Sheet-like of MoV-SmIII assembly containing [MoV(CN)8]3- and Sm3+ ions as building blocks

    Indian Academy of Sciences (India)

    Shu-Lin Ma; Shi Ren; Yue Ma; Dai-Zheng Liao

    2009-07-01

    The reaction of [Mo(CN)8]3- with Sm3+ and 2,2'-bipyridine (bpy) lead to a sheet-like bimetallic complex, {Sm(H2O)9[Sm2(bpy)2(OH)2.75(NO3)0.25][Mo(CN)8]2} (1) in EtOH/H2O mixture solvent. The complex 1 crystallizes in monoclinic, space group 2/. The structural investigation denotes that the layers interaction with each other by - stacks and hydrogen bonds result in a 3D network, containing Sm(H2O)$^{3+}_{9}$ as guest molecules in the holes. The magnetic behaviour of the complex 1 has been studied.

  3. Analysis on Improvement of Lightning Protection of Nuclear Auxiliary Building Ventilation System of LING AO PhaseⅡ%岭澳二期核辅助厂房通风系统防雷改进分析

    Institute of Scientific and Technical Information of China (English)

    李明钢; 王耀刚; 李东; 关济实; 张立蕊

    2016-01-01

    Affected by climate, it is always raining in Guang Dong province and the Daya bay nuclear power plant always suffers from lightning. Therefore, it is very important to improve the lightning protection facilities. In order to solve the problems that lightning protection of nuclear auxiliary building ventilation system and other related component in Daya bay nuclear power plant reactor protection system, and improve the lightning protection level, a plan about improving the lightning protection facilities is proposed, and further analysis and demonstration are made as well, which are based on the actual situation. The plan of improving the lightning protection facilities is of great significance to the safe and stable operation of Daya bay nuclear power station.%受气候影响,广东大亚湾核电站多发雷雨,而雷击会严重威胁核电站的安全稳定运行。因此,提高防雷设施十分重要。针对大亚湾核电站反应堆保护系统相关的核辅助厂房通风系统的信号回路结构及容易受到雷电干扰部分的防雷保护问题,结合实际情况,对核辅助厂房通风系统的防雷设施进行改进及分析论证,提高防雷等级。该防雷设施改进方案对大亚湾核电站的安全稳定运行有着重要的意义。

  4. [Fluoride deposition in the dental enamel following the use of a fluoride-containing gel studied by a nuclear physics method (PIGE)].

    Science.gov (United States)

    Treide, A; Wyrwich, C; Zschau, H E; Plier, F; Otto, G

    1990-01-01

    The caries-preventing activity of fluorine is a surfact in the medicine. Dentists and physicists analysed with a new nuclear physical method the fluorine uptake of the tooth enamel after application of new caries-preventive agents. The fluorine profile of the first 3 microns of the enamel surface from deciduous teeth was established after three years clinical treatment with two new developed fluorine gels from the VEB Leipziger Arzneimittelwerk in comparison with Elmexgelee and a control agent. The determination of the fluorine profiles was performed using proton-induced gamma rays emission (PIGE) on the 2-MV van de-Graaf accelerator of the institute of practical nuclear physics of the physical faculty from the Karl-Marx-Universität Leipzig. The two new developed gels and Elmexgelee caused a similar fluorine concentration in tooth enamel. The fluorine profiles from the new developed gel A and the clinical approved caries preventive agent Elmexgelee are comparable. Gel A is produced under the trade mark "Laweflour" by the VEB Leipziger Arzneimittelwerk.

  5. Zn13(CrxAl1-x)27 (x = 0.34-0.37): a new intermetallic phase containing icosahedra as building units

    Energy Technology Data Exchange (ETDEWEB)

    Thimmaiah, Srinivasa; Han, Mi-Kyung; Miller, Gordon J.

    2011-03-13

    The title compounds Zn{sub 13}(Cr{sub x}Al{sub 1-x}){sub 27} (x = 0.34-0.37) were obtained by melting the pure elements at 923 K, and followed by a heat treatment at 723 K in a tantalum container. According to single crystal structural analysis, the title compounds crystallize in the rhombohedral system, adopting a new structure type (R-3m, a = 7.5971(8), c = 36.816(6), for crystal I). Single crystal X-ray structural analysis reveals a statistical mixing of Cr/Al in their crystallographic positions. Single crystal and powder X-ray diffraction as well as energy dispersive X-ray analyses suggested the title phase to have a narrow homogeneity range. The substructure of Zn{sub 13}(Cr{sub x}Al{sub 1-x}){sub 27} shows close resemblance with the Mn{sub 3}Al{sub 10} structure type. A bonding analysis, through crystal orbital Hamiltonian populations (COHPs), of 'Cr{sub 9}Al{sub 18}Zn{sub 13}' as a representative composition indicated that both homo- and heteronuclear interactions are important for the stability of this new phase.

  6. New dicyano cyclometalated compounds containing Pd(II)-Tl(I) bonds as building blocks in 2D extended structures: synthesis, structure, and luminescence studies.

    Science.gov (United States)

    Sicilia, Violeta; Forniés, Juan; Fuertes, Sara; Martín, Antonio

    2012-10-15

    New mixed metal complexes [PdTl(C^N)(CN)(2)] [C^N = 7,8-benzoquinolinate (bzq, 3); 2-phenylpyridinate (ppy, 4)] have been synthesized by reaction of their corresponding precursors (NBu(4))[Pd(C^N)(CN)(2)] [C^N = bzq (1), ppy (2)] with TlPF(6). Compounds 3 and 4 were studied by X-ray diffraction, showing the not-so-common Pd(II)-Tl(I) bonds. Both crystal structures exhibit 2-D extended networks fashioned by organometallic "PdTl(C^N)(CN)(2)" units, each one containing a donor-acceptor Pd(II)-Tl(I) bond, which are connected through additional Tl···N≡C contacts and weak Tl···π (bzq) contacts in the case of 3. Solid state emissions are red-shifted compared with those of the precursors and have been assigned to metal-metal'-to-ligand charge transfer (MM'LCT [d/s σ*(Pd,Tl) → π*(C^N)]) mixed with some intraligand ((3)IL[π(C^N) → π*(C^N)]) character. In diluted solution either at room temperature or 77 K, the Pd-Tl bond is no longer retained as confirmed by mass spectrometry, NMR, and UV-vis spectroscopic techniques.

  7. Safety Implementation of Hydrogen Igniters and Recombiners for Nuclear Power Plant Severe Accident Management

    Institute of Scientific and Technical Information of China (English)

    XIAO Jianjun; ZHOU Zhiwei; JING Xingqing

    2006-01-01

    Hydrogen combustion in a nuclear power plant containment building may threaten the integrity of the containment. Hydrogen recombiners and igniters are two methods to reduce hydrogen levels in containment buildings during severe accidents. The purpose of this paper is to evaluate the safety implementation of hydrogen igniters and recombiners. This paper analyzes the risk of deliberate hydrogen ignition and investigates three mitigation measures using igniters only, hydrogen recombiners only or a combination of recombiners and igniters. The results indicate that steam can effectively control the hydrogen flame acceleration and the deflagration-to-detonation transition.

  8. Nuclear Medicine

    Science.gov (United States)

    ... for Parents/Teachers Resource Links for Students Glossary Nuclear Medicine What is nuclear medicine? What are radioactive ... NIBIB-funded researchers advancing nuclear medicine? What is nuclear medicine? Nuclear medicine is a medical specialty that ...

  9. Direct observation of electronic and nuclear ground state splitting in external magnetic field by inelastic neutron scattering on oxidized ferrocene and ferrocene containing polymers

    Directory of Open Access Journals (Sweden)

    Appel Markus

    2015-01-01

    Full Text Available The quantum mechanical splitting of states by interaction of a magnetic moment with an external magnetic field is well known, e.g., as Zeeman effect in optical transitions, and is also often seen in magnetic neutron scattering. We report excitations observed in inelastic neutron spectroscopy on the redox-responsive polymer poly(vinylferrocene. They are interpreted as splitting of the electronic ground state in the organometallic ferrocene units attached to the polymer chain where a magnetic moment is created by oxidation. In a second experiment using high resolution neutron backscattering spectroscopy we observe the hyperfine splitting, i.e., interaction of nuclear magnetic moments with external magnetic fields leading to sub-μeV excitations observable in incoherent neutron spin-flip scattering on hydrogen and vanadium nuclei.

  10. Municipal Building Energy Usage

    Data.gov (United States)

    Allegheny County / City of Pittsburgh / Western PA Regional Data Center — This data set contains energy use data from 2009-2014 for 139 municipally operated buildings. Metrics include: Site & Source EUI, annual electricity, natural...

  11. Evaluation of internal occupational exposure of workers from nuclear medicine services by aerosol analysis containing {sup 131}I; Avaliacao da exposicao interna de trabalhadores em servicos de medicina nuclear atraves da analise de aerossois contendo {sup 131}I

    Energy Technology Data Exchange (ETDEWEB)

    Carneiro, Luana Gomes; Sampaio, Camilla da Silva; Dantas, Ana Leticia Almeida; Lucena, Eder Augusto; Santos, Maristela Souza; Dantas, Bernardo Maranhao, E-mail: carneiro@ird.gov.br [Instituto de Radioprotecao e Dosimetria (IRD/CNEN-RJ),Rio de Janeiro, RJ (Brazil); Paula, Gustavo Affonso de [Escola SESC de Ensino Medio, Rio de Janeiro, RJ (Brazil)

    2014-07-01

    This study evaluated the risk of internal occupational exposure associated with the incorporation of {sup 131}I via inhalation, in Nuclear Medicine Services, using aerosol analysis techniques. Occupationally Exposed Individuals (IOE) involved in handling this radionuclide are subject to chronic exposure, which can lead to an increase in the committed effective dose. Results obtained in preliminary studies indicate the occurrence of incorporation of {sup 131}I by workers involved in handling solutions for radioiodine therapy procedures. The evaluation was carried out in radiopharmacy lab (nuclear medicine service) of a public hospital located in the city of Rio de Janeiro. After confirmed the presence of the radioisotope, by a qualitative assessment, it was determined an experimental arrangement for sample collection and were detected and quantitated the presence of steam {sup 131}I during routine work. The average concentration of activity obtained in this study was 3 Bq / m{sup 3}. This value is below of Derived Concentration in Air (DCA) of 8.4 x 10{sup 3} Bq of {sup 131}I / m{sup 3} corresponding to a committed effective dose of 1.76 x 10{sup -4} mSv. These results demonstrate that the studied area is safe in terms of internal exposure of workers. However, the presence of {sup 131}I should be periodically reevaluated, since this type of exposure contributes to the increase of the individual effective doses. Based on the data obtained improvements were suggested in the exhaust system and the use of good work practices in order to optimize the exposures.

  12. 阳江核电厂安全壳钢衬里模块化施工方案研究及应用%Research and Application of Modularized Scheme of Containment Liner of Yangjiang NPP Reactor Building

    Institute of Scientific and Technical Information of China (English)

    鲁勤武; 郝坚; 张淑霞; 郭俊营; 蔡晖

    2011-01-01

    核电厂的安全壳钢衬里模块实施方案中的模块方案、吊具结构、起重设备的实施研究及在阳江核电厂3#机组项目上的成功示范应用,为在核电在建项目上推行安全壳钢衬里模块化建造技术提供了工程实践指导.%Research of the modularized scheme in the design, spatial grid structure spreader and crane, and its successful application in Yangjiang NPP project 3# unit provided a reference for the modularized construction of containment liner in the nuclear construction projects.

  13. Building Materials

    Institute of Scientific and Technical Information of China (English)

    2008-01-01

    @@ Building Materials Sub-council of CCPIT is the other sub-council in construction field. CCPIT Building Materials Sub-council (CCPITBM), as well as CCOIC Build-ing Materials Chamber of Commerce, is au-thorized by CCPIT and state administration of building materials industry in 1992. CCPITBM is a sub-organization of CCPIT and CCOIC.

  14. Methodology of a PWR containment analysis during a thermal-hydraulic accident

    Energy Technology Data Exchange (ETDEWEB)

    Silva, Dayane F.; Sabundjian, Gaiane; Lima, Ana Cecilia S., E-mail: dayane.silva@usp.br, E-mail: gdjian@ipen.br, E-mail: aclima@ipen.br [Instituto de Pesquisas Energeticas e Nucleares (IPEN/CNEN-SP), Sao Paulo, SP (Brazil)

    2015-07-01

    The aim of this work is to present the methodology of calculation to Angra 2 reactor containment during accidents of the type Loss of Coolant Accident (LOCA). This study will be possible to ensure the safety of the population of the surroundings upon the occurrence of accidents. One of the programs used to analyze containment of a nuclear plant is the CONTAIN. This computer code is an analysis tool used for predicting the physical conditions and distributions of radionuclides inside a containment building following the release of material from the primary system in a light-water reactor during an accident. The containment of the type PWR plant is a concrete building covered internally by metallic material and has limits of design pressure. The methodology of containment analysis must estimate the limits of pressure during a LOCA. The boundary conditions for the simulation are obtained from RELAP5 code. (author)

  15. Análisis de accidentes severos en contenciones nucleares

    OpenAIRE

    1992-01-01

    Analysis for severe accidents has recently been added to the long list of requisites imposed on nuclear power plants. In this work we study the rationale and justiflcation for this type of analysis. Calculations for the structural response of the containment buildings can be performed on the computer using advanced nonlinear Finite Element codes. A state of the art review of these methods is carried out, proposing a methodology based on analysis by numerical methods with experimental validati...

  16. History of Nuclear India

    Science.gov (United States)

    Chaturvedi, Ram

    2000-04-01

    India emerged as a free and democratic country in 1947, and entered into the nuclear age in 1948 by establishing the Atomic Energy Commission (AEC), with Homi Bhabha as the chairman. Later on the Department of Atomic Energy (DAE) was created under the Office of the Prime Minister Jawahar Lal Nehru. Initially the AEC and DAE received international cooperation, and by 1963 India had two research reactors and four nuclear power reactors. In spite of the humiliating defeat in the border war by China in 1962 and China's nuclear testing in 1964, India continued to adhere to the peaceful uses of nuclear energy. On May 18, 1974 India performed a 15 kt Peaceful Nuclear Explosion (PNE). The western powers considered it nuclear weapons proliferation and cut off all financial and technical help, even for the production of nuclear power. However, India used existing infrastructure to build nuclear power reactors and exploded both fission and fusion devices on May 11 and 13, 1998. The international community viewed the later activity as a serious road block for the Non-Proliferation Treaty and the Comprehensive Test Ban Treaty; both deemed essential to stop the spread of nuclear weapons. India considers these treaties favoring nuclear states and is prepared to sign if genuine nuclear disarmament is included as an integral part of these treaties.

  17. Nuclear engineering vocabulary; Vocabulaire de l'ingenierie nucleaire

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2006-07-01

    The terms, expressions and definitions presented in this booklet come from the works carried out by the French specialized commission of nuclear engineering terminology and neology. This selection of terms cannot be found, in general, in classical dictionaries, or can be found but with a different meaning than the one used in nuclear engineering. All terms and expressions contained in this booklet have been already published in different issues of the Official Journal of the French Republic. This publication makes their use mandatory in replacement of foreign language equivalents inside all government services and public buildings. (J.S.)

  18. Measures for Equipment Installation in Nuclear Power Plant CI Main Building%核电厂常规岛主厂房设备安装保证措施研究

    Institute of Scientific and Technical Information of China (English)

    武春霖; 金欣

    2014-01-01

    阐述了AP1000核电是目前世界上最先进的核电堆型之一,海水冷却的常规岛 CI (Conventional Island)主厂房多采用半地下结构,在CI主厂房内的凝汽器、发电机定子、汽水分离再热器、除氧器等设备的重量和外形尺寸均比常规火电的设备重和大,其吊装措施在CI主厂房设计时应综合考虑,对施工质量和工程进度都是有益的。介绍了某AP1000核电厂设备安装的CI主厂房设计与设备安装的配合,为相关工程建设、设计者提供参考。%AP1000 unit is one of the most advanced nuclear reactors at present. The main building of sea water cooling CI (Conventional Island) is mostly of the semi-underground structure. The weight and dimension of CI major equipment in the main building, such as condenser,generator stator,MSR and deaerator etc. are bigger than that of the fossil power plant. In order to ensurre the construction quality and schedule,the equipment installation plan should be considered sufficiently. This paper introduced the design of CI main building and its influence on equipment installation for further reference to other designers.

  19. Transposing an active fault database into a seismic hazard fault model for nuclear facilities - Part 1: Building a database of potentially active faults (BDFA) for metropolitan France

    Science.gov (United States)

    Jomard, Hervé; Cushing, Edward Marc; Palumbo, Luigi; Baize, Stéphane; David, Claire; Chartier, Thomas

    2017-09-01

    The French Institute for Radiation Protection and Nuclear Safety (IRSN), with the support of the Ministry of Environment, compiled a database (BDFA) to define and characterize known potentially active faults of metropolitan France. The general structure of BDFA is presented in this paper. BDFA reports to date 136 faults and represents a first step toward the implementation of seismic source models that would be used for both deterministic and probabilistic seismic hazard calculations. A robustness index was introduced, highlighting that less than 15 % of the database is controlled by reasonably complete data sets. An example of transposing BDFA into a fault source model for PSHA (probabilistic seismic hazard analysis) calculation is presented for the Upper Rhine Graben (eastern France) and exploited in the companion paper (Chartier et al., 2017, hereafter Part 2) in order to illustrate ongoing challenges for probabilistic fault-based seismic hazard calculations.

  20. Polarographic determination of Iodide and Iodate, in Solutions Coming from Aerosols in Fission Products Containment Studies in Nuclear Power Stations; Determinacion Polarografica de Especies de Iodo (Ioduro y Iodato) en Soluciones Procedentes de Aerosoles, para Estudios de Contencion de Productos de Fision en Centrales Nucleares

    Energy Technology Data Exchange (ETDEWEB)

    Sanchez, M.; Ballesteros, O.; Fernandez, M.; Clavero, M.; Gonzalez, A. M. [Ciemat, Madrid (Spain)

    2000-07-01

    A polarographic method is described for the iodine species determination, iodide and iodate in water solutions. the iodate can be determined by differential pulse polarography. Calibration curves and the detection and determination limits have been obtained. Iodides is oxidized to iodate with sodium hypochlorite and the excess of oxidizing agent is destroyed with sodium sulphide. The concentration of iodide is calculated as the difference between the concentration of iodate in the sample before and after the oxidation. As an application, species of iodine in samples coming from the experimental plants GIRS (Gaseous Iodine Removal by Sprays) of Nuclear Fission Department of the CIEMAT, dedicated to fission products containment studies in nuclear power station, were determined. (Author) 10 refs.

  1. Solid-State Nuclear Magnetic Resonance Investigation of the Structural Topology and Lipid Interactions of a Viral Fusion Protein Chimera Containing the Fusion Peptide and Transmembrane Domain.

    Science.gov (United States)

    Yao, Hongwei; Lee, Myungwoon; Liao, Shu-Yu; Hong, Mei

    2016-12-13

    The fusion peptide (FP) and transmembrane domain (TMD) of viral fusion proteins play important roles during virus-cell membrane fusion, by inducing membrane curvature and transient dehydration. The structure of the water-soluble ectodomain of viral fusion proteins has been extensively studied crystallographically, but the structures of the FP and TMD bound to phospholipid membranes are not well understood. We recently investigated the conformations and lipid interactions of the separate FP and TMD peptides of parainfluenza virus 5 (PIV5) fusion protein F using solid-state nuclear magnetic resonance. These studies provide structural information about the two domains when they are spatially well separated in the fusion process. To investigate how these two domains are structured relative to each other in the postfusion state, when the ectodomain forms a six-helix bundle that is thought to force the FP and TMD together in the membrane, we have now expressed and purified a chimera of the FP and TMD, connected by a Gly-Lys linker, and measured the chemical shifts and interdomain contacts of the protein in several lipid membranes. The FP-TMD chimera exhibits α-helical chemical shifts in all the membranes examined and does not cause strong curvature of lamellar membranes or membranes with negative spontaneous curvature. These properties differ qualitatively from those of the separate peptides, indicating that the FP and TMD interact with each other in the lipid membrane. However, no (13)C-(13)C cross peaks are observed in two-dimensional correlation spectra, suggesting that the two helices are not tightly associated. These results suggest that the ectodomain six-helix bundle does not propagate into the membrane to the two hydrophobic termini. However, the loosely associated FP and TMD helices are found to generate significant negative Gaussian curvature to membranes that possess spontaneous positive curvature, consistent with the notion that the FP-TMD assembly may

  2. Platinoids and molybdenum in nuclear waste containment glasses: a structural study; Les platinoides et le molybdene dans des verres d'interet nucleaires: etude structurale

    Energy Technology Data Exchange (ETDEWEB)

    Le Grand, M. [CEA/VALRHO - site de Marcoule, Dept. de Recherche en Retraitement et en Vitrification (DRRV), 30 - Marcoule (France)]|[Paris-7 Univ., 75 (France)

    2000-07-01

    This work deals with the structure of borosilicate nuclear glasses and with some relationships between structure and macroscopic properties. Two types of elements which may disturb the industrial process - platinoids (Ru and Pd) and molybdenum - are central to this work. Platinoids induce weak modifications on the structure of the glass, causing a depolymerization of the glassy network, an increase of the {sup [3]}B/{sup [4]}B ratio and a modification of the medium range order around Si between 3.3 and 4.5 angstrom. The modifications of viscosity and density induced by platinoids in the glass are not due to the structural effect of the platinoids. The increase of viscosity is attributed to needle shaped RuO{sub 2}. It can be moderated by imposing reducing conditions during the elaboration of the glass. The slight difference between experimental and calculated densities is due to the increase of the volume percentage of bubbles in the glass with increasing platinoid content. Mo is either present in the glass as molybdic groupings, or mobilized in chemically complex molybdic crystalline phases. The chemical composition and mineralogy of these phases has been obtained using electronic microprobe data and XRD with Rietveld analysis. The distribution of the different elements between the crystalline phases and the glass is strongly influenced by the structural role of the various cations in the glass. The Mo present in the glass appears as MoO{sub 4} tetrahedra, independent of the borosilicate network. The formation of the crystalline phases can be explained by the existence of a precursor in which the MoO{sub 4} tetrahedra are concentrated in rich alkali and earth-alkali bearing areas of the glass. (author)

  3. 中广核大厦空调系统设计%Air conditioning Aesign for China General Nuclear Power Group Building

    Institute of Scientific and Technical Information of China (English)

    浦至; 江宋标; 李刚

    2016-01-01

    This paper introduces the design of the cold and heat source , water system and air system of the pro-ject.The application of Ice storage air conditioning system and BIM technology in super high rise office building is introduced in this paper , Provides some HVAC system design ideas for the similar projects .%介绍了该工程空调冷热源、水系统和风系统的设计。重点介绍了冰蓄冷系统以及BIM技术在超高层办公楼中的应用,供日后类似的工程设计参考。

  4. 阳江核电4号机组安全壳截锥体自密实混凝土施工方法%SELF-COMPACTING CONCRETE CONSTRUCTION METHOD FOR CONTAINMENT TRUNCATED CONE IN NO.4 UNIT OF YANGJIANG NUCLEAR POWER PLANT

    Institute of Scientific and Technical Information of China (English)

    沈刚; 王辉诚; 陈立胜; 裴新意

    2015-01-01

    阳江核电厂采用改进型压水堆CPR1000堆型,为确保安全壳截锥体超大环形预应力混凝土浇筑质量,经一系列配比试验和现场模拟试验研究,4号机组成功应用了自密实混凝土施工技术,并取得良好效果。作为核电行业同类结构应用自密实混凝土的首例,阳江核电4号机组安全壳截锥体自密实混凝土施工方法可为相关工程提供借鉴。%Upgraded pressurized water reactor of CPR1000 was adopted in Yangjiang Nuclear Power Plant (NPP). Based on a series of mixing tests and site mockup test studies, self-compacting concrete ( SCC ) technique was successfully applied to containment truncated cone of No.4 unit for the first time in NPP building industry, which could provide references for relevant projects with similar prestressed concrete structures.

  5. Systems and methods for processing irradiation targets through a nuclear reactor

    Science.gov (United States)

    Dayal, Yogeshwar; Saito, Earl F.; Berger, John F.; Brittingham, Martin W.; Morales, Stephen K.; Hare, Jeffrey M.

    2016-05-03

    Apparatuses and methods produce radioisotopes in instrumentation tubes of operating commercial nuclear reactors. Irradiation targets may be inserted and removed from instrumentation tubes during operation and converted to radioisotopes otherwise unavailable during operation of commercial nuclear reactors. Example apparatuses may continuously insert, remove, and store irradiation targets to be converted to useable radioisotopes or other desired materials at several different origin and termination points accessible outside an access barrier such as a containment building, drywell wall, or other access restriction preventing access to instrumentation tubes during operation of the nuclear plant.

  6. An assessment of the terrorist threat to use a nuclear or radiological device in an attack

    Energy Technology Data Exchange (ETDEWEB)

    Kingshott, B.F. [Grand Valley State University, 275C DeVos Center, 401 West Fulton Street, Grand Rapids, MI 49504 (United States)]. E-mail: kingshob@gvsu.edu

    2006-07-01

    This paper will discuss terrorism from the perspective of a terrorist organisation acquiring nuclear material to build weapons and how security of radiological material world wide will minimise the risk of such devices being used. It will discuss the need to improve security at nuclear waste processing and storage sites and the adequacy of current security. It will also discuss the phenomenon of suicide attacks by the bomb carriers and the role of the media in informing and educating the general public of the consequences should such a device containing nuclear material be detonated. (author)

  7. Numerical simulation on response and damage of nuclear containment under aircraft impact%飞机对核安全壳撞击破坏效应的数值模拟

    Institute of Scientific and Technical Information of China (English)

    张涛; 方秦; 吴昊; 龚自明

    2014-01-01

    To analyze the damage failure of the nuclear containment under the impact of large aircrafts, the refined finite element models of aircraft A320 and the Lingao nuclear containment were established. The process of the im-pact was simulated by using the commercial finite element software LS-DYNA. The results show that there are three noticeable peaks in the process, corresponding to the impact of the cockpit, engines and wings( fuel tank) respec-tively. The maximum peak load is mainly caused by the impact of the engines. Compared with other related litera-tures, the impact load-time curve is similar. But the time duration and the peak load are obviously different for the differences of the aircraft type, mass and impacting velocity. Under the take-off and landing velocity of 100 m/s, containment is seriously damaged and the impacting centre suffers localized perforation, very probably leading to nuclear leakage.%为了研究大型商用客机撞击核电站安全壳的破坏效应,通过建立精细化的空客A320以及岭澳核电站安全壳有限元模型,采用LS-DYNA软件对飞机撞击安全壳进行了数值模拟。分析结果表明:A320撞击力时程曲线出现3次明显的峰值,分别对应驾驶舱、引擎以及机翼(油箱)受撞击产生,其中引擎撞击导致最大峰值荷载。得到的撞击力时程曲线形状与已有研究结论相似,但因飞机型号、质量及撞击速度不同,撞击持续时间、峰值荷载大小及出现时刻存在明显差别。在飞机速度为100 m/s撞击下安全壳损伤严重,撞击中心发生局部穿透并很有可能引发核泄漏。

  8. Britain's delegation to CERN, the European Centre for Nuclear Research near Geneva, voted in favour of a project which take seven years to build, involve a 27 kilometre long tunnel, and cost 230 million pounds. Now LEP receives the go-ahead later this month

    CERN Multimedia

    Llewellyn Smith, Christopher Hubert

    1981-01-01

    Britain's delegation to CERN, the European Centre for Nuclear Research near Geneva, voted in favour of a project which take seven years to build, involve a 27 kilometre long tunnel, and cost 230 million pounds. Now LEP receives the go-ahead later this month

  9. Tools for the simulation of cathodic protection systems for diesel containers of a nuclear power plant; Herramienta para el modelado de sistemas de proteccion catodica para contenedores diesel de una planta nuclear

    Energy Technology Data Exchange (ETDEWEB)

    Bucio V, F. J.; Sainz M, E.; Ramirez S, R.; Celis del Angel, L.; Palacios H, J. [ININ, 52750 La Marquesa, Estado de Mexico (Mexico)]. e-mail: fbucio@nuclear.inin.mx

    2008-07-01

    The cathodic protection is the technique by which the harmful effects of the corrosion for metallic storage tanks can be resisted that they are on the ground. This method causes that all the metallic surface behaves like the cathode of an electrochemical cell. For systems of external cathodic protection, sacrifice anodes can be used or printed current, when sacrifice anodes are used, buried galvanic anodes in the ground are used and connected to the tank, and they are used generally in small tanks. With this technique the anodes are degraded leaving the metallic plate intact. The system proposed for the mathematical simulation of external cathodic protection systems, is an application dedicated to the simulation of a system of anodes for the corrosion protection of diesel containers installed on the ground, that allows to analyze the effects of the resulting current given to the motherboard of the container, that is to say, allows to observe the results before any physical installation and with this of reducing the expenses in the acquisition of unnecessary equipment or its defect, to realize an optimization in the equipment to install to obtain better results. The proposed system was divided in units of sequential processing and not like a whole, the previous thing to allow processing the problem in stages, because it consumes great amount of processing resources and storage during the execution of the same. The aplication was programmed in the programming language of called high level Python. Due to the auxiliary characteristics and units on which it counts, having like basic characteristic the being of open source, reason why it does not require of expensive payments to obtain a license. In the development of the system I am used and unit that allows to visualize controls style Windows, although it is counted on the same version that can be used in operating systems based on Linux. (Author)

  10. European protection principles against external hazards by means of Emergency Power Supply and Control Safety System Building in Nuclear Power Plants

    Energy Technology Data Exchange (ETDEWEB)

    Gallinat, Dipl Ing [Max Aicher Engineering GmbH, Freilassing (Germany)

    2016-10-15

    One of the most important nuclear power plant safety requirements is a redundant and independent power system. This requires such a design of emergency power systems that failure of one will not adversely impact the other. External hazards of natural origin or linked to human activity could potentially affect plant safety. The general objective of the design provisions is to ensure that the safety functions of the systems and components required to return the plant to a safe shutdown state and to prevent and limit radioactive release are not adversely affected. As external hazards are site dependent, Technical Guidelines specify that 'it is not necessary to take all of the hazards in a standardized design; such external hazards as external flooding, drought, ice formation and toxic, corrosive or combustible gases may be dealt with only for a specific plant, on a plant specific basis'. In accordance with the Technical Guidelines, external hazards are taken into consideration at the design stage consistently with internal events or hazards. The basic design principle is to protect against external hazards in accordance with the Technical Guidelines using a 'load case' procedure.

  11. Natural Analogues - One Way to Help Build Public Confidence in the Predicted Performance of a Mined Geologic Repository for Nuclear Waste

    Energy Technology Data Exchange (ETDEWEB)

    Stuckless, J. S.

    2002-02-26

    The general public needs to have a way to judge the predicted long-term performance of the potential high-level nuclear waste repository at Yucca Mountain. The applicability and reliability of mathematical models used to make this prediction are neither easily understood nor accepted by the public. Natural analogues can provide the average person with a tool to assess the predicted performance and other scientific conclusions. For example, hydrologists with the Yucca Mountain Project have predicted that most of the water moving through the unsaturated zone at Yucca Mountain, Nevada will move through the host rock and around tunnels. Thus, seepage into tunnels is predicted to be a small percentage of available infiltration. This hypothesis can be tested experimentally and with some quantitative analogues. It can also be tested qualitatively using a variety of analogues such as (1) well-preserved Paleolithic to Neolithic paintings in caves and rock shelters, (2) biological remains preserved in caves and rock shelters, and (3) artifacts and paintings preserved in man-made underground openings. These examples can be found in materials that are generally available to the non-scientific public and can demonstrate the surprising degree of preservation of fragile and easily destroyed materials for very long periods of time within the unsaturated zone.

  12. International symposium on seismic evaluation of existing nuclear facilities

    Energy Technology Data Exchange (ETDEWEB)

    Orbovic, N.; Bouchon, M. [Institut de Radioprotection et de Surete Nucleaire, IRSN, 92 - Fontenay aux Roses (France); Vendel, J.; Gelain, T. [IRSN/DPEA/SERAC, 91 - Gif sur Yvette (France)

    2003-10-01

    Below are summarized the works of Mrs N. Orbovic and M. Bouchon; B. Stojadinovic, N. Orbovic, M.Bouchon and J.T. Wiley; M. Bouchon, N. Orbovic and B. Foure; T. Gelain, F. Gensdarmes, R. Sestier-Carlin, J. Vendel and M. Bouchon dealing respectively with: 1) seismic assessment of existing nuclear facility: a case study position of the IRSN 2) static and dynamic evaluation of an existing nuclear facility reinforced concrete frame structure 3) experimental study of cracking of low-rise reinforced concrete shear walls 4) aeraulics study of crack networks on low-rise reinforced concrete walls subject to static cycling loading. The summaries are followed: 1) The Institute for Radioprotection and Nuclear Safety (IRSN) has the task of evaluating the seismic safety of existing building inventory in French nuclear facilities. Some of the existing structures are reinforced concrete frame buildings with masonry or reinforced concrete in-fill walls built during the 1960's, 70's and 80's following different building codes and seismic input data applicable at the time of construction. The studied building is a laboratory that was built in 1962. The building is composed of three different and independent blocks. The structure is a reinforced concrete frame with masonry in-fills and few stiff concrete elements. Moreover, the building contains an independent massive concrete cell. Structurally, the building has a number of irregularities. From the detailing standpoint, well known deficiencies of low-ductile reinforced concrete structures are evident especially, a lack of transverse reinforcement in the structural joints of the frame. A number of sensitivity studies were conducted using 2D and 3D linear models to evaluate seismic demand. Ambient vibration and regional earthquake records were used to check the soil nature and the existence or not of a possible site effect around the installation as well as to characterize the dynamic behavior of the building. 3D models

  13. Nuclear Confidence

    Institute of Scientific and Technical Information of China (English)

    2011-01-01

    The Fukushima nuclear accident provides valuable lessons for China national nuclear Corp.as it continues to expand its operations AS Japan’s Fukushima nuclear crisis sparks a global debate over nuclear safety,China National Nuclear Corp. (CNNC),the country’s largest nuclear plant operator, comes under the spotlight.

  14. Calculation Research of Hydrogen Production Amount in Containment after LOCAL in PWR Nuclear Power Plants%压水堆核电厂失水事故后安全壳内产氢量计算研究

    Institute of Scientific and Technical Information of China (English)

    胡建军

    2013-01-01

    The ORIGEN2 code is adopted to calculate the amount of hydrogen production in the core and sump region after LOCAL in PWR nuclear power plants,to reduce the conservatism for the design evaluation of the combustible gas control in the containment.The calculation model of radiolytic decomposition coolant and other related calculation model are used to calculate the amount of hYdrogen production after LOCA in a 600MW PWR nuclear power plant,and the results show that over conservatism of the original evaluation,and there still exists abundant time to prepare and startup the hydrogen recombiners in the containment after LOCAL.%采用ORIGEN2程序对压水堆核电厂失水事故工况下堆芯区和地坑区氢气的产生量进行计算,以合理减少安全壳内可燃气体的控制设计评价的保守性.通过冷却剂的辐照分解产氢以及其他相关计算模型,对600MW(电功率)级压水堆核电厂失水事故工况下的氢气产生量进行计算.计算结果表明原评价结果过于保守,在核电厂失水事故后仍有充分的时间准备投入安全壳内氢气复合器.

  15. A gene delivery system containing nuclear localization signal: Increased nucleus import and transfection efficiency with the assistance of RanGAP1.

    Science.gov (United States)

    Chen, Kang; Guo, Lingling; Zhang, Jiulong; Chen, Qing; Wang, Kuanglei; Li, Chenxi; Li, Weinan; Qiao, Mingxi; Zhao, Xiuli; Hu, Haiyang; Chen, Dawei

    2017-01-15

    In the present report, a degradable gene delivery system (PAMS/DNA/10NLS) containing nucleus location signal peptide (NLS) was prepared. The agarose gel electrophoresis, particle size and zeta potential of PAMS/DNA/10NLS were similar to those of PAMS/DNA, which proved that NLS did not affect the interaction between PAMS and DNA. PAMS/DNA/10NLS exhibited marked extracellular and intracellular degradation under acidic conditions. The degradation was believed to allow NLS to come into contact with importins easily, which was able to mediate the nucleus import. With the help of NLS, PAMS/DNA/10NLS exhibited a higher transfection capability than PAMS/DNA. Moreover, the transfection of PAMS/DNA/10NLS was less dependent on the breakdown of the nucleus envelope than PAMS/DNA. Considering that GTPase-activating protein 1 (RanGAP1) was able to activate the endogenous GTPase, which was necessary for NLS-mediated nucleus import, RanGAP1 overexpressed cells (RanGAP1 cells) were produced. This result showed that RanGAP1 cells had higher GTPase activities than normal cells. Both the nucleus import and transfection efficiency of PAMS/DNA/10NLS were markedly higher in RanGAP1 cells than that in normal cells. The in vivo transfection results also showed that the transfection efficiency of PAMS/DNA/10NLS was higher in RanGAP1 pre-treated mice than that in normal mice. These findings showed that PAMS/DNA/10NLS is a promising gene delivery system with the assistance of RanGAP1.

  16. G-patch domain containing 2, a gene highly expressed in testes, inhibits nuclear factor-κB and cell proliferation.

    Science.gov (United States)

    Hu, Fen; Gou, Lixia; Liu, Qing; Zhang, Wendian; Luo, Mengmeng; Zhang, Xiujun

    2015-02-01

    G-patch domain containing 2 (GPATC2), a human gene that is highly expressed in the testes, was implicated as a novel cancer/testis antigen. The present study investigated GPATC2 expression in a number of human cell lines and rat tissues, and its potential biological function in 293T cells. Semi‑quantitative reverse transcription-polymerase chain reaction analysis showed that GPATC2 was widely expressed in 15 human cell lines (representing different lineages) and in 11 different rat tissues, and that the GPATC2 mRNA relative expression level was significantly higher in the testis than it was in other tissues. 293T cells were transiently transfected with GPATC2-p enhanced green fluorescent protein (EGFP)‑N1 or GPATC2-pEGFP-C3 and the nuclei were stained with 4',6'‑diamidino‑2‑phenylindole. The results showed that GPATC2 is predominantly expressed in the nucleus of 293T cells. Overexpression of GPATC2 may inhibit transcription of the NF-κB reporter gene. The role of GPATC2 in proliferation was analyzed with cell counting kit-8, colony-forming efficiency and flow cytometry assays. The results indicated that over‑expression of GPATC2 in 293T cells significantly inhibited cell proliferation by decreasing the number of cells in S phase. By contrast, GPATC2 knockdown by RNA interference exhibited the opposite effect, suggesting that GPATC2 may be involved in inhibiting G1-S phase transition in 293T cells. In conclusion, these results provide novel insight into the breadth of expression of GPATC2 and its role in cell proliferation.

  17. Aphanomyces euteiches cell wall fractions containing novel glucan-chitosaccharides induce defense genes and nuclear calcium oscillations in the plant host Medicago truncatula.

    Directory of Open Access Journals (Sweden)

    Amaury Nars

    Full Text Available N-acetylglucosamine-based saccharides (chitosaccharides are components of microbial cell walls and act as molecular signals during host-microbe interactions. In the legume plant Medicago truncatula, the perception of lipochitooligosaccharide signals produced by symbiotic rhizobia and arbuscular mycorrhizal fungi involves the Nod Factor Perception (NFP lysin motif receptor-like protein and leads to the activation of the so-called common symbiotic pathway. In rice and Arabidopsis, lysin motif receptors are involved in the perception of chitooligosaccharides released by pathogenic fungi, resulting in the activation of plant immunity. Here we report the structural characterization of atypical chitosaccharides from the oomycete pathogen Aphanomyces euteiches, and their biological activity on the host Medicago truncatula. Using a combination of biochemical and biophysical approaches, we show that these chitosaccharides are linked to β-1,6-glucans, and contain a β-(1,3;1,4-glucan backbone whose β-1,3-linked glucose units are substituted on their C-6 carbon by either glucose or N-acetylglucosamine residues. This is the first description of this type of structural motif in eukaryotic cell walls. Glucan-chitosaccharide fractions of A. euteiches induced the expression of defense marker genes in Medicago truncatula seedlings independently from the presence of a functional Nod Factor Perception protein. Furthermore, one of the glucan-chitosaccharide fractions elicited calcium oscillations in the nucleus of root cells. In contrast to the asymmetric oscillatory calcium spiking induced by symbiotic lipochitooligosaccharides, this response depends neither on the Nod Factor Perception protein nor on the common symbiotic pathway. These findings open new perspectives in oomycete cell wall biology and elicitor recognition and signaling in legumes.

  18. Baltic nuclear projects

    Energy Technology Data Exchange (ETDEWEB)

    Adlys, Gediminas; Adliene, Diana [Kaunas Univ. of Technology (Lithuania)

    2009-07-01

    The Authors discuss the Baltic energy policy with respect to new nuclear power plants for Lithuania, Belarus and the Kaliningrad region. The construction of a new nuclear power plant in Lithuania would threaten Russian interests in the region. Therefore Lithuania is looking to Russian plans to build a new nuclear power plant in the Kaliningrad region as an attempt to subvert Lithuania's foreign partners and potential investors from participating in the Visaginas NPP project. However, the authors conclude, that the Visaginas NPP project is and must be the preferential project for the EU and NATO member states.

  19. Extraordinary Separation of Acetylene-Containing Mixtures with Microporous Metal-Organic Frameworks with Open O Donor Sites and Tunable Robustness through Control of the Helical Chain Secondary Building Units

    KAUST Repository

    Yao, Zizhu

    2016-03-02

    Acetylene separation is a very important but challenging industrial separation task. Here, through the solvothermal reaction of CuI and 5-triazole isophthalic acid in different solvents, two metal-organic frameworks (MOFs, FJU-21 and FJU-22) with open O donor sites and controllable robustness have been obtained for acetylene separation. They contain the same paddle-wheel {Cu2(COO2)4} nodes and metal-ligand connection modes, but with different helical chains as secondary building units (SBUs), leading to different structural robustness for the MOFs. FJU-21 and FJU-22 are the first examples in which the MOFs\\' robustness is controlled by adjusting the helical chain SBUs. Good robustness gives the activated FJU-22 a, which has higher surface area and gas uptakes than the flexible FJU-21 a. Importantly, FJU-22 a shows extraordinary separation of acetylene mixtures under ambient conditions. The separation capacity of FJU-22 a for 50:50 C2H2/CO2 mixtures is about twice that of the high-capacity HOF-3, and its actual separation selectivity for C2H2/C2H4 mixtures containing 1 % acetylene is the highest among reported porous materials. Based on first-principles calculations, the extraordinary separation performance of C2H2 for FJU-22 a was attributed to hydrogen-bonding interactions between the C2H2 molecules with the open O donors on the wall, which provide better recognition ability for C2H2 than other functional sites, including open metal sites and amino groups. © 2016 WILEY-VCH Verlag GmbH & Co. KGaA, Weinheim.

  20. Extraordinary Separation of Acetylene-Containing Mixtures with Microporous Metal-Organic Frameworks with Open O Donor Sites and Tunable Robustness through Control of the Helical Chain Secondary Building Units.

    Science.gov (United States)

    Yao, Zizhu; Zhang, Zhangjing; Liu, Lizhen; Li, Ziyin; Zhou, Wei; Zhao, Yunfeng; Han, Yu; Chen, Banglin; Krishna, Rajamani; Xiang, Shengchang

    2016-04-11

    Acetylene separation is a very important but challenging industrial separation task. Here, through the solvothermal reaction of CuI and 5-triazole isophthalic acid in different solvents, two metal-organic frameworks (MOFs, FJU-21 and FJU-22) with open O donor sites and controllable robustness have been obtained for acetylene separation. They contain the same paddle-wheel {Cu2(COO2)4} nodes and metal-ligand connection modes, but with different helical chains as secondary building units (SBUs), leading to different structural robustness for the MOFs. FJU-21 and FJU-22 are the first examples in which the MOFs' robustness is controlled by adjusting the helical chain SBUs. Good robustness gives the activated FJU-22 a, which has higher surface area and gas uptakes than the flexible FJU-21 a. Importantly, FJU-22 a shows extraordinary separation of acetylene mixtures under ambient conditions. The separation capacity of FJU-22 a for 50:50 C2H2/CO2 mixtures is about twice that of the high-capacity HOF-3, and its actual separation selectivity for C2H2/C2H4 mixtures containing 1% acetylene is the highest among reported porous materials. Based on first-principles calculations, the extraordinary separation performance of C2H2 for FJU-22 a was attributed to hydrogen-bonding interactions between the C2H2 molecules with the open O donors on the wall, which provide better recognition ability for C2H2 than other functional sites, including open metal sites and amino groups.

  1. CONTAIN independent peer review

    Energy Technology Data Exchange (ETDEWEB)

    Boyack, B.E. [Los Alamos National Lab., NM (United States); Corradini, M.L. [Univ. of Wisconsin, Madison, WI (United States). Nuclear Engineering Dept.; Denning, R.S. [Battelle Memorial Inst., Columbus, OH (United States); Khatib-Rahbar, M. [Energy Research Inc., Rockville, MD (United States); Loyalka, S.K. [Univ. of Missouri, Columbia, MO (United States); Smith, P.N. [AEA Technology, Dorchester (United Kingdom). Winfrith Technology Center

    1995-01-01

    The CONTAIN code was developed by Sandia National Laboratories under the sponsorship of the US Nuclear Regulatory Commission (NRC) to provide integrated analyses of containment phenomena. It is used to predict nuclear reactor containment loads, radiological source terms, and associated physical phenomena for a range of accident conditions encompassing both design-basis and severe accidents. The code`s targeted applications include support for containment-related experimental programs, light water and advanced light water reactor plant analysis, and analytical support for resolution of specific technical issues such as direct containment heating. The NRC decided that a broad technical review of the code should be performed by technical experts to determine its overall technical adequacy. For this purpose, a six-member CONTAIN Peer Review Committee was organized and a peer review as conducted. While the review was in progress, the NRC issued a draft ``Revised Severe Accident Code Strategy`` that incorporated revised design objectives and targeted applications for the CONTAIN code. The committee continued its effort to develop findings relative to the original NRC statement of design objectives and targeted applications. However, the revised CONTAIN design objectives and targeted applications. However, the revised CONTAIN design objectives and targeted applications were considered by the Committee in assigning priorities to the Committee`s recommendations. The Committee determined some improvements are warranted and provided recommendations in five code-related areas: (1) documentation, (2) user guidance, (3) modeling capability, (4) code assessment, and (5) technical assessment.

  2. Nuclear safeguards; Salvaguardias nucleares

    Energy Technology Data Exchange (ETDEWEB)

    Zurron, O.

    2015-07-01

    Safeguards control at the Juzbado Plant is implemented through the joint IAEA/EURATOM partnership approach in force within the European Union for all nuclear facilities. this verification agreement is designed to minimize burden on the operators whilst ensuring that both inspectorate achieve the objectives related to their respective safeguards regimes. This paper outlines the safeguards approaches followed by the inspectorate and the particularities of the Juzbado Plants nuclear material accountancy and control system. (Authors)

  3. Basic Nuclear Physics Research Needs for Nuclear Energy

    Science.gov (United States)

    Hill, Tony

    2008-10-01

    Basic nuclear physics research will play a central role in the development of the future nuclear facilities. Federal requirements for higher efficiencies, lower operating and construction costs, and advanced safeguards can all be impacted by the quality of nuclear data used in the fuel cycle calculations for design and licensing. Uncertainties in the underlying nuclear data propagate to uncertainties in integral and operational parameters, which drive margins and cost. Department of Energy (DOE) programs are underway to help develop the necessary nuclear research infrastructure. The Nuclear Energy office of DOE leads the development of new nuclear energy generation technologies to meet energy and climate change goals and advanced, proliferation resistant nuclear fuel technologies that maximize energy from nuclear fuel, while maintaining and enhancing the national nuclear infrastructure. These activities build on important work started over the last three years to deploy new nuclear plants in the United States by early in the next decade, and to develop advanced, next-generation nuclear technology. In this talk, I will discuss some of the foreseen opportunities and needs for basic nuclear research in nuclear energy.

  4. 核电站工业水池的地震反应分析%Seismic Response Analysis of Industry Pool Building on a Nuclear Power Station

    Institute of Scientific and Technical Information of China (English)

    薛志成; 裴强; 赵杰

    2013-01-01

    目的 探索核电站工业水池作为抗震物项进行动力计算时的内力分布规律及其危险工况,为工业水池合理截面设计及配筋方案提供技术支持.方法 基于大型有限元商业软件开发了工业水池构筑物进行地震反应分析的编码程序,该程序考虑了土-结构动力相互作用,并以黏弹性边界模拟无限地基的影响.结果 依据材料力学平截面假定实现了ANSYS三维实体单元应力到内力转化,得到了各种荷载工况作用下工业水池后墙弯矩最大值为101.8 kN·m,相对于反应位移法的计算结果小17%,并通过统计最大内力包络确定了工业水池的危险工况为空水状态与SL2地震波共同作用.结论 笔者确定出危险工况下最不利内力的方法比较准确且简单明了,易于工程设计应用.%As a seismic item,internal force distribution and risk case of industry pool in the nuclear power plant is explored while calculating the earthquake responses.The results can provide technical support for the design plan of sectional dimensions and reinforcement.The finite element program of seismic response analysis for industrial pool structures is developed based on commercial software.And soil-structure interaction is simulated by means of adding a viscoelastic boundary in the sides of the model.Based on the plane section assumes of materials mechanics,the transformation between the stress and internal force of three-dimensional solid elements is accomplished.Internal forces distribution and envelope of industrial pools are obtained from the simulation results,the value of the maximum bending moment is 101.8 that is 17% smaller than the calculation results of response displacement method,and then it is determined that the most dangerous case is the combined effects of SL2 seismic waves and empty pool.Based on the calculation results,it can be concluded that the method of determining the worst intemal force in the most dangerous case is

  5. Frontiers in nuclear medicine symposium: Nuclear medicine & molecular biology

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-04-01

    This document contains the abstracts from the American College of Nuclear Physicians 1993 Fall Meeting entitled, `Frontiers in Nuclear Medicine Symposium: Nuclear Medicine and Molecular Biology`. This meeting was sponsored by the US DOE, Office of Health and Environmental Research, Office of Energy Research. The program chairman was Richard C. Reba, M.D.

  6. Building calculations

    DEFF Research Database (Denmark)

    Jensen, Bjarne Christian; Hansen, Svend Ole

    Textbook on design of large panel building including rules on robustness and a method for producing the Statical documentattion......Textbook on design of large panel building including rules on robustness and a method for producing the Statical documentattion...

  7. Building America

    Energy Technology Data Exchange (ETDEWEB)

    Brad Oberg

    2010-12-31

    IBACOS researched the constructability and viability issues of using high performance windows as one component of a larger approach to building houses that achieve the Building America 70% energy savings target.

  8. Solar building

    OpenAIRE

    Zhang, Luxin

    2014-01-01

    In my thesis I describe the utilization of solar energy and solar energy with building integration. In introduction it is also mentioned how the solar building works, trying to make more people understand and accept the solar building. The thesis introduces different types of solar heat collectors. I compared the difference two operation modes of solar water heating system and created examples of solar water system selection. I also introduced other solar building applications. It is conv...

  9. Status of nuclear data activities in Korea

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Young-Ouk; Chang, Jonghwa [Nuclear Data Evaluation Lab., Korea Atomic Energy Research Inst., Yusung, Taejon 305-600 (Korea, Republic of)

    1998-03-01

    Although nuclear data activities in Korea are still in the early stage, considerable demands for more accurate and wide-range nuclear data from nuclear R and D fields activated a new nuclear data project titled as `Development of Nuclear Data System`. It was launched this year as one of nation-wide long-term nuclear R and D programs in Korea for the next decade. Its main goals are (1) to establish nuclear data system, (2) to build up the infra-structure for utilization of nuclear data and (3) to develop highly reliable nuclear data system. To achieve these goals, international cooperation and cultivation of human resource as well as construction of measurement facilities will be indispensable. This report briefly describes the demands of nuclear data from the nuclear R and D programs, current nuclear data activities and future plan with its strategy. (author)

  10. Healthy Buildings?

    Science.gov (United States)

    Grubb, Deborah

    Health problems related to school buildings can be categorized in five major areas: sick-building syndrome; health-threatening building materials; environmental hazards such as radon gas and asbestos; lead poisoning; and poor indoor air quality due to smoke, chemicals, and other pollutants. This paper provides an overview of these areas,…

  11. Building envelope

    CSIR Research Space (South Africa)

    Gibberd, Jeremy T

    2009-01-01

    Full Text Available This chapter describes the way building envelopes can contribute to developing green buildings and sets out some objectives that could be aimed for. It also proposes a number of approaches that can be used to help design green building envelopes...

  12. Nuclear Fabrication Consortium

    Energy Technology Data Exchange (ETDEWEB)

    Levesque, Stephen [EWI, Columbus, OH (United States)

    2013-04-05

    This report summarizes the activities undertaken by EWI while under contract from the Department of Energy (DOE) Office of Nuclear Energy (NE) for the management and operation of the Nuclear Fabrication Consortium (NFC). The NFC was established by EWI to independently develop, evaluate, and deploy fabrication approaches and data that support the re-establishment of the U.S. nuclear industry: ensuring that the supply chain will be competitive on a global stage, enabling more cost-effective and reliable nuclear power in a carbon constrained environment. The NFC provided a forum for member original equipment manufactures (OEM), fabricators, manufacturers, and materials suppliers to effectively engage with each other and rebuild the capacity of this supply chain by : Identifying and removing impediments to the implementation of new construction and fabrication techniques and approaches for nuclear equipment, including system components and nuclear plants. Providing and facilitating detailed scientific-based studies on new approaches and technologies that will have positive impacts on the cost of building of nuclear plants. Analyzing and disseminating information about future nuclear fabrication technologies and how they could impact the North American and the International Nuclear Marketplace. Facilitating dialog and initiate alignment among fabricators, owners, trade associations, and government agencies. Supporting industry in helping to create a larger qualified nuclear supplier network. Acting as an unbiased technology resource to evaluate, develop, and demonstrate new manufacturing technologies. Creating welder and inspector training programs to help enable the necessary workforce for the upcoming construction work. Serving as a focal point for technology, policy, and politically interested parties to share ideas and concepts associated with fabrication across the nuclear industry. The report the objectives and summaries of the Nuclear Fabrication Consortium

  13. Nuclear physics

    Energy Technology Data Exchange (ETDEWEB)

    Sang, David (Bishop Luffa Comprehensive School, Chichester (UK))

    1990-01-01

    Nuclear Physics covers the aspects of radioactivity and nuclear physics dealt with in the syllabuses of all the A-level examination boards; in particular, it provides detailed coverage of the Joint Matriculation Board option in nuclear physics. It deals with the discovery of the atomic nucleus, the physics of nuclear processes, and nuclear technology. (author).

  14. Coherent fragmentation of 12C nuclei of momentum 4.5 GeV/ c per nucleon through the 8Beg.s.+4He channel in a nuclear photoemulsion containing lead nuclei

    Science.gov (United States)

    Belaga, V. V.; Gerasimov, S. G.; Dronov, V. A.; Peresadko, N. G.; Pisetskaya, A. V.; Rusakova, V. V.; Fetisov, V. N.; Kharlamov, S. P.; Shesterkina, L. N.

    2017-07-01

    A two-particle channel in which an unbound nucleus of 8Be in the ground state (8Beg.s.) was one of the fragments was selected among events where 12C nuclei of momentum 4.5 GeV/c per nucleon undergo coherent dissociation into three alpha particles. The events in question were detected in a track nuclear photoemulsion containing lead nuclei, which was irradiated at the synchrophasotron of the Laboratory of High Energies at the Joint Institute for Nuclear Research (JINR, Dubna). The average transverse momentum of alpha particles produced upon the decay of 8Beg.s. nuclei was 87±6 MeV/ c, while that for "single" alpha (αs) particles was 123±15 MeV/ c. The average value of the transverse-momentum transfer in the reaction being considered, Pt(12C), was 223 ± 20 MeV/ c. The average value of the cross section for this channel involving Ag and Br target nuclei was 13 ± 4 mb, while the cross section for the reaction on the Pb nucleus was 40 ± 15 mb. The Coulomb dissociation contribution evaluated on the basis of the number of events where the momentum P t(12C) did not exceed 0.1 GeV/c saturated about 20%. In nine events, the measured total transverse energy of the fragments in the reference frame comoving with the decaying carbon nucleus did not exceed 0.45 MeV, which did not contradict the excitation of the participant 12C nucleus to the level at 7.65 MeV. The average value of the transverse momentum in those events was 234 ± 25 MeV/ c.

  15. 核电厂SOP规程安注安喷操作界面优化研究%Optimization Research on SOP Operation Interface of Safety Injection and Containment Spray in Nuclear Power Plant

    Institute of Scientific and Technical Information of China (English)

    刘至; 殷中平; 李广

    2015-01-01

    状态导向法事故规程(以下简称SOP规程)在核电厂中的应用,提升了核电厂的事故处理能力,但现有的SOP规程组织架构在应对核电站常用的如安注、安喷等专设安全设施动作控制方面,仍存在自动动作确认复杂、需反复调用链接画面等不足. 通过对操作界面的优化研究,可以有效弥补SOP规程的不足. 对SOP规程操作界面优化研究的技术思路进行了综合介绍,给出了其技术要点,并与原SOP规程组织架构进行了分析对比.%The application of state oriented procedures ( SOP) in nuclear power plant enhances the capability of the nuclear power plant upon accident treatment; however the existing SOP organizational structure is insufficient in response to motion control of the engineered safety facilities, e. g. , safety injection and containment spray, etc. , for instance, the automatic action is complexly to be acknowledged, and the linked displays have to be called repeatedly. The deficiency of SOP can be effectively made up by optimization research of operation interface. The technical ideas of optimization research for SOP operation interface are elaborated comprehensively, and the technical points are given, the optimized technology and original SOP organization structure are analyzed and compared.

  16. Postirradiation Testing Laboratory (327 Building)

    Energy Technology Data Exchange (ETDEWEB)

    Kammenzind, D.E.

    1997-05-28

    A Standards/Requirements Identification Document (S/RID) is the total list of the Environment, Safety and Health (ES and H) requirements to be implemented by a site, facility, or activity. These requirements are appropriate to the life cycle phase to achieve an adequate level of protection for worker and public health and safety, and the environment during design, construction, operation, decontamination and decommissioning, and environmental restoration. S/RlDs are living documents, to be revised appropriately based on change in the site`s or facility`s mission or configuration, a change in the facility`s life cycle phase, or a change to the applicable standards/requirements. S/RIDs encompass health and safety, environmental, and safety related safeguards and security (S and S) standards/requirements related to the functional areas listed in the US Department of Energy (DOE) Environment, Safety and Health Configuration Guide. The Fluor Daniel Hanford (FDH) Contract S/RID contains standards/requirements, applicable to FDH and FDH subcontractors, necessary for safe operation of Project Hanford Management Contract (PHMC) facilities, that are not the direct responsibility of the facility manager (e.g., a site-wide fire department). Facility S/RIDs contain standards/requirements applicable to a specific facility that are the direct responsibility of the facility manager. S/RlDs are prepared by those responsible for managing the operation of facilities or the conduct of activities that present a potential threat to the health and safety of workers, public, or the environment, including: Hazard Category 1 and 2 nuclear facilities and activities, as defined in DOE 5480.23. Selected Hazard Category 3 nuclear, and Low Hazard non-nuclear facilities and activities, as agreed upon by RL. The Postirradiation Testing Laboratory (PTL) S/RID contains standards/ requirements that are necessary for safe operation of the PTL facility, and other building/areas that are the direct

  17. Sustainable building versus ecological building

    CSIR Research Space (South Africa)

    Van Wyk, Llewellyn V

    2010-04-01

    Full Text Available and sensitivity to a site that are required to efficiently meet the energy needs of a building and occupants with renewable energy (solar, wind, geothermal, etc), designers must apply holistic design principles and take advantage of the free, naturally... Building Handbook Volume 1 Sustainable Building versus Ecological Building Llewellyn van Wyk Principal Researcher CSIR Background and Context ?Evidence is mounting that humankind, and the environment that shapes its existence, are in the midst...

  18. Nuclear ventriculography

    Science.gov (United States)

    ... ventriculography (RNV); Multiple gate acquisition scan (MUGA); Nuclear cardiology; Cardiomyopathy - nuclear ventriculography ... 56. Udelson JE, Dilsizian V, Bonow RO. Nuclear cardiology. In: Bonow RO, Mann DL, Zipes DP, Libby ...

  19. Nuclear Medicine.

    Science.gov (United States)

    Badawi, Ramsey D.

    2001-01-01

    Describes the use of nuclear medicine techniques in diagnosis and therapy. Describes instrumentation in diagnostic nuclear medicine and predicts future trends in nuclear medicine imaging technology. (Author/MM)

  20. Nuclear Explosion Monitoring History and Research and Development

    Science.gov (United States)

    Hawkins, W. L.; Zucca, J. J.

    2008-12-01

    Within a year after the nuclear detonations over Hiroshima and Nagasaki the Baruch Plan was presented to the newly formed United Nations Atomic Energy Commission (June 14, 1946) to establish nuclear disarmament and international control over all nuclear activities. These controls would allow only the peaceful use of atomic energy. The plan was rejected through a Security Council veto primarily because of the resistance to unlimited inspections. Since that time there have been many multilateral, and bilateral agreements, and unilateral declarations to limit or eliminate nuclear detonations. Almost all of theses agreements (i.e. treaties) call for some type of monitoring. We will review a timeline showing the history of nuclear testing and the more important treaties. We will also describe testing operations, containment, phenomenology, and observations. The Comprehensive Nuclear Test Ban Treaty (CTBT) which has been signed by 179 countries (ratified by 144) established the International Monitoring System global verification regime which employs seismic, infrasound, hydroacoustic and radionuclide monitoring techniques. The CTBT also includes on-site inspection to clarify whether a nuclear explosion has been carried out in violation of the Treaty. The US Department of Energy (DOE) through its National Nuclear Security Agency's Ground-Based Nuclear Explosion Monitoring R&D Program supports research by US National Laboratories, and universities and industry internationally to detect, locate, and identify nuclear detonations. This research program builds on the broad base of monitoring expertise developed over several decades. Annually the DOE and the US Department of Defense jointly solicit monitoring research proposals. Areas of research include: seismic regional characterization and wave propagation, seismic event detection and location, seismic identification and source characterization, hydroacoustic monitoring, radionuclide monitoring, infrasound monitoring, and

  1. Proceedings of the 3rd International Symposium on Material Chemistry in Nuclear Environment (MATERIAL CHEMISTRY '02, MC '02); March 13-15, 2002, Tsukuba

    OpenAIRE

    MC'02企画委員会

    2003-01-01

    The volume contains all presented papers during the the 3rd International Symposium on Material Chemistry in Nuclear Environment: MATERIAL CHEMISTRY '02 (MC'02), held March 13-15, 2002. The purpose of this symposium is to provide an international forum for the discussion of recent progress in the field of materials chemistry in nuclear environments. This symposium intends to build on the success of the previous symposiums held in Tsukuba in 1992 and 1996. The topics discussed in the symposium...

  2. INL Green Building Strategy

    Energy Technology Data Exchange (ETDEWEB)

    Jennifer Dalton

    2005-05-01

    Green buildings, also known as sustainable buildings, resource efficient buildings, and high performance buildings, are structures that minimize the impact on the environment by using less energy and water, reducing solid waste and pollutants, and limiting the depletion of natural resources. As Idaho National Laboratory (INL) becomes the nation’s premier nuclear energy research laboratory, the physical infrastructure will be established to help accomplish the mission. This infrastructure, particularly the buildings, should incorporate green design features in order to be environmentally responsible and reflect an image of progressiveness and innovation to the public and prospective employees. With this in mind, the recommendations described in this strategy are intended to form the INL foundation for green building standards. The recommendations in this strategy are broken down into three levels: Baseline Minimum, Leadership in Energy and Environmental Design (LEED)Certification, and Innovative. Baseline Minimum features should be included in all new occupied buildings no matter what the purpose or size. These features do not require significant research, design, or capital costs and yet they can reduce Operation and Maintenance (O&M) costs and produce more environmentally friendly buildings. LEED Certification features are more aggressive than the Baseline Minimums in that they require documentation, studies, and/or additional funding. Combined with the Baseline Minimums, many of the features in this level will need to be implemented to achieve the goal of LEED certification. LEED Silver certification should be the minimum goal for all new buildings (including office buildings, laboratories, cafeterias, and visitor centers) greater than 25,000 square feet or a total cost of $10 million. Innovative features can also contribute to LEED certification, but are less mainstream than those listed in the previous two levels. These features are identified as areas where

  3. Building Connecticut's clinical biodosimetry laboratory surge capacity to mitigate the health consequences of radiological and nuclear disasters: A collaborative approach between the state biodosimetry laboratory and Connecticut's medical infrastructure

    Energy Technology Data Exchange (ETDEWEB)

    Albanese, Joseph [Yale New Haven Health Center for Emergency Preparedness and Disaster Response, New Haven, CT 06510 (United States)], E-mail: Joseph.Albanese@ynhh.org; Martens, Kelly [Yale New Haven Health Center for Emergency Preparedness and Disaster Response, New Haven, CT 06510 (United States); Emergency Department, Yale-New Haven Hospital, New Haven, CT (United States); Arnold, Jeffrey L. [Emergency Department, Natividad Medical Center, Salinas, CA (United States); Kelley, Katherine [Connecticut Department of Public Health, Hartford, CT (United States); Kristie, Virginia [Hartford Hospital, Hartford, CT (United States); Forte, Elaine; Schneider, Mark [Yale New Haven Health Center for Emergency Preparedness and Disaster Response, New Haven, CT 06510 (United States); Dainiak, Nicholas [Yale New Haven Health Center for Emergency Preparedness and Disaster Response, New Haven, CT 06510 (United States); Department of Medicine, Bridgeport Hospital, Bridgeport, CT (United States); Yale University School of Medicine, New Haven, CT (United States)

    2007-07-15

    used to further optimize biodosimetry specimen processing protocols in Connecticut. Based on our findings, we conclude that clinical laboratory professionals are an important resource for assisting with the processing biodosimetry specimens that are used for triage of patients from accidental or terrorist-related mass-casualty radiological or nuclear catastrophies. The approach described in this paper to enroll and train clinical laboratorians in sample preparation for dicentric analysis forms the basis for the next step (namely, further training on harvesting cultured cells and preparing cytogenetic slides) in collaborative efforts between the State of Connecticut's Biodosimetry Laboratory and the state's medical infrastructure towards building laboratory surge capacity to estimate radiation dose in victims of a mass casualty event.

  4. “经济与核武并行路线”及朝鲜经济政策走向%Strategy of Carrying out Economic Construction and Building Nuclear Armed Forces Simultaneously and North Korean Economic Policy Trend

    Institute of Scientific and Technical Information of China (English)

    谭红梅

    2015-01-01

    North Korea proposed the strategy of carrying out economic construction and building nuclear armed forces simultaneously on March 2013.For various factors, economy was more emphasized in this strategy than the similar policy in the past while the national defense was the priority.However, such an economic reform can not re-move the drawbacks of planned economy;therefore, it is limited.Besides, factors such as nuclear weapon develop-ment and investment environment may impede and challenge North Korea’ s economic cause.It is proposed that North Korea should improve its economic efficiency and management, as well as attract more foreign investment and open wider to the outside world.%2013年3月,朝鲜提出金正恩时代的“国家运行基本政策”———“经济与核武并行路线”。其中经济领域的任务,呈现不同以往的特征,对经济的重视较以往已达到了更高的程度,多种因素促使朝鲜把经济当作最重要的任务之一,同样为“并行路线”,金日成时期的“并行路线”重在国防,金正恩则将焦点置于经济。然而,不涉及计划经济本身的弊端的经济改革仍将是有限度的,加之核开发问题、投资环境等一系列制约性因素,未来朝鲜在经济领域所推行的任务仍将面临各种障碍和挑战,其预期的效果也将有待时间的检验。在内部提高效率改善经济管理,同时为从外部引进外资而扩大开放将成为今后一个时期朝鲜的经济政策方向。

  5. Methods of increasing the performance of radionuclide generators used in nuclear medicine: daughter nuclide build-up optimisation, elution-purification-concentration integration, and effective control of radionuclidic purity.

    Science.gov (United States)

    Le, Van So; Do, Zoe Phuc-Hien; Le, Minh Khoi; Le, Vicki; Le, Natalie Nha-Truc

    2014-06-10

    Methods of increasing the performance of radionuclide generators used in nuclear medicine radiotherapy and SPECT/PET imaging were developed and detailed for 99Mo/99mTc and 68Ge/68Ga radionuclide generators as the cases. Optimisation methods of the daughter nuclide build-up versus stand-by time and/or specific activity using mean progress functions were developed for increasing the performance of radionuclide generators. As a result of this optimisation, the separation of the daughter nuclide from its parent one should be performed at a defined optimal time to avoid the deterioration in specific activity of the daughter nuclide and wasting stand-by time of the generator, while the daughter nuclide yield is maintained to a reasonably high extent. A new characteristic parameter of the formation-decay kinetics of parent/daughter nuclide system was found and effectively used in the practice of the generator production and utilisation. A method of "early elution schedule" was also developed for increasing the daughter nuclide production yield and specific radioactivity, thus saving the cost of the generator and improving the quality of the daughter radionuclide solution. These newly developed optimisation methods in combination with an integrated elution-purification-concentration system of radionuclide generators recently developed is the most suitable way to operate the generator effectively on the basis of economic use and improvement of purposely suitable quality and specific activity of the produced daughter radionuclides. All these features benefit the economic use of the generator, the improved quality of labelling/scan, and the lowered cost of nuclear medicine procedure. Besides, a new method of quality control protocol set-up for post-delivery test of radionuclidic purity has been developed based on the relationship between gamma ray spectrometric detection limit, required limit of impure radionuclide activity and its measurement certainty with respect to

  6. Nuclear Theory - Nuclear Power

    Science.gov (United States)

    Svenne, J. P.; Canton, L.; Kozier, K. S.

    2008-01-01

    The results from modern nuclear theory are accurate and reliable enough to be used for practical applications, in particular for scattering that involves few-nucleon systems of importance to nuclear power. Using well-established nucleon-nucleon (NN) interactions that fit well the NN scattering data, and the AGS form of the three-body theory, we have performed precise calculations of low-energy neutron-deuteron (n+d) scattering. We show that three-nucleon force effects that have impact on the low-energy vector analyzing powers have no practical effects on the angular distribution of the n+d cross-section. There appear to be problems for this scattering in the evaluated nuclear data file (ENDF) libraries, at the incident neutron energies less than 3.2 MeV. Supporting experimental data in this energy region are rather old (>25 years), sparse and often inconsistent. Our three-body results at low energies, 50 keV to 10.0 MeV, are compared to the ENDF/B-VII.0 and JENDL (Japanese Evaluated Nuclear Data Library) -3.3 evaluated angular distributions. The impact of these results on the calculated reactivity for various critical systems involving heavy water is shown.

  7. Earthquake engineering for nuclear facilities

    CERN Document Server

    Kuno, Michiya

    2017-01-01

    This book is a comprehensive compilation of earthquake- and tsunami-related technologies and knowledge for the design and construction of nuclear facilities. As such, it covers a wide range of fields including civil engineering, architecture, geotechnical engineering, mechanical engineering, and nuclear engineering, for the development of new technologies providing greater resistance against earthquakes and tsunamis. It is crucial both for students of nuclear energy courses and for young engineers in nuclear power generation industries to understand the basics and principles of earthquake- and tsunami-resistant design of nuclear facilities. In Part I, "Seismic Design of Nuclear Power Plants", the design of nuclear power plants to withstand earthquakes and tsunamis is explained, focusing on buildings, equipment's, and civil engineering structures. In Part II, "Basics of Earthquake Engineering", fundamental knowledge of earthquakes and tsunamis as well as the dynamic response of structures and foundation ground...

  8. 基于势流体的核反应堆贮液容器动力特性分析%Dynamic Characteristic Analysis for Liquid Storage Container in Nuclear Reactors with a Potential-Based Fluid Formulation

    Institute of Scientific and Technical Information of China (English)

    艾红雷; 张毅雄

    2011-01-01

    The calculation scale of fluid-structure coupling is so huge that it was rarely used in engineering. A potential-based fluid formulation is used in this paper. The formulation connects the coupling terms of the fluid-structure characteristic value equation,so nonlinear continuous equation of liquid flowing is simplified to linear elliptic equation. In this way,the calculation scale was reduced to a great extent. It was verified in many examples that the formulation is very efficient to solve the dynamic problem of liquid storage container,which can be used in nuclear reactor engineering.%由于流-固耦合计算规模十分庞大,很少在工程中应用.本文采用势流体函数理论,将流-固耦合特征值方程的耦合项通过势函数联系,流体流动的非线性连续性方程可简化为线性椭圆方程,大大地缩减了流-固耦合计算的规模.通过实际的算例验证表明,采用基于势流体的流-固耦合方法求解贮液容器动力问题是十分高效的,适合在核反应堆工程中推广运用.

  9. Neuroepithelial transforming gene 1 (Net1) binds to caspase activation and recruitment domain (CARD)- and membrane-associated guanylate kinase-like domain-containing (CARMA) proteins and regulates nuclear factor κB activation.

    Science.gov (United States)

    Vessichelli, Mariangela; Ferravante, Angela; Zotti, Tiziana; Reale, Carla; Scudiero, Ivan; Picariello, Gianluca; Vito, Pasquale; Stilo, Romania

    2012-04-20

    The molecular complexes containing CARMA proteins have been recently identified as a key components in the signal transduction pathways that regulate activation of nuclear factor κB (NF-κB) transcription factor. Here, we used immunoprecipitation coupled with mass spectrometry to identify cellular binding partners of CARMA proteins. Our data indicate that the Rho guanine nucleotide exchange factor Net1 binds to CARMA1 and CARMA3 in resting and activated cells. Net1 expression induces NF-κB activation and cooperates with BCL10 and CARMA proteins in inducing NF-κB activity. Conversely, shRNA-mediated abrogation of Net1 results in impaired NF-κB activation following stimuli that require correct CARMA-BCL10-MALT1 complex formation and functioning. Microarray expression data are consistent with a positive role for Net1 on NF-κB activation. Thus, this study identifies Net1 as a CARMA-interacting molecule and brings important information on the molecular mechanisms that control NF-κB transcriptional activity.

  10. Neuroepithelial Transforming Gene 1 (Net1) Binds to Caspase Activation and Recruitment Domain (CARD)- and Membrane-associated Guanylate Kinase-like Domain-containing (CARMA) Proteins and Regulates Nuclear Factor κB Activation*

    Science.gov (United States)

    Vessichelli, Mariangela; Ferravante, Angela; Zotti, Tiziana; Reale, Carla; Scudiero, Ivan; Picariello, Gianluca; Vito, Pasquale; Stilo, Romania

    2012-01-01

    The molecular complexes containing CARMA proteins have been recently identified as a key components in the signal transduction pathways that regulate activation of nuclear factor κB (NF-κB) transcription factor. Here, we used immunoprecipitation coupled with mass spectrometry to identify cellular binding partners of CARMA proteins. Our data indicate that the Rho guanine nucleotide exchange factor Net1 binds to CARMA1 and CARMA3 in resting and activated cells. Net1 expression induces NF-κB activation and cooperates with BCL10 and CARMA proteins in inducing NF-κB activity. Conversely, shRNA-mediated abrogation of Net1 results in impaired NF-κB activation following stimuli that require correct CARMA-BCL10-MALT1 complex formation and functioning. Microarray expression data are consistent with a positive role for Net1 on NF-κB activation. Thus, this study identifies Net1 as a CARMA-interacting molecule and brings important information on the molecular mechanisms that control NF-κB transcriptional activity. PMID:22343628

  11. Transactions of the fifth symposium on space nuclear power systems

    Energy Technology Data Exchange (ETDEWEB)

    El-Genk, M.S.; Hoover, M.D. (eds.)

    1988-01-01

    This paper contains the presented papers at the fourth symposium on space nuclear power systems. Topics of these paper include: space nuclear missions and applications, reactors and shielding, nuclear electric and nuclear propulsion, high-temperature materials, instrumentation and control, energy conversion and storage, space nuclear fuels, thermal management, nuclear safety, simulation and modeling, and multimegawatt system concepts. (LSP)

  12. Transactions of the fourth symposium on space nuclear power systems

    Energy Technology Data Exchange (ETDEWEB)

    El-Genk, M.S.; Hoover, M.D. (eds.)

    1987-01-01

    This paper contains the presented papers at the fourth symposium on space nuclear power systems. Topics of these papers include: space nuclear missions and applications, reactors and shielding, nuclear electric and nuclear propulsion, refractory alloys and high-temperature materials, instrumentation and control, energy conversion and storage, space nuclear fuels, thermal management, nuclear safety, simulation and modeling, and multimegawatt system concepts. (LSP)

  13. The role of nuclear law in nuclear safety after Fukushima; El rol del derecho nuclear en seguridad nuclear luego de Fukushima

    Energy Technology Data Exchange (ETDEWEB)

    Cardozo, Diva E. Puig, E-mail: d.puig@adinet.com.uy [International Nuclear Law Association (INLA), Montevideo (Uruguay)

    2013-07-01

    The paper contains the following topics: nuclear law, origin and evolution, role of the legal instruments on nuclear safety, nuclear safety the impact of major nuclear accidents: Chernobyl and Fukushima. The response of the nuclear law post Fukushima. Safety and security. International framework for nuclear safety: nuclear convention joint convention on safety on spent fuel management and on the safety of radioactive waste management. The Fukushima World Conference on Nuclear Safety. Convention on Prompt Notification and Assistance in case of a Nuclear Accident or Radiological Emergency. Plan of Action for Nuclear Safety. IAEA recommendations for the safety transport of radioactive material. International framework for nuclear security. Convention on the Physical Protection of Nuclear Materials. International Convention for the Suppression of Acts Against Nuclear Terrorism. Resolution No. 1540 of the Security Council of United Nations (2004). Measures to strengthen international safety. Code of conduct on the safety research reactor.

  14. Nuclear forensics: Soil content

    Energy Technology Data Exchange (ETDEWEB)

    Beebe, Merilyn Amy [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

    2015-08-31

    Nuclear Forensics is a growing field that is concerned with all stages of the process of creating and detonating a nuclear weapon. The main goal is to prevent nuclear attack by locating and securing nuclear material before it can be used in an aggressive manner. This stage of the process is mostly paperwork; laws, regulations, treaties, and declarations made by individual countries or by the UN Security Council. There is some preliminary leg work done in the form of field testing detection equipment and tracking down orphan materials; however, none of these have yielded any spectacular or useful results. In the event of a nuclear attack, the first step is to analyze the post detonation debris to aid in the identification of the responsible party. This aspect of the nuclear forensics process, while reactive in nature, is more scientific. A rock sample taken from the detonation site can be dissolved into liquid form and analyzed to determine its chemical composition. The chemical analysis of spent nuclear material can provide valuable information if properly processed and analyzed. In order to accurately evaluate the results, scientists require information on the natural occurring elements in the detonation zone. From this information, scientists can determine what percentage of the element originated in the bomb itself rather than the environment. To this end, element concentrations in soils from sixty-nine different cities are given, along with activity concentrations for uranium, thorium, potassium, and radium in various building materials. These data are used in the analysis program Python.

  15. Fire modeling of the Heiss Dampf Reaktor containment

    Energy Technology Data Exchange (ETDEWEB)

    Nicolette, V.F. [Sandia National Labs., Albuquerque, NM (United States); Yang, K.T. [Notre Dame Univ., IN (United States)

    1995-09-01

    This report summarizes Sandia National Laboratories` participation in the fire modeling activities for the German Heiss Dampf Reaktor (HDR) containment building, under the sponsorship of the United States Nuclear Regulatory Commission. The purpose of this report is twofold: (1) to summarize Sandia`s participation in the HDR fire modeling efforts and (2) to summarize the results of the international fire modeling community involved in modeling the HDR fire tests. Additional comments, on the state of fire modeling and trends in the international fire modeling community are also included. It is noted that, although the trend internationally in fire modeling is toward the development of the more complex fire field models, each type of fire model has something to contribute to the understanding of fires in nuclear power plants.

  16. Building Languages

    Science.gov (United States)

    ... Training Manually Coded English (MCE) Natural Gestures Speech Speech Reading (Lip Reading) Even though American Sign Language (ASL) is not a building block, it is sometimes used together with one or more building blocks. Close Information For... Media Policy Makers File Formats Help: How do I view ...

  17. Building Procurement

    DEFF Research Database (Denmark)

    Andersson, Niclas

    2007-01-01

    ‘The procurement of construction work is complex, and a successful outcome frequently elusive’. With this opening phrase of the book, the authors take on the challenging job of explaining the complexity of building procurement. Even though building procurement systems are, and will remain, comple...

  18. A container

    DEFF Research Database (Denmark)

    2012-01-01

    A container assembly for the containment of fluids or solids under a pressure different from the ambient pressure comprising a container (2) comprising an opening and an annular sealing, a lid (3) comprising a central portion (5) and engagement means (7) for engaging the annular flange, and seali...

  19. A container

    DEFF Research Database (Denmark)

    2012-01-01

    A container assembly for the containment of fluids or solids under a pressure different from the ambient pressure comprising a container (2) comprising an opening and an annular sealing, a lid (3) comprising a central portion (5) and engagement means (7) for engaging the annular flange, and seali...

  20. Nuclear control

    Energy Technology Data Exchange (ETDEWEB)

    Yoon, Wan Kee [Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)

    1995-02-01

    International cooperation in nuclear industries requires nuclear control as prerequisites. The concept of nuclear control is based on the Treaty on the Non-proliferation of Nuclear Weapon (NPT). The International Atomic Energy Agency (IAEA) plays central role in implementing nuclear control. Nuclear control consists of nuclear safeguards, physical protection, and export/import control. Each member state of NPT is subject to the IAEA`s safeguards by concluding safeguards agreements with the IAEA. IAEA recommends member states to implement physical protection on nuclear materials by `The Physical Protection of Nuclear Material` and `The Convention on the Physical Protection of Nuclear Material` of IAEA. Export/Import Control is to deter development of nuclear weapons by controlling international trade on nuclear materials, nuclear equipments and technology. Current status of domestic and foreign nuclear control implementation including recent induction of national inspection system in Korea is described and functions of recently set-up Technology Center for Nuclear Control (TCNC) under the Korea Atomic Energy Research Institute (KAERI) are also explained. 6 tabs., 11 refs. (Author).

  1. Nuclear Pasta Formation

    CERN Document Server

    Schneider, A S; Hughto, J; Berry, D K

    2013-01-01

    The formation of complex nonuniform phases of nuclear matter, known as nuclear pasta, is studied with molecular dynamics simulations containing 51200 nucleons. A phenomenological nuclear interaction is used that reproduces the saturation binding energy and density of nuclear matter. Systems are prepared at an initial density of 0.10fm$^{-3}$ and then the density is decreased by expanding the simulation volume at different rates to densities of 0.01 fm$^{-3}$ or less. An originally uniform system of nuclear matter is observed to form spherical bubbles ("swiss cheese"), hollow tubes, flat plates ("lasagna"), thin rods ("spaghetti") and, finally, nearly spherical nuclei with decreasing density. We explicitly observe nucleation mechanisms, with decreasing density, for these different pasta phase transitions. Topological quantities known as Minkowski functionals are obtained to characterize the pasta shapes. Different pasta shapes are observed depending on the expansion rate. This indicates non equilibrium effects...

  2. World nuclear outlook 1995

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-09-29

    As part of the EIA program to provide energy information, this analysis report presents the current status and projections through 2015 of nuclear capacity, generation, and fuel cycle requirements for all countries in the world using nuclear power to generate electricity for commercial use. It also contains information and forecasts of developments in the uranium market. Long-term projections of US nuclear capacity, generation, and spent fuel discharges for two different scenarios through 2040 are developed for the Department of Energy`s Office of Civilian Radioactive Waste Management (OCRWM). In turn, the OCRWM provides partial funding for preparation of this report. The projections of uranium requirements are provided to the Organization for Economic Cooperation and Development (OECD) for preparation of the Nuclear Energy Agency/OECD report, Summary of Nuclear Power and Fuel Cycle Data in OECD Member Countries.

  3. World nuclear outlook 1994

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1994-12-01

    As part of the EIA program to provide energy information, this analysis report presents the current status and projections through 2010 of nuclear capacity, generation, and fuel cycle requirements for all countries in the world using nuclear power to generate electricity for commercial use. It also contains information and forecasts of developments in the uranium market. Long-term projections of US nuclear capacity, generation, and spent fuel discharges for three different scenarios through 2040 are developed for the Department of Energy`s Office of Civilian Radioactive Waste Management (OCRWM). In turn, the OCRWM provides partial funding for preparation of this report. The projections of uranium requirements are provided to the Organization for Economic Cooperation and Development (OECD) for preparation of the Nuclear Energy Agency/OECD report, Summary of Nuclear Power and Fuel Cycle Data in OECD Member Countries.

  4. European Nuclear Features

    Energy Technology Data Exchange (ETDEWEB)

    Barre, B.; Gonzalez, E.; Diaz Diaz, J.L.; Jimenez, J.L.; Velarde, G.; Navarro, J.M.; Hittner, D.; Dominguez, M.T.; Bollini, G.; Martin, A.; Suarez, J.; Traini, E.; Lang-Lenton, J.

    2004-09-01

    ''European Nuclear Features - ENF'' is a joint publication of the three specialized technical journals, Nuclear Espana (Spain), Revue General Nucleaire (France), and atw - International Journal of Nuclear Power (Germany). The ENF support the international Europeen exchange of information and news about energy and nuclear power. News items, comments, and scientific and technical contributions will cover important aspects of the field. The second issue of ENF contains contributions about theses topics, among others: Institutional and Political Changes in the EU. - CIEMAT Department of Nuclear Fission: A General Overview. - Inertial Fusion Energy at DENIM. - High Temperature Reactors. European Research Programme. - On Site Assistance to Khmelnitsky NPP 1 and 2 (Ukraine). - Dismantling and Decommissioning of Vandellos I. (orig.)

  5. Nuclear energy debate

    CERN Document Server

    Healey, Justin

    2012-01-01

    The debate over the introduction of nuclear power in Australia has recently become more heated in light of safety concerns over the nuclear reactor meltdown emergency in Japan. Australia has also just committed to a carbon trading scheme to address its reliance on coal-fired energy and reduce greenhouse emissions. With 40% of the world's uranium located in Australia, the economic, environmental and health considerations are significant. This book contains an overview of global nuclear energy use and production, and presents a range of current opinions debating the pros and cons of Australia's

  6. Unrestricted re-use of decommissioned nuclear laboratories

    Energy Technology Data Exchange (ETDEWEB)

    Cornelissen, R.; Noynaert, L.; Harnie, S.; Marien, J.

    1996-09-18

    A decommissioning strategy was developed by the Belgian Nuclear Research Centre SCK/CEN. In this strategy decommissioning works are limited to the radioactive parts of the nuclear installation. After obtaining an attestation for unrestricted reuse of the building after removal of all radioactivity, the building can be used for new industrial purposes outside the nuclear field. The decommissioning activities according to this strategy have been applied in four buildings. The results are described.

  7. Modeling of delayed strains of concrete under biaxial loadings. Application to the reactor containment of nuclear power plants; Modelisation des deformations differees du beton sous sollicitations biaxiales. application aux enceintes de confinement de batiments reacteurs des centrales nucleaires

    Energy Technology Data Exchange (ETDEWEB)

    Benboudjema, F

    2002-12-15

    The prediction of delayed strains is of crucial importance for durability and long-term serviceability of concrete structures (bridges, containment vessels of nuclear power plants, etc.). Indeed, creep and shrinkage cause cracking, losses of pre-stress and redistribution of stresses, and also, rarely, the ruin of the structure. The objective of this work is to develop numerical tools, able to predict the long-term behavior of concrete structures. Thus, a new hydro mechanical model is developed, including the description of drying, shrinkage, creep and cracking phenomena for concrete as a non-saturated porous medium. The modeling of drying shrinkage is based on an unified approach of creep and shrinkage. Basic and drying creep models are based on relevant chemo-physical mechanisms, which occur at different scales of the cement paste. The basic creep is explicitly related to the micro-diffusion of the adsorbed water between inter-hydrates and intra-hydrates and the capillary pores, and the sliding of the C-S-H gel at the nano-porosity level. The drying creep is induced by the micro-diffusion of the adsorbed water at different scales of the porosity, under the simultaneous effects of drying and mechanical loadings. Drying shrinkage is, therefore, assumed to result from the elastic and delayed response of the solid skeleton, submitted to both capillary and disjoining pressures. Furthermore, the cracking behavior of concrete is described by an orthotropic elastoplastic damage model. The coupling between all these phenomena is performed by using effective stresses which account for both external applied stresses and pore pressures. This model has been incorporated into a finite element code. The analysis of the long-term behavior is also performed on concrete specimens and prestressed concrete structures submitted to simultaneous drying and mechanical loadings. (author)

  8. Hydrogen risk in the Containment Filtered Venting System

    Energy Technology Data Exchange (ETDEWEB)

    Na, Young Su; Ha, Kwang Soon [KAERI, Daejeon (Korea, Republic of); Cho, Song-Won [NSE, Daejeon (Korea, Republic of)

    2015-05-15

    It was observed that the thermal hydraulic conditions in the CFVS (Containment Filtered Venting System) vessel sharply changed markedly, especially the steam condensation in the early CFVS operation can affect the hydrogen behavior such as the combustion. This paper summarizes the calculated results on hydrogen concentration in the CFVS vessel, which was presented at The Ninth Korea-Japan Symposium on Nuclear Thermal Hydraulics and Safety (NTHAS9) last year. The MELCOR computer code calculated the thermal-hydraulic conditions in the containment building of OPR 1000, and in the cylindrical CFVS vessel with 3 m in diameter and 6.5 m in height under an SBO. After the operation of the CFVS, the pressure and temperature in the containment building decreased, and those in the CFVS vessel jumped from the initial conditions of atmosphere pressure and room temperature. These big differences of thermal-hydraulic conditions can make the volumetric concentrations of steam and gas mixtures in the CFVS vessel to be changed in comparison with those in the containment building. The volumetric concentration of hydrogen increased from 6% in the containment to 14% in the CFVS vessel after the operation of the CFVS, while the concentration of steam decreased from 58% in the containment to 3% in the CFVS vessel. The increased volumetric concentration of hydrogen (14%) with the other concentrations of steam (3%) and air (60%) in the CFVS vessel exists within the region of the burn limit in the Shapiro diagram. This possibility of the hydrogen combustion can threaten the integrity of the CFVS.

  9. Energy from nuclear fission an introduction

    CERN Document Server

    De Sanctis, Enzo; Ripani, Marco

    2016-01-01

    This book provides an overview on nuclear physics and energy production from nuclear fission. It serves as a readable and reliable source of information for anyone who wants to have a well-balanced opinion about exploitation of nuclear fission in power plants. The text is divided into two parts; the first covers the basics of nuclear forces and properties of nuclei, nuclear collisions, nuclear stability, radioactivity, and provides a detailed discussion of nuclear fission and relevant topics in its application to energy production. The second part covers the basic technical aspects of nuclear fission reactors, nuclear fuel cycle and resources, safety, safeguards, and radioactive waste management. The book also contains a discussion of the biological effects of nuclear radiation and of radiation protection, and a summary of the ten most relevant nuclear accidents. The book is suitable for undergraduates in physics, nuclear engineering and other science subjects. However, the mathematics is kept at a level that...

  10. Materials in Nuclear Waste Disposition

    Science.gov (United States)

    Rebak, Raul B.

    2014-03-01

    Commercial nuclear energy has been used for over 6 decades; however, to date, none of the 30+ countries with nuclear power has opened a repository for high-level waste (HLW). All countries with nuclear waste plan to dispose of it in metallic containers located in underground geologically stable repositories. Some countries also have liquid nuclear waste that needs to be reduced and vitrified before disposition. The five articles included in this topic offer a cross section of the importance of alloy selection to handle nuclear waste at the different stages of waste processing and disposal.

  11. Nuclear structure far from stability

    CERN Document Server

    Vretenar, D

    2005-01-01

    Modern nuclear structure theory is rapidly evolving towards regions of exotic short-lived nuclei far from stability, nuclear astrophysics applications, and bridging the gap between low-energy QCD and the phenomenology of finite nuclei. The principal objective is to build a consistent microscopic theoretical framework that will provide a unified description of bulk properties, nuclear excitations and reactions. Stringent constraints on the microscopic approach to nuclear dynamics, effective nuclear interactions, and nuclear energy density functionals, are obtained from studies of the structure and stability of exotic nuclei with extreme isospin values, as well as extended asymmetric nucleonic matter. Recent theoretical advances in the description of structure phenomena in exotic nuclei far from stability are reviewed.

  12. Nuclear structure far from stability

    Science.gov (United States)

    Vretenar, D.

    2005-04-01

    Modern nuclear structure theory is rapidly evolving towards regions of exotic shortlived nuclei far from stability, nuclear astrophysics applications, and bridging the gap between low-energy QCD and the phenomenology of finite nuclei. The principal objective is to build a consistent microscopic theoretical framework that will provide a unified description of bulk properties, nuclear excitations and reactions. Stringent constraints on the microscopic approach to nuclear dynamics, effective nuclear interactions, and nuclear energy density functionals, are obtained from studies of the structure and stability of exotic nuclei with extreme isospin values, as well as extended asymmetric nucleonic matter. Recent theoretical advances in the description of structure phenomena in exotic nuclei far from stability are reviewed.

  13. Religious building energy use

    Energy Technology Data Exchange (ETDEWEB)

    Spielvogel, L.G.; Rudin, A.

    1988-02-01

    The Interfaith Coalition on Energy (ICE) was organized in 1980 by the Philadelphia area religious community and, funded in 1982 by local private foundations and corporations, began an energy management program for religious buildings whose utility bills are paid by congregations. Since that time, ICE has completed on-site energy audits for 226 congregations with a total of 546 buildings. Each audit report contains a description of the facilities and their energy systems, a baseline year of energy data, a computation of energy use per square foot, and a list of recommendations to reduce energy costs in order of simple payback.

  14. Building Inclusion

    NARCIS (Netherlands)

    Jeanet Kullberg; Isik Kulu-Glasgow

    2009-01-01

    The social inclusion of immigrants and ethnic minorities is a central issue in many European countries. Governments face challenges in ensuring housing for immigrants, delivering public services, promoting neighbourhood coexistence and addressing residential segregation. The Building Inclusion proje

  15. Superpower nuclear minimalism

    Energy Technology Data Exchange (ETDEWEB)

    Graben, E.K.

    1992-01-01

    During the Cold War, the United States and the Soviet Union competed in building weapons -- now it seems like America and Russia are competing to get rid of them the fastest. The lengthy process of formal arms control has been replaced by exchanges of unilateral force reductions and proposals for reciprocal reductions not necessarily codified by treaty. Should superpower nuclear strategies change along with force postures President Bush has yet to make a formal pronouncement on post-Cold War American nuclear strategy, and it is uncertain if the Soviet/Russian doctrine of reasonable sufficiency formulated in the Gorbachev era actually heralds a change in strategy. Some of the provisions in the most recent round of unilateral proposals put forth by Presidents Bush and Yeltsin in January 1992 are compatible with a change in strategy. Whether such a change has actually occurred remains to be seen. With the end of the Cold War and the breakup of the Soviet Union, the strategic environment has fundamentally changed, so it would seem logical to reexamine strategy as well. There are two main schools of nuclear strategic thought: a maximalist school, mutual assured destruction (MAD) which emphasizes counterforce superiority and nuclear war- fighting capability, and a MAD-plus school, which emphasizes survivability of an assured destruction capability along with the ability to deliver small, limited nuclear attacks in the event that conflict occurs. The MAD-plus strategy is based on an attempt to conventionalize nuclear weapons which is unrealistic.

  16. Sustainable Buildings

    DEFF Research Database (Denmark)

    Tommerup, Henrik M.; Elle, Morten

    The scientific community agrees that: all countries must drastically and rapidly reduce their CO2 emissions and that energy efficient houses play a decisive role in this. The general attitude at the workshop on Sustainable Buildings was that we face large and serious climate change problems...... that need urgent action. The built environment is an obvious area to put effort into because of the large and cost-effective energy saving potential and potential for Renewable Energy-based supply systems for buildings....

  17. U.S. Nuclear Power Reactor Plant Status

    Data.gov (United States)

    Nuclear Regulatory Commission — Demographic data on U.S. commercial nuclear power reactors, including: plant name/unit number, docket number, location, licensee, reactor/containment type, nuclear...

  18. Carbon Efficient Building Solutions

    Directory of Open Access Journals (Sweden)

    Pellervo Matilainen

    2010-03-01

    Full Text Available Traditionally, the Finnish legislation have focused on energy use and especially on energy used for heating space in buildings. However, in many cases this does not lead to the optimal concept in respect to minimizing green house gases. This paper studies how CO2 emission levels are affected by different measures to reduce energy use in buildings. This paper presents two real apartment buildings with different options of energy efficiency and power sources. The calculations clearly show that in the future electricity and domestic hot water use will have high importance in respect to energy efficiency, and therefore also CO2 equivalent (eq emissions. The importance increases when the energy efficiency of the building increases. There are big differences between average Finnish production and individual power plants; CO2 eq emissions might nearly double depending on the energy source and the power plant type. Both a building with an efficient district heating as a power source, and a building with ground heat in addition to nuclear power electricity as a complimentary electricity source performed very similarly to each other in respect to CO2 eq emissions. However, it is dangerous to conclude that it is not important which energy source is chosen. If hypothetically, the use of district heating would dramatically drop, the primary energy factor and CO2 eq emissions from electricity would rise, which in turn would lead to the increase of the ground heat systems emissions. A problem in the yearly calculations is that the fact that it is very important, sometimes even crucial, when energy is needed, is always excluded.

  19. Nuclear Scans

    Science.gov (United States)

    Nuclear scans use radioactive substances to see structures and functions inside your body. They use a special ... images. Most scans take 20 to 45 minutes. Nuclear scans can help doctors diagnose many conditions, including ...

  20. Nuclear Chemistry.

    Science.gov (United States)

    Chemical and Engineering News, 1979

    1979-01-01

    Provides a brief review of the latest developments in nuclear chemistry. Nuclear research today is directed toward increased activity in radiopharmaceuticals and formation of new isotopes by high-energy, heavy-ion collisions. (Author/BB)

  1. Nuclear Power in Space

    Science.gov (United States)

    1994-01-01

    In the early years of the United States space program, lightweight batteries, fuel cells, and solar modules provided electric power for space missions. As missions became more ambitious and complex, power needs increased and scientists investigated various options to meet these challenging power requirements. One of the options was nuclear energy. By the mid-1950s, research had begun in earnest on ways to use nuclear power in space. These efforts resulted in the first radioisotope thermoelectric generators (RTGs), which are nuclear power generators build specifically for space and special terrestrial uses. These RTGs convert the heat generated from the natural decay of their radioactive fuel into electricity. RTGs have powered many spacecraft used for exploring the outer planets of the solar system and orbiting the sun and Earth. They have also landed on Mars and the moon. They provide the power that enables us to see and learn about even the farthermost objects in our solar system.

  2. Nuclear weapons, nuclear effects, nuclear war

    Energy Technology Data Exchange (ETDEWEB)

    Bing, G.F.

    1991-08-20

    This paper provides a brief and mostly non-technical description of the militarily important features of nuclear weapons, of the physical phenomena associated with individual explosions, and of the expected or possible results of the use of many weapons in a nuclear war. Most emphasis is on the effects of so-called ``strategic exchanges.``

  3. Nuclear structure

    CERN Document Server

    Nazarewicz, W

    1999-01-01

    Current developments in nuclear structure are discussed from a theoretical perspective. The studies of the nuclear many-body system provide us with invaluable information about the nature of the nuclear interaction, nucleonic correlations at various energy-distance scales, and the modes of the nucleonic matter.

  4. Our Buildings, Ourselves.

    Science.gov (United States)

    Roodman, David Malin; Lenssen, Nicholas

    1994-01-01

    Reviews in detail environmental impacts associated with buildings. Discusses building construction, internal environments, building life spans, building materials, protection from climate, and amenities. (LZ)

  5. Safety analysis report 231-Z Building

    Energy Technology Data Exchange (ETDEWEB)

    Powers, C.S.

    1989-03-01

    This report provides an intensive review of the nuclear safety of the operation of the 231-Z Building. For background information complete descriptions of the floor plan, building services, alarm systems, and glove box systems are included in this report. In addition, references are included to The Plutonium Laboratory Radiation Work Procedures, Safety Guides, 231-Z Operating Procedures Manual and Nuclear Materials accountability Procedures. Engineered and administrative features contribute to the overall safety of personnel, the building, and environs. The consequences of credible incidents were considered and are discussed.

  6. International Nuclear Security Situation And China’s Approach

    Institute of Scientific and Technical Information of China (English)

    Liu Chong

    2016-01-01

    Since 2010,the three Nuclear Security Summits have made a number of achievements,but the international nuclear security situation is still not relaxed.The rapid development of China’s domestic nuclear facilities and a large amount of nuclear and radioactive materials related to nuclear power,active international nuclear black market in China’s surrounding regions,rather serious domestic and international terrorist threats as well as the emerging technology development bring about new challenges to nuclear security.Facing the complicated and long-term nuclear security situation,China from the perspective of monitoring mechanism,laws and regulations system,technical capability-building and nuclear emergency preparedness,takes a series of effective measures to build the national nuclear security capacity,and strictly fulfills its international obligations,actively participates in upgrading the international nuclear non-proliferation regime and relevant international rules,and actively takes part in the Nuclear Security Summit process,strengthens bilateral cooperation on nuclear security with major countries especially the United States of America,and jointly organizes various training with International Atomic Energy Agency,which has made great contributions to upgrading the global nuclear security level.At the end of the Nuclear Security Summit process,China should continue to strengthen its domestic nuclear security capacity building,and promote the international community to treat the root causes and symptoms,adopt a comprehensive strategy,and work together,effectively prevent and dissolve the nuclear terrorist threats.

  7. 徐大堡核电站运行和维修技术支持大楼的火灾自动报警系统设计%Automatic Fire Alarm System Design of Operation and Maintenance Technical Support Building of XU Dapu Nuclear Power Plant

    Institute of Scientific and Technical Information of China (English)

    韩圆

    2016-01-01

    Compared with other auxiliary workshops,XU Dapu Nuclear Power Plant has the characteristic of higher personnel density,more fire compartments and more concentrated communication machine rooms, etc. This paper introduced the design of the automatic fire alarm system based on the fire detection requirements,fire-fighting requirements and the characteristics of the building. The design could provide a certain guarantee for the safe operation of the building,and also provide a reference of automatic fire alarm system design for the operation and maintenance technology support building of subsequent AP1000 million kilowatt PWR nuclear power plant.%相比核电站其他辅助厂房,徐大堡核电站运行和维修技术支持大楼具有人员密度高、防火分区多、通信机房集中等特点。根据该建筑物特点、火灾探测和灭火要求对大楼火灾自动报警系统进行设计,为大楼安全运行提供一定保障,也为后续A P1000百万千瓦级压水堆核电站运行和维修技术支持大楼的火灾自动报警系统设计提供参考。

  8. Nuclear spectroscopy

    CERN Document Server

    Ajzenberg-Selove, Fay

    1960-01-01

    Nuclear Spectroscopy, Part B focuses on the ways in which experimental data may be analyzed to furnish information about nuclear parameters and nuclear models in terms of which the data are interpreted.This book discusses the elastic and inelastic potential scattering amplitudes, role of beta decay in nuclear physics, and general selection rules for electromagnetic transitions. The nuclear shell model, fundamental coupling procedure, vibrational spectra, and empirical determination of the complex potential are also covered. This publication is suitable for graduate students preparing for exper

  9. Nuclear research reactors in Brazil

    Energy Technology Data Exchange (ETDEWEB)

    Cota, Anna Paula Leite; Mesquita, Amir Zacarias, E-mail: aplc@cdtn.b, E-mail: amir@cdtn.b [Centro de Desenvolvimento da Tecnologia Nuclear (CDTN/CNEN-MG), Belo Horizonte, MG (Brazil)

    2011-07-01

    The rising concerns about global warming and energy security have spurred a revival of interest in nuclear energy, giving birth to a 'nuclear power renaissance' in several countries in the world. Particularly in Brazil, in the recent years, the nuclear power renaissance can be seen in the actions that comprise its nuclear program, summarily the increase of the investments in nuclear research institutes and the government target to design and build the Brazilian Multipurpose research Reactor (BMR). In the last 50 years, Brazilian research reactors have been used for training, for producing radioisotopes to meet demands in industry and nuclear medicine, for miscellaneous irradiation services and for academic research. Moreover, the research reactors are used as laboratories to develop technologies in power reactors, which are evaluated today at around 450 worldwide. In this application, those reactors become more viable in relation to power reactors by the lowest cost, by the operation at low temperatures and, furthermore, by lower demand for nuclear fuel. In Brazil, four research reactors were installed: the IEA-R1 and the MB-01 reactors, both at the Instituto de Pesquisas Energeticas Nucleares (IPEN, Sao Paulo); the Argonauta, at the Instituto de Engenharia Nuclear (IEN, Rio de Janeiro) and the IPR-R1 TRIGA reactor, at the Centro de Desenvolvimento da Tecnologia Nuclear (CDTN, Belo Horizonte). The present paper intends to enumerate the characteristics of these reactors, their utilization and current academic research. Therefore, through this paper, we intend to collaborate on the BMR project. (author)

  10. Nuclear research reactors in Brazil

    Energy Technology Data Exchange (ETDEWEB)

    Cota, Anna Paula Leite; Mesquita, Amir Zacarias, E-mail: aplc@cdtn.b, E-mail: amir@cdtn.b [Centro de Desenvolvimento da Tecnologia Nuclear (CDTN/CNEN-MG), Belo Horizonte, MG (Brazil)

    2011-07-01

    The rising concerns about global warming and energy security have spurred a revival of interest in nuclear energy, giving birth to a 'nuclear power renaissance' in several countries in the world. Particularly in Brazil, in the recent years, the nuclear power renaissance can be seen in the actions that comprise its nuclear program, summarily the increase of the investments in nuclear research institutes and the government target to design and build the Brazilian Multipurpose research Reactor (BMR). In the last 50 years, Brazilian research reactors have been used for training, for producing radioisotopes to meet demands in industry and nuclear medicine, for miscellaneous irradiation services and for academic research. Moreover, the research reactors are used as laboratories to develop technologies in power reactors, which are evaluated today at around 450 worldwide. In this application, those reactors become more viable in relation to power reactors by the lowest cost, by the operation at low temperatures and, furthermore, by lower demand for nuclear fuel. In Brazil, four research reactors were installed: the IEA-R1 and the MB-01 reactors, both at the Instituto de Pesquisas Energeticas Nucleares (IPEN, Sao Paulo); the Argonauta, at the Instituto de Engenharia Nuclear (IEN, Rio de Janeiro) and the IPR-R1 TRIGA reactor, at the Centro de Desenvolvimento da Tecnologia Nuclear (CDTN, Belo Horizonte). The present paper intends to enumerate the characteristics of these reactors, their utilization and current academic research. Therefore, through this paper, we intend to collaborate on the BMR project. (author)

  11. Analysis for Eccentric Multi Canister Overpack (MCO) Drops at the Canister Storage Building (CSB) (CSB-S-0073)

    Energy Technology Data Exchange (ETDEWEB)

    TU, K.C.

    1999-10-08

    Multi-Canister Overpacks (MCOs) containing spent nuclear fuel (SNF) will be routinely handled at the Canister Storage Building (CSB) during fuel movement operations in the SNF Project. This analysis was performed to investigate the potential for damage from an eccentric accidental drop onto the standard storage tube, overpack tube, service station, or sample/weld station. Appendix D was added to the FDNW document to include the peer Review Comment Record & transmittal record.

  12. Development of nuclear fuel cycle technologies - bases of long-term provision of fuel and environmental safety of nuclear power

    Energy Technology Data Exchange (ETDEWEB)

    Solonin, M.I.; Polyakov, A.S.; Zakharkin, B.S.; Smelov, V.S.; Nenarokomov, E.A.; Mukhin, I.V. [SSC, RF, A.A. Bochvar ALL-Russia Research Institute of Inorganic Materials, Moscow (Russian Federation)

    2000-07-01

    To-day nuclear power is one of the options, however, to-morrow it may become the main source of the energy, thus, providing for the stable economic development for the long time to come. The availability of the large-scale nuclear power in the foreseeable future is governed by not only the safe operation of nuclear power plants (NPP) but also by the environmentally safe management of spent nuclear fuel, radioactive waste conditioning and long-term storage. More emphasis is to be placed to the closing of the fuel cycle in view of substantial quantities of spent nuclear fuel arisings. The once-through fuel cycle that is cost effective at the moment cannot be considered to be environmentally safe even for the middle term since the substantial build-up of spent nuclear fuel containing thousands of tons Pu will require the resolution of the safe management problem in the nearest future and is absolutely unjustified in terms of moral ethics as a transfer of the responsibility to future generations. The minimization of radioactive waste arisings and its radioactivity is only feasible with the closed fuel cycle put into practice and some actinides and long-lived fission radionuclides burnt out. The key issues in providing the environmentally safe fuel cycle are efficient processes of producing fuel for NPP, radionuclide after-burning included, a long-term spent nuclear fuel storage and reprocessing as well as radioactive waste management. The paper deals with the problems inherent in producing fuel for NPP with a view for the closed fuel cycle. Also discussed are options of the fuel cycle, its effectiveness and environmental safety with improvements in technologies of spent nuclear fuel reprocessing and long-lived radionuclide partitioning. (authors)

  13. Kuosheng Mark III containment analyses using GOTHIC

    Energy Technology Data Exchange (ETDEWEB)

    Lin, Ansheng, E-mail: samuellin1999@iner.gov.tw; Chen, Yen-Shu; Yuann, Yng-Ruey

    2013-10-15

    Highlights: • The Kuosheng Mark III containment model is established using GOTHIC. • Containment pressure and temperature responses due to LOCA are presented. • The calculated results are all below the design values and compared with the FSAR results. • The calculated results can be served as an analysis reference for an SPU project in the future. -- Abstract: Kuosheng nuclear power plant in Taiwan is a twin-unit BWR/6 plant, and both units utilize the Mark III containment. Currently, the plant is performing a stretch power uprate (SPU) project to increase the core thermal power to 103.7% OLTP (original licensed thermal power). However, the containment response in the Kuosheng Final Safety Analysis Report (FSAR) was completed more than twenty-five years ago. The purpose of this study is to establish a Kuosheng Mark III containment model using the containment program GOTHIC. The containment pressure and temperature responses under the design-basis accidents, which are the main steam line break (MSLB) and the recirculation line break (RCLB) accidents, are investigated. Short-term and long-term analyses are presented in this study. The short-term analysis is to calculate the drywell peak pressure and temperature which happen in the early stage of the LOCAs. The long-term analysis is to calculate the peak pressure and temperature of the reactor building space. In the short-term analysis, the calculated peak drywell to wetwell differential pressure is 140.6 kPa for the MSLB, which is below than the design value of 189.6 kPa. The calculated peak drywell temperature is 158 °C, which is still below the design value of 165.6 °C. In addition, in the long-term analysis, the calculated peak containment pressure is 47 kPa G, which is below the design value of 103.4 kPa G. The calculated peak values of containment temperatures are 74.7 °C, which is lower than the design value of 93.3 °C. Therefore, the Kuosheng Mark III containment can maintain the integrity after

  14. Peripheral blood mitochondrial DNA/nuclear DNA (mtDNA/nDNA) ratio as a marker of mitochondrial toxicities of stavudine containing antiretroviral therapy in HIV-infected Malawian patients.

    Science.gov (United States)

    Kampira, Elizabeth; Dzobo, Kevin; Kumwenda, Johnstone; van Oosterhout, Joep J; Parker, M Iqbal; Dandara, Collet

    2014-07-01

    Mitochondrial toxicity is a major concern related to nucleoside reverse transcriptase inhibitors. Common manifestations are peripheral neuropathy and lipodystrophy. Depletion of mitochondria has been associated with mitochondrial dysfunction. We investigated whether mitochondria DNA (mtDNA) levels in peripheral blood can be used as biomarker of stavudine-associated mitochondrial toxicities. We enrolled 203 HIV-infected Malawian adult patients on stavudine-containing ART and 64 healthy controls of Bantu origin in a cross-sectional study. Total DNA was extracted from whole blood.The glyceraldehyde-3-phosphate dehydrogenase gene was used to estimate nuclear DNA (nDNA) levels and the ATP synthase-8 mitochondrial DNA gene to estimate mtDNA levels, from which mtDNA/nDNA ratios were determined. MtDNA subhaplogroups were established by sequencing. Among patients, peripheral neuropathy was present in 21% (43/203), lipodystrophy in 18% (20/112), elevated lactate level (>2.5 mmol/L) in 17% (19/113). Healthy controls had a higher median mtDNA/nDNA ratio when compared to HIV/AIDS patients (6.64 vs. 5.08; p=0.05), patients presenting with peripheral neuropathy (6.64 vs. 3.40, p=0.039), and patients with high lactate levels (6.64 vs. 0.68, p=0.024), respectively. Significant differences in median mtDNA/nDNA ratios were observed between patients with high and normal lactate levels (5.88 vs. 0.68, p=0.018). The median mtDNA/nDNA ratio of patients in subhaplogroup L0a2 was much lower (0.62 vs. 8.50, p=0.01) than that of those in subhaplogroup L2a. Our data indicate that peripheral blood mtDNA/nDNA ratio is a marker of mitochondrial toxicities of stavudine and is associated with elevated lactate levels and mtDNA subhaplogroups. This could open the prospect to select a substantial group of patients who will not have problematic side effects from stavudine, an affordable and effective antiretroviral drug that is being phased out in Africa due to its toxicity.

  15. Prospects for nuclear safety research

    Energy Technology Data Exchange (ETDEWEB)

    Beckjord, E.S.

    1995-04-01

    This document is the text of a paper presented by Eric S. Beckjord (Director, Nuclear Regulatory Research/NRC) at the 22nd Water Reactor Safety Meeting in Bethesda, MD in October 1994. The following topics are briefly reviewed: (1) Reactor vessel research, (2) Probabilistic risk assessment, (3) Direct containment heating, (4) Advanced LWR research, (5) Nuclear energy prospects in the US, and (6) Future nuclear safety research. Subtopics within the last category include economics, waste disposal, and health and safety.

  16. Asbestos in Buildings: What You Should Know.

    Science.gov (United States)

    Safe Buildings Alliance, Washington, DC.

    Thirty-one critical questions about asbestos, its use in school buildings, and the risks it poses to health are answered in this booklet. Issued by the Safe Buildings Alliance, an incorporated association of manufacturers that once supplied asbestos-containing materials for building construction, the booklet's purpose is to provide information…

  17. Asbestos in Buildings: What You Should Know.

    Science.gov (United States)

    Safe Buildings Alliance, Washington, DC.

    Thirty-one critical questions about asbestos, its use in school buildings, and the risks it poses to health are answered in this booklet. Issued by the Safe Buildings Alliance, an incorporated association of manufacturers that once supplied asbestos-containing materials for building construction, the booklet's purpose is to provide information…

  18. Container II

    OpenAIRE

    Baraklianou, Stella

    2016-01-01

    Container II, self-published artists book.\\ud The book was made on the occasion of the artists residency at the Banff Arts Centre, in Alberta Canada. \\ud \\ud Container II is a performative piece, it worked in conjunction with the photographic installation "Stage Set: Cool Tone" . (photographic floor installation, Reclaimed wood, frames, 130x145cm, 2016) \\ud The photographic installation was also part of the artists residency titled "New Materiality" at the Banff Arts Centre. \\ud \\ud Limited E...

  19. The Acceptance Strategy for Nuclear Power Plant In Indonesia

    Science.gov (United States)

    Suhaemi, Tjipta; Syaukat, Achmad

    2010-06-01

    THE ACCEPTANCE STRATEGY FOR NUCLEAR POWER PLANT IN INDONESIA. Indonesia has planned to build nuclear power plants. Some feasibility studies have been conducted intensively. However, the processes of NPP introduction are still uncertain. National Energy Plan in Indonesia, which has been made by some governmental agencies, does not yet give positive impact to the government decision to construct the nuclear power plant (NPP). This paper discusses the process of NPP introduction in Indonesia, which has been colored with debate of stakeholder and has delayed decision for go-nuclear. The technology paradigm is used to promote NPP as an alternative of reliable energy resources. This paradigm should be complemented with international politic-economic point of view. The international politic-economic point of view shows that structural powers, consisting of security, production, finance, and knowledge structures, within which the NPP is introduced, have dynamic characteristics. The process of NPP introduction in Indonesia contains some infrastructure development (R&D, legislation, regulation, energy planning, site study, public acceptance efforts, etc), but they need a better coherent NPP implementation program and NPP Acceptance Program. Strategic patterns for NPP acceptance described in this paper are made by considering nuclear regulation development and the interest of basic domestic participation. The first NPP program in Indonesia having proven technology and basic domestic participation is and important milestone toward and optimal national energy-mix.

  20. About a hypothetical terrorist attack on a nuclear power plant

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2001-10-01

    After the terrorism attack on the World Trade Center, a record number ( two thirds) of US citizens favour the use of nuclear energy and consider nuclear plants to be safe. At the same time 59% definitely support building more nuclear plants, less than in March during the Californian crisis, but more than earlier., Most american citizens ( 84%) continue to support licence renewal for nuclear plants and 72 % agree with keeping the option open to build new nuclear plants in the future. The strongest supporters are those who have visited a nuclear plant or information centre. (N.C.)

  1. Nuclear material operations manual

    Energy Technology Data Exchange (ETDEWEB)

    Tyler, R.P.

    1981-02-01

    This manual provides a concise and comprehensive documentation of the operating procedures currently practiced at Sandia National Laboratories with regard to the management, control, and accountability of nuclear materials. The manual is divided into chapters which are devoted to the separate functions performed in nuclear material operations-management, control, accountability, and safeguards, and the final two chapters comprise a document which is also issued separately to provide a summary of the information and operating procedures relevant to custodians and users of radioactive and nuclear materials. The manual also contains samples of the forms utilized in carrying out nuclear material activities. To enhance the clarity of presentation, operating procedures are presented in the form of playscripts in which the responsible organizations and necessary actions are clearly delineated in a chronological fashion from the initiation of a transaction to its completion.

  2. INL High Performance Building Strategy

    Energy Technology Data Exchange (ETDEWEB)

    Jennifer D. Morton

    2010-02-01

    High performance buildings, also known as sustainable buildings and green buildings, are resource efficient structures that minimize the impact on the environment by using less energy and water, reduce solid waste and pollutants, and limit the depletion of natural resources while also providing a thermally and visually comfortable working environment that increases productivity for building occupants. As Idaho National Laboratory (INL) becomes the nation’s premier nuclear energy research laboratory, the physical infrastructure will be established to help accomplish this mission. This infrastructure, particularly the buildings, should incorporate high performance sustainable design features in order to be environmentally responsible and reflect an image of progressiveness and innovation to the public and prospective employees. Additionally, INL is a large consumer of energy that contributes to both carbon emissions and resource inefficiency. In the current climate of rising energy prices and political pressure for carbon reduction, this guide will help new construction project teams to design facilities that are sustainable and reduce energy costs, thereby reducing carbon emissions. With these concerns in mind, the recommendations described in the INL High Performance Building Strategy (previously called the INL Green Building Strategy) are intended to form the INL foundation for high performance building standards. This revised strategy incorporates the latest federal and DOE orders (Executive Order [EO] 13514, “Federal Leadership in Environmental, Energy, and Economic Performance” [2009], EO 13423, “Strengthening Federal Environmental, Energy, and Transportation Management” [2007], and DOE Order 430.2B, “Departmental Energy, Renewable Energy, and Transportation Management” [2008]), the latest guidelines, trends, and observations in high performance building construction, and the latest changes to the Leadership in Energy and Environmental Design

  3. Nuclear power generation incorporating modern power system practice

    CERN Document Server

    Myerscough, PB

    1992-01-01

    Nuclear power generation has undergone major expansion and developments in recent years; this third edition contains much revised material in presenting the state-of-the-art of nuclear power station designs currently in operation throughout the world. The volume covers nuclear physics and basic technology, nuclear station design, nuclear station operation, and nuclear safety. Each chapter is independent but with the necessary technical overlap to provide a complete work on the safe and economic design and operation of nuclear power stations.

  4. Nuclear and particle physics

    CERN Document Server

    Amsler, Claude

    2015-01-01

    Nuclear and Particle Physics provides an introductory course on nuclear and particle physics for undergraduate and early-graduate students, which the author has taught for several years at the University of Zurich. It contains fundamentals on both nuclear and particle physics, giving emphasis to the discovery and history of developments in the field, and is experimentally/phenomenologically oriented. It contains detailed derivations of formulae such as 2–3 body phase space, the Weinberg-Salam model, and neutrino scattering. Originally published in German as Kern- und Teilchenphysik, several sections have been added to this new English version to cover modern topics, including updates on neutrinos, the Higgs boson, the top quark and bottom quark physics.

  5. Competence Building

    DEFF Research Database (Denmark)

    Borrás, Susana; Edquist, Charles

    on the one hand, and the real world of innovation policy-making on the other, typically not speaking to each other. With this purpose in mind, this paper discusses the role of competences and competence-building in the innovation process from a perspective of innovation systems; it examines how governments...... and public agencies in different countries and different times have actually approached the issue of building, maintaining and using competences in their innovation systems; it examines what are the critical and most important issues at stake from the point of view of innovation policy, looking particularly...

  6. Study of deuterons induced nuclear reactions on light elements (N, Al and Si): Application to containment materials of radioactive wastes; Etude des reactions nucleaires induites par des deuterons sur des elements legers (N, Al, Si): application aux materiaux de confinement des dechets radioactifs

    Energy Technology Data Exchange (ETDEWEB)

    Pellegrino, St

    2004-03-01

    Nuclear reaction analysis is well adapted to the quantification of light element. Profiles of concentration in order to follow elements migration into materials can be undertaken. This technique is used to study the behavior of the future matrices for nuclear waste containment. This technique is isotopic, characterized by a good signal-to-background ratio and a very low detection limit. The probability of a nuclear reaction is linked to a parameter called 'cross section' we have to know in order to carry out quantitative analysis. We have determined excitation curves for nitrogen, aluminium and silicon. These experiments were done with deuterons from 0.5 to 2 MeV. Two methods for the cross section characterization are presented and are in agreement with each other. The second one reduces uncertainty. Data are incorporated in the simulation software SIMNRA. We have compared the results obtained on different samples when we use data in literature or data of the study. We have noticed a great fit improvement with the data of this study. The new cross sections of this work will be integrated in the general data base SIGMABASE. Applications on materials such as Si{sub 3}N{sub 4}, nano-metric powders, WCN and nuclear glass YLaMgSiAlON studied for radioactive waste containment are also presented. (author)

  7. Current challenges for education of nuclear engineers. Beyond nuclear basics

    Energy Technology Data Exchange (ETDEWEB)

    Schoenfelder, Christian [AREVA GmbH, Offenbach (Germany). Training Center

    2014-07-15

    In past decades, curricula for the education of nuclear engineers (either as a major or minor subject) have been well established all over the world. However, from the point of view of a nuclear supplier, recent experiences in large and complex new build as well as modernization projects have shown that important competences required in these projects were not addressed during the education of young graduates. Consequently, in the past nuclear industry has been obliged to either accept long periods for job familiarization, or to develop and implement various dedicated internal training measures. Although the topics normally addressed in nuclear engineering education (like neutron and reactor physics, nuclear materials or thermohydraulics and the associated calculation methods) build up important competences, this paper shows that the current status of nuclear applications requires adaptations of educational curricula. As a conclusion, when academic nuclear engineering curricula start taking into account current competence needs in nuclear industry, it will be for the benefit of the current and future generation of nuclear engineers. They will be better prepared for their future job positions and career perspectives, especially on an international level. The recommendations presented should not only be of importance for the nuclear fission field, but also for the fusion community. Here, the Horizon 2020 Roadmap to Fusion as published in 2012 now is focusing on ITER and on a longer-term development of fusion technology for a future demonstration reactor DEMO. The very challenging work program is leading to a strong need for exactly those skills that are described in this article.

  8. Nuclear fundamentals remain

    Directory of Open Access Journals (Sweden)

    Stošić Zoran V.

    2012-01-01

    Full Text Available For Japan, the situation has become extremely difficult since counter-measures to deal with the nuclear accident had to be carried out along with dealing with the broader disaster caused by earthquake and the tsunami. In terms of damage, the Tohoku earthquake and the tsunami have caused the most fatalities and the largest economic loss ever from an earthquake and/or tsunami. The impact of this natural disaster is present not only in Japan but world-wide. The state of affairs in the global energy sector is affected by the consequences which may be lasting for decades. These effects are subject of this article dealing not with the nuclear accident at Fukushima Daiichi NPPs itself, but rather with the world-wide consequences and after effect on nuclear energy development. This includes: environmental damages, socio-economic effects, actions of safety authorities, extended protective measures against external events, the impact on global nuclear energy, triggered nuclear phase-outs and changes in new build plans as well as the sustainability of energy mix itself and an outlook.

  9. International symposium on seismic evaluation of existing nuclear facilities

    Energy Technology Data Exchange (ETDEWEB)

    Orbovic, N.; Bouchon, M. [Institut de Radioprotection et de Surete Nucleaire, IRSN, 92 - Fontenay aux Roses (France); Vendel, J.; Gelain, T. [IRSN/DPEA/SERAC, 91 - Gif sur Yvette (France)

    2003-10-01

    Below are summarized the works of Mrs N. Orbovic and M. Bouchon; B. Stojadinovic, N. Orbovic, M.Bouchon and J.T. Wiley; M. Bouchon, N. Orbovic and B. Foure; T. Gelain, F. Gensdarmes, R. Sestier-Carlin, J. Vendel and M. Bouchon dealing respectively with: 1) seismic assessment of existing nuclear facility: a case study position of the IRSN 2) static and dynamic evaluation of an existing nuclear facility reinforced concrete frame structure 3) experimental study of cracking of low-rise reinforced concrete shear walls 4) aeraulics study of crack networks on low-rise reinforced concrete walls subject to static cycling loading. The summaries are followed: 1) The Institute for Radioprotection and Nuclear Safety (IRSN) has the task of evaluating the seismic safety of existing building inventory in French nuclear facilities. Some of the existing structures are reinforced concrete frame buildings with masonry or reinforced concrete in-fill walls built during the 1960's, 70's and 80's following different building codes and seismic input data applicable at the time of construction. The studied building is a laboratory that was built in 1962. The building is composed of three different and independent blocks. The structure is a reinforced concrete frame with masonry in-fills and few stiff concrete elements. Moreover, the building contains an independent massive concrete cell. Structurally, the building has a number of irregularities. From the detailing standpoint, well known deficiencies of low-ductile reinforced concrete structures are evident especially, a lack of transverse reinforcement in the structural joints of the frame. A number of sensitivity studies were conducted using 2D and 3D linear models to evaluate seismic demand. Ambient vibration and regional earthquake records were used to check the soil nature and the existence or not of a possible site effect around the installation as well as to characterize the dynamic behavior of the building. 3D models

  10. The Role of Nuclear Diplomacy

    Directory of Open Access Journals (Sweden)

    S. Sriwidjaja

    2007-01-01

    Full Text Available In the midst of nuclear countries and non-nuclear countries in the framework of non-proliferation and disarmament, Indonesia has played an important role. Indonesia has been actively involved in each activity at the international level to create a world free from nuclear weapons. This involvements needs to be maintained and increased in the years to come. As a large country, Indonesia should play a key role in the field of nuclear diplomacy. All of the efforts of nuclear diplomacy as mentioned above had a clear objective to support Indonesia’s energy program, at the institution framework as well as capacity building. Indonesia’s effort is also directed to attain appropriated international public acceptance.

  11. Building Sandcastles

    DEFF Research Database (Denmark)

    Jensen, Steffen Moltrup Ernø; Korsgaard, Steffen; Shumar, Wes

    of entrepreneurship education. Our theoretical and methodological approach builds on Actor-Network Theory. The empirical settings of our study consist of two entrepreneurship courses which differ in terms of temporal extension and physical setting. Data is collected using observation and interview techniques. Our...

  12. Building economics

    DEFF Research Database (Denmark)

    Pedersen, D.O.(red.)

    Publikationen er på engelsk. Den omfatter alle indlæg på det fjerde internationale symposium om byggeøkonomi, der blev arrangeret af SBI for det internationale byggeforskningsråd CIB. De fem bind omhandler: Methods of Economic Evaluation, Design Optimization, Ressource Utilization, The Building...

  13. Building Partnerships.

    Science.gov (United States)

    Kisner, Mary J.; And Others

    1997-01-01

    Defines school-business partnerships and reviews changes in such partnerships over the past 25 years. Provides steps to building effective partnerships for school-to-work activities: review the school's mission; select partners that will bring strength to the relationship; set clearly defined, realistic goals; maintain the partnership; and…

  14. Sustainable Buildings

    DEFF Research Database (Denmark)

    Tommerup, Henrik M.; Elle, Morten

    The scientific community agrees that: all countries must drastically and rapidly reduce their CO2 emissions and that energy efficient houses play a decisive role in this. The general attitude at the workshop on Sustainable Buildings was that we face large and serious climate change problems...

  15. Building Procurement

    DEFF Research Database (Denmark)

    Andersson, Niclas

    2007-01-01

    despite this excellent book, the knowledge, expertise, well-articulated argument and collection of recent research efforts that are provided by the three authors will help to make project success less elusive. The book constitutes a thorough and comprehensive investigation of building procurement, which......, which gives the book a challenging contribution to the existing body of knowledge....

  16. Building Partnerships.

    Science.gov (United States)

    Kisner, Mary J.; And Others

    1997-01-01

    Defines school-business partnerships and reviews changes in such partnerships over the past 25 years. Provides steps to building effective partnerships for school-to-work activities: review the school's mission; select partners that will bring strength to the relationship; set clearly defined, realistic goals; maintain the partnership; and…

  17. Existing buildings

    DEFF Research Database (Denmark)

    Gram-Hanssen, Kirsten

    2014-01-01

    their homes. These policy measures include building regulations, energy tax and different types of incentives and information dissemination. The conclusion calls for new and innovative policy measures to cope with the realities of renovations of owner-occupied houses and how energy efficiency improvement...

  18. Siting of nuclear facilities. Selections from Nuclear Safety

    Energy Technology Data Exchange (ETDEWEB)

    Buchanan, J.R.

    1976-07-01

    The report presented siting policy and practice for nuclear power plants as developed in the U.S. and abroad. Twenty-two articles from Nuclear Safety on this general topic are reprinted since they provide a valuable reference source. The appendices also include reprints of some relevant regulatory rules and guides on siting. Advantages and disadvantages of novel siting concepts such as underground containment, offshore siting, and nuclear energy parks are addressed. Other topics include site criteria, risk criteria, and nuclear ship criteria.

  19. Technology development of nuclear material safeguards for DUPIC fuel cycle

    Energy Technology Data Exchange (ETDEWEB)

    Hong, Jong Sook; Kim, Ho Dong; Kang, Hee Young; Lee, Young Gil; Byeon, Kee Ho; Park, Young Soo; Cha, Hong Ryul; Park, Ho Joon; Lee, Byung Doo; Chung, Sang Tae; Choi, Hyung Rae; Park, Hyun Soo

    1997-07-01

    During the second phase of research and development program conducted from 1993 to 1996, nuclear material safeguards studies system were performed on the technology development of DUPIC safeguards system such as nuclear material measurement in bulk form and product form, DUPIC fuel reactivity measurement, near-real-time accountancy, and containment and surveillance system for effective and efficient implementation of domestic and international safeguards obligation. By securing in advance a optimized safeguards system with domestically developed hardware and software, it will contribute not only to the effective implementation of DUPIC safeguards, but also to enhance the international confidence build-up in peaceful use of spent fuel material. (author). 27 refs., 13 tabs., 89 figs.

  20. Political economy and social psychology of nuclear safety

    Energy Technology Data Exchange (ETDEWEB)

    Choe, Gwang Sik

    2009-03-15

    The contents of this book are consideration on independence of nuclear safety regulations, analysis of trend in internal and external on effectualness of nuclear safety regulations, political psychology of a hard whistle, how to deal with trust and distrust on regulation institute, international trend and domestic trend of nuclear safe culture, policy for building of trust of people on nuclear safety and regulations, measurement and conception of nuclear safety and for who imposes legal controls?.

  1. Nuclear Fission

    Science.gov (United States)

    Denschlag, J. O.

    This chapter first gives a survey on the history of the discovery of nuclear fission. It briefly presents the liquid-drop and shell models and their application to the fission process. The most important quantities accessible to experimental determination such as mass yields, nuclear charge distribution, prompt neutron emission, kinetic energy distribution, ternary fragment yields, angular distributions, and properties of fission isomers are presented as well as the instrumentation and techniques used for their measurement. The contribution concentrates on the fundamental aspects of nuclear fission. The practical aspects of nuclear fission are discussed in http://dx.doi.org/10.1007/978-1-4419-0720-2_57 of Vol. 6.

  2. Nuclear Safety

    Energy Technology Data Exchange (ETDEWEB)

    Silver, E G [ed.

    1989-01-01

    This document is a review journal that covers significant developments in the field of nuclear safety. Its scope includes the analysis and control of hazards associated with nuclear energy, operations involving fissionable materials, and the products of nuclear fission and their effects on the environment. Primary emphasis is on safety in reactor design, construction, and operation; however, the safety aspects of the entire fuel cycle, including fuel fabrication, spent-fuel processing, nuclear waste disposal, handling of radioisotopes, and environmental effects of these operations, are also treated.

  3. Collapsing Containers.

    Science.gov (United States)

    Brown, Justina L.; Battino, Rubin

    1994-01-01

    Describes variations on atmospheric pressure demonstrations and some systematic studies. Demonstrations use steam, generated either externally or internally to the container, to sweep out residual air. Preferred vessels collapsed slowly. Demonstrations use plastic milk jugs set in layers of aluminum foil, pop bottles immersed in 4-L beakers…

  4. Foldable container

    NARCIS (Netherlands)

    Kusuma, G.; Herder, J.L.

    2009-01-01

    The invention relates to a foldable container (1) having a bottom plate (2), upstanding long sidewalls (3) and upstanding short sidewalls (4) that are connected to the bottom plate with a hinge, and an optionally detachable roof (5), wherein at least one of the long sidewalls and short sidewalls and

  5. Microwave-gated dynamic nuclear polarization

    DEFF Research Database (Denmark)

    Bornet, Aurélien; Pinon, Arthur; Jhajharia, Aditya

    2016-01-01

    Dissolution dynamic nuclear polarization (D-DNP) has become a method of choice to enhance signals in nuclear magnetic resonance (NMR). Recently, we have proposed to combine cross-polarization (CP) with D-DNP to provide high polarization P((13)C) in short build-up times. In this paper, we show...

  6. Nuclear physicist, arms control advocate

    CERN Multimedia

    Chang, K

    2002-01-01

    Victor F. Weisskopf, a nuclear physicist who worked on the Manhattan Project to build the first atomic bomb in World War II and later became an ardent advocate of arms control, died Monday at his home in Newton, MA, USA. He was 93 (1 page).

  7. Nuclear physics principles and applications

    CERN Document Server

    Lilley, J S

    2001-01-01

    This title provides the latest information on nuclear physics. Based on a course entitled Applications of Nuclear Physics. Written from an experimental point of view this text is broadly divided into two parts, firstly a general introduction to Nuclear Physics and secondly its applications.* Includes chapters on practical examples and problems* Contains hints to solving problems which are included in the appendix* Avoids complex and extensive mathematical treatments* A modern approach to nuclear physics, covering the basic theory, but emphasising the many and important applicat

  8. Panel report: nuclear physics

    Energy Technology Data Exchange (ETDEWEB)

    Carlson, Joseph A [Los Alamos National Laboratory; Hartouni, Edward P [LLNL

    2010-01-01

    supports the project Building a Universal Nuclear Energy Density Fuctional whose goals are to provide the unified approach to calculating the properties of nuclei. The successful outcome of this, and similar projects is a first steps toward a predictive nuclear theory based on fundamental interactions between constituent nucleons. The application of this theory to the domain of nuclei important for national security missions will require computational resources at the extreme scale, beyond what will be available in the near term future.

  9. The Drivers of Indias Nuclear Weapons Program

    Science.gov (United States)

    2014-06-01

    is also building a prototype fast-breeder reactor near Kalpakkam.46 Fast-breeder reactors use nuclear fission to turn regular uranium into plutonium... nuclear reactor finally went critical in 2013,57 which marked a major milestone for this vessel in reaching operational status. Once underway, the...collections/peace_agreements/ ip_lahore19990221. pdf . 165 Ganguly and Biringer, “ Nuclear Crisis Stability,” 914. 166 Ministry of External Affairs, New

  10. Nuclear Nonproliferation Strategies for South Asia

    Science.gov (United States)

    1994-05-03

    a nuclear arsenal. India is presumed to possess components for nuclear weapons including the actual fissile material "pits" or "cores" for weapons...weapons with various aircraft and with ŕ "Lack of Capital Deters Russians from Building VVERs in India," Nucleonics Week, October 1, 1992; "India...ban on the production of fissile materials for nuclear explosive devices or outside of safeguards. India opposes regional arms control measures that

  11. Paraspeckles: a novel nuclear domain

    DEFF Research Database (Denmark)

    Fox, Archa H; Lam, Yun Wah; Leung, Anthony K L

    2002-01-01

    BACKGROUND: The cell nucleus contains distinct classes of subnuclear bodies, including nucleoli, splicing speckles, Cajal bodies, gems, and PML bodies. Many nuclear proteins are known to interact dynamically with one or other of these bodies, and disruption of the specific organization of nuclear...... relocalize quantitatively to unique cap structures at the nucleolar periphery when transcription is inhibited. CONCLUSIONS: We have identified a novel nuclear compartment, termed paraspeckles, found in both primary and transformed human cells. Paraspeckles contain at least three RNA binding proteins that all...

  12. Paraspeckles. A novel nuclear domain

    DEFF Research Database (Denmark)

    Fox, Archa H; Lam, Yun Wah; Leung, Anthony K L

    2002-01-01

    BACKGROUND: The cell nucleus contains distinct classes of subnuclear bodies, including nucleoli, splicing speckles, Cajal bodies, gems, and PML bodies. Many nuclear proteins are known to interact dynamically with one or other of these bodies, and disruption of the specific organization of nuclear...... relocalize quantitatively to unique cap structures at the nucleolar periphery when transcription is inhibited. CONCLUSIONS: We have identified a novel nuclear compartment, termed paraspeckles, found in both primary and transformed human cells. Paraspeckles contain at least three RNA binding proteins that all...

  13. Building Bridges

    DEFF Research Database (Denmark)

    The report Building Bridges adresses the questions why, how and for whom academic audience research has public value, from the different points of view of the four working groups in the COST Action IS0906 Transforming Audiences, Transforming Societies – “New Media Genres, Media Literacy and Trust...... in the Media”, “Audience Interactivity and Participation”, “The Role of Media and ICT Use for Evolving Social Relationships” and “Audience Transformations and Social Integration”. Building Bridges is the result of an ongoing dialogue between the Action and non-academic stakeholders in the field of audience...... Belgrade), Leo Pekkala (Finnish Centre for Media Education and Audiovisual Media/MEKU), Julie Uldam (Network on Civic Engagement and Social Innovation) and Gabriella Velics (Community Media Forum Europe)....

  14. Building Letters

    Institute of Scientific and Technical Information of China (English)

    2005-01-01

    Cabinet是种十分吸引人却很简单的衬线字体,是由一名匿名字体设计师专门为Building Letters最新的资金筹集活动所设计的。这个Building Letters包中包含一个CDROM,有32种字体,以及一本专门设计的杂志和两张由Eboy和Emigre所设计的海报。字体光盘样例是由世界顶级的字体设计师们设计的.

  15. Proceedings of the nuclear Inter Jura`93. Nuclear energy and sustainable development: the role of law

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-12-31

    The importance of the law for the future of the nuclear energy within the context of the sustainable development is discussed in this Nuclear Inter Jura - Rio`93, which contains the individual papers, reports of working groups and a proposal of standards of good behavior for the civilian nuclear industry. This congress is divided in five sections: licensing and decommissioning; nuclear liability cover; international nuclear trade; radiological protection and radioactive waste management.

  16. Building economics

    DEFF Research Database (Denmark)

    Pedersen, D.O.(red.)

    Publikationen er på engelsk. Den omfatter alle indlæg på det fjerde internationale symposium om byggeøkonomi, der blev arrangeret af SBI for det internationale byggeforskningsråd CIB. De fem bind omhandler: Methods of Economic Evaluation, Design Optimization, Ressource Utilization, The Building...... Market og Economics and Technological Forecasting in Construction. Et indledende bind bringer statusrapporter for de fem forskningsområder, og det sidste bind sammenfatter debatten på symposiet....

  17. Elements from chlorine to calcium nuclear reactions

    CERN Document Server

    Kunz, Wunibald

    1968-01-01

    Nuclear Tables: Part II Nuclear Reactions, Volume 3: The Elements from Chlorine to Calcium contains tabulations of the nuclear reaction values of elements chlorine, argon, potassium, and calcium. These tabulations provide the calculated Q-values of the elements and their isotopes. This book will be of value to general chemistry researchers.

  18. Swedish Opinion on Nuclear Power 1986 - 2011

    Energy Technology Data Exchange (ETDEWEB)

    Holmberg, Soeren

    2012-11-01

    This report contains the Swedish opinion on Nuclear Power and European Attitudes on Nuclear Power. It also includes European Attitudes Towards the Future of Three Energy Sources; Nuclear Energy, Wind Power and Solar Power - with a focus on the Swedish opinion. Results from measurements done by the SOM Inst. are presented.

  19. Renovation work at Building 280

    CERN Multimedia

    EN Department

    2010-01-01

    Processing units and containers will be temporarily installed in front of Building 280 between 17 and 21 February 2010 while renovation work is carried out on electrical equipment. During this period, the Route FERMI, i.e. the area between Buildings 280 and 530, will be closed to traffic. You are requested to comply with the road signs in place. Thank you for your understanding. For further information, please call 160481. EN-EL Group

  20. Effects of aging in containment spray injection system of PWR reactor containment; Efeitos do envelhecimento no sistema de injecao de borrifo da contencao de reatores a agua pressurizada

    Energy Technology Data Exchange (ETDEWEB)

    Borges, Diogo da S.; Lava, Deise D.; Affonso, Renato R.W.; Guimaraes, Antonio C.F.; Moreira, Maria de L., E-mail: diogosb@outlook.com, E-mail: deise_dy@hotmail.com, E-mail: raoniwa@yahoo.com.br, E-mail: tony@ien.gov.br, E-mail: malu@ien.gov.br [Instituto de Engenharia Nuclear (IEN/CNEN-RJ), Rio de Janeiro, RJ (Brazil)

    2014-07-01

    This paper presents a contribution to the study of the components aging process in commercial plants of Pressurized Water Reactors (PWR). The analysis is done by applying the method of Fault trees, Monte Carlo Method and Fussell-Vesely Importance Measurement. The study on the aging of nuclear plants, is related to economic factors involved directly with the extent of their operational life, and also provides important data on issues of safety. The most recent case involving the process of extending the life of a PWR plant can be seen in Angra 1 Nuclear Power Plant by investing $ 27 million in the installation of a new reactor cover. The corrective action generated an extension of the useful life of Angra 1 estimated in twenty years, and a great savings compared to the cost of building a new plant and the decommissioning of the first, if it had reached the operation time out 40 years. The extension of the lifetime of a nuclear power plant must be accompanied by special attention from the most sensitive components of the systems to the aging process. After the application of the methodology (aging analysis of Containment Spray Injection System (CSIS)) proposed in this paper, it can be seen that increasing the probability of failure of each component, due to the aging process, generate an increased general unavailability of the system that contains these basic components. The final results obtained were as expected and can contribute to the maintenance policy, preventing premature aging in nuclear power systems.