The nonlinear finite element analysis program NUCAS (NUclear Containment Analysis System) for reinforced concrete containment building

Energy Technology Data Exchange (ETDEWEB)

Lee, Sang Jin; Lee, Hong Pyo; Seo, Jeong Moon [Korea Atomic Energy Research Institute, Taejeon (Korea)

2002-03-01

The maim goal of this research is to develop a nonlinear finite element analysis program NUCAS to accurately predict global and local failure modes of containment building subjected to internal pressure. In this report, we describe the techniques we developed throught this research. An adequate model to the analysis of containment building such as microscopic material model is adopted and it applied into the development Reissner-Mindlin degenerated shell element. To avoid finite element deficiencies, the substitute strains based on the assumed strain method is used in the shell formulation. Arc-length control method is also adopted to fully trace the peak load-displacement path due to crack formation. In addition, a benchmark test suite is developed to investigate the performance of NUCAS and proposed as the future benchmark tests for nonlinear analysis of reinforced concrete. Finally, the input format of NUCAS and the examples of input/output file are described. 39 refs., 65 figs., 8 tabs. (Author)

Influence of temperature on strain monitoring of degradation in concrete containment buildings

International Nuclear Information System (INIS)

Ding, Y.; Jaffer, S.; Angell, P.

2015-01-01

Concrete containment buildings (CCBs) are important safety structures in a nuclear power plant (NPP). The CCBs can be made of reinforced and post-tensioned (P-T) concrete. Post-tensioning concrete induces compressive stresses, which have to be overcome for the concrete to crack under tensile loads. However, post-tensioned CCBs may undergo pre-stressing losses as they age, which could affect their performance under accident conditions. CANDU 6 reactor buildings contain grouted post-tensioned tendons as the primary reinforcement. The grouting of the tendons makes direct monitoring of pre-stressing losses via lift-off testing impossible. Therefore, instruments have been installed on an existing reactor building to measure and monitor strains and stresses in the concrete and the deformation of the concrete structure to detect aging degradation and indirectly evaluate the pre-stressing losses. However, the instrumentation readings are affected by temporary volume changes in the concrete caused by the influence of environmental factors, particularly temperature, on concrete. In this work, the focus is on developing an understanding of the effect of temperature on the interpretation of instrumentation data from a reactor building. Vibrating Wire Strain Gauge (VWSG) data has been analysed. The influence of concrete coefficient of thermal expansion and temperature distribution within the reactor building walls, on VWSG data, is discussed based on the analysis of the available instrumentation data and available numerical simulation results. The present study demonstrates that temperature distribution within the containment concrete has a significant impact on the VWSG measurements and the coefficient of thermal expansion of concrete is an important factor in the correction of VWSG data for thermal strain. It is recommended that VWSG data obtained over small temperature variations be considered for interpretation to assess pre-stressing losses. (authors)

Extreme accident mitigation - analysis of a low pressure secondary containment building

International Nuclear Information System (INIS)

Vaughan, G.J.; Dunbar, I.H.

1987-01-01

Although whole core accidents are sufficiently unlikely as to be beyond the design basis, the Secondary Containment Building [SCB] is expected to have some effect in mitigating the consequences of such accidents. From a design point of view there are many advantages in having a low pressure SCB fitted with a filtered vent, so studies have been undertaken of the response of such a building to the large sodium fires that might follow a severe accident. The behaviour of the sodium oxide aerosols has been studied using the code AEROSIM. The efficiency of an aerosol scrubber has been investigated experimentally. A simple code, SECCONTAIN, has been developed to model the effects of sodium fires in buildings, and has been applied to a specific design of a low pressure SCB. (author)

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

Science.gov (United States)

Philipose, K.; Shenton, B.

2011-04-01

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 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.

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.

Study of Real Time Location System For Worker in Containment Building at Nuclear Power Plant

Energy Technology Data Exchange (ETDEWEB)

Lee, S. Y.; Kim, G. S. [Samchang Enterprise Company, Ulsan (Korea, Republic of); Kim, H. S. [Ulsan Univ., Ulsan (Korea, Republic of)

2012-03-15

Workers are required special management to minimize radiation exposure in nuclear power plant. Especially, there are many limitation in their activities at containment building in nuclear power plant. Test personnel shall administer the workers by tracing the location of them inside containment building in nuclear power plant. They may be exposed to the unnecessary radiation due to a complex and high radiation area in the building. Test personnel needs to manage efficiently for worker's safety and work hours at containment building. Therefore, it is critical for the test personnel to notice the risk to the workers by identifying the location when the workers are facing the dangerous situation on the high area. In this paper, we introduce requirements and design method to develop the one and two dimensional RTLS(Real Time Locating System) by using CSS(Chirp Spread Spectrum) which enables precise location measurement and robust data communication even indoor environment with serious electromagnetic interference caused by complicated structure such as the inside of containment building in the nuclear power plant. In the algorithm to compute the distance, it is suggested to use SDS-TWR(Symmetrical Double-Sided Two-Way Ranging) to solve the issue of indirect routes, and develop the power circuit with 10mW of designing gain for output power to meet the KCC standard in order to increase the raging distance, in addition, communication between Anchor and distance measuring computer shall be designed to increase energy using time of Tags(nodes) by using CAN(Controller Area Network) communication.

Failure modes of a concrete nuclear-containment building subjected to hydrogen detonation

International Nuclear Information System (INIS)

Fugelso, L.E.; Butler, T.A.

1983-01-01

Calculated response for the Indian Point reactor containment building to static internal pressure and one case of a dynamic pressure representing hydrogen combustion and detonation are presented. Comparison of the potential failure modes is made. 9 figures

The analysis of the containment building for global effects of an aircraft crash

International Nuclear Information System (INIS)

Varpasuo, P.; Kenttaelae, J.

1981-01-01

The aim of the analysis was to establish the displacement and stress states for the whole building in four time points during the transient as well as determine the acceleration time histories, and acceleration response spectra for five points inside the containment building. The five points inside the containment were located between the foundation slab and the upper edge of the containment building. The total amount of nodal points in the model was 800 and the total amount of degrees of freedom was 4300; the amount of quadrilateral shell elements was 900. STARDYNE AND SAPOV programs and direct integration were used for analysis. As for the results of the analysis the following statements can be made: The results calculated by SAPIV and STARDYNE programs are essentially identical. Only the more refined LCCT-11 shell element used in STARDYNE instead of LCCT-9 element used in SAPIV causes the STARDYNE model to be more flexible and this shows in the response histories as a certain phase lag. STARDYNE response leaves gradually behind SAPIV response. The unexpected thing in acceleration responses was that the response in horizontal direction perpendicular to the load application direction was twice as large as the acceleration response in load application direction. (orig./HP)

Investigation of superstructure damping identification for the HDR containment building

International Nuclear Information System (INIS)

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

1985-01-01

A method for the estimation of first mode structural damping, developed by other investigators, was applied to shaker test data of the HDR containment building. Due to inadequate precision in the experimental phase measurements no valid results could be obtained. Based on modal analysis it was also noted that for systems such as the HDR building, contributions of higher modes are not negligible as was assumed in the original approach. Therefore, the procedure for the determination of superstructure damping using experimental data was extended to include the effects of higher modes. The extended method does not lead to any higher order nonlinear equations than the first mode approximation and was found to be as simple to apply as the original approach

Assessment of Effective Prestressed Force of Nuclear Containment Building using SI Technique

Energy Technology Data Exchange (ETDEWEB)

Lee, H. P.; Jang, J. B.; Hwang, K. M.; Song, Y. C. [Korea Electric Power Research Institute, Daejeon (Korea, Republic of)

2010-10-15

Bonded tendons have been used in reactor buildings of heavy water reactors and the light water reactors of some nuclear power plants operating in Korea. The assessment of prestressed forces on those bonded tendons is becoming an important issue in assuring their continuous operation beyond their design life. In order to assess the effective prestressed force on the bonded tendon, indirect assessment techniques have been applying to the test beams which were manufactured on construction time. Therefore, this research mainly forced to establish the assessment methodology to measure directly the effective prestressed force on the bonded tendon of containment buildings using System Identification (SI) technique. To accomplish this purpose, simple SI method was proposed and adapted three dimensional finite element analysis of the 1:4 scale prestressed concrete containment vessel (PCCV) tested by Sandia National Laboratory in 2000

The theoretical modelling of aerosol behaviour within containment buildings

International Nuclear Information System (INIS)

Dunbar, I.H.

1988-01-01

The modelling of the deposition of aerosol particles within the containment building plays an important part in determining the effectiveness of the building in reducing releases of activity following accidents. This paper describes attempts to ensure the accuracy of computer codes which model aerosol behaviour, with special reference to the code AEROSIM-M. Code intercomparisons have been used to test the reliability of the coding and the accuracy of the numerical methods. Those codes which assume that the particle size distribution is always lognormal give significantly different results from those which do not make this assumption but instead discretise the range of particle sizes. When the same physical assumptions are made, the predictions of different discrete codes are in reasonable agreement. In comparisons between an earlier version of AEROSIM and sodium fire experiments, the code achieved good agreement on the overall time-scale of deposition. An extensive set of tests of AEROSIM-M against experiments relevant to LWR conditions is underway. (author)

Aircraft Impact Assessment of APR1400 Reactor Containment Building

International Nuclear Information System (INIS)

Moon, Il Hwan; Kim, Do Yeon; Kim, Jae Hee; Kim, Sang Yun

2011-01-01

The implementation of a protection to withstand aircraft impact on safety-related structures and systems is basically based on a probabilistic evaluation for each site, if the licensing body doesn't require a deterministic approach. Existing nuclear power plants in Korea were designed based on the probabilistic approach, and the aircraft impact hazard remained less than a probability of 10 -7 . However, a man-made aircraft impact have been considered as a possible external accident for the nuclear power plant. New plant designs that are to be constructed in the U.S. after July 2009 must consider the effect of impact from a large commercial aircraft according to the requirements of 10 CFR 50.150. Especially, Reactor Containment Building (RCB) housing the safety-related equipment and fuels should be protected safely against aircraft crash without perforation and scabbing failure of external wall. APR1400 RCB is constructed as a prestressed concrete containment vessel (PCCV) which is surrounded by the auxiliary building housing additional safety-related equipment and other systems. In this study, the aircraft impact analyses for the RCB are carried out using Riera forcing function and aircraft model. Considered external wall thickness is 4 ft 6 in. for the cylindrical wall and 4 ft for the dome. Actual strengths of concrete and steel are considered as the material properties. For these analyses, the dynamic increment factor and concrete aging effect are considered in accordance with NEI 07-13(2011)

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)

1998-12-31

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)

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)

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.

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

International Nuclear Information System (INIS)

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

Dose and radon measurements inside houses containing ash as building material

International Nuclear Information System (INIS)

Bodnar, R.; Lendvai, Z.; Somlai, J.; Nemeth, C.

1996-01-01

Radon concentration and external dose have been measured in dwellings that contain by-products of coal burning for building materials. The concentrations of 40 K, 232 Th, 238 U and 226 Ra have been determined in the materials. The date are analyzed according to indices frequently used for decision of utilizing the by-products. The observed daily fluctuation of the radon concentration in dwellings might exceed a factor of 5. (author)

Japanese contributions to containment structure, assembly and maintenance and reactor building for ITER

International Nuclear Information System (INIS)

Shibanuma, Kiyoshi; Honda, Tsutomu; Kanamori, Naokazu

1991-06-01

Joint design work on Conceptual Design Activity of International Thermonuclear Experimental Reactor (ITER) with four parties, Japan, the United States, the Soviet Union and the European Community began in April 1988 and was successfully completed in December 1990. In Japan, the home team was established in wide range of collaboration between JAERI and national institute, universities and heavy industries. The Fusion Experimental Reactor (FER) Team at JAERI is assigned as a core of the Japanese home team to support the joint Team activity and mainly conducted the design and R and D in the area of containment structure, remote handling and plant system. This report mainly describes the Japanese contribution on the ITER containment structure, remote handling and reactor building design. Main areas of contributions are vacuum vessel, attaching locks, electromagnetic analysis, cryostat, port and service line layout for containment structure, in-vessel handling equipment design and analysis, blanket handling equipment design and related short term R and D for assembly and maintenance, and finally reactor building design and analysis based on the equipment and service line layout and components flow during assembly and maintenance. (author)

Best-estimate LOCA simulation in a PWR-W containment building with a detailed 3D GOTHIC model

International Nuclear Information System (INIS)

Jimenez, G.; Fernandez-Cosials, K.; Bocanegra, R.; Lopez-Alonso, E.

2015-01-01

The design-basis accidents in a PWR-W containment building are usually simulated with a lumped parameter model, normally used for license analysis. Nevertheless, some phenomenology is difficult to be simulated with a lumped model: the condensation rate in each structure, stagnant water areas, temperature in different compartments, sumps and recirculation pumps disabled because of lack of water, etc. Therefore, for the detailed study of the thermal-hydraulic (TH) behaviour in every room of the containment building could be more appropriate to do it with a detailed 3D representation of the containment building geometry. The main objective of this project has been to build a 3D PWR-W containment model with the GOTHIC code to analyze the detailed behavior during a design basis accident. In the process of the 3D GOTHIC model development some previous steps were necessary: a detailed CAD model of the containment, followed by a simplified model adapted to the GOTHIC geometric capabilities. Once the geometry has been adapted to the GOTHIC requirements, the 3D model is created with this information. A design-basis accident has been simulated with the 3D model (LBLOCA), and the local TH behaviour is analysed. The results show that in comparison with a lumped parameter model, high temperatures are reached locally. Nevertheless the average pressure behaviour is found to be similar to that given by a lumped parameter model. The present paper demonstrates that is possible to build a 3D PWR-W model with the GOTHIC code with enough resolution to analyse the TH behaviour in each one of the containment rooms but at the same time with reasonable computing time. Once the GOTHIC model has been created a new road is opened enabling the simulation of other accidents such as MSLB, a SBLOCA or even a long-term SBO sequence. This document is made up of an abstract and the slides of the presentation. (authors)

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

International Nuclear Information System (INIS)

Lee, Kyoungsoo; Han, Sang Eul; Hong, Jung-Wuk

2013-01-01

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

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.

Periodic Safety Review of Tendon Pre-stress of Concrete Containment Building for a CA U-Type clear Power Plant

Energy Technology Data Exchange (ETDEWEB)

Joo, Kwang Ho; Lim, Woo Sang [Korea Hydro and clear Power Co., Daejeon (Korea, Republic of)

2009-10-15

Generally, as the tendon pre-stress of concrete containment buildings at nuclear power plants decreases as time passes due to the concrete creep, concrete shrinkage and the relaxation of tendon strands, the tendon pre-stress must secure the structural integrity of these buildings by maintaining its value higher than that of the designed pre-stress during the overall service life of the nuclear power plants. Moreover, if necessary, the degree of tendon pre-stress must also guarantee the structural integrity of concrete containment buildings over their lifetimes. This paper evaluated the changes in the tendon pre-stress of a concrete containment building subject to time-limited aging as an item in a periodic safety review (PSR) of Wolsong unit 1, a CANDU-type nuclear power plant to ensure that the structural integrity can be maintained until the next PSR period after the designed lifetime.

Assessment of the Internal Pressure Fragility of the Hanul NPP Units 3 and 4 Containment Building Using a Nonlinear Finite Element Analysis

Energy Technology Data Exchange (ETDEWEB)

Park, Hyung Kui; Hahm, Dea Gi; Choi, In Kil [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

2013-10-15

The sensitivity of the concrete strength is relatively higher compared to that of the steel strength. According to changes in the structure of the material, about 6-10% ultimate internal pressure differences occurred. Thirty sets of an FE model considering the material uncertainty of concrete and steel were composed for the internal pressure fragility assessment. From the internal pressure fragility assessment of the target containment building, the median capacity of liner leakage is estimated to be 116 psi. As can be seen from the Fukushima nuclear power plant accident, the containment building is the final protecting shield to prevent radiation leakage. Thus, a structural soundness evaluation for the containment pressure loads owing to a severe accident is very important. Recently, a probabilistic safety assessment has been commonly used to take into account the possible factors of uncertainty in a structural system. An assessment of the internal pressure fragility of the CANDU type containment buildings considering the correlation of structural material variables, and an assessment of the internal pressure fragility of the CANDU type containment buildings using a nonlinear finite element analysis, were also performed. However, for PWR type containment buildings, a fragility assessment has not been performed yet using a nonlinear finite element model (FEM) analysis. In this study, for the Hanul NPP units 3 and 4 containment building, the internal pressure fragility assessment was established using an FEM analysis. To do this, a three-dimensional finite element model, material property values, and a sensitive analysis were developed. A nonlinear finite element analysis of the Hanul NPP units 3 and 4 containment building was performed for a material sensitivity analysis and internal pressure fragility assessment.

Assessment of the Internal Pressure Fragility of the Hanul NPP Units 3 and 4 Containment Building Using a Nonlinear Finite Element Analysis

International Nuclear Information System (INIS)

Park, Hyung Kui; Hahm, Dea Gi; Choi, In Kil

2013-01-01

The sensitivity of the concrete strength is relatively higher compared to that of the steel strength. According to changes in the structure of the material, about 6-10% ultimate internal pressure differences occurred. Thirty sets of an FE model considering the material uncertainty of concrete and steel were composed for the internal pressure fragility assessment. From the internal pressure fragility assessment of the target containment building, the median capacity of liner leakage is estimated to be 116 psi. As can be seen from the Fukushima nuclear power plant accident, the containment building is the final protecting shield to prevent radiation leakage. Thus, a structural soundness evaluation for the containment pressure loads owing to a severe accident is very important. Recently, a probabilistic safety assessment has been commonly used to take into account the possible factors of uncertainty in a structural system. An assessment of the internal pressure fragility of the CANDU type containment buildings considering the correlation of structural material variables, and an assessment of the internal pressure fragility of the CANDU type containment buildings using a nonlinear finite element analysis, were also performed. However, for PWR type containment buildings, a fragility assessment has not been performed yet using a nonlinear finite element model (FEM) analysis. In this study, for the Hanul NPP units 3 and 4 containment building, the internal pressure fragility assessment was established using an FEM analysis. To do this, a three-dimensional finite element model, material property values, and a sensitive analysis were developed. A nonlinear finite element analysis of the Hanul NPP units 3 and 4 containment building was performed for a material sensitivity analysis and internal pressure fragility assessment

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...

Experimental study of the leakage rate through cracked reinforced concrete wall elements for defining the functional failure criteria of containment buildings

International Nuclear Information System (INIS)

Choun, Young Sun; Cho, Nam So

2004-01-01

Containment buildings in nuclear power plants should maintain their structural safety as well as their functional integrity during an operation period. To maintain the functional integrity, the wall and dome of the containment buildings have to maintain their air tightness under extreme loading conditions such as earthquakes, missile impact, and severe accidents. For evaluating the functional failure of containments, it is important to predict the leak amount through cracked concrete walls. The leakage through concrete cracks has been studied since 1972. Buss examined the flow rate of air through a pre-existing crack in a slab under air pressure. Rizkalla el al. initiated an experimental study for the leakage of prestressed concrete building segments under uniaxial and biaxial loadings to simulate the loading condition of containment buildings under an internal pressure. Recently, Salmon el al. initiated an experimental program for determining the leak rates in typical reinforced concrete shear walls subjected to beyond design basis earthquakes. This study investigates the cracking behavior of reinforced concrete containment wall elements under a uniaxial tension and addresses the outline of the leakage test for unlined containment wall elements

Piercing of the containment shell of a reactor building in case of airplane crash

International Nuclear Information System (INIS)

Herzog, M.

1978-01-01

The author presents a simple calculation model for a realistic check of the piercing safety of containments of reactor buildings in case of airplane crash. Its application is illustrated by a numerical example (Starfighter crash on the Unterweser nuclear power plant). (orig.) [de

The spectroscopic study of building composites containing natural sorbents.

Science.gov (United States)

Król, M; Mozgawa, W

2011-08-15

This work presents the results of FT-IR spectroscopic studies of heavy metal cations (Ag(+), Pb(2+), Zn(2+), Cd(2+) and Cr(3+)) immobilization from aqueous solutions on natural sorbents. The sorption has been conducted on sodium forms of zeolite (clinoptilolite) and clay minerals (mixtures containing mainly montmorillonite and kaolinite) which have been separated from natural Polish deposit. In the next part of the work both sorbents were used to obtain new building composites. It was proven those heavy metal cations' sorption causes changes in IR spectra of the zeolite and clay minerals. These alterations are dependent on the way the cations were sorbed. In the case of zeolite, variations of the bands corresponding to the characteristic ring vibrations have been observed. These rings occur in pseudomolecular complexes 4-4-1 (built of alumino- and silicooxygen tetrahedra) which constitute the secondary building units (SBU) and form spatial framework of the zeolite. The most significant changes have been determined in the region of pseudolattice vibrations (650-700 cm(-1)). In the instance of clay minerals, changes in the spectra occur at two ranges: 1200-800 cm(-1)--the range of the bands assigned to asymmetric Si-O(Si,Al) and bending Al-OH vibrations and 3800-3000 cm(-1)--the range of the bands originating from OH(-) groups stretching vibrations. Next results indicate possibilities of applying the used natural sorbents for the obtainment of new building materials having favourable composition and valuable properties. The zeolite was used for obtaining autoclaved materials with an addition of CaO, and the clay minerals for ceramic sintered materials with an addition of quartz and clinoptilolite were produced. FT-IR studies were also conducted on the obtained materials. Copyright © 2010 Elsevier B.V. All rights reserved.

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.

Contribution to the simulation of the behavior of containment buildings in nuclear power plants

International Nuclear Information System (INIS)

Jason, Ludovic

2016-01-01

In this document, containment buildings of nuclear power plants in reinforced and prestressed concrete are studied. The mechanical behavior is first investigated. It includes studies at different scales, from the industrial scale at which it is difficult to obtain detailed information about the crack openings, to the structural scale at which it becomes possible to develop more refined approaches (steel-concrete bond, modeling of the different heterogeneities, constitutive models for concrete,...). When it is possible, the developments are based on the combination between modeling, simulation and experiments. A new steel-concrete bond model is especially developed. Its interest, compared to the classical 'perfect bond' hypothesis is particularly discussed. An adaptive condensation technique is finally proposed to bridge the gap between the scale of the containment and the scale of Structural Representative Volumes. As the tightness of the containment buildings is related to the fluid flow through concrete, two approaches are proposed and compared. The first one is based on a chained hydro mechanical simulation and tends to show that the mechanical damage is only influent when it crosses the whole concrete section. In this case, a localized approach is preferred from which a reference crack opening is defined. (author) [fr

Assessment of fission product release from the reactor containment building during severe core damage accidents in a PWR

International Nuclear Information System (INIS)

Fermandjian, J.; Evrard, J.M.; Generino, G.

1984-07-01

Fission product releases from the RCB associated with hypothetical core-melt accidents ABβ, S 2 CDβ and TLBβ in a PWR-900 MWe have been performed using French computer codes (in particular, the JERICHO Code for containment response analysis and AEROSOLS/B1 for aerosol behavior in the containment) related to thermalhydraulics and fission product behavior in the primary system and in the reactor containment building

Development of degradation D/B system for the containment building of NPP

International Nuclear Information System (INIS)

Cho, M. S.; Song, Y. C.; Yim, J. H.; Kim, D. K.; Lee, J. S.

2001-01-01

The Degradation D/B System is developed for digitalizing the history of the Containment building of nuclear power plant. It have 6 D/B which are consist of General, Design drawing, Material, Construction, ISI·SIT·ILRT D/B. For efficient operation of the system, utilities are also developed such as the aging and repair data management program for concrete and steel structures, the data search engine with various options helping users find what they want, and the data exchange program restoring and updating input data

Integrated leak rate testing of the fast flux test facility reactor containment building

International Nuclear Information System (INIS)

James, E.B.; Farabee, O.A.; Bliss, R.J.

1978-01-01

The initial Integrated Leak Rate Test (ILRT) of the Fast Flux Test Facility containment building was performed from May 27 to June 2, 1978. The test was conducted in air with systems vented and with the containment recirculating coolers in operation. 10 psig and 5 psig tests were run using the absolute pressure test method. The measured leakage rates were .033% Vol/24 hr. and -.0015% Vol/24 hrs. respectively. Subsequent verification tests at both 10 psig and 5 psig proved that the test equipment was operating properly and it was sensitive enough to detect leaks at low pressures. This ILRT was performed at a lower pressure than any previous ILRT on a reactor containment structure in the United States. While the initial design requirements for ice condenser containments called for a part pressure test at 6 psig, the tests were waived due to the apparent statistical problems of data analysis and the repeatability of the data itself at such low pressure. In contrast to this belief, both the 5 and 10 psig ILRT's were performed in a successful manner at FFTF

Floor Response Spectra of Nuclear Containment Building with Soil-Structure Interaction

Energy Technology Data Exchange (ETDEWEB)

Seo, Choon Gyo; Ryu, Jeong Soo [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

2008-10-15

This paper presents a seismic analysis technique for a 3D soil-structure interaction(SSI) system in frequency domain, based on the finite element formulation incorporating frequency-dependent dynamic infinite elements for the far field soil region. Earthquake input motions are regarded as traveling SV-wave which is vertically incident from a far-field soil region. In which, the equivalent earthquake forces in the frequency domain are calculated using the exterior rigid boundary method and the free field response analysis. For the application, floor response spectra analyses for nuclear containment building on a soil medium is carried out, the obtained results are compared with the free field response by other solution.

Phenomenological uncertainty analysis of containment building pressure load caused by severe accident sequences

International Nuclear Information System (INIS)

Park, S.Y.; Ahn, K.I.

2014-01-01

Highlights: • Phenomenological uncertainty analysis has been applied to level 2 PSA. • The methodology provides an alternative to simple deterministic analyses and sensitivity studies. • A realistic evaluation provides a more complete characterization of risks. • Uncertain parameters of MAAP code for the early containment failure were identified. - Abstract: This paper illustrates an application of a severe accident analysis code, MAAP, to the uncertainty evaluation of early containment failure scenarios employed in the containment event tree (CET) model of a reference plant. An uncertainty analysis of containment pressure behavior during severe accidents has been performed for an optimum assessment of an early containment failure model. The present application is mainly focused on determining an estimate of the containment building pressure load caused by severe accident sequences of a nuclear power plant. Key modeling parameters and phenomenological models employed for the present uncertainty analysis are closely related to the in-vessel hydrogen generation, direct containment heating, and gas combustion. The basic approach of this methodology is to (1) develop severe accident scenarios for which containment pressure loads should be performed based on a level 2 PSA, (2) identify severe accident phenomena relevant to an early containment failure, (3) identify the MAAP input parameters, sensitivity coefficients, and modeling options that describe or influence the early containment failure phenomena, (4) prescribe the likelihood descriptions of the potential range of these parameters, and (5) evaluate the code predictions using a number of random combinations of parameter inputs sampled from the likelihood distributions

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

International Nuclear Information System (INIS)

Spletzer, B.L.; Lambert, L.D.; Bergman, V.L.

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

Electric cable insulation pyrolysis and ignition resulting from potential hydrogen burn scenarios for nuclear containment buildings

International Nuclear Information System (INIS)

Berlad, A.L.; Jaung, R.; Pratt, W.T.

1982-01-01

Electric cable insulation in nuclear containment buildings may participate in pyrolysis and combustion processes engendered by hydrogen burn phenomena. This paper examines these pyrolysis/ignition processes of those polymeric materials present in the electric cable insulation and their possible relation to hydrogen burn scenarios

Control of hydrogen concentration in reactor containment buildings by using passive catalytic recombiners

International Nuclear Information System (INIS)

Wolff, U.

1993-01-01

Severe accidents in nuclear power plants have the potential to generate hydrogen within the reactor containment building in concentrations likely to deflagrate or even detonate. This could endanger the containment integrity. Autocatalytic devices have been developed by the NIS company in Hanau, Germany, to control the hydrogen concentration within the containment. These devices have been tested by the Battelle Institute in Frankfurt, Germany, under conditions relevant to severe accidents. The catalytic device functions as required in a wide band of gas mixtures ranging from inerted conditions with low-hydrogen and/or low-oxygen concentrations up to detonable mixtures. The device starts up quickly, and has a high resistance against catalyst poisons including the effects of oil or cable fires. The device makes a strong contribution to gas mixing in the containment atmosphere. The paper summarizes the development work done and describes the final design of the device. Theoretical tools for analysis and prediction of catalyst performance in containment environments have been developed by the Battelle Institute and the Technical University of Munich. These tools have been verified and validated against experimental data. A phenomenological discussion of accident scenarios is used to explain the functional requirements for the autocatalytic devices in the control of hydrogen. Both the potential for and limitations of such devices for hydrogen control are discussed for large dry containments (PWRs) and for those which are originally inerted (BWRs)

Investigation of cable deterioration in the containment building of the Savannah River Nuclear Reactor

International Nuclear Information System (INIS)

Gillen, K.T.; Clough, R.L.; Jones, L.H.

1982-08-01

This report describes an investigation of the deterioration of polyethylene and polyvinylchloride cable materials which occurred in the containment building of the Savannah River nuclear reactor located at Aiken, South Carolina. Radiation dosimetry and temperature mapping data of the containment area indicated that the maximum dose experienced by the cable materials was only 2.5 Mrad at an average operating temperature of 43 0 C. Considering this relatively moderate environment, the amount of material degradation seemed surprising. To understand these findings, an experimental program was performed on the commercial polyethylene and polyvinylchloride materials used at the plant to investigate their degradation behavior under combined γ-radiation and elevated temperature conditions. It is established that the material deterioration at the plant resulted from radiation-induced oxidation and that the degradation rate can be correlated with local levels of radiation intensity in the containment area

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.

Investigation of cable deterioration in the containment building of the Savannah River Nuclear Reactor

Energy Technology Data Exchange (ETDEWEB)

Gillen, K.T.; Clough, R.L.; Jones, L.H.

1982-08-01

This report describes an investigation of the deterioration of polyethylene and polyvinylchloride cable materials which occurred in the containment building of the Savannah River nuclear reactor located at Aiken, South Carolina. Radiation dosimetry and temperature mapping data of the containment area indicated that the maximum dose experienced by the cable materials was only 2.5 Mrad at an average operating temperature of 43/sup 0/C. Considering this relatively moderate environment, the amount of material degradation seemed surprising. To understand these findings, an experimental program was performed on the commercial polyethylene and polyvinylchloride materials used at the plant to investigate their degradation behavior under combined ..gamma..-radiation and elevated temperature conditions. It is established that the material deterioration at the plant resulted from radiation-induced oxidation and that the degradation rate can be correlated with local levels of radiation intensity in the containment area.

Comparison of computer codes relative to the aerosol behavior in the reactor containment building during severe core damage accidents in a PWR

International Nuclear Information System (INIS)

Fermandjian, J.; Bunz, H.; Dunbar, I.; Gauvain, J.; Ricchena, R.

1986-01-01

The present study concerns a comparative exercise, performed within the framework of the Commission of the European Communities, of the computer codes (AEROSIM-M, UK; AEROSOLS/B1, France; CORRAL-2, CEC and NAUA Mod5, Germany) used in order to assess the aerosol behavior in the reactor containment building during severe core damage accidents in a PWR. Topics considered in this paper include aerosols, containment buildings, reactor safety, fission product release, reactor cores, meltdown, and monitoring

Thermal stress analysis of reactor containment building considering severe weather condition

International Nuclear Information System (INIS)

Lee, Yun; Kim, Yun-Yong; Hyun, Jung-Hwan; Kim, Do-Gyeum

2014-01-01

Highlights: • We examine that through-wall crack risk in cold weather is high. • It is predicted that cracking in concrete wall will not happen in hot region. • Cracking due to hydration heat can be controlled by appropriate curing condition. • Temperature differences between inner and outer face is relatively small in hot weather. - Abstract: Prediction of concrete cracking due to hydration heat in mass concrete such as reactor containment building (RCB) in nuclear power plant is a crucial issue in construction site. In this study, the numerical analysis for heat transfer and stress development is performed for the containment wall in RCB by considering the severe weather conditions. Finally, concrete cracking risk in hot and cold weather is discussed based on analysis results. In analyses considering severe weather conditions, it is found that the through-wall cracking risk in cold weather is high due to the abrupt temperature difference between inside concrete and the ambient air in cold region. In hot weather, temperature differences between inner and outer face is relatively small, and accordingly the relevant cracking risk is relatively low in contrast with cold weather

Biaxial behavior of plain concrete of nuclear containment building

Energy Technology Data Exchange (ETDEWEB)

Lee, Sang-Keun E-mail: sklee0806@bcline.com; Song, Young-Chul; Han, Sang-Hoon

2004-01-01

To provide biaxial failure behavior characteristics of concrete of a standard Korean nuclear containment building, the concrete specimens with the dimensions of 200 mmx200 mmx60 mm were tested under different biaxial load combinations. The specimens were subjected to biaxial load combinations covering the three regions of compression-compression, compression-tension, nd tension-tension. To avoid a confining effect due to friction in the boundary surface between the concrete specimen and the loading platen, the loading platens with Teflon pads were used. The principal deformations in the specimens were recorded, and the failure modes along with each stress ratio were examined. Based on the strength data, the biaxial ultimate strength envelopes were developed and the biaxial stress-strain responses in three different biaxial loading regions were plotted. The test results indicated hat the concrete strength under equal biaxial compression, f{sub 1}=f{sub 2}, is higher by about 17% on the average than that under the uniaxial compression and the concrete strength under biaxial tension is almost independent of the stress ratio and is similar to that under the uniaxial tension.

Biaxial behavior of plain concrete of nuclear containment building

International Nuclear Information System (INIS)

Lee, Sang-Keun; Song, Young-Chul; Han, Sang-Hoon

2004-01-01

To provide biaxial failure behavior characteristics of concrete of a standard Korean nuclear containment building, the concrete specimens with the dimensions of 200 mmx200 mmx60 mm were tested under different biaxial load combinations. The specimens were subjected to biaxial load combinations covering the three regions of compression-compression, compression-tension, nd tension-tension. To avoid a confining effect due to friction in the boundary surface between the concrete specimen and the loading platen, the loading platens with Teflon pads were used. The principal deformations in the specimens were recorded, and the failure modes along with each stress ratio were examined. Based on the strength data, the biaxial ultimate strength envelopes were developed and the biaxial stress-strain responses in three different biaxial loading regions were plotted. The test results indicated hat the concrete strength under equal biaxial compression, f 1 =f 2 , is higher by about 17% on the average than that under the uniaxial compression and the concrete strength under biaxial tension is almost independent of the stress ratio and is similar to that under the uniaxial tension

Nonstationary pressure build up in full-pressure containments after a loss-of-coolant accident

International Nuclear Information System (INIS)

Mansfeld, G.

1977-01-01

The time histories of pressure, temperature and pressure difference during the pressure build up phase of a loss-of-coolant accident (LOCA) in the primary system in full-pressure containments of water cooled nuclear power reactors are treated. These are important for the design of such containments. The experiments within the German research program RS 50 ''Druckverteilung im Containment'' offered, for the first time, the opportunity to observe experimentally fluid-dynamic processes in a multiple divided full-pressure containment, and to test at the same time, computer codes which serve to describe the physical processes during the LOCA. The comparison of the results calculated by the computer codes ZOCO VI and DDIFF with the experimental results showed apparent deviations by special arrangements of the compartments and the vent flow paths of a model containment for the calculation of time dependent pressure-, temperature- and pressure difference-histories. The deviations lead to the development of the analytical model and computer code COFLOW. This new model was primarily designed to deal with the fluid-dynamic processes in the beginning phase of the blowdown as maximal pressure differences appear. Furthermore, it can be used to determine the maximum containment pressure, as well as for long term calculations. The analytical model and computer code COFLOW shows a better correlation between theory and experiment than previous codes

Shell finite element of reinforced concrete for internal pressure analysis of nuclear containment building

Energy Technology Data Exchange (ETDEWEB)

Lee, Hong Pyo, E-mail: hplee@kepri.re.k [Nuclear Power Laboratory, Korea Electric Power Research Institute, 103-16 Munji-Dong, Yuseong-Gu, Daejeon 305-380 (Korea, Republic of)

2011-02-15

Research highlights: Finite element program with 9-node degenerated shell element was developed. The developed program was mainly forced to analyze nuclear containment building. Concrete material model is adapted Niwa and Yamada failure criteria. The performance of program developed is verified through various numerical examples. The numerical analysis results similar to the experimental data. - Abstract: This paper describes a 9-node degenerated shell finite element (FE), an analysis program developed for ultimate pressure capacity evaluation and nonlinear analysis of a nuclear containment building. The shell FE developed adopts the Reissner-Mindlin (RM) assumptions to consider the degenerated shell solidification technique and the degree of transverse shear strain occurring in the structure. The material model of the concrete determines the level of the concrete stress and strain by using the equivalent stress-equivalent strain relationship. When a crack occurs in the concrete, the material behavior is expressed through the tension stiffening model that takes adhesive stress into account and through the shear transfer mechanism and compressive strength reduction model of the crack plane. In addition, the failure envelope proposed by Niwa is adopted as the crack occurrence criteria for the compression-tension region, and the failure envelope proposed by Yamada is used for the tension-tension region. The performance of the program developed is verified through various numerical examples. The analysis based on the application of the shell FE developed from the results of verified examples produced results similar to the experiment or other analysis results.

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)

GASFLOW: A computational model to analyze accidents in nuclear containment and facility buildings

International Nuclear Information System (INIS)

Travis, J.R.; Nichols, B.D.; Wilson, T.L.; Lam, K.L.; Spore, J.W.; Niederauer, G.F.

1993-01-01

GASFLOW is a finite-volume computer code that solves the time-dependent, compressible Navier-Stokes equations for multiple gas species. The fluid-dynamics algorithm is coupled to the chemical kinetics of combusting liquids or gases to simulate diffusion or propagating flames in complex geometries of nuclear containment or confinement and facilities' buildings. Fluid turbulence is calculated to enhance the transport and mixing of gases in rooms and volumes that may be connected by a ventilation system. The ventilation system may consist of extensive ductwork, filters, dampers or valves, and fans. Condensation and heat transfer to walls, floors, ceilings, and internal structures are calculated to model the appropriate energy sinks. Solid and liquid aerosol behavior is simulated to give the time and space inventory of radionuclides. The solution procedure of the governing equations is a modified Los Alamos ICE'd-ALE methodology. Complex facilities can be represented by separate computational domains (multiblocks) that communicate through overlapping boundary conditions. The ventilation system is superimposed throughout the multiblock mesh. Gas mixtures and aerosols are transported through the free three-dimensional volumes and the restricted one-dimensional ventilation components as the accident and fluid flow fields evolve. Combustion may occur if sufficient fuel and reactant or oxidizer are present and have an ignition source. Pressure and thermal loads on the building, structural components, and safety-related equipment can be determined for specific accident scenarios. GASFLOW calculations have been compared with large oil-pool fire tests in the 1986 HDR containment test T52.14, which is a 3000-kW fire experiment. The computed results are in good agreement with the observed data

Earthquake proof device for nuclear power plant building

International Nuclear Information System (INIS)

Okada, Yasuo.

1991-01-01

The structure of the present invention enables three dimensional vibration proof, i.e., in horizontal and vertical directions of a reactor container building. That is, each of the reactor container building and a reactor auxiliary building is adapted as an independent structure. The periphery of the reactor container building is surrounded by the reactor auxiliary building. The reactor auxiliary building is supported against the ground by way of a horizontal vibration proof device. The reactor container building is supported against the ground by way of a three-dimensional vibration proof device that prevents vibrations in both of the horizontal directions, and the vertical directions. The reactor container building is connected to the auxiliary building by way of a vertical vibration proof device. With such a constitution, although the reactor container building is vibration proof against both of the horizontal and the vertical vibrations, the vertical vibration proofness is an extension of inherent vertical vibration period. Accordingly, the head of the building undergoes rocking vibrations. However, since the reactor container building is connected to the reactor auxiliary building, the rocking vibrations are prevented by the reactor auxiliary building. As a result, safety upon occurrence of an earthquakes can be ensured. (I.S.)

New lumped-mass-stick model based on modal characteristics of structures: development and application to a nuclear containment building

Science.gov (United States)

Roh, Hwasung; Lee, Huseok; Lee, Jong Seh

2013-06-01

In this study, a new lumped-mass-stick model (LMSM) is developed based on the modal characteristics of a structure such as eigenvalues and eigenvectors. The simplified model, named the "frequency adaptive lumped-massstick model," hasonly a small number of stick elements and nodes to provide the same natural frequencies of the structure and is applied to a nuclear containment building. To investigate the numerical performance of the LMSM, a time history analysis is carried out on both the LMSM and the finite element model (FEM) for a nuclear containment building. A comparison of the results shows that the dynamic responses of the LMSM in terms of displacement and acceleration are almost identical to those of the FEM. In addition, the results in terms of fl oor response spectra at certain elevations are also in good agreement.

Annual energy analysis of concrete containing phase change materials for building envelopes

International Nuclear Information System (INIS)

Thiele, Alexander M.; Jamet, Astrid; Sant, Gaurav; Pilon, Laurent

2015-01-01

Highlights: • Adding PCM to concrete walls can significantly reduce the cooling needs of buildings. • Climate, season, and wall orientation strongly affect energy and cost savings. • The PCM melting temperature should be near the desired indoor temperature. • Benefits are maximum for outdoor temperature oscillating around set indoor temperature. • Adding PCM had little effect on heating energy needs and associated cost savings. - Abstract: This paper examines the annual energy and cost savings potential of adding microencapsulated phase change material to the exterior concrete walls of an average-sized single family home in California climate zones 3 (San Francisco, CA) and 9 (Los Angeles, CA). The annual energy and cost savings were larger for South- and West-facing walls than for other walls. They were also the largest when the phase change temperature was near the desired indoor temperature. The addition of microencapsulated phase change material to the building walls reduced the cooling load in summer substantially more than the heating load in winter. This was attributed to the cold winter temperatures resulting in nearly unidirectional heat flux on many days. The annual cooling load reduction in an average-sized single family home in San Francisco and in Los Angeles ranged from 85% to 100% and from 53% to 82%, respectively, for phase change material volume fraction ranging from 0.1 to 0.3. The corresponding annual electricity cost savings ranged from $36 to $42 in San Francisco and from $94 to $143 in Los Angeles. From an energy standpoint, the best climate for using building materials containing uniformly distributed microencapsulated phase change material would have outdoor temperature oscillations centered around the desired indoor temperature for the entire year

Mesothelioma among employees with likely contact with in-place asbestos-containing building materials.

Science.gov (United States)

Anderson, H A; Hanrahan, L P; Schirmer, J; Higgins, D; Sarow, P

1991-12-31

The occurrence of mesothelioma is a sentinel event in occupational and environmental disease. A mesothelioma surveillance system was established utilizing existing computerized Wisconsin vital statistics data maintained since 1959 and a Cancer Reporting System (CRS) established in 1978. Review of the death certificate listing of usual occupation and industry from 487 mesothelioma deaths in Wisconsin from 1959 to 1989 led to the investigation of 41 persons with likely exposure to inplace asbestos-containing building materials (ACBM): 12 school teachers, 10 school maintenance employees, 7 public building maintenance workers, 5 private building maintenance workers, and 7 commercial and factory workers performing maintenance activities. For 10 (34%) of the 29 maintenance workers the only source of asbestos exposure identified was their maintenance work. For five (17%) histories indicated some prior employment in occupations and industries with probable asbestos exposures. Opportunities for indirect occupational exposure were identified for ten who had been employed in the residential construction industry. One maintenance worker was exposed to asbestos in the household and another had neighborhood exposure. For 9 (75%) of the school teachers, the only identifiable potential source of asbestos exposure was derived from in-place ACBM in schools. One teacher had spent a season in the merchant marine aboard an iron ore-hauling ship and 2 had worked in the residential construction industry. Two of the teachers were sisters, and in two instances, two teachers had taught in the same school facility. We conclude that individuals occupationally exposed to in-place ACBM are at risk for the subsequent development of mesothelioma.

Shell finite element of reinforced concrete for internal pressure analysis of nuclear containment building

International Nuclear Information System (INIS)

Lee, Hong Pyo

2011-01-01

Research highlights: → Finite element program with 9-node degenerated shell element was developed. → The developed program was mainly forced to analyze nuclear containment building. → Concrete material model is adapted Niwa and Yamada failure criteria. → The performance of program developed is verified through various numerical examples. → The numerical analysis results similar to the experimental data. - Abstract: This paper describes a 9-node degenerated shell finite element (FE), an analysis program developed for ultimate pressure capacity evaluation and nonlinear analysis of a nuclear containment building. The shell FE developed adopts the Reissner-Mindlin (RM) assumptions to consider the degenerated shell solidification technique and the degree of transverse shear strain occurring in the structure. The material model of the concrete determines the level of the concrete stress and strain by using the equivalent stress-equivalent strain relationship. When a crack occurs in the concrete, the material behavior is expressed through the tension stiffening model that takes adhesive stress into account and through the shear transfer mechanism and compressive strength reduction model of the crack plane. In addition, the failure envelope proposed by Niwa is adopted as the crack occurrence criteria for the compression-tension region, and the failure envelope proposed by Yamada is used for the tension-tension region. The performance of the program developed is verified through various numerical examples. The analysis based on the application of the shell FE developed from the results of verified examples produced results similar to the experiment or other analysis results.

Nuclear reactor building

International Nuclear Information System (INIS)

Oshima, Nobuaki.

1991-01-01

The secondary container in a nuclear reactor building is made of a transparent structure having a shielding performance such as lead glass, by which the inside of the secondary container can be seen without undergoing radiation exposure. In addition, an operator transportation facility capable of carrying about 5 to 10 operators at one time is disposed, and the side of the facility on the secondary container is constituted with a transparent material such as glass, to provide a structure capable of observing the inside of the secondary container. The ventilation and air conditioning in the operator's transportation facility is in communication with the atmosphere of a not-controlled area. Accordingly, operators at the outside of the reactor building can reach the operator's transportation facility without taking and procedures for entering the controlled area and without undergoing radiation exposure. The inside of the secondary container in the reactor building can be seen from various directions through the transparent structure having the shielding performance. (N.H.)

XPS investigations of ruthenium deposited onto representative inner surfaces of nuclear reactor containment buildings

Energy Technology Data Exchange (ETDEWEB)

Mun, C. [Institut de Radioprotection et de Surete Nucleaire (IRSN), Direction de la Prevention des Accidents Majeurs (DPAM), Centre de Cadarache, BP3-13115 Saint-Paul-lez-Durance (France)]. E-mail: christian.mun@irsn.fr; Ehrhardt, J.J. [Laboratoire de Chimie Physique et Microbiologie pour l' Environnement (LCPME) UMR 7564, CNRS-Nancy University-405, rue de Vandoeuvre 54600 Villers-les-Nancy (France)]. E-mail: ehrhardt@lcpe.cnrs-nancy.fr; Lambert, J. [Laboratoire de Chimie Physique et Microbiologie pour l' Environnement (LCPME) UMR 7564, CNRS-Nancy University-405, rue de Vandoeuvre 54600 Villers-les-Nancy (France); Madic, C. [Commissariat a l' Energie Atomique (CEA), Direction de l' Energie Nucleaire, Centre de Saclay, 91191 Gif-sur-Yvette Cedex (France)]. E-mail: charles.madic@cea.fr

2007-07-15

In the case of a hypothetical severe accident in a nuclear power plant, interactions of gaseous RuO{sub 4} with reactor containment building surfaces (stainless steel and epoxy paint) could possibly lead to a black Ru-containing deposit on these surfaces. Some scenarios include the possibility of formation of highly radiotoxic RuO{sub 4}(g) by the interactions of these deposits with the oxidizing medium induced by air radiolysis, in the reactor containment building, and consequently dispersion of this species. Therefore, the accurate determination of the chemical nature of ruthenium in the deposits is of the high importance for safety studies. An experiment was designed to model the interactions of RuO{sub 4}(g) with samples of stainless steel and of steel covered with epoxy paint. Then, these deposits have been carefully characterised by scanning electron microscopy (SEM/EDS), electron probe microanalysis (EPMA) and X-ray photoelectron spectroscopy (XPS). The analysis by XPS of Ru deposits formed by interaction of RuO{sub 4}(g), revealed that the ruthenium is likely to be in the IV oxidation state, as the shapes of the Ru 3d core levels are very similar with those observed on the RuO{sub 2}.xH{sub 2}O reference powder sample. The analysis of O 1s peaks indicates a large component attributed to the hydroxyl functional groups. From these results, it was concluded that Ru was present on the surface of the deposits as an oxyhydroxide of Ru(IV). It has also to be pointed out that the presence of 'pure' RuO{sub 2}, or of a thin layer of RuO{sub 3} or Ru{sub 2}O{sub 5}, coming from the decomposition of RuO{sub 4} on the surface of samples of stainless steel and epoxy paint, could be ruled out. These findings will be used for further investigations of the possible revolatilisation phenomena induced by ozone.

GASFLOW: the theoretical model to analyze accidents in nuclear containments, confinements, and facility buildings

International Nuclear Information System (INIS)

Travis, J.R.; Wilson, T.L.

1993-01-01

This report documents the governing physical equations for GASFLOW, a finite-volume computer code for solving transient, three-dimensional, compressible, Navier-Stokes equations for multiple gas species. The code is designed to be a best-estimate tool for predicting the transport, mixing, and combustion of hydrogen and other gases in nuclear reactor containments, confinements, and other facility buildings. An analysis with GASFLOW will result in time-dependent gas species concentrations throughout the structure analyzed, and in the event of combustion the pressure and temperature loadings on the walls and internal structures. GASFLOW can model geometrically complex containment systems with multiple compartments and internal structures. It can calculate gas behavior of low-speed buoyancy-driven flows, of diffusion-dominated flows, and during deflagrations. The code can model condensation heat transfer to walls and internal structures by natural and forced convection; chemical kinetics of combustion of hydrogen or hydrocarbon fuels; and fluid turbulence. Heat conduction within walls and structures is considered one-dimensional. 17 refs., 1 fig., 1 tab

Fiber reinforced concrete as a material for nuclear reactor containment buildings

International Nuclear Information System (INIS)

Mallikarjuna; Banthia, N.; Mindess, S.

1991-01-01

The fiber reinforced concrete as a constructional material for nuclear reactor containment buildings calls for an examination of its individual characteristics and potentialities due to its inherent superiority over normal plain and reinforced concrete. In the present investigation, first, to study the static behavior of straight, hooked-end and crimped fibers, recently developed nonlinear three-dimensional interface (contact) element has been used in conjunction with the eight nodded hexahedron and two nodded bar elements for concrete and steel fiber respectively. Then impact tests were carried out on fiber reinforced concrete beams with an instrumented drop weight impact machine. Two different concrete mixes were tested: normal strength and high strength concrete specimens. Fibers in the concrete mix found to significantly increase the ductility and the impact resistance of the composite. Deformed fibers increase peak pull-out load and pull-out distance, and perform better in the steel fiber reinforced concrete (SFRC) structures. (author)

Darlington GS vacuum building - containment shell

International Nuclear Information System (INIS)

Huterer, J.; Ha, E.C.; Brown, D.G.; Cheng, P.C.

1985-01-01

The paper describes the consequences of new design requirements for the Darlington vacuum building on its structural configuration, analytical and reinforcing steel layout. Attention focuses on the ring girder where the juncture of dome and perimeter wall produces a complex post-tensioning layout, and attendant difficulties in design and construction. At the wall base, full fixity imposes large local stresses. Long-term, shrinkage and creep, and temperature effects become significant. A research program and in-house analytical procedure established time-dependent concrete behaviour and corresponding wall-sectional stresses. The outcome is examined in terms of reinforcement, temperature controls, and wall liner requirements. (orig.)

Dutch Building Decree

NARCIS (Netherlands)

Scholten, N.P.M.

2000-01-01

On the 1 October 1992 a change in the Dutch building legislation took effect: the revised Housing Act, the Building Decree and the technical documents related to this legislation came into force. This publication contains an English translation of the Building Decree. In order to give an idea of the

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.

Influence of Steel Fibers on the Structural Performance of a Prestressed Concrete Containment Building

International Nuclear Information System (INIS)

Choun, Youngsun; Hahm, Daegi; Park, Junhee

2013-01-01

A large number of previous experimental investigations indicate that the use of steel fibers in conventional reinforced concrete (RC) can enhance the structural and functional performance of prestressed concrete containment buildings (PCCBs) in nuclear power plants. A prevention of through-wall cracks and an increase of the post-cracking ductility will improve the ultimate internal pressure capacity, and a high shear resistance under cyclic loadings will increase the seismic resisting capacity. In this study, the effects of steel fiber reinforced concrete (SFRC) on the ultimate pressure and seismic capacities of a PCCB are investigated. The effects of steel fibers on the ultimate pressure and shear resisting capacities of a PCCB are investigated. It is revealed that both of the ultimate pressure capacity and the shear resisting capacity of a PCCB can be greatly enhanced by introducing steel fibers in a conventional RC. Estimation results indicate that the ultimate pressure capacity and maximum lateral displacement of a PCCB can be improved by 16% and 64%, respectively, if a conventional RC contains hooked steel fibers in a volume fraction of 1.0%

Influence of Steel Fibers on the Structural Performance of a Prestressed Concrete Containment Building

Energy Technology Data Exchange (ETDEWEB)

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

2013-05-15

A large number of previous experimental investigations indicate that the use of steel fibers in conventional reinforced concrete (RC) can enhance the structural and functional performance of prestressed concrete containment buildings (PCCBs) in nuclear power plants. A prevention of through-wall cracks and an increase of the post-cracking ductility will improve the ultimate internal pressure capacity, and a high shear resistance under cyclic loadings will increase the seismic resisting capacity. In this study, the effects of steel fiber reinforced concrete (SFRC) on the ultimate pressure and seismic capacities of a PCCB are investigated. The effects of steel fibers on the ultimate pressure and shear resisting capacities of a PCCB are investigated. It is revealed that both of the ultimate pressure capacity and the shear resisting capacity of a PCCB can be greatly enhanced by introducing steel fibers in a conventional RC. Estimation results indicate that the ultimate pressure capacity and maximum lateral displacement of a PCCB can be improved by 16% and 64%, respectively, if a conventional RC contains hooked steel fibers in a volume fraction of 1.0%.

Proposed design criteria for containments in Germany

International Nuclear Information System (INIS)

Schnellenbach, G.

1976-01-01

Till now all containments of German nuclear power plants have been fabricated in steel. However the nuclear power plants Gundremmingen II (KRB II) and Schmehausen II (HTR) will have prestressed concrete containments. The construction of these plants will probably start in 1975. Containments have to fulfill special tasks differing from those of pressure vessels. Because of this, design criteria for pressure vessels are not applicable to containments. On the other hand normal regulations for prestressed concrete structures are insufficient for containments. The containments KRB II and HTR are buildings of different types. KRB II is located in the interior of the reactor building of the SW-72-type. It is surrounded by a thick-walled concrete structure. HTR has the classical shape for concrete containments - vertical cylinder with spherical cap. It surrounds the reactor-building. The containment has to withstand aircraft impact forces. This influences its liner too. Design criteria have been developed for both containments, taking into consideration the special properties of these buildings. Design criteria are discussed for service-load conditions, test conditions, various forms of accident and for the ultimate load conditions. The influence of extreme external loads on the design is described. (author)

Hydraulic behaviour of a representative structural volume for containment buildings

International Nuclear Information System (INIS)

Jason, Ludovic; Pijaudier-Cabot, Gilles; Ghavamian, Shahrokh; Huerta, Antonio

2007-01-01

For particular structures like containment buildings of nuclear power plants, the study of the hydraulic behaviour is of great concern. These structures are indeed the third barrier used to protect the environment in case of accidents. The evolution of the leaking rate through the porous medium is closely related to the changes in the permeability during the ageing process of the structure. It is thus essential to know the relation between concrete degradation and the transfer property when the consequences of a mechanical loading on the hydraulic behaviour have to be evaluated. A chained approach is designed for this purpose. The mechanical behaviour is described by an elastic plastic damage formulation, where damage is responsible for the softening evolution while plasticity accounts for the development of irreversible strains. The drying process is evaluated according to a non-linear equation of diffusion. From the knowledge of the damage and the degree of saturation, a relation is proposed to calculate the permeability of concrete. Finally, the non-homogeneous distribution of the hydraulic conductivity is included in the hydraulic problem which is in fact the association of the mass balance equation for gas phase and Darcy law. From this methodology, it is shown how an indicator for the hydraulic flows can be deduced

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.

Nuclear reactor containment device

International Nuclear Information System (INIS)

Ichiki, Tadaharu.

1980-01-01

Purpose: To reduce the volume of a containment shell and decrease the size of a containment equipment for BWR type reactors by connecting the containment shell and a suppression pool with slanted vent tubes to thereby shorten the vent tubes. Constitution: A pressure vessel containing a reactor core is installed at the center of a building and a containment vessel for the nuclear reactor that contains the pressure vessel forms a cabin. To a building situated below the containment shell, is provided a suppression chamber in which cooling water is charged to form a suppression pool. The suppression pool is communicated with vent tubes that pass through the partition wall of the containment vessel. The vent tubes are slanted and their lower openings are immersed in coolants. Therefore, if accident is resulted and fluid at high temperature and high pressure is jetted from the pressure vessel, the jetting fluid is injected and condensated in the cooling water. (Moriyama, K.)

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.

Radiation doses in buildings containing coal

International Nuclear Information System (INIS)

Somlai, J.; Kanyar, B.; Nenyei, A.; Nemeth, Z.; Nemeth, Cs.

2001-01-01

Using coal-slag with high concentration of 226 Ra as building material could result excess dose of people living in these dwellings. The gamma dose rate, the radon concentration and the radionuclide concentration of built-in slags were measured in kindergartens, schools and homes of three towns (Ajka, Tatabanya, Varpalota). The absorbed dose rates exceeded significantly the world average (80 nGy/h) and the annual dose reached 3-4 mSv in some cases. The dose coming from radon is significant in the case of slags, which did not originate from power plants but from smaller stoves and furnaces because in these cases the burning temperature is lower, so the radon emanation is higher. The dose in the latter cases could reach 10-20 mSv/year. (author)

First-passage Probability Estimation of an Earthquake Response of Seismically Isolated Containment Buildings

International Nuclear Information System (INIS)

Hahm, Dae-Gi; Park, Kwan-Soon; Koh, Hyun-Moo

2008-01-01

The awareness of a seismic hazard and risk is being increased rapidly according to the frequent occurrences of the huge earthquakes such as the 2008 Sichuan earthquake which caused about 70,000 confirmed casualties and a 20 billion U.S. dollars economic loss. Since an earthquake load contains various uncertainties naturally, the safety of a structural system under an earthquake excitation has been assessed by probabilistic approaches. In many structural applications for a probabilistic safety assessment, it is often regarded that the failure of a system will occur when the response of the structure firstly crosses the limit barrier within a specified interval of time. The determination of such a failure probability is usually called the 'first-passage problem' and has been extensively studied during the last few decades. However, especially for the structures which show a significant nonlinear dynamic behavior, an effective and accurate method for the estimation of such a failure probability is not fully established yet. In this study, we presented a new approach to evaluate the first-passage probability of an earthquake response of seismically isolated structures. The proposed method is applied to the seismic isolation system for the containment buildings of a nuclear power plant. From the numerical example, we verified that the proposed method shows accurate results with more efficient computational efforts compared to the conventional approaches

NucleDyne's passive containment system

International Nuclear Information System (INIS)

Falls, O.B. Jr.; Kleimola, F.W.

1987-01-01

A simple definition of the passive containment system is that it is a total safeguards system for light water reactors designed to prevent and contain any accidental release of radioactivity. Its passive features utilize the natural laws of physics and thermodynamics. The system encompasses three basic containments constructed as one integrated structure on the reactor building foundation. The primary containment encloses the reactor pressure vessel and coolant system and passive engineered safety systems and components. Auxiliary containment enclosures house auxiliary systems and components. Secondary containment (the reactor building), housing the primary and auxiliary containment structures, provides a second containment barrier as added defense-in-depth against leakage of radioactivity for all accidents assumed by the industry. The generic features of the passive containment system are applicable to both the boiling water reactors and the pressurized water reactors as standardized features for all power ranges. These features provide for a zero source term, the industry's ultimate safety goal. This paper relates to a four-loop pressurized water reactor

The probability of containment failure by direct containment heating in surry

International Nuclear Information System (INIS)

Pilch, M.M.; Allen, M.D.; Bergeron, K.D.; Tadios, E.L.; Stamps, D.W.; Spencer, B.W.; Quick, K.S.; Knudson, D.L.

1995-05-01

In a light-water reactor core melt accident, if the reactor pressure vessel (RPV) fails while the reactor coolant system (RCS) at high pressure, the expulsion of molten core debris may pressurize the reactor containment building (RCB) beyond its failure pressure. A failure in the bottom head of the RPV, followed by melt expulsion and blowdown of the RCS, will entrain molten core debris in the high-velocity steam blowdown gas. This chain of events is called a high-pressure melt ejection (HPME). Four mechanisms may cause a rapid increase in pressure and temperature in the reactor containment: (1) blowdown of the RCS, (2) efficient debris-to-gas heat transfer, (3) exothermic metal-steam and metal-oxygen reactions, and (4) hydrogen combustion. These processes, which lead to increased loads on the containment building, are collectively referred to as direct containment heating (DCH). It is necessary to understand factors that enhance or mitigate DCH because the pressure load imposed on the RCB may lead to early failure of the containment

Ice condenser containment analysis with the GOTHIC code

International Nuclear Information System (INIS)

Yadon, T.P.

1996-01-01

Analytical methodologies have recently been developed by Duke Power Company (Duke) to calculate the thermodynamic response of the ice condenser containment buildings at the McGuire and Catawba Nuclear Stations to high-energy line breaks. The GOTHIC computer code (Version 4.0) was utilized for these analyses. In the ice condenser containment design, a large mass of ice stored within the containment building is used to absorb the energy released from high-energy line breaks, thereby limiting the peak pressure and temperature in the containment building to within design limits. The McGuire and Catawba Nuclear Stations (both two-unit, 3411 MWth four-loop Westinghouse plants) are of the ice condenser containment design

Assessment and management of ageing of major nuclear power plant components important to safety: Concrete containment buildings

International Nuclear Information System (INIS)

1998-06-01

The report presents the results of the Co-ordinated Research Programme (CRP) on the Management of Ageing of Concrete Containment Buildings (CCBs) addressing current practices and techniques for assessing fitness-for-service and the inspection, monitoring and mitigation of ageing degradation of selected components of CANDU reactor, BWR reactor, PWR reactor and WWER plants. These practices are intended to help all involved directly and indirectly in ensuring the safe operation of NPPs and also to provide a common technical basis for dialogue between plant operators and regulators when dealing with age-related licensing issues

Ageing degradation in the Gentilly-1 concrete containment building

International Nuclear Information System (INIS)

Jaffer, S.; Pentecost, S.; Angell, P.; Shenton, B.

2015-01-01

Concrete containment buildings (CCBs) are designed for a service life up to 40 years, but nuclear power plant (NPP) refurbishment can extend service life beyond 60 years. Only limited testing can be conducted on an in-service CCB. The Gentilly-1 (G-1) NPP is in a safe, sustainable shutdown state and the G-1 CCB was available for testing to determine age-related degradation that may be relevant to operating CCBs. Visual observation of the G-1 CCB helped to identify various signs of degradation. However, field testing, via concrete removal, was performed to: (i) examine reinforcing bars and concrete to determine their condition and in-situ stresses and (ii) examine condition of post-tensioned (P-T) wires. The concrete was also subjected to laboratory tests to evaluate its physical, mechanical and chemical properties such as compressive strength, carbonation depth, chloride content and presence of internal degradation. The degradation mechanisms that were clearly visible include macro- and micro-cracking, efflorescence, and weathering. The reinforcing bars in the perimeter wall and dome exposed during the program showed no evidence of active corrosion. Corrosion products were observed on the surfaces of most exposed P-T wires in the perimeter wall, but none were present on P-T wires exposed in the dome. Laboratory testing on the concrete cores extracted from the CCB revealed compressive strength in excess of the design requirements, low carbonation depths (< 10 mm) and no appreciable chlorides. Micro-cracking was observed in the samples recovered from the wall and dome. To date, the observed micro-cracking has had no apparent visible affect on the performance of the CCB concrete. (authors)

A research on verification of the CONTAIN CODE model and the uncertainty reduction method for containment integrity

Energy Technology Data Exchange (ETDEWEB)

Park, Jae-Hong; Kim, Moo-Hwan; Bae, Seong-Won; Byun, Sang-Chul [Pohang University of Science and Technology, Pohang (Korea, Republic of)

1998-03-15

The final objectives of this study are to establish the way of measuring the integrity of containment building structures and safety analysis in the period of a postuIated severe accidents and to decrease the uncertainty of these methods. For that object, the CONTAIN 1.2 codes model for analyzing the severe accidents phenomena and the heat transfer between the air inside the containment buildings and inner walls have been reviewed and analyzed. For the double containment wall provided to the next generation nuclear reactor, which is different to the previous type of containment, the temperature and pressure rising history were calculated and compared to the results of previous ones.

Pipe line construction for reactor containment buildings

International Nuclear Information System (INIS)

Aoki, Masataka; Yoshinaga, Toshiaki

1978-01-01

Purpose: To prevent the missile phenomenon caused by broken fragments due to pipe whip phenomenon in a portion of pipe lines connected to a reactor containment from prevailing to other portions. Constitution: Various pipe lines connected to the pressure vessel are disposed at the outside of the containments and they are surrounded with a plurality of protection partition walls respectively independent from each other. This can eliminate the effect of missile phenomena upon pipe rupture from prevailing to the pipe lines and instruments. Furthermore this can afford sufficient spaces for the pipe lines, as well as for earthquake-proof supports. (Horiuchi, T.)

A numerical study of external building walls containing phase change materials (PCM)

International Nuclear Information System (INIS)

Izquierdo-Barrientos, M.A.; Belmonte, J.F.; Rodríguez-Sánchez, D.; Molina, A.E.; Almendros-Ibáñez, J.A.

2012-01-01

Phase Change Materials (PCMs) have been receiving increased attention, due to their capacity to store large amounts of thermal energy in narrow temperature ranges. This property makes them ideal for passive heat storage in the envelopes of buildings. To study the influence of PCMs in external building walls, a one-dimensional transient heat transfer model has been developed and solved numerically using a finite difference technique. Different external building wall configurations were analyzed for a typical building wall by varying the location of the PCM layer, the orientation of the wall, the ambient conditions and the phase transition temperature of the PCM. The integration of a PCM layer into a building wall diminished the amplitude of the instantaneous heat flux through the wall when the melting temperature of the PCM was properly selected according to the season and wall orientation. Conversely, the results of the work show that there is no significant reduction in the total heat lost during winter regardless of the wall orientation or PCM transition temperature. Higher differences were observed in the heat gained during the summer period, due to the elevated solar radiation fluxes. The high thermal inertia of the wall implies that the inclusion of a PCM layer increases the thermal load during the day while decreasing the thermal load during the night. - Highlights: ► A comparative simulation of a building wall with and without PCMs has been conducted. ► PCM is selected according with the season, the wall orientation and the melting temperature. ► PCM in a building wall help to diminish the internal air temperature swings and to regulate the heat transfer.

IM-16: A new microporous germanosilicate with a novel framework topology containing d4r and mtw composite building units

International Nuclear Information System (INIS)

Lorgouilloux, Yannick; Dodin, Mathias; Paillaud, Jean-Louis; Caullet, Philippe; Michelin, Laure; Josien, Ludovic; Ersen, Ovidiu; Bats, Nicolas

2009-01-01

The synthesis and the structure of IM-16 a new germanosilicate with a novel zeolitic topology prepared hydrothermally with the ionic liquid 3-ethyl-1-methyl-3H-imidazol-1-ium as the organic structure-directing agent are reported. The structure of calcined and partially rehydrated IM-16 of chemical formula |(H 2 O) 0.16 |[Si 3.47 Ge 2.53 O 12 ] was solved from powder XRD data in space group Cmcm with a=15.0861(2) A, b=17.7719(3) A, c=19.9764(3) A, V=5355.84(12) A 3 (Z=16). This new zeolite framework type contains 10-MRs channels and may be described from the d4r and mtw composite building units. - Graphical abstract: The synthesis and the structure of IM-16 a new germanosilicate with a novel zeolitic topology prepared hydrothermally with the ionic liquid 3-ethyl-1-methyl-3H-imidazol-1-ium as the organic structure-directing agent are reported. This new zeolite framework type contains 10-MRs channels and may be described from the d4r and mtw composite building units

Building Reproducible Science with Singularity Containers

CERN Multimedia

CERN. Geneva

2018-01-01

Michael Bauer first began working with containers at GSI national lab in Darmstadt, Germany, in 2017 while taking a semester off of school at the University of Michigan. Michael met Greg Kurtzer, project lead of Singularity, during his time at GSI and he began contributing heavily to the Singularity project. At the start of summer 2017, Greg hired Michael to work at the ...

Strain-based failure criteria for steel containments

International Nuclear Information System (INIS)

Fanous, F.; Greimann, L.F.

1989-01-01

The Containment Integrity Division of the Sandia National Laboratories (Sandia) has been conducting a program to evaluate the performance of containment buildings with internal pressure. Sandia has suggested that in the absence of leakage past penetrations, containment buildings will fail by rupturing after large plastic strains are developed up to ultimate strain of the material. This paper represents a portion of work conducted at Ames Laboratory for Sandia, the objective of which was to identify fabrication details that may affect the performance of a containment building. Construction drawings for nine steel containment buildings were surveyed, and several significant strain concentration regions were identified by using recommendations from Sandia and Section NE-3217 of the ASME Boiler and Pressure Vessel Code. These following regions were identified as: eccentricities in stiffener patterns around penetrations, eccentricities in containment shell middle surface, flat plate covers used on spare penetrations, containment base connection details, and containment heads. Examples of each of these regions were analyzed by the finite-element method, by simplified equations or both. In the case of middle surface eccentricities, the strains were found to be self-limiting. Even though flat plates have primary strains, they are typically designed so as not to control. Bolts in the base connection have primary strains and may control. The circumferential compressive strains introduced at the knuckle during buckling of the containment head grow as the pressure increases, but are somewhat restricted by the meridional tension. Finally, three analysis techniques and their associated failure criteria for the analysis of containment strength are introduced. (orig.)

Building air exhaustion device

International Nuclear Information System (INIS)

Suzuki, Seijiro.

1995-01-01

An opening is formed on the side wall of a building such as of a nuclear power plant, and a blow out panel is held (supported) by a clip for closing the opening. A large-diameter pipeline is connected at one end to the opening so as to cover the blow out panel, and immersed at the other end in a pool water. When a pipeline such as of main steam pipelines is ruptured in the building, high temperature and high pressure coolants are flown out from the ruptured port, and the pressure in the building is elevated. The blow out panel falls off from the side of the building by the elevation of the pressure in the building. Steams or compressed air discharged from the opening is introduced to the pool through the large diameter pipeline, then the steams are condensed by the pool water and radioactive materials contained in the condensed steams are kept in the pool water. Radioactive materials contained in the released compression air are also removed into the pool water. (I.N.)

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.

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

International Nuclear Information System (INIS)

Choun, Youngsun; Hahm, Daegi

2014-01-01

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

Steel containment buckling

International Nuclear Information System (INIS)

Butler, T.A.; Baker, W.E.

1987-01-01

Two aspects of buckling of a free-standing nuclear containment building were investigated in a combined experimental and analytical program. In the first part of the study, the response of a scale model of a containment building to dynamic base excitation is investigated. A simple harmonic signal was used for preliminary studies followed by experiments with scaled earthquake signals as the excitation source. The experiments and accompanying analyses indicate that the scale model response to earthquake-type excitations is very complex and that current analytical methods may require that a dynamic capacity reduction factor be incorporated. The second part of the study quantified the effects of framing at large penetrations on the static buckling capacity of scale model containments. Results show little effect from the framing for the scale models constructed from the polycarbonate, Lexan. However, additional studies with a model constructed of the prototypic steel material are recommended. (orig.)

Steel containment buckling

International Nuclear Information System (INIS)

Butler, T.A.; Baker, W.E.

1986-01-01

Two aspects of buckling of a free-standing nuclear steel containment building were investigated in a combined experimental and analytical program. In the first part of the study, the response of a scale model of a containment building to dynamic base excitation is investigated. A simple harmonic signal was used for preliminary studies followed by experiments with scaled earthquake signals as the excitation source. The experiments and accompanying analyses indicate that the scale model response to earthquake-type excitations is very complex and that current analytical methods may require a dynamic capacity reduction factor to be incorporated. The second part of the study quantified the effects of framing at large penetrations on the static buckling capacity of scale model containments. Results show little effect from the framing for the scale models constructed from the polycarbonate, Lexan. However, additional studies with a model constructed of the prototypic steel material are suggested

Reactor building

International Nuclear Information System (INIS)

Ebata, Sakae.

1990-01-01

At least one valve rack is disposed in a reactor building, on which pipeways to a main closure valve, valves and bypasses of turbines are placed and contained. The valve rack is fixed to the main body of the building or to a base mat. Since the reactor building is designed as class A earthquake-proofness and for maintaining the S 1 function, the valve rack can be fixed to the building main body or to the base mat. With such a constitution, the portions for maintaining the S 1 function are concentrated to the reactor building. As a result, the dispersion of structures of earthquake-proof portion corresponding to the reference earthquake vibration S 1 can be prevented. Accordingly, the conditions for the earthquake-proof design of the turbine building and the turbine/electric generator supporting rack are defined as only the class B earthquake-proof design conditions. In view of the above, the amount of building materials can be saved and the time for construction can be shortened. (I.S.)

AP1000 Containment Design and Safety Assessment

International Nuclear Information System (INIS)

Wright, Richard F.; Ofstun, Richard P.; Bachere, Sebastien

2002-01-01

The AP1000 is an up-rated version of the AP600 passive plant design that recently received final design certification from the US NRC. Like AP600, the AP1000 is a two-loop, pressurized water reactor featuring passive core cooling and passive containment safety systems. One key safety feature of the AP1000 is the passive containment cooling system which maintains containment integrity in the event of a design basis accident. This system utilizes a high strength, steel containment vessel inside a concrete shield building. In the event of a pipe break inside containment, a high pressure signal actuates valves which allow water to drain from a storage tank atop the shield building. Water is applied to the top of the containment shell, and evaporates, thereby removing heat. An air flow path is formed between the shield building and the containment to aid in the evaporation and is exhausted through a chimney at the top of the shield building. Extensive testing and analysis of this system was performed as part of the AP600 design certification process. The AP1000 containment has been designed to provide increased safety margin despite the increased reactor power. The containment volume was increased to accommodate the larger steam generators, and to provide increased margin for containment pressure response to design basis events. The containment design pressure was increased from AP600 by increasing the shell thickness and by utilizing high strength steel. The passive containment cooling system water capacity has been increased and the water application rate has been scaled to the higher decay heat level. The net result is higher margins to the containment design pressure limit than were calculated for AP600 for all design basis events. (authors)

Long-Term Behaviors of the OPC Concrete with Fly-ash and Type V Concrete Applied on Reactor Containment Building

International Nuclear Information System (INIS)

Yoon, Eui Sik; Lee, Hee Taik; Paek, Yong Lak; Park, Young Soo

2010-01-01

The prestressed concrete has been used extensively in the construction of Reactor Containment Buildings (RCBs) in Korea in order to strengthen the RCBs and at the same time, prevent the release of radiation due to the Design Basis Accident and Design Basis Earthquake. It is well known that the prestressed concrete loses its prestressing force over the age, and the shrinkage and creep of the concrete significantly contributes to these long term prestressing losses. In this study, an evaluations of long term behaviors of the concrete such as creep and shrinkage have been performed for two types of concretes : Ordinary Portland Cement containing fly-ash used for the Shin- Kori 1 and 2 NPP and Type V cement used for the Ul- Chin 5 and 6 NPP

Long-Term Behaviors of the OPC Concrete with Fly-ash and Type V Concrete Applied on Reactor Containment Building

Energy Technology Data Exchange (ETDEWEB)

Yoon, Eui Sik; Lee, Hee Taik; Paek, Yong Lak [Korea Institute of Nuclear Safety, Daejeon (Korea, Republic of); Park, Young Soo [Korea Hydro and Nuclear Power Co., Busan (Korea, Republic of)

2010-10-15

The prestressed concrete has been used extensively in the construction of Reactor Containment Buildings (RCBs) in Korea in order to strengthen the RCBs and at the same time, prevent the release of radiation due to the Design Basis Accident and Design Basis Earthquake. It is well known that the prestressed concrete loses its prestressing force over the age, and the shrinkage and creep of the concrete significantly contributes to these long term prestressing losses. In this study, an evaluations of long term behaviors of the concrete such as creep and shrinkage have been performed for two types of concretes : Ordinary Portland Cement containing fly-ash used for the Shin- Kori 1 and 2 NPP and Type V cement used for the Ul- Chin 5 and 6 NPP

Investigation of the Condensation Effect at IRWST Pool Surface on Containment Back Pressure in APR1400 Containment

International Nuclear Information System (INIS)

Lee, Eui Jong; Lee, Jin Yong; Lee, Byung Chul

2006-01-01

The APR1400 has several new design concepts in order to improve the plant safety functions during a postulated accident. The In-Containment Refueling Water Storage Tank (IRWST) is one of the new design concepts of APR1400 and installed at the bottom of containment building to promote the plant safety functions by simplifying emergency core cooling water source and preventing release of the fission product during an accidents. This design feature, however, brings about uncertainty factors which may necessitate conventional prediction of temperature and pressure of containment building improved or revised under accident conditions. The hot steam which is released from RCS break enters into the IRWST through four Pressure Relief Dampers (PRDs). It is expected to be condensed with water stored in IRWST, colder than incoming steam. The purpose of this study is to examine closely the influence of the condensation effect at IRWST on containment back pressure in APR1400 containment building using the GOTHIC code which can predict the steam condensation on IRWST pool surface

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...

Calculation of radiation dose rate arisen from radionuclide contained in building materials

International Nuclear Information System (INIS)

Lai Tien Thinh; Nguyen Hao Quang

2008-01-01

This paper presents some results that we used MCNP5 program to calculate radiation dose rate arisen from radionuclide in building materials. Since then, the limits of radionuclide content in building materials are discussed. The calculation results by MCNP are compared with those calculated by analytical method. (author)

Study of the sodium oxide aerosol behavior in a containment building

International Nuclear Information System (INIS)

Fermandjian, Jean.

1982-01-01

Fast breeder reactor safety analysis needs validated models to predict the behavior of sodium oxide aerosols (released during hypothetical accidents) in the different reactor compartments and, in particular, to evaluate the quantity (and the size distribution) of the particles which can be released outside the containment building by taking into account the associated devices (ventilation, especially). In order to validate the computer models, experimental tests were performed by CEA/DSN (Atomic Energy Commission/Nuclear Safety Department) at Cadarache: sodium pool fire tests in a 400 m 3 concrete vessel (CASSANDRE tests) and in a 4.4 m 3 steel vessel (EMIS tests). Furthermore, we utilized the results of the experimental tests performed by our German colleagues of KFK/LAF (Kernforschungszentrum Karlsruhe/Laboratorium fuer Aerosolphysik und Filtertechnik): sodium pool fire tests in a 220 m 3 steel vessel (FAUNA tests). The application of the computer models to the experimental tests and to the reactor case allowed us: - to explain the differences observed between the results given by the codes ''with log-normal hypothesis'' (HAARM 3) and ''with finite difference'' (PARDISEKO 3B), - to define the limits of application of the codes ''with log-normal hypothesis'', - to determine the important parameters (characteristics of the aerosol source, form factors of the agglomerates and collision efficiency) and the important phenomena (turbulent coagulation, in particular) [fr

Large panel design for containment air baffle

International Nuclear Information System (INIS)

Orr, R.S.

1992-01-01

The movable air baffle shield means in accordance with the present invention provides an efficient method of cooling the space surrounding the containment vessel while also providing the capability of being moved away from the containment vessel during inspection. The containment apparatus comprises a generally cylindrical sealed containment vessel for containing at least a portion of a nuclear power generation plant, a disparate shield building surrounding and housing the containment vessel therein and spaced outwardly thereof so as to form an air annulus in the space between the shield building and the containment vessel, a shield baffle means positioned in the air annulus around at least a portion of the sides of the containment vessel providing a coolant path between the baffle means and the containment vessel to permit cooling of the containment vessel by air, the shield baffle means being movable to afford access to the containment vessel. 9 figs

340 Facility secondary containment and leak detection

International Nuclear Information System (INIS)

Bendixsen, R.B.

1995-01-01

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

Comparison of computer codes relative to the aerosol behavior in the reactor containment building during severe core damage accidents in a PWR

International Nuclear Information System (INIS)

Fermandjian, J.; Dunbar, I.; Gauvain, J.; Ricchena, R.

1986-02-01

The present study concerns a comparative exercise, performed within the framework of the Commission of the European Communities, of the computer codes (AEROSISM-M, UK; AEROSOLS/BI, France; CORRAL-2, CEC and NAUA Mod5, Germany) used in order to assess the aerosol behavior in the reactor containment building during severe core damage accidents in a PWR

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...

Simulation of hydrogen deflagration and detonation in a BWR reactor building

International Nuclear Information System (INIS)

Manninen, M.; Silde, A.; Lindholm, I.; Huhtanen, R.; Sjoevall, H.

2002-01-01

A systematic study was carried out to investigate the hydrogen behaviour in a BWR reactor building during a severe accident. BWR core contains a large amount of Zircaloy and the containment is relatively small. Because containment leakage cannot be totally excluded, hydrogen can build up in the reactor building, where the atmosphere is normal air. The objective of the work was to investigate, whether hydrogen can form flammable and detonable mixtures in the reactor building, evaluate the possibility of onset of detonation and assess the pressure loads under detonation conditions. The safety concern is, whether the hydrogen in the reactor building can detonate and whether the external detonation can jeopardize the containment integrity. The analysis indicated that the possibility of flame acceleration and deflagration-to-detonation transition (DDT) in the reactor building could not be ruled out in case of a 20 mm 2 leakage from the containment. The detonation analyses indicated that maximum pressure spike of about 7 MPa was observed in the reactor building room selected for the analysis

19 CFR 10.540 - Packing materials and containers for shipment.

Science.gov (United States)

2010-04-01

...-Singapore Free Trade Agreement Rules of Origin § 10.540 Packing materials and containers for shipment. (a... the United States. Accordingly, in applying either the build-down or build-up method for determining... shipping container which it purchased from Company B in Singapore. The shipping container is originating...

Dose Evaluation of Neutron within Containment Building of a CE type Nuclear Power Plant

Energy Technology Data Exchange (ETDEWEB)

Kim, Tae Wook; Han, Jae Mun; Kim, Kyung Doek; Yun, Cheol Whan; Suh, Jang Soo; Kim, Young Jae [Nuclear Environment Technology Institute, Daejeon (Korea, Republic of)

2005-03-15

From measured results of the neutron fields at some principal places within the containment building in a CE type nuclear power plant in operation, the radiation exposure of a worker to the neutron at there was evaluated and the equivalent dose reflecting new recommendation (ICRP 60) was compared with that doing the old one (ICRP 26). The measured neutron field was also compared with calibration neutron field. From the analysis, the following conclusion was obtained: the average neutron radiation weighting factor according to new recommendation is 2.41 to 2.71 times higher than the old one. The average neutron radiation weighting factor at the measured place was similar to that at calibration neutron field. The average neutron energy at measured place was between 42 and 158 keV and higher than that of calibration field of 500 keV. So, the measured equivalent dose in nuclear power plant could be overestimated compared to the real equivalent dose.

Final Safety Analysis Document for Building 693 Chemical Waste Storage Building at Lawrence Livermore National Laboratory

International Nuclear Information System (INIS)

Salazar, R.J.; Lane, S.

1992-02-01

This Safety Analysis Document (SAD) for the Lawrence Livermore National Laboratory (LLNL) Building 693, Chemical Waste Storage Building (desipated as Building 693 Container Storage Unit in the Laboratory's RCRA Part B permit application), provides the necessary information and analyses to conclude that Building 693 can be operated at low risk without unduly endangering the safety of the building operating personnel or adversely affecting the public or the environment. This Building 693 SAD consists of eight sections and supporting appendices. Section 1 presents a summary of the facility designs and operations and Section 2 summarizes the safety analysis method and results. Section 3 describes the site, the facility desip, operations and management structure. Sections 4 and 5 present the safety analysis and operational safety requirements (OSRs). Section 6 reviews Hazardous Waste Management's (HWM) Quality Assurance (QA) program. Section 7 lists the references and background material used in the preparation of this report Section 8 lists acronyms, abbreviations and symbols. Appendices contain supporting analyses, definitions, and descriptions that are referenced in the body of this report

Building roof with conical holes containing PCM to reduce the cooling load: Numerical study

International Nuclear Information System (INIS)

Alawadhi, Esam M.; Alqallaf, Hashem J.

2011-01-01

Highlights: → We investigated a roof structure with cone frustum holes containing PCM. → Different types of PCM and geometries of the PCM are presented. → The results indicate that the heat flux at the indoor space is reduced by 39%. - Abstract: The thermal effectiveness of a building's roof with phase change material (PCM) is presented in this paper. The considered model consists of a concrete slab with vertical cone frustum holes filled with PCM. The objective of incorporating the PCM into the roof structure is to utilize its high latent heat of fusion to reduce the heat gain during the energy demanded peak hours, by absorbing the incoming energy through the melting process in the roof before it reaches the indoor space. The thermal effectiveness of the proposed roof-PCM system is determined by comparing the heat flux at the indoor surface to a roof without the PCM during typical working hours. A parametric study is conducted to assess the effects of the cone frustum geometry, and the kind of PCM used. The n-Eicosane shows the best performance among the examined PCMs, and the conical geometry of the PCM container is the best in term of thermal effectiveness. The results indicate that the heat flux at the indoor surface of the roof can be reduced up to 39% for a certain type of PCM and geometry of PCM cone frustum holes.

Excessive leakage measurement using pressure decay method in containment building local leakage rate test at nuclear power plant

Energy Technology Data Exchange (ETDEWEB)

Lee, Won Kyu; Kim, Chang Soo; Kim, Wang Bae [KHNP, Central Research Institute, Daejeon (Korea, Republic of)

2016-06-15

There are two methods for conducting the containment local leakage rate test (LLRT) in nuclear power plants: the make-up flow rate method and the pressure decay method. The make-up flow rate method is applied first in most power plants. In this method, the leakage rate is measured by checking the flow rate of the make-up flow. However, when it is difficult to maintain the test pressure because of excessive leakage, the pressure decay method can be used as a complementary method, as the leakage rates at pressures lower than normal can be measured using this method. We studied the method of measuring over leakage using the pressure decay method for conducting the LLRT for the containment building at a nuclear power plant. We performed experiments under conditions similar to those during an LLRT conducted on-site. We measured the characteristics of the leakage rate under varies pressure decay conditions, and calculated the compensation ratio based on these data.

Axisymmetric analysis of a 1:6-scale reinforced concrete containment building using a distributed cracking model for the concrete

International Nuclear Information System (INIS)

Weatherby, J.R.

1987-09-01

Results of axisymmetric structural analyses of a 1:6 scale model of a reinforced concrete nuclear containment building are presented. Both a finite element shell analysis and a simplified membrane analysis were made to predict the structural response and ultimate pressure capacity of the model. Analytical results indicate that the model will fail at an internal pressure of 187 psig when the stress level in the hoop reinforcement at the midsection of the cylinder exceeds the ultimate strength of the bar splices. 5 refs., 34 figs., 6 tabs

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

LHCb Dockerized Build Environment

Science.gov (United States)

Clemencic, M.; Belin, M.; Closier, J.; Couturier, B.

2017-10-01

Used as lightweight virtual machines or as enhanced chroot environments, Linux containers, and in particular the Docker abstraction over them, are more and more popular in the virtualization communities. The LHCb Core Software team decided to investigate how to use Docker containers to provide stable and reliable build environments for the different supported platforms, including the obsolete ones which cannot be installed on modern hardware, to be used in integration builds, releases and by any developer. We present here the techniques and procedures set up to define and maintain the Docker images and how these images can be used to develop on modern Linux distributions for platforms otherwise not accessible.

An Experimental Test of Factors Attracting Deer Mice into Buildings.

Science.gov (United States)

Kuenzi, Amy J; Douglass, Richard

2009-09-01

Deer mice (Peromyscus maniculatus) are the principal reservoir host of Sin Nombre virus (SNV). Deer mice use a wide variety of habitats including peridomestic settings in and around human dwellings, their presence in and around homes has been implicated as a risk factor for acquiring Hantavirus Pulmonary Syndrome. Deer mice are believed to enter buildings in order to gain access to a variety of resources including food, bedding material, and better thermal microclimates. However, no one has experimentally tested which factors influence mice use of buildings. We conducted experiments using small simulated buildings to determine the effects of two factors, i.e., food and bedding material, on mouse activity in these buildings. We also examined if these effects varied with time of year. We found that deer mice entered our buildings regardless of the presence or absence of food or bedding. However, the amount of activity in buildings was affected by what they contained. We found significantly higher indices of activity in buildings containing food compared to both empty buildings (control) and buildings containing bedding material. Time of year did not affect activity in buildings.

Performance of Sequoyah Containment Anchorage System

International Nuclear Information System (INIS)

Fanous, F.; Greimann, L.; Wassef, W.; Bluhm, D.

1993-01-01

Deformation of a steel containment anchorage system during a severe accident may result in a leakage path at the containment boundaries. Current design criteria are based on either ductile or brittle failure modes of headed bolts that do not account for factors such as cracking of the containment basemat or deformation of the anchor bolt that may affect the behavior of the containment anchorage system. The purpose of this study was to investigate the performance of a typical ice condenser containment's anchorage system. This was accomplished by analyzing the Sequoyah Containment Anchorage System. Based on a strength of materials approach and assuming that the anchor bolts are resisting the uplift caused by the internal pressure, one can estimate that the failure of the anchor bolts would occur at a containment pressure of 79 psig. To verify these results and to calibrate the strength of materials equation, the Sequoyah containment anchorage system was analyzed with the ABAQUS program using a three-dimensional, finite-element model. The model included portions of the steel containment building, shield building, anchor bolt assembly, reinforced concrete mat and soil foundation material

Mononuclear, trinuclear, and hetero-trinuclear supramolecular complexes containing a new tri-sulfonate ligand and cobalt(II)/copper(II)-(1,10-phenanthroline) 2 building blocks

Science.gov (United States)

Yu, Yunfang; Wei, Yongqin; Broer, Ria; Sa, Rongjian; Wu, Kechen

2008-03-01

Novel mononuclear, trinuclear, and hetero-trinuclear supermolecular complexes, [Co(phen) 2(H 2O)(HTST)]·2H 2O ( 1), [Co 3(phen) 6(H 2O) 2(TST) 2]·7H 2O ( 2), and [Co 2Cu(phen) 6(H 2O) 2(TST) 2]·10H 2O ( 3), have been synthesized by the reactions of a new tri-sulfonate ligand (2,4,6-tris(4-sulfophenylamino)-1,3,5-triazine, H 3TST) with the M2+ ( M=Co, Cu) and the second ligand 1,10-phenanthroline (phen). Complex 1 contains a cis-Co(II)(phen) 2 building block and an HTST as monodentate ligand; complex 2 consists of two TST as bidentate ligands connecting one trans- and two cis-Co(II)(phen) 2 building blocks; complex 3 is formed by replacing the trans-Co(II)(phen) 2 in 2 with a trans-Cu(II)(phen) 2, which is the first reported hetero-trinuclear supramolecular complex containing both the Co(II)(phen) 2 and Cu(II)(phen) 2 as building blocks. The study shows the flexible multifunctional self-assembly capability of the H 3TST ligands presenting in these supramolecular complexes through coordinative, H-bonding and even π- π stacking interactions. The photoluminescent optical properties of these complexes are also investigated and discussed as well as the second-order nonlinear optical properties of 1.

The inner containment of an EPR trademark pressurized water reactor

Energy Technology Data Exchange (ETDEWEB)

Ostermann, Dirk; Krumb, Christian; Wienand, Burkhard [AREVA GmbH, Offenbach (Germany)

2014-08-15

On February 12, 2014 the containment pressure and subsequent leak tightness tests on the containment of the Finnish Olkiluoto 3 EPR trademark reactor building were completed successfully. The containment of an EPR trademark pressurized water reactor consists of an outer containment to protect the reactor building against external hazards (such as airplane crash) and of an inner containment that is subjected to internal overpressure and high temperature in case of internal accidents. The current paper gives an overview of the containment structure, the design criteria, the validation by analyses and experiments and the containment pressure test.

Continuous commissioning of buildings: A case study of a campus building in Denmark

DEFF Research Database (Denmark)

Markoska, Elena; Jradi, Muhyiddine; Jørgensen, Bo Nørregaard

2016-01-01

The general trend in building commissioning is that the commissioning is often either insufficiently comprehensive in its execution, or it is not conducted at all. As such, it has been observed that buildings often will contain faults that have not been discovered during the commissioning phase....... In this paper, we present a framework for continuous verification and commissioning of a building with a set of performance tests that are able to monitor the performance and functionality with a daily granularity. The performance tests are run on a newly constructed campus building in Denmark, over the course...... of three months, and the results of the performance tests are presented within a dashboard application, which helps verify that the building is performing accordingly to its original design intent....

Enhancing reproducibility in scientific computing: Metrics and registry for Singularity containers

Science.gov (United States)

Prybol, Cameron J.; Kurtzer, Gregory M.

2017-01-01

Here we present Singularity Hub, a framework to build and deploy Singularity containers for mobility of compute, and the singularity-python software with novel metrics for assessing reproducibility of such containers. Singularity containers make it possible for scientists and developers to package reproducible software, and Singularity Hub adds automation to this workflow by building, capturing metadata for, visualizing, and serving containers programmatically. Our novel metrics, based on custom filters of content hashes of container contents, allow for comparison of an entire container, including operating system, custom software, and metadata. First we will review Singularity Hub’s primary use cases and how the infrastructure has been designed to support modern, common workflows. Next, we conduct three analyses to demonstrate build consistency, reproducibility metric and performance and interpretability, and potential for discovery. This is the first effort to demonstrate a rigorous assessment of measurable similarity between containers and operating systems. We provide these capabilities within Singularity Hub, as well as the source software singularity-python that provides the underlying functionality. Singularity Hub is available at https://singularity-hub.org, and we are excited to provide it as an openly available platform for building, and deploying scientific containers. PMID:29186161

Enhancing reproducibility in scientific computing: Metrics and registry for Singularity containers.

Directory of Open Access Journals (Sweden)

Vanessa V Sochat

Full Text Available Here we present Singularity Hub, a framework to build and deploy Singularity containers for mobility of compute, and the singularity-python software with novel metrics for assessing reproducibility of such containers. Singularity containers make it possible for scientists and developers to package reproducible software, and Singularity Hub adds automation to this workflow by building, capturing metadata for, visualizing, and serving containers programmatically. Our novel metrics, based on custom filters of content hashes of container contents, allow for comparison of an entire container, including operating system, custom software, and metadata. First we will review Singularity Hub's primary use cases and how the infrastructure has been designed to support modern, common workflows. Next, we conduct three analyses to demonstrate build consistency, reproducibility metric and performance and interpretability, and potential for discovery. This is the first effort to demonstrate a rigorous assessment of measurable similarity between containers and operating systems. We provide these capabilities within Singularity Hub, as well as the source software singularity-python that provides the underlying functionality. Singularity Hub is available at https://singularity-hub.org, and we are excited to provide it as an openly available platform for building, and deploying scientific containers.

Airborne asbestos fibre levels in buildings: a summary of UK measurements.

Science.gov (United States)

Burdett, G J; Jaffrey, S A; Rood, A P

1989-01-01

The UK Health and Safety Executive, in conjunction with the Department of the Environment, has carried out a number of surveys of airborne asbestos fibre concentrations in buildings. All samples have been collected on membrane filters and analysed by analytical transmission electron microscopy. Four categories of buildings under normal occupation have been investigated; non-domestic buildings containing sprayed or trowelled asbestos, domestic buildings containing sprayed asbestos or asbestos plaster, buildings with warm air heaters containing asbestos and buildings without asbestos materials. A number of buildings have also been surveyed during and after the removal of asbestos materials. The choice of measurement indices and analytical procedures is reviewed, before measurements are compared in terms of the concentration of asbestos fibres greater than 5 microns long. The decision whether to remove asbestos from occupied buildings is discussed with reference to the associated cost and risk. In the present survey, management of undamaged asbestos appeared preferable to large-scale removal.

Alternative containers for low-level wastes containing large amounts of tritium

International Nuclear Information System (INIS)

Gause, E.P.; Lee, B.S.; MacKenzie, D.R.; Wiswall, R. Jr.

1984-11-01

High-activity tritiated waste generated in the United States is mainly composed of tritium gas and tritium-contaminated organic solvents sorbed onto Speedi-Dri which are packaged in small glass bulbs. Low-activity waste consists of solidified and adsorbed liquids. In this report, current packages for high-activity gaseous and low-activity adsorbed liquid wastes are emphasized with regard to containment potential. Containers for low-level radioactive waste containing large amounts of tritium need to be developed. An integrity may be threatened by: physical degradation due to soil corrosion, gas pressure build-up (due to radiolysis and/or biodegradation), rapid permeation of tritium through the container, and corrosion from container contents. Literature available on these points is summarized in this report. 136 references, 20 figures, 40 tables

Deactivation of Building 7602

International Nuclear Information System (INIS)

Yook, H.R.; Barnett, J.R.; Collins, T.L.

1995-10-01

The Department of Energy (DOE) has sponsored research and development programs in Building 7602 at Oak Ridge National Laboratory (ORNL) since 1984. This work focused on development of advanced technology for processing nuclear fuels. Building 7602 was used for engineering-scale tests using depleted and natural uranium to simulate the nuclear fuel. In April 1994 the DOE Office of Nuclear Energy (NE) sent supplemental FY 1994 guidance to ORNL stating that in FY 1995 and beyond, Building 7602 is considered surplus to NE programs and missions and shall be shut down (deactivated) and maintained in a radiologically and industrially safe condition with minimal surveillance and maintenance (S ampersand M). DOE-NE subsequently provided FY 1995 funding to support the deactivation activities. Deactivation of Building 7602 was initiated on October 1, 1994. The principal activity during the first quarter of FY 1995 was removal of process materials (chemicals and uranium) from the systems. The process systems were operated to achieve chemical solution concentrations needed for reuse or disposal of the solutions prior to removal of the materials from the systems. During this phase of deactivation the process materials processed and removed were: (1) Uranyl nitrate solution 30,178 L containing 4490 kg of uranium; (2) Nitric acid (neutralized) 9850 L containing less than 0.013 kg of uranium; (3) Organic solution 3346 L containing 265 kg of uranium; (4) Uranium oxide powder 95 kg; and (5) Miscellaneous chemicals. At the end of December 1994, the process systems and control systems were shut down and deactivated. Disposition of the process materials removed from the process systems in Building 7602 proved to be the most difficult part of the deactivation. An operational stand down and funding reductions at Y-12 prevented planned conversion of the uranyl nitrate solution to depleted uranium oxide powder. This led to disposal of the uranyl nitrate solution as waste

VT Locations of State of Vermont Buildings

Data.gov (United States)

Vermont Center for Geographic Information — (Link to Metadata) This data layer contains the locations of buildings/facilities owned and/or leased by the State of Vermont. Data was obtained from Buildings and...

Elements for computing and forecasting the leakage rate of the inner containment of nuclear reactor buildings

International Nuclear Information System (INIS)

Asali, M.; Capra, B.; Mazars, J.; Colliat, J.B.

2015-01-01

This study aims at introducing a methodology based on a macro-element discretization to compute and forecast the air leak rate of double-wall reactor buildings during air pressure tests. Assumptions at the basis of a weakly coupled strategy are checked in the case of a typical porous concrete section of an inner containment modeled during a 33 year period including four decennial regulatory pressure tests. However, air leakage due to porosity is only part of in situ measurements. Leakage due to cracking is another part and should be taken into account. A first macro-element is then presented, that superimposes Darcy flow within a porous matrix together with Poiseuille flow within a crack. Those elements are then used in a 3D hydraulic model to compute more accurately the total air leakage rate of considered structures. (authors)

Experimental study of a laboratory concrete material representative of containment buildings: desorption isotherms and permeability determination

International Nuclear Information System (INIS)

Semete, P.; Fevrier, B.; Delorme, J.; Sanahuja, J.; Desgree, P.; Le Pape, Y.

2015-01-01

The isotherm sorption curve is a first order parameter for the calculations of concrete drying and/or creep using Finite Element Analysis. An experimental campaign was undertaken by EDF MMC in order to characterize the first desorption isotherm at room temperature of a laboratory material representative of concrete containment buildings. Long term drying tests were carried out on cement paste and on three samples geometries on concrete (with radial and axial one-dimensional drying on thin disks and multi-dimensional drying on Representative Elementary Volumes). The measurements results (porosity, densities and mass loss curves) are provided and the isotherms obtained for the four different configurations are compared. Several analyses of the results are proposed including the assessment of a criterion for the determination of the moisture content final balance (estimation of the asymptotic mass loss) and the back-analysis of equivalent permeability. (authors)

Radioactive substances in the Danish building materials

International Nuclear Information System (INIS)

Ulbak, K.

1986-01-01

Building materials as any other materials of natural occurrence contain small concentrations of natural radioactive elements. This natural radioactivity affects people inside buildings. This publiccation refers measurements of the Danish building materials, and radiation doses originating from this source affecting the Danish population are related to the other components of background radioactivity. (EG)

User Driven Innovative Building Design

DEFF Research Database (Denmark)

Christiansson, Per; Sørensen, Kristian Birch; Steffensen, K. G.

2009-01-01

During recent years there has been an ever-increasing focus on the possibilities to change the building process to raise quality on the final building products as well as on the activities of actors involved in the building process. One reason for this interest is the new opportunities evolving due...... Space. In addition to these spaces there are supporting artifacts like Idea Bank and Good Story/Best Practice bank as well as Ontology containers and access to Communities of Practice and Interest. The project has so far validated the need for enhanced methods to involve end-users of buildings...

Building codes : obstacle or opportunity?

Science.gov (United States)

Alberto Goetzl; David B. McKeever

1999-01-01

Building codes are critically important in the use of wood products for construction. The codes contain regulations that are prescriptive or performance related for various kinds of buildings and construction types. A prescriptive standard might dictate that a particular type of material be used in a given application. A performance standard requires that a particular...

GOTHIC MODEL OF BWR SECONDARY CONTAINMENT DRAWDOWN ANALYSES

International Nuclear Information System (INIS)

Hansen, P.N.

2004-01-01

This article introduces a GOTHIC version 7.1 model of the Secondary Containment Reactor Building Post LOCA drawdown analysis for a BWR. GOTHIC is an EPRI sponsored thermal hydraulic code. This analysis is required by the Utility to demonstrate an ability to restore and maintain the Secondary Containment Reactor Building negative pressure condition. The technical and regulatory issues associated with this modeling are presented. The analysis includes the affect of wind, elevation and thermal impacts on pressure conditions. The model includes a multiple volume representation which includes the spent fuel pool. In addition, heat sources and sinks are modeled as one dimensional heat conductors. The leakage into the building is modeled to include both laminar as well as turbulent behavior as established by actual plant test data. The GOTHIC code provides components to model heat exchangers used to provide fuel pool cooling as well as area cooling via air coolers. The results of the evaluation are used to demonstrate the time that the Reactor Building is at a pressure that exceeds external conditions. This time period is established with the GOTHIC model based on the worst case pressure conditions on the building. For this time period the Utility must assume the primary containment leakage goes directly to the environment. Once the building pressure is restored below outside conditions the release to the environment can be credited as a filtered release

A new CANDU-600 containment structure

International Nuclear Information System (INIS)

Serban, V.; Bobei, M.; Gheorghiu, M.; Popescu, M.; Stanciu, M.; Dinica, D.; Alexandru, C.

1994-01-01

This paper is presenting a structure made of reinforced concrete with rectangular cross-section, box-divided, prefabricated and modulled on a bay 6.5 m wide and 4.5 m high, and provided with a steel liner. The building has an overall basement in which the steel liner is embedded and which is supporting the building walls. The inner structure is common to the containment as well and it is carried out for each room (generally 6.5 m by 6.5 m) having intermediar floors at the necessary elevations. The containment dimensions, on horizontal plane are 6 x 6.5 m by 5 x 6.5 m and the total height of the side walls is 30.5 m. The containment is closed in A-C direction by a prefabricated semi-cylinder which is supported by the side walls and 5 intermediate arches. The fuel transfer deck structure is common to the inner structure and the containment structure. The Calandria vault is a separate individual structure located above E1. 100. For CANDU-600 main equipment the same arrangement was maintained, some unsignificant modifications being made, for example, the access areas located in the four corners of the building as well as the location of some auxiliary systems. The paper is also including a set of 1:200 scale drawings, comments on the construction manner and the results of the building structural analysis. The suggested solution is evidencing economical benefits facilities in the operation and construction of the plant and it is specially recommended for areas with high seismic events. (author)

Role of BWR secondary containments in severe accident mitigation: issues and insights from recent analyses

International Nuclear Information System (INIS)

Greene, S.R.

1988-01-01

All commercial boiling water reactor (BWR) plants in the US employ primary containments of the pressure suppression design. These primary containments are surrounded and enclosed by a secondary containment consisting of a reactor building and refueling bay (MK I and MK II designs), a shield building, auxiliary building and fuel building (MK III), or an auxiliary building and enclosure building (Grand Gulf style MK III). Although secondary containment designs are highly plant specific, their purpose is to minimize the ground level release of radioactive material for a spectrum of traditional design basis accidents. While not designed for severe accident mitigation, these secondary containments might also reduce the radiological consequences of severe accidents. This issue is receiving increasing attention due to concerns that BWR MK I primary containment integrity would be lost should a significant mass of molten debris escape the reactor vessel during a severe accident. This paper presents a brief overview of domestic BWR secondary containment designs and highlights plant-specific features that could influence secondary containment severe accident survivability and accident mitigation effectiveness. Current issues surrounding secondary containment performance are discussed, and insights gained from recent ORNL secondary containment studies of Browns Ferry, Peach Bottom, and Shoreham are presented. Areas of significant uncertainty are identified and recommendations for future research are presented

Containment Leakage Rate Testing Program in NPP Krsko

International Nuclear Information System (INIS)

Dudas, M.; Heruc, Z.

2002-01-01

NPP Krsko adopted new regulations for testing of the reactor building containment as stipulated by 10CFR50 (Code of Federal Regulation) Appendix J, Option B instead of the previous requirement 10CFR50 Appendix J now renamed to 10CFR50 Appendix J, Option A. In the USA a thorough analyses of nuclear power plants reactor building containment testing was conducted. As part of these analyses the test results obtained from testing of various reactor-building containments in the last ten years were reviewed. It was concluded that it would be meaningful to, based on test results historical data, reconsider possibility of redefining testing intervals. The official proposal of such approach was reviewed and approved by the NRC and published in September of 1995 in the FR Vol.60 No.186. Based on directions from 10CFR50 Appendix J, Option B, the new criteria for definition of test intervals were created. Criteria were based upon past performance during testing (Performance-based Requirements) and safety impact. At NPP Krsko, the analyses of the Reactor Building Containment. Integrity Test results was performed . This included test results of the Containment Integrated Leak Rate Testing (CILRT or Type A tests), Containment Isolation Valves Local Leak Rater Tests (Type C tests) and Mechanical and Electrical Penetrations Local Leak Rate tests (Type B tests). In accordance with instructions from NEI 94-01 and based on analyses of test results, NPP Krsko created Containment Leakage Rate Testing Program with the purpose to establish the performance-based definition of test intervals, inspection scope, trending and reporting. Equally, the program gives instructions how to evaluate test results and how to deal with the containment penetration or isolation valve repair contingency. All changes caused with transition from Option A to Option B are marginal to public safety. (author)

Possibilities of using new technology materials in constructing the radioactive waste containers The paper will consider using the latest technologies in material science for building

International Nuclear Information System (INIS)

Itu, Razvan Bogdan

2008-01-01

The paper will consider using the latest technologies in materials science for building the radioactive waste containers. A new amorphous steel has been discovered by the scientists from the University of Virginia, a material three times stronger then conventional steel and non-magnetic. Scientists shown that this steel, DARVA - Glass 101, has superior anticorrosive proprieties. The paper will also consider using Para-Aramides in protecting the radioactive waste containers. Chemical and physical properties of these materials shown a great tensile strength and the inter-chain bonds make these materials extremely strong. (author)

The evolution of CANDU containment design

International Nuclear Information System (INIS)

Pendergast, Duane R.; Meneley, Daniel A.

1995-01-01

This paper reviews Canadian containment design, reflects on forces which have shaped the evolving designs and contemplates future containment design subject to existing constraints of Canadian and International nuclear power regulations. The discussion mentions modifications which could play a role in easing customary restrictions on siting while meeting the intent and literal definition of Canadian licensing requirements. Many different containment concepts have been considered and deployed over the years. Professor Birkhofer points out that the earliest systems installed were 'dry containment'. These rely on large containment buildings designed to contain all the the steam from a loss of coolant. It was soon realized the large water inventory of boiling water reactors would require very large and expensive containment buildings. This led to the development of pressure suppression concepts. Various pressure suppression schemes have been devised to condense steam and thus reduce design pressure and volume requirements. Examples include the forcing of steam into condensing water pools of BWR's steam condensation by passage into arrays of ice, dousing spray systems in CANDU reactors, and the spray condenser systems of late model Soviet designed VVER - 440 reactors. The fundamental concept of energy removal by steam condensation can result in a small containment volume requiring low design pressure capability

Nuclear reactor melt-retention structure to mitigate direct containment heating

International Nuclear Information System (INIS)

Tutu, N.K.; Ginsberg, T.; Klages, J.R.

1991-01-01

This patent describes a nuclear reactor melt-retention structure that functions to retain molten core material within a melt retention chamber to mitigate the extent of direct containment heating. The structure being adapted to be positioned within or adjacent to a pressurized or boiling water nuclear reactor containment building at a location such that at least a portion of the melt retention structure is lower than and to one side of the nuclear reactor pressure vessel, and such that the structure is adjacent to a gas escape channel means that communicates between the reactor cavity and the containment building of the reactor. It comprises a melt-retention chamber, wall means defining a passageway extending between the reactor cavity underneath the reactor pressure vessel and one side of the chamber, the passageway including vent means extending through an upper wall portion thereof. The vent means being in communication with the upper region of the reactor containment building, whereby gas and steam discharged from the reactor pressure vessel are vented through the passageway and vent means into the gas-escape channel means and the reactor containment building

Building Condition and Suitability Evaluation Manual.

Science.gov (United States)

MGT of America, Inc., Tallahassee, FL.

This educational facility evaluation manual contains the overall building condition rating form and the supporting check sheets which have been field tested in several states and, where appropriate, modified for use in the Idaho School Facilities Needs Assessment. The exterior building condition form examines the foundation, structure, walls,…

Direct containment heating models in the CONTAIN code

International Nuclear Information System (INIS)

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

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.

Igloo containment system for improvised explosive devices

International Nuclear Information System (INIS)

Dyckes, G.W.

1980-09-01

A method for containing or partially containing the blast and dispersal of radioactive particulate from improvised explosive devices is described. The containment system is restricted to devices located in fairly open areas at ground level, e.g., devices concealed in trucks, vans, transportainers, or small buildings which are accessible from all sides

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...

Neutron dosimetry inside the containment building of Spanish nuclear power plants with PADC based dosemeters

Energy Technology Data Exchange (ETDEWEB)

Garcia-Fuste, M.J. [Grup de Fisica de les Radiacions. Departament de Fisica. Edifici C. Universitat Autonoma de Barcelona, E-08193 Bellaterra (Spain); Domingo, C., E-mail: carles.domingo@uab.ca [Grup de Fisica de les Radiacions. Departament de Fisica. Edifici C. Universitat Autonoma de Barcelona, E-08193 Bellaterra (Spain); Amgarou, K.; Bouassoule, T.; Castelo, J. [Grup de Fisica de les Radiacions. Departament de Fisica. Edifici C. Universitat Autonoma de Barcelona, E-08193 Bellaterra (Spain)

2009-10-15

The Spanish Nuclear Safety Council (Consejo de Seguridad Nuclear, CSN) recommends performing neutron individual dose assignments at workplaces based on ambient dose equivalent measurements using area monitors and by estimating the amount of time that workers spend in the different monitored environments. In addition, some Spanish nuclear power plants estimate the neutron dose equivalent using albedo thermoluminescence dosemeters (TLD). In the period 2004-2006, our group, together with other research centers, participated in a project, funded by the CSN, with the support of the Spanish Nuclear Power Plants Association (UNESA), to investigate in situ which could be the best practical procedure for individual neutron dose monitoring in nuclear power plants. As part of this survey, several units of the UAB PADC based neutron dosemeter were exposed, on a methacrylate phantom simulating a human body, at four different places inside the containment building of the Asco I nuclear power plant. The influence of different types of calibration neutron fields is analysed and the dose equivalent for each point is estimated.

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

International Nuclear Information System (INIS)

Choun, Youngsun; Park, Junhee

2014-01-01

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

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.

Mercury-Containing Devices and Demolition

Science.gov (United States)

Some items inside residential buildings contain mercury, which poses a persistent and toxic human health and environmental threat. These materials should be carefully salvaged for proper recycling to prevent mercury contamination prior to demolition.

Acoustic building infiltration measurement system

Science.gov (United States)

Muehleisen, Ralph T.; Raman, Ganesh

2018-04-10

Systems and methods of detecting and identifying a leak from a container or building. Acoustic pressure and velocity are measured. Acoustic properties are acquired from the measured values. The acoustic properties are converted to infiltration/leakage information. Nearfield Acoustic Holography (NAH) may be one method to detect the leakages from a container by locating the noise sources.

Radio-contaminant behaviour in the cover-gas space and the containment building of a sodium-cooled fast reactor in accident conditions

International Nuclear Information System (INIS)

Mathe, Emmanuel

2014-01-01

In the context of the Generation IV initiative, the consequences of a severe-accident (SA) in a sodium-cooled fast reactor must be studied. A SFR (Sodium cooled Fast Reactor) severe accident involves the disruption of the core by super-criticality involving the destruction of a certain number of fuel assemblies. Subsequently the interaction between hot fuel and liquid sodium can lead to a vapor explosion which could create a breach in the primary system. Some contaminated liquid sodium would thus be ejected into the containment building. In this situation, the evaluation of potential releases to the environment (the source term) must forecast the quantity and the chemical speciation of the radio-contaminants likely to be released from the containment building. One critical risk of a SA is the production of contaminated aerosols in the containment building by spray ejection of primary-system sodium. Being pyrophoric, the sodium droplets react with oxygen first oxidizing then burning, with significant heat of combustion. As well as evaluating the consequences of a pressure rise inside the containment, the evolution of the sodium must be assessed since not only is it activated and contaminated but, in oxide form, very toxic. Ultimately, the aerosols are the main radiological risk acting as the vector for radionuclide transport to the environment in the event of a problem with the confinement. These aerosols could evolve and interact with the FP (Fissile Products) and these interactions could modify the physical and chemical nature of the PF. We model a large part of the events that occur during a SA inside a SFR from the sodium spray fire to the reaction between sodium aerosols and PF (iodine). At first, we develop a numerical model (NATRAC) that simulates the sodium spray fire, calculates the temperature and the pressure inside the containment as well as the mass of aerosols produced during this kind of fire. The simulation has been validated with different

Building Mainteance Module I: Orientation to Building Maintenance. Instructor's Guide.

Science.gov (United States)

Eck, Francis

This document contains teacher's materials for a seven-lesson Missouri secondary education course on building maintenance fundamentals. The document begins with an explanation of its components and how to use them. Next is a table that associates individual instructional materials in the lessons with the competencies they teach. The lessons are:…

Dynamic analysis of a reactor building on alluvial soil

International Nuclear Information System (INIS)

Arya, A.S.; Chandrasekaran, A.R.; Paul, D.K.; Warudkar, A.S.

1977-01-01

The reactor building consists of reinforced concrete internal framed structure enclosed in double containment shells of prestressed and reinforced concrete all resting on a common massive raft. The external cylindrical shell is capped by a spherical dome while the internal shell carries a cellular gird slab. The building is partially buried under ground. The soil consists of alluvial going to 1000 m depth. The site lies in a moderate seismic zone. The paper presents the dynamic analysis of the building including soil-structure interaction. The mathematical model consists of four parallel, suitably interconnected struxtures, namely inner containment, outer containment, internal frame and the calandria vault. Each one of the parallel structures consists of lumped-mass beam elements. The soil below the raft and on the sides of outer containment shell is represented by elastic springs in both horizontal and vertical directions. The various assumpions required to be made in developing the mathematical model are briefly discussed in the paper. (Auth.)

The French nuclear power plant reactor building containment contributions of prestressing and concrete performances in reliability improvements and cost savings

International Nuclear Information System (INIS)

Rouelle, P.; Roy, F.

1998-01-01

The Electricite de France's N4 CHOOZ B nuclear power plant, two units of the world's largest PWR model (1450 Mwe each), has earned the Electric Power International's 1997 Powerplant Award. This lead NPP for EDF's N4 series has been improved notably in terms of civil works. The presentation will focus on the Reactor Building's inner containment wall which is one of the main civil structures on a technical and safety point of view. In order to take into account the necessary evolution of the concrete technical specification such as compressive strength low creep and shrinkage, the HSC/HPC has been used on the last N4 Civaux 2 NPP. As a result of the use of this type of professional concrete, the containment withstands an higher internal pressure related to severe accident and ensures higher level of leak-tightness, thus improving the overall safety of the NPP. On that occasion, a new type of prestressing has been tested locally through 55 C 15 S tendons using a new C 1500 FE Jack. These updated civil works techniques shall allow EDF to ensure a Reactor Containment lifespan for more than 50 years. The gains in terms of reliability and cost saving of these improved techniques will be developed hereafter

Multi-scale approach of the mechanical behaviour of reinforced concrete structures - Application to nuclear plant containment buildings

International Nuclear Information System (INIS)

David, M.

2012-01-01

This thesis develops a multi-scale strategy to describe the mechanical behaviour of steel reinforcements and prestressing tendons in a reinforced concrete structure. This strategy is declined in several steps, which allow gradual integration of new physical phenomena. The first asymptotic model represents the effective elastic behaviour of heterogeneities periodically distributed on a surface. It combines an elastic interface behaviour and a membrane behaviour. A second asymptotic model then focuses on the behaviour of rigid fibers distributed on a surface, which may slide with respect to the surrounding volume. These models induce less stress concentrations than the usual truss models. They are implemented in the finite element code Code-Aster, and validated with respect to reference three-dimensional simulations. Their interaction with a macroscopic crack is studied. Finally, this strategy allows the modeling of experimental tests carried out on a portion of a containment building in real scale. (author)

Building 774: open for business

CERN Multimedia

CERN Bulletin

2015-01-01

In July 2012, the demolition of Building 936 on the Prévessin site marked the start of the Building 774 project. On 23 February, less than three years later, the new 3900 m2 building was handed over to the BE department.   The brand new Building 774. (Credits: Francesco Soppelsa) Located near to the CERN Control Centre, Building 774 contains offices, laboratories and meeting rooms, as well as a huge public area consisting of a 104-seat auditorium, a changing room/shower area in the basement and a pleasant cafeteria open from 8 a.m. to 5 p.m., offering a wide range of refreshments including hot meals at lunchtime. “There were a few twists and turns during the construction of this building, but it all turned out well in the end!" says Michael Poehler, a member of the GS-SE group and the technical coordinator of the project. (Credits: Francesco Soppelsa) The 120 occupants of the building have just moved into their brand new home, bringing all the members of the...

Aerosol behavior in the reactor containment building during severe accident

International Nuclear Information System (INIS)

Berthion, Y.; Lhiaubet, G.; Gauvain, J.

1984-07-01

Thermohydraulic behavior inside a PWR containment during severe accident depends on decay heat transferred to the sump water by aerosol gravitational settling and deposition. Conversely, aerosol behavior depends on thermal hydraulic conditions, especially atmosphere moisture for soluble aerosol GsI, and CsOH. Therefore, a small iterative procedure between thermo-hydraulic and aerosol calculations has been performed in order to evaluate the importance of this coupling between the two phenomena. In this paper, it is shown that with this procedure and using our codes JERICHO, RICOCHET and AEROSOLS/B1, the steam condensation on aerosols is an important phenomenon for a correct estimation of the attenuation factor of the suspended mass of aerosols in the airborne of the containment. Then, we have a more realistic assessment of the source term released by the containment

Reactor coolant system and containment aqueous chemistry

International Nuclear Information System (INIS)

Torgerson, D.F.

1986-01-01

Fission products released from fuel during reactor accidents can be subject to a variety of environments that will affect their ultimate behavior. In the reactor coolant system (RCS), for example, neutral or reducing steam conditions, radiation, and surfaces could all have an effect on fission product retention and chemistry. Furthermore, if water is encountered in the RCS, the high temperature aqueous chemistry of fission products must be assessed to determine the quantity and chemical form of fission products released to the containment building. In the containment building, aqueous chemistry will determine the longer-term release of volatile fission products to the containment atmosphere. Over the past few years, the principles of physical chemistry have been rigorously applied to the various chemical conditions described above. This paper reviews the current state of knowledge and discusses the future directions of chemistry research relating to the behavior of fission products in the RCS and containment

Nuclear reactor melt-retention structure to mitigate direct containment heating

Science.gov (United States)

Tutu, Narinder K.; Ginsberg, Theodore; Klages, John R.

1991-01-01

A light water nuclear reactor melt-retention structure to mitigate the extent of direct containment heating of the reactor containment building. The structure includes a retention chamber for retaining molten core material away from the upper regions of the reactor containment building when a severe accident causes the bottom of the pressure vessel of the reactor to fail and discharge such molten material under high pressure through the reactor cavity into the retention chamber. In combination with the melt-retention chamber there is provided a passageway that includes molten core droplet deflector vanes and has gas vent means in its upper surface, which means are operable to deflect molten core droplets into the retention chamber while allowing high pressure steam and gases to be vented into the upper regions of the containment building. A plurality of platforms are mounted within the passageway and the melt-retention structure to direct the flow of molten core material and help retain it within the melt-retention chamber. In addition, ribs are mounted at spaced positions on the floor of the melt-retention chamber, and grid means are positioned at the entrance side of the retention chamber. The grid means develop gas back pressure that helps separate the molten core droplets from discharged high pressure steam and gases, thereby forcing the steam and gases to vent into the upper regions of the reactor containment building.

Containment design for Indian PHWRs - evolution and future trends

International Nuclear Information System (INIS)

Chatterjee, S.K.; Srinivasan, G.R.; Das, M.; Prakash, P.; Mulgund, S.

1994-01-01

The design of containment systems for PHWRs in India has undergone progressive improvements to enhance their reliability and effectiveness. The state-of-the-art containment design incorporates a double containment structure for minimizing radioactivity release to the environment, a completely passive vapour suppression system with huge suppression pool for limiting pressure build-up during postulated LOCA and various engineered systems for depressurizing the containment and cleaning the containment environment following an accident. The containment related Engineered Safety Features (ESFS) include Reactor Building (RB) coolers, Primary Containment Controlled Discharge (PCCD) system, Primary Containment Filtration and Pump-Back (PCFPB) system and Secondary Containment Filtered Recirculation and Purge (SCFRP) system. Studies indicate that the unique feature of double containment with huge suppression pool at basement and associated ESFs not only ensures near zero ground level release during Design Basis Accident (DBA) conditions, but also provides adequate assurance for containment integrity even in beyond DBA scenario. In this paper, an outline of the containment design evolution in Indian PHWRs is presented and salient features of standardized containment design are highlighted. Important containment related studies are discussed and outstanding safety issues viz. hydrogen generation and management, containment venting, containment over pressure capability, etc. are addressed. (author). 16 refs., 1 tab., 8 figs

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

International Nuclear Information System (INIS)

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

2014-01-01

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)

Characterization of the Three Mile Island Unit-2 reactor building atmosphere prior to the reactor building purge

International Nuclear Information System (INIS)

Hartwell, J.K.; Mandler, J.W.; Duce, S.W.; Motes, B.G.

1981-05-01

The Three Mile Island Unit-2 reactor building atmosphere was sampled prior to the reactor building purge. Samples of the containment atmosphere were obtained using specialized sampling equipment installed through penetration R-626 at the 358-foot (109-meter) level of the TMI-2 reactor building. The samples were subsequently analyzed for radionuclide concentration and for gaseous molecular components (O 2 , N 2 , etc.) by two independent laboratories at the Idaho National Engineering Laboratory (INEL). The sampling procedures, analysis methods, and results are summarized

Analysis of wallboard containing a phase change material

Science.gov (United States)

Tomlinson, J. J.; Heberle, D. P.

Phase change materials (PCMs) used on the interior of buildings hold the promise for improved thermal performance by reducing the energy requirements for space conditioning and by improving thermal comfort by reducing temperature swings inside the building. Efforts are underway to develop a gypsum wallboard containing a hydrocarbon PCM. With a phase change temperature in the room temperature range, the PCM wallboard adds substantially to the thermal mass of the building while serving the same architectural function as conventional wallboard. To determine the thermal and economic performance of this PCM wallboard, the Transient Systems Simulation Program (TRNSYS) was modified to accommodate walls that are covered with PCM plasterboard, and to apportion the direct beam solar radiation to interior surfaces of a building. The modified code was used to simulate the performance of conventional and direct-gain passive solar residential-sized buildings with and without PCM wallboard. Space heating energy savings were determined as a function of PCM wallboard characteristics. Thermal comfort improvements in buildings containing the PCM were qualified in terms of energy savings. The report concludes with a present worth economic analysis of these energy savings and arrives at system costs and economic payback based on current costs of PCMs under study for the wallboard application.

Asbestos-Containing Materials (ACM) and Demolition

Science.gov (United States)

There are specific federal regulatory requirements that require the identification of asbestos-containing materials (ACM) in many of the residential buildings that are being demolished or renovated by a municipality.

Integrated severe accident containment analysis with the CONTAIN computer code

International Nuclear Information System (INIS)

Bergeron, K.D.; Williams, D.C.; Rexroth, P.E.; Tills, J.L.

1985-12-01

Analysis of physical and radiological conditions iunside the containment building during a severe (core-melt) nuclear reactor accident requires quantitative evaluation of numerous highly disparate yet coupled phenomenologies. These include two-phase thermodynamics and thermal-hydraulics, aerosol physics, fission product phenomena, core-concrete interactions, the formation and combustion of flammable gases, and performance of engineered safety features. In the past, this complexity has meant that a complete containment analysis would require application of suites of separate computer codes each of which would treat only a narrower subset of these phenomena, e.g., a thermal-hydraulics code, an aerosol code, a core-concrete interaction code, etc. In this paper, we describe the development and some recent applications of the CONTAIN code, which offers an integrated treatment of the dominant containment phenomena and the interactions among them. We describe the results of a series of containment phenomenology studies, based upon realistic accident sequence analyses in actual plants. These calculations highlight various phenomenological effects that have potentially important implications for source term and/or containment loading issues, and which are difficult or impossible to treat using a less integrated code suite

Use of EMW radiation in the building industry at defects in buildings

Directory of Open Access Journals (Sweden)

Sobotka Jindřich

2017-01-01

Full Text Available This paper discusses theory and application of microwave radiation and experimental optimization of microwave radiation to eliminate moisture content in wood elements. It will be appreciated that the rising moisture leaking into the structure, resulting in defects and structures of the buildings themselves. Owing to its properties, microwave radiation has been used in the construction industry in modern times, in particular to dry wet masonry of buildings. Effects of electromagnetic radiation on building structures lead to relatively sharp decreases in moisture content from damp building structures or elements. The influence of electromagnetic radiation on building structures lead to oscillation of water molecules contained in the material, which cause a phase transformation of water into vapour. Consequently, the vapour evaporates from the moist material, thereby drying the element exposed to radiation. The article describes experiments carried out at the Faculty of Civil Engineering of the Faculty of Technology in Brno that demonstrate successful decrease of water content in building materials using microwave radiation. First, the understanding of microwave radiation will be discussed. Following an analysis of research results an optimum intensity of microwave radiation sources as well as the necessary length of the irradiation of microwave radiation have been determined with respect to the particular type of building material and the success rate of elimination of moisture.

Training program for energy conservation in new-building construction. Volume II. Energy conservation technology: for the building inspector

Energy Technology Data Exchange (ETDEWEB)

None

1977-12-01

A Model Code for Energy Conservation in New Building Construction has been developed by those national organizations primarily concerned with the development and promulgation of model codes. The technical provisions are based on ASHRAE Standard 90-75 and are intended for use by state and local officials. This training manual contains the basic information necessary to acquaint the field building inspector with the concepts of energy conservation in buildings and instructs him in the basic techniques of field inspection of energy compliance.

NEK containment integrated leak rate test at full pressure

International Nuclear Information System (INIS)

Skaler, F.; Planinc, V.; Gregoric, D.; Cicvaric, D.

1999-01-01

NPP Krsko is a Pressure Water Reactor (PWR) Plant which has four barriers to prevent release of radioactive fission products. These four barriers are following: Fuel itself, Fuel Clad, Reactor Coolant System and Containment Building. Containment is the last barrier which can prevent release of fission product when other barriers have been already broken. To find out the real condition of containment vessel and to prove its ability of withstanding increased parameters during accident we have to perform Containment Integrated Leak Rate Test at least three times in every ten years of operation. CILRT 1999 in NPP Krsko was completely performed following regulation of 10CFR50 App. J Option A and ANSI/ANS 56.8-1987. The main goal of CILRT is to prove that the leakage of containment pathways and wall structures are within limits prescribed in Technical Specifications by pressurization of containment building above peak accident pressure Pa and measuring the mass changes of air using Ideal Gas Law.(author)

209-E Building -- Response to ventilation failure evaluation

International Nuclear Information System (INIS)

Foust, D.J.

1998-01-01

This document provides an evaluation and recommendations for radiological workplace air monitoring and response to ventilation failure for the Critical Mass Laboratory, 209-E Building. The Critical Mass Laboratory, part of the 209-E Building, was designed to provide a heavily shielded room where plutonium and uranium liquid solutions could be brought into various critical configurations under readily controlled and monitored conditions. The facility is contained within a one-story L-shaped concrete block and reinforced concrete building. One wing houses offices, a control room, shops, and a common area while the other wing includes an equipment room, the change room, work areas, and the two-story Critical Assembly Room (CAR). Three of the rooms contain radiologically contaminated equipment and materials

Buildings for the 21st Century, Fall 2001

Energy Technology Data Exchange (ETDEWEB)

2001-10-01

The Buildings for the 21st Century newsletter is produced by the Office of Building Technology, State and Community Programs and contains information on building programs, events, products, and initiatives, with a focus on energy efficiency and renewable energy. The fall issue includes information on weatherization, Boise's geothermal heating system, the BTS Core Databook, the Solar Decathlon, a Rebuild America partnership, the BigHorn Home Improvement Center, AIA's Top Ten Buildings, a sub-CFL procurement program, the U.S. investment in energy efficient research, new efficiency standards, PNNL's building software, and a calendar of meetings and conferences.

Vibration-damping structure for reactor building

International Nuclear Information System (INIS)

Kuno, Toshio; Iba, Chikara; Tanaka, Hideki; Kageyama, Mitsuru

1998-01-01

In a damping structure of a reactor building, an inner concrete body and a reactor container are connected by way of a vibration absorbing member. As the vibration absorbing member, springs or dampers are used. The inner concrete body and the reactor container each having weight and inherent frequency different from each other are opposed displaceably by way of the vibration absorbing member thereby enabling to reduce seismic input and reduce shearing force at least at leg portions. Accordingly, seismic loads are reduced to increase the grounding rate of the base thereby enabling to satisfy an allowable value. Therefore, it is not necessary to strengthen the inner concrete body and the reactor container excessively, the amount of reinforcing rods can be reduced, and the amount of a portion of the base buried to the ground can be reduced thereby enabling to constitute the reactor building easily. (N.H.)

Evaluation of internal/external exposure from interior building materials

International Nuclear Information System (INIS)

Furuta, Etsuko; Morita-Murase, Yuko; Yoshizawa, Yukio

2008-01-01

Internal exposure to alpha particles emitted from 222 Rn (radon) and its daughters is the second leading cause of lung cancer. As a source of indoor radon in home, there are interior building materials that contain radioactive minerals. These radioactive consumer products have been claimed by distributors to have effect of 'minus-ion' or 'radon spring' for healthy promotion. We analyzed radioactive nuclides contained in the interior building materials, and measured radon levels released from them. The results of gamma-ray spectrometry revealed that these interior building materials contain U- and Th-series nuclides. The densities of some radioactive nuclides in the tile used for a bathroom exceeded the exempt limits of International Basic Safety Standards. However, the radon densities released from the tile was lower than detectable limit. In contrast, one of the wallpaper released 34 Bq·m -3 of radon gas in a 50-liter container. This value is two times higher than the average radon level in Japanese homes. The minus-ion effect' wallpapers are thought to be a cause of residential exposure to radon. (author)

Insights into the behavior of LWR steel containment buildings during severe accidents

International Nuclear Information System (INIS)

Clauss, D.B.; Horschel, D.S.; Blejwas, T.E.

1987-01-01

Investigations into the performance of steel containment subject to pressure and temperature greater than their design basis loads are discussed. The timing, mechanism, and location of a containment failure, i.e., release of radioactive materials, have an important impact on the consequences of a severe accident. We review the results of experiments on steel containment models pressurized to failure, on aged and unaged seals subjected to elevated temperature and pressure, and on electrical penetration assemblies tested for leakage. Based on the results, the important features and details of analytical methods that can be used to predict containment performance are identified. Finally, we speculate on the performance of steel containments in severe accident conditions. (orig.)

Retrofitting solutions for two different occupancy levels of educational buildings in tropics

Science.gov (United States)

Yang, Junjing; Pantazaras, Alexandros; Lee, Siew Eang; Santamouris, Mattheos

2018-01-01

Within the multi-functionality of educational buildings, the energy conservation potential can be very different. In addition, among different retrofitting solutions investigated involving interventions on the building envelope, ventilation strategies, artificial lighting systems as well as equipment upgrading, different saving potential would come from different aspects. The opportunities for energy saving potential from the overall point of view and from the detailed aspect view of different retrofitting solutions would be very useful and important for building renovation decision making. This study presents a detailed retrofitting study of two different educational buildings. One represents a building with average occupancy variation and containing mainly offices and labs. The other one represents a building with high occupancy variation and containing mainly lecture rooms and studios. This comparison of the results gives an idea of the different energy saving potential for different types of educational buildings. Principal component analysis is also adopted to investigate the detailed performance of one of the buildings which is influenced stronger by these retrofitting solutions.

Synthesis of the IRSN report related to the containment of double walled enclosures of the operated fleet

International Nuclear Information System (INIS)

2013-01-01

This report presents the IRSN's analysis on studies and modifications planned by EDF within the frame of the VD3-1300 safety re-examination which more particularly concern the third containment barrier of a reactor and of its extensions, as well as the containment of some surrounding buildings. The addressed topics are: the approach associated with the 'containment' safety function, the condition, behaviour and control of the double walled enclosure, the system of suction and filtration of the space between enclosures, the extension of the third containment barrier, the containment of building surrounding the reactor building, the risk of bypass containment, the EDF organisation with respect to the containment safety function

Buildings for the 21st Century, Summer 2001. Office of Building Technology, State and Community Programs (BTS) Newsletter

International Nuclear Information System (INIS)

Burgert, S.

2001-01-01

The Buildings for the 21st Century newsletter is produced by the Office of Building Technology, State and Community Programs and contains information on building programs, events, products, and initiatives, with a focus on energy efficiency and renewable energy. The summer issue includes information on technology roadmap initiatives, new energy computer simulation software, an educational CD with energy lessons for teachers, a CD with energy-saving tips, a study on the efficiency of clothes washers, a loan program in New York, and a calendar of meetings and conferences

Buildings for the 21st Century, Summer 2001. Office of Building Technology, State and Community Programs (BTS) Newsletter

Energy Technology Data Exchange (ETDEWEB)

Burgert, S.

2001-07-11

The Buildings for the 21st Century newsletter is produced by the Office of Building Technology, State and Community Programs and contains information on building programs, events, products, and initiatives, with a focus on energy efficiency and renewable energy. The summer issue includes information on technology roadmap initiatives, new energy computer simulation software, an educational CD with energy lessons for teachers, a CD with energy-saving tips, a study on the efficiency of clothes washers, a loan program in New York, and a calendar of meetings and conferences.

Safety Research Experiment Facility Project. Conceptual design report. Volume IV. Reactor containment

International Nuclear Information System (INIS)

1975-12-01

The principal purpose of the SAREF Reactor Containment Building (RCB) is to prevent the uncontrolled release of radioactive materials to the atmosphere as a result of accidental occurrences inside the containment. The RCB houses numerous reactor systems and components including the Prestressed Concrete Reactor Vessel (PCRV). The design of the RCB is of reinforced concrete (steel-lined). The containment building is embedded nearly 100 feet in lava rock. It has therefore been necessary to independently formulate an appropriate and conservative design approach

Natural radioactivity and associated radiation hazards in building materials used in Peloponnese, Greece

International Nuclear Information System (INIS)

Papaefthymiou, H.; Gouseti, O.

2008-01-01

Five different kinds of building materials (Pozzolanic and Portland cements, limestone, white cement, marble powder and sand) commonly used in building construction in Peloponnese, Greece, and Portland cement's raw materials were analyzed for their natural radioactivity content, using γ-ray spectrometry. Pozzolanic and Portland cement (Cem II) samples were found to contain the highest average 226 Ra, 232 Th and 40 K activity concentrations compared with the other examined building material samples. This could be attributed to their containing fly ash, which was found to contain high natural radionuclide concentrations, especially that of 226 Ra (1041Bqkg -1 ). Results obtained were compared with the results reported by other Greek researchers and the worldwide values for building materials and soil. The calculated activity concentration index (I) values for all the examined building material samples were lower than the recommended exception limits for exposure to external γ-radiation

Predictive Solar-Integrated Commercial Building Load Control

Energy Technology Data Exchange (ETDEWEB)

Glasgow, Nathan [EdgePower Inc., Aspen, CO (United States)

2017-01-31

This report is the final technical report for the Department of Energy SunShot award number EE0007180 to EdgePower Inc., for the project entitled “Predictive Solar-Integrated Commercial Building Load Control.” The goal of this project was to successfully prove that the integration of solar forecasting and building load control can reduce demand charge costs for commercial building owners with solar PV. This proof of concept Tier 0 project demonstrated its value through a pilot project at a commercial building. This final report contains a summary of the work completed through he duration of the project. Clean Power Research was a sub-recipient on the award.

A New European COST Network 'NORM4Building' (TU1301) for the Reuse of NORM Containing Residues in Building Materials

International Nuclear Information System (INIS)

Schroeyers, W.; Schreurs, S.

2014-01-01

The new COST action was initiated on the 1st of January 2014 and runs for four years. COST is supported by the EU RTD Framework Program. In the presentation more information on how to participate in the network will be provided. In the presentation the new approach and new initiatives of the NORM4BUILDING network, that has its first meeting here in the DEAD SEA Hotel on the 12-13/02/2014, will be introduced. The NORM4Building materials network will be an open network of researchers. An Advisory Board consisting mainly from NORM processing and construction industries and relevant associations and regulators are invited to work in collaboration with the scientists that will populate the various working groups and the management committee of the new COST action

EDF reactor building containment: Monitoring of the pre-stressed concrete structure

International Nuclear Information System (INIS)

Badez, N.

2009-01-01

The concrete containments of the EDF PWR are pre-stressed, and are monitored to observe the ageing effects on the structure, in particular the evolutions of creep, shrinkage, pre-stress loss, and air leakage tightness. Monitoring devices are installed during construction period, and measurements are checked, stored on a data base, and analysed during all the plant operating life time. The topic of the presentation is to present each part of the EDF monitoring organisation. A continuous monitoring makes it possible to produce periodical comprehensive reports about the mechanical analysis of the structure, the strain stabilisation,... Periodical tests (each 10 years) are planned. They consist to submit the containment to an internal air pressure at the accidental pressure level. The monitoring system gives the strain values in order to check their linearity and reversibility with decreasing pressure. At the same time, the containment tightness is checked with a specific instrumentation to verify that leak rate is lower than the required level. A general view of instrumentation implemented on the containment (sensors, data acquisition), and a data analysis are presented

New "Risk-Targeted" Seismic Maps Introduced into Building Codes

Science.gov (United States)

Luco, Nicholas; Garrett, B.; Hayes, J.

2012-01-01

Throughout most municipalities of the United States, structural engineers design new buildings using the U.S.-focused International Building Code (IBC). Updated editions of the IBC are published every 3 years. The latest edition (2012) contains new "risk-targeted maximum considered earthquake" (MCER) ground motion maps, which are enabling engineers to incorporate a more consistent and better defined level of seismic safety into their building designs.

The Final Demise Of East Tennessee Technology Park Building K-33

International Nuclear Information System (INIS)

King, David A.

2011-01-01

Building K-33 was constructed in 1954 as the final section of the five-stage uranium enrichment cascade at the Oak Ridge Gaseous Diffusion Plant (ORGDP). The two original building (K-25 and K-27) were used to produce weapons grade highly enriched uranium (HEU). Building K-29, K-31, and K-33 were added to produce low enriched uranium (LEU) for nuclear power plant fuel. During ORGDP operations K-33 produced a peak enrichment of 2.5%. Thousands of tons of reactor tails fed into gaseous diffusion plants in the 1950s and early 1960s introducing some fission products and transuranics. Building K-33 was a two-story, 25-meters (82-feet) tall structure with approximately 30 hectare (64 acres) of floor space. The Operations (first) Floor contained offices, change houses, feed vaporization rooms, and auxiliary equipment to support enrichment operations. The Cell (second) Floor contained the enrichment process equipment and was divided into eight process units (designated K-902-1 through K-902-8). Each unit contained ten cells, and each cell contained eight process stages (diffusers) for a total of 640 enrichment stages. 1985: LEU buildings were taken off-line after the anticipated demand for uranium enrichment failed to materialize. 1987: LEU buildings were placed in permanent shutdown. Process equipment were maintained in a shutdown state. 1997: DOE signed an Action Memorandum for equipment removal and decontamination of Buildings K-29, K-31, K-33; BNFL awarded contract to reindustrialize the buildings under the Three Buildings D and D and Recycle Project. 2002: Equipment removal complete and effort shifts to vacuuming, chemical cleaning, scabbling, etc. 2005: Decontamination efforts in K-33 cease. Building left with significant 99 Tc contamination on metal structures and PCB contamination in concrete. Uranium, transuranics, and fission products also present on building shell. 2009: DOE targets Building K-33 for demolition. 2010: ORAU contracted to characterize Building K-33

Using Container Structures in Architecture and Urban Design

Science.gov (United States)

Grębowski, Karol; Kałdunek, Daniel

2017-10-01

The paper presents the use of shipping containers in architecture and urban design. Even today, houses and apartments are still too expensive. Since 1923 architects have been improving the living conditions of citizens by building very simple, repeatable forms. With prefabrication technology it became possible to build quicker, causing house prices to decrease. Apartments in block of flats became affordable to more and more people. Modernism had great impact on the quality of living spaces, despite the detrimental effect of large panel technology on social life. It gave people their own bathrooms, and gifted them with simple solutions we now consider indispensable. The ambition to build cheaply but effectively is still here. The future of housing lies in prefabricated apartment modules. A well optimized creation process is the key, but taking into consideration the mistakes made by past generations should be the second most important factor. Studies show that large panel buildings were too monumental and solid for a housing structure, and offered no public spaces between them. Lack of urban design transformed a great idea into blocks that are considered to be ugly and unfriendly. Diversity is something that large panel structures were missing. While most block of flats were being constructed out of the same module (Model 770), differentiated architecture was difficult to achieve. Nowadays, increasing numbers of shipping containers are being used for housing purposes. These constructions show that it is possible to create astonishing housing with modules. Shipping containers were not designed to be a building material, but in contrast to large panel modules, there are many more possibilities of their transformation. In this paper the authors propose a set of rules that, if followed, would result in cheaper apartments, while keeping in consideration both tremendous architecture and friendly urban design. What is more, the proposed solution is designed to adapt to

Taxing land for urban containment : Reflections on a Dutch debate

NARCIS (Netherlands)

Korthals Altes, W.K.

2009-01-01

Excessive land use regulations aimed at containing urban sprawl have been criticised, because they may overcompensate for the external effects of uncontrolled greenfield development and contribute to stagnation in house building. Taxes on building in green spaces may be an instrument for balancing

Bellefonte primary containment structure

International Nuclear Information System (INIS)

Olyniec, J.H.

1981-01-01

Construction of the reactor building primary containment structure at the Bellefonte Nuclear Plant involved several specialized construction techniques. This two unit plant is one of the nine nuclear units at six different sites now under construction by the Tennessee Valley Authority (TVA). The post-Tensioned, cast-in-place interior steel lined containment structure is unique within TVA. Problems during construction were identified at weekly planning meetings, and options were discussed. Close coordination between craft supervisors and on-site engineering personnel drew together ''hands-on''experience and technical background. Details of the construction techniques, problems, and solutions are presented

Survey and specimen taking of building materials which are destined for house building in The Netherlands

International Nuclear Information System (INIS)

Boer, J.F. den

1985-11-01

This investigation deals with the following items: (a) Some building materials cause an increase of the natural radioactive radiation level indoors, especially building materials containing a certain kind of phosphogypsum. The radiation level depends among other things on the applied quantity of building materials and on the location in the building (walls, floors or roofs, etc.). The soil underneath dwellings can also be an important radiation source. The report gives a listing of the kind of building materials used for dwellings in The Netherlands, both present ones as well as possible future ones. A survey of the quantities applied and the location of application in dwellings is also given. The different types of soil underneath the dwellings are discussed. (b) Samples were collected from various factories, dealers and other sources (both present and future samples) of the most important building materials and components thereof. The samples were handed over to Division of Technology for Society TNO, Radiological Service TNO and Netherland Energy Research Foundation, in order to measure the activity concentrations and the radon exhalations. A listing of the samples is given. (Auth.)

Natural radioactivity and associated radiation hazards in building materials used in Peloponnese, Greece

Energy Technology Data Exchange (ETDEWEB)

Papaefthymiou, H. [Division of Physics, Inorganic and Nuclear Chemistry, Department of Chemistry, University of Patras, Patras 265 00 (Greece)], E-mail: epap@chemistry.upatras.gr; Gouseti, O. [Division of Physics, Inorganic and Nuclear Chemistry, Department of Chemistry, University of Patras, Patras 265 00 (Greece)

2008-09-15

Five different kinds of building materials (Pozzolanic and Portland cements, limestone, white cement, marble powder and sand) commonly used in building construction in Peloponnese, Greece, and Portland cement's raw materials were analyzed for their natural radioactivity content, using {gamma}-ray spectrometry. Pozzolanic and Portland cement (Cem II) samples were found to contain the highest average {sup 226}Ra, {sup 232}Th and {sup 40}K activity concentrations compared with the other examined building material samples. This could be attributed to their containing fly ash, which was found to contain high natural radionuclide concentrations, especially that of {sup 226}Ra (1041Bqkg{sup -1}). Results obtained were compared with the results reported by other Greek researchers and the worldwide values for building materials and soil. The calculated activity concentration index (I) values for all the examined building material samples were lower than the recommended exception limits for exposure to external {gamma}-radiation.

Comparison of european computer codes relative to the aerosol behavior in PWR containment buildings during severe core damage accidents

International Nuclear Information System (INIS)

Fermandjian, J.; Beonio-Brocchieri, F.

1986-09-01

The present study concerns a comparative exercise, performed within the framework of the Commission of the European Communities, of the computer codes used in reactor safety in order to assess their capability of realistically describing the aerosol behavior in PWR reactor containment buildings during severe accidents. The codes included in the present study are the following: AEROSIM-M, AEROSOLS/Bl, CORRAL-2, NAUA Mod5. In AEROSIM-M, AEROSOLS/Bl and NAUA Mod5, the integro-differential equation for the evolution of the particle mass distribution is approximated by a set of coupled first order differential equations. To this end, the particle distribution function is replaced by a number of discrete monodisperse fractions. The CORRAL-2 has an essentially empirical basis (processes not explicitely modelled, but their net effects accounted for). The physical processes taken into account in the codes are shown finally

A compactification of the Bruhat-Tits building

CERN Document Server

Landvogt, Erasmus

1996-01-01

The aim of this work is the definition of the polyhedral compactification of the Bruhat-Tits building of a reductive group over a local field. In addition, an explicit description of the boundary is given. In order to make this work as self-contained as possible and also accessible to non-experts in Bruhat-Tits theory, the construction of the Bruhat-Tits building itself is given completely.

Mark III Containment vessel/annulus concrete design

International Nuclear Information System (INIS)

Chang, P.S.; Moussa, M.M.

1981-01-01

Recently, engineers have been considering the significant dynamic impact of safety/relief valve (S/RV) discharge loads on the containment structures, safety equipment, and piping systems in BWR type reactors. For a plant in the construction stage, extensive modifications will be made to qualify these new loads. The lower portion of the containment vessel serves as a suppression pool pressure boundary and is designed to sustain the effects of postulated loss of coolant accidents, seismic occurrences, S/RV discharge loads, and other effects. Extremely high spectral peak accelerations of the free-standing steel containment vessel can be obtained during the air dearing process of the S/RV discharge. Parametric studies indicated that a substantial reduction in response can be obtained by increasing the stiffness of the steel containment vessel in the lover area. A concrete backing configuration in the suppression pool area of Mark III Containment is proposed in this paper. A composite action is assumed between the steel containment vessel shell and the concrete section. The system is physically separated from the shield building. This approach warrants an early erection of the shield building and a late installation of piping systems in the containment vessel suppression pool area. Finite element analyses are performed by using ASHSD2 and EASE2 computer codes. The results of the analyses have shown the proposed stress criteria are satisfied. The approach pressented is justified to be a workable system for a new plant design. (orig./HP)

Effects of hydrogen burning and associated engineered safety features on containment building response

International Nuclear Information System (INIS)

Iyer, S.S.; Deem, R.E.

1982-01-01

It is established that large amounts of hydrogen can be generated during degraded core events. The burning of this hydrogen can produce resulting loads which may represent a serious challenge to containment integrity. This paper presents some perspectives on hydrogen behavior during various degraded core events for a large dry containment. The analysis addresses the hydrogen transport and its subsequent diffusion once released to the containment. Since the distribution of hydrogen in the containment depends on the rate of release and various driving forces, the effects from various subsystems (i.e. fan coolers, sprays, heat structures, etc.) are examined to determine the sensitivity of each effect on the overall containment response. The sensitivity of results due to subcompartmentalization of the containment is also examined. Effects from localized hydrogen pocketing and burning will be addressed with emphasis on its relative impact on containment integrity

Numerical modelling of the processes in the WWER-1000 containment building during cold leg LOCA using the CONTEMPT-LT/026 code

International Nuclear Information System (INIS)

Kolev, N.I.; Sybotinov, L.S.

1984-01-01

The CONTEMPT-LT/026 code has been used to produce numerical results for the processes in a WWER-1000 containment building during cold leg LOCA with break at the reactor vessel. The objective of the analysis is to estimate the maximal loads on the containment in case of LOCA. Available design data for the geometry and for the operational characteristics of the low-pressure ECC system and the sprinkler system have been used. Boundary conditions such as mass flow and enthalpies at the breach are given by a RELAP4/MOD6 computation. Hydrogen explosions in the containment are not considered. It is found that in case of normal functioning of the low-pressure ECC system the maximal pressure is 3,26±0,44 bar. In the case of malfunctioning of the low-pressure ECC system, the predicted maximal pressure is 4±0,44 bar, when: a) only 50% of the heat transfer surface of the heat exchanger is effectively used due to pollution; b) the main pipeline of the sprinkler is broken; c) the pipeline to the heat exchanger is partially broken so that the mass flow through the exchanger is only 50% of the nominal; and d) ECC low-pressure ECC system attains its maximal efficiency within 3 min, the predicted maximal pressure is 4±0,44 bar

Comparison of european computer codes relative to the aerosol behavior in PWR containment buildings during severe core damage accidents. (Modelling of steam condensation on the particles)

International Nuclear Information System (INIS)

Bunz, H.; Dunbar, L.H.; Fermandjian, J.; Lhiaubet, G.

1987-11-01

An aerosol code comparison exercise was performed within the framework of the Commission of European Communities (Division of Safety of Nuclear Installations). This exercise, focused on the process of steam condensation onto the aerosols occurring in PWR containment buildings during severe core damage accidents, has allowed to understand the discrepancies between the results obtained. These discrepancies are due, in particular, to whether the curvature effect is modelled or not in the codes

Development of a methodology for defining whole-building energy design targets for commercial buildings: Phase 2, Development concept stage report

Energy Technology Data Exchange (ETDEWEB)

Jones, J.W. (American Society of Heating, Refrigerating and Air-Conditioning Engineers, Inc., Atlanta, GA (USA)); Deringer, J.J. (Deringer Group, Riva, MD (USA)); Hall, J.D. (American Inst. of Architects, Washington, DC (USA)) (comps.)

1990-09-01

The Whole-Building Energy Design Targets project is being conducted for the US Department of Energy (DOE) by the Pacific Northwest Laboratory (PNL). The objective of the project is to develop a flexible methodology for setting energy performance guidelines with which architects, engineers, planners, and owners can assess energy efficiency in commercial building design. This volume, the third in the four-volume report on the Targets project concept stage, contains the minutes of the workshops as well as summaries of the expert's written comments prepared at the close of each workshop. In Section 2, the building energy simulation workshop is summarized. Section 3 provides a summary of the building cost workshop.

Final environmental assessment: TRU waste drum staging building, Technical Area 55, Los Alamos National Laboratory

International Nuclear Information System (INIS)

1996-01-01

Much of the US Department of Energy's (DOE's) research on plutonium metallurgy and plutonium processing is performed at Los Alamos National Laboratory (LANL), in Los Alamos, New Mexico. LANL's main facility for plutonium research is the Plutonium Facility, also referred to as Technical Area 55 (TA-55). The main laboratory building for plutonium work within the Plutonium Facility (TA-55) is the Plutonium Facility Building 4, or PF-4. This Environmental Assessment (EA) analyzes the potential environmental effects that would be expected to occur if DOE were to stage sealed containers of transuranic (TRU) and TRU mixed waste in a support building at the Plutonium Facility (TA-55) that is adjacent to PF-4. At present, the waste containers are staged in the basement of PF-4. The proposed project is to convert an existing support structure (Building 185), a prefabricated metal building on a concrete foundation, and operate it as a temporary staging facility for sealed containers of solid TRU and TRU mixed waste. The TRU and TRU mixed wastes would be contained in sealed 55-gallon drums and standard waste boxes as they await approval to be transported to TA-54. The containers would then be transported to a longer term TRU waste storage area at TA-54. The TRU wastes are generated from plutonium operations carried out in PF-4. The drum staging building would also be used to store and prepare for use new, empty TRU waste containers

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)

Methodology of a PWR containment analysis during a thermal-hydraulic accident

International Nuclear Information System (INIS)

Silva, Dayane F.; Sabundjian, Gaiane; Lima, Ana Cecilia S.

2015-01-01

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)

Alternatives for high-level waste forms, containers, and container processing systems

International Nuclear Information System (INIS)

Crawford, T.W.

1995-01-01

This study evaluates alternatives for high-level waste forms, containers, container processing systems, and onsite interim storage. Glass waste forms considered are cullet, marbles, gems, and monolithic glass. Small and large containers configured with several combinations of overpack confinement and shield casks are evaluated for these waste forms. Onsite interim storage concepts including canister storage building, bore holes, and storage pad were configured with various glass forms and canister alternatives. All favorable options include the monolithic glass production process as the waste form. Of the favorable options the unshielded 4- and 7-canister overpack options have the greatest technical assurance associated with their design concepts due to their process packaging and storage methods. These canisters are 0.68 m and 0.54 m in diameter respectively and 4.57 m tall. Life-cycle costs are not a discriminating factor in most cases, varying typically less than 15 percent

Regression Tree-Based Methodology for Customizing Building Energy Benchmarks to Individual Commercial Buildings

Science.gov (United States)

Kaskhedikar, Apoorva Prakash

According to the U.S. Energy Information Administration, commercial buildings represent about 40% of the United State's energy consumption of which office buildings consume a major portion. Gauging the extent to which an individual building consumes energy in excess of its peers is the first step in initiating energy efficiency improvement. Energy Benchmarking offers initial building energy performance assessment without rigorous evaluation. Energy benchmarking tools based on the Commercial Buildings Energy Consumption Survey (CBECS) database are investigated in this thesis. This study proposes a new benchmarking methodology based on decision trees, where a relationship between the energy use intensities (EUI) and building parameters (continuous and categorical) is developed for different building types. This methodology was applied to medium office and school building types contained in the CBECS database. The Random Forest technique was used to find the most influential parameters that impact building energy use intensities. Subsequently, correlations which were significant were identified between EUIs and CBECS variables. Other than floor area, some of the important variables were number of workers, location, number of PCs and main cooling equipment. The coefficient of variation was used to evaluate the effectiveness of the new model. The customization technique proposed in this thesis was compared with another benchmarking model that is widely used by building owners and designers namely, the ENERGY STAR's Portfolio Manager. This tool relies on the standard Linear Regression methods which is only able to handle continuous variables. The model proposed uses data mining technique and was found to perform slightly better than the Portfolio Manager. The broader impacts of the new benchmarking methodology proposed is that it allows for identifying important categorical variables, and then incorporating them in a local, as against a global, model framework for EUI

Analysis of Gamma Dose Rate Caused by Corrosion Products inside the Containment Building of Yonngwang Nuclear Power Plant Unit 3 During Shutdown Period

Energy Technology Data Exchange (ETDEWEB)

Ha, Wi Ho; Kim, Jae Cheon; Kim, Soon Young; Kim, Jong Kyung [Hanyang Univ., Seoul (Korea, Republic of)

2005-07-01

Occupational radiation exposure(ORE) of nuclear power plant(NPP) workers mainly occurs during the shutdown period. Major radioactive sources are the corrosion products released from the reactor coolant system(RCS). The corrosion products consist of circulating crud and deposited crud. Major radioactive corrosion products, {sup 58}Co and {sup 60}Co, are known to contribute approximately more than 70% of the total ORE. In this study, the corrosion products regarding cobalt were evaluated during the shutdown period, and gamma dose rates caused by them were calculated at the main working area inside the containment building of the Yonggwang NPP Unit 3.

Effect and Removal Mechanisms of 6 Different Washing Agents for Building Wastes Containing Chromium

Directory of Open Access Journals (Sweden)

Wang Xing-run

2012-01-01

Full Text Available With the building wastes contaminated by chromium in Haibei Chemical Plan in China as objects, we studied the contents of total Cr and Cr (VI of different sizes, analyzed the effect of 6 different washing agents, discussed the removal mechanisms of 6 different washing agents for Cr in various forms, and finally selected applicable washing agent. As per the results, particle size had little impact on the contents of total Cr and Cr (VI; after one washing with water, the removal rate of total Cr and Cr (VI was 75% and 78%, respectively, and after the second washing with 6 agents, the removal rate of citric acid was the highest, above 90% for total Cr and above 99% for hexavalent chromium; the pH of building wastes were reduced by citric acid, and under acid condition, hexavalent chromium was reduced to trivalent chromium spontaneously by organic acid, which led to better removal rate of acid soluble Cr and reducible Cr; due to the complexing action, citric acid had best removal rate for oxidizable trivalent chromium. In conclusion, citric acid is the most applicable second washing agent for building wastes.

Establishment of the evaluation method of the tendon effective stress in the containment building and the concrete material nonlinear model(II)

International Nuclear Information System (INIS)

Chung, Chul Hun; Park, Jae Gyun; Kim, Jong Suk; Yun, Yeon Suk; Kim, Se Hun; Chung, Dong Jin

2006-12-01

To elevate the structural integrity of the NPP containment building more rigorously, the effective prestress, which is one of the most affecting elements, needs to be estimated exactly. In the second year study, we evaluated the proposed effective prestress measuring method which uses pressure decreasing technique through experiments. It is possible to improve the effective prestress measuring method by test beam, which is being applied for the investigation of the Nuclear Power Plant in operation. We performed a finite element analysis to evaluate the effect of the prestress loss of the tendon to the behavior of the structure. According to the results, the effect of the prestress loss of the vertical and circumventive tendon to some level in the confinement building was analyzed. Another requirement for te rigorous evaluation of the structural soundness is the fast and exact analysis of structural responses under such extreme loads as earthquakes. To achieve this goal, we need analysis models that can describe nonlinear behavior of each material well. In this second year, based on the analysis results during first year, we propose a guideline for the concrete modeling via ABAQUS, a multi-purpose finite element analysis program, and perform static and dynamic analyses

308 Building deactivation function analysis report

International Nuclear Information System (INIS)

Lund, D.P.

1995-09-01

The document contains the functions, function definitions, function interfaces, function interface definitions, Input Computer Automated Manufacturing Definition (IDEFO) diagrams, and a function hierarchy chart that describes what needs to be performed to deactivate the 308 Building

309 Building deactivation function analysis report

International Nuclear Information System (INIS)

Lund, D.P.

1995-09-01

The document contains the functions, function definitions, function interfaces, function interface definitions, Input Computer Automated Manufacturing Definition (IDEFO) diagrams, and a function hierarchy chart that describe what needs to be performed to deactivate the 309 Building

Mononuclear, trinuclear, and hetero-trinuclear supramolecular complexes containing a new tri-sulfonate ligand and cobalt(II)/copper(II)-(1,10-phenanthroline)2 building blocks

International Nuclear Information System (INIS)

Yu Yunfang; Wei Yongqin; Broer, Ria; Sa Rongjian; Wu Kechen

2008-01-01

Novel mononuclear, trinuclear, and hetero-trinuclear supermolecular complexes, [Co(phen) 2 (H 2 O)(HTST)].2H 2 O (1), [Co 3 (phen) 6 (H 2 O) 2 (TST) 2 ].7H 2 O (2), and [Co 2 Cu(phen) 6 (H 2 O) 2 (TST) 2 ].10H 2 O (3), have been synthesized by the reactions of a new tri-sulfonate ligand (2,4,6-tris(4-sulfophenylamino)-1,3,5-triazine, H 3 TST) with the M 2+ (M=Co, Cu) and the second ligand 1,10-phenanthroline (phen). Complex 1 contains a cis-Co(II)(phen) 2 building block and an HTST as monodentate ligand; complex 2 consists of two TST as bidentate ligands connecting one trans- and two cis-Co(II)(phen) 2 building blocks; complex 3 is formed by replacing the trans-Co(II)(phen) 2 in 2 with a trans-Cu(II)(phen) 2 , which is the first reported hetero-trinuclear supramolecular complex containing both the Co(II)(phen) 2 and Cu(II)(phen) 2 as building blocks. The study shows the flexible multifunctional self-assembly capability of the H 3 TST ligands presenting in these supramolecular complexes through coordinative, H-bonding and even π-π stacking interactions. The photoluminescent optical properties of these complexes are also investigated and discussed as well as the second-order nonlinear optical properties of 1. - Graphical abstract: Novel mononuclear, trinuclear, and hetero-trinuclear supermolecular complexes, [Co(phen) 2 (H 2 O)(HTST)].2H 2 O (1), [Co 3 (phen) 6 (H 2 O) 2 (TST) 2 ].7H 2 O (2), and [Co 2 Cu(phen) 6 (H 2 O) 2 (TST) 2 ].10H 2 O (3), have been synthesized by the reactions of a new tri-sulfonate ligand (2,4,6-tris(4-sulfophenylamino)-1,3,5-triazine, H 3 TST) with the M 2+ (M=Co, Cu) and the second ligand 1,10-phenanthroline (phen). The study shows the flexible multifunctional self-assembly capability of H 3 TST ligand presenting in these supramolecular complexes

19 CFR 10.462 - Packing materials and containers for shipment.

Science.gov (United States)

2010-04-01

... Free Trade Agreement Rules of Origin § 10.462 Packing materials and containers for shipment. (a... disregarded in determining the regional value content of a good imported into the United States. Accordingly, in applying either the build-down or build-up method for determining the regional value content of...

Polychlorinated biphenyl sources, environmental levels, and exposures in school buildings

Science.gov (United States)

Background: Building materials and components containing polychlorinated biphenyls (PCBs) were used in some U.S. school buildings until the late 1970s and may be present today. There is limited information on source factors and occupant exposures. Methods: Analysis of PCBs in mat...

Study of radon diffusion coefficient for technologically enhanced building construction materials

International Nuclear Information System (INIS)

Narula, A.K.; Goyal, S.K.; Chauhan, R.P.; Chakarvarti, S.K.

2012-01-01

Most building materials of natural origin contain small amounts of Naturally Occurring Radioactive Materials (NORMs), mainly radionuclides from the 226 Ra and 232 Th decay chains and 40 K. The origin of these materials is the earths crust, but they find their way into building materials, air, water, food and the human body itself. The worldwide average indoor effective dose due to gamma rays from building materials is estimated to be about 0.4 mSv per year. In many parts of the world, building materials containing radioactive materials have been used for generations. As individuals spend more than 80% of their time indoors, the internal and external radiation exposure from building materials creates prolonged exposure situations. The internal (inhalation) radiation exposure is due to 222 Rn and their short lived decay products exhaled from building materials into the room air. The average activity concentrations of 226 Ra, 232 Th and 40 K in the earths crust are 35, 30 and 400 Bq/kg respectively. However, elevated levels of natural radionuclides causing annual doses of several mSv were identified in some regions around the world. Recycled industrial by-products containing Technologically Phosphogypsum, a by-product in the production of phosphate fertilizers is used as building material, and red mud, a waste from primary aluminum production, is used in bricks, ceramics and tiles. The increased tendency of the building material industry to use industrial wastes as substitutes for natural products having relatively high activity concentration of NORMs and the increased exposure caused by them were the driving forces for undertaking the present investigation. (author)

The Radon Book. Preventive measures in new buildings

International Nuclear Information System (INIS)

Clavensjoe, Bertil; Aakerblom, Gustav

2004-01-01

This book describes in text and picture how one can prevent that the radon concentrations in new buildings become to high. The book's centre of gravity lies on how to build in order to prevent that radon gas from the ground enters the building. The book contains extensive information about ground radon and how to examine the ground before constructing a new building. Release of radon from ground water and construction material is treated, as well as technology for measurement of radon and gamma radiation. The book presents current threshold values/recommended values for radon and the authorities' regulations and recommendations. The book is directed to persons who professionally need knowledge about radon and how to prevent that radon is accumulated in new buildings

Passive cooling containment study

International Nuclear Information System (INIS)

Shin, J.J.; Iotti, R.C.; Wright, R.F.

1993-01-01

Pressure and temperature transients of nuclear reactor containment following postulated loss of coolant accident with a coincident station blackout due to total loss of all alternating current power are studied analytically and experimentally for the full scale NPR (New Production Reactor). All the reactor and containment cooling under this condition would rely on the passive cooling system which removes reactor decay heat and provides emergency core and containment cooling. Containment passive cooling for this study takes place in the annulus between containment steel shell and concrete shield building by natural convection air flow and thermal radiation. Various heat transfer coefficients inside annular air space were investigated by running the modified CONTEMPT code CONTEMPT-NPR. In order to verify proper heat transfer coefficient, temperature, heat flux, and velocity profiles were measured inside annular air space of the test facility which is a 24 foot (7.3m) high, steam heated inner cylinder of three foot (.91m) diameter and five and half foot (1.7m) diameter outer cylinder. Comparison of CONTEMPT-NPR and WGOTHIC was done for reduced scale NPR

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

International Nuclear Information System (INIS)

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

2014-01-01

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)

Sargent and Lundy containment tests revisited

International Nuclear Information System (INIS)

Henry, Robert E.; Hammersley, Robert J.

2005-01-01

The pressurization experiments performed in the intermediate scale Sargent and Lundy containment test facility provide numerous insights into the dominant heat and mass transfer processes under design basis accident conditions similar to a large break Loss of Coolant Accident (LOCA). These experiments were the first integral tests to examine the containment response to a dynamic blowdown from the Reactor Coolant System (RCS). Measurements included the blowdown rate of the simulated Reactor Pressure Vessel (RPV), the pressure in containment as well as the containment temperatures in the top and bottom of the containment vessel. Furthermore, various experiments were performed with the blowdown location changed from the vessel bottom to the lower third of the vessel, the upper third of the vessel and near the top of the RPV to examine the influence of different types of break elevations, i.e. different characterizations of the exhausting steam-water mixture. Perhaps the most insightful set of measurements from these experiments were those that varied the cold water mass initially resident in the bottom of the simulated containment vessel. The role of this water as a function of its initial mass and the break location showed substantial influence of this water if the blowdown location provided sufficient energy to disperse this cold water into the containment building atmosphere. This is demonstrated in Figure 1 taken from Kolflat, 1960. All of these are relevant to an understanding of the dominant physical processes for this type of postulated accident condition. As such, it is important that all of these insights are retained and used in models for the containment building thermal-hydraulic response under accident conditions. Reference: Kolflat, A., 1960, 'Resulting of 1959 Nuclear Power Plant Containment Test', Sargent and Lundy Report SL-1800; Kolflat, A. and Chittenden, W. A., 1957, 'A New Approach to the Design of Containment Shells for Atomic Power Plants

Space-sharing Strategy for Building Dynamic Container Yard Storage Considering Uncertainty on Number of Incoming Containers

Directory of Open Access Journals (Sweden)

Siti Nurminarsih

2017-12-01

Full Text Available The implementation of AEC (Asian Economic Community leads to demand increase at ports in Indonesia. This increasing demand is followed by operational efficiency at the port as well. In fact, ports in Indonesia have an average dwell time for 5 days. One of the causes of this long dwell time is container transfer inefficiencies during loading process. In this research, we will focus in yard management and increasing land utilization. To increase the land utilization, we develop the space-sharing concept to reduce the initial space needed for a given workload. Since the ships arrivals are also varying, this concept will be possible. We develop the concept by adding uncertainty on number of incoming containers at operational level as the determining factor in planning a shared yard area. We propose a simulation approach to evaluate strategies in making yard template.

GEM Building Taxonomy (Version 2.0)

Science.gov (United States)

Brzev, S.; Scawthorn, C.; Charleson, A.W.; Allen, L.; Greene, M.; Jaiswal, Kishor; Silva, V.

2013-01-01

This report documents the development and applications of the Building Taxonomy for the Global Earthquake Model (GEM). The purpose of the GEM Building Taxonomy is to describe and classify buildings in a uniform manner as a key step towards assessing their seismic risk, Criteria for development of the GEM Building Taxonomy were that the Taxonomy be relevant to seismic performance of different construction types; be comprehensive yet simple; be collapsible; adhere to principles that are familiar to the range of users; and ultimately be extensible to non-buildings and other hazards. The taxonomy was developed in conjunction with other GEM researchers and builds on the knowledge base from other taxonomies, including the EERI and IAEE World Housing Encyclopedia, PAGER-STR, and HAZUS. The taxonomy is organized as a series of expandable tables, which contain information pertaining to various building attributes. Each attribute describes a specific characteristic of an individual building or a class of buildings that could potentially affect their seismic performance. The following 13 attributes have been included in the GEM Building Taxonomy Version 2.0 (v2.0): 1.) direction, 2.)material of the lateral load-resisting system, 3.) lateral load-resisting system, 4.) height, 5.) date of construction of retrofit, 6.) occupancy, 7.) building position within a block, 8.) shape of the building plan, 9.) structural irregularity, 10.) exterior walls, 11.) roof, 12.) floor, 13.) foundation system. The report illustrates the pratical use of the GEM Building Taxonomy by discussing example case studies, in which the building-specific characteristics are mapped directly using GEM taxonomic attributes and the corresponding taxonomic string is constructed for that building, with "/" slash marks separating attributes. For example, for the building shown to the right, the GEM Taxonomy string is: DX1/MUR+CLBRS+MOCL2/LWAL3/

Modular assembly of metal-organic super-containers incorporating calixarenes

Science.gov (United States)

Wang, Zhenqiang; Dai, Feng-Rong

2018-01-16

A new strategy to design container molecules is presented. Sulfonylcalix[4]arenes, which are synthetic macrocyclic containers, are used as building blocks that are combined with various metal ions and tricarboxylate ligands to construct metal-organic `super-containers` (MOSCs). These MOSCs possess both endo and exo cavities and thus mimic the structure of viruses. The synthesis of MOSCs is highly modular, robust, and predictable.

Dynamic analysis of a reactor building on alluvial soil

International Nuclear Information System (INIS)

Arya, A.S.; Chandrasekaran, A.R.; Paul, D.K.

1977-01-01

The reactor building consists of reinforced concrete internal framed structure enclosed in double containment shells of prestressed and reinforced concrete all resting on a common massive raft. The external cylindrical shell is capped by a spherical dome while the internal shell carries a cellular grid slab. The building is partially buried under ground. The soil consists of alluvial going to 1000 m depth. The site lies in a moderate seismic zone. The paper presents the dynamic analysis of the building including soil-structure interaction. The mathematical model consists of four parallel, suitably interconnected structures, namely inner containment, outer containment, internal frame and the calandria vault. Each one of the parallel structures consists of lumped-mass beam elements. The soil below the raft and on the sides of outer containment shell is represented by elastic springs in both horizontal and vertical directions. The various assumptions required to be made in developing the mathematical model are briefly discussed in the paper. Transfer matrix technique has been used to determine the frequencies and mode shapes. The deformations due to bending, shear and effect of the rotary inertia have been included. Various alternatives of laterally interconnecting the internals and the shells have been examined and the best alternative from earthquake considerations has been obtained. In the study, the effect of internal structure flexibility and Calandria vault flexibility on the whole building have been studied. The resulting base raft motion and the structural timewise response of all floors have been determined for the design basis (safe shutdown) earthquake by mode superposition

Differential pressures on building walls during tornados

International Nuclear Information System (INIS)

Yeh, G.C.K.

1975-01-01

In the United States, containment structures and some auxiliary structures (control building, auxiliary building, spent fuel building, etc.) in nuclear power plants are required to be designed to withstand the effects of the design basis tornado. In addition to velocity pressures and missile impact a tornado also gives rise to a rapid change in atmospheric pressure, which can, in cases of closed or partially vented structures, produce direct differential pressure loading. In this paper a digital computer program is described which applies a tornado-induced, time-dependent atmospheric pressure change to a building and calculates the differential pressure histories across the interior and exterior walls of the building. Laws for quasi-steady, one-dimensional motion of an ideal compressible gas are used to calculate the pressures due to the flow of air through ports, doors and windows in the building. Numerical examples show that for each assumed atmospheric pressure change history a vent area to compartment volume ratio may be specified as the criterion for a building to be considered fully vented. (orig.) [de

Building of nuclear power plant

International Nuclear Information System (INIS)

Saito, Takashi.

1997-01-01

A first nuclear plant and a second nuclear power plant are disposed in adjacent with each other in a building for a nuclear reactor. A reactor container is disposed in each of the plants, and each reactor container is surrounded by a second containing facility. A repairing chamber capable of communicating with the secondary containing facilities for both of the secondary containing facilities is disposed being in contact with the second containing facility of each plant for repairing control rod driving mechanisms or reactor incorporated-type recycling pumps. Namely, the repairing chamber is in adjacent with the reactor containers of both plants, and situated between both of the plants as a repairing chamber to be used in common for both plants. Air tight inlet/exit doors are formed to the inlets/exits of both plants of the repairing chamber. Space for the repairing chamber can be reduced to about one half compared with a case where the repairing chamber is formed independently on each plant. (I.N.)

Elimination of the containment spray additive for Vogtle electric generating plant

International Nuclear Information System (INIS)

Lowery, K.G.

1995-01-01

This paper discusses the details for elimination of the spray additive portion of the containment spray system (CSS) in a pressurized water reactor (PWR) power plant. A particular emphasis is placed on nuclear power plant design associated with operation and maintenance (O and M), cost control strategies, and reliability initiatives. The CSS is an engineered safeguard system that functions to reduce reactor containment building pressure and temperature and the quantity of airborne fission products in the containment atmosphere subsequent to a loss-of-coolant accident (LOCA). Pressure and temperature reduction is accomplished by spraying water into the containment building atmosphere. Sodium hydroxide (NaOH) is added to the containment spray water to increase its pH. Results of recent studies on the behavior of fission products in the post-LOCA containment environment have demonstrated that the iodine removal can be effectively performed by boric acid sprays without the NaOH additive and by deposition on the internal surfaces of the containment building. Thus, the NaOH, the SAT, the chemical injection system (eductor) which delivers the additive to the spray system, and the related testing and maintenance required by the Technical Specifications can be eliminated. The NaOH will be replaced by TSP in baskets in the containment sump area. The TSP is needed for pH control during the recirculation phase following a LOCA. The deletion of the requirement for the SAT will result in a reduction of regulatory requirements in that the level of surveillance will be reduced. The safety analysis acceptance limits will still be met

Bats roosting in public buildings: A preliminary assessment from ...

African Journals Online (AJOL)

Madagascar has many synanthropic bat species but relatively little is known about how people interact with them. A preliminary assessment on the presence of bats in buildings and their interactions with people was conducted in the eastern town of Moramanga. Fifty of the 156 buildings were reported to contain active bat ...

Building integrated PV for commercial and institutional structures, a sourcebook for architects

Energy Technology Data Exchange (ETDEWEB)

Eiffert, P.; Kiss, G.

2000-02-14

This sourcebook on building-integrated photovoltaics (BIPV) is intended for architects and designers interested in learning more about today's sustainable solar buildings. The booklet includes 16 design briefs describing actual structures; they illustrate how electricity-generating BIPV products (such as special roofing systems, vertical-wall systems, skylights, and awnings, all of which contain PV cells, modules, and films) can be integrated successfully into many different kinds of buildings. It also contains basic information about BIPV technologies, an overview of US product development activities and development programs, descriptions of major software design tools, and a bibliography.

Integrated analysis of core debris interactions and their effects on containment integrity using the CONTAIN computer code

International Nuclear Information System (INIS)

Carroll, D.E.; Bergeron, K.D.; Williams, D.C.; Tills, J.L.; Valdez, G.D.

1987-01-01

The CONTAIN computer code includes a versatile system of phenomenological models for analyzing the physical, chemical and radiological conditions inside the containment building during severe reactor accidents. Important contributors to these conditions are the interactions which may occur between released corium and cavity concrete. The phenomena associated with interactions between ejected corium debris and the containment atmosphere (Direct Containment Heating or DCH) also pose a potential threat to containment integrity. In this paper, we describe recent enhancements of the CONTAIN code which allow an integrated analysis of these effects in the presence of other mitigating or aggravating physical processes. In particular, the recent inclusion of the CORCON and VANESA models is described and a calculation example presented. With this capability CONTAIN can model core-concrete interactions occurring simultaneously in multiple compartments and can couple the aerosols thereby generated to the mechanistic description of all atmospheric aerosol components. Also discussed are some recent results of modeling the phenomena involved in Direct Containment Heating. (orig.)

Effect of Nonlinear Hardening of Lead Rubber Bearing on Long Term Behavior of Base Isolated Containment Building

International Nuclear Information System (INIS)

Park, Junhee; Choun, Young-Sun; Kim, Min-Kyu

2015-01-01

The rubber material used in laminated rubber bearings is the hyper elastic material whose stress-strain relationship can be defined as nonlinearly elastic. From the previous research, it was presented that the rubber hardness and stiffness was increased by the aging of LRB. The mechanical properties of LRB changed by aging can directly affect a nonlinear hardening behavior. Therefore it is needed to consider the nonlinear hardening effect for exactly evaluating the seismic safety of base isolated structure during the life time. In this study, the seismic response analysis of base isolated containment building was performed by using the bilinear model and the hardening model to identify the effect of structural response on the nonlinear hardening behavior of isolator. Moreover the floor response spectrum of base isolated structure considering the aging was analyzed by according to the analysis model of LRB.. The hardening behavior of lead rubber bearing occurs at high strain. Therefore it is reasonable to assume that the hysteretic model of LRB is the nonlinear hardening model for exactly evaluating the seismic response of base isolated structure. The nonlinear analysis of base isolated containment was performed by using the nonlinear hardening variables which was resulted from the test results and finite element analysis. From the analysis results, it was represented that the FRS was higher about 40% with nonlinear hardening model than with the bilinear model. Therefore the seismic response of base isolated structure with bilinear model can be underestimated than the real response. It is desired that the nonlinear hardening model of LRB is applied for the seismic risk evaluation requiring the ultimate state of LRB

Dynamic analysis of steel-concrete structure of TVO power plant containment building

International Nuclear Information System (INIS)

Hakala, M.; Karjunen, T.

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.)

Testing of a steel containment vessel model

International Nuclear Information System (INIS)

Luk, V.K.; Hessheimer, M.F.; Matsumoto, T.; Komine, K.; Costello, J.F.

1997-01-01

A mixed-scale containment vessel model, with 1:10 in containment geometry and 1:4 in shell thickness, was fabricated to represent an improved, boiling water reactor (BWR) Mark II containment vessel. A contact structure, installed over the model and separated at a nominally uniform distance from it, provided a simplified representation of a reactor shield building in the actual plant. This paper describes the pretest preparations and the conduct of the high pressure test of the model performed on December 11-12, 1996. 4 refs., 2 figs

1998 ACEEE summer study on energy efficiency in buildings: Proceedings

Energy Technology Data Exchange (ETDEWEB)

NONE

1998-07-01

These proceedings are contained in the following 10 volumes: (1) Residential buildings--Technologies, design and performance analysis; (2) Residential buildings--Program design, implementation and evaluation; (3) Commercial buildings--Technologies, design and performance analysis; (4) Commercial buildings--Program design, implementation and evaluation; (5) International collaborations and global market issues; (6) Deregulation of the utility industry and role of energy services companies; (7) Market transformation; (8) Information technologies, consumer behavior, and non-energy benefits; (9) Sustainable development, climate change, energy planning, and policy; and (10) Building industry trends. Papers have been processed separately for inclusion on the data base.

Throughput maximization of parcel sorter systems by scheduling inbound containers

NARCIS (Netherlands)

Haneyah, S.W.A.; Schutten, Johannes M.J.; Fikse, K.; Clausen, Uwe; ten Hompel, Michael; Meier, J. Fabian

2013-01-01

This paper addresses the inbound container scheduling problem for automated sorter systems in express parcel sorting. The purpose is to analyze which container scheduling approaches maximize the throughput of sorter systems. We build on existing literature, particularly on the dynamic load balancing

Pressure suppression device for nuclear reactor building

International Nuclear Information System (INIS)

Ikegame, Noboru.

1992-01-01

In a nuclear reactor building, there are disposed cooling coils connected to an air supply duct at the outside of the building, an air supply blower, an air supply duct having the top end opened, an exhaustion duct having the top end opened and a bypassing pipeline interposed between the exhaustion duct and the air supply duct on the side of the inlet of the cooling coils. In the reactor building, when a radioactive material leakage accident should occur, an isolation valve is closed to isolate the building from the outside. Further, bypassing isolation valve is opened to form a closed cooling circuit by the cooling coils, the air supply blower and the air supply duct, the exhaustion duct and the bypassing pipeline in the reactor building. With such a constitution, since air as the atmosphere in the building is circulated through the closed cooling circuit and cooled by the cooling coils, the temperature is not elevated. Accordingly, since the pressure elevation of the atmosphere in the building is suppressed, the atmosphere containing radioactive materials do not flow out of the building. (I.N.)

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

International Nuclear Information System (INIS)

Jeon, Se-Jin; Jin, Byeong-Moo

2016-01-01

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.

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.

NPR and ANSI Containment Study Using Passive Cooling Techniques

International Nuclear Information System (INIS)

Shin, J. J.; Iotti, R. C.; Wright, R. F.

1993-01-01

Passive containment cooling study of NPR (New Production Reactor) and ANSI (Advanced Neutron Source) following postulated loss of coolant accident with a coincident station blackout due to total loss of all alternating current power are studied analytically and experimentally. All the reactor and containment cooling under this condition would rely on the passive cooling system which removes reactor decay heat and provides emergency core and containment cooling. Containment passive emergency core and containment cooling. Containment passive cooling for this study takes place in the annulus between containment steel shell and concrete shield building by natural convection air flow and concrete shield building by natural convection air flow and thermal radiation. Various heat transfer coefficients inside annular air space were investigated by running the modified Contempt code Contempt-Npr. In order to verify proper heat transfer coefficient, temperature, heat flux and velocity profiles were measured inside annular air space of the test facility which is a 24 foot (7.3m) high, steam heated inner cylinder of three foot (.91m) diameter and five and halt foot (1.7m) diameter outer cylinder. Comparison of Contempt-Npr and WGOTHIC was done for reduced scale Npr. It is concluded that Npr and ANSI containments can be passively cooled with air alone without extended cooling surfaces or passive water spray

Building Maintenance. Student Learning Guide.

Science.gov (United States)

Palm Beach County Board of Public Instruction, West Palm Beach, FL.

This student learning guide contains one module for completing a course in building maintenance. It is designed especially for use in secondary schools in Palm Beach County, Florida. The module covers one task, and consists of a purpose, performance objective, enabling objectives, learning activities keyed to resources, information sheets, student…

Seismic evaluation of the LLNL plutonium facility (Building 332)

International Nuclear Information System (INIS)

Hall, W.J.; Sozen, M.A.

1982-03-01

The expected performance of the Lawrence Livermore National Laboratory (LLNL) Plutonium Facility (Building 332) subjected to earthquake ground motion has been evaluated. Anticipated behavior of the building, glove boxes, ventilation system and other systems critical for containment of plutonium is described for three severe postulated earthquake excitations. Based upon this evaluation, some damage to the building, glove boxes and ventilation system would be expected but no collapse of any structure is anticipated as a result of the postulated earthquake ground motions

Structural Integrity Assessment of Reactor Containment Subjected to Aircraft Crash

International Nuclear Information System (INIS)

Kim, Junyong; Chang, Yoonsuk

2013-01-01

When an accident occurs at the NPP, containment building which acts as the last barrier should be assessed and analyzed structural integrity by internal loading or external loading. On many occasions that can occur in the containment internal such as LOCA(Loss Of Coolant Accident) are already reflected to design. Likewise, there are several kinds of accidents that may occur from the outside of containment such as earthquakes, hurricanes and strong wind. However, aircraft crash that at outside of containment is not reflected yet in domestic because NPP sites have been selected based on the probabilistic method. After intentional aircraft crash such as World Trade Center and Pentagon accident in US, social awareness for safety of infrastructure like NPP was raised world widely and it is time for assessment of aircraft crash in domestic. The object of this paper is assessment of reactor containment subjected to aircraft crash by FEM(Finite Element Method). In this paper, assessment of structural integrity of containment building subjected to certain aircraft crash was carried out. Verification of structure integrity of containment by intentional severe accident. Maximum stress 61.21MPa of horizontal shell crash does not penetrate containment. Research for more realistic results needed by steel reinforced concrete model

Numerical Analysis of a Passive Containment Filtered Venting System

International Nuclear Information System (INIS)

Kim, Taejoon; Ha, Huiun; Heo, Sun

2014-01-01

The passive Containment Filtered Venting system (CFVS) does not have principally any kind of isolation valves or filtering devices which need periodic maintenance. In this study, the hydro-thermal analysis is presented to investigate the existence of flow instability in the passive CFVS and its performance under the pressure change of APR+ containment building with LB-LOCA M/E data. The Passive Containment Filtered Venting System was suggested as a part in i-Power development project and the operation mechanism was investigated by numerical modeling and simulation using GOTHIC8.0 system code. There are four Phases for consideration to investigate the pressurization of the containment building, loss of hydrostatic head in the pipe line of CFVS, opening of pipe line and gas ejection to the coolant tank, and the head recovery inside the pipe as the containment gas exhausted. The simulation results show that gas generation rate determine the timing of head recovery in the CFVS pipe line and that the equipment of various devices inducing pressure loss at the pipe can give the capacity of Phase control of the passive CFVS operation

Large N saddle formulation of quadratic building block theories

International Nuclear Information System (INIS)

Halpern, M.B.

1980-01-01

I develop a large N saddle point formulation for the broad class of 'theories of quadratic building blocks'. Such theories are those on which the sums over internal indices are contained in quadratic building blocks, e.g. PHI 2 = Σsup(N)sub(a-1)PHi sup(a)sup(a). The formulation applies as well to fermions, derivative coupling and non-polynomial interactions. In a related development, closed Schwinger-Dyson equations for Green functions of the building blocks are derived and solved for large N. (orig.)

Enhancement of the basic seismic assessment of the Los Alamos National Laboratory facilities and buildings

International Nuclear Information System (INIS)

Fritz-de la Orta, G.O.

1995-01-01

This paper presents the results of a comparison of values obtained for the seismic security of 479 buildings and facilities at Los Alamos National Laboratory following the methodology adapted from Dr. Otto Frit's original System, and the requirements contained both in FEMA-154 ''Rapid Visual Screening of Buildings for Potential Hazards: A Handbook'' and FEMA-187 ''NEHRP Handbook for the Seismic Evaluation of Existing Buildings.'' These comparisons were made from five buildings chosen randomly illustrating a wide variety of construction types and building configurations. Each building is divided into sectors, defined as portions of it that are attached additions to the original building, or portions separated by an expansion joint between the structural systems. The five buildings studied contain a total of sixteen sectors. The paper is divided into the following sections: Introduction; Basic Concepts of the LANL Methodology; Basic Concepts of FEMA-178; Highlights of the Comparison; Comments on the Results; and Final Words

Life management for a non replaceable structure: the reactor building

International Nuclear Information System (INIS)

Torres, V.; Francia, L.

1998-01-01

Phase 1 of UNESA N.P.P. Lifetime Management Project identified and ranked important components, relative to plant life management. The list showed the Reactor Containment Structure in the third position, and thirteen concrete structures were among the list top twenty. Since the Reactor Containment Building, together with the Reactor Vessel, is the only non-replaceable plant component, and has a big impact on the plant technical life, there is an increasing interest on understanding its behavior to maintain structural integrity. This paper presents: a) IAEA (International Atomic Energy Agency) Coordinated Research Program experiences and studies. Under this Program, international experts address the most frequent degradation mechanisms affecting the containment building. b) IAEA Aging Management Program adapted to our plants. The paper addresses the aging mechanisms affecting the concrete structures, reinforcing steel and prestress systems as well as the aging management programs and the mitigation and control methods. Finally, this paper presents a new module called STRUCTURES, included in phase 2 of the above mentioned project, which will monitor and document the different aging mechanisms and management programs described in item b) regarding the Reactor Containment Building (concrete liner, post stressing system, anchor elements). This module will also support the Maintenance Rule related practices. (Author)

Concrete containment integrity program at EPRI

International Nuclear Information System (INIS)

Winkleblack, R.K.; Tang, Y.K.

1984-01-01

Many in the nuclear power plant business believe that the catastrophic failure mode for reactor containment structures is unrealistic. One of the goals of the EPRI containment integrity program is to demonstrate that this is true. The objective of the program is to provide the utility industry with an experimental data base and a test-validated analytical method for realistically evaluating the actual over-pressure capability of concrete containment buildings and to predict leakage behavior if higher pressures were to occur. The ultimate goal of this research effort is to characterize the containment leakage mode and rate as a function of internal pressure and time so that the risk can be realistically assessed for hypothetical degraded core accidents. Progress in the first and second phases of the three-phase analytical and testing efforts is discussed

Investigating the presence of hazardous materials in buildings

International Nuclear Information System (INIS)

Gustitus, D.A.; Blaisdell, P.M.

1996-01-01

Environmental hazards in buildings can be found in the air, on exposed surfaces, or hidden in roofs, walls, and systems. They can exist in buildings in solid, liquid, and gaseous states. A sound methodology for investigating the presence of environmental hazards in buildings should include several components. The first step in planning an investigation of environmental hazards in buildings is to ascertain why the investigation is to be performed. Research should be performed to review available documentation on the building. Next, a visual inspection of the building should be performed to identify and document existing conditions, and all suspect materials containing environmental hazards. Lastly, samples of suspect materials should be collected for testing. It is important to sample appropriate materials, based on the information obtained during the previous steps of the investigation. It is also important to collect the samples using standard procedures. Pollutants of concern include asbestos, lead, PCBs, and radon

Operation and maintenance of the technical installations in buildings

DEFF Research Database (Denmark)

Nielsen, O.(red.)

The report contains twelve papers from a seminar on operation and maintenance, held at the Danish Building Research Institute in October 1976. The papers deal, among other things, with dimensioning and balancing of pipesystems, design of ventilating systems for adequate operation and maintenance,......, cost and quality in maintenance, maintenance service companies, as well as organization and training for building services maintenance....

Self-Contained Cross-Cutting Pipeline Software Architecture

OpenAIRE

Patwardhan, Amol; Patwardhan, Rahul; Vartak, Sumalini

2016-01-01

Layered software architecture contains several intra-layer and inter-layer dependencies. Each layer depends on shared components making it difficult to release a code change, bug fix or feature without exhaustive testing and having to build the entire software code base. This paper proposed self-contained, cross-cutting pipeline architecture (SCPA) that is independent of existing layers. We chose 2 open source projects and 3 internal intern projects that used n-tier architecture and applied t...

Determination of the NPP Cernavoda reactor building seismic response

International Nuclear Information System (INIS)

Krutzik, N.J.; Rotaru, I.; Bobei, M.; Mingiuc, C.; Serban, V.

1997-01-01

Seismic input for systems and equipment installed in buildings depends on: - the seismic movement in free field on site; - the building movement in the soil; - the building deflection. The percentage of the 3 movements for the system and equipment input, depends on the position of the systems and equipment inside the building as well on the type of the foundation soil. The type of the foundation soil is important because if it is stiff it transfers a lot of energy to the building, energy which amplify the movement of the building on the top. If the foundation soil is soft, it accommodates the overall movement of the building in the soil, amplifying the movement to lower levels and the building response is attenuated if a resonance phenomenon between the whole building movement and the seismic excitation does not exist. This input is given with the design floor response spectra (FRS), in the logarithmic scale and seismic anchor movement (SAM). The design floor response spectra for NPP Cernavoda U1 Nuclear Building were determined in several stages starting with simple models (STICK type) without twisting movement and ending with detailed 3-dimensional models. From the point of view of dynamic behavior, the Reactor Building can be considered to be made up of 4 sub-structures: the containment building, internal structures containing separate elements such as the reactor vault, the fuel transfer structure and itself. Each sub-structure has its own movement (some of the structures present also some local effects) which combines with the overall movement of the building in the soil and the seismic excitation produce the total movement so that the response spectrum for each point of the sub-structure is specific. One should note that for structures which also show the twisting effect, the selection of the points on the floor, for the determination on the response spectra, is an engineering decision so that the response should be relevant for the equipment installed on the

An Assessment for A Filtered Containment Venting Strategy Using Decision Tree Models

International Nuclear Information System (INIS)

Shin, Hoyoung; Jae, Moosung

2016-01-01

In this study, a probabilistic assessment of the severe accident management strategy through a filtered containment venting system was performed by using decision tree models. In Korea, the filtered containment venting system has been installed for the first time in Wolsong unit 1 as a part of Fukushima follow-up steps, and it is planned to be applied gradually for all the remaining reactors. Filtered containment venting system, one of severe accident countermeasures, prevents a gradual pressurization of the containment building exhausting noncondensable gas and vapor to the outside of the containment building. In this study, a probabilistic assessment of the filtered containment venting strategy, one of the severe accident management strategies, was performed by using decision tree models. Containment failure frequencies of each decision were evaluated by the developed decision tree model. The optimum accident management strategies were evaluated by comparing the results. Various strategies in severe accident management guidelines (SAMG) could be improved by utilizing the methodology in this study and the offsite risk analysis methodology

An Assessment for A Filtered Containment Venting Strategy Using Decision Tree Models

Energy Technology Data Exchange (ETDEWEB)

Shin, Hoyoung; Jae, Moosung [Hanyang University, Seoul (Korea, Republic of)

2016-10-15

In this study, a probabilistic assessment of the severe accident management strategy through a filtered containment venting system was performed by using decision tree models. In Korea, the filtered containment venting system has been installed for the first time in Wolsong unit 1 as a part of Fukushima follow-up steps, and it is planned to be applied gradually for all the remaining reactors. Filtered containment venting system, one of severe accident countermeasures, prevents a gradual pressurization of the containment building exhausting noncondensable gas and vapor to the outside of the containment building. In this study, a probabilistic assessment of the filtered containment venting strategy, one of the severe accident management strategies, was performed by using decision tree models. Containment failure frequencies of each decision were evaluated by the developed decision tree model. The optimum accident management strategies were evaluated by comparing the results. Various strategies in severe accident management guidelines (SAMG) could be improved by utilizing the methodology in this study and the offsite risk analysis methodology.

Structural acceptance criteria Remote Handling Building Tritium Extraction Facility

Energy Technology Data Exchange (ETDEWEB)

Mertz, G.

1999-12-16

This structural acceptance criteria contains the requirements for the structural analysis and design of the Remote Handling Building (RHB) in the Tritium Extraction Facility (TEF). The purpose of this acceptance criteria is to identify the specific criteria and methods that will ensure a structurally robust building that will safely perform its intended function and comply with the applicable Department of Energy (DOE) structural requirements.

Structural acceptance criteria Remote Handling Building Tritium Extraction Facility

International Nuclear Information System (INIS)

Mertz, G.

1999-01-01

This structural acceptance criteria contains the requirements for the structural analysis and design of the Remote Handling Building (RHB) in the Tritium Extraction Facility (TEF). The purpose of this acceptance criteria is to identify the specific criteria and methods that will ensure a structurally robust building that will safely perform its intended function and comply with the applicable Department of Energy (DOE) structural requirements

2nd International Conference on Construction and Building Research

CERN Document Server

Fernández-Plazaola, Igor; Hidalgo-Delgado, Francisco; Martínez-Valenzuela, María; Medina-Ramón, Francisco; Oliver-Faubel, Inmaculada; Rodríguez-Abad, Isabel; Salandin, Andrea; Sánchez-Grandia, Rafael; Tort-Ausina, Isabel; Construction and Building Research

2014-01-01

Many areas of knowledge converge in the building industry and therefore research in this field necessarily involves an interdisciplinary approach. Effective research requires strong relations between a broad variety of scientific and technological domains and more conventional construction or craft processes, while also considering advanced management processes, where all the main actors permanently interact. This publication takes an interdisciplinary approach grouping various studies on the building industry chosen from among the works presented for the 2nd International Conference on Construction and Building Research. The papers examine aspects of materials and building systems; construction technology; energy and sustainability; construction management; heritage, refurbishment and conservation. The information contained within these pages may be of interest to researchers and practitioners in construction and building activities from the academic sphere, as well as public and private sectors.

Build an Inexpensive Wind Tunnel to Test CO2 Cars

Science.gov (United States)

McCormick, Kevin

2012-01-01

As part of the technology education curriculum, the author's eighth-grade students design, build, test, and race CO2 vehicles. To help them in refining their designs, they use a wind tunnel to test for aerodynamic drag. In this article, the author describes how to build a wind tunnel using inexpensive, readily available materials. (Contains 1…

The Benefits of Incorporating Shipping Containers into the Climate Change Adaption Plans at NASA Wallops Flight Facility

Science.gov (United States)

Hamilton, Carl Kenneth Gonzaga

2017-01-01

The National Aeronautics and Space Administration has several centers and facilities located near the coast that are undoubtedly susceptible to climate change. One of those facilities is Wallops Flight Facility on the Eastern Shore of Virginia which is separated into three areas: Main Base, Mainland, and the Island. Wallops Island has numerous buildings and assets that are vulnerable to flood inundation, intense storms, and storm surge. The shoreline of Wallops Island is prone to beach erosion and is slated for another beach replenishment project in 2019. In addition, current climate projections for NASAs centers and facilities, conducted by the Climate Adaptation Science Investigators, warn of inevitable increases in annual temperature, precipitation, sea level rise, and extreme events such as heat waves. The aforementioned vulnerabilities Wallops Island faces in addition to the projections of future climate change reveal an urgency for NASA to adjust how new buildings at its centers and facilities near the coast are built to adapt to the inevitable effects of climate change. Although the agency has made strides to mitigate the effects of climate change by incorporating L.E.E.D. into new buildings that produce less greenhouse gas, the strides for the agency to institute clear climate adaptation policies for the buildings at its centers and facilities near the coast seem to lag behind. As NASA continues to formulate formidable climate change adaptation plans for its centers and facilities, an architectural trend that should be examined for its potential to replace several old buildings at Wallops Island is shipping containers buildings. Shipping containers or Intermodal Steel Building Units offer an array of benefits such as strength, durability, versatility, modular, and since they can be upcycled, they are also eco-friendly. Some disadvantages of shipping containers are they contain harmful chemicals, insulation must be added, fossil fuels must be used to

Reactor building with internal structure of which the movements are independent of those of the general raft and process for building these internal structures

International Nuclear Information System (INIS)

Hista, J.C.

1982-01-01

This reactor building includes a containment enclosure for the internal structures composed of a slab wedged on its periphery against the containment enclosure gusset and resting on the general raft by means of a peripheral bearing ring, a compressible layer being provided between the general raft and the slab [fr

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.

Most Recent Sampling Results for Annex III Building

Science.gov (United States)

Contains email from Scott Miller, US EPA to Scott Kramer. Subject: Most Recent Sampling Results for Annex III Building. (2:52 PM) and Gore(TM) Surveys Analytical Results U.S. Geological Survey, Montgomery, AL.

Methods for eluting radiocesium from zeolite ion exchange material in a column in the TMI-2 reactor containment building

International Nuclear Information System (INIS)

Knauer, J.B.; Campbell, D.O.; Collins, E.D.; King, L.J.

1982-07-01

Two alternative procedures were evaluated at Oak Ridge National Laboratory for potential use in eluting the radiocesium from Linde Ionsiv IE-95 zeolite in the pushcart ion exchange column in the TMI-2 containment building. The elution mechanism was iosotopic exchange of the radiocesium with stable cesium. Small zeolite ion exchange columns that had been loaded during ORNL tests of the Submerged Demineralizer System (SDS) flowsheet were eluted during these tests. One column was eluted using 0.25 M CsNO 3 , and a second column was eluted using 0.25 M CsH 2 BO 3 . Both eluent solutions were effective for removing the cesium. The 0.25 CsNO 3 eluent removed approx. 91% of the 137 Cs in 20 bed volumes and approx. 92% in 37.5 bed volumes. The 0.25 M CsH 2 BO 3 eluent removed approx. 82% of the 137 Cs in 20 bed volumes and approx. 85% in 40 bed volumes. In both cases, the radiation levels on the columns were reduced by a factor of approx. 30

Natural radioactivity of building materials in Austria

International Nuclear Information System (INIS)

Sorantin, H.; Steger, F.

1984-03-01

About 120 samples of natural and manufactured building materials have been analyzed by gamma-spectrometry for their Thorium 232-, Radium 226- and Potassium 40 - content. Granites showed generally the greatest amounts of the above mentioned radionuclides, whereas other natural products like sand, gravels, marbles and gypsum contained only traces of radionuclides. As regards the manufactured building materials only some types of bricks and chemical gypsum showed relatively high concentrations of radionuclides, while the rest of the bricks, tiles, plaster and accessory materials fulfilled the criteria set up in the OECD-NEA report 1979. (Author)

Building the universe

International Nuclear Information System (INIS)

Sutton, Christine

1985-01-01

The book 'In Building the Universe' contains a collection of articles from the magazine 'New Scientist', compiled and edited to provide an overview of the field of particle physics. A picture of the basic constituents of matter (quarks and leptons) is given, together with the four fundamental forces that hold them together. The operation of these forces in the first instance of the hot young Universe is described. Also, the development of the accelerators and detectors used in elementary particle physics, is discussed. (UK)

Nation-building Initiatives of the Olusegun Obasanjo Administration ...

African Journals Online (AJOL)

uon1

contained about 250 ethnic groups with over 350 spoken languages (Almond, et ..... necessity for a central government, and the identification with the central ... There are three elements of nation-building: ideology, integration of society and.

Pressurized Water Reactor containment in Russia

International Nuclear Information System (INIS)

Taymouri, Majid.

1993-01-01

One of the most important systems of nuclear power plants from an economical point of view and view point of safety is containment; Therefore, the containments designed in Russia were studied in the first chapter. Russian general rules and requirements of structure of accident localization system were illustrated. Methods of accident localization system rooms tested for tightness and strength are presented in chapter three. Russian specialists have been working hard to ensure the safety culture in building structures and operational procedures and the have successfully implemented these objectives in new nuclear power plant designs and rules

Mastering CMake a cross-platform build system : version 3.1

CERN Document Server

Martin, Ken

2015-01-01

CMake is an open-source build tool enabling collaboration among software developers working on distinct platforms by using a common build specification to drive their native build tools. Mastering CMake explains how to use the CMake suite of tools, including CTest and CPack, to develop, build, test, and package software for distribution. It covers use of the command-line and GUI tools on Linux (UNIX), Microsoft Windows, and Mac OS X. This book also contains a guide for converting projects to CMake and writing CMake code to specify build rules to compile sources, create static and shared libraries, link executables, run custom commands, run tests, and install artifacts. It also includes a copy of key portions of the official reference documentation.

Air conditioning device for reactor buildings

International Nuclear Information System (INIS)

Kikuchi, Shiro.

1982-01-01

Purpose: To decrease the opening areas of pipe lines for an air conditioning device at the portions passing through the shielding walls of a reactor building for a FBR type reactor, as well as reduce the size of the building. Constitution: Airs in the building for containing reactor are liquefied in an air liquefying mechanism. The liquefied airs are sent by way of pipe lines to each of evaporators, wherein each of the chambers are cooled because of latent heat of evaporation and evaporated airs are released to each of the chambers. The airs released to each of the chambers are collected into an exhaust chamber and sent by way of a duct to the air liquefying mechanism and liquefied again. Since the volume of the liquefied airs may be smaller than the amount conventionally required for usual cooled airs, the pipe lines passing through the shielding walls of the building can be of smaller diameter. This can decrease the opening areas of the pipe lines at the portions passing through the walls of the shieldings and, since the opening areas are smaller, the structure of the radiation shieldings can be simplified in these portions. Further, since the space of the pipe lines in the building is reduced extremely, the size of the building can be reduced. (Moriyama, K.)

Allegheny County Municipal Building Energy and Water Use

Data.gov (United States)

Allegheny County / City of Pittsburgh / Western PA Regional Data Center — This dataset contains energy and water use information from 2010 to 2014 for 144 County-operated buildings. Metrics include: kBtu (thousand British thermal units),...

CONTEMPT-DG containment analysis code

International Nuclear Information System (INIS)

Deem, R.E.; Rousseau, K.

1982-01-01

The assessment of hydrogen burning in a containment building during a degraded core event requires a knowledge of various system responses. These system responses (i.e. heat sinks, fan cooler units, sprays, etc.) can have a marked effect on the overall containment integrity results during a hydrogen burn. In an attempt to properly handle the various system responses and still retain the capability to perform sensitivity analysis on various parameters, the CONTEMPT-DG computer code was developed. This paper will address the historical development of the code, its various features, and the rationale for its development. Comparisons between results from the CONTEMPT-DG analyses and results from similar MARCH analyses will also be given

PCCS model development for SBWR using the CONTAIN code

International Nuclear Information System (INIS)

Tills, J.; Murata, K.K.; Washington, K.E.

1994-01-01

The General Electric Simplified Boiling Water Reactor (SBWR) employs a passive containment cooling system (PCCS) to maintain long-term containment gas pressure and temperature below design limits during accidents. This system consists of a steam supply line that connects the upper portion of the drywell with a vertical shell-and-tube single pass heat exchanger located in an open water pool outside of the containment safety envelope. The heat exchanger tube outlet is connected to a vent line that is submerged below the suppression pool surface but above the main suppression pool horizontal vents. Steam generated in the post-shutdown period flows into the heat exchanger tubes as the result of suction and/or a low pressure differential between the drywell and suppression chamber. Operation of the PCCS is complicated by the presence of noncondensables in the flow stream. Build-up of noncondensables in the exchanger and vent line for the periods when the vent is not cleared causes a reduction in the exchanger heat removal capacity. As flow to the exchanger is reduced due to the noncondensable gas build-up, the drywell pressure increases until the vent line is cleared and the noncondensables are purged into the suppression chamber, restoring the heat removal capability of the PCCS. This paper reports on progress made in modeling SBWR containment loads using the CONTAIN code. As a central part of this effort, a PCCS model development effort has recently been undertaken to implement an appropriate model in CONTAIN. The CONTAIN PCCS modeling approach is discussed and validated. A full SBWR containment input deck has also been developed for CONTAIN. The plant response to a postulated design basis accident (DBA) has been calculated with the CONTAIN PCCS model and plant deck, and the preliminary results are discussed

Reuse of Material Containing Natural Radionuclides - 12444

Energy Technology Data Exchange (ETDEWEB)

Metlyaev, E.G.; Novikova, N.J. [Burnasyan Federal Medical Biophysical Centre, Moscow (Russian Federation)

2012-07-01

Disposal of and use of wastes containing natural radioactive material (NORM) or technologically enhanced natural radioactive material (TENORM) with excessive natural background as a building material is very important in the supervision body activity. At the present time, the residents of Octyabrsky village are under resettlement. This village is located just near the Priargunsky mining and chemical combine (Ltd. 'PPGHO'), one of the oldest uranium mines in our country. The vacated wooden houses in the village are demolished and partly used as a building material. To address the issue of potential radiation hazard of the wooden beams originating from demolition of houses in Octyabrsky village, the contents of the natural radionuclides (K-40, Th-232, Ra-226, U- 238) are being determined in samples of the wooden beams of houses. The NORM contents in the wooden house samples are higher, on average, than their content in the reference sample of the fresh wood shavings, but the range of values is rather large. According to the classification of waste containing the natural radionuclides, its evaluation is based on the effective specific activity. At the effective specific activity lower 1.5 kBq/kg and gamma dose rate lower 70 μR/h, the material is not considered as waste and can be used in building by 1 - 3 classes depending upon A{sub eff} value. At 1.5 kBq/kg < A{sub eff} ≤ 4 kBq/kg (4 class), the wooden beams might be used for the purpose of the industrial building, if sum of ratios between the radionuclide specific activity and its specific activity of minimum significance is lower than unit. The material classified as the waste containing the natural radionuclides has A{sub eff} higher 1.5 kBq /kg, and its usage for the purpose of house-building and road construction is forbidden. As for the ash classification and its future usage, such usage is unreasonable, because, according to the provided material, more than 50% of ash samples are considered as

Structural response of rectilinear containment to overpressurization

International Nuclear Information System (INIS)

Pfeiffer, P.A.; Kulak, R.F.

1995-01-01

Containment structures for nuclear reactors are the final barrier between released radionuclides and the public. Containment structures are constructed from steel, reinforced concrete, or prestressed concrete. US nuclear reactor containment geometries tend to be cylindrical with elliptical or hemispherical heads. The older Soviet designed reactors do not use a containment building to mitigate the effects of accidents. Instead, they employ a sealed set of rectilinear, interconnected compartments, collectively called the accident localization system (ALS), to reduce the release of radionuclides to the atmosphere during accidents. The purpose of this paper is to present a methodology that can be used to find the structural capacity of reinforced concrete structures. The method is applicable to both cylindrical and rectilinear geometries. As an illustrative example, the methodology is applied to a generic VVER-440/V213 design

State-of-the-art Review : Vol. 2B. Integrated Building Concepts

DEFF Research Database (Denmark)

van der Aa, Ad; Andresen, Inger; Asada, Hideo

an overview of 23 case study buildings from 9 countries with integrated building concepts. The overview provides descriptions of the buildings and their contexts, a description of the integrated energy systems, and the overall performance of the building with respect to energy, indoor environment and costs......The purpose of this report is to give examples of integrated building concepts and related available performance data and information. The report does not aspire to give a complete overview of all possible integrated building concepts and processes. The buildings included in the report have been...... selected according to the knowledge of the participants in the project, as characteristic examples of the concepts and the challenges they represent. The report will be a common basis for the research and development work that is going to be carried out within the IEA Annex 44 project. The report contains...

Theoretical and experimental studies on in-plane stiffness of integrated container structure

Directory of Open Access Journals (Sweden)

Xiaoxiong Zha

2016-03-01

Full Text Available This article presents analytical, numerical, and experimental studies on the in-plane stiffness of container buildings. First, based on diaphragm theory, parallel corrugated direction stiffness of corrugated sheet has been deduced, and based on energy method, shear modulus of two elastic principal directions of orthotropic plate has been deduced, and through stiffness conversion method, the stiffness relationship between parallel corrugated direction and vertical corrugated direction has been obtained. Combined with container frame, the container stiffness of loading end and non-loading end, as bottom side beam fixed, has been obtained. Second, through the software Abaqus, full-scale container model has been established. The loading–displacement curve of finite element model has been compared with theoretical analysis and has a good agreement. Third, through 20 and 40 ft container, corresponding experimental verification has been done, and by comparison of container stiffness, the theoretical analysis and finite element simulation have been verified. Finally, based on verified finite element model, parametric analysis of corrugated sheet size, corrugated sheeting cross section, elasticity modulus of top side beam, and every plate action for container stiffness have been given. Research result has made feasible in design and construction of container buildings and can provide some references to corresponding specification preparation.

Technical Support Document: 50% Energy Savings Design Technology Packages for Highway Lodging Buildings

Energy Technology Data Exchange (ETDEWEB)

Jiang, Wei; Gowri, Krishnan; Lane, Michael D.; Thornton, Brian A.; Rosenberg, Michael I.; Liu, Bing

2009-09-28

This Technical Support Document (TSD) describes the process, methodology and assumptions for development of the 50% Energy Savings Design Technology Packages for Highway Lodging Buildings, a design guidance document intended to provide recommendations for achieving 50% energy savings in highway lodging properties over the energy-efficiency levels contained in ANSI/ASHRAE/IESNA Standard 90.1-2004, Energy Standard for Buildings Except Low-Rise Residential Buildings.

Site-Specific Soundscape Design for the Creation of Sonic Architectures and the Emergent Voices of Buildings

Directory of Open Access Journals (Sweden)

Jordan Lacey

2014-01-01

Full Text Available Does a building contain its own Voice? And if so, can that Voice be discovered, transformed and augmented by soundscape design? Barry Blesser’s writings on acoustic space, discuss reverberation and resonant frequencies as providing architectural spaces with characteristic listening conditions related to the architectural space’s dimensions and materiality. The paper argues that Blesser and Salter expand such discussion into pantheistic speculation when suggesting that humanity contains the imaginative capacity to experience spaces as “living spirits”. This argument is achieved by building on the speculation through the discussion of a soundscape design methodology that considers space as containing pantheistic qualities. Sonic architectures are created with electroacoustic sound installations that recompose existing architectural soundscapes, to create the conditions for the emergence of the Voices of buildings. This paper describes two soundscape designs, Revoicing the Striated Soundscape and Subterranean Voices, which transformed existing architectural soundscapes for the emergence of Voices in a laneway and a building located in the City of Melbourne, Australia.

Using Sorting Networks for Skill Building and Reasoning

Science.gov (United States)

Andre, Robert; Wiest, Lynda R.

2007-01-01

Sorting networks, used in graph theory, have instructional value as a skill- building tool as well as an interesting exploration in discrete mathematics. Students can practice mathematics facts and develop reasoning and logic skills with this topic. (Contains 4 figures.)

Trust and Relationship Building in Electronic Commerce.

Science.gov (United States)

Papadopoulou, Panagiota; Andreou, Andreas; Kanellis, Panagiotis; Martakos, Drakoulis

2001-01-01

Discussion of the need for trust in electronic commerce to build customer relationships focuses on a model drawn from established theoretical work on trust and relationship marketing that highlights differences between traditional and electronic commerce. Considers how trust can be built into virtual environments. (Contains 50 references.)…

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.

Liquid metal reactor applications of the CONTAIN code

International Nuclear Information System (INIS)

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

1988-01-01

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

Containment performance working group report. Draft report for comment

International Nuclear Information System (INIS)

1985-05-01

Containment buildings for power reactors have been studied to estimate their leak rate as a function of increasing internal pressure and temperature associated with severe accident sequences involving significant core damage. Potential leak paths through containment penetration assemblies (such as equipment hatches, airlocks, purge and vent valves, and electrical penetrations) have been identified and their contributions to leak area for the containment are incorporated into containment response analyses of selected severe accident sequences to predict the containment leak rate and pressure/temperature response as a function of time. Because of lack of reliable experimental data on the leakage behavior of containment penetrations and isolation barriers at pressures beyond their design conditions, an analytical approach has been used to estimate the leakage behavior of components found in specific reference plants that approximately characterize the various containment types

Radioactivity of natural and artificial building materials - a comparative study.

Science.gov (United States)

Szabó, Zs; Völgyesi, P; Nagy, H É; Szabó, Cs; Kis, Z; Csorba, O

2013-04-01

Building materials and their additives contain radioactive isotopes, which can increase both external and internal radioactive exposures of humans. In this study Hungarian natural (adobe) and artificial (brick, concrete, coal slag, coal slag concrete and gas silicate) building materials were examined. We qualified 40 samples based on their radium equivalent, activity concentration, external hazard and internal hazard indices and the determined threshold values of these parameters. Absorbed dose rate and annual effective dose for inhabitants living in buildings made of these building materials were also evaluated. The calculations are based on (226)Ra, (232)Th and (40)K activity concentrations determined by gamma-ray spectrometry. Measured radionuclide concentrations and hence, calculated indices and doses of artificial building materials show a rather disparate distribution compared to adobes. The studied coal slag samples among the artificial building materials have elevated (226)Ra content. Natural, i.e. adobe and also brick samples contain higher amount of (40)K compared to other artificial building materials. Correlation coefficients among radionuclide concentrations are consistent with the values in the literature and connected to the natural geochemical behavior of U, Th and K elements. Seven samples (coal slag and coal slag concrete) exceed any of the threshold values of the calculated hazard indices, however only three of them are considered to be risky to use according to the fact that the building material was used in bulk amount or in restricted usage. It is shown, that using different indices can lead to different conclusions; hence we recommend considering more of the indices at the same time when building materials are studied. Additionally, adding two times their statistical uncertainties to their values before comparing to thresholds should be considered for providing a more conservative qualification. We have defined radon hazard portion to point

Solar-heated and cooled savings and loan building-1-Leavenworth, Kanasas

Science.gov (United States)

1981-01-01

Report describes heating and cooling system which furnishes 90 percent of annual heating load, 70 percent of cooling load, and all hot water for two-story building. Roof-mounted flat-plate collectors allow three distinct flow rates and are oriented south for optimum energy collection. Building contains fully automated temperature controls is divided into five temperature-load zones, each with independent heat pump.

About Microservices, Containers and their Underestimated Impact on Network Performance

OpenAIRE

Kratzke, Nane

2017-01-01

Microservices are used to build complex applications composed of small, independent and highly decoupled processes. Recently, microservices are often mentioned in one breath with container technologies like Docker. That is why operating system virtualization experiences a renaissance in cloud computing. These approaches shall provide horizontally scalable, easily deployable systems and a high-performance alternative to hypervisors. Nevertheless, performance impacts of containers on top of hyp...

4th international conference in sustainability in energy and buildings

CERN Document Server

Höjer, Mattias; Howlett, Robert; Jain, Lakhmi

2013-01-01

This volume contains the proceedings of the Fourth International Conference on Sustainability in Energy and Buildings, SEB12, held in Stockholm, Sweden, and is organised by KTH Royal Institute of Technology, Stockholm, Sweden in partnership with KES International. The International Conference on Sustainability in Energy and Buildings focuses on a broad range of topics relating to sustainability in buildings but also encompassing energy sustainability more widely. Following the success of earlier events in the series, the 2012 conference includes the themes Sustainability, Energy, and Buildings and Information and Communication Technology, ICT. The SEB’12 proceedings includes invited participation and paper submissions across a broad range of renewable energy and sustainability-related topics relevant to the main theme of Sustainability in Energy and Buildings. Applicable areas include technology for renewable energy and sustainability in the built environment, optimisation and modeling techniques, informati...

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

Hydrogen burn assessment with the CONTAIN code

International Nuclear Information System (INIS)

van Rij, H.M.

1986-01-01

The CONTAIN computer code was developed at Sandia National Laboratories, under contract to the US Nuclear Regulatory Commission (NRC). The code is intended for calculations of containment loads during severe accidents and for prediction of the radioactive source term in the event that the containment leaks or fails. A strong point of the CONTAIN code is the continuous interaction of the thermal-hydraulics phenomena, aerosol behavior and fission product behavior. The CONTAIN code can be used for Light Water Reactors as well as Liquid Metal Reactors. In order to evaluate the CONTAIN code on its merits, comparisons between the code and experiments must be made. In this paper, CONTAIN calculations for the hydrogen burn experiments, carried out at the Nevada Test Site (NTS), are presented and compared with the experimental data. In the Large-Scale Hydrogen Combustion Facility at the NTS, 21 tests have been carried out. These tests were sponsored by the NRC and the Electric Power Research Institute (EPRI). The tests, carried out by EG and G, were performed in a spherical vessel 16 m in diameter with a design pressure of 700 kPa, substantially higher than that of most commercial nuclear containment buildings

Approximation for maximum pressure calculation in containment of PWR reactors

International Nuclear Information System (INIS)

Souza, A.L. de

1989-01-01

A correlation was developed to estimate the maximum pressure of dry containment of PWR following a Loss-of-Coolant Accident - LOCA. The expression proposed is a function of the total energy released to the containment by the primary circuit, of the free volume of the containment building and of the total surface are of the heat-conducting structures. The results show good agreement with those present in Final Safety Analysis Report - FSAR of several PWR's plants. The errors are in the order of ± 12%. (author) [pt

Concrete containment tests: Phase 2, Structural elements with liner plates: Interim report

International Nuclear Information System (INIS)

Hanson, N.W.; Roller, J.J.; Schultz, D.M.; Julien, J.T.; Weinmann, T.L.

1987-08-01

The tests described in this report are part of Phase 2 of the Electric Power Research Institute (EPRI) program. The overall objective of the EPRI program is to provide a test-verified analytical method of estimating capacities of concrete reactor containment buildings under internal overpressurization from postulated degraded core accidents. The Phase 2 testing included seven large-scale specimens representing structural elements from reinforced and prestressed concrete reactor containment buildings. Six of the seven test specimens were square wall elements. Of these six specimens, four were used for biaxial tension tests to determine strength, deformation, and leak-rate characteristics of full-scale wall elements representing prestressed concrete containment design. The remaining two square wall elements were used for thermal buckling tests to determine whether buckling of the steel liner plate would occur between anchorages when subjected to a sudden extreme temperature differential. The last of the seven test specimens for Phase 2 represented the region where the wall and the basemat intersect in a prestressed concrete containment building. A multi-directional loading scheme was used to produce high bending moments and shear in the wall/basemat junction region. The objective of this test was to determine if there is potential for liner plate tearing in the junction region. Results presented include observed behavior and extensive measurements of deformations and strains as a function of applied load. The data are being used to confirm analytical models for predicting strength and deformation of containment structures in a separate parallel analytical investigation sponsored by EPRI

Development of the APR+ Auxiliary Building General Arrangement (GA)

International Nuclear Information System (INIS)

Moon, Hyung Keun; Park, Young Sheop; Kang, Yong Chul

2011-01-01

The general arrangement (GA) drawing of a nuclear power plant is the most basic drawing which contains all of the plant equipment, systems, and rooms. Therefore, it should be issued at an early design stage to provide the contours of the overall plant structure. This type of drawing is typically used widely throughout the design stages. The development project of APR+ (Advanced Power Reactor+), as a succeeding model of the APR1400 (Advanced Power Reactor 1400) design, has its own GA that encompasses all of its power buildings. This was developed starting in October of 2009. Among several of the buildings in this design, the Auxiliary Building (AB) is one of the most important buildings to produce electricity, and to protect against undesirable radiation emissions. This paper focuses on the design characteristics of the general arrangement of the AB

Analysis of the metallic containment integrity of Angra I

International Nuclear Information System (INIS)

Costa, J.R.

1981-01-01

The main goal of this work is to evaluate the pressure and temperature long-term behavior inside the metalic containment of a PWR building subjected to a postulated loss-of-coolant accident. The computer program used was CONDRU 4. Calculations were made for Angra I plant assuming the ocurrence of the worst accident to the containment integrity. The results obtained from CONDRU were compared with those from CONTEMPT-LT and COCO, which are codes similar to CONDRU. (Author) [pt

Results. Building integrated energy supply; Resultater. Bygningsintegreret energiforsyning

Energy Technology Data Exchange (ETDEWEB)

Jensen, Rasmus L.; Noergaard, J.; Daniels, O.; Justesen, R.O.

2011-08-15

In the future, buildings will not only act as consumers of energy but as producers as well. For these ''prosumers'', energy production by use of solar panels, photovoltaics and heat pumps etc will be essential. The objective of this project was to find the most optimal combinations of building insulation and use of renewable energy sources in existing buildings in terms of economics and climate impacts. Five houses were analyzed based on different personal load, consumption profiles, solar orientation and proposed building envelope improvements and use of combinations of renewable energy systems. The analysis was conducted by making a large number of simulations of which the best combinations were selected. The final result takes form of a single top-50 list with the best combinations of energy systems according to CO{sub 2} emission, energy consumption and economics. The present report contains the conclusions of and comments on the project's results. (ln)

Building envelope regulations on thermal comfort in glass facade buildings and energy-saving potential for PMV-based comfort control

Energy Technology Data Exchange (ETDEWEB)

Hwang, Ruey-Lung; Shu, Shiu-Ya [Department of Architecture, National United University, 1, Lien-Da, Kung-Ching Li, Miaoli, 36003 (China)

2011-04-15

This paper presents an investigation of the effect of building envelope regulation on thermal comfort and on the energy-saving potential for PMV-based comfort control in glass facade buildings. Occurrences and severity of overheating, based on the PMV-PPD model contained in ISO 7730, were used for the thermal comfort assessment. Parametric study simulations for an actual building with a large glass facade were carried out to predict the changes in thermal comfort levels in a space due to different glazing types, depths of overhang and glazing areas, which are the key parameters of the building envelope regulation index, named ENVLOAD, in Taiwan. The result demonstrates that the ENVLOAD has significant effect on thermal comfort. Additionally, comparative simulations between PMV-based comfort control and conventional thermostatic control were performed to investigate the changes in the energy-saving potential of a thermal comfort-controlled space due to changes of its ENVLOAD. The results demonstrate that the energy-saving potential in a PMV-based controlled space increases with low ENVLOAD conditions. (author)

ITER containment design-assist analysis

International Nuclear Information System (INIS)

Nguyen, T.H.

1992-03-01

In this report, the analysis methods, models and assumptions used to predict the pressure and temperature transients in the ITER containment following a loss of coolant accident are presented. The ITER reactor building is divided into 10 different volumes (zones) based on their functional design. The base model presented in this report will be modified in volume 2 in order to determine the peak pressure, the required size of openings between various functional zones and the differential pressures on walls separating these zones

An obstacle to building a time machine

International Nuclear Information System (INIS)

Carroll, S.M.; Farhi, E.; Guth, A.H.

1992-01-01

Gott has shown that a spacetime with two infinite parallel cosmic strings passing each other with sufficient velocity contains closed timelike curves. We discuss an attempt to build such a time machine. Using the energy-momentum conservation laws in the equivalent (2+1)-dimensional theory, we explicitly construct the spacetime representing the decay of one gravitating particle into two. We find that there is never enough mass in an open universe to build the time machine from the products of decays of stationary particles. More generally, the Gott time machine cannot exist in any open (2+1)-dimensional universe for which the total momentum is timelike

Regulation proposal for voluntary energy efficiency labelling of commercial buildings

International Nuclear Information System (INIS)

Lamberts, Roberto; Goulart, Solange; Carlo, Joyce; Westphal, Fernando

2006-01-01

Despite of Brazil not being between the major world energy consumers, the consumption of electricity has significantly increased in the late years. The National Energy Balance of 2005, published by the Brazilian Ministry of Energy, showed an increasing of the participation of electricity in the final energy consumption of 15.7% in 2002 to 16.2% in 2004. Initially, a brief review of the initiatives taken by Brazilian Government aiming to limit and control the energy consumption in buildings is presented. Then, the regulation proposal containing the technical requirements to classify the energy efficiency level of buildings is shown. The purpose of this voluntary regulation is to provide conditions to certify the energy efficiency level of Brazilian buildings (commercial and public). It specifies the methods for energy efficiency rating of buildings and includes requirements to attend energy conservation measures in three main issues: lighting system; air conditioning system and envelope. The regulation applies to large buildings (minimum total area of 500 m 2 or when the energy demand is greater than or equal to 2,3 kV, including: Conditioned buildings; Partially conditioned buildings and Naturally ventilated buildings. (author)

Quantitative NMR Approach to Optimize the Formation of Chemical Building Blocks from Abundant Carbohydrates

DEFF Research Database (Denmark)

Elliot, Samuel Gilbert; Tolborg, Søren; Sádaba, Irantzu

2017-01-01

-containing catalysts such as Sn-Beta. These compounds are potential building blocks for polyesters with additional olefin and alcohol functionalities. We employ an NMR approach to identify, quantify and optimize the formation these building blocks in the chemocatalytic transformation of abundant carbohydrates by Sn...

Composition of 12-18th century window glass in Belgium: Non-figurative windows in secular buildings and stained-glass windows in religious buildings

International Nuclear Information System (INIS)

Schalm, Olivier; Janssens, Koen; Wouters, Hilde; Caluwe, Danielle

2007-01-01

A set of ca. 500 window glass fragments originating from different historical sites in Belgium and covering the period 12 th -18 th century was analyzed by means of electron probe microanalysis. Most samples are archaeological finds deriving from non-figurative windows in secular buildings. However, the analyzed set also contains glass sampled from still existing non-figurative windows in secular buildings and stained-glass windows in religious buildings. A sudden compositional change at the end of the 14 th century can be noticed among the series of glass compositions that were obtained. These changes could be related to the use of different glassmaker recipes and to the introduction of new raw materials for glass making

Composition of 12-18 th century window glass in Belgium: Non-figurative windows in secular buildings and stained-glass windows in religious buildings

Science.gov (United States)

Schalm, Olivier; Janssens, Koen; Wouters, Hilde; Caluwé, Danielle

2007-07-01

A set of ca. 500 window glass fragments originating from different historical sites in Belgium and covering the period 12 th-18 th century was analyzed by means of electron probe microanalysis. Most samples are archaeological finds deriving from non-figurative windows in secular buildings. However, the analyzed set also contains glass sampled from still existing non-figurative windows in secular buildings and stained-glass windows in religious buildings. A sudden compositional change at the end of the 14 th century can be noticed among the series of glass compositions that were obtained. These changes could be related to the use of different glassmaker recipes and to the introduction of new raw materials for glass making.

Natural Ventilation of Buildings through Light Shafts. Design-Based Solution Proposals

Science.gov (United States)

Ángel Padilla-Marcos, Miguel; Meiss, Alberto; Feijó-Muñoz, Jesús

2017-10-01

This work analyses how the built environment affects the quality of the air to be introduced into buildings from light shafts. Several factors such as urban environment and building design intervene in the ability of the light shaft to produce its air change process. Urban areas continuously pollute the air in cities which affects the human health and the environment sustainability. Poor air quality outside buildings supposes a big energy waste to promote an acceptable air quality inside buildings. That requires a large flow rate to maintain the indoor air quality which is translated to an energy efficiency term. The main objective focuses on the impact of standardized architecture design in the quality of the indoor air dependent on the air change in the light shaft. The air change capacity of the outdoor space is numbered analysed using the concept of air change efficiency (ACE). ACE is determined by the built environment, the wind conditions and the design of the building containing light shafts. This concept is comparatively evaluated inside a control domain virtually defined to obtain the mean age of the air for a known air volume. The longer the light shaft in the wind direction is, the better the ACE is compared with other options. Light shafts up to 12 metres high are the most suitable in order to obtain acceptable efficiency results. Other studied cases verify that assumption. Different simplified tools for the technicians to evaluate the design of buildings containing light shafts are proposed. Some strategies of architectural design of buildings with light shafts to be used for ventilation are presented.

NANOSTRUCTURED METAL OXIDE CATALYSTS VIA BUILDING BLOCK SYNTHESES

Energy Technology Data Exchange (ETDEWEB)

Craig E. Barnes

2013-03-05

A broadly applicable methodology has been developed to prepare new single site catalysts on silica supports. This methodology requires of three critical components: a rigid building block that will be the main structural and compositional component of the support matrix; a family of linking reagents that will be used to insert active metals into the matrix as well as cross link building blocks into a three dimensional matrix; and a clean coupling reaction that will connect building blocks and linking agents together in a controlled fashion. The final piece of conceptual strategy at the center of this methodology involves dosing the building block with known amounts of linking agents so that the targeted connectivity of a linking center to surrounding building blocks is obtained. Achieving targeted connectivities around catalytically active metals in these building block matrices is a critical element of the strategy by which single site catalysts are obtained. This methodology has been demonstrated with a model system involving only silicon and then with two metal-containing systems (titanium and vanadium). The effect that connectivity has on the reactivity of atomically dispersed titanium sites in silica building block matrices has been investigated in the selective oxidation of phenols to benezoquinones. 2-connected titanium sites are found to be five times as active (i.e. initial turnover frequencies) than 4-connected titanium sites (i.e. framework titanium sites).

Containment concepts assessment for the SEAFP reactor

International Nuclear Information System (INIS)

Di Pace, L.; Natalizio, A.

2000-01-01

A simple methodology has been developed for making relative comparisons of potential containment designs for future fusion reactors. The assessment methodology requires only conceptual design information. The application of this methodology, at the early stages of a fusion reactor design, provides designers useful information regarding the suitability of various containment designs and design features. Because the radiation hazard from the operation of future fusion power reactors is expected to be low, the containment design, in addition to public safety, needs to take into account worker safety considerations, as well as factors important to the reliable and economical operation of the power plant. Several containment concepts have been assessed with a methodology that takes into account public safety, worker safety, operability and maintainability as well as cost. This paper describes this methodology and presents the results of the assessment. The paper concludes that, to obtain a containment design that is optimised with respect to safety, operational and cost factors, designers should focus on a containment that is conceptually simple-that is, one utilising a single, large containment building without relying on special features such as expansion volumes, pressure suppression pools or spray systems

Facility for the storage of spent, heat-emitting and container-enclosed nuclear reactor fuel assemblies

International Nuclear Information System (INIS)

Hennings, U.

1987-01-01

Patent for facility for the storage of spent, heat-emitting and container-enclosed nuclear reactor fuel assemblies, which are arranged within a building in a horizontal position and are cooled by a gas stream, whereby the building has a storage and a loading zone, characterized by the fact that pallet trucks arranged one above the other in a row and such that an interspace is left for the receiving positions for the containers, the the pallet trucks can be moved along rails that extend between two side walls arranged opposite to one another in the storage zone, that the storage zone can be loaded and unloaded by opening located in these two side walls, and that the gas stream only circulates within the building

Automated mapping of building facades by machine learning

DEFF Research Database (Denmark)

Höhle, Joachim

2014-01-01

Facades of buildings contain various types of objects which have to be recorded for information systems. The article describes a solution for this task focussing on automated classification by means of machine learning techniques. Stereo pairs of oblique images are used to derive 3D point clouds...

Trends in the development of reactor containments

International Nuclear Information System (INIS)

Turricchia, A.

1977-01-01

The paper presents a review of the technical developments which the containment systems of BWRs, PWRs and HWRs have undergone in the USA, Europe and Canada. The great variety of existing containment systems have been classified for each type of reactor, according to: principle of operation (i.e. dry containment; pressure suppression containment; containment with vacuum building; sub-atmospheric containment; etc.); type and number of the physical barriers provided against the dispersion of fission products to the environment (single containment, double containment, single containment with local collection of the leaks from the most probable leakage paths, or with pressurization of the potential leakage paths, etc.); and structural characteristics of the containment barriers (reinforced concrete, prestressed concrete, metal containment, liners). In the framework of this classification the main features of the various containment systems are illustrated, with special emphasis on the most modern designs. The difference in trend among various countries and various designers are highlighted. A review is also made of the various containment auxiliary systems which would operate in accident conditions (isolation systems, heat removal system, atmosphere control system, etc.). Also for these systems the main design criteria are set forth and present trends are described. Finally, a brief survey is also made of the present trends with regards to the design of containment structures against external events be they of natural origin (earthquake, tornadoes, etc.) or connected with human activities (airplane crash, explosions, etc.) [fr

Commercial disposal of High Integrity Containers (HICs) containing EPICOR-II prefilters from Three Mile Island

International Nuclear Information System (INIS)

McConnell, J.W. Jr.; Lynch, R.J.; Tyacke, M.J.

1985-09-01

This report describes the processes of loading, transporting, and commercially disposing of 45 High Integrity Containers (HICs), each containing an EPICOR-II prefilter. Also described are the improvements that were applied in the disposition of the 45 commercial EPICOR-II prefilters at the Idaho National Engineering Laboratory (INEL), versus those used for the demonstration unit. The significance of this effort was that the commercial disposal campaign involved the first-of-a-kind production use of a reinforced concrete HIC at the US Ecology, Inc. facility in the State of Washington. This allowed for safe disposal of high-specific-activity ion exchange material in EPICOR-II prefilters generated during the cleanup of the Unit-2 Auxiliary and Fuel Handling Building of the Three Mile Island Nuclear Power Station. 26 figs

Response of a NPP reactor building under seismic action with regard to different soil properties

International Nuclear Information System (INIS)

Wagenknecht, E.

1987-01-01

The object of this investigation is the response of a reactor building on seismic action with systematic variation of the soil stiffness. A thin-walled orthotropic containment shell on varying heavy and rigid foundations is regarded as calculation model. The soil stiffness is simulated by meand of spring elements for horizontal translation and for rocking motions of the building. By the response spectra method the loads of the containment shell are calculated for a horizontal seismic excitation. The investigation is aimed at determining the influence of differentiated soil stiffnesses on the containment action effects and at recognizing the causes for the occuring effects. The results are thoroughly represented by selected quantities of the building's response, the effects from the soil-structure interaction are discussed and the causes of the effects cleary explained. Apossibility is provided for determining critical soil stiffnesses which cause a siginificat intensification effect. The results of the investigations show that both the soil stiffness and structural configuration of the reactor building particulary in case of the substructure being heavy and rigid, exert a decisive on the loading of the superstructure. (orig.)

Reactor building pressure proof test (PPT) and leak rate test (LRT) of Qinshan phase III (CANDU) project

International Nuclear Information System (INIS)

Gu Jun; Shi Jinqi; Fan Fuping

2004-12-01

As the first reactor building (R/B) without stainless steel liner in china, TQNPC studied the containment characteristics, such as strong concrete absorb/release air effect, poor containment penetration. etc. And carefully prepared test scheme and emergency response, creatively introduced the instrument air self-supply system in reactor building, developed the special measurement and analysis system for PPT and LRT, organized work under high-pressure on large-scale in the test. Finally got the containment leak rate result and the test-cost-time value is the best in all same type tests. (authors)

The Economics of Connecting of Small Buildings to Geothermal District Heating Systems

Energy Technology Data Exchange (ETDEWEB)

Rafferty, Kevin

2003-03-01

Many of the communities co-located with geothermal resources are very small and as a result the buildings they contain tend to be small as well. Generally, small buildings (10,000 ft2) use heating systems which are not hot water based. Since geothermal district heating systems deliver hot water, the costs associated with the conversion of small building heating systems to use hot water for heating is an issue of great influence in terms of the potential development of such systems. This paper examines the typical retrofit costs associated with conversion of small buildings and the level of savings necessary to attract the interest of owners. In general, the prospects for connection of such buildings based only on energy savings is not positive.

The economics of connecting of small buildings to geothermal district heating systems

Energy Technology Data Exchange (ETDEWEB)

Rafferty, Kevin

2001-01-01

Many of the communities co-located with geothermal resources are very small and as a result the buildings they contain tend to be small as well. Generally, small buildings (10,000 ft2) use heating systems which are not hot water based. Since geothermal district heating systems deliver hot water, the costs associated with the conversion of small building heating systems to use hot water for heating is an issue of great influence in terms of the potential development of such systems. This paper examines the typical retrofit costs associated with conversion of small buildings and the level of savings necessary to attract the interest of owners. In general, the prospects for connection of such buildings based only on energy savings is not positive.

Self-leveling mortar as a possible cause of symptoms associated with "sick building syndrome".

Science.gov (United States)

Lundholm, M; Lavrell, G; Mathiasson, L

1990-01-01

In newly constructed houses and buildings in which self-leveling mortar containing casein has been used, residents and office employees have noted a bad odor and have complained of headache, eye and throat irritation, and tiredness. These problems were suspected to result from the degradation products emitted from the mortar. Samples obtained from dry mortar powder and from mortar in buildings where casein was used and from control buildings were found to contain microorganisms (mean of 10(2) culture forming units/g). Environmental species were predominantly found, e.g., Bacillus, Clostridium, Micrococcus, and Propionibacterium. Fungi were found occasionally; no evidence of bacterial degradation was found. Headspace and gas chromatographic-mass spectrometric analysis of air from the newly constructed houses and from hydroxide-degraded casein revealed the presence of amines in the 0.003-0.013 ppm range and the presence of ammonia and sulfhydryl compounds, all of which in low concentrations can cause the symptoms observed. These substances, however, were not detected in control buildings.

A reference container concept for spent fuel disposal: structural safety for dimensioning of the reference container

International Nuclear Information System (INIS)

Choi, Jongwon; Kwon, Sangki; Kang, Chulhyung; Kwon, Youngjoo

2002-01-01

This paper presents the mechanical and thermal stress analysis of a disposal canister to provide basic information for dimensioning the canister and configuration of the canister components. The structural stress analysis is carried out using a finite element analysis code, NISA, and focused on the structural strength of the canister against the expected external pressures due to the swelling of the bentonite buffer and the hydrostatic head, and the thermal load build up in the container

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

International Nuclear Information System (INIS)

Murata, K.K.; Williams, D.C.; Griffith, R.O.; Gido, R.G.; Tadios, E.L.; Davis, F.J.; Martinez, G.M.; Washington, K.E.; Tills, J.

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

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.

Building Better Buildings: Sustainable Building Activities in California Higher Education Systems.

Science.gov (United States)

Sowell, Arnold; Eichel, Amanda; Alevantis, Leon; Lovegreen, Maureen

2003-01-01

This article outlines the activities and recommendations of California's sustainable building task force, discusses sustainable building activities in California's higher education systems, and highlights key issues that California is grappling with in its implementation of sustainable building practices. (EV)

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

Directory of Open Access Journals (Sweden)

Ahmer Ali

2017-06-01

Full Text Available 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.

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.

Introduction to Large-sized Test Facility for validating Containment Integrity under Severe Accidents

International Nuclear Information System (INIS)

Na, Young Su; Hong, Seongwan; Hong, Seongho; Min, Beongtae

2014-01-01

An overall assessment of containment integrity can be conducted properly by examining the hydrogen behavior in the containment building. Under severe accidents, an amount of hydrogen gases can be generated by metal oxidation and corium-concrete interaction. Hydrogen behavior in the containment building strongly depends on complicated thermal hydraulic conditions with mixed gases and steam. The performance of a PAR can be directly affected by the thermal hydraulic conditions, steam contents, gas mixture behavior and aerosol characteristics, as well as the operation of other engineering safety systems such as a spray. The models in computer codes for a severe accident assessment can be validated based on the experiment results in a large-sized test facility. The Korea Atomic Energy Research Institute (KAERI) is now preparing a large-sized test facility to examine in detail the safety issues related with hydrogen including the performance of safety devices such as a PAR in various severe accident situations. This paper introduces the KAERI test facility for validating the containment integrity under severe accidents. To validate the containment integrity, a large-sized test facility is necessary for simulating complicated phenomena induced by an amount of steam and gases, especially hydrogen released into the containment building under severe accidents. A pressure vessel 9.5 m in height and 3.4 m in diameter was designed at the KAERI test facility for the validating containment integrity, which was based on the THAI test facility with the experimental safety and the reliable measurement systems certified for a long time. This large-sized pressure vessel operated in steam and iodine as a corrosive agent was made by stainless steel 316L because of corrosion resistance for a long operating time, and a vessel was installed in at KAERI in March 2014. In the future, the control systems for temperature and pressure in a vessel will be constructed, and the measurement system

Theoretical investigations to the mass- and energy transport in light water reactor containment buildings

International Nuclear Information System (INIS)

Hocke, K.D.; Bisanz, R.; Ploeger, G.

1982-12-01

In this report loss-of-coolant accidents in water-cooled nuclear power reactors will be described with regard to their effects on the reactor containment system. The general presentation of containment systems and the accident sequences is completed by performances of the physical and mathematical treatment of the flow dynamics. Following a survey of existing computer codes for containment analysis problems, a detailed model description of the computer codes ZOCO 6 and BEACON-MOD 2A is given. A variation of important model parameters within the ZOCO 6 program explains the field of application and leads to a valuation of the model assumptions. The obtained results are presented graphically including latest publications. (orig.) [de

Improving the performance of sorter systems by scheduling inbound containers

NARCIS (Netherlands)

Haneyah, S.W.A.; Schutten, Johannes M.J.; Fikse, K.

2013-01-01

This paper addresses the inbound containers scheduling problem for automated sorter systems in two different industrial sectors: parcel & postal sorting and baggage handling. We build on existing literature, particularly on the dynamic load balancing algorithm designed for the parcel hub scheduling

Building 12-42F modification, Pantex Plant, Amarillo, Texas

International Nuclear Information System (INIS)

1991-02-01

The Environment Assessment (EA) has been prepared pursuant to the implementing regulations to the National Environmental Policy Act (NEPA), which require federal agencies to assess the environmental impacts of a proposed action to determine whether that action requires the preparation of an Environmental Impact Statement (EIS) or if a Finding of No Significant Impact (FONSI) can be issued. NEPA requires that an EA provide an interdisciplinary review of the proposed action in order to identify possible preferable alternatives and to identify mitigative measures that will prevent environmental impacts. If it is determined that the proposed action will have unavoidable significant environmental impact, then as EIS shall be prepared. The proposed project is to modify Building 12-42F and entry into the Sandia Pantex Weapons Evaluation Test Laboratory. The modification's primary function is to provide additional space for testing and monitoring equipment to support the activities in the existing Building 12-42F. The modification will also facilitate the reconfiguration of the personnel offices, break room and conference area. The proposed Building 12-42F modification relates to the interiors of Buildings 12-42F and 12-42A. These buildings contain a centrifuge and associated testing and monitoring equipment. The proposed addition will encompass the existing entry into Building 12-42A. Building 12-42A will be accessed through the proposed Building 12-42F modification

Study of Containment Vent Strategies During Severe Accident Progression for the CANDU6 Plant

Energy Technology Data Exchange (ETDEWEB)

Jin, Youngho; Ahn, K. I. [KAERI, Daejeon (Korea, Republic of)

2015-05-15

In March, 2011, Fukushima daichi nuclear power plants experienced a long term station blackout. Severe core damage occurred and a large amount of radioactive materials are released outside of the plants. After this terrible accident Nuclear Safety and Security Commission (NSSC) enforced to increase nuclear safety for all operating plants in Korea. To increase plant safety, both hardware reinforcement and software improvement are encouraged. Hardware reinforcement includes the preparation of the external water injection paths to the RCS and the spent fuel pool, a filtered containment venting system (CFVS), and AC power generating truck. Software improvement includes the increase of the effectiveness of the severe accident management guidance (SAMG) and plant staff training. To comply with NSSC's request, Wolsong Unit 1 has fulfilled the hardware reinforcement including the installation of a CFVS and started the extension of a SAMG to the low power and shutdown operation mode. Current SAMG deals accident occurred during full power operation only. The CFVS is designed to open and to close isolation valves manually. It does not require AC power. The operation of the CFVS prevents the reactor containment building failure due to the over-pressurization but it may release radioactive materials out of the reactor containment building. This paper discusses the radiological source terms for the containment vent strategy during severe accident progression which occurred during shutdown operation mode. This work is a part of the development of shutdown SAMG.. The CFVS is an effective means to control the containment pressure when the local air coolers are unavailable. Radioactive materials may release through the CFVS, but their amounts are reduced significantly. The alternative means, i.e., containment vent through the ventilation system which does not have an effective filter, is not a good choice to control the containment condition. It can maintain the containment

Analysis of failures in concrete containments

International Nuclear Information System (INIS)

Moreno-Gonzalez, A.

1989-09-01

The function of Containment, in an accident event, is to avoid the release of radioactive substances into the surroundings. Containment failure, therefore, is defined as the appearance of leak paths to the external environment. These leak paths may appear either as a result of loss of leaktightness due to degradation of design conditions or structural failure with containment material break. This document is a survey of the state of the art of Containment Failure Analysis. It gives a detailed description of all failure mechanisms, indicating all the possible failure modes and their causes, right from failure resulting from degradation of the materials to structural failure and linear breake failure. Following the description of failure modes, possible failure criteria are identified, with special emphasis on structural failure criteria. These criteria have been obtained not only from existing codes but also from the latest experimental results. A chapter has been dedicated exclusively to failure criteria in conventional structures, for the purpose of evaluating the possibility of application to the case of containment. As the structural behaviour of the containment building is very complex, it is not possible to define failure through a single parameter. It is therefore advisable to define a methodology for containment failure analysis which could be applied to a particular containment. This methodology should include prevailing load and material conditions together with the behaviour of complex conditions such as the liner-anchorage-cracked concrete interaction

Masonry Procedures. Building Maintenance. Module V. Instructor's Guide.

Science.gov (United States)

Eck, Francis

This curriculum guide, one of six modules keyed to the building maintenance competency profile developed by industry and education professionals, provides materials for a masonry procedures unit containing eight lessons. Lesson topics are masonry safety practices; set forms; mix concrete; patch and/or repair concrete; pour and finish concrete; mix…

AP1000 shield building: a constructability challenge

International Nuclear Information System (INIS)

Di Giuseppe, Giovanni; Bonanno, Domenico

2010-01-01

The AP1000 Shield Building, an enhanced structure which surrounds the containment vessel, consists of standard Reinforced Concrete (RC) and composite Steel and Concrete (SC) construction. In the SC module the surface steel plates, (with attached shear studs and angles) filled with concrete, act as the steel reinforcement in concrete. This is a relatively new design technology that required the appropriate use of structural codes, supplemented with information from applicable tests on similar composite steel and concrete construction. Being a newer design concept, existing codes do not provide explicit guidance on SC construction so a review of literature and test data on composite structures similar to AP1000 shield building was done in order to confirm the technical basis for the design. The SC walls, air inlet structure and roof of the Shield Building will be constructed using modular construction practices and then transported to site and lifted into place. These modules, working also as permanent form-work, will be filled with high strength Self- Consolidating Concrete. (SCC) This paper provides a focused and integrated presentation of the enhanced shield building design methodology, testing, constructability and inspection. (authors)

Analytical studies related to Indian PHWR containment system performance

International Nuclear Information System (INIS)

Haware, S.K.; Markandeya, S.G.; Ghosh, A.K.; Kushwaha, H.S.; Venkat Raj, V.

1998-01-01

Build-up of pressure in a multi-compartment containment after a postulated accident, the growth, transportation and removal of aerosols in the containment are complex processes of vital importance in deciding the source term. The release of hydrogen and its combustion increases the overpressure. In order to analyze these complex processes and to enable proper estimation of the source term, well tested analytical tools are necessary. This paper gives a detailed account of the analytical tools developed/adapted for PSA level 2 studies. (author)

Numerical analysis on thermal performance of roof contained PCM of a single residential building

International Nuclear Information System (INIS)

Li, Dong; Zheng, Yumeng; Liu, Changyu; Wu, Guozhong

2015-01-01

Highlights: • Thermal performance of different roofs in cold area of China are investigated. • Effects of five different conditions on thermal performance of roofs are analyzed. • Delay time of temperatures peak in PCM roofs are beyond 3 h than common roof. - Abstract: The phase change material (PCM) applied in the roof can decrease the building energy consumption and improve the thermal comfort by enhancing the thermal energy storage capacity of building envelope. In the present work, the thermal performance of different kinds of roofs with and without PCM in Northeast and cold area of China, i.e. common roof and PCM roofs, have been investigated numerically. This study also explored the influencing factors of thermal behavior of the roofs, such as solar radiation intensity, transition temperature and latent heat of PCM, roof slope, PCM layer thickness, and absorption coefficients of external roof surface. The results show that the PCM roofs effect on the temperature delay in the room is very strong and the delay time of temperatures peak of base layer in PCM roofs are beyond 3 h than common roof. The effect of transition temperature and latent heat of PCM on the thermal performance of roofs is relatively weak, compared with the roof slope, PCM layer thickness and absorption coefficients of external roof surface

FIRE EVACUATION FROM HIGH-RISE BUILDINGS

Directory of Open Access Journals (Sweden)

Korol'chenko Aleksandr Yakovlevich

2012-10-01

Full Text Available The authors argue that no collapse of structures is likely in the event of a fire emergency in multistoried buildings, rather, other fire-related factors may endanger the lives of people inside high-rise buildings exposed to the fire emergency, including open fire, sparks, high ambient temperature, smoke and toxic combustion products, reduced concentration of oxygen, and combined influence of various factors. In case of fire, the temperature inside buildings reaches 1100 °С. It exceeds the temperature of the ambient air acceptable for humans by far (70 °С. The experiments demonstrate that combustion products contain hundreds of toxic chemical compounds. The most hazardous of them include carbon oxide, carbon dioxide, chloride and cyanic hydrogen, aldehydes and acrolein. The author provides the pattern of their influence on the human body. The smoke consists of unburned particles of carbon and aerosols. The size of particles fluctuates within 0.05-50 MMK. Smoke produces a physiological and psychological impact on human beings. It has been proven that dangerous fire factors emerge within the first five to ten minutes of the emergency situation. Evacuation is the principal method of safety assurance. However, the velocity of propagation of smoke and heat is so high that even if the fire prevention system is in operation, people may be blocked both on the floors that are exposed to the fire and those that escape its propagation. New evacuation and rescue methods are recommended by the author. Various ways and methods of use of life-saving facilities are also provided. Safe evacuation is feasible from buildings where the number of stories does not exceed 10- 12. During evacuation, high density human streams are formed inside buildings, therefore, the period of stay in a burning building is increased. The calculations have proven that a two-minute delay of evacuation converts into a safe evacuation of only 13-15% of people. Low reliability of

Hawaii demand-side management resource assessment. Final report, Reference Volume 1: Building prototype analysis

Energy Technology Data Exchange (ETDEWEB)

NONE

1995-04-01

This report provides a detailed description of, and the baseline assumptions and simulation results for, the building prototype simulations conducted for the building types designated in the Work Plan for Demand-side Management Assessment of Hawaii`s Demand-Side Resources (HES-4, Phase 2). This report represents the second revision to the initial building prototype description report provided to DBEDT early in the project. Modifications and revisions to the prototypes, based on further calibration efforts and on comments received from DBEDT Staff have been incorporated into this final version. These baseline prototypes form the basis upon which the DSM measure impact estimates and the DSM measure data base were developed for this project. This report presents detailed information for each of the 17 different building prototypes developed for use with the DOE-21E program (23 buildings in total, including resorts and hotels defined separately for each island) to estimate the impact of the building technologies and measures included in this project. The remainder of this section presents some nomenclature and terminology utilized in the reports, tables, and data bases developed from this project to denote building type and vintage. Section 2 contains a more detailed discussion of the data sources, the definition of the residential sector building prototypes, and results of the DOE-2 analysis. Section 3 provides a similar discussion for the commercial sector. The prototype and baseline simulation results are presented in a separate section for each building type. Where possible, comparison of the baseline simulation results with benchmark data from the ENERGY 2020 model or other demand forecasting models specific to Hawaii is included for each building. Appendix A contains a detailed listing of the commercial sector baseline indoor lighting technologies included in the existing and new prototypes by building type.

Building performance simulation for sustainable buildings

NARCIS (Netherlands)

Hensen, J.L.M.

2010-01-01

This paper aims to provide a general view of the background and current state of building performance simulation, which has the potential to deliver, directly or indirectly, substantial benefits to building stakeholders and to the environment. However the building simulation community faces many

Development of Latent Heat Storage Phase Change Material Containing Plaster

Directory of Open Access Journals (Sweden)

Diana BAJARE

2016-05-01

Full Text Available This paper reviews the development of latent heat storage Phase Change Material (PCM containing plaster as in passive application. Due to the phase change, these materials can store higher amounts of thermal energy than traditional building materials and can be used to add thermal inertia to lightweight constructions. It was shown that the use of PCMs have advantages stabilizing the room temperature variations during summer days, provided sufficient night ventilation is allowed. Another advantage of PCM usage is stabilized indoor temperature on the heating season. The goal of this study is to develop cement and lime based plaster containing microencapsulated PCM. The plaster is expected to be used for passive indoor applications and enhance the thermal properties of building envelope. The plaster was investigated under Scanning Electron Microscope and the mechanical, physical and thermal properties of created plaster samples were determined.

Using containers with ATLAS offline software

CERN Document Server

Vogel, Marcelo; The ATLAS collaboration

2017-01-01

This paper describes the deployment of ATLAS offline software in containers for software development. For this we are using Docker, which is a lightweight virtualization technology that encapsulates a piece of software inside a complete file system. The deployment of offline releases via containers removes the strict requirement of compatibility between the runtime environment needed for job execution and the configuration of worker nodes at computing sites. If these two are decoupled from each other, sites can upgrade their nodes whenever and however they see fit. In this work, ATLAS software is distributed in containers either via the CernVM File System (CVMFS) or by means of a full ATLAS offline release installation. In software development, separating the build and runtime environment from the development environment allows users to take advantage of many modern code development tools that may not be available in production runtime setups like SLC6. It also frees developers from depending on resources lik...

MALAYSIAN WEATHER DATA (TRY) FOR ENERGY SIMULATIONS IN BUILDINGS

DEFF Research Database (Denmark)

Reimann, Gregers Peter

2001-01-01

Detailed energy simulations for buildings in Malaysia have become possible after the recent construction of a Malaysian TRY (Test Reference Year) based on 21 years of hourly weather data from Subang Meteorological Station. The climatic parameters contained in the TRY are dry bulb temperature, wet...

19 CFR 10.539 - Retail packaging materials and containers.

Science.gov (United States)

2010-04-01

...-Singapore Free Trade Agreement Rules of Origin § 10.539 Retail packaging materials and containers. Packaging... requirement. The United States importer of good C decides to use the build-down method, RVC=((AV−VNM)/AV... content requirement. In applying this method, the non-originating blister packages are taken into account...

Containment venting as a mitigation technique for BWR MARK I plant ATWS

International Nuclear Information System (INIS)

Harrington, R.M.

1987-01-01

Containment venting is studied as a mitigation strategy for preventing or delaying severe fuel damage following hypothetical BWR Anticipated Transient Without Scram (ATWS) accidents initiated by MSIV-closure, and compounded by failure of the Standby Liquid Control (SLC) system injection of sodium pentaborate solution and by the failure of manually initiated control rod insertion. The venting of primary containment after reaching 75 psia (0.52 MPa) is found to result in the release of the vented steam inside the reactor building, and to result in inadequate Net Positive Suction Head (NPSH) for any system pumping from the pressure suppression pool. CONTAIN code calculations show that personnel access to large portions of the reactor building would be lost soon after the initiation of venting and that the temperatures reached would be likely to result in independent equipment failures. It is concluded that containment venting would be more likely to cause or to hasten the onset of severe fuel damage than to prevent or to delay it. Two alternative strategies that do not require containment venting, but that could delay or prevent severe fuel damage, are analyzed. BWR-LTAS code results are presented for a successful mitigation strategy in which the reactor vessel is depressurized, and for one in which the reactor vessel remains at pressure

Geophysics: Building E5476 decommissiong, Aberdeen Proving Ground

International Nuclear Information System (INIS)

Miller, S.F.; Thompson, M.D.; McGinnis, M.G.; McGinnis, L.D.

1992-11-01

Building E5476 was one of ten potentially contaminated sites in the Canal Creek and Westwood areas of the Edgewood section of Aberdeen Proving Ground examined by a geophysical team from Argonne National Laboratory in April and May of 1992. Noninvasive geophysical surveys, including magnetics, electrical resistivity, and ground-penetrating radar, were conducted around the perimeter of the building to guide a sampling program prior to decommissioning and dismantling. The large number of magnetic sources surrounding the building are believed to be contained in construction fill. The smaller anomalies, for the most part, were not imaged with ground radar or by electrical profiling. Large magnetic anomalies near the southwest comer of the building are due to aboveground standpipes and steel-reinforced concrete. Two high-resistivity areas, one projecting northeast from the building and another south of the original structure, may indicate the presence of organic pore fluids in the subsurface. A conductive lineament protruding from the south wall that is enclosed by the southem, high-resistivity feature is not associated with an equivalent magnetic anomaly. Magnetic and electrical anomalies south of the old landfill boundary are probably not associated with the building. The boundary is marked by a band of magnetic anomalies and a conductive zone trending northwest to southeast. The cause of high resistivities in a semicircular area in the southwest comer, within the landfill area, is unexplained

Building a capacity building manual

CSIR Research Space (South Africa)

Clinton, DD

2010-02-01

Full Text Available Organizations 2010 Building a capacity building manual Daniel D. Clinton, Jr., P.E., F.NSPE Chair, WFEO Capacity Building Committee Dr Andrew Cleland, FIPENZ, Chief Executive, IPENZ, NZ Eng David Botha, FSAICE, Executive Director, SAICE, SA Dawit... 2010 Tertiary level University curricula Coaches and mentors Facilities EXCeeD Remuneration of Academics Experiential training Outreach to Students Students chapters Young members forum World Federation of Engineering Organizations 2010 Post...

Overpressurization performance of containment structures

International Nuclear Information System (INIS)

Barr, P.; Bleackley, M.; Harrop, L.P.; Hargreaves, J.; Jowett, J.; Phillips, D.W.

1987-01-01

The containment building of a PWR is the outermost engineered barrier between the reactor and the environment. The most important element of such a containment system is the pressure boundary structure and its associated seals and penetrations. This containment structure is designed deterministically to withstand a number of loads and load combinations of which the dominant one is generally the internal pressure due to the double-ended guillotine break in one of the primary circuit loops. Typically, the design basis large LOCA produces a peak pressure increase in the region of 0.3 MPa in some 10 seconds and with a duration of up to a few tens of seconds. The assessment of overpressure performance of the containment structure is a key component of the PWR safety case, and is usually carried out by estimating a static factor of safety to some failure limit state. These estimates can be made using simple force-balance calculations or complicated finite element calculations, and both approaches have merit. In this paper we examine these approaches and discuss their value in estimating failure pressures and failure modes for a variety of internal pressurization transients. This discussion covers both general design and risk considerations and is illustrated by numerical examples taken from previous and on-going analysis

Composite containment for nuclear power

International Nuclear Information System (INIS)

Harstead, G.A.; Soeoet, O.

1977-01-01

Fundamentally, a nuclear reactor containment structure provides three major functions; namely, (1), to withstand loads due to pressure and temperature increase due to Design Basis Accident (DBA) (2), to withstand environmental loads such as seismic, tornado and normal loads, and (3) act as a radiation shield. Conventional design practise is to employ either a steel vessel and concrete shield building or a steel lined concrete structure. This paper deals with a new concept in which a steel liner is employed which carries much of the primary membrane loads. This type of structure is similar in some aspects to the previously described systems: a) A mat, lined with a thin plate on its top surface, is similar to concrete containment. b) A cylinder and hemispherical dome, made up of steel plate and concrete, is about 2.5 feet thick (the minimum required for radiation shielding). Although the steel plate and concrete are in contact, as in concrete containment, the steel plate in composite containment is much thicker than the liner. There are two main advantages over present practise; namely reduction of materials and therefore reduced capital cost and even more significantly a shortened construction schedule which will permit more flexibility in overall plant construction schedule and will benefit the cash flow situation. (Auth.)

Certification of building thermographers: experiences after three courses

Science.gov (United States)

Kauppinen, Timo; Hekkanen, Martti; Paloniitty, Sauli; Krankka, Juha

2006-04-01

The certification procedure of building thermographers was started in 2003, even though thermography has been used in Finland in building survey since late 70's. There has been about a 25 years' unorganized and more or less wild period, without any generally accepted rules for interpretation, as well as how to order thermography services, how to report the results, how to do the practical work in the buildings etc. The service was provided by consultants with varied backgrounds. More operators have come into the market and building developers and contractors have begun to use thermography for quality control in new building and in renovation planning. In the year 2004 various organizations in building trade launched a pilot project to certificate building thermographers. The structure and the topics of the course were introduced in Thermosense 2005. By the end of the year 2005 the third course was completed. From the beginning of the procedure to the end of the third course about 40 persons have received a certificate. During the certification process, two guidelines have been published, as part of RT (Building Information) - files: instructions for ordering, for practical field work and for reporting of thermography survey in buildings. The guidelines also contain basics for interpretation. The interpretation is consistent with the other existing directions (building codes etc). At the turn of 2005 - 2006 a new book of building thermography was published. There is still lack of comprehensive as well as unambiguous rules for interpretation. In the paper we will present experiences on the courses, the main problems posed to the participants and findings during the last two - three years' field work. We will also introduce briefly the structure and content of the guidelines and an example how to use thermography as a tool of quality control in new building. The case studies are new one-family houses in a housing fair and exhibition area in the city of Oulu.

Numerical model for stack gas diffusion in terrain with buildings. Variations in air flow and gas concentration with additional building near stack

International Nuclear Information System (INIS)

Sada, Koichi; Michioka, Takenobu; Ichikawa, Yoichi; Komiyama, Sumito; Numata, Kunio

2009-01-01

A numerical simulation method for predicting atmospheric flow and stack gas diffusion using a calculation domain of several km around a stack under complex terrain conditions containing buildings has been developed. The turbulence closure technique using a modified k-ε-type model without a hydrostatic approximation was used for flow calculation, and some of the calculation grids near the ground were treated as buildings using a terrain-following coordinate system. Stack gas diffusion was predicted using the Lagrangian particle model, that is, the stack gas was represented by trajectories of released particles. The developed numerical model was applied to a virtual terrain and building conditions in this study prior to the applications of a numerical model for real terrain and building conditions. The height of the additional building (H a ), located about 200 m leeward from the stack, was varied (i.e., H a =0, 20, 30 and 50 m), and its effects on airflow and the concentration of stack gas at a released height of 75 m were calculated. Furthermore, effective stack height, which was used in the safety analysis of atmospheric diffusion for nuclear facilities in Japan, was evaluated from the calculated ground-level concentration of stack gas. The cavity region behind the additional building was calculated, and turbulence near the cavity was observed to decrease when the additional building was present. According to these flow variations with the additional building, tracer gas tended to diffuse to the ground surface rapidly with the additional building at the leeward position of the cavity, and the ground-level stack gas concentration along the plume axis also increased with the height of the additional building. However, the variations in effective stack height with the height of the additional building were relatively small and ranged within several m in this study. (author)

Research and development strategy on the behavior of containments during severe accidents

International Nuclear Information System (INIS)

Lecomte, C.

1990-06-01

In case of an hypothetical severe accident leading to core melting, the last barrier preventing radionucleide release in the environnment is the containment of the main reactor building. The French research and development programmes aimed at understanding the containment behavior during severe accidents relate to several domains; some of them are: - assessment of hydrogen behavior - corium behavior and coolability - ultimate resistance of the containments and leaktightness - caracterization of filtered venting procedure. All these aspects are covered by code calculations and experimental developments

Data on the interaction between thermal comfort and building control research.

Science.gov (United States)

Park, June Young; Nagy, Zoltan

2018-04-01

This dataset contains bibliography information regarding thermal comfort and building control research. In addition, the instruction of a data-driven literature survey method guides readers to reproduce their own literature survey on related bibliography datasets. Based on specific search terms, all relevant bibliographic datasets are downloaded. We explain the keyword co-occurrences of historical developments and recent trends, and the citation network which represents the interaction between thermal comfort and building control research. Results and discussions are described in the research article entitled "Comprehensive analysis of the relationship between thermal comfort and building control research - A data-driven literature review" (Park and Nagy, 2018).

Effect of Operating Pressure on Hydrogen Risk in Filtered Containment Venting System

Energy Technology Data Exchange (ETDEWEB)

Na, Young Su; Cho, Song-Won; Ha, Kwang Soon [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

2016-10-15

The FCVS (Filtered Containment Venting System) has the main objectives of both the depressurization in the containment building and the decontamination of fission products generated under a severe accident. One of the commercial wet-type FCVSs consists of a cylindrical pressure vessel including a scrubbing solution and filters. A FCVS vessel can be installed on the outside of the containment building, and is connected with the containment through a pipe. When the pressure in the containment building approaches the setting value, a valve on a pipe between the containment and the FCVS opens to operate the FCVS. The amount of steam and gas mixtures generated under a severe accident can be released into the FCVS, where the nozzles of a pipe are submerged into a scrubbing solution in a FCVS vessel. Non-condensable gases and fine aerosols can enter a scrubbing solution, and they then pass the filters. The decontaminated gases are finally discharged from the FCVS into the outside environment. Previous studies have introduced critical issues with the operation of the FCVS. Reference [2] assessed the effect of the operating pressure of the FCVS on the hydrogen risk in a FCVS vessel. The volumetric concentrations of hydrogen and steam in a postulated FCVS with a 3 m diameter and 6.5 m height were calculated using the MELCOR computer code (v. 1.8.6). After the operation of the FCVS, the pressure and temperature in the FCVS vessel jumped from the initial conditions of the atmosphere pressure and room temperature. For the FCVS operating pressure of 5 bar, the hydrogen concentration increased from 6% in the containment to 14% in a FCVS vessel, whereas the steam concentration decreased from 58% in the containment to 3% in a FCVS vessel. The increased hydrogen concentration with air in a FCVS vessel can exists within the region of the burn limit in the Shapiro diagram. This possibility of the hydrogen combustion can threaten the integrity of the FCVS. To mitigate the hydrogen risk

Ultimate load model test for Sizewell 'B' primary containment

International Nuclear Information System (INIS)

Crowder, R.

1988-01-01

This paper considers the factors influencing the adoption of an ultimate load factor for the Sizewell 'B' PWR primary containment structure. As part of the validation process for the ultimate load analysis method, a proposal has been made by Nuclear Design Associates to build and test a 1/10th scale model of the containment structure, which would proceed following the granting of section 2 consent for Sizewell 'B'. The modelling principles, construction method and test proposals are examined in some detail. The proposal is currently being considered by the CEGB's Project Management Team. (author)

CONTEMPT: computer program for predicting containment pressure-temperature response to a loss-of-coolant accident

International Nuclear Information System (INIS)

Hsii, Y.H.

1978-04-01

The CONTEMPT code is used by Babcock and Wilcox for containment analysis following a postulated loss of coolant accident. An additional model is described which is used for the calculation of long term post reflood mass and energy releases to the containment that is used for the containment design basis LOCA calculations. These calculations maximize the rate of energy flow to the containment. The mass and energy data are given to the containment designer for use in calculating the containment building design pressure and temperature and in sizing containment heat removal equipment

Bellanca building, Yellowknife : building envelope retrofit project

Energy Technology Data Exchange (ETDEWEB)

Rajewski, G. [A.D. Williams Engineering Inc., Edmonton, AB (Canada)

2008-07-01

The Bellanca building is a ten-story, commercial office building, located in Yellowknife, Northwest Territories. The owner was concerned about annual fuel consumption, relative to other buildings of similar size. Tenants reported cold drafts and some ice build-up had been reported in the past, on the exterior of the cladding. In addition, some water penetration had occurred during rainfall. This presentation provided background information on the Bellanca building and discussed a building envelope retrofit project. A.D. Williams was hired in late 2006 in order to provide an opinion on the present condition of the building envelope. This presentation described the site investigation and presented an interior and exterior review of the building. It also presented a thermographic survey in order to map thermal anomalies and establish trends. Following acceptance of the report on findings, one of five options was selected for further development. This included removal of existing cladding, exterior gypsum wallboard, fiberglass insulation and application of BASF Walltite CT foam, sheathing, rigid insulation, drainage plane and new cladding. The preliminary design was then presented. This paper also described the tender and award of the contract; construction phase; and substantial completion of the project. tabs, figs.

Smart buildings: Energy efficient conditioning of building occupants

NARCIS (Netherlands)

Zeiler, W.; Houten, van M.A.; Boxem, G.; Vehler, R.; Verhoeven, M.; Fremouw, M.

2009-01-01

To further optimize energy performance of buildings, intelligent building control offers new possibilities. Intelligent Software Agents (ISA) can be implemented at different levels of building automation. Individual agents for individual climate control for each user of the building in combination

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.

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

International Nuclear Information System (INIS)

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

Building online genomics applications using BioPyramid.

Science.gov (United States)

Stephenson, Liam; Wakeham, Yoshua; Seidenman, Nick; Choi, Jarny

2018-03-29

BioPyramid is a python package, which serves as a scaffold for building an online application for the exploration of gene expression data. It is designed for bioinformaticians wishing to quickly share transformed data and interactive analyses with collaborators. Current R-based tools similarly address the need to quickly share "omics"-data in an exploratory format, but these are generally small-scale, single-dataset solutions. Biopyramid is written in python pyramid framework and scalable to address longer-term or more complex projects. It contains a number of components designed to reduce the time and effort in building such an application from scratch, including gene annotation, dataset models and visualisation tools. Freely available at http://github.com/jarny/biopyramid. Implemented in python and javascript. jarnyc@unimelb.edu.au.

Measurement of natural radioactivity in building materials used in Urumqi, China.

Science.gov (United States)

Ding, Xiang; Lu, Xinwei; Zhao, Caifeng; Yang, Guang; Li, Nan

2013-07-01

Building materials contain natural radionuclides (226)Ra, (232)Th and (40)K, which cause direct radiation exposure of the public. The concentrations of (226)Ra, (232)Th and (40)K in commonly used building materials of Urumqi, China have been analysed using gamma-ray spectrometry. The concentrations of (226)Ra, (40)K and (232)Th in the studied building materials range from 19.8 to 87.4, from 273.3 to 981.2 and from 11.6 to 47.7 Bq kg(-1), respectively. The radium equivalent activity (Raeq), gamma index (Iγ) and alpha index (Iα) were calculated to assess the radiation hazards to people living in dwellings made of the materials studied. The calculated Raeq values of all the building materials are lower than the limit of 370 Bq kg(-1) for building materials. The values of Iγ and Iα of all the building materials are less than unity. The study shows that these materials may be safely used as construction materials and do not pose significant radiation hazards.

Ketenimines Generated from Ynamides: Versatile Building Blocks for Nitrogen-Containing Scaffolds.

Science.gov (United States)

Dodd, Robert H; Cariou, Kevin

2018-02-16

Using ynamides as readily available starting materials, a single step can generate highly reactive ketenimines, which can then undergo a variety of transformations. The choice of the method for generating the ketenimine dictates the outcome of the reaction that can, moreover, be precisely steered through minor variations of the starting material. This Concept gives an overview of the different existing methodologies for this objective, showcasing the diverse nitrogen-containing frameworks that can be obtained by this highly versatile strategy. © 2018 Wiley-VCH Verlag GmbH & Co. KGaA, Weinheim.

Translate the cradle to cradle principles for a building

NARCIS (Netherlands)

van de Westerlo, Bas; Halman, Johannes I.M.; Durmisevic, Elma; Durmisevic, E.; Pasic, A.

2012-01-01

Various guidelines for Cradle to Cradle in the built environment were established since 1992. However, it’s not clear how the Cradle to Cradle principles can be translated to the realization of a building. This paper contains information from literature with a focus on applying the Cradle to Cradle

Occupational Education for Students with Special Needs: Building Maintenance.

Science.gov (United States)

Nassau County Board of Cooperative Educational Services, Westbury, NY.

This curriculum resource guide on building maintenance is one of a series of seventeen specialized curriculum guides for occupational education of the marginal, handicapped, or special needs occupational education student. The guide begins with six behavior clusters that contain a series of forty-two instructional topics designed to teach…

Global building inventory for earthquake loss estimation and risk management

Science.gov (United States)

Jaiswal, Kishor; Wald, David; Porter, Keith

2010-01-01

We develop a global database of building inventories using taxonomy of global building types for use in near-real-time post-earthquake loss estimation and pre-earthquake risk analysis, for the U.S. Geological Survey’s Prompt Assessment of Global Earthquakes for Response (PAGER) program. The database is available for public use, subject to peer review, scrutiny, and open enhancement. On a country-by-country level, it contains estimates of the distribution of building types categorized by material, lateral force resisting system, and occupancy type (residential or nonresidential, urban or rural). The database draws on and harmonizes numerous sources: (1) UN statistics, (2) UN Habitat’s demographic and health survey (DHS) database, (3) national housing censuses, (4) the World Housing Encyclopedia and (5) other literature.

Waterford Institute of Technology, Tourism and Leisure Building

Directory of Open Access Journals (Sweden)

Chris Croly

2012-04-01

Full Text Available The Tourism and Leisure Building at Waterford Institute of Technology contains all of the passive design elements that would be expected in a landmark environmentally-conscious educational development. The design however also addresses energy conservation in complex, high-energy kitchen systems in an innovative way, bringing a new level of environmental performance to catering in Ireland.

Building a Disciplinary Metadata Standards Directory

Directory of Open Access Journals (Sweden)

Alexander Ball

2014-07-01

Full Text Available The Research Data Alliance (RDA Metadata Standards Directory Working Group (MSDWG is building a directory of descriptive, discipline-specific metadata standards. The purpose of the directory is to promote the discovery, access and use of such standards, thereby improving the state of research data interoperability and reducing duplicative standards development work.This work builds upon the UK Digital Curation Centre's Disciplinary Metadata Catalogue, a resource created with much the same aim in mind. The first stage of the MSDWG's work was to update and extend the information contained in the catalogue. In the current, second stage, a new platform is being developed in order to extend the functionality of the directory beyond that of the catalogue, and to make it easier to maintain and sustain. Future work will include making the directory more amenable to use by automated tools.

Dry storage developments in France build on CASCAD experience

International Nuclear Information System (INIS)

Bonnet, C.; Giraud, C.

1992-01-01

The CASCAD dry store, located at CEA's research centre at Cadarache, stores spent fuel from the EL4 heavy water reactor and the Osiris research reactor. The design was based on the following criteria: Storage period. Interim storage is provided for 50 years. Containment. The fuel is contained by a multiple barrier system consisting of: the fuel canister (primary barrier); the sealed stainless steel storage well; and the storage building which includes a ventilation system to provide dynamic containment during handling operations. The fuel is loaded into canisters at the reactor site to avoid contamination in the storage building. The integrity of the primary barrier is periodically monitored by sampling of air from the storage well. Cooling. The storage wells are cooled by a natural convection system that maintains the temperature of the fuel below its stated limit and the temperature of the concrete below 80 o C. Criticality. Criticality incidents are prevented by static design measures such as maintaining a minimum pitch between storage wells and providing sufficient storage well diameter. Radiation protection. Radiation shielding limits the maximum equivalent dose rate for operating personnel to less than 25μSv/h at the handling cell floor and the wall adjoining the control room, and to less than 7.5μSv/h at the outside walls of the storage building. Cannister design. The canister must resist corrosion caused by condensation as well as pressure due to radiolytic gases. The canister must also withstand a drop of up to 10m without losing its integrity. The design has now been adapted to accommodate light reactor fuels and is known as CASCAD+. (Author)

The Share of Preservation Issues when Planning a Library Building

Directory of Open Access Journals (Sweden)

Marie-Thérèse Varlamoff

2002-07-01

Full Text Available Primarily and historically a library was a place where books or manuscripts were kept. „ Thékos” means warehouse or storage area in Greek. But nowadays a library is more than a depository. It is also a place where you can read books and access the information they contain. In the case of a new building or of the rehabilitation of an old building it might also serve as a showcase for politicians or decision makers. Hence the necessity to combine preservation issues, accessibility and architecture.

Danish building typologies and building stock analyses

DEFF Research Database (Denmark)

Wittchen, Kim Bjarne; Kragh, Jesper

energy savings in residential buildings. The intension with this analysis was to investigate the possible energy reduction in Denmark if the same approach had been taken for the entire Danish building stock. The report concludes that the ZeroHome initiative clearly results in energy savings, but far from...... enough to meet the government’s plan to make Danish buildings free from use of fossil fuels by 2035. This will probably require around 50 % energy savings in the Danish building stock as a whole. However, the project has proven that dedicated engagement of locals can speed up market penetration...... for energy savings in the existing Building stock....

NRC new sustainable building

International Nuclear Information System (INIS)

Semczyszyn, D.

2004-01-01

'Full text:' The National Research Council Institute For Fuel Cell Innovation is relocating to a purpose-built 71,343 sq. Ft. (6598 sq. M) Research, Testing, Evaluation, and Industry Incubation Facility in the spring of 2006. The new facility will contain Hydrogen-ready laboratories, the existing relocated Hydrogen Safe Environmental Test Chamber, a hydrogen vehicle maintenance bay, a hydrogen vehicle refuelling station, and the following demonstration projects and features: 1. A Ground Source Heat Pump: This long-proven natural-source heating and cooling technology to provide climate control for the new IFCI's atrium and galleria. It is being designed by Keen Engineering of North Vancouver, BC. 2. 5 KW Solid Oxide Fuel Cell System: Fuelled by natural gas and in the future, from biomass, the fuel cell will also produce approximately 15 kW of waste heat, which will be captured and used to supply heat for the building. The Solid Oxide Fuel Cell will be supplied by Fuel Cell Technologies in Kingston, ON. 3. LEED Building certification: Attaining LEED 'green building' certification is considered an important complement to the plans for the new NRC-IFCI, because it will provide respected third-party verification of government's commitment to efficient building design and construction. Project architects Bunting Coady of Vancouver, BC believe the IFCI has strong potential to earn gold LEED certification. 4. Photovoltaic hydrogen source for back-up power fuel cell system: A photovoltaic array will capture energy from sunlight to power an electrolyzer that will produce and store hydrogen for a PEM fuel cell emergency backup power system. The electrolyzer will be provided by Hydrogenics of Mississauga, ON. Photovoltaics are being designed and installed by the British Columbia Institute of Technology. (author)

Being in a "Green" Building Elicits "Greener" Recycling, but Not Necessarily "Better" Recycling.

Science.gov (United States)

Wu, David W-L; DiGiacomo, Alessandra; Lenkic, Peter J; Wong, Vanessa K; Kingstone, Alan

2016-01-01

Previous observational work revealed that transient populations in a sustainable building disposed of waste more accurately when compared to patrons in a non-sustainable building. The current study uses an experimental design to replicate this observed effect and to investigate whether or not the built environment influences motivational factors to impact behavior. We find support that a building designed and built to communicate an atmosphere of sustainability can influence waste disposal behavior. Participants in the sustainable building used the garbage receptacle significantly less and compensated by tending to select the containers and organics receptacle more, which actually resulted in more errors overall. Our findings suggest that building atmospherics can motivate people to recycle more. However, atmospherics alone do not appear to be sufficient to elicit the desired performance outcome.

Feasibility Study to Reduce Thermal Resistance of Finned Containment Wall in Simplified OPR1000

Energy Technology Data Exchange (ETDEWEB)

Lee, Jong Hwi; Kang, Hie Chan [Kunsan National University, Gunsan (Korea, Republic of); Noh, Hyung Gyun [Pohang University, Pohang (Korea, Republic of)

2016-05-15

This concept is securing of cooling capability by using finned containment itself, it could be another alternative for achieving decompression of containment as heat sink. The objective of this study is a feasibility test to estimate the heat transfer performance from the finned containment wall in case of OPR1000. The commercial code, ANSYS CFX 16 was used in this work. The number of grids is about 1.8 million. Therefore, 250mm rebar affects more considerable than that of 50mm to the temperature distribution. For this reasons, temperature distribution of z-axis direction was showed significant changes in (c). The heat transfer in three types of containment was 267.6W, 265.2W and 307.8W, respectively. The Type B case increased up to 15% of heat transfer than the baseline containment building. Three different types of containment wall were tested by numerical simulation to understand the cooling performance of finned containment wall. We can conclude as follows: For the finned containment wall type A that fins are installed inside and outside with the same rebar configuration of conventional containment building, the heat transfer is almost the same as conventional containment wall. The finned containment wall type B that volume fraction of rebar is increased transfer the heat 15% more compared with conventional one. The cross-sectional area or volume fraction of the rebar to attach fin is important to enhance the heat transfer. The fin efficiency of the fin is very low as 3.1% in the present cases.

Effects of secondary containment air cleanup system leakage on the accident offsite dose as determined during preop tests of the Sequoyah Nuclear Plant

International Nuclear Information System (INIS)

Klaes, L.J.; Nass, S.A.; Proctor, L.D.

1981-01-01

The Sequoyah Nuclear Plant has two secondary containments. One is the annular region between the primary containment and the shield building surrounding the primary containment. The second is the auxiliary building secondary containment enclosure which is potentially subject to direct airborne radioactivity. Two air cleanup systems are provided to serve these areas. The emergency gas treatment system (EGTS) serves the annulus between the primary containment and the shield building, and the auxiliary building gas treatment system (ABGTS) serves the area inside of the auxiliary building secondary containment enclosure. The major function served by these air cleanup systems is that of controlling and processing airborne contamination released in these areas during any accident up to a design basis accident. This is accomplished by (1) creating a negative pressure in the areas served to ensure that no unprocessed air is released to the atmosphere, (2) providing filtration units to process all air exhausted from the secondary containment spaces, and (3) providing a low-leakage enclosure to limit exhaust flows. Offsite dose effects due to secondary containment release rates, bypass leakage, and duct and damper leakages are presented and parameter variations are considered. For the EGTS, a recirculation system, the most important parameter is the total inleakage of the system which causes an increase in both whole body (gamma) and thyroid (iodine) doses. For the ABGTS, a once-through system, the most important paramter is the inleakage which bypasses the filters resulting in an increase in the thyroid dose only. Actual preoperational test data are utilized. Problems encountered during the preop test are summarized. Solutions incorporated to bring the EGTS and ABGTS air cleanup systems within the test acceptance criteria required to meet offsite dose limitations are discussed and the resultant calculated offsite dose is presented

Analyses of a steel containment vessel with an outer contact structure under severe internal overpressurization conditions

International Nuclear Information System (INIS)

Porter, V.L.

1994-01-01

Many Mark-I and Mark-II BWR plants are designed with a steel vessel as the primary containment. Typically, the steel containment vessel (SCV) is enclosed within a reinforced concrete shield building with only a small gap (74-90 mm) separating the two structures. This paper describes finite element analyses performed to evaluate the effects of contact and friction between a steel containment vessel and an outer contact structure when the containment vessel is subjected to large internal pressures. These computations were motivated by a joint program on containment integrity involving the Nuclear Power Engineering Corporation (NUPEC) of Japan, the US Nuclear Regulatory Commission (NRC), and Sandia National Laboratories for testing model containments. Under severe accident loading conditions, the steel containment vessel in a typical Mark-I or Mark-II plant may deform under internal pressurization such that it contacts the inner surface of a shield building wall. (Thermal expansion from increasing accident temperatures would also close the gap between the SCV and the shield building, but temperature effects are not considered in these analyses.) The amount and location of contact and the pressure at which it occurs all affect how the combined structure behaves. A preliminary finite element model has been developed to analyze a model of a typical steel containment vessel con-ling into contact with an outer structure. Both the steel containment vessel and the outer contact structure were modelled with axisymmetric shell finite elements. Of particular interest are the influence that the contact structure has on deformation and potential failure modes of the containment vessel. Furthermore, the coefficient of friction between the two structures was varied to study its effects on the behavior of the containment vessel and on the uplift loads transmitted to the contact structure. These analyses show that the material properties of an outer contact structure and the amount

Tritium concentration reducing method in atmosphere in nuclear reactor containment facility

International Nuclear Information System (INIS)

Hirasawa, Yoshiya; Kigoshi, Yasutane; Yonenaga, Haruo.

1992-01-01

A portion of water content in an atmosphere is condensed by a condensation/evaporation device disposed in a nuclear reactor containment building and then a portion of the condensed water is evaporated in the atmosphere. A portion of hydrogen nuclides constituting the evaporated water content is subjected to isotopic exchange with tritium nuclides in the atmosphere. A portion of water content in the atmosphere applied with the isotopic exchange is condensed in the condensation/evaporation device. That is, the hydrogen nuclides in steams are applied with isotopic exchange with tritium nuclides, and steams incorporating tritium nuclides are condensed again in the condensation/evaporation device, to transfer the tritium nuclides in the atmosphere to condensed water. The condensed water is recovered without releasing the tritium nuclides to the outside of the reactor containment building, thereby enabling to reduce the tritium concentration in the atmosphere. (N.H.)

SOLAR RADIATION ESTIMATION ON BUILDING ROOFS AND WEB-BASED SOLAR CADASTRE

Directory of Open Access Journals (Sweden)

G. Agugiaro

2012-07-01

Full Text Available The aim of this study is the estimation of solar irradiance on building roofs in complex Alpine landscapes. Very high resolution geometric models of the building roofs are generated by means of advanced automated image matching methods. Models are combined with raster and vector data sources to estimate the incoming solar radiation hitting the roofs. The methodology takes into account for atmospheric effects, site latitude and elevation, slope and aspect of the terrain as well as the effects of shadows cast by surrounding buildings, chimneys, dormers, vegetation and terrain topography. An open source software solution has been developed and applied to a study area located in a mountainous site and containing some 1250 residential, commercial and industrial buildings. The method has been validated by data collected with a pyranometer and results made available through a prototype WebGIS platform.

Overview of the Westinghouse Small Modular Reactor building layout

Energy Technology Data Exchange (ETDEWEB)

Cronje, J. M. [Westinghouse Electric Company LLC, Centurion (South Africa); Van Wyk, J. J.; Memmott, M. J. [Westinghouse Electric Company LLC, Cranberry Township, PA (United States)

2012-07-01

The Westinghouse Small Modular Reactor (SMR) is an 800 MWt (>225 MWe) integral pressurized water reactor (iPWR), in which all of the components typically associated with the nuclear steam supply system (NSSS) of a nuclear power plant are incorporated within a single reactor pressure vessel. This paper is the third in a series of four papers, which describe the design and functionality of the Westinghouse SMR. It focuses in particular upon the plant building layout and modular design of the Westinghouse SMR. In the development of small modular reactors, the building layout is an area where the safety of the plant can be improved by applying new design approaches. This paper will present an overview of the Westinghouse SMR building layout and indicate how the design features improve the safety and robustness of the plant. The Westinghouse SMR is designed with no shared systems between individual reactor units. The main buildings inside the security fence are the nuclear island, the rad-waste building, the annex building, and the turbine building. All safety related equipment is located in the nuclear island, which is a seismic class 1 building. To further enhance the safety and robustness of the design, the reactor, containment, and most of the safety related equipment are located below grade on the nuclear island. This reduces the possibility of severe damage from external threats or natural disasters. Two safety related ultimate heat sink (UHS) water tanks that are used for decay heat removal are located above grade, but are redundant and physically separated as far as possible for improved safety. The reactor and containment vessel are located below grade in the center of the nuclear island. The rad-waste and other radioactive systems are located on the bottom floors to limit the radiation exposure to personnel. The Westinghouse SMR safety trains are completely separated into four unconnected quadrants of the building, with access between quadrants only allowed

Modular development mat reinforcing and liners containment/annulus building. Final report supplement. Volume I

International Nuclear Information System (INIS)

Wainrib, J.

1978-06-01

The feasibility of developing a modular system approach for the construction of containment mats has been established. The investigative results obtained from a plant used for the modular study has determined that (1) modularization results in a 10-week reduction in the construction schedule critical path over that for the conventional approach, and (2) modularization is cost effective and could result in a savings of approximately $10,700,000. Accordingly, it is recommended that the modular system approach be adopted as standard practice for the construction of containment mats

Geophysics: Building E5481 decommissioning, Aberdeen Proving Ground

International Nuclear Information System (INIS)

Thompson, M.D.; McGinnis, M.G.; McGinnis, L.D.; Miller, S.F.

1992-11-01

Building E5481 is one of ten potentially contaminated sites in the Canal Creek and Westwood areas of the Edgewood section of Aberdeen Proving Ground examined by a geophysical team from Argonne National Laboratory in April and May of 1992. Noninvasive geophysical surveys, including magnetics, electrical resistivity, and ground-penetrating radar, were conducted around the perimeter of the building to guide a sampling program prior to decommissioning and dismantling. The building is located on the northern margin of a landfill that was sited in a wetland. The large number of magnetic sources surrounding the building are believed to be contained in construction fill that had been used to raise the grade. The smaller anomalies, for the most part, are not imaged with ground radar or by electrical profiling. A conductive zone trending northwest to southeast across the site is spatially related to an old roadbed. Higher resistivity areas in the northeast and east are probably representive of background values. Three high-amplitude, positive, rectangular magnetic anomalies have unknown sources. The features do not have equivalent electrical signatures, nor are they seen with radar imaging

EXTRACTION OF BUILDING BOUNDARY LINES FROM AIRBORNE LIDAR POINT CLOUDS

Directory of Open Access Journals (Sweden)

Y.-H. Tseng

2016-10-01

Full Text Available Building boundary lines are important spatial features that characterize the topographic maps and three-dimensional (3D city models. Airborne LiDAR Point clouds provide adequate 3D spatial information for building boundary mapping. However, information of boundary features contained in point clouds is implicit. This study focuses on developing an automatic algorithm of building boundary line extraction from airborne LiDAR data. In an airborne LiDAR dataset, top surfaces of buildings, such as roofs, tend to have densely distributed points, but vertical surfaces, such as walls, usually have sparsely distributed points or even no points. The intersection lines of roof and wall planes are, therefore, not clearly defined in point clouds. This paper proposes a novel method to extract those boundary lines of building edges. The extracted line features can be used as fundamental data to generate topographic maps of 3D city model for an urban area. The proposed method includes two major process steps. The first step is to extract building boundary points from point clouds. Then the second step is followed to form building boundary line features based on the extracted boundary points. In this step, a line fitting algorithm is developed to improve the edge extraction from LiDAR data. Eight test objects, including 4 simple low buildings and 4 complicated tall buildings, were selected from the buildings in NCKU campus. The test results demonstrate the feasibility of the proposed method in extracting complicate building boundary lines. Some results which are not as good as expected suggest the need of further improvement of the method.

The cobalt-60 container scanner

International Nuclear Information System (INIS)

Jigang, A.; Liye, Z.; Yisi, L.; Haifeng, W.; Zhifang, W.; Liqiang, W.; Yuanshi, Z.; Xincheng, X.; Furong, L.; Baozeng, G.; Chunfa, S.

1997-01-01

The Institute of Nuclear Energy Technology (INET) has successfully designed and constructed a container (cargo) scanner, which uses cobalt-60 of 100-300 Ci as radiation source. The following performances of the Cobalt-60 container scanner have been achieved at INET: a) IQI (Image Quality Indicator) - 2.5% behind 100 mm of steel; b) CI (Contrast Indicator) - 0.7% behind 100 mm of steel; c) SP (Steel Penetration) - 240 mm of steel; d) Maximum Dose per Scanning - 0.02mGy; e) Throughput - twenty 40-foot containers per hour. These performances are equal or similar to those of the accelerator scanners. Besides these nice enough inspection properties, the Cobalt-60 scanner possesses many other special features which are better than accelerator scanners: a) cheap price - it will be only or two tenths of the accelerator scanner's; b) low radiation intensity - the radiation protection problem is much easier to solve and a lot of money can be saved on the radiation shielding building; c) much smaller area for installation and operation; d) simple operation and convenient maintenance; e) high reliability and stability. The Cobalt-60 container (or cargo) scanner is satisfied for boundary customs, seaports, airports and railway stations etc. Because of the nice special features said above, it is more suitable to be applied widely. Its high properties and low price will make it have much better application prospects

CVMFS Build and Release Pipeline Using Docker Microservces

CERN Document Server

CERN. Geneva

2018-01-01

IceCube is a cubic kilometer neutrino detector located at the south pole. CVMFS is a key component to IceCube’s Distributed High Throughput Computing analytics workflow for sharing 500GB of software across datacenters worldwide. Building the IceCube software suite across multiple platforms and deploying it into CVMFS has until recently been a manual, time consuming task that doesn’t fit well within an agile continuous delivery framework. Within the last 2 years a plethora of tooling around microservices has created an opportunity to upgrade the IceCube software build and deploy pipeline. We present a framework using Kubernetes to deploy Buildbot. The Buildbot pipeline is a set of pods (docker containers) in the Kubernetes cluster that builds the IceCube software across multiple platforms, tests the new software for critical errors, syncs the software to a containerized CVMFS server, and finally executes a publish. The time from code commit to CVMFS publish has been greatly reduced and has enabled t...

Carpentry and Finishing Procedures. Building Maintenance. Module II. Instructor's Guide.

Science.gov (United States)

Hawk, Sam; Brunk, Art

This curriculum guide, keyed to the building maintenance competency profile developed by industry and education professionals, provides three units on carpentry and finishing procedures. The first unit, Exterior Carpentry, contains the following lessons: carpentry safety procedures, ladder and scaffolding safety, door installation/repair,…

Assessment of radioactivity in building material(granite) in Sudan

International Nuclear Information System (INIS)

Osman, Z. A; Salih, I; Albadwai, K. A; Salih, A. M; Salih, S. A.

2016-01-01

In the present work radioactivity in building materials (granite) central Sudan was evaluated. In general the building materials used in Sudan are derived either from rocks or soil. These contain trace amounts of naturally occurring radioactive materials(NORMs), so it contains radionuclides from uranium and thorium series and natural potassium. The levels of these radionuclides vary according to the geology of their site of origin. High levels increase the risk of radiation exposure in homes(especially exposure due to radon). Investigation of radioactivity in granite used of the building materials in Sudan is carried out, a total of 18 major samples of granite have been collected and measured using X- ray fluorescence system (30 mci). The activity concentrations have been determined for uranium ("2"3"8U), thorium ('2"3"2Th) and potassium("4"0K) in each sample. The concentrations of uranium have been found to range from 14.81 Bq/kg to 24.572 Bq/kg, thorium between 10.02 Bq/kg and 10.020-84.79 Bq/kg and the potassium concentration varies between 13.33 Bq/kg to 82.13 Bq/kg. Limits of radioactivity in the granite are based on dose criteria for controls. This study can be used as a reference for more extensive studies of the same subject in future. (Author)

Dose reduction factors from a radioactive cloud for large buildings

International Nuclear Information System (INIS)

Grand, J. le; Roux, Y.

1986-01-01

A set of complex and accurate computer codes has been established to determine the transport of photons emitted from a radioactive cloud through various media. The geometrical and physical description of large buildings with various numbers of floors and rooms can be done by the user. The codes can calculate, in any room or apartment, the characteristics of the photon fields (photon flux, energy flux and distribution, direction distribution) and whole-body absorbed dose rates in a phantom standing or lying on the floor. The dose reduction factor is then the quotient of the mean absorbed dose rate in the apartment to the absorbed dose rate in the phantom standing on the ground outdoors. Applications to several modern multistorey buildings are presented. The results show the influence of various parameters such as density and composition of building materials, the fraction of the external building surface containing apertures and initial photon energy. (author)

Behaviour of prestressed concrete containment structures

International Nuclear Information System (INIS)

MacGregor, J.G.; Murray, D.W.; Simmonds, S.H.

1980-05-01

The most significant finds from a study to assess the response of prestressed concrete secondary containment structures for nuclear reactors under the influence of high internal overpressures are presented. A method of analysis is described for determining the strains and deflections including effects of inelastic behaviour at various points in the structure resulting from increasing internal pressures. Experimentally derived relationships between the strains and crack spacing, crack width and leakage rate are given. These procedures were applied to the Gentilly-2 containment building to obtain the following results: (1) The first through-the-wall cracks would occur in the dome at 48 psi or 2.3 times the proof test pressure. (2) At this pressure leakage would begin and would increase exponentially as the pressure increases such that at 93% of the predicted failure load the calculated leakage rate would be approximately equal to the volume of the containment each second. (3) Assuming the pressurizing medium could be supplied sufficiently rapidly, failure would occur due to rupture of the horizontal tendons at approximately 77 psi. (author)

Compliance with building energy regulations for new-build dwellings

International Nuclear Information System (INIS)

Pan, Wei; Garmston, Helen

2012-01-01

Despite increasingly stringent building energy regulations worldwide, non-compliance exists in practice. This paper examines the profile of compliance with building energy regulations for new-build dwellings. In total 404 new-build dwellings completed in the UK from 2006 to 2009 were investigated. Only a third of these dwellings were evidenced as being compliant with Building Regulations Part L (England and Wales). Such low compliance casts a serious concern over the achievability of the UK Government's target for all new-build homes to be ‘zero carbon’ from 2016. Clearly evidenced was a lack of knowledge of Part L and its compliance requirements among the supply and building control sides of new-build dwellings. The results also indicate that the compliance profile was influenced by factors including Standard Assessment Procedure (UK Government's methodology for energy efficiency) calculation submissions, learning and experience of builders and building controls with Part L, use of Part L1A checklist, the introduction of energy performance certificate (EPC), build method, dwelling type, and project size. Better compliance was associated with flats over houses and timber frame over masonry. The use of EPC and Part L1A checklist should be encouraged. Key to addressing the lack of compliance with building energy regulations is training. -- Highlights: ► There exists a lack of compliance, worldwide, with building energy regulations. ► The implementation of England and Wales building energy regulations is problematic. ► Training, learning and experience of builders and building control are critical. ► Energy performance certificate and Part L 2006 checklist helped achieve compliance. ► Flats achieved better compliance over houses; and timber frame over masonry.

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

International Nuclear Information System (INIS)

Horschel, D.S.

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

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.

Solar energy in buildings solved by building information modeling

Science.gov (United States)

Chudikova, B.; Faltejsek, M.

2018-03-01

Building lead us to use renewable energy sources for all types of buildings. The use of solar energy is the alternatives that can be applied in a good ratio of space, price, and resultant benefits. Building Information Modelling is a modern and effective way of dealing with buildings with regard to all aspects of the life cycle. The basis is careful planning and simulation in the pre-investment phase, where it is possible to determine the effective result and influence the lifetime of the building and the cost of its operation. By simulating, analysing and insert a building model into its future environment where climate conditions and surrounding buildings play a role, it is possible to predict the usability of the solar energy and establish an ideal model. Solar systems also very affect the internal layout of buildings. Pre-investment phase analysis, with a view to future aspects, will ensure that the resulting building will be both low-energy and environmentally friendly.

Solar Water Heater Systems for Building Trades Class.

Science.gov (United States)

Ryan, Milton; And Others

This teaching unit serves as a guide for the installation of active solar water heating systems. It contains a project designed for use with secondary level students of a building trades class. Students typically would meet 2 to 3 hours per day and would be able to complete the activity within a 1-week time period. Objectives of this unit include:…

Building 2000

International Nuclear Information System (INIS)

Den Ouden, C.; Steemers, T.C.

1992-01-01

This is the first volume of Building 2000, a pilot project of the Commission's R and D-programme 'Solar Energy Applications to Buildings' with the purpose of encouraging the adoption of solar architecture in large buildings. In this first rich illustrated volume the results of the design studies illustrating passive solar architecture in buildings in the European Community are presented in particular for the building categories as mentioned in the subtitle. In a second volume, a similar series of studies is presented for the building categories: office buildings, public buildings and hotels and holiday complexes. Several Design Support Workshops were organized during the Building 2000 programme during which Building 2000 design teams could directly exchange ideas with the various design advice experts represented at these workshops. In the second part of the Building 2000 final report a summary of a selection of many reports is presented (15 papers), as produced by Design Support experts. Most of the design support activities resulted in changes of the various designs, as have been reported by the design teams in the brochures presented in the first part of this book. It is to be expected that design aids and simulation tools for passive solar options, daylighting concepts, comfort criteria etc., will be utilized more frequently in the future. This will result in a better exchange of information between the actual design practitioners and the European R and D community. This technology transfer will result in buildings with a higher quality with respect to energy and environmental issues

Building 2000

Energy Technology Data Exchange (ETDEWEB)

Den Ouden, C [EGM Engineering BV, Dordrecht (Netherlands); Steemers, T C [Commission of the European Communities, Brussels (Belgium)

1992-01-01

This is the first volume of Building 2000, a pilot project of the Commission's R and D-programme 'Solar Energy Applications to Buildings' with the purpose of encouraging the adoption of solar architecture in large buildings. In this first rich illustrated volume the results of the design studies illustrating passive solar architecture in buildings in the European Community are presented in particular for the building categories as mentioned in the subtitle. In a second volume, a similar series of studies is presented for the building categories: office buildings, public buildings and hotels and holiday complexes. Several Design Support Workshops were organized during the Building 2000 programme during which Building 2000 design teams could directly exchange ideas with the various design advice experts represented at these workshops. In the second part of the Building 2000 final report a summary of a selection of many reports is presented (15 papers), as produced by Design Support experts. Most of the design support activities resulted in changes of the various designs, as have been reported by the design teams in the brochures presented in the first part of this book. It is to be expected that design aids and simulation tools for passive solar options, daylighting concepts, comfort criteria etc., will be utilized more frequently in the future. This will result in a better exchange of information between the actual design practitioners and the European R and D community. This technology transfer will result in buildings with a higher quality with respect to energy and environmental issues.

Limitation On The Concentration Of Radioactive Elastothane In Building Materiel's Available In Israel

International Nuclear Information System (INIS)

Kovler, K.; Haquin, G.; Ne'eman, E.; Lavi, N.

1999-01-01

Most building materials contain naturally occurring radioactive elements the most important of which are 40 K and the members of two natural radioactive series, which can be represented by the isotopes 232 Th and 226 Ra. The presence of these radioisotopes in the building materials causes external exposure to the people that live in the house. 226 Ra can also enhance the concentration of 222 Rn and of its daughters in the house. Concentrations of natural radionuclides ( 226 Ra, 232 Th, 40 K) in the samples of building products, building binders, in lightweight aggregates, normal-weight aggregates and in industrial by-products used in construction industry of Israel were determined by gamma-ray spectrometer with a Ge-detector. A methodology was introduced to regulate the use of building materials that cause increase in indoor radiation exposure

Non-linear dynamic response of reactor containment

International Nuclear Information System (INIS)

Takemori, T.; Sotomura, K.; Yamada, M.

1975-01-01

A computer program was developed to investigate the elasto-plastic behavior of structures. This program is outlined and the problems of non-linear response of structures are discussed. Since the mode superposition method is only valid in an elastic analysis, the direct integration method was adopted here. As the sample model, an actual reactor containment (reactor building) of PWR plant was adopted. This building consists of three components, that is, a concrete internal structure, a steel containment vessel and a concrete outer shield wall. These components are resting on a rigid foundation mat. Therefore they were modeled with a lumped mass model respectively and coupled on the foundation. The following assumptions were employed to establish the properties of dynamic model: rocking and swaying springs of soil can be obtained from an elastic half-space solution, and the hysteretic characteristic of springs is bi-linear; springs connecting each mass are dealt with shear beams so that both bending and shear deflections can be included (Hysteretic characteristics of springs are linear, bi-linear and tri-linear for the internal structure, the containment vessel and the outer shield wall, respectively); generally, each damping coefficient is given for each mode in modal superposition (However, a damping matrix must be made directly in a non-linear response). Therefore the damping matrix of the model was made by combining the damping matrices [C] of each component obtained by Caughy's method and a damping value of the rocking and swaying by the half-space solution. On the basis of above conditions, the non-linear response of the structure was obtained and the difference between elastic and elasto-plastic analysis is presented

A regulatory view of containment integrity in the United Kingdom

International Nuclear Information System (INIS)

Bradford, P.M.; Patchett, C.M.

1994-01-01

This paper reviews the approach of HM Nuclear Installations Inspectorate (NII) to containment integrity in the United Kingdom (UK). NII is that part of the regulatory authority, the Health and Safety Executive (HSE), which administers the UK's nuclear site licensing system. A major part of the licensing process lies in the assessment of licensees' submissions for new and existing plant. The purpose of this paper is to: briefly review our revised Safety Assessment Principles, describe our assessment and inspection activities on the primary containment building of the Sizewell B PWR which is progressing to full power operation in 1994 and, to indicate our views on the possible directions for future research into containment design and performance. (author). 5 refs

Connection between radon emanation and some structural properties of coal-slag as building material

International Nuclear Information System (INIS)

Somlai, J.; Jobbagy, V.; Somlai, K.; Kovacs, J.; Nemeth, Cs.; Kovacs, T.

2008-01-01

Radionuclides of natural origin may accumulate in different industrial waste materials and by-products. The use of coal bottom ash or coal-slag as building material in Hungary is widespread. Because of the elevated radium content of coal-slag, high radon concentration has been detected in buildings containing coal-slag as building material. In two towns, where buildings contain coal-slag with almost the same radium concentration, the indoor radon concentrations have been found to differ significantly. In order to investigate the cause of the difference in the emanation coefficients, slag samples from the two locations were examined for grain-size distribution, density, pore volume, and specific surface. The applied methods were: gamma spectrometry for the radium concentration of the samples; Lucas cell method for the radon emanation; nitrogen absorption-desorption isotherms analyzed using the BET theory and mercury poremeter for the specific surface and pore volume. It was found that the great difference in the emanation coefficients (1.35±0.13% and 14.3±0.92%) of the coal-slag samples is primarily influenced by the pore volume and the specific surface

Sequential Ground Motion Effects on the Behavior of a Base-Isolated RCC Building

Directory of Open Access Journals (Sweden)

Zhi Zheng

2017-01-01

Full Text Available The sequential ground motion effects on the dynamic responses of reinforced concrete containment (RCC buildings with typical isolators are studied in this paper. Although the base isolation technique is developed to guarantee the security and integrity of RCC buildings under single earthquakes, seismic behavior of base-isolated RCC buildings under sequential ground motions is deficient. Hence, an ensemble of as-recorded sequential ground motions is employed to study the effect of including aftershocks on the seismic evaluation of base-isolated RCC buildings. The results indicate that base isolation can significantly attenuate the earthquake shaking of the RCC building under not only single earthquakes but also seismic sequences. It is also found that the adverse aftershock effect on the RCC can be reduced due to the base isolation applied to the RCC. More importantly, the study indicates that disregarding aftershocks can induce significant underestimation of the isolator displacement for base-isolated RCC buildings.

Core catcher for nuclear reactor core meltdown containment

International Nuclear Information System (INIS)

Driscoll, M.J.; Bowman, F.L.

1978-01-01

A bed of graphite particles is placed beneath a nuclear reactor core outside the pressure vessel but within the containment building to catch the core debris in the event of failure of the emergency core cooling system. Spray cooling of the debris and graphite particles together with draining and flooding of coolant fluid of the graphite bed is provided to prevent debris slump-through to the bottom of the bed

Synthesis of a novel polyester building block from pentoses by tin-containing silicates

DEFF Research Database (Denmark)

Elliot, Samuel Gilbert; Andersen, Christian; Tolborg, Søren

2017-01-01

a product containing functional groups originating from trans-2,5-dihydroxy-3-pentenoic acid methyl ester in the polyester backbone. The reactivity of the incorporated olefin and hydroxyl moieties was investigated using trifluoroacetic anhydride and thiol-ene chemisitry, thus illustrating the potential...

Investigation of conditions inside the reactor building annulus of a PWR plant of KONVOI type in case of severe accidents with increased containment leakages

International Nuclear Information System (INIS)

Bakalov, Ivan; Sonnenkalb, Martin

2018-01-01

Improvements of the implemented severe accident management (SAM) concepts have been done in all operating German NPPs after the Fukushima Daiichi accidents following recommendations of the German Reactor Safety Commission (RSK) and as a result of the stress test being performed. The efficiency of newly developed severe accident management guidelines (SAMG) for a PWR KONVOI reference plant related to the mitigation of challenging conditions inside the reactor building (RB) annulus due to increased containment leakages during severe accidents have been assessed. Based on two representative severe accident scenarios the releases of both hydrogen and radionuclides into the RB annulus have been predicted with different boundary conditions. The accident scenarios have been analysed without and with the impact of several SAM measures (already planned or proposed in addition), which turned out to be efficient to mitigate the consequences. The work was done within the frame of a research project financially supported by the Federal Ministry BMUB.

Investigation of conditions inside the reactor building annulus of a PWR plant of KONVOI type in case of severe accidents with increased containment leakages

Energy Technology Data Exchange (ETDEWEB)

Bakalov, Ivan [Gesellschaft fuer Anlagen- und Reaktorsicherheit (GRS) gGmbH, Berlin (Germany); Sonnenkalb, Martin [Gesellschaft fuer Anlagen- und Reaktorsicherheit (GRS) gGmbH, Koeln (Germany)

2018-02-15

Improvements of the implemented severe accident management (SAM) concepts have been done in all operating German NPPs after the Fukushima Daiichi accidents following recommendations of the German Reactor Safety Commission (RSK) and as a result of the stress test being performed. The efficiency of newly developed severe accident management guidelines (SAMG) for a PWR KONVOI reference plant related to the mitigation of challenging conditions inside the reactor building (RB) annulus due to increased containment leakages during severe accidents have been assessed. Based on two representative severe accident scenarios the releases of both hydrogen and radionuclides into the RB annulus have been predicted with different boundary conditions. The accident scenarios have been analysed without and with the impact of several SAM measures (already planned or proposed in addition), which turned out to be efficient to mitigate the consequences. The work was done within the frame of a research project financially supported by the Federal Ministry BMUB.

The sick-building syndrome; Das Sick-Building-Syndrom

Energy Technology Data Exchange (ETDEWEB)

Henne, A.; Neumann, H.F.; Winneke, G.

1992-12-31

The sick-building syndrome is characterized by the presence of general, non-specific symptoms (e.g., headache, tiredness, respiratory problems, eye trouble, vertigo, nausea, unspecific hypersensitivity) in association with a particular indoor ambience. It is clearly distinguishable from `building-related illness`, referring to a well-defined clinical syndrome due to staying in a building and for which a cause can, in general, be established. Disorders in the case of the sick-building syndrome are manifold and confirmed objectifiable results are hardly available so far. Yet there are some organ-related methods for the confirmation of findings concerning, for instance, the eyes, the skin and the area of the nose. The causes of the incidence of sick-building syndrome are more or less unclear. It is a multifactorial phenomenon involving physical, biological, chemical, individual-specific and psychological factors. Buildings where sick-building syndrome occurs typically exhibit certain properties. The European Community has already made proposals for the investigation of incriminated buildings. A systematic survey by questionnaire together with individual interviews plays an import part towards clarifying the syndrome. (orig./UWA) [Deutsch] Das Sick-Building-Syndrom beschreibt das Vorhandensein von allgemeinen, nicht spezifischen Symptomen (z.B. Kopfschmerzen, Muedigkeit, Atembeschwerden, Augenreizungen, Schwindelgefuehl, Uebelkeit, unspezifische Ueberempfindlichkeit), assoziiert mit einer besonderen Innenraumumgebung. Deutlich hiervon abzugrenzen ist die ``Building related illness``, bei der ein klinisch definiertes Krankheitsbild vorliegt, das durch den Aufenthalt im Gebaeude verursacht wird und fuer das im allgemeinen eine Ursache ermittelt werden kann. Das Beschwerdebild beim Sick-Building-Syndrom ist vielfaeltig, und gesicherte, objektivierbare Befunde liegen hierzu bisher kaum vor. Dennoch gibt es einige organbezogenen Methoden zur Befundabsicherung, z.B. fuer das

Sampling and decontamination plan for the Transuranic Storage Area--1/-R container storage unit

International Nuclear Information System (INIS)

Barry, G.A.

1992-11-01

This document describes the sampling and decontamination of the Transuranic Storage Area (TSA)-l/-R container storage area and the earthen-covered portion of the TSA-2 container storage unit at the Radioactive Waste Management Complex. Stored containers from the earthen-covered asphalt pads will be retrieved from the TSA-l/-R and TSA-2 container storage units. Container retrieval will be conducted under the TSA retrieval enclosure, a fabricated steel building to be constructed over the earthen-covered pad to provide containment and weather protection. Following container retrieval, the TSA retrieval enclosure will be decontaminated to remove radioactive and hazardous contamination. The underlying soils will be sampled and analyzed to determine whether any contaminated soils require removal

Energy Efficiency, Building Productivity and the Commercial Buildings Market

Energy Technology Data Exchange (ETDEWEB)

Jones, D.W.

2002-05-16

The energy-efficiency gap literature suggests that building buyers are often short-sighted in their failure to apply life-cycle costing principles to energy efficient building technologies, with the result that under investment in these advanced technology occurs. This study examines the reasons this behavior may occur, by analyzing the pressures that market forces place on purchasers of buildings. Our basic conclusion is that the fundamental manner in which the buildings sector does business creates pressures to reduce initial capital outlays and to hedge against a variety of risks, including the ability of building owners to capture benefits from energy efficiency. Starting from the position that building buyers' willingness to pay drives choices over building attributes, we examine basic market principles, the structure of the buildings market, including the role of lenders, and policies that promote penetration of energy efficient technologies. We conclude that greater attention to buyers, and to the incentives and constraints they face, would promote a better understanding of building investment choices and contribute to better policies to promote the penetration of these technologies into markets.

BIM, GIS and semantic models of cultural heritage buildings

Directory of Open Access Journals (Sweden)

Pavel Tobiáš

2016-12-01

Full Text Available Even though there has been a great development of using building information models in the AEC (Architecture/Engineering/Construction sector recently, creation of models of existing buildings is still not very usual. The cultural heritage documentation is still, in most cases, kept in the form of 2D drawings while these drawings mostly contain only geometry without semantics, attributes or definitions of relationships and hierarchies between particular building elements. All these additional information would, however, be very providential for the tasks of cultural heritage preservation, i.e. for the facility management of heritage buildings or for reconstruction planning and it would be suitable to manage all geometric and non-geometric information in a single 3D information model. This paper is based on the existing literature and focuses on the historic building information modelling to provide information about the current state of the art. First, a summary of available software tools is introduced while not only the BIM tools but also the related GIS software is considered. This is followed by a review of existing efforts worldwide and an evaluation of the facts found.

Irregular Shaped Building Design Optimization with Building Information Modelling

Directory of Open Access Journals (Sweden)

Lee Xia Sheng

2016-01-01

Full Text Available This research is to recognise the function of Building Information Modelling (BIM in design optimization for irregular shaped buildings. The study focuses on a conceptual irregular shaped “twisted” building design similar to some existing sculpture-like architectures. Form and function are the two most important aspects of new buildings, which are becoming more sophisticated as parts of equally sophisticated “systems” that we are living in. Nowadays, it is common to have irregular shaped or sculpture-like buildings which are very different when compared to regular buildings. Construction industry stakeholders are facing stiff challenges in many aspects such as buildability, cost effectiveness, delivery time and facility management when dealing with irregular shaped building projects. Building Information Modelling (BIM is being utilized to enable architects, engineers and constructors to gain improved visualization for irregular shaped buildings; this has a purpose of identifying critical issues before initiating physical construction work. In this study, three variations of design options differing in rotating angle: 30 degrees, 60 degrees and 90 degrees are created to conduct quantifiable comparisons. Discussions are focused on three major aspects including structural planning, usable building space, and structural constructability. This research concludes that Building Information Modelling is instrumental in facilitating design optimization for irregular shaped building. In the process of comparing different design variations, instead of just giving “yes or no” type of response, stakeholders can now easily visualize, evaluate and decide to achieve the right balance based on their own criteria. Therefore, construction project stakeholders are empowered with superior evaluation and decision making capability.

Guide for the recovery of high grade waste paper from federal office buildings through at-source separation

Energy Technology Data Exchange (ETDEWEB)

1978-01-01

This guide is intended to serve as a manual for organizing and managing office waste paper recovery programs in Canadian federal buildings. Waste paper generated in such buildings is of particular interest for recycling as it is produced in sufficiently large amounts, and contains large amounts of high-grade waste paper which obtain good prices from paper mills. The key to successful recovery of such paper is separation, at the source of waste generation, from other less-valuable papers and non-paper materials. In recommending ways to do this, the manual covers assessment of the viability of a collection program in a particular building, estimating the quantities of waste generated, calculating storage space necessary, marketing the paper collected, using proper collection and storage containers, promoting employee awareness, and administering and monitoring the program. A sample cost-benefit analysis is given for a general office building with 1,000 employees. Includes glossary. 14 refs., 10 figs., 5 tabs.

Accident loads for a VVER-440/213 containment

Energy Technology Data Exchange (ETDEWEB)

Techy, Z. [Institute for Electric Power Research (VEIKI), Budapest (Hungary); Lajtha, G. [Institute for Electric Power Research (VEIKI), Budapest (Hungary); Taubner, R. [Institute for Electric Power Research (VEIKI), Budapest (Hungary)

1995-08-01

Specific features of the VVER-440/213 containment are the subdivided rectangular building and the localization system including the bubbler trays and air traps. Accident loads are calculated for a large break loss of coolant accident (LBLOCA). The maximum pressure and temperature loads are calculated with different codes during the blowdown phase of the LBLOCA. The uncertainty margins of the maximum pressure are given in this case. Sensitivity studies are performed for different leakage rates and hydraulic data of the containment. The effects of the active and passive spray systems on the depressurization are presented in this paper. The maximum pressure loads are also examined in case of degraded conditions of the localization system. (orig.).

Neutron dose rate in the upper part of a PWR containment. Comparison between measurements and TRIPOLI-2 calculations

International Nuclear Information System (INIS)

Vergnaud, T.; Bourdet, L.; Gonnord, J.; Nimal, J.C.; Champion, G.

1984-01-01

Conception of a reactor building requires large openings in the primary concrete shield for a postulated loss-of-coolant accident. Through these openings neutrons escape and produce dose rates in several parts of the reactor building. Some calculations using ANISN, DOT and essentially TRIPOLI-2 codes allow to compute the neutron dose rates at several places such as reactor containment operating floor and containment annulus. Some complementary shields are provided and the instrumentations are placed in area where the dose rate is lower. Comparisons are presented between measurements and calculations

Impact of whole-building hygrothermal modelling on the assessment of indoor climate in a library building

Energy Technology Data Exchange (ETDEWEB)

Steeman, M.; Janssens, A. [Ghent University, Department of Architecture and Urban Planning, Jozef Plateaustraat 22, B-9000 Gent (Belgium); De Paepe, M. [Ghent University, Department of Flow, Heat and Combustion Mechanics, Sint-Pietersnieuwstraat 41, B-9000 Gent (Belgium)

2010-07-15

This paper focuses on the importance of accurately modelling the hygrothermal interaction between the building and its hygroscopic content for the assessment of the indoor climate. Libraries contain a large amount of stored books which require a stable relative humidity to guarantee their preservation. On the other hand, visitors and staff must be comfortable with the indoor climate. The indoor climate of a new library building is evaluated by means of measurements and simulations. Complaints of the staff are confirmed by measured data during the winter and summer of 2007-2008. For the evaluation of the indoor climate, a building simulation model is used in which the porous books are either described by a HAM model or by a simplified isothermal model. Calculations demonstrate that the HAM model predicts a more stable indoor climate regarding both temperature and relative humidity variations in comparison to the estimations by the simplified model. This is attributed to the ability of the HAM model to account for the effect of temperature variations on moisture storage. Moreover, by applying the HAM model, a good agreement with the measured indoor climate is found. As expected, a larger exposed book surface ameliorates the indoor climate because a more stable indoor relative humidity is obtained. Finally, the building simulation model is used to improve the indoor climate with respect to the preservation of valuable books. Results demonstrate that more stringent interventions on the air handling unit are expected when a simplified approach is used to model the hygroscopic books. (author)

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

International Nuclear Information System (INIS)

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

1993-01-01

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

EPIQR - a decision making tool for apartment building refurbishment

Energy Technology Data Exchange (ETDEWEB)

Caccavelli, D. [Centre Scientifique et Technique du Batiment, Cedex (France); Balaras, C. [National Observatory of Athens, Athens (Greece); Bluyssen, P. [TNO Building and Construction Research, Delft (Netherlands); Flourentzou, F. [Ecole Polytechnique Federale de Lausanne, Lausanne (France); Jaggs, M. [Building Research Establishment, Watford (United Kingdom); Wetzel, C. [Fraunhofer-Institut fur Bauphysik, Holzkirchen (Germany); Wittchen, K. [Danish Building Reasearch Institute, Hoersholm (Denmark)

1999-11-01

In a large majority of European countries, the amount of the maintenance and refurbishment works represents nearly 50% of the total amount spent in the building sector. New requirements are being added to the necessity of maintaining or re-establishing the building stock`s usage value. They are linked to the determination to reduce energy consumption, pollutant emissions, work site wastes, to improve the Indoor Environment Quality and all the modern conveniences inside apartment. Aware of this matter, the European Community has launched a two-year European research project, entitled EPIQR (Energy Performance, Indoor Environmental Quality, Retrofit) involving seven research institutions in the frame of the JOULE III programme. The purpose is to give architects and contracting authorities a multimedia tool to enable them to simultaneously grasp the whole process of apartment building refurbishment or retrofit. It has a number of functions: Assess the building`s degradation state based on a technical diagnosis after a standardised and complete inspection of the building; Prepare work proposals. These take into account not only the renovation of the building but also the improvement of the energy performance and IEQ; Estimate the costs corresponding to these works. A data base, containing the costs of 800 refurbishment works, provides a fast estimate of the total amount of the works being considered; Estimate the evolution of the degradation of the components if none of the works were to be carried out, as well as the refurbishment costs which would result. This paper provides an overview of the EPIQR methodology and the final deliverables of the project. (au)

High-performance commercial building systems

Energy Technology Data Exchange (ETDEWEB)

Selkowitz, Stephen

2003-10-01

This report summarizes key technical accomplishments resulting from the three year PIER-funded R&D program, ''High Performance Commercial Building Systems'' (HPCBS). The program targets the commercial building sector in California, an end-use sector that accounts for about one-third of all California electricity consumption and an even larger fraction of peak demand, at a cost of over $10B/year. Commercial buildings also have a major impact on occupant health, comfort and productivity. Building design and operations practices that influence energy use are deeply engrained in a fragmented, risk-averse industry that is slow to change. Although California's aggressive standards efforts have resulted in new buildings designed to use less energy than those constructed 20 years ago, the actual savings realized are still well below technical and economic potentials. The broad goal of this program is to develop and deploy a set of energy-saving technologies, strategies, and techniques, and improve processes for designing, commissioning, and operating commercial buildings, while improving health, comfort, and performance of occupants, all in a manner consistent with sound economic investment practices. Results are to be broadly applicable to the commercial sector for different building sizes and types, e.g. offices and schools, for different classes of ownership, both public and private, and for owner-occupied as well as speculative buildings. The program aims to facilitate significant electricity use savings in the California commercial sector by 2015, while assuring that these savings are affordable and promote high quality indoor environments. The five linked technical program elements contain 14 projects with 41 distinct R&D tasks. Collectively they form a comprehensive Research, Development, and Demonstration (RD&D) program with the potential to capture large savings in the commercial building sector, providing significant economic benefits to

Voluminator 2.0 - Speeding up the Approximation of the Volume of Defective 3d Building Models

Science.gov (United States)

Sindram, M.; Machl, T.; Steuer, H.; Pültz, M.; Kolbe, T. H.

2016-06-01

Semantic 3D city models are increasingly used as a data source in planning and analyzing processes of cities. They represent a virtual copy of the reality and are a common information base and source of information for examining urban questions. A significant advantage of virtual city models is that important indicators such as the volume of buildings, topological relationships between objects and other geometric as well as thematic information can be derived. Knowledge about the exact building volume is an essential base for estimating the building energy demand. In order to determine the volume of buildings with conventional algorithms and tools, the buildings may not contain any topological and geometrical errors. The reality, however, shows that city models very often contain errors such as missing surfaces, duplicated faces and misclosures. To overcome these errors (Steuer et al., 2015) have presented a robust method for approximating the volume of building models. For this purpose, a bounding box of the building is divided into a regular grid of voxels and it is determined which voxels are inside the building. The regular arrangement of the voxels leads to a high number of topological tests and prevents the application of this method using very high resolutions. In this paper we present an extension of the algorithm using an octree approach limiting the subdivision of space to regions around surfaces of the building models and to regions where, in the case of defective models, the topological tests are inconclusive. We show that the computation time can be significantly reduced, while preserving the robustness against geometrical and topological errors.

THERMAL HYDRAULIC ISSUES OF CONTAINMENT FILTERED VENTING SYSTEM FOR A LONG OPERATING TIME

Directory of Open Access Journals (Sweden)

YOUNG SU NA

2014-12-01

Full Text Available This study investigated the thermal hydraulic issues in the Containment Filtered Venting System (CFVS for a long operating time using the MELCOR computer code. The modeling of the CFVS, including the models for pool scrubbing and the filter, was added to the input file for the OPR-1000, and a Station Blackout (SBO was chosen as an accident scenario. Although depressurization in the containment building as a primary objective of the CFVS was successful, the decontamination feature by scrubbing and filtering in the CFVS for a long operating time could fail by the continuous evaporation of the scrubbing solution. After the operation of the CFVS, the atmosphere temperature in the CFVS became slightly above the water saturation temperature owing to the release of an amount of steam with high temperature from the containment building to the scrubbing solution. Reduced pipe diameters at the inlet and outlet of the CFVS vessel mitigated the evaporation of scrubbing water by controlling the amount of high-temperature steam and the water saturation temperature.

Swisswoodhouse -a building for the 2000-Watt Society; Swisswoodhouse - ein Gebaeude fuer die 2000-Watt-Gesellschaft - Synthesebericht

Energy Technology Data Exchange (ETDEWEB)

Menz, T.; Wallbaum, H.; Hardziewski, R.; Graf, S.; Trachsel-Gerber, N.; Koschenz, M.; Guentert, P.

2009-05-15

This report deals with a building conceived to meet the requirements of the Swiss '2000-Watt Society' concept. The aims of the project are discussed which feature the demonstration of a forward-looking architectural layout, comfortable and healthy living, environmentally compatible and low resource consumption, standardisation and cost reduction. The report contains seven sections: Basics of the '2000-Watt Society' concept, optimisation of the whole building system, investor-orientated rating, use-oriented monitoring system, the development of the building, standardised building technology and, finally, a description of this pilot project.

Permanent monitoring of containment integrity: the sexten system

International Nuclear Information System (INIS)

Germain, J.L.; Janneteau, E.

1993-01-01

Reactor containment integrity is of prime importance to the safety of PWR units. It is checked by means of tests performed at high pressure during the containment building pressure tests. These periodical tests are supplemented in France by permanent monitoring using the SEXTEN system. First feasibility tests for this system were carried out in 1980. The encouraging results obtained led to the development of a prototype, followed by an industrial system which has since been installed in all French PWR units. This system measures the containment leak rate, with corrections for the compressed air intakes used by the air-operated valves. Leaktightness is expressed in terms of the leak rate for a 60 mbar overpressure. If the leak rate exceeds a fixed limit value, leak detection operations are initiated, using SEXTEN. A new version of the system, known as SEXTEN 2 is being developed. (authors). 2 figs

Build and Execute Environment

Energy Technology Data Exchange (ETDEWEB)

2017-04-21

At exascale, the challenge becomes to develop applications that run at scale and use exascale platforms reliably, efficiently, and flexibly. Workflows become much more complex because they must seamlessly integrate simulation and data analytics. They must include down-sampling, post-processing, feature extraction, and visualization. Power and data transfer limitations require these analysis tasks to be run in-situ or in-transit. We expect successful workflows will comprise multiple linked simulations along with tens of analysis routines. Users will have limited development time at scale and, therefore, must have rich tools to develop, debug, test, and deploy applications. At this scale, successful workflows will compose linked computations from an assortment of reliable, well-defined computation elements, ones that can come and go as required, based on the needs of the workflow over time. We propose a novel framework that utilizes both virtual machines (VMs) and software containers to create a workflow system that establishes a uniform build and execution environment (BEE) beyond the capabilities of current systems. In this environment, applications will run reliably and repeatably across heterogeneous hardware and software. Containers, both commercial (Docker and Rocket) and open-source (LXC and LXD), define a runtime that isolates all software dependencies from the machine operating system. Workflows may contain multiple containers that run different operating systems, different software, and even different versions of the same software. We will run containers in open-source virtual machines (KVM) and emulators (QEMU) so that workflows run on any machine entirely in user-space. On this platform of containers and virtual machines, we will deliver workflow software that provides services, including repeatable execution, provenance, checkpointing, and future proofing. We will capture provenance about how containers were launched and how they interact to annotate

Mobile crowdsourcing of data for fault detection and diagnosis in smart buildings

DEFF Research Database (Denmark)

Lazarova-Molnar, Sanja; Pór Logason, Halldór; Andersen, Peter Grønbæk

2016-01-01

Energy use of buildings represents roughly 40% of the overall energy consumption. Most of the national agendas contain goals related to reducing the energy consumption and carbon footprint. Timely and accurate fault detection and diagnosis (FDD) in building management systems (BMS) have...... the potential to reduce energy consumption cost by approximately 15-30%. Most of the FDD methods are data-based, meaning that their performance is tightly linked to the quality and availability of relevant data. Based on our experience, faults and relevant events data is very sparse and inadequate, mostly...... propose a strategy of how to successfully deploy this building occupants' crowdsourcing application. Copyright is held by the owner/author(s). Publication rights licensed to ACM....

Danish building typologies

DEFF Research Database (Denmark)

Wittchen, Kim Bjarne; Kragh, Jesper

The objective of TABULA is to develop a harmonised building typology for European countries. Each national building typology will consist of a set of residential model buildings with characteristic energy-related properties (element areas of the thermal building envelope, U-values, supply system...... efficiencies). The model buildings will each represent a specific construction period of the country in question and a specific building size. Furthermore the number of buildings, flats and the overall floor areas will be given, which are represented by the different building types of the national typologies....

Hydrogen distribution analysis for CANDU 6 containment using the GOTHIC containment analysis code

International Nuclear Information System (INIS)

Nguyen, T.H.; Collins, W.M.

1995-01-01

Hydrogen may be generated in the reactor core by the zircaloy-steam reaction for a postulated loss of coolant accident (LOCA) scenario with loss of emergency core cooling (ECC). It is important to predict hydrogen distribution within containment in order to determine if flammable mixtures exist. This information is required to determine the best locations in containment for the placement of mitigation devices such as igniters and recombiners. For large break loss coolant accidents, hydrogen is released after the break flow has subsided. Following this period of high discharge the flow in the containment building undergoes transition from forced flow to a buoyancy driven flow (particularly when local air coolers (LACS) are not credited). One-dimensional computer codes (lumped parameter) are applicable during the initial period when a high degree of mixing occurs due to the forced flow generated by the break. However, during the post-blowdown phase the assumption of homogeneity becomes less accurate, and it is necessary to employ three-dimensional codes to capture local effects. This is particularly important for purely buoyant flows which may exhibit stratification effects. In the present analysis a three-dimensional model of CANDU 6 containment was constructed with the GOTHIC computer code using a relatively coarse mesh adequate enough to capture the salient features of the flow during the blowdown and hydrogen release periods. A 3D grid representation was employed for that portion of containment in which the primary flow (LOCA and post-LOCA) was deemed to occur. The remainder of containment was represented by lumped nodes. The results of the analysis indicate that flammable concentrations exist for several minutes in the vicinity of the break and in the steam generator enclosure. This is due to the fact that the hydrogen released from the break is primarily directed upwards into the steam generator enclosure due to buoyancy effects. Once hydrogen production ends

Roles of concrete technology for containment of radioactive contaminants

International Nuclear Information System (INIS)

Kitsutaka, Yoshinori; Imamoto, Keiichi

2014-01-01

A large amount of radioactive materials was emitted in the environment by the reactor accident at Fukushima Daiichi Nuclear Power Plant. Nuclear debris still remains in the reactor container. An investigative committee was organized in Japan Concrete Institute to study on the containment of radioactive materials and the safe utilization of concrete materials. We have investigated the effect of the hydrogen explosion upon the property of concrete and the transfer of materials into the concrete. We also present the outline of the advice made by Japan Concrete Institute about technologies on the concrete materials for the waterproofing in buildings and for water-shielding walls. (J.P.N.)

Numerical simulation of radioisotope's dependency on containment performance for large dry PWR containment under severe accidents

International Nuclear Information System (INIS)

Mehboob, Khurram; Xinrong, Cao; Ahmed, Raheel; Ali, Majid

2013-01-01

Highlights: • Calculation and comparison of activity of BURN-UP code with ORIGEN2 code. • Development of SASTC computer code. • Radioisotopes dependency on containment ESFs. • Mitigation in atmospheric release with ESFs operation. • Variation in radioisotopes source term with spray flow and pH value. -- Abstract: During the core melt accidents large amount of fission products can be released into the containment building. These fission products escape into the environment to contribute in accident source term. The mitigation in environmental release is demanded for such radiological consequences. Thus, countermeasures to source term, mitigations of release of radioactivity have been studied for 1000 MWe PWR reactor. The procedure of study is divided into five steps: (1) calculation and verification of core inventory, evaluated by BURN-UP code, (2) containment modeling based on radioactivity removal factors, (3) selection of potential accidents initiates the severe accident, (4) calculation of release of radioactivity, (5) study the dependency of release of radioactivity on containment engineering safety features (ESFs) inducing mitigation. Loss of coolant accident (LOCA), small break LOCA and flow blockage accidents (FBA) are selected as initiating accidents. The mitigation effect of ESFs on source term has been studied against ESFs performance. Parametric study of release of radioactivity has been carried out by modeling and simulating the containment parameters in MATLAB, which takes BURN-UP outcomes as input along with the probabilistic data. The dependency of iodine and aerosol source term on boric and caustic acid spray has been determined. The variation in source term mitigation with the variation of containment spray flow rate and pH values have been studied. The variation in containment retention factor (CRF) has also been studied with the ESF performance. A rapid decrease in source term is observed with the increase in pH value

Measurement of Ra-226 in building materials, with a Na I (Tl) scintillation counter

International Nuclear Information System (INIS)

Vallejo, L.R.; Fuenteseca, J.W.; Rivera, C.A.; Aros, F.H.

1992-01-01

Ra-226 concentration in building materials is determined using gamma-ray spectrometry. Ra-226 contained in sundry materials employed in the construction of dwelling houses and public buildings in Antofagasta city is determined by counting the Pb-214 peaks at 295 KeV and 352 keV, and the Bi-214 peak at 609 keV recorded by means of a 7.5-cm Nal (TI) scintillation counter. (author)

Characterization report for Buildings 3706 and 37006A

International Nuclear Information System (INIS)

Smith, D.S.

1997-06-01

The 3706 and 3706A Buildings were originally constructed to perform small-scale experiments in support of all Hanford Engineering Works production activities. The primary focus was to perform radiochemical trials aimed at improving the bismuth phosphate process. The facility housed 19 offices, 2 shops, a dark room, 2 storerooms, a lunchroom, locker room, ventilating equipment room, sanitary restrooms, and 57 laboratories, including a special laboratory with 0.6-m-(2-ft) thick concrete walls reserved for the hottest analytical work. The 3706 Building was decontaminated and remodeled in 1954 and 1955, and many of the laboratories were converted to offices at that time. By 1964, the facility was called the General Services Building, and although it still contained some analytical laboratories, the majority of the space was devoted to mail, duplicating, photographic, and drafting services; a first aid station, and the 300 Area Hanford Patrol headquarters. All laboratory work was eventually phased out by the end of the 1980's. The primary objective of the characterization activities described in this report is to properly designate the building debris waste in preparation for demolition of the building and disposal at the Environmental Restoration Disposal Facility Waste. The scope of services for this characterization project included the following tasks: historical records review; facility inspection; radiological surveys; data quality objective; sampling and analysis instruction; field sampling and laboratory analysis; preparation of this characterization report

A regulatory view of containment integrity in the United Kingdom

Energy Technology Data Exchange (ETDEWEB)

Bradford, P M; Patchett, C M [Health and Safety Executive, Bootle (United Kingdom). Nuclear Installations Inspectorate

1994-12-31

This paper reviews the approach of HM Nuclear Installations Inspectorate (NII) to containment integrity in the United Kingdom (UK). NII is that part of the regulatory authority, the Health and Safety Executive (HSE), which administers the UK`s nuclear site licensing system. A major part of the licensing process lies in the assessment of licensees` submissions for new and existing plant. The purpose of this paper is to: briefly review our revised Safety Assessment Principles, describe our assessment and inspection activities on the primary containment building of the Sizewell B PWR which is progressing to full power operation in 1994 and, to indicate our views on the possible directions for future research into containment design and performance. (author). 5 refs.

BREEAM [Building Research Establishment Environmental Assessment Method] BRE [Building Research Establishment] assessment method for buildings

International Nuclear Information System (INIS)

Baldwin, R.

1994-01-01

Buildings account for a large share of environmental impacts in their construction, use, and demolition. In western Europe, buildings account for ca 50% of primary energy use (hence CO 2 output), far outweighing the contribution of the transport and industrial sectors. Other impacts from building energy use include the use of chemicals such as chlorofluorocarbons for cooling. In the United Kingdom, the Building Research Establishment (BRE) has developed a certificate system for environmental labelling of buildings so that the performance of the building against a set of defined environmental criteria can be made visible to clients. This system thus rewards positive actions to improve the environmental performance of buildings and assists in marketing to an environmentally aware clientele. Issues included in assessments for awarding the certificate are addressed under three main headings: global issues and use of resources, local issues, and indoor issues. Global issues include ozone depletion and CO 2 emissions; local issues include public health and water conservation; and indoor issues include air quality and lighting. 8 refs., 1 tab

Commissioning of the steel containment and its related components of the Loviisa II. nuclear power plant

International Nuclear Information System (INIS)

Tuominen, J.; Pietikaeinen, L.; Kutramoinen, H.

1982-01-01

The outer concrete wall of the containment building serves as a protective system for the components in side. It contains the hermetically sealed steel pressure vessel for retaining the release of radioactive contamination in an accident situation. During a loss-of-coolant accident the pressure is reduced in two steps. The various testing procedures of the containment locks, their main-tenance and repair, the pressure and tightness tests of the steel containment and the preliminary operational tests of the other components of the containment system has been presented. (R.P.)

Study of containment air cooler capacity in steam air environment during accident conditions

International Nuclear Information System (INIS)

Kansal, M.; Mohan, N.; Bhawal, R.N.; Bajaj, S.S.

2002-01-01

Full text: The air coolers are provided for controlling the temperature in the reactor building during normal operation. These air coolers also serve as the main heat sink for the removal of energy from high enthalpy air-steam mixture expected in reactor building under accident conditions. A subroutine COOLER has been developed to estimate the heat removal rate of the air coolers at high temperature and steam conditions. The subroutine COOLER has been attached with the code PACSR (post accident containment system response) used for containment pressure temperature calculation. The subroutine was validated using design parameters at normal operating condition. A study was done to estimate the heat removal rate for some postulated accident conditions. The study reveals that, under accident conditions, the heat removal rate of air coolers increases several times compared with normal operating conditions

Building 2000

International Nuclear Information System (INIS)

Den Ouden, C.; Steemers, T.C.

1992-01-01

This is the second volume of Building 2000, a pilot project of the Commission's R and D-programme 'Solar Energy Applications to Buildings' with the purpose of encouraging the adoption of solar architecture in large buildings. In this second rich illustrated volume the results of the design studies illustrating passive solar architecture in buildings in the European Community are presented in particular for the building categories as mentioned in the subtitle. In the first volume, a similar series of studies is presented for the building categories: schools, laboratories and universities, and sports and educational centres. Several Design Support Workshops were organized during the Building 2000 programme during which Building 2000 design teams could directly exchange ideas with the various design advice experts represented at these workshops. In the second part of the Building 2000 final report a summary of a selection of many reports is presented (11 papers), as produced by Design Support experts. Most of the design support activities resulted in changes of the various designs, as have been reported by the design teams in the brochures presented in the first part of this book. It is to be expected that design aids and simulation tools for passive solar options, daylighting concepts, comfort criteria etc., will be utilized more frequently in the future. This will result in a better exchange of information between the actual design practitioners and the European R and D community. This technology transfer will result in buildings with a higher quality with respect to energy and environmental issues

Building 2000

Energy Technology Data Exchange (ETDEWEB)

Den Ouden, C [EGM Engineering BV, Dordrecht (Netherlands); Steemers, T C [Commission of the European Communities, Brussels (Belgium)

1992-01-01

This is the second volume of Building 2000, a pilot project of the Commission's R and D-programme 'Solar Energy Applications to Buildings' with the purpose of encouraging the adoption of solar architecture in large buildings. In this second rich illustrated volume the results of the design studies illustrating passive solar architecture in buildings in the European Community are presented in particular for the building categories as mentioned in the subtitle. In the first volume, a similar series of studies is presented for the building categories: schools, laboratories and universities, and sports and educational centres. Several Design Support Workshops were organized during the Building 2000 programme during which Building 2000 design teams could directly exchange ideas with the various design advice experts represented at these workshops. In the second part of the Building 2000 final report a summary of a selection of many reports is presented (11 papers), as produced by Design Support experts. Most of the design support activities resulted in changes of the various designs, as have been reported by the design teams in the brochures presented in the first part of this book. It is to be expected that design aids and simulation tools for passive solar options, daylighting concepts, comfort criteria etc., will be utilized more frequently in the future. This will result in a better exchange of information between the actual design practitioners and the European R and D community. This technology transfer will result in buildings with a higher quality with respect to energy and environmental issues.

FCA containment and surveillance (C/S) system

International Nuclear Information System (INIS)

Ogawa, Hironobu; Mukaiyama, Takehiko; Yokota, Yasuhiro.

1994-11-01

The Fast Critical Assembly (FCA) facility of the Japan Atomic Energy Research Inst. (JAERI) is internationally recognized as one of the most sensitive facility in the world from the viewpoint of international safeguards, because the facility possesses a large amount of metallic uranium and metallic plutonium, which are needed to perform various physical experiments. These material are subject to frequent verifications by the inspectorate, the International Atomic Energy Agency (IAEA) and the domestic authority (Science and Technology Agency of Japan, STA). Those verifications require inspectors to access to these materials for measurements and applications of seals. Human resources increase of irradiations and restrictions on the freedom of physical experiments, that are inevitably associated with these inspection activities, have been a serious problem that causes significant burdens for all relating parties. To decrease these burdens without any confliction with the inspection goals, an advanced comprehensive system of containment and surveillance has been developed. The FCA Containment and Surveillance (C/S) System consists of tow independent subsystems, i. e. Portal Monitor (P/M) and Penetration Monitor(PN/M). In this system the internal wall of the reactor building is used as a part of containment for the safeguards purpose, which enables the portal, that is installed at the internal wall of the reactor building, to be used as an area for monitoring of any removal of nuclear material. A metal detector of high sensitivity has been selected for the system since all nuclear materials possessed by the FCA has metallic forms. The internal wall has several penetrations for utility purposes, which should also be monitored for the purpose of detecting any removal of nuclear material from the reactor core area. A penetration monitor system has been developed for this purpose. This report describes functions of the system and their operation procedures. (author)

Study of improving the thermal response of a construction material containing a phase change material

Science.gov (United States)

Laaouatni, A.; Martaj, N.; Bennacer, R.; Elomari, M.; El Ganaoui, M.

2016-09-01

The use of phase change materials (PCMs) for improving the thermal comfort in buildings has become an attractive application. This solution contributes to increasing the thermal inertia of the building envelope and reducing power consumption. A building element filled with a PCM and equipped with ventilation tubes is proposed, both for increasing inertia and contributing to refreshing building envelope. A numerical simulation is conducted by the finite element method in COMSOL Multiphysics, which aims to test the thermal behaviour of the developed solution. An experimental study is carried out on a concrete block containing a PCM with ventilation tubes. The objective is to see the effect of PCM coupled with ventilation on increasing the inertia of the block. The results show the ability of this new solution to ensure an important thermal inertia of a building.

Molecular Building Blocks for Nanotechnology From Diamondoids to Nanoscale Materials and Applications

CERN Document Server

Mansoori, G. Ali; Assoufid, Lahsen; Zhang, Guoping

2007-01-01

This book is a result of the research and educational activities of a group of outstanding scientists worldwide who have authored the chapters of this book dealing with the behavior of nanoscale building blocks. It contains a variety of subjects covering computational, dry and wet nanotechnology. The state-of-the-art subject matters presented here provide the reader with the latest developments on ongoing nanoscience and nanotechnology research from the bottom-up approach, which starts with with atoms and molecules as molecular building blocks.

Building founding method

International Nuclear Information System (INIS)

Tateno, Seiya; Hirako, Shizuka.

1996-01-01

The lower portion of a reactor building is buried at a level of a base rock. In the step of building construction, the base rock around the building is dug of keeping a construction space. The base rock present between the digging line and the building is replaced with an artificial base rock comprising aggregates and cement having a building constraining force substantially equal with that of the lower supporting base rock to obtain constraining force for the side portion of the building. The building itself is made of concrete steels. As the material for replacing the base rock between the digging line and the building, non-reinforced concrete having no steels may provide sufficient function. The burying depth is determined so as to align the surface of the base rock with the level of the base floor of the building. With such procedures, since it is not necessary to increase the area of the lower portion of the building, the amount of the materials for the building can be reduced. In addition, the earthquakes stability can be ensured without changing the shape of the building. (I.N.)

Ultimate internal pressure capacity of concrete containment structures

International Nuclear Information System (INIS)

Krishnaswamy, C.N.; Namperumal, R.; Al-Dabbagh, A.

1983-01-01

Lesson learned from the accident at Three-Mile Island nuclear plant has necessitated the computation of the ultimate internal pressure capacity of containment structures as a licensing requirement in the U.S. In general, a containment structure is designed to be essentially elastic under design accident pressure. However, as the containment pressure builds up beyond the design value due to a more severe postulated accident, the containment response turns nonlinear as it sequentially passes through cracking of concrete, yielding of linear plate, yielding of rebar, and yielding of post-tensioning tendon (if the containment concrete is prestressed). This paper reports on the determination of the ultimate internal pressure capacity and nonlinear behavior of typical reinforced and prestressed concrete BWR containments. The probable modes of failure, the criteria for ultimate pressure capacity, and the most critical sections are described. Simple equations to hand-calculate the ultimate pressure capacity and the nonlinear behavior at membrane sections of the containment shell are presented. A nonlinear finite element analysis performed to determine the nonlinear behavior of the entire shell including nonmembrane sections is briefly discribed. The analysis model consisted of laminated axisymmetric shell finite elements with nonlinear stress-strain properties for each material. Results presented for typical BWR concrete containments include nonlinear response plots of internal pressure versus containment deflection and strains in the liner, rebar, and post-tensioning tendons at the most stressed section in the shell. Leak-tightness of the containment liner and the effect of thermal loads on the ultimate capacity are discussed. (orig.)

Integrating Responsive Building Elements in Buildings

DEFF Research Database (Denmark)

Haase, Matthias; Amato, Alex; Heiselberg, Per

2006-01-01

energy strategies to develop guidelines and procedures for estimation of environmental performance of responsive building elements and integrated building concepts This paper introduces the ideas of this collaborative work and discusses its usefulness for Hong Kong and China. Special focus was put...

Global building physics

DEFF Research Database (Denmark)

Rode, Carsten

2013-01-01

High ambitions are set for the building physics performance of buildings today. No single technology can achieve fulfilment of these ambitions alone. Integrated, multi-facetted solutions and optimization are necessary. A holistic, or ‘global’, technological perspective is needed, which includes all...... aspects of the building as defined in building engineering. We live in an international society and building solutions are developed across country borders. Building physics is a global theme. The International Association of Building Physics has global appeal. This brief article reports the keynote...

Global Building Physics

DEFF Research Database (Denmark)

Rode, Carsten

2012-01-01

High ambitions are set for the building physics performance of buildings today. No single technology can achieve fulfilment of these ambitions alone. Integrated, multi-facetted solutions and optimization are necessary. A holistic, or “global”, technological perspective is needed, which includes all...... aspects of the building as defined in building engineering. We live in an international society and building solutions are developed across country borders. Building physics is a global theme. The International Association of Building Physics has global appeal. The keynote lecture and this brief paper...

Significance of Building Maintenance Management on Life-Span of Buildings

Directory of Open Access Journals (Sweden)