Experiences from the design and construction of plug II in the Prototype Repository

International Nuclear Information System (INIS)

Dahlstroem, Lars-Olof

2009-12-01

The intention with this document is to summarise the comprehensive documentation and experience that was gained during the design and construction of the temporary plugs in the Prototype Repository experiment at Aespoe HRL. The Prototype Repository experiment was designed to in full scale test the engineered barriers and their function, including the plug that separate the deposition tunnel from the temporary access- and transportation tunnels that are at atmospheric pressure. This plug is designed and constructed as a concrete plug with a spherical front side and a flat pressurised side. This report presents the processes and operations that were considered when developing the 'plug', design, construction and verification. In the Prototype Repository the demand of leakage control is very high and the maximum length of the plugs is constrained due to available clearance space, experimental set-up and configuration. Therefore a typical 'friction plug' normally used to block waterways in connection with hydropower plants, is not suitable. Instead a plug constructed as an 'arch plug' with abutments was considered. In order to minimize the Excavation Disturbed Zone (EDZ) the abutments, in which the plug is inserted, was excavated by seam drilling with coring technique. The steel formwork was pre-assembled at the ground surface before taken down to the tunnel. The steel was bolted and welded together and crossbars and plywood were mounted on top. Before taken down to the tunnel, the formwork was separated into smaller pieces that were easier to transport down the tunnel but easy to assembly at the Prototype Repository experiment. Before assembling the formwork, a retaining wall was installed to resist the earth and compaction pressure developed from the backfill material. The retaining wall consists of pre-fabricated concrete beams that were installed parallel with the installation of the backfill. Reinforcement was cut and bent at the factory and was ready for

Prototype CIRCE plant - industrial demonstration of heavy water production from reformed hydrogen source

International Nuclear Information System (INIS)

Spagnolo, D.A.; Boniface, H.A.; Sadhankar, R.R.; Everatt, A.E.; Miller, A.I.; Blouin, J.

2002-01-01

Heavy water (D 2 0) production has been dominated by the Girdler-Sulphide (G-S) process, which suffers several intrinsic disadvantages that lead to high production costs. Processes based on hydrogen/water exchange have become more attractive with the development of proprietary wetproofed catalysts by AECL. One process that is synergistic with industrial hydrogen production by steam methane reforming (SMR), the Combined Industrial Reforming and Catalytic Exchange (CIRCE) process, offers the best prospect for commercialization. SMRs are common globally in the oil-upgrading and ammonia industries. To study the CIRCE process in detail, AECL, in collaboration with Air Liquide Canada, constructed a prototype CIRCE plant (PCP) in Hamilton, Ontario. The plant became fully operational in 2000 July and is expected to operate to at least late fall of 2002. To-date, plant operation has confirmed the adequacy of the design and the capability of enriching deuterium to produce heavy water without compromising hydrogen production. The proprietary wetproofed catalyst has performed as expected, both in activity and in robustness. (author)

Construction technique for a chemical plant (III)

International Nuclear Information System (INIS)

1978-08-01

This book mentions design of instrumentation and construction for a chemical plant, which deals with the change of instrumentation, construction, choice of material test, construction of thermal insulation work for a chemical plant, about classification and main materials, the problems on construction, painting plan and construction for a chemical plant such as paint and painting, safety and hygiene, cleaning of a chemical plant on the time for washing and decision of the way of washing, start up test for a chemical plant such as introduction of the check, construction and repair.

Experience in construction and operation of HWR plants in Argentina

International Nuclear Information System (INIS)

Madero, C.C.; Cosentino, J.O.

1982-01-01

''ATUCHA I'', the first nuclear power plant in Argentina, is in commerical operation since 1974 with a high capacity factor. The reactor is based on the MZFR prototype designed by SIEMENS with natural uranium and heavy water and PWR technic. The plant was built by SIEMENS on a turnkey contract and was rated 340 MWe. The offer presented in that opportunity by KWU was based on two reactors (ATUCHA I type) inside one single containment, due to the limitation in power of the reactor. Subsequent changes in the nature of the contract resulted in an active participation of CNEA engineering groups in the erection and commissioning of the reactor. In 1978 the national government approved a nuclear power plan to install four 600 MWe HWR plants until 1995. To start implementing this program, CNEA called for tenders for the supply of components and services for the ATUCHA II plant, in connection with the establishment of a local engineering company and the supply and construction of a heavy water production plant. In 1980 a contract was signed with KWU and the local company ENACE was formed to act as architect engineer and site coordinator. The plant will be located in the ATUCHA I site and the reactor will be similar but double in power to that one. Following the schedule of the nuclear plan, CNEA has just started preliminary studies for the next nuclear plant. ENACE will be responsible for the preparation of an offer for an ATUCHA reactor type. Local engineering and manufacturing firms, upon request and coordination from CNEA, and evaluating the local capacity to participate in the design and construction of a CANDU type nuclear plant. Final decision on this fourth nuclear plant in Argentina will be taken middle 1983. (J.P.N.)

MMSW. A large-size micromegas quadruplet prototype. Design and construction

Energy Technology Data Exchange (ETDEWEB)

Kuger, Fabian; Sidiropoulou, Ourania [Julius Maximilians Universitaet, Wuerzburg (Germany); European Organization for Nuclear Research (CERN), Geneva (Switzerland); Bianco, Michele; Danielsson, Hans; Degrange, Jordan; Oliveira, Rui de; Farina, Eduardo; Iengo, Paolo; Perez Gomez, Francisco; Sekhniaidze, Givi; Sforza, Federico; Vergain, Maurice; Wotschack, Joerg [European Organization for Nuclear Research (CERN), Geneva (Switzerland); Duedder, Andreas; Lin, Tai-Hua; Schott, Matthias [Johannes Gutenberg-Universitaet, Mainz (Germany)

2016-07-01

Two micromegas detector quadruplets with an area of 0.5 m{sup 2} (MMSW) have been recently constructed and tested at CERN and University of Mainz. They serve as prototypes for the planned upgrade project of the ATLAS muon system. Their design is based on the resistive-strip technology and thus renders the detectors spark tolerant. The applied 'mechanically floating' mesh design allows for large area Micromegas construction and facilitates detector cleaning before assembly. Each quadruplet comprises four detection layers with 1024 readout strips and a strip pitch of 415 μm. In two out of the four layers the strips are inclined by ± 1.5 to allow for the measurement of a second coordinate. We present the detector concept and report on the experience gained during the detector construction.

ITER Fast Plant System Controller prototype based on PXIe platform

International Nuclear Information System (INIS)

Ruiz, M.; Vega, J.; Castro, R.; Sanz, D.; López, J.M.; Arcas, G. de; Barrera, E.; Nieto, J.; Gonçalves, B.; Sousa, J.; Carvalho, B.; Utzel, N.; Makijarvi, P.

2012-01-01

Highlights: ► Implementation of Fast Plant System Controller (FPSC) for ITER CODAC. ► Efficient data acquisition and data movement using EPICS. ► Performance of PCIe technologies in the implementation of FPSC. - Abstract: The ITER Fast Plant System Controller (FPSC) is based on embedded technologies. The FPSC will be devoted to both data acquisition tasks (sampling rates higher than 1 kHz) and control purposes (feedback loop actuators). Some of the essential requirements of these systems are: (a) data acquisition and data preprocessing; (b) interfacing with different networks and high speed links (Plant Operation Network, timing network based on IEEE1588, synchronous data transference and streaming/archiving networks); and (c) system setup and operation using EPICS (Experimental Physics and Industrial Control System) process variables. CIEMAT and UPM have implemented a prototype of FPSC using a PXIe (PCI eXtension for Instrumentation) form factor in a R and D project developed in two phases. The paper presents the main features of the two prototypes developed that have been named alpha and beta. The former was implemented using LabVIEW development tools as it was focused on modeling the FPSC software modules, using the graphical features of LabVIEW applications, and measuring the basic performance in the system. The alpha version prototype implements data acquisition with time-stamping, EPICS monitoring using waveform process variables (PVs), and archiving. The beta version prototype is a complete IOC implemented using EPICS with different software functional blocks. These functional blocks are integrated and managed using an ASYN driver solution and provide the basic functionalities required by ITER FPSC such as data acquisition, data archiving, data pre-processing (using both CPU and GPU) and streaming.

Construction method for plant facility

International Nuclear Information System (INIS)

Ito, Arata; Hirono, Hideharu; Kyoda, Shigeru; Hanawa, Minoru; Sato, Hitoshi

1998-01-01

A caisson structure is disposed on a construction site for facilities of nuclear power plants. A digging work is performed below the caisson structure and, simultaneous with the digging work, a construction of a base, construction of plant facilities including a building and installation of plant facility are performed on the caisson structure. Then, the caisson structure is sank together with the structures on a base rock in association with the progress of the digging work and secured on the base rock. When securing them on the base rock, a groove is formed to the base rock along tuyere of the caisson structure so that the tuyere and a ceiling portion of the caisson structure are in direct contact with the base rock. Since the construction for the containing building conducted on the caisson structure is performed simultaneous with the digging work conducted below the caisson structure, the term required for the construction of the plant facilities can greatly reduced. (N.H.)

Prototype CIRCE plant-industrial demonstration of heavy-water production from a reformed hydrogen source

Energy Technology Data Exchange (ETDEWEB)

Spagnolo, D.A.; Boniface, H.A.; Sadhankar, R.R.; Everatt, A.E.; Miller, A.I. [Atomic Energy of Canada Limited, Chalk River, Ontario (Canada); Blouin, J. [Air Liquide Canada, Hamilton, Ontario (Canada)

2002-09-01

Heavy-water (D{sub 2}0) production has been dominated by the Girdler-Sulphide (G-S) process, which suffers several intrinsic disadvantages that lead to high production costs. Processes based on hydrogen/water exchange have become more attractive with the development of proprietary wetproofed catalysts by AECL. One process that is synergistic with industrial hydrogen production by steam methane reforming (SMR), the combined industrial reforming and catalytic exchange (CIRCE) process, offers the best prospect for commercialization. SMRs are common globally in the oil upgrading and ammonia industries. To study the CIRCE process in detail, AECL, in collaboration with Air Liquide Canada, constructed a prototype CIRCE plant (PCP) in Hamilton, ON. The plant became fully operational in 2000 July and is expected to operate to at least the late fall of 2002. To date, plant operation has confirmed the adequacy of the design and the capability of enriching deuterium to produce heavy water without compromising hydrogen production. The proprietary wetproofed catalyst has performed as expected, both in activity and in robustness. (author)

Prototype CIRCE plant-industrial demonstration of heavy-water production from a reformed hydrogen source

International Nuclear Information System (INIS)

Spagnolo, D.A.; Boniface, H.A.; Sadhankar, R.R.; Everatt, A.E.; Miller, A.I.; Blouin, J.

2002-09-01

Heavy-water (D 2 0) production has been dominated by the Girdler-Sulphide (G-S) process, which suffers several intrinsic disadvantages that lead to high production costs. Processes based on hydrogen/water exchange have become more attractive with the development of proprietary wetproofed catalysts by AECL. One process that is synergistic with industrial hydrogen production by steam methane reforming (SMR), the combined industrial reforming and catalytic exchange (CIRCE) process, offers the best prospect for commercialization. SMRs are common globally in the oil upgrading and ammonia industries. To study the CIRCE process in detail, AECL, in collaboration with Air Liquide Canada, constructed a prototype CIRCE plant (PCP) in Hamilton, ON. The plant became fully operational in 2000 July and is expected to operate to at least the late fall of 2002. To date, plant operation has confirmed the adequacy of the design and the capability of enriching deuterium to produce heavy water without compromising hydrogen production. The proprietary wetproofed catalyst has performed as expected, both in activity and in robustness. (author)

Summary of nuclear power plant construction

International Nuclear Information System (INIS)

Tamura, Saburo

1973-01-01

Various conditions for the construction of nuclear power plants in Japan without natural resources were investigated. Expansion of the sites of plants, change of reactor vessels, standardization of nuclear power plants, possiblity of the reduction of construction period, approaching of nuclear power plants to consuming cities, and group construction were studied. Evaluation points were safety and economy. Previous sites of nuclear power plants were mostly on plane ground or cut and enlarge sites. Proposals for underground or offshore plants have been made. The underground plants were made at several places in Europe, and the ocean plant is now approved in U.S.A. as a plant on a man-made island. Vessels for containing nuclear reactors are the last barriers to the leakage of radioactive substance. At the initial period, the vessels were made of steel, which were surrounded by shielding material. Those were dry well type containers. Then, vessel type changed to pressure-suppression type wet containers. Now, it tends to concrete (PC or RC) type containers. There is the policy on the standardization of nuclear power plants by U.S.A.E.C. in recent remarkable activity. The merit and effect of the standardization were studied, and are presented in this paper. Cost of the construction of nuclear power plants is expensive, and interest of money is large. Then, the reduction of construction period is an important problem. The situations of plants approaching to consuming cities in various countries were studied. Idea of group construction is described. (Kato, T.)

U Plant Geographic Zone Cleanup Prototype

International Nuclear Information System (INIS)

Romine, L.D.; Leary, K.D.; Lackey, M.B.; Robertson, J.R.

2006-01-01

The U Plant geographic zone (UPZ) occupies 0.83 square kilometers on the Hanford Site Central Plateau (200 Area). It encompasses the U Plant canyon (221-U Facility), ancillary facilities that supported the canyon, soil waste sites, and underground pipelines. The UPZ cleanup initiative coordinates the cleanup of the major facilities, ancillary facilities, waste sites, and contaminated pipelines (collectively identified as 'cleanup items') within the geographic zone. The UPZ was selected as a geographic cleanup zone prototype for resolving regulatory, technical, and stakeholder issues and demonstrating cleanup methods for several reasons: most of the area is inactive, sufficient characterization information is available to support decisions, cleanup of the high-risk waste sites will help protect the groundwater, and the zone contains a representative cross-section of the types of cleanup actions that will be required in other geographic zones. The UPZ cleanup demonstrates the first of 22 integrated zone cleanup actions on the Hanford Site Central Plateau to address threats to groundwater, the environment, and human health. The UPZ contains more than 100 individual cleanup items. Cleanup actions in the zone will be undertaken using multiple regulatory processes and decision documents. Cleanup actions will include building demolition, waste site and pipeline excavation, and the construction of multiple, large engineered barriers. In some cases, different cleanup actions may be taken at item locations that are immediately adjacent to each other. The cleanup planning and field activities for each cleanup item must be undertaken in a coordinated and cohesive manner to ensure effective execution of the UPZ cleanup initiative. The UPZ zone cleanup implementation plan (ZCIP) [1] was developed to address the need for a fundamental integration tool for UPZ cleanup. As UPZ cleanup planning and implementation moves forward, the ZCIP is intended to be a living document that will

Construction technique for a chemical plant (I)

International Nuclear Information System (INIS)

1978-08-01

This book mentions the order of plant construction, building plant and related regulations, basic engineering design data, provide of equipment, plan and management on building plant, quality control, the budget and contract for building plant, public works for building chemical plant like road construction, basic plan and building for a chemical plant, introduction and principle on foundation improvement method, including pile foundation and design for footing, construction and installation for a chemical plant and a rotary machine for a chemical plant.

Construction technique for a chemical plant (II)

International Nuclear Information System (INIS)

1978-08-01

This book deals with design and construction for a chemical plant which includes design and building of steel structure for a chemical plant with types, basic regulation, plan, shop fabrication for steel structure and field construction. It explains design and construction of making building for a chemical construction with measurement, types of building and basic rule of the building, design of the building, constructing plumbing for a chemical plant with plan, management of material, checking for construction, construction of electrical installation on plan, know-how to construction and maintenance.

Biointrusion test plan for the Permanent Isolation Surface Barrier Prototype

International Nuclear Information System (INIS)

Link, S.O.; Cadwell, L.L.; Brandt, C.A.; Downs, J.L.; Rossi, R.E.; Gee, G.W.

1994-04-01

This document provides a testing and monitoring plan for the biological component of the prototype barrier slated for construction at the Hanford Site. The prototype barrier is an aboveground structure engineered to demonstrate the basic features of an earthen cover system. It is designed to permanently isolate waste from the biosphere. The features of the barrier include multiple layers of soil and rock materials and a low-permeability asphalt sublayer. The surface of the barrier consists of silt loam soil, covered with plants. The barrier sides are reinforced with rock or coarse earthen-fill to protect against wind and water erosion. The sublayers inhibit plant and animal intrusion and percolation of water. A series of tests will be conducted on the prototype barrier over the next several years to evaluate barrier performance under extreme climatic conditions. Plants and animals will play a significant role in the hydrologic and water and wind erosion characteristics of the prototype barrier. Studies on the biological component of the prototype barrier will include work on the initial revegetation of the surface, continued monitoring of the developing plant community, rooting depth and dispersion in the context of biointrusion potential, the role of plants in the hydrology of the surface and toe regions of the barrier, the role of plants in stabilizing the surface against water and wind erosion, and the role of burrowing animals in the hydrology and water and wind erosion of the barrier

Virtual Prototyping for Construction Site Co2 Emissions and Hazard Detection

Directory of Open Access Journals (Sweden)

Johnny Kwok Wai Wong

2014-08-01

Full Text Available The need for an efficient means of managing emissions and identifying potential hazard black spots in construction processes effectively and at the lowest cost possible has been highlighted in the construction sector. This study illustrates an integrated 5D model developed for quantifying carbon emissions and simulating the pattern of emissions of construction processes as a whole using virtual prototyping technologies. The predicted construction emissions data for each activity is generated and plotted to visually demonstrate the emission rates alongside the integrated four-dimensional VP framework of the construction project. The model also consists of a pro-active construction management system (PCMS, which assist the project team to detect sources of danger to on-site workers and provide pro-active warnings to them so as to avoid fatal accidents that are often caused by falling from heights and being struck by moving objects. A Hong Kong high-rise housing development project is used to exhibit the application of the carbon emission visualisation and potential accident detection system. This tool aims to encourage construction industry practitioners to become more environmentally conscious and pro-active in carbon mitigation and safety performance.

Construction of a sTGC Prototype for the ATLAS-MUON Upgrade

CERN Document Server

Guan, Liang; The ATLAS collaboration; Zhu, Junjie; Smakhtin, Vladimir; Shoa, Meir

2014-01-01

The innermost station (Small Wheel) of the ATLAS muon spectrometer end-cap will be replaced with the New Small Wheel (NSW) to profit from the high luminosity runs of LHC after phase I upgrade . sTGC will be the primary trigger detectors proving Level-1 trigger as well as complementing the precision muon tracking. In order to qualify materials and gain experiences for serious mass production of NSW sTGC detector modules, a 1.3 m x 1.1 mm sTGC quadruplet prototype is successfully constructed and tested. Details of the construction procedures will be presented. Control of the module flatness, machined strip board precision and alignment of different detector layers will be shown.

Construct ability Improvement for Nuclear Power Plants

Energy Technology Data Exchange (ETDEWEB)

Lee, Dae Soo; Lee, Jong Rim; Kim, Jong Ku [Korea Electric Power Research Institute, Taejon (Korea, Republic of)

1997-12-31

The purpose of this study was to identify methods for improving the construct ability of nuclear power plants. This study reviewed several references of current construction practices of domestic and overseas nuclear plants in order to identify potential methods for improving construct ability. The identified methods for improving construct ability were then evaluated based on the applicability to domestic nuclear plant construction. The selected methods are expected to reduce the construction period, improve the quality of construction, cost, safety, and productivity. Selection of which methods should be implemented will require further evaluation of construction modifications, design changes, contract revisions. Among construction methods studied, platform construction methods can be applied through construction sequence modification without significant design changes, and Over the Top construction method of the NSSS, automatic welding of RCL pipes, CLP modularization, etc., are considered to be applied after design modification and adjustment of material lead time. (author). 49 refs., figs., tabs.

Applicability of the 'constructional fire prevention for industrial plants' to power plants

International Nuclear Information System (INIS)

Hammacher, P.

1978-01-01

Power plants, especially nuclear power plants, are considered because of their high value and large construction volume to be among the most important industrial constructions of our time. They have a very exposed position from the point of view of fire prevention because of their constructional and operational concept. The efforts in the Federal Republic of Germany to standardize laws and regulations for fire prevention in industrial plants (industrial construction code, DIN 18230) must be supported if only because they would simplify the licensing procedure. However these regulations cannot be applied in many cases and especially in the main buildings of thermal power plants without restricting or even endangering the function or the safety of such plants. At the present state of the art many parts of the power plant can surely be defined as 'fire safe'. Fire endangered plant components and rooms are protected according to their importance by different measures (constructional measures, fire-fighting equipments, extractors for flue gases and for heat, fire-brigade of the plant). (orig.) [de

A CAREM fuel assembly prototype construction in order to verify its mechanical design using hydrodynamic testing

International Nuclear Information System (INIS)

Aparicio, Gaspar; Di Marco, Agustin; Falcone, Jose M.; Giorgis, Miguel A.; Mathot, Sergio R.; Migliori, Julio; Orlando, Oscar S.; Restelli, Miguel A.; Ruggirello, Gabriel; Sapia, Gustavo C.; Zinzallari, Fausto; Bianchi, Daniel R.; Volpi, Ricardo M.

2000-01-01

The scope of this paper is to describe the activities of several Groups from three Atomic Centers (C. A. Bariloche, C. A. Ezeiza and C. A. Constituyentes), involved in the manufacturing of a CAREM fuel assembly prototype. The Design Group (UAIN-CAB) carried out the fuel assembly engineering. Cladding components were constructed by the Special Alloys Pilot Factory (UAMCN-CAE). Engineering Group (UACN-CAC) manufactured the parts to be processed, resorting to qualified suppliers. Elastic spacers were completely designed and constructed by this Group, and fuel rods, control rods, guide tubes and spacers were also welded here. Research Reactors Fuels Group (UACN-CAC) carried out the dimensional control of the elaborated parts, while Postirradiation Testing Group (UACN-CAC) performed the assembling of the fuel element. This paper also refers to the design and development of special equipment and devices, all of them required for the prototype construction. (author)

Prototype of an expert system based nuclear power plant information systems

International Nuclear Information System (INIS)

Vegh, J.; Bodnar, M.; Buerger, L.; Tanyi, M.; Sefesik, F.

1994-01-01

The components and functioning of the GPCS information system applicable for intelligent process monitoring and alarm generation in a WWER-440 type nuclear power plant are described. The prototype system has been developed by using the G2 expert system, plant measurements were simulated by a WWER-440 compact simulator and by archive replay sessions performed by the VERONA-u core monitoring system. The GPCS contains an object oriented description of the basic subsystems of the plant and concentrates on the fast evaluation/displaying of measurements and alarms. The high-level information reflecting actual plant safety status is synthesized from primary measured data, by forming global alarms and by evaluating logical diagrams. (author). 10 refs, 4 figs

Advanced construction methods for new nuclear power plants

International Nuclear Information System (INIS)

Bilbao y Leon, Sama; Cleveland, John; Moon, Seong-Gyun; Tyobeka, Bismark

2009-01-01

The length of the construction and commissioning phases of nuclear power plants have historically been longer than for conventional fossil fuelled plants, often having a record of delays and cost overruns as a result from several factors including legal interventions and revisions of safety regulations. Recent nuclear construction projects however, have shown that long construction periods for nuclear power plants are no longer the norm. While there are several inter-related factors that influence the construction time, the use of advanced construction techniques has contributed significantly to reducing the construction length of recent nuclear projects. (author)

Construction of the Temelin nuclear power plant

International Nuclear Information System (INIS)

Jicha, J.

1989-01-01

The Temelin nuclear power plant with four WWER-1000 reactors is designed to supply electricity in an amount of 23 TWh/yr and heat in an amount of 8000 TJ/yr in the first stage. The maximum heat extraction should be 922 MW. The plant construction includes the building of 10 buildings, the total cost being 52 thousand million Czechoslovak crowns. Another 41 investment items are associated with the plant construction. The most important of them include constructions for leading out the electric power, for standby electricity supply for the power plant, and for the extraction of heat from the plant and its supply to the town of Ceske Budejovice. The first unit should be started up for test performance in November 1992, the second in 1994 and the whole power plant should be complete by 1998. The state of the construction by February 1989 is described in detail. Attention is also paid to the preparatory activity for the operation and to social welfare of the personnel. (Z.M.)

Construction labor productivity during nuclear power plant construction

International Nuclear Information System (INIS)

Murray, W.B.

1980-01-01

There is no single satisfactory way to measure productivity in the construction industry. The industry is too varied, too specialized and too dependent upon vast numbers of interrelations between trades, contractors, designers and owners. Hence, no universally reliable indices for measuring construction productivity has been developed. There are problems that are generic to all large union-built nuclear power plants. The actions of any one owner cannot rectify the shortcomings of the construction industry. The generic problems are being identified, and many national organizations are attempting to make the construction industry more productive by recommending various changes

Development of new construction technologies for nuclear power plant

International Nuclear Information System (INIS)

Kawamata, Susumu; Itoh, Daisuke; Ichizono, Katsuyuki

1995-01-01

In order to proceed rationally with the construction of a nuclear power station, the followings are the subject to solve beside reducing the construction cost: shortening the construction period, improving the quality, and securing safety in the construction work. As a measure to solve the matters, we correctly construct the plant mainly applying 'all-weather proof construction method' and 'pre-assembled large-block construction method'. Furthermore, as the plant construction control system, we perform a construction work applying the design change management system, pre-assessment for safety, and the whole facility check. As a result of our effort, it was attained that when we compare the matured plant with the first unit, the construction cost is reduced by 30%, the construction period is shortened by 12 months, site manpower is decreased by 30%, and the plant had no sudden shutdowns even during the trial operation period. (author)

Advanced plant engineering and construction of Japanese ABWRs

International Nuclear Information System (INIS)

Gotoh, N.; Sumikawa, J.; Yoshida, N.; Yoshida, M.

1998-01-01

Remarkable improvement has been made in recent nuclear power plant design and construction in Japan. These many improved engineering technologies has been made a good use in the lately commercial operated two world's first 1,356MWe ABW's (Advanced Boiling Water Reactors), and made a great contribution to the smooth progress and the completion of a highly reliable plant construction. Especially, two engineering technologies, (1), three-dimensional computer aided design system through engineering data-base, and (2), large scale modularising construction method, have been successfully applied as the integrated engineering technologies of the plant construction. And two integrated reviews, 'integrated design review, confirmation of new and changed design and prevention of failure recurrence' in the design stage, and 'constructing plant review' at the site, have been widely and systematically conducted as a link in the chain of steady reliability improvement activities. These advanced and/or continuous and steady technologies are one of most important factors for high reliability through the entire lifetime of a nuclear plant, including planning, design, construction, operation and maintenance stages. (author)

Construction and testing of a large scale prototype of a silicon tungsten electromagnetic calorimeter for a future lepton collider

International Nuclear Information System (INIS)

Rouëné, Jérémy

2013-01-01

The CALICE collaboration is preparing large scale prototypes of highly granular calorimeters for detectors to be operated at a future linear electron positron collider. After several beam campaigns at DESY, CERN and FNAL, the CALICE collaboration has demonstrated the principle of highly granular electromagnetic calorimeters with a first prototype called physics prototype. The next prototype, called technological prototype, addresses the engineering challenges which come along with the realisation of highly granular calorimeters. This prototype will comprise 30 layers where each layer is composed of four 9×9 cm 2 silicon wafers. The front end electronics is integrated into the detector layers. The size of each pixel is 5×5 mm 2 . This prototype enters its construction phase. We present results of the first layers of the technological prototype obtained during beam test campaigns in spring and summer 2012. According to these results the signal over noise ratio of the detector exceeds the R and D goal of 10:1

Nuclear power plant construction

International Nuclear Information System (INIS)

Lima Moreira, Y.M. de.

1979-01-01

The legal aspects of nuclear power plant construction in Brazil, derived from governamental political guidelines, are presented. Their evolution, as a consequence of tecnology development is related. (A.L.S.L.) [pt

Prototypical Rod Construction Demonstration Project

International Nuclear Information System (INIS)

1993-05-01

The objective of Phase 3 of the Prototypical Rod consolidation Demonstration Project (PRCDP) was to procure, fabricate, assemble, and test the Prototypical Rod consolidation System as described in the NUS Phase 2 Final Design Report. This effort required providing the materials, components, and fabricated parts which makes up all of the system equipment. In addition, it included the assembly, installation, and setup of this equipment at the Cold Test Facility. During the Phase 3 effort the system was tested on a component, subsystem, and system level. This volume 1, discusses the PRCDP Phase 3 Test Program that was conducted by the HALLIBURTON NUS Environmental Corporation under contract AC07-86ID12651 with the United States Department of Energy. This document, Volume 1, Book 3 discusses the following topics: Downender Test Results and Analysis Report; NFBC Canister Upender Test Results and Analysis Report; Fuel Assembly Handling Fixture Test Results and Analysis Report; and Fuel Canister Upender Test Results and Analysis Report

Construction-man hour estimation for nuclear power plants

International Nuclear Information System (INIS)

Paek, J.H.

1987-01-01

This study centers on a statistical analysis of the preliminary construction time, main construction time, and total construction man hours of nuclear power plants. The use of these econometric techniques allows the major man hour driving variables to be identified through multivariate analysis of time-series data on over 80 United States nuclear power plants. The analysis made in this study provides a clearer picture of the dynamic changes that have occurred in the man hours of these plants when compared to engineering estimates of man hours, and produces a tool that can be used to project nuclear power plant man hours

Analysis of nuclear power plant construction costs

International Nuclear Information System (INIS)

1986-01-01

The objective of this report is to present the results of a statistical analysis of nuclear power plant construction costs and lead-times (where lead-time is defined as the duration of the construction period), using a sample of units that entered construction during the 1966-1977 period. For more than a decade, analysts have been attempting to understand the reasons for the divergence between predicted and actual construction costs and lead-times. More importantly, it is rapidly being recognized that the future of the nuclear power industry rests precariously on an improvement in the cost and lead-time situation. Thus, it is important to study the historical information on completed plants, not only to understand what has occurred to also to improve the ability to evaluate the economics of future plants. This requires an examination of the factors that have affected both the realized costs and lead-times and the expectations about these factors that have been formed during the construction process. 5 figs., 22 tabs

Analysis of nuclear power plant construction costs

Energy Technology Data Exchange (ETDEWEB)

1986-01-01

The objective of this report is to present the results of a statistical analysis of nuclear power plant construction costs and lead-times (where lead-time is defined as the duration of the construction period), using a sample of units that entered construction during the 1966-1977 period. For more than a decade, analysts have been attempting to understand the reasons for the divergence between predicted and actual construction costs and lead-times. More importantly, it is rapidly being recognized that the future of the nuclear power industry rests precariously on an improvement in the cost and lead-time situation. Thus, it is important to study the historical information on completed plants, not only to understand what has occurred to also to improve the ability to evaluate the economics of future plants. This requires an examination of the factors that have affected both the realized costs and lead-times and the expectations about these factors that have been formed during the construction process. 5 figs., 22 tabs.

Construction plant requirements for nuclear sites

International Nuclear Information System (INIS)

Tatum, C.B.; Harris, J.A.

1981-01-01

Planning and developing the temporary construction plant facilities for a nuclear project is equivalent to providing utility services for a small city. Provision of adequate facilities is an important factor in the productivity of both the manual and non-manual work force. This paper summarizes construction facility requirements for a two unit (1300 MWe each) nuclear project. Civil, mechanical and electrical facilities are described, including design, installation and operation. Assignment of responsibility for specific work tasks regarding the construction plant is also discussed. In presenting this data, the authors seek to transfer experience and assist in the provision of adequate facilities on future projects

A Study on the Development of Prototype Seismic Isolation Device for NPP

Energy Technology Data Exchange (ETDEWEB)

Lee, Hongpyo; Cho, Myungsug; Kim, Sunyong; Lee, Yonghee; Kang Kyunghun [KHNP-CRI, Daejeon (Korea, Republic of)

2014-05-15

Korean nuclear power plants have been and still are based on seismic resistance design including all of the natural disasters. However, in regions of high seismic hazard, seismic isolation technology is needed to guarantee the seismic safety on nuclear power plants. To achieve this purpose, the research and development of seismic isolation system for the construction in high seismicity area is on-going in Korea. In this study, prototype seismic isolation devices as mentioned above are developed and tested to identify the basic shear and compressive characteristics of them. In this study, assessment performance of basic characteristics on the prototype LRB and EQS seismic isolation for nuclear power plant structures is employed to compare with design values. Based on the test results of compression and shear characteristics, it is judged that they meet the measuring efficiency range conditions which are presented in ISO 22762 and AASHOT guide specification. Therefore, prototype seismic isolation devices like LRB and EQS developed in this study can be expected to be used as reference data when designing a seismic isolation system for nuclear power plant structures in the future.

Influence of constructive parameters on the performance of two indirect evaporative cooler prototypes

International Nuclear Information System (INIS)

Tejero-González, Ana; Andrés-Chicote, Manuel; Velasco-Gómez, Eloy; Rey-Martínez, Francisco Javier

2013-01-01

Two equally-sized cross-flow heat-exchanger prototypes have been designed with a total heat exchange area of 6 m 2 and 3 m 2 respectively, constructed with polycarbonate hollow panels of different cross section. They are connected into a heat-recovery cycle within the whole experimental setup constructed for the tests, which mainly consists of: an Air Handling Unit to simulate the outdoor airstream conditions, a conditioned climate chamber, and a water circuit to provide the water supply required. They have been experimentally characterised in two operating modes in order to determine how evaporative cooling improves heat recovery in each case, focussing on the influence of modifying the constructive characteristics. To perform the evaporative cooling process, water is supplied to the exhaust airstream. Results are studied considering how constructive issues, outdoor air volume flow rate and temperature, as well as operating mode influence on the performance obtained. An Analysis of Variance shows how outdoor airflow has a key role in the performance of the systems; whereas entering outdoor air temperature determines cooling capacities. Improvements introduced by larger heat exchange areas compensate with their corresponding smaller cross sections, which hinder water – air distribution on the exhaust air side of the heat exchanger. Finally, these small devices achieve cooling capacities of up to 800 W, being able to partly support ventilation load and achieving around 50% of energy saving in ventilation cooling. -- Highlights: ► Two indirect evaporative cooler prototypes are experimentally characterised. ► Evaporative cooling improves heat recovery. ► Influence on performance of different heat exchange area and cross section is studied. ► Larger cross section favours evaporative cooling process. ► Effect of smaller heat exchange area is compensated by that of larger cross section

Nuclear power plant equipment design and construction rules

International Nuclear Information System (INIS)

Boiron, P.

1983-03-01

Presentation of the AFCEN (French association for nuclear power plant equipment design and construction rules) working, of its edition activity and of somes of its edited documents such as RCC-C (design and construction rules for PWR power plant fuel assemblies) and RCC-E (design and construction rules for nuclear facility electrical equipments) [fr

Nuclear power plant construction activity, 1986

International Nuclear Information System (INIS)

1987-01-01

Cost estimates, chronological data on construction progress, and the physical characteristics of nuclear units in commercial operation and units in the construction pipeline as of December 31, 1986, are presented. This report, which is updated annually, was prepared to provide an overview of the nuclear power plant construction industry. The report contains information on the status of nuclear generating units, average construction costs and lead-times, and construction milestones for individual reactors

Prototype equipment status monitor for plant operational configuration management

International Nuclear Information System (INIS)

DeVerno, M.; Trask, D.; Groom, S.

1998-01-01

CANDU plants, such as the Point Lepreau GS, have tens of thousands of operable devices. The status of each operable device must be immediately available to plan and execute future changes to the plant. Historically, changes to the plant's operational configuration have been controlled using manual and administrative methods where the status of each operable device is maintained on operational flowsheets located in the work control area of the main control room. The operational flowsheets are used to plan and develop Operating Orders (OOs) or Order-to-Operate (OTOs) and the control centre work processes are used to manage their execution. After performing each OO procedure, the operational flowsheets are updated to reflect the new plant configuration. This process can be very time consuming, and due to the manual processes, can lead to the potential for time lags and errors in the recording of the current plant configuration. Through a cooperative research and development program, Canadian CANDU utilities and Atomic Energy of Canada Limited, the design organization, have applied modern information technologies to develop a prototype Equipment Status Monitor (ESM) to address processes and information flow for efficient operational configuration management. The ESM integrates electronic operational flowsheets, equipment databases, engineering and work management systems, and computerized procedures to assess, plan, execute, track, and record changes to the plant's operational configuration. This directly leads to improved change control, more timely and accurate plant status information, fewer errors, and better decision making regarding future changes. These improvements to managing the plant's operational configuration are essential to increasing plant safety, achieving a high plant availability, and maintaining high capability and capacity factors. (author)

Prototype Development of an ICT System to Support Construction Management Based on Virtual Models and RFID

DEFF Research Database (Denmark)

Sørensen, Kristian Birch; Christiansson, Per; Svidt, Kjeld

2009-01-01

early example) of an ICT system was carried out to identify and formalise user needs in relation to construction management based on virtual models and radio frequency identification (RFID). The prototype was developed to support working processes in real-time project progress management, quality...

Nuclear Power Station Kalkar, 300 MWe Prototype Nuclear Power Plant with Fast Sodium Cooled Reactor (SNR-300), Plant description

International Nuclear Information System (INIS)

1984-06-01

The nuclear power station Kalkar (SNR-300) is a prototype with a sodium cooled fast reactor and a thermal power of 762 MW. The present plant description has been made available in parallel to the licensing procedure for the reactor plant and its core Mark-Ia as supplementary information for the public. The report gives a detailed description of the whole plant including the prevention measures against the impact of external and plant internal events. The radioactive materials within the reactor cooling system and the irradiation protection and surveillance measures are outlined. Finally, the operation of the plant is described with the start-up procedures, power operation, shutdown phases with decay heat removal and handling procedures

Pre evaluation for heat balance of prototype sodium cooled fast reactor

International Nuclear Information System (INIS)

Han, Ji Woong; Kim, De Hee; Yoon, Jung; Kim, Eui Kwang; Lee, Tae Ho

2012-01-01

Under the long term advanced SFR R and D plan, the design of prototype reactor has been carried out toward the construction of the prototype SFR plant by 2028. The R and D efforts in fluid system design will be focused on developing a prototype design of primary heat transport system(PHTS), intermediate heat transport system (IHTS), decay heat removal system(DHRS), steam generation system(SGS), and related auxiliary system design for a prototype reactor as shown in Fig. 1. In order to make progress system design, top tier requirements for prototype reactor related to design parameters of NSSS and BOP should be decided at first. The top tier requirement includes general design basis, capacity and characteristics of reactor, various requirements related to safety, performance, securities, economics, site, and etc.. Extensive discussion has been done within Korea Atomic Energy Research Institute(KAERI) for the decision of top tier requirements of the prototype reactor. The core outlet temperature, which should be described as top tier requirements, is one of the critical parameter for system design. The higher core exit temperature could contribute to increase the plant efficiency. However, it could also contribute to decrease the design margin for structure and safety. Therefore various operating strategies based on different core outlet temperatures should be examined and evaluated. For the prototype reactor two core outlet temperatures are taken into accounted. The lower temperature is for the operation condition and the higher temperature is for the system design and licensing process of the prototype reactor. In order to evaluate the operability of prototype reactor designed based on higher temperature, the heat balance calculations have been performed at different core outlet temperature conditions. The electrical power of prototype reactor was assumed to be 100MWe and reference operating conditions were decided based on existing available data. The

Methodology for modular nuclear plant design and construction

International Nuclear Information System (INIS)

Lapp, C.W.; Golay, M.

1992-01-01

During the past decade, the rising cost of nuclear power plant construction has caused the cancellation of many projects and has forced some utilities into bankruptcy. Many factors have contributed to capital cost increases, including regulatory changes, the absence of standard designs, and low worker productivity. Low worker productivity can be attributed to the conventional building process, which is not conductive to productive labor. This study presents innovative ways to reduce the capital cost of nuclear plants through more efficient construction processes designed to increase worker productivity. A major portion of the plant capital cost is the interest paid during construction on borrowed capital. Modular fabrication could potentially reduce interest payments by compressing the construction schedule of nuclear facilities. Additional cost savings expected from modular designs arise from improved quality, productivity, and schedule control in fabrication of plant elements within a factory environment

Modularization Technology in Power Plant Construction

International Nuclear Information System (INIS)

Kenji Akagi; Kouichi Murayama; Miki Yoshida; Junichi Kawahata

2002-01-01

Since the early 1980's, Hitachi has been developing and applying modularization technology to domestic nuclear power plant construction, and has achieved great rationalization. Modularization is one of the plant construction techniques which enables us to reduce site labor by pre-assembling components like equipment, pipes, valves and platforms in congested areas and installing them using large capacity cranes for cost reduction, better quality, safety improvement and shortening of construction time. In this paper, Hitachi's modularization technologies are described especially from with respect to their sophisticated design capabilities. The application of 3D-CAD at the detailed layout design stage, concurrent design environment achieved by the computer network, module design quantity control and the management system are described. (authors)

Construction of a full-length prototype of the BESIII drift chamber and on-detector test for the BESIII drift chamber electronics

International Nuclear Information System (INIS)

Qin Zhonghua; Wu Linghui; Liu Jianbei; Chinese Academy of Sciences, Beijing; Yan Zhikang; Hunan Univ., Changsha; Chen Yuanbo; Chen Chang; Xu Meihang; Wang Lan; Ma Xiaoyan; Jin Yan; Liu Rongguang; Tang Xiao; Zhang Guifang; Zhu Qiming; Sheng Huayi; Zhu Kejun

2007-01-01

A full-length prototype of the BESIII drift chamber was built. The experience gained on gas sealing, high voltage supply and front-end electronics installation should be greatly beneficial to the successful construction of the BESIII drift chamber. An on-detector test of the BESIII drift chamber electronics was carried out with the constructed prototype chamber. The noise performance, drift time and charge measurements, and electronics gains were examined specifically. The final test results indicate that the electronics have a good performance and can satisfy their design requirements. (authors)

Modular construction approach for advanced nuclear plants

International Nuclear Information System (INIS)

Johnson, F.T.; Orr, R.S.; Boudreaux, C.P.

1988-01-01

Modular construction has been designated as one of the major features of the AP600 program, a small innovative 600-MW (electric) advanced light water reactor (ALWR) that is currently being developed by Westinghouse and its subcontractors. This program is sponsored by the US Department of Energy (DOE) in conjunction with several other DOE and Electric Power Research Institute ALWR programs. Two major objectives of the AP600 program are as follows: (1) to provide a cost of power competitive with other power generation alternatives; and (2) to provide a short construction schedule that can be met with a high degree of certainty. The AP600 plant addresses these objectives by providing a simplified plant design and an optimized plant arrangement that result in a significant reduction in the number and size of systems and components, minimizes the overall building volumes, and consequently reduces the required bulk quantities. However, only by adopting a modular construction approach for the AP600 can the full cost and schedule benefits be realized from the advances made in the plant systems design and plant arrangement. Modularization is instrumental in achieving both of the above objectives, but most of all, a total modularization approach is considered absolutely essential to ensure that an aggressive construction schedule can be met with a high degree of certainty

Yemen watched from cement plant construction work. Cement plant koji wo toshite mita Yemen

Energy Technology Data Exchange (ETDEWEB)

Furuta, M [Kajima Corp., Tokyo (Japan)

1993-06-25

Construction of a cement plant was planned at southern part of Yemen. This is a cement plant with annual production 500,000 tons. The term of work was from January, 1990 to February, 1993. The present paper describes an outline the construction of this Cement Plant, the nationality and living environment in Yemen, and construction equipment which was used. The construction work consisted of 113,000m[sup 3] of digging, 82,000m[sup 3] of backfilling, 66,100m[sup 3] of concreting, and 29,285m[sup 3] of asphalt pavement. Reinforcing steel weighing 6,400 tons and steel frame weighing 3,600 tons were totally used. Equipment weighing 7,912 tons and electric devices weighing 1,299 tons were totally installed. For this construction work, two crawler cranes, six hydraulic cranes, aggregate plant, concrete mixers, and construction equipment, such as bulldozers, shovels, and dumpers, were brought from Japan. 5 figs.

Toshiba's developments on construction techniques of nuclear power plants

International Nuclear Information System (INIS)

Hayashi, Y.; Itoh, N.

1987-01-01

Reliable and economic energy supplies are fundamental requirements of energy policies in Japan. To accomplish these needs, nuclear power plants are being increased in Japan. In recent years, construction cost increases and schedule extensions have affected the capital cost of nuclear energy, compared with fossil power plants, due to lower costs of oil and coal. On the other hand, several severe regulations have been applied to nuclear power plant designs. High-quality and cooperative engineering and harmonized design of equipment and parts are strongly required. Therefore, reduced construction costs and scheduling, as well as higher quality and reliability, are the most important items for nuclear industry. Toshiba has developed new construction techniques, as well as design and engineering tools for control and management, that demonstrate the positive results achieved in the shorter construction period of 1100-MW(electric) nuclear power plants. The normal construction period so far is 64 months, whereas the current construction period is 52 months. (New construction techniques are partially applied). In future years, the construction period will be lowered to 48 months. (New construction techniques are fully applied). A construction period is defined as time from the start of rock inspection to the start of commercial operation

Evaluation of construction cost of pyro-partitioning plant

International Nuclear Information System (INIS)

Kinoshita, Kensuke; Kurata, Masateru; Inoue, Tadashi

1999-01-01

This study was conducted to evaluate the construction cost of a pyro-partitioning plant. The plant capacity was chosen to accommodate processing of the HLLW generated by PUREX reprocessing of 800 ton of spent LWR fuel. The block flow diagram and mass balance obtained from our previous experimental data were used to produce a detailed process-flow diagram and to design the plant. In this evaluation, the plant was estimated to cover an area of about 90 m x 70 m, and to cost $576 million for construction. This study shows that the cost of process equipments, such as reaction vessels, accountability tanks and so on, is just about 13% of total construction cost. On the other hand, the cost of process robots and the equipments for key measurement point (KMP) is major part in the cost of in-cell equipment. So it is clear that the construction cost can be reduced by reducing the number of material balance area (MBA) and KMP. (author)

Strengthening of nuclear power plant construction safety management

International Nuclear Information System (INIS)

Yu Jun

2012-01-01

The article describes the warning of the Fukushima nuclear accident, and analyzes the major nuclear safety issues in nuclear power development in China, problems in nuclear power plants under construction, and how to strengthen supervision and management in nuclear power construction. It also points out that the development of nuclear power must attach great importance to the safety, and nuclear power plant construction should strictly implement the principle of 'safety first and quality first'. (author)

Prototype moving-ring reactor

International Nuclear Information System (INIS)

Smith, A.C. Jr.; Ashworth, C.P.; Abreu, K.E.

1981-01-01

The objective of this work was to design a prototype fusion reactor based on fusion plasmas confined as ''Compact Toruses.' Six major criteria guided the prototype design. The prototype must: (1) produce net electricity decisively (P/sub net/ >70% of P/sub gross/), with P/sub net/ approximately 100 MW(e); (2) have small physical size (low project cost) but commercial plant; (3) have all features required of commerical plants; (4) avoid unreasonable extrapolation of technology; (5) minimize nuclear issues substantially, i.e. accident and waste issues of public concern, and (6) be modular (to permit repetitive fabrication of parts) and be maintainable with low occupational radiological exposures

Construction, Maintenance and Demolition of Nuclear Power Plants

Energy Technology Data Exchange (ETDEWEB)

Smet, Camiel de [Hilti Corporation, P.O. Box 333, FL-9494 Schaan (Liechtenstein)

2008-07-01

Hilti is your reliable partner in nuclear power plant construction, maintenance and demolition worldwide. Professional advice and innovative solutions for virtually every phase of construction and supply technologically leading products and systems to increase your productivity and help to create and maintain safe and lasting plants is offered. The solutions for nuclear power plants construction, maintenance and demolition have been employed with great success in many different countries on a wide variety of projects due in no small way to their worldwide availability. An unbroken, international exchange of experience upholds a permanent innovation process. This assures our customers that they always receive products on the very latest technological standard. This paper is not intended to cover all topics related to nuclear power plants. The idea is more to give a kind of an overview. The paper covers briefly the following topics: safety (corrosion and fire), fastenings, measuring and finally decommissioning of nuclear power plants. (author)

Construction, Maintenance and Demolition of Nuclear Power Plants

International Nuclear Information System (INIS)

Smet, Camiel de

2008-01-01

Hilti is your reliable partner in nuclear power plant construction, maintenance and demolition worldwide. Professional advice and innovative solutions for virtually every phase of construction and supply technologically leading products and systems to increase your productivity and help to create and maintain safe and lasting plants is offered. The solutions for nuclear power plants construction, maintenance and demolition have been employed with great success in many different countries on a wide variety of projects due in no small way to their worldwide availability. An unbroken, international exchange of experience upholds a permanent innovation process. This assures our customers that they always receive products on the very latest technological standard. This paper is not intended to cover all topics related to nuclear power plants. The idea is more to give a kind of an overview. The paper covers briefly the following topics: safety (corrosion and fire), fastenings, measuring and finally decommissioning of nuclear power plants. (author)

NSS design and plant construction interfaces

International Nuclear Information System (INIS)

Stewart, J.J.; Cobb, W.A.

1976-01-01

Interface management between NSS design, balance-of-plant design, and plant construction may have a significant effect on schedule stretchout and total plant costs. The paper discusses the importance of the NSS supplier's interface management role, the favorable and unfavorable influencing factors, and examples of interface areas in which experience has demonstrated that problems may arise. Where appropriate, actions are defined to avoid the problems or mitigate the consequences

Prototype Environmental Assessment of the impacts of siting and construction of an SPS ground receiving station

Science.gov (United States)

Hill, J.

1980-01-01

A prototype assessment of the environmental impacts of siting and constructing a Satellite Power System (SPS) Ground Receiving Station (GRS) is reported. The objectives of the study were: (1) to develop an assessment of the nonmicrowave related impacts of the reference system SPS GRS on the natural environment; (2) to assess the impacts of GRS construction and operations in the context of actual baseline data for a site in the California desert; and (3) to identify critical GRS characteristics or parameters that are most significant in terms of the natural environment.

Three integrated photovoltaic/sound barrier power plants. Construction and operational experience

International Nuclear Information System (INIS)

Nordmann, T.; Froelich, A.; Clavadetscher, L.

2002-01-01

After an international ideas competition by TNC Switzerland and Germany in 1996, six companies where given the opportunity to construct a prototype of their newly developed integrated PV-sound barrier concepts. The main goal was to develop highly integrated concepts, allowing the reduction of PV sound barrier systems costs, as well as the demonstration of specific concepts for different noise situations. This project is strongly correlated with a German project. Three of the concepts of the competition are demonstrated along a highway near Munich, constructed in 1997. The three Swiss installations had to be constructed at different locations, reflecting three typical situations for sound barriers. The first Swiss installation was the world first Bi-facial PV-sound barrier. It was built on a highway bridge at Wallisellen-Aubrugg in 1997. The operational experience of the installation is positive. But due to the different efficiencies of the two cell sides, its specific yield lies somewhat behind a conventional PV installation. The second Swiss plant was finished in autumn 1998. The 'zig-zag' construction is situated along the railway line at Wallisellen in a densely inhabited area with some local shadowing. Its performance and its specific yield is comparatively low due to a combination of several reasons (geometry of the concept, inverter, high module temperature, local shadows). The third installation was constructed along the motor way A1 at Bruettisellen in 1999. Its vertical panels are equipped with amorphous modules. The report show, that the performance of the system is reasonable, but the mechanical construction has to be improved. A small trial field with cells directly laminated onto the steel panel, also installed at Bruettisellen, could be the key development for this concept. This final report includes the evaluation and comparison of the monitored data in the past 24 months of operation. (author)

Plant Engineering and Construction System with Knowledge Management: A Case Study in NPP Construction in Hitachi-GE NE

International Nuclear Information System (INIS)

Mochida, T.; Hamamoto, M.; Nakamitsu, N.

2016-01-01

Full text: Hitachi-GE Nuclear Energy, Ltd. (HGNE) has more than 40 years BWR plants construction experience. The company continues to develop plant engineering system and plant construction systems based on the experience and the lessons learned. Currently, these systems are integrated in a variety of knowledge bases using the latest information technology (IT). Their performance is continuously validated in the recent NPP constructions. Typical examples are shown as case studies for knowledge management. These plant engineering and construction management systems are essential to achieve the on-time and on-budget-goals in NPP construction projects. (author

Problems and prospects of nuclear power plants construction

Directory of Open Access Journals (Sweden)

Pergamenshhik Boris Klimentyevich

2014-02-01

Full Text Available 60 years ago, in July 1954 in the city of Obninsk near Moscow the world's first nuclear power plant was commissioned with a capacity of 5 MW. Today more than 430 nuclear units with a total capacity of almost 375000 MW are in operation in dozens of the countries worldwide. 72 electrical power units are currently under construction, 8 of them are located in the Russian Federation. There will be no alternative to nuclear energy in the coming decades. Among the factors contributing to the construction of nuclear power plants reckon limited fossil fuel supply, lack of air and primarily carbon dioxide emissions. The holding back factors are breakdown, hazard, radioactive wastes, high construction costs and long construction period. Nuclear accidents in the power plant of «Three-Mile-Island» in the USA, in Chernobyl and in Japan have resulted in termination of construction projects and closure of several nuclear power plants in the Western Europe. The safety systems have become more complex, material consumption and construction costs have significantly increased. The success of modern competing projects like EPR-1600, AP1000, ABWR, national ones AES-2006 and VVER-TOI, as well as several others, depends not only on structural and configuration but also on construction and technological solutions. The increase of the construction term by one year leads to growth of estimated total costs by 3—10 %. The main improvement potentials include external plate reinforcement, pre-fabricated large-block assembly, production and installation of the equipment packages and other. One of the crucial success factors is highly skilled civil engineers training.

A COMPUTERIZED OPERATOR SUPPORT SYSTEM PROTOTYPE

Energy Technology Data Exchange (ETDEWEB)

Thomas A. Ulrich; Roger Lew; Ronald L. Boring; Ken Thomas

2015-03-01

A computerized operator support system (COSS) is proposed for use in nuclear power plants to assist control room operators in addressing time-critical plant upsets. A COSS is a collection of technologies to assist operators in monitoring overall plant performance and making timely, informed decisions on appropriate control actions for the projected plant condition. A prototype COSS was developed in order to demonstrate the concept and provide a test bed for further research. The prototype is based on four underlying elements consisting of a digital alarm system, computer-based procedures, piping and instrumentation diagram system representations, and a recommender module for mitigation actions. The initial version of the prototype is now operational at the Idaho National Laboratory using the Human System Simulation Laboratory.

Nuclear power plant containment construction

International Nuclear Information System (INIS)

Schabert, H.P.; Danisch, R.; Strickroth, E.

1975-01-01

The Nuclear Power Plant Containment Construction includes the spherical steel safety enclosure for the reactor and the equipment associated with the reactor and requiring this type of enclosure. This steel enclosure is externally structurally protected against accident by a concrete construction providing a foundation for the steel enclosure and having a cylindrical wall and a hemispherical dome, these parts being dimensioned to form an annular space surrounding the spherical steel enclosure, the latter and the concrete construction heretofore being concentrically arranged with respect to each other. In the disclosed construction the two parts are arranged with their vertical axis horizontally offset from each other so that opposite to the offsetting direction of the concrete construction a relatively large space is formed in the now asymmetrical annular space in which reactor auxiliary equipment not requiring enclosure by the steel containment vessel or safety enclosure, may be located outside of the steel containment vessel and inside of the concrete construction where it is structurally protected by the latter

The construction and evaluation of a prototype system for an image intensifier-based volume computed tomography imager

International Nuclear Information System (INIS)

Ning, R.

1989-01-01

A volumetric reconstruction of a three-dimensional (3-D) object has been at the forefront of exploration in medical applications for a long time. To achieve this goal, a prototype system for an image intensifier(II)-based volume computed tomography (CT) imager has been constructed. This research has been concerned with constructing and evaluating such a prototype system by phantom studies. The prototype system consists of a fixed x-ray tube, a specially designed aluminum filter that will reduce the dynamic range of projection data, an antiscatter grid, a conventional image intensifier optically coupled to a charge-coupled device (CCC) camera, a computer controlled turntable on which phantoms are placed, a digital computer including an A/D converter and a graphic station that displays the reconstructed images. In this study, three different phantoms were used: a vascular phantom, a resolution phantom and a Humanoid reg-sign chest phantom. The direct 3-D reconstruction from the projections was performed using a cone beam algorithm and vascular reconstruction algorithms. The image performance of the system for the direct 3-D reconstruction was evaluated. The spatial resolution limits of the system were estimated through observing the reconstructed images of the resolution phantom. By observing the images reconstructed from the projections, it can be determined that the image performance of the prototype system for a direct 3-D reconstruction is reasonably good and that the vascular reconstruction algorithms work very well. The results also indicate that the 3-D reconstructions obtained with the 11-based volume CT imager have nearly equally good resolution in x, y and z directions and are superior to a conventional CT in the resolution of the z direction

Clinch River Breeder Reactor Plant Project: construction schedule

International Nuclear Information System (INIS)

Purcell, W.J.; Martin, E.M.; Shivley, J.M.

1982-01-01

The construction schedule for the Clinch River Breeder Reactor Plant and its evolution are described. The initial schedule basis, changes necessitated by the evaluation of the overall plant design, and constructability improvements that have been effected to assure adherence to the schedule are presented. The schedule structure and hierarchy are discussed, as are tools used to define, develop, and evaluate the schedule

New plant construction cost and schedule

International Nuclear Information System (INIS)

Akins, M. J.

2009-01-01

The presentation covers the following topics: cost structure; capital costs; variation of capital costs; trends in power plant construction; studies of costs completion; periods and risks. Nuclear plant costs have recently risen so rapidly that vendors are not willing to publicly commit to cost estimates: ∼ $2000/Kw overnight costs in 2006 in the US market > $4000/Kw and in 2008 in the US market > $6000/Kw in 2008 in emerging markets. There is vendors pricing uncertainty. Current contract models may not apply. Current construction projects have problems: Olkiluoto-3 is reported to be 50% over budget and two years behind schedule, increasing perceptions that nuclear costs will continue to increase rapidly; Price of materials is a big volatile unknown, which may decrease Labor could become more available due to limited number of new projects; Lack of debt/credit to finance new project may decrease demand of new construction

Design, construction, prototype tests and performance of a vertex chamber for the MAC detector

International Nuclear Information System (INIS)

Ash, W.W.; Band, H.R.; Bloom, E.D.; Bosman, M.; Camporesi, T.; Chadwick, G.B.; Delfino, M.C.; De Sangro, R.; Ford, W.T.; Gettner, M.W.; Goderre, G.P.; Godfrey, G.L.; Groom, D.E.; Hurst, R.B.; Johnson, J.R.; Lau, K.H.; Lavine, T.L.; Leedy, R.E.; Lippi, I.; Maruyama, T.; Messner, R.L.; Moromisato, J.H.; Moss, L.J.; Muller, F.; Nelson, H.N.; Peruzzi, I.; Piccolo, M.; Prepost, R.; Pyrlik, J.; Qi, N.; Read, A.L. Jr.; Ritson, D.M.; Rosenberg, L.J.; Shambroom, W.D.; Sleeman, J.C.; Smith, J.G.; Venuti, J.P.; Verdini, P.G.; Goeler, E. von; Wald, H.B.; Weinstein, R.; Wiser, D.E.; Zdarko, R.W.; Istituto Nazionale di Fisica Nucleare, Frascati; Houston Univ., TX; Northeastern Univ., Boston, MA; Stanford Univ., CA; Stanford Linear Accelerator Center, CA; Utah Univ., Salt Lake City; Wisconsin Univ., Madison

1987-01-01

The design considerations, construction techniques, prototype tests and performance characteristics of a pressurized drift chamber used in the MAC detector at PEP are described. The chamber consists of 324 aluminized mylar tubes of 6.9 mm diameter with wall thickness of 100 μm. With appropriate shielding it operates successfully at 4.6 cm from the beam line. It was simple to construct and was configured to permit any malfunctioning tubes to be remotely disconnected without affecting operation. The chamber operated without problems for two years in the PEP environmental with a gas mixture of 49.5% argon, 49.5% CO 2 , 1% CH 4 , at 4 atm absolute pressure. The mean spatial resolution averaged over all tubes was 45 μm. The time to distance relation for this gas mixture, along with the geometric positioning of individual wires relative to the central tracking chamber, was obtained with data from Bhabha scattering events. We also describe resolution studies performed with a prototype chamber in a SLAC test beam. A wide range of gases, gas pressures, and electronic parameters were explored. These studies proved that resolutions in the 10-50 μm range were possible. Our experience demonstrates that chambers of this type provide high precision tracking and are particularly suited for operation in regions with difficult physical access and/or high ambient radiation levels. (orig.)

Design, construction, prototype tests and performance of a vertex chamber for the MAC detector

Science.gov (United States)

Ash, W. W.; Band, H. R.; Bloom, E. D.; Bosman, M.; Camporesi, T.; Chadwick, G. B.; Delfino, M. C.; De Sangro, R.; Ford, W. T.; Gettner, M. W.; Goderre, G. P.; Godfrey, G. L.; Groom, D. E.; Hurst, R. B.; Johnson, J. R.; Lau, K. H.; Lavine, T. L.; Leedy, R. E.; Lippi, I.; Maruyama, T.; Messner, R. L.; Moromisato, J. H.; Moss, L. J.; Muller, F.; Nelson, H. N.; Peruzzi, I.; Piccolo, M.; Prepost, R.; Pyrlik, J.; Qi, N.; Read, A. L.; Ritson, D. M.; Rosenberg, L. J.; Shambroom, W. D.; Sleeman, J. C.; Smith, J. G.; Venuti, J. P.; Verdini, P. G.; Von Goeler, E.; Wald, H. B.; Weinstein, R.; Wiser, D. E.; Zdarko, R. W.

1987-11-01

The design considerations, construction techniques, prototype tests and performance characteristics of a pressurized drift chamber used in the MAC detector at PEP are described. The chamber consists of 324 aluminized mylar tubes of 6.9 mm diameter with wall thickness of 100 μm. With appropriate shielding it operates successfully at 4.6 cm from the beam line. It was simple to construct and was configured to permit any malfunctioning tubes to be remotely disconnected without affecting operation. The chamber operated without problems for two years in the PEP environment with a gas mixture of 49.5% argon, 49.5% CO 2, 1% CH 4, at 4 atm absolute pressure. The mean spatial resolution averaged over all tubes was 45 μm. The time to distance relation for this gas mixture, along with the geometric positioning of individual wires relative to the central tracking chamber, was obtained with data from Bhabha scattering events. We also describe resolution studies performed with a prototype chamber in a SLAC test beam. A wide range of gases, gas pressures, and electronic parameters were explored. These studies proved that resolutions in the 10-50 μm range were possible. Our experience demonstrates that chambers of this type provide high precision tracking and are particularly suited for operation in regions with difficult physical access and/or high ambient radiation levels.

Belowground advantages in construction cost facilitate a cryptic plant invasion.

Science.gov (United States)

Caplan, Joshua S; Wheaton, Christine N; Mozdzer, Thomas J

2014-04-30

The energetic cost of plant organ construction is a functional trait that is useful for understanding carbon investment during growth (e.g. the resource acquisition vs. tissue longevity tradeoff), as well as in response to global change factors like elevated CO2 and N. Despite the enormous importance of roots and rhizomes in acquiring soil resources and responding to global change, construction costs have been studied almost exclusively in leaves. We sought to determine how construction costs of aboveground and belowground organs differed between native and introduced lineages of a geographically widely dispersed wetland plant species (Phragmites australis) under varying levels of CO2 and N. We grew plants under ambient and elevated atmospheric CO2, as well as under two levels of soil nitrogen. We determined construction costs for leaves, stems, rhizomes and roots, as well as for whole plants. Across all treatment conditions, the introduced lineage of Phragmites had a 4.3 % lower mean rhizome construction cost than the native. Whole-plant construction costs were also smaller for the introduced lineage, with the largest difference in sample means (3.3 %) occurring under ambient conditions. In having lower rhizome and plant-scale construction costs, the introduced lineage can recoup its investment in tissue construction more quickly, enabling it to generate additional biomass with the same energetic investment. Our results suggest that introduced Phragmites has had an advantageous tissue investment strategy under historic CO2 and N levels, which has facilitated key rhizome processes, such as clonal spread. We recommend that construction costs for multiple organ types be included in future studies of plant carbon economy, especially those investigating global change. Published by Oxford University Press on behalf of the Annals of Botany Company.

Construction of a Radio-Telescope Prototype in the 12 GHz Band

Science.gov (United States)

Ordóñez, J.; Quijano, A.; Luna, A.

2017-07-01

Radio astronomy is important in the branch of the Astronomy that studies the celestial bodies through their emissions in the domain of the radio waves, to obtain information of these bodies, astronomers must design new types of telescopes that can capture radiation at different wavelengths, including radio telescopes. This paper presents the construction of a prototype of an educational radio telescope, which is made using materials that are easily accessible and inexpensive. The construction of a radio telescope, will allow to carry out research in the field of radio astronomy, since at present it has not been possible to penetrate this branch due to the lack of an adequate equipment in the University of Nariño. The issues that are addressed in the construction of this instrument, its use and the analysis of the data, are very varied and with a high content of multidiciplinariety, gathering basic topics in areas such as astrophysics, physics, electronics, computing, mechanics, which are necessary for Concrete the efficient use of this instrument. For the development of the project, it counts with the advice of the director and researcher of the astronomical observatory of the University of Nariño MSc. Alberto Quijano Vodniza and Dr. Abraham Luna Castellanos of the National Institute of Astrophysics, Optics and Electronics INAOE. In addition to the construction of radiotelescope the final phase consists of the storage and analysis of data obtained with the observation of some celestial bodies that comply with The range in the 12 GHz band for study.

Design and construction of a prototype for distillation of 131 I by the dry method

International Nuclear Information System (INIS)

Palacios Gonzalez, O.G.M.

1993-01-01

Due to need of a procedure standard for production of 131 I in the Mexican Republic, is very important stablish, based in two proof for the method in hot of distillation in dry development satisfactory (radiochemistry purity of distillation 99.7 %. The development of the methodology used is based in the necessity to experience with greater amount of raw material or activity in the white as soon more time of irradiation, and, using a semiautomatic for the personal agent of the production of prototype is independent of specific characteristics to method for dry distillation, as: raw materials used, temperatures of distillation and gas for carry to 131 I. The proof to prototype are functional mechanical type, however to perfect the dry method of distillation is necessary to finish the stage of factibility to prototype. The results of proofs were in form general satisfactory waiting only to refine details and to propose the construction of a better equipment of distillation used stainless steel with completed more exacts for to garantized an useful life great to equipment and to obtain a production of 131 I continuously in the next years. (Author). 21 refs, 26 figs, 8 tabs

A prototype for actinide alpha monitoring in liquid effluents of reprocessing plants

International Nuclear Information System (INIS)

Bardone, G.; Mattia, B.; Durante, R.; Frazzoli, F.V.

1983-01-01

The report deals with the design criteria of prototype measuring device, based on the alpha spectrometry, aimed to the determination of actinides solutions in reprocessing plants. The described instrument is considered as the result of a preliminary stage of development. Taking into account the experimental results obtained with Pu bearing solutions the performances achievable are evaluated; in particular, it turns out that the minimum detectable activity is about 10 -5 Ci/l

A Study on Nonconformance and Construction Method Improvement for Nuclear Power Plant

International Nuclear Information System (INIS)

Kim, Jong Yeob; Roh, Myung Sub

2014-01-01

Advanced power reactor was developed by domestic technology, and finally exported to abroad. In order to place the current nuclear power industrial base, construction has played a big role. Without magnificent construction technology, it would have been impossible to get a safe nuclear power plant on time and in budget. Construction industry occupies very large portion of the economy in South Korea and it has been a core of South Korea's economic growth. With a competitive construction industry and advanced nuclear power plant construction know-how, South Korea could provide safe and reliable nuclear power plants in domestic and world. However there are many repairs and number of corrective actions are in actual construction. Thus, this paper suggested the result of nonconformance and construction method improvement for nuclear power plant. Constructional engineering is a kind of science that has a variety of disciplines including structure, geology, mechanical equipment and other fields. Thus, the development of constructional engineering is closely associated with experience from failure and application advanced construction method. The recent experience in nuclear power plants construction has shown that those improved methods are fully applicable and can help shorten the construction schedule. The future of nuclear power plant construction seems to be more encouraged, even though it has many obstacles

The quality of the DSM-IV obsessive-compulsive personality disorder construct as a prototype category.

Science.gov (United States)

Hummelen, Benjamin; Wilberg, Theresa; Pedersen, Geir; Karterud, Sigmund

2008-06-01

The study evaluated the quality of the DSM-IV obsessive-compulsive personality disorder (OCPD) construct as a prototype category. A sample of 2237 patients from the Norwegian Network of Psychotherapeutic Day Hospitals was examined by a variety of psychometric analyses. A high number of OCPD patients (77%) had co-occurrent PDs, but only the co-occurrence with paranoid was significantly higher than expected. Exploratory factor analysis of the PD criteria indicated that OCPD consists of 2 dimensions. The first dimension, perfectionism, was constituted by OCPD criteria only and was significantly related to obsessive-compulsive disorder. The second dimension, aggressiveness, included 2 OCPD criteria, reluctance to delegate and stubbornness, but was also defined by criteria from paranoid, antisocial, and borderline PD. Confirmatory factor analysis of the OCPD criteria indicated a poor fit of both a unitary model and a 3-dimensional model. Overall, the OCPD criteria had poor psychometric properties. Although it seems that the quality of the DSM-IV OCPD as a prototype construct is insufficient, it may be improved by deleting the criteria hoarding behavior and miserliness. Alternative criteria could be related to problems in close relationships involving the need for predictability. Such revisions may add a third dimension to the 2 dimensions of perfectionism and aggressiveness.

Comparative Studies of Core Thermal Hydraulic Design Methods for the Prototype Sodium Cooled Fast Reactor

International Nuclear Information System (INIS)

Choi, Sun Rock; Lim, Jae Yong; Kim, Sang Ji

2013-01-01

In this work, various core thermal-hydraulic design methods, which have arisen during the development of a prototype SFR, are compared to establish a proper design procedure. Comparative studies have been performed to determine the appropriate design method for the prototype SFR. The results show that the minimization method show a lower cladding midwall temperature than the fixed outlet temperature methods and superior thermal safety margin with the same coolant flow. The Korea Atomic energy Research Institute (KAERI) has performed a conceptual SFR design with the final goal of constructing a prototype plant by 2028. The main objective of the SFR prototype plant is to verify the TRU metal fuel performance, reactor operation, and transmutation ability of high-level wastes. The core thermal-hydraulic design is used to ensure the safe fuel performance during the whole plant operation. Compared to the critical heat flux in typical light water reactors, nuclear fuel damages in SFR subassemblies are arisen from a creep induced failure. The creep limit is evaluated based on both the maximum cladding temperature and the uncertainties of the design parameters. Therefore, the core thermalhydraulic design method, which eventually determines the cladding temperature, is highly important to assure a safe and reliable operation of the reactor systems

Experience gathered from the transport of a fuel element prototype of the CNA-II (Atucha-II nuclear power plant) type

International Nuclear Information System (INIS)

Pastorini, A.; Belinco, C.G.; El Bis, E.D.; Sacchi, M.A.; Mayans, C.O.; Martin Ghiselli, A.; Marcora, G.R.

1990-01-01

This work describes the needs to materialize the transport of a fuel element prototype of the CNA-II (Atucha-II nuclear power plant) type, under special conditions, from the Fabrication Pilot Plant sited at the Constituyentes Atomic Center and the Ezeiza Atomic Center, for its subsequent analysis at the High Pressure Experimental Loop. The special conditions under which the transport has been made responded to the fact that the prototype presents a fragile adjustment between rods and separators, necessary to be preserved. (Author) [es

Pipework in power plant construction

International Nuclear Information System (INIS)

Schwarzbach, K.

1984-01-01

With the development of conventional power plant construction to large unit sizes and because of the stringent safety requirements in nuclear poer stations, pipework installation has developed into a difficult operation closely inter-related with safety engineering. It is an important factor as far as completion dates and costs are concerned during the timely implementation of a subsequent construction phase which is characterized by high capital intensiveness. In order to keep both under control, prior planning and execution supported by electronic data processing are essential. (orig.) [de

DOE's annealing prototype demonstration projects

International Nuclear Information System (INIS)

Warren, J.; Nakos, J.; Rochau, G.

1997-01-01

One of the challenges U.S. utilities face in addressing technical issues associated with the aging of nuclear power plants is the long-term effect of plant operation on reactor pressure vessels (RPVs). As a nuclear plant operates, its RPV is exposed to neutrons. For certain plants, this neutron exposure can cause embrittlement of some of the RPV welds which can shorten the useful life of the RPV. This RPV embrittlement issue has the potential to affect the continued operation of a number of operating U.S. pressurized water reactor (PWR) plants. However, RPV material properties affected by long-term irradiation are recoverable through a thermal annealing treatment of the RPV. Although a dozen Russian-designed RPVs and several U.S. military vessels have been successfully annealed, U.S. utilities have stated that a successful annealing demonstration of a U.S. RPV is a prerequisite for annealing a licensed U.S. nuclear power plant. In May 1995, the Department of Energy's Sandia National Laboratories awarded two cost-shared contracts to evaluate the feasibility of annealing U.S. licensed plants by conducting an anneal of an installed RPV using two different heating technologies. The contracts were awarded to the American Society of Mechanical Engineers (ASME) Center for Research and Technology Development (CRTD) and MPR Associates (MPR). The ASME team completed its annealing prototype demonstration in July 1996, using an indirect gas furnace at the uncompleted Public Service of Indiana's Marble Hill nuclear power plant. The MPR team's annealing prototype demonstration was scheduled to be completed in early 1997, using a direct heat electrical furnace at the uncompleted Consumers Power Company's nuclear power plant at Midland, Michigan. This paper describes the Department's annealing prototype demonstration goals and objectives; the tasks, deliverables, and results to date for each annealing prototype demonstration; and the remaining annealing technology challenges

Engineering development in nuclear power plant construction

International Nuclear Information System (INIS)

Guenther, P.

1979-01-01

Proceeding from the up-to-now experience in the erection of nuclear power stations, especially of the first and second unit of the Greifswald nuclear power plant, the following essential aspects of the development of constructional engineering are discussed: (1) constructional features and criteria, (2) organizational management, (3) current status and problems in prelimary operations, and (4) possibilities of further expenditure reductions in constructing nuclear power stations

Computer aided construction engineering system for nuclear power plants

International Nuclear Information System (INIS)

Yoshinaga, Toshiaki; Nakajima, Akira; Miyahara, Ryohei; Miura, Jun

1990-01-01

The construction CAE system for nuclear power plants is the tool for the construction work simulator (procedure, processes and management simulation) connected to 3D-CAD (three-dimensional plant layout planning CAD). The data used for construction work simulation are registered in the data base as the installation smallest unit data from the 3D-CAD. This construction work simulator comprises the automatic installation procedure decision system, with which a construction planner decides installation procedure by using a high performance graphic work station, and based on a 3D-CAD model, utilizing empirical procedure logic, the dialogue system for making the installation procedure more optimal by utilizing effectively the graphic function, the evaluation system for synthetically evaluating workability, personnel plan and so on by adding the simulation of human behavior based on these procedures, the schedule system which carries out work process simulation based on the above, the data base system for letting to do these plans effectively and the project management system. By means of these, the plant construction of high quality is expected. (K.I.)

High temperature alloys for the primary circuit of a prototype nuclear process heat plant

International Nuclear Information System (INIS)

Ennis, P.J.; Schuster, H.

1979-01-01

As part of a comprehensive materials test programme for the High Temperature Reactor Project 'Prototype Plant for Nuclear Process Heat' (PNP), high temperature alloys are being investigated for primary circuit components operating at temperatures above 750 0 C. On the basis of important material parameters, in particular corrosion behaviour and mechanical properties in primary coolant helium, the potential of candidate alloys is discussed. By comparing specific PNP materials data with the requirements of PNP and those of conventional plant, the implications for the materials programme and component design are given. (orig.)

The manual of a computer software 'FBR Plant Planning Design Prototype System'

International Nuclear Information System (INIS)

2003-10-01

This is a manual of a computer software 'FBR Plant Planning Design Prototype System', which enables users to conduct case studies of deviated FBR design concepts based on 'MONJU'. The calculations simply proceed as the user clicks displayed buttons, therefore step-by-step explanation is supposed not be necessary. The following pages introduce only particular features of this software, i.e, each interactive screens, functions of buttons and consequences after clicks, and the quitting procedure. (author)

Engineering and training simulators: A combined approach for nuclear plant construction projects

International Nuclear Information System (INIS)

Harnois, Olivier; Gain, Pascal; Bartak, Jan; Gathmann, Ralf

2007-01-01

Full text: Simulation technologies have always been widely used on nuclear applications, but with a clear division between engineering application, using highly validated code run in batch mode, and training purpose where real time computation is a mandatory requirement. Thanks to the flexibility of modern simulation technology and the increased performance of computers, it becomes now possible to develop Nuclear Power plant simulators that can be used both for engineering and training purposes. In the last years, the revival of nuclear industry raised a number of new construction or plant finishing projects in which the application of this combined approach would result in decisive improvement on plant construction lead times, better project control and cost optimizations. The simulator development is to be executed in a step-wise approach, scheduled in parallel with the plant design and construction phases. During a first step, the simulator will model the plant nuclear island systems plus the corresponding instrumentation and control, specific malfunctions and local commands. It can then be used for engineering activities defining and validating the plant operating strategies in case of incidents or accidents. The Simulator executive Station and Operator Station will be in prototype version with an interface imagery enabling monitoring and control of the simulator. Availability of such simulation platform leads to a significant increase in efficiency of the engineering works, the possibility to validate basic design hypotheses and detect defects and conflicts early. The second phase will consist in the fully detailed simulation of Main Control Room plant supervision and control MMI, taking into account I and C control loops detailed design improvement, while having sufficient fidelity in order to be suitable for the future operator training. Its use will enable the engineering units not only to specify and validate normal, incident and accident detailed plant

Construction of overseas nuclear power plants for first time by Japanese industry

International Nuclear Information System (INIS)

Maruyama, Tohru; Naruse, Yoshihiro; Yabuta, Hitoshi

2010-01-01

In response to the worldwide demand for stable energy supplies and the reduction of greenhouse gas emissions, nuclear power plant construction projects have been expanding on a global scale. Even in the United States, where no nuclear power plants have been constructed over the past 30 years, there are plans for the construction of more than 30 plants. Toshiba has been awarded a contract for a nuclear power plant construction project in the U.S., the first case of overseas nuclear power plant construction by Japanese industry. Toshiba America Nuclear Energy Corporation (TANE), the first U.S. subsidiary in our nuclear business, located in Charlotte, North Carolina, is engaged in this globally prominent project, applying various technologies and know-how that we have cultivated over many years of experience in developing and constructing nuclear power plants in Japan and adapting them to U.S. business practices, laws, and regulations. (author)

Experimental Facilities and Plan for a Prototype SFR

International Nuclear Information System (INIS)

Chang, Jinwook

2013-01-01

Contents of the presentation: 1. STELLA; 2. Under Sodium Viewing; 3. Sodium-CO 2 Interaction Test; Overview of the Sodium Integral Effect Test Loop for Safety Simulation and Assessment (STELLA) Program, the scope of the experiment and the overall characteristics of STELLA-1: Phase 1: STELLA-1, Individual component test; • Performance evaluation of key sodium components; • Heat exchanger design codes V&V. Phase 2: STELLA-2, Integral effect test; • Verification of dynamic plant response after reactor shutdown; • Construction of test DB to support specific design approval for the prototype SFR

New developments in nuclear power plant construction

International Nuclear Information System (INIS)

Bivens, A.C.

1983-01-01

Specific examples of construction activities are presented which demonstrate that excellent results have been achieved in the areas of cost, schedule and quality. Examples of innovation and development are given that would be particularly applicable to future work either for new plants or for plants not yet completed. (author)

RK-TBA prototype RF source

International Nuclear Information System (INIS)

Houck, T.; Anderson, D.; Giordano, G.

1996-01-01

A prototype rf power source based on the Relativistic Klystron Two-Beam Accelerator (RK-TBA) concept is being constructed at the Lawrence Berkeley National Laboratory to study physics, engineering, and costing issues. The prototype is described and compared to a full scale design appropriate for driving the Next Linear Collider (NLC). Specific details of the induction core tests and pulsed power system are presented. The 1-MeV, 1.2-kA induction gun currently under construction is also described in detail

Construction techniques and management methods for BWR plants

International Nuclear Information System (INIS)

Shimizu, Yohji; Tateishi, Mizuo; Hayashi, Yoshishige

1989-01-01

Toshiba is constantly striving for safer and more efficient plant construction to realize high-quality BWR plants within a short construction period. To achieve these aims, Toshiba has developed and improved a large number of construction techniques and construction management methods. In the area of installation, various techniques have been applied such as the modularization of piping and equipment, shop installation of reactor internals, etc. Further, installation management has been upgraded by the use of pre-installation review programs, the development of installation control systems, etc. For commissioning, improvements in commissioning management have been achieved through the use of computer systems, and testing methods have also been upgraded by the development of computer systems for the recording and analysis of test data and the automatic adjustment of controllers in the main control system of the BWR. This paper outlines these construction techniques and management methods. (author)

Obtention process of phosphorus 32 starting from commercial sulfur and design and construction of the radiochemical separation prototype

International Nuclear Information System (INIS)

Duarte A, C.; Alanis M, J.; Gutierrez R, C.

2002-01-01

In this work an obtention process of phosphorus 32 ( 32 P) in orthophosphoric acid form (H 3 32 PO 4 ) is described starting from commercial sulfur. Also the design and construction of the experimental prototype used in the radiochemical separation and their results in three tests carried out is reported. (Author)

The remaining risk to be accepted with test facilities and prototype plants, and the relevant legal provisions of nuclear law

International Nuclear Information System (INIS)

Mayinger, T.

1995-01-01

The first chapter explains the provisions laid down in nuclear law to assure that precaution is taken to prevent damage resulting from the operation of nuclear power reactors, in order to set a line for comparison with the relevant legal provisions relating to test facilities and prototype plants. The comparative analysis shows that the means and methods of precaution are defined to comprise three approaches, namely measures taken to avert danger, measures taken to prevent danger, and measures for (remaining) risk minimization. All three approaches are intended to prevent occurrence of specifically nuclear events. The second chapter characterizes power reactors, prototype plant and test facilities and develops criteria for distinction. The third chapter establishes the systematics for comparison, showing whether and how the mandatory precaution to prevent damage defined for power reactors, prototype plant, and test facilities can be distinguished from each other, the results being represented in a systematic survey of licensing requirements as laid down in section 7, sub-section 2 ATG (Atomic Energy Act). (orig./HP) [de

Nuclear plant construction and investment risk

International Nuclear Information System (INIS)

Studness, C.M.

1984-01-01

Escalated cost estimations, delays and cancellations in nuclear construction have caused a preoccupation with the risks of nuclear power plant construction that dominates utility stock investment, overshadowing increased earnings per share and recent growth in production. The issue will be resolved when increased power demand requires new construction, but the effect has so far been to erode the economic advantage of nuclear power and threaten the ability of utilities to get rate increases high enough to cover their costs. Projected delays and cost escalations and their effects must go into an economic appraisal of the investment risks

The Scintillator Tile Hadronic Calorimeter Prototype

International Nuclear Information System (INIS)

Rusinov, V.

2006-01-01

A high granularity scintillator hadronic calorimeter prototype is described. The calorimeter is based on a novel photodetector - Silicon Photo-Multiplier (SiPM). The main parameters of SiPM are discussed as well as readout cell construction and optimization. The experience with a small prototype production and testing is described. A new 8 k channel prototype is being manufactured now

The modularization construction of piping system installation in AP1000 plant

International Nuclear Information System (INIS)

Lu Song; Wang Yuan; Wei Junming

2012-01-01

Modularization construction is the main technique used in AP1000 plants, the piping Modularization installation will impact directly to the module construction as the important part of the Modularization construction. After the piping system has took the modularization design in AP1000 plants, some installation works of piping system has moved from the site to fabrication shop. With improving the construction quality and minimizing the time frame of project, the critical paths can be optimized. This paper has analyzed the risk and challenge that met during the modularization construction period of piping systems though introducing the characteristic of modularization construction for AP1000 piping systems, and get construction experiences from the First AP1000 plants in the world, then it will be the firmly basics for the wide application of modularization construction in the future. (authors)

Signalling network construction for modelling plant defence response.

Directory of Open Access Journals (Sweden)

Dragana Miljkovic

Full Text Available Plant defence signalling response against various pathogens, including viruses, is a complex phenomenon. In resistant interaction a plant cell perceives the pathogen signal, transduces it within the cell and performs a reprogramming of the cell metabolism leading to the pathogen replication arrest. This work focuses on signalling pathways crucial for the plant defence response, i.e., the salicylic acid, jasmonic acid and ethylene signal transduction pathways, in the Arabidopsis thaliana model plant. The initial signalling network topology was constructed manually by defining the representation formalism, encoding the information from public databases and literature, and composing a pathway diagram. The manually constructed network structure consists of 175 components and 387 reactions. In order to complement the network topology with possibly missing relations, a new approach to automated information extraction from biological literature was developed. This approach, named Bio3graph, allows for automated extraction of biological relations from the literature, resulting in a set of (component1, reaction, component2 triplets and composing a graph structure which can be visualised, compared to the manually constructed topology and examined by the experts. Using a plant defence response vocabulary of components and reaction types, Bio3graph was applied to a set of 9,586 relevant full text articles, resulting in 137 newly detected reactions between the components. Finally, the manually constructed topology and the new reactions were merged to form a network structure consisting of 175 components and 524 reactions. The resulting pathway diagram of plant defence signalling represents a valuable source for further computational modelling and interpretation of omics data. The developed Bio3graph approach, implemented as an executable language processing and graph visualisation workflow, is publically available at http://ropot.ijs.si/bio3graph/and can be

Construction of prototype of on-line analyzer detection system for coal on belt conveyor using neutron activation technique

International Nuclear Information System (INIS)

Rony Djokorayono; Agus Cahyono; MP Indarzah; SG Usep; Sukandar

2015-01-01

The use of on-line neutron activation technique for coal analysis is proposed as an alternative method for analysis based on sampling technique. Compared to this conventional technique, the on-line neutron activation technique has much shorter time of analysis and more accurate results. The construction of detection system prototype for the on-line analyzer is described in this paper. This on-line analyzer consists of detection system, data acquisition system, and computer console. This detection system comprises several modules, i.e. NaI(Tl) scintillation detector completed with a photomultiplier tube (PMT), pre-amplifier, single channel analyzer (SCA), and analog signal transmitter and pulse counter processor. The construction processes of these four modules include the development of configuration block, lay out, and selection of electronic components. The modules have been integrated and tested. This detection system was tested using radioactive element Zn-65 having energy of 1115.5 keV and activity of 1 μCi. The test results show that the prototype of the on-line analyzer detection system has functioned as expected. (author)

Geodesy problems in nuclear power plant construction

International Nuclear Information System (INIS)

Eory, K.

1981-01-01

The special geodetic problems encountered during the construction of the Paks nuclear power plants are treated. The main building with its hermetically connected components including the reactor, the steam generators, the circulation pumps etc. impose special requirements on the control net of datum points. The geodesy tasks solved during the construction of the main building are presented in details. (R.P.)

Current problems associated with nuclear plant construction contracts

International Nuclear Information System (INIS)

Albano, Raffaele.

1977-01-01

The expansion of nuclear electricity generating programmes has brought to the fore the problems associated with construction of this type of power plant. The paper analyses the contracts for such construction and describes the most common, the turnkey contract. The present tendency is to limit the scope of turnkey contracts to the nuclear system or simply to the reactor and this is especially common in advanced nuclear countries such as the US, Canada, Japan, UK and France, and this is also the case in Italy where the question of contracting nuclear plants is debated. In Germany the power utilities hold a large number of shares in the manufacturing industry and the turnkey contract is therefore more economically attractive. A detailed description of the contracting procedure is provided, including the suppliers' and purchasers' responsibilities, plant commissioning tests and handing over of the plant to the operator. (NEA) [fr

Application of RFID to High-Reliability Nuclear Power Plant Construction

International Nuclear Information System (INIS)

Kenji Akagi; Masayuki Ishiwata; Kenji Araki; Jun-ichi Kawahata

2006-01-01

In nuclear power plant construction, countless variety of parts, products, and jigs more than one million are treated under construction. Furthermore, strict traceability to the history of material, manufacturing, and installation is required for all products from the start to finish of the construction, which enforce much workforce and many costs at every project. In an addition, the operational efficiency improvement is absolutely essential for the effective construction to reduce the initial investment for construction. As one solution, RFID (Radio Frequent Identification) application technology, one of the fundamental technologies to realize a ubiquitous society, currently expands its functionality and general versatility at an accelerating pace in mass-production industry. Hitachi believes RFID technology can be useful of one of the key solutions for the issues in non-mass production industry as well. Under this situation, Hitachi initiated the development of next generation plant concept (ubiquitous plant construction technology) which utilizes information and RFID technologies. In this paper, our application plans of RFID technology to nuclear power is described. (authors)

Application of RFID to High-Reliability Nuclear Power Plant Construction

Energy Technology Data Exchange (ETDEWEB)

Akagi, Kenji; Ishiwata, Masayuki; Araki, Kenji; Kawahata, Jun-ichi [Hitachi, Ltd. (Japan)

2006-07-01

In nuclear power plant construction, countless variety of parts, products, and jigs more than one million are treated under construction. Furthermore, strict traceability to the history of material, manufacturing, and installation is required for all products from the start to finish of the construction, which enforce much workforce and many costs at every project. In an addition, the operational efficiency improvement is absolutely essential for the effective construction to reduce the initial investment for construction. As one solution, RFID (Radio Frequent Identification) application technology, one of the fundamental technologies to realize a ubiquitous society, currently expands its functionality and general versatility at an accelerating pace in mass-production industry. Hitachi believes RFID technology can be useful of one of the key solutions for the issues in non-mass production industry as well. Under this situation, Hitachi initiated the development of next generation plant concept (ubiquitous plant construction technology) which utilizes information and RFID technologies. In this paper, our application plans of RFID technology to nuclear power is described. (authors)

Design of micro-reactors and solar photocatalytic prototypes

International Nuclear Information System (INIS)

Flores E, R.M.; Hernandez H, M.; Perusquia del Cueto, M.R.; Bonifacio M, J.; Jimenez B, J.; Ortiz O, H.B.; Castaneda J, G.; Lugo H, M.

2007-01-01

In the ININ is carried out research in heterogeneous photocatalysis using artificial light for to degrade organic compounds. In this context, it is sought to use the solar radiation as energy source to knock down costs. Of equal form it requires to link the basic and applied research. For it, a methodology that allows to design and to build micro-reactors and plants pilot has been developed, like previous step, to request external supports and to a future commercialization. The beginning of these works gave place to the partial construction of a prototype of photocatalytic reactor of the cylinder-parabolic composed type (CPC)

Construction status report: nuclear power plants, data for decisions. Status report

International Nuclear Information System (INIS)

1976-01-01

The document is the 28th edition summarizing the results of a management information system established by the Executive Director for Operations on the construction/fuel load activities of nuclear power plants. The report uses data collected from applicants sponsoring these projects, Office of Inspection and Enforcement, and the Office of Standards Development; and analyzed by the Office of Management Information and Program Control in the implementation of Management Information Systems. The status of 87 plants authorized to engage in construction in Region I through V is summarized in this document. This total includes (4) plants with construction exemptions, and (14) plants with an LWA

Analysis of power ramp rate and minimum power controllability of the MMS model for a plant dynamics analysis of a Prototype SFR

International Nuclear Information System (INIS)

Kim, Eui Kwang; Kim, Dehee; Joo, Hyungkook; Lee, Taeho

2014-01-01

A full plant dynamic model was developed for a prototype SFR using the Modular Modeling System (MMS). It includes the modeling of various subsystems such as the neutronics, primary and intermediate sodium systems of the NSSS, steam and water systems of the BOP, BOP controls, and the supervisory plant controls. The NSSS model is subdivided into component models, such as a Core, IHXs, Pumps, SGs, and the rest of the NSSS loop model. The BOP model is subdivided into a steam subsystem, feedwater subsystem, and preheater subsystem. Plant transient tests were performed to study the operational considerations. It includes varying the power ramp rate and studying the controllability at minimum power. Plant transient tests were performed to study operational considerations by using the MMS model for a prototype SFR. It includes varying the power ramp rate, studying the controllability at the minimum power set point. At a power ramp rate of higher than 2%, the steam temperature has a large deviation from the target. As the power set point decreases, the PHTS hot leg temperature and steam temperature tend to have higher deviations. After further refinement of the MMS model, it can be useful for developing the plant operation logics of the prototype SFR

Proposal for the construction of the staged Scyllac prototype

International Nuclear Information System (INIS)

Nunnally, W.C.; McDonald, T.E.

1975-07-01

After the completion of the present feedback experiment on Scyllac, the machine will be reconfigured into a toroidal staged theta pinch. A 0.9-m prototype of the Staged Scyllac experiment is proposed which will be used to test the components required for the implosion-heating and staging circuits in a system environment. In addition, various systems of the Staged Scyllac, such as the trigger system and the gap-monitoring system, can be developed on the prototype before installation on the full experiment. (auth)

Luminosity Measurement at ATLAS Development, Construction and Test of Scintillating Fibre Prototype Detectors

CERN Document Server

Ask, S; Braem, André; Cheiklali, C; Efthymiopoulos, I; Fournier, D; de La Taille, C; Di Girolamo, B; Grafström, P; Joram, C; Haguenauer, Maurice; Hedberg, V; Lavigne, B; Maio, A; Mapelli, A; Mjörnmark, U; Puzo, P; Rijssenbeek, M; Santos, J; Saraiva, J G; Stenzel, H; Thioye, M; Valladolid, E; Vorobel, V

2006-01-01

We are reporting about a scintillating fibre tracking detector which is proposed for the precise determination of the absolute luminosity of the CERN LHC at interaction point 1 where the ATLAS experiment is located. The detector needs to track protons elastically scattered under $\\mu$rad angles in direct vicinity to the LHC beam. It is based on square shaped scintillating plastic fibres read out by multi-anode photomultiplier tubes and is housed in Roman Pots. We describe the design and construction of prototype detectors and the results of a beam test experiment at DESY. The excellent detector performance established in this test validates the detector design and supports the feasibility of the proposed challenging method of luminosity measurement.

Improvement of QA/QC activities in the construction of nuclear power plant

International Nuclear Information System (INIS)

Jinji Tomita; Shigetaka Tomaru

1987-01-01

Construction of commercial nuclear power plants in Japan started at around 1965. In this presentation are described quality assurance (QA) activities of a plant supplier who is a manufacturer of the key components as well. The QA activities until now are divided into several periods of the construction history in Japan. First term is 1960's when the QA activities are featured as the study and implementation through the construction of imported plants. Since then technologies and procedures of our own have been established and improved for the construction of high reliability plants. Our present QA activities are based on the active reflection of those lessons learned of past experiences. (author)

Nuclear power plants. Construction status report, data as of September 30, 1977

International Nuclear Information System (INIS)

1977-10-01

The report provides information for monitoring the progress of construction of nuclear power plants. It provides data for synchronizing the licensing process with predicted fuel loading dates, as well as providing a central federal government report for commercial reactor construction. It utilizes data collected from the utilities sponsoring these projects and the Office of Inspection and Enforcement, NRC, and analyzed by the Office of Management Information and Program Control in the implementation of Management Information Systems. T he status of 93 plants authorized to engage in construction activities is summarized. This total includes (4) plants with construction exemptions, and (11) plants with Limited Work Authorization Permits

Design and construction of a large aperture, quadrupole electromagnet prototype for ILSE

International Nuclear Information System (INIS)

Stuart, M.; Faltens, A.; Fawley, W.M.; Peters, C.; Vella, M.C.

1995-04-01

We are currently constructing a prototype quadrupole electromagnet for the proposed Induction Linac Systems Experiment (ILSE) at LBL. ILSE will address many physi and engineering issues relevant to the design of a heavy-ion fusion driver accelerator. The pulsed electromagnet has two layers of current windings and will produce a field gradient exceeding 25 T/m at a repetition rate of 1 Hz steady-state. In this paper, we discuss how the interaction of various concerns such as maximum dynamic aperture, short lattice period, field quality, iron yoke weight, heat transfer, and voltage standoff have led to our particular design choices. We also present 2- and 3-D numerical calculations concerning field topography and the results of transport simulations of space-charge dominated ion beams with ILSE parameters

Construction and commissioning experience of evolutionary water cooled nuclear power plants

International Nuclear Information System (INIS)

2004-04-01

Electricity market liberalization is an established fact in several countries and there is a trend to adopt it in other countries. The essential aim of market liberalization is to improve the overall economic efficiency. In order that nuclear power remains a viable option for electricity generation, its costs should be competitive with alternative sources while, at the same time, it should have a safe and reliable operation record. The capital cost of nuclear power plants (NPPs) generally accounts for 43-70% of the total nuclear electricity generation costs, compared to 26-48% for coal plants and 13-32% for gas plants. Most of these expenditures are incurred during the construction phase of a NPP. The achievement of shorter construction periods using improved technology and construction methods has a significant benefit on the costs incurred prior to any production of electricity. This document is intended to make the recent worldwide experience on construction and commissioning of evolutionary water cooled NPPs available to Member States and especially to those with nuclear power plants under construction/planning, and to those seriously considering nuclear power projects in the future. The final aim is to assist utilities and other organizations in Member States to improve the construction of nuclear power plants and achieve shortened schedules and reduced costs without compromising quality and safety. This document aims to provide an overview of the most advanced technologies, methods and processes used in construction and commissioning of recent nuclear projects. To better achieve this objective the presentation is selectively focused more on the new developments rather than providing a full review of all issues related to construction and commissioning. The experience described in this TECDOC applies to managers, engineers, supervisors, technicians and workers in various organizations dealing with the site construction and commissioning of nuclear power plants

Design and construction of a prototype vaporization calorimeter for the assay of radioisotopic samples

International Nuclear Information System (INIS)

Tormey, T.V.

1979-10-01

A prototype vaporization calorimeter has been designed and constructed for use in the assay of low power output radioisotopic samples. The prototype calorimeter design was based on that of a previous experimental instrument used by H.P. Stephens, to establish the feasibility of the vaporization calorimetry technique for this type of power measurement. The calorimeter is composed of a mechanical calorimeter assembly together with a data acquisition and control system. Detailed drawings of the calorimeter assembly are included and additional drawings are referenced. The data acquisition system is based on an HP 9825A programmable calculator. A description of the hardware is provided together with a listing of all system software programs. The operating procedure is outlined, including initial setup and operation of all related equipment. Preliminary system performance was evaluated by making a series of four measurements on two nominal 1.5W samples and on a nominal 0.75W sample. Data for these measurements indicate that the absolute accuracy (one standard deviation) is approx. = 0.0035W in this power range, resulting in an estimated relative one standard deviation accuracy of 0.24% at 1.5W and 0.48% at 0.75W

Construction costs, payback times, and the leaf economics of carnivorous plants.

Science.gov (United States)

Karagatzides, Jim D; Ellison, Aaron M

2009-09-01

Understanding how different plant species and functional types "invest" carbon and nutrients is a major goal of plant ecologists. Two measures of such investments are "construction costs" (carbon needed to produce each gram of tissue) and associated "payback times" for photosynthesis to recover construction costs. These measurements integrate among traits used to assess leaf-trait scaling relationships. Carnivorous plants are model systems for examining mechanisms of leaf-trait coordination, but no studies have measured simultaneously construction costs of carnivorous traps and their photosynthetic rates to determine payback times of traps. We measured mass-based construction costs (CC(mass)) and photosynthesis (A(mass)) for traps, leaves, roots, and rhizomes of 15 carnivorous plant species grown under greenhouse conditions. There were highly significant differences among species in CC(mass) for each structure. Mean CC(mass) of carnivorous traps (1.14 ± 0.24 g glucose/g dry mass) was significantly lower than CC(mass) of leaves of 267 noncarnivorous plant species (1.47 ± 0.17), but all carnivorous plants examined had very low A(mass) and thus, long payback times (495-1551 h). Our results provide the first clear estimates of the marginal benefits of botanical carnivory and place carnivorous plants at the "slow and tough" end of the universal spectrum of leaf traits.

Quality assurance in the construction of nuclear power plants

International Nuclear Information System (INIS)

Bernsen, S.A.

1975-01-01

A general survey of quality-assurance (QA) practices as they relate to the construction phase of nuclear power plants is presented. The article briefly outlines the evolution of construction QA requirements, describes construction practices and organizational relations that help identify the unique construction-phase features that affect QA practices, identifies some of the principal requirements and programmatic problems involving construction, and discusses potential trends and suggested guidelines for the implementation of particular practices. (U.S.)

Rationalizing of construction engineering of nuclear power plants with pressurized water reactors

International Nuclear Information System (INIS)

Schmidt, S.

1977-01-01

Construction of large power plants requires further reduction of construction efforts and the construction period. A new constructional and technological solution has been developed with the steel-cell composite structure applied in the Greifswald nuclear power plant 'Bruno Leuschner' for the first time. Principles of design, fabrication, transport, and mounting are described. The benefits of the method are indicated. (author)

Learning through delivery, Westinghouse AP1000 plant construction

International Nuclear Information System (INIS)

Gorgemans, J.; Hinman, R.D.; Steuck, C.M.; Greco, P.L.

2014-01-01

The AP1000 plant, which is a 1100 MWe class pressurized water reactor with passive safety features, is designed around a conventional 2 loop, 2 steam generator primary system configuration with 2 hot legs, 4 reactor coolant pumps directly mounted in the steam generator lower head and 4 cold legs. A particular feature of AP1000 is its modular construction to minimize the time and cost of construction. Modular construction allows activities to be run in parallel, it allows more activities to be performed in a controlled factory instead of in the field, and it provides a better level of quality. The AP1000 plant design includes 106 structural modules and 52 mechanical modules. Structural modules include all penetrations for piping, cable trays, HVAC duct runs, and all reinforcement for pipe, equipment hangers, and supports. Structural modules are shipped in sub-modules to support transportation by rail or truck or barge. Mechanical modules contain equipment such as pumps, tanks, heat exchangers, air-handling units, and filters along with interconnecting pipes, valves, instruments, wiring and support services. Modular construction requires strong coordination between engineering, supply chain and construction. A total of 8 AP1000 units are currently under construction in China and in the United States. The lessons learned and best practices of each new AP1000 construction are systematically incorporated into the standard design. (A.C.)

Prototype 350 MHz niobium spoke-loaded cavities

International Nuclear Information System (INIS)

Delayen, J. R.; Kedzie, M.; Mammosser, J.; Piller, C.; Shepard, K. W.

1999-01-01

This paper reports the development of 350 MHz superconducting cavities of a spoke-loaded geometry, intended for the velocity range 0.2 < v/c < 0.6. Two prototype single-cell cavities have been designed, one optimized for velocity v/c = 0.4, and the other for v/c = 0.29. Construction of the prototype niobium cavities is nearly complete. Details of the design and construction are discussed, along with the results of cold tests

Prototype 350 MHz niobium spoke-loaded cavities.

Energy Technology Data Exchange (ETDEWEB)

Delayen, J. R.; Kedzie, M.; Mammosser, J.; Piller, C.; Shepard, K. W.

1999-05-10

This paper reports the development of 350 MHz superconducting cavities of a spoke-loaded geometry, intended for the velocity range 0.2 < v/c < 0.6. Two prototype single-cell cavities have been designed, one optimized for velocity v/c = 0.4, and the other for v/c = 0.29. Construction of the prototype niobium cavities is nearly complete. Details of the design and construction are discussed, along with the results of cold tests.

Application of linear scheduling method (LSM) for nuclear power plant (NPP) construction

International Nuclear Information System (INIS)

Kim, Woojoong; Ryu, Dongsoo; Jung, Youngsoo

2014-01-01

Highlights: • Mixed use of linear scheduling method with traditional CPM is suggested for NPP. • A methodology for selecting promising areas for LSM application is proposed. • A case-study is conducted to validate the proposed LSM selection methodology. • A case-study of reducing NPP construction duration by using LSM is introduced. - Abstract: According to a forecast, global energy demand is expected to increase by 56% from 2010 to 2040 (EIA, 2013). The nuclear power plant construction market is also growing with sharper competition. In nuclear power plant construction, scheduling is one of the most important functions due to its large size and complexity. Therefore, it is crucial to incorporate the ‘distinct characteristics of construction commodities and the complex characteristics of scheduling techniques’ (Jung and Woo, 2004) when selecting appropriate schedule control methods for nuclear power plant construction. However, among various types of construction scheduling techniques, the traditional critical path method (CPM) has been used most frequently in real-world practice. In this context, the purpose of this paper is to examine the viability and effectiveness of linear scheduling method (LSM) applications for specific areas in nuclear power plant construction. In order to identify the criteria for selecting scheduling techniques, the characteristics of CPM and LSM were compared and analyzed first through a literature review. Distinct characteristics of nuclear power plant construction were then explored by using a case project in order to develop a methodology to select effective areas of LSM application to nuclear power plant construction. Finally, promising areas for actual LSM application are suggested based on the proposed evaluation criteria and the case project. Findings and practical implications are discussed for further implementation

Application of linear scheduling method (LSM) for nuclear power plant (NPP) construction

Energy Technology Data Exchange (ETDEWEB)

Kim, Woojoong, E-mail: minidung@nate.com [Central Research Institute, Korea Hydro and Nuclear Power Co., Ltd, Daejeon 305-343 (Korea, Republic of); Ryu, Dongsoo, E-mail: energyboy@khnp.co.kr [Central Research Institute, Korea Hydro and Nuclear Power Co., Ltd, Daejeon 305-343 (Korea, Republic of); Jung, Youngsoo, E-mail: yjung97@mju.ac.kr [College of Architecture, Myongji University, Yongin 449-728 (Korea, Republic of)

2014-04-01

Highlights: • Mixed use of linear scheduling method with traditional CPM is suggested for NPP. • A methodology for selecting promising areas for LSM application is proposed. • A case-study is conducted to validate the proposed LSM selection methodology. • A case-study of reducing NPP construction duration by using LSM is introduced. - Abstract: According to a forecast, global energy demand is expected to increase by 56% from 2010 to 2040 (EIA, 2013). The nuclear power plant construction market is also growing with sharper competition. In nuclear power plant construction, scheduling is one of the most important functions due to its large size and complexity. Therefore, it is crucial to incorporate the ‘distinct characteristics of construction commodities and the complex characteristics of scheduling techniques’ (Jung and Woo, 2004) when selecting appropriate schedule control methods for nuclear power plant construction. However, among various types of construction scheduling techniques, the traditional critical path method (CPM) has been used most frequently in real-world practice. In this context, the purpose of this paper is to examine the viability and effectiveness of linear scheduling method (LSM) applications for specific areas in nuclear power plant construction. In order to identify the criteria for selecting scheduling techniques, the characteristics of CPM and LSM were compared and analyzed first through a literature review. Distinct characteristics of nuclear power plant construction were then explored by using a case project in order to develop a methodology to select effective areas of LSM application to nuclear power plant construction. Finally, promising areas for actual LSM application are suggested based on the proposed evaluation criteria and the case project. Findings and practical implications are discussed for further implementation.

Radioactive air emissions notice of construction and application for approval to construct the Hanford Waste Vitrification Plant

International Nuclear Information System (INIS)

1992-10-01

The Hanford Site is owned by the US Government and operated by the US Department of Energy, Richland Field Office. The Hanford Site manages and produces dangerous waste and mixed waste. (containing both radioactive and dangerous components). The US Department of Energy, Richland Field Office, currently stores mixed waste, resulting from various processing operations, in underground storage tanks. The Hanford Waste Vitrification Plant will be constructed and operated to process the high-activity fraction of mixed waste stored in these underground tanks. The Hanford Waste Vitrification Plant will solidify pretreated tank waste into a glass product that will be packaged for disposal in a national repository. Emissions from the Hanford Waste Vitrification Plant will be regulated by both the federal and state Clean Air Acts. The proposed Hanford Waste Vitrification Plant represents a new source of radioactive air emissions. Construction of the plant will require approval from both federal and state agencies. The Notice of Construction and Application for Approval to Construct the Hanford Waste Vitrification Plant contains information required under Title 40 of the Code of Federal Regulations, Chapter 61; and Chapter 246-247 of the Washington Administrative Code for a proposed new source of radioactive air emissions. The document contents are based on information contained in the Hanford Waste Vitrification Plant Reference Conceptual Design Report, the Hanford Waste Vitrification Plant Preliminary Safety Analysis Report, Revision 0, and subsequent design changes made before August 1, 1992. The contents of this document may be modified to include more specific information generated during subsequent detailed design phases. Modifications will be submitted for regulatory review and approval, as appropriate

The supply chain of civil construction industries for support the nuclear power plant construction in Indonesia

International Nuclear Information System (INIS)

Dharu Dewi; Sriyana; Moch-Djoko Birmano; Sahala Lumbanraja; Nurlaila

2013-01-01

The use of domestic products for electricity infrastructure has been set out in the Ministerial Decree number: 54/M-IND/PER/3/2012, but the infrastructure of nuclear power plants (NPP) construction has not been included. Therefore, the potential of the local industries needs to be mapped it especially supply chain of civil construction industries to estimate the capability of the local component level (DCL) at the nuclear power plant project in Indonesia. NPP is a high-technology so that if NPP will be constructed, it is necessary to involve the national capability as media technology transfer, especially for EPC (Engineering, Procurement and Construction) services. Civil construction (civil part) play role is very large, about 21%. Therefore it is necessary in particular the role of the national civil construction industry to increase the capability of local content. Preparation of Civil construction infrastructure are depend on the supply chain of raw materials. The aim of the research was to map the supply chain of the civil construction industries. Methodology this study is a survey of national industries, literature review, and searching web site. The result study is a map of civil construction industries with raw material supply chain. (author)

Forecasting manpower requirements for nuclear power plant construction

International Nuclear Information System (INIS)

Seltzer, N.; Schriver, W.R.

1978-01-01

This paper presents both the methodology and results of a segment of a comprehensive construction manpower demand forecasting system aimed at forecasting virtually all construction manpower requirements in the United States of America. The part of the system dealing with the demand for construction workers needed to build nuclear powered electricity generating plants is discussed here. The object of the system is to forecast manpower construction needs for each of 29 construction crafts on a monthly basis in each of 10 geographical regions of the United States. The method used is to establish profiles of the types of workers and time phasing required in the past. Profiling was done for different types of plants, different capacity classes, and different geographical locations. An appropriate worker profile matrix cannot simply be multiplied by the capacity of the proposed plant if the number of man-hours required per kilowatt of generating capacity is not constant. The value of this latter variable has changed considerably recently - presumably because of an increased awareness of environmental and safety considerations. Econometric techniques are used to forecast values for man-hours per kilowatt which are then multiplied by projected new capacity to be put in place. The resulting total man-hour requirement is then allocated over time and by craft through use of a worker profile matrix. The summary results indicate that 20 percent increases in man-hours required per kilowatt of capacity can be expected between 1977 and 1981. Total construction labour demand will rise from 65,700 work-years in 1977 to nearly 96,600 work-years in 1981. Forecasts of the actual number of different types of workers to be demanded in each month and in each region are available from the system. (author)

Modularization in construction processes New Nuclear Power Plants

International Nuclear Information System (INIS)

Martinez, I.; Cobos, A.; Herrera Ropero, D.

2012-01-01

The aim of this work is that it has the capacity and expertise to analyze the suitability of modular technology design and construction compared to conventional nuclear plants. It will define the criteria for selecting the areas of modularity and the impact on design and its interfaces with engineering, supply, including logistics and construction.

Construction times and the decommissioning of nuclear power plants

International Nuclear Information System (INIS)

Erramuspe, H.J.

1988-01-01

The construction and the decommissioning periods of nuclear power plants (NPP), are studied, due to their importance in the generation costs. With reference to the construction periods of these plants, a review is made of the situation and technical improvements made in different countries, with the purpose of shortening them. In regard to the decommissioning of NPP, the present and future situations are reviewed in connection with different stages of decommissioning and their related problems, as the residual radioactivity of different components, and the size of the final wastes to be disposed of. The possibilities of plant life extensions are also revised in connection with these problems. Finally, the expected decommissioning costs are analyzed. (Author) [es

Development of a fresh plutonium fuel container for a prototype fast breeder reactor

International Nuclear Information System (INIS)

Ohtake, T.; Takahashi, S.; Mishima, T.; Kurakami, J.; Yamamoto, Y.; Ohuchi, Y.

1989-01-01

Japan gives a good deal of encouragement to development of a fast breeder reactor (which is considered as the most likely candidate for nuclear power generation) to secure long-term energy source. And, following an experimental fast breeder reactor Joyo, a prototype fast breeder reactor Monju is now under vigorous construction. Related to development of the prototype fast breeder reactor, it is necessary and important to develop transport container which is used for transporting fresh fuel assemblies from Plutonium Fuel Production Facility to the Monju power plant. Therefore, the container is now being developed by Power Reactor and Nuclear Fuel Development Corporation (PNC). Currently, shipment and vibration tests, handling performance tests, shielding performance tests and prototype container tests are executed with prototype containers fabricated according to a final design, in order to experimentally confirm soundness of transport container and its contents, and propriety of design technique. This paper describes the summary of general specifications and structures of this container and the summary of preliminary safety analysis of package

Quality control during construction of power plants

International Nuclear Information System (INIS)

Hartstern, R.F.

1982-01-01

This paper traces the background and examines the necessity for a program to control quality during the construction phase of a power plant. It also attempts to point out considerations for making these programs cost effective

A study of public acceptance of construction of atomic power plant

International Nuclear Information System (INIS)

Harada, Kazunori; Matsuhashi, Ryuji; Yoshida, Yoshikuni

2011-01-01

In June 2010, Basic Energy Plan was approved in a Cabinet meeting. It says that Japan aims to construct more than 14 atomic power plants by 2030. Today, there are 12 plans of construction of atomic power plant, but it is hard to say that their plans easily come off. That's because public acceptance of atomic power plant is low in Japan, for example local residents wage opposition campaigns. This study conducts a survey in the form of a questionnaire and analyzes it by Analytical Hierarchical Process (AHP). Analytic Hierarchy Process is a structured technique for dealing with complex decisions. A questionnaire using AHP is very easy to answer and analyze. This survey was conducted in 2 areas. First area is Hohoku-cho, Yamaguchi Pref. that had a plan of construction of atomic power plant and the plan was demolished by opposition campaigns. Second area is Kaminoseki-cho, Yamaguchi Pref. that has a plan of construction of atomic power plant now and the plan is working order. Public acceptance can be calculated from survey data of 2 areas, and it helps to understand why first area disapproved a plan of atomic power plant and second area approves it. We consider a model to analyze public acceptance. (author)

Study on nuclear power plant project construction and management mode in China

International Nuclear Information System (INIS)

Wang Kai; Chen Lian

2009-01-01

Project management mode plays a key role in project construction, especially in nuclear power field. From the aspects of right, responsibility and benefit, this paper discussed the differences among the common used project management modes. Also the main kinds of the construction management modes used in China's nuclear power plants were summarized. At last, considering the experience of Ningde nuclear power plant, this paper put forward several perspectives about the selection of project management mode in nuclear power plant construction. (authors)

Incineration plant for low active waste at Inshass, LAWI

International Nuclear Information System (INIS)

Krug, W.; Thoene, L.; Schmitz, H.J.; Abdelrazek, I.D.

1993-10-01

The LAWI (Low Active Waste Incinerator) prototype incinerating plant was devised and constructed according to the principle of the Juelich thermoprocess and installed at the Egyptian research centre Inshass. In parallel, AEA Cairo devised and constructed their own operations building for this plant with all the features, infrastructural installations and rooms required for operating the plant and handling and treating low-level radioactive wastes. The dimensions of this incinerator were selected so as to be sufficient for the disposal of solid, weakly radioactive combustible wastes from the Inshass Research Centre and the environment (e.g. Cairo hospitals). (orig./DG) [de

Application of ABWR construction database to nuclear power plant project

International Nuclear Information System (INIS)

Takashima, Atsushi; Katsube, Yasuhiko

1999-01-01

Tokyo Electric Power Company (TEPCO) completed the construction of Kashiwazaki-Kariwa Nuclear Power Station Unit No. 6 and No. 7 (K-6/7) as the first advanced boiling water reactors (ABWR) in the world successfully. K-6 and K-7 started their commercial operations in November, 1996 and in July, 1997 respectively. We consider ABWR as a standard BWR in the world as well as in Japan because ABWR is highly reputed. However, because the interval of our nuclear power plant construction is going to be longer, our engineering level on plant construction will be declining. Hence it is necessary for us to maintain our engineering level. In addition to this circumstance, we are planning to wide application of separated purchase orders for further cost reduction. Also there is an expectation for our contribution to ABWR plant constructions overseas. As facing these circumstances, we have developed a construction database based on our experience for ABWR construction. As the first step of developing the database for these use, we analyzed our own activities in the previous ABWR construction. Through this analysis, we could define activity units of which the project consists. As the second step, we clarified the data which are treated in each activity unit and the interface among them. By taking these steps, we could develop our database efficiently. (author)

Rock cavity construction of a nuclear power plant: a case study

International Nuclear Information System (INIS)

Loken, P.C.; Bakke, J.; Gloersen, I.

1979-01-01

The major findings of a comprehensive study of the major aspects of rock cavity construction of a large nuclear power plant are: (1) current technology is adequate for the realization of such construction; (2) a method for estimating the probability of rock fallout and gross cavity instability is presently not available; (3) certain design modifications and amplifications must be made to prevent dependent failures; (4) no significant reduction in the immediate radiological effects of Class 9 accidents will result unless special design measures are made for this purpose; (5) the vulnerability of the plant to certain external effects is significantly reduced; (6) the total time for the realization of such construction will be significantly longer than that for a traditionally constructed plant; and (7) the extra cost will be substantial

Development of A Plant Navigation System

International Nuclear Information System (INIS)

Furuta, Tomihiko; Nakagawa, Tsuneo; Kubota, Ryuji; Ikeda, Kouji

1998-01-01

A 'Plant Navigation System (PNS)' is under development to assist nuclear power plant (NPP) operators by automatically displaying the plant situation and plant operational procedures on a CRT screen when abnormalities occur. The operation procedures given in a symptom-oriented manual are expressed in a tree - type flowchart (modified PAD). The optimum operation procedure for an NPP is selected automatically using built-in diagnostic logics based on the current status of the NPP. Concerning the plant situation, the PNS displays important information only on the current status of the NPP. A prototype PNS system is being constructed. (authors)

The de-construction programme for EDF'S first generation power plants

International Nuclear Information System (INIS)

Zask, G.; Corcuff, A.

2003-01-01

Before 2001 EDF had adopted a 'long wait' scenario for the de-construction of nuclear power plants, consisting of waiting for a period of 5 to 10 years for IAEA level 2 (partial release of the site), then postponing the total de-construction of the facility for 25 to 50 years, in order to benefit from the natural decay of the radioactivity and thereby reduce the dosimetry of the personnel and the costs. Today, as regards the 8 power plants of the first generation and Creys-Malville, EDF has decided to undertake the total de-construction over a period of 25 years of all its reactors that have ceased commercial operation. The forecast cost of this programme amounts to Euro 3 billion. It thus intends to demonstrate its capacity to control, within the scale of the human lifespan, the entire life cycle of its nuclear power plants, while minimising the impact on man and the environment. This choice of immediate dismantling for the power plants of the first generation does not prejudge what will be done, when the time comes, for the PWR plants currently in operation. The paper has the following contents: 1. General; 2.The facilities concerned; 3. Chronological sequence adopted for de-construction; 4. Milestones and critical paths; 4.1. Simplification of the administrative procedures; 4.2. The waste channels; 4.3. Industrial organisation; 4.3.1. Creation of Centre d'Ingenierie De-construction et Environnement (CIDEN); 4.3.2. Responsibilities, interfaces and co-ordination of the various departments concerned (Role of owner: Responsibility as nuclear operator; Overall co-ordination; Operational steering of projects); 4.3.3. Internal authorization process; 4.3.4. Obtaining and maintaining skills (Training; Environment; De-construction; Radiological protection, radiology, radioecology; Processing of waste and approval of the cycle); 4.3.5. Monitoring of works and surveillance of service providers; 4.3.6. Radiological protection, environment; 4.3.7. Control of conventional

Integrated construction management technology for power plants

International Nuclear Information System (INIS)

Okada, Hisako; Miura, Jun; Nishitani, Yasuhiko

2003-01-01

The improvement and rationalization of the plant construction technology has been promoted in order to shorten the construction period, to improve the quality and reliability, and especially to reduce construction costs. With the recent remarkable advances of computer technology, it is necessary to introduce an electronic information technology (IT) into the construction field, and to develop a business process. In such a situation, Hitachi has developed and applied integrated construction support system, which is consistent among design, production and construction. This system has design information and schedule information made electronically as a basic database, and characterizes with project management function based on that information. By introduction of this system, electronic processing of information and reduction of paperwork has enabled high efficiency and standardization of on-site indirect work. Furthermore, by collaboration with the civil company, electrical data exchange has been carried out and developed techniques to improve the interface between mechanical and civil work. High accuracy of construction planning and unification of schedule data have been achieved, and consequently, rework and adjustment at the job site have been greatly reduced. (author)

Direct containment heating experiments in Zion Nuclear Power Plant geometry using prototypic materials

International Nuclear Information System (INIS)

Binder, J.L.; McUmber, L.M.; Spencer, B.W.

1993-01-01

Direct Containment Heating (DCH) experiments have been completed which utilize prototypic core materials. The experiments reported on here are a continuation of the Integral Effects Testing (IET) DCH program. The experiments incorporated a 1/40 scale model of the Zion Nuclear Power Plant containment structures. The model included representations of the primary system volume, RPV lower head, cavity and instrument tunnel, and the lower containment structures. The experiments were steam driven. Iron-alumina thermite with chromium was used as a core melt stimulant in the earlier IET experiments. These earlier IET experiments at Argonne National Laboratory (ANL) and Sandia National Laboratories (SNL) provided useful data on the effect of scale on DCH phenomena; however, a significant question concerns the potential experiment distortions introduced by the use of non-prototypic iron/alumina thermite. Therefore, further testing with prototypic materials has been carried out at ANL. Three tests have been completed, DCH-U1A, U1B and U2. DCH-U1A and U1B employed an inerted containment atmosphere and are counterpart to the IET-1RR test with iron/alumina thermite. DCH-U2 employed nominally the same atmosphere composition of its counterpart iron/alumina test, IET-6. All tests, with prototypic material, have produced lower peak containment pressure rises; 45, 111 and 185 kPa in U1A, U1B and U2, compared to 150 and 250 kPa IET-1RR and 6. Hydrogen production, due to metal-steam reactions, was 33% larger in U1B and U2 compared to IET-1RR and IET-6. The pressurization efficiency was consistently lower for the corium tests compared to the IET tests

International comparison of economic and technical indexes of nuclear power plant construction

International Nuclear Information System (INIS)

Majer, P.; Fialova, H.

1988-01-01

The comparison of capital costs of the construction of nuclear power plants takes into consideration the following aspects: the delineation of the installation, the determination of costs and their break-down, the impact of the time factor, the conversion of the costs to a comparable unit. Power plants are always compared with roughly the same power capacity, this even when conditions for construction are not fully comparable. Construction costs may be divided into, e.g., pre-construction costs, direct capital costs, indirect capital costs, interest during construction. The time factor is manifest in the duration of construction and in the concrete year of construction for which the comparison is being made. The inflationary rise in prices and interests are increasing capital costs by roughly 5 - 8% per annum. The comparison of costs expressed in different currencies is made either by conversion using the rate of exchange or by comparing the time expended for the construction of the power plant. Various methods of comparison are discussed. (J.B.). 7 refs

[Risk communication in construction of new nuclear power plant].

Science.gov (United States)

He, Gui-Zhen; Lü, Yong-Long

2013-03-01

Accompanied by construction of new nuclear power plants in the coming decades in China, risk management has become increasingly politicized and contentious. Nuclear risk communication is a critical component in helping individuals prepare for, respond to, and recover from nuclear power emergencies. It was discussed that awareness of trust and public attitudes are important determinants in nuclear power risk communication and management. However, there is limited knowledge about how to best communicate with at-risk populations around nuclear power plant in China. To bridge this gap, this study presented the attitudinal data from a field survey in under-building Haiyang nuclear power plant, Shandong Province to measure public support for and opposition to the local construction of nuclear power plant. The paper discussed the structure of the communication process from a descriptive point of view, recognizing the importance of trust and understanding the information openness. The results showed that decision-making on nuclear power was dominated by a closed "iron nuclear triangle" of national governmental agencies, state-owned nuclear enterprises and scientific experts. Public participation and public access to information on nuclear constructions and assessments have been marginal and media was a key information source. As information on nuclear power and related risks is very restricted in China, Chinese citizens (51%) tend to choose the government as the most trustworthy source. More respondents took the negative attitudes toward nuclear power plant construction around home. It drew on studies about risk communication to develop some guidelines for successful risk communication. The conclusions have vast implications for how we approach risk management in the future. The findings should be of interest to state and local emergency managers, community-based organizations, public health researchers, and policy makers.

Delays in nuclear power plant construction. Volume II. Final report

International Nuclear Information System (INIS)

Mason, G.E.; Larew, R.E.; Borcherding, J.D.; Okes, S.R. Jr.; Rad, P.F.

1977-01-01

The report identifies barriers to shortening nuclear power plant construction schedules and recommends research efforts which should minimize or eliminate the identified barriers. The identified barriers include (1) Design and Construction Interfacing Problems; (2) Problems Relating to the Selection and Use of Permanent Materials and Construction Methods; (3) Construction Coordination and Communication Problems; and (4) Problems Associated with Manpower Availability and Productivity

Delays in nuclear power plant construction. Volume I. Final report

International Nuclear Information System (INIS)

1977-01-01

The report identifies barriers to shortening nuclear power plant construction schedules and recommends research efforts which should minimize or eliminate the identified barriers. The identified barriers include: (1) Design and Construction Interfacing Problems; (2) Problems Relating to the Selection and Use of Permanent Materials and Construction Methods; (3) Construction Coordination and Communication Problems; and (4) Problems Associated with Manpower Availability and Productivity

Prototype fast breeder reactor main options

International Nuclear Information System (INIS)

Bhoje, S.B.; Chellapandi, P.

1996-01-01

Fast reactor programme gets importance in the Indian energy market because of continuous growing demand of electricity and resources limited to only coal and FBR. India started its fast reactor programme with the construction of 40 MWt Fast Breeder Test Reactor (FBTR). The reactor attained its first criticality in October 1985. The reactor power will be raised to 40 MWt in near future. As a logical follow-up of FBTR, it was decided to build a prototype fast breeder reactor, PFBR. Considering significant effects of capital cost and construction period on economy, systematic efforts are made to reduce the same. The number of primary and secondary sodium loops and components have been reduced. Sodium coolant, pool type concept, oxide fuel, 20% CW D9, SS 316 LN and modified 9Cr-1Mo steel (T91) materials have been selected for PFBR. Based on the operating experience, the integrity of the high temperature components including fuel and cost optimization aspects, the plant temperatures are recommended. Steam temperature of 763 K at 16.6 MPa and a single TG of 500 MWe gross output have been decided. PFBR will be located at Kalpakkam site on the coast of Bay of Bengal. The plant life is designed for 30 y and 75% load factor. In this paper the justifications for the main options chosen are given in brief. (author). 2 figs, 2 tabs

75 FR 32313 - Specifications and Drawings for Construction Direct Buried Plant

Science.gov (United States)

2010-06-08

... construction units for Fiber-to-the-Home, remove redundant or outdated requirements, and simplify the.... Because of Fiber-to-the-Home construction and advancements made in construction installation methods and... Construction Direct Buried Plant AGENCY: Rural Utilities Service, USDA. ACTION: Proposed Rule. SUMMARY: The...

Construction of Industrial Electron Beam Plant for Wastewater Treatment

International Nuclear Information System (INIS)

Han, B.; Kim, J.; Kim, Y.; Kim, S.; Lee, M.; Choi, J.; Ahn, S.; Makarov, I.E.; Ponomarev, A.V.

2004-01-01

A pilot plant for treating 1,000 m3/day of dyeing wastewater with e-beam has been constructed and operated since 1998 in Daegu, Korea together with the biological treatment facility. The wastewater from various stages of the existing purification process has been treated with electron beam in this plant, and it gave rise to elaborate the optimal technology of the electron beam treatment of wastewater with increased reliability at instant changes in the composition of wastewater. Installation of the e-beam pilot plant resulted in decolorizing and destructive oxidation of organic impurities in wastewater, appreciable to reduction of chemical reagent consumption, in reduction of the treatment time, and in increase in flow rate limit of existing facilities by 30-40%. Industrial plant for treating 10,000 m3/day, based upon the pilot experimental result, is under construction and will be finished by 2005. This project is supported by the International Atomic Energy Agency (IAEA) and Korean Government

New consumer load prototype for electricity theft monitoring

International Nuclear Information System (INIS)

Abdullateef, A I; Salami, M J E; Musse, M A; Onasanya, M A; Alebiosu, M I

2013-01-01

Illegal connection which is direct connection to the distribution feeder and tampering of energy meter has been identified as a major process through which nefarious consumers steal electricity on low voltage distribution system. This has contributed enormously to the revenue losses incurred by the power and energy providers. A Consumer Load Prototype (CLP) is constructed and proposed in this study in order to understand the best possible pattern through which the stealing process is effected in real life power consumption. The construction of consumer load prototype will facilitate real time simulation and data collection for the monitoring and detection of electricity theft on low voltage distribution system. The prototype involves electrical design and construction of consumer loads with application of various standard regulations from Institution of Engineering and Technology (IET), formerly known as Institution of Electrical Engineers (IEE). LABVIEW platform was used for data acquisition and the data shows a good representation of the connected loads. The prototype will assist researchers and power utilities, currently facing challenges in getting real time data for the study and monitoring of electricity theft. The simulation of electricity theft in real time is one of the contributions of this prototype. Similarly, the power and energy community including students will appreciate the practical approach which the prototype provides for real time information rather than software simulation which has hitherto been used in the study of electricity theft

New consumer load prototype for electricity theft monitoring

Science.gov (United States)

Abdullateef, A. I.; Salami, M. J. E.; Musse, M. A.; Onasanya, M. A.; Alebiosu, M. I.

2013-12-01

Illegal connection which is direct connection to the distribution feeder and tampering of energy meter has been identified as a major process through which nefarious consumers steal electricity on low voltage distribution system. This has contributed enormously to the revenue losses incurred by the power and energy providers. A Consumer Load Prototype (CLP) is constructed and proposed in this study in order to understand the best possible pattern through which the stealing process is effected in real life power consumption. The construction of consumer load prototype will facilitate real time simulation and data collection for the monitoring and detection of electricity theft on low voltage distribution system. The prototype involves electrical design and construction of consumer loads with application of various standard regulations from Institution of Engineering and Technology (IET), formerly known as Institution of Electrical Engineers (IEE). LABVIEW platform was used for data acquisition and the data shows a good representation of the connected loads. The prototype will assist researchers and power utilities, currently facing challenges in getting real time data for the study and monitoring of electricity theft. The simulation of electricity theft in real time is one of the contributions of this prototype. Similarly, the power and energy community including students will appreciate the practical approach which the prototype provides for real time information rather than software simulation which has hitherto been used in the study of electricity theft.

Prototype ion source for JT-60 neutral beam injectors

International Nuclear Information System (INIS)

Akiba, M.

1981-01-01

A prototype ion source for JT-60 neutral beam injectors has been fabricated and tested. Here, we review the construction of the prototype ion source and report the experimental results about the source characteristics that has been obtained at this time. The prototype ion source is now installed at the prototype unit of JT-60 neutral beam injection units and the demonstration of the performances of the ion source and the prototype unit has just started

Support to design and construction of the PBMR plant

International Nuclear Information System (INIS)

Cazorla, F.; Moron, P.; Gonzalez, J. I.

2010-01-01

Developing the new reactor design to a licensable state for constructing a pilot plant is a tough task require specific resources, concerning knowledge and previous experience, which trespassing the pure scientific or technologic knowledge linked to the reactor conceptual design. Taking into consideration the experience derived from the collaboration between the South African company PBMR (PTY) Ltd.; the Pebble Bed Modular Reactor Designer, and Tecnatom SA, the article presents some of the aspects in which the companies or organization in charge of the design can demand external support to license and construct the pilot plants with guaranteed success. (Author)

Construction and test of a full-scale prototype of an ATLAS muon spectrometer tracking chamber

International Nuclear Information System (INIS)

Biscossa, A.; Cambiaghi, M.; Conta, C.; Ferrari, R.; Fraternali, M.; Freddi, A.; Iuvino, G.; Lanza, A.; Livan, M.; Negri, A.; Polesello, G.; Rimoldi, A.; Vercellati, F.; Vercesi, V.; Bagnaia, P.; Bini, C.; Capradossi, G.; Ciapetti, G.; Creti, P.; De Zorzi, G.; Iannone, M.; Lacava, F.; Mattei, A.; Nisati, L.; Oberson, P.; Pontecorvo, L.; Rosati, S.; Veneziano, S.; Zullo, A.; Daly, C.H.; Davisson, R.; Guldenmann, H.; Lubatti, H.J.; Zhao, T.

1999-01-01

We have built a full scale prototype of the precision tracking chambers (Monitored Drift Tubes, MDT) for the muon spectrometer of the Atlas Experiment at the LHC collider. This article describes in detail the procedures used in constructing the drift tubes and in assembling the chamber. It presents data showing that the required mechanical precision has been achieved as well as test beam results displaying the over all chamber performance. The article presents data demonstrating the derivation of the space-time relation of the drift tubes by the autocalibration procedure using real data from the tracks crossing the chamber. Autocalibration is the procedure which must be used during run time

Design aspects of 50 m3/d prototype mobile desalination unit

International Nuclear Information System (INIS)

Bhattacharyya, K.P.; Srivastava, V.K.; Tewari, P.K.

2004-01-01

Supply of fresh water on sustainable basis to all inhabitants is the national responsibility. As a part of national programme to improve quality of life in our society, Desalination Division, BARC has undertaken a project on construction of barge mounted mobile desalination unit of capacity 50 m 3 /d under the domain of health care. The plant is capable of producing safe drinking water at any site and condition where potable water is limited from water sources as lakes and dams, spring, river, bores, estuaries, and open sea. The unit is also capable of purifying nuclear, biological and chemical contaminated water source namely arsenic, fluoride and nitrate. However, the main objective of this prototype mobile unit is to derive potable water from sea water. The barge mounted desalination plant could be useful to the people on shore, in areas like Rann of Kutch or coastal areas which had been affected by natural calamities like floods or severe drought; in small islands like Lakshadeep and Andaman and Nicobar. This type of mobile unit could also be useful for constructional purposes of plants located adjoining to the shore. The plant encompasses state of art reverse osmosis (RO) technology with membrane based ultrafiltration (UF) pretreatment system along with built-in back wash provision and remineralisation. The system is designed for heavy duty tasks in order to withstand frequent relocation from site to site and in skid patterns for portable transportation via road upon requirement. The conceptual design of the plant is over. The design and constructional aspects of the mobile plant are elaborated in this paper. (author)

Application of rapid prototyping technology in the prototype manufacturing for evaluation of NPP components and equipments

International Nuclear Information System (INIS)

Park, C. Y.; Kim, J. W.; Shon, H. K.; Choi, H. S.; Yang, D. Y.

2001-01-01

A brief overview of rapid prototyping technology in which a part with complex shape can be produced easily and rapidly in a layer-by-layer additive manner is given in this article. In addition, a prototype model of a complex fan is manufactured using three-dimensional solid CAD modeling and Laminated Object Manufacturing (LOM), a rapid prototyping technology. This enables designers to verify and modify design rapidly at an early stage of product development; and the prototype model of a fan can be used as a pattern for various secondary casting process such as vacumm casting, lost-paper casting to make prototypes of a fan. It has been shown that the combination of three-dimensional solid CAD modeling and rapid prototyping technology can reduce greatly the cost and time of prototyping of fans and turbine blades in comparison with conventional CNC machining. It should also be noted that rapid prototyping technology enables the visualization of various physical and chemical defects at a nuclear power plant so that it can help engineers understand those defects in an effective way

Plant reproduction is altered by simulated herbicide drift to constructed plant communities

Science.gov (United States)

Herbicide drift may have unintended impacts on native vegetation, adversely affecting structure and function of plant communities. However, these potential effects have been rarely studied or quantified. To determine potential ecological effects of herbicide drift, we construct...

Project management of the build of the shore test facility for the prototype of PWR II

International Nuclear Information System (INIS)

Clarkson, D.T.

1987-01-01

The PWR II is a new design of nuclear steam raising plant for the Royal Navy's submarines. It features improved engineering for safety, increased power, increased shock resistance, reduced noise transmission to sea and reduced manning requirement. It is to be tested in a new prototype testing facility, the Shore Test Facility, which is a section of submarine hull containing a prototype of the nuclear steam raising plant and its support system. It is installed at the Vulcan Naval Reactor Test establishment at Dounreay in Scotland. The function of the establishment is to test new designs of core and reactor plant, validate the mathematical models used in their design, develop improved methods of operation and maintenance of the plant and test new items of equipment. The Shore Test Facility was built in large sections at Barrow-in-Furness and transported to Scotland. The project management for the construction of the Shore Test Facility is explained. It involves personnel from the Royal Navy, and a large number of people working for the contractors involved in the buildings, transportation, operation and maintenance of the Facility. (U.K.)

High confidence in falsely recognizing prototypical faces.

Science.gov (United States)

Sampaio, Cristina; Reinke, Victoria; Mathews, Jeffrey; Swart, Alexandra; Wallinger, Stephen

2018-06-01

We applied a metacognitive approach to investigate confidence in recognition of prototypical faces. Participants were presented with sets of faces constructed digitally as deviations from prototype/base faces. Participants were then tested with a simple recognition task (Experiment 1) or a multiple-choice task (Experiment 2) for old and new items plus new prototypes, and they showed a high rate of confident false alarms to the prototypes. Confidence and accuracy relationship in this face recognition paradigm was found to be positive for standard items but negative for the prototypes; thus, it was contingent on the nature of the items used. The data have implications for lineups that employ match-to-suspect strategies.

Plants in constructed wetlands help to treat agricultural processing wastewater

Directory of Open Access Journals (Sweden)

Mark Grismer

2008-05-01

Full Text Available Over the past three decades, wineries in the western United States and sugarcane processing for ethanol in Central and South America have experienced problems related to the treatment and disposal of process wastewater. Both winery and sugarcane (molasses wastewaters are characterized by large organic loadings that change seasonally and are detrimental to aquatic life. We examined the role of plants for treating these wastewaters in constructed wetlands. In the greenhouse, subsurface-flow flumes with volcanic rock substrates and plants steadily removed approximately 80% of organic-loading oxygen demand from sugarcane process wastewater after about 3 weeks of plant growth; unplanted flumes removed about 30% less. In field studies at two operational wineries, we evaluated the performance of similar-sized, paired, subsurface constructed wetlands with and without plants; while both removed most of the oxygen demand, removal rates in the planted system were slightly greater and significantly different from those of the unplanted system under field conditions.

NetCDF based data archiving system applied to ITER Fast Plant System Control prototype

International Nuclear Information System (INIS)

Castro, R.; Vega, J.; Ruiz, M.; De Arcas, G.; Barrera, E.; López, J.M.; Sanz, D.; Gonçalves, B.; Santos, B.; Utzel, N.; Makijarvi, P.

2012-01-01

Highlights: ► Implementation of a data archiving solution for a Fast Plant System Controller (FPSC) for ITER CODAC. ► Data archiving solution based on scientific NetCDF-4 file format and Lustre storage clustering. ► EPICS control based solution. ► Tests results and detailed analysis of using NetCDF-4 and clustering technologies on fast acquisition data archiving. - Abstract: EURATOM/CIEMAT and Technical University of Madrid (UPM) have been involved in the development of a FPSC (Fast Plant System Control) prototype for ITER, based on PXIe (PCI eXtensions for Instrumentation). One of the main focuses of this project has been data acquisition and all the related issues, including scientific data archiving. Additionally, a new data archiving solution has been developed to demonstrate the obtainable performances and possible bottlenecks of scientific data archiving in Fast Plant System Control. The presented system implements a fault tolerant architecture over a GEthernet network where FPSC data are reliably archived on remote, while remaining accessible to be redistributed, within the duration of a pulse. The storing service is supported by a clustering solution to guaranty scalability, so that FPSC management and configuration may be simplified, and a unique view of all archived data provided. All the involved components have been integrated under EPICS (Experimental Physics and Industrial Control System), implementing in each case the necessary extensions, state machines and configuration process variables. The prototyped solution is based on the NetCDF-4 (Network Common Data Format) file format in order to incorporate important features, such as scientific data models support, huge size files management, platform independent codification, or single-writer/multiple-readers concurrency. In this contribution, a complete description of the above mentioned solution is presented, together with the most relevant results of the tests performed, while focusing in the

The evaluation, design and construction of the uranium plant for Chemwes Limited

International Nuclear Information System (INIS)

Viljoen, E.B.; Bluhm, B.J.; Pilkington, W.; Taylor, J.L.; Robinson, J.E.; Le Grange, P.

1981-01-01

The Chemwes uranium plant was designed and constructed within fifteen months; commissioning started during June 1979, and the plant was producing at design capacity four months later. This account highlights the procedures and methods adopted to bring the plant into production. The description of the various phases includes some details of the early evaluation, and the feasibility and optimization studies; of the financing, project management, design, construction, and commissioning of the plant; and of the training of personnel. Some of the mistakes made and the factors that contributed to the success are also listed [af

A framework for quantifying the extent of impact to plants from linear construction.

Science.gov (United States)

Xiao, Jun; Shi, Peng; Wang, Ya-Feng; Yu, Yang; Yang, Lei

2017-05-30

We present a novel framework that accurately evaluates the extent of a linear project's effect from the variability of the structure of the plant community while avoiding interference caused by pioneer species and invasive species. This framework was based on the change of dominant species in the plant community affected by construction. TWINSPAN classification and variation of the integrated importance value (IIV) of each plant species group were used to characterize the process of change in the structure of the plant community. Indicator species group and its inflection point were defined and used to judge the extent of the effects of pipelines. Our findings revealed that dominant species in the working area of the pipeline construction were different from the original plant communities. With the disturbance decreased, the composition and structure of the plant communities gradually changed. We considered the outer limit of the area affected by the construction to be the first area in which the plant community reached a steady state and was similar to the original community. The framework could be used in the post eco-environment impact assessment of linear construction to estimate the intensity of disturbance and recovery condition.

Data processing project management in the construction of plants and power stations

International Nuclear Information System (INIS)

Huelsen, H.; Hayen, W.

1987-01-01

The requirements of project management in plant construction i.e. basic data, supervision and control became more and more detailed. These requirements can only satisfactorily be met with the help of data processing. Piping design requires up to 50% of the whole amount of engineering in design and management of plant construction. We present data processing project management system which explains the connections of single aspects. Its connections consists of: collection of basic data, plant design and installation, supervision of planning and installation, planning and calculation, collection, use, administration and approval of plan data, procurement material, construction of the model (1:25), and installation. (orig.) [de

Theoretical Modeling and Experimental Investigation of the Thermal Performance of the LHC Prototype Lattice Cryostats

CERN Document Server

Riddone, G

1997-01-01

This thesis presents the thermal performance of the LHC (Large Hadron Collider) prototype cryostats both in steady-state and in transient conditions. LHC will be built in the 27 km LEP tunnel and will provide proton-proton collisions. It will make use of superconducting magnets operating in static bath of superfluid helium at 1.9 K. The thesis is mainly divided in three parts. The first part cont ains three chapters which present a brief overview of the LHC project. Part 1-Chapter 1 gives a short introduction to the LHC design layout and performance. Part 1-Chapter 2 refers to LHC cryogenic s ystem and describes the general architecture of the cryogenic plants, the temperature levels and the heat loads. The 50 m long LHC prototype half-cell contains one twin-bore quadrupole and four twin-a perture dipoles. In Part 1-Chapter 3 the design and construction of the prototype dipole and quadrupole cryostats are presented. The LHC prototype cryostats have integrated cryogenic lines, while the final LHC cryostats hav...

Application of PSA level 1 for the Fugen prototype ATR plant

International Nuclear Information System (INIS)

Ikeda, H.; Iguchi, Y.; Sotsu, M.; Seki, O.; Satou, S.

1997-01-01

This paper presents application of PSA Level-1 for Prototype Advanced Thermal Reactor Plant ''Fugen'' in consideration of the design characteristics of such reactor and verify the safety aspect of Fugen using thus established procedure, ATR resembles the boiling water reactor (BWR) in a number of points, but there are also some differences between the ATR and the BWR. Therefore. PSA procedure have been established by taking such difference into consideration and by referring to experience of PSA in USA and Japan. Moreover, the core damage frequency was calculated on Fugen by using thus established procedure. As a result, it was verified that results including the maximum value of the uncertainty estimation were found to be quite satisfactory against the target value of reactor damage frequency defined by the International Atomic Energy Agency (IAEA). (author)

Development of construction technology for nuclear power plants

International Nuclear Information System (INIS)

Schnellenbach, G.

1975-01-01

Stringent safety requirements for nuclear power plants create new technological problems in their construction. The development is influenced by the mode of operation of the respective reactors which leads to different construction styles of the reactor buildings. Accomodation of extraordinary load cases such as earthquake, airplane crash, and blast due to chemical explosions, requires additional treatment. Significant new problems arise for the prestressed concrete reactor pressure vessels and concrete containments, prestressed or reinforced. (orig.) [de

Computer integrated construction at AB building in reprocessing plant

International Nuclear Information System (INIS)

Takami, Masahiro; Azuchi, Takehiro; Sekiguchi, Kenji

1999-01-01

JNFL (Japan Nuclear Fuel Limited) is now processing with construction of the spent nuclear fuel reprocessing plant at Rokkasho Village in Aomori Prefecture, which is coming near to the busiest period of construction. Now we are trying to complete the civil work of AB Building and KA Building in a very short construction term by applying CIC (Computer Integrated Construction) concept, in spite of its hard construction conditions, such as the massive and complicated building structure, interferences with M and E (Mechanical and Electrical) work, severe winter weather, remote site location, etc. The key technologies of CIC are three-dimensional CAD, information network, and prefabrication and mechanization of site work. (author)

New experience on construction and installation work in Qinshan PHWR nuclear power plant

International Nuclear Information System (INIS)

Lu Huaxiang

2004-01-01

The article provides a summary of the new experience on construction management and construction technology in the field of civil construction and installation work in Qinshan PHWR nuclear power plant, with focus on innovation in project management mode, new technology application and computerized management of construction and installation work. Management innovation, technical innovation and information technology are the key contributors to overall success of Qinshan PHWR nuclear power plant in construction and installation work. The new experience derived in these fields will be of great significance to promote independent construction of the new-round nuclear power projects in China. (author)

SEMPaC - an expert system prototype associated with safety parameter display system of a nuclear power plant

International Nuclear Information System (INIS)

Hirama, K.

1989-01-01

This work presents SEMPaC, an expert system prototype: it provides means to support diagnosis and to make decisions during abnormal transients that cause the trip of nuclear power plant. The system operation is associated with Safety Parameter Display System - SPDS that was recommended by U. S. Nuclear Regulatory Commission (NRC) after the Three-Mile Island (TMI) accident analysis. (author)

Design of Object-based Information System Prototype

OpenAIRE

Suhyeon Yoo; Sumi Shin; Hyesun Kim

2014-01-01

Researchers who use science and technology information were found to ask an information service in which they can excerpt the contents they needed, rather than using the information at article level. In this study, we micronized the contents of scholarly articles into text, image, and table and then constructed a micro-content DB to design a new information system prototype based on this micro-content. After designing the prototype, we performed usability test for this prototype so as to conf...

Quality control of three main materials for civil construction of nuclear power plant

International Nuclear Information System (INIS)

Wang Feng

2011-01-01

The construction and operation of nuclear power plant is a systematic engineering. To ensure quality and safety of nuclear power plants, each work from design to operation can have certain impact on the quality and safety of the project. The quality of each related work shall be controlled. Starting from the quality control over raw materials for the civil construction of nuclear power plant, this article mainly analyzes how to control the quality and manage the three main materials of steel, concrete and modular parts in the civil construction. (author)

Development of prototype reactor maintenance. (2) Application to piping support of sodium-cooled reactor prototype

International Nuclear Information System (INIS)

Arai, Masanobu; Kunogi, Kosuke; Aizawa, Kosuke; Chikazawa, Yoshitaka; Takaya, Shigeru; Kubo, Shigenobu; Kotake, Shoji; Ito, Takaya; Yamaguchi, Akira

2017-01-01

A maintenance program on piping support of prototype fast breeder reactor Monju are studied. Based on degradation mechanism, snubbers in Monju primary cooling system showed lifetime more than the plant lifetime of 30 years by experiments conservatively. For the first step during construction, visual inspection on accessible all supports could be available. In that visual inspection, mounting conditions and damages of all accessible supports could be monitored. One of major features of the Monju primary piping system is large thermal expansion due to large temperature difference between maintenance and operation conditions. Thanks to that large thermal expansion, integrity of piping supports could be monitored by measuring piping displacement. When technologies of piping displacement monitoring are matured in Monju, visual inspection on piping support could be shifted to piping displacement monitoring. At that stage, the visual inspection could be limited only on representative supports. (author)

Reactivation of nuclear power plant construction projects. Plant status, policy issues and regulatory options

International Nuclear Information System (INIS)

Spangler, M.B.

1986-07-01

Prior to the TMI-2 accident on March 28, 1979, four nuclear power plant units that had previously been issued a construction permit were cancelled, principally because of reduced projections of regional power demand. Since that time, an additional 31 units with CPs have been cancelled and eight units deferred. On December 23, 1985 one of the deferred units (Limerick-2) was reactivated and construction resumed. The primary objective of this policy study is to identify the principal issues requiring office-level consideration in the event of reactivation of the construction of one or more of the nuclear power plants falling into two categories: (1) LWR units issued a construction permit whose construction has been cancelled, and (2) LWR units whose construction has been deferred. The study scope is limited to identifying regulatory issues or questions deserving analysis rather than providing, at this time, answers or recommended actions. Five tasks are addressed: a tabulation and discussion of the status of all cancelled and deferred LWR units; and identification of potential safety and environmental issues; an identification of regulatory or policy issues and needed information to determine the desirability of revising certain rules and policies; and identification of regulatory options and decision criteria; and an identification of decision considerations in determining staff requirements and organizational coordination of LWR reactivation policy and implementation efforts. 41 refs

Reactor plant construction productivity, why so different

International Nuclear Information System (INIS)

Palmeter, S.B.

1976-01-01

The manual labor component (manhours per kw) required to construct a nuclear power plant has increased radically since the advent of the fixed price turnkey projects of the late 1960's and early 1970's. Utilities and their architect-engineers have been, for the past several years, evaluating and diagnosing possible reasons for the increase and, in particular, the wide variation in labor manhours per kw among plants built in the same time frame. Since construction labor can amount to as much as 35--40% of direct capital cost, ways and means must be found to arrest this manhour escalation. One important way is by improving productivity. Some of the manhour increase is beyond an owner's control, e.g. NRC regulatory and other federal and state requirements adding to the scope of work. Several areas where there is potential for productivity improvement are identified as follows: (1) Revise contract strategy and bid work on a fixed price basis. This can be done by utilizing bid packages where the scope of work is clearly identified and based on well defined plans and specifications. (2) Upgrade the quality of construction management and remove first line supervision from union control. Use periodic work sampling to pinpoint causes and cure for poor productivity. (3) Reduce design complexity and improve constructibility by means of innovative design and material utilization--models help. (4) Improve labor productivity by restoring management rights in collective bargaining agreements. If this is not possible, go open shop or owner build with your own work force

A new surface treatment for the prototype Rcs of the BESIII spectrometer

International Nuclear Information System (INIS)

Zhang Jiawen; Du Zizhen; Han Jifeng; Li Jiancheng; Li Rubai; Liu Qian; Qian, Sen; Wang Yifang; Xie Yigang; Xie Yuguang; Zhao Jianbin; Min Fasu; Zhao Haiquan; Zhao, T.

2005-01-01

The prototype resistive plate chambers (RPCs) for the BESIII spectrometer were constructed by using resistive electrodes made from a special type of phenolic paper laminates developed by us. The surface quality of these laminates is superior to other bakelite plates that have been used to construct RPCs elsewhere. A method for adjusting the resistivety of these laminates was also developed. Extensive studies were conducted by using a number of prototype RPCs in the last several years. Tests have shown prototype RPCs made by using our resistive plates without the linseed oil treatment can achieve the level of performance comparable to RPCs with linseed oil treated bakelite or resistive glass electrodes. In this paper, we will discuss the construction of these prototype RPCs. The test results of a prototype RPC that have been monitored for a year will be reported. Based on favorable test results of prototypes, the RPC production for the muon identifier of the BESIII spectrometer has started at the Beijing Gaonengkedi Science and Technology Co. Ltd. in early 2004 using the technology that we developed

Evaluation of the energy required for constructing and operating a fusion power plant

International Nuclear Information System (INIS)

Buende, R.

1982-09-01

The energy required for constructing and operating a tokamak fusion power plant is appraised with respect to the energy output during the lifetime of the plant. A harvesting factor is deduced as a relevant figure of energetic merit and is used for a comparison between fusion, fission, and coal-fired power plants. Because fusion power plants involve considerable uncertainties the comparison is supplemented by a sensitivity analysis. In comparison with Light Water Reactor plants fusion power plants appear to be rather favourable in this respect. The energy required for providing the fuel is relatively low for fusion plants, thus overcompensating the considerable higher amount of energy necessary for constructing the fusion power plant. (orig.)

Electric utility power plant construction costs, 1st Edition

International Nuclear Information System (INIS)

Anon.

1993-01-01

New UDI report combines historical construction costs for more than 1,000 coal, oil, gas, nuclear and geothermal units that have entered commercial operation since 1966 and projected power plant construction costs for about 400 utility-owned generating units scheduled to enter commercial operation during the next 20 years. Key design characteristics and equipment suppliers, A/E, constructor and original installed cost data. Direct construction costs without AFUDC are provided where known. Historical construction cost data are also provided for about 130 utility-owned hydroelectric, gas turbine, combined-cycle and diesel units (these data are generally for units entering service after 1980)

The VERITAS Prototype and the Upcoming VERITAS Array

Science.gov (United States)

VERITAS Collaboration; Badran, H. M.; Blaylock, G.; Bond, I. H.; Boyle, P. J.; Bradbury, S. M.; Buckley, J. H.; Byrum, K.; Carter-Lewis, D. A.; Celik, O.; Cogan, P.; Cui, W.; Daniel, M.; de La Calle Perez, I.; Dowkontt, P.; Duke, C.; Fegan, D. J.; Fegan, S. J.; Finley, J. P.; Fortson, L. F.; Gammell, S.; Gibbs, K.; Gillanders, G. H.; Grube, J.; Guiterrez, K. J.; Hall, J.; Hanna, D.; Holder, J.; Horan, D.; Hughes, S.; Humensky, T. B.; Jung, I.; Kenny, G. E.; Kertzman, M.; Kieda, D.; Kildea, J.; Knapp, J.; Kosack, K.; Krawczynski, H.; Krennrich, F.; Lang, M. J.; Le Bohec, S.; Linton, E.; Lloyd-Evans, J.; Mendoza, D.; Merriman, A.; Milovanovic, A.; Moriarty, P.; Nagai, T.; Olevitch, M.; Ong, R. A.; Pallassini, R.; Perkins, J.; Petry, D.; Pizlo, F.; Pohl, M.; Power-Mooney, B.; Quinn, J.; Quinn, M.; Ragan, K.; Rebillot, P.; Reynolds, P. T.; Rose, H. J.; Schroedter, M.; Sembroski, G. H.; Swordy, S. P.; Syson, A.; Valcarcel, L.; Vassiliev, V. V.; Wagner, R.; Wakely, S. P.; Walker, G.; Weekes, T. C.; White, R. J.; Zweerink, J.

2005-02-01

The prototype for the VERITAS imaging atmospheric Cherenkov telescope array was successfully operated in southern Arizona between September 2003 and April 2004. The prototype consisted of 86 mirror facets mounted centrally on a 12-meter dish, which was built to accommodate up to 350 facets when converted to a complete VERITAS telescope. The camera consisted of half of the full 499 pixel camera. The signal and trigger electronics were nearly identical to those that will be used for the individual VERITAS array telescopes. By observing the Crab and Mrk421, as well as performing a variety of tests, the characteristics of the instrument were evaluated. The prototype met all performance expectations and served as a valuable test bed for the current design, as well as for the construction and operation of VERITAS. This prototype instrument is now being upgraded to a complete VERITAS telescope that will be operated during the construction of the full VERITAS array. The array is expected to be operational by November 2006.

47 CFR 32.2003 - Telecommunications plant under construction.

Science.gov (United States)

2010-10-01

... 47 Telecommunication 2 2010-10-01 2010-10-01 false Telecommunications plant under construction. 32.2003 Section 32.2003 Telecommunication FEDERAL COMMUNICATIONS COMMISSION (CONTINUED) COMMON CARRIER SERVICES UNIFORM SYSTEM OF ACCOUNTS FOR TELECOMMUNICATIONS COMPANIES Instructions for Balance Sheet...

Experience in constructing a spent nuclear fuel reprocessing plant in Japan

International Nuclear Information System (INIS)

Hashimoto, K.; Sakuma, A.; Inoue, K.

1977-01-01

Towards the end of 1970, Japan Gasoline Co. Ltd. (JGC) and Saint-Gobain Techniques Nouvelles of France received an order for the construction of a reprocessing plant from Power Reactor and Nuclear Fuel Development Corporation, as a joint prime contractor. The work executed by JGC in this project is reported and consisted of: (1) Procurement, inspection and schedule control of equipment and materials other than those imported from Europe; (2) Conclusion of contracts with various subcontractors relating to the building construction, piping and other work; and (3) Supervision of field work. The field work began in June 1971 and was completed in about 40 months. The overall field labour mobilized during that time totalled about 410,000 man-days, and 900,000 man-hours were spent by the JGC engineers. With the object of constructing a high-quality plant, JGC since 1969 has started to investigate subcontractors in Japan as well as undertaking the selection, education and training of prospective subcontractors. For the welding work in particular, techniques were imported from France and domestic techniques were developed at the same time. Completion of the blank tests was estimated to require 33 months, but the schedule was delayed about seven months for various reasons. Obviously there is room for many improvements when constructing future nuclear chemical plants. However, careful consideration should also be given from the basic design stage onward, to the methods and sequence of construction so that a simplified plan can be obtained from which the work could be easily executed without resorting to special technology. This would lead to reduction in construction time, and a safer and more reliable plant at lower cost. (author)

Eight years' operation of the SGHWR prototype

International Nuclear Information System (INIS)

Phillips, J.L.

1976-01-01

Experience gained of the SGHWR system during the first eight years of operation of the UKAEA's 100 MW(e) prototype at AEE Winfrith is discussed. Modifications and additions have been made to the plant to overcome problems which only operation of a prototype unit can reveal. No problems have arisen which could not be overcome by the application of normal engineering resources, and there is no reason why the commercial successor to the prototype should be other than a fully viable proposition. (author)

Construction and operation of a support facilities (Building 729) for operation/testing of a prototype accelerator/storage ring (XLS) and machine shop for the National Synchrotron Light Source at Brookhaven National Laboratory, Upton, New York

International Nuclear Information System (INIS)

1992-06-01

Proposed action is to construct at BNL a 5,600-ft 2 support building, install and operate a prototypic 200 MeV accelerator and a prototypic 700 MeV storage ring within, and to construct and operate a 15 kV substation to power the building. The accelerator and storage ring would comprise the x-ray lithography source or XLS

Safety-related concrete structure design and construction of Rokkasho Reprocessing Plant

International Nuclear Information System (INIS)

Morishita, Hideki; Munakata, Yoshinari; Togashi, Akihito

2003-01-01

The Rokkasho Reprocessing Plant of the Japan Nuclear Fuel Co. Ltd., is a facility to reprocess remained uranium without firing and newly formed plutonium contained in spent fuels used at the nuclear power stations, to produce fuels to be repeatedly used. Constructions in this facility has some characteristics shown as follows: 1) radiation shielding and seismic isolated functions like those at the nuclear power plants, 2) reduction of wall thickness based on partially using heavy concrete at walls required for radiation shielding, 3) protective design against fly-coming matters such as aircrafts, 4) construction period reduction based on winter construction and large scale block engineering. Here were described characteristics of designs on radiation shielding, seismic isolated and fly-coming matters protection construction engineering and quality control on concrete. (G.K.)

HSE management for AP1000 nuclear plant construction in EPC mode

International Nuclear Information System (INIS)

He Xiaogang; Wei Zhong

2010-01-01

As a new nuclear type, AP1000 will become the development direction of Chinese nuclear project. EPC General Contract mode is favored by nuclear owners both at home and abroad. Therefore, there is necessity for studying HSE management system and method suitable for AP1000 nuclear plant construction (ANPC) based on combination of AP1000 construction characters in EPC mode. This can not only ensure safety for ANPC but also positively promote national nuclear power development. For this reason, based on site HSE management of the first AP1000 nuclear plant under construction, HSE management system and method for ANPC in EPC mode was proposed after analysis of the character of EPC mode and ANPC character. It is hoped that it will be helpful for safe construction for ANPC. (authors)

Nuclear Power Plants. Construction status report, data as of February 28, 1978

International Nuclear Information System (INIS)

1978-03-01

Data on the construction status of nuclear power plants in the US as of February 28, 1978 are presented. The data include licensing activities affecting the construction as well as detailed information on construction activities and schedules

Risks and challenges associated with the design and construction of a nuclear power plant

International Nuclear Information System (INIS)

Liebana Martinez, B.; Armas Garcia, A.; Martinez Gozalo, I.

2011-01-01

The construction of a nuclear power plant project, considering the period prior to the operation of the plant, requires a very strict risk control to ensure compliance with a series of challenges. The present paper identifying the most important challenges facing the construct ability and license requirements of the process, identifying the interfaces and proposing a methodology of construction to meet the challenge of a construction process in 5 years.

Experience from construction and operation of Karachi nuclear power plant

International Nuclear Information System (INIS)

Zaidi, S.M.N.

1977-01-01

Pakistan's first nuclear power plant (KANUPP) is owned and operated by the Pakistan Atomic Energy Commission (PAEC). It uses a heavy water moderated and cooled natural uranium fuelled reactor. Total installed capacity is 137 MW(e). It was designed, constructed and commissioned by Canadian General Electric Co. Ltd. (CGE) as Prime Contractor. Construction started in mid-1966 and was completed in mid 1970; commissioning started in early 1970 and was completed at the end of 1972. Intensive on-the-job training for 20 engineers and 15 operators was provided by CGE in Canada. Ten engineers also worked in CGE's design offices. With this key group of engineers and technicians PAEC had no difficulty in taking over the plant from CGE after completion. The construction of the plant in a developing country presented special problems to CGE. The relatively small local construction firms had limited experience and equipment. Construction plant, equipment and tools were scarce. Fabrication and workshop facilities of limited scope were available but their quotations were relatively high. A scarcity of engineering, technical and skilled manpower for the construction of the project left as the only alternative on-site training for carefully recruited technicians. The results were most gratifying and compared favourably with CGE's Canadian experience. Welding, pipe fitting, tubing work and electrical connections were excellent. The local staff's productivity and dedication were very good. In the commissioning period, PAEC and CGE engineers and technicians worked as one team, testing and debugging the equipment and systems and demonstrating the contractual performance warranties. This period extended to approximately three years due to many technical problems resulting from equipment failures, environmental problems, system problems, plant loading limitations in view of the relatively small size of the grid system and special requirement of fuel conditioning to avoid premature fuel

Nuclear power plants. Construction status report, data as of April 30, 1978

International Nuclear Information System (INIS)

1978-05-01

Data on the construction status of nuclear power plants in the U.S. as of April 30, 1978 are presented. The data include licensing activities affecting the construction as well as detailed information on construction activities and schedules

Nuclear power plants. Construction status report, data as of June 30, 1977. Data for decisions

International Nuclear Information System (INIS)

1977-07-01

The report is designed to provide the necessary information for monitoring the progress of construction of nuclear power plants. It provides data for synchronizing the licensing process with predicted fuel loading dates, as well as providing a central federal government report for commercial reactor construction. It utilizes data collected from the utilities sponsoring these projects and the Office of Inspection and Enforcement, NRC, and analyzed by the Office of Management Information and Program Control in the implementation of Management Information Systems. The status of the 92 plants authorized to engage in construction activities is summarized. This total includes 4 plants with construction exemptions, and 18 plants with Limited Work Authorization Permits

The research on the material management system in nuclear power plant construction process

International Nuclear Information System (INIS)

Liu Xuegeng; Huang Zhongping

2010-01-01

According to the module construction speciality of nuclear power plant, this article analyzes the relationship between the actual amount of the material transported to the construction site and the planed needs of the material, and points out the zero inventory management target in the nuclear power plant construction site. Based on this, the article put forward a nuclear power plant material management system which is based on the 'pull' information driver. This system is composed by material coding sub-system, procurement and site material integrated management sub-system and project control sub-system, and is driven by the material demand from construction site to realize the JIT purchasing. This structure of the system can reduce the gap between the actual amount of the material transported to the site and the planed needs of the material and achieve the target of reducing storage at construction site. (authors)

EVMS for nuclear power plant construction: status and implementation

International Nuclear Information System (INIS)

Roh, M. S.; Kwak, J. K.; Park, S. Y.

2012-01-01

The Earned Value Management System (EVMS) method integrates three critical elements of project management scope, cost and time management. It requires the periodic monitoring of actual expenditures and physical scope accomplishments and allows calculation of cost and schedule variances along with performance indices. It allows for casting of project cost and schedule at completion and highlights the possible need for corrective action. It is anticipated that there will be intense competition in the nuclear industry as the cost and time for nuclear power plant construction. In order to attain competitive advantages, utilizing advanced project control systems by integrating cost and time management is of great concern for practitioners. This paper is to review the status of EVMS and its effective implementation to nuclear power plant construction

Initial performance of the PIGMI prototype

International Nuclear Information System (INIS)

Stovall, J.E.

1979-01-01

The PIGMI (Pion Generator for Medical Irradiations) program at LASL is an accelerator development program aimed at completing the design of an accelerator suitable for use as a pion generator in a hospital-based radiotherapy program. The major thrust of the program has been the design of a 7 MeV prototype accelerator which emphasizes compactness, economy of construction, and operation and reliability. To achieve these goals the design of the prototype has exploited a number of innovations in proton linac technology. An overview of the program discussing the major innovative features of the prototype is presented. The initial operating experience is discussed and initial performance measurements are presented

Issues and measures in the design process from the perspective of risk management of construction projects. study of power plant construction projects accident cases

International Nuclear Information System (INIS)

Iwahara, Hirohiko; Shiraki, Wataru; Inomo, Hitoshi; Hasegawa, Syuichi

2015-01-01

Construction of power plants, foundation work, consisting of a wide variety of construction work, such as plant equipment work. And, civil engineering, technician electrical such as different engineering field, is a comprehensive construction project that works for the design conditions of the structure. However, if the cooperation design conditions is not sufficient, as a construction project, the optimal structures may not be said to have been built. As a result, total cost or increased, including the initial cost of the end construction projects, it is be a cause of the accident. Previous studies, plant equipment construction, is related to safety management and risk of foundation work such as individual construction were many. In this paper, as an example the power plant construction, and performs the following discussion from the point of view of risk management of large-scale construction projects that these individual construction work together with each other. The importance of design conditions cooperation, (1) 'Challenges and countermeasures of ordering method of construction projects', to verify from the (2) 'actually happened substation foundation displacement accident'. And on whether or not the construction project order institutions can be involved in the design from the site preparation stage, we study (3) for 'construction work scope and risk control the construction project ordering institutions to implement' the risk to the natural disaster (earthquake). From these, we describe the challenges and measures in the construction project of the design process. (author)

4D Simulation for Nuclear Power Plant Construction

International Nuclear Information System (INIS)

Jeong, Seo G.; Suh, Kune Y.

2006-01-01

For the timely and competitive response to rapidly changing energy environment at the turn of millennium, there is a desperate need to build the nuclear power plant (NPP) in the virtual reality of digital engineering prior to commissioning. To construct a NPP is a highly integrated, voluminous project. Verification of design and initial planning is prerequisite to construction to confirm optimal fabrication and high productivity. This paper presents the design feasibility by simulating the initial construction plan of NPP using four-dimensional (4D) simulation. The virtual reality method, using three dimensional (3D) computer-aided design (CAD) model, enables various designs in the project launching stage to be promptly and exactly previewed

Simulation of power plant construction in competitive Korean electricity market

International Nuclear Information System (INIS)

Ahn, Nam Sung; Huh, Sung Chul

2001-01-01

This paper describes the forecast of power plant construction in competitive Korean electricity market. In Korea, KEPCO (Korean Electric Power Corporation, fully controlled by government) was responsible for from the production of the electricity to the sale of electricity to customer. However, the generation part is separated from KEPCO and six generation companies were established for whole sale competition from April 1st, 2001. The generation companies consist of five fossil power companies and one nuclear power company. Fossil power companies are schedule to be sold to private companies including foreign investors. Nuclear power company is owned by government. The competition in generation market will start from 2003. ISO (Independence System Operator) will purchase the electricity from the power exchange market. The market price is determined by the SMP (System Marginal Price) which is decided by the balance between demand and supply of electricity in power exchange market. Under this uncertain circumstance, the energy policy planners are interested to the construction of the power plant in the future. These interests are accelerated due to the recent shortage of electricity supply in California. In the competitive market, investors are no longer interested in the investment for the capital intensive, long lead time generating technologies. Large nuclear and coal plants were no longer the top choices. Instead, investors in the competitive market are interested in smaller, more efficient, cheaper, cleaner technologies such as CCGT (Combined Cycle Gas Turbine). Electricity is treated as commodity in the competitive market. The investor's behavior in the commodity market shows that the new investment decision is made when the market price exceeds the sum of capital cost and variable cost of the new facility and the existing facility utilization depends on the marginal cost of the facility. This investor's behavior can be applied to the new investments for the

Design and construction of nuclear power plants

International Nuclear Information System (INIS)

Meiswinkel, Ruediger; Meyer, Julian; Schnell, Juergen

2013-01-01

Despite all the efforts being put into expanding renewable energy sources, large-scale power stations will be essential as part of a reliable energy supply strategy for a longer period. Given that they are low on CO2 emissions, many countries are moving into or expanding nuclear energy to cover their baseload supply. Building structures required for nuclear installations whose protective function means they are classified as safety-related, have to meet particular construction requirements more stringent than those involved in conventional construction. This book gives a comprehensive overview from approval aspects given by nuclear and construction law, with special attention to the interface between plant and construction engineering, to a building structure classification. All life cycle phases are considered, with the primary focus on execution. Accidental actions on structures, the safety concept and design and fastening systems are exposed to a particular treatment. Selected chapters of the German concrete yearbook ''Beton-Kalender'' are now available in English. The new English BetonKalender Series delivers internationally useful engineering expertise and industrial know-how from Germany.

Construction Technologies for Nuclear Power Plants

International Nuclear Information System (INIS)

2011-01-01

One of the IAEA's statutory objectives is to 'seek to accelerate and enlarge the contribution of atomic energy to peace, health and prosperity throughout the world'. One way this objective is achieved is through the publication of a range of technical series. Two of these are the IAEA Nuclear Energy Series and the IAEA Safety Standards Series. According to Statute Article III, A.6, the IAEA safety standards establish 'standards of safety for protection of health and minimization of danger to life and property.' The safety standards include the Safety Fundamentals, Safety Requirements and Safety Guides. These standards are written primarily in a regulatory style, and are binding on the IAEA for its own programmes. The principal users are the regulatory bodies in Member States and other national authorities. The IAEA Nuclear Energy Series comprises reports designed to encourage and assist R and D on and practical application of, nuclear energy for peaceful uses. This includes practical examples to be used by owners and operators of utilities in Member States, implementing organizations, academia, and government officials, among others. This information is presented in guides, reports on technology status and advances, and best practices for peaceful uses of nuclear energy based on inputs from international experts. The IAEA Nuclear Energy Series complements the IAEA Safety Standards Series. There are three distinct significant phases in a nuclear power plant (NPP) project after the signing of a contract; engineering, procurement, and construction and commissioning. Experience gained over the last forty years has shown that the construction phase is one of the most critical phases for the success of a project. Success is defined as completing the project with the specified quality, and within budget and schedule. The key to a successful construction project is to have an established programme that integrates the critical attributes into the overall project. Some of

Design considerations and construction of an experimental prototype of concentrating solar power tower system in Saudi Arabia

International Nuclear Information System (INIS)

Abu-Hamdeh, Nidal H.; Alnefaie, Khaled A.

2016-01-01

Highlights: • Article is about designing and building a small scale prototype solar power tower system. • Calculations revealed that 10 heliostats are required to direct incident solar rays. • Design requirements showed that a solar tower of 7 m height should be used. • Storage tanks are cylindrical vessels with height of 1 m and a diameter of 1.5 m each. • The percentage error in the thermal power obtained from this system is about 5.3%. - Abstract: A prototype of a solar power tower system was designed and constructed to produce electricity from solar energy. This prototype of a solar power tower system was constructed and installed at King Abdulaziz University in Saudi Arabia where solar intensity is excessive. Heliostats were implemented to capture the solar rays during daylight. These mirrors are used to direct the solar energy to a solar receiver that is made of alloy steel so that thermal energy is conveyed to a thermal fluid inside the receiver. Based on a detailed selection procedure presented in this article, a final number of ten heliostats were chosen to direct the solar energy to the solar receiver. In addition; two motors were used to control the heliostat rotational and elevation movements. The thermal fluid is a molten salt mixture (which consists of 60% NaNO_3 and 40% KNO_3). Cold and hot storage tanks were manufactured from steel and they were insulated with calcium silicate from all sides. A one-meter high and one and a half-meter cylindrical vessel was adopted for each of the cold and hot tanks. In this article, a detailed design analysis of each component is presented. The thermal power transferred to the water in the heat exchanger as it is heated by the molten salt was measured and found to be 11.26 kW. The thermal power given by the molten salt in the heat exchanger was also measured and found to be 12.31 kW. The design thermal power was 13 kW. The percentage error in the thermal power obtained is about 5.3%.

New technologies for lower-cost design and construction of new nuclear power plants. Annex 20

International Nuclear Information System (INIS)

Ritterbusch, S.E.; Bryan, R.E.; Harmon, D.L.

2002-01-01

Electric Power Research Institute studies indicate that in order to be competitive with gas-fired electric power plant capital costs, new nuclear plant capital cost in the USA must be decreased by at least 35% to 40% relative to costs of some Advanced Light Water Reactors designed in the early 1990s. To address this need, the U. S. Department of Energy is sponsoring three separate projects under its Nuclear Energy Research Initiative. These projects are the Risk-Informed Assessment of Regulatory and Design Requirements for Future Nuclear Power Plants, the Smart Equipment Nuclear Power Plant Program, and the Design, Procure, Construct, Install and Test Program. The goal of the Design-Construction program is reduction of the complete nuclear plant design-procure-construct-install-test cycle schedule and cost. A 3D plant model was combined with a construction schedule to produce a 4D visualization of plant construction, which was then used to analyze plant construction methods. Insights include the need for concurrent engineering, a plant-wide central database, and use of the World-Wide WEB. The goal of Smart Equipment program is to design, develop, and evaluate the methods for implementing smart equipment and predictive maintenance technology. 'Smart' equipment means components and systems that are instrumented and monitored to detect incipient failures in order to improve their reliability. The resulting smart equipment methods will be combined with a more risk-informed regulatory approach to allow plant designers to (1) simplify designs without compromising overall reliability and safety and (2) maintain more reliable plants at lower cost. Initial results show that rotating equipment such as charging pumps would benefit most from smart instrumentation and that the technique of Bayesian Belief Networks would be most appropriate for providing input to a health monitoring system. (author)

Will nuclear power plant standardization reduce the licensing impact on construction

International Nuclear Information System (INIS)

Allen, J.M.; Bingham, W.G.; Keith, D.G.

1976-01-01

The NRC and the nuclear industry have been pursuing standardization quite vigorously in an effort to reduce the cost and schedule for the design and construction of nuclear power plants. The NRC is currently reviewing standard plant applications submitted under each of four standardization options. In addition, the NRC has published Standard Review Plans and Standard Technical Specifications. Although problems exist in the implementation of standardization and in areas unaffected by standardization, each of these standardization methods has the potential to reduce the licensing impact on construction

Practice of knowledge management in Prototype and Plant Development Center (PDC)

International Nuclear Information System (INIS)

Mohamad Safuan Sulaiman; Rapieh Aminuddin; Rosli Darmawan; Mohd Ashhar Khalid

2007-01-01

As reflecting the evolvement and movement of world economy direction, Malaysia move one step a head towards knowledge based economy (K-Economy). The movement indirectly changes the Malaysian Nuclear Agency (Nuclear Malaysia) environment to contribute to the K-Economy in the field of science and technology. Therefore, the practice of knowledge management is slowly introduced to the Nuclear Malaysia community to support the K-Economy. This paper describes the detail of the practice of knowledge management at macro and micro level in an organization. The Prototype and Plant Development Center(PDC) under the Technical Support Division, Technical Service Program has been chosen to be the case study in implementing the practice of knowledge management in Nuclear Malaysia. The main objective of this paper is to introduce the right practice of Knowledge management in an organization and PDC as among the first case for this purpose. (Author)

Nitrogen and COD Removal from Septic Tank Wastewater in Subsurface Flow Constructed Wetlands: Plants Effects.

Science.gov (United States)

Collison, R S; Grismer, M E

2015-11-01

We evaluated subsurface flow (SSF) constructed wetland treatment performance with respect to organics (COD) and nitrogen (ammonium and nitrate) removal from domestic (septic tank) wastewater as affected by the presence of plants, substrate "rock" cation exchange capacity (CEC), laboratory versus field conditions and use of synthetic as compared to actual domestic wastewater. This article considers the effects of plants on constructed wetland treatment in the field. Each constructed wetland system was comprised of two beds (2.6 m long by 0.28 m wide and deep filled with ~18 mm crushed lava rock) separated by an aeration tank connected in series. The lava rock had a porosity of ~47% and a CEC of 4 meq/100 gm. One pair of constructed wetland systems was planted with cattails in May 2008, while an adjacent pair of systems remained un-planted. Collected septic tank or synthesized wastewater was allowed to gravity feed each constructed wetland system and effluent samples were regularly collected and tested for COD and nitrogen species during four time periods spanning November 2008 through June 2009. These effluent concentrations were tested for statistical differences at the 95% level for individual time periods as well as the overall 6-month period. Organics removal from domestic wastewater was 78.8% and 76.1% in the planted and un-planted constructed wetland systems, respectively, while ammonium removal was 94.5% and 90.2%, respectively. Similarly, organics removal from the synthetic wastewater of equivalent strength was 88.8% and 90.1% for planted and un-planted constructed wetland systems, respectively, while ammonium removal was 96.9% and 97.3%, respectively.

Prototype Hanford Surface Barrier: Design basis document

International Nuclear Information System (INIS)

Myers, D.R.; Duranceau, D.A.

1994-11-01

The Hanford Site Surface Barrier Development Program (BDP) was organized in 1985 to develop the technology needed to provide a long-term surface barrier capability for the Hanford Site and other arid sites. This document provides the basis of the prototype barrier. Engineers and scientists have momentarily frozen evolving barrier designs and incorporated the latest findings from BDP tasks. The design and construction of the prototype barrier has required that all of the various components of the barrier be brought together into an integrated system. This integration is particularly important because some of the components of the protective barreir have been developed independently of other barreir components. This document serves as the baseline by which future modifications or other barrier designs can be compared. Also, this document contains the minutes of meeting convened during the definitive design process in which critical decisions affecting the prototype barrier's design were made and the construction drawings

PANDA Muon System Prototype

Science.gov (United States)

Abazov, Victor; Alexeev, Gennady; Alexeev, Maxim; Frolov, Vladimir; Golovanov, Georgy; Kutuzov, Sergey; Piskun, Alexei; Samartsev, Alexander; Tokmenin, Valeri; Verkheev, Alexander; Vertogradov, Leonid; Zhuravlev, Nikolai

2018-04-01

The PANDA Experiment will be one of the key experiments at the Facility for Antiproton and Ion Research (FAIR) which is under construction now in the territory of the GSI Helmholtz Centre for Heavy Ion Research in Darmstadt, Germany. PANDA is aimed to study hadron spectroscopy and various topics of the weak and strong forces. Muon System is chosen as the most suitable technology for detecting the muons. The Prototype of the PANDA Muon System is installed on the test beam line T9 at the Proton Synchrotron (PS) at CERN. Status of the PANDA Muon System prototype is presented with few preliminary results.

PANDA Muon System Prototype

Directory of Open Access Journals (Sweden)

Abazov Victor

2018-01-01

Full Text Available The PANDA Experiment will be one of the key experiments at the Facility for Antiproton and Ion Research (FAIR which is under construction now in the territory of the GSI Helmholtz Centre for Heavy Ion Research in Darmstadt, Germany. PANDA is aimed to study hadron spectroscopy and various topics of the weak and strong forces. Muon System is chosen as the most suitable technology for detecting the muons. The Prototype of the PANDA Muon System is installed on the test beam line T9 at the Proton Synchrotron (PS at CERN. Status of the PANDA Muon System prototype is presented with few preliminary results.

Development and construction of a large TPC prototype for the ILC and study of τ polarisation in τ decays with the ILD detector

International Nuclear Information System (INIS)

Schade, Peter

2009-11-01

This thesis presents two studies which have been made in the framework of the detector development for the International Large Detector (ILD). In the preparation phase for the ILD, prototype studies are performed to develop and optimise the sub-detector technologies which will come into operation. Complementary to these hardware studies, expected physics scenarios are being investigated in full detector simulations. These simulations demonstrate the physics potential of the detector concept and are a benchmark for the detector and the accelerator design. The first part of this thesis gives an introduction to the physics questions addressed to the ILC. Also, the machine and the ILD detector concept are presented. The second part is dedicated to the development and the construction to a large Time Projection Chamber (TPC) prototype (LP). A TPC is foreseen as one of ILD's sub-detectors and shall measure the trajectories of charged particles with an accuracy unprecedented by TPCs operated before. The new prototype offers an infrastructure for the development of modern TPC readout structures which can fulfil the required criteria. Before construction, the design plans of the LP have been optimised for a low material budget of the structure and a very homogeneous drift field. During the manufacturing of the LP, experience with construction techniques has been gained for the construction of the ILD TPC. The third part deals with a simulation study for a polarisation measurement of τ leptons in the process e + e - → τ 1 τ 1 → χ 1 0 χ 1 0 ττ. Here, the τ 1 is the supersymmetric partner of the τ lepton. This simulation study shows the feasibility of the measurement in the chosen SUSY scenario and estimates the accuracy to be expected. Both studies address in particular the track reconstruction capabilities of the ILD detector. Conclusions of the discussed studies and an outlook are presented in part IV. (orig.)

Socio-demographic and economic aspects of nuclear power plant construction and operation

International Nuclear Information System (INIS)

1984-01-01

The proceedings contain 10 papers of which 9 have been inputted in INIS. The papers deal with the economic, social and ecological consequences of the construction of nuclear power plants. Various approaches are listed to the economic evaluation of the said consequences. The question is discussed of the efficiency of investments for the construction of nucliear power plants as are the probiems of sitting large projects. (E.S.)

75 FR 59933 - Specifications and Drawings for Construction of Direct Buried Plant

Science.gov (United States)

2010-09-29

... include new construction units for Fiber-to-the-Home, remove redundant or outdated requirements, and... in Fiber-to-the-Home construction as well as installation methods and materials. In order for... for Construction of Direct Buried Plant AGENCY: Rural Utilities Service, USDA. ACTION: Final rule...

A Study of the potency of construction service industries to support the first nuclear power plant construction in Indonesia

International Nuclear Information System (INIS)

Dharu Dewi; Sriyana

2008-01-01

The study was conducted to identify the potency of construction service industries to participate in nuclear power plant program in Indonesia. The potency is identified by evaluation results of national industries potency in some multinational construction service industries. The research methodology chosen was the survey method by sending questionnaires, visits to National industries, interview, and literature study. The data collection technique was sampling purposive. Data can be obtained from both primary and secondary data. The study results showed that the performance of construction service industries to support the NPP program must be increased through the selection of competent human resources, reliable equipment and an effective and efficient project management system, so that they can be expected to play necessary role in the nuclear power plant construction in Indonesia. (author)

The Northeast Utilities generic plant computer system

International Nuclear Information System (INIS)

Spitzner, K.J.

1980-01-01

A variety of computer manufacturers' equipment monitors plant systems in Northeast Utilities' (NU) nuclear and fossil power plants. The hardware configuration and the application software in each of these systems are essentially one of a kind. Over the next few years these computer systems will be replaced by the NU Generic System, whose prototype is under development now for Millstone III, an 1150 Mwe Pressurized Water Reactor plant being constructed in Waterford, Connecticut. This paper discusses the Millstone III computer system design, concentrating on the special problems inherent in a distributed system configuration such as this. (auth)

Changing priorities of codes and standards -- quality engineering: Experiences in plant construction, maintenance, and operation

International Nuclear Information System (INIS)

Antony, D.D.; Suleski, P.F.; Meier, J.C.

1994-01-01

Application of the ASME Code across various fossil and nuclear plants necessitates a Company approach adapted by unique status of each plant. This arises from State Statutes, Federal Regulations and consideration of each plant's as-built history over a broad time frame of design, construction and operation. Additionally, the National Board Inspection Code accompanies Minnesota Statutes for plants owned by Northern States Power Company. This paper addresses some key points on NSP's use of ASME Code as a principal mechanical standard in plant design, construction and operation. A primary resource facilitating review of Code provisions is accurate status on current plant configuration. As plant design changes arise, the Code Edition/Addenda of original construction and installed upgrades or replacements are considered against available options allowed by current standards and dialog with the Jurisdictional Authority. Consistent with the overall goal of safe and reliable plant operation, there are numerous Code details and future needs to be addressed in concert with expected plant economics and planned outages for implementation. The discussion begins in the late 60's with new construction of Monticello and Prairie Island (both nuclear), through Sherburne County Units 1 through 3 (fossil), and their changes, replacements or repairs as operating plants

Experience in the construction of a spent nuclear fuel reprocessing plant

International Nuclear Information System (INIS)

Yamashita, Hiroshi

1976-01-01

The construction and operation of a reprocessing plant was first published in 1956. The Reprocessing Expert Committee of AEC was established in 1959, and the preliminary design was finished in 1964 by NCP of Britain. The detailed design was completed in 1969 by SGN of France, and the training of operators was carried out in parallel with this in France. The results of the safety investigation was approved in Jan. 1970, and the construction was started in June 1971. The site of the reprocessing plant is the eastern part of the Tokai Establishment of PNC. The process adopted is the wet Purex process having been established in large practical plants. The treating capacity is 0.7 t/day. The main processes are acceptance and storage, mechanical treatment, and chemical treatment. The reprocessing facilities comprise the main shop, the analysis station, the main exhaust stack, the decontamination station, the solid waste store, the sea discharge pipe, and other incidental facilities. The construction works were about 7 months behind the schedule when the water flow test was finished. The chemical test was finished in March, 1975, and the uranium test is in progress since Sept., 1975. The problems for future are the developments of effective waste treatment and storing techniques, and the researches have been carried out by PNC. The construction project of the second plant is urgently required, since it takes 10 years from planning to operation. (Kako, I.)

Development of Advanced Concept for Shortening Construction Period of ABWR Plant

International Nuclear Information System (INIS)

Hiroshi Ijichi; Toshio Yamashita; Masahiro Tsutagawa; Hiroya Mori; Nobuaki Ooshima; Jun Miura; Minoru Kanechika; Nobuaki Miura

2002-01-01

Construction of a nuclear power plant (NPP) requires a very long period because of large amount of construction materials and many issues for negotiation among multiple sections. Shortening the construction period advances the date of return on an investment, and can also result in reduced construction cost. Therefore, the study of this subject has a very high priority for utilities. We achieved a construction period of 37 months from the first concrete work to fuel loading (F/L) (51.5 months from the inspection of the foundation (I/F) to the start of commercial operation (C/O)) at the Kashiwazaki-Kariwa NPPs No. 6 and 7 (KK-6/7), which are the first ABWR plants in the world. At TEPCO's next plant, we think that a construction period of less than 36 months (45 months from I/F to C/O) can be realized based on conventional methods such as early start of equipment installation and blocking of equipment to be brought in advance. Furthermore, we are studying the feasibility of a 21.5-month construction period (30 months from I/F to C/O) with advanced ideas and methods. The important concepts for a 21.5-month construction period are adoption of a new building structure that is the steel plate reinforced concrete (SC) structure and promotion of extensive modularization of equipment and building structure. With introducing these new concepts, we are planning the master schedule (M/S) and finding solutions to conflicts in the schedule of area release from building construction work to equipment installation work (schedule-conflicts.) In this report, we present the shortest construction period and an effective method to put it into practice for the conventional general arrangement (GA) of ABWR. In the future, we will continue the study on the improvement of building configuration and arrangements, and make clear of the concept for large composite modules of building structures and equipment. (authors)

Study concerning the erection within the precincts of INR Pitesti of TRIGA prototype nuclear heating plant

International Nuclear Information System (INIS)

Ciocanescu, M.; Ionescu, M.; Constantin, L.

1993-01-01

This paper presents the problems of nuclear plant energy production as heating source for industrial processes and urban district heating. The study is based on the TRIGA concept due to some of its advantages in comparison with other concepts. The system solutions for a prototype implementation and the aspects of the economical and financial efficiency are outlined. The conclusion is drawn that the TRIGA 53 MWt-reactor is suitable to meet the heating needs of urban and industrial heating systems in this country

Information management system for design, construction and operation of nuclear power plants

International Nuclear Information System (INIS)

Bolch, M.C.; Jones, C.R.

1990-01-01

This paper describes the principal requirements and features of a computerized information management system (IMS) believed to be a necessary part of the program to design, build and operate the next generation of nuclear power plants in the United States. This way a result of extensive review and input from an industry group studying future nuclear power plant construction improvements. The needs of the power plant constructor, owner and operator for such a computerized technical data base are described in terms of applications and scope and timing of turnover of the IMS by the plant designer. The applications cover the full life cycle of the plant including project control, construction activities, quality control, maintenance and operation. The scope of the IMS is also described in terms of the technical data to be included, hardware and software capabilities and training. The responsibilities of the plant designer for developing the IMS and generating the technical data base is defined as part of the plant process. The requirements to be met include a comprehensive plant data model and computer system hardware and software

Information management system for design, construction and operation of nuclear power plants

Energy Technology Data Exchange (ETDEWEB)

Bolch, M.C. (Duke Power Co. (US)); Jones, C.R. (S. Levy Inc. (US))

1990-01-01

This paper describes the principal requirements and features of a computerized information management system (IMS) believed to be a necessary part of the program to design, build and operate the next generation of nuclear power plants in the United States. This way a result of extensive review and input from an industry group studying future nuclear power plant construction improvements. The needs of the power plant constructor, owner and operator for such a computerized technical data base are described in terms of applications and scope and timing of turnover of the IMS by the plant designer. The applications cover the full life cycle of the plant including project control, construction activities, quality control, maintenance and operation. The scope of the IMS is also described in terms of the technical data to be included, hardware and software capabilities and training. The responsibilities of the plant designer for developing the IMS and generating the technical data base is defined as part of the plant process. The requirements to be met include a comprehensive plant data model and computer system hardware and software.

A Computuerized Operator Support System Prototype

Energy Technology Data Exchange (ETDEWEB)

Thomas, Ken [Idaho National Lab. (INL), Idaho Falls, ID (United States); Boring, Ronald [Idaho National Lab. (INL), Idaho Falls, ID (United States); Lew, Roger [Idaho National Lab. (INL), Idaho Falls, ID (United States); Ulrich, Tom [Idaho National Lab. (INL), Idaho Falls, ID (United States); Villim, Richard [Idaho National Lab. (INL), Idaho Falls, ID (United States)

2013-11-01

A report was published by the Idaho National Laboratory in September of 2012, entitled Design to Achieve Fault Tolerance and Resilience, which described the benefits of automating operator actions for transients. The report identified situations in which providing additional automation in lieu of operator actions would be advantageous. It recognized that managing certain plant upsets is sometimes limited by the operator’s ability to quickly diagnose the fault and to take the needed actions in the time available. Undoubtedly, technology is underutilized in the nuclear power industry for operator assistance during plant faults and operating transients. In contrast, other industry sectors have amply demonstrated that various forms of operator advisory systems can enhance operator performance while maintaining the role and responsibility of the operator as the independent and ultimate decision-maker. A computerized operator support system (COSS) is proposed for use in nuclear power plants to assist control room operators in addressing time-critical plant upsets. A COSS is a collection of technologies to assist operators in monitoring overall plant performance and making timely, informed decisions on appropriate control actions for the projected plant condition. The COSS does not supplant the role of the operator, but rather provides rapid assessments, computations, and recommendations to reduce workload and augment operator judgment and decision-making during fast-moving, complex events. This project proposes a general model for a control room COSS that addresses a sequence of general tasks required to manage any plant upset: detection, validation, diagnosis, recommendation, monitoring, and recovery. The model serves as a framework for assembling a set of technologies that can be interrelated to assist with each of these tasks. A prototype COSS has been developed in order to demonstrate the concept and provide a test bed for further research. The prototype is based

A Computuerized Operator Support System Prototype

Energy Technology Data Exchange (ETDEWEB)

Thomas, Ken [Idaho National Lab. (INL), Idaho Falls, ID (United States); Boring, Ronald [Idaho National Lab. (INL), Idaho Falls, ID (United States); Lew, Roger [Idaho National Lab. (INL), Idaho Falls, ID (United States); Ulrich, Tom [Idaho National Lab. (INL), Idaho Falls, ID (United States); Villim, Richard [Idaho National Lab. (INL), Idaho Falls, ID (United States)

2013-08-01

A report was published by the Idaho National Laboratory in September of 2012, entitled Design to Achieve Fault Tolerance and Resilience, which described the benefits of automating operator actions for transients. The report identified situations in which providing additional automation in lieu of operator actions would be advantageous. It recognized that managing certain plant upsets is sometimes limited by the operator’s ability to quickly diagnose the fault and to take the needed actions in the time available. Undoubtedly, technology is underutilized in the nuclear power industry for operator assistance during plant faults and operating transients. In contrast, other industry sectors have amply demonstrated that various forms of operator advisory systems can enhance operator performance while maintaining the role and responsibility of the operator as the independent and ultimate decision-maker. A computerized operator support system (COSS) is proposed for use in nuclear power plants to assist control room operators in addressing time-critical plant upsets. A COSS is a collection of technologies to assist operators in monitoring overall plant performance and making timely, informed decisions on appropriate control actions for the projected plant condition. The COSS does not supplant the role of the operator, but rather provides rapid assessments, computations, and recommendations to reduce workload and augment operator judgment and decision-making during fast-moving, complex events. This project proposes a general model for a control room COSS that addresses a sequence of general tasks required to manage any plant upset: detection, validation, diagnosis, recommendation, monitoring, and recovery. The model serves as a framework for assembling a set of technologies that can be interrelated to assist with each of these tasks. A prototype COSS has been developed in order to demonstrate the concept and provide a test bed for further research. The prototype is based

Nuclear power plants: data for decisions. Construction status report: data as of July 31, 1977

International Nuclear Information System (INIS)

1977-08-01

This management report is designed to provide the necessary information for monitoring the progress of construction of nuclear power plants. It provides data for synchronizing the licensing process with predicted fuel loading dates, as well as providing a central federal government report for commercial reactor construction. It utilizes data collected from the utilities sponsoring these projects and the Office of Inspection and Enforcement, NRC, and analyzed by the Office of Management Information and Program Control in the implementation of Management Information Systems. The status of the 91 plants authorized to engage in construction activities in Regions I thru V is summarized in this document. This total includes (4) plants with construction exemptions, and (10) plants with Limited Work Authorization Permits

Construction and beam-tests of silicon-tungsten prototype modules for the CMS High Granularity Calorimeter for HL-LHC

CERN Document Server

Quast, Thorben

2017-01-01

As part of its HL-LHC upgrade program, CMS is developing a High Granularity Calorimeter (HGCAL) to replace the existing endcap calorimeters. The HGCAL will be realised as a sampling calorimeter, including an electromagnetic compartment comprising 28 layers of silicon pad detectors with pad areas of 0.5 - 1.0 cm$^2$ interspersed with absorbers.Prototype modules, based on 6-inch hexagonal silicon pad sensors with 128 channels, have been constructed and include many of the features required for this challenging detector. In 2016, beam tests of sampling configurations made from these modules have been conducted both at FNAL and at CERN using the Skiroc2 front-end chip (designed for the CALICE experiment for ILC). This year, the setup is extended with CALICE's AHCAL prototype and it is further tested in dedicated beam tests at CERN. There, the new Skiroc2-CMS front-end chip is used for the first time.We present final results from our studies in 2016, including noise performance, calibration with MIPs, energy and p...

Construction and 60 kV tests of the prototype pulser for the LHC injection kicker system

CERN Document Server

Barnes, M J; Carlier, E; Ducimetière, L; Schröder, G; Vossenberg, Eugène B

1999-01-01

The European Laboratory for Particle Physics (CERN) is constructing the Large Hadron Collider (LHC). Two counter-rotating proton beams will be injected into the LHC at an energy of 450 GeV by two kicker magnet systems, producing magnetic field pulses of approximately 900 ns rise time and 6.6 mu s flat top duration with a ripple of less than +or-0.5Both injection systems are composed of 4 travelling wave kicker magnets of 2.17 m length each, powered by pulse forming networks (PFNs). To achieve the high-required kick strength of 1.2 Tm, for a compact and cost efficient design, a characteristic impedance of 5 Ohms has been chosen. The design strategy for the magnets and generators has been defined after detailed analysis of existing systems. The electrical circuit has been optimised using the circuit analysis software PSpice. Most known parasitics have been modelled. A prototype PFN has been constructed at CERN and successfully tested at 60 kV. A calibration procedure has been developed and utilised for obtainin...

Construction and operation of biogas plants. Bau und Betrieb von Biogasanlagen

Energy Technology Data Exchange (ETDEWEB)

Koenig, F. von

1985-01-01

Biogas utilisation in agriculture has increased considerably as a consequence of the energy crisis. So far, energy production was the most important aspect, and the high-quality natural fertilizer offered by the fermentation residues was commonly neglected. This fertilizer is an effective substitute for commercial fertilizers and thus contributes to the reduction of environmental pollution. The book discusses the chemical and biological mechanisms, the criteria of selection for plants and materials, optimum gas production techniques, uses of the product gas, and the advantages and properties of the biofertilizer produced. Planning procedures, design, construction, function and performance of several biogas production plants now in operation are described. Hints are given for do-it-yourself construction, as are cost-benefit calculations and decision aids for construction.

AGS booster prototype magnets

International Nuclear Information System (INIS)

Danby, G.; Jackson, J.; Lee, Y.Y.; Phillips, R.; Brodowski, J.; Jablonski, E.; Keohane, G.; McDowell, B.; Rodger, E.

1987-01-01

Prototype magnets have been designed and constructed for two half cells of the AGS Booster. The lattice requires 2.4m long dipoles, each curved by 10 0 . The multi-use Booster injector requires several very different standard magnet cycles, capable of instantaneous interchange using computer control from dc up to 10 Hz

Major factors influencing craft productivity in nuclear power plant construction

International Nuclear Information System (INIS)

Borcherding, J.D.; Sebastian, S.J.

1980-01-01

This paper reports on a research study whose objective was to determine the most influential factors adversely affecting craft productivity in nuclear power plant construction from the perspective of the tradesmen employed at the sites. Data were collected through the use of a questionnaire survey and group interview sessions, predominantly with workmen, at six nuclear power plant construction projects. Craftsmen were chosen as the major data base because of their awareness of how their time would actually be spent on the project. Topics considered include the factors influencing craft productivity, material availability, redoing work, crew interfacing, overcrowded work areas, instruction time, inspection delays, craft turnover, craft absenteeism, foreman changes, foreman incompetence, engineering design lead time, comprehensive scheduling of the design function, the responsibility of the utility, value engineering, plant standardization, the effective utilization of the planning and scheduling system, and the labor-management committee

Remote maintenance lessons learned on prototypical reprocessing equipment

International Nuclear Information System (INIS)

Kring, C.T.; Schrock, S.L.

1990-01-01

A major objective of the Consolidated Fuel Reprocessing Program at the Oak Ridge National Laboratory is to develop and demonstrate the technology required to reprocess spent nuclear fuel. The Fuel Recycle Division, over the past 16 years, has undertaken this objective by designing and testing prototypical hardware representing essentially every major equipment item currently included in most fuel reprocessing plant conceptual designs. These designs are based on total remote maintenance to increase plant availability and reduce radiation exposure to plant operators. The designs include modular equipment to facilitate maintainability and the remote manipulation necessary to accomplish maintenance tasks. Prototypic equipment has been installed and tested in a cold mock-up of a reprocessing hot cell, called the remote operations and maintenance demonstration facility. The applied maintenance concept utilizes the dexterity and mobility of bridge-mounted, force-reflecting servomanipulators. Prototypic processing equipment includes a remote disassembly system, a remote shear system, a rotary dissolver, a remote automated sampler system, removable equipment racks to support chemical process equipment items, and the advanced servomanipulators. Each of these systems and a brief description of functions are discussed

Technology programs in support of advanced light water reactor plants: Construction

International Nuclear Information System (INIS)

Eichen, E.P.

1989-10-01

Stone ampersand Webster Engineering Corporation (SWEC) is conducting several independent, yet interrelated, studies of light water reactor plants to improve constructibility and quality, to reduce costs and schedule duration, and to simplify design. This document discusses construction approaches. 77 refs., 5 figs., 6 tabs

Design and construction of a prototype for the obtention of 32 P

International Nuclear Information System (INIS)

Alanis M, J.

2003-12-01

In the National Institute of Nuclear Research (ININ) it was designed, built and proved a prototype to obtain 32 P in form of H 3 32 PO 4 , starting from irradiated Sα. The beginning of the prototype it is based on a distillation system in dry of the Sα in nitrogen atmosphere, and in the formation of the ion 32 PO 4 3- in acid solution. Due to the handling of radioactive material during the process, the prototype is inside a hot cell and it has a cylindrical oven that opens up lengthwise to the half, with controller of temperature and with a system of empty air for to transport reagents and products. The air-vacuum system is provided of filters and traps. The tests showed a recovery from 14 to 15% of the activity obtained during the irradiation. (Author)

International construction trends for power plants

International Nuclear Information System (INIS)

Armor, A.F.

1991-01-01

In this review of trends in new, worldwide plant construction it is apparent that the technologies being applied are often geared to the cost of money issue. In an era when interest rates can fluctuate widely, particularly in Third World countries, the need to put new power plants on-line quickly has become a key issue. For example, this has largely triggered the move to smaller, more dispersed plants, with unit sizes 400 MW and below, compared with the 1,000 MW + sizes of 10-20 years ago. It has also renewed the emphasis on modular methods of building components, and on innovative transportation procedures. It has given support to the packaged power plants, such as PFBC, which can be largely pre-assembled. In the US, it has spawned a new infrastructure of independent constructors and power generators, who have partially lifted the burden of new plant financing from the shoulders of the utilities. Yet, national needs are not always the same. Fuels may or may not be indigenous. Environmental restrictions are nationally, or even locally, imposed. Government subsidies and strategic needs can override the short-term objectives. This paper briefly surveys current approaches to new generating plants in some key areas of the world. One aspect of electric power generation seems clear. In terms of power consumption, the world is on the move again - not only in third world countries, but also in the developed nations as the memories of the oil embargo of 15 years ago fade. Trends are discussed for the US, Japan, the rest of Asia, South Africa, Western Europe, Russia, and Eastern Europe

Construction and test of the final CMS Barrel Drift Tube Muon Chamber prototype

Energy Technology Data Exchange (ETDEWEB)

Aguilar-Benitez, M.; Alberdi, J.; Arneodo, M.; Banicz, K.; Benettoni, M.; Benvenuti, A.; Bethke, S.; Cerrada, M. E-mail: cerrada@ciemat.es; Cirio, R.; Colino, N.; Conti, E.; Dallavalle, M.; Daniel, M.; Dattola, D.; Daudo, F.; De Giorgi, M.; Dosselli, U.; Fanfani, A.; Fanin, C.; Fouz, M.C.; Gasparini, F.; Gasparini, U.; Giacomelli, P.; Giordano, V.; Gonella, F.; Grandi, C.; Guaita, P.; Guerzoni, M.; Lacaprara, S.; Lippi, I.; Marcellini, S.; Marin, J.; Martinelli, R.; Maselli, S.; Meneguzzo, A.; Migliore, E.; Mocholi, J.; Monaco, V.; Montanari, A.; Montanari, C.; Odorici, F.; Oller, J.C.; Paoletti, S.; Passaseo, M.; Pegoraro, M.; Peroni, C.; Puerta, J.; Reithler, H.; Romero, A.; Romero, L.; Ronchese, P.; Rossi, A.M.; Rovelli, T.; Sacchi, R.; Salicio, J.M.; Staiano, A.; Steinbeck, T.; Torassa, E.; Travaglini, R.; Ventura, L.; Ventura, S.; Vitelli, A.; Voetee, F.; Wegner, M.; Willmott, C.; Zotto, P.; Zumerle, G

2002-03-21

A prototype of the CMS Barrel Muon Detector incorporating all the features of the final chambers was built using the mass production assembly procedures and tools. The performance of this prototype was studied in a muon test beam at CERN and the results obtained are presented in this paper.

135 tf climbing crane for the construction of large scale plants

International Nuclear Information System (INIS)

1981-01-01

Development of a larger capacity, wider working radius and higher lift climbing crane was in demand since the large block construction method become common in plant construction. At first, scaling up of the conventional climbing crane was planned. But, it turned out that the deflection at the top of the jib would cause the load to drift at takeoff in crane operation. Therefore, the crane was newly designed to solve the problem. Some of its advantage are as follows. (1) This crane can be used as either a climbing or a nonclimbing type depending on installation locations and objective plants. (2) Accurate and easy operation is achieved because of little deflection at the top of the jib. (3) Efficient crane operation is possible through high speed hoisting and slewing motions in frequent auxiliary hoisting operations. (4) The construction time can be shortened by adopting pin joints between the blocks and by reducing the number of assembling parts at the site. A nonclimbing type crane is now in operation at the nuclear power plant in Kashiwazaki and a climbing type will be in operation at the nuclear power plant in Fukushima this year. The report presents an outline of the specifications, structures and advantages. (author)

Current status of construction of nuclear power plants No. 7, No. 8 in Korea

International Nuclear Information System (INIS)

Sug, S.H.

1979-01-01

The up-to-date accomplishment and future work in the construction of nuclear power plants in Korea are outlined. The scope of the construction project of the No. 7 and No. 8 power plants, selection of the suppliers of the main instruments, assessment of the planning, architecture, engineering, construction fund, procurement of nuclear fuel, and the necessities of home production of various nuclear materials are briefly summarized. (author)

AGS Booster prototype magnets

Energy Technology Data Exchange (ETDEWEB)

Danby, G.; Jackson, J.; Lee, Y.Y.; Phillips, R.; Brodowski, J.; Jablonski, E.; Keohane, G.; McDowell, B.; Rodger, E.

1987-03-19

Prototype magnets have been designed and constructed for two half cells of the AGS Booster. The lattice requires 2.4m long dipoles, each curved by 10/sup 0/. The multi-use Booster injector requires several very different standard magnet cycles, capable of instantaneous interchange using computer control from dc up to 10 Hz.

Technology programs in support of advanced light water reactor plants: Construction

International Nuclear Information System (INIS)

Eichen, E.P.

1987-12-01

Stone ampersand Webster Engineering Corporation (SWEC) is conducting several independent, yet interrelated, studies of light water reactor plants to improve constructibility and quality, to reduce costs and schedule durations, and to simplify design. This document discusses successes and problems in construction. 49 refs., 16 figs., 8 tabs

Nuclear power plants. The market for services, retrofitting, construction of new plants and dismantling of older plants in Europe through 2030

International Nuclear Information System (INIS)

Briese, Dirk; Hoemske, Tom

2010-01-01

The power plant scene in Europe is characterized by new power plant projects and retrofitting projects everywhere. This is due to the ageing of existing power plants and to increasing energy demand. Currently, there are projects for 48 power plant units with an installed capacity of 70 GW. According to a study of the nuclear power plant sector, about 16 GW will probably be constructed prior to 2030. The reference scenario presented in this article assumes a dynamic increase of 15 thousand million Euros per annum through 2016/2018. (orig.)

Using game technologies to improve the safety of construction plant operations.

Science.gov (United States)

Guo, Hongling; Li, Heng; Chan, Greg; Skitmore, Martin

2012-09-01

Many accidents occur world-wide in the use of construction plant and equipment, and safety training is considered by many to be one of the best approaches to their prevention. However, current safety training methods/tools are unable to provide trainees with the hands-on practice needed. Game technology-based safety training platforms have the potential to overcome this problem in a virtual environment. One such platform is described in this paper - its characteristics are analysed and its possible contribution to safety training identified. This is developed and tested by means of a case study involving three major pieces of construction plant, which successfully demonstrates that the platform can improve the process and performance of the safety training involved in their operation. This research not only presents a new and useful solution to the safety training of construction operations, but illustrates the potential use of advanced technologies in solving construction industry problems in general. Copyright © 2011 Elsevier Ltd. All rights reserved.

Design and Construction of a Beam Position Monitor Prototype for the Test Beam Line of the CTF3

CERN Document Server

Garcia Garrigos, Juan Jose

2008-01-01

A prototype of Beam Position Monitor (BPM) for the Test Beam Line (TBL) of the 3rd CLIC Test Facility (CTF3) at CERN has been designed and constructed at IFIC in collaboration with the CERN CTF3 team. The design is a scaled version of the BPMs of the CTF3 linac. The design goals are a resolution of 5 μm, an overall precision of 50 μm, in a circular vacuum chamber of 24 mm, in a frequency bandwidth between 10 kHz and 100MHz.The BPMis an inductive type BPM. Beam positions are derived from the image current created by a high frequency electron bunch beam into four electrodes surrounding the vacuum chamber. In this work we describe the mechanical design and construction, the description of the associated electronics together with the first calibration measurements performed in a wire test bench at CERN.

Wind Power Plants Fundamentals, Design, Construction and Operation

CERN Document Server

Twele, Jochen

2012-01-01

Wind power plants teaches the physical foundations of usage of Wind Power. It includes the areas like Construction of Wind Power Plants, Design, Development of Production Series, Control, and discusses the dynamic forces acting on the systems as well as the power conversion and its connection to the distribution system. The book is written for graduate students, practitioners and inquisitive readers of any kind. It is based on lectures held at several universities. Its German version it already is the standard text book for courses on Wind Energy Engineering but serves also as reference for practising engineers.

Function-oriented display system: background and first prototypes

International Nuclear Information System (INIS)

Andresen, Gisle; Friberg, Maarten; Teigen, Arild; Pirus, Dominique

2004-04-01

The objective of the function-oriented displays and alarm project is to design, implement and evaluate Human System Interfaces (HSI) based on a function-oriented design philosophy. Function-oriented design is an approach for designing HSIs where the plant's functions, identified through a function analysis, are used for determining the content, organisation, and management of displays. The project has used the 'FITNESS approach', originally developed by EDF in France, as a starting point. FITNESS provides an integrated display system consisting of process operating displays, operating procedures, alarms and trend displays - all based on a functional decomposition of the plant. So far, two prototypes have been implemented on the FRESH PWR simulator in HAMMLAB. The first prototype focused on the condensate pumps. Three process operating displays representing functions at different levels of the functional hierarchy were implemented. Computerised startup and shutdown procedures for the condensate pumps function were also implemented. In the second prototype, the scope was increased to cover the main feedwater system. The displays of the first prototype were redesigned and additional displays were created. In conclusion, the first phase of the project has been completed successfully, and we are now ready to enter the second phase. In the second phase, the scope of the prototype will be increased further to include the steam-generators and function-oriented disturbance operating procedures. The prototype will be evaluated in a user test conducted later in 2004. (Author)

Concerning the structure of occupational accidents involving construction workers in the erection of nuclear power plants

International Nuclear Information System (INIS)

Nowak, B.; Roebenack, K.D.

1991-01-01

An investigation of 561 occupational accidents involving construction workers which took place during the construction of nuclear power plants failed to show any significant deviation in comparison with general construction as regards process classification, classification of accidents according to occupation and situation, and accidents severity. Occupational accidents which are typial for nuclear power plant construction are a rare exception. (orig.) [de

The analysis of energy-time sequences in the nuclear power plants construction

International Nuclear Information System (INIS)

Milivojevic, S.; Jovanovic, V.; Riznic, J.

1983-01-01

The current nuclear energy development pose many problems; one of them is nuclear power plant construction. They are evaluated energy and time features of the construction and their relative ratios by the analysis of available data. The results point at the reached efficiency of the construction and, in the same time, they are the basis for real estimation of energy-time sequences of the construction in the future. (author)

Financial qualifications review of applicants for nuclear power plant construction permits

International Nuclear Information System (INIS)

Hendrickson, P.L.; Mullen, M.F.; Carr, D.B.

1988-09-01

The NRC and its predecessor the AEC have had a regulatory requirement since 1956 that utilities seeking a construction permit for a nuclear power plant be financially qualified to construct and operate the plant. Several amendments to the requirements were made over the years including an attempt in 1982 to drop financial qualification review for electric utilities. This attempt was subsequently found invalid by a federal court. Nevertheless, financial qualification reviews consume significant amounts of NRC staff time and time at Atomic Safety and Licensing Board hearings. The analysis reported in this study was conducted to determine whether there is any empirical evidence of a relationship between a utility's financial health at the time of its construction permits application and the subsequent safety performance of the operating plant. The principal financial measures used to test for this relationship were bond rating, interest coverage ratio, debt/asset ratio, debt/equity ratio, and rate of return on equity. The principal safety measure was the long-term average of the scores assigned the utility in four key areas by the NRC under the Systematic Assessment of Licensee Performance program. The results of the analysis showed no evidence of a relationship between financial health at the time of the construction permit and subsequent safety performance. 7 refs., 16 figs., 4 tabs

Building technology on construction site of nuclear power plant at Zaporozh'e

Energy Technology Data Exchange (ETDEWEB)

Dusek, R; Matyas, V [Vodni Stavby, Prague (Czechoslovakia)

1981-12-01

Basic data and technical and economic indexes are shown for a WWER 1000 nuclear power plant being built 120 km off Zaporozh'e (USSR). The schedule of construction and the choice of the means of mechanization used for building work are reported. Discussed are building machines used, the location of assembly cranes of the main unit, the design and the building technology of the reactor part, the engine house, deisel generator station, the special operations building, the use of concrete and steel units in the building, and the procurement of materials for the construction. The knowledge gained from the building of the power plant will be applied in the CSSR in the building of 1000 MW unit power plants.

Comparison of grey water treatment performance by a cascading sand filter and a constructed wetland.

Science.gov (United States)

Kadewa, W W; Le Corre, K; Pidou, M; Jeffrey, P J; Jefferson, B

2010-01-01

A novel unplanted vertical flow subsurface constructed wetland technology comprising three shallow beds (0.6 m length, 0.45 m width and 0.2 m depth) arranged in a cascading series and a standard single-pass Vertical Flow Planted Constructed Wetland (VFPCW, 6 m² and 0.7 m depth) were tested for grey water treatment. Particular focus was on meeting consent for published wastewater reuse parameters and removal of anionic surfactants. Treatment performance at two hydraulic loading rates (HLR) of 0.08, and 0.17 m³ m⁻² d⁻¹ were compared. Both technologies effectively removed more than 90% turbidity and more than 96% for organics with the prototype meeting the most stringent reuse standard of < 2 NTU and <10 mg/L. However, surfactant removal in the VFPCW was higher (76-85%) than in the prototype which only achieved more than 50% removal at higher loading rate. Generally, the prototype performed consistently better than the VFPCW except for surfactant removal. However, at higher loading rates, both systems did not meet the reuse standard of <1 mg L⁻¹ for anionic surfactants. This observation confirms that shallow beds provide a more oxidised environment leading to higher BOD₅ and COD removals. Presence of plants in the VFPCW led to higher anionic surfactant removal, through increased microbial and sorption processes.

Quality assurance during site construction of nuclear power plants

International Nuclear Information System (INIS)

1981-01-01

This Safety Guide provides requirements and recommendations related to the establishment and implementation of a quality assurance programme for the site construction activities at nuclear power plants. These include activities such as fabricating, erecting, installing, handling, storing, cleaning, flushing, inspecting, testing, modifying, repairing, and maintaining

Cockroft Walton accelerator prototype

International Nuclear Information System (INIS)

Hutapea, Sumihar.

1976-01-01

Prototype of a Cockroft Walton generator using ceramic and plastic capacitors is discussed. Compared to the previous generator, the construction and components are much more improved. Pralon is used for the high voltage insulation column and plastic is used as a dielectric material for the high voltage capacitor. Cockroft Walton generator is used as a high tension supply for an accelerator. (author)

Construction and beam-tests of silicon-tungsten prototype modules for the CMS High Granularity Calorimeter for HL-LHC

Science.gov (United States)

Quast, Thorben

2018-02-01

As part of its HL-LHC upgrade program, CMS is developing a High Granularity Calorimeter (HGCAL) to replace the existing endcap calorimeters. The HGCAL will be realised as a sampling calorimeter, including an electromagnetic compartment comprising 28 layers of silicon pad detectors with pad areas of 0.5-1.0 cm2 interspersed with absorbers. Prototype modules, based on 6-inch hexagonal silicon pad sensors with 128 channels, have been constructed and include many of the features required for this challenging detector. In 2016, beam tests of sampling configurations made from these modules have been conducted both at FNAL and at CERN using the Skiroc2 front-end ASIC (designed by the CALICE collaboration for ILC). In 2017, the setup has been extended with CALICE's AHCAL prototype, a scinitillator based sampling calorimeter, and it was further tested in dedicated beam tests at CERN. There, the new Skiroc2-CMS front-end ASIC was used for the first time. We highlight final results from our studies in 2016, including position resolution as well as precision timing-measurements. Furthermore, the extended setup in 2017 is discussed and first results from beam tests with electrons and pions are shown.

Rapid Prototyping with Fourth Generation Systems - an Empirical Study

DEFF Research Database (Denmark)

Grønbæk, Kaj

1989-01-01

Discusses experiences on the development and use of horizontal and vertical prototypes. Explains the difference. Resolves that horizontal prototypes can be developed with 'little effort', but end users are reluctant to become involved in the development process. Contrastingly resolves that vertical...... prototypes appear to stimulate constructive response. Reasons that developers should be aware of the tacit knowledge which plays an important part in users' work practices and should be involved early in the development process. Proposes three techniques to meet the requirements – participation, simulation...

Abstract of articles presented at the seminar of investigating the construction of nuclear power plant in Iran

International Nuclear Information System (INIS)

Hariri, A.; Khonsari Moosavi, R.; Shoai-Naini, J.; Motamedi, M.A.

1982-01-01

Under five subtitles papers had been presented to the seminar of investigating the construction of nuclear power plant held at Isfahan by Atomic Energy Organization of Iran (AEOI). 1.The necessity of constructing nuclear power plants in Iran with relation to the development of nuclear technology. 2.Seven articles survey the problem of fuel cycling and the potentiallity of AEOI in this field. 3. Four papers allocate to the technology of nuclear safety and radiation protection. 4.Three papers evaluate technical and scientific capabitities of AEOI for constructing nuclear power plants, and two paper about planning and training man power with an aim toward construction of nuclear power plants

Meditation on the construction of exemplar plant for briquetted coal gasification

Energy Technology Data Exchange (ETDEWEB)

Zhou Kuiyi [China National Coal Industry Import and Export Corporation, Beijing (China)

1997-12-31

China uses a considerable amount of anthracite, but the fines from anthracite mining are not sufficiently used. This project involved the construction of a plant for the manufacture of anthracite briquettes under high pressure, for use in gasification plants. The characteristics of the coals used and the types of briquette formed are described. 2 tabs.

Fabrication and testing history prototypes and production units

Energy Technology Data Exchange (ETDEWEB)

1954-09-01

From April, 1951 to Aug, 1954, New York Shipbuilding Corp. carried out a subcontract with E.I. du Pont de Nemours & Company that was without parallel in the shipyard`s history. The work, designated the NYX Project for reasons of security, was vital to the operations of the Savannah River Plant, Aiken, S.C., which was then being designed and constructed by du Pont for the Atomic Energy Commission. It consisted of three broad parts: developmental and experimental work; fabrication and testing of a prototype unit; fabrication of production units. Five production units were ultimately built, one of them converted from the prototype. All were fabricated from stainless steel, and involved welding techniques, control of thermal distortion and tolerances never previously attempted on assemblies of comparable size. Du Pont`s technical experience and the background of New York Ship in heavy construction, particularly in the fabrication of naval gun turrets, were combined from the outset to resolve the difficult fabrication problems that occurred almost daily. Representatives of both companies worked together as a team in the shops and at supervisory levels to an unprecedented extent. The report is intended primarily to summarize New York Ship`s part in the project, but also includes some of du Pont`s activities since the work of the two organizations was so interrelated. Because of the scope of the program, it will not always be possible to provide detailed information, but rather to record what happened in general terms. Where the reader desires more specific data, he should refer to original plans and records, including various reports compiled during the course of the project.

Biogas plants: Design, construction and operation

International Nuclear Information System (INIS)

2001-01-01

At the big readiness of waste coming from the agricultural activities are looked for the production of Energy and Payments, the biogas like product of the organic decomposition under anaerobic conditions, their composition and characteristic. The elements that conform the design as the digester, the storage, the load tanks and it discharges and the conduction is described and analyzed. They are given a series of elements to obtain the characteristics of the system possible to place as: planning, calculations, evaluation, execution and operation. Lastly the steps are indicated that should be continued in the construction of the plant including planning for the work

A full-scale prototype for the tracking chambers of the ALICE muon spectrometer. Part II- Electronics. Preamplifier; Read-out prototype

Energy Technology Data Exchange (ETDEWEB)

Courtat, P.; Charlet, D.; Lebon, S.; Martin, J.M.; Sellem, R.; Wanlin, E. [CEA Centre d' Etudes Nucleaires de Saclay, 91 - Gif-sur-Yvette (France). Service d' Electronique Physique; Douet, R.; Harroch, H.; Bimbot, L.; Jouan, D.; Kharmandarian, L.; Le Bornec, Y.; Mac Cormick, M.; Willis, N. [Paris-11 Univ., 91 - Orsay (France). Institut de Physique Nucleaire

1999-07-01

A full scale prototype of one module of the first tracking station has already been constructed. It will be equipped with the new read-out electronics proposed for the final chambers. Before integration of the whole chain, tests have been carried out on the individual components in discrete circuit prototypes. The different parts of the chain are described, together with the tests performed. The final version with integrated circuits in then described. (author)

A full-scale prototype for the tracking chambers of the ALICE muon spectrometer. Part II- Electronics. Preamplifier; Read-out prototype

International Nuclear Information System (INIS)

Courtat, P.; Charlet, D.; Lebon, S.; Martin, J.M.; Sellem, R.; Wanlin, E.; Douet, R.; Harroch, H.; Bimbot, L.; Jouan, D.; Kharmandarian, L.; Le Bornec, Y.; Mac Cormick, M.; Willis, N.

1999-01-01

A full scale prototype of one module of the first tracking station has already been constructed. It will be equipped with the new read-out electronics proposed for the final chambers. Before integration of the whole chain, tests have been carried out on the individual components in discrete circuit prototypes. The different parts of the chain are described, together with the tests performed. The final version with integrated circuits in then described. (author)

AP1000 plant construction in China: Ansaldo Nucleare contribution

International Nuclear Information System (INIS)

Frogheri, Monica; Saiu, Gianfranco

2009-01-01

On 24th of July 2007 Westinghouse Electric Co. signed landmark contracts with China's State Nuclear Power Technology Corporation (SNPTC), to provide four AP1000 nuclear power plants in China. The AP1000 is a two-loop 1117 MWe Pressurized Water Reactor (PWR). It is based on proven technology, but with an emphasis on safety features that rely on natural driving forces, such as pressurized gas, gravity flow, natural circulation flow and convection. Ansaldo Nucleare has provided a significant support to the passive plant technology development and, starting from 2000, is cooperating with Westinghouse to development of the AP1000 Plant. In the frame of the AP1000 Chinese agreement, Ansaldo Nucleare, in Joint Venture with Mangiarotti Nuclear, has signed a contract with Westinghouse for the design and the supply of innovative components to be installed in the first AP1000 unit to be constructed at the Sanmen site. The contract includes: the design of the steel containment vessel, preparation of construction and fabrication, specifications, design and supply of SCV mechanical penetrations, air locks and equipment hatches. Moreover, Ansaldo Nucleare is in charge of the final design of the AP1000 PRHR-HX and together with Mangiarotti Nuclear will supply the component for the Sanmen Unit 1 NPP. The paper presents an overview of the design and manufacturing activities performed by Ansaldo Nucleare and its partners for the AP1000 plant in China. (authors)

Probabilistic cost estimating of nuclear power plant construction projects

International Nuclear Information System (INIS)

Finch, W.C.; Perry, L.W.; Postula, F.D.

1978-01-01

This paper shows how to identify and isolate cost accounts by developing probability trees down to component levels as justified by value and cost uncertainty. Examples are given of the procedure for assessing uncertainty in all areas contributing to cost: design, factory equipment pricing, and field labor and materials. The method of combining these individual uncertainties is presented so that the cost risk can be developed for components, systems and the total plant construction project. Formats which enable management to use the probabilistic cost estimate information for business planning and risk control are illustrated. Topics considered include code estimate performance, cost allocation, uncertainty encoding, probabilistic cost distributions, and interpretation. Effective cost control of nuclear power plant construction projects requires insight into areas of greatest cost uncertainty and a knowledge of the factors which can cause costs to vary from the single value estimates. It is concluded that probabilistic cost estimating can provide the necessary assessment of uncertainties both as to the cause and the consequences

A concise biogas plant construction suitable for Ghana and other tropical countries

Energy Technology Data Exchange (ETDEWEB)

Gbagbo, J.K.N.

1997-04-01

This report is intended to be used by people in the field of biogas for workshops, technicians, teachers to educate as well as to carry out hands on constructions in Ghana and other tropical countries. Chapter 1, discusses the biogas technology, what a biogas plant is, and how it functions. Chapter 2, describes the entire process. Chapter 3, discusses the necessary conditions for fermentation. Chapter 4, the measuring parameters for monitoring the system. Chapter 5, describes the various types of biogas plants suitable for tropical countries. Chapter 6, describes a planning guide for Ghana and other tropical countries. Chapter 7, discusses digester sizing and finally, Chapter 8, describes a concise biogas plant construction suitable for the rural areas of Ghana and other tropical countries. (au)

Technical data for concentrated solar power plants in operation, under construction and in project

Directory of Open Access Journals (Sweden)

Ugo Pelay

2017-08-01

Full Text Available This article presents technical data for concentrated solar power (CSP plants in operation, under construction and in project all over the world in the form of tables. These tables provide information about plants (e.g., name of the CSP plant, country of construction, owner of the plant, aim of the plant and their technical characteristics (e.g., CSP technology, solar power, area of the plant, presence and type of hybridization system, electricity cost, presence and type of TES, power cycle fluid, heat transfer fluid, operating temperature, operating pressure, type of turbine, type and duration of storage, etc.. Further interpretation of the data and discussions on the current state-of-the-art and future trends of CSP can be found in the associated research article (Pelay et al., 2017 [1].

Facial Prototype Formation in Children.

Science.gov (United States)

Inn, Donald; And Others

This study examined memory representation as it is exhibited in young children's formation of facial prototypes. In the first part of the study, researchers constructed images of faces using an Identikit that provided the features of hair, eyes, mouth, nose, and chin. Images were varied systematically. A series of these images, called exemplar…

Rationalization of design and construction of buildings for nuclear power plants

Energy Technology Data Exchange (ETDEWEB)

Satoh, Shunsaku; Mitsumatsu, Kazuo

1987-02-01

This article presents various rationalization methods introduced in the past few years for design and construction of BWR nuclear power plant buildings. When the site for a nuclear power plant has been decided, investigation is made on various aspects of possible earthquakes, based on which anti-earthquake design for the plant site is established. The next step is to examine the displacements and stresses that may occur to various parts of the bulding from a postulated earthquake. This is normally called the earthquake response analysis and consists of calculating the behaviors of the buildings using large computers. A seismic controlled structure system has recently proposed, aiming to reduce the displacements and stresses of the building itself by controlling the flexibility of the installed seismic apparatus against the input of external loads. Lately, high strength concrete and high strength reinforcing steel bars (rebars) are being considered for practical application. If advanced computers and related accessories are utilized to the maximum, it will lead not only to efficiency in the design work but to the possibility of optimized design. For rational construction, a combined scaffolding and temporary support has been devised to reduce the time and volume of required temporary work. What have been developed for rationalization of construction work also include robots for heavy weight rebar fabrication, horizontal reed blind type rebars, portable concrete distributor, all weather environment facilities, and construction materials conveyance system. (Nogami, K.).

Rationalization of design and construction of buildings for nuclear power plants

International Nuclear Information System (INIS)

Satoh, Shunsaku; Mitsumatsu, Kazuo

1987-01-01

This article presents various rationalization methods introduced in the past few years for design and construction of BWR nuclear power plant buildings. When the site for a nuclear power plant has been decided, investigation is made on various aspects of possible earthquakes, based on which anti-earthquake design for the plant site is established. The next step is to examine the displacements and stresses that may occur to various parts of the bulding from a postulated earthquake. This is normally called the earthquake response analysis and consists of calculating the behaviors of the buildings using large computers. A seismic controlled structure system has recently proposed, aiming to reduce the displacements and stresses of the building itself by controlling the flexibility of the installed seismic apparatus against the input of external loads. Lately, high strength concrete and high strength reinforcing steel bars (rebars) are being considered for practical application. If advanced computers and related accessories are utilized to the maximum, it will lead not only to efficiency in the design work but to the possibility of optimized design. For rational construction, a combined scaffolding and temporary support has been devised to reduce the time and volume of required temporary work. What have been developed for rationalization of construction work also include robots for heavy weight rebar fabrication, horizontal reed blind type rebars, portable concrete distributor, all weather environment facilities, and construction materials conveyance system. (Nogami, K.)

A Study on the Approach to Quality Management in Construction of Nuclear Power Plants

Energy Technology Data Exchange (ETDEWEB)

Pingish, Panupong [Korea Advanced Institute of Science and Technology, Daejeon (Korea, Republic of); Choi, Kwang Sik [Korea Institute of Nuclear Safety, Daejeon (Korea, Republic of)

2010-05-15

The quality of works and services in nuclear facilities are important aspect of public safety and environmental protection. In the general legal framework for the regulation of nuclear power plants of each country, the requirement which effectiveness, overall quality management programme be established should be present. The organization having overall responsibility for a nuclear power plant shall be responsible for the establishment and implementation of the overall quality management programme for that plant. The construction methods available for new nuclear power plants are generally the same as those used for other big construction projects. The construction stage of a nuclear power plant includes a multitude of activities affecting quality which are performed by various organizations with specific responsibilities assigned to them. At the present, the IAEA source materials have been changing some documents for supporting tendency in the nuclear technology likewise in term of quality assurance concept to quality management concept. The principle goal for quality management is achieved assurance and sustainable with nuclear safety. This system brings all the requirements for managing facilities and activities together by only one system

A Study on the Approach to Quality Management in Construction of Nuclear Power Plants

International Nuclear Information System (INIS)

Pingish, Panupong; Choi, Kwang Sik

2010-01-01

The quality of works and services in nuclear facilities are important aspect of public safety and environmental protection. In the general legal framework for the regulation of nuclear power plants of each country, the requirement which effectiveness, overall quality management programme be established should be present. The organization having overall responsibility for a nuclear power plant shall be responsible for the establishment and implementation of the overall quality management programme for that plant. The construction methods available for new nuclear power plants are generally the same as those used for other big construction projects. The construction stage of a nuclear power plant includes a multitude of activities affecting quality which are performed by various organizations with specific responsibilities assigned to them. At the present, the IAEA source materials have been changing some documents for supporting tendency in the nuclear technology likewise in term of quality assurance concept to quality management concept. The principle goal for quality management is achieved assurance and sustainable with nuclear safety. This system brings all the requirements for managing facilities and activities together by only one system

Special issue on start of construction of the Ohma nuclear power plant of J-Power

International Nuclear Information System (INIS)

Takahashi, Taizo

2008-01-01

The Electric Power Development Co., Ltd. (J-Power) started construction of its Ohma nuclear power plant - a 1383 MWe Advanced Boiling Water Reactor (ABWR) - in Aomori prefecture on May 2008. The reactor of the Ohma plant will be the first to load MOX fuels in all of its reactor cores. It will be able to consume a quarter of all the recycled MOX fuels produced at Rokkasho reprocessing plant and hence make a major contribution to Japan's policy of recycling plutonium recovered from spent fuels. Special issue reviewed history and overview of the Ohma plant as well as its significance to enhance power generation portfolio in corresponding with national interests. Local governor's expectations and present state of the Ohma plant were also described. After preparation works, construction began on excavation of foundation for the service building, proceeding as always with safety the foremost priority during construction. (T. Tanaka)

Construction permit of nuclear power plants in case of leasing

International Nuclear Information System (INIS)

Anon.

1983-01-01

Guiding lines (unofficial): 1. A leasing company can be founded to finance and to operate a nuclear power plant. 2. The leasing company does not require a license according to section 7 of the Atomic Energy Act, for it neither constructs nor posesses the nuclear power plant. 3. This also applies if the proprietor, and later on operator, of the nuclear power plant holds an interest in this leasing company as a shareholder. Section 7, and 19 subsection 3 of the Atomic Energy Act. Higher Administrative Court of Rhineland Palatinate, Decision of July 20sup(th), 1982. (orig.) [de

Three integrated photovoltaic/sound barrier power plants. Construction and operational experience; Drei integrierte PV-Schallschutz Versuchsfelder. Bau und Erprobung

Energy Technology Data Exchange (ETDEWEB)

Nordmann, T.; Froelich, A.; Clavadetscher, L.

2002-07-01

After an international ideas competition by TNC Switzerland and Germany in 1996, six companies where given the opportunity to construct a prototype of their newly developed integrated PV-sound barrier concepts. The main goal was to develop highly integrated concepts, allowing the reduction of PV sound barrier systems costs, as well as the demonstration of specific concepts for different noise situations. This project is strongly correlated with a German project. Three of the concepts of the competition are demonstrated along a highway near Munich, constructed in 1997. The three Swiss installations had to be constructed at different locations, reflecting three typical situations for sound barriers. The first Swiss installation was the world first Bi-facial PV-sound barrier. It was built on a highway bridge at Wallisellen-Aubrugg in 1997. The operational experience of the installation is positive. But due to the different efficiencies of the two cell sides, its specific yield lies somewhat behind a conventional PV installation. The second Swiss plant was finished in autumn 1998. The 'zig-zag' construction is situated along the railway line at Wallisellen in a densely inhabited area with some local shadowing. Its performance and its specific yield is comparatively low due to a combination of several reasons (geometry of the concept, inverter, high module temperature, local shadows). The third installation was constructed along the motor way A1 at Bruettisellen in 1999. Its vertical panels are equipped with amorphous modules. The report show, that the performance of the system is reasonable, but the mechanical construction has to be improved. A small trial field with cells directly laminated onto the steel panel, also installed at Bruettisellen, could be the key development for this concept. This final report includes the evaluation and comparison of the monitored data in the past 24 months of operation. (author)

Characterisation and Control of a Prototype HTS SMES Device

International Nuclear Information System (INIS)

Hawley, C J; Cuiuri, D; Cook, C D; Gower, S A; Beales, T P

2006-01-01

A 2.79 kJ prototype high transition temperature Superconducting Magnetic Energy Storage (SMES) device has been constructed. The coil for the prototype has been wound using High Temperature Superconducting (HTS) BSCCO-2223 tape. The refrigeration system is a gaseous helium cold head cryocooler used to maintain the SMES coil at a temperature of 30 K, improving the I c characteristic of the coil by a factor of 4.7 compared to that at 77 K. The SMES device is capable of supplying a 3-phase load during power interruptions, and has been constructed during a program to develop a larger 20 kJ system aimed at industrial applications

Application and development analysis of nuclear power plant modular construction

International Nuclear Information System (INIS)

Fang Xiaopeng

2015-01-01

Modular Construction is currently one of the major development trends for the nuclear power plant construction technology worldwide. In the first-of-a-kind AP1000 Nuclear Power Project practiced in China, the large-scale structural modules and mechanical modules have been successfully fabricated, assembled and installed. However, in the construction practice of the project, some quality issues are identified with the assembly and installation process of large-scale structural modules in addition to the issue of incomplete supply of mechanical modules, which has failed to fully demonstrate the features and merits of modular construction. This paper collects and consolidates the issues of modular construction of AP1000 first of a kind reactor, providing root cause analysis in the aspects of process design, quality control, site construction logic, interface management in the process of module fabrication, assembly and installation; modular construction feasibility assessment index is proved based on the quantification and qualitative analysis of the impact element. Based on the modular construction feasibility, NPP modular construction improvement suggestions are provided in the aspect of modular assembly optimization definition, tolerance control during the fitting process and the construction logic adjustment. (author)

A novel approach to the generation of seamless constructs for plant transformation

DEFF Research Database (Denmark)

Kronbak, Remy; Ingvardsen, Christina R.; Madsen, Claus K.

2014-01-01

Background: When creating plant transformation vectors, full control of nucleotides flanking the insert in the final construct may be desirable. Modern ligase-independent methods for DNA-recombination are based on linearization by classical type II restriction endonucleases (REs) alone or in comb......Background: When creating plant transformation vectors, full control of nucleotides flanking the insert in the final construct may be desirable. Modern ligase-independent methods for DNA-recombination are based on linearization by classical type II restriction endonucleases (REs) alone...... on wheat and barley endosperm cells for transient gfp expression.Conclusions: All nucleotides flanking an insert in a biolistic plant transformation vector can be customized by means of SRL in combination with SLIC. Especially type IIS REs promote an efficient cloning result. Based on our findings, we...

Development of advanced concept for shortening construction period of ABWR plant (part 2)

International Nuclear Information System (INIS)

Fujita, Tomohiro; Satoh, Takashi

2003-01-01

The construction of the first building fully applying SC structure, which is indispensable for shortening construction period of ABWR plants (21.5 months from the first concrete work to fuel loading), has been started since August 2002 in Japan. Before the construction start, a pre-construction test with some actual size SC panels was carried out to confirm the SC modular construction method. The outline of the design and the construction of the first full-SC building and the results of the pre-construction test are reported. (author)

Construction work for prototype fast breeder reactor MONJU

International Nuclear Information System (INIS)

Suzuki, Yasuyuki; Tsuji, Koichi; Shimizu, Hisashi

1991-01-01

The main construction work of MONJU was started from the excavation for building foundation in October 1985, the containment vessel was prepared in April 1987, the reactor vessel was installed in October 1988, and the installation of the whole equipment was completed in April 1991. Fuji Electric made preparations for construction matching the above master schedule in consideration of construction schedule quality assurance and safety and accomplished the work within the scheduled time without personal injury as long as 2.35 million hours. (author)

Software V ampersand V methods for digital plant protection system

International Nuclear Information System (INIS)

Kim, Hung-Jun; Han, Jai-Bok; Chun, Chong-Son; Kim, Sung; Kim, Kern-Joong.

1997-01-01

Careful thought must be given to software design in the development of digital based systems that play a critical role in the successful operation of nuclear power plants. To evaluate the software verification and validation methods as well as to verify its system performance capabilities for the upgrade instrumentation and control system in the Korean future nuclear power plants, the prototype Digital Plant, Protection System (DPPS) based on the Programmable Logic Controller (PLC) has been constructed. The system design description and features are briefly presented, and the software design and software verification and validation methods are focused. 6 refs., 2 figs

Operation management of the prototype heavy water reactor 'Fugen'

International Nuclear Information System (INIS)

Muramatsu, Akira; Takei, Hiroaki; Iwanaga, Shigeru; Noda, Masao; Hara, Hidemi

1983-01-01

The advanced thermal reactor Fugen power station has continued almost smooth operation since it began the full scale operation as the first homemade power reactor in Japan in March, 1979. In the initial period of operation, some troubles were experienced, but now, it can be said that the operational techniques of heavy water-moderated, boiling light water-cooled, pressure tube type reactors have been established, through the improvement of the operational method and equipment, and the operational experience. Also, the verification of the operational ability, maintainability, reliability and safety of this new type reactor, that is the mission of the prototype reactor, achieved steadily the good results. Hereafter, the verification of operational performance is the main objective because it is required for the design, construction and operation of the demonstration reactor. The organization for the operation management and operation, the communication at the time of the abnormality, the operation of the plant, that is, start up, stop and the operation at the rated output, the works during plant stoppage, the operation at the time of the plant abnormality, the operation of waste treatment facility and others, the improvement of the operational method, and the education and training of operators are reported. (Kako, I.)

Cultural prototypes and dimensions of honor.

Science.gov (United States)

Cross, Susan E; Uskul, Ayse K; Gerçek-Swing, Berna; Sunbay, Zeynep; Alözkan, Cansu; Günsoy, Ceren; Ataca, Bilge; Karakitapoglu-Aygün, Zahide

2014-02-01

Research evidence and theoretical accounts of honor point to differing definitions of the construct in differing cultural contexts. The current studies address the question "What is honor?" using a prototype approach in Turkey and the Northern United States. Studies 1a/1b revealed substantial differences in the specific features generated by members of the two groups, but Studies 2 and 3 revealed cultural similarities in the underlying dimensions of self-respect, moral behavior, and social status/respect. Ratings of the centrality and personal importance of these factors were similar across the two groups, but their association with other relevant constructs differed. The tripartite nature of honor uncovered in these studies helps observers and researchers alike understand how diverse responses to situations can be attributed to honor. Inclusion of a prototype analysis into the literature on honor cultures can provide enhanced coverage of the concept that may lead to testable hypotheses and new theoretical developments.

Risk factors during construction of power plants using renewable energy sources

Directory of Open Access Journals (Sweden)

Nefedova Lyudmila Veniaminovna

2016-12-01

Full Text Available The authors consider main characteristics of modern development of renewable energy sources (RES. It is dedicated that there are some technical and economic barriers to the widespread use of renewable energy. For example, RES are inconstancy in time and space and have low density of energy flow. High capital intensity and cost price, long-term construction, a considerable degree of different kinds of risk, lack of competitiveness with hydrocarbon species generation in the existing regulatory environment are also inherent to RES. The role of the regulatory framework is shown according to perspective plans of construction of power plants using renewable energy sources. The main requirements which are applied to measures of state support of construction industry of renewable energy development are formulated. Current condition of construction industry of RES in Russia is assessed. The problems of risks which arise during construction of renewable energy facilities according to results of practical use of RES are discussed. And it is rather important to use stage assessment for the construction phase of the project during risk analysis of construction of alternative energy sources. The main groups of RES risks are described. The importance of regulatory and resource risks for effective development of renewable energy in Russia according to the method of strategic planning with the identification of the adverse effects of gradation factors are determined. The analysis of financial risks types and methods of its management during construction power generation projects based on different types of renewable energy resources are made. In the end of the article the authors make a conclusion, that the development of projects for the construction of power plants with the use of innovative technical solutions to ensure minimal risks to the environment and safe operation in various climatic conditions is a priority.

Effect of construction time, interest rate, and inflation on the capital cost of nuclear power plants

International Nuclear Information System (INIS)

Abel, P.S.; Greybeck, E.M.; Omberg, R.P.

1981-09-01

Cost estimates for nuclear power plants currently under construction are on the order of four billion dollars. It will be shown, in this paper, that this is a direct consequence of relatively high inflation rates and relatively long construction times. If either inflation rates or construction times, or a combination thereof, should decrease significantly, cost estimates for nuclear power plants could return to approximately two billion dollars

arXiv Construction and beam-tests of silicon-tungsten prototype modules for the CMS High Granularity Calorimeter for HL-LHC

CERN Document Server

INSPIRE-00664095

2018-02-26

As part of its HL-LHC upgrade program, CMS is developing a High Granularity Calorimeter (HGCAL) to replace the existing endcap calorimeters. The HGCAL will be realised as a sampling calorimeter, including an electromagnetic compartment comprising 28 layers of silicon pad detectors with pad areas of 0.5–1.0 cm2 interspersed with absorbers. Prototype modules, based on 6-inch hexagonal silicon pad sensors with 128 channels, have been constructed and include many of the features required for this challenging detector. In 2016, beam tests of sampling configurations made from these modules have been conducted both at FNAL and at CERN using the Skiroc2 front-end ASIC (designed by the CALICE collaboration for ILC). In 2017, the setup has been extended with CALICE's AHCAL prototype, a scinitillator based sampling calorimeter, and it was further tested in dedicated beam tests at CERN. There, the new Skiroc2-CMS front-end ASIC was used for the first time. We highlight final results from our studies in 2016, including ...

Construction method for plant and facility for performing the method

International Nuclear Information System (INIS)

Matsuura, Tadashi; Koda, Koichi; Miyahara, Ryohei; Hasegawa, Hiroshi; Tatehoko, Kazuto; Takeda, Masakado; Yoshinaga, Toshiaki.

1997-01-01

For constructing a nuclear power plant, it is necessary to dispose a large-scaled temporarily constructed yard for install or operate a large crane. Rails are laid in series over located positions of a plurality of buildings, and a gantry crane which moves on rails and has a size striding over the buildings is disposed. The crane can work for loading operation required for the construction of a plurality of buildings and can operate over the entire region for the range of the loading operation even for large weighted loads. The gantry crane is moved toward the seashore, and construction materials and products transported on the sea are received by the gantry crane and installed to the buildings. The transportation on the land for the construction materials and products is reduced to improve efficiency. In addition, the rails are extended beyond the region where the buildings are constructed, and a yard is constructed along the extended region. The transportation from the yard can be conducted economically and efficiently with no relaying operation. (N.H.)

Country Report Summary: Japan [Project Management in Nuclear Power Plant Construction: Guidelines and Experience

International Nuclear Information System (INIS)

2012-01-01

The Hokkaido Electric Power Company (HEPCO) is the owner of the Tomari NPP comprising three operating PWR units. The latest unit to be connected to the grid, Tomari Unit 3, is a 3-loop PWR power plant with an electric output of 912 MW(e) supplied by Mitsubishi Heavy Industries (MHI). This is the newest unit in HEPCO and it is the newest PWR unit in Japan as well. The first concrete at Tomari Unit 3 was poured at the end of summer in 2004. The unit entered into commercial operation in December 2009. The Tomari site is located on a northern Japanese island. It is battered by strong winds and receives much snow in the winter. Therefore, civil works and building construction were temporarily suspended every year from the beginning of December until the end of March. This increased construction duration by one year compared to other sites. Consequently from first concrete to the start of commercial operation construction at Tomari lasted 64 months. There are specific factors in the approach to construction of nuclear power plants in Japan. (1) Japanese legislation defines that the sole licensee must be the electric power company. This implies that the electric power company is responsible for the safety of the plant and in that capacity it must submit for approval the Safety Analysis Report (SAR) but it is also responsible for the design and reliability of the plant; hence it must also submit for approval the Construction Plan (CP), containing all necessary detailed design information. Consequently, the electric power company becomes the sole counterpart to the regulatory body on all aspects of the project. (2) All Japanese electric power companies are considerably large and have the tradition to do the engineering of their power plant themselves, and this not only for nuclear but also for conventional power plant. Therefore, the owner/utilities in Japan carry themselves the burden of major portions of the engineering, procurement and construction (EPC) of their NPPs

Welding Metallurgy of Nickel-Based Superalloys for Power Plant Construction

Science.gov (United States)

Tung, David C.

Increasing the steam temperature and pressure in coal-fired power plants is a perpetual goal driven by the pursuit of increasing thermal cycle efficiency and reducing fuel consumption and emissions. The next target steam operating conditions, which are 760°C (1400°F) and 35 MPa (5000 psi) are known as Advanced Ultra Supercritical (AUSC), and can reduce CO2 emissions up to 13% but this cannot be achieved with traditional power plant construction materials. The use of precipitation-strengthened Nickel-based alloys (superalloys) is required for components which will experience the highest operating temperatures. The leading candidate superalloys for power plant construction are alloys 740H, 282, and 617. Superalloys have excellent elevated temperature properties due to careful microstructural design which is achieved through very specific heat treatments, often requiring solution annealing or homogenization at temperatures of 1100 °C or higher. A series of postweld heat treatments was investigated and it was found that homogenization steps before aging had no noticeable effect on weld metal microhardness, however; there were clear improvements in weld metal homogeneity. The full abstract can be viewed in the document itself.

Nuclear power plants: construction status report, data as of 6/30/82

International Nuclear Information System (INIS)

1982-10-01

This report is compiled by the Nuclear Regulatory Commission's Office of Resource Management to provide information necessary for monitoring progress of all nuclear power plants which have Construction Permits. The report includes data from utilities sponsoring the construction, as well as from NRC's Office of Inspection and Enforcement. This data is used to synchronize the licensing process with predicted fuel load dates for this central Federal Government presentation of commercial reactor construction

Nuclear power plants. Construction status report, data as of 30 Nov. 78

International Nuclear Information System (INIS)

1978-12-01

The report is compiled to provide the information necessary for monitoring progress of the 94 plants under authorized construction. The report includes data from utilities sponsoring the construction, as well as from NRC's Office of Inspection and Enforcement, which have been analyzed by the OMPA in implementing Management Information Systems. This data is used to synchronize the licensing process with predicted fuel load dates for this central Federal Government presentation of commercial reactor construction

Nuclear power plants: construction status report, data as of 03/31/82

International Nuclear Information System (INIS)

1982-06-01

This report is compiled by the Nuclear Regulatory Commission's Office of Resource Management to provide information necessary for monitoring progress of all nuclear power plants which have Construction Permits. The report includes data from utilities sponsoring the construction, as well as from NRC's Office of Inspection and Enforcement. This data is used to synchronize the licensing process with predicted fuel load dates for this central Federal Government presentation of commercial reactor construction

32 CFR 644.486 - Disposal of buildings and improvements constructed under emergency plant facilities (EPF) or...

Science.gov (United States)

2010-07-01

... 32 National Defense 4 2010-07-01 2010-07-01 true Disposal of buildings and improvements constructed under emergency plant facilities (EPF) or similar contracts. 644.486 Section 644.486 National... Disposal of buildings and improvements constructed under emergency plant facilities (EPF) or similar...

Understanding young and older male drivers' willingness to drive while intoxicated: the predictive utility of constructs specified by the theory of planned behaviour and the prototype willingness model.

Science.gov (United States)

Rivis, Amanda; Abraham, Charles; Snook, Sarah

2011-05-01

The present study examined the predictive utility of constructs specified by the theory of planned behaviour (TPB) and prototype willingness model (PWM) for young and older male drivers' willingness to drive while intoxicated. A cross-sectional questionnaire was employed. Two hundred male drivers, recruited via a street survey, voluntarily completed measures of attitude, subjective norm, perceived behavioural control, prototype perceptions, and willingness. Findings showed that the TPB and PWM variables explained 65% of the variance in young male drivers' willingness and 47% of the variance in older male drivers' willingness, with the interaction between prototype favourability and similarity contributing 7% to the variance explained in older males' willingness to drive while intoxicated. The findings possess implications for theory, research, and anti-drink driving campaigns. ©2010 The British Psychological Society.

Magnetic refrigeration at room temperature - from magnetocaloric materials to a prototype

DEFF Research Database (Denmark)

Kuhn, Luise Theil; Pryds, Nini; Bahl, Christian Robert Haffenden

2011-01-01

Based on the magnetocaloric effect, magnetic refrigeration at room temperature has for the past decade been a promising, environmentally friendly new energy technology predicted to have a significantly higher efficiency than the present conventional methods. However, so far only a few prototype...... refrigeration machines have been presented worldwide and there are still many scientific and technological challenges to be overcome. We report here on the MagCool project, which spans all the way from basic materials studies to the construction of a prototype. Emphasis has been on ceramic magnetocaloric...... materials, their shaping and graded composition for technological use. Modelling the performance of a permanent magnet with optimum use of the flux and relatively low weight, and designing and constructing a prototype continuous magnetic refrigeration device have also been major tasks in the project...

Magnetic refrigeration at room temperature - from magnetocaloric materials to a prototype

International Nuclear Information System (INIS)

Kuhn, L Theil; Pryds, N; Bahl, C R H; Smith, A

2011-01-01

Based on the magnetocaloric effect, magnetic refrigeration at room temperature has for the past decade been a promising, environmentally friendly new energy technology predicted to have a significantly higher efficiency than the present conventional methods. However, so far only a few prototype refrigeration machines have been presented worldwide and there are still many scientific and technological challenges to be overcome. We report here on the MagCool project, which spans all the way from basic materials studies to the construction of a prototype. Emphasis has been on ceramic magnetocaloric materials, their shaping and graded composition for technological use. Modelling the performance of a permanent magnet with optimum use of the flux and relatively low weight, and designing and constructing a prototype continuous magnetic refrigeration device have also been major tasks in the project.

Construction quality assurance for nuclear power plants

Energy Technology Data Exchange (ETDEWEB)

NONE

1983-10-01

This Standard contains the requirements for the quality assurance program applicable to the construction phase of a nuclear power plant. This Standard covers all activities carried out for and by the owner from the receipt of components or materials on the site to their incorporation in systems or structures as required by drawings or other formal engineering information. It also covers the provision of required support activities and equipment and applies at all stages on the site as far as the testing of components or systems before they are submitted for commissioning. 2 figs.

Construction quality assurance for nuclear power plants

International Nuclear Information System (INIS)

1983-10-01

This Standard contains the requirements for the quality assurance program applicable to the construction phase of a nuclear power plant. This Standard covers all activities carried out for and by the owner from the receipt of components or materials on the site to their incorporation in systems or structures as required by drawings or other formal engineering information. It also covers the provision of required support activities and equipment and applies at all stages on the site as far as the testing of components or systems before they are submitted for commissioning. 2 figs

Assessment of modular construction for safety-related structures at advanced nuclear power plants

International Nuclear Information System (INIS)

Braverman, J.; Morante, R.; Hofmayer, C.

1997-03-01

Modular construction techniques have been successfully used in a number of industries, both domestically and internationally. Recently, the use of structural modules has been proposed for advanced nuclear power plants. The objective in utilizing modular construction is to reduce the construction schedule, reduce construction costs, and improve the quality of construction. This report documents the results of a program which evaluated the proposed use of modular construction for safety-related structures in advanced nuclear power plant designs. The program included review of current modular construction technology, development of licensing review criteria for modular construction, and initial validation of currently available analytical techniques applied to concrete-filled steel structural modules. The program was conducted in three phases. The objective of the first phase was to identify the technical issues and the need for further study in order to support NRC licensing review activities. The two key findings were the need for supplementary review criteria to augment the Standard Review Plan and the need for verified design/analysis methodology for unique types of modules, such as the concrete-filled steel module. In the second phase of this program, Modular Construction Review Criteria were developed to provide guidance for licensing reviews. In the third phase, an analysis effort was conducted to determine if currently available finite element analysis techniques can be used to predict the response of concrete-filled steel modules

Courthouse Prototype Building

Energy Technology Data Exchange (ETDEWEB)

Malhotra, Mini [ORNL; New, Joshua Ryan [ORNL; Im, Piljae [ORNL

2018-02-01

As part of DOE's support of ANSI/ASHRAE/IES Standard 90.1 and IECC, researchers at Pacific Northwest National Laboratory (PNNL) apply a suite of prototype buildings covering 80% of the commercial building floor area in the U.S. for new construction. Efforts have started on expanding the prototype building suite to cover 90% of the commercial building floor area in the U.S., by developing prototype models for additional building types including place of worship, public order and safety, public assembly. Courthouse is courthouse is a sub-category under the “Public Order and Safety" building type category; other sub-categories include police station, fire station, and jail, reformatory or penitentiary.ORNL used building design guides, databases, and documented courthouse projects, supplemented by personal communication with courthouse facility planning and design experts, to systematically conduct research on the courthouse building and system characteristics. This report documents the research conducted for the courthouse building type and proposes building and system characteristics for developing a prototype building energy model to be included in the Commercial Building Prototype Model suite. According to the 2012 CBECS, courthouses occupy a total of 436 million sqft of floor space or 0.5% of the total floor space in all commercial buildings in the US, next to fast food (0.35%), grocery store or food market (0.88%), and restaurant or cafeteria (1.2%) building types currently included in the Commercial Prototype Building Model suite. Considering aggregated average, courthouse falls among the larger with a mean floor area of 69,400 sqft smaller fuel consumption intensity building types and an average of 94.7 kBtu/sqft compared to 77.8 kBtu/sqft for office and 80 kBtu/sqft for all commercial buildings.Courthouses range in size from 1000 sqft to over a million square foot building gross square feet and 1 courtroom to over 100 courtrooms. Small courthouses

Business data processing in the service of quality and safety in nuclear power plant construction

International Nuclear Information System (INIS)

Chassignet, C.

1980-01-01

Construction of a nuclear power plant implies collection and correlation of several thousand items of information which must be identified and which must remain retrievable throughout the service life of the plant. The Framatome Corporation, which has one of the largest nuclear power plant construction programs in the world, therefore set up a processing and checking system for the documents containing this information. The author describes the functions and principles of this system (known as SHARAD), together with its technical data and its operation [fr

Utilization of virtual prototyping in development of CMM

International Nuclear Information System (INIS)

Raneda, A.; Pessi, P.; Siuko, M.; Handroos, H.; Palmer, J.; Vilenius, M.

2003-01-01

The characteristic advantages of hydraulics (high power density, simple construction and reliability) together with the characteristics of water as the pressure medium (fire and environmentally safe, chemically neutral, not activated nor affected by radiation) are highlighted in critical applications such as remote handling operations in International Thermonuclear Experimental Reactor (ITER). However, component cost and lack of wide selection of water hydraulic components make it difficult to build and to test complex water hydraulic systems. The use of virtual prototyping for the development of water hydraulic tools can be used to address this problem. Rapidly increased computational power has created conditions for extensive numerical calculations, enabling computer aided virtual prototyping to replace physical prototype phases in product development

[Complex technology for water and wastewater disinfection and its industrial realization in prototype unit].

Science.gov (United States)

Arakcheev, E N; Brunman, V E; Brunman, M V; Konyashin, A V; Dyachenko, V A; Petkova, A P

Usage of complex automated electrolysis unit for drinking water disinfection and wastewater oxidation and coagulation is scoped, its ecological and energy efficiency is shown. Properties of technological process of anolyte production using membrane electrolysis of brine for water disinfection in municipal pipelines and potassium ferrate production using electrochemical dissolution of iron anode in NaOH solution for usage in purification plants are listed. Construction of modules of industrial prototype for anolyte and ferrate production and applied aspects of automation of complex electrolysis unit are proved. Results of approbation of electrolytic potassium ferrate for drinking water disinfection and wastewater, rain water and environmental water oxidation and coagulation are shown.

Constructing wetlands: measuring and modeling feedbacks of oxidation processes between plants and clay-rich material

Science.gov (United States)

Saaltink, Rémon; Dekker, Stefan C.; Griffioen, Jasper; Wassen, Martin J.

2016-04-01

Interest is growing in using soft sediment as a building material in eco-engineering projects. Wetland construction in the Dutch lake Markermeer is an example: here the option of dredging some of the clay-rich lake-bed sediment and using it to construct 10.000 ha of wetland will soon go under construction. Natural processes will be utilized during and after construction to accelerate ecosystem development. Knowing that plants can eco-engineer their environment via positive or negative biogeochemical plant-soil feedbacks, we conducted a six-month greenhouse experiment to identify the key biogeochemical processes in the mud when Phragmites australis is used as an eco-engineering species. We applied inverse biogeochemical modeling to link observed changes in pore water composition to biogeochemical processes. Two months after transplantation we observed reduced plant growth and shriveling as well as yellowing of foliage. The N:P ratios of plant tissue were low and were affected not by hampered uptake of N but by enhanced uptake of P. Plant analyses revealed high Fe concentrations in the leaves and roots. Sulfate concentrations rose drastically in our experiment due to pyrite oxidation; as reduction of sulfate will decouple Fe-P in reducing conditions, we argue that plant-induced iron toxicity hampered plant growth, forming a negative feedback loop, while simultaneously there was a positive feedback loop, as iron toxicity promotes P mobilization as a result of reduced conditions through root death, thereby stimulating plant growth and regeneration. Given these two feedback mechanisms, we propose that when building wetlands from these mud deposits Fe-tolerant species are used rather than species that thrive in N-limited conditions. The results presented in this study demonstrate the importance of studying the biogeochemical properties of the building material and the feedback mechanisms between plant and soil prior to finalizing the design of the eco-engineering project.

Costs of construction, operation and maintenance of nuclear power plants - determinant factors

International Nuclear Information System (INIS)

Silva, R.A. da

1981-01-01

A study about the construction costs of the Angra-1 nuclear power plant, including direct costs, equipment costs, installation and indirect costs such as: engineering, job-training and administration is presented. The operation and maintenance costs of the Angra-1 nuclear power plant and costs of energy generation are still studied. (E.G.) [pt

Harmonizing the prototypes concerning the fast reactors of 4. generation

International Nuclear Information System (INIS)

Anon.

2008-01-01

In january 2008, an agreement was signed between the Japan Atomic Energy Agency (JAEA), the American Department of Energy (DOE) and the French Atomic Energy Commission, in order to harmonize the projects of the 3 countries for the development of prototypes of sodium-cooled fast reactors. This cooperation concerns the following issues: -) the purpose of the prototypes, -) common set of safety rules, -) technical innovations for reducing construction, operating and maintenance costs, and -) information exchange about the level of power, the type of nuclear fuels and the time schedule of these prototypes. (A.C.)

Delays in nuclear power plant construction. Progress report, September 15, 1976--September 14, 1977

International Nuclear Information System (INIS)

Mason, G.E.; Larew, R.E.

1977-01-01

This report identifies barriers to shortening nuclear power plant construction schedules and recommends research efforts that should minimize or eliminate the identified barriers. The identified barriers include: (1) design and construction interfacing problems; (2) problems relating to the selection and use of permanent materials and construction methods; (3) construction coordination and communication problems; and (4) problems associated with manpower availability and productivity;

[Ecological risk assessment of dam construction for terrestrial plant species in middle reach of Lancangjiang River, Southwest China].

Science.gov (United States)

Li, Xiao-Yan; Dong, Shi-Kui; Liu, Shi-Liang; Peng, Ming-Chun; Li, Jin-Peng; Zhao, Qing-He; Zhang, Zhao-Ling

2012-08-01

Taking the surrounding areas of Xiaowan Reservoir in the middle reach of Lancangjiang River as study area, and based on the vegetation investigation at three sites including electricity transmission area (site 1), electricity-transfer substation and roadsides to the substation (site 2), and emigration area (site 3) in 1997 (before dam construction), another investigation was conducted on the vegetation composition, plant coverage, and dominant species at the same sites in 2010 (after dam construction), aimed to evaluate the ecological risk of the dam construction for the terrestrial plant species in middle reach of Lancangjiang River. There was an obvious difference in the summed dominance ratio of dominant species at the three sites before and after the dam construction. According the types of species (dominant and non-dominant species) and the changes of plant dominance, the ecological risk (ER) for the plant species was categorized into 0 to IV, i.e., no or extremely low ecological risk (0), low ecological risk (I), medium ecological risk (II), high ecological risk (III), and extremely high ecological risk (IV). As affected by the dam construction, the majority of the species were at ER III, and a few species were at ER IV. The percentage of the plant species at ER III and ER IV at site 3 was higher than that at sites 1 and 2. The decrease or loss of native plants and the increase of alien or invasive plants were the major ecological risks caused by the dam construction. Effective protection strategies should be adopted to mitigate the ecological risk of the dam construction for the terrestrial plants at species level.

Role of Plants in a Constructed Wetland: Current and New Perspectives

Directory of Open Access Journals (Sweden)

Amit Gross

2013-04-01

Full Text Available The role of plants in the treatment of effluents by constructed wetland (CW systems is under debate. Here, we review ways in which plants can affect CW processes and suggest two novel functions for plants in CWs. The first is salt phytoremediation by halophytes. We have strong evidence that halophytic plants can reduce wastewater salinity by accumulating salts in their tissues. Our studies have shown that Bassia indica, a halophytic annual, is capable of salt phytoremediation, accumulating sodium to up to 10% of its dry weight. The second novel use of plants in CWs is as phytoindicators of water quality. We demonstrate that accumulation of H2O2, a marker for plant stress, is reduced in the in successive treatment stages, where water quality is improved. It is recommended that monitoring and management of CWs consider the potential of plants as phytoremediators and phytoindicators.

Prototype and proposed ISABELLE dipoles

International Nuclear Information System (INIS)

McInturff, A.D.; Sampson, W.B.; Robins, K.E.; Dahl, P.F.; Damm, R.

1977-01-01

Data are presented on the latest dipole prototypes to update the operational parameters possible for ISABELLE. This data base will constantly expand until the start of construction of the storage rings. The data will include field quality, stray field magnitudes, quench temperature and propagation times, protection capabilities singly and in multiple units, maximum central fields obtained and training behavior. Performance of the dipoles versus temperature and mode of refrigeration will be discussed. The single layer cosine theta turns distribution coils' parameters are better than those required for the operation of the 200 x 200 GeV version of ISABELLE. The double layer prototype has exceeded the magnetic field performance and two dimensional quality of field needed for the 400 x 400 GeV version of ISABELLE

Prototyping the PANDA Barrel DIRC

Energy Technology Data Exchange (ETDEWEB)

Schwarz, C., E-mail: C.Schwarz@gsi.de [GSI Helmholtzzentrum für Schwerionenforschung GmbH, Darmstadt (Germany); Kalicy, G.; Dzhygadlo, R.; Gerhardt, A.; Götzen, K.; Hohler, R.; Kumawat, H.; Lehmann, D.; Lewandowski, B.; Patsyuk, M.; Peters, K.; Schepers, G.; Schmitt, L.; Schwiening, J.; Traxler, M.; Zühlsdorf, M. [GSI Helmholtzzentrum für Schwerionenforschung GmbH, Darmstadt (Germany); Dodokhov, V.Kh. [Joint Institute for Nuclear Research, Dubna (Russian Federation); Britting, A.; Eyrich, W.; Lehmann, A. [Friedrich Alexander-University of Erlangen-Nuremberg, Erlangen (Germany); and others

2014-12-01

The design of the Barrel DIRC detector for the future PANDA experiment at FAIR contains several important improvements compared to the successful BABAR DIRC, such as focusing and fast timing. To test those improvements as well as other design options a prototype was build and successfully tested in 2012 with particle beams at CERN. The prototype comprises a radiator bar, focusing lens, mirror, and a prism shaped expansion volume made of synthetic fused silica. An array of micro-channel plate photomultiplier tubes measures the location and arrival time of the Cherenkov photons with sub-nanosecond resolution. The development of a fast reconstruction algorithm allowed to tune construction details of the detector setup with test beam data and Monte-Carlo simulations.

Augmented reality for improved communication of construction and maintenance plans in nuclear power plants

International Nuclear Information System (INIS)

Sorensen, Soren S.

2010-01-01

The purpose of implementing Augmented Reality, AR, in the planning, construction and maintenance of Nuclear Power Plants is to secure strict control, precise and correct constructions, exact execution of assignments and heightened safety at all levels. Communication of construction plans to ensure precise and correct assembly of structural elements is essential in all building projects. This is especially crucial in the construction of nuclear plants and installation of new components. The current ways in which construction plans are communicated, blueprints, 3D digital models and written descriptions all embody the need for significant levels of abstraction and interpretation, and are thus both difficult to understand and can lead to misinterpretations. A simulation system with full scale three dimensional models experienced in the physical setting where operations are to take place would bring operators closer to the real life assignments. Augmented Reality is a visualization technology that provides this motivation. (author)

Development of a prototype graphic simulation program for severe accident training

International Nuclear Information System (INIS)

Kim, Ko Ryu; Jeong, Kwang Sub; Ha, Jae Joo

2000-05-01

This is a report of the development process and related technologies of severe accident graphic simulators, required in industrial severe accident management and training. Here, we say 'a severe accident graphic simulator' as a graphics add-in system to existing calculation codes, which can show the severe accident phenomena dynamically on computer screens and therefore which can supplement one of main defects of existing calculation codes. With graphic simulators it is fairly easy to see the total behavior of nuclear power plants, where it was very difficult to see only from partial variable numerical information. Moreover, the fast processing and control feature of a graphic simulator can give some opportunities of predicting the severe accident advancement among several possibilities, to one who is not an expert. Utilizing graphic simulators' we expect operators' and TSC members' physical phenomena understanding enhancement from the realistic dynamic behavior of plants. We also expect that severe accident training course can gain better training effects using graphic simulator's control functions and predicting capabilities, and therefore we expect that graphic simulators will be effective decision-aids tools both in sever accident training course and in real severe accident situations. With these in mind, we have developed a prototype graphic simulator having surveyed related technologies, and from this development experiences we have inspected the possibility to build a severe accident graphic simulator. The prototype graphic simulator is developed under IBM PC WinNT environments and is suited to Uljin 3and4 nuclear power plant. When supplied with adequate severe accident scenario as an input, the prototype can provide graphical simulations of plant safety systems' dynamic behaviors. The prototype is composed of several different modules, which are phenomena display module, MELCOR data interface module and graphic database interface module. Main functions of

Construction and test of a fine-grained liquid argon preshower prototype

Science.gov (United States)

Davis, R. A.; Gingrich, D. M.; Pinfold, J. L.; Rodning, N. L.; Boos, E.; Zhautykov, B. O.; Aubert, B.; Bazan, A.; Beaugiraud, B.; Boniface, J.; Colas, J.; Eynard, G.; Jezequel, S.; Leflour, T.; Linossier, O.; Nicoleau, S.; Rival, F.; Sauvage, G.; Thion, J.; VanDenPlas, D.; Wingerter-Seez, I.; Zitoun, R.; Zolnierowski, Y. P.; Chmeissani, M.; Fernandez, E.; Garrido, Ll.; Martinez, M.; Padilla, C.; Gordon, H. A.; Radeka, V.; Rahm, D.; Stephani, D.; Baisin, L.; Berset, J. C.; Chevalley, J. L.; Gianotti, F.; Gildemeister, O.; Marin, C. P.; Nessi, M.; Poggioli, L.; Richter, W.; Vuillemin, V.; Baze, J. M.; Gosset, L.; Lavocat, P.; Lottin, J. P.; Mansoulié, B.; Meyer, J. P.; Renardy, J. F.; Schwindling, J.; Teiger, J.; Collot, J.; de Saintignon, P.; Dzahini, D.; Hostachy, J. Y.; Hoummada, A.; Laborie, G.; Mahout, G.; Hervas, L.; Chekhtman, A.; Cousinou, M. C.; Dargent, P.; Dinkespiller, B.; Etienne, F.; Fassnacht, P.; Fouchez, D.; Martin, L.; Miotto, A.; Monnier, E.; Nagy, E.; Olivetto, C.; Tisserant, S.; Battistoni, G.; Camin, D. V.; Cavalli, D.; Costa, G.; Cozzi, L.; Fedyakin, N.; Ferrari, A.; Mandelli, L.; Mazzanti, M.; Perini, L.; Resconi, S.; Sala, P.; Beaudoin, G.; Depommier, P.; León-Florián, E.; Leroy, C.; Roy, P.; Augé, E.; Chase, R.; Chollet, J. C.; de La Taille, C.; Fayard, L.; Fournier, D.; Hrisoho, A.; Merkel, B.; Noppe, J. M.; Parrour, G.; Pétroff, P.; Schaffer, A.; Seguin-Moreau, N.; Serin, L.; Tisserand, V.; Vichou, I.; Canton, B.; David, J.; Genat, J. F.; Imbault, D.; Le Dortz, O.; Savoy-Navarro, A.; Schwemling, P.; Eek, L. O.; Lund-Jensen, B.; Söderqvist, J.; Lefebvre, M.; Robertson, S.; RD3 Collaboration

1997-02-01

A separate liquid argon preshower detector consisting of two layers featuring a fine granularity of 2.5 × 10 -3 was studied by the RD3 collaboration. A prototype covering approximately 0.8 in pseudo-rapidity and 9° in azimuth was built and tested at CERN in July 94. CMOS and GaAs VLSI preamplifiers were designed and tested for this occasion. The combined response of this detector and an accordion electromagnetic calorimeter prototype to muons, electrons and photons is presented. For minimum ionizing tracks a signal-to-noise ratio of 4.5 per preshower layer was measured. Above 150 GeV the space resolution for electrons is better than 250 μm in both directions. The precision on the electromagnetic shower direction, determined together with the calorimeter, is better than 4 mrad above 50 GeV. It is concluded that the preshower detector would adequately fulfil its role for future operation at CERN Large Hadron Collider.

Construction and test of a fine-grained liquid argon preshower prototype

International Nuclear Information System (INIS)

Davis, R.A.; Gingrich, D.M.; Pinfold, J.L.

1997-01-01

A separate liquid argon preshower detector consisting of two layers featuring a fine granularity of 2.5 x 10 -3 was studied by the RD3 collaboration. A prototype covering approximately 0.8 in pseudo-rapidity and 9 circle in azimuth was built and tested at CERN in July 94. CMOS and GaAs VLSI preamplifiers were designed and tested for this occasion. The combined response of this detector and an accordion electromagnetic calorimeter prototype to muons, electrons and photons is presented. For minimum ionizing tracks a signal-to-noise ratio of 4.5 per preshower layer was measured. Above 150 GeV the space resolution for electrons is better than 250 μm in both directions. The precision on the electromagnetic shower direction, determined together with the calorimeter, is better than 4 mrad above 50 GeV. It is concluded that the preshower detector would adequately fulfil its role for future operation at CERN Large Hadron Collider. (orig.)

Construction and test of a fine-grained liquid argon preshower prototype

CERN Document Server

Davis, R; Pinfold, J L; Rodning, N L; Boos, E; Zhautykov, B O; Aubert, Bernard; Bazan, A; Beaugiraud, B; Boniface, J; Colas, Jacques; Eynard, G; Jézéquel, S; Le Flour, T; Linossier, O; Nicoleau, S; Rival, F; Sauvage, G; Thion, J; Van den Plas, D; Wingerter-Seez, I; Zitoun, R; Zolnierowski, Y; Chmeissani, M; Fernández, E; Garrido, L; Martínez, M; Padilla, C; Gordon, H A; Radeka, V; Rahm, David Charles; Stephani, D; Baisin, L; Berset, J C; Chevalley, J L; Gianotti, F; Gildemeister, O; Marin, C P; Nessi, Marzio; Poggioli, Luc; Richter, W; Vuillemin, V; Baze, J M; Gosset, L G; Lavocat, P; Lottin, J P; Mansoulié, B; Meyer, J P; Renardy, J F; Schwindling, J; Teiger, J; Collot, J; de Saintignon, P; Dzahini, D; Hostachy, J Y; Hoummada, A; Laborie, G; Mahout, G; Hervás, L; Chekhtman, A; Cousinou, M C; Dargent, P; Dinkespiler, B; Etienne, F; Fassnacht, P; Fouchez, D; Martin, L; Miotto, A; Monnier, E; Nagy, E; Olivetto, C; Tisserant, S; Battistoni, G; Camin, D V; Cavalli, D; Costa, G; Cozzi, L; Fedyakin, N N; Ferrari, A; Mandelli, L; Mazzanti, M; Perini, L; Resconi, S; Sala, P R; Beaudoin, G; Depommier, P; León-Florián, E; Leroy, C; Roy, P; Augé, E; Chase, Robert L; Chollet, J C; de La Taille, C; Fayard, Louis; Fournier, D; Hrisoho, A T; Merkel, B; Noppe, J M; Parrour, G; Pétroff, P; Schaffer, A C; Seguin-Moreau, N; Serin, L; Tisserand, V; Vichou, I; Canton, B; David, J; Genat, J F; Imbault, D; Le Dortz, O; Savoy-Navarro, Aurore; Schwemling, P; Eek, L O; Lund-Jensen, B; Söderqvist, J; Lefebvre, M; Robertson, S

1997-01-01

A separate liquid argon preshower detector consisting of two layers featuring a fine granularity of 2.5~10$^{\\mathrm{-3}}$ was studied by the RD3 collaboration. A prototype covering approximately 0.8 in pseudo-rapidity and 9 degrees in azimuth was built and tested at CERN in July 94. CMOS and GaAs VLSI preamplifiers were designed and tested for this occasion. The combined response of this detector and an accordion electromagnetic calorimeter prototype to muons, electrons and photons is presented. For minimum ionizing tracks a signal-to-noise ratio of 4.5 per preshower layer was measured. Above 150~GeV the space resolution for electrons is better than 250~$\\mu$m in both directions. The precision on the electromagnetic shower direction, determined together with the calorimeter, is better than 4 mrad above 50~GeV. It is concluded that the preshower detector would adequately fulfil its role for future operation at CERN Large Hadron Collider.

Projecting labor demand and worker immigration at nuclear power plant construction sites: an evaluation of methodology

International Nuclear Information System (INIS)

Herzog, H.W. Jr; Schlottmann, A.M.; Schriver, W.R.

1981-12-01

The study evaluates methodology employed for the projection of labor demand at, and worker migration to, nuclear power plant construction sites. In addition, suggestions are offered as to how this projection methodology might be improved. The study focuses on projection methodologies which forecast either construction worker migration or labor requirements of alternative types of construction activity. Suggested methodological improvements relate both to institutional factors within the nuclear power plant construction industry, and to a better use of craft-specific data on construction worker demand/supply. In addition, the timeliness and availability of the regional occupational data required to support, or implement these suggestions are examined

From research plots to prototype biomass plantations

Energy Technology Data Exchange (ETDEWEB)

Kenney, W.A.; Vanstone, B.J.; Gambles, R.L.; Zsuffa, L. [Univ. of Toronto, Ontario (Canada)

1993-12-31

The development of biomass energy plantations is now expanding from the research plot phase into the next level of development at larger scale plantings. This is necessary to provide: more accurate information on biomass yields, realistic production cost figures, venues to test harvesting equipment, demonstration sites for potential producers, and a supply of feedstock for prototype conversion facilities. The paper will discuss some of these objectives and some of the challenges encountered in the scale-up process associated with a willow prototype plantation project currently under development in Eastern Canada.

Countertransference as a Prototype: The Development of a Measure

Science.gov (United States)

Hofsess, Christy D.; Tracey, Terence J. G.

2010-01-01

Countertransference is a concept that is widely acknowledged, but there exists little definitional consensus, making research in the area difficult. The authors adopted a prototype theory (E. H. Rosch, 1973a, 1973b; see C. B. Mervis & E. Rosch, 1981, for a review) to examine this construct because it conceptually fits well with constructs that…

The Mark III vertex chamber and prototype test results

International Nuclear Information System (INIS)

Grab, C.

1987-07-01

A vertex chamber has been constructed for use in the Mark III experiment. The chamber is positioned inside the current main drift chamber and will be used to trigger data collection, to aid in vertex reconstruction, and to improve the momentum resolution. This paper discusses the chamber's construction and performance and tests of the prototype

Prototype tokamak fusion reactor based on SiC/SiC composite material focusing on easy maintenance

International Nuclear Information System (INIS)

Nishio, S.; Ueda, S.; Kurihara, R.; Kuroda, T.; Miura, H.; Sako, K.; Takase, H.; Seki, Y.; Adachi, J.; Yamazaki, S.; Hashimoto, T.; Mori, S.; Shinya, K.; Murakami, Y.; Senda, I.; Okano, K.; Asaoka, Y.; Yoshida, T.

2000-01-01

If the major part of the electric power demand is to be supplied by tokamak fusion power plants, the tokamak reactor must have an ultimate goal, i.e. must be excellent in construction cost, safety aspect and operational availability (maintainability and reliability), simultaneously. On way to the ultimate goal, the approach focusing on the safety and the availability (including reliability and maintainability) issues must be the more promising strategy. The tokamak reactor concept with the very high aspect ratio configuration and the structural material of SiC/SiC composite is compatible with this approach, which is called the DRastically Easy Maintenance (DREAM) approach. This is because SiC/SiC composite is a low activation material and an insulation material, and the high aspect ratio configuration leads to a good accessibility for the maintenance machines. As the intermediate steps along this strategy between the experimental reactor such as international thermonuclear experimental reactor (ITER) and the ultimate goal, a prototype reactor and an initial phase commercial reactor have been investigated. Especially for the prototype reactor, the material and technological immaturities are considered. The major features of the prototype and commercial type reactors are as follows. The fusion powers of the prototype and the commercial type are 1.5 and 5.5 GW, respectively. The major/minor radii for the prototype and the commercial type are of 12/1.5 m and 16/2 m, respectively. The plasma currents for the prototype and the commercial type are 6 and 9.2 MA, respectively. The coolant is helium gas, and the inlet/outlet temperatures of 500/800 and 600/900 deg. C for the prototype and the commercial type, respectively. The thermal efficiencies of 42 and 50% are obtainable in the prototype and the commercial type, respectively. The maximum toroidal field strengths of 18 and 20 tesla are assumed in the prototype and the commercial type, respectively. The thermal

Contribution of research and development and engineering to a large reprocessing plant project. Extension of the La Hague plant

International Nuclear Information System (INIS)

Boutaud de la Combe, P.; Courouble, J.M.; Sauteron, J.; Redon, A.

1983-01-01

Two reprocessing plants are operated by Cogema: Marcoule (since 1958) and La Hague (since 1967). Since 1976 the latter has been reprocessing LWR assemblies in its 'HAO' workshop, operation of which has provided industrial experience in the reprocessing of this type of fuel. This experience will be drawn upon in the construction of extensions to the La Hague plant, namely the UP3 plant, which will have a capacity of 800 t/a, and UP2-800, which will expand the present plant likewise to a capacity of 800 t/a. These extensions will contain a number of improvements, particularly in the areas of safety and waste treatment, and of procedure and equipment. A considerable R and D contribution is provided by the French Atomic Energy Commission (CEA), which is the licence holder, with its laboratories at Fontenay and the pilot workshop and industrial prototypes service at Marcoule. This activity supports all phases of the project, from the establishment of basic principles to the definition of essential characteristics of equipment, covering also the testing of full-scale prototypes (mock-ups) for the principal components: rotating continuous dissolver, swinging decanter, subcritical pulsed columns, used-solvent distilling apparatus, fission-product vitrification furnace, etc. Engineering work for the new facilities is performed by the Societe generale pour les techniques nouvelles in four phases: (1) establishment of basic data; (2) preparation of preliminary plans (including an estimate and a preliminary schedule) and of the preliminary safety reports; (3) drafting of the 'project' file, giving definitive costs and deadlines; (4) implementation, up to and including the operational testing stage. All phases of design and implementation are subject to a quality assurance programme. Extension of the La Hague plant represents an investment of 23,500 million French francs (in July 1981). Construction is expected to be completed in 1989. (author)

Prototype of generic server for wind power plants using IEC 61400-25 standard

DEFF Research Database (Denmark)

Olsen, Andreas K.; Ösdil, B.; Poulsen, Bjarne

2006-01-01

from interfaces for control and monitoring to a standardized and secure way of handling communication. An analysis focusing on isolating the necessary requirements has been carried out based on the IEC61400-25 in order to create a generic prototype which can be used by WPP vendors. The main...... communications interface of the prototype utilizes web services and the prototype developed is comprised of several independent modules to allow for the possibility of choosing a fully customizable setup by the end user. Configuration of the system needs to be done in a simple way, ensuring a flexible...... and reusable system, where different choices for the system can be added or left out depending on user specifications. From the requirements a prototype with the purpose of examining the key aspects of these definitions has been elaborated....

Needs for Constructing and Possibilities of Nuclear Power Plants Interconnection to the Croatian Electricity Grid

International Nuclear Information System (INIS)

Zeljko, M.; Bajs, D.

1998-01-01

Due to development of electric power system and considering an increase of electrical energy consumption, needs for larger units in new power plants are obvious. Connection of large nuclear power plants to the grid, depending on their power and location, usually requires significant investments in transmission network development and construction. Considering the capacity of the 400 kV transmission network in Croatia, this problem is evident. This paper deals with the possibilities of nuclear power plants construction, as one possible option in electric power system development, and their interconnection to the electricity grid. (author)

Design of micro-reactors and solar photocatalytic prototypes; Diseno de micro-reactores y prototipos fotocataliticos solares

Energy Technology Data Exchange (ETDEWEB)

Flores E, R.M.; Hernandez H, M.; Perusquia del Cueto, M.R.; Bonifacio M, J.; Jimenez B, J.; Ortiz O, H.B.; Castaneda J, G.; Lugo H, M. [ININ, Km. 36.5 Carr. Mexico-Toluca, 52750 La Marquesa, Ocoyoacac (Mexico)]. e-mail: rmfe@nuclear.inin.mx

2007-07-01

In the ININ is carried out research in heterogeneous photocatalysis using artificial light for to degrade organic compounds. In this context, it is sought to use the solar radiation as energy source to knock down costs. Of equal form it requires to link the basic and applied research. For it, a methodology that allows to design and to build micro-reactors and plants pilot has been developed, like previous step, to request external supports and to a future commercialization. The beginning of these works gave place to the partial construction of a prototype of photocatalytic reactor of the cylinder-parabolic composed type (CPC)

Utilizing Rapid Prototyping for Architectural Modeling

Science.gov (United States)

Kirton, E. F.; Lavoie, S. D.

2006-01-01

This paper will discuss our approach to, success with and future direction in rapid prototyping for architectural modeling. The premise that this emerging technology has broad and exciting applications in the building design and construction industry will be supported by visual and physical evidence. This evidence will be presented in the form of…

The Brazilian participation in the nuclear power plant construction

International Nuclear Information System (INIS)

Fabricio, R.A.C.

1981-01-01

A brief review about the origin of the brazilian nuclear power program and the strategy adopted for its implementation in Brazil is presented. The creation of the Nuclebras Engineering S/A, the Germany technology transfer and the personell job-training in Brasil are discussed. Some management models used for nuclear power plant construction in the world are still presented. (E.G.) [pt

Licensing for the construction of 'Almirante Alvaro Alberto' nuclear power plant

International Nuclear Information System (INIS)

1974-09-01

The BRAZILIAN NUCLEAR ENERGIA COMMISSION (Comissao Nacional de Energia Nuclear - CNEN) presents in Report n 0 51 of its Reactors Department all the requirements for the construction permit of 'Almirante Alvaro Alberto' Nuclear Power Plant [pt

Nuclear power plants: 2004 atw compact statistics

International Nuclear Information System (INIS)

Anon.

2005-01-01

In late 2004, nuclear power plants were available for power supply or were under construction in 32 countries worldwide. A total of 441 nuclear power plants, i.e. two plants more than in late 2003, were in operation with an aggregate gross power of approx. 386 GWe and an aggregate net power, respectively, of 362 GWe, in 31 countries. The available capacity of nuclear power plants increased by approx. 5 GWe as a result of the additions by the six units newly commissioned: Hamaoka 5 (Japan), Ulchin 6 (Korea), Kalinin 3 (Russia), Khmelnitski 2 (Ukraine), Qinshan II-2 (People's Republic of China), and Rowno 4 (Ukraine). In addition, unit 3 of the Bruce A nuclear power plant in Canada with a power of 825 MWe was restarted after an outage of many years. Contrary to earlier plans, a recommissioning program was initiated for the Bruce A-1 and A-2 units, which are also down at present. Five plants were decommissioned for good in 2004; Chapelcross 1 to 4 with 50 MWe each in the United Kingdom, and Ignalina 1 with 1 300 MWe in Lithuania. 22 nuclear generating units with an aggregate gross power of 19 GWe in nine countries were under construction in late 2004. In India, construction work was started on a new project, the 500 MWe PFBR prototype fast breeder reactor. In France, the EDF utility announced its intention to build an EPR on the Flamanville site beginning in 2007. (orig.)

AGROBACTERIUM-MEDIATED TRANSFORMATION OF COMPOSITAE PLANTS. I. CONSTRUCTION OF TRANSGENIC PLANTS AND «HAIRY» ROOTS WITH NEW PROPERTIES

Directory of Open Access Journals (Sweden)

N. A.Matvieieva

2013-02-01

Full Text Available The review explores some of the recent advances and the author's own researchs concerning biotechnological approaches for Agrobacterium tumefaciens- and A. rhizogenes-mediated transformation of Compositae family plants. This paper reviews the results of genetic transformation of Compositae plants, including edible (Cichorium intybus, Lactuca sativa, oil (Helianthus annuus, decorative (Gerbera hybrida, medical (Bidens pilosa, Artemisia annua, Artemisia vulgaris, Calendula officinalis, Withania somnifera etc. plant species. Some Compositae genetic engineering areas are considered including creation of plants, resistant to pests, diseases and herbicides, to the effect of abiotic stress factors as well as plants with altered phenotype. The article also presents the data on the development of biotechnology for Compositae plants Cynara cardunculus, Arnica montana, Cichorium intybus, Artemisia annua "hairy" roots construction.

Progressive building methods in nuclear power plant construction

International Nuclear Information System (INIS)

Sikura, V.

1980-01-01

A detailed description is given of the new prospective technologies used in the construction of the Bohunice V-1 nuclear power plant. They include the use of steel and large-area forms, the use of profile sheets as a substitute for forms, assembled raw partitions, wall shells consisting of clamped porous concrete slabs, assembled roof shells, special finish of concrete walls, bearing wall deep foundation, the use of modern building machinery for concreting, reinforcing and welding works. (M.S.)

State of the art and further development of reinforced concrete wall cells for nuclear power plant construction

International Nuclear Information System (INIS)

Uhlemann, E.; Wartenberg, J.

1985-01-01

Reinforced concrete wall cells have been developed for nuclear power plant construction by the USSR and GDR. In this article, a new type of these cells, which will be used for constructing auxiliary equipment of the Stendal nuclear power plant, is described

CORR Guidelines. Preparing and Conducting Review Missions of Construction Project Readiness for Nuclear Power Plants

International Nuclear Information System (INIS)

2013-01-01

The construction readiness review (CORR) mission for nuclear power plant projects has been established with the aim of conducting peer reviews of construction projects related to nuclear power plants. Such a mission provides a detailed assessment of readiness for construction, construction progress, readiness for turnover, as well as recommendations for improvement. Organizations in Member States, such as nuclear utilities, owners, regulators and technical support organizations, can benefit from such reviews. A team of international experts with complementing specialities will conduct the CORR mission. The review is based on appropriate IAEA publications, such as IAEA Safety Standards Series Guides and IAEA Nuclear Energy Series publications, as well as on internationally recognized project and construction management guides. Mission findings are summarized in a mission report, which includes a list of recommendations, suggestions and identified good practices. The review is not intended to be a regulatory inspection or an audit against international codes and standards. Rather, it is a peer review aimed at improving implementation processes and procedures through an exchange of technical experiences and practices at the working level. The mission is applicable at any stage of a nuclear power plant construction project, although two specific phases are targeted: (1) start of construction mission (Phase 1 mission) and (2) an in-progress mission (Phase 2 mission). Missions are initiated when official requests are submitted by Member States through the appropriate IAEA channels

Rapid prototyping of the Central Safety System for Nuclear Risk in ITER

Energy Technology Data Exchange (ETDEWEB)

Scibile, L. [ITER Organization, CS 90 046, St. Paul-lez-Durance, Cedex (France); Ambrosino, G. [Consorzio CREATE, Universita degli Studi di Napoli Federico II, via Claudio 21, 80125, Napoli (Italy); De Tommasi, G., E-mail: detommas@unina.i [Consorzio CREATE, Universita degli Studi di Napoli Federico II, via Claudio 21, 80125, Napoli (Italy); Pironti, A. [Consorzio CREATE, Universita degli Studi di Napoli Federico II, via Claudio 21, 80125, Napoli (Italy)

2010-07-15

The Central Safety System for Nuclear Risk (CSS-N) coordinates the safety control systems to ensure nuclear safety for the ITER complex. Since the CSS-N is a safety critical system, its validation and commissioning play a very important role; in particular the required level of reliability must be demonstrated. In such a scenario, it is strongly recommended to use modeling and simulation tools since the early design phase. Indeed, the modeling tools will help in the definition of the control system requirements. Furthermore the models can than be used for the rapid prototyping of the safety system. Hardware-in-the-loop simulations can also be performed in order to assess the performance of the control hardware against a plant simulator. The proposed approach relies on the availability of a plant simulator to develop the prototype of the control system. This paper introduces the methodology used to design and develop both the CSS-N Oriented Plant Simulator and the CSS-N Prototype.

Rapid prototyping of the Central Safety System for Nuclear Risk in ITER

International Nuclear Information System (INIS)

Scibile, L.; Ambrosino, G.; De Tommasi, G.; Pironti, A.

2010-01-01

The Central Safety System for Nuclear Risk (CSS-N) coordinates the safety control systems to ensure nuclear safety for the ITER complex. Since the CSS-N is a safety critical system, its validation and commissioning play a very important role; in particular the required level of reliability must be demonstrated. In such a scenario, it is strongly recommended to use modeling and simulation tools since the early design phase. Indeed, the modeling tools will help in the definition of the control system requirements. Furthermore the models can than be used for the rapid prototyping of the safety system. Hardware-in-the-loop simulations can also be performed in order to assess the performance of the control hardware against a plant simulator. The proposed approach relies on the availability of a plant simulator to develop the prototype of the control system. This paper introduces the methodology used to design and develop both the CSS-N Oriented Plant Simulator and the CSS-N Prototype.

Nuclear power plant construction and financial assistance - as regards subsidies for promotion of power plant siting

International Nuclear Information System (INIS)

Shindo, M.

1983-01-01

This paper describes the institutional framework for the granting of subsidies in particular to promote nuclear power plant construction in Japan. It also analyses the technical criteria applied and lists the type of improvements to various facilities and equipment made with such subsidies. (NEA) [fr

Micropole Undulators In Synchrotron Radiation Technology: Design And Construction Of A Submillimeter Period Prototype With A 3 Kilogauss Peak Field At SSRL

Science.gov (United States)

Tatchyn, Roman; Csonka, Paul

1986-01-01

The availability of undulators with submillimeter periods will profoundly affect the future development of soft x-ray sources and their attendant instrumentation. Outputs comparable to those of present-day conventional undulators, obtainable with much lower energy storage rings, is only one promising aspect of such devices. This paper critically examines some of the future prospects of such devices and describes the design and practical construction of a 1" long prototype consisting of 35 periods. A proposed experiment to test this device on a linac is described.

Micropole undulators in synchrotron radiation technology: Design and construction of a submillimeter period prototype with a 3 kilogauss peak field at SSRL

International Nuclear Information System (INIS)

Tatchyn, R.; Csonka, P.

1987-01-01

The availability of undulators with submillimeter periods profoundly affects the future development of soft x-ray sources and their attendant instrumentation. Outputs comparable to those of present-day conventional undulators, obtainable with much lower energy storage rings, is only one promising aspect of such devices. This paper critically examines some of the future prospects of such devices and describes the design and practical construction of a 1'' long prototype consisting of 35 periods. A proposed experiment to test this device on a linac is described

MPACT Fast Neutron Multiplicity System Prototype Development

Energy Technology Data Exchange (ETDEWEB)

D.L. Chichester; S.A. Pozzi; J.L. Dolan; M.T. Kinlaw; S.J. Thompson; A.C. Kaplan; M. Flaska; A. Enqvist; J.T. Johnson; S.M. Watson

2013-09-01

This document serves as both an FY2103 End-of-Year and End-of-Project report on efforts that resulted in the design of a prototype fast neutron multiplicity counter leveraged upon the findings of previous project efforts. The prototype design includes 32 liquid scintillator detectors with cubic volumes 7.62 cm in dimension configured into 4 stacked rings of 8 detectors. Detector signal collection for the system is handled with a pair of Struck Innovative Systeme 16-channel digitizers controlled by in-house developed software with built-in multiplicity analysis algorithms. Initial testing and familiarization of the currently obtained prototype components is underway, however full prototype construction is required for further optimization. Monte Carlo models of the prototype system were performed to estimate die-away and efficiency values. Analysis of these models resulted in the development of a software package capable of determining the effects of nearest-neighbor rejection methods for elimination of detector cross talk. A parameter study was performed using previously developed analytical methods for the estimation of assay mass variance for use as a figure-of-merit for system performance. A software package was developed to automate these calculations and ensure accuracy. The results of the parameter study show that the prototype fast neutron multiplicity counter design is very nearly optimized under the restraints of the parameter space.

Virtual Prototyping and Validation of Cpps within a New Software Framework

Directory of Open Access Journals (Sweden)

Sebastian Neumeyer

2017-02-01

Full Text Available As a result of the growing demand for highly customized and individual products, companies need to enable flexible and intelligent manufacturing. Cyber-physical production systems (CPPS will act autonomously in the future in an interlinked production and enable such flexibility. However, German mid-sized plant manufacturers rarely use virtual technologies for design and validation in order to design CPPS. The research project Virtual Commissioning with Smart Hybrid Prototyping (VIB-SHP investigated the usage of virtual technologies for manufacturing systems and CPPS design. Aspects of asynchronous communicating, intelligent- and autonomous-acting production equipment in an immersive validation environment, have been investigated. To enable manufacturing system designers to validate CPPS, a software framework for virtual prototyping has been developed. A mechatronic construction kit for production system design integrates discipline-specific models and manages them in a product lifecycle management (PLM solution. With this construction kit manufacturing designers are able to apply virtual technologies and the validation of communication processes with the help of behavior models. The presented approach resolves the sequential design process for the development of mechanical, electrical, and software elements and ensures the consistency of these models. With the help of a bill of material (BOM- and signal-based alignment of the discipline-specific models in an integrated mechatronic product model, the communication of the design status and changes are improved. The re-use of already-specified and -designed modules enable quick behavior modeling, code evaluation, as well as interaction with the virtualized assembly system in an immersive environment.

Design and construction of landslide preventive construction at Yamasubara hydroelectric power plant site. Yamasubata hatsudensho chiten ni okeru jisuberi taisaku koji no sekkei seko ni tsuite

Energy Technology Data Exchange (ETDEWEB)

Takase, H; Ito, M; Sakata, M [The Kyushu Electric Power Co. Inc., Fukuoka (Japan)

1993-07-30

This paper reports the design and construction of landslide preventive construction at the site of the Yamasubara hydroelectric power plant (with a maximum output of 40,700 kW) and the result of slope stability verification after completion of the construction. The moderate slope on top of the primary slide has sands presumed to be colluvial deposit distributed with a depth of 10 m or more, where occurrence of a secondary slip was feared as triggered by the primary slide. The power plant protective constructions consisted of concrete walls to protect the entire power plant including buildings, and falling stone protective fences installed around the surge tanks. The temporary measures were so set that groundwater levels are lowered to a level that can assure the slide safety factor of 1.0 or more by means of drain boring using the down-the-hole hammer type. The permanent protective construction used rock anchors that are superior in constructability and economy. The stability of sliding slope faces was verified to confirm effects of the protective constructions. The verification included observations of groundwater level behavior, water well-up from drain holes, and movements in the slopes. The result showed that the protective constructions have give sufficient effects. Continued slope stability control is important. 16 figs., 7 tabs.

The licensing procedure for construction and operation of nuclear power plants

International Nuclear Information System (INIS)

Salvatore, J.E.L.

1980-03-01

The licensing procedure for the construction and operation of the nuclear power plants in Brazil is analysed, according to the International Atomic Energy Agency orientation. The risks related to the nuclear energy is also emphasized. (A.L.) [pt

Mechatronic Prototype of Parabolic Solar Tracker.

Science.gov (United States)

Morón, Carlos; Díaz, Jorge Pablo; Ferrández, Daniel; Ramos, Mari Paz

2016-06-15

In the last 30 years numerous attempts have been made to improve the efficiency of the parabolic collectors in the electric power production, although most of the studies have focused on the industrial production of thermoelectric power. This research focuses on the application of this concentrating solar thermal power in the unexplored field of building construction. To that end, a mechatronic prototype of a hybrid paraboloidal and cylindrical-parabolic tracker based on the Arduido technology has been designed. The prototype is able to measure meteorological data autonomously in order to quantify the energy potential of any location. In this way, it is possible to reliably model real commercial equipment behavior before its deployment in buildings and single family houses.

Steam generators under construction for the SNR-300 power plant

Energy Technology Data Exchange (ETDEWEB)

Essebaggers, J

1975-07-01

The prototype straight tube and the helical coil-steam generator has been designed and fabricated of which the straight tube steam generator has been successfully tested for over 3000 hours at prototypical conditions and is presently being dismantled for detailed examination of critical designed features. The prototype helical coil steam generator is presently under testing in the 50 MWt test facility at TNO-Hengelo with approximately 500 hours of operation at full load conditions. In an earlier presentation the design and fabrication of the prototype steam generators have been presented, while for this presentation the production units for SNR-300 will be discussed. Some preliminary information will be presented at this meeting of the dismantling operations of the prototype straight tube steam generator. (author)

Steam generators under construction for the SNR-300 power plant

International Nuclear Information System (INIS)

Essebaggers, J.

1975-01-01

The prototype straight tube and the helical coil-steam generator has been designed and fabricated of which the straight tube steam generator has been successfully tested for over 3000 hours at prototypical conditions and is presently being dismantled for detailed examination of critical designed features. The prototype helical coil steam generator is presently under testing in the 50 MWt test facility at TNO-Hengelo with approximately 500 hours of operation at full load conditions. In an earlier presentation the design and fabrication of the prototype steam generators have been presented, while for this presentation the production units for SNR-300 will be discussed. Some preliminary information will be presented at this meeting of the dismantling operations of the prototype straight tube steam generator. (author)

The STEP standard as an approach for design and prototyping

OpenAIRE

Plantec , Alain; Ribaud , Vincent

1998-01-01

International audience; STEP is an ISO standard (ISO-10303) for the computer-interpretable representation and exchange of product data. Parts of STEP standardize conceptual structures and usage of information in generic or specific domains. The standardization process of these constructs is an evolutionary approach , which uses generated prototypes at different phases of the process. This paper presents a method for the building of prototype generators, inspired by this standardization proces...

Tool application CAD / CAM for design and construction of a prototype of plastic injection mold

Directory of Open Access Journals (Sweden)

Albert Miyer Suárez Castrillón

2015-11-01

Full Text Available The study, development and production of injection molds comes with the implementation of CAD and CAM tools available on the market; using these tools, a prototype injection mold for thermoplastic materials was designed and built, based on a mold is injection in the laboratory of the University of Pamplona, in which a couple of modifications were made in order to experiment with its design. The prototype was manufactured through a 3D scan of the original mold to provide the CAD / CAM files with the simulated 3D printing technique for performing an experimental study with the prototype for adjusting temperature and pressure sensors and for coatings metallic materials for use in the injection molding process.

The Brazilian experience in the civil construction of nuclear power plants

International Nuclear Information System (INIS)

Gonzaga, L.A.

1985-01-01

The processes and phases of technology absorption, together with the resultant Experience-Factor Model for civil Works, considering philosophy of operation of the civil contractor, design aspects and some structural influences for constructing nuclear power plants are presented. (Author) [pt

The Brazilian experience in the civil construction of nuclear power plants

International Nuclear Information System (INIS)

Gonzaga, L.A.

1985-01-01

The processes and phases of technology absorption, together with the resultant Experience Factor Model for Civil Works, considering philosophy of operation of the civil contractor, design aspects and some structural influences for constructing nuclear power plants are presented. (author) [pt

Deployment of a Prototype Plant GFP Imager at the Arthur Clarke Mars Greenhouse of the Haughton Mars Project

Directory of Open Access Journals (Sweden)

Robert J. Ferl

2008-04-01

Full Text Available The use of engineered plants as biosensors has made elegant strides in the past decades, providing keen insights into the health of plants in general and particularly in the nature and cellular location of stress responses. However, most of the analytical procedures involve laboratory examination of the biosensor plants. With the advent of the green fluorescence protein (GFP as a biosensor molecule, it became at least theoretically possible for analyses of gene expression to occur telemetrically, with the gene expression information of the plant delivered to the investigator over large distances simply as properly processed fluorescence images. Spaceflight and other extraterrestrial environments provide unique challenges to plant life, challenges that often require changes at the gene expression level to accommodate adaptation and survival. Having previously deployed transgenic plant biosensors to evaluate responses to orbital spaceflight, we wished to develop the plants and especially the imaging devices required to conduct such experiments robotically, without operator intervention, within extraterrestrial environments. This requires the development of an autonomous and remotely operated plant GFP imaging system and concomitant development of the communications infrastructure to manage dataflow from the imaging device. Here we report the results of deploying a prototype GFP imaging system within the Arthur Clarke Mars Greenhouse (ACMG an autonomously operated greenhouse located within the Haughton Mars Project in the Canadian High Arctic. Results both demonstrate the applicability of the fundamental GFP biosensor technology and highlight the difficulties in collecting and managing telemetric data from challenging deployment environments.

Construction of an experimental plot seeder of wheat planting and compare it by imported one

Directory of Open Access Journals (Sweden)

I Eskandari

2016-09-01

Full Text Available Introduction Researchers frequently include multiple cultivars and fertility levels in field experiments. Therefore, the experiments sowing operation must represent a considerable saving in time and labor, compared to hand sowing. Greater flexibility in experimental design and setup could be achieved by equipment that enables quick changes in the cultivar and fertilizer rates from one plot to the next. A satisfactory seed drill must distribute a given quantity of seed evenly over a predetermined length of coulter row, the coulters must be spaced at exact intervals and depth of sowing must be uniform. In a self-propelled type of plot seeder, no coulter should run in a wheel track as the compaction of the soil can cause observable differences in vigor between plants in such a row and those in un-compacted rows. The machine should sow in succession from a try in which a series of seed pocket separated clearly and must be put into distributer funnel by an assistant operator. The length of gap being varied according to the nature and purpose of the plot. The objectives of this experiment were 1- to design and construct a local self-propelled plot seeder and 2- To compare it with the imported (Wintersteiger plot seeder in cereal breeding programs. Materials and Methods A small-plot seeder was designed and constructed to meet this objective. The unit consists of the following basic components: a toolbar for pulling a set of six blade coulter, an air compressor for lifting and putting down the openers and metering transmission drive wheel, an operators chair and work rack, one belt seed distribution. A cone-celled and rotor seed distributor is used for seed distribution to the openers. The cone system is connected to the gearbox and allows for great flexibility in changing cultivars, crop species, and plot length. This is driven by the separate drive wheel. The cone-celled distributor sows all the seed of the sample in making one complete turn. The

Power plant construction lead times: The value of contingency planning

International Nuclear Information System (INIS)

Rubin, L.J.

1985-01-01

In this paper an analysis of two different approaches to the construction of a major power plant (nuclear) is presented. The analysis compares an accelerated, ''go-for-broke'' strategy-which has some risk of being delayed-with a more deliberate contingency construction schedule in terms of revenue requirements and costs of electricity. It is demonstrated that under a wide variety of circumstances there are important advantages to the contingency strategy, but that the magnitude of those advantages is sensitive to the character of the power system being examined and to the flexibility of the contingency approach

Hanford prototype-barrier status report: FY 1995

International Nuclear Information System (INIS)

Gee, G.W.; Ward, A.L.; Gilmore, B.G.; Ligotke, M.W.; Link, S.O.

1995-11-01

Surface barriers (or covers) have been proposed for use at the Hanford Site as a means to isolate certain waste sites that, for reasons of cost or worker safety or both, may not be exhumed. Surface barriers are intende to isolated the wastes from the accessible environment and to provide long-term protection to future populations that might use the Hanford Site. Currently, no ''proven'' long-term barrier system is available. For this reason, the Hanford Site Permanent Isolation Surface-Barrier Development Program (BDP) was organized to develop the technology needed to provide long-term surface barrier capability for the Hanford Site for the US Department of Energy (DOE). Designs have been proposed to meet the most stringent needs for long-term waste disposal. The objective of the current barrier design is to use natural materials to develop a protective barrier system that isolates wastes for at least 1000 years by limiting water, plant, animal, and human intrusion; and minimizing erosion. The design criteria for water drainage has been set at 0.5 mm/yr. While other design criteria are more qualitative, it is clear that waste isolation for an extended time is the prime objective of the design. Constructibility and performance. are issues that can be tested and dealt with by evaluating prototype designs prior to extensive construction and deployment of covers for waste sites at Hanford

Natural and construction materials and plant products. Raw materials, constructional physics, design and construction. 2. upd. and enl. ed.; Natuerliche und pflanzliche Baustoffe. Rohstoff - Bauphysik - Konstruktion

Energy Technology Data Exchange (ETDEWEB)

Holzmann, Gerhard; Wangelin, Matthias; Bruns, Rainer

2012-07-01

The book discusses all relevant renewable constructional materials made from fibre or dyeing plants along with their physical and chemical fundamentals. Protection of resources, environmental protection, and pollutants in constructional materials are gone into as well. [German] Dieses Buch behandelt alle wichtige nachwachsenden, pflanzlichen Baustoffe aus Faser- und Faerberpflanzen sowie dazugehoerige physikalische und chemische Grundlagen. Angesprochen werden auch Ressourcen- und Umweltschutz sowie Schadstoffe aus Bauprodukten.

Geopolymerisation of silt generated from construction and demolition waste washing plants.

Science.gov (United States)

Lampris, C; Lupo, R; Cheeseman, C R

2009-01-01

Recycling plants that size, sort and wash construction and demolition waste can produce high quality aggregate. However, they also produce up to 80ton per hour of filter cake waste containing fine (waste and normally landfilled. This research investigated the potential to form geopolymers containing silt, which would allow this problematic waste to be beneficially reused as aggregate. This would significantly improve the economic viability of recycling plants that wash wastes. Silt filter cakes have been collected from a number of aggregate washing plants operating in the UK. These were found to contain similar aluminosilicate crystalline phases. Geopolymer samples were produced using silt and silt mixed with either metakaolin or pulverised fuel ash (PFA). Silt geopolymers cured at room temperature had average 7-day compressive strengths of 18.7MPa, while partial substitution of silt by metakaolin or PFA increased average compressive strengths to 30.5 and 21.9MPa, respectively. Curing specimens for 24h at 105 degrees C resulted in a compressive strength of 39.7MPa and microstructural analysis confirmed the formation of dense materials. These strengths are in excess of those required for materials to be used as aggregate, particularly in unbound applications. The implications of this research for the management of waste silt at construction and demolition waste washing plants are discussed.

'Concrete shell formwork' technology applied to the construction of the Paks Nuclear Power Plant

International Nuclear Information System (INIS)

Fejes, A.

1982-01-01

The conventional formworking technology could not meet the unusual requirements needed in constructing the concrete walls of the nuclear power plant building. A new concrete shell formworking developed in the Soviet Union has been adapted to meet the criteria. Prefabricated concrete shells are mounted separately during construction on separated parts of the reinforcing structure. The steps of the construction process are described with the economic evaluation of this new construction technology. (R.P.)

Summary report on safety and licensing strategy support for the ABR prototype

International Nuclear Information System (INIS)

Cahalan, J. E.; Nuclear Engineering Division

2007-01-01

Argonne National Laboratory is providing support to the US Department of Energy in the Global Nuclear Energy Partnership (GNEP) in certification of an advanced, sodium-cooled fast reactor. The reactor is to be constructed as a prototype for future commercial power reactors that will produce electricity while consuming actinides recovered from light water reactor spent fuel. This prototype reactor has been called the Advanced Burner Reactor, or ABR, and is now often referred to as the advanced recycle reactor. As part of its activities, Argonne is providing technical services to assist definition of a safety and licensing strategy for the ABR prototype, and to further implementation of the strategy. In FY06, an organizational meeting was held for DOE and its laboratory contractors to discuss licensing alternatives and review previous licensing experience for the Fast Flux Test Facility (FFTF) and the Clinch River Breeder Reactor Plant (CRBRP). Near the end of FY06, a report summarizing the discussions and conclusions was written. One of the top-level conclusions recorded in the report was a recommendation to follow a licensing strategy that included the US Nuclear Regulatory Commission (NRC) as the regulatory review and licensing authority. In FY07, activities ar Argonne to support safety and licensing progress have continued. These activities have focused on further evaluation of licensing alternatives; assessment of design, analysis, and documentation implications of licensing paths; and initial technical interactions with the Nuclear Regulatory Commission. This report summarizes FY07 activities

Architectures of prototypes and architectural prototyping

DEFF Research Database (Denmark)

Hansen, Klaus Marius; Christensen, Michael; Sandvad, Elmer

1998-01-01

together as a team, but developed a prototype that more than fulfilled the expectations of the shipping company. The prototype should: - complete the first major phase within 10 weeks, - be highly vertical illustrating future work practice, - continuously live up to new requirements from prototyping......This paper reports from experience obtained through development of a prototype of a global customer service system in a project involving a large shipping company and a university research group. The research group had no previous knowledge of the complex business of shipping and had never worked...... sessions with users, - evolve over a long period of time to contain more functionality - allow for 6-7 developers working intensively in parallel. Explicit focus on the software architecture and letting the architecture evolve with the prototype played a major role in resolving these conflicting...

Collaborative Prototyping

DEFF Research Database (Denmark)

Bogers, Marcel; Horst, Willem

2014-01-01

of the prototyping process, the actual prototype was used as a tool for communication or development, thus serving as a platform for the cross-fertilization of knowledge. In this way, collaborative prototyping leads to a better balance between functionality and usability; it translates usability problems into design......This paper presents an inductive study that shows how collaborative prototyping across functional, hierarchical, and organizational boundaries can improve the overall prototyping process. Our combined action research and case study approach provides new insights into how collaborative prototyping...... can provide a platform for prototype-driven problem solving in early new product development (NPD). Our findings have important implications for how to facilitate multistakeholder collaboration in prototyping and problem solving, and more generally for how to organize collaborative and open innovation...

The design and construction of the windscale vitrification plant and vitrified product store

International Nuclear Information System (INIS)

Heafield, W.; Woodall, A.; Elsden, A.D.

1987-01-01

The paper describes the background of High Level Waste storage and vitrification development in the UK and its application to Reprocessing Operations at Sellafield. The main stages in the vitrification process and associated maintenance facilities are described together with the layout of the Windscale Vitrification Plant (WVP) and associated Vitrified Product Store (VPS). The design and construction techniques employed for example, the use of Computer Aided Design and the effect of automatic pipe bending/orbital welding and the use of precast units for cell construction, are discussed and current construction progress is highlighted. The vitrification process uses complex mechanical plant operating in high temperature and radiation fields. An extensive engineering and process development programme has been carried out. A full scale inactive facility (FSIF) has been constructed and the objectives and results from the operation of FSIF are presented. In addition to engineering and process development, a comprehensive programme of glass technology development has been carried out to establish maximum waste incorporation levels, reaction kinetic and product properties of the candidate glass formulations

Annual technical report of the prototype fast breeder reactor Monju. 2012

International Nuclear Information System (INIS)

2013-09-01

The prototype fast breeder reactor Monju has accumulated technical achievements in order to establish the fast breeder reactor cycle technology in Japan using the operation and maintenance experience, etc. This annual report summarizes the primary achievements and the data related to the plant management in Monju during fiscal 2012. From the aspect of the design evaluation, the following items are summarized: 1) Comprehensive safety assessments of Monju taking into account the accident at Fukushima Daiichi Nuclear Power Station of Tokyo Electric Power Company, 2) Evaluation of nuclear characteristics based on the data of core confirmation test, 3) Evaluation of hydrogen flux from steam generator tubes, 4) Construction of the advanced safeguards system, 5) Development of a plant dynamics analytical model for the Monju ex-vessel fuel storage system. Then, from the aspect of the maintenance technology, the following items are summarized: 1) Response to the administrative order to the defect of maintenance management, 2) Recovery of in vessel transfer machine dropping accident, 3) Work management by introduction of packaged isolation, 4) Evaluation of result of vibration control of RID sampling blower for secondary sodium loop. Furthermore, from the aspect of the plant management, this report summarizes the data related to the main topics, the history of plant condition, the sodium and water purity management, the radioactive waste management, the equipment inspection and so on. (author)

Construction risks of nuclear power plants for use in cost-effectiveness considerations

International Nuclear Information System (INIS)

Bock-Werthmann, W.

1986-08-01

The construction risk study is concerned with a nuclear power station of 1300 MW(e) design output. The risk figures obtained demonstrate that construction risks of nuclear power plants form a substantial share of the total risk from all steps of the nuclear fuel cycle. When compared with other risk figures it is apparent that only the fatalities caused by the extraction of uranium are of similar magnitude. (55 references). (DG)

Plant dynamics studies towards design of plant protection system for PFBR

Energy Technology Data Exchange (ETDEWEB)

Natesan, K., E-mail: natesan@igcar.gov.in [Nuclear and Safety Engineering Group, Indira Gandhi Centre for Atomic Research, Kalpakkam 603 102 (India); Kasinathan, N.; Velusamy, K.; Selvaraj, P.; Chellapandi, P. [Nuclear and Safety Engineering Group, Indira Gandhi Centre for Atomic Research, Kalpakkam 603 102 (India)

2012-09-15

Highlights: Black-Right-Pointing-Pointer Analysis of various design basis events in a fast breeder reactor towards design of plant protection system. Black-Right-Pointing-Pointer Plant dynamic modeling of a sodium cooled fast breeder reactor. Black-Right-Pointing-Pointer Selection of optimum set of plant parameters for considering best plant availability. - Abstract: Prototype fast breeder reactor (PFBR) is a 500 MWe (1250 MWt) liquid sodium cooled pool type reactor currently under construction in India. For a safe and efficient operation of the plant, it is necessary that the reactor is protected from all the transients that may occur in the plant. In order to accomplish this, adequate number of SCRAM parameters is required in the plant protection system with reliable instrumentation. For identifying the SCRAM parameters, the neutronic and thermal hydraulic responses of the plant for various possible events need to be established. Towards this, a one dimensional plant dynamics code DYANA-P has been developed with thermal hydraulic models for reactor core, hot and cold pools, intermediate heat exchangers, pipelines, steam generator, primary sodium circuits and secondary sodium circuits. The code also incorporates neutron kinetics and reactivity feedback models. By a comprehensive plant dynamics study an optimum list of SCRAM parameters and the maximum permissible response time for various instruments used for deriving them have been arrived at.

The use of halophytic plants for salt phytoremediation in constructed wetlands.

Science.gov (United States)

Farzi, Abolfazl; Borghei, Seyed Mehdi; Vossoughi, Manouchehr

2017-07-03

This research studied the use of constructed wetlands (CWs) to reduce water salinity. For this purpose, three halophytic species of the Chenopodiaceae family (Salicornia europaea, Salsola crassa, and Bienertia cycloptera) that are resistant to saline conditions were planted in the CWs, and experiments were conducted at three different salinity levels [electrical conductivity (EC)∼2, 6, 10 dS/m]. EC and concentrations of calcium (Ca), magnesium (Mg), sodium (Na), and chlorine (Cl) were measured before and after phytoremediation with a retention time of 1 week. The results suggested that these plants were able to grow well and complete their life cycles at all the salinity levels within this study. Moreover, these plants reduced the measured parameters to acceptable levels. Therefore, these plants can be considered good options for salt phytoremediation.

Case study: Proposed application of project management techniques for construction of nuclear power plant in Malaysia

International Nuclear Information System (INIS)

Syahirah Abdul Rahman; Phongsakorn Prak Tom; Wan Abd Hadi Wan Abu Bakar; Shaharum Ramli

2010-01-01

This study discusses the techniques of project management for the construction of nuclear power plants that can be used in Malaysia. Nuclear power reactors are expected to apply is the categories of Gen III + reactor where it is safer and more modern than the first generation of reactors built in the 1970s. The objective of this study is that the construction of this reactor to be completed by the stipulated time and not exceed the cost estimates. In addition, project management is also able to meet all the specifications and achieve the quality standard. In this study, the techniques used in project management to ensure the success of construction projects of nuclear power plants are a Gantt Chart, CPM/ PERT and Microsoft Project. From the study, found that these techniques can assist in facilitating the management of the project for the construction of nuclear power plants to ensure that the estimated time and cost can be managed more effectively as well as quality of care. (author)

Development of a prototype graphic simulation program for severe accident training

Energy Technology Data Exchange (ETDEWEB)

Kim, Ko Ryu; Jeong, Kwang Sub; Ha, Jae Joo

2000-05-01

This is a report of the development process and related technologies of severe accident graphic simulators, required in industrial severe accident management and training. Here, we say 'a severe accident graphic simulator' as a graphics add-in system to existing calculation codes, which can show the severe accident phenomena dynamically on computer screens and therefore which can supplement one of main defects of existing calculation codes. With graphic simulators it is fairly easy to see the total behavior of nuclear power plants, where it was very difficult to see only from partial variable numerical information. Moreover, the fast processing and control feature of a graphic simulator can give some opportunities of predicting the severe accident advancement among several possibilities, to one who is not an expert. Utilizing graphic simulators' we expect operators' and TSC members' physical phenomena understanding enhancement from the realistic dynamic behavior of plants. We also expect that severe accident training course can gain better training effects using graphic simulator's control functions and predicting capabilities, and therefore we expect that graphic simulators will be effective decision-aids tools both in sever accident training course and in real severe accident situations. With these in mind, we have developed a prototype graphic simulator having surveyed related technologies, and from this development experiences we have inspected the possibility to build a severe accident graphic simulator. The prototype graphic simulator is developed under IBM PC WinNT environments and is suited to Uljin 3and4 nuclear power plant. When supplied with adequate severe accident scenario as an input, the prototype can provide graphical simulations of plant safety systems' dynamic behaviors. The prototype is composed of several different modules, which are phenomena display module, MELCOR data interface module and graphic database

Rethink! prototyping transdisciplinary concepts of prototyping

CERN Document Server

Nagy, Emilia; Stark, Rainer

2016-01-01

In this book, the authors describe the findings derived from interaction and cooperation between scientific actors employing diverse practices. They reflect on distinct prototyping concepts and examine the transformation of development culture in their fusion to hybrid approaches and solutions. The products of tomorrow are going to be multifunctional, interactive systems – and already are to some degree today. Collaboration across multiple disciplines is the only way to grasp their complexity in design concepts. This underscores the importance of reconsidering the prototyping process for the development of these systems, particularly in transdisciplinary research teams. “Rethinking Prototyping – new hybrid concepts for prototyping” was a transdisciplinary project that took up this challenge. The aim of this programmatic rethinking was to come up with a general concept of prototyping by combining innovative prototyping concepts, which had been researched and developed in three sub-projects: “Hybrid P...

Prototype plant for nuclear process heat (PNP), reference phase

International Nuclear Information System (INIS)

Fladerer, R.; Schrader, L.

1982-07-01

The coal gasification processes using nuclear process heat being developed within the framwork of the PNP project, have the advantages of saving feed coal, improving efficiency, reducing emissions, and stabilizing energy costs. One major gasification process is the hydrogasification of coal for producing SNG or gas mixture of carbon monoxide and hydrogen; this process can also be applied in a conventional route. The first steps to develop this process were planning, construction and operation of a semi-technical pilot plant for hydrogasification of coal in a fluidized bed having an input of 100 kg C/h. Before the completion of the development phase (reference phase) describing here, several components were tested on part of which no operational experience had so far been gained; these were the newly developed devices, e.g. the inclined tube for feeding coal into the fluidized bed, and the raw gas/hydrogenation gas heat exchanger for utilizing the waste heat of the raw gas leaving the gasifier. Concept optimizing of the thoroughly tested equipment parts led to an improved operational behaviour. Between 1976 and 1980, the semi-technical pilot plant was operated for about 19,400 hours under test conditions, more than 7,400 hours of which it has worked under gasification conditions. During this time approx. 1,100 metric tons of dry brown coal and more than 13 metric tons of hard coal were gasified. The longest coherent operational phase under gasification conditions was 748 hours in which 85.4 metric tons of dry brown coal were gasified. Carbon gasification rates up to 82% and methane contents in the dry raw gas (free of N 2 ) up to 48 vol.% were obtained. A detailed evaluation of the test results provided information of the results obtained previously. For the completion of the test - primarily of long-term tests - the operation of the semi-technical pilot plant for hydrogasification of coal is to be continued up to September 1982. (orig.) [de

Evaluation of Computer-Based Procedure System Prototype

Energy Technology Data Exchange (ETDEWEB)

Johanna Oxstrand; Katya Le Blanc; Seth Hays

2012-09-01

relevant for the task and situation at hand, which has potential consequences of taking up valuable time when operators must be responding to the situation, and potentially leading operators down an incorrect response path. Other challenges related to PBPs are the management of multiple procedures, place-keeping, finding the correct procedure for the task at hand, and relying on other sources of additional information to ensure a functional and accurate understanding of the current plant status (Converse, 1995; Fink, Killian, Hanes, & Naser, 2009; Le Blanc & Oxstrand, 2012). The main focus of this report is to describe the research activities conducted to address the remaining two objectives; Develop a prototype CBP system based on requirements identified and Evaluate the CBP prototype. The emphasis will be on the evaluation of an initial CBP prototype in at a Nuclear Power Plant.

Controls and interlocks for a prototype 1MHz beam chopper

International Nuclear Information System (INIS)

Waters, G.; Bishop, D.; Barnes, M.J.; Wait, G.D.

1991-05-01

A prototype 1 MHz beam chopper for the proposed KAON Factory at TRIUMF has been constructed. The chopper is an electric field device, driven by a tetrode based pulser, for deflecting a charged particle beam. Associated with the tetrode used in the prototype design are high voltage power supplies for the electrodes. We use an FET based grid pulser and a sequencer capable of accurate digital control of pulse timing to 0.4 ns. A safety interlock and control system using a programmable controller with fibre optic links has been built. This has given us the versatility required in a prototype system. (Author) 4 refs., 5 figs

Operation management of the prototype heavy water reactor 'Fugen'

Energy Technology Data Exchange (ETDEWEB)

Muramatsu, Akira; Takei, Hiroaki; Iwanaga, Shigeru; Noda, Masao; Hara, Hidemi (Power Reactor and Nuclear Fuel Development Corp., Tokyo (Japan))

1983-09-01

The advanced thermal reactor Fugen power station has continued almost smooth operation since it began the full scale operation as the first homemade power reactor in Japan in March, 1979. In the initial period of operation, some troubles were experienced, but now, it can be said that the operational techniques of heavy water-moderated, boiling light water-cooled, pressure tube type reactors have been established, through the improvement of the operational method and equipment, and the operational experience. Also, the verification of the operational ability, maintainability, reliability and safety of this new type reactor, that is the mission of the prototype reactor, achieved steadily the good results. Hereafter, the verification of operational performance is the main objective because it is required for the design, construction and operation of the demonstration reactor. The organization for the operation management and operation, the communication at the time of the abnormality, the operation of the plant, that is, start up, stop and the operation at the rated output, the works during plant stoppage, the operation at the time of the plant abnormality, the operation of waste treatment facility and others, the improvement of the operational method, and the education and training of operators are reported.

THREE-DIMENSIONAL GEOFILTRATIONAL MODEL OF THE ROGUN HYDRO POWER PLANT CONSTRUCTION SITE

Directory of Open Access Journals (Sweden)

Khokhotva Sergey Nikolaevich

2017-05-01

Full Text Available The article deals with technique of creation and results of calculations of the three-dimensional geofiltrational model of the Rogun HPP construction site. When performing works on creation of the Rogun HPP three-dimensional geofiltration model, geological and hydrogeological conditions of the Rogun HPP construction site were analyzed. They showed that the construction site consists mostly of fractured rocks of various weathering degrees. In terms of preservation, four preservation zones were identified in the rock mass. These zones define the features of hydrogeological conditions that have emerged in the area of construction. Calculation results illustrated the absence of seepage areas on the lower slope of dam; this is the indication of normal operation of the dam impervious circuit. The drainage system of the underground hydropower plant has a high efficiency. Operation of the drainage galleries complex leads to a significant reduction of piezometric pressure on roofs of the machine and transformer halls. Above the underground structures a completely drained area is formed. Completed forecast calculations on geofiltration model of the Rogun hydropower plant determine the hydrostatic pressure and piezometric pressure at any point of the modeled area. These data can be used as loads while designing of lining of underground workings.

Worldwide construction

International Nuclear Information System (INIS)

Williamson, M.

1994-01-01

The paper lists major construction projects in worldwide processing and pipelining, showing capacities, contractors, estimated costs, and time of construction. The lists are divided into refineries, petrochemical plants, sulfur recovery units, gas processing plants, pipelines, and related fuel facilities. This last classification includes cogeneration plants, coal liquefaction and gasification plants, biomass power plants, geothermal power plants, integrated coal gasification combined-cycle power plants, and a coal briquetting plant

Big five general contractors dominate civil construction market of nuclear power plants

International Nuclear Information System (INIS)

Anon.

1985-01-01

The Japanese construction industry is a key industry accounting for about 20 % of the GNP, and the investment in construction amounted to 51,200 billion yen in fiscal 1984. 515,000 firms employing about 5.5 million workers belong to the industry. 99.4 % of these firms is the enterprises capitalized at less than 100 million yen, and most of them are small self-employment enterprises. The Construction Business Law provides that those who wish to engage in construction are required to obtain a permit from the Construction Ministry or from a local prefectural governor. There are big five and seven sub-major construction companies in Japan. The big five formed the tie-up relations with three nuclear reactor manufacturers. 76 civil engineering and construction companies recorded the sales related to nuclear power in 1983 amounting to 330.9 billion yen, equivalent to 21 % of the total nuclear-related sales. The construction of nuclear power plants and the characteristics of the construction, and the activities of the big five in the field of nuclear industry are reported. (Kako, I.)

Mechatronic Prototype of Parabolic Solar Tracker

Directory of Open Access Journals (Sweden)

Carlos Morón

2016-06-01

Full Text Available In the last 30 years numerous attempts have been made to improve the efficiency of the parabolic collectors in the electric power production, although most of the studies have focused on the industrial production of thermoelectric power. This research focuses on the application of this concentrating solar thermal power in the unexplored field of building construction. To that end, a mechatronic prototype of a hybrid paraboloidal and cylindrical-parabolic tracker based on the Arduido technology has been designed. The prototype is able to measure meteorological data autonomously in order to quantify the energy potential of any location. In this way, it is possible to reliably model real commercial equipment behavior before its deployment in buildings and single family houses.

Construction works of large scale impervious wall in construction of No.2 plant in Onagawa Nuclear Power Station, Tohoku Electric Power Co., Inc

International Nuclear Information System (INIS)

Ueda, Kozaburo; Sugeno, Yoshisada; Takahashi, Hitoshi

1991-01-01

The main buildings for No. 2 plant in Onagawa Nuclear Power Station are constructed on the bedrocks about 14 m below the sea surface. Therefore, for the purpose of executing the works by shutting seawater off and dry work, the large scale impervious wall of about 500 m extension was installed underground. The feature of this impervious wall is the depth of embedment of about 3 m into the hard bedrocks having the uniaxial compressive strength of 2000 kg/cm 2 at maximum, carried out with the newly developed hard rock excavator. The outline of these construction works is reported. No. 2 plant in Onagawa Nuclear Power Station is the BWR plant of 825 MWe output. The construction works of the power station were began in August, 1989, and the rate of progress in civil engineering works as of the end of September, 1990 was 21.3%. The planning of the impervious wall, the geological features at the site, the method of shutting seawater off, the selection of wall materials, the design of the wall body, the investigation of the quantity of spring water, the execution of the construction and execution management, and the confirmation of the effect of the wall are reported. (K.I.)

A room-temperature liquid calorimeter prototype for the SSC

International Nuclear Information System (INIS)

Brandenburg, G.W.; Geer, S.H.; Oliver, J.; Sadowski, E.; Theriot, D.

1990-01-01

Calorimeters will be an extremely important part of SSC detectors as they have been in existing collider detectors. The main issues that need to be addressed are: (1) energy resolution of jets and electrons, (2) segmentation, (3) hermiticity, (4) response time, and (5) radiation resistance. An attractive possibility on all these counts is the use of room-temperature liquids together with uranium, as pioneered by UA1. The authors are planning a prototype calorimeter which consists of a sealed vessel containing both the radiator plates and the readout pads. This geometry has been appropriately named the swimming pool design. The general mechanical starting point is similar to the SLD liquid argon calorimeters. The points they wish to address are the following: (1) Simple and reliable modular construction techniques, (2) Satisfactory electrical connections with minimal geometric impact, (3) The necessity of isolating radiator plates and liquid to maintain purity, (4) What materials can be immersed without compromising the liquid purity. The design and construction of the swimming pool electromagnetic calorimeter prototype is being carried out at the Harvard High Energy Physics Laboratory. This is one of the first attempts to build a full-scale prototype of such a design

Plant X-tender: An extension of the AssemblX system for the assembly and expression of multigene constructs in plants

Science.gov (United States)

Machens, Fabian; Coll, Anna; Baebler, Špela; Messerschmidt, Katrin; Gruden, Kristina

2018-01-01

Cloning multiple DNA fragments for delivery of several genes of interest into the plant genome is one of the main technological challenges in plant synthetic biology. Despite several modular assembly methods developed in recent years, the plant biotechnology community has not widely adopted them yet, probably due to the lack of appropriate vectors and software tools. Here we present Plant X-tender, an extension of the highly efficient, scar-free and sequence-independent multigene assembly strategy AssemblX, based on overlap-depended cloning methods and rare-cutting restriction enzymes. Plant X-tender consists of a set of plant expression vectors and the protocols for most efficient cloning into the novel vector set needed for plant expression and thus introduces advantages of AssemblX into plant synthetic biology. The novel vector set covers different backbones and selection markers to allow full design flexibility. We have included ccdB counterselection, thereby allowing the transfer of multigene constructs into the novel vector set in a straightforward and highly efficient way. Vectors are available as empty backbones and are fully flexible regarding the orientation of expression cassettes and addition of linkers between them, if required. We optimised the assembly and subcloning protocol by testing different scar-less assembly approaches: the noncommercial SLiCE and TAR methods and the commercial Gibson assembly and NEBuilder HiFi DNA assembly kits. Plant X-tender was applicable even in combination with low efficient homemade chemically competent or electrocompetent Escherichia coli. We have further validated the developed procedure for plant protein expression by cloning two cassettes into the newly developed vectors and subsequently transferred them to Nicotiana benthamiana in a transient expression setup. Thereby we show that multigene constructs can be delivered into plant cells in a streamlined and highly efficient way. Our results will support faster

Plant X-tender: An extension of the AssemblX system for the assembly and expression of multigene constructs in plants.

Science.gov (United States)

Lukan, Tjaša; Machens, Fabian; Coll, Anna; Baebler, Špela; Messerschmidt, Katrin; Gruden, Kristina

2018-01-01

Cloning multiple DNA fragments for delivery of several genes of interest into the plant genome is one of the main technological challenges in plant synthetic biology. Despite several modular assembly methods developed in recent years, the plant biotechnology community has not widely adopted them yet, probably due to the lack of appropriate vectors and software tools. Here we present Plant X-tender, an extension of the highly efficient, scar-free and sequence-independent multigene assembly strategy AssemblX, based on overlap-depended cloning methods and rare-cutting restriction enzymes. Plant X-tender consists of a set of plant expression vectors and the protocols for most efficient cloning into the novel vector set needed for plant expression and thus introduces advantages of AssemblX into plant synthetic biology. The novel vector set covers different backbones and selection markers to allow full design flexibility. We have included ccdB counterselection, thereby allowing the transfer of multigene constructs into the novel vector set in a straightforward and highly efficient way. Vectors are available as empty backbones and are fully flexible regarding the orientation of expression cassettes and addition of linkers between them, if required. We optimised the assembly and subcloning protocol by testing different scar-less assembly approaches: the noncommercial SLiCE and TAR methods and the commercial Gibson assembly and NEBuilder HiFi DNA assembly kits. Plant X-tender was applicable even in combination with low efficient homemade chemically competent or electrocompetent Escherichia coli. We have further validated the developed procedure for plant protein expression by cloning two cassettes into the newly developed vectors and subsequently transferred them to Nicotiana benthamiana in a transient expression setup. Thereby we show that multigene constructs can be delivered into plant cells in a streamlined and highly efficient way. Our results will support faster

The Atomics International (AI) prototype large breeder reactor (PLBR)

International Nuclear Information System (INIS)

McDonald, J.S.; Campise, A.V.; Brunings, J.

1978-01-01

The AI-PLBR breeder plant design prepared for ERDA and EPRI is of 1000 MWe size, utilizing a loop-type sodium system configuration and producing 2200 psig/850 0 F steam. A 'bullseye' core geometry type sodium system configuration and is employed with Pu0 2 -UO 2 fuel and UO 2 fertile material. The reactor outlet coolant temperature is 930 0 F. A modified 'A'-frame refueling system is employed, which is capable of handling 1/3 of a core loading in 12 days. An inducer-type mechanical pump is used in the primary circuit because of its excellent NPSH characteristics. Hockey sticks steam generators are used to produce near-fossil steam conditions at the turbine throttle. The balance of plant (BOP) design was developed by the architectural-engineering firm of Burns and Roe. It includes Allis-Chalmers - KWU 1800-rpm tandem-compound turbine, selected with high-,intermediate-, and two double-flow low-pressure cylinders equipped with two moisture separator cyclones. A design feature to enhance the licensability of the reference design is the three-level Decay Heat Removal System (DHRS), which consists of normal, backup, and diverse decay heat removal paths. The Atomics International PLBR design illustrated the technical soundness of the LMFBR system for meeting the world's long-term electrical energy supply needs. The design includes design features to assure licensability and innovative engineering features to enhance reliability, constructability, economics, and U.S. utility grid compatibility. The design concept provides a sound basis for the future detailed design of a prototype plant and subsequent development of larger LMFBR plants. (author)

A comparative analysis of methods to represent uncertainty in estimating the cost of constructing wastewater treatment plants.

Science.gov (United States)

Chen, Ho-Wen; Chang, Ni-Bin

2002-08-01

Prediction of construction cost of wastewater treatment facilities could be influential for the economic feasibility of various levels of water pollution control programs. However, construction cost estimation is difficult to precisely evaluate in an uncertain environment and measured quantities are always burdened with different types of cost structures. Therefore, an understanding of the previous development of wastewater treatment plants and of the related construction cost structures of those facilities becomes essential for dealing with an effective regional water pollution control program. But deviations between the observed values and the estimated values are supposed to be due to measurement errors only in the conventional regression models. The inherent uncertainties of the underlying cost structure, where the human estimation is influential, are rarely explored. This paper is designed to recast a well-known problem of construction cost estimation for both domestic and industrial wastewater treatment plants via a comparative framework. Comparisons were made for three technologies of regression analyses, including the conventional least squares regression method, the fuzzy linear regression method, and the newly derived fuzzy goal regression method. The case study, incorporating a complete database with 48 domestic wastewater treatment plants and 29 industrial wastewater treatment plants being collected in Taiwan, implements such a cost estimation procedure in an uncertain environment. Given that the fuzzy structure in regression estimation may account for the inherent human complexity in cost estimation, the fuzzy goal regression method does exhibit more robust results in terms of some criteria. Moderate economy of scale exists in constructing both the domestic and industrial wastewater treatment plants. Findings indicate that the optimal size of a domestic wastewater treatment plant is approximately equivalent to 15,000 m3/day (CMD) and higher in Taiwan

Site infrastructure as required during the construction and erection of nuclear power plants

International Nuclear Information System (INIS)

Haas, K.F.; Wagner, H.

1978-01-01

In general, in an exchange of experience on constructing nuclear power plants priority is given to design and lay-out, financing, quality assurance etc., but in this paper an attempt has been made to describe range and type of site infrastructure required during construction and erection. Site infrastructure will make considerable demands on the planning, supply of material and maintenance that may result from the frequently very isolated location of power plant sites. Examples for specific values and experiences are given for a nuclear power plant with two units on the 1300-MW type at present under construction of the Persian Gulf in Iran. Data concerning the site infrastructure, including examples, are given and explained on the basis of graphs. The site is split up into a technical and a social infrastructure. The main concern of the technical site infrastructure is the timely provision and continuous availability of electric energy, water, communication grids, workshops, warehouses, offices, transport and handling facilities, as well as the provision of heavy load roads, harbour facilities, etc. The social site infrastructure in general comprises accommodation, food supplies and the care and welfare of all site personnel, which includes a hospital, school, self-service shop, and sport and recreation facilities. (author)

Fire protection programme during construction of the Chashma nuclear power plant

International Nuclear Information System (INIS)

Mian Umer, M.

1998-01-01

A clear view is given of several measures that have been taken with regard to fire prevention, protection and fire fighting during all phases of the construction, installation and commissioning of the Chasma nuclear power plant to protect personnel and equipment so that any delays in plant operation as a result of fire incident can be avoided. These measures include the precautions taken, the provisions made for fire extinguishers and hydrants, and the setting up of a fire brigade. An overview is also given of the fire incidents that have occurred. (author)

Construction and bench testing of a prototype rotatable collimator for the LHC

CERN Document Server

Markiewicz, T; Keller, L; Aberle, O; Bertarelli, A; Gradassi, P; Marsili, A; Redaelli, S; Rossi, A; Salvachua, B; Valentino, G

2014-01-01

A second generation prototype rotatable collimator has been fabricated at SLAC and delivered to CERN for further vacuum, metrology, function and impedance tests. The design features two cylindrical Glidcop jaws designed to each absorb 12 kW of beam in steady state and up to 60 kW in transitory beam loss with no damage and minimal thermal distortion [1]. The design is motivated by the use of a radiation resistant high Z low impedance readily available material. A vacuum rotation mechanism using the standard LHC collimation jaw positioning motor system allows each jaw to be rotated to present a new 2 cm high surface to the beam if the jaw surface were to be damaged by multiple full intensity beam bunch impacts in a asynchronous beam abort. Design modifications to improve on the first generation prototype, pre-delivery functional tests performed at SLAC and post-delivery test results at CERN are presented.

10-MWe solar-thermal central-receiver pilot plant: collector subsystem foundation construction. Revision No. 1

Energy Technology Data Exchange (ETDEWEB)

1979-12-18

Bid documents are provided for the construction of the collector subsystem foundation of the Barstow Solar Pilot Plant, including invitation to bid, bid form, representations and certifications, construction contract, and labor standards provisions of the Davis-Bacon Act. Instructions to bidders, general provisions and general conditions are included. Technical specifications are provided for the construction. (LEW)

Pretension construction of safety shell in Chashma nuclear power plant

International Nuclear Information System (INIS)

Gong Zhenbin; Li Yinong; Ni Shaowen

1999-01-01

19T16 post-tension grouped anchor system is applied to the safety shell pretension in Chashma Nuclear Power Plant. The stretching force of each bundle is about 3800 kN and the prestressed reinforcement is stretched in five stages. The double-control measurement of stress controlling and extension checking is applied in strict accordance with the principle of symmetrical construction

Technology infusion of intellectual 3D printers-based prototyping of products into learning process

Science.gov (United States)

Boshhenko, T. V.; Chepur, P. V.

2018-03-01

The article considers the prospects for the technologies of intellectual design and prototyping applying 3D printers. It presents basic technologies of 3D printing, currently developed and released for construction. The experience of educational activities in the University to train students for the Academic Competitions on three-dimensional modeling and prototyping is described in the present article. Requirements for the prototyping implementation are given, allowing obtaining a positive effect from the technology infusion released for construction. The results of activities to train students for the Academic Competition are stated. It is established that the proposed approaches to the training of students have led to the highest score in the national contest in Novosibirsk when performing tasks for prototyping a stand for a cell phone and manufacturing the product on a 3D printer at the SLS technology, selective laser sintering. The conclusions about the possibilities and prospects of development of this direction in the industry in the entire country are drawn.

The application of prototype point processes for the summary and description of California wildfires

Science.gov (United States)

Nichols, K.; Schoenberg, F.P.; Keeley, J.E.; Bray, A.; Diez, D.

2011-01-01

A method for summarizing repeated realizations of a space-time marked point process, known as prototyping, is discussed and applied to catalogues of wildfires in California. Prototype summaries are constructed for varying time intervals using California wildfire data from 1990 to 2006. Previous work on prototypes for temporal and space-time point processes is extended here to include methods for computing prototypes with marks and the incorporation of prototype summaries into hierarchical clustering algorithms, the latter of which is used to delineate fire seasons in California. Other results include summaries of patterns in the spatial-temporal distribution of wildfires within each wildfire season. ?? 2011 Blackwell Publishing Ltd.

Development of off-gas filters for reprocessing plants. Development and construction of an off-gas filter system for large reprocessing plants. Off-gas section of the resolver test stand of the IHCh

International Nuclear Information System (INIS)

Furrer, J.; Kaempffer, R.; Wilhelm, J.G.; Pfauter, C.; Jannakos, K.; Apenberg, W.; Lange, W.; Mendel, W.; Potgeter, G.; Zabel, G.

1976-01-01

The test of the highly impregnated iodine sorption material AC 6,120 was continued in the laboratory under simulated conditions of a 1,500 t/a uranium reprocessing plant. The influence of NO in nitrogen as the carrier gas on the removal efficiency of the sorption material has been especially examined. Several experiments on the removal efficiency of iodine sorption by the material AC 6,120 were carried out in the original off-gas of the French processing plant SAP Marcoule while the filter system was installed on the one side directly behind the dissolver and on the other side behind the iodine desorption columm. The first iodine filter developed at LAF II was installed in the off-gas line of the dissolver in the Karlsruhe reprocessing plant. The filter system for the dissolver off-gas handling test rig of the IHCh was specified and ordered with an engineering firm. The conception of the prototype off-gas filter system was selected and a lock and transport system allowing to replace filters was designed and subjected for testing. Five alternative solutions were set up in order to find the appropriate filter concept. The method of selection based on the evaluation of performance criteria. According to the selected solution a filter drum was designed and constructed. The lock of the filter system has been designed and realized. Preliminary tests have been made. (orig.) [de

Design and Prototyping of a High Granularity Scintillator Calorimeter

International Nuclear Information System (INIS)

Zutshi, Vishnu

2016-01-01

A novel approach for constructing fine-granularity scintillator calorimeters, based on the concept of an Integrated Readout Layer (IRL) was developed. The IRL consists of a printed circuit board inside the detector which supports the directly-coupled scintillator tiles, connects to the surface-mount SiPMs and carries the necessary front-end electronics and signal/bias traces. Prototype IRLs using this concept were designed, prototyped and successfully exposed to test beams. Concepts and implementations of an IRL carried out with funds associated with this contract promise to result in the next generation of scintillator calorimeters.

Design and Prototyping of a High Granularity Scintillator Calorimeter

Energy Technology Data Exchange (ETDEWEB)

Zutshi, Vishnu [Northern Illinois Univ., DeKalb, IL (United States). Dept. of Physics

2016-03-27

A novel approach for constructing fine-granularity scintillator calorimeters, based on the concept of an Integrated Readout Layer (IRL) was developed. The IRL consists of a printed circuit board inside the detector which supports the directly-coupled scintillator tiles, connects to the surface-mount SiPMs and carries the necessary front-end electronics and signal/bias traces. Prototype IRLs using this concept were designed, prototyped and successfully exposed to test beams. Concepts and implementations of an IRL carried out with funds associated with this contract promise to result in the next generation of scintillator calorimeters.

Status of the construction of the KLOE Drift Chamber

International Nuclear Information System (INIS)

Dell'Agnello, S.

1997-01-01

A status report on the construction of the drift chamber for the KLOE experiment at the LNF DAΦNE Φ-factory is given. Physics requirements, detector design performance and its key mechanical features and components are briefly reviewed. The program currently consists of (i) the preparation of final detector components, complemented by (ii) extensive tests of prototypes of critical mechanical parts (like the end plates) and the ''test construction'' of a 1:1 chamber prototype. These two sub-programs are pursued in parallel. Single-component prototype checks include surveys of their shape and size, of accuracy of wire-hole drilling, measurements of their displacement or buckling under nominal load. The ''test construction'' is the debugging of mechanical assembly, survey and alignment of mechanics and of wire-stringing robotics, the actual stringing of a sample 2000 holes drilled on the prototype end plates, the measurement of electrical properties of strung wires, as well as of their mechanical tension. These extensive tests have been successfully completed; they represent an effective hands-on training of the construction group, and will allow a prompt and steady start of the drift chamber wire stringing as all necessary components became available at LNF. (orig.)

Project management in fossil plant construction: A perspective for the Nineties

International Nuclear Information System (INIS)

Bhatia, N.K.

1991-01-01

The continuing growth in demand for electric power, and the reluctance of electric utility management to commit to new capacity additions has created a potential for somewhat hectic activity in the fossil power plant construction market. With the changing matrix of power plant types and ownerships, the project manager is called upon to deliver a complex product with exacting contract requirements: lump sum contracts, competitive pricing, short schedules, and performance guarantees. A shortage of experienced professionals in the ranks of the owners, engineers, contractors, and suppliers magnifies the challenge. Plant replication, automation, creative management of vendors and contractors, and participative management of the work force will be key elements of successful projects. Partnering between the clients and the engineers-constructors will be an interesting new relationship model

Overall plant concept for a tank-type fast reactor

International Nuclear Information System (INIS)

Yamaki, Hideo; Davies, S.M.; Goodman, L.

1984-01-01

Japanese nuclear industries are expressing interest in the merits of the tank-type FBR as a large plant (demonstration) after JOYO (experimental, in operation) and MONJU (prototype, under construction). In response to this growing interest in a tank-type FBR demonstration plant, Hitachi has initiated a conceptual study of a 1000 MWe tank plant concept in collaboration with GE and Bechtel. Key objectives of this study have been: to select reliable and competitive tank plant concepts, with emphases on a seismic-resistant and compact tank reactor system;to select reliable shutdown heat removal system;and to identify R and D items needed for early 1990s construction. Design goals were defined as follows: capital costs must be less than twice, and as close as practical to 1.5 those of equivalent LWR plants;earthquake resistant structures to meet stringent Japanese seismic conditions must be as simple and reliable as practical;safety must be maintained at LWR-equivalent risks;and R and D needs must be limited to minimum cost for the limited time allowed. This paper summarizes the overall plant concepts with some selected topics, whereas detailed descriptions of the reactor assembly and the layout design are found in separate papers

Small-Scale Readout System Prototype for the STAR PIXEL Detector

International Nuclear Information System (INIS)

Szelezniak, Michal; Anderssen, Eric; Greiner, Leo; Matis, Howard; Ritter, Hans Georg; Stezelberger, Thorsten; Sun, Xiangming; Thomas, James; Vu, Chinh; Wieman, Howard

2008-01-01

Development and prototyping efforts directed towards construction of a new vertex detector for the STAR experiment at the RHIC accelerator at BNL are presented. This new detector will extend the physics range of STAR by allowing for precision measurements of yields and spectra of particles containing heavy quarks. The innermost central part of the new detector is a high resolution pixel-type detector (PIXEL). PIXEL requirements are discussed as well as a conceptual mechanical design, a sensor development path, and a detector readout architecture. Selected progress with sensor prototypes dedicated to the PIXEL detector is summarized and the approach chosen for the readout system architecture validated in tests of hardware prototypes is discussed

Virtual Reality for Prototyping Service Journeys

Directory of Open Access Journals (Sweden)

Costas Boletsis

2018-04-01

Full Text Available The use of virtual elements for developing new service prototyping environments and more realistic simulations has been suggested as a way to optimise the service prototyping process. This work examines the application of virtual reality (VR in prototyping service journeys and it hypothesises that VR can recreate service journeys in a highly immersive, agile, and inexpensive manner, thus allowing users to have a representative service experience and enabling service designers to extract high-quality user feedback. To that end, a new service prototyping method, called VR service walkthrough, is presented and evaluated through an empirical comparative study. A VR service walkthrough is a virtual simulation of a service journey, representing how the service unfolds over space and time. A comparative study between the VR service walkthrough method and an adapted service walkthrough method evaluates the application of both methods using a location-based audio tour guide service as a case study. Two user groups (each with 21 users were used to evaluate both methods based on two factors: the user experience they offered and the subjective meaningfulness and quality of feedback they produced. Results show that the VR service walkthrough method gave a performance similar to that of the service walkthrough method. It was also able to communicate the service concept in an immersive way and foster constructive feedback.

Problems and experience of regulatory review associated with plant construction and commissioning

International Nuclear Information System (INIS)

Commander, W.

1979-01-01

The work of the Assessment Branch of NII covering the regulatory review during design safety assessment, construction, commissioning and operation is described commencing with the nuclear licensing procedure through licence variations and conditions attached to the licence, to the final stages of plant construction up to commercial operation and full power production. The importance of the application of safety assessment principles is outlined, the importance of the Safety Inspectorate Schedule described, and the need to retain organisational and regulatory flexibility emphasised. (author)

Outline of principle of design construction of demolished concrete from electric power plant

International Nuclear Information System (INIS)

Takahashi, Tomohiko; Sakagami, Takeharu; Inagaki, Hirokazu; Morozumi, Hironori; Muranaka, Kenji

2005-01-01

'The principle of design construction of recycled demolished concrete from electric power plant' (a plan) is going to be published by TSCE Concrete Committee in 2005. The abstract of the above principle is described. A large amount of demolished concrete is generated by decommissioning of atomic power plant. About 450,000 to 500,000t of concrete with small radiation level per an atomic power plant will be generated. This report included decommissioning of Tokai power plant, characteristics of subject of demolished concrete, the recycled demolished concrete, fresh conditions of the recycled demolished concrete, the strength, deformation properties, durability, alkali silica reactivity of them and control measurement. (S.Y.)

Technology programs in support of advanced light water reactor plants: Construction

International Nuclear Information System (INIS)

Eichen, E.P.

1989-01-01

Under Contract No. AC03-86SF16565, Stone ampersand Webster Engineering Corporation (SWEC) is conducting several independent, yet interrelated, studies of light water reactor plants to improve constructibility and quality, to reduce costs and schedule durations, and to simplify design. This document discusses design requirements. 36 refs., 57 figs., 56 tabs

Metal and metalloid removal in constructed wetlands, with emphasis on the importance of plants and standardized measurements: A review

International Nuclear Information System (INIS)

Marchand, L.; Mench, M.; Jacob, D.L.; Otte, M.L.

2010-01-01

This review integrates knowledge on the removal of metals and metalloids from contaminated waters in constructed wetlands and offers insight into future R and D priorities. Metal removal processes in wetlands are described. Based on 21 papers, the roles and impacts on efficiency of plants in constructed wetlands are discussed. The effects of plant ecotypes and class (monocots, dicots) and of system size on metal removal are addressed. Metal removal rates in wetlands depend on the type of element (Hg > Mn > Fe = Cd > Pb = Cr > Zn = Cu > Al > Ni > As), their ionic forms, substrate conditions, season, and plant species. Standardized procedures and data are lacking for efficiently comparing properties of plants and substrates. We propose a new index, the relative treatment efficiency index (RTEI), to quantify treatment impacts on metal removal in constructed wetlands. Further research is needed on key components, such as effects of differences in plant ecotypes and microbial communities, in order to enhance metal removal efficiency. - A new index, the relative treatment efficiency index (RTEI), to quantify treatment impacts on metal and metalloid removal in constructed wetlands.

Prototyping and testing of a fully autonomous road construction beacon, the iCone.

Science.gov (United States)

2010-04-01

A revolutionary portable traffic monitoring device is developed, extensively prototyped and thoroughly tested throughout the State of New York as well as several other states. The resulting device, trademarked as the iCone, simplifies the process o...

Hanford prototype-barrier status report FY 1996

Energy Technology Data Exchange (ETDEWEB)

Gee, G.W.; Ward, A.L.; Gilmore, B.G.; Link, S.O.; Dennis, G.W.; O`Neil, T.K.

1996-11-01

A prototype surface barrier is being evaluated as part of a treatability study at the 200-BP-1 Operable Unit in the 200 East Area of the Hanford Site. Tests include the application of irrigation water to the northern half of the barrier and subsequent measurement of water balance, wind and water erosion, subsidence, plant establishment,a nd plant and animal intrusion. The tests are designed to evaluate both irrigated and nonirrigated sideslope and vegetated surfaces over a period of 3 years. This report documents findings from the second year of testing.

Hanford prototype-barrier status report FY 1996

International Nuclear Information System (INIS)

Gee, G.W.; Ward, A.L.; Gilmore, B.G.; Link, S.O.; Dennis, G.W.; O'Neil, T.K.

1996-11-01

A prototype surface barrier is being evaluated as part of a treatability study at the 200-BP-1 Operable Unit in the 200 East Area of the Hanford Site. Tests include the application of irrigation water to the northern half of the barrier and subsequent measurement of water balance, wind and water erosion, subsidence, plant establishment,a nd plant and animal intrusion. The tests are designed to evaluate both irrigated and nonirrigated sideslope and vegetated surfaces over a period of 3 years. This report documents findings from the second year of testing

Use of industrial isotopes in the construction of an integrated steel plant

International Nuclear Information System (INIS)

Narasimha Rao, Y.V.; Prasad, G.C.

1977-01-01

The applications of radioisotopes by industrial radiography methods in the control of quality of welding of steel structures and equipment during the construction of a steel plant are highlighted. Some of the main units that are controlled in a steel plant by the radiography methods are boilers, pressure vessels, blast furnace shells and stoves, L.D. convertors, technological pipelines etc. After briefly describing the different radioisotopes (sources) and the accessories required for radiography work, the different techniques adopted for determining the defects in the welded joints are mentioned. A mention is also made of the different types of image quality indicators (penetrameters) and their relative advantages. The norms for control and acceptance of the defects for different structures are also covered. Finally, the safety requirements that are to be followed during radiography work at the site of erection, where different agencies of construction work simultaneously are dealt with. (author)

A Continuing Education Short Course and Engineering Curriculum to Accelerate Workforce Development in Wind Power Plant Design, Construction, and Operations

Energy Technology Data Exchange (ETDEWEB)

Tinjum, James [Univ. of Wisconsin, Madison, WI (United States)

2012-11-29

Significant advances in wind turbine technology and wind turbine power plant capabilities are appearing in the U.S. Sites that only 10 years ago might have been overlooked are being considered for build out. However, the development of a skilled workforce in the engineering fields and construction trades lags the potential market, especially if the industry is expected to site, design, construct, and operate sufficient wind power plant sites to meet the potential for 20% wind energy by 2030. A select few firms have penetrated the engineer-procure-construction (EPC) market of wind power plant construction. Competition and know-how in this market is vital to achieve cost-effective, design-construct solutions. The industry must produce or retrain engineers, contractors, and technicians to meet ambitious goals. Currently, few universities offer undergraduate or graduate classes that teach the basics in designing, building, and maintaining wind power plants that are safe, efficient, and productive.

Measurements of the radioactivity of power plant by-products processed into construction materials

International Nuclear Information System (INIS)

Marcinkowski, S.A.; Dudelewski, H.A.

1992-01-01

The subject of the recycling of residual products comprising, inter alia, fly ash and slags accuring from the combustion of black and brown coal in modern coal dust boilers in the power industry has been topical for a number of years. Numerous discussions and articles in technical periodicals and the daily press have revolved around the problem of the radioactivity of construction materials or construction elements obtained from fly ash or slags of power plant. In Poland, this was a forbidden subject until the publication in 1980 by the Warsaw institute of construction technology of standard no. 234 entitled: 'Recommendations for establishing the natural radioactivity of products processed into construction materials'. (orig.) [de

Study on modular construction management in AP1000 nuclear plant project

International Nuclear Information System (INIS)

Fang Xiaopeng; Shen Wenrong; Sun Kebin; Wei Zhong

2010-01-01

The construction of AP1000 Nuclear Power Plant (NPP) has commenced in China. The AP1000 NPP features a passive design concept and modular construction technology. Based on the management of the construction of current AP1000 NNP, this paper describes the effects on Nuclear Island (NI) construction project management resulting from modular construction technology, as well as new construction techniques and methods. This paper puts forward new requirements for construction schedule management of the nuclear island construction at different levels. The AP1000 NI construction logic features the parallel construction of civil and structural erection as the main approach, with the integrated schedule of module fabrication, assembly and installation as support. The structural modules of AP1000 project are prefabricated in shop, delivered to site as sub-modules and assembled to integrated structural module. The assembled module is transported to the construction site, hoisted and finally set in NI. This paper illustrates how to ensure the construction quality of structural modules by analyzing the interface process and key links in the quality control program, and introduces how to ensure the safety of heavy structural components during various construction phases by evaluating and analyzing the construction safety process. This paper also makes an analysis of the safe environment for the assembly and installation of Containment Vessel, the management of product protection and personnel safety inside the Containment Building during 'Open Top' construction, raises to implement effective protection for the numerous pre-set mechanical modules and equipments, as well as personnel safety protection programs and measures. The modular construction feature of AP1000 NPP design requires technique improvement and management innovation during the NI construction. This paper makes a study and research on the control management of schedule, quality and safety of AP1000 NPP NI

Looking back on safety management in construction of advanced thermal nuclear power plant 'Fugen'

International Nuclear Information System (INIS)

Emori, Kengo

1979-01-01

The safety management of the advanced thermal nuclear power plant ''Fugen'' during the period from the preparation of plant construction in October, 1970, to the full power operation in March, 1979, is looked back and explained. Any large human and material accidents did not occur during the long construction time. The total numbers of persons and hours were 1.397 x 10 6 workers and 11.55 x 10 6 hours, respectively. The number of labor accidents was twenty with no dead person, the number of loss days was 645 days, the number of accident rate was 1.73, the intensity rate was 0.06, and the mean rate of labor accidents per year per 1000 workers was 6.4. The radiation exposure dose was 65.27 man-rem for the managed 1804 workers in total, during the testing and operating periods. These data show that the safety management for ''Fugen'' is very excellent, considering the following special features: 1) there were many works which were carried out for the first time, 2) the construction of the plant was conducted by five contractors taking partial charge, there were many kinds of construction works, the construction and testing periods were long, and the workers had to go to the site from Tsuruga city by car and bus. The organization of preventing disasters, the concrete implementation items for safety management, including the planning of activities, various meetings, patrol, education and training, the honoring system, the prevention of traffic accident and so on, and the results of actual safety management are explained with the reflection. (Nakai, Y.)

Development of technology for brown coal liquefaction. Design, construction and operation of pilot plant; development of 50t/d pilot plant

Energy Technology Data Exchange (ETDEWEB)

1986-08-01

As for the development of 50t/d pilot plant for the development of liquefaction plant of Victorian brown coal in Austraria, outline of the contents about the second stage construction following the first stage construction up to this time is reported from the following 4 viewpoints; 1: design of process apparatuses, 2: manufacture of apparatuses, 3: fieldwork of the construction and 4: operation of the first stage facilities. On the first item the outline of detail design made by Japanese and Australian companies is described. On the second item the acceptance of purchasing goods from Japan and Australia and the condition of inspection and quality assurance to specific principal parts are described. On the third item the supplementary construction of the first stage, contents of constructions of the second stage are described. On the fourth item, preparation for operation, target, the whole circumstances and the results of maintenance, especially review of operation technique, training of operators, and occurrence and repair of troubles are described. As other relevant works, envirommental assessment, waste disposal, enviromental monitoring for exhaust gases, drainage and working enviroments, safety measure, educational training and moreover activities for local district people and the state of labor market as the support for execution of the project are described.

Description of the prototype fast reactor at Dounreay

International Nuclear Information System (INIS)

Jensen, S.E.; Oelgaard, P.L.

1995-12-01

The Prototype Fast Reactor (PFR) at Dounreay, UK, started operation in 1975 and was closed down in 1994. The present report contains a description of the PFR nuclear power plant, based on information available in literature and on information supplied during a visit to the plant. The report covers a description of the site and plant arrangement, the buildings and structures, the reactor core and other vessel internals, the control system, the main cooling system, the decay heat removal system, the emergency core cooling system, the containment system, the steam and power conversion system, the fuel handling system, plant safety features, the control and instrumentation systems and the sodium purification systems. (au) 16 refs

Rapid Prototyping High-Performance MR Safe Pneumatic Stepper Motors

NARCIS (Netherlands)

Groenhuis, Vincent; Stramigioli, Stefano

2018-01-01

In this paper we show that pneumatic stepper motors for MR safe robots can be constructed using rapid prototyping techniques such as 3-D printing and laser-cutting. The designs are lightweight, completely metal-free and fully customizable. Besides MR safe robotic systems, other potential

Design consideration on hydrogen production demonstration plant of thermochemical IS process

International Nuclear Information System (INIS)

Iwatsuki, Jin; Noguchi, Hiroki; Terada, Atsuhiko; Kubo, Shinji; Sakaba, Nariaki; Onuki, Kaoru; Hino, Ryutaro

2009-03-01

Preliminary design study was carried out on the hydrogen production demonstration plant of thermochemical IS process. In the pilot test, hydrogen production will be examined under prototypical condition using an apparatus made of industrial materials, which is driven by the sensible heat of helium gas heated by an electric heater that simulates the High Temperature Engineering Test Reactor (HTTR). Tentative system condition was defined considering the HTTR specification and the experience on the construction and the operation of the mock-up test facility using methane reforming for hydrogen production. The process condition and the system flow diagram were discussed to meet the system condition. Based on the defined process condition, types of the main components were discussed taking the corrosion resistance of the structural materials into consideration. Applicable rules and regulations were also surveyed regarding the plant construction and operation. (author)

Fabrication and test of prototype ring magnets for the ALS [Advanced Light Source

International Nuclear Information System (INIS)

Tanabe, J.; Avery, R.; Caylor, R.; Green, M.I.; Hoyer, E.; Halbach, K.; Hernandez, S.; Humphries, D.; Kajiyama, Y.; Keller, R.; Low, W.; Marks, S.; Milburn, J.; Yee, D.

1989-03-01

Prototype Models for the Advanced Light Source (ALS) Booster Dipole, Quadrupole and Sextupole and the Storage Ring Gradient Magnet, Quadrupole and Sextupole have been constructed. The Booster Magnet Prototypes have been tested. The Storage Ring Magnets are presently undergoing tests and magnetic measurements. This paper reviews the designs and parameters for these magnets, briefly describes features of the magnet designs which respond to the special constraints imposed by the requirements for both accelerator rings, and reviews some of the results of magnet measurements for the prototype. 13 refs., 7 figs., 1 tab

Architectural prototyping

DEFF Research Database (Denmark)

Bardram, Jakob Eyvind; Christensen, Henrik Bærbak; Hansen, Klaus Marius

2004-01-01

A major part of software architecture design is learning how specific architectural designs balance the concerns of stakeholders. We explore the notion of "architectural prototypes", correspondingly architectural prototyping, as a means of using executable prototypes to investigate stakeholders...

Approaches to assessment of socio-demographic and economic aspects of nuclear power plant construction and operation

International Nuclear Information System (INIS)

Uvirova, E.

1984-01-01

The paper informs of solving the task of economic evaluation of transient and permanent social consequences of the construction and operation of nuclear power plants. The solution takes place in three stages: 1. drafting of methodology, 2. trial of methodology in localities of current nuclear power plant construction, 3. analysis of results and finalizing of methodology. The task is aimed at studying the questions of the return and profitability of investments, the evaluation of optimal economic lifetime, and the effective restoration of basic funds. Its model solution shows the national economy relations of nuclear power. Also discussed is the question of the use of non-balance heat from nuclear power plants. (E.S.)

BNL 56 MHz HOM Damper Prototype Fabrication at JLab

Energy Technology Data Exchange (ETDEWEB)

Huque, Naeem A. [Jefferson Lab., Newport News, VA (United States); Daly, Edward F. [Jefferson Lab., Newport News, VA (United States); Clemens, William A. [Jefferson Lab., Newport News, VA (United States); McIntyre, Gary T. [Brookhaven National Lab. (BNL), Upton, NY (United States); Wu, Qiong [Brookhaven National Lab. (BNL), Upton, NY (United States); Seberg, Scott [Brookhaven National Lab. (BNL), Upton, NY (United States); Bellavia, Steve [Brookhaven National Lab. (BNL), Upton, NY (United States)

2015-09-01

A prototype Higher-Order Mode (HOM) Damper was fabricated at JLab for the Relativistic Heavy-Ion Collider's (RHIC) 56 MHz cavity at Brookhaven National Laboratory (BNL). Primarily constructed from high RRR Niobium and Sapphire, the coaxial damper presented significant challenges in electron-beam welding (EBW), brazing and machining via acid etching. The results of the prototype operation brought about changes in the damper design, due to overheating braze alloys and possible multi-pacting. Five production HOM dampers are currently being fabricated at JLab. This paper outlines the challenges faced in the fabrication process, and the solutions put in place.

Integration of artificial intelligence systems for nuclear power plants surveillance and diagnostics

International Nuclear Information System (INIS)

Chetry, Moon K.

2012-01-01

The objective of this program is to design, construct operate, test, and evaluate a prototype integrated monitoring and diagnostic system for a nuclear power plant. It is anticipated that this technology will have wide application to other complex systems (e.g., fossil power plants, chemical processing plants, and possibly air traffic control systems). Over the past decade, the University of Tennessee (UT) and others have carried out many projects utilizing various methodologies of artificial intelligence (expert systems, neural networks, fuzzy systems and genetic algorithms) to enhance the performance (safety, efficiency, reliability, and availability) of nuclear power plants. Investigations and studies have included a) instrumentation surveillance and calibration validation, b) inferential sensing to calibration of feed water venture flow during fouling, c) thermodynamic performance modeling with iterative improvement of plant heat rate, d) diagnosis of nuclear power plant transients

Wind Energy and Wildlife Pre- and Post-Construction Project at Pantex Plant

Energy Technology Data Exchange (ETDEWEB)

Matlack, Raymond S. [Texas A & M Univ., College Station, TX (United States)

2018-01-03

From 2009-2017, we conducted pre- and post-construction monitoring of wildlife at the Pantex Plant before and after construction of five wind turbines on the plant in 2014-2015. Pre-construction acoustic monitoring for bats was conducted at five sites on Pantex. Acoustic (here after Anabat) files were downloaded 30 times with Anabat files recorded from 6/21/2010 through 1/17/2014. The resulting data include over 3,000,000 files and we hope to analyze them in the future. We were never successful recording acoustic data after 2014 (post-construction). This is despite numerous attempts to trouble shoot our acoustic monitors. Wind damage to cables going from the body of the monitor to their microphones could not be repaired or replaced while towers were standing. Sampling of breeding birds was accomplished through point counts conducted at sites selected for turbine construction and others selected as control sites. Precipitation varied greatly over the course of the study, from a low of 17.81 cm (7.01 inches) during 2011 to a high of 87.96 cm (34.63 inches) during 2015. The pre-construction portion of the project was characterized by fairly extreme drought starting in 2011. Total precipitation for 2011 and 2012 was just 49.12 cm (19.34 inches), less than 50% of the average for a two-year period. The impact of this drought on nesting grassland birds manifest as low nesting species richness and abundance. In 2011 and 2012, 20 and 17 species were documented during point counts, respectively. Post-construction sampling followed the wet year of 2015 (87.96 cm, 34.63 inches). Species richness of nesting birds in 2016 and 2017 was considerably higher than during the drought, 40 and 37 species, respectively. We suspect changes in resource availability associated with relief from drought starting after 2015 was responsible for the recovery/increase in species detected during the breeding season; less importantly any changes from installation of turbines or changes in surface

Model-based explanation of plant knowledge

Energy Technology Data Exchange (ETDEWEB)

Huuskonen, P.J. [VTT Electronics, Oulu (Finland). Embedded Software

1997-12-31

This thesis deals with computer explanation of knowledge related to design and operation of industrial plants. The needs for explanation are motivated through case studies and literature reviews. A general framework for analysing plant explanations is presented. Prototypes demonstrate key mechanisms for implementing parts of the framework. Power plants, steel mills, paper factories, and high energy physics control systems are studied to set requirements for explanation. The main problems are seen to be either lack or abundance of information. Design knowledge in particular is found missing at plants. Support systems and automation should be enhanced with ways to explain plant knowledge to the plant staff. A framework is formulated for analysing explanations of plant knowledge. It consists of three parts: 1. a typology of explanation, organised by the class of knowledge (factual, functional, or strategic) and by the target of explanation (processes, automation, or support systems), 2. an identification of explanation tasks generic for the plant domain, and 3. an identification of essential model types for explanation (structural, behavioural, functional, and teleological). The tasks use the models to create the explanations of the given classes. Key mechanisms are discussed to implement the generic explanation tasks. Knowledge representations based on objects and their relations form a vocabulary to model and present plant knowledge. A particular class of models, means-end models, are used to explain plant knowledge. Explanations are generated through searches in the models. Hypertext is adopted to communicate explanations over dialogue based on context. The results are demonstrated in prototypes. The VICE prototype explains the reasoning of an expert system for diagnosis of rotating machines at power plants. The Justifier prototype explains design knowledge obtained from an object-oriented plant design tool. Enhanced access mechanisms into on-line documentation are

Model-based explanation of plant knowledge

Energy Technology Data Exchange (ETDEWEB)

Huuskonen, P J [VTT Electronics, Oulu (Finland). Embedded Software

1998-12-31

This thesis deals with computer explanation of knowledge related to design and operation of industrial plants. The needs for explanation are motivated through case studies and literature reviews. A general framework for analysing plant explanations is presented. Prototypes demonstrate key mechanisms for implementing parts of the framework. Power plants, steel mills, paper factories, and high energy physics control systems are studied to set requirements for explanation. The main problems are seen to be either lack or abundance of information. Design knowledge in particular is found missing at plants. Support systems and automation should be enhanced with ways to explain plant knowledge to the plant staff. A framework is formulated for analysing explanations of plant knowledge. It consists of three parts: 1. a typology of explanation, organised by the class of knowledge (factual, functional, or strategic) and by the target of explanation (processes, automation, or support systems), 2. an identification of explanation tasks generic for the plant domain, and 3. an identification of essential model types for explanation (structural, behavioural, functional, and teleological). The tasks use the models to create the explanations of the given classes. Key mechanisms are discussed to implement the generic explanation tasks. Knowledge representations based on objects and their relations form a vocabulary to model and present plant knowledge. A particular class of models, means-end models, are used to explain plant knowledge. Explanations are generated through searches in the models. Hypertext is adopted to communicate explanations over dialogue based on context. The results are demonstrated in prototypes. The VICE prototype explains the reasoning of an expert system for diagnosis of rotating machines at power plants. The Justifier prototype explains design knowledge obtained from an object-oriented plant design tool. Enhanced access mechanisms into on-line documentation are

Improvement of design and construction technology in Japanese nuclear power plants

International Nuclear Information System (INIS)

Yomei Kato; Kiyoshi Shmizu

1987-01-01

Nuclear power generation currently offers economic merits superior to those of other methods dependant on such thermal power ganeration as petroleum, LNG, or coal. However, it is essential for the nuclear power generation continuously to retain economic superiority through concurently maintaining its high safety features and outstanding reliability. For achieving this purpose, taking into account of importance explained above, we have been developing and improving those of technologies such as design, engineering, and construction regarding the both field of management and techniques useful for plant construction. This paper covers the several instructive matters which Hitachi has accomplished throughout having had his hand in the project jobs. (author)

Design and construction of a prototype for the obtention of 32P

International Nuclear Information System (INIS)

Duarte A, C.

2003-01-01

The 32 P are a pure emitting radioisotope of maximum energy of 1.71 MeV with half life of 14.28 days that he has applications in the industry, in agriculture, in medicine, in biology and in ecology (6,11,12,13,17,21,22,23,24,25,26,27,28,29,30,31,32 33).The 32 P can be used in the industry like radiotracer in the investigation of some operations and processes and as element of measurement of some industrial meters. In agriculture is used as radiotracer (29) in the investigation of diverse biological processes that have to do with the production of diverse nutritious products. In medicine has uses but very therapeutic mainly in the treatment of some become cancerous (28, 31, 25, 27) in the diagnosis of blood disorders (24) and like part of materials of production of aortic prosthesis (6). The 32 P are also used in the molecular investigation in biology and in genetics (33), and in studies of ecosystems (32) and of DNA (22). One can obtain the 32 P by means of diverse nuclear reactions depending on the material used as matter it prevails, since it doesn't exist in the nature. But anyone in the ways of obtaining it it should imply a process of radiochemical separation that involves so many steps like they are required, depending on the material used as matter prevails, of the purity with which he wants himself to obtain and of the resources that it has available. The objective of this work was design, to build and to prove a prototype to obtain the 32 P to leave of the irradiation of S α with fast neutrons at experimental level, which implies also to design a process that contemplates diverse stages and procedures for each one of them. The process was outlined in five stages: matter purification prevails, preparation of irradiation capsules, irradiation of irradiation capsules, transport and opening capsules of irradiation and radiochemical separation. In the last stage it was where uses the prototype of radiochemical separation in basis to the outlined process and

Renovation of the Wave Dragon Nissum Bredning Prototype

DEFF Research Database (Denmark)

Tedd, James; Kofoed, Jens Peter; Friis-Madsen, Erik

2006-01-01

This paper presents developments of the Wave Dragon, a large offshore wave energy converter. A prototype has been tested in a real sea environment for over 20 months. During 2005 the plant has been in harbor for a major overhaul of several of its components. The motivation for the upgrades...

Optimalisation of national industry participation in nuclear power plant construction

International Nuclear Information System (INIS)

Sriyana

2008-01-01

A study of national industry participation based on recent data has already been conducted. The current industry data is used to estimate the optimum level of national industry participation in nuclear power plant (NPP) construction based on the prior study. The purpose of the study is to give a figure of the optimum level of national industry participation in NPP construction. The scope of the study is the NPP construction project in related to the potency of national industry to participate in the project. The methodology used in the study are literature study, web surfing for industrial data, and on-the-spot industry survey that are potential to participate in NPP construction. In addition to that, discussion with expertise of industrial practitioner was also conducted. The study concludes that (1) based on the recent national industry capability provided and compared to prior similar study, it is estimated that the level of national industry participation in the first NPP construction with the capacity of 1000 MWe PWR is about 40%. (2) to accelerate NPP technology transfer, we need to build a small size NPP. The nuclear island will be developed by BATAN in cooperation with national industry and the non-nuclear island will be developed by national industry. Universities and other academicians should be involved to support and keep the sustainability of man power availability in developing the NPP technology. (author)

The influence of prototype testing in three-dimensional aortic models on fenestrated endograft design.

Science.gov (United States)