Strategies for healthcare facilities, construction, and real estate management.

Science.gov (United States)

Lee, James G

2012-05-01

Adventist HealthCare offers the following lessons learned in improving the value of healthcare facilities, construction, and real estate management: Use an integrated approach. Ensure that the objectives of the approach align the hospital or health system's mission and values. Embrace innovation. Develop a plan that applies to the whole organization, rather than specific business units. Ensure commitment of senior leaders.

Construction of an underground facility for ''in-situ'' experimentation in the boom clay

International Nuclear Information System (INIS)

Bonne, A.; Manfroy, P.; Van Haelewijn, R.; Heremans, R.

1985-01-01

The Belgian R and D Programme concerning the disposal of high-level and alpha-bearing radioactive waste in continental geological formations was launched by SCK/CEN, Mol in 1974. The programme is characterised by its site and formation specific approach, i.e. Mol and Boom clay. In the framework of site confirmation, an important issue is the ''in situ'' experimentation which should allow to determine with a higher degree of confidence the numerical value of the data needed for the evaluations, assessments and designs. The present report deals with the construction of an underground experimental facility, which was scheduled to be fully completed in mid 1984. Initially, the completion was scheduled for the end of 1983, but supplementary experiments related to geomechanics and mining capabilities and to be performed during the construction phase of the experimental facility delayed the completion of the underground facility. During the construction, a continuous observation was made of the behaviour of the clay mass and the structures. In this final contract-report, only the as-built structure, the time schedule and the ''in situ'' experiments launched or performed during the construction phase are dealt with

Field and laboratory test methods for geomembranes during waste management facility construction

International Nuclear Information System (INIS)

Allen, S.R.; McCutchan, J.B.

1991-01-01

Hazardous waste management facilities are required to use approved lining and leak detection systems to prevent the migration of waste into the environment. Synthetic flexible membrane liners (FMLs) have effectively served as the critical barrier for waste containment and fluid migration. The U.S. EPA has established minimum technology requirements for the construction of lined facilities that include detailed and documented Construction Quality Assurance (CQA) plans. The U.S. EPA (EPA) recognizes that CQA during field construction is imperative for successful completion of project work and long-term facility operation. This paper discusses the importance of CQA during FML installation and the practical aspects of implementing a successful CQA program. Standard methods used for FML evaluation, in both the field and laboratory, are discussed and specific aspects of seam testing and data evaluation are addressed. The general importance of comprehensive definition of geomembrane seam field failures is strongly emphasized so that an appropriate response to test failures can be recommended

The construction of irradiated material examination facility

International Nuclear Information System (INIS)

Ro, Seung Gy; Lee, Key Soon; Herr, Young Hoi

1990-03-01

A detail design of the examination process, the hot cell facility and the annexed facility of the irradiated material examination facility (IMEF) which will be utilized to examine and evaluate physical and mechanical properties of neutron-irradiated materials, has been performed. Also a start-up work of the underground structure construction has been launched out. The project management and tasks required for the license application were duly carried out. The resultant detail design data will be used for the next step. (author)

Summarisation of construction and commissioning experience for nuclear power integrated test facility

International Nuclear Information System (INIS)

Xiao Zejun; Jia Dounan; Jiang Xulun; Chen Bingde

2003-01-01

Since the foundation of Nuclear Power Institute of China, it has successively designed various engineering experimental facilities, and constructed nuclear power experimental research base, and accumulated rich construction experiences of nuclear power integrated test facility. The author presents experience on design, construction and commissioning of nuclear power integrated test facility

STACY and TRACY: nuclear criticality experimental facilities under construction

International Nuclear Information System (INIS)

Kobayashi, I.; Takeshita, I.; Yanagisawa, H.; Tsujino, T.

1992-01-01

Japan Atomic Energy Research Institute is constructing a Nuclear Fuel Cycle Safety Engineering Research Facility, NUCEF, where the following research themes essential for evaluating safety problems relating to back-end technology in nuclear fuel cycle facilities will be studied: nuclear criticality safety research; research on advanced reprocessing processes and partitioning; and research on transuranic waste treatment and disposal. To perform nuclear criticality safety research related to the reprocessing of light water reactor spent fuels, two criticality experimental facilities, STACY and TRACY, are under construction. STACY (Static Criticality Facility) will be used for the study of criticality conditions of solution fuels, uranium, plutonium and their mixtures. TRACY (Transient Criticality Facility) will be used to investigate criticality accident phenomena with uranium solutions. The construction progress and experimental programmes are described in this Paper. (author)

Construction of STACY (Static Experiment Critical Facility)

International Nuclear Information System (INIS)

Murakami, Kiyonobu; Onodera, Seiji; Hirose, Hideyuki

1998-08-01

Two critical assemblies, STACY (Static Experiment Critical Facility) and TRACY (Transient Experiment Critical Facility), were constructed in NUCEF (Nuclear Fuel Cycle Safety Engineering Research Facility) to promote researches on the criticality safety at a reprocessing facility. STACY aims at providing critical data of uranium nitrate solution, plutonium nitrate solution and their mixture while varying concentration of solution fuel, core tank shape and size and neutron reflecting condition. STACY achieved first criticality in February 1995, and passed the licensing inspection by STA (Science and Technology Agency of Japan) in May. After that a series of critical experiments commenced with 10 w/o enriched uranium solution. This report describes the outline of STACY at the end of FY 1996. (author)

LSST summit facility construction progress report: reacting to design refinements and field conditions

Science.gov (United States)

Barr, Jeffrey D.; Gressler, William; Sebag, Jacques; Seriche, Jaime; Serrano, Eduardo

2016-07-01

The civil work, site infrastructure and buildings for the summit facility of the Large Synoptic Survey Telescope (LSST) are among the first major elements that need to be designed, bid and constructed to support the subsequent integration of the dome, telescope, optics, camera and supporting systems. As the contracts for those other major subsystems now move forward under the management of the LSST Telescope and Site (T and S) team, there has been inevitable and beneficial evolution in their designs, which has resulted in significant modifications to the facility and infrastructure. The earliest design requirements for the LSST summit facility were first documented in 2005, its contracted full design was initiated in 2010, and construction began in January, 2015. During that entire development period, and extending now roughly halfway through construction, there continue to be necessary modifications to the facility design resulting from the refinement of interfaces to other major elements of the LSST project and now, during construction, due to unanticipated field conditions. Changes from evolving interfaces have principally involved the telescope mount, the dome and mirror handling/coating facilities which have included significant variations in mass, dimensions, heat loads and anchorage conditions. Modifications related to field conditions have included specifying and testing alternative methods of excavation and contending with the lack of competent rock substrate where it was predicted to be. While these and other necessary changes are somewhat specific to the LSST project and site, they also exemplify inherent challenges related to the typical timeline for the design and construction of astronomical observatory support facilities relative to the overall development of the project.

Design ampersand construction innovations of the defense waste processing facility

International Nuclear Information System (INIS)

McKibben, J.M.; Pair, C.R.; Bethmann, H.K.

1990-01-01

Construction of the Defense Waste Processing Facility (DWPF) at the Savannah River Site (SRS) is essentially complete. The facility is designed to convert high-level radioactive waste, now contained in large steel tanks as aqueous salts and sludge, into solid borosilicate glass in stainless steel canisters. All processing of the radioactive material and operations in a radioactive environment will be done remotely. The stringent requirements dictated by remote operation and new approaches to the glassification process led to the development of a number of first-of-a-kind pieces of equipment, new construction fabrication and erection techniques, and new applications of old techniques. The design features and construction methods used in the vitrification building and its equipment were to accomplish the objective of providing a state-of-the-art vitrification facility. 3 refs., 10 figs

AOV Facility Tool/Facility Safety Specifications -

Data.gov (United States)

Department of Transportation — Develop and maintain authorizing documents that are standards that facilities must follow. These standards are references of FAA regulations and are specific to the...

Construction plan of ion irradiation facility in JAERI

International Nuclear Information System (INIS)

Tanaka, Ryuichi

1987-01-01

The Takasaki Radiation Chemistry Research Establishment of Japan Atomic Energy Research Institute (JAERI) started the construction of an ion irradiation facility to apply ion beam to the research and development of radiation resistant materials for severe environment, the research on biotechnology and new functional materials. This project was planned as ion beam irradiation becomes an effective means for the research on fundamental physics and advanced technology, and the national guideline recently emphasizes the basic and pioneering field in research and development. This facility comprises an AVF cyclotron with an ECR ion source (maximum proton energy: 90 MeV), a 3 MV tandem accelerator, a 3 MV single end type Van de Graaf accelerator and a 400 kV ion implanter. In this report, the present status of planning the accelerators and the facility to be constructed, the outline of research plan, the features of the accelerators, and the beam characteristics are described. In this project, the research items are divided into the materials for space environment, the materials for nuclear fusion reactors, biotechnology, new functional materials, and ion beam technology. The ion beams required for the facility are microbeam, pulsed beam, multiple beam, neutron beam and an expanded irradiation field. (Kako, I.)

Construction, characteristics and present status of high-fluence irradiation facility at University of Tokyo

International Nuclear Information System (INIS)

Tabata, Yoneho; Kobayashi, Hitoshi; Tagawa, Seiichi; Kouchi, Noriyuki.

1989-01-01

New ion accelerator facility (HIT Facility) was constructed at Research Center for Nuclear Science and Technology, University of Tokyo. This facility, which was equipped with some special apparatus, has been mainly dedicated to the study of radiation effects of ion beams on materials. In this report, the construction, the characteristics and the present status of this facility are described. (author)

Fabulous Facilities: New Constructions and Renovations.

Science.gov (United States)

American Libraries, 1997

1997-01-01

Renovation and construction projects in 18 public and academic libraries across the United States are showcased, with 23 photographs illustrating library interiors and exteriors. Discussion centers on architecture, costs, technology infrastructure and equipment, preservation of old facilities, furniture, and library functions. (AEF)

Construction of calibration pads facility, Walker Field, Grand Junction, Colorado

International Nuclear Information System (INIS)

Ward, D.L.

1978-08-01

A gamma-ray spectrometer facility was completed at Walker Field Airport, Grand Junction, Colorado, in November 1976. This report describes spectrometers and their calibration, the construction of the spectrometer facility, the radioelement concentrations, procedures for using the facilites, and environmental considerations

Evaluation on applicability of construction methods and construction quality of low-diffusion layer of cavern type radioactive waste disposal facility

International Nuclear Information System (INIS)

Takechi, Shin-ichi; Yokozeki, Kosuke; Terada, Kenji; Akiyama, Yoshihiro; Yada, Tsutomu; Tsuji, Yukikazu

2014-01-01

A performance verification experiment of cavern type radioactive waste disposal facility with a real scale construction is being conducted to evaluate the applicability of proposed construction methods and construction quality of the facility. In this paper, we confirmed that the low-diffusion layer, which is one of the cementitious materials based members, could be filled with mortar from end to end of the member; cracks of low-diffusion layer would not affect the long-term safety evaluation of the facility. And also we figured out the relationship between the material strength and the accumulated temperature, relationship between diffusion coefficient and porosity of low-diffusion layer. (author)

49 CFR 37.41 - Construction of transportation facilities by public entities.

Science.gov (United States)

2010-10-01

... public entities. 37.41 Section 37.41 Transportation Office of the Secretary of Transportation... transportation facilities by public entities. (a) A public entity shall construct any new facility to be used in providing designated public transportation services so that the facility is readily accessible to and usable...

Construction of the two-phase critical flow test facility

International Nuclear Information System (INIS)

Chung, C. H.; Chang, S. K.; Park, H. S.; Min, K. H.; Choi, N. H.; Kim, C. H.; Lee, S. H.; Kim, H. C.; Chang, M. H.

2002-03-01

The two-phase critical test loop facility has been constructed in the KAERI engineering laboratory for the simulation of small break loss of coolant accident entrained with non-condensible gas of SMART. The test facility can operate at 12 MPa of pressure and 0 to 60 C of sub-cooling with 0.5 kg/s of non- condensible gas injection into break flow, and simulate up to 20 mm of pipe break. Main components of the test facility were arranged such that the pressure vessel containing coolant, a test section simulating break and a suppression tank inter-connected with pipings were installed vertically. As quick opening valve opens, high pressure/temperature coolant flows through the test section forming critical two-phase flow into the suppression tank. The pressure vessel was connected to two high pressure N2 gas tanks through a control valve to control pressure in the pressure vessel. Another N2 gas tank was also connected to the test section for the non-condensible gas injection. The test facility operation was performed on computers supported with PLC systems installed in the control room, and test data such as temperature, break flow rate, pressure drop across test section, gas injection flow rate were all together gathered in the data acquisition system for further data analysis. This test facility was classified as a safety related high pressure gas facility in law. Thus the loop design documentation was reviewed, and inspected during construction of the test loop by the regulatory body. And the regulatory body issued permission for the operation of the test facility

Support of Construction and Verification of Out-of-Pile Fuel Assembly Test Facilities

International Nuclear Information System (INIS)

Park, Nam Gyu; Kim, K. T.; Park, J. K.

2006-12-01

Fuel assembly and components should be verified by the out-of-pile test facilities in order to load the developed fuel in reactor. Even though most of the component-wise tests have been performed using the facilities in land, the assembly-wise tests has been depended on the oversees' facility due to the lack of the facilities. KAERI started to construct the assembly-wise mechanical/hydraulic test facilities and KNF, as an end user, is supporting the mechanical/hydraulic test facility construction by using the technologies studied through the fuel development programs. The works performed are as follows: - Test assembly shipping container design and manufacturing support - Fuel handling tool design : Gripper, Upper and lower core simulators for assembly mechanical test facility, Internals for assembly hydraulic test facility - Manufacture of test specimens : skeleton and assembly for preliminary functional verification of assembly mechanical/hydraulic test facilities, two assemblies for the verification of assembly mechanical/hydraulic test facilities, Instrumented rod design and integrity evaluation - Verification of assembly mechanical/hydraulic test facilities : test data evaluation

Support of Construction and Verification of Out-of-Pile Fuel Assembly Test Facilities

Energy Technology Data Exchange (ETDEWEB)

Park, Nam Gyu; Kim, K. T.; Park, J. K. [KNF, Daejeon (Korea, Republic of)] (and others)

2006-12-15

Fuel assembly and components should be verified by the out-of-pile test facilities in order to load the developed fuel in reactor. Even though most of the component-wise tests have been performed using the facilities in land, the assembly-wise tests has been depended on the oversees' facility due to the lack of the facilities. KAERI started to construct the assembly-wise mechanical/hydraulic test facilities and KNF, as an end user, is supporting the mechanical/hydraulic test facility construction by using the technologies studied through the fuel development programs. The works performed are as follows: - Test assembly shipping container design and manufacturing support - Fuel handling tool design : Gripper, Upper and lower core simulators for assembly mechanical test facility, Internals for assembly hydraulic test facility - Manufacture of test specimens : skeleton and assembly for preliminary functional verification of assembly mechanical/hydraulic test facilities, two assemblies for the verification of assembly mechanical/hydraulic test facilities, Instrumented rod design and integrity evaluation - Verification of assembly mechanical/hydraulic test facilities : test data evaluation.

Evaluation on construction quality of pit filler material of cavern type radioactive waste disposal facility

International Nuclear Information System (INIS)

Takechi, Shin-ichi; Yokozeki, Kosuke; Shimbo, Hiroshi; Terada, Kenji; Akiyama, Yoshihiro; Yada, Tsutomu; Tsuji, Yukikazu

2014-01-01

The pit filler material of the underground cavern-type radioactive waste disposal facility, which is poured directly around the radioactive waste packages where high temperature environment is assumed by their decay heat, is concerned to be adversely affected on the filling behavior and its hardened properties. There also are specific issues that required quality of construction must be achieved by unmanned construction with remote operation, because the pit filler construction shall be done under radiation environment. In this paper, the mix proportion of filler material is deliberated with filling experiments simulating high temperature environment, and also the effect of temperature on hardened properties are confirmed with high temperature curing test. Subsequently, the feasibility of unmanned construction method of filler material by pumping, and by movable bucket, are comparatively discussed through a real size demonstration. (author)

Construction alternatives for free-standing facilities.

Science.gov (United States)

Brown, G

1990-01-01

Many hospitals are exploring free-standing facilities as an option for providing more efficient imaging services. Mr. Brown discusses the pros and cons of an emerging building technology, manufactured construction, in which building and site preparation are done simultaneously. He presents the criteria managers should use to make a knowledgeable decision.

Upgraded Features of Newly Constructed Fuel Assembly Mechanical Characterization Test Facility in KAERI

Energy Technology Data Exchange (ETDEWEB)

Lee, Kang Hee; Kang, Heung Seok; Yoon, Kyung Ho; Kim, Hyung Kyu; Lee, Young Ho; Kim, Soo Ho; Yang, Jae Ho [KAERI, Daejeon (Korea, Republic of)

2016-05-15

Fuel assembly mechanical characterization test facility (FAMeCT) in KAERI is newly constructed with upgraded functional features such as increased loading capacity, under-water vibration testing and severe earthquake simulation for extended fuel design guideline. The facility building is compactly designed in the scale of 3rd floor building and has regions for assembly-wise mechanical test equipment, dynamic load (seismic) simulating test system, small scale hydraulic loop and component wise test equipment. Figure 1 shows schematic regional layout of the facility building. Mechanical test platform and system is designed to increase loading capacity for axial compression test. Structural stability of the support system of new upper core plate simulator is validated through a limit case functional test. Fuel assembly mechanical characterization test facility in KAERI is newly constructed and upgraded with advanced functional features such as uprated loading capacity, under-water vibration testing and severe earthquake simulation for extended fuel design guideline. This paper briefly introduce the test facility construction and scope of the facility and is focused on the upgraded design features of the facility. Authors hope to facilitate the facility more in the future and collaborate with the industry.

Construction and Commissioning of PAL-XFEL Facility

Directory of Open Access Journals (Sweden)

In Soo Ko

2017-05-01

Full Text Available The construction of Pohang Accelerator Laboratory X-ray Free-Electron Laser (PAL-XFEL, a 0.1-nm hard X-ray free-electron laser (FEL facility based on a 10-GeV S-band linear accelerator (LINAC, is achieved in Pohang, Korea by the end of 2016. The construction of the 1.11 km-long building was completed by the end of 2014, and the installation of the 10-GeV LINAC and undulators started in January 2015. The installation of the 10-GeV LINAC, together with the undulators and beamlines, was completed by the end of 2015. The commissioning began in April 2016, and the first lasing of the hard X-ray FEL line was achieved on 14 June 2016. The progress of the PAL-XFEL construction and its commission are reported here.

Engineered surface barriers for waste disposal sites: lysimeter facility design and construction

International Nuclear Information System (INIS)

Phillips, S.J.; Ruben, M.S.; Kirkham, R.R.

1988-01-01

A facility to evaluate performance of engineered surface carriers for confinement of buried wastes has been designed, constructed, and operations initiated. The Field Lysimeter Test Facility is located at the US Department of Energy's Hanford Site in Richland, Washington. The facility consists of 18 one-dimensional drainage and weighing lysimeters used to evaluate 7 replicated barrier treatments. Distinct layers of natural earth materials were used to construct layered soil and rock barriers in each lysimeter. These barrier designs are capable in principal of significantly reducing or precluding infiltration of meteoric water through barriers into underlying contaminated zones. This paper summarizes salient facility design and construction features used in testing of the Hanford Site's engineered surface barriers

SPECIFICITY IN DEVELOPMENT OF CONSTRUCTION INDUSTRY

Directory of Open Access Journals (Sweden)

O. S. Golubova

2012-01-01

Full Text Available Specificity in development of construction industry of the Republic of Belarus determines  character of competition on the construction market, forms a pricing, marketing and product policy of building companies. Construction represents itself as a highly developed complex where interaction of business entities is of rather complicated multilateral character.

32 CFR 22.310 - Statutes concerning certain research, development, and facilities construction grants.

Science.gov (United States)

2010-07-01

... higher education for the performance of research and development or for the construction of research or... for research and development, or of a grant for the construction of research or other facilities... research and development or for the construction of research or other facilities are to be awarded to...

RADIATION CONTROL DURING THE CONSTRUCTION OF THE OLYMPIC FACILITIES IN SOCHI CITY

Directory of Open Access Journals (Sweden)

I. K. Romanovich

2015-01-01

Full Text Available This paper presents data on the organization and results of the provision of the radiation safety in the period of preparation for the Winter Olympic and Paralympic games in Sochi, 2014. The following topics are overviewed in the paper: allocation of land plots for construction of the Olympic facilities; organization of the sanitary surveillance of the imported equipment, construction materials and designs for the construction of the Olympic facilities; putting the Olympic venues into operation. Dose rate of gamma radiation at all land plots, which were allocated for the construction of the Olympic facilities, conformed to the requirements of sanitary regulations. The average dose rate of gamma radiation was 0.11 μSv h-1 in the Coastal cluster and 0.14 μSv h-1 in the Mountain cluster. The radon fluence rate from the ground surface exceeded the prescribed limit of 80 mBq m-2 s-1 only at the land plot allocated for construction of the «House of receiving official delegations «Achipse» and the «House of receiving official delegations «Psekhako» in the Mountain cluster. The maximal value of 188 mBq m-2 s -1 was registered here. The buildings projects for this area included using radon protection measures, which were implemented during the construction.

Safety and environmental process for the design and construction of the National Ignition Facility

Energy Technology Data Exchange (ETDEWEB)

Brereton, S.J., LLNL

1998-05-27

The National Ignition Facility (NIF) is a U.S. Department of Energy (DOE) laser fusion experimental facility currently under construction at the Lawrence Livermore National Laboratory (LLNL). This paper describes the safety and environmental processes followed by NIF during the design and construction activities.

Automatic Construction of Java Programs from Functional Program Specifications

OpenAIRE

Md. Humayun Kabir

2015-01-01

This paper presents a novel approach to construct Java programs automatically from the input functional program specifications on natural numbers from the constructive proofs of the input specifications using an inductive theorem prover called Poiti'n. The construction of a Java program from the input functional program specification involves two phases. The theorem prover is used to construct a higher order functional (HOF) program from the input specification expressed as an existential the...

Construction and testing of the Mirror Fusion Test Facility magnets

International Nuclear Information System (INIS)

Kozman, T.; Shimer, D.; VanSant, J.; Zbasnik, J.

1986-08-01

This paper describes the construction and testing of the Mirror Fusion Test Facility superconducting magnet set. Construction of the first Yin Yang magnet was started in 1978. And although this particular magnet was later modified, the final construction of these magnets was not completed until 1985. When completed these 42 magnets weighed over 1200 tonnes and had a maximum stored energy of approximately 1200 MJ at full field. Together with power supplies, controls and liquid nitrogen radiation shields the cost of the fabrication of this system was over $100M. General Dynamics/Convair Division was responsible for the system design and the fabrication of 20 of the magnets. This contract was the largest single procurement action at the Lawrence Livermore National Laboratory. During the PACE acceptance tests, the 26 major magnets were operated at full field for more than 24 hours while other MFTF subsystems were tested. From all of the data, the magnets operated to the performance specifications. For physics operation in the future, additional helium and nitrogen leak checking and repair will be necessary. In this report we will discuss the operation and testing of the MFTF Magnet System, the world's largest superconducting magnet set built to date. The topics covered include a schedule of the major events, summary of the fabrication work, summary of the installation work, summary of testing and test results, and lessons learned

Technical specification for transferring tank construction data to the Oak Ridge Environmental Information System (OREIS)

International Nuclear Information System (INIS)

1996-06-01

The primary goal of this technical specification is to meet the consolidated environmental data requirements defined by the Federal Facility Agreement (FFA) and the Tennessee Oversight Agreement as they pertain to tank construction data maintained in Oak Ridge, Tennessee, by the US Department of Energy's Maintenance and Operations contractor Lockheed Martin Energy Systems, Inc., and prime contractors to the Department of Energy. This technical specification describes the organizational responsibilities for loading tank construction data into OREIS, describes the logical and physical data transfer files, addresses business rules and submission rules, addresses configuration control of this technical specification, and addresses required changes to the current OREIS data base structure based on site requirements. This technical specification addresses the tank construction data maintained by the Y-12, K-25, and ORNL sites that will be sent to OREIS. The initial submission of data will include only inactive Environmental Restoration tanks as specified by the FFA

48 CFR 801.602-80 - Legal and technical review-Office of Construction and Facilities Management and National Cemetery...

Science.gov (United States)

2010-10-01

...-Office of Construction and Facilities Management and National Cemetery Administration. 801.602-80 Section... Responsibilities 801.602-80 Legal and technical review-Office of Construction and Facilities Management and National Cemetery Administration. An Office of Construction and Facilities Management or National Cemetery...

Financing Educational Facility Construction: Prevailing Wage Litigation.

Science.gov (United States)

Goldblatt, Steven M.; Wood, R. Craig

This chapter presents an up-to-date analysis of prevailing state wage laws that affect educational facility construction or renovation and highlights relevant prevailing wage litigation in many states. Currently, 13 states have no prevailing wage laws for public works. The other 37 states and the District of Columbia do have prevailing wage laws…

Standard Specification for Nuclear Facility Transient Worker Records

CERN Document Server

American Society for Testing and Materials. Philadelphia

1995-01-01

1.1 This specification covers the required content and provides retention requirements for records needed for in-processing of nuclear facility transient workers. 1.2 This specification applies to records to be used for in-processing only. 1.3 This specification is not intended to cover specific skills records (such as equipment operating licenses, ASME inspection qualifications, or welding certifications). 1.4 This specification does not reduce any regulatory requirement for records retention at a licensed nuclear facility. Note 1—Nuclear facilities operated by the U.S. Department of Energy (DOE) are not licensed by the U.S. Nuclear Regulatory Commission (NRC), nor are other nuclear facilities that may come under the control of the U.S. Department of Defense (DOD) or individual agreement states. The references in this specification to licensee, the U.S. NRC Regulatory Guides, and Title 10 of the U.S. Code of Federal Regulations are to imply appropriate alternative nomenclature with respect to DOE, DOD...

Factors affecting the implementation of green specifications in construction.

Science.gov (United States)

Lam, Patrick T I; Chan, Edwin H W; Poon, C S; Chau, C K; Chun, K P

2010-01-01

Green specifications constitute one of the important elements in green construction. New sustainability requirements and changing priorities in construction management have spurred the emerging green specifications to a faster pace of development. A cross-sectional survey has been conducted in Hong Kong in 2007 to identify principal factors leading to the success of preparing green specifications. Based on extensive construction management literature, 20 variables concerning sustainable construction were summarized. Using the Mann-Whitney U-test, the subtle differences between stakeholders in specifying construction work have been detected even with the high consistency of the responses among the groups. Moreover, five independent factors for successful specification of green construction have been categorized by factor analysis. They are related to (1) green technology and techniques, (2) reliability and quality of specification, (3) leadership and responsibility, (4) stakeholder involvement, and (5) guide and benchmarking systems. Whilst the first and fourth factors are generally more important, different stakeholder groups have different emphases. The results of the survey have been validated against established principles. 2009 Elsevier Ltd. All rights reserved.

Lead Coolant Test Facility Technical and Functional Requirements, Conceptual Design, Cost and Construction Schedule

International Nuclear Information System (INIS)

Soli T. Khericha

2006-01-01

This report presents preliminary technical and functional requirements (T and FR), thermal hydraulic design and cost estimate for a lead coolant test facility. The purpose of this small scale facility is to simulate lead coolant fast reactor (LFR) coolant flow in an open lattice geometry core using seven electrical rods and liquid lead or lead-bismuth eutectic. Based on review of current world lead or lead-bismuth test facilities and research need listed in the Generation IV Roadmap, five broad areas of requirements of basis are identified: Develop and Demonstrate Prototype Lead/Lead-Bismuth Liquid Metal Flow Loop Develop and Demonstrate Feasibility of Submerged Heat Exchanger Develop and Demonstrate Open-lattice Flow in Electrically Heated Core Develop and Demonstrate Chemistry Control Demonstrate Safe Operation and Provision for Future Testing. These five broad areas are divided into twenty-one (21) specific requirements ranging from coolant temperature to design lifetime. An overview of project engineering requirements, design requirements, QA and environmental requirements are also presented. The purpose of this T and FRs is to focus the lead fast reactor community domestically on the requirements for the next unique state of the art test facility. The facility thermal hydraulic design is based on the maximum simulated core power using seven electrical heater rods of 420 kW; average linear heat generation rate of 300 W/cm. The core inlet temperature for liquid lead or Pb/Bi eutectic is 420 C. The design includes approximately seventy-five data measurements such as pressure, temperature, and flow rates. The preliminary estimated cost of construction of the facility is $3.7M. It is also estimated that the facility will require two years to be constructed and ready for operation

Buffer Construction Methodology in Demonstration Test For Cavern Type Disposal Facility

International Nuclear Information System (INIS)

Yoshihiro, Akiyama; Takahiro, Nakajima; Katsuhide, Matsumura; Kenji, Terada; Takao, Tsuboya; Kazuhiro, Onuma; Tadafumi, Fujiwara

2009-01-01

A number of studies concerning a cavern type disposal facility have been carried out for disposal of low level radioactive waste mainly generated by power plant decommissioning in Japan. The disposal facility is composed of an engineered barrier system with concrete pit and bentonite buffer, and planed to be constructed in sub-surface 50 - 100 meters depth. Though the previous studies have mainly used laboratory and mock-up tests, we conducted a demonstration test in a full-size cavern. The main objectives of the test were to study the construction methodology and to confirm the quality of the engineered barrier system. The demonstration test was planned as the construction of full scale mock-up. It was focused on a buffer construction test to evaluate the construction methodology and quality control in this paper. Bentonite material was compacted to 1.6 Mg/m 3 in-site by large vibrating roller in this test. Through the construction of the buffer part, a 1.6 Mg/m 3 of the density was accomplished, and the data of workability and quality is collected. (authors)

Construction and initial operation of the Advanced Toroidal Facility

International Nuclear Information System (INIS)

Bell, G.L.; Bell, J.D.; Benson, R.D.

1989-08-01

The Advanced Toroidal Facility (ATF) torsatron was designed on a physics basis for access to the second stability regime and on an engineering basis for independent fabrication of high-accuracy components. The actual construction, assembly, and initial operation of ATF are compared with the characteristics expected during the design of ATF. 31 refs., 19 figs., 2 tabs

The Abbott School Construction Program: NJ Department of Education Proposed Facilities Regulations. Analysis of Preschool Issues

Science.gov (United States)

Ponessa, Joan; Boylan, Ellen

2004-01-01

This report on preschool facilities analyzes regulations proposed by the New Jersey Department of Education (NJDOE) to implement the Educational Facilities Construction and Financing Act. (EFCFA). EFCFA, which authorizes and governs New Jersey's public school construction program, was enacted in July 2000 to implement the State Supreme Court's…

Performance specifications for proton medical facility

Energy Technology Data Exchange (ETDEWEB)

Chu, W.T.; Staples, J.W.; Ludewigt, B.A.; Renner, T.R.; Singh, R.P.; Nyman, M.A.; Collier, J.M.; Daftari, I.K.; Petti, P.L.; Alonso, J.R. [Lawrence Berkeley Lab., CA (United States); Kubo, H.; Verhey, L.J. [University of California Davis Medical Center, Sacramento, CA (United States). Cancer Center]|[California Univ., San Francisco, CA (United States). School of Medicine; Castro, J.R. [Lawrence Berkeley Lab., CA (United States)]|[University of California Davis Medical Center, Sacramento, CA (United States). Cancer Center]|[California Univ., San Francisco, CA (United States). School of Medicine

1993-03-01

Performance specifications of technical components of a modern proton radiotherapy facility are presented. The technical items specified include: the accelerator; the beam transport system including rotating gantry; the treatment beamline systems including beam scattering, beam scanning, and dosimetric instrumentation; and an integrated treatment and accelerator control system. Also included are treatment ancillary facilities such as diagnostic tools, patient positioning and alignment devices, and treatment planning systems. The facility specified will accommodate beam scanning enabling the three-dimensional conformal therapy deliver .

7 CFR 3015.16 - Construction and facility improvement.

Science.gov (United States)

2010-01-01

... subgrant. (b) Bids and contracts or subcontracts of $100,000 or less. Unless otherwise required by law, the... payment bonds. (c) Bids and contracts or subcontracts exceeding $100,000. Unless otherwise required by law... § 3015.16 Construction and facility improvement. (a) Scope. This section covers requirements for bid...

Draft Environmental Impact Statement for Construction and Operation of a Depleted Uranium Hexafluoride Conversion Facility at the Paducah, Kentucky, Site

International Nuclear Information System (INIS)

2003-01-01

This document is a site-specific environmental impact statement (EIS) for construction and operation of a proposed depleted uranium hexafluoride (DUF 6 ) conversion facility at the U.S. Department of Energy (DOE) Paducah site in northwestern Kentucky (Figure S-1). The proposed facility would convert the DUF 6 stored at Paducah to a more stable chemical form suitable for use or disposal. In a Notice of Intent (NOI) published in the ''Federal Register'' (FR) on September 18, 2001 (''Federal Register'', Volume 66, page 48123 [66 FR 48123]), DOE announced its intention to prepare a single EIS for a proposal to construct, operate, maintain, and decontaminate and decommission two DUF 6 conversion facilities at Portsmouth, Ohio, and Paducah, Kentucky, in accordance with the National Environmental Policy Act of 1969 (NEPA) (''United States Code'', Title 42, Section 4321 et seq. [42 USC 4321 et seq.]) and DOE's NEPA implementing procedures (''Code of Federal Regulations'', Title 10, Part 1021 [10 CFR Part 1021]). Subsequent to award of a contract to Uranium Disposition Services, LLC (hereafter referred to as UDS), Oak Ridge, Tennessee, on August 29, 2002, for design, construction, and operation of DUF 6 conversion facilities at Portsmouth and Paducah, DOE reevaluated its approach to the NEPA process and decided to prepare separate site-specific EISs. This change was announced in a ''Federal Register'' Notice of Change in NEPA Compliance Approach published on April 28, 2003 (68 FR 22368); the Notice is included as Attachment B to Appendix C of this EIS. This EIS addresses the potential environmental impacts from the construction, operation, maintenance, and decontamination and decommissioning (DandD) of the proposed conversion facility at three alternative locations within the Paducah site; from the transportation of depleted uranium conversion products to a disposal facility; and from the transportation, sale, use, or disposal of the fluoride-containing conversion products

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...

Managing risks during the construction of a power generation facility

International Nuclear Information System (INIS)

Loulakis, M.C.

1992-01-01

The construction of a power generation facility is a substantial undertaking that involves considerable risks to all parties involved. While contractors are accustomed to dealing with risks, construction owners are typically more naive about not only the risks they are assuming in the construction of a project, but also about the role they play on the project itself. Owners and developers of power facilities must understand at the outset that their role during the construction of a project is as integral to the success of the project as that of the designer and contractor. In addition, owners should also understand that there are virtually no risks on a construction project that cannot be shifted among the contracting parties as part of the business deal. Consequently, an owner may contractually be assuming the risks of (1) unusually severe weather, (2) unexpected subsurface conditions, (3) strikes at the turbine supplier's plant or (4) changes in law - as well as the increases in price and delays to project completion associated with such risks. In light of this, a prudent owner will evaluate more than just whether there is sufficient financing to complete the construction of a contemplated project. Prudent owners will conduct a risk management review of the project structure and the contracting terms, with the primary focus being (1) the identification and analysis of the most significant risks faced, (2) a determination of how such risks can be either mitigated or eliminated, and (3) the assessment of the financial exposure to the owner should the potential risk become a reality. This paper will present the framework that owners and developers of power generation projects can use in undertaking such a risk management review

Principal provisions of engineering and geological survey methodology in designing and construction of underground laboratory as a part of facility of RW underground isolation

International Nuclear Information System (INIS)

Prokopova, O.A.

2006-01-01

The most critical moment is the choice of a site for radioactive waste geological repository. Here the role of engineering and geological prospecting as a basis for the construction of a facility for underground isolation appears especially important; it is followed by finding a suitable area and subsequent allocation of the site and facility construction sites. The decision on the selection of construction site for the underground repository is taken by the principle 'descent from the general to the particular', which is a continuous process with the observance of stages in research for the design and exploration work. Each stage of research is typified by specific scale and methods of geological and geophysical studies and scientific research to be fulfilled in scopes sufficient for solution of basic problems for the designing. (author)

Construction and material specification

Science.gov (United States)

2002-01-01

These Construction and Material Specifications are written to the Bidder before award of the : Contract and to the Contractor after award of the Contract. The sentences that direct the Contractor to perform Work are written as commands. For example, ...

Current state of the construction of an integrated test facility for hydrogen risk

Energy Technology Data Exchange (ETDEWEB)

Na, Young Su; Hong, Seong-Ho; Hong, Seong-Wan [KAERI, Daejeon (Korea, Republic of)

2015-05-15

Experimental research on hydrogen as a combustible gas is important for an assessment of the integrity of a containment building under a severe accident. The Korea Atomic Energy Research Institute (KAERI) is preparing a large-scaled test facility, called SPARC (SPray-Aerosol-Recombiner-Combustion), to estimate the hydrogen behavior such as the distribution, combustion and mitigation. This paper introduces the experimental research activity on hydrogen risk, which was presented at International Congress on Advances in Nuclear Power Plants (ICAPP) this year. The KAERI is preparing a test facility, called SPARC (SPray-Aerosol-Recombiner-Combustion test facility), for an assessment of the hydrogen risk. In the SPARC, hydrogen behavior such as mixing with steam and air, distribution, and combustion in the containment atmosphere will be observed. The SPARC consists of a pressure vessel with a 9.5 m height and 3.4 m in diameter and the operating system to control the thermal hydraulic conditions up to 1.5 MPa at 453 K in a vessel. The temperature, pressure, and gas concentration at various locations will be measured to estimate the atmospheric behavior in a vessel. To install the SPARC, an experimental building, called LIFE (Laboratory for Innovative mitigation of threats from Fission products and Explosion), was constructed at the KAERI site. LIFE has an area of 480 m''2 and height of 18.6 m, and it was designed by considering the experimental safety and specification of a large-sized test facility.

Application for approval to construct the Waste Receiving And Processing facility

International Nuclear Information System (INIS)

1993-02-01

The following Application For Approval Of Construction is being submitted by the US Department of Energy, Richland Field Office pursuant to 40 CFR 61.07, ''Application for Approval of Construction or Modification,'' for the Waste Receiving and Processing (WRAP) Module 1 facility (also referred to as WRAP 1). The WRAP 1 facility will be a new source of radioactive emissions to the atmosphere. The WRAP 1 facility will be housed in the new 2336-W Building, which will be located in the 200 West Area south of 23rd Street and west of Dayton Avenue. The 200 West Area is located within the boundary of the Hanford Site. The mission of the WRAP 1 facility is to examine, assay, characterize, treat, and repackage solid radioactive and mixed waste to enable permanent disposal of the waste in accordance with all applicable regulations. The solid wastes to be handled in the WRAP 1 facility include low-level waste (LLW), Transuranic (TRU) waste, TRU mixed waste, and low-level mixed waste (LLMW). The WRAP 1 facility will only accept contact handled (CH) waste containers. CH waste is a waste category whose external surface dose rate does not exceed 200 mrem/h. These containers have a surface dose rate of less than 200 mrem/h

Advances in technology for the construction of deep-underground facilities

Energy Technology Data Exchange (ETDEWEB)

1987-12-31

The workshop was organized in order to address technological issues important to decisions regarding the feasibility of strategic options. The objectives of the workshop were to establish the current technological capabilities for deep-underground construction, to project those capabilities through the compressed schedule proposed for construction, and to identify promising directions for timely allocation of existing research and development resources. The earth has been used as a means of protection and safekeeping for many centuries. Recently, the thickness of the earth cover required for this purpose has been extended to the 2,000- to 3,000-ft range in structures contemplated for nuclear-waste disposal, energy storage, and strategic systems. For defensive missile basing, it is now perceived that the magnitude of the threat has increased through better delivery systems, larger payloads, and variable tactics of attack. Thus, depths of 3,000 to 8,000 ft are being considered seriously for such facilities. Moreover, it appears desirable that the facilities be operational (if not totally complete) for defensive purposes within a five-year construction schedule. Deep excavations such as mines are similar in many respects to nearsurface tunnels and caverns for transit, rail, sewer, water, hydroelectric, and highway projects. But the differences that do exist are significant. Major distinctions between shallow and deep construction derive from the stress fields and behavior of earth materials around the openings. Different methodologies are required to accommodate other variations resulting from increased depth, such as elevated temperatures, reduced capability for site exploration, and limited access during project execution. This report addresses these and other questions devoted to geotechnical characterization, design, construction, and excavation equipment.

Design and construction of low level radioactive waste disposal facility at Rokkasho storage center

International Nuclear Information System (INIS)

Takahashi, K.; Itoh, H.; Iimura, H.; Shimoda, H.

1992-01-01

Japan Nuclear Fuel Industries Co., Inc. (JNFI) which has been established to dispose through burial the low-level radioactive waste (LLW) produced by nuclear power stations over the country is now constructing Rokkasho LLW Storage Center at Rokkasho Village,Aomori Prefecture. At this storage center JNFI plans to bury about 200,000m 3 , of LLW (equivalent to about one million drums each with a 200 liter capacity), and ultimately plans to bury about 600,000m 3 about 3 million drums of LLW. About the construction of the burial facilities for the first-stage LLW equivalent to 200,000 drums (each with a 200-liter capacity) we obtained the government's permit in November, 1990 and set out the construction work from the same month, which has since been promoted favorably. The facilities are scheduled to start operation from December, 1992. This paper gives an overview of at these facilities

Design and construction of the defense waste processing facility project at the Savannah River Plant

International Nuclear Information System (INIS)

Baxter, R.G.

1986-01-01

The Du Pont Company is building for the Department of Energy a facility to vitrify high-level radioactive waste at the Savannah River Plant (SRP) near Aiken, South Carolina. The Defense Waste Processing Facility (DWPF) will solidify existing and future radioactive wastes by immobilizing the waste in Processing Facility (DWPF) will solidify existing and future radioactives wastes by immobilizing the waste in borosilicate glass contained in stainless steel canisters. The canisters will be sealed, decontaminated and stored, prior to emplacement in a federal repository. At the present time, engineering and design is 90% complete, construction is 25% complete, and radioactive processing in the $870 million facility is expected to begin by late 1989. This paper describes the SRP waste characteristics, the DWPF processing, building and equipment features, and construction progress of the facility

Outline of construction and facility features of Onagawa nuclear power station Unit No. 2

International Nuclear Information System (INIS)

Umimura, Yoshiharu; Tsunoda, Ryohei; Watanabe, Kazunori

1996-01-01

Tohoku Electric Power Company promotes development of various power sources to provide a stable supply of electricity in the future, and nuclear power takes a leading part. In August 1989, construction of Onagawa nuclear power plant Unit No. 2 (825MW) was started, following Unit No. 1 (524MW) which went on line in 1984 as Tohoku Electric's first nuclear power plant unit. Unit No. 2 began commercial operation in July 1995 through satisfactory construction work such as RPV hydraulic test in March 1994, fuel loading in October 1994, and various startup tests in each power stage. The design and construction of Unit No. 2 reflect construction and operation experience gained from Unit No. 1, and the latest technology, including that of the LWR Improvement and Standardization Program, was adopted to enhance facility reliability, improve operation and maintenance performance, and reduce worker dosage. Features of the facility, construction techniques, and a description of preoperation of Onagawa nuclear power plant Unit No. 2 are described in this paper. (author)

Corrosion behaviour of steel rebars embedded in a concrete designed for the construction of an intermediate-level radioactive waste disposal facility

Directory of Open Access Journals (Sweden)

Schulz F.M.

2013-07-01

Full Text Available The National Atomic Energy Commission of the Argentine Republic is developing a nuclear waste disposal management programme that contemplates the design and construction of a facility for the final disposal of intermediate-level radioactive wastes. The repository is based on the use of multiple, independent and redundant barriers. The major components are made in reinforced concrete so, the durability of these structures is an important aspect for the facility integrity. This work presents an investigation performed on an instrumented reinforced concrete prototype specifically designed for this purpose, to study the behaviour of an intermediate level radioactive waste disposal facility from the rebar corrosion point of view. The information obtained will be used for the final design of the facility in order to guarantee a service life more or equal than the foreseen durability for this type of facilities.

Physics and detector simulation facility Type O workstation specifications

International Nuclear Information System (INIS)

Chartrand, G.; Cormell, L.R.; Hahn, R.; Jacobson, D.; Johnstad, H.; Leibold, P.; Marquez, M.; Ramsey, B.; Roberts, L.; Scipioni, B.; Yost, G.P.

1990-11-01

This document specifies the requirements for the front-end network of workstations of a distributed computing facility. This facility will be needed to perform the physics and detector simulations for the design of Superconducting Super Collider (SSC) detectors, and other computations in support of physics and detector needs. A detailed description of the computer simulation facility is given in the overall system specification document. This document provides revised subsystem specifications for the network of monitor-less Type 0 workstations. The requirements specified in this document supersede the requirements given. In Section 2 a brief functional description of the facility and its use are provided. The list of detailed specifications (vendor requirements) is given in Section 3 and the qualifying requirements (benchmarks) are described in Section 4

A Qualitative Comparison on Guidelines for Construction Workers Accommodation and Facility

OpenAIRE

Khamis Norasyikin; Suratkon Azeanita; Mohammad Hairuddin; Yaman Siti Khalijah

2017-01-01

Construction industry in Malaysia covers almost 1.3 million workers. Thus, realizing the importance of human-centred trait, a long-term plan that is led by the Construction Industry Development Board Malaysia (CIDB) has been designed to improve accommodation and facilities of workers at construction site. In conjunction to that, the Institute for Industrial Research and Standards Malaysia (SIRIM) has developed Malaysia Standard (MS 2593:2015) as the guideline for improvement of accommodation ...

Safety of nuclear fuel cycle facilities. Safety requirements

International Nuclear Information System (INIS)

2008-01-01

This publication covers the broad scope of requirements for fuel cycle facilities that, in light of the experience and present state of technology, must be satisfied to ensure safety for the lifetime of the facility. Topics of specific reference include aspects of nuclear fuel generation, storage, reprocessing and disposal. Contents: 1. Introduction; 2. The safety objective, concepts and safety principles; 3. Legal framework and regulatory supervision; 4. The management system and verification of safety; 5. Siting of the facility; 6. Design of the facility; 7. Construction of the facility; 8. Commissioning of the facility; 9. Operation of the facility; 10. Decommissioning of the facility; Appendix I: Requirements specific to uranium fuel fabrication facilities; Appendix II: Requirements specific to mixed oxide fuel fabrication facilities; Appendix III: Requirements specific to conversion facilities and enrichment facilities

Construction and operation of replacement hazardous waste handling facility at Lawrence Berkeley Laboratory

International Nuclear Information System (INIS)

1992-09-01

The US Department of Energy (DOE) has prepared an environmental assessment (EA), DOE/EA-0423, for the construction and operation of a replacement hazardous waste handling facility (HWHF) and decontamination of the existing HWHF at Lawrence Berkeley Laboratory (LBL), Berkeley, California. The proposed facility would replace several older buildings and cargo containers currently being used for waste handling activities and consolidate the LBL's existing waste handling activities in one location. The nature of the waste handling activities and the waste volume and characteristics would not change as a result of construction of the new facility. Based on the analysis in the EA, DOE has determined that the proposed action would not constitute a major Federal action significantly affecting the quality of the human environment within the meaning of the National Environmental Policy Act (NEPA) of 1969, 42 USC. 4321 et seq. Therefore, an environmental impact statement is not required

Proposal for construction of a proton--proton storage accelerator facility (Isabelle)

International Nuclear Information System (INIS)

1975-06-01

A proposal is made for the construction of proton storage rings at the Brookhaven Alternating Gradient Synchrotron (AGS) using superconducting magnets for which much of the technology has already been developed. This proton-proton colliding beam facility, ''ISABELLE,'' will provide large increases in both the center-of-mass energy and the luminosity, key machine parameters for high energy physics. The physics potential and the general description of the facility are discussed in detail, and the physical plant layout, a cost estimate and schedule, and future options are given.(U.S.)

FEASIBILITY OF CONSTRUCTION OF SOLAR ENERGY FACILITIES ON THE TERRITORY OF RUSSIA

Directory of Open Access Journals (Sweden)

Виталий Игоревич Беляев

2017-11-01

Full Text Available The article shows the energy problems that could solve the construction of solar energy facilities in Russia. From various points of view, it is considered how rational is the placement of solar stations in Russia. A number of problems experienced by solar energy are presented directly on the territory of Russia. A comparison of Russia with Western states with respect to the construction of solar stations is shown. A new branch of "green" energy in the world is presented - bio photovoltaic systems

Fast Flux Test Facility, Sodium Storage Facility project-specific project management plan

International Nuclear Information System (INIS)

Shank, D.R.

1994-01-01

This Project-Specific Project Management Plan describes the project management methods and controls used by the WHC Projects Department to manage Project 03-F-031. The Sodium Storage Facility provides for storage of the 260,000 gallons of sodium presently in the FFTF Plant. The facility will accept the molten sodium transferred from the FFTF sodium systems, and store the sodium in a solid state under an inert cover gas until such time as a Sodium Reaction Facility is available for final disposal of the sodium

Fast Flux Test Facility, Sodium Storage Facility project-specific project management plan

Energy Technology Data Exchange (ETDEWEB)

Shank, D.R.

1994-12-29

This Project-Specific Project Management Plan describes the project management methods and controls used by the WHC Projects Department to manage Project 03-F-031. The Sodium Storage Facility provides for storage of the 260,000 gallons of sodium presently in the FFTF Plant. The facility will accept the molten sodium transferred from the FFTF sodium systems, and store the sodium in a solid state under an inert cover gas until such time as a Sodium Reaction Facility is available for final disposal of the sodium.

Brayton Isotope Power System (BIPS) facility specification

International Nuclear Information System (INIS)

1976-01-01

General requirements for the Brayton Isotope Power System (BIPS)/Ground Demonstration System (GDS) assembly and test facility are defined. The facility will include provisions for a complete test laboratory for GDS checkout, performance, and endurance testing, and a contamination-controlled area for assembly, fabrication, storage, and storage preparation of GDS components. Specifications, schedules, and drawings are included

Brayton Isotope Power System (BIPS) facility specification

Energy Technology Data Exchange (ETDEWEB)

1976-05-31

General requirements for the Brayton Isotope Power System (BIPS)/Ground Demonstration System (GDS) assembly and test facility are defined. The facility will include provisions for a complete test laboratory for GDS checkout, performance, and endurance testing, and a contamination-controlled area for assembly, fabrication, storage, and storage preparation of GDS components. Specifications, schedules, and drawings are included.

Development of inherent technologies for advanced PWR core - A study on the current status and the construction feasibility of critical facilities

Energy Technology Data Exchange (ETDEWEB)

Yang, Won Sik; Yang, Hyun Seok [Chosun University, Kwangju (Korea); Kim, Chang Hyo; Shim, Hyung Jin [Seoul National University, Seoul (Korea)

1999-03-01

The objective of this study is to examine the appropriateness of constructing critical facilities in our country and to decide a course of constructing them if necessary by surveying the status and utilization of foreign facilities and by investigating the demand for domestic facilities. We investigated the status and the utilization of foreign critical facilities through literature survey and personal visitation. In our judgement, critical facilities are necessary for developing the advanced reactors and fuels which are being studied as parts of the Nuclear R and D Program by MOST. Considering the construction cost and the current state of domestic economy, however, it is unjustifiable to build three different types of critical facilities (the light water, the heavy water, and the fast critical facility). It appears to be reasonable to build a light water critical, considering the construction cost, degree of utilization, and other constraints. (author). 89 refs., 134 figs., 64 tabs.

Construction of new biological research facility for internal emitter and prospect

International Nuclear Information System (INIS)

Matsuoka, Osamu

1979-01-01

The construction of the new biological research facility for internal emitters is to start in 1979 in the National Institute of Radiological Sciences. The bodily harm of plutonium had been studied in 1965 for the first time in Japan, and mice and rats were tested as the experimental animals. The conceptual design of the biological research facility for internal emitters has been conducted from 1976 to 1978. The causes making the construction of this facility difficult are as follows: 1) the regulation concerning the handling of plutonium has no lower limit, and the animals administered with dosage of plutonium are not permitted to be kept outdoors, 2) the waste disposal of dead bodies and excrements of the animals is controlled very severely, 3) many animal breeders with the knowledge of radiation protection are needed for the special experiment, and 4) the budget is not sufficient for this experiment of handling plutonium. To resolve these problems, much efforts have been exerted on the test of breeding dogs and monkeys, the disposal of radioactive animal wastes, the treatment of urine of radioactive animals, the reduction of labor for breeding contaminated animals, and keeping of safety. The present situation of the researches on internal emitters in the USA, Germany, Britain, France and the Soviet Union is reviewed for reference. The outline of the new biological research facility for internal emitters is presented. The building has seven floors with the total area of about 13,000 m 2 , and comprises three controlled areas and no contamination laboratories. The future experiments, which are expected to be conducted after the completion of this facility, are the animal tests to evaluate the influence of fissile materials, especially plutonium, and the fundamental experiments to take out the radioactive nuclides accidentally taken into bodies. (Nakai, Y.)

Dismantling of nuclear facilities

International Nuclear Information System (INIS)

Tallec, M.; Kus, J.P.

2009-01-01

Nuclear facilities have a long estimable lifetime but necessarily limited in time. At the end of their operation period, basic nuclear installations are the object of cleansing operations and transformations that will lead to their definitive decommissioning and then to their dismantling. Because each facility is somewhere unique, cleansing and dismantling require specific techniques. The dismantlement consists in the disassembly and disposing off of big equipments, in the elimination of radioactivity in all rooms of the facility, in the demolition of buildings and eventually in the reconversion of all or part of the facility. This article describes these different steps: 1 - dismantling strategy: main de-construction guidelines, expected final state; 2 - industries and sites: cleansing and dismantling at the CEA, EDF's sites under de-construction; 3 - de-construction: main steps, definitive shutdown, preparation of dismantling, electromechanical dismantling, cleansing/decommissioning, demolition, dismantling taken into account at the design stage, management of polluted soils; 4 - waste management: dismantlement wastes, national policy of radioactive waste management, management of dismantlement wastes; 5 - mastery of risks: risk analysis, conformability of risk management with reference documents, main risks encountered at de-construction works; 6 - regulatory procedures; 7 - international overview; 8 - conclusion. (J.S.)

Construction of JRR-3 spent fuel dry storage facility

International Nuclear Information System (INIS)

Adachi, M.

1982-01-01

To store the JRR-3 metallic natural uranium spent fuel elements, dry storage facility has been constructed in JAERI. This facility has a capacity of about 30T of uranium. The elements are placed in encapsulated canister, then stored in drywell in the store. The store is basically an ordinary concrete box, about 12m long, 13m wide, and 5m deep. The store comprises a 10 x 10 lattice array of the drywells. The drywell consists of a stainless steel liner which is 2.5m deep, 36cm ID and 0.8cm thickness. A drywell also has an air inlet, outlet pipe for radiation monitoring and a shield plug in carbon steel for radiation protection. A canister which consists of stainless steel with 0.5cm thickness contains 36 elements. Sealing of the canister is accomplished by fusion welding

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

The Design and Construction of the Advanced Mixed Waste Treatment Facility

Energy Technology Data Exchange (ETDEWEB)

Harrop, G.

2003-02-27

The Advanced Mixed Treatment Project (AMWTP) privatized contract was awarded to BNFL Inc. in December 1996 and construction of the main facility commenced in August 2000. The purpose of the advanced mixed waste treatment facility is to safely treat plutonium contaminated waste, currently stored in drums and boxes, for final disposal at the Waste Isolation Pilot Plant (WIPP). The plant is being built at the Idaho National Engineering and Environmental Laboratory. Construction was completed in 28 months, to satisfy the Settlement Agreement milestone of December 2002. Commissioning of the related retrieval and characterization facilities is currently underway. The first shipment of pre-characterized waste is scheduled for March 2003, with AMWTP characterized and certified waste shipments from June 2003. To accommodate these challenging delivery targets BNFL adopted a systematic and focused construction program that included the use of a temporary structure to allow winter working, proven design and engineering principles and international procurement policies to help achieve quality and schedule. The technology involved in achieving the AMWTP functional requirements is primarily based upon a BNFL established pedigree of plant and equipment; applied in a manner that suits the process and waste. This technology includes the use of remotely controlled floor mounted and overhead power manipulators, a high power shredder and a 2000-ton force supercompactor with the attendant glove box suite, interconnections and automated material handling. The characterization equipment includes real-time radiography (RTR) units, drum and box assay measurement systems, drum head space gas sampling / analysis and drum venting, drum coring and sampling capabilities. The project adopted a particularly stringent and intensive pre-installation testing philosophy to ensure that equipment would work safely and reliably at the required throughput. This testing included the complete off site

The Design and Construction of the Advanced Mixed Waste Treatment Facility

International Nuclear Information System (INIS)

Harrop, G.

2003-01-01

The Advanced Mixed Treatment Project (AMWTP) privatized contract was awarded to BNFL Inc. in December 1996 and construction of the main facility commenced in August 2000. The purpose of the advanced mixed waste treatment facility is to safely treat plutonium contaminated waste, currently stored in drums and boxes, for final disposal at the Waste Isolation Pilot Plant (WIPP). The plant is being built at the Idaho National Engineering and Environmental Laboratory. Construction was completed in 28 months, to satisfy the Settlement Agreement milestone of December 2002. Commissioning of the related retrieval and characterization facilities is currently underway. The first shipment of pre-characterized waste is scheduled for March 2003, with AMWTP characterized and certified waste shipments from June 2003. To accommodate these challenging delivery targets BNFL adopted a systematic and focused construction program that included the use of a temporary structure to allow winter working, proven design and engineering principles and international procurement policies to help achieve quality and schedule. The technology involved in achieving the AMWTP functional requirements is primarily based upon a BNFL established pedigree of plant and equipment; applied in a manner that suits the process and waste. This technology includes the use of remotely controlled floor mounted and overhead power manipulators, a high power shredder and a 2000-ton force supercompactor with the attendant glove box suite, interconnections and automated material handling. The characterization equipment includes real-time radiography (RTR) units, drum and box assay measurement systems, drum head space gas sampling / analysis and drum venting, drum coring and sampling capabilities. The project adopted a particularly stringent and intensive pre-installation testing philosophy to ensure that equipment would work safely and reliably at the required throughput. This testing included the complete off site

Facile construction of a random protein domain insertion library using an engineered transposon.

Science.gov (United States)

Shah, Vandan; Pierre, Brennal; Kim, Jin Ryoun

2013-01-15

Insertional fusion between multiple protein domains represents a novel means of creating integrated functionalities. Currently, there is no robust guideline for selection of insertion sites ensuring the desired functional outcome of insertional fusion. Therefore, construction and testing of random domain insertion libraries, in which a host protein domain is randomly inserted into a guest protein domain, significantly benefit extensive exploration of sequence spaces for insertion sites. Short peptide residues are usually introduced between protein domains to alleviate structural conflicts, and the interdomain linker residues may affect the functional outcome of protein insertion complexes. Unfortunately, optimal control of interdomain linker residues is not always available in conventional methods used to construct random domain insertion libraries. Moreover, most conventional methods employ blunt-end rather than sticky-end ligation between host and guest DNA fragments, thus lowering library construction efficiency. Here, we report the facile construction of random domain insertion libraries using an engineered transposon. We show that random domain insertion with optimal control of interdomain linker residues was possible with our engineered transposon-based method. In addition, our method employs sticky-end rather than blunt-end ligation between host and guest DNA fragments, thus allowing for facile construction of relatively large sized libraries. Copyright © 2012 Elsevier Inc. All rights reserved.

Development of Integral Effect Test Facility P and ID and Technical Specification for SMART Fluid System

International Nuclear Information System (INIS)

Lee, Sang Il; Jung, Y. H.; Yang, H. J.; Song, S. Y.; Han, O. J.; Lee, B. J.; Kim, Y. A.; Lim, J. H.; Park, K. W.; Kim, N. G.

2010-01-01

SMART integral test loop is the thermal hydraulic test facility with a high pressure and temperature for simulating the major systems of the prototype reactor, SMART-330. The objective of this project is to conduct the basic design for constructing SMART ITL. The major results of this project include a series of design documents, technical specifications and P and ID. The results can be used as the fundamental materials for making the detailed design which is essential for manufacturing and installing SMART ITL

Research on the Construction Management and Sustainable Development of Large-Scale Scientific Facilities in China

Science.gov (United States)

Guiquan, Xi; Lin, Cong; Xuehui, Jin

2018-05-01

As an important platform for scientific and technological development, large -scale scientific facilities are the cornerstone of technological innovation and a guarantee for economic and social development. Researching management of large-scale scientific facilities can play a key role in scientific research, sociology and key national strategy. This paper reviews the characteristics of large-scale scientific facilities, and summarizes development status of China's large-scale scientific facilities. At last, the construction, management, operation and evaluation of large-scale scientific facilities is analyzed from the perspective of sustainable development.

Risk management at the stage of design of high-rise construction facilities

Science.gov (United States)

Politi, Violetta

2018-03-01

This paper describes the assessment of the probabilistic risk of an accident formed in the process of designing a technically complex facility. It considers values of conditional probabilities of the compliance of load-bearing structures with safety requirements, provides an approximate list of significant errors of the designer and analyzes the relationship between the degree of compliance and the level of danger of errors. It describes and proposes for implementation the regulated procedures related to the assessment of the safety level of constructive solutions and the reliability of the construction process participants.

324 and 327 Facilities Environmental Effluent Specifications

International Nuclear Information System (INIS)

JOHNSON, D.L.

1999-01-01

These effluent specifications address requirements for the 324/321 Facilities, which are undergoing stabilization activities. Effluent specifications are imposed to protect personnel, the environment and the public, by ensuring adequate implementation and compliance with federal and state regulatory requirements and Hanford programs

Predisposal Management of Radioactive Waste from Nuclear Fuel Cycle Facilities. Specific Safety Guide

International Nuclear Information System (INIS)

2016-01-01

This Safety Guide provides guidance on the predisposal management of all types of radioactive waste (including spent nuclear fuel declared as waste and high level waste) generated at nuclear fuel cycle facilities. These waste management facilities may be located within larger facilities or may be separate, dedicated waste management facilities (including centralized waste management facilities). The Safety Guide covers all stages in the lifetime of these facilities, including their siting, design, construction, commissioning, operation, and shutdown and decommissioning. It covers all steps carried out in the management of radioactive waste following its generation up to (but not including) disposal, including its processing (pretreatment, treatment and conditioning). Radioactive waste generated both during normal operation and in accident conditions is considered

Radiation control aspects of the civil construction for a high power free electron laser (FEL) facility

International Nuclear Information System (INIS)

Dunn, T.; Neil, G.; Stapleton, G.

1996-01-01

The paper discusses some of the assumptions and methods employed for the control of ionizing radiation in the specifications for the civil construction of a planned free electron laser facility based on a 200 MeV, 5 mA superconducting recirculation electron accelerator. Consideration is given firstly to the way in which the underlying building configuration and siting aspects were optimized on the basis of the early assumptions of beam loss and radiation goals. The various design requirements for radiation protection are then considered, and how they were folded into an aesthetically pleasing and functional building

Long term integrity of spent fuel and construction materials for dry storage facilities

Energy Technology Data Exchange (ETDEWEB)

Saegusa, T [CRIEPI (Japan)

2012-07-01

In Japan, two dry storage facilities at reactor sites have already been operating since 1995 and 2002, respectively. Additionally, a large scale dry storage facility away from reactor sites is under safety examination for license near the coast and desired to start its operation in 2010. Its final storage capacity is 5,000tU. It is therefore necessary to obtain and evaluate the related data on integrity of spent fuels loaded into and construction materials of casks during long term dry storage. The objectives are: - Spent fuel rod: To evaluate hydrogen migration along axial fuel direction on irradiated claddings stored for twenty years in air; To evaluate pellet oxidation behaviour for high burn-up UO{sub 2} fuels; - Construction materials for dry storage facilities: To evaluate long term reliability of welded stainless steel canister under stress corrosion cracking (SCC) environment; To evaluate long term integrity of concrete cask under carbonation and salt attack environment; To evaluate integrity of sealability of metal gasket under long term storage and short term accidental impact force.

Technical specifications for the Oak Ridge Critical Experiments Facility

International Nuclear Information System (INIS)

Stinnett, R.M.

1986-01-01

These Technical Specifications for the Oak Ridge Critical Experiments Facility (CEF) delineate limiting conditions of operation for the facility. The CEF is used primarily for testing the High Flux Isotope Reactor (HFIR) fuel assemblies. Specifically, the Criticality Testing Unit, Liquid (CTUL), located in the CEF, is used for the HFIR fuel assembly test. The test is performed to satisfy the surveillance requirements of the HFIR Technical Specifications. The test is used to determine the water-submerged shutdown margin for each fuel assembly. 11 refs

Environmental assessment report: Nuclear Test Technology Complex. [Construction and operation of proposed facility

Energy Technology Data Exchange (ETDEWEB)

Tonnessen, K.; Tewes, H.A.

1982-08-01

The US Department of Energy (USDOE) is planning to construct and operate a structure, designated the Nuclear Test Technology Complex (NTTC), on a site located west of and adjacent to the Lawrence Livermore National Laboratory. The NTTC is designed to house 350 nuclear test program personnel, and will accommodate the needs of the entire staff of the continuing Nuclear Test Program (NTP). The project has three phases: land acquisition, facility construction and facility operation. The purpose of this environmental assessment report is to describe the activities associated with the three phases of the NTTC project and to evaluate potential environmental disruptions. The project site is located in a rural area of southeastern Alameda County, California, where the primary land use is agriculture; however, the County has zoned the area for industrial development. The environmental impacts of the project include surface disturbance, high noise levels, possible increases in site erosion, and decreased air quality. These impacts will occur primarily during the construction phase of the NTTC project and can be mitigated in part by measures proposed in this report.

FFTF constructibility

International Nuclear Information System (INIS)

Weber, S.A.; Hulbert, D.I.

1975-01-01

The influence of the design criteria on the constructibility of the Fast Flux Test Facility is described. Specifically, the effects of requirements due to maintenance accessibility, inerting of cells, seismicity, codes, and standards are addressed. The design and construction techniques developed to minimize the impact of the design criteria on cost and schedule are presented with particular emphasis on the cleanliness and humidity controls imposed during construction of the sodium systems. (U.S.)

IAEA Guidance for Safeguards Implementation in Facility Design and Construction

International Nuclear Information System (INIS)

Sprinkle, J.; Hamilton, A.; Poirier, S.; Catton, A.; Ciuculescu, C.; Ingegneri, M.; Plenteda, R.

2015-01-01

One of the IAEA's statutory objectives is to seek to accelerate and enlarge the contribution of nuclear energy to peace, health and prosperity throughout the world. One way the IAEA works to achieve this objective is through the publication of technical series that can provide guidance to Member States. These series include the IAEA Services Series, the IAEA Safety Standard Series, the IAEA Nuclear Security Series and the IAEA Nuclear Energy Series. The Nuclear Energy Series is comprised of publications designed to encourage and assist research and development on, and practical application of, nuclear energy for peaceful purposes. This includes guidance to be used by owners and operators of utilities, academia, vendors and government officials. The IAEA has chosen the Nuclear Energy Series to publish guidance for States regarding the consideration of safeguards in nuclear facility design and construction. Historically, safeguards were often applied after a facility was designed or maybe even after it was built. However, many in the design and construction community would prefer to include consideration of these requirements from the conceptual design phase in order to reduce the need for retro-fits and modifications. One can then also take advantage of possible synergies between safeguards, security, safety and environmental protection and reduce the project risk against cost increments and schedule slippage. The IAEA is responding to this interest with a suite of publications in the IAEA Nuclear Energy Series, developed with the assistance of a number of Member State Support Programmes through a joint support programme task: · International Safeguards in Nuclear Facility Design and Construction (NP-T-2.8, 2013), · International Safeguards in the Design of Nuclear Reactors (NP-T-2.9, 2014), · International Safeguards in the Design of Spent Fuel Management (NF-T-3.1, tbd), · International Safeguards in the Design of Fuel Fabrication Plants (NF-T-4.7, tbd

A Qualitative Comparison on Guidelines for Construction Workers Accommodation and Facility

Directory of Open Access Journals (Sweden)

Khamis Norasyikin

2017-01-01

Full Text Available Construction industry in Malaysia covers almost 1.3 million workers. Thus, realizing the importance of human-centred trait, a long-term plan that is led by the Construction Industry Development Board Malaysia (CIDB has been designed to improve accommodation and facilities of workers at construction site. In conjunction to that, the Institute for Industrial Research and Standards Malaysia (SIRIM has developed Malaysia Standard (MS 2593:2015 as the guideline for improvement of accommodation and facilities for workers which is able to contribute to the achievement of the target in the Construction Industry Transformation Programme (CITP. However, a phenomenon that is centred on the level of itscorroboration compared with other similar guidelines has been voiced by some practitioners of construction, especially when the guideline are likely to be the basis of a new related act. Therefore, based on MS 2593:2015, this introductory research is conducted to qualitatively analyse the corroborative level of the guideline compared to its counterpart guidelines. By using a comprehensive document analysis method which anchored to frequency approach and assisted by NVivo v.8 software, the report found out that the Malaysia-based guideline is on par to the restwith some introduction of new variables (especially towards leisure and social aspects. Thus, further research on gauging industry’s willingness and existing compliance rates is deemed appropriate in order to inculcate positive impacts towards the objectives of MS 2593:2015, and subsequently contributes to the formation of the forthcoming corresponding act.

Manhattan Project buildings and facilities at the Hanford Site: A construction history

Energy Technology Data Exchange (ETDEWEB)

Gerber, M.S.

1993-09-01

This document thoroughly examines the role that the Hanford Engineer Works played in the Manhattan project. The historical aspects of the buildings and facilities are characterized. An in depth look at the facilities, including their functions, methods of fabrication and appearance is given for the 100 AREAS, 200 AREAS, 300 AREAS, 500, 800 and 900 AREAS, 600 AREA, 700 AREA, 1100 AREA and temporary construction structures.

Manhattan Project buildings and facilities at the Hanford Site: A construction history

International Nuclear Information System (INIS)

Gerber, M.S.

1993-09-01

This document thoroughly examines the role that the Hanford Engineer Works played in the Manhattan project. The historical aspects of the buildings and facilities are characterized. An in depth look at the facilities, including their functions, methods of fabrication and appearance is given for the 100 AREAS, 200 AREAS, 300 AREAS, 500, 800 and 900 AREAS, 600 AREA, 700 AREA, 1100 AREA and temporary construction structures

Preliminary Feasibility Study on the Construction of Steel Hot Cell Facility for Precise Manipulated Examinations

International Nuclear Information System (INIS)

Ahn, Sangbok; Kwon, Hyungmun; Kim, Heemoon; Kim, Dosik; Min, Duckkee; Hong, Kwonpyo

2006-01-01

Hot laboratory is essential facility to research and develop in the nuclear industries to examine radioactive materials. The post irradiation examinations for irradiated fuels and materials should be mainly conducted in the hot cell facility to protect radiations to operators. Hot cells are divided into a concrete hot cell and a steel hot cell according to the wall materials. Usually a concrete hot cell is applied to test for high level radioactive materials like as a fuel assembly, rods, and large structure specimens, and a steel hot cell for comparatively lower level activity materials in fuel fragments, and small structural materials. A steel hot cell has many benefits in a specimen manipulation, construction and maintenance costs. In recent the test for the irradiated materials is more frequently required a small and precise manipulating examination for higher degree tests of research and developments. Unfortunately hot laboratory facilities in domestics have mainly constituted of concrete hot cells, and not ready for techniques in steel hot cells. In this paper the construction feasibility of steel hot cell facility is preliminary reviewed in the points of the status of domestic facilities, the test demand prospect and detailed plans

Ten years of cryo-magnetic W7-X test facility construction and operation

International Nuclear Information System (INIS)

Renard, B.; Dispau, G.; Donati, A.; Genini, L.; Gournay, J.F.; Kuster, O.; Molinie, F.; Schild, T.; Touzery, R.; Vieillard, L.; Walter, C.

2011-01-01

The construction, commissioning, and operation phases of the W7-X cryo-magnetic test facility in CEA Saclay lasted ten years. The large diversity of equipments called, specialties involved and problems solved attest the expertise that was required to operate the test facility and test the coils. Nearly one hundred cryogenic tests were performed on the seventy W7-X coils, at a rate always increasing, using two cryostats each holding two coils. This paper presents the test facility and its operation first, the cryogenic difficulties that were confronted with their solutions, the electro-magnetic difficulties encountered along with corrective actions, and finally the instrumentation and data acquisition aspects. (authors)

Environmental assessment for the construction and operation of waste storage facilities at the Paducah Gaseous Diffusion Plant, Paducah, Kentucky

Energy Technology Data Exchange (ETDEWEB)

NONE

1994-06-01

DOE is proposing to construct and operate 3 waste storage facilities (one 42,000 ft{sup 2} waste storage facility for RCRA waste, one 42,000 ft{sup 2} waste storage facility for toxic waste (TSCA), and one 200,000 ft{sup 2} mixed (hazardous/radioactive) waste storage facility) at Paducah. This environmental assessment compares impacts of this proposed action with those of continuing present practices aof of using alternative locations. It is found that the construction, operation, and ultimate closure of the proposed waste storage facilities would not significantly affect the quality of the human environment within the meaning of NEPA; therefore an environmental impact statement is not required.

Environmental assessment for the construction and operation of waste storage facilities at the Paducah Gaseous Diffusion Plant, Paducah, Kentucky

International Nuclear Information System (INIS)

1994-06-01

DOE is proposing to construct and operate 3 waste storage facilities (one 42,000 ft 2 waste storage facility for RCRA waste, one 42,000 ft 2 waste storage facility for toxic waste (TSCA), and one 200,000 ft 2 mixed (hazardous/radioactive) waste storage facility) at Paducah. This environmental assessment compares impacts of this proposed action with those of continuing present practices aof of using alternative locations. It is found that the construction, operation, and ultimate closure of the proposed waste storage facilities would not significantly affect the quality of the human environment within the meaning of NEPA; therefore an environmental impact statement is not required

Construction of a Solid State Research Facility, Building 3150

International Nuclear Information System (INIS)

1993-07-01

The Department of Energy (DOE) proposes to construct a new facility to house the Materials Synthesis Group (MSG) and the Semiconductor Physics Group (SPG) of the Solid State Division, Oak Ridge National Laboratory (ORNL). The location of the proposed action is Roane County, Tennessee. MSG is involved in the study of crystal growth and the preparation and characterization of advanced materials, such as high-temperature superconductors, while SPG is involved in semiconductor physics research. All MSG and a major pardon of SPG research activities are now conducted in Building 2000, a deteriorating structure constructed in the 1940. The physical deterioration of the roof; the heating, ventilation, and air conditioning (HVAC) system; and the plumbing make this building inadequate for supporting research activities. The proposed project is needed to provide laboratory and office space for MSG and SPG and to ensure that research activities can continue without interruption due to deficiencies in the building and its associated utility systems

The Abbott School Construction Program: Report on the NJ Department of Education Proposed Regulations on Long-Range Facilities Plans

Science.gov (United States)

Ponessa, Joan

2004-01-01

This report on Long Range Facilities Plans (LRFPs) analyzes regulations proposed by the New Jersey Department of Education (NJDOE) to implement the Educational Facilities Construction and Financing Act. (EFCFA). EFCFA, which authorizes and governs New Jersey's public school construction program, was enacted in July 2000 to implement the State…

A discussion on the proposal of construction of a verification facility at CIAE for the AD-RCNPS R and D

International Nuclear Information System (INIS)

Ding Dazhao

2000-01-01

ADS is a prospective innovative nuclear power system based on the development of high power proton accelerator and well developed technology of power reactor. Its advantage and benefit in respect of waste transmutation and fuel breeding were recognized by international nuclear community. ADS provides more flexibility from viewpoint of operation and control. To made ADS to be a reliable one, a series of important problem in the components of ADS--accelerator, reactor, material and neutron physics are enumerated. The R and D of a new nuclear power system is a long term activity, including conceptual study, verification of the principle, experimental facility, prototype and commercial demonstration. To construction a verification facility is an essential step in promoting the R and D of ADS from conceptual study to technical comprehension. A verification facility that consisted of a swimming pool reactor at CIAE driven by a pulsed low energy high current accelerator is proposed. According to those experiments that should be carried out at this facility, the specifications of accelerator and the modification of the reactor core structure are given

JSME construction standard for superconducting magnets of fusion facilities. Toward the construction of ITER

International Nuclear Information System (INIS)

Nakasone, Yuji; Takahashi, Yukio; Sato, Kazuyoshi; Nishimura, Arata; Suzuki, Tetsuya; Irie, Hirosada; Nakahira, Masataka

2009-01-01

The present paper describes the general view of the construction standard, which the Japan Society of Mechanical Engineers (JSME) has recently set up and published, for superconducting magnet structures to be used in nuclear fusion facilities. The present target of the standard is tokamak-type fusion energy facilities, especially the International Thermonuclear Experimental Reactor called ITER for short. The standard contains rules for structural materials including cryogenic materials, structural design considering magnetic forces, manufacture including welding and installation, nondestructive testing, pressure proof tests and leak tests of toroidal field magnet structures. The standard covers requirements for structural integrity, deformation control, and leak tightness of all the components of the superconducting magnets and their supports except for superconducting strands and electrical insulators. The standard does not cover deterioration, which may occur in service as a result of corrosion, radiation effects, or instability of material. The standard consists of seven articles and twelve mandatory and non-mandatory appendices to the articles; i.e., (1) Scope, roles and responsibilities, (2) Materials, (3) Structural design, (4) Fabrication and installation, (5) Non-destructive examination, (6) Pressure and leak testing, and (7) Terms used in general requirements. (author)

Design, construction, and operation of the contact size reduction facility at the West Valley Demonstration Project

International Nuclear Information System (INIS)

Frank, D.E.; Reeves, S.R.; Valenti, P.J.

1988-05-01

This paper describes the design, construction and initial operation of the Contact-Handled Size Reduction Facility (CSRF) at the West Valley Demonstration Project. The facility was constructed to size reduce contaminated tanks, piping, and other metallic scrap and package the scrap for disposal. In addition, the CSRF has the capability to decontaminate scrap prior to disposal. The anticipated result of decontaminating the scrap is to reduce waste classified as transuranic or low-level Class B and C to Class A or release for unrestricted use as nonradioactive equipment. 10 figs., 1 tab

Construction and operation of replacement hazardous waste handling facility at Lawrence Berkeley Laboratory. Environmental Assessment

Energy Technology Data Exchange (ETDEWEB)

1992-09-01

The US Department of Energy (DOE) has prepared an environmental assessment (EA), DOE/EA-0423, for the construction and operation of a replacement hazardous waste handling facility (HWHF) and decontamination of the existing HWHF at Lawrence Berkeley Laboratory (LBL), Berkeley, California. The proposed facility would replace several older buildings and cargo containers currently being used for waste handling activities and consolidate the LBL`s existing waste handling activities in one location. The nature of the waste handling activities and the waste volume and characteristics would not change as a result of construction of the new facility. Based on the analysis in the EA, DOE has determined that the proposed action would not constitute a major Federal action significantly affecting the quality of the human environment within the meaning of the National Environmental Policy Act (NEPA) of 1969, 42 USC. 4321 et seq. Therefore, an environmental impact statement is not required.

Measurements of nuclear data and possibility to construct the nuclear data production facility based on electron linac

Energy Technology Data Exchange (ETDEWEB)

Namkung, Won; Ko, In Soo; Cho, Moo Hyun; Kim, Gui Nyun; Lee, Young Seok; Kang, Heung Sik [Pohang University of Science and Technology, Pohang(Korea)

2001-04-01

In order to construct an infrastructure to produce nuclear data, we studied three main items; (1) Study on the possibility to construct a facility for nuclear data production, (2) Production of nuclear data for nuclear power plant, and (3) Pulsed neutron source based on a 100-MeV electron linac at Pohang Accelerator Laboratory (PAL). We confirmed the possibility to build a nuclear data production facility utilizing a 100-MeV electron linac at PAL and manpower who wanted to participate the nuclear data production experiments. In order to measure the nuclear data for nuclear power plant, we used several nuclear data production facilities in abroad. We measured total cross sections and neutron caprure cross sections for {sup nat}Dy and {sup nat}Hf using the pulsed neutron facility in the Research Reactor Institute, Kyoto University (KURRI). The neutron capture cross sections for {sup 161,162,163,164}Dy were measured at KURRI in the neutron energy region between 0.001 eV and several tens keV, and at the fast neutron facility in Tokyo Institute of Technology in the neutron energy region between 10 keV and 100 keV. We also measured the neutron capture cross sections and gamma multiplicity of {sup 232}Th at the IBR30 in Dubna, Russia. We have construct a pulsed neutron source using a 100-MeV electron linac at PAL. We measured neutron time-of-flight (TOF) spectra in order to check the characteristics of the pulsed neutron source. We also measured a neutron total cross sections of W and Cu. The pulsed neutron facility can be utilized in the education facility for nuclear data production and the test facility for the R and D purpose of the nuclear data production facility. 29 refs., 57 figs., 22 tabs. (Author)

Construction and Verification of PLC LD-programs by LTL-specification

Directory of Open Access Journals (Sweden)

E. V. Kuzmin

2013-01-01

Full Text Available An approach to construction and verification of PLC LD-programs for discrete problems is proposed. For the specification of the program behavior, we use the linear-time temporal logic LTL. Programming is carried out in the LD-language (Ladder Diagram according to an LTL-specification. The correctness analysis of an LTL-specification is carried out by the symbolic model checking tool Cadence SMV. A new approach to programming and verification of PLC LD-programs is shown by an example. For a discrete problem, we give a LD-program, its LTL-specification and an SMV-model. The purpose of the article is to describe an approach to programming PLC, which would provide a possibility of LD-program correctness analysis by the model checking method. Under the proposed approach, the change of the value of each program variable is described by a pair of LTL-formulas. The first LTL-formula describes situations which increase the value of the corresponding variable, the second LTL-formula specifies conditions leading to a decrease of the variable value. The LTL-formulas (used for speci- fication of the corresponding variable behavior are constructive in the sense that they construct the PLC-program (LD-program, which satisfies temporal properties expressed by these formulas. Thus, the programming of PLC is reduced to the construction of LTLspecification of the behavior of each program variable. In addition, an SMV-model of a PLC LD-program is constructed according to LTL-specification. Then, the SMV-model is analysed by the symbolic model checking tool Cadence SMV.

Constructing the Exploratory Studies Facility at Yucca Mountain

International Nuclear Information System (INIS)

Kalia, H.N.; Replogle, J.M.

1996-01-01

Yucca Mountain Site Characterization Office of the US Department of Energy (DOE) is constructing an underground Exploratory Studies Facility (ESF), approximately 160 km (100 miles) northwest of Las Vegas, Nevada. This facility is being used to obtain geological, hydrological, geomechanical, thermomechanical and geochemical information to characterize, Yucca Mountain as a potential site to isolate High-Level Radioactive Waste from the accessible environment. The ESF, when completed, will consist of two ramps from surface (North and South ramp) to the potential repository horizon formations, a drift connecting the two ramps, test alcoves, and above and below ground operational support facilities. The ramps and connecting drift are being mined by a 7.62 m (25 ft) diameter, fully shielded, Tunnel Boring Machine (TBM). This paper describes the current status of the construction of the ESF and test alcoves. At the time of this writing, the following has been accomplished: North Ramp excavation is complete; four test alcoves have been excavated and are in use for scientific experiments; the excavation has reached the potential repository horizon; the drift connecting the two ramps is being excavated, and the excavation of a test alcove for thermal testing is in progress. The mining operations are ahead of schedule, and to date March 26, 1996, the TBM has excavated over 4623 m(15,160 ft.) without any major breakdowns or accidents. The average advance for a three shift (two mining shifts) production day has been 33.46 m (110 ft.). Maximum advance for a week was 218.3 m (716 ft.). An Alpine Miner (AM 75) roadheader is being used to excavate test alcoves. The major ground support system consists of Supper Swellex rock bolts, steel sets as required, Williams rock bolts and channels, and welded wire fabric. Various sections of the tunnel have been instrumented, and the entire excavation has been geologically mapped. To date, the site conditions have been those predicted

Construction and operation of an improved radiation calibration facility at Brookhaven National Laboratory. Environmental assessment

International Nuclear Information System (INIS)

1994-10-01

Calibration of instruments used to detect and measure ionizing radiation has been conducted over the last 20 years at Brookhaven National Laboratory's (BNL) Radiation Calibration Facility, Building 348. Growth of research facilities, projects in progress, and more stringent Department of Energy (DOE) orders which involve exposure to nuclear radiation have placed substantial burdens on the existing radiation calibration facility. The facility currently does not meet the requirements of DOE Order 5480.4 or American National Standards Institute (ANSI) N323-1978, which establish calibration methods for portable radiation protection instruments used in the detection and measurement of levels of ionizing radiation fields or levels of radioactive surface contaminations. Failure to comply with this standard could mean instrumentation is not being calibrated to necessary levels of sensitivity. The Laboratory has also recently obtained a new neutron source and gamma beam irradiator which can not be made operational at existing facilities because of geometry and shielding inadequacies. These sources are needed to perform routine periodic calibrations of radiation detecting instruments used by scientific and technical personnel and to meet BNL's substantial increase in demand for radiation monitoring capabilities. To place these new sources into operation, it is proposed to construct an addition to the existing radiation calibration facility that would house all calibration sources and bring BNL calibration activities into compliance with DOE and ANSI standards. The purpose of this assessment is to identify potential significant environmental impacts associated with the construction and operation of an improved radiation calibration facility at BNL

Design and construction of solidification and dewatering facility at Alabama Power Company's Farley Nuclear Plant

International Nuclear Information System (INIS)

Farnsworth, P.

1988-01-01

The approximate total cost of the structure and supporting piping systems is estimated to be 4.1 million dollars. Total dose savings per year could be as high as 70 man Rem for resin processing alone. The ability to store refueling equipment, process contaminated oils, load and unload trucks and containers regardless of weather conditions and support repair work on equipment greatly enhances the cost effectiveness of the project. It will take at least one year of operation of the facility to accurately assess the true cost savings to Alabama Power Company. The morale factor for the Waste and Decon Group has escalated measurably due to the dose reduction to our personnel. Plant and company management are well pleased due to the possibility of a spill or release to the environment has been eliminated which was on intangible cost. Facility construction has been completed as of this date and resin transfer anticipated within the next few days. Some of the problems encountered in planning and constructing this solidification and dewatering facility are presented. A safety evaluation for the facility is included in the appendix

Construction and initial operation of MHD PbLi facility at UCLA

Energy Technology Data Exchange (ETDEWEB)

Smolentsev, S., E-mail: sergey@fusion.ucla.edu; Li, F.-C.; Morley, N.; Ueki, Y.; Abdou, M.; Sketchley, T.

2013-06-15

Highlights: • New MHD PbLi loop has been constructed and tested at UCLA. • Pressure diagnostics system has been developed and successfully tested. • Ultrasound Doppler velocimeter is tested as velocity diagnostics. • Experiments on pressure drop reduction have been performed. • Experiments on MHD flow in a duct with SiC flow channel insert are underway. -- Abstract: A magnetohydrodynamic flow facility MaPLE (Magnetohydrodynamic PbLi Experiment) that utilizes molten eutectic alloy lead–lithium (PbLi) as working fluid has been constructed and tested at University of California, Los Angeles. The loop operation parameters are: maximum magnetic field 1.8 T, PbLi temperature up to 350 °C, maximum PbLi flow rate with/without a magnetic field 15/50 l/min, maximum pressure head 0.15 MPa. The paper describes the loop itself and its major components, basic operation procedures, experience of handling PbLi, initial loop testing, flow diagnostics and current and near-future experiments. The obtained test results of the loop and its components have demonstrated that the new facility is fully functioning and ready for experimental studies of magnetohydrodynamic, heat and mass transfer phenomena in PbLi flows and also can be used in mock up testing in conditions relevant to fusion applications.

Efficiency improvement of the investment and innovation activities in the transport facility construction field with public-private partnership involvement

Science.gov (United States)

Shibayeva, Marina; Serebryakova, Yelena; Shalnev, Oleg

2017-10-01

Growing demand to increase the investment volume in modernization and development projects for transport infrastructure define the urgency of the current study. The amount of private sector investments in the field is insufficient to implement the projects for road construction due to their significant capital intensity and long payoff period. The implementation of social significant infrastructure projects on the principles of public-private partnership is one of the key strategic directions of growth for transport facilities. The authors come up with a concept and methodology for modeling the investment and innovation activity in the transport facility construction. Furthermore, there is developed a model to find the balance between public and private sector investments in implementing construction projects for transport infrastructure with involvement of PPP (further - public-private partnership). The suggested concepts aim to improve the efficiency rate of the investment and innovation activity in the field of transport facility construction on the basis of public and private sectors collaboration.

Scientific Support of Construction of Unique Buildings and Structures and Facilities of Increased Danger

Science.gov (United States)

Alekhin, V. N.; Antipin, A. A.; Gorodilov, S. N.

2017-11-01

A range of works on scientific support for the construction of unique buildings and the structures and facilities of increased danger, such as airport facilities, long-span and high-rise buildings is being implemented at the department “Computer Aided Design in Civil Engineering” of Ural Federal University. The scope of work includes: numerical simulation of wind and snow loads, analysis of progressive collapse and seismic impacts, verification of design solutions. The results of wind, snow loads and progressive collapse of airport buildings in the cities of Orenburg, Rostov-on-Don and Perm are considered in the article.

Technical specifications for the Pajarito Site Critical Experiments Facility

International Nuclear Information System (INIS)

Malenfant, R.E.; Paxton, H.C.

1980-12-01

This document is to satisfy the requirement for technical specifications spelled out in DOE Manual Chapter 0540, Safety of DOE-Owned Reactors. Technical specifications are defined in Sec. 0540-048, and the requirement for them appears in Sec. 0540-015. The following technical specifications update the document, Technical Specifications for the Pajarito Site Critical Experiments Facility

Construction and operation costs of constructed wetlands treating wastewater.

Science.gov (United States)

Gkika, Dimitra; Gikas, Georgios D; Tsihrintzis, Vassilios A

2014-01-01

Design data from nine constructed wetlands (CW) facilities of various capacities (population equivalent (PE)) are used to estimate construction and operation costs, and then to derive empirical equations relating the required facility land area and the construction cost to PE. In addition, comparisons between the costs of CW facilities based on various alternative construction materials, i.e., reinforced concrete and earth structures (covered with either high density polyethylene or clay), are presented in relation to the required area. The results show that earth structures are economically advantageous. The derived equations can be used for providing a preliminary cost estimate of CW facilities for domestic wastewater treatment.

Staff technical position on regulatory considerations in the design and construction of the exploratory shaft facility

International Nuclear Information System (INIS)

Gupta, D.; Peshel, J.; Bunting, J.

1991-07-01

The staff of the US Nuclear Regulatory Commission has prepared this staff technical position for the purpose of compiling and further clarifying previous staff positions on regulatory considerations in the design and construction of the exploratory shaft facility (ESF). (The US Department of Energy (DOE) now refers to the ESF as the ''exploratory studies facility.'' DOE's change in terminology does not affect the positions taken in this guidance.) This document lists the key regulations in 10 CFR Part 60 that should be considered in the design and construction of the ESF and presents the staff position statements and corresponding discussions. 13 refs., 1 fig

Improving NAVFAC's total quality management of construction drawings with CLIPS

Science.gov (United States)

Antelman, Albert

1991-01-01

A diagnostic expert system to improve the quality of Naval Facilities Engineering Command (NAVFAC) construction drawings and specification is described. C Language Integrated Production System (CLIPS) and computer aided design layering standards are used in an expert system to check and coordinate construction drawings and specifications to eliminate errors and omissions.

Promoting the Construction of an Optimal Nurse's Office Facility: One School District's Experience.

Science.gov (United States)

McKibben, Cynthia; DiPaolo, Sonja J.

1997-01-01

Details recommendations for updating or constructing nurses' offices based upon a descriptive study done in one midwestern school district. Suggestions are provided on size, location, and equipment needed. Also addressed is the communication process needed to persuade a board of education and school administrators that nursing facilities must be a…

Proactive information provision for reducing social construct risk of nuclear facility

International Nuclear Information System (INIS)

Kitamura, Masaharu; Takahashi, Makoto; Hashizume, Hidetoshi; Shiraishi, Natsuki; Yagi, Ekou

2006-01-01

Outlines of, and the empirical observations from, an action research project aiming at improvement of relationship between nuclear community and the public have been reported in this paper. Ultimate goal of the project is effective reduction of social construct risk of nuclear power plants. As an initial approach to the goal, a proactive information provision scheme has been designed based on the knowledge acquired during our previous attempt of public communication named repetitive dialogue forum. The information contents consistent with the actual need of local citizens has been derived from the previous experiences and provided in the present project. Although the project is in its incipient stage, the observations are informative enough to develop the project further to attain the ultimate purpose of reducing the social construct component of technological risk of nuclear facilities. (author)

Construction and engineering report for advanced nuclear fuel development facility

International Nuclear Information System (INIS)

Cho, S. W.; Park, J. S.; Kwon, S.J.; Lee, K. W.; Kim, I. J.; Yu, C. H.

2003-09-01

The design and construction of the fuel technology development facility was aimed to accommodate general nuclear fuel research and development for the HANARO fuel fabrication and advanced fuel researches. 1. Building size and room function 1) Building total area : approx. 3,618m 2 , basement 1st floor, ground 3th floor 2) Room function : basement floor(machine room, electrical room, radioactive waste tank room), 1st floor(research reactor fuel fabrication facility, pyroprocess lab., metal fuel lab., nondestructive lab., pellet processing lab., access control room, sintering lab., etc), 2nd floor(thermal properties measurement lab., pellet characterization lab., powder analysis lab., microstructure analysis lab., etc), 3rd floor(AHU and ACU Room) 2. Special facility equipment 1) Environmental pollution protection equipment : ACU(2sets), 2) Emergency operating system : diesel generator(1set), 3) Nuclear material handle, storage and transport system : overhead crane(3sets), monorail hoist(1set), jib crane(2sets), tank(1set) 4) Air conditioning unit facility : AHU(3sets), packaged air conditioning unit(5sets), 5) Automatic control system and fire protection system : central control equipment(1set), lon device(1set), fire hose cabinet(3sets), fire pump(3sets) etc

Ecological studies related to construction of the Defense Waste Processing Facility on the Savannah River Site

International Nuclear Information System (INIS)

Scott, D.E.; Pechmann, J.H.K.; Knox, J.N.; Estes, R.A.; McGregor, J.H.; Bailey, K.

1988-12-01

The Savannah River Ecology Laboratory has completed 10 years of ecological studies related to the construction of the Defense Waste Processing Facility (DWPF) on the Savannah River Site. This progress report examines water quality studies on streams peripheral to the DWPF construction site and examines the effectiveness of ''refuge ponds'' in ameliorating the effects of construction on local amphibians. Individual papers on these topics are indexed separately. 93 refs., 15 figs., 15 tabs

Designing and constructing/installing technical security countermeasures (TSCM) into supersensitive facilities

International Nuclear Information System (INIS)

Davis, D.L.

1988-01-01

The design and construction of supersensitive facilities and the installation of systems secure from technical surveillance and sabotage penetration involve ''TSCM'' in the broad sense of technical ''security'' countermeasures. When the technical threat was at a lower level of intensity and sophistication, it was common practice to defer TSCM to the future facility occupant. However, the New Moscow Embassy experience has proven this course of action subject to peril. Although primary concern with the embassy was audio surveillance, elsewhere there are other threats of equal or greater concern, e.g., technical implants may be used to monitor readiness status or interfere with the operation of C3I and weapons systems. Present and future technical penetration threats stretch the imagination. The Soviets have committed substantial hard scientific resources to a broad range of technical intelligence, even including applications or parapsychology. Countering these threats involves continuous TSCM precautions from initial planning to completion. Designs and construction/installation techniques must facilitate technical inspections and preclude the broadest range of known and suspected technical penetration efforts

Designing and constructing/installing technical security countermeasures (TSCM) into supersensitive facilities

Energy Technology Data Exchange (ETDEWEB)

Davis, D.L.

1988-01-01

The design and construction of supersensitive facilities and the installation of systems secure from technical surveillance and sabotage penetration involve ''TSCM'' in the broad sense of technical ''security'' countermeasures. When the technical threat was at a lower level of intensity and sophistication, it was common practice to defer TSCM to the future facility occupant. However, the New Moscow Embassy experience has proven this course of action subject to peril. Although primary concern with the embassy was audio surveillance, elsewhere there are other threats of equal or greater concern, e.g., technical implants may be used to monitor readiness status or interfere with the operation of C3I and weapons systems. Present and future technical penetration threats stretch the imagination. The Soviets have committed substantial hard scientific resources to a broad range of technical intelligence, even including applications or parapsychology. Countering these threats involves continuous TSCM precautions from initial planning to completion. Designs and construction/installation techniques must facilitate technical inspections and preclude the broadest range of known and suspected technical penetration efforts.

Meal/smoking areas and personal hygiene facilities

International Nuclear Information System (INIS)

1981-01-01

Specific facilities for eating, drinking, smoking, washing, changing and laundering are necessary components in the overall radiation protection program. The location, design, construction, use, maintenance and monitoring of these facilities are considered in this guideline

The specificity of decommissioning waste for disposal and from different facilities

International Nuclear Information System (INIS)

Jones, J.; Hilden, W.; Pla Campana, E.; )

2005-01-01

Full text: During the decommissioning of nuclear installations significant waste quantities arise, the bulk being material which qualifies for free release or exemption. Only minor quantities have to be submitted to regulatory control and have either to be disposed or can be released, recycled or reused under certain conditions defined by the regulatory body. Actually, it is almost impossible to derive at meaningful data for the expected waste quantities by a simple propagation of the experiences made in other installations. Rather, the quantities and categorisation are significantly installation specific and are determined by a variety of factors such as the plant construction and operation history, the thoroughness of facility characterisation in preparation for decommissioning, the timing of the decommissioning exercise, the kind and scope of the applied waste treatment and conditioning techniques, the possibility for recycling or reusing irradiated or contaminated materials as well as the applicable national legislation. Further international co-operation aiming at the development of waste estimation techniques is required. Moreover, a harmonisation of national legislation might help to compare waste arisings under the various decommissioning exercises

Ecological studies related to construction of the Defense Waste Processing Facility on the Savannah River Site

Energy Technology Data Exchange (ETDEWEB)

Scott, D.E.; Pechmann, J.H.K.; Knox, J.N.; Estes, R.A.; McGregor, J.H.; Bailey, K. (ed.)

1988-12-01

The Savannah River Ecology Laboratory has completed 10 years of ecological studies related to the construction of the Defense Waste Processing Facility (DWPF) on the Savannah River Site. This progress report examines water quality studies on streams peripheral to the DWPF construction site and examines the effectiveness of refuge ponds'' in ameliorating the effects of construction on local amphibians. Individual papers on these topics are indexed separately. 93 refs., 15 figs., 15 tabs. (MHB)

30 CFR 75.1903 - Underground diesel fuel storage facilities and areas; construction and safety precautions.

Science.gov (United States)

2010-07-01

... areas; construction and safety precautions. 75.1903 Section 75.1903 Mineral Resources MINE SAFETY AND...; construction and safety precautions. (a) Permanent underground diesel fuel storage facilities must be— (1... with at least 240 pounds of rock dust and provided with two portable multipurpose dry chemical type...

Preliminary engineering specifications for a test demonstration multilayer protective barrier cover system

International Nuclear Information System (INIS)

Phillips, S.J.; Gilbert, T.W.; Adams, M.R.

1985-03-01

This report presents preliminary engineering specifications for a test protective barrier cover system and support radiohydrology facility to be constructed at the Hanford Protective Barrier Test Facility (PBTF). Construction of this test barrier and related radiohydrology facility is part of a continuing effort to provide construction experience and performance evaluation of alternative barrier designs used for long-term isolation of disposed radioactive waste materials. Design specifications given in this report are tentative, based on interim engineering and computer simulation design efforts. Final definitive design specifications and engineering prints will be produced in FY 1986. 6 refs., 10 figs., 1 tab

ISABELLE: a proposal for construction of a proton--proton storage accelerator facility

International Nuclear Information System (INIS)

1976-05-01

The construction of an Intersecting Storage Accelerator Facility (ISA or ISABELLE) at Brookhaven National Laboratory is proposed. ISABELLE will permit the exploration of proton-proton collisions at center-of-mass energies continuously variable from 60 to 400 GeV and with luminosities of 10 32 to 10 33 cm -2 sec -1 over the entire range. An overview of the physics potential of this machine is given, covering the production of charged and neutral intermediate vector bosons, the hadron production at high transverse momentum, searches for new, massive particles, and the energy dependence of the strong interactions. The facility consists of two interlaced rings of superconducting magnets in a common tunnel about 3 km in circumference. The proton beams will collide at eight intersection regions where particle detectors will be arranged for studying the collision processes. Protons of approximately 30 GeV from the AGS will be accumulated to obtain the design current of 10A prior to acceleration to final energy. The design and performance of existing full-size superconducting dipoles and quadrupoles is described. The conceptual design of the accelerator systems and the conventional structures and buildings is presented. A preliminary cost estimate and construction schedule are given. Possible future options such as proton-antiproton, proton-deuteron and electron-proton collisions are discussed

Design, construction and commissioning of the new solid waste management and storage facilities of Ignalina NPP, Lithuania

Energy Technology Data Exchange (ETDEWEB)

Goehring, R.; Wenninger, K. [RWE NUKEM GmbH, Alzenau (Germany)

2006-04-15

The contract for the design, construction and commissioning (turn-key) of the New Solid Waste Management and Storage Facilities (SWMSF) has been awarded to RWE NUKEM GmbH. The contract was signed on the 30.11.2005. The New Solid Waste Management and Storage Facilities (SWMSF) are financed by the Ignalina Decommissioning Support Fund which is managed by European Bank for Reconstruction and Development (EBRD). The new facilities are required on the Ignalina Nuclear Power Plant (INPP) in order to support ongoing decomissioning work, including removal of waste from existing waste storage buildings. (orig.)

Construction and performance of the magnetic bunch compressor for the THz facility at Chiang Mai University

International Nuclear Information System (INIS)

Saisut, J.; Kusoljariyakul, K.; Rimjaem, S.; Kangrang, N.; Wichaisirimongkol, P.; Thamboon, P.; Rhodes, M.W.; Thongbai, C.

2011-01-01

The Plasma and Beam Physics Research Facility at Chiang Mai University has established a THz facility to focus on the study of ultra-short electron pulses. Short electron bunches can be generated from a system that consists of a radio-frequency (RF) gun with a thermionic cathode, an alpha magnet as a magnetic bunch compressor, and a linear accelerator as a post-acceleration section. The alpha magnet is a conventional and simple instrument for low-energy electron bunch compression. With the alpha magnet constructed in-house, several hundred femtosecond electron bunches for THz radiation production can be generated from the thermionic RF gun. The construction and performance of the alpha magnet, as well as some experimental results, are presented in this paper.

Construction and performance of the magnetic bunch compressor for the THz facility at Chiang Mai University

Science.gov (United States)

Saisut, J.; Kusoljariyakul, K.; Rimjaem, S.; Kangrang, N.; Wichaisirimongkol, P.; Thamboon, P.; Rhodes, M. W.; Thongbai, C.

2011-05-01

The Plasma and Beam Physics Research Facility at Chiang Mai University has established a THz facility to focus on the study of ultra-short electron pulses. Short electron bunches can be generated from a system that consists of a radio-frequency (RF) gun with a thermionic cathode, an alpha magnet as a magnetic bunch compressor, and a linear accelerator as a post-acceleration section. The alpha magnet is a conventional and simple instrument for low-energy electron bunch compression. With the alpha magnet constructed in-house, several hundred femtosecond electron bunches for THz radiation production can be generated from the thermionic RF gun. The construction and performance of the alpha magnet, as well as some experimental results, are presented in this paper.

Construction of the neutron beam facility at Australia's OPAL research reactor

International Nuclear Information System (INIS)

Kennedy, Shane J.

2006-01-01

Australia's new research reactor, OPAL, has been designed principally for neutron beam science and radioisotope production. It has a capacity for 18 neutron beam instruments, located at the reactor face and in a neutron guide hall. The neutron beam facility features a 20 l liquid deuterium cold neutron source and cold and thermal supermirror neutron guides. Nine neutron beam instruments are under development, of which seven are scheduled for completion in early 2007. The project is approaching the hot-commissioning stage, when criticality will be demonstrated. Installation of the neutron beam transport system and neutron beam instruments in the neutron guide hall and at the reactor face is underway, and the path to completion of this project is relatively clear. This paper will outline the key features of the OPAL reactor, and will describe the neutron beam facility in particular. The status of the construction and a forecast of the program to completion, including commissioning and commencement of routine operation in 2007 will also be discussed

Application of quality assurance to the design, procurement and construction of the fast flux test facility

International Nuclear Information System (INIS)

Garland, D.L.; Glasscock, R.B.

1978-01-01

Experience has clearly demonstrated the need for effective quality assurance programmes throughout the design, procurement and construction phases of the Fast Flux Test Facility (FFTF). Formal quality assurance programmes for FFTF have contributed significantly to the achievement of project objectives thus far in a safe, reliable and predictable manner. Quality assurance programmes empolyed by major FFTF Project participants are based on the requirements of RDT Standard F 2-2, one of the first and most comprehensive standards of its kind. RDT F 2-2 is similar in its basic requirements to ANSI N45.2 and other quality assurance programme standards but differs in its degree of specificity, particularly in its coverage of development activities. RDT F 2-2 is widely applied to a variety of large and small nuclear energy development projects and technology programmes. Full implementation of RDT F 2-2 across the FFTF Project has had its problems and rewards. Problems have been encountered involving misinterpretation or overapplication of requirements. In some instances the problems pointed to the need for more specific requirements, and so the standard was amended to rectify the shortcomings. One valuable lesson learned is that feedback of use experience is essential to the development of a living, viable standard which can be beneficially applied to other projects. Benefits and cost savings have accrued from the preventive aspects of RDT F 2-2. Some examples of experiences and resulting amendments to RDT F 2-2, and their favourable impact on facility costs and schedule, are discussed in this paper. (author)

SINBAD—The accelerator R&D facility under construction at DESY

Energy Technology Data Exchange (ETDEWEB)

Dorda, U., E-mail: ulrich.dorda@desy.de [DESY, Hamburg & Zeuthen (Germany); Assmann, R.; Brinkmann, R.; Flöttmann, K.; Hartl, I.; Hüning, M.; Kärtner, F.; Fallahi, A.; Marchetti, B.; Nie, Y.; Osterhoff, J.; Schlarb, H.; Zhu, J. [DESY, Hamburg & Zeuthen (Germany); Maier, A.R. [University Hamburg (Germany)

2016-09-01

The SINBAD facility (Short INnovative Bunches and Accelerators at DESY) is a long-term dedicated accelerator research and development facility currently under construction at DESY. It will be located in the premises of the old DORIS accelerator complex and host multiple independent experiments cost-effectively accessing the same central infrastructure like a central high power laser. With the removal of the old DORIS accelerator being completed, the refurbishment of the technical infrastructure is currently starting up. The presently ongoing conversion of the area into the SINBAD facility and the currently foreseen layout is described. The first experiment will use a compact S-band linac for the production of ultra-short bunches at hundred MeV. Once established, one of the main usages will be to externally inject electrons into a laser-driven plasma wakefield accelerator to boost the energy to GeV-level while maintaining a usable beam quality, ultimately aiming to drive an FEL. The second experiment already under planning is the setup of an attosecond radiation source with advanced technology. Further usage of the available space and infrastructure is revised and national and international collaborations are being established.

Analysis of general specifications for nuclear facilities environmental monitoring vehicles

International Nuclear Information System (INIS)

Xu Xiaowei

2014-01-01

At present, with the nuclear energy more increasingly extensive application, the continuous stable radiation monitoring has become the focus of the public attention. The main purpose of the environmental monitoring vehicle for the continuous monitoring of the environmental radiation dose rate and the radionuclides concentration in the medium around nuclear facilities is that the environmental radiation level and the radioactive nuclides activity in the environment medium are measured. The radioactive pollution levels, the scope contaminated and the trends of the pollution accumulation are found out. The change trends for the pollution are observed and the monitoring results are explained. The domestic demand of the environmental monitoring for the nuclear facilities is shown in this report. The changes and demands of the routine environmental monitoring and the nuclear emergency monitoring are researched. The revision opinions for EJ/T 981-1995 General specifications for nuclear facilities environmental monitoring vehicles are put forward. The purpose is to regulate domestic environmental monitoring vehicle technical criterion. The criterion makes it better able to adapt and serve the environmental monitoring for nuclear facilities. The technical guarantee is provided for the environmental monitoring of the nuclear facilities. (authors)

Bioprinting Cellularized Constructs Using a Tissue-specific Hydrogel Bioink

Science.gov (United States)

Skardal, Aleksander; Devarasetty, Mahesh; Kang, Hyun-Wook; Seol, Young-Joon; Forsythe, Steven D.; Bishop, Colin; Shupe, Thomas; Soker, Shay; Atala, Anthony

2016-01-01

Bioprinting has emerged as a versatile biofabrication approach for creating tissue engineered organ constructs. These constructs have potential use as organ replacements for implantation in patients, and also, when created on a smaller size scale as model "organoids" that can be used in in vitro systems for drug and toxicology screening. Despite development of a wide variety of bioprinting devices, application of bioprinting technology can be limited by the availability of materials that both expedite bioprinting procedures and support cell viability and function by providing tissue-specific cues. Here we describe a versatile hyaluronic acid (HA) and gelatin-based hydrogel system comprised of a multi-crosslinker, 2-stage crosslinking protocol, which can provide tissue specific biochemical signals and mimic the mechanical properties of in vivo tissues. Biochemical factors are provided by incorporating tissue-derived extracellular matrix materials, which include potent growth factors. Tissue mechanical properties are controlled combinations of PEG-based crosslinkers with varying molecular weights, geometries (linear or multi-arm), and functional groups to yield extrudable bioinks and final construct shear stiffness values over a wide range (100 Pa to 20 kPa). Using these parameters, hydrogel bioinks were used to bioprint primary liver spheroids in a liver-specific bioink to create in vitro liver constructs with high cell viability and measurable functional albumin and urea output. This methodology provides a general framework that can be adapted for future customization of hydrogels for biofabrication of a wide range of tissue construct types. PMID:27166839

Bioprinting Cellularized Constructs Using a Tissue-specific Hydrogel Bioink.

Science.gov (United States)

Skardal, Aleksander; Devarasetty, Mahesh; Kang, Hyun-Wook; Seol, Young-Joon; Forsythe, Steven D; Bishop, Colin; Shupe, Thomas; Soker, Shay; Atala, Anthony

2016-04-21

Bioprinting has emerged as a versatile biofabrication approach for creating tissue engineered organ constructs. These constructs have potential use as organ replacements for implantation in patients, and also, when created on a smaller size scale as model "organoids" that can be used in in vitro systems for drug and toxicology screening. Despite development of a wide variety of bioprinting devices, application of bioprinting technology can be limited by the availability of materials that both expedite bioprinting procedures and support cell viability and function by providing tissue-specific cues. Here we describe a versatile hyaluronic acid (HA) and gelatin-based hydrogel system comprised of a multi-crosslinker, 2-stage crosslinking protocol, which can provide tissue specific biochemical signals and mimic the mechanical properties of in vivo tissues. Biochemical factors are provided by incorporating tissue-derived extracellular matrix materials, which include potent growth factors. Tissue mechanical properties are controlled combinations of PEG-based crosslinkers with varying molecular weights, geometries (linear or multi-arm), and functional groups to yield extrudable bioinks and final construct shear stiffness values over a wide range (100 Pa to 20 kPa). Using these parameters, hydrogel bioinks were used to bioprint primary liver spheroids in a liver-specific bioink to create in vitro liver constructs with high cell viability and measurable functional albumin and urea output. This methodology provides a general framework that can be adapted for future customization of hydrogels for biofabrication of a wide range of tissue construct types.

Surveillance of construction worker injuries: the utility of trade-specific analysis.

Science.gov (United States)

Hunting, K L; Welch, L S; Nessel-Stephens, L; Anderson, J; Mawudeku, A

1999-07-01

Construction is a dangerous industry, with high rates of both fatal and nonfatal injuries. To learn more about the causes of nonfatal construction worker injuries, and to identify injury cases for further work site-based investigations or prevention programs, we established an emergency department-based surveillance program in November 1990. This article describes circumstances of injury, diagnoses, and demographic characteristics of injured construction workers for 2,791 cases identified through mid-August, 1997. Lacerations and strains and sprains were the most frequent diagnoses; cutting and piercing objects were the leading causes of injury among all construction workers, followed by falls and overexertion. Because of the variety of work performed in this industry, more detailed injury descriptions, by trade, are most useful for thinking about injury prevention. To illustrate this, we profile injury patterns among workers from four specific trades: carpenters, electricians, plumbers, and ironworkers. Areas of concern highlighted by the trade-specific analyses include eye injuries among plumbers; falls from ladders among electricians and plumbers; slips, trips, and falls on the same level among ironworkers; electrical exposure among electricians; and, amputations among carpenters.

Lessons Learned from the 200 West Pump and Treatment Facility Construction Project at the US DOE Hanford Site - A Leadership for Energy and Environmental Design (LEED) Gold-Certified Facility

Energy Technology Data Exchange (ETDEWEB)

Dorr, Kent A.; Ostrom, Michael J.; Freeman-Pollard, Jhivaun R.

2013-01-11

CH2M Hill Plateau Remediation Company (CHPRC) designed, constructed, commissioned, and began operation of the largest groundwater pump and treatment facility in the U.S. Department of Energy’s (DOE) nationwide complex. This one-of-a-kind groundwater pump and treatment facility, located at the Hanford Nuclear Reservation Site (Hanford Site) in Washington State, was built to an accelerated schedule with American Recovery and Reinvestment Act (ARRA) funds. There were many contractual, technical, configuration management, quality, safety, and Leadership in Energy and Environmental Design (LEED) challenges associated with the design, procurement, construction, and commissioning of this $95 million, 52,000 ft groundwater pump and treatment facility to meet DOE’s mission objective of treating contaminated groundwater at the Hanford Site with a new facility by June 28, 2012. The project team’s successful integration of the project’s core values and green energy technology throughout design, procurement, construction, and start-up of this complex, first-of-its-kind Bio Process facility resulted in successful achievement of DOE’s mission objective, as well as attainment of LEED GOLD certification, which makes this Bio Process facility the first non-administrative building in the DOE Office of Environmental Management complex to earn such an award.

Construction of mixed waste storage RCRA facilities, Buildings 7668 and 7669: Environmental assessment

International Nuclear Information System (INIS)

1994-04-01

The Department of Energy has prepared an environmental assessment, DOE/EA-0820, to assess the potential environmental impacts of constructing and operating two mixed waste Resource Conservation and Recovery Act (RCRA) storage facilities. The new facilities would be located inside and immediately west of the security-fenced area of the Oak Ridge National Laboratory Hazardous Waste Management Area in Melton Valley, Tennessee. Based on the analyses in the environmental assessment, the Department has determined that the proposed action does not constitute a major Federal action significantly affecting the quality of the human environment within the meaning of the National Environmental Policy Act of 1969. Therefore, the preparation of an environmental impact statement is not required, and the Department is issuing this finding of no significant impact

Siting history and current construction status of disposal facility for low and intermediate level radioactive waste in Korea

International Nuclear Information System (INIS)

Sakai, Akihiro; Kikuchi, Saburo; Maruyama, Masakatsu

2008-01-01

Korean government decided disposal site for low and intermediate level radioactive waste (LILW), which is located at coastal area near the Wolsong nuclear power plants in Gyeong-Ju city in December. 2005, based on the result of votes of residents in four candidate sites. Since then, Korea Hydro and Nuclear Power Co., Ltd (KHNP), which is the management company of the LILW disposal facility, has carried out the preparation for construction of disposal facility and its licensing process. At the first phase, 100 thousand drums in 200 liter are planned to be disposed of in the rock cavern type disposal facility located at the depth from 80m to 130m below the sea level, and finally 800 thousand drums in 200 liter are planned to be disposed of in the site. This report shows the history of siting for the LILW disposal, the outline of design of disposal facility and current status of its construction, based on the information which was obtained mainly during our visit to the disposal site in Korea. (author)

Issues related to the licensing of final disposal facilities for radioactive waste

International Nuclear Information System (INIS)

Medici, M.A.; Alvarez, D.E.; Lee Gonzales, H.; Piumetti, E.H.; Palacios, E.

2010-01-01

The licensing process of a final disposal facility for radioactive waste involves the design, construction, pre-operation, operation, closure and post closure stages. While design and pre-operational stages are, to a reasonable extent, similar to other kind of nuclear or radioactive facilities, construction, operation, closure and post-closure of a radioactive waste disposal facility have unique meanings. As consequence of that, the licensing process should incorporate these particularities. Considering the long timeframes involved at each stage of a waste disposal facility, it is convenient that the development of the project being implemented in and step by step process, be flexible enough as to adapt to new requirements that would arise as a consequence of technology improvements or due to variations in the socio-economical and political conditions. In Argentina, the regulatory Standard AR 0.1.1 establishes the general guideline for the 'Licensing of Class I facilities (relevant facilities)'. Nevertheless, for radioactive waste final disposal facilities a new specific guidance should be developed in addition to the Basic Standard mentioned. This paper describes the particularities of final disposal facilities indicating that a specific licensing system for this type of facilities should be foreseen. (authors) [es

Lessons Learned From The 200 West Pump And Treatment Facility Construction Project At The US DOE Hanford Site - A Leadership For Energy And Environmental Design (LEED) Gold-Certified Facility

International Nuclear Information System (INIS)

Dorr, Kent A.; Ostrom, Michael J.; Freeman-Pollard, Jhivaun R.

2012-01-01

CH2M Hill Plateau Remediation Company (CHPRC) designed, constructed, commissioned, and began operation of the largest groundwater pump and treatment facility in the U.S. Department of Energy's (DOE) nationwide complex. This one-of-a-kind groundwater pump and treatment facility, located at the Hanford Nuclear Reservation Site (Hanford Site) in Washington State, was built in an accelerated manner with American Recovery and Reinvestment Act (ARRA) funds and has attained Leadership in Energy and Environmental Design (LEED) GOLD certification, which makes it the first non-administrative building in the DOE Office of Environmental Management complex to earn such an award. There were many contractual, technical, configuration management, quality, safety, and LEED challenges associated with the design, procurement, construction, and commissioning of this $95 million, 52,000 ft groundwater pump and treatment facility. This paper will present the Project and LEED accomplishments, as well as Lessons Learned by CHPRC when additional ARRA funds were used to accelerate design, procurement, construction, and commissioning of the 200 West Groundwater Pump and Treatment (2W PandT) Facility to meet DOE's mission of treating contaminated groundwater at the Hanford Site with a new facility by June 28, 2012

Lessons Learned From The 200 West Pump And Treatment Facility Construction Project At The US DOE Hanford Site - A Leadership For Energy And Environmental Design (LEED) Gold-Certified Facility

Energy Technology Data Exchange (ETDEWEB)

Dorr, Kent A. [CH2M HILL Plateau Remediation Company, Richland, WA (United States); Ostrom, Michael J. [CH2M HILL Plateau Remediation Company, Richland, WA (United States); Freeman-Pollard, Jhivaun R. [CH2M HILL Plateau Remediation Company, Richland, WA (United States)

2012-11-14

CH2M Hill Plateau Remediation Company (CHPRC) designed, constructed, commissioned, and began operation of the largest groundwater pump and treatment facility in the U.S. Department of Energy's (DOE) nationwide complex. This one-of-a-kind groundwater pump and treatment facility, located at the Hanford Nuclear Reservation Site (Hanford Site) in Washington State, was built in an accelerated manner with American Recovery and Reinvestment Act (ARRA) funds and has attained Leadership in Energy and Environmental Design (LEED) GOLD certification, which makes it the first non-administrative building in the DOE Office of Environmental Management complex to earn such an award. There were many contractual, technical, configuration management, quality, safety, and LEED challenges associated with the design, procurement, construction, and commissioning of this $95 million, 52,000 ft groundwater pump and treatment facility. This paper will present the Project and LEED accomplishments, as well as Lessons Learned by CHPRC when additional ARRA funds were used to accelerate design, procurement, construction, and commissioning of the 200 West Groundwater Pump and Treatment (2W P&T) Facility to meet DOE's mission of treating contaminated groundwater at the Hanford Site with a new facility by June 28, 2012.

Development and implementation of a construction environmental protection program at a solid radioactive waste management facility

Energy Technology Data Exchange (ETDEWEB)

Wong, T.S. [Atomic Energy of Canada Limited, Mississauga, Ontario (Canada); Bishop, T. [Atomic Energy of Canada Limited, Saint John, New Brunswick (Canada); Hickman, C.N. [Point Lepreau Generating Station, Saint John, New Brunswick (Canada)

2007-07-01

Refurbishment of ageing nuclear stations has great economic and environmental benefits, including reduced greenhouse gas emissions. The Government of New Brunswick (NB) decided in 2005 to refurbish the Point Lepreau Generating Station with Atomic Energy of Canada Limited (AECL) as the general contractor. The project includes construction of additional radioactive waste management facilities. AECL developed, for the construction project, an environmental protection program to comply with commitments made during the environmental assessment process, and regulatory requirements. The program covers detailed environmental plans, training courses, and engagement of consultants to provide training and conduct monitoring of the construction activities. Construction related environmental effects have been successfully mitigated and the monitoring results indicate compliance with all environmental requirements. (author)

20 CFR 670.210 - How are center facility improvements and new construction handled?

Science.gov (United States)

2010-04-01

... 20 Employees' Benefits 3 2010-04-01 2010-04-01 false How are center facility improvements and new construction handled? 670.210 Section 670.210 Employees' Benefits EMPLOYMENT AND TRAINING ADMINISTRATION, DEPARTMENT OF LABOR THE JOB CORPS UNDER TITLE I OF THE WORKFORCE INVESTMENT ACT Site Selection and Protection...

Environmental assessment for the construction, operation, and decommissioning of the Waste Segregation Facility at the Savannah River Site

International Nuclear Information System (INIS)

1998-01-01

This Environmental Assessment (EA) has been prepared by the Department of Energy (DOE) to assess the potential environmental impacts associated with the construction, operation and decontamination and decommissioning (D ampersand D) of the Waste Segregation Facility (WSF) for the sorting, shredding, and compaction of low-level radioactive waste (LLW) at the Savannah River Site (SRS) located near Aiken, South Carolina. The LLW to be processed consists of two waste streams: legacy waste which is currently stored in E-Area Vaults of SRS and new waste generated from continuing operations. The proposed action is to construct, operate, and D ampersand D a facility to process low-activity job-control and equipment waste for volume reduction. The LLW would be processed to make more efficient use of low-level waste disposal capacity (E-Area Vaults) or to meet the waste acceptance criteria for treatment at the Consolidated Incineration Facility (CIF) at SRS

The construction of a facility for 14 Mev neutron activation analysis of oxygen in aluminium

International Nuclear Information System (INIS)

Bjoernstad, T.; Alstad, J.

1984-02-01

The article describes the construction and performance of a facility for 14 MeV neutron activation analysis, mainly for oxygen in aluminium, at the University of Oslo. It consists of a sealed tube neutron generator, a biaxial rotation system for samples in irradiation position, a mechanism for automatic separation of sample and container, and appropriate detectors and counting electronics. Especially considered are the procedures for sample preparation and packing, standardization, optimization of the energy range for integration and optimization of the irradiation, decay and counting times. The applicability of the facility is exemplified by analytical results from comparative investigations in different laboratories using different methods. (Auth.)

Lessons Learned From a Decade of Design, Construction, and Operations of the Environmental Management Waste Management Facility in Oak Ridge, Tennessee - 12062

Energy Technology Data Exchange (ETDEWEB)

Williams, Joe [Bechtel National, Inc., Oak Ridge, TN 37830 (United States)

2012-07-01

The Environmental Management Waste Management Facility (EMWMF) is the Department of Energy's on-site disposal facility for radioactive and hazardous waste generated by the CERCLA cleanup of the Oak Ridge Reservation (ORR). EMWMF recently completed building out to its maximum site capacity and is approaching a decade of operating experience. In meeting the challenges of design, construction, and operation of a mixed waste and low-level radioactive waste disposal facility within the framework of CERCLA, the Bechtel Jacobs Company LLC (BJC) project team learned valuable lessons that may be beneficial to other disposal facilities. Since project inception in 1998, the scope of the effort includes five regulator-approved designs, four phases of construction, and utilization of half of EMWMF's 1.63 M m{sup 3} of airspace during disposal of waste streams from across the ORR. Funding came from the broadest possible range of sources - privatization, American Recovery and Reinvestment Act, and two funding appropriation accounts. In the process of becoming the cost effective disposal outlet for the majority of the ORR cleanup waste, EMWMF overcame numerous challenges. Lessons learned were a key factor in achieving that success. Many of EMWMF's challenges are common to other disposal facilities. Sharing the successes and lessons learned will help other facilities optimize design, construction, and operations. (author)

Materials and construction techniques for cryogenic wind tunnel facilities for instruction/research use

Science.gov (United States)

Morse, S. F.; Roper, A. T.

1975-01-01

The results of the cryogenic wind tunnel program conducted at NASA Langley Research Center are presented to provide a starting point for the design of an instructional/research wind tunnel facility. The advantages of the cryogenic concept are discussed, and operating envelopes for a representative facility are presented to indicate the range and mode of operation. Special attention is given to the design, construction and materials problems peculiar to cryogenic wind tunnels. The control system for operation of a cryogenic tunnel is considered, and a portion of a linearized mathematical model is developed for determining the tunnel dynamic characteristics.

Lessons Learned from the 200 West Pump and Treatment Facility Construction Project at the US DOE Hanford Site - A Leadership for Energy and Environmental Design (LEED) Gold-Certified Facility - 13113

Energy Technology Data Exchange (ETDEWEB)

Dorr, Kent A.; Freeman-Pollard, Jhivaun R.; Ostrom, Michael J. [CH2M HILL Plateau Remediation Company, P.O. Box 1600, MSIN R4-41, 99352 (United States)

2013-07-01

CH2M Hill Plateau Remediation Company (CHPRC) designed, constructed, commissioned, and began operation of the largest groundwater pump and treatment facility in the U.S. Department of Energy's (DOE) nationwide complex. This one-of-a-kind groundwater pump and treatment facility, located at the Hanford Nuclear Reservation Site (Hanford Site) in Washington State, was built to an accelerated schedule with American Recovery and Reinvestment Act (ARRA) funds. There were many contractual, technical, configuration management, quality, safety, and Leadership in Energy and Environmental Design (LEED) challenges associated with the design, procurement, construction, and commissioning of this $95 million, 52,000 ft groundwater pump and treatment facility to meet DOE's mission objective of treating contaminated groundwater at the Hanford Site with a new facility by June 28, 2012. The project team's successful integration of the project's core values and green energy technology throughout design, procurement, construction, and start-up of this complex, first-of-its-kind Bio Process facility resulted in successful achievement of DOE's mission objective, as well as attainment of LEED GOLD certification (Figure 1), which makes this Bio Process facility the first non-administrative building in the DOE Office of Environmental Management complex to earn such an award. (authors)

Lessons Learned from the 200 West Pump and Treatment Facility Construction Project at the US DOE Hanford Site - A Leadership for Energy and Environmental Design (LEED) Gold-Certified Facility - 13113

International Nuclear Information System (INIS)

Dorr, Kent A.; Freeman-Pollard, Jhivaun R.; Ostrom, Michael J.

2013-01-01

CH2M Hill Plateau Remediation Company (CHPRC) designed, constructed, commissioned, and began operation of the largest groundwater pump and treatment facility in the U.S. Department of Energy's (DOE) nationwide complex. This one-of-a-kind groundwater pump and treatment facility, located at the Hanford Nuclear Reservation Site (Hanford Site) in Washington State, was built to an accelerated schedule with American Recovery and Reinvestment Act (ARRA) funds. There were many contractual, technical, configuration management, quality, safety, and Leadership in Energy and Environmental Design (LEED) challenges associated with the design, procurement, construction, and commissioning of this $95 million, 52,000 ft groundwater pump and treatment facility to meet DOE's mission objective of treating contaminated groundwater at the Hanford Site with a new facility by June 28, 2012. The project team's successful integration of the project's core values and green energy technology throughout design, procurement, construction, and start-up of this complex, first-of-its-kind Bio Process facility resulted in successful achievement of DOE's mission objective, as well as attainment of LEED GOLD certification (Figure 1), which makes this Bio Process facility the first non-administrative building in the DOE Office of Environmental Management complex to earn such an award. (authors)

Economic Feasibility Analysis of the Application of Geothermal Energy Facilities to Public Building Structures

Directory of Open Access Journals (Sweden)

Sangyong Kim

2014-03-01

Full Text Available This study aims to present an efficient plan for the application of a geothermal energy facility at the building structure planning phase. Energy consumption, energy cost and the primary energy consumption of buildings were calculated to enable a comparison of buildings prior to the application of a geothermal energy facility. The capacity for energy savings and the costs related to the installation of such a facility were estimated. To obtain more reliable criteria for economic feasibility, the lifecycle cost (LCC analysis incorporated maintenance costs (reflecting repair and replacement cycles based on construction work specifications of a new renewable energy facility and initial construction costs (calculated based on design drawings for its practical installation. It is expected that the findings of this study will help in the selection of an economically viable geothermal energy facility at the building construction planning phase.

Characterization and remediation of soil prior to construction of an on-site disposal facility at Fernald

International Nuclear Information System (INIS)

Hunt, A.; Jones, G.; Nelson, K.

1998-03-01

During the production years at the Feed Materials Production Center (FMPC), the soil of the site and the surrounding areas was surficially impacted by airborne contamination. The volume of impacted soil is estimated at 2.2 million cubic yards. During site remediation, this contamination will be excavated, characterized, and disposed of. In 1986 the US Environmental Protection Agency (EPA) and the Department of Energy (DOE) entered into a Federal Facility Compliance Agreement (FFCA) covering environmental impacts associated with the FMPC. A site wide Remedial Investigation/Feasibility Study (RI/FS) was initiated pursuant to the Comprehensive Environmental Response, Compensation, and Liability Act, as amended by the Superfund Amendments and Reauthorization Act (CERCLA). The DOE has completed the RI/FS process and has received approval of the final Records of Decision. The name of the facility was changed to the Fernald Environmental Management Project (FEMP) to emphasize the change in mission to environmental restoration. Remedial actions which address similar scopes of work or types of contaminated media have been grouped into remedial projects for the purpose of managing the remediation of the FEMP. The Soil Characterization and Excavation Project (SCEP) will address the remediation of FEMP soils, certain waste units, at- and below-grade material, and will certify attainment of the final remedial limits (FRLs) for the FEMP. The FEMP will be using an on-site facility for low level radioactive waste disposal. The facility will be an above-ground engineered structure constructed of geological material. The area designated for construction of the base of the on-site disposal facility (OSDF) is referred to as the footprint. Contaminated soil within the footprint must be identified and remediated. Excavation of Phase 1, the first of seven remediation areas, is complete

Design Guide for Selection and Specification of Kevlar Rope for Ocean Engineering and Construction.

Science.gov (United States)

1976-07-01

public rtoieco cnd sol . It i Idim .buttm Is ul"rnimi.. OCEAN ENGINEERING AND CONSTRUCTION PROJECT OFFICE CHESAPEAKE DIVISION NAVAL FACILITIES ENGINEERING...be to have no more than one layer. This is impractical for oceano - graphic purposes. Assuming a need to spooi many layers of rope under tension

The planning, construction, and operation of a radioactive waste storage facility for an Australian state radiation regulatory authority

Energy Technology Data Exchange (ETDEWEB)

Wallace, J.D.; Kleinschmidt, R.; Veevers, P. [Radiation Health, Queensland (Australia)

1995-12-31

Radiation regulatory authorities have a responsibility for the management of radioactive waste. This, more often than not, includes the collection and safe storage of radioactive sources in disused radiation devices and devices seized by the regulatory authority following an accident, abandonment or unauthorised use. The public aversion to all things radioactive, regardless of the safety controls, together with the Not In My Back Yard (NIMBY) syndrome combine to make the establishment of a radioactive materials store a near impossible task, despite the fact that such a facility is a fundamental tool for regulatory authorities to provide for the radiation safety of the public. In Queensland the successful completion and operational use of such a storage facility has taken a total of 8 years of concerted effort by the staff of the regulatory authority, the expenditure of over $2 million (AUS) not including regulatory staff costs and the cost of construction of an earlier separate facility. This paper is a summary of the major developments in the planning, construction and eventual operation of the facility including technical and administrative details, together with the lessons learned from the perspective of the overall project.

Construction and characterization of the redesigned PGAA facility at The University of Texas at Austin

International Nuclear Information System (INIS)

Revay, Zs.; Harrison, R.K.; Alvarez, E.; Biegalski, S.R.; Landsberger, S.

2007-01-01

The prompt gamma activation analysis (PGAA) facility at The University of Texas at Austin (UT) has been redesigned and reconstructed. As a result of the new shielding of the system, the neutron (at all energies) and gamma-ray backgrounds have been reduced by more than an order of magnitude, considerably improving the signal-to-noise ratio for the characteristic peaks. The prompt gamma peaks from the construction materials have also been decreased, providing better detection limits for elements. The calibration of the new system is shown in detail. All these efforts significantly improved the sensitivity and reliability of the chemical analyses performed in the facility. The characteristics of the improved PGAA system are also presented

Facile construction of 3D graphene/MoS2 composites as advanced electrode materials for supercapacitors

Science.gov (United States)

Sun, Tianhua; Li, Zhangpeng; Liu, Xiaohong; Ma, Limin; Wang, Jinqing; Yang, Shengrong

2016-11-01

Flower-like molybdenum disulfide (MoS2) microstructures are synthesized based on three-dimensional graphene (3DG) skeleton via a simple and facile one-step hydrothermal method, aiming at constructing series of novel composite electrode materials of 3DG/MoS2 with high electrochemical performances for supercapacitors. The electrochemical properties of the samples are evaluated by cyclic voltammetry and galvanostatic charge/discharge tests. Specifically, the optimal 3DG/MoS2 composite exhibits remarkable performances with a high specific capacitance of 410 F g-1 at a current density of 1 A g-1 and an excellent cycling stability with ca. 80.3% capacitance retention after 10,000 continuous charge-discharge cycles at a high current density of 2 A g-1, making it adaptive for high-performance supercapacitors. The enhanced electrochemical performances can be ascribed to the combination of 3DG and flower-like MoS2, which provides excellent charge transfer network and electrolyte diffusion channels while effectively prevents the collapse, aggregation and morphology change of active materials during charge-discharge process. The results demonstrate that 3DG/MoS2 composite is one of the attractive electrode materials for supercapacitors.

Construction of new critical experiment facilities in JAERI

International Nuclear Information System (INIS)

Takeshita, Isao; Itahashi, Takayuki; Ogawa, Kazuhiko; Tonoike, Kotaro; Matsumura, Tatsuro; Miyoshi, Yoshinori; Nakajima, Ken; Izawa, Naoki

1995-01-01

Japan Atomic Energy Research Institute (JAERI) has promoted the experiment research program on criticality safety since early in 1980s and two types of new critical facilities, Static Experiment Critical Facility (STACY) and Transient Experiment Critical Facility (TRACY) were completed on 1994 in Nuclear Fuel Cycle Safety Engineering Research Facility (NUCEF) of JAERI Tokai Research Establishment. STACY was designed so as to obtain critical mass data of low enriched uranium and plutonium solution which is extensively handled in LWR fuel reprocessing plant. TRACY is the critical facility where critical accident phenomenon is demonstrated with low enriched uranium nitrate solution. For criticality safety experiments with both facilities, the Fuel Treatment System is attached to them, where composition and concentration of uranium and plutonium nitrate solutions are widely varied so as to obtain experiments data covering fuel solution conditions in reprocessing plant. Design performances of both critical facilities were confirmed through mock-up tests of important components and cold function tests. Hot function test has started since January of 1995 and some of the results on STACY are to be reported. (author)

77 FR 33782 - License Amendment To Construct and Operate New In Situ Leach Uranium Recovery Facility; Uranium...

Science.gov (United States)

2012-06-07

... and Operate New In Situ Leach Uranium Recovery Facility; Uranium One Americas; Ludeman AGENCY: Nuclear... provided the first time that a document is referenced. The Ludeman facility In Situ Leach Uranium Recovery... request to amend Source Material License SUA-1341 to construct and operate a new in situ leach uranium...

Design and construction of γ-rays irradiation facility for remote-handling parts and components of fusion reactor

International Nuclear Information System (INIS)

Yagi, Toshiaki; Morita, Yousuke; Seguchi, Tadao

1995-03-01

For the evaluation of radiation resistance of remote-handling system for International Thermonuclear Experimental Reactor(ITER), 'high dose-rate and high temperature (upper 350degC) γ-rays irradiation facility' was designed and constructed. In this facility, the parts and components of remote-handling system such as sensing devices, motors, optical glasses, wires and cables, etc., are tested by irradiation with 2x10 6 Roentgen/h Co-60 γ-rays at a temperature up to 350degC under various atmospheres (dry nitrogen gas, argon gas, dry air and vacuum). (author)

A facile strategy to construct binder-free flexible carbonate composite anode at low temperature with high performances for lithium-ion batteries

International Nuclear Information System (INIS)

Shi, Shaojun; Zhang, Ming; Deng, Tingting; Wang, Ting; Yang, Gang

2017-01-01

Graphical abstract: The schematic illustration of the strategy for preparations and the mechanism for the stability of structure Display Omitted -- Highlights: •A facile strategy is applied to construct flexible carbonate composite anode. •Carbon nano-fiber matrix serves as fast charge channel and efficient buffer. •High specific capacity of 958 mAh g −1 at 100 mA g −1 is obtained. •After 200 cycles at 1 A g −1 , there is not obvious capacity decline. •The mechanism for stress release is further analyzed. -- Abstract: High temperature is usually necessary for carbon modification or electrospinning to obtain flexible anode with excellent conductivity and stability. However, due to the unstable instinct of carbonate, it’s hard to obtain carbonate when any of the synthesis process undergoes high temperature treatment. Thus, a facile strategy is applied to construct binder-free flexible carbonate composite anode at low temperature with high electrochemical performances. The carbon nano-fiber matrix is first synthesized through electrospinning followed by a facile solvothermal process to in-situ grow carbonate on carbon nano-fibers to form a well combinative flexible anode. The carbon nano-fiber matrix serves not only as a fast channel for charge transfer, but also as an efficient buffer to release the stress resulting from the hysteresis of lithiation for carbonate particles during repeated charge/discharge cycles. Owing to the synergistic effect of carbon nano-fiber and the carbonate, the flexible anode exhibits high specific capacity of 958 mAh g −1 . And after 200 cycles at 1 A g −1 , no obvious capacity decline. The reaction mechanism for stress release is also well analyzed to display the merit of our strategy. It is considered as one of the most promising way to get binder-free flexible carbonate anode with remarkable properties.

Improved E-ELT subsystem and component specifications, thanks to M1 test facility

Science.gov (United States)

Dimmler, M.; Marrero, J.; Leveque, S.; Barriga, Pablo; Sedghi, B.; Kornweibel, N.

2014-07-01

During the last 2 years ESO has operated the "M1 Test Facility", a test stand consisting of a representative section of the E-ELT primary mirror equipped with 4 complete prototype segment subunits including sensors, actuators and control system. The purpose of the test facility is twofold: it serves to study and get familiar with component and system aspects like calibration, alignment and handling procedures and suitable control strategies on real hardware long before the primary mirror (hereafter M1) components are commissioned. Secondly, and of major benefit to the project, it offered the possibility to evaluate component and subsystem performance and interface issues in a system context in such detail, that issues could be identified early enough to feed back into the subsystem and component specifications. This considerably reduces risk and cost of the production units and allows refocusing the project team on important issues for the follow-up of the production contracts. Experiences are presented in which areas the results of the M1 Test Facility particularly helped to improve subsystem specifications and areas, where additional tests were adopted independent of the main test facility. Presented are the key experiences of the M1 Test Facility which lead to improved specifications or identified the need for additional testing outside of the M1 Test Facility.

Facility Description 2012. Summary report of the encapsulation plant and disposal facility designs

International Nuclear Information System (INIS)

Palomaeki, J.; Ristimaeki, L.

2013-10-01

The purpose of the facility description is to be a specific summary report of the scope of Posiva's nuclear facilities (encapsulation plant and disposal facility) in Olkiluoto. This facility description is based on the 2012 designs and completing Posiva working reports. The facility description depicts the nuclear facilities and their operation as the disposal of spent nuclear fuel starts in Olkiluoto in about 2020. According to the decisions-in-principle of the government, the spent nuclear fuel from Loviisa and Olkiluoto nuclear power plants in operation and in future cumulative spent nuclear fuel from Loviisa 1 and 2, Olkiluoto 1, 2, 3 and 4 nuclear power plants, is permitted to be disposed of in Olkiluoto bedrock. The design of the disposal facility is based on the KBS-3V concept (vertical disposal). Long-term safety concept is based on the multi-barrier principle i.e. several release barriers, which ensure one another so that insufficiency in the performance of one barrier doesn't jeopardize long-term safety of the disposal. The release barriers are the following: canister, bentonite buffer and deposition tunnel backfill, and the host rock around the repository. The canisters are installed into the deposition holes, which are bored to the floor of the deposition tunnels. The canisters are enveloped with compacted bentonite blocks, which swell after absorbing water. The surrounding bedrock and the central and access tunnel backfill provide additional retardation, retention, and dilution. The nuclear facilities consist of an encapsulation plant and of underground final disposal facility including other aboveground buildings and surface structures serving the facility. The access tunnel and ventilation shafts to the underground disposal facility and some auxiliary rooms are constructed as a part of ONKALO underground rock characterization facility during years 2004-2014. The construction works needed for the repository start after obtaining the construction

Final environmental impact statement, construction and operation of the Spallation Neutron Source Facility. Summary

International Nuclear Information System (INIS)

1999-04-01

DOE proposes to construct and operate a state-of-the-art, short-pulsed, spallation neutron source comprised of an ion source, a linear accelerator, a proton accumulator ring, and an experiment building containing a liquid mercury target and a suite of neutron scattering instrumentation. The proposed Spallation Neutron Source would be designed to operate at a proton beam power of 1 megawatt. The design would accommodate future upgrades to a peak operating power of 4 megawatts. These upgrades may include construction of a second proton accumulator ring and a second target. This document analyzes the potential environmental impacts from the proposed action and the alternatives. The analysis assumes a facility operating at a power of 1 MW and 4 MW over the life of the facility. The two primary alternatives analyzed in this FEIS are: the proposed action (to proceed with building the Spallation Neutron Source) and the No-Action Alternative. The No-Action Alternative describes the expected condition of the environment if no action were taken. Four siting alternatives for the Spallation Neutron Source are evaluated: Oak Ridge National Laboratory, Oak Ridge, TN, (preferred alternative); Argonne National Laboratory, Argonne, IL; Brookhaven National Laboratory, Upton, NY; and Los Alamos National Laboratory, Los Alamos, NM

Spatial accessibility to specific sport facilities and corresponding sport practice: the RECORD Study

OpenAIRE

Karusisi, No?lla; Thomas, Fr?d?rique; M?line, Julie; Chaix, Basile

2013-01-01

International audience; BACKGROUND: Physical activity is considered as a major component of a healthy lifestyle. However, few studies have examined the relationships between the spatial accessibility to sport facilities and sport practice with a sufficient degree of specificity. The aim of this study was to investigate the associations between the spatial accessibility to specific types of sports facilities and the practice of the corresponding sports after carefully controlling for various i...

Further Improvements Needed in Navy’s Oversight and Management of Contracting for Facilities Construction on Diego Garcia.

Science.gov (United States)

1984-05-23

1981, the Navy awarded a cost reimbursable contract to a joint venture to construct facility projects for fiscal years 1981 and 1982 with an estimated...through fiscal year 1986. In July 1981, the Navy awarded a cost reimburs - able contract (cost plus award fee) to Raymond, Brown & Root, Molem, a joint...Navy’s oversight and management of the acquisition of these facilities. A COST REIMBURSABLE CONTRACT MAKES STRONG CONTRACT ADMINISTRATION VITAL Under

Development of a test facility to evaluate the optimal design of BMPs for managing environmental problems at construction sites.

Science.gov (United States)

2012-06-01

The following document is the final report for ALDOT Project 930655 which summarizes the design and : construction of the Auburn University Erosion and Sediment Control Testing Facility (AUESCTF) along : with several intermediatescale, f...

Assessment of the proposed decontamination and waste treatment facility at LLNL

International Nuclear Information System (INIS)

Cohen, J.J.

1987-01-01

To provide a centralized decontamination and waste treatment facility (DWTF) at LLNL, the construction of a new installation has been planned. Objectives for this new facility were to replace obsolete, structurally and environmentally sub-marginal liquid and solid waste process facilities and decontamination facility and to bring these facilities into compliance with existing federal, state and local regulations as well as DOE orders. In a previous study, SAIC conducted a preliminary review and evaluation of existing facilities at LLNL and cost effectiveness of the proposed DWTF. This document reports on a detailed review of specific aspects of the proposed DWTF

Sandia National Laboratories Facilities Management and Operations Center Design Standards Manual

Energy Technology Data Exchange (ETDEWEB)

Fattor, Steven [Sandia National Laboratories (SNL-NM), Albuquerque, NM (United States)

2014-06-01

The manual contains general requirements that apply to nonnuclear and nonexplosive facilities. For design and construction requirements for modifications to nuclear or explosive facilities, see the project-specific design requirements noted in the Design Criteria.

Spatial accessibility to specific sport facilities and corresponding sport practice: the RECORD Study.

Science.gov (United States)

Karusisi, Noëlla; Thomas, Frédérique; Méline, Julie; Chaix, Basile

2013-04-20

Physical activity is considered as a major component of a healthy lifestyle. However, few studies have examined the relationships between the spatial accessibility to sport facilities and sport practice with a sufficient degree of specificity. The aim of this study was to investigate the associations between the spatial accessibility to specific types of sports facilities and the practice of the corresponding sports after carefully controlling for various individual socio-demographic characteristics and neighborhood socioeconomic variables. Data from the RECORD Study involving 7290 participants recruited in 2007-2008, aged 30-79 years, and residing in the Paris metropolitan area were analyzed. Four categories of sports were studied: team sports, racket sports, swimming and related activities, and fitness. Spatial accessibility to sport facilities was measured with two complementary approaches that both take into account the street network (distance to the nearest facility and count of facilities around the dwelling). Associations between the spatial accessibility to sport facilities and the practice of the corresponding sports were assessed using multilevel logistic regression after adjusting for individual and contextual characteristics. High individual education and high household income were associated with the practice of racket sports, swimming or related activities, and fitness over the previous 7 days. The spatial accessibility to swimming pools was associated with swimming and related sports, even after adjustment for individual/contextual factors. The spatial accessibility to facilities was not related to the practice of other sports. High neighborhood income was associated with the practice of a racket sport and fitness. Accessibility is a multi-dimensional concept that integrates educational, financial, and geographical aspects. Our work supports the evidence that strategies to increase participation in sport activities should improve the spatial and

The present status of medical application of particle accelerator. Started construction of a new medically dedicated proton accelerator facility in Tsukuba

International Nuclear Information System (INIS)

Sakae, Takeji; Maruhashi, Akira

1999-01-01

A new facility of PMRC starts the construction in the neighborhood of Tsukuba university hospital, in order to establish technical skill for practical use in the cancer treatment and to grope for new skill. The facility has a linac injection system, a compact synchrotron, two rotating gantry rooms and two fixed horizontal beam lines. The outline of the design arranged for the facility is reviewed. As one of the important technique for the treatment, investigation into target adjusting accuracy in respiration-gated proton irradiation is presented. (author)

Construction of the Neutron Beam Facility at Australia's OPAL Research Reactor

International Nuclear Information System (INIS)

Kennedy, J.S.

2005-01-01

Full text: Australia's new research reactor, OPAL, has been designed for high quality neutron beam science and radioisotope production. It has a capacity for eighteen neutron beam instruments to be located at the reactor face and in a neutron guide hall. The new neutron beam facility features a 20 litre liquid deuterium cold neutron source and supermirror neutron reflecting guides for intense cold and thermal neutron beams. Nine neutron beam instruments are under development, of which seven are scheduled for completion in early 2007. The project is approaching the hot-commissioning stage, where criticality will be demonstrated. Installation of the neutron beam transport system and neutron beam instruments in the neutron guide hall and at the reactor face is underway, and the path to completion of this project is relatively clear. The lecture will outline Australia's aspirations for neutron science at the OPAL reactor, and describe the neutron beam facility under construction. The status of this project and a forecast of the program to completion, including commissioning and commencement of routine operation in 2007 will also be discussed. This project is the culmination of almost a decade of effort. We now eagerly anticipate catapulting Australia's neutron beam science capability to meet the best in the world today. (author)

Enhancing quality of construction on nuclear facilities

International Nuclear Information System (INIS)

Buchert, K.P.

1984-01-01

From the author's viewpoint and the viewpoint of others, the quality of construction on both nuclear projects and many other non-nuclear projects has decreased. The trend toward recent QA and QC methods of contractors doing their own inspection has not only tended to reduce the quality of construction, but also has discouraged qualified inspectors from accepting positions where this type of QA and QC is practiced. In addition, the methods have decreased the desired interaction between design engineers and construction management. The paper contains detailed recommendations on how the quality of construction can be enhanced on nuclear projects. It is also shown that construction quality must be obtained by different methods than those used to obtain manufacturing quality

Specificity and detail in autobiographical memory: Same or different constructs?

Science.gov (United States)

Kyung, Yoonhee; Yanes-Lukin, Paula; Roberts, John E

2016-01-01

Research on autobiographical memory has focused on whether memories are coded as specific (i.e., describe a single event that happened at a particular time and place). Although some theory and research suggests that the amount of detail in autobiographical memories reflects a similar underlying construct as memory specificity, past research has not investigated whether these variables converge. Therefore, the present study compared the proportion of specific memories and the amount of detail embedded in memory responses to cue words. Results demonstrated that memory detail and proportion of specific memories were not correlated with each other and showed different patterns of association with other conceptually relevant variables. When responses to neutral cue words were examined in multiple linear and logistic regression analyses, the proportion of specific memories uniquely predicted less depressive symptoms, low emotional avoidance, lower emotion reactivity, better executive control and lower rumination, whereas the amount of memory detail uniquely predicted the presence of depression diagnosis, as well as greater depressive symptoms, subjective stress, emotion reactivity and rumination. Findings suggest that the ability to retrieve specific memories and the tendency to retrieve detailed personal memories reflect different constructs that have different implications in the development of emotional distress.

High-rise construction in historical cities through the example of Saint Petersburg

Science.gov (United States)

Granstrem, Maria; Zolotareva, Milena; Slavina, Tatyana

2018-03-01

The article sets forth results of the landscape visual analysis of the interaction of high-rise construction facilities with the environment of historical urban spaces. A toxic connection of high-rise construction facilities with the established urban landscape was analyzed and recorded. One of the latest stages of the reconstruction of historical cities, which penetrated many European countries at the end of the 20th century, also started in the beginning of the 21st century in Russia, where the reconstruction of historical facilities and territories became one of the leading trends of architectural activity. Therefore, problems of the interaction between the old city and new high-rise construction nearby historical centers are extremely relevant for Russian architects. Specific features of Russian high-rise construction within visual borders of historical cities, developed at the turn of the 20th-21st centuries, repeat past urban-planning mistakes spread in Europe in the second half of the 20th century. High-rise construction in close proximity to historical centers of cities violates an established scale and destroys a historical city silhouette.

Horonobe Underground Research Laboratory project. Plans of investigations during shaft and drift excavation (Construction of underground facilities: Phase II)

International Nuclear Information System (INIS)

2005-06-01

Horonobe Underground Research Laboratory Project is planned for over 20 years to establish the scientific and technical basis for the underground disposal of high-level radioactive wastes in Japan. The investigations are conducted by JNC in three phases, from the surface (Phase I), during the construction of the underground facilities (Phase II), and using the facilities (Phase III). This report concerns the investigation plans for Phase II. During excavation of shafts and drifts, detailed geological and borehole investigation will be conducted and the geological model constructed in Phase I is evaluated and revised by newly acquired data of geophysical and geological environment. Detailed in-situ experiments, as well as the effects of shaft excavation, are also done to study long-term changes, rock properties, groundwater flow and chemistry to ensure the reliability of repository technology and establish safety assessment methodology. (S. Ohno)

Facility effluent monitoring plan for the tank farms facilities

International Nuclear Information System (INIS)

Crummel, G.M.; Gustavson, R.D.; Kenoyer, J.L.; Moeller, M.P.

1991-11-01

A facility effluent monitoring plan is required by the US Department of Energy in DOE Order 5400.1 for any operations that involve hazardous materials and radioactive substances that could impact employee or public safety or the environment. This document is prepared using the specific guidelines identified in A Guide for Preparing Hanford Site Facility Effluent Monitoring Plans, WHC-EP-0438. This facility effluent monitoring plan assesses effluent monitoring systems and evaluates whether they are adequate to ensure the public health and safety as specified in applicable federal, state, and local requirements. This facility effluent monitoring plan is the first annual report. It shall ensure long-range integrity of the effluent monitoring systems by requiring an update whenever a new process or operation introduces new hazardous materials or significant radioactive materials. This document must be reviewed annually even if there are no operational changes, and it must be updated as a minimum three years. A variety of liquid wastes are generated in processing treatment, and disposal operations throughout the Hanford Site. The Tank Farms Project serves a major role in Hanford Site waste management activities as the temporary repository for these wastes. Stored wastes include hazardous components regulated under the Resource Conservation and Recovery Act of 1976 (RCRA) and as by-product material regulated under the Atomic Energy Act of 1954. A total of 177 single- and double-shell tanks (SST and DST) have been constructed in the 200 East and 200 West Areas of the Hanford Site. These facilities were constructed to various designs from 1943 to 1986. The Tank Farms Project is comprised of these tanks along with various transfer, receiving, and treatment facilities

Information System Specific in Achievement of Construction Projects

Directory of Open Access Journals (Sweden)

Cătălin Onuţu

2005-01-01

Full Text Available Because of the economic changes from our country and also of the rapid adjusting necessity to the requirement of a market economy, it is observed a huge request for information, and especially techniques, tools, methodologies that would facilitate the managerial activity in any field. In the construction field the problem is even more serious because of specific aspects and of the traditional information system that is very stiff. Formal and bureaucratic, and this makes the adjusting process of specialist to the economic realities to be more difficult.

Rapid expression of transgenes driven by seed-specific constructs in leaf tissue: DHA production

Directory of Open Access Journals (Sweden)

Zhou Xue-Rong

2010-03-01

Full Text Available Abstract Background Metabolic engineering of seed biosynthetic pathways to diversify and improve crop product quality is a highly active research area. The validation of genes driven by seed-specific promoters is time-consuming since the transformed plants must be grown to maturity before the gene function can be analysed. Results In this study we demonstrate that genes driven by seed-specific promoters contained within complex constructs can be transiently-expressed in the Nicotiana benthamiana leaf-assay system by co-infiltrating the Arabidopsis thaliana LEAFY COTYLEDON2 (LEC2 gene. A real-world case study is described in which we first assembled an efficient transgenic DHA synthesis pathway using a traditional N. benthamiana Cauliflower Mosaic Virus (CaMV 35S-driven leaf assay before using the LEC2-extended assay to rapidly validate a complex seed-specific construct containing the same genes before stable transformation in Arabidopsis. Conclusions The LEC2-extended N. benthamiana assay allows the transient activation of seed-specific promoters in leaf tissue. In this study we have used the assay as a rapid preliminary screen of a complex seed-specific transgenic construct prior to stable transformation, a feature that will become increasingly useful as genetic engineering moves from the manipulation of single genes to the engineering of complex pathways. We propose that the assay will prove useful for other applications wherein rapid expression of transgenes driven by seed-specific constructs in leaf tissue are sought.

Construction of irradiated material examination facility-basic design

International Nuclear Information System (INIS)

Ro, Seung Gy; Kim, Eun Ka; Hong, Gye Won; Herr, Young Hoi; Hong, Kwon Pyo; Lee, Myeong Han; Baik, Sang Youl; Choo, Yong Sun; Baik, Seung Je

1989-02-01

The basic design of the hot cell facility which has the main purpose of doing mechanical and physical property tests of irradiated materials, the examination process, and the annexed facility has been made. Also basic and detall designs for the underground excavation work have been performed. The project management and tasks required for the license application have been carried out in due course. The facility is expected to be completed by the end of 1992, if the budgetary support is sufficient. (Author)

25 CFR 502.22 - Construction and maintenance of the gaming facility, and the operation of that gaming is...

Science.gov (United States)

2010-04-01

... 25 Indians 2 2010-04-01 2010-04-01 false Construction and maintenance of the gaming facility, and the operation of that gaming is conducted in a manner which adequately protects the environment and the public health and safety. 502.22 Section 502.22 Indians NATIONAL INDIAN GAMING COMMISSION...

Baseline concentrations of radionuclides and heavy metals in soils and vegetation around the DARHT facility: Construction phase (1996)

International Nuclear Information System (INIS)

Fresquez, P.R.; Haagenstad, H.T.; Naranjo, L. Jr.

1997-04-01

As part of the Department of Energy's Mitigation Action Plan for the Dual Axis Radiographic Hydrodynamic Test (DARHT) Facility at Los Alamos National Laboratory (LANL), baseline concentrations of radionuclides ( 3 H, 137 Cs, 90 Sr, 238 Pu, 239 Pu, 241 Am, total U), and heavy metals (Ag, As, Ba, Be, Cd, Cr, Cu, Hg, Ni, Pb, Sb, Se and Tl) in soil, sediment, and vegetation (overstory and understory) around the DARHT facility during the construction phase in 1996 were determined. Also, U and Be concentrations in soil samples collected in 1993 from within the proposed DARHT facility area are reported. Most radionuclides in soils, sediments, and vegetation were within current background and/or long-term regional statistical reference levels

38 CFR 18.423 - New construction.

Science.gov (United States)

2010-07-01

... 38 Pensions, Bonuses, and Veterans' Relief 2 2010-07-01 2010-07-01 false New construction. 18.423... construction. (a) Design and construction. Each facility or part of a facility constructed by, on behalf of, or... facility is readily accessible to and usable by handicapped persons, if the construction was commenced...

10 CFR 1040.73 - New construction.

Science.gov (United States)

2010-01-01

... 10 Energy 4 2010-01-01 2010-01-01 false New construction. 1040.73 Section 1040.73 Energy... § 1040.73 New construction. (a) Design and construction. Each facility or part of a facility constructed... the construction was commenced after the effective date of this subpart. (b) Alteration. Each facility...

ENVIRONMENTAL SPECIFICATION REQUIREMENTS

International Nuclear Information System (INIS)

TIFFT, S.R.

2003-01-01

Through regulations, permitting or binding negotiations, Regulators establish requirements, limits, permit conditions and Notice of Construction (NOC) conditions with which the Office of River Protection (ORP) and the Tank Farm Contractor (TFC) must comply. Operating Specifications are technical limits which are set on a process to prevent injury to personnel, or damage to the facility or environment. The main purpose of this document is to provide specification limits and recovery actions for the TFC Environmental Surveillance Program at the Hanford Site. Specification limits are given for monitoring frequencies and permissible variation of readings from an established baseline or previous reading. The requirements in this document are driven by environmental considerations and data analysis issues, rather than facility design or personnel safety issues. This document is applicable to all SST and DST waste tanks, and the associated catch tanks and receiver tanks, and transfer systems. This Tank Farm ESD implements environmental-regulatory limits on the configuration and operation of the Hanford Tank Farms facility that have been established by Regulators. This ESD contains specific field operational limits and recovery actions for compliance with airborne effluent regulations and agreements, liquid effluents regulations and agreements, and environmental tank system requirements. The scope of this ESD is limited to conditions that have direct impact on Operations/Projects or that Operations/Projects have direct impact upon. This document does not supercede or replace any DOE Orders, regulatory permits, notices of construction, or Regulatory agency agreements binding on the ORP or the TFC. Refer to the appropriate regulation, permit, or NOC for an inclusive listing of requirements

45 CFR 84.23 - New construction.

Science.gov (United States)

2010-10-01

... 45 Public Welfare 1 2010-10-01 2010-10-01 false New construction. 84.23 Section 84.23 Public... construction. (a) Design and construction. Each facility or part of a facility constructed by, on behalf of, or... of the facility is readily accessible to and usable by handicapped persons, if the construction was...

ENVIRONMENTAL SPECIFICATION REQUIREMENTS

International Nuclear Information System (INIS)

TIFFT, S.R.

2003-01-01

Through regulations, permitting or binding negotiations, Regulators establish requirements, limits, permit conditions and Notice of Construction (NOC) conditions with which the Office of River Protection (ORP) and the Tank Farm Contractor (TFC) must comply. Operating Specifications are technical limits which are set on a process to prevent injury to personnel, or damage to the facility or environment. The main purpose of this document is to provide specification limits and recovery actions for the TFC Environmental Surveillance Program at the Hanford Site. Specification limits are given for monitoring frequencies and permissible variation of readings from an established baseline or previous reading. The requirements in this document are driven by environmental considerations and data analysis issues, rather than facility design or personnel safety issues. This document is applicable to all single-shell tank (SST) and double-shell tank (DST) waste tanks, and the associated catch tanks and receiver tanks, and transfer systems. This Tank Farm Environmental Specifications Document (ESD) implements environmental-regulatory limits on the configuration and operation of the Hanford Tank Farms facility that have been established by Regulators. This ESD contains specific field operational limits and recovery actions for compliance with airborne effluent regulations and agreements, liquid effluents regulations and agreements, and environmental tank system requirements. The scope of this ESD is limited to conditions that have direct impact on Operations Projects or that Operations/Projects have direct impact upon. This document does not supercede or replace any DOE Orders, regulatory permits, notices of construction, or Regulatory agency agreements binding on the ORP or the TFC. Refer to the appropriate regulation, permit, or NOC for an inclusive listing of requirements

Specific character of sustainable innovative development of transport construction in self-regulation conditions

Science.gov (United States)

Gumba, Khuta; Belyaeva, Svetlana

2017-10-01

The providing of sustainable development is impossible without activating the innovative activity of backbone economical sectors, in particular of transport construction. The system of self-regulation of activities is a specific feature of the transport industry development. The authors carried out the correlation analysis of innovative activity of construction enterprises, which proved the necessity of improving the normative and technical documents. The authors proposed and calculated the index of the legislation stability in the industry. The article suggests recommendations on the activation of innovative development in construction industry basing on the results of the modeling.

Technical Site Information: Planning group of the Directorate and Conventional Construction Division

International Nuclear Information System (INIS)

1993-11-01

This document presents the technical site information for the Superconducting Super Collider project. The Ellis County, Texas site was selected by the Department of Energy in 1989. After assembling the initial staff at temporary facilities in Dallas, the SSC Laboratory began site-specific design work. The resulting design for the SSC accelerators, experimental areas, and laboratory facilities were described in the Site-Specific Conceptual Design Report of July 1990. Since then, design specifications for the technical components and conventional facilities have been formulated. In fact, a very significant amount of surface and underground construction has been initiated and many buildings have been completed. Testing of prototypes for most technical components is advanced. The construction phase of the SSC project is approximately 20% complete. At this time, it is appropriate to capture the conventional design work which has taken place since 1990. This documents records regional and physical information used in site studies, summarizes the site studies for conventional facilities, and presents site layouts for buildings and utilities as they would have been at the end of the construction project. As such, this documents summarizes and complements the work of many groups in the SSC laboratory, the Texas National Research Laboratory Commission (TNRLC), and several subcontractors to the SSC project. The document contains extensive references to their work contained in other drafts and final reports. In particular, it borrows heavily from the Site Development Plan (released in draft form in January, 1992) which has, to date, guided aspects of site development

Technical Site Information: Planning group of the Directorate and Conventional Construction Division

Energy Technology Data Exchange (ETDEWEB)

NONE

1993-11-01

This document presents the technical site information for the Superconducting Super Collider project. The Ellis County, Texas site was selected by the Department of Energy in 1989. After assembling the initial staff at temporary facilities in Dallas, the SSC Laboratory began site-specific design work. The resulting design for the SSC accelerators, experimental areas, and laboratory facilities were described in the Site-Specific Conceptual Design Report of July 1990. Since then, design specifications for the technical components and conventional facilities have been formulated. In fact, a very significant amount of surface and underground construction has been initiated and many buildings have been completed. Testing of prototypes for most technical components is advanced. The construction phase of the SSC project is approximately 20% complete. At this time, it is appropriate to capture the conventional design work which has taken place since 1990. This documents records regional and physical information used in site studies, summarizes the site studies for conventional facilities, and presents site layouts for buildings and utilities as they would have been at the end of the construction project. As such, this documents summarizes and complements the work of many groups in the SSC laboratory, the Texas National Research Laboratory Commission (TNRLC), and several subcontractors to the SSC project. The document contains extensive references to their work contained in other drafts and final reports. In particular, it borrows heavily from the Site Development Plan (released in draft form in January, 1992) which has, to date, guided aspects of site development.

Specific features of modern multifunctional high-rise building construction

Science.gov (United States)

Manukhina, Lyubov; Samosudova, Natal'ja

2018-03-01

The article analyzes the main reasons for the development of high-rise building construction the most important of which-is a limitation of the urban areas and, consequently, the high price of land reserved for construction. New engineering and compositional solutions for the creation of new types of buildings are considered - complex technical designs of a large number of storeys completely meet the new requirements for safety and comfort. Some peculiarities of designing high-rise buildings and searching for optimal architectural and planning solutions are revealed since, with external architectural simplicity, high-rise buildings have complex structural and technological and space-planning solutions. We consider the specific features of a high-rise housing in various countries around the world, including Russia, such as the layout of the multi-storey residential buildings, depending on the climatic characteristics of the regions, assessment of the geological risk of the construction site, the choice of parameters and functional purpose of the sections of the territory of high-rise construction, location of the town-planning object for substantiating the overall dimensions of the building, assessment of changes aeration and engineering and hydrological conditions of the site. A special place in the article on the problems of improvement of the territory, the device of courtyards, landscaping, the device of playing and sports grounds. The main conclusion in the article is the following problem - when developing high-rise housing construction, the development of high-rise housing, and an increase in the population density in the territory of large cities of Russia, necessary to create a comfortable and safe level of residents living and not a decrease, but an improvement in the quality of the urban environment.

29 CFR 1926.752 - Site layout, site-specific erection plan and construction sequence.

Science.gov (United States)

2010-07-01

... 29 Labor 8 2010-07-01 2010-07-01 false Site layout, site-specific erection plan and construction... Steel Erection § 1926.752 Site layout, site-specific erection plan and construction sequence. (a... strength or sufficient strength to support the loads imposed during steel erection. (c) Site layout. The...

Licensing of the OPAL reactor during construction and commissioning

International Nuclear Information System (INIS)

Summerfield, M.

2007-01-01

This paper presents a description of the licensing activities associated with the construction and commissioning of the Australian Nuclear Science and Technology Organisation's (ANSTO) OPAL reactor. It addresses the Construction Licence, the interface between ANSTO, INVAP (the contractor with responsibility for design and construction of the facility) and the Australian Radiation Protection and Nuclear Safety Agency (ARPANSA, the Australian nuclear regulator) during the construction of OPAL, specific licensing issues that have arisen during the construction and commissioning process, and the Operating Licence Application. Particular emphasis will be given to the way in which the licensing process is integrated into the overall project program and the lessons learnt that may be of benefit to other licensees and regulators

Construction feasibility of OTEC platforms. Final report

Energy Technology Data Exchange (ETDEWEB)

Brewer, J H; Harwood, P; Solberg, K; Fjeld, S

1978-12-01

This study provides an evaluation of the feasibility of constructing either steel or concrete OTEC platforms of both spar and ship shape configurations for a range of platform sizes with respect to existing, developed shipyard or fabrication yard facilities that are currently active in marine vessel construction within the US. This brief study is quite broad in scope. Many parameters, including plant size; vessel type, size, configuration, and dimensions; position of heat exchangers; existing construction facility size, geographic location, and potential for modification; and, availability of undeveloped deep water construction sites affect the conclusions drawn. Nevertheless, the conclusions should remain valid and not change significantly, unless there are major changes in either vessel size or US construction capabilities. The various concepts are ranked in order of their feasibility and practicality of construction in existing or modified existing facilities and new facilities.

Status of RIB facilities in Asia

International Nuclear Information System (INIS)

Tanihata, Isao

1998-01-01

Radioactive Ion Beam Facilities in Asia are presented. In China, in-flight separation type facilities are in operation at the Institute of Modern Physics in Lanzhou and the other at Tandem facility in China Institute of Atomic Energy in Beijing. The storage-ring facility is proposed and approved in Lanzhou. In India, the Variable Energy Cyclotron Facility in Calcutta start to construct an ISOL-type facility. In Japan, in-flight separation type facilities are working at Research Center for Nuclear Physics in Osaka, and at RIKEN. Also a separator start its operation in medical facility in Chiba. In RIKEN, the construction of RI Beam Factory has been started. An ISOL-type facility is proposed in the Japan Hadron Facility in KEK. Table I summarize these facilities

Construction and operation of a tritium extraction facility at the Savannah River Site. Final environmental impact statement

International Nuclear Information System (INIS)

1999-03-01

DOE proposes to construct and operate a Tritium Extraction Facility (TEF) at H Area on the Savannah River Site (SRS) to provide the capability to extract tritium from commercial light water reactor (CLWR) targets and from targets of similar design. The proposed action is also DOE's preferred alternative. An action alternative is to construct and operate TEF at the Allied General Nuclear Services facility, which is adjacent to the eastern side of the SRS. Under the no-action alternative DOE could incorporate tritium extraction capabilities in the accelerator for production of tritium. This EIS is linked to the Final Programmatic Environmental Impact Statement for Tritium Supply and Recycling, from which DOE determined that it would produce tritium either in an accelerator or in a commercial light water reactor. The purpose of the proposed action and alternatives evaluated in this EIS is to provide tritium extraction capability to support either tritium production technology. The EIS assesses the environmental impacts from the proposed action and the alternatives, including the no action alternative

Design and construction of the facility for neutron depth profiling in research reactor RECH-1

International Nuclear Information System (INIS)

Mutis P, Octavio; Navarro A, Gustavo; Henriquez A, Carlos; Pereda B, Claudio

2002-01-01

Here is described the experimental facility for Neutron Depth Profiling, NDP, constructed at the CCHEN laboratories, as well as some general aspects of the technique. It is also shown applications to the concentration analysis of 10 B and 6 Li as a function of depth for borophosphosilicate glass, BPSG, and for a thick sinter of 6 Li in a zinc-nickel-manganese oxide. Achieved depth resolution is comparable to that obtained in reference advanced laboratories. (author)

Lunar materials for construction of space manufacturing facilities

Science.gov (United States)

Criswell, D. R.

1977-01-01

Development of industrial operations in deep space would be prohibitively expensive if most of the construction and expendable masses had to be transported from earth. Use of lunar materials reduces the needed investments by a factor of 15 to 20. It is shown in this paper that judicious selection of lunar materials will allow one to obtain hydrogen, nitrogen, carbon, helium and other specific elements critical to the support of life in large space habitats at relatively low costs and lower total investment even further. Necessary selection techniques and extraction schemes are outlined. In addition, tables are presented of the oxide and elemental abundances characteristic of the mare and highland regions of the moon which should be useful in evaluating what can be extracted from the lunar soils.

Status of the SXFEL Facility

Directory of Open Access Journals (Sweden)

Zhentang Zhao

2017-06-01

Full Text Available The Shanghai soft X-ray Free-Electron Laser facility (SXFEL is being developed in two steps; the SXFEL test facility (SXFEL-TF, and the SXFEL user facility (SXFEL-UF. The SXFEL-TF is a critical development step towards the construction a soft X-ray FEL user facility in China, and is under commissioning at the Shanghai Synchrotron Radiation Facility (SSRF campus. The test facility is going to generate 8.8 nm FEL radiation using an 840 MeV electron linac passing through the two-stage cascaded HGHG-HGHG or EEHG-HGHG (high-gain harmonic generation, echo-enabled harmonic generation scheme. The construction of the SXFEL-TF started at the end of 2014. Its accelerator tunnel and klystron gallery were ready for equipment installation in April 2016, and the installation of the SXFEL-TF linac and radiator undulators were completed by the end of 2016. In the meantime, the SXFEL-UF, with a designated wavelength in the water window region, began construction in November 2016. This was based on upgrading the linac energy to 1.5 GeV, and the building of a second undulator line and five experimental end-stations. Construction status and the future plans of the SXFEL are reported in this paper.

Control system specification for a cyclotron and neutron therapy facility

International Nuclear Information System (INIS)

Jacky, J.; Risler, R.; Kalet, I.; Wootton, P.; Barke, A.; Brossard, S.; Jackson, R.

1991-01-01

It is usually considered an essential element of good practice in engineering to produce a specification for a system before building it. However, it has been found to be quite difficult to produce useful specifications of large software systems. The authors have nearly completed a comprehensive specification for the computer control system of a cyclotron and treatment facility that provides particle beams for cancer treatments with fast neutrons, production of medical isotopes, and physics experiments. They describe the control system as thoroughly as is practical using standard technical English, supplemented by tables, diagrams, and some algebraic equations. This specification comprises over 300 single-spaced pages. A more precise and compact specification might be achieved by making greater use of formal mathematical notations instead of English. They have begun work on a formal specification of the system, using the Z and Petri net notations

Concept for the generation of the model designated for the simulation of interaction between enterprises comprising one major construction company

Directory of Open Access Journals (Sweden)

Dubovkina Alla Viktorovna

2014-12-01

Full Text Available The author offers an original concept designated for the generation of the model designated to simulate interaction between the enterprises comprising one major construction company within the framework of the production and logistics chain, comprising production facilities, transport enterprises, construction and assembly companies. The author has identified the factors that may produce an adverse effect on construction operations or cause untimely commissioning of a construction facility. The author employed methods of mathematics to describe the operations performed by each constituent enterprise. A graphic model describing each operation was compiled through the integration of mathematical functions. The model binds specific operations, performed by constituent companies, to deadlines, drives attention to interaction bottlenecks, and makes adjustments to assure reliable attainment of the main goal, that is, the timely commissioning of a construction facility.

Sports Facilities Development and Urban Generation

OpenAIRE

Maassoumeh Barghchi; Dasimah B.   Omar; Mohd S.   Aman

2009-01-01

Problem statement: One major issue on sports facilities construction is the question of their funding and justification for investment. Due to, requirement of huge money for construction, constant maintenance costs and ancillary needs, which are almost certainly with substantial public investment, therefore, sports facilities have been considered. Further, sports facilities construction boom have been started for more than two decades. Approach: Recent sports facilities construction was not p...

Critical experiments facility and criticality safety programs at JAERI

International Nuclear Information System (INIS)

Kobayashi, Iwao; Tachimori, Shoichi; Takeshita, Isao; Suzaki, Takenori; Miyoshi, Yoshinori; Nomura, Yasushi

1985-10-01

The nuclear criticality safety is becoming a key point in Japan in the safety considerations for nuclear installations outside reactors such as spent fuel reprocessing facilities, plutonium fuel fabrication facilities, large scale hot alboratories, and so on. Especially a large scale spent fuel reprocessing facility is being designed and would be constructed in near future, therefore extensive experimental studies are needed for compilation of our own technical standards and also for verification of safety in a potential criticality accident to obtain public acceptance. Japan Atomic Energy Research Institute is proceeding a construction program of a new criticality safety experimental facility where criticality data can be obtained for such solution fuels as mainly handled in a reprocessing facility and also chemical process experiments can be performed to investigate abnormal phenomena, e.g. plutonium behavior in solvent extraction process by using pulsed colums. In FY 1985 detail design of the facility will be completed and licensing review by the government would start in FY 1986. Experiments would start in FY 1990. Research subjects and main specifications of the facility are described. (author)

Construction program for a large superconducting MHD magnet system at the coal-fired flow facility

International Nuclear Information System (INIS)

Wang, S.T.; Genens, L.; Gonczy, J.; Ludwig, H.; Lieberg, M.; Kraft, E.; Gacek, D.; Huang, Y.C.; Chen, C.J.

1980-01-01

The Argonne National Laboratory has designed and is constructing a 6 T large aperture superconducting MHD magnet for use in the Coal-Fired Flow Facility (CFFF) at the University of Tennessee Space Institute (UTSI) at Tullahoma, Tennessee. The magnet system consists of the superconducting magnet, a magnet power supply, an integrated instrumentation for operation, control and protection, and a complete cryogenic facility including a CTI Model 2800 helium refrigerator/liquefier with two compressors, helium gas handling system and a 7500 liter liquid helium dewar. The complete system will be tested at Argonne, IL in 1981. The magnet design is reviewed, and the coil fabrication programs are described in detail

Remote handling technology for nuclear fuel cycle facilities

International Nuclear Information System (INIS)

Sakai, Akira; Maekawa, Hiromichi; Ohmura, Yutaka

1997-01-01

Design and R and D on nuclear fuel cycle facilities has intended development of remote handling and maintenance technology since 1977. IHI has completed the design and construction of several facilities with remote handling systems for Power Reactor and Nuclear Fuel Development Corporation (PNC), Japan Atomic Energy Research Institute (JAERI), and Japan Nuclear Fuel Ltd. (JNFL). Based on the above experiences, IHI is now undertaking integration of specific technology and remote handling technology for application to new fields such as fusion reactor facilities, decommissioning of nuclear reactors, accelerator testing facilities, and robot simulator-aided remote operation systems in the future. (author)

Preliminary design for the Waste Receiving And Processing Facility Module 1: Volume 3, Outline specifications

International Nuclear Information System (INIS)

1992-03-01

This report presents specifications related to the buildings and equipment of the wrap facility. The facility will retrieve, process, and certify transuranic, mixed, and low-level radioactive wastes for disposal

Mixed Waste Management Facility (MWMF) closure, Savannah River Plant: Clay cap test section construction report

Energy Technology Data Exchange (ETDEWEB)

1988-02-26

This report contains appendices 3 through 6 for the Clay Cap Test Section Construction Report for the Mixed Waste Management Facility (MWMF) closure at the Savannah River Plant. The Clay Cap Test Program was conducted to evaluate the source, lab. permeability, in-situ permeability, and compaction characteristics, representative of kaolin clays from the Aiken, South Carolina vicinity. (KJD)

Comparison of concepts for independent spent fuel storage facilities

International Nuclear Information System (INIS)

Held, Ch.; Hintermayer, H.P.

1978-01-01

The design and the construction costs of independent spent fuel storage facilities show significant differences, reflecting the fuel receiving rate (during the lifetime of the power plant or within a very short period), the individual national policies and the design requirements in those countries. Major incremental construction expenditures for storage facilities originate from the capacity and the type of the facilities (casks or buildings), the method of fuel cooling (water or air), from the different design of buildings, the redundancy of equipment, an elaborate quality assurance program, and a single or multipurpose design (i.e. interim or long-term storage of spent fuel, interim storage of high level waste after fuel storage). The specific costs of different designs vary by a factor of 30 to 60 which might in the high case increase the nuclear generating costs remarkably. The paper also discusses the effect of spent fuel storage on fuel cycle alternatives with reprocessing or disposal of spent fuel. (author)

Specifically Designed Constructed Wetlands: A Novel Treatment Approach for Scrubber Wastewater

Energy Technology Data Exchange (ETDEWEB)

John H. Rodgers Jr; James W. Castle; Chris Arrington: Derek Eggert; Meg Iannacone

2005-09-01

A pilot-scale wetland treatment system was specifically designed and constructed at Clemson University to evaluate removal of mercury, selenium, and other constituents from flue gas desulfurization (FGD) wastewater. Specific objectives of this research were: (1) to measure performance of a pilot-scale constructed wetland treatment system in terms of decreases in targeted constituents (Hg, Se and As) in the FGD wastewater from inflow to outflow; (2) to determine how the observed performance is achieved (both reactions and rates); and (3) to measure performance in terms of decreased bioavailability of these elements (i.e. toxicity of sediments in constructed wetlands and toxicity of outflow waters from the treatment system). Performance of the pilot-scale constructed wetland treatment systems was assessed using two criteria: anticipated NPDES permit levels and toxicity evaluations using two sentinel toxicity-testing organisms (Ceriodaphnia dubia and Pimephales promelas). These systems performed efficiently with varied inflow simulations of FGD wastewaters removing As, Hg, and Se concentrations below NPDES permit levels and reducing the toxicity of simulated FGD wastewater after treatment with the constructed wetland treatment systems. Sequential extraction procedures indicated that these elements (As, Hg, and Se) were bound to residual phases within sediments of these systems, which should limit their bioavailability to aquatic biota. Sediments collected from constructed wetland treatment systems were tested to observe toxicity to Hyalella azteca or Chironomus tetans. Complete survival (100%) was observed for H. azteca in all cells of the constructed wetland treatment system and C. tentans had an average of 91% survival over the three treatment cells containing sediments. Survival and growth of H. azteca and C. tentans did not differ significantly between sediments from the constructed wetland treatment system and controls. Since the sediments of the constructed

Environmental Assessment for the construction and operation of the Health Physics Site Support Facility on the Savannah River Site

International Nuclear Information System (INIS)

1995-07-01

DOE has prepared an environmental assessment for the proposed construction and operation of the Health Physics Site Support Facility on the Savannah River Site. This (new) facility would meet requirements of the site radiological protection program and would ensure site compliance with regulations. It was determined that the proposed action is not a major Federal action significantly affecting the quality of the environment within the meaning of NEPA. Therefore, a finding of no significant impact is made, and no environmental impact statement is needed

Environmental footprint of constructed wetlands treating wastewater.

Science.gov (United States)

Gkika, Dimitra; Gikas, Georgios D; Tsihrintzis, Vassilios A

2015-01-01

The aim of the study is to determine environmentally friendlier construction materials for constructed wetland facilities treating wastewater. This is done by computing the environmental footprint of the facility based on the methodology of life cycle assessment (LCA). This methodology reveals the dominant aggravating processes during the construction of a constructed wetland (CW) and can help to create alternative environmentally friendlier solutions. This methodology was applied for the determination of the overall environmental profile of a hybrid CW facility. The LCA was applied first to the facility as originally designed, where reinforced concrete was used in some components. Then, alternative construction materials to reinforced concrete were used, such as earth covered with high density polyethylene (HDPE) or clay, and LCA was applied again. Earth structures were found to have reduced environmental impact compared to concrete ones, and clay was found environmentally friendlier compared to HDPE. Furthermore, estimation of the construction costs of the three scenarios indicate that the last scenario is also the least expensive.

A guide to the management of tailings facilities

International Nuclear Information System (INIS)

Bedard, C.; Ferguson, K.; Gladwin, D.; Lang, D.; Maltby, J.; McCann, M.; Poirier, P.; Schwenger, R.; Vezina, S.; West, S.; Duval, J.; Gardiner, E.; Jansons, K.; Lewis, B.; Matthews, J.; Mchaina, D.; Puro, M.; Siwik, R.; Welch, D.

1998-01-01

The 'Guide to the Management of Tailings Facilities' has been developed by the Mining Association of Canada in an effort to provide guidance to its member companies on sound practices for the safe and environmentally responsible management of tailings facilities. The guide is a reference tool to help companies ensure that they are managing their tailings facilities responsibly, integrating environmental and safety considerations in a consistent manner, with continuous improvement in the operation of tailings facilities. The key to managing tailings responsibly is consistent application of engineering capabilities through the full life cycle. The guide provides a basis for the development of customized tailings management systems to address specific needs at individual operations, and deals with environmental impacts, mill tailing characteristics, tailings facility studies and plans, dam and related structure design, and control and monitoring. Aspects relating to tailings facility siting, design, construction, operation, decommissioning and closure are also fully treated. 1 tab., 3 figs

Conceptual design for the Waste Receiving and Processing facility Module 2A

International Nuclear Information System (INIS)

1992-07-01

This is part of a Conceptual Design Report (CDR) for the Waste Receiving and Processing (WRAP) Module 2A facility at the Hanford Reservation. The mission of the facility is to receive, process, package, certify, and ship for permanent burial at the Hanford site disposal facilities those contact handled (CH) low-level radioactive mixed wastes (LLMW) that: (1) are currently in retrievable storage at the Hanford Central Waste Complex (HCWC) awaiting a treatment capability to permit permanent disposal compliant with the Land Disposal Restrictions and; (2) are forecasted to be generated over the next 30 years. The primary sources of waste to be treated include the currently stored waste from the 183-H solar basin evaporators, secondary solids from the future Hanford site liquid effluent treatment facilities, thermal treatment facility ash, other WRAP modules, and other miscellaneous waste from storage and onsite/offsite waste generators consisting of compactible and non-compactible solids, contaminated soils, and metals. This volume, Volume III is a compilation of the outline specifications that will form the basis for development of the Title design construction specifications. This volume contains abbreviated CSI outline specifications for equipment as well as non-equipment related construction and material items. For process and mechanical equipment, data sheets are provided with the specifications which indicate the equipment overall design parameters. This volume also includes a major equipment list

Biological shielding design and qualification of concreting process for construction of electron beam irradiation facility

International Nuclear Information System (INIS)

Petwal, V.C.; Kumar, P.; Suresh, N.; Parchani, G.; Dwivedi, J.; Thakurta, A.C.

2011-01-01

A technology demonstration facility for irradiation of food and agricultural products is being set-up by RRCAT at Indore. The facility design is based on linear electron accelerator with maximum beam power of 10 kW and can be operated either in electron mode at 10 MeV or photon modes at 5/7.5 MeV. Biological shielding has been designed in accordance with NCRP 51 to achieve dose rate at all accessible points outside the irradiation vault less than the permissible limit of 0.1 mR/hr. In addition to radiation attenuation property, concrete must have satisfactory mechanical properties to meet the structural requirements. There are number of site specific variables which affect the structural, thermal and radiological properties of concrete, leading to considerable difference in actual values and design values. Hence it is essential to establish a suitable site and environmental specific process to cast the concrete and qualify the process by experimental measurement. For process qualification we have cast concrete test blocks of different thicknesses up to 3.25 m and evaluated the radiological and mechanical properties by radiometry, ultrasonic and mechanical tests. In this paper we describe the biological shielding design of the facility and analyse the results of tests carried out for qualification of the process. (author)

15 CFR 8b.18 - New construction.

Science.gov (United States)

2010-01-01

... 15 Commerce and Foreign Trade 1 2010-01-01 2010-01-01 false New construction. 8b.18 Section 8b.18... construction. (a) Design and construction. Each facility or part of a facility constructed by, on behalf of, or... construction was commenced after the effective date of this part. (b) Alteration. Each facility or part of a...

Quality assurance during construction of civil engineering structures important to safety of nuclear facilities

International Nuclear Information System (INIS)

2011-11-01

The present manual is developed to deal with quality assurance aspect of civil engineering structures in a greater detail. This manual gives detail to develop QA plans specific to multifarious activities of civil engineering construction

Use and construction of new facilities

International Nuclear Information System (INIS)

Anttila, K.

1972-01-01

In 1971 a vertical beam tube was constructed to increase possibilities in using the FiR1 reactor, especially in taking neutron radiographs. The most suitable location for the beam tube was found on top of the radial graphite reflector near the end of the thermal column. The constructional details of the vertical beam tube are given. Neutron radiography pictures has been taken at the FiR 1 reactor using neutron beams from the thermal column, radial beam tube and from the vertical beam tube. In order to reveal dynamic phenomena inside various objects a neutron- TV - system was built. The most important areas of using neutron radiography have until now been the inspection of some special industrial devices and the radiography of radioactive fuel elements. Several other and perhaps new applications for this kind of research were also found e.g. the research of solidification of metal alloys; diffusion of moisture in concrete; icing of an automobile carburettor; paths of liquid gasoline and the effect of various additives in gasoline preventing icing; and brazed joints between metals. The Monte Carlo calculations of the new cold neutron source, which is now under construction at the FiR1 are presented

Construction safety program for the National Ignition Facility Appendix A: Safety Requirements

International Nuclear Information System (INIS)

Cerruti, S.J.

1997-01-01

These rules apply to all LLNL employees, non-LLNL employees (including contract labor, supplemental labor, vendors, personnel matrixed/assigned from other National Laboratories, participating guests, visitors and students) and construction contractors/subcontractors. The General Safety and Health rules shall be used by management to promote accident prevention through indoctrination, safety and health training and on-the-job application. As a condition for contracts award, all contractors and subcontractors and their employees must certify on Form S ampersand H A-1 that they have read and understand, or have been briefed and understand, the National Ignition Facility OCIP Project General Safety Rules

Construction safety program for the National Ignition Facility Appendix A: Safety Requirements

Energy Technology Data Exchange (ETDEWEB)

Cerruti, S.J.

1997-01-14

These rules apply to all LLNL employees, non-LLNL employees (including contract labor, supplemental labor, vendors, personnel matrixed/assigned from other National Laboratories, participating guests, visitors and students) and construction contractors/subcontractors. The General Safety and Health rules shall be used by management to promote accident prevention through indoctrination, safety and health training and on-the-job application. As a condition for contracts award, all contractors and subcontractors and their employees must certify on Form S & H A-1 that they have read and understand, or have been briefed and understand, the National Ignition Facility OCIP Project General Safety Rules.

Structural health monitoring and lifecycle-management for civil engineering constructions in power plants and industrial facilities; Zustandsueberwachung und Lebensdauermanagement von baulichen Einrichtungen in Kraftwerken und Industrieanlagen

Energy Technology Data Exchange (ETDEWEB)

Lehnen, Dieter; Demmer, Martin; Pfister, Tobias [ZERNA Planen und Pruefen GmbH, Bochum (Germany)

2013-09-01

In contrast to other fields of engineering, structural health monitoring and lifecycle management for civil engineering constructions in power plants and industrial facilities have to be developed yet. The necessity of this development immediately arises from the building regulations law with its extensive set of regulations as well as from economic constraints. Approaches and methods of structural health monitoring and lifecycle management for civil engineering constructions in power plants and industrial facilities could be improved intensively during recent years. The paper focuses on practical examples that show the necessity of comprehensive and strategic structural health monitoring in conjunction with lifecycle management for civil engineering constructions in power plants and industrial facilities unambiguously und clear. (orig.)

Study on construction technology for repository

International Nuclear Information System (INIS)

Tanai, Kenji; Iwasa, Kengo; Hasegawa, Hiroshi; Miura, Kazuhiko; Okutsu, Kazuo; Kobayashi, Masaaki

1999-11-01

For the construction of underground facilities comprising access tunnels, connecting tunnels, main tunnels and disposal tunnels, a large number of tunnels will be excavated in deep rock formations. These excavations will extend hundreds kilometers in total length. Therefore, special attention must be paid, to transporting large volume of debris, ventilation, emergency escape routes in case of accident, and other factors. In addition, special attention must also paid to potential accidents which might in underground excavations, including unstable facing phenomena (such as collapse and swelling of facing at weak layer sections), spring water flow resulting collapse of rock, gas eruption, and rock burst. While considering these factors to be emphasized during the construction of geological disposal facilities, the investigation reviewed the existing working methods on individual construction technologies of access tunnels, main tunnels, connecting tunnels, disposal tunnels, and disposal pit, based on the recognition that the present state deals with a wide range of geological environments, and conducted investigation about the construction methods for each tunnel on the basis current technologies, and described the outline of these methods. Furthermore, for the items to be particularly emphasized on site characterization and siting data such as ground pressure and spring water, the investigation reviewed the current countermeasure works, and made survey on the phenomena appeared during actual tunnel construction works and their countermeasures, and carried out a study on effectiveness of these countermeasures. This constructing of disposal site in deep geological formations is basically possible by applying, or confirming, current excavation technologies for tunnels and underground facilities. A systematic construction system combines separate technologies relating to construction, (excavation technology, tunnel support work method, etc.). Such systems can be

Advantages of co-located spent fuel reprocessing, repository and underground reactor facilities

International Nuclear Information System (INIS)

Mahar, James M.; Kunze, Jay F.; Wes Myers, Carl; Loveland, Ryan

2007-01-01

The purpose of this work is to extend the discussion of potential advantages of the underground nuclear park (UNP) concept by making specific concept design and cost estimate comparisons for both present Generation III types of reactors and for some of the modular Gen IV or the GNEP modular concept. For the present Gen III types, we propose co-locating reprocessing and (re)fabrication facilities along with disposal facilities in the underground park. The goal is to determine the site costs and facility construction costs of such a complex which incorporates the advantages of a closed fuel cycle, nuclear waste repository, and ultimate decommissioning activities all within the UNP. Modular power generation units are also well-suited for placement underground and have the added advantage of construction using current and future tunnel boring machine technology. (authors)

Construction and fitting of NUCEF

International Nuclear Information System (INIS)

Takeshita, Isao; Itahashi, Takayuki; Izawa, Naoki; Okazaki, Shuji

1994-01-01

NUCEF consists of two criticality experiment devices, three alpha-gamma cells, the experimental equipments contained in about 90 glove boxes and many others. The background and the course of the construction and fitting of NUCEF are described on the selection of important research, the rationalization of facilities, the integration of the criticality safety experiments facility(CSEF) and the TRU safety test facility(TRUST), the safety examination, and the construction and fitting. The whole NUCEF, the static criticality facility(STACY), the transient criticality facility(TRACY), the mock-up test of the machinery and equipment for both criticality facilities, the solution fuel preparation facility, cells and glove boxes and the equipment contained in them, the analysis facility consists of four analysis rooms, and the radioactive waste facility for gas, liquid and solid wastes are described. The classification of these facilities based on the relevant laws is shown. The way of thinking in the basic design and the detailed design is explained. The permission of nuclear reactor installation and the use of nuclear fuel substances was obtained. The design and the method of works were approved. The inspection is reported. The measures for the security are explained. (K.I.)

Preliminary analysis of West Valley Waste Removal System equipment development and mock demonstration facilities

International Nuclear Information System (INIS)

Janicek, G.P.

1981-06-01

This report defines seven areas requiring further investigation to develop and demonstrate a safe and viable West Valley Waste Removal System. These areas of endeavor are discussed in terms of their minimum facility requirements. It is concluded that utilizing separated specific facilities at different points in time is of a greater advantage than an exact duplication of the West Valley tanks. Savannah River Plant's full-scale, full-circle and half-circle tanks, and their twelfth scale model tank would all be useful to varying degrees but would require modifications. Hanford's proposed full-size mock tank would be useful, but is not seriously considered because its construction may not coincide with West Valley needs. Costs of modifying existing facilities and/or constructing new facilities are assessed in terms of their benefit to the equipment development and mock demonstration. Six facilities were identified for further analysis which would benefit development of waste removal equipment

HTTR hydrogen production system. Structure and main specifications of mock-up test facility (Contract research)

International Nuclear Information System (INIS)

Kato, Michio; Aita, Hideki; Inagaki, Yoshiyuki; Hayashi, Koji; Ohashi, Hirofumi; Sato, Hiroyuki; Iwatsuki, Jin; Takada, Shoji; Inaba, Yoshitomo

2007-03-01

The mock-up test facility was fabricated to investigate performance of the steam generator for mitigation of the temperature fluctuation of helium gas and transient behavior of the hydrogen production system for HTTR and to obtain experimental data for verification of a dynamic analysis code. The test facility has an approximate hydrogen production capacity of 120Nm 3 /h and the steam reforming process of methane; CH 4 +H 2 O=3H 2 +CO, was used for hydrogen production of the test facility. An electric heater was used as a heat source instead of the reactor in order to heat helium gas up to 880degC (4MPa) at the chemical reactor inlet which is the same temperature as the HTTR hydrogen production system. Fabrication of the test facility was completed in February in 2002, and seven cycle operations were carried out from March in 2002 to December in 2004. This report describes the structure and main specifications of the test facility. (author)

Design and construction of hazardous waste landfill components

International Nuclear Information System (INIS)

Frano, A.J.; Numes, G.S.

1985-01-01

This paper discusses design and construction of two sections of a hazardous waste landfill at Peoria Disposal Company's hazardous waste management facilities in central Illinois. One section, an existing disposal facility, was retrofitted with leachate control and containment features for additional security. The second section, a new facility which had been previously permitted for development with a single clay liner, was modified to include a double liner and revised leachate collection system for additional security, and an all-weather construction and operation access ramp. The two sections of the landfill were granted a development permit allowing construction. An operating permit was granted after construction and certification by the designer allowing waste disposal operations. The sections will be accepting waste material at publication. Design and construction included: planning studies, design analyses, permitting, preparation of construction contract documents, construction assistance, monitoring construction, and certification

Final environmental assessment for a refinement of the power delivery component of the Southern Nevada Water Authority Treatment and Transmission Facility

International Nuclear Information System (INIS)

1998-07-01

The Southern Nevada Water Authority (SNWA) is designing and constructing a system of regional water supply facilities to meet current and projected water demands and increase system reliability. The existing Southern Nevada Water system is being upgraded with a number of improvements to increase the capacity of the system. However, even the expanded system is expected to be unable to meet projected peak daily water demands by the year 1999. As a result, new facilities are being designed and constructed to operate in conjunction with the upgraded Southern Nevada Water system. These new facilities, known as the Southern Nevada Water Authority Treatment and Transmission Facility (SNWA-TTF), include four primary components: a new raw water intake; new transmission facilities including below ground pipelines, tunnels, and above ground pumping stations; a water treatment facility; and new power supply facilities. Because existing power supplies would not be adequate for the new water treatment facilities, new power facilities, consisting of two new 230 kV-69 kV substations and new 69 and 230 kV power lines, are being constructed. This environmental assessment is specifically on the new power facilities

Design of the PRIDE Facility

International Nuclear Information System (INIS)

You, Gil Sung; Choung, Won Myung; Lee, Eun Pyo; Cho, Il Je; Kwon, Kie Chan; Hong, Dong Hee; Lee, Won Kyung; Ku, Jeong Hoe

2009-01-01

From 2007, KAERI is developing a PyRoprocess Integrated inactive DEmonstration facility (the PRIDE facility). The maximum annual treatment capacity of this facility will be a 10 ton-HM. The process will use a natural uranium feed material or a natural uranium mixed with some surrogate material for a simulation of a spent fuel. KAERI has also another plan to construct a demonstration facility which can treat a real spent fuel by pyroprocessing. This facility is called by ESPF, Engineering Scale Pyroprocess Facility. The ESPF will have the same treatment capability of spent fuel with the PRIDE facility. The only difference between the PRIDE and the ESPF is a radiation shielding capability. From the PRIDE facility designing works and demonstration with a simulated spent fuel after construction, it will be able to obtain the basic facility requirements, remote operability, interrelation properties between process equipment for designing of the ESPF. The flow sheet of the PRIDE processes is composed of five main processes, such as a decladding and voloxidation, an electro-reduction, an electrorefining, an electro-winning, and a salt waste treatment. The final products from the PRIDE facility are a simulated TRU metal and U metal ingot

Evaporative removal of sodium: interim progress report and preliminary facility specification

International Nuclear Information System (INIS)

Welch, F.H.

1978-01-01

A summary of the current Evaporative Removal of Sodium (ERNA) activities at the Energy Systems Group is presented. Also included is a review of earlier work on sodium evaporation. As a result of this work it was concluded that the ERNA process was extremely successful and worthy of future consideration as a recognized process for reactor components. Also included in the report is a Preliminary Outline Specification for a large facility to remove sodium from full size CRBR fuel rod assemblies

Solid Waste Operations Complex W-113, Detail Design Report (Title II). Volume 3: Specifications

International Nuclear Information System (INIS)

1995-09-01

The Solid Waste Retrieval Facility--Phase 1 (Project W113) will provide the infrastructure and the facility required to retrieve from Trench 04, Burial ground 4C, contact handled (CH) drums and boxes at a rate that supports all retrieved TRU waste batching, treatment, storage, and disposal plans. This includes (1) operations related equipment and facilities, viz., a weather enclosure for the trench, retrieval equipment, weighing, venting, obtaining gas samples, overpacking, NDE, NDA, shipment of waste and (2) operations support related facilities, viz., a general office building, a retrieval staff change facility, and infrastructure upgrades such as supply and routing of water, sewer, electrical power, fire protection, roads, and telecommunication. Title I design for the operations related equipment and facilities was performed by Raytheon/BNFL, and that for the operations support related facilities including infrastructure upgrade was performed by KEH. These two scopes were combined into an integrated W113 Title II scope that was performed by Raytheon/BNFL. Volume 3 is a compilation of the construction specifications that will constitute the Title II materials and performance specifications. This volume contains CSI specifications for non-equipment related construction material type items, performance type items, and facility mechanical equipment items. Data sheets are provided, as necessary, which specify the equipment overall design parameters

Solid Waste Operations Complex W-113, Detail Design Report (Title II). Volume 3: Specifications

Energy Technology Data Exchange (ETDEWEB)

NONE

1995-09-01

The Solid Waste Retrieval Facility--Phase 1 (Project W113) will provide the infrastructure and the facility required to retrieve from Trench 04, Burial ground 4C, contact handled (CH) drums and boxes at a rate that supports all retrieved TRU waste batching, treatment, storage, and disposal plans. This includes (1) operations related equipment and facilities, viz., a weather enclosure for the trench, retrieval equipment, weighing, venting, obtaining gas samples, overpacking, NDE, NDA, shipment of waste and (2) operations support related facilities, viz., a general office building, a retrieval staff change facility, and infrastructure upgrades such as supply and routing of water, sewer, electrical power, fire protection, roads, and telecommunication. Title I design for the operations related equipment and facilities was performed by Raytheon/BNFL, and that for the operations support related facilities including infrastructure upgrade was performed by KEH. These two scopes were combined into an integrated W113 Title II scope that was performed by Raytheon/BNFL. Volume 3 is a compilation of the construction specifications that will constitute the Title II materials and performance specifications. This volume contains CSI specifications for non-equipment related construction material type items, performance type items, and facility mechanical equipment items. Data sheets are provided, as necessary, which specify the equipment overall design parameters.

Radioactive Air Emmission Notice of Construction (NOC) for the Waste Receiving and Processing Facility (WRAP)

Energy Technology Data Exchange (ETDEWEB)

MENARD, N.M.

2000-12-01

This document serves as a notice of construction (NOC) pursuant to the requirements of Washington Administrative Code (WAC) 246-247-060, and as a request for approval to modify pursuant to 40 Code of Federal Regulations (CFR) 61.07 for the Waste Receiving and Processing (WRAP) Facility. The rewrite of this NOC incorporates all the approved revisions (Sections 5.0, 6.0, 8.0, and 9.0), a revised potential to emit (PTE) based on the revised maximally exposed individual (MEI) (Sections 8.0, 10.0, 11.0, 12.0, 13.0, 14.0, and 15.0), the results of a study on fugitive emissions (Sections 6.0, 10.0, and 15.0), and reflects the current operating conditions at the WRAP Facility (Section 5.0). This NOC replaces DOE/RL-93-15 and DOE/RL-93-16 in their entirety. The primary function of the WRAP Facility is to examine, assay, characterize, treat, verify, and repackage radioactive material and mixed waste. There are two sources of emissions from the WRAP Facility: stack emissions and fugitive emissions. The stack emissions have an unabated total effective dose equivalent (TEDE) estimate to the hypothetical offsite MEI of 1.13 E+02 millirem per year. The abated TEDE for the stack emissions is estimated at 5.63 E-02 millirem per year to the MEI. The fugitive emissions have an unabated TEDE estimate to the hypothetical offsite MEI of 5.87 E-04. There is no abatement for the fugitive emissions.

Ecological studies related to construction of the Defense Waste Processing Facility on the Savannah River Site

Energy Technology Data Exchange (ETDEWEB)

Pechmann, J.H.K.; Scott, D.E.; McGregor, J.H.; Estes, R.A.; Chazal, A.C.

1993-02-01

The Defense Waste Processing Facility (DWPF) was built on the Savannah River Site (SRS) during the mid-1980's. The Savannah River Ecology Laboratory (SREL) has completed 12 years of ecological studies related to the construction of the DWPF complex. Prior to construction, the 600-acre site (S-Area) contained a Carolina bay and the headwaters of a stream. Research conducted by the SREL has focused primarily on four questions related to these wetlands: (1) Prior to construction, what fauna and flora were present at the DWPF site and at similar, yet undisturbed, alternative sites (2) By comparing the Carolina bay at the DWPF site (Sun Bay) with an undisturbed control Carolina bay (Rainbow Bay), what effect is construction having on the organisms that inhabited the DWPF site (3) By comparing control streams with streams on the periphery of the DWPF site, what effect is construction having on the peripheral streams (4) How effective have efforts been to lessen the impacts of construction, both with respect to erosion control measures and the construction of refuge ponds'' as alternative breeding sites for amphibians that formerly bred at Sun Bay Through the long-term census-taking of biota at the DWPF site and Rainbow Bay, SREL has begun to evaluate the impact of construction on the biota and the effectiveness of mitigation efforts. Similarly, the effects of erosion from the DWPF site on the water quality of S-Area peripheral streams are being assessed. This research provides supporting data relevant to the National Environmental Policy Act (NEPA) of 1969, the Endangered Species Act of 1973, Executive Orders 11988 (Floodplain Management) and 11990 (Protection of Wetlands), and United States Department of Energy (DOE) Guidelines for Compliance with Floodplain/Wetland Environmental Review Requirements (10CFR1022).

U.S. Environmental Protection Agency Clear Air Act notice of construction for the spent nuclear fuel project - Cold Vacuum Drying Facility, project W-441

International Nuclear Information System (INIS)

Turnbaugh, J.E.

1996-01-01

This document provides information regarding the source and the estimated quantity of potential airborne radionuclide emissions resulting from the operation of the Cold Vacuum Drying (CVD) Facility. The construction of the CVD Facility is scheduled to commence on or about December 1996, and will be completed when the process begins operation. This document serves as a Notice of Construction (NOC) pursuant to the requirements of 40 Code of Federal Regulations (CFR) 61 for the CVD Facility. About 80 percent of the U.S. Department of Energy's spent nuclear fuel (SNF) inventory is stored under water in the Hanford Site K Basins. Spent nuclear fuel in the K West Basin is contained in closed canisters, while the SNF in the K East Basin is in open canisters, which allow release of corrosion products to the K East Basin water. Storage of the current inventory in the K Basins was originally intended to be on an as-needed basis to sustain operation of the N Reactor while the Plutonium-Uranium Extraction (PUREX) Plant was refurbished and restarted. The decision in December 1992 to deactivate the PURF-X Plant left approximately 2,100 MT (2,300 tons) of uranium as part of the N Reactor SNF in the K Basins with no means for near-term removal and processing. The CVD Facility will be constructed in the 100 Area northwest of the 190 K West Building, which is in close proximity to the K East and K West Basins (Figures 1 and 08572). The CVD Facility will consist of five processing bays, with four of the bays fully equipped with processing equipment and the fifth bay configured as an open spare bay. The CVD Facility will have a support area consisting of a control room, change rooms, and other functions required to support operations

General service and child immunization-specific readiness assessment of healthcare facilities in two selected divisions in Bangladesh.

Science.gov (United States)

Shawon, Md Shajedur Rahman; Adhikary, Gourab; Ali, Md Wazed; Shamsuzzaman, Md; Ahmed, Shahabuddin; Alam, Nurul; Shackelford, Katya A; Woldeab, Alexander; Lim, Stephen S; Levine, Aubrey; Gakidou, Emmanuela; Uddin, Md Jasim

2018-01-25

Service readiness of health facilities is an integral part of providing comprehensive quality healthcare to the community. Comprehensive assessment of general and service-specific (i.e. child immunization) readiness will help to identify the bottlenecks in healthcare service delivery and gaps in equitable service provision. Assessing healthcare facilities readiness also helps in optimal policymaking and resource allocation. A health facility survey was conducted between March 2015 and December 2015 in two purposively selected divisions in Bangladesh; i.e. Rajshahi division (high performing) and Sylhet division (low performing). A total of 123 health facilities were randomly selected from different levels of service, both public and private, with variation in sizes and patient loads from the list of facilities. Data on various aspects of healthcare facility were collected by interviewing key personnel. General service and child immunization specific service readiness were assessed using the Service Availability and Readiness Assessment (SARA) manual developed by World Health Organization (WHO). The analyses were stratified by division and level of healthcare facilities. The general service readiness index for pharmacies, community clinics, primary care facilities and higher care facilities were 40.6%, 60.5%, 59.8% and 69.5%, respectively in Rajshahi division and 44.3%, 57.8%, 57.5% and 73.4%, respectively in Sylhet division. Facilities at all levels had the highest scores for basic equipment (ranged between 51.7% and 93.7%) and the lowest scores for diagnostic capacity (ranged between 0.0% and 53.7%). Though facilities with vaccine storage capacity had very high levels of service readiness for child immunization, facilities without vaccine storage capacity lacked availability of many tracer items. Regarding readiness for newly introduced pneumococcal conjugate vaccine (PCV) and inactivated polio vaccine (IPV), most of the surveyed facilities reported lack of

SUBSURFACE CONSTRUCTION AND DEVELOPMENT ANALYSIS

International Nuclear Information System (INIS)

N.E. Kramer

1998-01-01

The purpose of this analysis is to identify appropriate construction methods and develop a feasible approach for construction and development of the repository subsurface facilities. The objective of this analysis is to support development of the subsurface repository layout for License Application (LA) design. The scope of the analysis for construction and development of the subsurface Repository facilities covers: (1) Excavation methods, including application of knowledge gained from construction of the Exploratory Studies Facility (ESF). (2) Muck removal from excavation headings to the surface. This task will examine ways of preventing interference with other subsurface construction activities. (3) The logistics and equipment for the construction and development rail haulage systems. (4) Impact of ground support installation on excavation and other construction activities. (5) Examination of how drift mapping will be accomplished. (6) Men and materials handling. (7) Installation and removal of construction utilities and ventilation systems. (8) Equipping and finishing of the emplacement drift mains and access ramps to fulfill waste emplacement operational needs. (9) Emplacement drift and access mains and ramps commissioning prior to handover for emplacement operations. (10) Examination of ways to structure the contracts for construction of the repository. (11) Discussion of different construction schemes and how to minimize the schedule risks implicit in those schemes. (12) Surface facilities needed for subsurface construction activities

Strategy of Construction and Demolition Waste Management after Chemical Industry Facilities Removal

Science.gov (United States)

Tashkinova, I. N.; Batrakova, G. M.; Vaisman, Ya I.

2017-06-01

Mixed waste products are generated in the process of irrelevant industrial projects’ removal if conventional techniques of their demolition and dismantling are applied. In Russia the number of unused chemical industry facilities including structures with high rate of wear is growing. In removing industrial buildings and production shops it is used conventional techniques of demolition and dismantling in the process of which mixed waste products are generated. The presence of hazardous chemicals in these wastes makes difficulties for their use and leads to the increasing volume of unutilized residues. In the process of chemical industry facilities’ removal this fact takes on special significance as a high level of hazardous chemicals in the waste composition demands for the realization of unprofitable measures aimed at ensuring environmental and industrial safety. The proposed strategy of managing waste originated from the demolition and dismantling of chemical industry facilities is based on the methodology of industrial metabolism which allows identifying separate material flows of recycled, harmful and ballast components, performing separate collection of components during removal and taking necessary preventive measures. This strategy has been tested on the aniline synthesis plant being in the process of removal. As a result, a flow of 10 wt. %, subjected to decontamination, was isolated from the total volume of construction and demolition waste (C&D waste). The considered approach allowed using the resource potential of more than 80wt. % of waste and minimizing the disposed waste volume.

FELIX: construction and testing of a facility to study electromagnetic effects for first wall, blanket, and shield systems

International Nuclear Information System (INIS)

Praeg, W.F.; Turner, L.R.; Biggs, J.A.; Knott, M.J.; Lari, R.J.; McGhee, D.G.; Wehrle, R.B.

1983-01-01

An experimental test facility for the study of electromagnetic effects in the FWBS systems of fusion reactors has been constructed over the past 1-1/2 years at Argonne National Laboratory (ANL). In a test volume of 0.76 m 3 a vertical pulsed 0.5 T dipole field (B < 50 T/s) is perpendicular to a 1 T solenoid field. Power supplies of 2.75 MW and 5.5 MW and a solid state switch rated 13 kV, 13.1 kA (170 MW) control the pulsed magnetic fields. The total stored energy in the coils is 2.13 MJ. The coils are designed for a future upgrade to 4 T or the solenoid and 1 T for the dipole field (a total of 23.7 MJ). This paper describes the design and construction features of the facility. These include the power supplies, the solid state switches, winding and impregnation of large dipole saddle coils, control of the magnetic forces, computer control of FELIX and of experimental data acquisition and analysis, and an initial experimental test setup to analyze the eddy current distribution in a flat disk

FELIX: Construction and testing of a facility to study electromagnetic effects for First Wall, Blanket, and Shield systems

International Nuclear Information System (INIS)

Praeg, W.F.; Biggs, J.; Knott, M.J.; Lari, R.J.; McGhee, D.G.; Turner, L.R.; Wehrle, R.

1983-01-01

An experimental test facility for the study of electromagnetic effects in the FWBS systems of fusion reactors has been constructed over the past 2-1/2 years at Argonne National Laboratory (ANL). In a test volume of 0.76 m 3 a vertical pulsed 0.5 T dipole field (B < 50 T/s) is perpendicular to a 1 T solenoid field. Power supplies of 2.75 MW and 5.5 MW and a solid state switch rated 13 kV, 13.1 kA (170 MW) control the pulsed magnetic fields. The total stored energy in the coils is 2.13 MJ. The coils are designed for a future upgrade to 4 T for the solenoid and 1 T for the dipole field (a total of 23.7 MJ). This paper describes the design and construction features of the facility. These include the power supplies, the solid state switches, winding and impregnation of large dipole saddle coils, control of the magnetic forces, computer control of FELIX and of experimental data acquisition and analysis, and an initial experimental test setup to analyze the eddy current distribution in a flat disk

Safety analysis report for the Cold Vacuum Drying Facility, phase 1, supporting civil/structural construction

International Nuclear Information System (INIS)

Pili-Vincens, C.

1997-01-01

The US Department of Energy established the K Basins Spent Nuclear Fuel Project to address safety and environmental concerns associated with deteriorating spent nuclear fuel presently stored under water in the Hanford Site's K Basins, which are located near the Columbia River. Recommendations for a series of aggressive projects to construct and operate systems and facilities to manage the safe removal of K Basins fuel were made in WHC-EP-0830, Hanford Spent Nuclear Fuel Recommended Path Forward,' and its subsequent update, WHC-SD-SNF-SP-005, Hanford Spent Nuclear Fuel Project Integrated Process Strategy for K Basins Fuel. The integrated process strategy recommendations include the following process steps: fuel preparation activities at the K Basins, including removing the fuel elements from their K Basin canisters, separating fuel particulate from fuel elements and fuel fragments greater than 0.6 cm (0.25 in.) in any dimension, removing excess sludge from the fuel and fuel fragments by means of flushing, as necessary, and packaging the fuel into multicanister overpacks; removal of free water by draining and vacuum drying at the Cold Vacuum Drying Facility (CVDF), a new facility in the 100 K Area of the Hanford Site. This report is contains the safety analysis for the Cold Vacuum Drying Facility, Phase 1

14 CFR 1251.302 - New construction.

Science.gov (United States)

2010-01-01

... 14 Aeronautics and Space 5 2010-01-01 2010-01-01 false New construction. 1251.302 Section 1251.302... Accessibility § 1251.302 New construction. (a) Design and construction. Each facility or part of a facility..., if the construction (ground breaking) was commenced after the effective date of this part. (b...

34 CFR 104.23 - New construction.

Science.gov (United States)

2010-07-01

... 34 Education 1 2010-07-01 2010-07-01 false New construction. 104.23 Section 104.23 Education... Accessibility § 104.23 New construction. (a) Design and construction. Each facility or part of a facility..., if the construction was commenced after the effective date of this part. (b) Alteration. Each...

Construction of BIM-based SMART-ITL Facility Management System

International Nuclear Information System (INIS)

Jeon, Woo-Jin; Yi, Sung-Jae; Park, Hyun-Sik; Ryu, Sung-Uk; Bae, Hwang; Hwang, Sang-Chul; Min, Byung-Eui

2015-01-01

The flow area and volume are scaled down to 1/49. The ratio of the hydraulic diameter is 1/7. Therefore, SMART-ITL is a large-scale thermalhydraulic test facility with about 45 m height, which is consisted of 10 m underground and 35 m from the ground level. Until now, the management of design data and maintenance of large scale test facilities have been managed based on hard-copy information. Recently, Thermal Hydraulics Safety Research Division (THSRD) at Korea Atomic Energy Research Institute (KAERI) has developed Facility Management System (FMS) based Building Information Modeling (BIM) to manage its design data more effectively for these large scale test facilities of SMART-ITL and ATLAS, and this BIM technology has been applied to SMART-ITL at the first. This study proposed a method of effective management and maintenance of design data applied to the SMART-ITL. That is, a FMS was developed based on the BIM technology for SMART-ITL. Figure 2 shows an overview of FMS development process based on BIM technology. SMART-ITL FMS facilitates its management and maintenance more effectively and accurately by 3- dimensional visualization. It enables the shape information of large scale test facilities to be visualized intuitively in a virtual space, and the efficient maintenance of data and instruments is possible by linking 3D shape information

Construction of BIM-based SMART-ITL Facility Management System

Energy Technology Data Exchange (ETDEWEB)

Jeon, Woo-Jin; Yi, Sung-Jae; Park, Hyun-Sik; Ryu, Sung-Uk; Bae, Hwang [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of); Hwang, Sang-Chul; Min, Byung-Eui [DDRsoft Co., Daejeon (Korea, Republic of)

2015-10-15

The flow area and volume are scaled down to 1/49. The ratio of the hydraulic diameter is 1/7. Therefore, SMART-ITL is a large-scale thermalhydraulic test facility with about 45 m height, which is consisted of 10 m underground and 35 m from the ground level. Until now, the management of design data and maintenance of large scale test facilities have been managed based on hard-copy information. Recently, Thermal Hydraulics Safety Research Division (THSRD) at Korea Atomic Energy Research Institute (KAERI) has developed Facility Management System (FMS) based Building Information Modeling (BIM) to manage its design data more effectively for these large scale test facilities of SMART-ITL and ATLAS, and this BIM technology has been applied to SMART-ITL at the first. This study proposed a method of effective management and maintenance of design data applied to the SMART-ITL. That is, a FMS was developed based on the BIM technology for SMART-ITL. Figure 2 shows an overview of FMS development process based on BIM technology. SMART-ITL FMS facilitates its management and maintenance more effectively and accurately by 3- dimensional visualization. It enables the shape information of large scale test facilities to be visualized intuitively in a virtual space, and the efficient maintenance of data and instruments is possible by linking 3D shape information.

Review of the Tritium Extraction Facility design

International Nuclear Information System (INIS)

Barton, R.W.; Bamdad, F.; Blackman, J.

2000-01-01

The Defense Nuclear Facilities Safety Board (DNFSB) is an independent executive branch agency responsible for technical safety oversight of the US Department of Energy's (DOE's) defense nuclear facilities. One of DNFSB's responsibilities is the review of design and construction projects for DOE's defense nuclear facilities to ensure that adequate health and safety requirements are identified and implemented. These reviews are performed with the expectation that facility designs are being developed within the framework of a site's Integrated Safety Management (ISM) program. This paper describes the application of ISM principles in DNFSB's ongoing review of the Tritium Extraction Facility (TEF) design/construction project

Review of the Tritium Extraction Facility Design

International Nuclear Information System (INIS)

Ronald W. Barton; Farid Bamdad; Joel Blackman

2000-01-01

The Defense Nuclear Facilities Safety Board (DNFSB) is an independent executive branch agency responsible for technical safety oversight of the U.S. Department of Energy's (DOE's) defense nuclear facilities. One of DNFSB's responsibilities is the review of design and construction projects for DOE's defense nuclear facilities to ensure that adequate health and safety requirements are identified and implemented. These reviews are performed with the expectation that facility designs are being developed within the framework of a site's Integrated Safety Management (ISM) program. This paper describes the application of ISM principles in DNFSB's ongoing review of the Tritium Extraction Facility (TEF) design/construction project

Effects of wind-energy facilities on grassland bird distributions

Science.gov (United States)

Shaffer, Jill A.; Buhl, Deb

2016-01-01

The contribution of renewable energy to meet worldwide demand continues to grow. Wind energy is one of the fastest growing renewable sectors, but new wind facilities are often placed in prime wildlife habitat. Long-term studies that incorporate a rigorous statistical design to evaluate the effects of wind facilities on wildlife are rare. We conducted a before-after-control-impact (BACI) assessment to determine if wind facilities placed in native mixed-grass prairies displaced breeding grassland birds. During 2003–2012, we monitored changes in bird density in 3 study areas in North Dakota and South Dakota (U.S.A.). We examined whether displacement or attraction occurred 1 year after construction (immediate effect) and the average displacement or attraction 2–5 years after construction (delayed effect). We tested for these effects overall and within distance bands of 100, 200, 300, and >300 m from turbines. We observed displacement for 7 of 9 species. One species was unaffected by wind facilities and one species exhibited attraction. Displacement and attraction generally occurred within 100 m and often extended up to 300 m. In a few instances, displacement extended beyond 300 m. Displacement and attraction occurred 1 year after construction and persisted at least 5 years. Our research provides a framework for applying a BACI design to displacement studies and highlights the erroneous conclusions that can be made without the benefit of adopting such a design. More broadly, species-specific behaviors can be used to inform management decisions about turbine placement and the potential impact to individual species. Additionally, the avoidance distance metrics we estimated can facilitate future development of models evaluating impacts of wind facilities under differing land-use scenarios.

The search for charged-lepton specific forces and the PEGASYS facility

International Nuclear Information System (INIS)

Perl, M.L.

1989-02-01

This paper discusses the electroproduction of lepton pairs as a method of searching for a charged-lepton specific force, and as a general method of searching for deviations from conventional quantum electrodynamics. The use of the PEGASYS facility for these purposes is briefly described. Search possibilities in other energy ranges are noted. 22 refs., 11 figs

Massachusetts Large Blade Test Facility Final Report

Energy Technology Data Exchange (ETDEWEB)

Rahul Yarala; Rob Priore

2011-09-02

Project Objective: The Massachusetts Clean Energy Center (CEC) will design, construct, and ultimately have responsibility for the operation of the Large Wind Turbine Blade Test Facility, which is an advanced blade testing facility capable of testing wind turbine blades up to at least 90 meters in length on three test stands. Background: Wind turbine blade testing is required to meet international design standards, and is a critical factor in maintaining high levels of reliability and mitigating the technical and financial risk of deploying massproduced wind turbine models. Testing is also needed to identify specific blade design issues that may contribute to reduced wind turbine reliability and performance. Testing is also required to optimize aerodynamics, structural performance, encourage new technologies and materials development making wind even more competitive. The objective of this project is to accelerate the design and construction of a large wind blade testing facility capable of testing blades with minimum queue times at a reasonable cost. This testing facility will encourage and provide the opportunity for the U.S wind industry to conduct more rigorous testing of blades to improve wind turbine reliability.

22 CFR 142.17 - New construction.

Science.gov (United States)

2010-04-01

... 22 Foreign Relations 1 2010-04-01 2010-04-01 false New construction. 142.17 Section 142.17 Foreign... ACTIVITIES RECEIVING FEDERAL FINANCIAL ASSISTANCE Accessibility § 142.17 New construction. (a) Design and construction. Each facility or part of a facility constructed by, on behalf of, or for the use of a recipient...

22 CFR 217.23 - New construction.

Science.gov (United States)

2010-04-01

... 22 Foreign Relations 1 2010-04-01 2010-04-01 false New construction. 217.23 Section 217.23 Foreign... ACTIVITIES RECEIVING FEDERAL FINANCIAL ASSISTANCE Accessibility § 217.23 New construction. (a) Design and construction. Each facility or part of a facility constructed by, on behalf of, or for the use of a recipient...

Concrete structures for nuclear facilities

International Nuclear Information System (INIS)

1996-01-01

The detailed requirements for the design and fabrication of the concrete structures for nuclear facilities and for the documents to be submitted to the Finnish Centre for Radiation and Nuclear Safety (STUK) are given in the guide. It also sets the requirements for the inspection of concrete structures during the construction and operation of facilities. The requirements of the guide primarily apply to new construction. As regards the repair and modification of nuclear facilities built before its publication, the guide is followed to the extent appropriate. The regulatory activities of the Finnish Centre for Radiation and Nuclear Safety during a nuclear facility's licence application review and during the construction and operation of the facility are summarised in the guide YVL 1.1

45 CFR 605.23 - New construction.

Science.gov (United States)

2010-10-01

... 45 Public Welfare 3 2010-10-01 2010-10-01 false New construction. 605.23 Section 605.23 Public... Accessibility § 605.23 New construction. (a) Design and construction. Each facility or part of a facility... persons, if the construction was commenced after the effective date of this part. (b) Alteration. Each...

Management of construction safety at KKNPP site

International Nuclear Information System (INIS)

Khare, P.K.

2016-01-01

Construction is considered as one of the most hazardous activities owing to the number of accidents and injuries. At KKNPP, management of industrial safety has been envisaged since the preliminary stage of construction planning, including design aspects. The governing principles of safety management are evolved from the Factories Act, 1948, the Atomic Energy(Factories) Rules, 1996, AERB safety guidelines on Control of works (2011) and Corporate HSE policy of NPCIL (2014). Numerous risk assessment and hazard control measures are adopted consistently to ensure a safe work environment during the construction, which includes Job Hazard Analysis, work permit through Computerized Maintenance Management System, safety procedures, exclusive safety training facility for the contractor's workmen, safety motivational measures, safety surveillance and reporting through Safety Related Deficiencies Management System. Assessment of efficacy of safety management system is continuously done through safety audits and observations are being circulated and discussed in committee meetings. Fire safety is also being taken care of since inception of project work. Well-equipped fire station with trained fire fighters was made available since the beginning as per AERB safety standard on fire protection system for Nuclear facilities. Fire prevention measures specific to the work are implemented during all activities. (author)

7 CFR 1717.605 - Design standards, plans and specifications, construction standards, and RUS accepted materials.

Science.gov (United States)

2010-01-01

..., construction standards, and RUS accepted materials. 1717.605 Section 1717.605 Agriculture Regulations of the... standards, plans and specifications, construction standards, and RUS accepted materials. All borrowers... system design, construction standards, and the use of RUS accepted materials. Borrowers must comply with...

ENVIRONMENTAL SAMPLING USING LOCATION SPECIFIC AIR MONITORING IN BULK HANDLING FACILITIES

Energy Technology Data Exchange (ETDEWEB)

Sexton, L.; Hanks, D.; Degange, J.; Brant, H.; Hall, G.; Cable-Dunlap, P.; Anderson, B.

2011-06-07

Since the introduction of safeguards strengthening measures approved by the International Atomic Energy Agency (IAEA) Board of Governors (1992-1997), international nuclear safeguards inspectors have been able to utilize environmental sampling (ES) (e.g. deposited particulates, air, water, vegetation, sediments, soil and biota) in their safeguarding approaches at bulk uranium/plutonium handling facilities. Enhancements of environmental sampling techniques used by the IAEA in drawing conclusions concerning the absence of undeclared nuclear materials or activities will soon be able to take advantage of a recent step change improvement in the gathering and analysis of air samples at these facilities. Location specific air monitoring feasibility tests have been performed with excellent results in determining attribute and isotopic composition of chemical elements present in an actual test-bed sample. Isotopic analysis of collected particles from an Aerosol Contaminant Extractor (ACE) collection, was performed with the standard bulk sampling protocol used throughout the IAEA network of analytical laboratories (NWAL). The results yielded bulk isotopic values expected for the operations. Advanced designs of air monitoring instruments such as the ACE may be used in gas centrifuge enrichment plants (GCEP) to detect the production of highly enriched uranium (HEU) or enrichments not declared by a State. Researchers at Savannah River National Laboratory in collaboration with Oak Ridge National Laboratory are developing the next generation of ES equipment for air grab and constant samples that could become an important addition to the international nuclear safeguards inspector's toolkit. Location specific air monitoring to be used to establish a baseline environmental signature of a particular facility employed for comparison of consistencies in declared operations will be described in this paper. Implementation of air monitoring will be contrasted against the use of smear

Methodology and resources for the evaluation of the construction of knowledge about the concept of density and specific mass

OpenAIRE

Tânia Inácio de Oliveira; Nádia Vilela Pereira; Cláudio Boghi; Juliano Schimiguel; Dorlivete Moreira Shitsuka

2017-01-01

Abstract: The teaching of physics concepts involves the construction of knowledge in the students' minds. The aim of this article is to present a case report of teaching density and specific mass concepts in high school technical education classes. The study analyzes the results of the construction of methodology and development of a product so that teachers of Physics can give their students the construction of the concept of density of objects and the specific mass of the substances and per...

Adaptation of the ITER facility design to a Canadian site

International Nuclear Information System (INIS)

Smith, S.

2001-01-01

This paper presents the status of Canadian efforts to adapt the newly revised ITER facility design to suit the specific characteristics of the proposed Canadian site located in Clarington, west of Toronto, Ontario. ITER Canada formed a site-specific design team in 1999, comprising participants from three Canadian consulting companies to undertake this work. The technical aspects of this design activity includes: construction planning, geotechnical investigations, plant layout, heat sink design, electrical system interface, site-specific modifications and tie-ins, seismic design, and radwaste management. These areas are each addressed in this paper. (author)

Review of the Design, Construction, and Coming Scientific Capabilities of the New Arecibo HF Facility

Science.gov (United States)

Sulzer, M. P.

2010-12-01

complete power system for planetary radar, the HF facility, and site backup. Design of the mesh is complete and the construction phase has started. One of the tower base concrete pads will sit on ground that is softer than expected and this pad is being designed by the engineering firm Amman and Whitney. The other five use the standard design provided by the tower manufacturer. Amman and Whitney are also reviewing the mesh support design and have recommended some changes in the cable support system in order to provide better temperature stability. As the project construction is completed in the next few months, we face the problems of producing a practical scientific facility. This facility is inherently a lot less complicated than the HAARP facility in Alaska. Nonetheless, a computer control and monitoring system is very desirable, both to allow the most complete control over the transmitted waveforms, and to allow the highest reliability of operation. We are currently reviewing the best ways to accomplish this. We expect that a basic system will be in place for the first couple of operational campaigns, with full flexibility coming later. The basic operation would be similar to our previous facility at Islote, vertical operation with continuous wave or a simple pulse sequence on a single frequency.

ERDA test facilities, East Mesa Test Site. Geothermal resource investigations, Imperial Valley, California

Energy Technology Data Exchange (ETDEWEB)

1976-01-01

Detailed specifications which must be complied with in the construction of the ERDA Test Facilities at the East Mesa Site for geothermal resource investigations in Imperial Valley, California are presented for use by prospective bidders for the construction contract. The principle construction work includes a 700 gpm cooling tower with its associated supports and equipment, pipelines from wells, electrical equipment, and all earthwork. (LCL)

Opening and construction of facilities in succession for particle beam therapy of cancer

International Nuclear Information System (INIS)

Nakano, Takashi; Yamamoto, Kazutaka; Hishikawa, Yoshio; Totoki, Tadahide; Hoshino, Junichi; Aoki, Takashi; Yoshiyuki, Takeshi; Hirabayashi, Masayuki; Nakamura, Fumito

2011-01-01

This feature article describes the current state of practical particle beam therapy of cancer, its future prospect, recent opening/construction of its facilities and manufacturers' view with following 9 topics presented by relevant experts. Gunma University (topic 1) started the carbon ion therapy from Mar., 2010, and has treated more than 100 cancer patients to aim the treatment of about 600 patients/year after several years. Fukui Prefectural Hospital Proton Therapy Center (topic 2) started from this March with proton beams for patients with its therapeutic standard, in cooperation with insurance companies and hotels for patients' convenience. Medipolis Proton Therapy and Research Center (Kagoshima Pref.) (topic 3) started this year with proton beams for 13 patients hitherto with reference protocol of Hyogo Ion Beam Medical Center. A new stereotactic irradiation system of proton beams for breast cancer has been developed. Construction of Saga Heavy Ion Medical Accelerator in Tosu (Saga Pref.) (topic 4) began this year to be completed in 2013. Aizawa Hospital (Nagano Pref.) (topic 5) plans to introduce the small-sized proton accelerator-gantry system (Sumitomo Heavy Ind., Ltd.) aiming the practice in 2013. Association for Nuclear Technology in Medicine (topic 6) reports the trends of current and future construction inside/outside Japan. Manufacturers comment their respective business: high-speed scanning irradiation system, next generation handling system of patient and particle beam therapy information system by Toshiba (topic 7); designation of the whole heavy ion beam therapy system (with NIRS), proton beam (as in topic 5) and system of BNCT (boron neutron-capture therapy) (Kyoto Univ.) by Sumitomo Heavy Ind., Ltd. (topic 8); and small-size proton therapeutic machine with 4D tracing capability for patient's movement (Hokkaido Univ.) and with spot-scanning irradiation technique by Hitachi (topic 9). (author)

Status on the construction of the fuel irradiation test facility

International Nuclear Information System (INIS)

Park, Kook Nam; Sim, Bong Shick; Lee, Chung Young; Yoo, Seong Yeon

2005-01-01

As a facility to examine general performance of nuclear fuel under irradiation condition in HANARO, Fuel Test Loop(FTL) has been developed which can accommodate 3 fuel pins at the core irradiation hole(IR1 hole) taking consideration user's test requirement. 3-Pin FTL consists of In-Pile Test Section (IPS) and Out-of- Pile System (OPS). Test condition in IPS such as pressure, temperature and the water quality, can be controlled by OPS. 3-Pin FTL Conceptual design was set up in 2001 and had completed detail design including a design requirement and basic Piping and Instrument Diagram (P and ID) in 2004. The safety analysis report was prepared and submitted in early 2005 to the regulatory body(KINS) for review and approval of FTL. In 2005, the development team is going to purchase and manufacture hardware and make a contract for construction work. In 2006, the development team is going to install an FTL system performance test shall be done as a part of commissioning. After a 3-Pin FTL development which is expected to be finished by the 2007, FTL will be used for the irradiation test of the new PWR-type fuel and the usage of HANARO will be enhanced

Construction safety program for the National Ignition Facility

International Nuclear Information System (INIS)

Cerruti, S.J.

1997-01-01

The Construction Safety Program (CSP) for NIF sets forth the responsibilities, guidelines, rules, policies and regulations for all workers involved in the construction, special equipment installation, acceptance testing, and initial activation and operation of NIF at LLNL during the construction period of NIF. During this period, all workers are required to implement measures to create a universal awareness which promotes safe practice at the work site, and which will achieve NIF's management objectives in preventing accidents and illnesses. Construction safety for NIF is predicated on everyone performing their jobs in a manner which prevents job-related disabling injuries and illnesses. The CSP outlines the minimum environment, safety, and health (ES ampersand H) standards, LLNL policies and the Construction Industry Institute (CII) Zero Injury Techniques requirements that all workers at the NIF construction site shall adhere to during the construction period of NIF. It identifies the safety requirements which the NIF organizational Elements, construction contractors and construction subcontractors must include in their safety plans for the construction period of NIF, and presents safety protocols and guidelines which workers shall follow to assure a safe and healthful work environment. The CSP also identifies the ES ampersand H responsibilities of LLNL employees, non-LLNL employees, construction contractors, construction subcontractors, and various levels of management within the NIF Program at LLNL. In addition, the CSP contains the responsibilities and functions of ES ampersand H support organizations and administrative groups, and describes their interactions with the NIF Program

Construction safety program for the National Ignition Facility

Energy Technology Data Exchange (ETDEWEB)

Cerruti, S.J.

1997-01-01

The Construction Safety Program (CSP) for NIF sets forth the responsibilities, guidelines, rules, policies and regulations for all workers involved in the construction, special equipment installation, acceptance testing, and initial activation and operation of NIF at LLNL during the construction period of NIF. During this period, all workers are required to implement measures to create a universal awareness which promotes safe practice at the work site, and which will achieve NIF`s management objectives in preventing accidents and illnesses. Construction safety for NIF is predicated on everyone performing their jobs in a manner which prevents job-related disabling injuries and illnesses. The CSP outlines the minimum environment, safety, and health (ES&H) standards, LLNL policies and the Construction Industry Institute (CII) Zero Injury Techniques requirements that all workers at the NIF construction site shall adhere to during the construction period of NIF. It identifies the safety requirements which the NIF organizational Elements, construction contractors and construction subcontractors must include in their safety plans for the construction period of NIF, and presents safety protocols and guidelines which workers shall follow to assure a safe and healthful work environment. The CSP also identifies the ES&H responsibilities of LLNL employees, non-LLNL employees, construction contractors, construction subcontractors, and various levels of management within the NIF Program at LLNL. In addition, the CSP contains the responsibilities and functions of ES&H support organizations and administrative groups, and describes their interactions with the NIF Program.

Facile construction of terpridine-based metallo-polymers in hydrogels, crystals and solutions directed by metal ions.

Science.gov (United States)

Li, Yajuan; Guo, Jiangbo; Dai, Bo; Geng, Lijun; Shen, Fengjuan; Zhang, Yajun; Yu, Xudong

2018-07-01

Driven by tunable metal-ligand interactions, a polydentate ligand TC containing terpyridine and carboxylic acid units was developed to construct metallo-polymers that showed multiple aggregation modes with controlled macroscopic properties. In the presence of different kind of Zn 2+ ions or NaOH, TC could form metallo-polymers via π-π stacking and metal-ligand interaction that further trapped water molecules, resulting in hydrogels and crystals. Moreover, these TC/Zn 2+ hydrogels could transform to soluble and fluorescent aggregates in the presence of NaOH due to the formation of binuclear metallo-polymers with enhanced ICT emission. The metal-ligand interactions tuned by different metal salts in gels, crystals, and sols were also studied and illustrated in detail, it was also proved that water was an essential linker for constructing Na + -based metallo-polymers from the TC/NaOH crystal data. This work demonstrated the engineered coordination pathways in generating controllable hydrogels and metallo-polymers for the first time, which led to novel approach for facilely constructing a number of hydrogels with tailorable macroscopic properties. Copyright © 2018 Elsevier Inc. All rights reserved.

Design of the disposal facility 2012

International Nuclear Information System (INIS)

Saanio, T.; Ikonen, A.; Keto, P.; Kirkkomaeki, T.; Kukkola, T.; Nieminen, J.; Raiko, H.

2013-11-01

The spent nuclear fuel accumulated from the nuclear power plants in Olkiluoto in Eurajoki and in Haestholmen in Loviisa will be disposed of in Olkiluoto. A facility complex will be constructed at Olkiluoto, and it will include two nuclear waste facilities according to Government Degree 736/2008. The nuclear waste facilities are an encapsulation plant, constructed to encapsulate spent nuclear fuel and a disposal facility consisting of an underground repository and other underground rooms and above ground service spaces. The repository is planned to be excavated to a depth of 400 - 450 meters. Access routes to the disposal facility are an inclined access tunnel and vertical shafts. The encapsulated fuel is transferred to the disposal facility in the canister lift. The canisters are transferred from the technical rooms to the disposal area via central tunnel and deposited in the deposition holes which are bored in the floors of the deposition tunnels and are lined beforehand with compacted bentonite blocks. Two parallel central tunnels connect all the deposition tunnels and these central tunnels are inter-connected at regular intervals. The solution improves the fire safety of the underground rooms and allows flexible backfilling and closing of the deposition tunnels in stages during the operational phase of the repository. An underground rock characterization facility, ONKALO, is excavated at the disposal level. ONKALO is designed and constructed so that it can later serve as part of the repository. The goal is that the first part of the disposal facility will be constructed under the building permit phase in the 2010's and operations will start in the 2020's. The fuel from 4 operating reactors as well the fuel from the fifth nuclear power plant under construction, has been taken into account in designing the disposal facility. According to the information from TVO and Fortum, the amount of the spent nuclear fuel is 5,440 tU. The disposal facility is being excavated

Excavation of shafts and research galleries at the Mizunami Underground Research Laboratory. Construction work of MIU part 4. Construction progress report, fiscal year 2010-2011

International Nuclear Information System (INIS)

2014-11-01

This progress report presents an outline compilation of construction activities, primary tasks performed, construction progress and safety patrol report, in fiscal year 2010-2011. The outline of construction activities is a summary based on the scope of work planned in 2010-2011: the main activities are based on the Tono Geoscience Center weekly reports; and the construction progress is based on the planned and actual schedules. The safety patrol report is based on defects recording by the safety manager of the Geoscience Facility Construction Section. Regarding the plan and actual performance of the construction work of MIU part IV (March 16, 2010 - March 15, 2012) performance carried out from April 1, 2010 until March 15, 2012 is described in this report. The attached appendices have been provided: regarding content in the excavated material bellowing the environmental standards, technical specifications of fiscal year 2010-2011 in construction work of MIU part IV, also photos of construction activities. (author)

Notification: EPA Region 10 Management Controls Over Allowing Substantial Public Funds to Construct the Spokane County Wastewater Treatment Facility

Science.gov (United States)

January 20, 2012. This EPA's OIG is initiating a review from an OIG hotline complaint regarding whether federal funds were properly used to construct the new Spokane County wastewater treatment facility in accordance with 40 CFR 35, Subpart K.

Robins Air Force Base Solar Cogeneration Facility design

Energy Technology Data Exchange (ETDEWEB)

Pierce, B.L.; Bodenschatz, C.A.

1982-06-01

A conceptual design and a cost estimate have been developed for a Solar Cogeneration Facility at Robins Air Force Base. This demonstration solar facility was designed to generate and deliver electrical power and process steam to the existing base distribution systems. The facility was to have the potential for construction and operation by 1986 and make use of existing technology. Specific objectives during the DOE funded conceptual design program were to: prepare a Solar Cogeneration Facility (overall System) Specification, select a preferred configuration and develop a conceptual design, establish the performance and economic characteristics of the facility, and prepare a development plan for the demonstration program. The Westinghouse team, comprised of the Westinghouse Advanced Energy Systems Division, Heery and Heery, Inc., and Foster Wheeler Solar Development Corporation, in conjunction with the U.S. Air Force Logistics Command and Georgia Power Company, has selected a conceptual design for the facility that will utilize the latest DOE central receiver technology, effectively utilize the energy collected in the application, operate base-loaded every sunny day of the year, and be applicable to a large number of military and industrial facilities throughout the country. The design of the facility incorporates the use of a Collector System, a Receiver System, an Electrical Power Generating System, a Balance of Facility - Steam and Feedwater System, and a Master Control System.

Indigenous Construction Materials for Theater Facilities

Science.gov (United States)

2013-09-01

is shown as a step-by-step plan in Figure 1. ERDC TR-13-13 5 Figure 1. Infrastructure planning. The pyramid can be initially divided into two...disadvantages in terms of constructability, structural integrity, environmental impact, and sociocultural impacts. The lower portions of the pyramid ...United States or the Nile in Sudan and Egypt ) is vital to the local economy and can provide a means for transport- ing such construction materials

The construction of solid waste form test and inspection facility

International Nuclear Information System (INIS)

Park, Hun Hwee; Lee, Kang Moo; Jung, In Ha; Kim, Sung Hwan; Yoo, Jeong Woo; Lee, Jong Youl; Bae, Sang Min

1988-01-01

The solid waste form test and inspection facility is a facility to test and inspect the characteristics of waste forms, such as homogenity, mechanical structure, thermal behaviour, water resistance and leachability. Such kinds of characteristics in waste forms are required to meet a certain conditions for long-term storage or for final disposal of wastes. The facility will be used to evaluate safety for the disposal of wastes by test and inspection. At this moment, the efforts to search the most effective management of the radioactive wastes generated from power plants and radioisotope user are being executed by the people related to this field. Therefore, the facility becomes more significant tool because of its guidance of sucessfully converting wastes into forms to give a credit to the safety of waste disposal for managing the radioactive wastes. In addition the overall technical standards for inspecting of waste forms such as the standardized equipment and processes in the facility will be estabilished in the begining of 1990's when the project of waste management will be on the stream. Some of the items of the project have been standardized for the purpose of localization. In future, this facility will be utilized not only for the inspection of waste forms but also for the periodic decontamination apparatus by remote operation techniques. (Author)

Governance Change In Facilities Management: An Institutional Perspectives

Directory of Open Access Journals (Sweden)

Muhammad Kaleem Zahirul Hassan

2012-12-01

Full Text Available Governance of a specific field is shaped by not only the instrumental rationality but also the institutional rationality. In this research the instrumental rationality was manifested by the service providers and consultants who played a pivotal role in the construction of new governance in the field of facilities services in the Netherlands. Further, the role of institutional rationality was investigated wherein it was found that the logic of rationalization shaped the governance in the field of facilities services. Moreover, the implication for the explanation of practice variation by institutional theory is discussed.

Ecological studies related to the construction of the Defense Waste Processing Facility on the Savannah River Site

International Nuclear Information System (INIS)

Scott, D.E.; Chazel, A.C.; Pechmann, J.H.K.; Estes, R.A.

1993-06-01

The Defense Waste Processing Facility (DWPF) was built on the Savannah River Site (SRS) during the mid-1980's. The Savannah River Ecology Laboratory (SREL) has completed 14 years of ecological studies related to the construction of the DWPF complex. Prior to construction, the 600-acre site (S-Area) contained a Carolina bay and the headwaters of a stream. Research conducted by the SREL has focused primarily on four questions related to these wetlands: (1) Prior to construction, what fauna and flora were present at the DWPF site and at similar, yet undisturbed, alternative sites? (2) By comparing the Carolina bay at the DWPF site (Sun Bay) with an undisturbed control Carolina bay (Rainbow Bay), what effect is construction having on the organisms that inhabited the DWPF site? (3) By comparing control streams with streams on the periphery of the DWPF site, what effect is construction having on the peripheral streams? (4) How effective have efforts been to lessen the impacts of construction, both with respect to erosion control measures and the construction of ''refuge ponds'' as alternative breeding sites for amphibians that formerly bred at Sun Bay? Through the long-term census-taking of biota at the DWPF site and Rainbow Bay, SREL has begun to evaluate the impact of construction on the biota and the effectiveness of mitigation efforts. Similarly, the effects of erosion from the DWPF site on the water quality of S-Area peripheral streams are being assessed. This research provides supporting data relevant to the National Environmental Policy Act (NEPA) of 1969, the Endangered Species Act of 1973, Executive Orders 11988 (Floodplain Management) and 11990 (Protection of Wetlands), and United States Department of Energy (DOE) Guidelines for Compliance with Floodplain/Wetland Environmental Review Requirements (10 CFR 1022)

Radioactive Air Emmission Notice of Construction (NOC) Application for the Waste Receiving and Processing Facility (WRAP)

International Nuclear Information System (INIS)

MENARD, N.M.

2000-01-01

This document serves as a notice of construction (NOC) pursuant to the requirements of Washington Administrative Code (WAC) 246-247-060, and as a request for approval to modify pursuant to 40 Code of Federal Regulations (CFR) 61.07 for the Waste Receiving and Processing (WRAP) Facility. The rewrite of this NOC incorporates all the approved revisions (Sections 5.0, 6.0, 8.0, and 9.0), a revised potential to emit (PTE) based on the revised maximally exposed individual (MEI) (Sections 8.0, 10.0, 11.0, 12.0, 13.0, 14.0, and 15.0), the results of a study on fugitive emissions (Sections 6.0, 10.0, and 15.0), and reflects the current operating conditions at the WRAP Facility (Section 5.0). This NOC replaces DOE/RL-93-15 and DOE/RL-93-16 in their entirety. The primary function of the WRAP Facility is to examine, assay, characterize, treat, verify, and repackage radioactive material and mixed waste. There are two sources of emissions from the WRAP Facility: stack emissions and fugitive emissions. The stack emissions have an unabated total effective dose equivalent (TEDE) estimate to the hypothetical offsite MEI of 1.13 E+02 millirem per year. The abated TEDE for the stack emissions is estimated at 5.63 E-02 millirem per year to the MEI. The fugitive emissions have an unabated TEDE estimate to the hypothetical offsite MEI of 5.87 E-04. There is no abatement for the fugitive emissions

Baseline concentrations of radionuclides and heavy metals in soils and vegetation around the DARHT facility: Construction phase (1997). Progress report

International Nuclear Information System (INIS)

Fresquez, P.R.; Haagenstad, H.T.; Naranjo, L. Jr.

1998-06-01

As part of the Department of Energy's Mitigation Action Plan for the Dual Axis Radiographic Hydrodynamic Test (DARHT) facility at Los Alamos National Laboratory (LANL), baseline concentrations of radionuclides ( 3 H, 137 Cs, 90 Sr, 238 Pu, 239,240 Pu, 241 Am, and tot U) and heavy metals (Ag, As, Ba, Be, Cd, Cr, Cu, Hg, Ni, Pb, Sb, Se, and Tl) in soil, sediment, and vegetation (overstory and understory) around the DARHT facility during the construction phase in 1997 were determined. Most radionuclides and heavy metals in soils, sediments, and vegetation, with the exception of 90 Sr in soils and sediments, were within upper (95%) limit background concentrations. Although the levels of 90 Sr in soils and sediments around the DARHT facility were higher than background, they were below LANL screening action levels ( -1 dry) and are of no concern

Validation of temporal and spatial consistency of facility- and speed-specific vehicle-specific power distributions for emission estimation: A case study in Beijing, China.

Science.gov (United States)

Zhai, Zhiqiang; Song, Guohua; Lu, Hongyu; He, Weinan; Yu, Lei

2017-09-01

Vehicle-specific power (VSP) has been found to be highly correlated with vehicle emissions. It is used in many studies on emission modeling such as the MOVES (Motor Vehicle Emissions Simulator) model. The existing studies develop specific VSP distributions (or OpMode distribution in MOVES) for different road types and various average speeds to represent the vehicle operating modes on road. However, it is still not clear if the facility- and speed-specific VSP distributions are consistent temporally and spatially. For instance, is it necessary to update periodically the database of the VSP distributions in the emission model? Are the VSP distributions developed in the city central business district (CBD) area applicable to its suburb area? In this context, this study examined the temporal and spatial consistency of the facility- and speed-specific VSP distributions in Beijing. The VSP distributions in different years and in different areas are developed, based on real-world vehicle activity data. The root mean square error (RMSE) is employed to quantify the difference between the VSP distributions. The maximum differences of the VSP distributions between different years and between different areas are approximately 20% of that between different road types. The analysis of the carbon dioxide (CO 2 ) emission factor indicates that the temporal and spatial differences of the VSP distributions have no significant impact on vehicle emission estimation, with relative error of less than 3%. The temporal and spatial differences have no significant impact on the development of the facility- and speed-specific VSP distributions for the vehicle emission estimation. The database of the specific VSP distributions in the VSP-based emission models can maintain in terms of time. Thus, it is unnecessary to update the database regularly, and it is reliable to use the history vehicle activity data to forecast the emissions in the future. In one city, the areas with less data can still

Commissioning of the Winfrith Aerosol Deposition and Pipe Flow Facility (ADPFF)

International Nuclear Information System (INIS)

Ball, M.H.E.; Mitchell, J.P.; Brighton, F.R.

1991-02-01

A facility has been constructed to investigate the turbulent deposition behaviour of micron-sized particles in large pipes. These studies are designed to generate suitable data to test and develop the ATLAS code, being developed by the AEA Safety and Reliability Business, to model aerosol transport through reactor components in certain severe accident sequences. The design specification of the Aerosol Deposition and Pipe Flow Facility (ADPFF) is described, together with the basic control instrumentation and commissioning trials. A preliminary assessment of the air velocity profiles measured at a Reynolds number of 10 5 is also included. The ADPFF meets the design specification and is available for the start of the first series of experiments to study aerosol deposition behaviour. (author)

Facile preparation of 3D hierarchical coaxial-cable-like Ni-CNTs@beta-(Ni, Co) binary hydroxides for supercapacitors with ultrahigh specific capacitance.

Science.gov (United States)

Zhang, Manyu; Ma, Xiaowei; Bi, Han; Zhao, Xuebing; Wang, Chao; Zhang, Jie; Li, Yuesheng; Che, Renchao

2017-09-15

A facile chemical method for Co doping Ni-CNTs@α-Ni(OH) 2 combining with an in situ phase transformation process is successfully proposed and employed to synthesize three-dimensional (3D) hierarchical Ni-CNTs@β-(Ni, Co) binary hydroxides. This strategy can effectively maintain the coaxial-cable-like structure of Ni-CNTs@α-Ni(OH) 2 and meanwhile increase the content of Co as much as possible. Eventually, the specific capacitances and electrical conductivity of the composites are remarkably enhanced. The optimized composite exhibits high specific capacitances of 2861.8F g -1 at 1A g -1 (39.48F cm -2 at 15mAcm -2 ), good rate capabilities of 1221.8F g -1 at 20A g -1 and cycling stabilities (87.6% of capacitance retention after 5000cycles at 5A g -1 ). The asymmetric supercapacitor (ASC) constructed with the as-synthesized composite and activated carbon as positive and negative electrode delivers a high specific capacitance of 287.7F g -1 at 1A g -1 . The device demonstrates remarkable energy density (96Whkg -1 ) and high power density (15829.4Wkg -1 ). The retention of capacitance remains 83.5% at the current density of 5A g -1 after 5000cycles. The charged and discharged samples are further studied by ex situ electron energy loss spectroscopy (EELS) analysis, XRD and SEM to figure out the reasons of capacitance fading. Overall, it is believable that this facile synthetic strategy can be applied to prepare various nanostructured metal hydroxide/CNT composites for high performance supercapacitor electrode materials. Copyright © 2017. Published by Elsevier Inc.

Bulk Fuel Storage and Delivery Systems Infrastructure Military Construction Requirements for Japan

National Research Council Canada - National Science Library

Padgett, Gary

2000-01-01

.... Specifically, this audit evaluated requirements for bulk fuel storage facilities at three locations in Japan. We also evaluated the management control program as it relates to the bulk fuel storage military construction requirements validation process.

Problems of development and putting into education process an electronic textbook on special discipline 'General theory and construction of heat-and-power engineering facilities'

International Nuclear Information System (INIS)

Karitskaya, S.G.; Ruzanov, K.A.; Davletov, V.S.

2005-01-01

The results of work of making the electronic textbook of special discipline ('General theory and construction of heat-and-power engineering facilities' are brought. The principles and requirements, presented towards literature of such type, are outlined. (author)

Shallow groundwater intrusion to deeper depths caused by construction and drainage of a large underground facility. Estimation using 3H, CFCs and SF6 as trace materials

International Nuclear Information System (INIS)

Hagiwara, Hiroki; Iwatsuki, Teruki; Hasegawa, Takuma; Nakata, Kotaro; Tomioka, Yuichi

2015-01-01

This study evaluates a method to estimate shallow groundwater intrusion in and around a large underground research facility (Mizunami Underground Research Laboratory-MIU). Water chemistry, stable isotopes (δD and δ 18 O), tritium ( 3 H), chlorofluorocarbons (CFCs) and sulfur hexafluoride (SF 6 ) in groundwater were monitored around the facility (from 20 m down to a depth of 500 m), for a period of 5 years. The results show that shallow groundwater inflows into deeper groundwater at depths of between 200–400 m. In addition, the content of shallow groundwater estimated using 3 H and CFC-12 concentrations is up to a maximum of about 50%. This is interpreted as the impact on the groundwater environment caused by construction and operation of a large facility over several years. The concomitant use of 3 H and CFCs is an effective method to determine the extent of shallow groundwater inflow caused by construction of an underground facility. (author)

7 CFR 15b.19 - New construction.

Science.gov (United States)

2010-01-01

... 7 Agriculture 1 2010-01-01 2010-01-01 false New construction. 15b.19 Section 15b.19 Agriculture... ACTIVITIES RECEIVING FEDERAL FINANCIAL ASSISTANCE Accessibility § 15b.19 New construction. (a) Design and construction. Each facility or part of a facility constructed by, on behalf of, or for the use of a recipient...

41 CFR 101-8.310 - New construction.

Science.gov (United States)

2010-07-01

... 41 Public Contracts and Property Management 2 2010-07-01 2010-07-01 true New construction. 101-8... FINANCIAL ASSISTANCE 8.3-Discrimination Prohibited on the Basis of Handicap § 101-8.310 New construction. (a) Design and construction. Each facility or part of a facility constructed by, on behalf of, or for the use...

Construction and commissioning test report of the CEDM test facility

Energy Technology Data Exchange (ETDEWEB)

Chung, C. H.; Kim, J. T.; Park, W. M.; Youn, Y. J.; Jun, H. G.; Choi, N. H.; Park, J. K.; Song, C. H.; Lee, S. H.; Park, J. K

2001-02-01

The test facility for performance verification of the control element drive mechanism (CEDM) of next generation power plant was installed at the site of KAERI. The CEDM was featured a mechanism consisting of complicated mechanical parts and electromagnetic control system. Thus, a new CEDM design should go through performance verification tests prior to it's application in a reactor. The test facility can simulate the reactor operating conditions such as temperature, pressure and water quality and is equipped with a test chamber to accomodate a CEDM as installed in the power plant. This test facility can be used for the following tests; endurance test, coil cooling test, power measurement and reactivity rod drop test. The commissioning tests for the test facility were performed up to the CEDM test conditions of 320 C and 150 bar, and required water chemistry was obtained by operating the on-line water treatment system.

Construction and commissioning test report of the CEDM test facility

International Nuclear Information System (INIS)

Chung, C. H.; Kim, J. T.; Park, W. M.; Youn, Y. J.; Jun, H. G.; Choi, N. H.; Park, J. K.; Song, C. H.; Lee, S. H.; Park, J. K.

2001-02-01

The test facility for performance verification of the control element drive mechanism (CEDM) of next generation power plant was installed at the site of KAERI. The CEDM was featured a mechanism consisting of complicated mechanical parts and electromagnetic control system. Thus, a new CEDM design should go through performance verification tests prior to it's application in a reactor. The test facility can simulate the reactor operating conditions such as temperature, pressure and water quality and is equipped with a test chamber to accomodate a CEDM as installed in the power plant. This test facility can be used for the following tests; endurance test, coil cooling test, power measurement and reactivity rod drop test. The commissioning tests for the test facility were performed up to the CEDM test conditions of 320 C and 150 bar, and required water chemistry was obtained by operating the on-line water treatment system

Yucca Mountain Site Characterization Project exploratory studies facilities construction status

International Nuclear Information System (INIS)

Allan, J.N.; Leonard, T.M.

1993-01-01

This paper discusses the progress to date on the construction planning and development of the Yucca Mountain Site Characterization Project (YMP) Exploratory Studies Facilities (ESF). The purpose of the ESF is to determine early site suitability and to characterize the subsurface of the Yucca Mountain site to assess its suitability for a potential high level nuclear waste repository. The present ESF configuration concept is for two main ramps to be excavated by tunnel boring machines (TBM) from the surface to the Topopah Spring Member of the Paintbrush Tuff Formation. From the main ramps, slightly above Topopah Spring level, supplemental ramps will be penetrated to the Calico Hills formation below the potential repository. There will be exploratory development drifts driven on both levels with the Main Test Area being located on the Topopah Spring level, which is the level of the proposed repository. The Calico Hills formation lies below the Topopah Spring member and is expected to provide the main geo-hydrologic barrier between the potential repository and the underlying saturated zones in the Crater Flat Tuff

Double-shelled silicon anode nanocomposite materials: A facile approach for stabilizing electrochemical performance via interface construction

Science.gov (United States)

Du, Lulu; Wen, Zhongsheng; Wang, Guanqin; Yang, Yan-E.

2018-04-01

The rapid capacity fading induced by volumetric changes is the main issue that hinders the widespread application of silicon anode materials. Thus, double-shelled silicon composite materials where lithium silicate was located between an Nb2O5 coating layer and a silicon active core were configured to overcome the chemical compatibility issues related to silicon and oxides. The proposed composites were prepared via a facile co-precipitation method combined with calcination. Transmission electron microscopy and X-ray photoelectron spectroscopy analysis demonstrated that a transition layer of lithium silicate was constructed successfully, which effectively hindered the thermal inter-diffusion between the silicon and oxide coating layers during heat treatment. The electrochemical performance of the double-shelled silicon composites was enhanced dramatically with a retained specific capacity of 1030 mAh g-1 after 200 cycles at a current density of 200 mA g-1 compared with 598 mAh g-1 for a core-shell Si@Nb2O5 composite that lacked the interface. The lithium silicate transition layer was shown to play an important role in maintaining the high electrochemical stability.

DEVELOPMENT FEATURES OF LEASING RELATIONS IN CONSTRUCTION

Directory of Open Access Journals (Sweden)

Patimat A. Abdulkhalikova

2017-01-01

Full Text Available Abstract. Objectives Leasing, which is an alternative to traditional forms of investment for Russia, is currently among the most effective methods of financing construction organisations. Under conditions of shortage of available financial resources, leasing allows the modernisation of production to be carried out, modern equipment to be used or new production facilities to be opened in the shortest possible time. The purpose of the study is to comprehensively substantiate the specifics of leasing operations in construction and demonstrate its advantages as a tool for financing construction organisations. Methods The theoretical basis of the study was the fundamental provisions of economic, financial and management theory. During the process of research, logical, statistical and comparative analysis methods were used alongside expert evaluation and factor analysis approaches. Results For a leasing company whose purpose is to identify potential risk areas associated with the possibility of exceeding planned costs, it is recommended that a feasibility analysis be carried out prior to forming a loan portfolio. It is established that the transactions of a leasing company with a construction organisation can be presented as a separate investment project with a complex financial structure and a combination of interrelated long-term contracts. It is shown that the standardisation of principles of corporate governance and risk management is capable not only of reducing the susceptibility of a construction organisation to risk, but also of increasing the degree of trust on the part of customers and counterparties. Conclusion The expediency of using leasing in construction is due to the insufficient volume of private funds for the acquisition of equipment, which becomes particularly relevant against the background of rapidly aging facilities of construction organisations. Under conditions of largescale technical re-equipment, in which advanced