National Waterway Network (line), Geographic WGS84, BTS (2006) [usace_nav_waterway_lin_BTS_2006

Data.gov (United States)

Louisiana Geographic Information Center — The National Waterway Network is a comprehensive network database of the nation's navigable waterways. The data set covers the 48 contiguous states plus the District...

National Waterway Network (node), Geographic WGS84, BTS (2006) [usace_nav_waterway_nod_BTS_2006

Data.gov (United States)

Louisiana Geographic Information Center — The National Waterway Network is a comprehensive network database of the nation's navigable waterways. The data set covers the 48 contiguous states plus the District...

OPG waterways public safety program

Energy Technology Data Exchange (ETDEWEB)

Bennett, T [Ontario Power Generation Inc., Niagara Falls, ON (Canada)

2009-07-01

Ontario Power Generation (OPG) has 64 hydroelectric generating stations, 241 dams, and 109 dams in Ontario's registry with the International Commission on Large Dams (ICOLD). In 1986, it launched a formal dam safety program. This presentation addressed the importance of public safety around dams. The safety measures are timely because of increasing public interaction around dams; the public's unawareness of hazards; public interest in extreme sports; easier access by recreational vehicles; the perceived right of public to access sites; and the remote operation of hydroelectric stations. The presentation outlined the OPG managed system approach, with particular reference to governance; principles; standards and procedures; and aspects of implementation. Specific guidelines and governing documents for public safety around dams were identified, including guidelines for public safety of waterways; booms and buoys; audible warning devices and lights; public safety signage; fencing and barricades; and risk assessment for public safety around waterways. The presentation concluded with a discussion of audits and management reviews to determine if safety objectives and targets have been met. figs.

Digital waterway construction based on inland electronic navigation chart

Science.gov (United States)

Wang, Xue; Pan, Junfeng; Zhu, Weiwei

2015-12-01

With advantages of large capacity, long distance, low energy consumption, low cost, less land occupation and light pollution, inland waterway transportation becomes one of the most important constituents of the comprehensive transportation system and comprehensive water resources utilization in China. As one of "three elements" of navigation, waterway is the important basis for the development of water transportation and plays a key supporting role in shipping economic. The paper discuss how to realize the informatization and digitization of waterway management based on constructing an integrated system of standard inland electronic navigation chart production, waterway maintenance, navigation mark remote sensing and control, ship dynamic management, and water level remote sensing and report, which can also be the foundation of the intelligent waterway construction. Digital waterway construction is an information project and also has a practical meaning for waterway. It can not only meet the growing high assurance and security requirements for waterway, but also play a significant advantage in improving transport efficiency, reducing costs, promoting energy conservation and so on. This study lays a solid foundation on realizing intelligent waterway and building a smooth, efficient, safe, green modern inland waterway system, and must be considered as an unavoidable problem for the coordinated development between "low carbon" transportation and social economic.

Hydrology of and Current Monitoring Issues for the Chicago Area Waterway System, Northeastern Illinois

Science.gov (United States)

Duncker, James J.; Johnson, Kevin K.

2015-10-28

The Chicago Area Waterway System (CAWS) consists of a combination of natural and manmade channels that form an interconnected navigable waterway of approximately 90-plus miles in the metropolitan Chicago area of northeastern Illinois. The CAWS serves the area as the primary drainage feature, a waterway transportation corridor, and recreational waterbody. The CAWS was constructed by the Metropolitan Water Reclamation District of Greater Chicago (MWRDGC). Completion of the Chicago Sanitary and Ship Canal (initial portion of the CAWS) in 1900 breached a low drainage divide and resulted in a diversion of water from the Lake Michigan Basin. A U.S. Supreme Court decree (Consent Decree 388 U.S. 426 [1967] Modified 449 U.S. 48 [1980]) limits the annual diversion from Lake Michigan. While the State of Illinois is responsible for the diversion, the MWRDGC regulates and maintains water level and water quality within the CAWS by using several waterway control structures. The operation and control of water levels in the CAWS results in a very complex hydraulic setting characterized by highly unsteady flows. The complexity leads to unique gaging requirements and monitoring issues. This report provides a general discussion of the complex hydraulic setting within the CAWS and quantifies this information with examples of data collected at a range of flow conditions from U.S. Geological Survey streamflow gaging stations and other locations within the CAWS. Monitoring to address longstanding issues of waterway operation, as well as current (2014) emerging issues such as wastewater disinfection and the threat from aquatic invasive species, is included in the discussion.

Designing Facilities for Collaborative Operations

Science.gov (United States)

Norris, Jeffrey; Powell, Mark; Backes, Paul; Steinke, Robert; Tso, Kam; Wales, Roxana

2003-01-01

A methodology for designing operational facilities for collaboration by multiple experts has begun to take shape as an outgrowth of a project to design such facilities for scientific operations of the planned 2003 Mars Exploration Rover (MER) mission. The methodology could also be applicable to the design of military "situation rooms" and other facilities for terrestrial missions. It was recognized in this project that modern mission operations depend heavily upon the collaborative use of computers. It was further recognized that tests have shown that layout of a facility exerts a dramatic effect on the efficiency and endurance of the operations staff. The facility designs (for example, see figure) and the methodology developed during the project reflect this recognition. One element of the methodology is a metric, called effective capacity, that was created for use in evaluating proposed MER operational facilities and may also be useful for evaluating other collaboration spaces, including meeting rooms and military situation rooms. The effective capacity of a facility is defined as the number of people in the facility who can be meaningfully engaged in its operations. A person is considered to be meaningfully engaged if the person can (1) see, hear, and communicate with everyone else present; (2) see the material under discussion (typically data on a piece of paper, computer monitor, or projection screen); and (3) provide input to the product under development by the group. The effective capacity of a facility is less than the number of people that can physically fit in the facility. For example, a typical office that contains a desktop computer has an effective capacity of .4, while a small conference room that contains a projection screen has an effective capacity of around 10. Little or no benefit would be derived from allowing the number of persons in an operational facility to exceed its effective capacity: At best, the operations staff would be underutilized

33 CFR 207.100 - Inland waterway from Delaware River to Chesapeake Bay, Del. and Md. (Chesapeake and Delaware...

Science.gov (United States)

2010-07-01

... enter or pass through any part of the waterway will be contingent on the vessel's having adequate... facilities are of limited capacity, and permission to occupy them for periods exceeding 24 hours must be...

Safety And Reduce In Pollution Issues For Inland Waterway Transportation

Directory of Open Access Journals (Sweden)

Van Huong Dong

2017-04-01

Full Text Available According to the Ministry of Transport inland water transport is one of the five modes of transport in our country play a very important role. Inland waterway transport not only plays a major role in transporting large volumes of goods and passengers but also creates millions of jobs contributing to ensuring social security and national defense and security. However there are still many inadequacies in waterway transportation such as unequal waterway traffic The phenomenon of exploitation of river resources as planned or Process technology is not as planned exploitation of sand gravel etc. are common in most rivers and canals in the country. The signaling system is not synchronized between the signal of the inland waterway management unit and the signal of the owner The handling of domestic goods transportation and inland port management is inadequate The force of the means of development is fast uneven but concentrated in some urban areas and industrial parks. Therefore the Ministry of Transport has proposed a scheme to facilitate the development of a synchronized inland waterway infrastructure linking with other modes of transport To improve the capacity of the crew and the inland waterway transport crews. To create favorable conditions for inland waterway transportation business with reasonable transportation costs Improve the quality of water transport services Ensure safety and environmental friendliness Make a distinct advantage over other modes of transport. Specifically will develop promulgate mechanisms The policy is to facilitate the development of inland waterway infrastructure Build and promulgate mechanism The policy of supporting the development of the fleet has a reasonable structure with a fleet of about 30 self-propelled ships accounting for about 70 of the total number of inland waterway vessels To prioritize the development of the container fleet Inland waterway transportation and training retraining of human resources for

29 CFR 780.407 - System must be nonprofit or operated on a share-crop basis.

Science.gov (United States)

2010-07-01

... 29 Labor 3 2010-07-01 2010-07-01 false System must be nonprofit or operated on a share-crop basis... Requirements Under Section 13(b)(12) The Irrigation Exemption § 780.407 System must be nonprofit or operated on... on facilities of any irrigation system unless the ditches, canals, reservoirs, or waterways in...

78 FR 11747 - Drawbridge Operation Regulations; Chelsea River, Chelsea and East Boston, MA

Science.gov (United States)

2013-02-20

... Management Facility (M-30), U.S. Department of Transportation, West Building Ground Floor, Room W12-140, 1200.... John McDonald, Project Officer, First Coast Guard District, telephone (617) 223-8364, john.w.mcdonald.... The waterway is transited predominantly by commercial operators delivering petroleum products to...

75 FR 11870 - Inland Waterways Users Board

Science.gov (United States)

2010-03-12

... DEPARTMENT OF DEFENSE Department of the Army; Corps of Engineers Inland Waterways Users Board AGENCY: Department of the Army, U.S. Army Corps of Engineers, DoD. ACTION: Notice of open meeting... is made of the forthcoming meeting. Name of Committee: Inland Waterways Users Board (Board). Date...

78 FR 44934 - Inland Waterways Users Board

Science.gov (United States)

2013-07-25

... DEPARTMENT OF DEFENSE Department of the Army; Corps of Engineers Inland Waterways Users Board AGENCY: Department of the Army, U.S. Army Corps of Engineers, DoD. ACTION: Notice of open meeting... is made of the forthcoming meeting. Name of Committee: Inland Waterways Users Board (Board). Date...

75 FR 57264 - Inland Waterways Users Board

Science.gov (United States)

2010-09-20

... DEPARTMENT OF DEFENSE Department of the Army; Corps of Engineers Inland Waterways Users Board AGENCY: Department of the Army, U.S. Army Corps of Engineers, DoD. ACTION: Notice of open meeting... is made of the forthcoming meeting. Name of Committee: Inland Waterways Users Board (Board). Date...

76 FR 11216 - Inland Waterways Users Board

Science.gov (United States)

2011-03-01

... DEPARTMENT OF DEFENSE Department of the Army; Corps of Engineers Inland Waterways Users Board AGENCY: Department of the Army, U.S. Army Corps of Engineers, DoD. ACTION: Notice of open meeting... is made of the forthcoming meeting. Name of Committee: Inland Waterways Users Board (Board). Date...

78 FR 72070 - Inland Waterways Users Board

Science.gov (United States)

2013-12-02

... DEPARTMENT OF DEFENSE Department of the Army; Corps of Engineers Inland Waterways Users Board AGENCY: Department of the Army, U.S. Army Corps of Engineers, DoD. ACTION: Notice of open meeting... is made of the forthcoming meeting. Name of Committee: Inland Waterways Users Board (Board). Date...

77 FR 69447 - Inland Waterways Users Board

Science.gov (United States)

2012-11-19

... DEPARTMENT OF DEFENSE Department of the Army; Corps of Engineers Inland Waterways Users Board AGENCY: Department of the Army, U.S. Army Corps of Engineers, DoD. ACTION: Notice of open meeting... is made of the forthcoming meeting. Name of Committee: Inland Waterways Users Board (Board). Date...

77 FR 22769 - Amendment to the Inland Waterways Users Board

Science.gov (United States)

2012-04-17

... DEPARTMENT OF DEFENSE Office of the Secretary Amendment to the Inland Waterways Users Board AGENCY... charter for the Inland Waterways Users Board (hereafter referred to as ``the Board''). The Board is... shall invite primary commercial users and shippers of the inland and intracoastal waterways to serve on...

77 FR 35903 - Safety Zone, Atlantic Intracoastal Waterway; Emerald Isle, NC

Science.gov (United States)

2012-06-15

... 1625-AA00 Safety Zone, Atlantic Intracoastal Waterway; Emerald Isle, NC AGENCY: Coast Guard, DHS... zone on the waters of the Atlantic Intracoastal Waterway at Emerald Isle, North Carolina. The safety... Intracoastal Waterway, mile 226, at Emerald Isle, North Carolina. [[Page 35904

Initial operation of the Holifield facility

International Nuclear Information System (INIS)

Ball, J.B.

1982-01-01

The Holifield Heavy Ion Research Facility (HHIRF) is located at Oak Ridge National Laboratory and operated, by the Physics Division, as a national user facility for research in heavy-ion science. The facility operates two accelerators: the new Pelletron electrostatic accelerator, designed to accelerate all ions at terminal potentials up to 25 million volts, and the Oak Ridge Isochronous Cyclotron (ORIC) which, in addition to its stand-alone capabilities, has been modified to serve also as a booster accelerator for ion beams from the Pelletron. In addition, a number of state-of-the-art experimental devices, a new data acquisition computer system, and special user accommodations have been implemented as part of the facility. The construction of the facility was completed officially in June of this year. This paper reports on the present status of facility operation, observations from testing and running of the 25 MV Pelletron, experience with coupled operation of the Pelletron with the ORIC booster, and a brief summary of the experimental devices now available at the facility

Initial operation of the Holifield Facility

International Nuclear Information System (INIS)

Ball, J.B.

1983-01-01

The Holifield Heavy Ion Research Facility (HHIRF) is located at Oak Ridge National Laboratory and operated, by the Physics Division, as a national user facility for research in heavy-ion science. The facility operates two accelerators: the new pelletron electrostatic accelerator, designed to accelerate all ions at terminal potentials up to 25 million volts, and the Oak Ridge Isochronous Cyclotron (ORIC) which, in addition to its stand-alone capabilities, has been modified to serve also as a booster accelerator for ion beams from the Pelletron. In addition, a number of state-of-the-art experimental devices, a new data acquisition computer system, and special user accommodations have been implemented as part of the facility. The construction of the facility was completed officially in June of this year. This paper reports on the present status of facility operation, observations from testing and running of the 25 MV Pelletron, experience with coupled operation of the Pelletron with the ORIC booster, and a brief summary of the experimental devices now available at the facility

Operation of spent fuel storage facilities

International Nuclear Information System (INIS)

1994-01-01

This Safety Guide was prepared as part of the IAEA's programme on safety of spent fuel storage. This is for interim spent fuel storage facilities that are not integral part of an operating nuclear power plant. Following the introduction, Section 2 describes key activities in the operation of spent fuel storage facilities. Section 3 lists the basic safety considerations for storage facility operation, the fundamental safety objectives being subcriticality, heat removal and radiation protection. Recommendations for organizing the management of a facility are contained in Section 4. Section 5 deals with aspects of training and qualification; Section 6 describes the phases of the commissioning of a spent fuel storage facility. Section 7 describes operational limits and conditions, while Section 8 deals with operating procedures and instructions. Section 9 deals with maintenance, testing, examination and inspection. Section 10 presents recommendations for radiation and environmental protection. Recommendations for the quality assurance (QA) system are presented in Section 11. Section 12 describes the aspects of safeguards and physical protection to be taken into account during operations; Section 13 gives guidance for decommissioning. 15 refs, 5 tabs

77 FR 44463 - Safety Zone, Atlantic Intracoastal Waterway; Emerald Isle, NC

Science.gov (United States)

2012-07-30

... 1625-AA00 Safety Zone, Atlantic Intracoastal Waterway; Emerald Isle, NC AGENCY: Coast Guard, DHS... waters of the Atlantic Intracoastal Waterway at Emerald Isle, North Carolina. The safety zone is... Bridge crossing the Atlantic Intracoastal Waterway, mile 226, at Emerald Isle, North Carolina. The safety...

77 FR 57063 - Safety Zone, Atlantic Intracoastal Waterway; Emerald Isle, NC

Science.gov (United States)

2012-09-17

... 1625-AA00 Safety Zone, Atlantic Intracoastal Waterway; Emerald Isle, NC AGENCY: Coast Guard, DHS... zone on the waters of the Atlantic Intracoastal Waterway at Emerald Isle, North Carolina. The safety... NC 58 Fixed Bridge crossing the Atlantic Intracoastal Waterway, mile 226, at Emerald Isle, North...

77 FR 64906 - Safety Zone, Atlantic Intracoastal Waterway; Emerald Isle, NC

Science.gov (United States)

2012-10-24

... 1625-AA00 Safety Zone, Atlantic Intracoastal Waterway; Emerald Isle, NC AGENCY: Coast Guard, DHS... zone on the waters of the Atlantic Intracoastal Waterway at Emerald Isle, North Carolina. The safety... NC 58 Fixed Bridge crossing the Atlantic Intracoastal Waterway, mile 226, at Emerald Isle, North...

Evaluation of Hydraulic Fracturing (Fracking) Plays for Potential Impact on USACE-Managed Waterways

Science.gov (United States)

2015-01-01

Approved for public release; distribution is unlimited. ERDC/TN DOTS-15-1 January 2015 Evaluation of Hydraulic Fracturing ( Fracking ) Plays...fracturing operations (hydrofracturing or “ fracking ”) to increase petrochemical (natural gas and petroleum) production resulted in elevated environmental...Shale, has raised concerns that fracking operations could impact waterways managed by the U.S. Army Corps of Engineers (USACE). The purpose of this

Navigated Waterways of Louisiana, Geographic NAD83, LOSCO (1999) [navigated_waterways_LOSCO_1999

Data.gov (United States)

Louisiana Geographic Information Center — This is a line dataset of navigated waterways fitting the LOSCO definition: it has been traveled by vessels transporting 10,000 gallons of oil or fuel as determined...

Operating procedures: Fusion Experiments Analysis Facility

Energy Technology Data Exchange (ETDEWEB)

Lerche, R.A.; Carey, R.W.

1984-03-20

The Fusion Experiments Analysis Facility (FEAF) is a computer facility based on a DEC VAX 11/780 computer. It became operational in late 1982. At that time two manuals were written to aid users and staff in their interactions with the facility. This manual is designed as a reference to assist the FEAF staff in carrying out their responsibilities. It is meant to supplement equipment and software manuals supplied by the vendors. Also this manual provides the FEAF staff with a set of consistent, written guidelines for the daily operation of the facility.

Operating procedures: Fusion Experiments Analysis Facility

International Nuclear Information System (INIS)

Lerche, R.A.; Carey, R.W.

1984-01-01

The Fusion Experiments Analysis Facility (FEAF) is a computer facility based on a DEC VAX 11/780 computer. It became operational in late 1982. At that time two manuals were written to aid users and staff in their interactions with the facility. This manual is designed as a reference to assist the FEAF staff in carrying out their responsibilities. It is meant to supplement equipment and software manuals supplied by the vendors. Also this manual provides the FEAF staff with a set of consistent, written guidelines for the daily operation of the facility

Facility design, construction, and operation

International Nuclear Information System (INIS)

1995-04-01

France has been disposing of low-level radioactive waste (LLW) at the Centre de Stockage de la Manche (CSM) since 1969 and now at the Centre de Stockage de l'Aube (CSA) since 1992. In France, several agencies and companies are involved in the development and implementation of LLW technology. The Commissariat a l'Energie Atomic (CEA), is responsible for research and development of new technologies. The Agence National pour la Gestion des Dechets Radioactifs is the agency responsible for the construction and operation of disposal facilities and for wastes acceptance for these facilities. Compagnie Generale des Matieres Nucleaires provides fuel services, including uranium enrichment, fuel fabrication, and fuel reprocessing, and is thus one generator of LLW. Societe pour les Techniques Nouvelles is an engineering company responsible for commercializing CEA waste management technology and for engineering and design support for the facilities. Numatec, Inc. is a US company representing these French companies and agencies in the US. In Task 1.1 of Numatec's contract with Martin Marietta Energy Systems, Numatec provides details on the design, construction and operation of the LLW disposal facilities at CSM and CSA. Lessons learned from operation of CSM and incorporated into the design, construction and operating procedures at CSA are identified and discussed. The process used by the French for identification, selection, and evaluation of disposal technologies is provided. Specifically, the decisionmaking process resulting in the change in disposal facility design for the CSA versus the CSM is discussed. This report provides' all of the basic information in these areas and reflects actual experience to date

Facility approach to tokamak operation

International Nuclear Information System (INIS)

Edmonds, P.H.; Gabbard, W.A.

1981-01-01

In anticipation of the appearance of more advanced tokamaks and other fusion relevant experiments, program has been established at ORNL to systemically identify the requirements of an effective machine operations group. This program is presently applied to the ISX-B experiment. With its continuing development, it is expected to provide major support in the identification of potential problem areas and to assist in the generation of the necessary procedures for forthcoming devices. The present and future generations of large plasma devices will function as facilities, operated by an operations group as service to the plasma physicists and diagnosticians. The purpose of the program discussed here is to develop and to encourage an orderly transition to the facility-like style of operation

Defense waste processing facility radioactive operations. Part 1 - operating experience

International Nuclear Information System (INIS)

Little, D.B.; Gee, J.T.; Barnes, W.M.

1997-01-01

The Savannah River Site's Defense Waste Processing Facility (DWPF) near Aiken, SC is the nation's first and the world's largest vitrification facility. Following a ten year construction program and a 3 year non-radioactive test program, DWPF began radioactive operations in March 1996. This paper presents the results of the first 9 months of radioactive operations. Topics include: operations of the remote processing equipment reliability, and decontamination facilities for the remote processing equipment. Key equipment discussed includes process pumps, telerobotic manipulators, infrared camera, Holledge trademark level gauges and in-cell (remote) cranes. Information is presented regarding equipment at the conclusion of the DWPF test program it also discussed, with special emphasis on agitator blades and cooling/heating coil wear. 3 refs., 4 figs

Defense Waste Processing Facility -- Radioactive operations -- Part 3 -- Remote operations

International Nuclear Information System (INIS)

Barnes, W.M.; Kerley, W.D.; Hughes, P.D.

1997-01-01

The Savannah River Site's Defense Waste Processing Facility (DWPF) near Aiken, South Carolina is the nation's first and world's largest vitrification facility. Following a ten year construction period and nearly three years of non-radioactive testing, the DWPF began radioactive operations in March 1996. Radioactive glass is poured from the joule heated melter into the stainless steel canisters. The canisters are then temporarily sealed, decontaminated, resistance welded for final closure, and transported to an interim storage facility. All of these operations are conducted remotely with equipment specially designed for these processes. This paper reviews canister processing during the first nine months of radioactive operations at DWPF. The fundamental design consideration for DWPF remote canister processing and handling equipment are discussed as well as interim canister storage

Maintenance, repair and operation (MRO) of shutdown facilities

International Nuclear Information System (INIS)

Kenny, S.

2006-01-01

What level of maintenance does one apply to a shutdown facility? Well it depends on who you ask. Operations staff sees facilities that have completed their useful life cycle as a cost drain while Decommissioning staff sees this as the start of a new life cycle. Based on the decommissioning plan for the particular facility the building could complete another full life cycle while under decommissioning whether it is in storage with surveillance mode or under active decommissioning. This paper will explore how you maintain a facility and systems for many years after its useful life until final decommissioning is completed. When a building is declared redundant, who looks after it until the final decommissioning end state is achieved? At the AECL, Chalk River Labs site the safe shutdown and turnover process is one key element that initiates the decommissioning process. The real trick is orchestrating maintenance, repair and operation plans for a facility that has been poorly invested in during its last years of useful life cycle. To add to that usually shutdowns are prolonged for many years beyond the expected turnover period. During this presentation I will cover what AECL is doing to ensure that the facilities are maintained in a proper state until final decommissioning can be completed. All facilities or systems travel through the same life cycle, design, construction, commissioning, operation, shutdown and demolition. As we all know, nuclear facilities add one more interesting twist to this life cycle called Decommissioning that lands between shutdown and demolition. As a facility nears the shutdown phase, operations staff loose interest in the facility and stop investing in upgrades, repairs and maintenance but continue to invest and focus on maximizing operations. Facility maintenance standards produced by the International Facility Maintenance Association (IFMA) based on a survey done every year state that 2.2% of the total operating costs for the site should be

High level waste facilities - Continuing operation or orderly shutdown

International Nuclear Information System (INIS)

Decker, L.A.

1998-04-01

Two options for Environmental Impact Statement No action alternatives describe operation of the radioactive liquid waste facilities at the Idaho Chemical Processing Plant at the Idaho National Engineering and Environmental Laboratory. The first alternative describes continued operation of all facilities as planned and budgeted through 2020. Institutional control for 100 years would follow shutdown of operational facilities. Alternatively, the facilities would be shut down in an orderly fashion without completing planned activities. The facilities and associated operations are described. Remaining sodium bearing liquid waste will be converted to solid calcine in the New Waste Calcining Facility (NWCF) or will be left in the waste tanks. The calcine solids will be stored in the existing Calcine Solids Storage Facilities (CSSF). Regulatory and cost impacts are discussed

Establishment and Operation of User Facilities

International Nuclear Information System (INIS)

Cho, Yong Sub; Kwon, Hyeok Jung; Kim, Kye Ryung

2008-05-01

PEFP(Proton Engineering Frontier Project) has launched on a new enterprise to develop the technologies for the future relating to the proton beam and spin-off technologies in 2002. PEFP planned to supply 20MeV and 100MeV proton beam by the development of the 100MeV, 20mA linear accelerator during ten years from 2002 to 2012. The final goal of this project is establishment of 20MeV and 100MeV user facilities. To do this, we must develop the key technologies for establishing user facilities. Before the main facilities are normally operated, we have established the test user facilities to support various kinds of users' basic experiments and pilot studies. The necessity of this research are as follows; - Domestic achievement of key technologies for the development and design of the user facilities for the several tens to hundreds MeV class high current proton beam - Beam application researches can be revitalized and improved the efficiency by the establishment and operation of user facilities and test facilities. - Ion implantation facilities have contributed to increase Industrial applications - It is more effective in saving money that users use the PEFP's user facility than other country's user facilities. - It is possible to contribute to the local society and commercialize the beam application technologies by the establishment of PEFP's research branch in Kyungju

PROJECTIZING AN OPERATING NUCLEAR FACILITY

International Nuclear Information System (INIS)

Adams, N

2007-01-01

This paper will discuss the evolution of an operations-based organization to a project-based organization to facilitate successful deactivation of a major nuclear facility. It will describe the plan used for scope definition, staff reorganization, method estimation, baseline schedule development, project management training, and results of this transformation. It is a story of leadership and teamwork, pride and success. Workers at the Savannah River Site's (SRS) F Canyon Complex (FCC) started with a challenge--take all the hazardous byproducts from nearly 50 years of operations in a major, first-of-its-kind nuclear complex and safely get rid of them, leaving the facility cold, dark, dry and ready for whatever end state is ultimately determined by the United States Department of Energy (DOE). And do it in four years, with a constantly changing workforce and steadily declining funding. The goal was to reduce the overall operating staff by 93% and budget by 94%. The facilities, F Canyon and its adjoined sister, FB Line, are located at SRS, a 310-square-mile nuclear reservation near Aiken, S.C., owned by DOE and managed by Washington Group International subsidiary Washington Savannah River Company (WSRC). These facilities were supported by more than 50 surrounding buildings, whose purpose was to provide support services during operations. The radiological, chemical and industrial hazards inventory in the old buildings was significant. The historical mission at F Canyon was to extract plutonium-239 and uranium-238 from irradiated spent nuclear fuel through chemical processing. FB Line's mission included conversion of plutonium solutions into metal, characterization, stabilization and packaging, and storage of both metal and oxide forms. The plutonium metal was sent to another DOE site for use in weapons. Deactivation in F Canyon began when chemical separations activities were completed in 2002, and a cross-functional project team concept was implemented to successfully

OPG - Waterways public safety program

Energy Technology Data Exchange (ETDEWEB)

Bennett, Tony [Ontario Power Generation (Canada)

2011-07-01

Ontario Power Generation (OPG) operates 65 hydroelectric generating stations in Ontario and has 241 dams. Security around dams is an important matter to minimize exposure of the public to hazards and to prevent an uncontrolled release of water and also to be prepared in case of failure. The purpose of this presentation is to describe the waterways public safety program developed by OPG in association with the Ontario Waterpower Associattion, the Canadian Dam Association and the Ontario Ministry of Natural Resoruces. This program takes a managed system approach with continuous review to address specific and changing conditions of sites. Policies, accountability mechanisms and assessments are first planned, and then implemented, every day functioning is monitored, corrective actions are developed on the basis of issues and reports are compiled for planning of new improvements. This research program provided OPG with new methods for preventing accidents more efficiently.

Performance confirmation operation of water environment control facility

International Nuclear Information System (INIS)

Magome, Hirokatsu; Okada, Yuji; Tomita, Kenji; Iida, Kazuhiro; Ando, Hitoshi; Yonekawa, Akihisa; Ueda, Haruyasu; Hanawa, Hiroshi; Kanno, Masaru; Sakuta, Yoshiyuki

2015-09-01

In Japan Atomic Energy Agency, in order to solve the problem in the long-term operation of a light water reactor, preparation which does the irradiation experiment of light-water reactor fuel and material was advanced. JMTR stopped after the 165th operation cycle in August 2006, and is advancing renewal of the irradiation facility towards re-operation. The material irradiation test facility was installed from 2008 fiscal year to 2012 fiscal year in JMTR. The material irradiation test facility is used for IASCC study, and consists of mainly three equipments. This report described performance operating test of the water environmental control facilities for IASCC study carried out 2013 fiscal year. (author)

Facility design, installation and operation

International Nuclear Information System (INIS)

Fleischmann, A.W.

1985-01-01

Problems that may arise when considering the design, construction and use of a facility that could contain up to tens of petabecquerel of either cobalt-60 or caesium-137 are examined. The safe operation of an irradiation facility depends on an appreciation of the in built safety systems, adequate training of personnel and the existence of an emergency system

Fuel Supply Shutdown Facility Interim Operational Safety Requirements

International Nuclear Information System (INIS)

BENECKE, M.W.

2000-01-01

The Interim Operational Safety Requirements for the Fuel Supply Shutdown (FSS) Facility define acceptable conditions, safe boundaries, bases thereof, and management of administrative controls to ensure safe operation of the facility

Analysis Of Inland Waterway Transport For Container Shipping: Cikarang To Port Of TanjungPriok

Science.gov (United States)

Achmadi, T.; Nur, H. I.; Rahmadhon, L. R.

2018-03-01

Industry's development which is in the center of Cikarang's industrial estate causes a considerable increase from 7% to 13% of container's flow from and to Port of Tanjung Priok per year. Therefore, those obstacles rise the number of traffic congestion and transport cost. This research aims to analyze the potential alternative of transportation in order to transport containers at the route of Tanjung Priok to Cikarang utilizing Inland Waterways Transport through Cikarang Bekasi Laut (CBL) river. This research will be conducted by comparing component of total logistic cost that emerging caused by container trucks and vessels. Self Propelled Container Barge (SPCB) is a pointed alternative transportation in which it is used to transport containers through the waterways. The result of analysis obtained that the capacity of Cikarang Bekasi Laut river is 18,558 roundtrip per year. Furthermore, the collaboration of 3 SPCB operations, as well payload 32 TEUS can decrease the amount of road traffic congestion/density of Cikarang-Port of Tanjung Priok as much as 18.6%. The cost of containers shipping per unit transported by truck is IDR 2.2 Million per TEUs, whereas containers shipping transported by Inland Waterways cost only IDR 1.8 Million per TEUs.

Operating large controlled thermonuclear fusion research facilities

International Nuclear Information System (INIS)

Gaudreau, M.P.J.; Tarrh, J.M.; Post, R.S.; Thomas, P.

1987-01-01

The MIT Tara Tandem Mirror is a large, state of the art controlled thermonuclear fusion research facility. Over the six years of its design, implementation, and operation, every effort was made to minimize cost and maximize performance by using the best and latest hardware, software, and scientific and operational techniques. After reviewing all major DOE fusion facilities, an independent DOE review committee concluded that the Tara operation was the most automated and efficient of all DOE facilities. This paper includes a review of the key elements of the Tara design, construction, operation, management, physics milestones, and funding that led to this success. The authors emphasize a chronological description of how the system evolved from the proposal stage to a mature device with an emphasis on the basic philosophies behind the implementation process. This description can serve both as a qualitative and quantitative database for future large experiment planning. It includes actual final costs and manpower spent as well as actual run and maintenance schedules, number of data shots, major system failures, etc. The paper concludes with recommendations for the next generation of facilities

Bank erosion processes in waterways

NARCIS (Netherlands)

Duro, G.; Uijttewaal, W.S.J.; Kleinhans, M; Crosato, A.

2017-01-01

Waterways serve for several functions besides  transporting goods and people. The ecological  importance of navigable rivers has taken much  attention during recent decades bringing efforts  to improve these natural corridors for fauna and  flora (Boeters et al.,

Margins of the law pertaining to water supplies and waterways

International Nuclear Information System (INIS)

Bickel, C.

1981-01-01

The author examines legal questions coming from points of contact of the law pertaining to water supplies and waterways on the one hand with the Waste Management Law, the Atomic Energy Law and Criminal Law on the other hand. He tries to find ways for solving the practical problems which arise with the execution of the law pertaining to water supplies and waterways. (HSCH) [de

Remote operation and maintenance demonstration facility at ORNL

International Nuclear Information System (INIS)

Harvey, H.W.; Floyd, S.D.; Kuban, D.P.; Singletary, B.H.; Stradley, J.G.

1978-01-01

The Remote Operation and Maintenance Facility is a versatile facility arranged to mock up various hot cell configurations. Modular units of simulated shielding and viewing windows were built to provide flexibility in arrangement. The facility is fully equipped with hoists, manipulators, television, and other basic equipment and services necessary to provide capability for both remote operation and maintenance of several selected functional process equipment groups

Operating large controlled thermonuclear fusion research facilities

International Nuclear Information System (INIS)

Gaudreau, M.P.J.; Tarrh, J.M.; Post, R.S.; Thomas, P.

1987-10-01

The MIT Tara Tandem Mirror is a large, state of the art controlled thermonuclear fusion research facility. Over the six years of its design, implementation, and operation, every effort was made to minimize cost and maximize performance by using the best and latest hardware, software, and scientific and operational techniques. After reviewing all major DOE fusion facilities, an independent DOE review committee concluded that the Tara operation was the most automated and efficient of all DOE facilities. This paper includes a review of the key elements of the Tara design, construction, operation, management, physics milestones, and funding that led to this success. We emphasize a chronological description of how the system evolved from the proposal stage to a mature device with an emphasis on the basic philosophies behind the implementation process. This description can serve both as a qualitative and quantitative database for future large experiment planning. It includes actual final costs and manpower spent as well as actual run and maintenance schedules, number of data shots, major system failures, etc. The paper concludes with recommendations for the next generation of facilities. 13 refs., 15 figs., 3 tabs

Remote Operation and Maintenance Demonstration Facility at ORNL

International Nuclear Information System (INIS)

Harvey, H.W.; Floyd, S.D; Kuban, D.P.; Singletary, B.H.; Stradley, J.G.

1978-01-01

The Remote Operation and Maintenance Facility is a versatile facility arranged to mock-up various hot-cell configurations. Modular units of simulated shielding and viewing windows were built to provide flexibility in arrangement. The facility is fully equipped with hoists, manipulators, television, and the other basic equipment and services necessary to provide capability for both remote operation and maintenance of several selected functional process equipment groups. 6 figures

CLIMATE CHANGE AND THE RISK MANAGEMENT IN SERBIAN INLAND WATERWAY TRANSPORT

Directory of Open Access Journals (Sweden)

Todor Backalic

2012-12-01

Full Text Available Climate changes require special attention and global monitoring. Impacts on nature and industry are increasingly evident. Water transport could be the backbone of the future European combined transport system. Unfortunately, risks in water transport are perhaps an under researched area and consequently, this article outlines a rationale, why it is necessary to develop competence about risk in water transport. The development of the cargo transport in river traffic depends directly on technical-exploitative characteristics of the network of inland waterways. Research of navigational abilities of inland waterways always comes before building ships or making a transport schedule. Navigation characteristics of rivers have to be determined as precise as possible, especially from the aspect of determination the possible draught of vessels. River transport due to their operational business and environmental conditions faced with several risks having different degrees of consequences. Current risk assessment methods for water transport just consider some dramatic events. We present a new method for the assessment of risk and vulnerability of water transport where river depth represents a crucial part. The analysis of water level changes on Serbian rivers during the last sixty years was done.

Recreation value of a waterway and changes in this value

International Nuclear Information System (INIS)

Aittoniemi, P.

1991-01-01

The uniquely rich hydrological and archipelagic nature of Finland creates versatile opportunities for spending of leisure time. As various uses of waterways compete with each other, it is difficult to compare advantages and disadvantages of operations in view of various interests. This is why efforts have been made to develop methods to make the effect commensurable. Usability of shores is one important factor in the assessment of recreation use of waterways. When influence of water level changes in usability of shores is estimated, shore and bottom slope and quality, and uses and user numbers of the shores must be known. In several assessment methods, usability of shore is depicted by distance of the shifted shoreline (due to the changed water level) from the 'good' status. The studies on changes in the recreation value or usability of shores should be started by making efforts to classify and estimate various effects separately. If the value is wished to be given as one figure, the calculation basis applied, the weights and the used value functions must be stated clearly with the results. It is equally important to make a sensitivity analysis, i.e. to study effects of changes in uncertain input data on the results

Enhanced operator-training simulator for the Fast Flux Test Facility

International Nuclear Information System (INIS)

Schrader, F.D.; Swanson, C.D.

1983-01-01

The FFTF Plant Operator Training Simulator Facility has proven to be a valuable asset throughtout the testing, startup and early operational phases of the Fast Flux Test facility. However, limitations inherent in the existing simulation facility, increased emphasis on the required quality of operator training, and an expanded scope of applications (e.g., MNI development) justify an enhanced facility. Direct use of plant operators in the development of improved reactor control room displays and other man/machine interface equipment and procedures increases the credibility of proposed techniques and reported results. The FFTF Plant Operator Training Simulator provides a key element in this development program

A regional waterway management system for balancing recreational boating and resource protection.

Science.gov (United States)

Swett, Robert A; Listowski, Charles; Fry, Douglas; Boutelle, Stephen; Fann, David

2009-06-01

Florida's coasts have been transformed over the past three decades as population growth and unprecedented demand for individual shore access to bays and estuaries led to the creation of residential canal developments. Thousands of miles of channels and basins were dredged as a by-product of this urbanization process. The navigable waterways that resulted are now being stressed by increasing boat traffic and canal-side activities. Recognizing their common goal to preserve the recreational and ecological value of southwest Florida waterways, the Florida Department of Environmental Protection, the four-county West Coast Inland Navigation District, and the University of Florida Sea Grant College Program signed a Memorandum of Agreement. The signatories agreed to develop a science-based Regional Waterway Management System (RWMS), which is a new approach to waterway planning and permitting based on carefully mapped channel depths, a census of actual boat populations, and the spatial extent of natural resources. The RWMS provides a comprehensive, regional overview of channel conditions and the geographic distribution and severity of existing impediments to safe navigation and resource protection. RWMS information and analyses result in regional-scale permitting to accommodate water-dependent uses while minimizing environmental impacts and reducing public expenditures. Compared with traditional approaches to waterway management, the science-based RWMS is relatively unbiased, objective, transparent, ecologically sound, and fiscally prudent.

Overview - Defense Waste Processing Facility Operating Experience

International Nuclear Information System (INIS)

Norton, M.R.

2002-01-01

The Savannah River Site's Defense Waste Processing Facility (DWPF) near Aiken, SC is the world's largest radioactive waste vitrification facility. Radioactive operations began in March 1996 and over 1,000 canisters have been produced. This paper presents an overview of the DWPF process and a summary of recent facility operations and process improvements. These process improvements include efforts to extend the life of the DWPF melter, projects to increase facility throughput, initiatives to reduce the quantity of wastewater generated, improved remote decontamination capabilities, and improvements to remote canyon equipment to extend equipment life span. This paper also includes a review of a melt rate improvement program conducted by Savannah River Technology Center personnel. This program involved identifying the factors that impacted melt rate, conducting small scale testing of proposed process changes and developing a cost effective implementation plan

The operation of post-irradiation examination facility

International Nuclear Information System (INIS)

Kim, Eun Ka; Min, Duk Ki; Lee, Young Kil

1994-12-01

The operation of post-irradiation examination facility was performed as follow. HVAC and pool water treatment system were continuously operated, and radiation monitoring in PIE facility has been carried out to maintain the facility safely. Inspection of the fuel assembly (F02) transported from Kori Unit 1 was performed in pool, and fuel rods extracted from the fuel assembly (J44) of Kori Unit 2 NPP were examined in hot cell. A part of deteriorated pipe line of drinking water was exchanged for stainless steel pipe to prevent leaking accidents. Halon gas system was also installed in the exhausting blower room for fire fighting. And IAEA inspection camera for safeguard of nuclear materials was fixed at the wall in pool area. Radiation monitoring system were improved to display the area radioactive value at CRT monitor in health physics control room. And automatic check system for battery and emergency diesel generator was developed to measure the voltage and current of them. The performance test of oxide thickness measuring device installed in hot cell for irradiated fuel rod and improvement of the device were performed, and good measuring results using standard sample were obtained. The safeguard inspection of nuclear materials and operation inspection of the facility were carried out through the annual operation inspection, quarterly IAEA inspection and quality assurance auditing. 26 tabs., 43 figs., 14 refs. (Author) .new

Forstering cooperation in inland waterway networks : a gaming and simulation approach (chapter 23)

NARCIS (Netherlands)

Veenstra, A.W.; Meijeren, van J.; Harmsen, J.M.A.; Verbraeck, A.; Negenborn, R.R.; Ocampa-Martinez, C.

2015-01-01

Inland waterway transport is an important economic activity in the Netherlands and in Europe. Especially in the hinterland transport of containers, inland shipping is expected to form the backbone of a multimodal transport system. To support and strengthen the inland waterway industry in the

Relationships Between Perceived Coastal Waterway Condition and Social Aspects of Quality of Life

Directory of Open Access Journals (Sweden)

Melanie E. Cox

2006-06-01

Full Text Available Previous research has shown that the presence of natural areas is beneficial to human well-being. However, to date there have been few published studies of the effects that the condition of natural areas have on well-being. We hypothesize that coastal waterways that are perceived to be in better condition are visited more often by local residents, and as a result, residents will develop a stronger sense of place and stronger social relations with other residents, which will in turn lead to a higher quality of life. A survey was conducted to test this hypothesis in two coastal regions in Queensland, Australia. A weak relationship was found between perceived coastal quality and the number of recreational visits. In both study areas, frequency of visits to coastal waterways was significantly related to quality of life through an increased sense of place and social contacts. In the Douglas region, sense of place and social capital were closely related, and social capital was also related to quality of life. In both study areas, residents were most likely to visit waterways that were located in close proximity to their residence, suggesting that management of all waterways is essential for human well-being, and that benefits to humans will result from rehabilitating degraded waterways.

Operation of the nuclear fuel cycle test facilities -Operation of the hot test loop facilities

International Nuclear Information System (INIS)

Chun, S. Y.; Jeong, M. K.; Park, C. K.; Yang, S. K.; Won, S. Y.; Song, C. H.; Jeon, H. K.; Jeong, H. J.; Cho, S.; Min, K. H.; Jeong, J. H.

1997-01-01

A performance and reliability of a advanced nuclear fuel and reactor newly designed should be verified by performing the thermal hydraulics tests. In thermal hydraulics research team, the thermal hydraulics tests associated with the development of an advanced nuclear fuel and reactor haven been carried out with the test facilities, such as the Hot Test Loop operated under high temperature and pressure conditions, Cold Test Loop, RCS Loop and B and C Loop. The objective of this project is to obtain the available experimental data and to develop the advanced measuring techniques through taking full advantage of the facilities. The facilities operated by the thermal hydraulics research team have been maintained and repaired in order to carry out the thermal hydraulics tests necessary for providing the available data. The performance tests for the double grid type bottom end piece which was improved on the debris filtering effectivity were performed using the PWR-Hot Test Loop. The CANDU-Hot Test Loop was operated to carry out the pressure drop tests and strength tests of CANFLEX fuel. The Cold Test Loop was used to obtain the local velocity data in subchannel within HANARO fuel bundle and to study a thermal mixing characteristic of PWR fuel bundle. RCS thermal hydraulic loop was constructed and the experiments have been carried out to measure the critical heat flux. In B and C Loop, the performance tests for each component were carried out. (author). 19 tabs., 78 figs., 19 refs

Operation of the nuclear fuel cycle test facilities -Operation of the hot test loop facilities

Energy Technology Data Exchange (ETDEWEB)

Chun, S. Y.; Jeong, M. K.; Park, C. K.; Yang, S. K.; Won, S. Y.; Song, C. H.; Jeon, H. K.; Jeong, H. J.; Cho, S.; Min, K. H.; Jeong, J. H.

1997-01-01

A performance and reliability of a advanced nuclear fuel and reactor newly designed should be verified by performing the thermal hydraulics tests. In thermal hydraulics research team, the thermal hydraulics tests associated with the development of an advanced nuclear fuel and reactor haven been carried out with the test facilities, such as the Hot Test Loop operated under high temperature and pressure conditions, Cold Test Loop, RCS Loop and B and C Loop. The objective of this project is to obtain the available experimental data and to develop the advanced measuring techniques through taking full advantage of the facilities. The facilities operated by the thermal hydraulics research team have been maintained and repaired in order to carry out the thermal hydraulics tests necessary for providing the available data. The performance tests for the double grid type bottom end piece which was improved on the debris filtering effectivity were performed using the PWR-Hot Test Loop. The CANDU-Hot Test Loop was operated to carry out the pressure drop tests and strength tests of CANFLEX fuel. The Cold Test Loop was used to obtain the local velocity data in subchannel within HANARO fuel bundle and to study a thermal mixing characteristic of PWR fuel bundle. RCS thermal hydraulic loop was constructed and the experiments have been carried out to measure the critical heat flux. In B and C Loop, the performance tests for each component were carried out. (author). 19 tabs., 78 figs., 19 refs.

Identification of facility constraints that impact transportation operations

International Nuclear Information System (INIS)

Peterson, R.W.; Pope, R.B.

1990-01-01

As Federal waste Management Systems (FWMS) receiving facilities become available, the US Department of Energy (DOE) intends to begin accepting spent nuclear fuel from US utilities for eventual permanent disposal. Transporting the radioactive spent fuel to the repository will require development of a complex network of equipment, services, and operations personnel that will comprise the Transportation Operations System. This paper identifies and discusses, in a qualitative manner, the key reactor facility constraints that will eventually need to be assessed in detail on a site-specific basis to guide the development of the FWMS transportation cask fleet. This evaluation of constraints is needed to assess their impact on the size, composition, availability, and use of the cask fleet and to assist in the development of the transportation system support facilities such as a cask maintenance facility. Such assessment will also be needed to support decisions on modifying shipping facilities (i.e., reactors), identification and design of interface hardware, and on the designs of receiving facilities

Detection of multi-drug resistant Escherichia coli in the urban waterways of Milwaukee, WI

Directory of Open Access Journals (Sweden)

Anthony D. Kappell

2015-04-01

Full Text Available Urban waterways represent a natural reservoir of antibiotic resistance which may provide a source of transferable genetic elements to human commensal bacteria and pathogens. The objective of this study was to evaluate antibiotic resistance of Escherichia coli isolated from the urban waterways of Milwaukee, WI compared to those from Milwaukee sewage and a clinical setting in Milwaukee. Antibiotics covering 10 different families were utilized to determine the phenotypic antibiotic resistance for all 259 E. coli isolates. All obtained isolates were determined to be multi-drug resistant. The E. coli isolates were also screened for the presence of the genetic determinants of resistance including ermB (macrolide resistance, tet(M (tetracycline resistance, and β-lactamases (blaOXA, blaSHV, and blaPSE. E. coli from urban waterways showed a greater incidence of antibiotic resistance to 8 of 17 antibiotics tested compared to human derived sources. These E. coli isolates also demonstrated a greater incidence of resistance to higher numbers of antibiotics compared to the human derived isolates. The urban waterways demonstrated a greater abundance of isolates with co-occurrence of antibiotic resistance than human derived sources. When screened for 5 different antibiotic resistance genes conferring macrolide, tetracycline, and β-lactam resistance, clinical E. coli isolates were more likely to harbor ermB and blaOXA than isolates from urban waterway. These results indicate that Milwaukee’s urban waterways may select for a greater incidence of multiple antibiotic resistance organisms and likely harbor a different antibiotic resistance gene pool than clinical sources. The implications of this study are significant to understanding the presence of resistance in urban freshwater environments by supporting the idea that sediment from urban waterways serves as a reservoir of antibiotic resistance.

Conditions of using floating cranes for lifting sunken objects on inland waterways

OpenAIRE

Slobodan M. Radojević

2012-01-01

This paper presents the conditions for using floating cranes for lifting sunken vessels and other objects on inland waterways. Basic technical data are given together with technical details for the usage of floa ting cranes for lifting sunken objects. The paper points to the importance of lifting sunken objects and their removal from inland waterways in the Republic of Serbia.

Conditions of using floating cranes for lifting sunken objects on inland waterways

Directory of Open Access Journals (Sweden)

Slobodan M. Radojević

2012-04-01

Full Text Available This paper presents the conditions for using floating cranes for lifting sunken vessels and other objects on inland waterways. Basic technical data are given together with technical details for the usage of floa ting cranes for lifting sunken objects. The paper points to the importance of lifting sunken objects and their removal from inland waterways in the Republic of Serbia.

Spent nuclear fuel project cold vacuum drying facility operations manual

International Nuclear Information System (INIS)

IRWIN, J.J.

1999-01-01

This document provides the Operations Manual for the Cold Vacuum Drying Facility (CVDF). The Manual was developed in conjunction with HNF-SD-SNF-SAR-002, Safety Analysis Report for the Cold Vacuum Drying Facility, Phase 2, Supporting Installation of Processing Systems (Garvin 1998) and, the HNF-SD-SNF-DRD-002, 1997, Cold Vacuum Drying Facility Design Requirements, Rev. 3a. The Operations Manual contains general descriptions of all the process, safety and facility systems in the CVDF, a general CVD operations sequence, and has been developed for the SNFP Operations Organization and shall be updated, expanded, and revised in accordance with future design, construction and startup phases of the CVDF until the CVDF final ORR is approved

Advanced Control Test Operation (ACTO) facility

International Nuclear Information System (INIS)

Ball, S.J.

1987-01-01

The Advanced Control Test Operation (ACTO) project, sponsored by the US Department of Energy (DOE), is being developed to enable the latest modern technology, automation, and advanced control methods to be incorporated into nuclear power plants. The facility is proposed as a national multi-user center for advanced control development and testing to be completed in 1991. The facility will support a wide variety of reactor concepts, and will be used by researchers from Oak Ridge National Laboratory (ORNL), plus scientists and engineers from industry, other national laboratories, universities, and utilities. ACTO will also include telecommunication facilities for remote users

Coefficients of Propeller-hull Interaction in Propulsion System of Inland Waterway Vessels with Stern Tunnels

Directory of Open Access Journals (Sweden)

Jan Kulczyk

2014-09-01

Full Text Available Propeller-hull interaction coefficients - the wake fraction and the thrust deduction factor - play significant role in design of propulsion system of a ship. In the case of inland waterway vessels the reliable method of predicting these coefficients in early design stage is missing. Based on the outcomes from model tests and from numerical computations the present authors show that it is difficult to determine uniquely the trends in change of wake fraction and thrust deduction factor resulting from the changes of hull form or operating conditions. Nowadays the resistance and propulsion model tests of inland waterway vessels are carried out rarely because of relatively high costs. On the other hand, the degree of development of computational methods enables’ to estimate the reliable values o interaction coefficients. The computations referred to in the present paper were carried out using the authors’ own software HPSDKS and the commercial software Ansys Fluent.

78 FR 59339 - Intracoastal Waterway Route “Magenta Line” on NOAA Nautical Charts

Science.gov (United States)

2013-09-26

... waterways have been based principally on surveys made from 60 to 80 years ago and, necessarily, are obsolete... found where the charted Intracoastal Waterway Route (``magenta line'') passes on the wrong side of aids... specifically seeks comments regarding: 1. How do you currently access the magenta line? On paper nautical...

Design, Fabrication, and Initial Operation of a Reusable Irradiation Facility

International Nuclear Information System (INIS)

Heatherly, D.W.; Thoms, K.R.; Siman-Tov, I.I.; Hurst, M.T.

1999-01-01

A Heavy-Section Steel Irradiation (HSSI) Program project, funded by the US Nuclear Regulatory Commission, was initiated at Oak Ridge National Laboratory to develop reusable materials irradiation facilities in which metallurgical specimens of reactor pressure vessel steels could be irradiated. As a consequence, two new, identical, reusable materials irradiation facilities have been designed, fabricated, installed, and are now operating at the Ford Nuclear Reactor at the University of Michigan. The facilities are referred to as the HSSI-IAR facilities with the individual facilities being designated as IAR-1 and IAR-2. This new and unique facility design requires no cutting or grinding operations to retrieve irradiated specimens, all capsule hardware is totally reusable, and materials transported from site to site are limited to specimens only. At the time of this letter report, the facilities have operated successfully for approximately 2500 effective full-power hours

Establishment and operation of a photovoltaic cell test facility

Energy Technology Data Exchange (ETDEWEB)

Pearsall, N.M.; Forbes, I.

1999-07-01

This report describes the setting up of a test facility at the University of Northumbria. Details of the equipment specification and procurement are given, and the commissioning and initial operation of the facility, and the measurement procedures for I-V characteristics, spectral response measurements, optical scanning and test charges are outlined. The business plan for the test facility is discussed, and operating experience is reviewed in terms of publicity, services provided, and collaboration.

Investigating driver willingness to drive through flooded waterways.

Science.gov (United States)

Pearson, Marti; Hamilton, Kyra

2014-11-01

Approximately 40% of all drowning deaths involve a motor vehicle. Regardless of its significance as a cause of flood-related mortality, there is continued prevalence of driving through flooded waterways in Australia and worldwide. We aimed to understand the motivational determinates of driving through flooded waterways in low and high-risk scenarios by utilizing an augmented theory of planned behaviour (TPB) with behavioural willingness as the outcome variable as well as the influence of additional predictors; namely perceived risk and past behaviour. Participants (n=174; Mage=27.43, SD=10.76) answered standard TPB-based questions in regards to attitudes, subjective norm, and perceived behavioural control (PBC), as well as additional variables of perceived risk (i.e., perceived susceptibility and perceived severity) and past behaviour. Support was found for the augmented TPB as attitude, subjective norm, and PBC predicted behavioural willingness. Support was also found for perceived severity in the high-risk but not the low-risk scenario. No support was found for perceived susceptibility. Past behaviour emerged as a significant predictor of willingness in the low and high-risk scenario. The findings provide support for an augmented TPB in understanding individuals' willingness to drive through flooded waterways, suggesting that a multi-strategy approach may be critical in attempts to reduce the incidence of such risky driving behaviour. Copyright © 2014 Elsevier Ltd. All rights reserved.

Operating manual for the critical experiments facility

International Nuclear Information System (INIS)

1986-01-01

The operation of the Critical Experiments Facility (CEF) requires careful attention to procedures in order that all safety precautions are observed. Since an accident could release large amounts of radioactivity, careful operation and strict enforcement of procedures are necessary. To provide for safe operation, detailed procedures have been written for all phases of the operation of this facility. The CEF operating procedures are not to be construed to constitute a part ofthe Technical Specifications. In the event of any discrepancy between the information given herein and the Technical Specifications, limits set forth in the Technical Specifications apply. All normal and most emergency operation conditions are covered by procedures presented in this manual. These procedures are designed to be followed by the operating personnel. Strict adherence to these procedures is expected for the following reasons. (1) To provide a standard, safe method of performing all operations, the procedures were written by reactor engineers experienced in supervising the operation of reactors and were reviewed by an organization with over 30 years of reactor operating experience. (2) To have an up-to-date description of operating techniques available at all times for reference and review, it is necessary that the procedures be written

Operating manual for the critical experiments facility

Energy Technology Data Exchange (ETDEWEB)

1986-01-01

The operation of the Critical Experiments Facility (CEF) requires careful attention to procedures in order that all safety precautions are observed. Since an accident could release large amounts of radioactivity, careful operation and strict enforcement of procedures are necessary. To provide for safe operation, detailed procedures have been written for all phases of the operation of this facility. The CEF operating procedures are not to be construed to constitute a part ofthe Technical Specifications. In the event of any discrepancy between the information given herein and the Technical Specifications, limits set forth in the Technical Specifications apply. All normal and most emergency operation conditions are covered by procedures presented in this manual. These procedures are designed to be followed by the operating personnel. Strict adherence to these procedures is expected for the following reasons. (1) To provide a standard, safe method of performing all operations, the procedures were written by reactor engineers experienced in supervising the operation of reactors and were reviewed by an organization with over 30 years of reactor operating experience. (2) To have an up-to-date description of operating techniques available at all times for reference and review, it is necessary that the procedures be written.

Spent Nuclear Fuel Project Cold Vacuum Drying Facility Operations Manual

International Nuclear Information System (INIS)

IRWIN, J.J.

1999-01-01

This document provides the Operations Manual for the Cold Vacuum Drying Facility (CVDF). The Manual was developed in conjunction with HNF-553, Spent Nuclear Fuel Project Final Safety Analysis Report Annex B--Cold Vacuum Drying Facility. The HNF-SD-SNF-DRD-002, 1999, (Cold Vacuum Drying Facility Design Requirements), Rev. 4. and the CVDF Final Design Report. The Operations Manual contains general descriptions of all the process, safety and facility systems in the CVDF, a general CVD operations sequence and references to the CVDF System Design Descriptions (SDDs). This manual has been developed for the SNFP Operations Organization and shall be updated, expanded, and revised in accordance with future design, construction and startup phases of the CVDF until the CVDF final ORR is approved

Optimum operation of a small power production facility

Energy Technology Data Exchange (ETDEWEB)

Capehart, B.L.; Mahoney, J.F.; Sivazlian, B.D.

1983-09-01

To help reduce the U.S.A.'s dependence on imported oil for electrical power generation, the 1978 National Energy Act established regulations to promote construction and operation of cogeneration and small power production facilities. Many of these facilities are presently under construction, with a great number planned. This paper examines the operation of a small power production facility with on-site generation and storage, on-site use, and connection to an electric utility grid system for the purpose of both selling excess power and buying power. It is assumed that the buying and selling price of electricity varies frequently during the day and that the relevant price and demand data may be accurately projected into the near future. With this system description, a mathematical model is formulated and solved by linear programming to obtain a series of periodic buy and sell decisions so as to maximize the profit from operating the small power production facility. Results are presented to illustrate the methodology for determining potential profits.

Annual Report of Radioactive Waste Facilities Operation in 2013

Institute of Scientific and Technical Information of China (English)

DU; Hong-ming; GAO; Zhi-gang; LIU; Fu-guo

2013-01-01

301,a section of Department of Radiochemistry,which manages 15 facilities and undertakes the administrative tasks of radioactive waste,is the important guarantee of scientific research production and safety in CIAE.1 The safe operation of the radioactive waste management facilities In 2013,in order to ensure the operation safety,we formulated the inspection regulations,which included regular operation inspection,week safety inspection from the leaders of the section and

26 CFR 1.132-7 - Employer-operated eating facilities.

Science.gov (United States)

2010-04-01

... Employer-operated eating facilities. (a) In general—(1) Condition for exclusion—(i) General rule. The value... dining room or cafeteria in which meals are served is treated as a separate eating facility, whether each such dining room or cafeteria has its own kitchen or other food-preparation area. (2) Employer-operated...

Operation manual for the INEL on-line mass-separator facility

International Nuclear Information System (INIS)

Anderl, R.A.

1984-06-01

This report is an operation manual for an on-line mass-separator facility which is located in Building 661 at the Test Reactor Area of the Idaho National Engineering Laboratory. The facility provides mass-separated sources of short-lived fission-product radionuclides whose decay properties can be studied using a variety of nuclear spectroscopic techniques. This facility is unique in that it utilizes the gas-jet technique to transport fission products from a 252 Cf source located in a hot cell to the ion source of the mass separator. This document includes the following: (a) a detailed description of the facility, (b) identification of equipment hazards and safety controls, (c) detailed operating procedures for startup, continuous operation and shutdown, (d) operating procedures for the californium hot cell, and (e) an operator's manual for the automated moving tape collector/data acquisition system. 7 references, 16 figures, 8 tables

Comparison of Multi-Scale Digital Elevation Models for Defining Waterways and Catchments Over Large Areas

Science.gov (United States)

Harris, B.; McDougall, K.; Barry, M.

2012-07-01

Digital Elevation Models (DEMs) allow for the efficient and consistent creation of waterways and catchment boundaries over large areas. Studies of waterway delineation from DEMs are usually undertaken over small or single catchment areas due to the nature of the problems being investigated. Improvements in Geographic Information Systems (GIS) techniques, software, hardware and data allow for analysis of larger data sets and also facilitate a consistent tool for the creation and analysis of waterways over extensive areas. However, rarely are they developed over large regional areas because of the lack of available raw data sets and the amount of work required to create the underlying DEMs. This paper examines definition of waterways and catchments over an area of approximately 25,000 km2 to establish the optimal DEM scale required for waterway delineation over large regional projects. The comparative study analysed multi-scale DEMs over two test areas (Wivenhoe catchment, 543 km2 and a detailed 13 km2 within the Wivenhoe catchment) including various data types, scales, quality, and variable catchment input parameters. Historic and available DEM data was compared to high resolution Lidar based DEMs to assess variations in the formation of stream networks. The results identified that, particularly in areas of high elevation change, DEMs at 20 m cell size created from broad scale 1:25,000 data (combined with more detailed data or manual delineation in flat areas) are adequate for the creation of waterways and catchments at a regional scale.

French en engineering and operation rules for plutonium facilities

International Nuclear Information System (INIS)

Bertolotti, G.; Drain, F.; Dubois, G.; Monnatte, J.; Mathieu, P.

1998-01-01

COGEMA is operating large size purifying and conditioning plutonium facilities at LA HAGUE and MOX fuels fabrication plant at Marcoule. A high safety standard is recognised for these facilities. It is mainly based on : - prevention of spreading of radioactive materials to workers and environment by physical barriers ensuring static containment and by a cascade of pressure differentials ensuring dynamic containment, - radiation shielding and remote controlled processes ensuring very low dose to workers, - prevention of criticality accident by criticality control methods and double contingency principle, - prevention of fire risks by control of ignition sources, adequate management of combustible materials, physical separation between zones where there is a risk of fire and the remainder of the facility. The facilities are operated while respecting safety requirements as described in the General Operating Rules. The equipment involved in safety functions are monitored and periodically checked. Continuous improvement by incorporation of feed back of safety experience results in: - effective decrease of exposure to operating staff; - reduction of solid waste, liquid and gaseous effluents; - no significant incident recorded. (author)

Report on operation of nuclear facilities in 1991

International Nuclear Information System (INIS)

1992-06-01

The Slovenian Nuclear Safety Administration (SNSA) prepared a report on nuclear safety in the republic of Slovenia in 1991 as part of its regular practice of reporting on its work to the Government and the National Assembly of the Republic of Slovenia. The report is divided into three thematic chapters covering the activities of the SNSA, the operation of nuclear facilities in Slovenia, the activity of international missions in Slovenia and the operation of nuclear facilities around the world.

Radiological dose assessment from the operation of Daeduk nuclear facilities

Energy Technology Data Exchange (ETDEWEB)

Hwang, Won Tae; Kim, Eun Han; Suh, Kyung Suk; Choi, Young Gil [Korea Atomic Energy Research Institute, Taejon (Korea)

2000-02-01

The objective of this project is to assure the public acceptance for nuclear facilities, and the environmental safety from the operation of Daeduk nuclear facilities, such as HANARO research reactor, nuclear fuel processing facilities and others. For identifying the integrity of their facilities, the maximum individual doses at the site boundary and on the areas with high population density were assessed. Also, the collective doses within radius 80 km from the site were assessed. The radiation impacts for residents around the site from the operation of Daeduk nuclear facilities in 1999 were neglectable. 8 refs., 10 figs., 27 tabs. (Author)

Operating procedures for the Pajarito Site Critical Assembly Facility

International Nuclear Information System (INIS)

Malenfant, R.E.

1983-03-01

Operating procedures consistent with DOE Order 5480.2, Chapter VI, and the American National Standard Safety Guide for the Performance of Critical Experiments are defined for the Pajarito Site Critical Assembly Facility of the Los Alamos National Laboratory. These operating procedures supersede and update those previously published in 1973 and apply to any criticality experiment performed at the facility

Defense Waste Processing Facility radioactive operations -- Part 2, Glass making

International Nuclear Information System (INIS)

Carter, J.T.; Rueter, K.J.; Ray, J.W.; Hodoh, O.

1996-01-01

The Savannah River Site's Defense Waste Processing Facility (DWPF) near Aiken, SC is the nation's first and world's largest vitrification facility. Following a ten year construction period and nearly 3 year non-radioactive test program, the DWPF began radioactive operations in March, 1996. The results of the first 8 months of radioactive operations are presented. Topics include facility production from waste preparation batching to canister filling

Fuel supply shutdown facility interim operational safety requirements

International Nuclear Information System (INIS)

Besser, R.L.; Brehm, J.R.; Benecke, M.W.; Remaize, J.A.

1995-01-01

These Interim Operational Safety Requirements (IOSR) for the Fuel Supply Shutdown (FSS) facility define acceptable conditions, safe boundaries, bases thereof, and management or administrative controls to ensure safe operation. The IOSRs apply to the fuel material storage buildings in various modes (operation, storage, surveillance)

Effect of facility on the operative costs of distal radius fractures.

Science.gov (United States)

Mather, Richard C; Wysocki, Robert W; Mack Aldridge, J; Pietrobon, Ricardo; Nunley, James A

2011-07-01

The purpose of this study was to investigate whether ambulatory surgery centers can deliver lower-cost care and to identify sources of those cost savings. We performed a cost identification analysis of outpatient volar plating for closed distal radius fractures at a single academic medical center. Multiple costs and time measures were taken from an internal database of 130 consecutive patients and were compared by venue of treatment, either an inpatient facility or an ambulatory, stand-alone surgery facility. The relationships between total cost and operative time and multiple variables, including fracture severity, patient age, gender, comorbidities, use of bone graft, concurrent carpal tunnel release, and surgeon experience, were examined, using multivariate analysis and regression modeling to identify other cost drivers or explanatory variables. The mean operative cost was considerably greater at the inpatient facility ($7,640) than at the outpatient facility ($5,220). Cost drivers of this difference were anesthesia services, post-anesthesia care unit, and operating room costs. Total surgical time, nursing time, set-up, and operative times were 33%, 109%, 105%, and 35% longer, respectively, at the inpatient facility. There was no significant difference between facilities for the additional variables, and none of those variables independently affected cost or operative time. The only predictor of cost and time was facility type. This study supports the use of ambulatory stand-alone surgical facilities to achieve efficient resource utilization in the operative treatment of distal radius fractures. We also identified several specific costs and time measurements that differed between facilities, which can serve as potential targets for tertiary facilities to improve utilization. Economic and Decisional Analysis III. Copyright © 2011 American Society for Surgery of the Hand. Published by Elsevier Inc. All rights reserved.

COMPARISON OF MULTI-SCALE DIGITAL ELEVATION MODELS FOR DEFINING WATERWAYS AND CATCHMENTS OVER LARGE AREAS

Directory of Open Access Journals (Sweden)

B. Harris

2012-07-01

Full Text Available Digital Elevation Models (DEMs allow for the efficient and consistent creation of waterways and catchment boundaries over large areas. Studies of waterway delineation from DEMs are usually undertaken over small or single catchment areas due to the nature of the problems being investigated. Improvements in Geographic Information Systems (GIS techniques, software, hardware and data allow for analysis of larger data sets and also facilitate a consistent tool for the creation and analysis of waterways over extensive areas. However, rarely are they developed over large regional areas because of the lack of available raw data sets and the amount of work required to create the underlying DEMs. This paper examines definition of waterways and catchments over an area of approximately 25,000 km2 to establish the optimal DEM scale required for waterway delineation over large regional projects. The comparative study analysed multi-scale DEMs over two test areas (Wivenhoe catchment, 543 km2 and a detailed 13 km2 within the Wivenhoe catchment including various data types, scales, quality, and variable catchment input parameters. Historic and available DEM data was compared to high resolution Lidar based DEMs to assess variations in the formation of stream networks. The results identified that, particularly in areas of high elevation change, DEMs at 20 m cell size created from broad scale 1:25,000 data (combined with more detailed data or manual delineation in flat areas are adequate for the creation of waterways and catchments at a regional scale.

Development of operation control expert system for off-site facilities

Energy Technology Data Exchange (ETDEWEB)

Takeuchi, Masaaki

1988-09-01

Concerning off-site facilities of oil refinary, changes of facilities and equipment are frequently made in order to cope flexibly with the market trends and changes of the social environment. In addition, it is desirable to introduce computerization into control and manipulation of off-site facilities for its fast, safe and sure operation. In order to achieve the above, against the existing exclusively control-oriented system, it is necessary to add the processing and generating functions to combinations between valves to be shut and piping as well as equipment to be used along the whole extent of the oil flow in the system and to add the function which makes verification of the above functions easy through a dialogue between users and the system. In order to realize the above, Cosmo Oil and Yokokawa Denki developed jointly an operation control expert system for off-site facilities and the system started its actual operation from October 1986. This article is an outline of the system. The result of its actual operation for one and a half years since its inception showed that the system was operated only by the staff responsible for the operation of the facilities, the workload was reduced to 1/3-1/4 of the workload before the adoption of the system and absolutely no omission of work nor mistake was experienced. (2 figs)

Spent Nuclear Fuel (SNF) Cold Vacuum Drying (CVD) Facility Operations Manual

Energy Technology Data Exchange (ETDEWEB)

IRWIN, J.J.

1999-07-02

This document provides the Operations Manual for the Cold Vacuum Drying Facility (CVDF). The Manual was developed in conjunction with HNF-553, Spent Nuclear Fuel Project Final Safety Analysis Report Annex B--Cold Vacuum Drying Facility. The HNF-SD-SNF-DRD-002, 1999, Cold Vacuum Drying Facility Design Requirements, Rev. 4, and the CVDF Final Design Report. The Operations Manual contains general descriptions of all the process, safety and facility systems in the CVDF, a general CVD operations sequence and references to the CVDF System Design Descriptions (SDDs). This manual has been developed for the SNFP Operations Organization and shall be updated, expanded, and revised in accordance with future design, construction and startup phases of the CVDF until the CVDF final ORR is approved.

Developing operating procedures for a low-level radioactive waste disposal facility

Energy Technology Data Exchange (ETDEWEB)

Sutherland, A.A.; Miner, G.L.; Grahn, K.F.; Pollard, C.G. [Rogers and Associates Engineering Corp., Salt Lake City, UT (United States)

1993-10-01

This document is intended to assist persons who are developing operating and emergency procedures for a low-level radioactive waste disposal facility. It provides 25 procedures that are considered to be relatively independent of the characteristics of a disposal facility site, the facility design, and operations at the facility. These generic procedures should form a good starting point for final procedures on their subjects for the disposal facility. In addition, this document provides 55 annotated outlines of other procedures that are common to disposal facilities. The annotated outlines are meant as checklists to assist the developer of new procedures.

Developing operating procedures for a low-level radioactive waste disposal facility

International Nuclear Information System (INIS)

Sutherland, A.A.; Miner, G.L.; Grahn, K.F.; Pollard, C.G.

1993-10-01

This document is intended to assist persons who are developing operating and emergency procedures for a low-level radioactive waste disposal facility. It provides 25 procedures that are considered to be relatively independent of the characteristics of a disposal facility site, the facility design, and operations at the facility. These generic procedures should form a good starting point for final procedures on their subjects for the disposal facility. In addition, this document provides 55 annotated outlines of other procedures that are common to disposal facilities. The annotated outlines are meant as checklists to assist the developer of new procedures

Operational Radiation Protection in Synchrotron Light and Free Electron Laser Facilities

Energy Technology Data Exchange (ETDEWEB)

Liu, James C.; Rokni, Sayed H.; /SLAC; Vylet, Vaclav; /Jefferson Lab

2009-12-11

The 3rd generation synchrotron radiation (SR) facilities are storage ring based facilities with many insertion devices and photon beamlines, and have low injection beam power (< few tens of watts), but extremely high stored beam power ({approx} 1 GW). The 4th generation x-ray free electron laser (FEL) facilities are based on an electron Linac with a long undulator and have high injection beam power (a few kW). Due to its electron and photon beam characteristics and modes of operation, storage ring and photon beamlines have unique safety aspects, which are the main subjects of this paper. The shielding design limits, operational modes, and beam losses are first reviewed. Shielding analysis (source terms and methodologies) and interlocked safety systems for storage ring and photon beamlines (including SR and gas bremsstrahlung) are described. Specific safety issues for storage ring top-off injection operation and FEL facilities are discussed. The operational safety program, e.g., operation authorization, commissioning, training, and radiation measurements, for SR facilities is also presented.

Operational Radiation Protection in Synchrotron Light and Free Electron Laser Facilities

International Nuclear Information System (INIS)

Liu, James C.; Rokni, Sayed H.; Vylet, Vaclav

2009-01-01

The 3rd generation synchrotron radiation (SR) facilities are storage ring based facilities with many insertion devices and photon beamlines, and have low injection beam power (< few tens of watts), but extremely high stored beam power (∼ 1 GW). The 4th generation x-ray free electron laser (FEL) facilities are based on an electron Linac with a long undulator and have high injection beam power (a few kW). Due to its electron and photon beam characteristics and modes of operation, storage ring and photon beamlines have unique safety aspects, which are the main subjects of this paper. The shielding design limits, operational modes, and beam losses are first reviewed. Shielding analysis (source terms and methodologies) and interlocked safety systems for storage ring and photon beamlines (including SR and gas bremsstrahlung) are described. Specific safety issues for storage ring top-off injection operation and FEL facilities are discussed. The operational safety program, e.g., operation authorization, commissioning, training, and radiation measurements, for SR facilities is also presented.

Facility Operations 1993 fiscal year work plan: WBS 1.3.1

Energy Technology Data Exchange (ETDEWEB)

1992-11-01

The Facility Operations program is responsible for the safe, secure, and environmentally sound management of several former defense nuclear production facilities, and for the nuclear materials in those facilities. As the mission for Facility Operations plants has shifted from production to support of environmental restoration, each plant is making a transition to support the new mission. The facilities include: K Basins (N Reactor fuel storage); N Reactor; Plutonium-Uranium Reduction Extraction (PUREX) Plant; Uranium Oxide (UO{sub 3}) Plant; 300 Area Fuels Supply (N Reactor fuel supply); Plutonium Finishing Plant (PFP).

Facility Operations 1993 fiscal year work plan: WBS 1.3.1

International Nuclear Information System (INIS)

1992-11-01

The Facility Operations program is responsible for the safe, secure, and environmentally sound management of several former defense nuclear production facilities, and for the nuclear materials in those facilities. As the mission for Facility Operations plants has shifted from production to support of environmental restoration, each plant is making a transition to support the new mission. The facilities include: K Basins (N Reactor fuel storage); N Reactor; Plutonium-Uranium Reduction Extraction (PUREX) Plant; Uranium Oxide (UO 3 ) Plant; 300 Area Fuels Supply (N Reactor fuel supply); Plutonium Finishing Plant (PFP)

Framework for Integrating Safety, Operations, Security, and Safeguards in the Design and Operation of Nuclear Facilities

Energy Technology Data Exchange (ETDEWEB)

Darby, John L. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Horak, Karl Emanuel [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); LaChance, Jeffrey L. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Tolk, Keith Michael [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Whitehead, Donnie Wayne [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)

2007-10-01

The US is currently on the brink of a nuclear renaissance that will result in near-term construction of new nuclear power plants. In addition, the Department of Energy’s (DOE) ambitious new Global Nuclear Energy Partnership (GNEP) program includes facilities for reprocessing spent nuclear fuel and reactors for transmuting safeguards material. The use of nuclear power and material has inherent safety, security, and safeguards (SSS) concerns that can impact the operation of the facilities. Recent concern over terrorist attacks and nuclear proliferation led to an increased emphasis on security and safeguard issues as well as the more traditional safety emphasis. To meet both domestic and international requirements, nuclear facilities include specific SSS measures that are identified and evaluated through the use of detailed analysis techniques. In the past, these individual assessments have not been integrated, which led to inefficient and costly design and operational requirements. This report provides a framework for a new paradigm where safety, operations, security, and safeguards (SOSS) are integrated into the design and operation of a new facility to decrease cost and increase effectiveness. Although the focus of this framework is on new nuclear facilities, most of the concepts could be applied to any new, high-risk facility.

Training manual for process operation and management of radioactive waste treatment facility

Energy Technology Data Exchange (ETDEWEB)

Shon, J. S.; Kim, K. J.; Ahn, S. J. [and others

2004-12-01

Radioactive Waste Treatment Facility (RWTF) has been operating for safe and effective treatment of radioactive wastes generated in the Korea Atomic Energy Research Institute (KAERI). In RWTF, there are evaporation, bituminization and solar evaporation processes for liquid waste, solid waste treatment process and laundry process. As other radioactive waste treatment facilities in foreign countries, the emergency situation such as fire and overflow of liquid waste can be taken place during the operation and result in the spread of contamination of radioactivity. So, easy and definite operating procedure is necessary for the safe operation of the facility. This manual can be available as easy and concise training materials for new employees and workers dispatched from service agency. Especially, in case of emergency urgently occurred during operation, everyone working in the facility can quickly stop the facility following this procedure.

Training manual for process operation and management of radioactive waste treatment facility

International Nuclear Information System (INIS)

Shon, J. S.; Kim, K. J.; Ahn, S. J.

2004-12-01

Radioactive Waste Treatment Facility (RWTF) has been operating for safe and effective treatment of radioactive wastes generated in the Korea Atomic Energy Research Institute (KAERI). In RWTF, there are evaporation, bituminization and solar evaporation processes for liquid waste, solid waste treatment process and laundry process. As other radioactive waste treatment facilities in foreign countries, the emergency situation such as fire and overflow of liquid waste can be taken place during the operation and result in the spread of contamination of radioactivity. So, easy and definite operating procedure is necessary for the safe operation of the facility. This manual can be available as easy and concise training materials for new employees and workers dispatched from service agency. Especially, in case of emergency urgently occurred during operation, everyone working in the facility can quickly stop the facility following this procedure

Socio-cultural impacts of construction and regulation of the waterway of Oulujoki river

International Nuclear Information System (INIS)

Ruotsala, H.

1992-01-01

The purpose of study was to clarify the socio-cultural impacts of the regulation and construction of Oulujoki river on the everyday life of people. Changes in work and livelihood, living and living satisfaction, and leisure time and recreation are considered as variables. Quantitative and qualitative methods were combined in the study. The principal study material is composed of answers to a questionnaire and of 109 thematic interviews on the topic. The hold of the study is phenomenological-hermeneutical, with the intention to interpret the matter from the viewpoint of the attitudes and requirements of the waterway users. The theoretical frame of reference was culture-ecological point of view and adaptive process. The emphasis of the study is on sociocultural adaptation. The attitude towards waterway construction and regulation was dependent on the background of the person interviewed. The attitude was considered e.g. by various interest groups and professional groups, such as farmers, inhabitants on the shore, recreation users, fishermen, municipal elected officials. Other important variables were age, family stage and sex. Big local differences in the attitudes could also be found. While prevailing values in society and peoples' modes of living are changing, also the attitude towards waterway and changes caused by waterway construction has changed in the region studied. The impacts on the sources of livelihood are minor for the moment, the impacts on living satisfaction and recreations are significant. While leisure time is increasing the recreation value of waterway increases, too. At the construction stage of the river, the economical and productional advantages took priority, and then no attention was paid to recreational use

Application of GIS tools in determining the navigability of waterways

Science.gov (United States)

Nadolny, Grzegorz; Rabant, Hubert; Szatten, Dawid

2017-11-01

This article presents the results of a research conducted on Lower Noteć river for the application of geographic information system (GIS) tools. The study consisted of longitudinal profile soundings of navigable route combined with statistical analysis of water levels. GIS software - ArcMap v. 10.0 was used to perform analysis of changes in waterway depth depending on hydrological conditions. A mileage of waterway sections was specified depending on whether they met or did not meet classification requirements in accordance with Polish law. The application of spatial data of Lower Noteć river developed for the purpose of the article is presented. Conducted analyses and obtained results demonstrate the importance of GIS tools in inland navigation studies.

Improvement of safety approach for accident during operation of LILW disposal facility: Application for operational safety assessment of the near-surface LILW disposal facility in Korea

Energy Technology Data Exchange (ETDEWEB)

Kim, Hyun Joo; Kim, Min Seong; Park, Jin Beak [Korea Radioactive Waste Agency, Daejeon (Korea, Republic of)

2017-06-15

To evaluate radiological impact from the operation of a low- and intermediate-level radioactive waste disposal facility, a logical presentation and explanation of expected accidental scenarios is essential to the stakeholders of the disposal facility. The logical assessment platform and procedure, including analysis of the safety function of disposal components, operational hazard analysis, operational risk analysis, and preparedness of remedial measures for operational safety, are improved in this study. In the operational risk analysis, both design measures and management measures are suggested to make it possible to connect among design, operation, and safety assessment within the same assessment platform. For the preparedness of logical assessment procedure, classifcation logic of an operational accident is suggested based on the probability of occurrence and consequences of assessment results. The improved assessment platform and procedure are applied to an operational accident analysis of the Korean low- and intermediate-level radioactive waste disposal facility and partly presented in this paper.

Improvement of safety approach for accident during operation of LILW disposal facility: Application for operational safety assessment of the near-surface LILW disposal facility in Korea

International Nuclear Information System (INIS)

Kim, Hyun Joo; Kim, Min Seong; Park, Jin Beak

2017-01-01

To evaluate radiological impact from the operation of a low- and intermediate-level radioactive waste disposal facility, a logical presentation and explanation of expected accidental scenarios is essential to the stakeholders of the disposal facility. The logical assessment platform and procedure, including analysis of the safety function of disposal components, operational hazard analysis, operational risk analysis, and preparedness of remedial measures for operational safety, are improved in this study. In the operational risk analysis, both design measures and management measures are suggested to make it possible to connect among design, operation, and safety assessment within the same assessment platform. For the preparedness of logical assessment procedure, classifcation logic of an operational accident is suggested based on the probability of occurrence and consequences of assessment results. The improved assessment platform and procedure are applied to an operational accident analysis of the Korean low- and intermediate-level radioactive waste disposal facility and partly presented in this paper

The Valduc waste incineration facility starts operations (iris process)

International Nuclear Information System (INIS)

Chateauvieux, H.; Guiberteuau, P.; Longuet, T.; Lannaud, J.; Lorich, M.

1998-01-01

In the operation of its facilities the Valduc Research Center produces alpha-contaminated solid waste and thus decided to build an incineration facility to treat the most contaminated combustible waste. The process selected for waste incineration is the IRIS process developed by the CEA at the Marcoule Nuclear Research Center. The Valduc Center asked SGN to build the incineration facility. The facility was commissioned in late 1996, and inactive waste incineration campaigns were run in 1997. The operator conducted tests with calibrated radioactive sources to qualify the systems for measuring holdup of active material from outside the equipment. Chlorinated waste incineration test runs were performed using the phosphatizing process developed by the Marcoule Research Center. Inspections performed after these incineration runs revealed the complete absence of corrosion in the equipment. Active commissioning of the facility is scheduled for mid-1998. The Valduc incinerator is the first industrial application of the IRIS process. (author)

78 FR 29393 - University of Missouri-Columbia Facility Operating License No. R-103

Science.gov (United States)

2013-05-20

... Facility Operating License No. R-103 AGENCY: Nuclear Regulatory Commission. ACTION: License renewal... the renewal of Facility Operating License No. R-103 (``Application''), which currently authorizes the... application for the renewal of Facility Operating License No. R-103, which, currently authorizes the licensee...

Establishment and Operation of User Facilities

International Nuclear Information System (INIS)

Kim, Kye Ryung; Park, B. S.; Lim, Y. K.; Lee, S. K.; Jung, J. P.

2005-08-01

The final goal of this project is to establish the proton beam user facility which can offer the suitable proton beam for the user's demand. In the first phase we developed the key technologies that were required for the establishment of 20MeV and 100MeV proton user facilities. The user's demand survey was also achieved, and the test user facility was established on the results of the demand survey. Using the test facility, the users performed their pilot studies. Now, we have finished the conceptual design for 20MeV proton user facility. During the first phase we performed the user's demand survey and produced many materials related to the proton beam utilizations in domestic or abroad. The survey results were reflected on the establishment of the test user facility and the conceptual design of 20MeV/100MeV proton beam user facilities. We have developed the key technologies which concern to beam energy control, flux control, uniform irradiation, dose and uniformity measurement, proton energy measurement, SOBP(Spread-out Bragg Peak) system using a rotating range modulator, and carried out the conceptual design of 20MeV proton user facility. The test user facility has been constructed and operated for both verifying the developed key technologies and performing the user's preliminary experiments. 45MeV low flux user facility was constructed in 2003 and has performed a lot of irradiation experiments. The development of 1.8MeV test user facility was completed. Also the low energy user facility that KAERI kept was upgraded and used for many users. Therefore, we provided our users with various beams. On the other hand, the following activities were carried out, such as, inviting the oversea researchers, giving support to users to use the beam in domestic and abroad, discussing the beam utilization technologies by visiting the foreign user facilities, etc

First operations of the LNS heavy ions facility

International Nuclear Information System (INIS)

Calabretta, L.; Ciavola, G.; Cuttone, G.; Gammino, S.; Gmaj, P.; Migneco, E.; Raia, G.; Rifuggiato, D.; Rovelli, A.; Sura, J.; Scuderi, V.; Acerbi, E.; Alessandria, F.; Bellomo, G.; Bosotti, A.; Martinis, C. de; Giove, D.; Michelato, P.; Pagani, C.; Rossi, L.

1996-01-01

A heavy ion facility is now available at laboratorio nazionale del Sud (LNS) of Catania. It can deliver beams with an energy up to 100 MeV/amu. The facility is based on a 15 MV HVEC tandem and a K=800 superconducting cyclotron as booster. During the last year, the facility came into operation. A 58 Ni beam delivered by the tandem has been radially injected in the SC and then has been accelerated and extracted at 30 MeV/amu. In this paper the status of the facility together with the experience gained during the commissioning will be extensively reported. (orig.)

Operational status of nuclear facilities in Japan. 2012 edition

International Nuclear Information System (INIS)

2012-01-01

This document is a compilation which provides an outline of the administration of nuclear facility safety regulations as well as various data including operational status, the status of periodical and safety inspections, the status of issues, and radiation management on nuclear power reactor facilities, reactor facilities in the research and development stage, and fabrication, reprocessing, disposal, and storage facilities in fiscal year 2011 (from April 2011 to March 2012). (J.P.N.)

Embracing Safe Ground Test Facility Operations and Maintenance

Science.gov (United States)

Dunn, Steven C.; Green, Donald R.

2010-01-01

Conducting integrated operations and maintenance in wind tunnel ground test facilities requires a balance of meeting due dates, efficient operation, responsiveness to the test customer, data quality, effective maintenance (relating to readiness and reliability), and personnel and facility safety. Safety is non-negotiable, so the balance must be an "and" with other requirements and needs. Pressure to deliver services faster at increasing levels of quality in under-maintained facilities is typical. A challenge for management is to balance the "need for speed" with safety and quality. It s especially important to communicate this balance across the organization - workers, with a desire to perform, can be tempted to cut corners on defined processes to increase speed. Having a lean staff can extend the time required for pre-test preparations, so providing a safe work environment for facility personnel and providing good stewardship for expensive National capabilities can be put at risk by one well-intending person using at-risk behavior. This paper documents a specific, though typical, operational environment and cites management and worker safety initiatives and tools used to provide a safe work environment. Results are presented and clearly show that the work environment is a relatively safe one, though still not good enough to keep from preventing injury. So, the journey to a zero injury work environment - both in measured reality and in the minds of each employee - continues. The intent of this paper is to provide a benchmark for others with operational environments and stimulate additional sharing and discussion on having and keeping a safe work environment.

Significance of Waterway Navigation Positioning Systems On Ship's Manoeuvring Safety

Science.gov (United States)

Galor, W.

The main goal of navigation is to lead the ship to the point of destination safety and efficiently. Various factors may affect ship realisating this process. The ship movement on waterway are mainly limited by water area dimensions (surface and depth). These limitations cause the requirement to realise the proper of ship movement trajectory. In case when this re requirement cant't fulfil then marine accident may happend. This fact is unwanted event caused losses of human health and life, damage or loss of cargo and ship, pollution of natural environment, damage of port structures or blocking the port of its ports and lost of salvage operation. These losses in same cases can be catas- trophical especially while e.i. crude oil spilling could be place. To realise of safety navigation process is needed to embrace the ship's movement trajectory by waterways area. The ship's trajectory is described by manoeuvring lane as a surface of water area which is require to realise of safety ship movement. Many conditions affect to ship manoeuvring line. The main are following: positioning accuracy, ship's manoeuvring features and phenomena's of shore and ship's bulk common affecting. The accuracy of positioning system is most important. This system depends on coast navigation mark- ing which can range many kinds of technical realisation. Mainly used systems based on lights (line), radionavigation (local system or GPS, DGPS), or radars. If accuracy of positiong is higer, then safety of navigation is growing. This article presents these problems exemplifying with approaching channel to ports situated on West Pomera- nian water region.

Operating a production facility without a CO and O agreement

International Nuclear Information System (INIS)

Smith, M. R.

2000-01-01

Issues that arise when an oil or natural gas facility is operated without a specific construction, ownership and operating (CO and O) agreement was explored. The lack of such an agreement may be due to the parties' inability to reach agreement, reliance on the land operating agreement, or the lack of diligent follow-up on the drafting, revision and execution of operating agreements. The paper examines the nature of ownership interests that obtain in the absence of a CO and O, the common situation in respect to CO and O agreements where the document has been circulated but has not been signed by the owners. A number of actual cases were cited to illustrate the effects of such an omission. It was concluded that ideally, a fully executed CO and O for each facility which deals specifically with the owners involved with the particular facility is the best of all worlds. However given the nature of some facilities, the expense, time and effort required to prepare and execute a separate CO and O, it is frequently omitted; in such situations it is convenient to fall back on the 1990 Operating Procedure of CAPL, which while general in nature and cannot adequately deal with every situation, deals with many common problems associated with the operation of facilities. It is recommended that even if a complete CO and O agreement cannot be executed, interim binding agreements should be used to avoid uncertainty until such time as a complete agreement can be finalized. A clause-by-clause comparison of the 1990 CAPL Operating Procedure and a 1996 model CO and O agreement, prepared by the Petroleum Joint Venture Association (PJVA), is appended

Operating experience of steam generator test facility

International Nuclear Information System (INIS)

Sureshkumar, V.A.; Madhusoodhanan, G.; Noushad, I.B.; Ellappan, T.R.; Nashine, B.K.; Sylvia, J.I.; Rajan, K.K.; Kalyanasundaram, P.; Vaidyanathan, G.

2006-01-01

Steam Generator (SG) is the vital component of a Fast Reactor. It houses both water at high pressure and sodium at low pressure separated by a tube wall. Any damage to this barrier initiates sodium water reaction that could badly affect the plant availability. Steam Generator Test Facility (SGTF) has been set up in Indira Gandhi Centre for Atomic Research (IGCAR) to test sodium heated once through steam generator of 19 tubes similar to the PFBR SG dimension and operating conditions. The facility is also planned as a test bed to assess improved designs of the auxiliary equipments used in Fast Breeder Reactors (FBR). The maximum power of the facility is 5.7 MWt. This rating is arrived at based on techno economic consideration. This paper covers the performance of various equipments in the system such as Electro magnetic pumps, Centrifugal sodium pump, in-sodium hydrogen meters, immersion heaters, and instrumentation and control systems. Experience in the system operation, minor modifications, overall safety performance, and highlights of the experiments carried out etc. are also brought out. (author)

200 Area treated effluent disposal facility operational test report

International Nuclear Information System (INIS)

Crane, A.F.

1995-01-01

This document reports the results of the 200 Area Treated Effluent Disposal Facility (200 Area TEDF) operational testing activities. These completed operational testing activities demonstrated the functional, operational and design requirements of the 200 Area TEDF have been met

Technological Advances, Human Performance, and the Operation of Nuclear Facilities

Science.gov (United States)

Corrado, Jonathan K.

Many unfortunate and unintended adverse industrial incidents occur across the United States each year, and the nuclear industry is no exception. Depending on their severity, these incidents can be problematic for people, the facilities, and surrounding environments. Human error is a contributing factor in many such incidents. This dissertation first explored the hypothesis that technological changes that affect how operators interact within the systems of the nuclear facilities exacerbate the cost of incidents caused by human error. I conducted a review of nuclear incidents in the United States from 1955 through 2010 that reached Level 3 (serious incident) or higher on the International Nuclear Events Scale (INES). The cost of each incident at facilities that had recently undergone technological changes affecting plant operators' jobs was compared to the cost of events at facilities that had not undergone changes. A t-test determined a statistically significant difference between the two groups, confirming the hypothesis. Next, I conducted a follow-on study to determine the impact of the incorporation of new technologies into nuclear facilities. The data indicated that spending more money on upgrades increased the facility's capacity as well as the number of incidents reported, but the incident severity was minor. Finally, I discuss the impact of human error on plant operations and the impact of evolving technology on the 21st-century operator, proposing a methodology to overcome these challenges by applying the systems engineering process.

First operations of the LNS heavy ions facility

Energy Technology Data Exchange (ETDEWEB)

Calabretta, L. [INFN-LNS, Catania (Italy); Ciavola, G. [INFN-LNS, Catania (Italy); Cuttone, G. [INFN-LNS, Catania (Italy); Gammino, S. [INFN-LNS, Catania (Italy); Gmaj, P. [INFN-LNS, Catania (Italy); Migneco, E. [INFN-LNS, Catania (Italy); Raia, G. [INFN-LNS, Catania (Italy); Rifuggiato, D. [INFN-LNS, Catania (Italy); Rovelli, A. [INFN-LNS, Catania (Italy); Sura, J. [INFN-LNS, Catania (Italy); Scuderi, V. [INFN-LNS, Catania (Italy); Acerbi, E. [INFN-sezione di Milano (Italy)]|[Univ. degli studi di Milano, Lab. LASA (Italy); Alessandria, F. [INFN-sezione di Milano (Italy)]|[Univ. degli studi di Milano, Lab. LASA (Italy); Bellomo, G. [INFN-sezione di Milano (Italy)]|[Univ. degli studi di Milano, Lab. LASA (Italy); Bosotti, A. [INFN-sezione di Milano (Italy)]|[Univ. degli studi di Milano, Lab. LASA (Italy); Martinis, C. de [INFN-sezione di Milano (Italy)]|[Univ. degli studi di Milano, Lab. LASA (Italy); Giove, D. [INFN-sezione di Milano (Italy)]|[Univ. degli studi di Milano, Lab. LASA (Italy); Michelato, P. [INFN-sezione di Milano (Italy)]|[Univ. degli studi di Milano, Lab. LASA (Italy); Pagani, C. [INFN-sezione di Milano (Italy)]|[Univ. degli studi di Milano, Lab. LASA (Italy); Rossi, L. [INFN-sezione di Milano (Italy)]|[Univ. degli studi di Milano, Lab. LASA (Italy)

1996-11-11

A heavy ion facility is now available at laboratorio nazionale del Sud (LNS) of Catania. It can deliver beams with an energy up to 100 MeV/amu. The facility is based on a 15 MV HVEC tandem and a K=800 superconducting cyclotron as booster. During the last year, the facility came into operation. A {sup 58}Ni beam delivered by the tandem has been radially injected in the SC and then has been accelerated and extracted at 30 MeV/amu. In this paper the status of the facility together with the experience gained during the commissioning will be extensively reported. (orig.).

Occupational and Public Exposure During Normal Operation of Radioactive Waste Disposal Facilities

Directory of Open Access Journals (Sweden)

M. V. Vedernikova

2017-01-01

Full Text Available This paper focuses on occupational and public exposure during operation of disposal facilities receiving liquid and solid radioactive waste of various classes and provides a comparative analysis of the relevant doses: actual and calculated at the design stage. Occupational and public exposure study presented in this paper covers normal operations of a radioactive waste disposal facility receiving waste. Results: Analysis of individual and collective occupational doses was performed based on data collected during operation of near-surface disposal facilities for short-lived intermediate-, lowand very low-level waste in France, as well as nearsurface disposal facilities for long-lived waste in Russia. Further analysis of occupational and public doses calculated at the design stage was completed covering a near-surface disposal facility in Belgium and deep disposal facilities in the United Kingdom and the Nizhne-Kansk rock massive (Russia. The results show that engineering and technical solutions enable almost complete elimination of internal occupational exposure, whereas external exposure doses would fall within the range of values typical for a basic nuclear facility. Conclusion: radioactive waste disposal facilities being developed, constructed and operated meet the safety requirements effective in the Russian Federation and consistent with relevant international recommendations. It has been found that individual occupational exposure doses commensurate with those received by personnel of similar facilities abroad. Furthermore, according to the forecasts, mean individual doses for personnel during radioactive waste disposal would be an order of magnitude lower than the dose limit of 20 mSv/year. As for the public exposure, during normal operation, potential impact is virtually impossible by delaminating boundaries of a nuclear facility sanitary protection zone inside which the disposal facility is located and can be solely attributed to the use

Operation technology of the ventilation system of the radioactive waste treatment facility(II) - Design and operation note

Energy Technology Data Exchange (ETDEWEB)

Lee, K. M.; Lee, B. C.; Bae, S. M. [Korea Atomic Energy Research Institute, Taejon (Korea)

1999-12-01

As the radioactive waste treatment work, such as compaction and/or solidification of wastes, are done directly by the workers in the Radioactive Waste Treatment Facility, the reasonable design and operation of the ventilation system is essential. In this report, the design criteria and specification of the ventilation equipment, system operation method are described for the effective design and operation of ventilation system in the radioactive waste treatment facility. And the anti-vibration work which was done in the Radioactive Waste Treatment Facility in KAERI to reduce the effect of vibration due to the continuous operation of big rotational equipment, the intake fans and the exhaust fans, are described in the report. 11 refs., 10 figs., 12 tabs. (Author)

Confirming competence of operators - A regulatory approach to fuel cycle facilities

International Nuclear Information System (INIS)

Vesely, M.; Sigetich, J.

2013-01-01

For the past 40 years the Canadian Nuclear Safety Commission (CNSC), formerly the Atomic Energy Control Board, has certified workers in nuclear facilities. The requirement for certified personnel has ensured that workers assigned to positions that have a direct impact on the safe operation of the facility are fully qualified to perform their duties. This certification regime is defined in the regulatory framework under which the CNSC operates. Traditionally, this certification regime has been applied to Reactor Operators, Shift Supervisors and Health Physicists in Nuclear Power Plants and research reactors as well as to Exposure Device Operators who use nuclear substances for the purposes of industrial radiography. Stemming from progress made in implementing risk-informed regulatory oversight activities as well as a formal suggestion from the International Atomic Energy Agency - International Regulatory Review Service (IRRS) conducted on the CNSC in 2009, a regulatory approach to confirming the competence of Operators at Fuel Cycle Facilities has been initiated by CNSC staff. In the first stage of the implementation of this new regulatory approach, the CNSC had Cameco Corporation implement a formal internal qualification programme for the UF6 Operators at its Port Hope Conversion Facility (PHCF) in Port Hope, Ontario. In the future, following a review of the results of the qualification programme at the PHCF, the CNSC staff will evaluate the need for the application of a similar regulatory approach to confirm the competence of the Operators at other Fuel Cycle Facilities in Canada. (authors)

77 FR 5398 - Safety Zone; Atlantic Intracoastal Waterway, Vicinity of Marine Corps Base, Camp Lejeune, NC

Science.gov (United States)

2012-02-03

...-AA00 Safety Zone; Atlantic Intracoastal Waterway, Vicinity of Marine Corps Base, Camp Lejeune, NC... zone on the Atlantic Intracoastal Waterway (AICW) adjacent to Marine Corps Base (MCB) Camp Lejeune..., Vicinity of Marine Corps Base, Camp Lejeune, NC in the Federal Register (77 FR 1431). We received no...

Design and operation of the Surry Radwaste Facility

International Nuclear Information System (INIS)

Morris, L.L.; Halverson, W.C.

1993-01-01

In September 1991, Virginia Power started processing radioactive waste with a new Radwaste Facility at the Surry Power Station near Norfolk, Virginia. The Surry Radwaste Facility (SRF) was designed to process and store liquid waste, laundry waste, dry active waste, radioactive filters and spent ion-exchange resin. It also provides on-site decontamination services and a fully equipped hot machine shop. The NRC has recognized that the amount of planning and design, and the attention to detail, that was expended on the SRF Project in order to minimize personnel exposure and ensure efficient operation, is a licensee strength. Through its first year of operation, the facility has proven very successful. Using evaporation and demineralization, over 30 million liters of liquid have been released with no chemical impurities or detectable radioactivity (excluding tritium). Over 623,000 liters of concentrated boric acid waste liquid have been processed with the Bitumen Solidification System yielding 139,880 liters (660 drums) of low level Class A-Stable waste. Additional economic benefits will be realized as the effectiveness of the processing systems continues to improve due to increased operational experience and ergonomics

Spent Nuclear Fuel (SNF) Project Cold Vacuum Drying (CVD) Facility Operations Manual

Energy Technology Data Exchange (ETDEWEB)

IRWIN, J.J.

2000-02-03

This document provides the Operations Manual for the Cold Vacuum Drying Facility (CVDF). The Manual was developed in conjunction with HNF-SD-SNF-SAR-002, Safety Analysis Report for the Cold Vacuum Drying Facility, Phase 2, Supporting Installation of the Processing Systems (Garvin 1998) and, the HNF-SD-SNF-DRD-002, 1997, Cold Vacuum Drying Facility Design Requirements, Rev. 3a. The Operations Manual contains general descriptions of all the process, safety and facility systems in the CVDF, a general CVD operations sequence, and has been developed for the spent nuclear fuel project (SNFP) Operations Organization and shall be updated, expanded, and revised in accordance with future design, construction and startup phases of the CVDF until the CVDF final ORR is approved.

Spent Nuclear Fuel (SNF) Cold Vacuum Drying (CVD) Facility Operations Manual; FINAL

International Nuclear Information System (INIS)

IRWIN, J.J.

1999-01-01

This document provides the Operations Manual for the Cold Vacuum Drying Facility (CVDF). The Manual was developed in conjunction with HNF-553, Spent Nuclear Fuel Project Final Safety Analysis Report Annex B-Cold Vacuum Drying Facility. The HNF-SD-SNF-DRD-002, 1999, Cold Vacuum Drying Facility Design Requirements, Rev. 4, and the CVDF Final Design Report. The Operations Manual contains general descriptions of all the process, safety and facility systems in the CVDF, a general CVD operations sequence and references to the CVDF System Design Descriptions (SDDs). This manual has been developed for the SNFP Operations Organization and shall be updated, expanded, and revised in accordance with future design, construction and startup phases of the CVDF until the CVDF final ORR is approved

Spent Nuclear Fuel (SNF) Project Cold Vacuum Drying (CVD) Facility Operations Manual

International Nuclear Information System (INIS)

IRWIN, J.J.

2000-01-01

This document provides the Operations Manual for the Cold Vacuum Drying Facility (CVDF). The Manual was developed in conjunction with HNF-SD-SNF-SAR-002, Safety Analysis Report for the Cold Vacuum Drying Facility, Phase 2, Supporting Installation of the Processing Systems (Garvin 1998) and, the HNF-SD-SNF-DRD-002, 1997, Cold Vacuum Drying Facility Design Requirements, Rev. 3a. The Operations Manual contains general descriptions of all the process, safety and facility systems in the CVDF, a general CVD operations sequence, and has been developed for the spent nuclear fuel project (SNFP) Operations Organization and shall be updated, expanded, and revised in accordance with future design, construction and startup phases of the CVDF until the CVDF final ORR is approved

ORNL Trusted Corridors Project: Watts Bar Dam Inland Waterway Project

Energy Technology Data Exchange (ETDEWEB)

Walker, Randy M [ORNL; Gross, Ian G [ORNL; Smith, Cyrus M [ORNL; Hill, David E [ORNL

2011-11-01

Radiation has existed everywhere in the environment since the Earth's formation - in rocks, soil, water, and plants. The mining and processing of naturally occurring radioactive materials for use in medicine, power generation, consumer products, and industry inevitably generate emissions and waste. Radiological measuring devices have been used by industry for years to measure for radiation in undesired locations or simply identify radioactive materials. Since the terrorist attacks on the United States on 9-11-01 these radiation measuring devices have proliferated in many places in our nation's commerce system. DOE, TVA, the Army Corps and ORNL collaborated to test the usefulness of these devices in our nation's waterway system on this project. The purpose of the Watts Bar Dam ORNL Trusted Corridors project was to investigate the security, safety and enforcement needs of local, state and federal government entities for state-of-the-art sensor monitoring in regards to illegal cargo including utilization of the existing infrastructure. TVA's inland waterways lock system is a recognized and accepted infrastructure by the commercial carrier industry. Safety Monitoring activities included tow boat operators, commercial barges and vessels, recreational watercraft and their cargo, identification of unsafe vessels and carriers, and, monitoring of domestic and foreign commercial vessels and cargo identification. Safety Enforcement activities included cargo safety, tracking, identification of hazardous materials, waterway safety regulations, and hazardous materials regulations. Homeland Security and Law Enforcement Applications included Radiological Dispersive Devices (RDD) identification, identification of unsafe or illicit transport of hazardous materials including chemicals and radiological materials, and screening for shipments of illicit drugs. In the Fall of 2005 the SensorNet funding for the project expired. After several unsuccessful attempts to

ORNL Trusted Corridors Project: Watts Bar Dam Inland Waterway Project

International Nuclear Information System (INIS)

Walker, Randy M.; Gross, Ian G.; Smith, Cyrus M.; Hill, David E.

2011-01-01

Radiation has existed everywhere in the environment since the Earth's formation - in rocks, soil, water, and plants. The mining and processing of naturally occurring radioactive materials for use in medicine, power generation, consumer products, and industry inevitably generate emissions and waste. Radiological measuring devices have been used by industry for years to measure for radiation in undesired locations or simply identify radioactive materials. Since the terrorist attacks on the United States on 9-11-01 these radiation measuring devices have proliferated in many places in our nation's commerce system. DOE, TVA, the Army Corps and ORNL collaborated to test the usefulness of these devices in our nation's waterway system on this project. The purpose of the Watts Bar Dam ORNL Trusted Corridors project was to investigate the security, safety and enforcement needs of local, state and federal government entities for state-of-the-art sensor monitoring in regards to illegal cargo including utilization of the existing infrastructure. TVA's inland waterways lock system is a recognized and accepted infrastructure by the commercial carrier industry. Safety Monitoring activities included tow boat operators, commercial barges and vessels, recreational watercraft and their cargo, identification of unsafe vessels and carriers, and, monitoring of domestic and foreign commercial vessels and cargo identification. Safety Enforcement activities included cargo safety, tracking, identification of hazardous materials, waterway safety regulations, and hazardous materials regulations. Homeland Security and Law Enforcement Applications included Radiological Dispersive Devices (RDD) identification, identification of unsafe or illicit transport of hazardous materials including chemicals and radiological materials, and screening for shipments of illicit drugs. In the Fall of 2005 the SensorNet funding for the project expired. After several unsuccessful attempts to find a Federal sponsor

75 FR 5769 - Inland Waterways Users Board; Request for Nominations

Science.gov (United States)

2010-02-04

... ``various'' regions. For the purpose of selecting Board members, the waterways subjected to fuel taxes and... Products; (2) Coal and Coke; (3) Petroleum, Crude and Products; (4) Minerals, Ores, and Primary Metals and...

Simulation of facility operations and materials accounting for a combined reprocessing/MOX fuel fabrication facility

International Nuclear Information System (INIS)

Coulter, C.A.; Whiteson, R.; Zardecki, A.

1991-01-01

We are developing a computer model of facility operations and nuclear materials accounting for a facility that reprocesses spent fuel and fabricates mixed oxide (MOX) fuel rods and assemblies from the recovered uranium and plutonium. The model will be used to determine the effectiveness of various materials measurement strategies for the facility and, ultimately, of other facility safeguards functions as well. This portion of the facility consists of a spent fuel storage pond, fuel shear, dissolver, clarifier, three solvent-extraction stages with uranium-plutonium separation after the first stage, and product concentrators. In this facility area mixed oxide is formed into pellets, the pellets are loaded into fuel rods, and the fuel rods are fabricated into fuel assemblies. These two facility sections are connected by a MOX conversion line in which the uranium and plutonium solutions from reprocessing are converted to mixed oxide. The model of the intermediate MOX conversion line used in the model is based on a design provided by Mike Ehinger of Oak Ridge National Laboratory (private communication). An initial version of the simulation model has been developed for the entire MOX conversion and fuel fabrication sections of the reprocessing/MOX fuel fabrication facility, and this model has been used to obtain inventory difference variance estimates for those sections of the facility. A significant fraction of the data files for the fuel reprocessing section have been developed, but these data files are not yet complete enough to permit simulation of reprocessing operations in the facility. Accordingly, the discussion in the following sections is restricted to the MOX conversion and fuel fabrication lines. 3 tabs

The operation of post-irradiation examination facility

Energy Technology Data Exchange (ETDEWEB)

Kim, Eun Ka; Park, Kwang Jun; Lee, Won Sang [and others; Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)

1994-01-01

The operation and management of PIE facility was executed in 1993. An indigenous 16 x 16 PWR type fuel assembly (ID No. J44) which was discharged from Kori unit 2 power reactor was transported to KAERI`s PIE facility and in-pool nondestructive examination and hot cell examination for the fuel were carried out. Because the above-mentioned 16 x 16 fuel is different from 14 x 14 fuel in its size and array of fuel rods, several examination and handling equipment for the 16 x 16 type fuel were designed and fabricated. PIE facility was operated in normal condition with the periodical check and inspection of the devices. The filter housing on the roof hood in chemical analysis hot cell was modified mounting air pressure gauge to indicate the optimal filter exchanging time. The burst air heating coil plate and the broken blowing fan of the HVAC system were repaired. The defaced grand packing in pool water circulation pump was replaced with the mechanical seal to prevent the leakage from the pump shaft sealing. The radiation monitoring in the facility was carried out to maintain the safe working condition and several radiation monitors were repaired. Spare parts for the radiation monitoring system were prepared to maintain the facility safely. The performance test of the emergency electric power supply system including UPS, battery and diesel generator was carried out. Oxide layer thickness measuring device for the performance test. Several devices including spent fuel handling equipment for the 17 x 17 PWR type fuel assembly were designed and fabricated for the subsequent PIE of nuclear fuels. 35 tabs., 17 figs., 7 refs. (Author) .new.

Recent operational experiments at the LANSCE facility

Energy Technology Data Exchange (ETDEWEB)

Rybarcyk, Lawrence J [Los Alamos National Laboratory

2010-09-15

The Los Alamos Neutron Science Center (LANSCE) consists of a pulsed 800-MeV room-temperature linear accelerator and an 800-MeV accumulator ring. It simultaneously provides H{sup +} and H{sup -} beams to several user facilities that have their own distinctive requirements, e.g. intensity, chopping pattern, duty factor, etc.. This multibeam operation presents challenges both from the standpoint of meeting the individual requirements but also achieving good overall performance for the integrated operation. Various aspects of more recent operations including the some of these challenges will be discussed.

Design and operations at the National Tritium Labelling Facility

International Nuclear Information System (INIS)

Morimoto, H.; Williams, P.G.

1991-09-01

The National Tritium Labelling Facility (NTLF) is a multipurpose facility engaged in tritium labeling research. It offers to the biomedical research community a fully equipped laboratory for the synthesis and analysis of tritium labeled compounds. The design of the tritiation system, its operations and some labeling techniques are presented

77 FR 47826 - Inland Waterways Users Board; Request for Nominations

Science.gov (United States)

2012-08-10

... the Board, the waterways subjected to fuel taxes and described in Public Law 95-502, as amended, have... United States. These categories are (1) Farm and Food Products; (2) Coal and Coke; (3) Petroleum, Crude...

7 CFR 70.110 - Requirements for sanitation, facilities, and operating procedures in official plants.

Science.gov (United States)

2010-01-01

... 7 Agriculture 3 2010-01-01 2010-01-01 false Requirements for sanitation, facilities, and operating... Requirements for sanitation, facilities, and operating procedures in official plants. (a) The requirements for sanitation, facilities, and operating procedures in official plants shall be the applicable provisions stated...

Report on operation of nuclear facilities in Slovenia in 1991

International Nuclear Information System (INIS)

1992-11-01

Slovenian Nuclear Safety Administration (SNSA) is responsible for: nuclear safety, transport of nuclear and radioactive materials, safeguarding nuclear materials, and conducting regulatory process related to liability for nuclear damage, qualification and training of operators at nuclear facilities, quality assurance and inspection of nuclear facilities. The major nuclear facility supervised by SNSA is the Nuclear Power Plant in Krsko with a pressurized water reactor of 632 MW electric power. Beside the nuclear power plant, TRIGA Mark 11 Research Reactor of 250 kW thermal power operates within the Reactor Center of Jozef Stefan Institute. There is an interim storage of low and medium radioactive waste at the Reactor Center. Also the Uranium mine Zirovski Vrh was supervised by SNSA. All the nuclear power facilities in Republic of Slovenia were operating safely in 1991. There were no significant events that could be evaluated as a safety problem or a breach of technical specifications. A great part of activities of SNSA was focused on the next visit of the IAEA OSART team (Operational Safety Assessment Review Team) in Krsko Nuclear Power Plant and on the visit of the INSARR mission (Integrated Safety Assessment of Research Reactors) for the TRIGA Mark 11 Research Reactor. (author)

PROPOSED GUIDELINES ON DEVELOPING THE OPTIMISATION MODEL FOR PASSAGE PLANNING IN INLAND WATERWAYS NAVIGATION

OpenAIRE

Ivančić, Paško; Kasum, Joško; Pavić, Ivica

2013-01-01

Road transport networks are overloaded by the increasing number of vehicles [1]. This has resulted in the redirection and the increasing intensity of navigation on rivers, canals and lakes. Transportation by inland waterways of the European Union (EU) represents a reliable, economical and environmentally friendly mode of transport. The latter has been recognized as a key form of transport in the European intermodal transport system. Inland waterways as part of the transport system play an imp...

Operator-machine interface at a large laser-fusion facility

International Nuclear Information System (INIS)

Sutton, J.G.; Howell, J.A.

1982-01-01

The operator-machine interface at the Antares Laser Facility provides the operator with a means of controlling the laser system and obtaining operational and performance information. The goal of this interface is to provide an operator with access to the control system in a comfortable way, and to facilitate meeting operational requirements. We describe the philosophy and requirements behind this interface, the hardware used in building it, and the software environment

Facility operations transparency and remote monitoring

International Nuclear Information System (INIS)

Beddingfield, David

2006-01-01

Remote monitoring technologies offer many opportunities, not only to strengthen IAEA safeguards, but also to improve national, industrial and local oversight of various nuclear operations. Remote monitoring benefits in greater timeliness, reduced inspector presence and improved state-of-health awareness are well-known attributes. However, there is also the capability to organize data into a comprehensive knowledge of the 'normal operating envelope' of a facility. In considering future applications of remote monitoring there is also a need to develop a better understanding of the potential cost-savings versus higher up-front costs and potential long-term maintenance or upgrade costs. (author)

Decommissioning of the nuclear licensed facilities at the Fontenay aux Roses CEA Center; cleanup of nuclear licensed facility 57 and monitoring of operations and operating feedback

International Nuclear Information System (INIS)

Estivie, D.; Bohar, M.P.; Jeanjacques, M.; Binet, C.; Bremond, M.P.; Poyau, C.; Mandard, L.; Boissonneau, J.F.; Fouquereau, A.; Pichereau, E.

2008-01-01

This is a summary of the program for the decommissioning of all the CEA Licensed Nuclear Facilities in Fontenay aux Roses. The particularity of this center is now it is located in a built-up area. It is presented like example the operations to clean up the equipment of the Nuclear Licensed Facility 57 (NLF 57). Due to the diversity of the research and development work carried out on the reprocessing of spent fuel in it, this installation is emblematic of many of the technical and organizational issues liable to be encountered in the final closure of nuclear facilities. It was developed a method applied to establish the multi-annual budget, monitor the progress of operations and integrate, as work continues, the operating feedback. (author)

Microcomputer simulation model for facility performance assessment: a case study of nuclear spent fuel handling facility operations

International Nuclear Information System (INIS)

Chockie, A.D.; Hostick, C.J.; Otis, P.T.

1985-10-01

A microcomputer based simulation model was recently developed at the Pacific Northwest Laboratory (PNL) to assist in the evaluation of design alternatives for a proposed facility to receive, consolidate and store nuclear spent fuel from US commercial power plants. Previous performance assessments were limited to deterministic calculations and Gantt chart representations of the facility operations. To insure that the design of the facility will be adequate to meet the specified throughput requirements, the simulation model was used to analyze such factors as material flow, equipment capability and the interface between the MRS facility and the nuclear waste transportation system. The simulation analysis model was based on commercially available software and application programs designed to represent the MRS waste handling facility operations. The results of the evaluation were used by the design review team at PNL to identify areas where design modifications should be considered. 4 figs

76 FR 13422 - Lower Mississippi River Waterway Safety Advisory Committee; Vacancies

Science.gov (United States)

2011-03-11

... the Lower Mississippi River and its connecting navigable waterways, including the Gulf of Mexico. The... receive no salary, reimbursement of travel expenses, or other compensation from the Federal Government...

Techniques for controlling air pollution from the operation of nuclear facilities

Energy Technology Data Exchange (ETDEWEB)

1966-03-01

This manual is provided for the guidance of those persons or authorities who are responsible for the organization, control and operation of ventilation systems and air-cleaning installations in nuclear establishments. It is intended to generalize about existing experience in the operation of such systems at nuclear facilities including reactors and laboratories for production, use and handling of radionuclides and other toxic materials. This manual will provide designers and operators of nuclear facilities in which ventilation and air-cleaning systems are used with the factors which have to be considered to create safe working conditions inside facilities and without polluting the atmosphere or the environment to a hazardous level. Refs, 24 figs, 5 tabs.

Remotely operated facility for in situ solidification of fissile uranium

International Nuclear Information System (INIS)

McGinnis, C.P.; Collins, E.D.; Patton, B.D.

1986-01-01

A heavily shielded, remotely operated facility, located within the Radiochemical processing Plant at Oak Ridge National Laboratory (ORNL), has been designed and is being operated to convert approx.1000 kg of fissile uranium (containing approx.75% 235 U, approx.10% 233 U, and approx.140 ppM 232 U) from a nitrate solution (130 g of uranium per L) to a solid oxide form. This project, the Consolidated Edison Uranium Solidification Program (CEUSP), is being carried out in order to prepare a stable uranium form for longterm storage. This paper describes the solidification process selected, the equipment and facilities required, the experimental work performed to ensure successful operation, some problems that were solved, and the initial operations

76 FR 60076 - Lower Mississippi River Waterway Safety Advisory Committee; Vacancies

Science.gov (United States)

2011-09-28

... navigable waterways, including the Gulf of Mexico. 1. Five members representing River Port Authorities... consecutive terms. All members serve at their own expense and receive no salary reimbursement of travel...

Operation technology of air treatment system in nuclear facilities

CERN Document Server

Chun, Y B; Hwong, Y H; Lee, H K; Min, D K; Park, K J; Uom, S H; Yang, S Y

2001-01-01

Effective operation techniques were reviewed on the air treatment system to protect the personnel in nuclear facilities from the contamination of radio-active particles and to keep the environment clear. Nuclear air treatment system consisted of the ventilation and filtering system was characterized by some test. Measurement of air velocity of blowing/exhaust fan in the ventilation system, leak tests of HEPA filters in the filtering, and measurement of pressure difference between the areas defined by radiation level were conducted. The results acquired form the measurements were reflected directly for the operation of air treatment. In the abnormal state of virus parts of devices composted of the system, the repairing method, maintenance and performance test were also employed in operating effectively the air treatment system. These measuring results and techniques can be available to the operation of air treatment system of PIEF as well as the other nuclear facilities in KAERI.

Radiation protection -Operation of chemical wastewater treatment facility

International Nuclear Information System (INIS)

Lee, M. J.; Lim, M. H.; Ahn, S. S.; Jeong, Y. S.

1996-12-01

The wastewater and sewage treatment facility have been operated. From the results of operation, it was confirmed that the quality of treated wastewater was 1/5 or 1/10 lower than that of regulation of law for environmental conservation. The quality of treated sewage has been maintained to 70% of regulation of law for environmental conservation. (author). 14 tabs., 8 figs

Umatilla hatchery satellite facilities operation and maintenance. Annual report 1996

International Nuclear Information System (INIS)

Rowan, G.D.

1997-06-01

The Confederated Tribes of the Umatilla Indian Reservation (CTUIR) and Oregon Department of Fish and Wildlife (ODFW) are cooperating in a joint effort to enhance steelhead and re-establish salmon runs in the Umatilla River Basin. As an integral part of this program, Bonifer Pond, Minthorn Springs, Imeques C-mem-ini-kem and Thornhollow satellite facilities are operated for acclimation and release of juvenile summer steelhead (Oncorhynchus mykiss), fall and spring chinook salmon (O. tshawytscha) and coho salmon (O. kisutch). Minthorn is also used for holding and spawning adult summer steelhead and Three Mile Dam is used for holding and spawning adult fall chinook and coho salmon. Bonifer, Minthorn, Imeques and Thornhollow facilities are operated for acclimation and release of juvenile salmon and summer steelhead. The main goal of acclimation is to reduce stress from trucking prior to release and improve imprinting of juvenile salmonids in the Umatilla River Basin. Juveniles are transported to the acclimation facilities primarily from Umatilla and Bonneville Hatcheries. This report details activities associated with operation and maintenance of the Bonifer, Minthorn, Imeques, Thornhollow and Three Mile Dam facilities in 1996

APET methodology for Defense Waste Processing Facility: Mode C operation

International Nuclear Information System (INIS)

Taylor, R.P. Jr.; Massey, W.M.

1995-04-01

Safe operation of SRS facilities continues to be the highest priority of the Savannah River Site (SRS). One of these facilities, the Defense Waste Processing Facility or DWPF, is currently undergoing cold chemical runs to verify the design and construction preparatory to hot startup in 1995. The DWPFF is a facility designed to convert the waste currently stored in tanks at the 200-Area tank farm into a form that is suitable for long term storage in engineered surface facilities and, ultimately, geologic isolation. As a part of the program to ensure safe operation of the DWPF, a probabilistic Safety Assessment of the DWPF has been completed. The results of this analysis are incorporated into the Safety Analysis Report (SAR) for DWPF. The usual practice in preparation of Safety Analysis Reports is to include only a conservative analysis of certain design basis accidents. A major part of a Probabilistic Safety Assessment is the development and quantification of an Accident Progression Event Tree or APET. The APET provides a probabilistic representation of potential sequences along which an accident may progress. The methodology used to determine the risk of operation of the DWPF borrows heavily from methods applied to the Probabilistic Safety Assessment of SRS reactors and to some commercial reactors. This report describes the Accident Progression Event Tree developed for the Probabilistic Safety Assessment of the DWPF

New requirements to collect operational data that are essential for facility decommissioning

International Nuclear Information System (INIS)

Kristofova, K.; Valcuha, P.

2017-01-01

The paper describes the features of the first nuclear regulatory safety guide to be released by the Nuclear Regulatory Authority of the Slovak Republic (UJD SR) in field of decommissioning. This safety guide specifies requirements to collect those nuclear facility operational data that are essential for its decommissioning. Recommendations of international organisations as well as experience in selected countries are provided. The following operational data types necessary for decommissioning process are identified and analysed: design documentation including modifications and changes during operation, photo-documentation, operational events and material and radiological inventory of the nuclear facility. The guide establishes requirements for collection of the operational data that can be recorded in interconnected database modules. In addition, a structure of decommissioning database is proposed, representing material and radiological inventory of a nuclear facility. This inventory database forms a basis for planning of the decommissioning process. At last, the guide summarises recommendations for data collection, archiving and maintenance of database records and also their applications in safety documentation necessary for decommissioning of nuclear facilities in Slovakia. (authors)

Operational Readiness Review: Savannah River Replacement Tritium Facility

International Nuclear Information System (INIS)

1993-02-01

The Operational Readiness Review (ORR) is one of several activities to be completed prior to introducing tritium into the Replacement Tritium Facility (RTF) at the Savannah River Site (SRS). The Secretary of Energy will rely in part on the results of this ORR in deciding whether the startup criteria for RTF have been met. The RTF is a new underground facility built to safely service the remaining nuclear weapons stockpile. At RTF, tritium will be unloaded from old components, purified and enriched, and loaded into new or reclaimed reservoirs. The RTF will replace an aging facility at SRS that has processed tritium for more than 35 years. RTF has completed construction and is undergoing facility startup testing. The final stages of this testing will require the introduction of limited amounts of tritium. The US Department of Energy (DOE) ORR was conducted January 19 to February 4, 1993, in accordance with an ORR review plan which was developed considering previous readiness reviews. The plan also considered the Defense Nuclear Facilities Safety Board (DNFSB) Recommendations 90-4 and 92-6, and the judgements of experienced senior experts. The review covered three major areas: (1) Plant and Equipment Readiness, (2) Personnel Readiness, and (3) Management Systems. The ORR Team was comprised of approximately 30 members consisting of a Team Leader, Senior Safety Experts, and Technical Experts. The ORR objectives and criteria were based on DOE Orders, industry standards, Institute of Nuclear Power Operations guidelines, recommendations of external oversight groups, and experience of the team members

Operation of a low-level waste disposal facility and how to prevent problems in future facilities

International Nuclear Information System (INIS)

Di Sibio, R.

1985-01-01

Operation of a low-level waste facility is an ever increasing problem nationally, and specifically one that could grow to crisis proportion in Pennsylvania. There have been, nevertheless, a variety of changes over the years in the management of low level radioactive waste, particularly with regard to disposal facilities that can avert a crisis condition. A number of companies have been organized thru possible a broad range of services to the nuclear industry, including those that emphasize solidification of waste materials, engineering services, waste management, and transportation to disposal sites across the United States. This paper addresses one particular site and the problems which evolved at that site from an environmental perspective. It is important that it is clearly understood that, although these problems are resolvable, the lessons learned here are critical for the prevention of problems at future facilities. The focus of this paper is on the Maxey Flats, Kentucky disposal facility which was closed in 1977. It must be understood that the regulations for siting, management, burial techniques, waste classification, and the overall management of disposal sites were limited when this facility was in operation

Model training curriculum for Low-Level Radioactive Waste Disposal Facility Operations

Energy Technology Data Exchange (ETDEWEB)

Tyner, C.J.; Birk, S.M.

1995-09-01

This document is to assist in the development of the training programs required to be in place for the operating license for a low-level radioactive waste disposal facility. It consists of an introductory document and four additional appendixes of individual training program curricula. This information will provide the starting point for the more detailed facility-specific training programs that will be developed as the facility hires and trains new personnel and begins operation. This document is comprehensive and is intended as a guide for the development of a company- or facility-specific program. The individual licensee does not need to use this model training curriculum as written. Instead, this document can be used as a menu for the development, modification, or verification of customized training programs.

Model training curriculum for Low-Level Radioactive Waste Disposal Facility Operations

International Nuclear Information System (INIS)

Tyner, C.J.; Birk, S.M.

1995-09-01

This document is to assist in the development of the training programs required to be in place for the operating license for a low-level radioactive waste disposal facility. It consists of an introductory document and four additional appendixes of individual training program curricula. This information will provide the starting point for the more detailed facility-specific training programs that will be developed as the facility hires and trains new personnel and begins operation. This document is comprehensive and is intended as a guide for the development of a company- or facility-specific program. The individual licensee does not need to use this model training curriculum as written. Instead, this document can be used as a menu for the development, modification, or verification of customized training programs

Development of a monthly to seasonal forecast framework tailored to inland waterway transport in central Europe

Science.gov (United States)

Meißner, Dennis; Klein, Bastian; Ionita, Monica

2017-12-01

Traditionally, navigation-related forecasts in central Europe cover short- to medium-range lead times linked to the travel times of vessels to pass the main waterway bottlenecks leaving the loading ports. Without doubt, this aspect is still essential for navigational users, but in light of the growing political intention to use the free capacity of the inland waterway transport in Europe, additional lead time supporting strategic decisions is more and more in demand. However, no such predictions offering extended lead times of several weeks up to several months currently exist for considerable parts of the European waterway network. This paper describes the set-up of a monthly to seasonal forecasting system for the German stretches of the international waterways of the Rhine, Danube and Elbe rivers. Two competitive forecast approaches have been implemented: the dynamical set-up forces a hydrological model with post-processed outputs from ECMWF general circulation model System 4, whereas the statistical approach is based on the empirical relationship (teleconnection) of global oceanic, climate and regional hydro-meteorological data with river flows. The performance of both forecast methods is evaluated in relation to the climatological forecast (ensemble of historical streamflow) and the well-known ensemble streamflow prediction approach (ESP, ensemble based on historical meteorology) using common performance indicators (correlation coefficient; mean absolute error, skill score; mean squared error, skill score; and continuous ranked probability, skill score) and an impact-based evaluation quantifying the potential economic gain. The following four key findings result from this study: (1) as former studies for other regions of central Europe indicate, the accuracy and/or skill of the meteorological forcing used has a larger effect than the quality of initial hydrological conditions for relevant stations along the German waterways. (2) Despite the predictive

Environmental analysis of the operation of the ERDA facilities in Oak Ridge

International Nuclear Information System (INIS)

McWherter, J.R.

1975-01-01

An analysis of the environmental effects of current ERDA operations in Oak Ridge is being conducted to establish a baseline for the consideration of the environmental effects of additional facilities or modified operations in the future. An extensive ecological survey has been conducted for about one year; social and economic data were obtained; and an archaeological survey of the area was made. The facilities were described and the effluents associated with operations were quantified to the extent practical. The effects of effluent releases to the environment are being analyzed. The social effects of the ERDA facilities in Oak Ridge are also being studied. (auth)

Dosimetry and operation of irradiation facilities

International Nuclear Information System (INIS)

Vidal, P.E.

1985-01-01

The industrial use of ionizing radiation has required, from the very first, the measurement of delivered and absorbed doses; hence the necessity of providing dosimetric systems. Laboratories, scientists, industries and potential equipment manufacturers have all collaborated in this new field of activity. Dosimetric intercomparisons have been made by each industry at their own facilities and in collaboration with specialists, national organizations and the IAEA. Dosimetry has become a way of ensuring that treatment by irradiation has been carried out in accordance with the rules. It has become in effect assurance of quality. Routine dosimetry should determine a maximum and minimum dose. Numerous factors play a part in dosimetry. Industry is currently in possession of routine dosimetric systems that are sufficiently accurate, fairly easy to handle and reasonable in cost, thereby satisfying all the requirements of industry and the need for control. Dosimetry is important in the process of marketing irradiated products. The operator of an industrial irradiation facility bases his dosimetry on comparison with reference systems. Research aimed at simplifying the practice of routine dosimetry should be continued. New physical and chemical techniques will be incorporated into systems already in use. The introduction of microcomputers into the operation of radiation facilities has increased the value of dosimetry and made the conditions of treatment more widespread. Stress should be placed on research in several areas apart from reference systems, for example: dosimetric systems at temperatures from +8 deg. C to -45 deg. C, over the dose range 100 krad to a little more than 1 Mrad, liquids and fluidized solids carried at high speed through ducts, thin-film liquids circulating at a high flow rate, and various other problems. (author)

Manual for operation of the multipurpose thermalhydraulic test facility TOPFLOW (Transient Two Phase Flow Test Facility)

International Nuclear Information System (INIS)

Beyer, M.; Carl, H.; Schuetz, H.; Pietruske, H.; Lenk, S.

2004-07-01

The Forschungszentrum Rossendorf (FZR) e. V. is constructing a new large-scale test facility, TOPFLOW, for thermalhydraulic single effect tests. The acronym stands for transient two phase flow test facility. It will mainly be used for the investigation of generic and applied steady state and transient two phase flow phenomena and the development and validation of models of computational fluid dynamic (CFD) codes. The manual of the test facility must always be available for the staff in the control room and is restricted condition during operation of personnel and also reconstruction of the facility. (orig./GL)

Operational and safety requirement of radiation facility

International Nuclear Information System (INIS)

Zulkafli Ghazali

2007-01-01

Gamma and electron irradiation facilities are the most common industrial sources of ionizing radiation. They have been used for medical, industrial and research purposes since the 1950s. Currently there are more than 160 gamma irradiation facilities and over 600 electron beam facilities in operation worldwide. These facilities are either used for the sterilization of medical and pharmaceutical products, the preservation of foodstuffs, polymer synthesis and modification, or the eradication of insect infestation. Irradiation with electron beam, gamma ray or ultra violet light can also destroy complex organic contaminants in both liquid and gaseous waste. EB systems are replacing traditional chemical sterilization methods in the medical supply industry. The ultra-violet curing facility, however, has found more industrial application in printing and furniture industries. Gamma and electron beam facilities produce very high dose rates during irradiation, and thus there is a potential of accidental exposure in the irradiation chamber which can be lethal within minutes. Although, the safety record of this industry has been relatively very good, there have been fatalities recorded in Italy (1975), Norway (1982), El Salvador (1989) and Israel (1990). Precautions against uncontrolled entry into irradiation chamber must therefore be taken. This is especially so in the case of gamma irradiation facilities those contain large amounts of radioactivity. If the mechanism for retracting the source is damaged, the source may remain exposed. This paper will, to certain extent, describe safety procedure and system being installed at ALURTRON, Nuclear Malaysia to eliminate accidental exposure of electron beam irradiation. (author)

Joint Assessment of ETRR-2 Research Reactor Operations Program, Capabilities, and Facilities

International Nuclear Information System (INIS)

Bissani, M; O'Kelly, D S

2006-01-01

A joint assessment meeting was conducted at the Egyptian Atomic Energy Agency (EAEA) followed by a tour of Egyptian Second Research Reactor (ETRR-2) on March 22 and 23, 2006. The purpose of the visit was to evaluate the capabilities of the new research reactor and its operations under Action Sheet 4 between the U.S. DOE and the EAEA, ''Research Reactor Operation'', and Action Sheet 6, ''Technical assistance in The Production of Radioisotopes''. Preliminary Recommendations of the joint assessment are as follows: (1) ETRR-2 utilization should be increased by encouraging frequent and sustained operations. This can be accomplished in part by (a) Improving the supply-chain management for fresh reactor fuel and alleviating the perception that the existing fuel inventory should be conserved due to unreliable fuel supply; and (b) Promulgating a policy for sample irradiation priority that encourages the use of the reactor and does not leave the decision of when to operate entirely at the discretion of reactor operations staff. (2) Each experimental facility in operation or built for a single purpose should be reevaluated to focus on those that most meet the goals of the EAEA strategic business plan. Temporary or long-term elimination of some experimental programs might be necessary to provide more focused utilization. There may be instances of emerging reactor applications for which no experimental facility is yet designed or envisioned. In some cases, an experimental facility may have a more beneficial use than the purpose for which it was originally designed. For example, (a) An effective Boron Neutron Capture Therapy (BNCT) program requires nearby high quality medical facilities. These facilities are not available and are unlikely to be constructed near the Inshas site. Further, the BNCT facility is not correctly designed for advanced research and therapy programs using epithermal neutrons. (b) The ETRR-2 is frequently operated to provide color-enhanced gemstones but is

Joint Assessment of ETRR-2 Research Reactor Operations Program, Capabilities, and Facilities

Energy Technology Data Exchange (ETDEWEB)

Bissani, M; O' Kelly, D S

2006-05-08

A joint assessment meeting was conducted at the Egyptian Atomic Energy Agency (EAEA) followed by a tour of Egyptian Second Research Reactor (ETRR-2) on March 22 and 23, 2006. The purpose of the visit was to evaluate the capabilities of the new research reactor and its operations under Action Sheet 4 between the U.S. DOE and the EAEA, ''Research Reactor Operation'', and Action Sheet 6, ''Technical assistance in The Production of Radioisotopes''. Preliminary Recommendations of the joint assessment are as follows: (1) ETRR-2 utilization should be increased by encouraging frequent and sustained operations. This can be accomplished in part by (a) Improving the supply-chain management for fresh reactor fuel and alleviating the perception that the existing fuel inventory should be conserved due to unreliable fuel supply; and (b) Promulgating a policy for sample irradiation priority that encourages the use of the reactor and does not leave the decision of when to operate entirely at the discretion of reactor operations staff. (2) Each experimental facility in operation or built for a single purpose should be reevaluated to focus on those that most meet the goals of the EAEA strategic business plan. Temporary or long-term elimination of some experimental programs might be necessary to provide more focused utilization. There may be instances of emerging reactor applications for which no experimental facility is yet designed or envisioned. In some cases, an experimental facility may have a more beneficial use than the purpose for which it was originally designed. For example, (a) An effective Boron Neutron Capture Therapy (BNCT) program requires nearby high quality medical facilities. These facilities are not available and are unlikely to be constructed near the Inshas site. Further, the BNCT facility is not correctly designed for advanced research and therapy programs using epithermal neutrons. (b) The ETRR-2 is frequently operated to

U.S. Navigated Waterway Mile Marker Locations from USCOE source data, Geographic NAD83, LOSCO (2000) [river_mile_markers_USACE_1994

Data.gov (United States)

Louisiana Geographic Information Center — This is a point dataset representing 10,044 sequential mile positions of navigable inland waterways and the Gulf Intracoastal Waterway. These data were developed as...

Experience in startup and operation of fast flux facility

International Nuclear Information System (INIS)

Moffitt, W.C.

1980-01-01

The testing program was structured to perform all testing under formal testing procedures with a test engineer as the test director and the plant operators operating the systems and equipment. This provided excellent training and experience for the operators in preparation for eventual reactor operation. Operations preparations for the testing and operation activities has consisted of academic training, formal on-the-job training including systems operation and examinations by persons with an expert knowledge on that portion of the plant, training at EBR-II and the High Temperature Sodium Facility for selected senior operators, operating procedure preparation, training on an FFTF Control Room operator training simulator, and formal written, oral and operating examinations

The influence of hydrology and waterway distance on population structure of Chinook salmon Oncorhynchus tshawytscha in a large river.

Science.gov (United States)

Olsen, J B; Beacham, T D; Wetklo, M; Seeb, L W; Smith, C T; Flannery, B G; Wenburg, J K

2010-04-01

Adult Chinook salmon Oncorhynchus tshawytscha navigate in river systems using olfactory cues that may be influenced by hydrologic factors such as flow and the number, size and spatial distribution of tributaries. Thus, river hydrology may influence both homing success and the level of straying (gene flow), which in turn influences population structure. In this study, two methods of multivariate analysis were used to examine the extent to which four indicators of hydrology and waterway distance explained population structure of O. tshawytscha in the Yukon River. A partial Mantel test showed that the indicators of hydrology were positively associated with broad-scale (Yukon basin) population structure, when controlling for the influence of waterway distance. Multivariate multiple regression showed that waterway distance, supplemented with the number and flow of major drainage basins, explained more variation in broad-scale population structure than any single indicator. At an intermediate spatial scale, indicators of hydrology did not appear to influence population structure after accounting for waterway distance. These results suggest that habitat changes in the Yukon River, which alter hydrology, may influence the basin-wide pattern of population structure in O. tshawytscha. Further research is warranted on the role of hydrology in concert with waterway distance in influencing population structure in Pacific salmon.

Environmental aspects based on operation performance of nuclear fuel fabrication facilities

International Nuclear Information System (INIS)

2001-07-01

This publication was prepared within the framework of the IAEA Project entitled Development and Upgrading of Guidelines, Databases and Tools for Integrating Comparative Assessment into Energy System Analysis and Policy Making, which included the collection, review and input of data into a database on health and environmental impacts related to operation of nuclear fuel cycle facilities. The objectives of the report included assembling environmental data on operational performance of nuclear fabrication facilities in each country; compiling and arranging the data in a database, which will be easily available to experts and the public; and presenting data that may be of value for future environmental assessment of nuclear fabrication facilities

Gamma irradiation facility: Evaluation of operational modes

International Nuclear Information System (INIS)

Adesanmi, C.A.; Ali, M.S.; Shonowo, O.A.; Akueche, E.C.; Sadare, O.O.; Mustapha, T.K.; Yusuf, U.; Inyanda, A.K.

2007-01-01

The multipurpose Gamma Irradiation Facility (GIF) at the Nuclear Technology Centre (NTC), Sheda Science and Technology Complex (SHETSCO), Abuja, Nigeria is designed as a semi-commercial plant with facilities for research and development (R and D). The design takes into account the different needs of the various research applications which require a wide dose range, a variety of techniques, different product sizes, shapes, mass, volume, densities and types. Programmable doses are used for food irradiation (0.04 - 10 kGy), biological seed mutation breeding and sterile insect technique (STI) (0.01- 5 kGy) sterilization of medical, pharmaceutical and cosmetic products and packages (up to 25 kGy) and cross-linking of polymers (up to 100 kGy). The six different modes of operations (sample elevator, stationary, swiveling, 2-path inner lane and 2-path outer lane and 4-path line) were evaluated. The dose range, mass range and range of irradiation time practicable were established and advantages for radiation processing of food and industrial products were enumerated for the six modes of operations for the first time

Operation of the hot test loop facilities

International Nuclear Information System (INIS)

Cheong, Moon Ki; Park, Choon Kyeong; Won, Soon Yeon; Yang, Sun Kyu; Cheong, Jang Whan; Cheon, Se Young; Song, Chul Hwa; Jeon, Hyeong Kil; Chang, Suk Kyu; Jeong, Heung Jun; Cho, Young Ro; Kim, Bok Duk; Min, Kyeong Ho

1994-12-01

The objective of this project is to obtain the available experimental data and to develop the measuring techniques through taking full advantage of the facilities. The facilities operated by the thermal hydraulics department have been maintained and repaired in order to carry out the thermal hydraulics tests necessary for providing the available data. The performance tests for double grid type bottom end piece which was improved on the debris filtering effectivity were performed using the PWR-Hot Test Loop. The CANDU-Hot Test Loop was operated to carry out the pressure drop tests and strength tests of fuel. The Cold Test Loop was used to obtain the local velocity data in subchannel within fuel bundle and to understand the characteristic of pressure drop required for improving the nuclear fuel and to develop the advanced measuring techniques. RCS Loop, which is used to measure the CHF, is presently under design and construction. B and C Loop is designed and constructed to assess the automatic depressurization safety system behavior. 4 tabs., 79 figs., 7 refs. (Author) .new

Order of 21 May 1979 on Transport of Radioactive Materials by Road or by Inland Waterway (Dangerous Goods 1979, No.5)

International Nuclear Information System (INIS)

1979-01-01

This Order lays down in connection with radioactive materials (class IVb) to be carried by road or inland waterway that Section 32 of the Order of 15 April 1945 approving the transport of dangerous goods by rail, land or inland waterway will come into force on 1 October 1980. The Order prescribes that drivers of land vehicles and on inland waterways, persons responsible on board must carry a certificate concerning their cargo in accordance with the above Section. (NEA) [fr

Report on the operation of nuclear facilities in Slovenia in 1993

International Nuclear Information System (INIS)

Lovincic, D.

1994-01-01

The Slovenian Nuclear Safety Administration (SNSA) prepared a Report on Nuclear Safety in 1993 as part of its regular practice of reporting on its work to the Government and the National Assembly of the Republic of Slovenia. The report is divided into five thematic chapters covering the activities of the SNSA, the operation of nuclear facilities in Slovenia, the activity of international missions in Slovenia, the Posavje - 93 exercise and the operation of nuclear facilities around the world. (author)

Report on the operation of nuclear facilities in Slovenia in 1993

Energy Technology Data Exchange (ETDEWEB)

Lovincic, D [Slovenian Nuclear Safety Administration, Ljubljana (Slovenia)

1994-07-01

The Slovenian Nuclear Safety Administration (SNSA) prepared a Report on Nuclear Safety in 1993 as part of its regular practice of reporting on its work to the Government and the National Assembly of the Republic of Slovenia. The report is divided into five thematic chapters covering the activities of the SNSA, the operation of nuclear facilities in Slovenia, the activity of international missions in Slovenia, the Posavje - 93 exercise and the operation of nuclear facilities around the world. (author)

The Pajarito Site operating procedures for the Los Alamos Critical Experiments Facility

International Nuclear Information System (INIS)

Malenfant, R.E.

1991-12-01

Operating procedures consistent with DOE Order 5480.6, and the American National Standard Safety Guide for the Performance of Critical Experiments are defined for the Los Alamos Critical Experiments Facility (LACEF) of the Los Alamos National Laboratory. These operating procedures supersede and update those previously published in 1983 and apply to any criticality experiment performed at the facility. 11 refs

Operation of the Brookhaven National Laboratory Accelerator Test Facility

International Nuclear Information System (INIS)

Batchelor, K.; Ben-Zvi, I.; Botke, I.; Chou, T.S.; Fernow, R.; Fischer, J.; Fisher, A.; Gallardo, J.; Ingold, G.; Malone, R.; Palmer, R.; Parsa, Z.; Pogorelsky, I.; Rogers, J.; Sheehan, J.; Srinivasan-Rao, T.; Tsang, T.; Ulc, S.; van Steenbergen, A.; Wang, X.J.; Woodle, M.; Yu, L.H.

1992-01-01

Early operation of the 50 MeV high brightness electron linac of the Accelerator Test Facility is described along with experimental data. This facility is designed to study new linear acceleration techniques and new radiation sources based on linacs in combination with free electron lasers. The accelerator utilizes a photo-excited, metal cathode, radio frequency electron gun followed by two travelling wave accelerating sections and an Experimental Hall for the study program

Operators guide: Atmospheric Release Advisory Capability (ARAC) site facility

International Nuclear Information System (INIS)

Cassaro, E.; Lomonaco, L.

1979-01-01

The Atmospheric Release Advisory Capability (ARAC) is designed to help officials at designated DOE sites and other locations in estimating the effects of atmospheric releases of radionuclides or other hazardous materials by issuing real-time advisories to guide them in their planning. This report outlines the capabilities and sources of ARAC, and in more detail describes an ARAC Site Facility, its operating procedures and interactions with the ARAC Central Facility (ACF) located at LLL

Modal-split effects of climate change: The effects of low water levels on the competitive position of inland waterway transport in the River Rhine area

NARCIS (Netherlands)

Jonkeren, O.E.; Jourquin, B.; Rietveld, P.

2011-01-01

Future climate change is expected to affect inland waterway transport in most main natural waterways in Europe. For the river Rhine it is expected that, in summer, more and longer periods with low water levels will occur. In periods of low water levels inland waterway vessels have to reduce their

Remote operations in a Fusion Engineering Research Facility (FERF)

International Nuclear Information System (INIS)

Doggett, J.N.

1975-01-01

The proposed Fusion Engineering Research Facility (FERF) has been designed for the test and evaluation of materials that will be exposed to the hostile radiation environment created by fusion reactors. Because the FERF itself must create a very hostile radiation environment, extensive remote handling procedures will be required as part of its routine operations as well as for both scheduled and unscheduled maintenance. This report analyzes the remote-handling implications of a vertical- rather than horizontal-orientation of the FERF magnet, describes the specific remote-handling facilities of the proposed FERF installation and compares the FERF remote-handling system with several other existing and proposed facilities. (U.S.)

Decommissioning of nuclear facilities involving operations with uranium and thorium

International Nuclear Information System (INIS)

Shum, E.Y.; Neuder, S.M.

1990-01-01

When a licensed nuclear facility ceases operation, the U.S. Nuclear Regulatory Commission (NRC) ensures that the facility and its site are decontaminated to acceptable levels so they may safely be released for unrestricted public use. Because specific environmental standards or broad federal guidelines governing release of residual radioactive contamination have not been issued, NRC has developed ad hoc cleanup criteria for decommissioning nuclear facilities that involved uranium and thorium. Cleanup criteria include decontamination of buildings, equipment, and land. We will address cleanup criteria and their rationale; procedures for decommissioning uranium/thorium facilities; radiological survey designs and procedures; radiological monitoring and measurement; and cost-effectiveness to demonstrate compliance

Operability test procedure for PFP wastewater sampling facility

International Nuclear Information System (INIS)

Hirzel, D.R.

1995-01-01

Document provides instructions for performing the Operability Test of the 225-WC Wastewater Sampling Station which monitors the discharge to the Treated Effluent Disposal Facility from the Plutonium Finishing Plant. This Operability Test Procedure (OTP) has been prepared to verify correct configuration and performance of the PFP Wastewater sampling system installed in Building 225-WC located outside the perimeter fence southeast of the Plutonium Finishing Plant (PFP). The objective of this test is to ensure the equipment in the sampling facility operates in a safe and reliable manner. The sampler consists of two Manning Model S-5000 units which are rate controlled by the Milltronics Ultrasonic flowmeter at manhole No.C4 and from a pH measuring system with the sensor in the stream adjacent to the sample point. The intent of the dual sampling system is to utilize one unit to sample continuously at a rate proportional to the wastewater flow rate so that the aggregate tests are related to the overall flow and thereby eliminate isolated analyses. The second unit will only operate during a high or low pH excursion of the stream (hence the need for a pH control). The major items in this OTP include testing of the Manning Sampler System and associated equipment including the pH measuring and control system, the conductivity monitor, and the flow meter

The Mixed Waste Management Facility. Design basis integrated operations plan (Title I design)

International Nuclear Information System (INIS)

1994-12-01

The Mixed Waste Management Facility (MWMF) will be a fully integrated, pilotscale facility for the demonstration of low-level, organic-matrix mixed waste treatment technologies. It will provide the bridge from bench-scale demonstrated technologies to the deployment and operation of full-scale treatment facilities. The MWMF is a key element in reducing the risk in deployment of effective and environmentally acceptable treatment processes for organic mixed-waste streams. The MWMF will provide the engineering test data, formal evaluation, and operating experience that will be required for these demonstration systems to become accepted by EPA and deployable in waste treatment facilities. The deployment will also demonstrate how to approach the permitting process with the regulatory agencies and how to operate and maintain the processes in a safe manner. This document describes, at a high level, how the facility will be designed and operated to achieve this mission. It frequently refers the reader to additional documentation that provides more detail in specific areas. Effective evaluation of a technology consists of a variety of informal and formal demonstrations involving individual technology systems or subsystems, integrated technology system combinations, or complete integrated treatment trains. Informal demonstrations will typically be used to gather general operating information and to establish a basis for development of formal demonstration plans. Formal demonstrations consist of a specific series of tests that are used to rigorously demonstrate the operation or performance of a specific system configuration

77 FR 68155 - The Armed Forces Radiobiology Research Institute TRIGA Reactor: Facility Operating License No. R-84

Science.gov (United States)

2012-11-15

... Research Institute TRIGA Reactor: Facility Operating License No. R-84 AGENCY: Nuclear Regulatory Commission... considering an application for the renewal of Facility Operating License No. R-84 (Application), which... the renewal of Facility Operating License No. R-84, which currently authorizes the licensee to operate...

High-Level Functional and Operational Requirements for the Advanced Fuel Cycle Facility

International Nuclear Information System (INIS)

Charles Park

2006-01-01

This document describes the principal functional and operational requirements for the proposed Advanced Fuel Cycle Facility (AFCF). The AFCF is intended to be the world's foremost facility for nuclear fuel cycle research, technology development, and demonstration. The facility will also support the near-term mission to develop and demonstrate technology in support of fuel cycle needs identified by industry, and the long-term mission to retain and retain U.S. leadership in fuel cycle operations. The AFCF is essential to demonstrate a more proliferation-resistant fuel cycle and make long-term improvements in fuel cycle effectiveness, performance and economy

77 FR 26321 - Reed College, Reed Research Nuclear Reactor, Renewed Facility Operating License No. R-112

Science.gov (United States)

2012-05-03

... Nuclear Reactor, Renewed Facility Operating License No. R-112 AGENCY: Nuclear Regulatory Commission... Commission (NRC or the Commission) has issued renewed Facility Operating License No. R- 112, held by Reed... License No. R-112 will expire 20 years from its date of issuance. The renewed facility operating license...

Operation of the Brookhaven national laboratory accelerator test facility

International Nuclear Information System (INIS)

Batchelor, K.; Ben-Zvi, I.; Botke, I.; Chou, T.S.; Fernow, R.; Fischer, J.; Fisher, A.; Gallardo, J.; Ingold, G.; Malone, R.; Palmer, R.; Parsa, Z.; Pogorelsky, I.; Rogers, J.; Sheehan, J.; Srinivasan-Rao, T.; Tsang, T.; Ulc, S.; Van Steenbergen, A.; Wang, X.J.; Woodle, M.; Yu, L.H.

1992-01-01

Early operation of the 50 MeV high brightness electron linac of the Accelerator Test Facility is described along with experimental data. This facility is designed to study new linear acceleration techniques and new radiation sources based on linacs in combination with free electron lasers. The accelerator utilizes a photo-excited, metal cathode, radio frequency electron gun followed by two travelling wave accelerating sections and an Experimental Hall for the study program. (Author) 5 refs., 4 figs., tab

Evaluation of physical facilities and processing operations of major ...

African Journals Online (AJOL)

ADEYEYE

abattoirs were as a result of failure to enforce the use of standard facilities in carrying out abattoir operations and general maintenance ... incinerator, chemical treatment and disposal. Sub- .... Veterinary laboratory .... sustainable food security.

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)

Low-level wastewater treatment facility process control operational test report

International Nuclear Information System (INIS)

Bergquist, G.G.

1996-01-01

This test report documents the results obtained while conducting operational testing of a new TK 102 level controller and total outflow integrator added to the NHCON software that controls the Low-Level Wastewater Treatment Facility (LLWTF). The test was performed with WHC-SD-CP-OTP 154, PFP Low-Level Wastewater Treatment Facility Process Control Operational Test. A complete test copy is included in appendix A. The new TK 102 level controller provides a signal, hereafter referred to its cascade mode, to the treatment train flow controller which enables the water treatment process to run for long periods without continuous operator monitoring. The test successfully demonstrated the functionality of the new controller under standard and abnormal conditions expected from the LLWTF operation. In addition, a flow totalizer is now displayed on the LLWTF outlet MICON screen which tallies the process output in gallons. This feature substantially improves the ability to retrieve daily process volumes for maintaining accurate material balances

KSC facilities status and planned management operations. [for Shuttle launches

Science.gov (United States)

Gray, R. H.; Omalley, T. J.

1979-01-01

A status report is presented on facilities and planned operations at the Kennedy Space Center with reference to Space Shuttle launch activities. The facilities are essentially complete, with all new construction and modifications to existing buildings almost finished. Some activity is still in progress at Pad A and on the Mobile Launcher due to changes in requirements but is not expected to affect the launch schedule. The installation and testing of the ground checkout equipment that will be used to test the flight hardware is now in operation. The Launch Processing System is currently supporting the development of the applications software that will perform the testing of this flight hardware.

Occupational and Public Exposure During Normal Operation of Radioactive Waste Disposal Facilities

OpenAIRE

M. V. Vedernikova; I. A. Pron; M. N. Savkin; N. S. Cebakovskaya

2017-01-01

This paper focuses on occupational and public exposure during operation of disposal facilities receiving liquid and solid radioactive waste of various classes and provides a comparative analysis of the relevant doses: actual and calculated at the design stage. Occupational and public exposure study presented in this paper covers normal operations of a radioactive waste disposal facility receiving waste. Results: Analysis of individual and collective occupational doses was performed based on d...

Operations aspects of the Fermilab Central Helium Liquefier facility

International Nuclear Information System (INIS)

Geynisman, M.G.; Makara, J.N.

1996-09-01

The Fermilab Central Helium Liquefier (CHL) facility consists of helium and nitrogen reliquefier plants operated 24 hours-a-day to supply LHe at 4.6 K and LN 2 for the Fermilab Tevatron superconducting proton-antiproton collider ring and to recover warm return gases. Operating aspects of CHL, including different equipment and systems reliability, availability, maintenance experience, safety concerns, and economics aspects are discussed

Operations aspects of the Fermilab Central Helium Liquefier Facility

International Nuclear Information System (INIS)

Geynisman, M.G.; Makara, J.N.

1995-03-01

The Fermilab Central Helium Liquefier (CHL) facility consists of helium and nitrogen reliquefier plants operated 24 hours-a-day to supply LHe at 4.6 degrees K and LN 2 for the Fermilab Tevatron superconducting proton-antiproton collider ring and to recover warm return gases. Operating aspects of CHL, including different equipment and systems reliability, availability, maintenance experience, safety concerns, and economics aspects are discussed

Preliminary analysis of the operating characteristics of a generic repository receiving facility: Status report

International Nuclear Information System (INIS)

1985-10-01

The operating characteristics of a repository receiving facility structured around current technology and practices have been reviewed. Cask turnaround times and operator doses were estimated. Large throughout and long-term receiving operations at a nuclear waste repository result in an unprecedented number of casks being handled. While the current generation of material-handling equipment is adequate to process the casks, personnel radiation exposures for the generic facility analyzed are unacceptably high. This emphasizes the need for development of occupational radiation exposure control concepts for application in repository receiving facilities. 3 refs., 22 figs., 6 tabs

Licence applications for low and intermediate level waste predisposal facilities: A manual for operators

International Nuclear Information System (INIS)

2009-07-01

This publication covers all predisposal waste management facilities and practices for receipt, pretreatment (sorting, segregation, characterization), treatment, conditioning, internal relocation and storage of low and intermediate level radioactive waste, including disused sealed radioactive sources. The publication contains an Annex presenting the example of a safety assessment for a small radioactive waste storage facility. Facilities dealing with both short lived and long lived low and intermediate level waste generated from nuclear applications and from operation of small nuclear research reactors are included in the scope. Processing and storage facilities for high activity disused sealed sources and sealed sources containing long lived radionuclides are also covered. The publication does not cover facilities processing or storing radioactive waste from nuclear power plants or any other industrial scale nuclear fuel cycle facilities. Disposal facilities are excluded from the scope of this publication. Authorization process can be implemented in several stages, which may start at the site planning and the feasibility study stage and will continue through preliminary design, final design, commissioning, operation and decommissioning stages. This publication covers primarily the authorization needed to take the facility into operation

Start of operation of the barrel measuring facility II-01. Implementation into operational processes

International Nuclear Information System (INIS)

Buesing, B.; Escher, M.

2013-01-01

For the operation of the barrel measuring facility (FAME) II-01 a variety requirements to the measuring techniques were defined and tested in the frame of start-up. The used mechanical engineering and measuring technique complies with the state-of-the-art. Using the barrel measuring facility quality assured determinations of the dose rate and the nuclide-specific activity inventory were performed. For the evaluation of the gamma spectrometric measurements of FAME II-01 appropriately qualified personnel is available. The implementation of the facility in combination with the connection to the data base system PIK-AS and AVK it guaranteed that important data are available in real-time for the measuring process and the subsequent work steps. Besides this it is guaranteed that using the import/export functions relevant data are reviewed, supplemented and exchanged between the systems without transfer errors. The determined data of the dose rate and gamma spectrometric measurements allow an activity determination of the waste package with quality assurance and close to reality. Conservative assumptions in the frame of activity calculations for the later final disposal can be reduced. The automated operation of FAME allows also the reduction of radiation exposure of the personnel.

Space Infrared Telescope Facility (SIRTF) - Operations concept. [decreasing development and operations cost

Science.gov (United States)

Miller, Richard B.

1992-01-01

The development and operations costs of the Space IR Telescope Facility (SIRTF) are discussed in the light of minimizing total outlays and optimizing efficiency. The development phase cannot extend into the post-launch segment which is planned to only support system verification and calibration followed by operations with a 70-percent efficiency goal. The importance of reducing the ground-support staff is demonstrated, and the value of the highly sensitive observations to the general astronomical community is described. The Failure Protection Algorithm for the SIRTF is designed for the 5-yr lifetime and the continuous venting of cryogen, and a science driven ground/operations system is described. Attention is given to balancing cost and performance, prototyping during the development phase, incremental development, the utilization of standards, and the integration of ground system/operations with flight system integration and test.

French experience of regulation and operation on reprocessing facilities of LWR spent fuels

Energy Technology Data Exchange (ETDEWEB)

Mercier, J P [DES/SESUL (France)

1992-02-01

This presentation describes the French experience of regulation and operation on reprocessing facilities: how the safety assessment was made of UP3-A plant of the La Hague establishment for the building permit and operating license within the context of French nuclear regulations and the national debate on the need for reprocessing. Other factors discussed are how the public was involved, how the regulations were improved in the process and what the different stages of commissioning consisted of. In the design studies of a reprocessing facility, three complementary approaches are used: - observance of regulations born of technical considerations, and good practice, - analysis of the hazards, using deterministic and probabilistic methods, within the framework of a safety report, - review of experience feedback from such a facility or like plants. The design of the facility must permit the prevention of accidents and limit their consequences. Moreover, during all foreseeable cases (normal operating, incidents and accidents), the safety of the staff, the public and the environment with regard to consequences of radioactive releases and ionising radiations must be ensured. In the evaluation of these consequences, the approach used is voluntarily pessimistic in order to take into account every possible case. It is based on the main following principles: definition of the events considered for the dimensioning of the facility; redundancy and diversification; defense in depth which consists of the multiplication of the barriers. The experience feedback comes, on the one hand from operator's findings aiming at improving its facility, on the other hand from incidents, the lessons of which being taken into account after careful analysis. These incidents are analyzed by the Safety Authority upon presentation of the data by the operator and on site findings of inspections. In other respects, the aim of inspections is to check that the plant and its operating practices are

Nuclear Facilities Management Section Mutsu Office, Aomori Research and Development Center operations report. FY 2012 and 2013

International Nuclear Information System (INIS)

Tajima, Yoshihiro; Kuwabara, Jun; Oyokawa, Atsushi; Kabuto, Shoji; Araya, Naoyuki; Kikuchi, Kaoru; Miyamoto, Shingo; Nemoto, Hideyuki; Ohe, Osamu

2016-05-01

Nuclear Facilities Management Section implements the operation, maintenance and decommissioning of the first nuclear ship “MUTSU” and the operation and maintenance of the liquid waste facility and the solid waste facility where a small amount of nuclear fuel is used. This is the report on the operations of the Nuclear Facilities Management Section for FY 2012 and FY 2013. (author)

Operation of post-irradiation examination facility

Energy Technology Data Exchange (ETDEWEB)

Kim, Eun Ka; Park, Kwang Joon; Jeon, Yong Bum [and others; Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)

1995-02-01

In 1995, the post-irradiation examination (PIE) of nuclear fuels was performed as follows. The relation between burnup and top nozzle spring force of fuel assembly was obtained by measuring the holddown spring force on the Kori-1 reactor fuel assemblies. The resonance ultrasonic test for inspection of defect and moisture in fuel rod was carried out on fuel rods of C15 and J14 assemblies, and the change of fuel rod condition by storing in pool has been analyzed on the intentionally defected fuel rods (ID-C and ID-L) as well as intact fuel rod (1-2) by NDT in ht cell. The oxide layer thickness on cladding surface of J44-L12 fuel rod was measured by NDT method and metallography to reveal the oxidation as a function of temperature in the fuel rod, and the burnup of J44 fuel assembly was measured by chemical analysis. HVAC system and pool water treatment system of the PIE facility were continuously operated for air filtration and water purification. The monitoring of radiation and pool water in PIE facility has been carried out to maintain the facility safety, and electric power supply system was checked and maintained to supply the electric power to the facility normally. The developed measurement techniques of oxide layer thickness on fuel rod cladding and holddown spring force of top nozzle in fuel assembly were applied to examine the nuclear fuels. Besides, a radiation shielding glove box was designed and a hot cell compressor for volume reduction of radioactive materials was fabricated. 19 tabs., 38 figs., 7 refs. (Author) .new.

Operation and Maintenance of Water Pollution Control Facilities: A WPCF White Paper.

Science.gov (United States)

Hill, William R.; And Others

1979-01-01

Presented are the recommendations of the Water Pollution Control Federation for operation and maintenance consideration during the planning design, construction, and operation of wastewater treatment facilities. (CS)

DROUGHTS IN THE TIETÊ-PARANÁ WATERWAY: IMPACTS ON THE DIRECT, INDIRECT AND HIDDEN COSTS IN THE TRANSPORTATION OF SOYBEAN.

Directory of Open Access Journals (Sweden)

Rodrigo Carlo Toloi

2016-05-01

Full Text Available Brazil's agricultural economy is growing and increasing productivity. Therefore, it has required transportation systems with high load capacity and lower transportation costs. However, with the drought in the Southeast region of Brazil, the waterway Tietê-Paraná closed since May 2014 generating a loss of more than 30 million last year. Thus, this study investigates the impacts on direct, indirect and hidden costs resulting from this change of route for soy transport. The methodology consists of an exploratory, descriptive and bibliographic research that seeks to raise the main costs. The results show that failing to ensure the production of soybeans by the Tiete-Parana waterway and using the highway transportation costs for waterway users are increased by US$ 37,760,146.86.

Impacts of ramping inflexibility of conventional generators on strategic operation of energy storage facilities

DEFF Research Database (Denmark)

Nasrolahpour, Ehsan; Kazempour, Jalal; Zareipour, Hamidreza

2016-01-01

This paper proposes an approach to assist a pricemaker merchant energy storage facility in making its optimal operation decisions. The facility operates in a pool-based electricity market, where the ramping capability of other resources is limited. Also, wind power resources exist in the system...

Fast Flux Test Facility sodium pump operating experience - mechanical

International Nuclear Information System (INIS)

Buonamici, R.

1987-11-01

The Heat Transport System (HTS) pumps were designed, fabricated, tested, and installed in the Fast Flux Test Facility (FFTF) Plant during the period from September 1970 through July 1977. Since completion of the installation and sodium fill in December 1978, the FFTF Plant pumps have undergone extensive testing and operation with HTS testing and reactor operation. Steady-state hydraulic and mechanical performances have been and are excellent. In all, FFTF primary and secondary pumps have operated in sodium for approximately 75,000 hours and 79,000 hours, respectively, to August 24, 1987

Reliability Considerations for the Operation of Large Accelerator User Facilities

CERN Document Server

Willeke, F.J.

2016-01-01

The lecture provides an overview of considerations relevant for achieving highly reliable operation of accelerator based user facilities. The article starts with an overview of statistical reliability formalism which is followed by high reliability design considerations with examples. The article closes with operational aspects of high reliability such as preventive maintenance and spares inventory.

76 FR 62868 - Washington State University; Notice of Issuance of Renewed Facility Operating License No. R-76

Science.gov (United States)

2011-10-11

...; Notice of Issuance of Renewed Facility Operating License No. R-76 AGENCY: Nuclear Regulatory Commission. ACTION: Notice of issuance of renewed facility operating license No. R- 76. ADDRESSES: You can access.... Nuclear Regulatory Commission (NRC, the Commission) has issued renewed Facility Operating License No. R-76...

Trial operation of the advanced volume reduction facilities for LLW at JAEA

International Nuclear Information System (INIS)

Nakashio, Nobuyuki; Higuchi, Hidekazu; Momma, Toshiyuki; Kozawa, Kazushige; Touhei, Toshio; Sudou, Tomoyuki; Mitsuda, Motoyuki; Kurosawa, Shigenobu; Hemmi, Kou; Ishikawa, Joji; Kato, Mitsugu; Sato, Motoaki

2007-01-01

The Japan Atomic Energy Agency (JAEA) constructed the Advanced Volume Reduction Facilities (AVRF), in which volume reduction techniques are applied and achieved high volume reduction ratio, homogenization and stabilization by means of melting or super compaction processes for low level radioactive solid wastes. It will be able to produce waste packages for final disposal and to reduce the volume of stored wastes by operating the AVRF. The AVRF consist of the Waste Size Reduction and Storage Facilities (WSRSF) and the Waste Volume Reduction Facilities (WVRF); the former has cutting installations for large size wastes and the latter has melting units and a super compactor. Cutting installations in the WSRSF have been operating since July 1999. Radioactive wastes treated so far amount to 750 m 3 and the volume reduction ratio is from 1.7 to 3.7. The WVRF has been operating with non-radioactive wastes since February 2003 for the training and the homogeneity investigation in the melting processes. The operation of the pretreatment system in the WVRF with radioactive wastes has partly started in FY2005. (author)

The ITER Neutral Beam Test Facility towards SPIDER operation

Science.gov (United States)

Toigo, V.; Dal Bello, S.; Gaio, E.; Luchetta, A.; Pasqualotto, R.; Zaccaria, P.; Bigi, M.; Chitarin, G.; Marcuzzi, D.; Pomaro, N.; Serianni, G.; Agostinetti, P.; Agostini, M.; Antoni, V.; Aprile, D.; Baltador, C.; Barbisan, M.; Battistella, M.; Boldrin, M.; Brombin, M.; Dalla Palma, M.; De Lorenzi, A.; Delogu, R.; De Muri, M.; Fellin, F.; Ferro, A.; Gambetta, G.; Grando, L.; Jain, P.; Maistrello, A.; Manduchi, G.; Marconato, N.; Pavei, M.; Peruzzo, S.; Pilan, N.; Pimazzoni, A.; Piovan, R.; Recchia, M.; Rizzolo, A.; Sartori, E.; Siragusa, M.; Spada, E.; Spagnolo, S.; Spolaore, M.; Taliercio, C.; Valente, M.; Veltri, P.; Zamengo, A.; Zaniol, B.; Zanotto, L.; Zaupa, M.; Boilson, D.; Graceffa, J.; Svensson, L.; Schunke, B.; Decamps, H.; Urbani, M.; Kushwah, M.; Chareyre, J.; Singh, M.; Bonicelli, T.; Agarici, G.; Garbuglia, A.; Masiello, A.; Paolucci, F.; Simon, M.; Bailly-Maitre, L.; Bragulat, E.; Gomez, G.; Gutierrez, D.; Mico, G.; Moreno, J.-F.; Pilard, V.; Chakraborty, A.; Baruah, U.; Rotti, C.; Patel, H.; Nagaraju, M. V.; Singh, N. P.; Patel, A.; Dhola, H.; Raval, B.; Fantz, U.; Fröschle, M.; Heinemann, B.; Kraus, W.; Nocentini, R.; Riedl, R.; Schiesko, L.; Wimmer, C.; Wünderlich, D.; Cavenago, M.; Croci, G.; Gorini, G.; Rebai, M.; Muraro, A.; Tardocchi, M.; Hemsworth, R.

2017-08-01

SPIDER is one of two projects of the ITER Neutral Beam Test Facility under construction in Padova, Italy, at the Consorzio RFX premises. It will have a 100 keV beam source with a full-size prototype of the radiofrequency ion source for the ITER neutral beam injector (NBI) and also, similar to the ITER diagnostic neutral beam, it is designed to operate with a pulse length of up to 3600 s, featuring an ITER-like magnetic filter field configuration (for high extraction of negative ions) and caesium oven (for high production of negative ions) layout as well as a wide set of diagnostics. These features will allow a reproduction of the ion source operation in ITER, which cannot be done in any other existing test facility. SPIDER realization is well advanced and the first operation is expected at the beginning of 2018, with the mission of achieving the ITER heating and diagnostic NBI ion source requirements and of improving its performance in terms of reliability and availability. This paper mainly focuses on the preparation of the first SPIDER operations—integration and testing of SPIDER components, completion and implementation of diagnostics and control and formulation of operation and research plan, based on a staged strategy.

Radiological and the other safety aspects in the operation of electron beam facility

International Nuclear Information System (INIS)

Loterina, Roel Alamares

2003-01-01

The radiological safety aspects of the operation of an electron beam facility in general and the 3 MeV ALURTRON electron beam facility of the Malaysian Institute of Nuclear Technology Research (MINT) in particular were reviewed and evaluated. Evaluation was made based on existing records as well as actual monitoring around facility. Area monitoring results using TLDs are within permissible levels. The maximum reading of 7.29 mSv measured in year 2000 is very low as compared to the annual dose limit of 50 mSv/year. In general, the shielding for the installation is adequate and no significant radiation leakage were detected based on radiation survey results. However, measured radiation levels with a maximum of 1.9 mSv/h at the sampling ports easily exceed the limit of 25μSv/h. The facility is equipped with safety features, such as interlocked system, adequate shielding, engineered safety design of irradiation and accelerator rooms, and accessories such as conveyor system and product handling system. Warning lights and signals are adequately installed around the facility. Other identified hazards that may affect the operator, workers, and personnel were also evaluated based on previous records of monitoring. The ozone concentration levels with a maximum reading of 0.05 ppm measured in the environment of the facility are within the threshold limit value of 0.1 ppm. The measured noise levels at all locations around facility are generally below the maximum permissible level of 80dB. The ALURTRON has achieved a minimum safety requirement to warrant its full operation without relying on administrative controls and procedures to ensure safety in operation. (Auth.)

Safe operation of existing radioactive waste management facilities at Dalat Nuclear Research Institute

International Nuclear Information System (INIS)

Pham Van Lam; Ong Van Ngoc; Nguyen Thi Nang

2000-01-01

The Dalat Nuclear Research Reactor was reconstructed from the former TRIGA MARK-II in 1982 and put into operation in March 1984. The combined technology for radioactive waste management was newly designed and put into operation in 1984. The system for radioactive waste management at the Dalat Nuclear Research Institute (DNRI) consists of radioactive liquid waste treatment station and disposal facilities. The treatment methods used for radioactive liquid waste are coagulation and precipitation, mechanical filtering and ion- exchange. Near-surface disposal of radioactive wastes is practiced at DNRI In the disposal facilities eight concrete pits are constructed for solidification and disposal of low level radioactive waste. Many types of waste generated in DNRI and in some Nuclear Medicine Departments in the South of Vietnam are stored in the disposal facilities. The solidification of sludge has been done by cementation. Hydraulic compactor has done volume reduction of compatible waste. This paper presents fifteen-years of safe operation of radioactive waste management facilities at DNRI. (author)

Radiological operating experience at FFTF [Fast Flux Test Facility

International Nuclear Information System (INIS)

Bunch, W.L.; Prevo, P.R.

1986-11-01

The Fast Flux Test Facility has been in operation for approximately five years, including about one thousand days of full power operation of the Fast Test Reactor. During that time the collective dose equivalents received by operating personnel have been about two orders of magnitude lower than those typically received at commercial light water reactors. No major contamination problems have been encountered in operating and maintaining the plant, and release of radioactive gas to the environment has been minimal and well below acceptable limits. All shields have performed satisfactorily. Experience to date indicates an apparent radiological superiority of liquid metal reactor systems over current light water plants

Clinton P. Anderson Meson Physics Facility and its operational safety program

International Nuclear Information System (INIS)

Putnam, T.M.

1975-01-01

The Clinton P. Anderson Meson Physics Facility (LAMPF) at the Los Alamos Scientific Laboratory consists of/ (1) a medium-energy, high-intensity linear proton accelerator; (2) experimental areas designed to support a multidisciplined program of research and practical applications; and (3) support facilities for accelerator operations and the experimental program. The high-intensity primary and secondary beams at LAMPF and the varied research program create many interesting and challenging problems for the Health Physics staff. A brief overview of LAMPF is presented, and the Operational Safety Program is discussed, with emphasis on the radiological safety and health physics aspects

A history of trade routes and water-level regulation on waterways in Voyageurs National Park, Minnesota, USA

Science.gov (United States)

Christensen, Victoria G.; LaBounty, Andrew E.

2018-01-01

Unlike most national parks, main access to Voyageurs National Park is by boat. This remote system of interconnected waterways along the USA-Canada border was an important transportation route for thousands of years of American Indian occupation, leading up to and including the trade route of the voyageurs, or French-Canadian fur traders from around 1680 to 1870. The Ojibwe people collaborated with the voyageurs and the two cultures developed a trade network that continued to rely on these waterways. By the mid-1800s, European fashion changed, and the fur trade dwindled while the Ojibwe remained tied to the land and waters. The complexity of the waterways increased with the installation of dams on two of the natural lakes in the early 1900s. Modern water levels have affected—and in some cases destabilized—vulnerable landforms within the past century. The knowledge of these effects can be used by resource managers to weigh the consequences of hydrologic manipulation in Voyageurs National Park.

Operation of post-irradiation examination facility

Energy Technology Data Exchange (ETDEWEB)

Kim, E. G.; Jeon, Y. B.; Ku, D. S.

1996-12-01

In 1996, the post-irradiation examination(PIE) of nuclear fuels was performed as follows. It has been searched for the caution of defection of defected fuel rods of Youngkwang-4 reactor through NDT and metallographic examination that had been required by KEPCO. And in-pool inspection of Kori-1 spent fuel assembly(FO2) was carried out. HVAC system and pool water treatment system have been operated to maintain the facility safely, and electric power supply system was checked and maintained for the normal and steady supply electric power to the facility. Image processing software was developed for measurement of defection of spent fuel rods. Besides, a radiation shielding glove box was fabricated and a hot cell compressor for volume reduction of radioactive materials was fabricated and installed in hot cell. Safeguards of nuclear materials were implemented in strict accordance with the relevant Korean rules and regulations as well as the international non-proliferation regime. Also the IAEA inspection was carried out on the quarterly basis. (author). 31 tabs., 71 figs., 4 refs.

Helium turbomachinery operating experience from gas turbine power plants and test facilities

International Nuclear Information System (INIS)

McDonald, Colin F.

2012-01-01

The closed-cycle gas turbine, pioneered and deployed in Europe, is not well known in the USA. Since nuclear power plant studies currently being conducted in several countries involve the coupling of a high temperature gas-cooled nuclear reactor with a helium closed-cycle gas turbine power conversion system, the experience gained from operated helium turbomachinery is the focus of this paper. A study done as early as 1945 foresaw the use of a helium closed-cycle gas turbine coupled with a high temperature gas-cooled nuclear reactor, and some two decades later this was investigated but not implemented because of lack of technology readiness. However, the first practical use of helium as a gas turbine working fluid was recognized for cryogenic processes, and the first two small fossil-fired helium gas turbines to operate were in the USA for air liquefaction and nitrogen production facilities. In the 1970's a larger helium gas turbine plant and helium test facilities were built and operated in Germany to establish technology bases for a projected future high efficiency large nuclear gas turbine power plant concept. This review paper covers the experience gained, and the lessons learned from the operation of helium gas turbine plants and related test facilities, and puts these into perspective since over three decades have passed since they were deployed. An understanding of the many unexpected events encountered, and how the problems, some of them serious, were resolved is important to avoid them being replicated in future helium turbomachines. The valuable lessons learned in the past, in many cases the hard way, particularly from the operation in Germany of the Oberhausen II 50 MWe helium gas turbine plant, and the technical know-how gained from the formidable HHV helium turbine test facility, are viewed as being germane in the context of current helium turbomachine design work being done for future high efficiency nuclear gas turbine plant concepts. - Highlights: �

Modelling and operation strategies of DLR's large scale thermocline test facility (TESIS)

Science.gov (United States)

Odenthal, Christian; Breidenbach, Nils; Bauer, Thomas

2017-06-01

In this work an overview of the TESIS:store thermocline test facility and its current construction status will be given. Based on this, the TESIS:store facility using sensible solid filler material is modelled with a fully transient model, implemented in MATLAB®. Results in terms of the impact of filler site and operation strategies will be presented. While low porosity and small particle diameters for the filler material are beneficial, operation strategy is one key element with potential for optimization. It is shown that plant operators have to ponder between utilization and exergetic efficiency. Different durations of the charging and discharging period enable further potential for optimizations.

Operating manual for the High Flux Isotope Reactor. Description of the facility

Energy Technology Data Exchange (ETDEWEB)

None

1965-06-01

This report contains a comprehensive description of the High Flux Isotope Reactor facility. Its primary purpose is to supplement the detailed operating procedures, providing the reactor operators with background information on the various HFIR systems. The detailed operating procedures are presented in another report.

National Ignition Facility Control and Information System Operational Tools

International Nuclear Information System (INIS)

Marshall, C.D.; Beeler, R.G.; Bowers, G.A.; Carey, R.W.; Fisher, J.M.; Foxworthy, C.B.; Frazier, T.M.; Mathisen, D.G.; Lagin, L.J.; Rhodes, J.J.; Shaw, M.J.

2009-01-01

The National Ignition Facility (NIF) in Livermore, California, is the world's highest-energy laser fusion system and one of the premier large scale scientific projects in the United States. The system is designed to setup and fire a laser shot to a fusion ignition or high energy density target at rates up to a shot every 4 hours. NIF has 192 laser beams delivering up to 1.8 MJ of energy to a ∼2 mm target that is planned to produce >100 billion atm of pressure and temperatures of >100 million degrees centigrade. NIF is housed in a ten-story building footprint the size of three football fields as shown in Fig. 1. Commissioning was recently completed and NIF will be formally dedicated at Lawrence Livermore National Laboratory on May 29, 2009. The control system has 60,000 hardware controls points and employs 2 million lines of control system code. The control room has highly automated equipment setup prior to firing laser system shots. This automation has a data driven implementation that is conducive to dynamic modification and optimization depending on the shot goals defined by the end user experimenters. NIF has extensive facility machine history and infrastructure maintenance workflow tools both under development and deployed. An extensive operational tools suite has been developed to support facility operations including experimental shot setup, machine readiness, machine health and safety, and machine history. The following paragraphs discuss the current state and future upgrades to these four categories of operational tools.

On the Waterway Staff Training Management and Innovation%试论航道员工培训管理与创新

Institute of Scientific and Technical Information of China (English)

镇卫兵

2014-01-01

近年来我国航道事业随着社会经济的快速发展越来越被重视，航道作为水路运输的重要组成部分，其管理状况对水运发展起着直接影响作用。本文通过对航道现行体制与管理情况探讨，结合员工培训管理与创新分析，提出加强航道管理水平的策略，以实现水运交通事业快速持续健康发展的目标。%In recent years, with the rapid development of social economy, waterway business in China has been paid more and more attention. As an important part of water transportation, waterway's management conditions have a direct impact on water transportation development. Through the discussion of current system and management conditions of waterway, combined with analysis of employee training management and innovation, this article puts forward the strategies to strengthen the waterway management level, in order to achieve the goal of rapid, sustainable and healthy development of waterway transportation business.

Design and operation of radiation facilities

International Nuclear Information System (INIS)

Gay, H.G.

1983-01-01

The design, manufacture, and operation of Cobalt-60 Radiation Processing Facilities is a well established technology. However, the products requiring radiation processing are constantly increasing. Product and dose variations create different requirements in the irradiator design. Several basic design concepts which have been developed and installed by Atomic Energy of Canada Limited are discussed. Irradiators are most efficient when designed to handle a limited product density range at an established dose. Requirements for irradiators to process a multitude of different products at different doses leads to a reduction of irradiator efficiency with resultant increase in processing costs

Operator training facilities for CEGB advanced gas cooled reactors

International Nuclear Information System (INIS)

Green, J.F.; Birnie, S.

1980-01-01

The facilities provided at the Nuclear Power Training Centre of the CEGB for the training of operators fo the AGR are described. The simulator control desks are replicas of three AGR designs with, in addition, simulation of the Data Processing System for each station. Three modes of operation are envisaged: a.) Demonstration where the simulator is used by the tutor to illustrate lecture on plant behaviour. b.) Interaction where the student carries out normal procedures and experiences plant failure situations. c.) Investigation where engineering staff use the simulator for validation of modified operational procedures, ergonomic studies etc. (orig./HP)

A knowledge acquisition process to analyse operational problems in solid waste management facilities.

Science.gov (United States)

Dokas, Ioannis M; Panagiotakopoulos, Demetrios C

2006-08-01

The available expertise on managing and operating solid waste management (SWM) facilities varies among countries and among types of facilities. Few experts are willing to record their experience, while few researchers systematically investigate the chains of events that could trigger operational failures in a facility; expertise acquisition and dissemination, in SWM, is neither popular nor easy, despite the great need for it. This paper presents a knowledge acquisition process aimed at capturing, codifying and expanding reliable expertise and propagating it to non-experts. The knowledge engineer (KE), the person performing the acquisition, must identify the events (or causes) that could trigger a failure, determine whether a specific event could trigger more than one failure, and establish how various events are related among themselves and how they are linked to specific operational problems. The proposed process, which utilizes logic diagrams (fault trees) widely used in system safety and reliability analyses, was used for the analysis of 24 common landfill operational problems. The acquired knowledge led to the development of a web-based expert system (Landfill Operation Management Advisor, http://loma.civil.duth.gr), which estimates the occurrence possibility of operational problems, provides advice and suggests solutions.

ARM Operations and Engineering Procedure Mobile Facility Site Startup

Energy Technology Data Exchange (ETDEWEB)

Voyles, Jimmy W

2015-05-01

This procedure exists to define the key milestones, necessary steps, and process rules required to commission and operate an Atmospheric Radiation Measurement (ARM) Mobile Facility (AMF), with a specific focus toward on-time product delivery to the ARM Data Archive. The overall objective is to have the physical infrastructure, networking and communications, and instrument calibration, grooming, and alignment (CG&A) completed with data products available from the ARM Data Archive by the Operational Start Date milestone.

Efficacy of commercial algaecides to manage species of Phytophthora in suburban waterways

Science.gov (United States)

G. Curtis Colburn; Steven N. Jeffers

2010-01-01

Many commercial algaecides contain copper compounds as active ingredients. Phytophthora spp. and other oomycetes are known to be sensitive to copper-based fungicides. Therefore, algaecides registered to manage algae in natural waterways and irrigation waters also might be effective for mitigating or even eradicating Phytophthora ...

Fuel conditioning facility electrorefiner cadmium vapor trap operation

International Nuclear Information System (INIS)

Vaden, D. E.

1998-01-01

Processing sodium-bonded spent nuclear fuel at the Fuel Conditioning Facility at Argonne National Laboratory-West involves an electrometallurgical process employing a molten LiCl-KCl salt covering a pool of molten cadmium. Previous research has shown that the cadmium dissolves in the salt as a gas, diffuses through the salt layer and vaporizes at the salt surface. This cadmium vapor condenses on cool surfaces, causing equipment operation and handling problems. Using a cadmium vapor trap to condense the cadmium vapors and reflux them back to the electrorefiner has mitigated equipment problems and improved electrorefiner operations

Integrated operations plan for the MFTF-B Mirror Fusion Test Facility. Volume II. Integrated operations plan

Energy Technology Data Exchange (ETDEWEB)

1981-12-01

This document defines an integrated plan for the operation of the Lawrence Livermore National Laboratory (LLNL) Mirror Fusion Test Facility (MFTF-B). The plan fulfills and further delineates LLNL policies and provides for accomplishing the functions required by the program. This plan specifies the management, operations, maintenance, and engineering support responsibilities. It covers phasing into sustained operations as well as the sustained operations themselves. Administrative and Plant Engineering support, which are now being performed satisfactorily, are not part of this plan unless there are unique needs.

Integrated operations plan for the MFTF-B Mirror Fusion Test Facility. Volume II. Integrated operations plan

International Nuclear Information System (INIS)

1981-12-01

This document defines an integrated plan for the operation of the Lawrence Livermore National Laboratory (LLNL) Mirror Fusion Test Facility (MFTF-B). The plan fulfills and further delineates LLNL policies and provides for accomplishing the functions required by the program. This plan specifies the management, operations, maintenance, and engineering support responsibilities. It covers phasing into sustained operations as well as the sustained operations themselves. Administrative and Plant Engineering support, which are now being performed satisfactorily, are not part of this plan unless there are unique needs

Decontamination and recovery of a nuclear facility to allow continued operation

International Nuclear Information System (INIS)

Cavaghan, Josh

2017-01-01

A power supply failure caused a loss of power to key ventilation systems in an operating nuclear facility. The in-cell depression was lost, which led to an egress of activity through prepared areas and into the normal operating areas. After an initial programme of radiological monitoring to quantify and categorise the activity in the operating areas, a plan was developed for the decontamination and remediation of the plant. The scope of the recovery plan was substantial and featured several key stages. The contamination was almost entirely "1"3"7Cs, reflecting the α:β/γ ratio for the facility. In addition to the physical remediation work, several administrative controls were introduced such as new local rules, safety signage to indicate abnormal radiological conditions in certain areas and training of the decontamination teams. All areas of plant, which were contaminated, were returned to normal access arrangements and the plant was successfully returned to full operational capability, <12 months from the date of the event. (authors)

Implementation of conduct of operations at Paducah uranium hexafluoride (UF{sub 6}) sampling and transfer facility

Energy Technology Data Exchange (ETDEWEB)

Penrod, S.R. [Martin Marietta Energy Systems, Inc., KY (United States)

1991-12-31

This paper describes the initial planning and actual field activities associated with the implementation of {open_quotes}Conduct of Operations{close_quotes}. Conduct of Operations is an operating philosophy that was developed through the Institute of Nuclear Power Operations (INPO). Conduct of Operations covers many operating practices and is intended to provide formality and discipline to all aspects of plant operation. The implementation of these operating principles at the UF{sub 6} Sampling and Transfer Facility resulted in significant improvements in facility operations.

Implementation of conduct of operations at Paducah uranium hexafluoride (UF{sub 6}) sampling and transfer facility

Energy Technology Data Exchange (ETDEWEB)

Penrod, S.R. [Martin Marietta Energy Systems, Inc., KY (United States)

1991-12-31

This paper describes the initial planning and actual field activities associated with the implementation of {open_quotes}Conduct of Operations{close_quotes}, Conduct of Operations is an operating philosophy that was developed through the Institute of Nuclear Power Operations (INPO). Conduct of Operations covers many operating practices and is intended to provide formality and discipline to all aspects of plant operation. The implementation of these operating principles at the UF{sub 6} Sampling and Transfer Facility resulted in significant improvements in facility operations.

Operating manual for the Tower Shielding Facility

International Nuclear Information System (INIS)

1985-12-01

This manual provides information necessary to operate and perform maintenance on the reactor systems and all equipment or systems which can affect their operation or the safety of personnel at the Tower Shielding Facility. The first four chapters consist of introductory and descriptive material of benefit to personnel in training, the qualifications required for training, the responsibilities of the personnel in the organization, and the procedures for reviewing proposed experiments. Chapter 8, Emergency Procedures, is also a necessary part of the indoctrination of personnel. The procedures for operation of the Tower Shielding Reactor (TSR-II), its water cooling system, and the main tower hoists are outlined in Chapters 5, 6, and 7. The Technical Specification surveillance requirements for the TSR-II are summarized in Chapter 9. The maintenance and calibration schedule is spelled out in Chapter 10. The procedures for assembly and disassembly of the TSR-II are outlined in Chapter 11

Waste Encapsulation and Storage Facility interim operational safety requirements

CERN Document Server

Covey, L I

2000-01-01

The Interim Operational Safety Requirements (IOSRs) for the Waste Encapsulation and Storage Facility (WESF) define acceptable conditions, safe boundaries, bases thereof, and management or administrative controls required to ensure safe operation during receipt and inspection of cesium and strontium capsules from private irradiators; decontamination of the capsules and equipment; surveillance of the stored capsules; and maintenance activities. Controls required for public safety, significant defense-in-depth, significant worker safety, and for maintaining radiological consequences below risk evaluation guidelines (EGs) are included.

Map of gas facilities and operators in Northeast British Columbia

Energy Technology Data Exchange (ETDEWEB)

Anon.

2005-06-01

This map represents 57 gas facilities and operators and references location on the map to the facility and operator. The Northern Rockies Regional district is indicated, as is the Peace River Regional district. Roads, truck trails, railroads, pipeline and airstrips are indicated as well as oil and gas fields. Various protected areas and First Nations settlement areas and regions are also indicated. The following companies placed advertisements on the map, detailing the services they provide: Wellco Energy Services; C.E. Franklin Ltd.; the City of Fort St. John, Region of Chetwynd; Smith Bits; the City of Dawson Creek, Economic Development and Tourism; Fort Nelson and Northern Rockies Regional District; Pipetech Corp.; Kenwood; Hughes Christensen; Spartan Controls; FI Canada Oil Services Ltd.; Northstar Drillstem Testers Inc.; Rainbow Transport Ltd.1 fig.

Integrated safeguards and facility design and operations

International Nuclear Information System (INIS)

Tape, J.W.; Coulter, C.A.; Markin, J.T.; Thomas, K.E.

1987-01-01

The integration of safeguards functions to deter or detect unauthorized actions by an insider requires the careful communication and management of safeguards-relevant information on a timely basis. The traditional separation of safeguards functions into physical protection, materials control, and materials accounting often inhibits important information flows. Redefining the major safeguards functions as authorization, enforcement, and verification, and careful attention to management of information from acquisition to organization, to analysis, to decision making can result in effective safeguards integration. The careful inclusion of these ideas in facility designs and operations will lead to cost-effective safeguards systems. The safeguards authorization function defines, for example, personnel access requirements, processing activities, and materials movements/locations that are permitted to accomplish the mission of the facility. Minimizing the number of authorized personnel, limiting the processing flexibility, and maintaining up-to-date flow sheets will facilitate the detection of unauthorized activities. Enforcement of the authorized activities can be achieved in part through the use of barriers, access control systems, process sensors, and health and safety information. Consideration of safeguards requirements during facility design can improve the enforcement function. Verification includes the familiar materials accounting activities as well as auditing and testing of the other functions

Operational safety assessment of underground test facilities for mined geologic waste disposal

International Nuclear Information System (INIS)

Elder, H.K.

1993-01-01

This paper describes the operational safety assessment for the underground facilities for the exploratory studies facility (ESF) at the Yucca Mountain Project. The systematic identification and evaluation of hazards related to the ESF is an integral part of the systems engineering process; whereby safety is considered during planning, design, testing, and construction. A largely qualitative approach based on the analysis of potential accidents was used since radiological safety analysis was not required. The risk assessment summarized credible accident scenarios and the design provides mitigation of the risks to a level that the facility can be constructed and operated with an adequate level of safety. The risk assessment also provides reasonable assurance that all identifiable major accident scenarios have been reviewed and design mitigation features provided to ensure an adequate level of safety

Assessment of Radionuclides Release from Inshas LILW Disposal Facility Under Normal and Unusual Operational Conditions

International Nuclear Information System (INIS)

Zaki, A.A.

2008-01-01

Disposing of low and intermediate radioactive waste (LILW) is a big concern for Egypt due to the accumulated waste as a result of past fifty years of peaceful nuclear applications. Assessment of radionuclides release from Inshas LILW disposal facility under normal and unusual operational conditions is very important in order to apply for operation license of the facility. Aqueous release of radionuclides from this disposal facility is controlled by water flow, access of the water to the wasteform, release of the radionuclides from the wasteform, and transport to the disposal facility boundary. In this work, the release of 137 Cs , 6C o, and 90 Sr radionuclides from the Inshas disposal facility was studied under the change of operational conditions. The release of these radio contaminants from the source term to the unsaturated and saturated zones , to groundwater were studied. It was found that the concentration of radionuclides in a groundwater well located 150 m away from the Inshas disposal facility is less than the maximum permissible concentration in groundwater in both cases

Operation of Temporary Radioactive waste stoprage facility

Energy Technology Data Exchange (ETDEWEB)

Kinseem, A A; Abulfaraj, W H; Sohsah, M A; Kamal, S M; Mamoon, A M [Nuclear Engineering Department, Faculty of Engineering, King Abdelazizi University jeddah-21413, Saudi Arabia (Saudi Arabia)

1997-12-31

Radionuclides of various half lives have been in use for several years years at different Departments of king Abdulaziz university, the university hospital, and research center. The use of unsealed radionuclides in many laboratories, resulted in considerable amounts of solid and liquid radwaste, mainly radiopharmaceuticals. To avoid accumulation of radwastes in working areas, a temporary radioactive waste storage facility was built. Segregation of radwastes according to type was carried out, followed by collection into appropriate containers and transfer to the storage facility. Average radiation dose rate inside the store was maintained at about 75 {mu} h{sup -1} through use of appropriate shielding. The dose rates at points one meter outside the store walls were maintained at about 15-20 {mu}Sv h{sup -1}. Utilization of radioisotopes during the period of 1991-1995 resulted in a volume of about 1.8 m{sup 3} of solid radwaste and about 200 L of liquid radwaste. Records of the store inventory are maintained in a computer database, listing dates, types, activities and packaging data pertinent to the radwastes delivered to the store. Quality assurance procedures are implemented during the different stages of the radwaste collection, transportation, and storage. Construction and operation of the storage facility comply with radiation safety requirements for the workers handling the radwastes, the public and the environment. The capacity of the storage facility is such that it will accommodate storage of generated radwastes of long half life up to year 2016. Permanent disposal of such radwastes may be indicated afterwards. 2 figs., 3 tabs.

Operation and Maintenance Manual for the Central Facilities Area Sewage Treatment Plant

Energy Technology Data Exchange (ETDEWEB)

Norm Stanley

2011-02-01

This Operation and Maintenance Manual lists operator and management responsibilities, permit standards, general operating procedures, maintenance requirements and monitoring methods for the Sewage Treatment Plant at the Central Facilities Area at the Idaho National Laboratory. The manual is required by the Municipal Wastewater Reuse Permit (LA-000141-03) the sewage treatment plant.

Guidelines for operator competence - Optimising facility management processes; Leitfaden Betreiberkompetenz. Schritt fuer Schritt Facility Management Prozesse optimieren

Energy Technology Data Exchange (ETDEWEB)

Moser, R

2005-06-15

This brochure issued by IFMA (International Facility Management Association) Switzerland and the Swiss Federal Office of Energy (SFOE) presents interactive guidelines for energy management in the area of facility management. These guidelines are based on the results of a project carried out by the International Energy Agency's Annex 40 'Operator competence'. The guidelines provide a step-by-step guide from initial analysis through to successful project completion and answer many questions that may crop up during the process. The focus is placed on energy aspects. Tools and 14 sample process descriptions are provided along with practical examples. Theoretical aspects are also presented and discussed, including models for operator roles and the processes involved. Also, change, risk and knowledge management are examined. Notes and information on possibilities for further education are presented.

Guidelines for operator competence - Optimising facility management processes; Leitfaden Betreiberkompetenz. Schritt fuer Schritt Facility Management Prozesse optimieren

Energy Technology Data Exchange (ETDEWEB)

Moser, R.

2005-06-15

This brochure issued by IFMA (International Facility Management Association) Switzerland and the Swiss Federal Office of Energy (SFOE) presents interactive guidelines for energy management in the area of facility management. These guidelines are based on the results of a project carried out by the International Energy Agency's Annex 40 'Operator competence'. The guidelines provide a step-by-step guide from initial analysis through to successful project completion and answer many questions that may crop up during the process. The focus is placed on energy aspects. Tools and 14 sample process descriptions are provided along with practical examples. Theoretical aspects are also presented and discussed, including models for operator roles and the processes involved. Also, change, risk and knowledge management are examined. Notes and information on possibilities for further education are presented.

EnergySolution's Clive Disposal Facility Operational Research Model - 13475

Energy Technology Data Exchange (ETDEWEB)

Nissley, Paul; Berry, Joanne [EnergySolutions, 2345 Stevens Dr. Richland, WA 99354 (United States)

2013-07-01

EnergySolutions owns and operates a licensed, commercial low-level radioactive waste disposal facility located in Clive, Utah. The Clive site receives low-level radioactive waste from various locations within the United States via bulk truck, containerised truck, enclosed truck, bulk rail-cars, rail boxcars, and rail inter-modals. Waste packages are unloaded, characterized, processed, and disposed of at the Clive site. Examples of low-level radioactive waste arriving at Clive include, but are not limited to, contaminated soil/debris, spent nuclear power plant components, and medical waste. Generators of low-level radioactive waste typically include nuclear power plants, hospitals, national laboratories, and various United States government operated waste sites. Over the past few years, poor economic conditions have significantly reduced the number of shipments to Clive. With less revenue coming in from processing shipments, Clive needed to keep its expenses down if it was going to maintain past levels of profitability. The Operational Research group of EnergySolutions were asked to develop a simulation model to help identify any improvement opportunities that would increase overall operating efficiency and reduce costs at the Clive Facility. The Clive operations research model simulates the receipt, movement, and processing requirements of shipments arriving at the facility. The model includes shipment schedules, processing times of various waste types, labor requirements, shift schedules, and site equipment availability. The Clive operations research model has been developed using the WITNESS{sup TM} process simulation software, which is developed by the Lanner Group. The major goals of this project were to: - identify processing bottlenecks that could reduce the turnaround time from shipment arrival to disposal; - evaluate the use (or idle time) of labor and equipment; - project future operational requirements under different forecasted scenarios. By identifying

Review of Regulatory Quality Assurance Requirements for the Operation of Nuclear R and D Facilities

International Nuclear Information System (INIS)

Kwon, Hyuk Il; Lim, Nam Jin

2005-01-01

Korea Atomic Energy Research Institute (KAERI) has many R and D facilities in operation, including HANARO research reactor, radioactive waste treatment facility (RWTF), post-irradiation examination facility (PIEF) and irradiated material test facility (IMEF). Recently, nation-wide interest is focused on the safety and security of major industrial facilities. Safe operation of nuclear facilities is imperative because of the consequence of public disaster by radiological release/ contamination, in case of an accident. Recently, Ministry of Science and Technology (MOST) of the Korean government announced amendments of Atomic Energy laws to enforce requirements of the physical protection and radiological emergency. In this paper, the context of amended Atomic Energy laws were reviewed to confirm quality assurance measures and identify additional QA activities, if any, that is required by the amendment

7 CFR 1767.27 - Operation and maintenance expenses.

Science.gov (United States)

2010-01-01

..., DEPARTMENT OF AGRICULTURE (CONTINUED) ACCOUNTING REQUIREMENTS FOR RUS ELECTRIC BORROWERS Uniform System of... Waterways 544Maintenance of Electric Plant 545Maintenance of Miscellaneous Hydraulic Plant Other Power....1Load Dispatch-Reliability 561.2Load Dispatch-Monitor and Operate Transmission System 561.3Load Dispatch...

Techniques for controlling air pollution from the operation of nuclear facilities. Report of a panel

International Nuclear Information System (INIS)

1966-01-01

This manual is provided for the guidance of those persons or authorities who are responsible for the organization, control and operation of ventilation systems and air-cleaning installations in nuclear establishments. It is intended to generalize about existing experience in the operation of such systems at nuclear facilities including reactors and laboratories for production, use and handling of radionuclides and other toxic materials. This manual will provide designers and operators of nuclear facilities in which ventilation and air-cleaning systems are used with the factors which have to be considered to create safe working conditions inside facilities and without polluting the atmosphere or the environment to a hazardous level.

9 CFR 354.210 - Minimum standards for sanitation, facilities, and operating procedures in official plants.

Science.gov (United States)

2010-01-01

... 9 Animals and Animal Products 2 2010-01-01 2010-01-01 false Minimum standards for sanitation, facilities, and operating procedures in official plants. 354.210 Section 354.210 Animals and Animal Products... sanitation, facilities, and operating procedures in official plants. The provisions of §§ 354.210 to 354.247...

Applicability of market-based instruments for safeguarding water quality in coastal waterways: Case study for Darwin Harbour, Australia

Science.gov (United States)

Greiner, Romy

2014-02-01

Water pollution of coastal waterways is a complex problem due to the cocktail of pollutants and multiplicity of polluters involved and pollution characteristics. Pollution control therefore requires a combination of policy instruments. This paper examines the applicability of market-based instruments to achieve effective and efficient water quality management in Darwin Harbour, Northern Territory, Australia. Potential applicability of instruments is examined in the context of biophysical and economic pollution characteristics, and experience with instruments elsewhere. The paper concludes that there is potential for inclusion of market-based instruments as part of an instrument mix to safeguard water quality in Darwin Harbour. It recommends, in particular, expanding the existing licencing system to include quantitative pollution limits for all significant point polluters; comprehensive and independent pollution monitoring across Darwin Harbour; public disclosure of water quality and emissions data; positive incentives for landholders in the Darwin Harbour catchment to improve land management practices; a stormwater offset program for greenfield urban developments; adoption of performance bonds for developments and operations which pose a substantial risk to water quality, including port expansion and dredging; and detailed consideration of a bubble licensing scheme for nutrient pollution. The paper offers an analytical framework for policy makers and resource managers tasked with water quality management in coastal waterways elsewhere in Australia and globally, and helps to scan for MBIs suitable in any given environmental management situation.

Regulatory quality assurance requirements for the operation of nuclear R and D facilities in Korea

International Nuclear Information System (INIS)

Kwon, H.I.; Lim, N.J.

2006-01-01

Full text: Korea Atomic Energy Research Institute (KAERI) has many R and D facilities in operation. including HANARO research reactor, radioactive waste treatment facility (RWTF), post-irradiation examination facility (PIEF) and irradiated material test facility (IMEF). Recently. nation-wide interest is focused on the safety and security of major industrial facilities. Safe operation of nuclear facilities is imperative because of the consequence of public disaster by radiological release/contamination, in case of an accident. Recently, Ministry of Science and Technology (MOST) of the Korean government announced amendments of Atomic Energy laws to enforce requirements of the physical protection and radiological emergency. All provisions on nuclear safety regulation and radiation protection are entrusted to the Atomic Energy Act(AEA). The Act is enacted as the main law concerning the safety regulation of nuclear installations, and is supplemented by the Enforcement Decree and Enforcement Regulation of the Act. These Atomic Energy laws include provisions on the construction permission and the operation license of nuclear installations, such as nuclear power reactors, research reactors, nuclear ships, nuclear fuel fabrication facilities, spent fuel treatment facilities, etc. Regulatory requirements for the regulatory inspection and the safety measures for operation are also defined in the laws. The Notice of the MOST prescribes specific issues including regulatory requirements and technical standards, as entrusted by the AEA, the Decree and the Regulation. Detailed QA requirements for nuclear installations are specified differently, depending upon the type of facility. The guidelines for safety reviews and regulatory inspections are developed by the Korea Institute of Nuclear Safety (KINS), which is an exclusive organization for safety regulation of nuclear installations in Korea. In this paper, the context of the Atomic Energy laws were reviewed to confirm the

Operational characteristics of the OMEGA short-wavelength laser fusion facility

International Nuclear Information System (INIS)

Soures, J.M.; Hutchison, R.; Jacobs, S.; McCrory, R.L.; Peck, R.; Seka, W.

1984-01-01

Twelve beams of the OMEGA, 24 beam direct-drive laser facility have been converted to 351-nm wavelength operation. The performance characteristics of this short-wavelength facility will be discussed. Beam-to-beam energy balance of +-2.3% and on-target energy, at 351-nm, in excess of 70 J per beam have been demonstrated. Long-term performance (>600 shots) of the system has been optimized by appropriate choice of index matching liquid, optical materials and coatings. The application of this system in direct-drive laser fusion experiments will be discussed

The emergence of care facilities in Thailand for older German-speaking people: structural backgrounds and facility operators as transnational actors.

Science.gov (United States)

Bender, Désirée; Hollstein, Tina; Schweppe, Cornelia

2017-12-01

This paper presents findings from an ethnographic study of old age care facilities for German-speaking people in Thailand. It analyses the conditions and processes behind the development and specific designs of such facilities. It first looks at the intertwinement, at the socio-structural level, of different transborder developments in which the facilities' emergence is embedded. Second, it analyses the processes that accompany the emergence, development and organisation of these facilities at the local level. In this regard, it points out the central role of the facility operators as transnational actors who mediate between different frames of reference and groups of actors involved in these facilities. It concludes that the processes of mediation and intertwining are an important and distinctive feature of the emergence of these facilities, necessitated by the fact that, although the facilities are located in Thailand, their 'markets' are in the German-speaking countries of their target groups.

Study of the Relevance of the Quality of Care, Operating Efficiency and Inefficient Quality Competition of Senior Care Facilities.

Science.gov (United States)

Lin, Jwu-Rong; Chen, Ching-Yu; Peng, Tso-Kwei

2017-09-11

The purpose of this research is to examine the relation between operating efficiency and the quality of care of senior care facilities. We designed a data envelopment analysis, combining epsilon-based measure and metafrontier efficiency analyses to estimate the operating efficiency for senior care facilities, followed by an iterative seemingly unrelated regression to evaluate the relation between the quality of care and operating efficiency. In the empirical studies, Taiwan census data was utilized and findings include the following: Despite the greater operating scale of the general type of senior care facilities, their average metafrontier technical efficiency is inferior to that of nursing homes. We adopted senior care facility accreditation results from Taiwan as a variable to represent the quality of care and examined the relation of accreditation results and operating efficiency. We found that the quality of care of general senior care facilities is negatively related to operating efficiency; however, for nursing homes, the relationship is not significant. Our findings show that facilities invest more in input resources to obtain better ratings in the accreditation report. Operating efficiency, however, does not improve. Quality competition in the industry in Taiwan is inefficient, especially for general senior care facilities.

Controls on denitrification potential in nitrate-rich waterways and riparian zones of an irrigated agricultural setting.

Science.gov (United States)

Webster, Alex J; Groffman, Peter M; Cadenasso, Mary L

2018-02-21

Denitrification, the microbial conversion of NO 3 - to N gases, is an important process contributing to whether lotic and riparian ecosystems act as sinks for excess NO 3 - from agricultural activities. Though agricultural waterways and riparian zones have been a focus of denitrification research for decades, almost none of this research has occurred in the irrigated agricultural settings of arid and semi-arid climates. In this study, we conducted a broad survey of denitrification potential in riparian soils and channel sediment from 79 waterway reaches in the irrigated agricultural landscape of California's Central Valley. With this approach, we sought to capture the wide range of variation that arose from diverse waterway management and fluctuating flow conditions, and use this variation to identify promising management interventions. We explored associations of denitrification potentials with surface water NO 3 - -N, organic matter, flow conditions, vegetation cover, near-channel riparian bank slope, and channel geomorphic features using generalized linear mixed models. We found strong associations of sediment denitrification potentials with reach flow conditions, which we hypothesize was the result of variation in microbial communities' tolerance to dry-wet cycles. Denitrification potentials in riparian soils, in contrast, did not appear affected by flow conditions, but instead were associated with organic matter, vegetation cover, and bank slope in the riparian zone. These results suggest a strong need for further work on how denitrification responds to varying flow conditions and dry-wet cycles in non-perennial lotic ecosystems. Our findings also demonstrate that denitrifier communities respond to key features of waterway management, which can therefore be leveraged to control denitrification through a variety of management actions. This article is protected by copyright. All rights reserved. This article is protected by copyright. All rights reserved.

Process pump operating problems and equipment failures, F-Canyon Reprocessing Facility, Savannah River Plant

International Nuclear Information System (INIS)

Durant, W.S.; Starks, J.B.; Galloway, W.D.

1987-02-01

A compilation of operating problems and equipment failures associated with the process pumps in the Savannah River Plant F-Canyon Fuel Reprocessing Facility is presented. These data have been collected over the 30-year operation of the facility. An analysis of the failure rates of the pumps is also presented. A brief description of the pumps and the data bank from which the information was sorted is also included

42 CFR 412.405 - Preadmission services as inpatient operating costs under the inpatient psychiatric facility...

Science.gov (United States)

2010-10-01

... under the inpatient psychiatric facility prospective payment system. 412.405 Section 412.405 Public... Services of Inpatient Psychiatric Facilities § 412.405 Preadmission services as inpatient operating costs under the inpatient psychiatric facility prospective payment system. The prospective payment system...

A proposed regulatory policy statement on human factors requirements in the design and operation of Canadian nuclear facilities

International Nuclear Information System (INIS)

1986-10-01

With the increasing complexity of new nuclear facilities and the extent to which automation is being applied, it is essential that the staff who operate a facility be considered as integral components in the design and safety analyses. This policy statement is proposed to indicate those areas of facility design and operation where the role of the human operator must be especially examined

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

Management of Environmental Resources of Cutoff Bends Along the Tennessee-Tombigbee Waterway.

Science.gov (United States)

1987-11-01

WW2 , pp 51-67. Carey, W. C. 1964. "Discussion of ’Hydraulic Aspects of Arkansas River Sta- bilization,’" Journal of the Waterways and Harbors Division...photographs listed in Table A6, color infrared (IR) photographs of several of the Tombigbee River sites were obtained and used in a qualitative fashion. For

Operational experience of the fuel cleaning facility of Joyo

International Nuclear Information System (INIS)

Mukaibo, R.; Matsuno, Y.; Sato, I.; Yoneda, Y.; Ito, H.

1978-01-01

Spent fuel assemblies in 'Joyo', after they are taken out of the core, are taken to the Fuel Cleaning Facility in the reactor service building and sodium removal is done. The cleaning process is done by cooling the assembly with argon gas, steam charging and rinsing by demineralized water. Deposited sodium was 50 ∼ 60 g per assembly. The sodium and steam reaction takes about 15 minutes to end and the total time the fuel is placed in the pot is about an hour. The total number of assemblies cleaned in the facility was 95 as of November 1977. In this report the operational experience together with discussions of future improvements are given. (author)

Operational experience of the fuel cleaning facility of Joyo

Energy Technology Data Exchange (ETDEWEB)

Mukaibo, R; Matsuno, Y; Sato, I; Yoneda, Y; Ito, H [O-arai Engineering Centre, PNC, Ibaraki-ken, Tokio (Japan)

1978-08-01

Spent fuel assemblies in 'Joyo', after they are taken out of the core, are taken to the Fuel Cleaning Facility in the reactor service building and sodium removal is done. The cleaning process is done by cooling the assembly with argon gas, steam charging and rinsing by demineralized water. Deposited sodium was 50 {approx} 60 g per assembly. The sodium and steam reaction takes about 15 minutes to end and the total time the fuel is placed in the pot is about an hour. The total number of assemblies cleaned in the facility was 95 as of November 1977. In this report the operational experience together with discussions of future improvements are given. (author)

The target programme for water pollution control up to year 2005. The impact to alternative pollution load levels on inland waterways; Vesiensuojelun tavoitteet vuoteen 2005. Vaihtoehtoisten kuormitustasojen vaikutukset sisaevesissae

Energy Technology Data Exchange (ETDEWEB)

Marttunen, M. [eds.

1998-11-01

The publication presents waterway-specific pollution loading surveys connected with the target programme for water pollution control up to 2005 and the results of a survey concerning inland waters. The work evaluates and compares the magnitude and significance of future pollution loads from various sources on the state of the waterway and assesses the impact on the condition of the waterway of two alternative pollution loading levels. The survey was conducted on 24 lakes or parts thereof and 10 rivers. Sixteen of these are subject to loading from the pulls and paper industry. The waterways selected for examination were especially ones for which relatively recent loading analyses were available and to which water quality models have been applied. The general classification of fitness for use was used as a benchmark for changes occurring in the water quality of the waterways. The findings show that particularly the large waterway systems can be moved into a higher fitness for use class by reducing substantially the nutrient loading. Significant improvement in the condition of eutrophic lakes and coastal rivers with their internal loads is difficult. (orig.) 26 refs.

Meeting the challenges of bringing a new base facility operation model to Gemini Observatory

Science.gov (United States)

Nitta, Atsuko; Arriagada, Gustavo; Adamson, A. J.; Cordova, Martin; Nunez, Arturo; Serio, Andrew; Kleinman, Scot

2016-08-01

The aim of the Gemini Observatory's Base Facilities Project is to provide the capabilities to perform routine night time operations with both telescopes and their instruments from their respective base facilities without anyone present at the summit. Tightening budget constraints prompted this project as both a means to save money and an opportunity to move toward increasing remote operations in the future. We successfully moved Gemini North nighttime operation to our base facility in Hawaii in Nov., 2015. This is the first 8mclass telescope to completely move night time operations to base facility. We are currently working on implementing BFO to Gemini South. Key challenges for this project include: (1) This is a schedule driven project. We have to implement the new capabilities by the end of 2015 for Gemini North and end of 2016 for Gemini South. (2) The resources are limited and shared with operations which has the higher priority than our project. (3) Managing parallel work within the project. (4) Testing, commissioning and introducing new tools to operational systems without adding significant disruptions to nightly operations. (5) Staff buying to the new operational model. (6) The staff involved in the project are spread on two locations separated by 10,000km, seven time zones away from each other. To overcome these challenges, we applied two principles: "Bare Minimum" and "Gradual Descent". As a result, we successfully completed the project ahead of schedule at Gemini North Telescope. I will discuss how we managed the cultural and human aspects of the project through these concepts. The other management aspects will be presented by Gustavo Arriagada [2], the Project Manager of this project. For technical details, please see presentations from Andrew Serio [3] and Martin Cordova [4].

Operational safety analysis of the Olkiluoto encapsulation plant and disposal facility

International Nuclear Information System (INIS)

Rossi, J.; Suolanen, V.

2012-11-01

Radiation doses for workers of the facility, for inhabitants in the environment and for terrestrial ecosystem possibly caused by the encapsulation and disposal facilities to be built at Olkiluoto during its operation were considered in the study. The study covers both the normal operation of the plant and some hypothetical incidents and accidents. Release through the ventilation stack is assumed to be filtered both in normal operation and in hypothetical abnormal fault and accident cases. In addition the results for unfiltered releases are also presented. This research is limited to the deterministic analysis. During about 30 operation years of our four nuclear power plant units there have been found 58 broken fuel pins. Roughly estimating there has been one fuel leakage per year in a facility (includes two units). Based on this and adopting a conservative approach, it is estimated that one fuel pin per year could leak in normal operation during encapsulation process. The release magnitude in incidents and accidents is based on the event chains, which lead to loss of fuel pin tightness followed by a discharge of radionuclides into the handling space and to some degree to the atmosphere through the ventilation stack equipped with redundant filters. The most exposed group of inhabitants is conservatively assumed to live at the distance of 200 meters from the encapsulation and disposal plant and it will receive the largest doses in most dispersion conditions. The dose value to a member of the most exposed group was calculated on the basis of the weather data in such a way that greater dose than obtained here is caused only in 0.5 percent of dispersion conditions. The results obtained indicate that during normal operation the doses to workers remain small and the dose to the member of the most exposed group is less than 0.001 mSv per year. In the case of hypothetical fault and accident releases the offsite doses do not exceed either the limit values set by the safety

Conjunctive operation of river facilities for integrated water resources management in Korea

Directory of Open Access Journals (Sweden)

H. Kim

2016-10-01

Full Text Available With the increasing trend of water-related disasters such as floods and droughts resulting from climate change, the integrated management of water resources is gaining importance recently. Korea has worked towards preventing disasters caused by floods and droughts, managing water resources efficiently through the coordinated operation of river facilities such as dams, weirs, and agricultural reservoirs. This has been pursued to enable everyone to enjoy the benefits inherent to the utilization of water resources, by preserving functional rivers, improving their utility and reducing the degradation of water quality caused by floods and droughts. At the same time, coordinated activities are being conducted in multi-purpose dams, hydro-power dams, weirs, agricultural reservoirs and water use facilities (featuring a daily water intake of over 100 000 m3 day−1 with the purpose of monitoring the management of such facilities. This is being done to ensure the protection of public interest without acting as an obstacle to sound water management practices. During Flood Season, each facilities contain flood control capacity by limited operating level which determined by the Regulation Council in advance. Dam flood discharge decisions are approved through the flood forecasting and management of Flood Control Office due to minimize flood damage for both upstream and downstream. The operational plan is implemented through the council's predetermination while dry season for adequate quantity and distribution of water.

Czech interim spent fuel storage facility: operation experience, inspections and future plans

International Nuclear Information System (INIS)

Fajman, V.; Bartak, L.; Coufal, J.; Brzobohaty, K.; Kuba, S.

1999-01-01

The paper describes the situation in the spent fuel management in the Czech Republic. The interim Spent Fuel Storage Facility (ISFSF) at Dukovany, which was commissioned in January 1997 and is using dual transport and storage CASTOR - 440/84 casks, is briefly described. The authors deal with their experience in operating and inspecting the ISFSF Dukovany. The structure of the basic safety document 'Limits and Conditions of Normal Operation' is also mentioned, including the experience of the performance. The inspection activities focused on permanent checking of the leak tightness of the CASTOR 440/84 casks, the maximum cask temperature and inspections monitoring both the neutron and gamma dose rate as well as the surface contamination. The results of the inspections are mentioned in the presentation as well. The operator's experience with re-opening partly loaded and already dried CASTOR-440/84 cask, after its transport from NPP Jaslovske Bohunice to the NPP Dukovany is also described. The paper introduces briefly the concept of future spent fuel storage both from the NPP Dukovany and the NPP Temelin, as prepared by the CEZ. The preparatory work for the Central Interim Spent Nuclear Fuel Storage Facility (CISFSF) in the Czech Republic and the information concerning the planned storage technology for this facility is discussed in the paper as well. The authors describe the site selection process and the preparatory steps concerning new spent fuel facility construction including the Environmental Impact Assessment studies. (author)

Operational readiness review for the Waste Experimental Reduction Facility. Final report

International Nuclear Information System (INIS)

1993-11-01

An Operational Readiness Review (ORR) at the Idaho National Engineering Laboratory's (INEL's) Waste Experimental Reduction Facility (WERF) was conducted by EG ampersand G Idaho, Inc., to verify the readiness of WERF to resume operations following a shutdown and modification period of more than two years. It is the conclusion of the ORR Team that, pending satisfactory resolution of all pre-startup findings, WERF has achieved readiness to resume unrestricted operations within the approved safety basis. ORR appraisal forms are included in this report

Two years of operating experience with the Seattle clinical neutron therapy facility

International Nuclear Information System (INIS)

Risler, R.; Brossard, S.; Eenmaa, J.; Kalet, I.; Wootton, P.

1987-01-01

After five years of planning, equipment acquisition, facility construction and beam testing the Seattle Clinical Neutron Therapy facility became operational in October 1984. In the past two years nearly 300 people have been treated in clinical trials. During this time 82 % of the planned treatment sessions were performed on schedule, 3 % had to be rescheduled for patient related reasons and 15 % because of equipment problems. The facility is at present running on a 5 days/week schedule: Three ten-hour treatment days, one maintenance day and one research day (radiobiology, therapy related physics). Short runs for short lived isotopes are done between patient treatments. The isocentric gantry, capable of 360 rotation is equipped with a variable collimator with 40 independent leaves. This collimation system allows the use of complex field shapes without the necessity of handling radioactive components like collimator inserts or blocks. It has turned out to be a very essential part for the efficient operation of the facility. Major causes for equipment downtime were associated with the control system, the beryllium target system, RF and magnet systems and the treatment gantry. (author)

Feasibility study for a transportation operations system cask maintenance facility

Energy Technology Data Exchange (ETDEWEB)

Rennich, M.J.; Medley, L.G.; Attaway, C.R.

1991-01-01

The US Department of Energy (DOE), Office of Civilian Radioactive Waste Management (OCRWM) is responsible for the development of a waste management program for the disposition of spent nuclear fuel (SNF) and high-level waste (HLW). The program will include a transportation system for moving the nuclear waste from the sources to a geologic repository for permanent disposal. Specially designed casks will be used to safely transport the waste. The cask systems must be operated within limits imposed by DOE, the Nuclear Regulatory Commission (NRC), and the Department of Transportation (DOT). A dedicated facility for inspecting, testing, and maintaining the cask systems was recommended by the General Accounting Office (in 1979) as the best means of assuring their operational effectiveness and safety, as well as regulatory compliance. In November of 1987, OCRWM requested a feasibility study be made of a Cask Maintenance Facility (CMF) that would perform the required functions. 46 refs., 16 figs., 13 tabs.

Feasibility study for a transportation operations system cask maintenance facility

International Nuclear Information System (INIS)

Rennich, M.J.; Medley, L.G.; Attaway, C.R.

1991-01-01

The US Department of Energy (DOE), Office of Civilian Radioactive Waste Management (OCRWM) is responsible for the development of a waste management program for the disposition of spent nuclear fuel (SNF) and high-level waste (HLW). The program will include a transportation system for moving the nuclear waste from the sources to a geologic repository for permanent disposal. Specially designed casks will be used to safely transport the waste. The cask systems must be operated within limits imposed by DOE, the Nuclear Regulatory Commission (NRC), and the Department of Transportation (DOT). A dedicated facility for inspecting, testing, and maintaining the cask systems was recommended by the General Accounting Office (in 1979) as the best means of assuring their operational effectiveness and safety, as well as regulatory compliance. In November of 1987, OCRWM requested a feasibility study be made of a Cask Maintenance Facility (CMF) that would perform the required functions. 46 refs., 16 figs., 13 tabs

Space facilities: Meeting future needs for research, development, and operations

Science.gov (United States)

The National Facilities Study (NFS) represents an interagency effort to develop a comprehensive and integrated long-term plan for world-class aeronautical and space facilities that meet current and projected needs for commercial and government aerospace research and development and space operations. At the request of NASA and the DOD, the National Research Council's Committee on Space Facilities has reviewed the space related findings of the NFS. The inventory of more than 2800 facilities will be an important resource, especially if it continues to be updated and maintained as the NFS report recommends. The data in the inventory provide the basis for a much better understanding of the resources available in the national facilities infrastructure, as well as extensive information on which to base rational decisions about current and future facilities needs. The working groups have used the inventory data and other information to make a set of recommendations that include estimates of cast savings and steps for implementation. While it is natural that the NFS focused on cost reduction and consolidations, such a study is most useful to future planning if it gives equal weight to guiding the direction of future facilities needed to satisfy legitimate national aspirations. Even in the context of cost reduction through facilities closures and consolidations, the study is timid about recognizing and proposing program changes and realignments of roles and missions to capture what could be significant savings and increased effectiveness. The recommendations of the Committee on Space Facilities are driven by the clear need to be more realistic and precise both in recognizing current incentives and disincentives in the aerospace industry and in forecasting future conditions for U.S. space activities.

Operation of the cryogenic system for the Mirror Fusion Test Facility

International Nuclear Information System (INIS)

Chronis, W.C.; Slack, D.S.

1987-01-01

The cryogenic system for the Mirror Fusion Test Facility (MFTF) at Lawrence Livermore National Laboratory (LLNL) was designed to cool the entire MFTF-B system from ambient to operating temperature in less than 10 days. The system was successfully operated in the recent plant and capital equipment (PACE) acceptance tests, and results from these tests helped us correct problem areas and improve the system

Development of cloud-operating platform for detention facility design

Science.gov (United States)

Tun Lee, Kwan; Hung, Meng-Chiu; Tseng, Wei-Fan; Chan, Yi-Ping

2017-04-01

In the past 20 years, the population of Taiwan has accumulated in urban areas. The land development has changed the hydrological environment and resulted in the increase of surface runoff and shortened the time to peak discharge. The change of runoff characteristics increases the flood risk and reduces resilient ability of the city during flood. Considering that engineering measures may not be easy to implement in populated cities, detention facilities set on building basements have been proposed to compromise the increase of surface runoff resulting from development activities. In this study, a web-based operational platform has been developed to integrate the GIS technologies, hydrological analyses, as well as relevant regulations for the design of detention facilities. The design procedure embedded in the system includes a prior selection of type and size of the detention facility, integrated hydrological analysis for the developing site, and inspection of relevant regulations. After login the platform, designers can access the system database to retrieve road maps, land use coverages, and storm sewer information. Once the type, size, inlet, and outlet of the detention facility are assigned, the system can acquire the rainfall intensity-duration-frequency information from adjacent rain gauges to perform hydrological analyses for the developing site. The increase of the runoff volume due to the development and the reduction of the outflow peak through the construction of the detention facility can be estimated. The outflow peak at the target site is then checked with relevant regulations to confirm the suitability of the detention facility design. The proposed web-based platform can provide a concise layout of the detention facility and the drainageway of the developing site on a graphical interface. The design information can also be delivered directly through a web link to authorities for inspecting to simplify the complex administrative procedures.

75 FR 71545 - Changes to NARA Facilities' Hours of Operation

Science.gov (United States)

2010-11-24

... National Archives at Philadelphia is located at the Robert N.C. Nix Federal Building, 900 Market St... NATIONAL ARCHIVES AND RECORDS ADMINISTRATION 36 CFR Parts 1253, 1254, and 1280 [NARA-10-0004] RIN 3095-AB68 Changes to NARA Facilities' Hours of Operation AGENCY: National Archives and Records...

Dissolved oxygen analysis for hydropower additions on the Illinois River

International Nuclear Information System (INIS)

Sundquist, M.J.; Elver, S.A.

1993-01-01

The Illinois Waterway is comprised of a system of eight locks along the Illinois River, the Des Plaines River, and the Chicago Sanitary Ship Canal which allow commercial barge traffic between the Mississippi River and Lake Michigan at the City of Chicago. Opportunities for production of hydroelectric power is present at several of these lock and dams. This paper presents the field study and computer simulation conducted to determine the feasibility of constructing hydroelectric powerhouses on two of these lock and dams. So as not to degrade recent improvements to water quality, the Federal Energy Regulatory Commission (FERC), in issuing the construction and operating licenses for these two hydroelectric facilities, requires the hydropower additions to not reduce the dissolved oxygen (D.O.) level downstream of the hydroelectric facilities below 6 parts per million (ppm). Presently, the waterway discharge passes through taintor gates at both of these lock and dam facilities which creates aeration. The addition of hydroelectric powerhouses would divert water from these spillways through generation equipment; consequently, the spillway aeration would not occur. The purpose of the study was to determine the amount of power generation from these facilities, given the existing waterway water quality and the FERC D.O. criteria. A computer simulation generation analysis was conducted to provide a database of the waterway water quality. A four-month extensive field collection survey was conducted over the 63 kilometer (39 mile) reach of the waterway which comprises the two downstream pools of the Brandon Road and Dresden Island projects, and 3 kilometers (2 miles) upstream of the Brandon Road Project. The analysis revealed that the hydroelectric additions were economically feasible and are an example of how the benefits of hydroelectric development can be balanced with environmental concerns

Position paper: Inland waterways classification for South America : Core concepts and initial proposals

NARCIS (Netherlands)

Jaimurzina, A.; Koedijk, O.C.; Wilmsmeier, G.; Dohms, A.; Montiel, D.; Pauli, G.; Rigo, P; Spengler, T.; Wens, F.

2016-01-01

South America, as of yet, has not been able to take full advantage of its extensive system of naturally navigable waterways and in making them an integrated part of the region’s transport network to cater for the ever increasing demand for cargo and human mobility. Infrastructure limitations are one

Carbon footprint of construction, operation and maintenance of waterways and traffic; Merenkulun ja liikenteen hiilijalanjaelki. Osa 1: Merenkulun hiilijalanjaelki, Osa 2: Tie-, rata- ja meriliikenteen hiilijalanjaeljet

Energy Technology Data Exchange (ETDEWEB)

Illman, J.; Kumpulainen, A.; Pesola, A.; Vanhanen, J.

2012-07-01

through them. In the second part of this project, emissions caused by traffic operating on the road and rail networks and waterways were calculated. The sources of emissions were first identified and categorised into primary and secondary emissions. Primary emissions include the greenhouse gas emissions from fuels used by vehicles. Secondary emissions result from operations that enable traffic to flow such as the energy used by gas stations and railway stations or the construction and maintenance of parking areas. It was concluded that the emissions caused by traffic are significantly larger than those of constructing, using and maintaining the transport infrastructure. The infrastructure of the road network has a carbon footprint of 511 000 tCO{sub 2}/a, while the emissions of traffic on the network are around 8,3 MtCO{sub 2}/a. The emissions of the main railway infrastructure are approximately 142 000 tCO{sub 2}/a and railway traffic has a carbon footprint of 315 000 tCO{sub 2}/a. For waterways the infrastructure emissions are 150 000 tCO{sub 2}/a and the emissions caused by traffic 2,4 MtCO{sub 2}/a. The share of secondary emissions of total emissions remains small. (orig.)

Operational experiences and upgradation of waste management facilities Trombay, India

International Nuclear Information System (INIS)

Chander, Mahesh; Bodke, S.B.; Bansal, N.K.

2001-01-01

Full text: Waste Management Facilities Trombay provide services for the safe management of radioactive wastes generated from the operation of non power sources at Bhabha Atomic Research Centre, India. The paper describes in detail the current operational experience and facility upgradation by way of revamping of existing processes equipment and systems and augmentation of the facility by way of introducing latest processes and technologies to enhance the safety. Radioactive wastes are generated from the operation of research reactors, fuel fabrication, spent fuel reprocessing, research labs. manufacture of sealed sources and labeled compounds. Use of radiation sources in the field of medical, agriculture and industry also leads to generation of assorted solid waste and spent sealed radiation sources which require proper waste management. Waste Management Facilities Trombay comprise of Effluent Treatment Plant (ETP), Decontamination Centre (DC) and Radioactive Solid Waste Management Site (RSMS). Low level radioactive liquid effluents are received at ETP. Plant has 100 M 3 /day treatment capacity. Decontamination of liquid effluents is effected by chemical treatment method using co- precipitation as a process. Plant has 1800 M 3 of storage capacity. Chemical treatment system comprises of clarifloculator, static mixer and chemical feed tanks. Plant has concentrate management facility where chemical sludge is centrifuged to effect volume reduction of more that 15. Thickened sludge is immobilized in cement matrix. Decontamination Centre caters to the need of equipment decontamination from research reactors. Process used is ultrasonic chemical decontamination. Besides this DC provides services for decontamination of protective wears. Radioactive Solid Waste Management Site is responsible for the safe management of solid waste generated at various research reactors, plants, laboratories in Bhabha Atomic Research Centre. Spent sealed radiation sources are also stored

A Multi-Agent System for Tracking the Intent of Surface Contacts in Ports and Waterways

National Research Council Canada - National Science Library

Tan, Kok S

2005-01-01

...) and employ them to identify asymmetric maritime threats in port and waterways. Each surface track is monitored by a compound multi-agent system that comprise of the several intent models, each containing a nested multi-agent system...

76 FR 77119 - Special Local Regulations; Pompano Beach Holiday Boat Parade, Intracoastal Waterway, Pompano...

Science.gov (United States)

2011-12-12

...-AA08 Special Local Regulations; Pompano Beach Holiday Boat Parade, Intracoastal Waterway, Pompano Beach... Pompano Beach Holiday Boat Parade on Sunday, December 11, 2011. The marine parade will consist of... Friday, except Federal holidays. FOR FURTHER INFORMATION CONTACT: If you have questions on this temporary...

Operational Experience of an Open-Access, Subscription-Based Mass Spectrometry and Proteomics Facility

Science.gov (United States)

Williamson, Nicholas A.

2018-03-01

This paper discusses the successful adoption of a subscription-based, open-access model of service delivery for a mass spectrometry and proteomics facility. In 2009, the Mass Spectrometry and Proteomics Facility at the University of Melbourne (Australia) moved away from the standard fee for service model of service provision. Instead, the facility adopted a subscription- or membership-based, open-access model of service delivery. For a low fixed yearly cost, users could directly operate the instrumentation but, more importantly, there were no limits on usage other than the necessity to share available instrument time with all other users. All necessary training from platform staff and many of the base reagents were also provided as part of the membership cost. These changes proved to be very successful in terms of financial outcomes for the facility, instrument access and usage, and overall research output. This article describes the systems put in place as well as the overall successes and challenges associated with the operation of a mass spectrometry/proteomics core in this manner. [Figure not available: see fulltext.

Aquatic invertebrate sampling at selected outfalls in Operable Unit 1082; Technical areas 9, 11, 16 and 22

Energy Technology Data Exchange (ETDEWEB)

Cross, S.

1995-09-01

The Ecological Studies Team (EST) of ESH-20 at Los Alamos National Laboratory conducted preliminary aquatic sampling at outfalls within Operable Unit 1082 and nearby natural waterways. Eleven outfalls were sampled a total of eighteen times. Three natural waterways (upper Pajarito Canyon, Starmer`s Gulch, and Bulldog Spring) in the vicinity were sampled a total of six times. At most sites, EST recorded hydrological condition, physico-chemical parameters, wildlife uses, and vegetation. At each outfall with water and each natural waterway, EST collected an aquatic invertebrate sample which was analyzed by taxa composition, Wilhm`s biodiversity index, the community tolerance quotient (CTQ), and density. The physico-chemical parameters at most outfalls and natural waterways fell within the normal range of natural waters in the area. However, the outfalls are characterized by low biodiversity and severely stressed communities composed of a restricted number of taxa. The habitat at the other outfalls could probably support well-developed aquatic communities if sufficient water was available. At present, the hydrology at these outfalls is too slight and/or sporadic to support such a community in the foreseeable future. In contrast to the outfalls, the natural waterways of the area had greater densities of aquatic invertebrates, higher biodiversities, and lower CTQs.

Operating manual for the High Flux Isotope Reactor. Volume I. Description of the facility

Energy Technology Data Exchange (ETDEWEB)

1982-09-01

This volume contains a comprehensive description of the High Flux Isotope Reactor Facility. Its primary purpose is to supplement the detailed operating procedures, providing the reactor operators with background information on the various HFIR systems. The detailed operating procdures are presented in another report.

Operating manual for the High Flux Isotope Reactor. Volume I. Description of the facility

International Nuclear Information System (INIS)

1982-09-01

This volume contains a comprehensive description of the High Flux Isotope Reactor Facility. Its primary purpose is to supplement the detailed operating procedures, providing the reactor operators with background information on the various HFIR systems. The detailed operating procdures are presented in another report

77 FR 7613 - Dow Chemical Company; Dow Chemical TRIGA Research Reactor; Facility Operating License No. R-108

Science.gov (United States)

2012-02-13

... NUCLEAR REGULATORY COMMISSION [Docket No. 50-264; NRC-2012-0026] Dow Chemical Company; Dow Chemical TRIGA Research Reactor; Facility Operating License No. R-108 AGENCY: Nuclear Regulatory Commission... Facility Operating License No. R-108 (``Application''), which currently authorizes the Dow Chemical Company...

Basis for Interim Operation for Fuel Supply Shutdown Facility

International Nuclear Information System (INIS)

BENECKE, M.W.

2003-01-01

This document establishes the Basis for Interim Operation (BIO) for the Fuel Supply Shutdown Facility (FSS) as managed by the 300 Area Deactivation Project (300 ADP) organization in accordance with the requirements of the Project Hanford Management Contract procedure (PHMC) HNF-PRO-700, ''Safety Analysis and Technical Safety Requirements''. A hazard classification (Benecke 2003a) has been prepared for the facility in accordance with DOE-STD-1027-92 resulting in the assignment of Hazard Category 3 for FSS Facility buildings that store N Reactor fuel materials (303-B, 3712, and 3716). All others are designated Industrial buildings. It is concluded that the risks associated with the current and planned operational mode of the FSS Facility (uranium storage, uranium repackaging and shipment, cleanup, and transition activities, etc.) are acceptable. The potential radiological dose and toxicological consequences for a range of credible uranium storage building have been analyzed using Hanford accepted methods. Risk Class designations are summarized for representative events in Table 1.6-1. Mitigation was not considered for any event except the random fire event that exceeds predicted consequences based on existing source and combustible loading because of an inadvertent increase in combustible loading. For that event, a housekeeping program to manage transient combustibles is credited to reduce the probability. An additional administrative control is established to protect assumptions regarding source term by limiting inventories of fuel and combustible materials. Another is established to maintain the criticality safety program. Additional defense-in-depth controls are established to perform fire protection system testing, inspection, and maintenance to ensure predicted availability of those systems, and to maintain the radiological control program. It is also concluded that because an accidental nuclear criticality is not credible based on the low uranium enrichment

Change in operating parameters of the Continuous Electron Beam Accelerator Facility and Free Electron Laser, Thomas Jefferson National Accelerator Facility, Newport News, Virginia

Energy Technology Data Exchange (ETDEWEB)

NONE

1997-10-01

In this environmental assessment (EA), the US Department of Energy (DOE) reports the results of an analysis of the potential environmental impacts from a proposed change in operating parameters of the Continuous Electron Beam Accelerator Facility (CEBAF), and operation of the Free Electron Laser (FEL) facility beyond the initial demonstration period. With this proposal, DOE intends to increase CEBAF operating range from its current operating maximum beam energy of 4.0 GeV [giga-(billion) electron volts] to 8.0 GeV at a beam power of no greater than 1,000 kW [1 megawatt (MW)], its maximum attainable level, based on current technology and knowledge, without significant, costly equipment modifications. DOE has prepared an EA for this action to determine the potential for adverse impacts from operation of CEBAF and the FEL at the proposed levels. Changing the operating parameters of CEBAF would require no new major construction and minor modifications to the accelerator, its support systems, the FEL, and onsite utility systems. Modifications and performance improvements would be made to (1) the accelerator housed in the underground tunnels, (2) its support systems located in the above ground service buildings, and (3) the water and equipment cooling systems both in the tunnel and at the ground surface. All work would be performed on previously disturbed land and in, on, or adjacent to existing buildings, structures, and equipment. With the proposed action, the recently constructed FEL facility at the Jefferson Lab would operate in concert with CEBAF beyond its demonstration period and up to its maximum effective electron beam power level of 210 kW. In this EA, DOE evaluates the impacts of the no-action alternative and the proposed action alternative. Alternatives considered, but dismissed from further evaluation, were the use of another accelerator facility and the use of another technology.

Change in operating parameters of the Continuous Electron Beam Accelerator Facility and Free Electron Laser, Thomas Jefferson National Accelerator Facility, Newport News, Virginia

International Nuclear Information System (INIS)

1997-10-01

In this environmental assessment (EA), the US Department of Energy (DOE) reports the results of an analysis of the potential environmental impacts from a proposed change in operating parameters of the Continuous Electron Beam Accelerator Facility (CEBAF), and operation of the Free Electron Laser (FEL) facility beyond the initial demonstration period. With this proposal, DOE intends to increase CEBAF operating range from its current operating maximum beam energy of 4.0 GeV [giga-(billion) electron volts] to 8.0 GeV at a beam power of no greater than 1,000 kW [1 megawatt (MW)], its maximum attainable level, based on current technology and knowledge, without significant, costly equipment modifications. DOE has prepared an EA for this action to determine the potential for adverse impacts from operation of CEBAF and the FEL at the proposed levels. Changing the operating parameters of CEBAF would require no new major construction and minor modifications to the accelerator, its support systems, the FEL, and onsite utility systems. Modifications and performance improvements would be made to (1) the accelerator housed in the underground tunnels, (2) its support systems located in the above ground service buildings, and (3) the water and equipment cooling systems both in the tunnel and at the ground surface. All work would be performed on previously disturbed land and in, on, or adjacent to existing buildings, structures, and equipment. With the proposed action, the recently constructed FEL facility at the Jefferson Lab would operate in concert with CEBAF beyond its demonstration period and up to its maximum effective electron beam power level of 210 kW. In this EA, DOE evaluates the impacts of the no-action alternative and the proposed action alternative. Alternatives considered, but dismissed from further evaluation, were the use of another accelerator facility and the use of another technology

Operational experience at the Sludge Treatment Facility

International Nuclear Information System (INIS)

Sy, D.J.

1987-01-01

The Sludge Treatment Facility (STF) at the Oak Ridge Gaseous Diffusion Plant has been in operation since April 1987. The facility was designed to encapsulate hazardous sludge wastes in a cement matrix. Fixation will allow the waste to meet or exceed applicable compressive strength and leachability requirements. Thus, the grout mixture complies with the Resource Conservation and Recovery Act (RCRA) guidelines as a nonhazardous waste. The grout mixture is based upon a recipe formulation developed after several years of waste stream characterization and formulation studies. The wastes to be treated at the STF are wastes impounded in two ponds. The ponds have a combined capacity of 4.5 million gallons of sludge. The sludge is transferred from the ponds to a 15,000-gallon capacity storage tank by the use of a dredge. The grout mixture recipe dictates the amount of sludge, cement, fly ash, and admixture required for weighing per batch. All ingredients are weighed and then transferred to a tilt or high energy mixer for mixing. The grout mixture is then transferred to 89- or 96-gallon steel drums. The drums are placed in a storage yard designed for a point source discharge from the yard

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

Interactive CD based training on NDA instruments for facility operators and international inspectors

International Nuclear Information System (INIS)

Horley, E.C.; Smith, H.A.

1996-01-01

Interactive multimedia training is rapidly becoming a popular and highly effective medium for learning. An interactive CD based training module on the Active Well Coincidence counter is being developed for on-site training at nuclear facility, including foreign facilities. The training module incorporates interactive text, graphics and video that demonstrate the operating principles, and the use and set-up of the instrument. The user is in control of the pace of learning and of the directions taken to acquire information based on personal need. By being in control, the user stays highly motivated. A mix of visuals (text and graphics), audio clips (in different languages), and video (with audio) clips also keeps the interest level high. Skill reviews and evaluations can be incorporated into the training to provide feedback to the student. In addition, general background information is provided on gamma and neutron based MC and A measurements. This material serves as a condensed MC and A encyclopedia. By supplying an interactive CD with an NDA instrument, nuclear facilities will have greater assurance operators are properly trained in the set-up and operation of the NDA-equipment

A probabilistic risk assessment of the LLNL Plutonium Facility's evaluation basis fire operational accident. Revision 1

International Nuclear Information System (INIS)

Brumburgh, G.P.

1995-01-01

The Lawrence Livermore National Laboratory (LLNL) Plutonium Facility conducts numerous programmatic activities involving plutonium to include device fabrication, development of improved and/or unique fabrication techniques, metallurgy research, and laser isotope separation. A Safety Analysis Report (SAR) for the building 332 Plutonium Facility was completed in July 1994 to address operational safety and acceptable risk to employees, the public, government property, and the environmental. This paper outlines the PRA analysis of the Evaluation Basis Fire (EBF) operational accident. The EBF postulates the worst-case programmatic impact event for the Plutonium Facility

75 FR 76322 - Drawbridge Operation Regulation; Fox River, Oshkosh, WI

Science.gov (United States)

2010-12-08

... required to maintain and operate a marine radiotelephone, along with equipment to visually monitor the... the waterway. If you think that your business, organization, or governmental jurisdiction qualifies as... comment (see ADDRESSES) explaining why you think it qualifies and how and to what degree this rule would...

The FAO/IAEA interactive spreadsheet for design and operation of insect mass rearing facilities

International Nuclear Information System (INIS)

Caceres, Carlos; Rendon, Pedro

2006-01-01

An electronic spreadsheet is described which helps users to design, equip and operate facilities for the mass rearing of insects for use in insect pest control programmes integrating the sterile insect technique. The spreadsheet was designed based on experience accumulated in the mass rearing of the Mediterranean fruit fly, Ceratitis capitata (Wiedemann), using genetic sexing strains based on a temperature sensitive lethal (tsl) mutation. The spreadsheet takes into account the biological, production, and quality control parameters of the species to be mass reared, as well as the diets and equipment required. All this information is incorporated into the spreadsheet for user-friendly calculation of the main components involved in facility design and operation. Outputs of the spreadsheet include size of the different rearing areas, rearing equipment, volumes of diet ingredients, other consumables, as well as personnel requirements. By adding cost factors to these components, the spreadsheet can estimate the costs of facility construction, equipment, and operation. All the output parameters can be easily generated by simply entering the target number of sterile insects required per week. For other insect species, the biological and production characteristics need to be defined and inputted accordingly to obtain outputs relevant to these species. This spreadsheet, available under http://www-naweb.iaea.org/nafa/ipc/index.html, is a powerful tool for project and facility managers as it can be used to estimate facility cost, production cost, and production projections under different rearing efficiency scenarios. (author)

The FAO/IAEA interactive spreadsheet for design and operation of insect mass rearing facilities

Energy Technology Data Exchange (ETDEWEB)

Caceres, Carlos, E-mail: carlos.e.caceres@aphis.usda.co [International Atomic Energy Agency (IAEA), Seibersdorf (Austria). Agency' s Labs. Programme of Nuclear Techniques in Food and Agriculture; Rendon, Pedro [U.S. Department of Agriculture (USDA/APHIS/CPHST), Guatemala City (Guatemala). Animal and Plant Health Inspection. Center for Plant Health Science and Technology

2006-07-01

An electronic spreadsheet is described which helps users to design, equip and operate facilities for the mass rearing of insects for use in insect pest control programmes integrating the sterile insect technique. The spreadsheet was designed based on experience accumulated in the mass rearing of the Mediterranean fruit fly, Ceratitis capitata (Wiedemann), using genetic sexing strains based on a temperature sensitive lethal (tsl) mutation. The spreadsheet takes into account the biological, production, and quality control parameters of the species to be mass reared, as well as the diets and equipment required. All this information is incorporated into the spreadsheet for user-friendly calculation of the main components involved in facility design and operation. Outputs of the spreadsheet include size of the different rearing areas, rearing equipment, volumes of diet ingredients, other consumables, as well as personnel requirements. By adding cost factors to these components, the spreadsheet can estimate the costs of facility construction, equipment, and operation. All the output parameters can be easily generated by simply entering the target number of sterile insects required per week. For other insect species, the biological and production characteristics need to be defined and inputted accordingly to obtain outputs relevant to these species. This spreadsheet, available under http://www-naweb.iaea.org/nafa/ipc/index.html, is a powerful tool for project and facility managers as it can be used to estimate facility cost, production cost, and production projections under different rearing efficiency scenarios. (author)

Radioactive Operations Committee Review of the Intermediate-Level Waste Evaporator Facility, Building 2531 February 17, 1972

International Nuclear Information System (INIS)

Liberman, B.; Brooksbank, R.E.

1972-01-01

A subcommittee of the Radioactive Operations Committee met with the Operators of the Intermediate Level Waste Evaporator Facility on February 17, 1972, to discuss the status of the facility and its operations since the review of October 7, 1970, and reported in ORNL-CF-70-11-12. This review was made to determine the status of the ILWEF since the last review, to discuss compliance with previously recommended changes, and to review any new items of safety significance. Several recommendations were made.

Using chloride and other ions to trace sewage and road salt in the Illinois Waterway

Science.gov (United States)

Kelly, W.R.; Panno, S.V.; Hackley, Keith C.; Hwang, H.-H.; Martinsek, A.T.; Markus, M.

2010-01-01

Chloride concentrations in waterways of northern USA are increasing at alarming rates and road salt is commonly assumed to be the cause. However, there are additional sources of Cl- in metropolitan areas, such as treated wastewater (TWW) and water conditioning salts, which may be contributing to Cl- loads entering surface waters. In this study, the potential sources of Cl- and Cl- loads in the Illinois River Basin from the Chicago area to the Illinois River's confluence with the Mississippi River were investigated using halide data in stream samples and published Cl- and river discharge data. The investigation showed that road salt runoff and TWW from the Chicago region dominate Cl- loads in the Illinois Waterway, defined as the navigable sections of the Illinois River and two major tributaries in the Chicago region. Treated wastewater discharges at a relatively constant rate throughout the year and is the primary source of Cl- and other elements such as F- and B. Chloride loads are highest in the winter and early spring as a result of road salt runoff which can increase Cl- concentrations by up to several hundred mg/L. Chloride concentrations decrease downstream in the Illinois Waterway due to dilution, but are always elevated relative to tributaries downriver from Chicago. The TWW component is especially noticeable downstream under low discharge conditions during summer and early autumn when surface drainage is at a minimum and agricultural drain tiles are not flowing. Increases in population, urban and residential areas, and roadways in the Chicago area have caused an increase in the flux of Cl- from both road salt and TWW. Chloride concentrations have been increasing in the Illinois Waterway since around 1960 at a rate of about 1 mg/L/a. The increase is largest in the winter months due to road salt runoff. Shallow groundwater Cl- concentrations are also increasing, potentially producing higher base flow concentrations. Projected increases in population and

Behavior of plutonium-238 solutions in the soil and hydrology system at Mound Laboratory

International Nuclear Information System (INIS)

Rodgers, D.R.

1976-01-01

Because plutonium is a potentially hazardous material, extensive precautions have been exercised since Pu operations began at Mound Laboratory to carefully maintain strict control of the Pu and to prevent significant amounts from entering the environment. These precautions include elaborate facility and equipment design criteria, scientific expertise, experience, personnel training, management and operational control systems, and environmental monitoring. In spite of these precautions, in early 1974, core samples from area waterways collected and analyzed showed that 238 Pu concentrations in the sediment of certain waterways adjacent to the site were above the baseline levels expected ( 238 Pu deposits presented no immediate hazard to the general population in the area as indicated by the air and water concentrations which were well within accepted Radioactivity Concentration Guides (RCG) for 238 Pu. Data are presented from an investigation of the extent of the contamination, the source of Pu, how it was transported and deposited in waterways, and potential hazards of these deposits to the general public

Summary of facility and operating experience on helium engineering demonstration loop (HENDEL)

Energy Technology Data Exchange (ETDEWEB)

Ouchi, Yoshihiro; Fujisaki, Katsuo; Kobayashi, Toshiaki; Kato, Michio; Ota, Yukimaru; Watanabe, Syuji; Kobayashi, Hideki; Mogi, Haruyoshi [Japan Atomic Energy Research Inst., Oarai, Ibaraki (Japan). Oarai Research Establishment

1996-07-01

The HENDEL is a test facility to perform full scale demonstration tests on the core internals and high temperature components for the High Temperature Engineering Test Reactor(HTTR). The main systems consist of Mother(M) and Adapter(A), fuel stack Test(T{sub 1}) and in-core structure Test(T{sub 2}) sections. The (M+A) section can supply high temperature helium gas to the test section. The M+A section completed in March 1982 has been operated for about 22900 hours till February 1995. The T{sub 1} and T{sub 2} sections, completed in March 1983 and June 1986, have been operated for about 19400 and 16700 hours, respectively. In this period, a large number of tests have been conducted to verify the performance and safety features of the HTTR components. The results obtained from these tests have been effectively applied to the detailed design, licensing procedures and construction of the HTTR. The operating experience of the HENDEL for more than 10 years also brought us establishment of the technique of operation of a large scale helium gas loop, handling of helium gas and maintenance of high temperature facilities. The technique will be available for the operation of the HTTR. This paper mainly describes the summary of plant facirities, operating experience and maintenance on the HENDEL. (author)

Nuclear Safety Co-Ordination within Oak Ridge Operations Facilities

Energy Technology Data Exchange (ETDEWEB)

Johnson, W. A.; Pryor, W. A. [Research and Development Division, United States Atomic Energy Commission, Oak Ridge, TN (United States)

1966-05-15

The Oak Ridge Operations Office of the USAEC has within its jurisdiction multiple contractors and facilities for research and for the production of fissile materials for the atomic energy programme. Among these facilities are gaseous diffusion plants for the production of {sup 235}U-enriched uranium hexafluoride, plants for the fabrication of special components and fuel for research and production reactors, and laboratories for pilot plant studies and basic research in nuclear technology. One research laboratory is also actively engaged in criticality experimental programmes and has been a major contributor of criticality data for safety applications. These diversified programmes include the processing, fabrication and transport of practically all forms and isotopic enrichments of uranium in quantities commensurate with both laboratory and volume production requirements. Consequently, adequate nuclear safety control with reasonable economy for operations of this magnitude demands not only co-ordination and liaison between contractor and USAEC staffs, but a continuing reappraisal of safety applications in light of the most advanced information. This report outlines the role of the Oak Ridge Operations Office in these pursuits and describes as examples some specific problems in which this office co-ordinated actions necessary for their resolution. Other examples are given of parametric and procedural applications in plant processes and fissile shipments emphasizing the use of recent experimental or calculated data. These examples involve the use of mass and geometric variables, neutron absorbers and moderation control. Departures from limits specified in existing nuclear safety guides are made to advantage in light of new data, special equipment design, contingencies and acceptable risks. (author)

SUPERCONDUCTING RADIO-FREQUENCY MODULES TEST FACILITY OPERATING EXPERIENCE

International Nuclear Information System (INIS)

Soyars, W.; Bossert, R.; Darve, C.; Degraff, B.; Klebaner, A.; Martinez, A.; Pei, L.; Theilacker, J.

2008-01-01

Fermilab is heavily engaged and making strong technical contributions to the superconducting radio-frequency research and development program (SRF R and D). Four major SRF test areas are being constructed to enable vertical and horizontal cavity testing, as well as cryomodule testing. The existing Fermilab cryogenic infrastructure has been modified to service the SRF R and D needs. The project's first stage has been successfully completed, which allows for distribution of cryogens for a single-cavity cryomodule using the existing Cryogenic Test Facility (CTF) that houses three Tevatron satellite refrigerators. The cooling capacity available for cryomodule testing at Meson Detector Building (MDB) results from the liquefaction capacity of the CTF cryogenic system. The cryogenic system for a single 9-cell cryomodule is currently operational. The paper describes the status, challenges and operational experience of the initial phase of the project

200 Area Treated Effluent Disposal Facility operational test specification. Revision 2

International Nuclear Information System (INIS)

Crane, A.F.

1995-01-01

This document identifies the test specification and test requirements for the 200 Area Treated Effluent Disposal Facility (200 Area TEDF) operational testing activities. These operational testing activities, when completed, demonstrate the functional, operational and design requirements of the 200 Area TEDF have been met. The technical requirements for operational testing of the 200 Area TEDF are defined by the test requirements presented in Appendix A. These test requirements demonstrate the following: pump station No.1 and associated support equipment operate both automatically and manually; pump station No. 2 and associated support equipment operate both automatically and manually; water is transported through the collection and transfer lines to the disposal ponds with no detectable leakage; the disposal ponds accept flow from the transfer lines with all support equipment operating as designed; and the control systems operate and status the 200 Area TEDF including monitoring of appropriate generator discharge parameters

Development and implementation of the waste diversion program at MDS Nordion's Cobalt Operations Facility

International Nuclear Information System (INIS)

Wasiak, T.

2004-01-01

Historically, the MDS Nordion (MDSN) Cobalt Operations Facility sent solid waste for disposal to Atomic Energy of Canada Ltd.'s Chalk River Laboratories (AECL-CRL). A large portion of this waste was not contaminated. Because this non-contaminated waste originated in the 'active area' of the MDSN facility, it was routinely disposed of as low-level active waste. In 2002, MDSN undertook an initiative to develop and implement a more sophisticated and more economical waste management program. The Waste Diversion Program (WDP) ensures continued environmental and public protection, and reduces the demand on Canada's limited capacity for storage of radioactive material and the associated operating costs. The goal of the WDP is to reduce the volume of waste currently being shipped to AECL-CRL's Waste Management Operation as low-level active waste. The presentation discusses key elements of both the development and the implementation of WDP. It focuses on the following areas: the regulatory environment surrounding the waste disposal issues in Canada and abroad. Methods used by MDSN for determination of radionuclides, which could be present in the facility. Choice of equipment and calculation of individual alarm levels for each identified radionuclide. Key elements of the practical implementation of the program. CNSC Regulatory approval process. The bottom line - dollars and cents. The primary objective of the WDP is to ensure that only waste, which meets regulatory requirements, is diverted from the solid active waste stream. This has been successfully accomplished in MDSN's Cobalt Operations Facility. The objective of the presentation is to share the knowledge and experience obtained in the development process, and thus provide a guideline for other nuclear facilities interested in establishing similar proactive and cost effective programs. (author)

Operators guide: Atmospheric Release Advisory Capability (ARAC) site facility

International Nuclear Information System (INIS)

Lawver, B.S.

1977-01-01

In this report capabilities and services are described for the Atmospheric Release Advisory Capability (ARAC). The ARAC site system and its operating procedures and interactions with the ARAC central facility located at LLL is outlined. ARAC is designed to help officials at designated ERDA sites and other locations in estimating the effects of atmospheric releases of radionuclides or other hazardous materials by issuing real-time advisories to guide them in their planning

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...

The impact of ornithogenic inputs on phosphorous transport from altered wetland soils to waterways in East Mediterranean ecosystem.

Science.gov (United States)

Litaor, M Iggy; Reichmann, O; Dente, E; Naftaly, A; Shenker, M

2014-03-01

Large flocks of Eurasian crane (Grus grus, >35,000) have begun wintering in an altered wetland agro-ecosystem located in Northern Israel, a phenomenon that attracts more than 400,000 eco-tourists a year. A 100-ha plot has been used to feed the cranes in order to protect nearby fields. The objective of this study was to evaluate the influence of this bird's feeding practice on the P status of the altered wetland soils and waterways. We installed a series of wells at two depths (40 and 90 cm) between two major waterways in the feeding area and monitored the hydraulic heads and collected groundwater samples for elemental analyses. We collected six soil cores and four sediment samples from the waterways and conducted sequential P extraction. We found significant increase in groundwater soluble reactive P (SRP) (>0.5 mg l(-1)) compared with much lower concentrations (~0.06 mg l(-1)) collected in the period prior to the feeding. We found significant decrease in Fe((II)), Ca, and SO4 concentrations in the shallow groundwater (33, 208, and 213 mg l(-1), respectively) compared with the period prior to the feeding (47, 460, and 370 mg l(-1) respectively). An increase in the more labile P fraction was observed in soils and sediments compared with the period before the feeding. The P input by bird excrement to the feeding area was estimated around 700 kg P per season, while P removal by plant harvesting was estimated around 640 kg Pyr(-1). This finding supports the current eco-tourism practices in the middle of intensive farming area, suggesting little impact on waterways. Copyright © 2013 Elsevier B.V. All rights reserved.

Exploring the links between natural resource use and biophysical status in the waterways of the North Rupununi, Guyana.

Science.gov (United States)

Mistry, Jayalaxshmi; Simpson, Matthews; Berardi, Andrea; Sandy, Yung

2004-09-01

The North Rupununi District in south-west Guyana is comprised of a mosaic of ecosystems, including savannas, wetlands and forests, and is home to the Makushi Amerindians, who depend on the waterways for their subsistence needs. With logging and mining seen as increasing threats to the region, it is necessary to look at methods for engaging stakeholders in monitoring the status of their natural resources. This paper presents the results of a pilot study carried out to investigate water use by the Makushi Amerindians, and collect baseline data on the hydro-morphological aspects of the waterways. Methods included informal interviews, the use of the River Habitat Survey (RHS), and water quality measurements. The results indicate the heavy reliance of the Makushi on the waterways for their daily lives, particularly on fishing. Although ponds and creeks are important sources of fish, the rivers provide much larger catches of a greater diversity of fish species, both in the wet and dry seasons. The physical characteristics of the water sources used by the Makushi are mainly associated with the surrounding habitat types: the savanna areas containing the more nutrient rich white-water rivers, and the tropical forest areas containing the less nutrient rich black-water rivers. This study indicates that at present there is no direct evidence of adverse impacts on the waterways used by the Makushi in terms of fish catches, habitat conditions and water quality. A monitoring scheme was set up using this study's outputs as a baseline from which any future changes can be compared. Further work is to be carried out over the next three years to produce monitoring and sustainable management procedures for the North Rupununi ecosystems, by linking the physical attributes of the environment to biodiversity and subsequently local livelihoods, and by building capacity of local stakeholders through training.

Operating experience with superconducting cavities at the TESLA test facility

International Nuclear Information System (INIS)

Moeller, Wolf-Dietrich

2003-01-01

A description of the TESLA Test Facility, which has been set up at DESY by the TeV Energy Superconducting Accelerator (TESLA) collaboration, will be given as it is now after five years of installation and operation. The experience with the first three modules, each containing 8 superconducting 9-cell cavities, installed and operated in the TTF-linac will be described. The measurements in the vertical and horizontal cryostats as well as in the modules will be compared. Recent results of the operation at the TESLA design current, macropulses of 800 μsec with bunches of 3.2 nC at a rate of 2.25 MHz are given. New measurement results of the higher order modes (HOM) will be presented. The operation and optimisation of the TTF Free Electron Laser (TTF-FEL) will also be covered in this paper. (author)

78 FR 40519 - Cooper Nuclear Station; Application and Amendment to Facility Operating License Involving...

Science.gov (United States)

2013-07-05

... NUCLEAR REGULATORY COMMISSION [Docket No. 50-298; NRC-2013-0139] Cooper Nuclear Station; Application and Amendment to Facility Operating License Involving Proposed No Significant Hazards..., issued to Nebraska Public Power District (the licensee), for operation of the Cooper Nuclear Station (CNS...

Integrated Urban Flood Analysis considering Optimal Operation of Flood Control Facilities in Urban Drainage Networks

Science.gov (United States)

Moon, Y. I.; Kim, M. S.; Choi, J. H.; Yuk, G. M.

2017-12-01

eavy rainfall has become a recent major cause of urban area flooding due to the climate change and urbanization. To prevent property damage along with casualties, a system which can alert and forecast urban flooding must be developed. Optimal performance of reducing flood damage can be expected of urban drainage facilities when operated in smaller rainfall events over extreme ones. Thus, the purpose of this study is to execute: A) flood forecasting system using runoff analysis based on short term rainfall; and B) flood warning system which operates based on the data from pump stations and rainwater storage in urban basins. In result of the analysis, it is shown that urban drainage facilities using short term rainfall forecasting data by radar will be more effective to reduce urban flood damage than using only the inflow data of the facility. Keywords: Heavy Rainfall, Urban Flood, Short-term Rainfall Forecasting, Optimal operating of urban drainage facilities. AcknowledgmentsThis research was supported by a grant (17AWMP-B066744-05) from Advanced Water Management Research Program (AWMP) funded by Ministry of Land, Infrastructure and Transport of Korean government.

Research note: Mapping spatial patterns in sewer age, material, and proximity to surface waterways to infer sewer leakage hotspots

Science.gov (United States)

Hopkins, Kristina G.; Bain, Daniel J.

2018-01-01

Identifying areas where deteriorating sewer infrastructure is in close proximity to surface waterways is needed to map likely connections between sewers and streams. We present a method to estimate sewer installation year and deterioration status using historical maps of the sewer network, parcel-scale property assessment data, and pipe material. Areas where streams were likely buried into the sewer system were mapped by intersecting the historical stream network derived from a 10-m resolution digital elevation model with sewer pipe locations. Potential sewer leakage hotspots were mapped by identifying where aging sewer pipes are in close proximity (50-m) to surface waterways. Results from Pittsburgh, Pennsylvania (USA), indicated 41% of the historical stream length was lost or buried and the potential interface between sewers and streams is great. The co-location of aging sewer infrastructure (>75 years old) near stream channels suggests that 42% of existing streams are located in areas with a high potential for sewer leakage if sewer infrastructure fails. Mapping the sewer-stream interface provides an approach to better understand areas were failing sewers may contribute a disproportional amount of nutrients and other pathogens to surface waterways.

Effect of climate change on crop production patterns with implications to transport flows and inland waterways.

Science.gov (United States)

2011-12-01

This project analyzed the demand for transportation capacity and changes in transportation flows on : inland waterways due to shifts in crop production patterns induced by climate change. Shifts in the crop : production mix have been observed in rece...

RISK ASSESSMENT BY STRUCTURAL ANALYSIS AND VIBRATION MEASUREMENT EQUIPMENT OPERATING AT OIL FACILITIES

OpenAIRE

Marius STAN

2013-01-01

Vibration analysis applications in operation is one of the diagnostic methods ofoperation of the facility. Analysis of these types of failures indicated the existence of specificfeatures prints and related equipment vibration spectra. Modeling and identification of theseparticular aspects in the spectrum of vibration machines help to control the operation of oilfacilities built safely.

Environmental Audit at Santa Barbara Operations, Special Technologies Laboratory, Remote Sensing Laboratory, North Las Vegas Facilities

International Nuclear Information System (INIS)

1991-03-01

This report documents the results of the Environmental Audit of selected facilities under the jurisdiction of the DOE Nevada Operations Office (NV) that are operated by EG and G Energy Measurements, Incorporated (EG and G/EM). The facilities included in this Audit are those of Santa Barbara Operation (SBO) at Goleta, California; the Special Technologies Laboratory (STL) at Santa Barbara, California; and Las Vegas Area Operations (LVAO) including the Remote Sensing Laboratory (RSL) at Nellis Air Force Base in Nevada, and the North Las Vegas Facilities (NLVF) at North Las Vegas, Nevada. The Environmental Audit was conducted by the US Department of Energy's (DOE) Office of Environmental Audit, commencing on January 28, 1991 and ending on February 15, 1991. The scope of the Audit was comprehensive, addressing environmental activities in the technical areas of air, surface water/drinking water, groundwater, waste management, toxic and chemical materials, quality assurance, radiation, inactive waste sites, and environmental management. Also assessed was compliance with applicable Federal, state, and local regulations and requirements; internal operating requirements; DOE Orders; and best management practices. 8 tabs

Outsourcing strategy and tendering methodology for the operation and maintenance of CERN’s cryogenic facilities

Science.gov (United States)

Serio, L.; Bremer, J.; Claudet, S.; Delikaris, D.; Ferlin, G.; Ferrand, F.; Pezzetti, M.; Pirotte, O.

2017-12-01

CERN operates and maintains the world largest cryogenic infrastructure ranging from ageing but well maintained installations feeding detectors, test facilities and general services, to the state-of-the-art cryogenic system serving the flagship LHC machine complex. A study was conducted and a methodology proposed to outsource to industry the operation and maintenance of the whole cryogenic infrastructure. The cryogenic installations coupled to non LHC-detectors, test facilities and general services infrastructure have been fully outsourced for operation and maintenance on the basis of performance obligations. The contractor is responsible for the operational performance of the installations based on a yearly operation schedule provided by CERN. The maintenance of the cryogenic system serving the LHC machine and its detectors has been outsourced on the basis of tasks oriented obligations, monitored by key performance indicators. CERN operation team, with the support of the contractor operation team, remains responsible for the operational strategy and performances. We report the analysis, strategy, definition of the requirements and technical specifications as well as the achieved technical and economic performances after one year of operation.

Defense Waste Processing Facility staged operations: environmental information document

International Nuclear Information System (INIS)

1981-11-01

Environmental information is presented relating to a staged version of the proposed Defense Waste Processing Facility (DWPF) at the Savannah River Plant. The information is intended to provide the basis for an Environmental Impact Statement. In either the integral or the staged design, the DWPF will convert the high-level waste currently stored in tanks into: a leach-resistant form containing about 99.9% of all the radioactivity, and a residual, slightly contaminated salt, which is disposed of as saltcrete. In the first stage of the staged version, the insoluble sludge portion of the waste and the long lived radionuclides contained therein will be vitrified. The waste glass will be sealed in canisters and stored onsite until shipped to a Federal repository. In the second stage, the supernate portion of the waste will be decontaminated by ion exchange. The recovered radionuclides will be transferred to the Stage 1 facility, and mixed with the sludge feed before vitrification. The residual, slightly contaminated salt solution will be mixed with Portland cement to form a concrete product (saltcrete) which will be buried onsite in an engineered landfill. This document describes the conceptual facilities and processes for producing glass waste and decontaminated salt. The environmental effects of facility construction, normal operations, and accidents are then presented. Descriptions of site and environs, alternative sites and waste disposal options, and environmental consultations and permits are given in the base Environmental Information Document

Safety analysis--200 Area Savannah River Site: Separations Area operations Building 211-H Outside Facilities. Supplement 11, Revision 1

Energy Technology Data Exchange (ETDEWEB)

1993-01-01

The H-Area Outside Facilities are located in the 200-H Separations Area and are comprised of a number of processes, utilities, and services that support the separations function. Included are enriched uranium loadout, bulk chemical storage, water handling, acid recovery, general purpose evaporation, and segregated solvent facilities. In addition, services for water, electricity, and steam are provided. This Safety Analysis Report (SAR) documents an analysis of the H-Area Outside Facilities and is one of a series of documents for the Separations Area as specified in the SR Implementation Plan for DOE order 5481.1A. The primary purpose of the analysis was to demonstrate that the facility can be operated without undue risk to onsite or offsite populations, to the environment, and to operating personnel. In this report, risks are defined as the expected frequencies of accidents, multiplied by the resulting radiological consequences in person-rem. Following the summary description of facility and operations is the site evaluation including the unique features of the H-Area Outside Facilities. The facility and process design are described in Chapter 3.0 and a description of operations and their impact is given in Chapter 4.0. The accident analysis in Chapter 5.0 is followed by a list of safety related structures and systems (Chapter 6.0) and a description of the Quality Assurance program (Chapter 7.0). The accident analysis in this report focuses on estimating the risk from accidents as a result of operation of the facilities. The operations were evaluated on the basis of three considerations: potential radiological hazards, potential chemical toxicity hazards, and potential conditions uniquely different from normal industrial practice.

Safety analysis--200 Area Savannah River Site: Separations Area operations Building 211-H Outside Facilities. Supplement 11, Revision 1

International Nuclear Information System (INIS)

1993-01-01

The H-Area Outside Facilities are located in the 200-H Separations Area and are comprised of a number of processes, utilities, and services that support the separations function. Included are enriched uranium loadout, bulk chemical storage, water handling, acid recovery, general purpose evaporation, and segregated solvent facilities. In addition, services for water, electricity, and steam are provided. This Safety Analysis Report (SAR) documents an analysis of the H-Area Outside Facilities and is one of a series of documents for the Separations Area as specified in the SR Implementation Plan for DOE order 5481.1A. The primary purpose of the analysis was to demonstrate that the facility can be operated without undue risk to onsite or offsite populations, to the environment, and to operating personnel. In this report, risks are defined as the expected frequencies of accidents, multiplied by the resulting radiological consequences in person-rem. Following the summary description of facility and operations is the site evaluation including the unique features of the H-Area Outside Facilities. The facility and process design are described in Chapter 3.0 and a description of operations and their impact is given in Chapter 4.0. The accident analysis in Chapter 5.0 is followed by a list of safety related structures and systems (Chapter 6.0) and a description of the Quality Assurance program (Chapter 7.0). The accident analysis in this report focuses on estimating the risk from accidents as a result of operation of the facilities. The operations were evaluated on the basis of three considerations: potential radiological hazards, potential chemical toxicity hazards, and potential conditions uniquely different from normal industrial practice

The optimum operating conditions of the phased double-rotor facility at the ET-RR-1 reactor

Energy Technology Data Exchange (ETDEWEB)

Naguib, K.; Habib, N.; Wahba, M.; Kilany, M.; Adib, M. [National Research Centre, Cairo (Egypt). Reactor and Neutron Physics Dept.

1997-02-07

A pulsed neutron polyenergetic thermal beam at ET-RR-1 is produced by a phased double-rotor facility. One of the rotors has two diametrically opposite curved slots, while the second is designed to operate as a rotating collimator. The dimensions of the phased rotating collimator are selected to match the curved slot rotor. The calculated collimator transmissions at different operating conditions are found to be in good agreement with the experimental ones. The optimum operating conditions of the double-rotor facility are deduced. The calculations were carried out using a computer program RCOL. The RCOL was designed in FORTRAN-77 to operate on PCs. (author).

The optimum operating conditions of the phased double-rotor facility at the ET-RR-1 reactor

International Nuclear Information System (INIS)

Naguib, K.; Habib, N.; Wahba, M.; Kilany, M.; Adib, M.

1997-01-01

A pulsed neutron polyenergetic thermal beam at ET-RR-1 is produced by a phased double-rotor facility. One of the rotors has two diametrically opposite curved slots, while the second is designed to operate as a rotating collimator. The dimensions of the phased rotating collimator are selected to match the curved slot rotor. The calculated collimator transmissions at different operating conditions are found to be in good agreement with the experimental ones. The optimum operating conditions of the double-rotor facility are deduced. The calculations were carried out using a computer program RCOL. The RCOL was designed in FORTRAN-77 to operate on PCs. (author)

Research and development of power reactor technology supporting work, 3; Development of utility facility operation management technique

Energy Technology Data Exchange (ETDEWEB)

1990-03-01

Demands on utility facilities for nuclear technology development are increasingly sophisticated and diversified. It is important to meet requirements of securing the reliability of utility supply and ensuring the safety of facility operation and maintenance by means of technical supporting, data supply and quick contingency responses. A New computer system to make practicable man-machine interface, real-time data acquisition and operation data centralization has been developed based on the knowledge. Obtained from data base information and operation experience for the purpose of operation efficiency and labor saving. (author).

A probabilistic risk assessment of the LLNL Plutonium facility's evaluation basis fire operational accident

International Nuclear Information System (INIS)

Brumburgh, G.

1994-01-01

The Lawrence Livermore National Laboratory (LLNL) Plutonium Facility conducts numerous involving plutonium to include device fabrication, development of fabrication techniques, metallurgy research, and laser isotope separation. A Safety Analysis Report (SAR) for the building 332 Plutonium Facility was completed rational safety and acceptable risk to employees, the public, government property, and the environment. This paper outlines the PRA analysis of the Evaluation Basis Fire (EDF) operational accident. The EBF postulates the worst-case programmatic impact event for the Plutonium Facility

Treatment and conditioning of low-level radioactive waste in Belgium: initial operating results of the Cilva facility

International Nuclear Information System (INIS)

Monsch, O.; Renard, C.; Deckers, J.; Luycx, P.

1995-01-01

The Belgian National Radioactive Waste and Enriched Fissile Material Agency (ONDRAF), which is responsible for the management of all radioactive waste in Belgium, recently decided to commission the CILVA facility. Operation of this facility, which comprises a number of units for the treatment of low-level radwaste, has been contracted to ONDRAF's Belgoprocess subsidiary based at the Dessel site. A consortium comprising SGN and Fabricom was in charge of building the CILVA facility's waste preparation and conditioning (concrete solidification) units. The concrete solidification processes, which were devised and developed by SGN, have been qualified to secure ONDRAF certification of the process and the facility. This enabled active commissioning of the waste conditioning unit in mid-August 1994. Active commissioning of the waste preparation unit was carried out in several stages up to the beginning of 1995 in accordance with operating requirements. Initial operating results of the two units are presented. (author)

Design and operating technique for ventilating system of irradiated materials examination facility

International Nuclear Information System (INIS)

Hwang, Yong Hwa; Hong, Kwon Pyo; Eom, Sung Ho

1999-08-01

Ventilation and air filtering system is installed at IMEF to maintain optimized operating condition of the facility by keeping different negative pressure condition depending on contamination level in the IMEF due to its treatment of radioactive materials. Inspection on each system, air flow measurement, filter leak test and other related test are periodically performed as the performance test for increasing operational efficiency and safety. (Author). 16 refs., 21 tabs., 9 figs

Application of the Streamflow Prediction Tool to Estimate Sediment Dredging Volumes in Texas Coastal Waterways

Science.gov (United States)

Yeates, E.; Dreaper, G.; Afshari, S.; Tavakoly, A. A.

2017-12-01

Over the past six fiscal years, the United States Army Corps of Engineers (USACE) has contracted an average of about a billion dollars per year for navigation channel dredging. To execute these funds effectively, USACE Districts must determine which navigation channels need to be dredged in a given year. Improving this prioritization process results in more efficient waterway maintenance. This study uses the Streamflow Prediction Tool, a runoff routing model based on global weather forecast ensembles, to estimate dredged volumes. This study establishes regional linear relationships between cumulative flow and dredged volumes over a long-term simulation covering 30 years (1985-2015), using drainage area and shoaling parameters. The study framework integrates the National Hydrography Dataset (NHDPlus Dataset) with parameters from the Corps Shoaling Analysis Tool (CSAT) and dredging record data from USACE District records. Results in the test cases of the Houston Ship Channel and the Sabine and Port Arthur Harbor waterways in Texas indicate positive correlation between the simulated streamflows and actual dredging records.

Directions in low-level radioactive waste management. Low level-radioactive waste disposal: currently operating commercial facilities

International Nuclear Information System (INIS)

1983-09-01

This publication discusses three commercial facilities that receive and dispose of low-level radioactive waste. The facilities are located in Barnwell, South Carolina; Beatty, Nevada; and Richland, Washington. All three facilities initiated operations in the 1960s. The three facilities have operated without such major problems as those which led to the closure of three other commercial disposal facilities located in the United States. The Beatty site could be closed in 1983 as a result of a Nevada Board of Health ruling that renewal of the site license would be inimical to public health and safety. The site remains open pending federal and state court hearings, which began in January 1983, to resolve the Board of Health ruling. The three sites may also be affected by NRC's 10 CFR Part 61 regulations, but the impact of those regulations, issued in December 1982, has not yet been assessed. This document provides detailed information on the history and current status of each facility. This information is intended, primarily, to assist state officials - executive, legislative, and agency - in planning for, establishing, and managing low-level waste disposal facilities. 12 references

RISK ASSESSMENT BY STRUCTURAL ANALYSIS AND VIBRATION MEASUREMENT EQUIPMENT OPERATING AT OIL FACILITIES

Directory of Open Access Journals (Sweden)

Marius STAN

2013-05-01

Full Text Available Vibration analysis applications in operation is one of the diagnostic methods ofoperation of the facility. Analysis of these types of failures indicated the existence of specificfeatures prints and related equipment vibration spectra. Modeling and identification of theseparticular aspects in the spectrum of vibration machines help to control the operation of oilfacilities built safely.

High Performance Computing Facility Operational Assessment 2015: Oak Ridge Leadership Computing Facility

Energy Technology Data Exchange (ETDEWEB)

Barker, Ashley D. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States). Oak Ridge Leadership Computing Facility; Bernholdt, David E. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States). Oak Ridge Leadership Computing Facility; Bland, Arthur S. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States). Oak Ridge Leadership Computing Facility; Gary, Jeff D. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States). Oak Ridge Leadership Computing Facility; Hack, James J. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States). Oak Ridge Leadership Computing Facility; McNally, Stephen T. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States). Oak Ridge Leadership Computing Facility; Rogers, James H. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States). Oak Ridge Leadership Computing Facility; Smith, Brian E. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States). Oak Ridge Leadership Computing Facility; Straatsma, T. P. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States). Oak Ridge Leadership Computing Facility; Sukumar, Sreenivas Rangan [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States). Oak Ridge Leadership Computing Facility; Thach, Kevin G. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States). Oak Ridge Leadership Computing Facility; Tichenor, Suzy [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States). Oak Ridge Leadership Computing Facility; Vazhkudai, Sudharshan S. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States). Oak Ridge Leadership Computing Facility; Wells, Jack C. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States). Oak Ridge Leadership Computing Facility

2016-03-01

Oak Ridge National Laboratory’s (ORNL’s) Leadership Computing Facility (OLCF) continues to surpass its operational target goals: supporting users; delivering fast, reliable systems; creating innovative solutions for high-performance computing (HPC) needs; and managing risks, safety, and security aspects associated with operating one of the most powerful computers in the world. The results can be seen in the cutting-edge science delivered by users and the praise from the research community. Calendar year (CY) 2015 was filled with outstanding operational results and accomplishments: a very high rating from users on overall satisfaction that ties the highest-ever mark set in CY 2014; the greatest number of core-hours delivered to research projects; the largest percentage of capability usage since the OLCF began tracking the metric in 2009; and success in delivering on the allocation of 60, 30, and 10% of core hours offered for the INCITE (Innovative and Novel Computational Impact on Theory and Experiment), ALCC (Advanced Scientific Computing Research Leadership Computing Challenge), and Director’s Discretionary programs, respectively. These accomplishments, coupled with the extremely high utilization rate, represent the fulfillment of the promise of Titan: maximum use by maximum-size simulations. The impact of all of these successes and more is reflected in the accomplishments of OLCF users, with publications this year in notable journals Nature, Nature Materials, Nature Chemistry, Nature Physics, Nature Climate Change, ACS Nano, Journal of the American Chemical Society, and Physical Review Letters, as well as many others. The achievements included in the 2015 OLCF Operational Assessment Report reflect first-ever or largest simulations in their communities; for example Titan enabled engineers in Los Angeles and the surrounding region to design and begin building improved critical infrastructure by enabling the highest-resolution Cybershake map for Southern

Facility Will Help Transition Models Into Operations

Science.gov (United States)

Kumar, Mohi

2009-02-01

The U.S. National Oceanic and Atmospheric Administration's Space Weather Prediction Center (NOAA SWPC), in partnership with the U.S. Air Force Weather Agency (AFWA), is establishing a center to promote and facilitate the transition of space weather models to operations. The new facility, called the Developmental Testbed Center (DTC), will take models used by researchers and rigorously test them to see if they can withstand continued use as viable warning systems. If a model used in a space weather warning system crashes or fails to perform well, severe consequences can result. These include increased radiation risks to astronauts and people traveling on high-altitude flights, national security vulnerabilities from the loss of military satellite communications, and the cost of replacing damaged military and commercial spacecraft.

Nuclear safety and radiation protection report of the Tricastin operational hot base nuclear facilities - 2013

International Nuclear Information System (INIS)

2014-01-01

This safety report was established under the article 21 of the French law no. 2006-686 of June 13, 2006 relative to nuclear safety and information transparency. It presents, first, the Tricastin operational hot base facility (INB no. 157, Bollene, Vaucluse (FR)), a nuclear workshop for storage and maintenance and qualification operations on some EdF equipments. Then, the nuclear safety and radiation protection measures taken regarding the facility are reviewed: nuclear safety definition, radiation protection of intervening parties, safety and radiation protection improvement paths, crisis management, external and internal controls, technical situation of facilities, administrative procedures in progress. The incidents and accidents which occurred in 2013, if some, are reported as well as the effluents discharge in the environment. Finally, The radioactive materials and wastes generated by the facility is presented and sorted by type of waste, quantities and type of conditioning. The document concludes with a glossary and a list of recommendations from the Committees for health, safety and working conditions

Estimation of radon concentration in various operating areas of a reprocessing facility

International Nuclear Information System (INIS)

Jayan, M.P.; Ashok Kumar, P.; Raman, Anand; Gopalakrishnan, R.K.

2010-01-01

This paper reports 222 Rn concentration of various operating areas of a reprocessing facility and also the U-processing area, measured using a microcontroller based Continuous Radon Monitor (CRM) built indigenously by Radiation Safety Systems Division, Bhabha Atomic Research Centre

RCRA facility investigation/corrective measures study work plan for the 100-DR-1 operable unit, Hanford Site, Richland, Washington

International Nuclear Information System (INIS)

1992-09-01

Four areas of the Hanford Site (the 100, 200, 300, and 1100 Areas) have been included on the US Environmental Protection Agency's (EPA's) National Priorities List (NPL) under the Comprehensive Environmental Response, Compensation, and Liability Act of 1980 (CERCLA). Under the Hanford Federal Facility Agreement and Consent Order (Tri-Party Agreement, Ecology et. al. 1990a), signed by the Washington State Department of Ecology (Ecology), EPA, and the US Department of Energy (DOE), more than 1,000 inactive waste disposal and unplanned release sites on the Hanford Site have been grouped into a number of source and groundwater operable units. These operable units contain contamination in the form of hazardous waste, radioactive/hazardous mixed waste, and other CERCLA hazardous substances. Also included in the Tri-Party Agreement are 55 Resource Conservation and Recovery Act (RCRA) treatment, storage, or disposal (TSD) facilities that will be closed or permitted to operate in accordance with RCRA regulations. Some of the TSD facilities are included in the operable units. This work plan and the attached supporting project plans establish the operable unit setting and the objectives, procedures, tasks, and schedule for conducting the RCRA facility investigation/corrective measures study (RFI/CMS) for the 100-DR-1 source operable unit Source operable units include facilities and unplanned release sites that are potential sources of contamination

Hazard and operability study of the multi-function Waste Tank Facility. Revision 1

International Nuclear Information System (INIS)

Hughes, M.E.

1995-01-01

The Multi-Function Waste Tank Facility (MWTF) East site will be constructed on the west side of the 200E area and the MWTF West site will be constructed in the SW quadrant of the 200W site in the Hanford Area. This is a description of facility hazards that site personnel or the general public could potentially be exposed to during operation. A list of preliminary Design Basis Accidents was developed

An independent safety assessment of Department of Energy nuclear reactor facilities: Procedures, operations and maintenance

International Nuclear Information System (INIS)

Toto, G.; Lindgren, A.J.

1981-02-01

The 1979 accident at the Three Mile Island commercial nuclear power plant has led to a number of studies of nuclear reactors, in both the public and private sectors. One of these is that of the Department of Energy's (DOE) Nuclear Facilities Personnel Qualification and Training (NFPQT) Committee, which has outlined tasks for assessment of 13 reactors owned by DOE and operated by contractors. This report covers one of the tasks, the assessment of procedures, operations, and maintenance at the DOE reactor facilities, based on a review of actual documents used at the reactor sites

Sodium Fire Demonstration Facility Design and Operation

International Nuclear Information System (INIS)

Cho, Youngil; Kim, Jong-Man; Lee, Jewhan; Hong, Jonggan; Yeom, Sujin; Cho, Chungho; Jung, Min-Hwan; Gam, Da-Young; Jeong, Ji-Young

2014-01-01

Although sodium has good characteristics such as high heat transfer rate and stable nuclear property, it is difficult to manage because of high reactivity. Sodium is solid at the room temperature and it easily reacts with oxygen resulting in fire due to the reaction heat. Thus, sodium must be stored in a chemically stable place, i.e., an inert gas-sealed or oil filled vessel. When a sodium fire occurs, the Na 2 O of white fume is formed. It is mainly composed of Na 2 O 2 , NaOH, and Na 2 CO 3 , ranging from 0.1 to several tens of micrometers in size. It is known that the particle size increases by aggregation during floating in air. Thus, the protection method is important and should be considered in the design and operation of a sodium system. In this paper, sodium fire characteristics are described, and the demonstration utility of outbreak of sodium fire and its extinguishing is introduced. In this paper, sodium fire characteristics and a demonstration facility are described. The introduced sodium fire demonstration facility is the only training device used to observe a sodium fire and extinguish it domestically. Furthermore, the type of sodium fire will be diversified with the enhancement of the utility. It is expected that this utility will contribute to experience in the safe treatment of sodium by the handlers

Insights from the Probabilistic Safety Assessment Application to Subsurface Operations at the Preclosure Facilities

International Nuclear Information System (INIS)

Hwang, Mee Jeong; Jung, Jong Tae

2009-01-01

In this paper, we present the insights obtained through the PSA (Probabilistic Safety Assessment) application to subsurface operation at the preclosure facilities of the repository. At present, medium-low level waste repository has been constructed in Korea, and studies for disposal of high level wastes are under way. Also, safety analysis for repository operation has been performed. Thus, we performed a probabilistic safety analysis for surface operation at the preclosure facilities with PSA methodology for a nuclear power plant. Since we don't have a code to analyze the waste repository safety analysis, we used the codes, AIMS (Advanced Information Management System for PSA) and FTREX (Fault Tree Reliability Evaluation eXpert) which are developed for a nuclear power plant's PSA to develop ET (Event Tree) and FT (Fault Tree), and to quantify for an example analysis

76 FR 78151 - Special Local Regulations; Boca Raton Holiday Boat Parade, Intracoastal Waterway, Boca Raton, FL

Science.gov (United States)

2011-12-16

...-AA08 Special Local Regulations; Boca Raton Holiday Boat Parade, Intracoastal Waterway, Boca Raton, FL... Raton Holiday Boat Parade on Saturday, December 17, 2011. The marine parade will consist of... through Friday, except Federal holidays. FOR FURTHER INFORMATION CONTACT: If you have questions on this...

Operation of radiation monitoring system in radwaste form test facility

International Nuclear Information System (INIS)

Ryu, Young Gerl; Kim, Ki Hong; Lee, Jae Won; Kwac, Koung Kil

1998-08-01

RWFTF (RadWaste Form Test Facility) must have a secure radiation monitoring system (RMS) because of having a hot-cell capable of handling high radioactive materials. And then in controlled radiation zone, which is hot-cell and its maintenance and operation / control room, area dose rate, radioactivities in air-bone particulates and stack, and surface contamination are monitored continuously. For the effective management such as higher utilization, maintenance and repair, the status of this radiation monitoring system, the operation and characteristics of all kinds of detectors and other parts of composing this system, and signal treatment and its evaluation were described in this technical report. And to obtain the accuracy detection results and its higher confidence level, the procedure such as maintenance, functional check and system calibration were established and appended to help the operation of RMS. (author). 6 tabs., 30 figs

The insertion device magnetic measurement facility: Prototype and operational procedures

International Nuclear Information System (INIS)

Burkel, L.; Dejus, R.; Maines, J.; O'Brien, J.; Vasserman, I.; Pfleuger, J.

1993-03-01

This report is a description of the current status of the magnetic measurement facility and is a basic instructional manual for the operation of the facility and its components. Please refer to the appendices for more detailed information about specific components and procedures. The purpose of the magnetic measurement facility is to take accurate measurements of the magnetic field in the gay of the IDs in order to determine the effect of the ID on the stored particle beam and the emitted radiation. The facility will also play an important role when evaluating new ideas, novel devices, and inhouse prototypes as part of the ongoing research and development program at the APS. The measurements will be performed with both moving search coils and moving Hall probes. The IDs will be evaluated by computer modeling of the emitted radiation for any given (measured) magnetic field map. The quality of the magnetic field will be described in terms of integrated multipoles for the effect on Storage Ring performance and in terms of the derived trajectories for the emitted radiation. Before being installed on the Storage Ring, every device will be measured and characterized to assure that it is compatible with Storage Ring requirements and radiation specifications. The accuracy that the APS needs to achieve for magnetic measurements will be based on these specifications

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

RCRA facility investigation/corrective measures study work plan for the 100-HR-3 operable unit, Hanford Site, Richland, Washington

International Nuclear Information System (INIS)

1992-09-01

Four areas of the Hanford Site (the 100, 200, 300, and 1100 Areas) have been included on the US Environmental Protection Agency's (EPA's) National Priorities List (NPL) under the Comprehensive Environmental Response, Compensation, and Liability Act of 1980 (CERCLA). Under the Hanford Federal Facility Agreement and Consent Order, signed by the Washington State Department of Ecology (Ecology), EPA, and the US Department of Energy (DOE), more than 1000 inactive waste disposal and unplanned release sites on the Hanford Site have been grouped into a number of source and groundwater operable units. These operable units contain contamination in the form of hazardous waste, radioactive/hazardous mixed waste, and other CERCLA hazardous substances. Also included in the Tri-Party Agreement are 55 Resource Conservation and Recovery Act (RCRA) treatment, storage, or disposal (TSD) facilities that will be closed or permitted to operate in accordance with RCRA regulations, under the authority of Chapter 173-303 Washington Administrative Code (WAC). Some of the TSD facilities are included in the operable units. This work plan and the attached supporting project plans establish the operable unit setting and the objectives, procedures, tasks, and schedule for conducting the RCRA facility investigation/corrective measures study (RFI/CMS) for the 100-HR-3 operable unit. The 100-HR-3 operable unit underlies the D/DR and H Areas, the 600 Area between them, and the six source operable units these areas contain. The 100-HR-3 operable unit includes all contamination found in the aquifer soils and water within its boundary. Source operable units include facilities and unplanned release sites that are potential sources of contamination. Separate work plans have been initiated for the 100-DR-1 (DOE-RL 1992a) and 100-HR-1 (DOE-RL 1992b) source operable units

Operational Circular nr 5 - October 2000 USE OF CERN COMPUTING FACILITIES

CERN Multimedia

Division HR

2000-01-01

New rules covering the use of CERN Computing facilities have been drawn up. All users of CERN’s computing facilites are subject to these rules, as well as to the subsidiary rules of use. The Computing Rules explicitly address your responsibility for taking reasonable precautions to protect computing equipment and accounts. In particular, passwords must not be easily guessed or obtained by others. Given the difficulty to completely separate work and personal use of computing facilities, the rules define under which conditions limited personal use is tolerated. For example, limited personal use of e-mail, news groups or web browsing is tolerated in your private time, provided CERN resources and your official duties are not adversely affected. The full conditions governing use of CERN’s computing facilities are contained in Operational Circular N° 5, which you are requested to read. Full details are available at : http://www.cern.ch/ComputingRules Copies of the circular are also available in the Divis...

Soot concentrations along busy inland waterways in the Netherlands; Roetconcentraties langs drukke binnenvaarwegen in Nederland

Energy Technology Data Exchange (ETDEWEB)

Keuken, M.; Jonkers, S.; Moerman, M. [TNO Built Environment and Geosciences, Delft (Netherlands); Hoek, G. [Institute for Risk Assessment Sciences IRAS, Utrecht University, Utrecht (Netherlands)

2013-08-15

Exploratory research by TNO and IRAS shows that residents in the Netherlands are exposed to soot concentrations along busy inland waterways similar to living along a busy highway [Dutch] Verkennend onderzoek van TNO en IRAS laat zien dat bewoners langs drukke binnenvaarwegen worden blootgesteld aan roetconcentraties vergelijkbaar met wonen langs een drukke snelweg.

SNS Cryogenic Test Facility Kinney Vacuum Pump Commissioning and Operation at 2 K

Energy Technology Data Exchange (ETDEWEB)

Degraff, Brian D. [ORNL; Howell, Matthew P. [ORNL; Kim, Sang-Ho [ORNL; Neustadt, Thomas S. [ORNL

2017-07-01

The Spallation Neutron Source (SNS) at Oak Ridge National Laboratory (ORNL) has built and commissioned an independent Cryogenic Test Facility (CTF) in support of testing in the Radio-frequency Test Facility (RFTF). Superconducting Radio-frequency Cavity (SRF) testing was initially conducted with the CTF cold box at 4.5 K. A Kinney vacuum pump skid consisting of a roots blower with a liquid ring backing pump was recently added to the CTF system to provide testing capabilities at 2 K. System design, pump refurbishment and installation of the Kinney pump will be presented. During the commissioning and initial testing period with the Kinney pump, several barriers to achieve reliable operation were experienced. Details of these lessons learned and improvements to skid operations will be presented. Pump capacity data will also be presented.

SNS Cryogenic Test Facility Kinney Vacuum Pump Commissioning and Operation at 2 K

Science.gov (United States)

DeGraff, B.; Howell, M.; Kim, S.; Neustadt, T.

2017-12-01

The Spallation Neutron Source (SNS) at Oak Ridge National Laboratory (ORNL) has built and commissioned an independent Cryogenic Test Facility (CTF) in support of testing in the Radio-frequency Test Facility (RFTF). Superconducting Radio-frequency Cavity (SRF) testing was initially conducted with the CTF cold box at 4.5 K. A Kinney vacuum pump skid consisting of a roots blower with a liquid ring backing pump was recently added to the CTF system to provide testing capabilities at 2 K. System design, pump refurbishment and installation of the Kinney pump will be presented. During the commissioning and initial testing period with the Kinney pump, several barriers to achieve reliable operation were experienced. Details of these lessons learned and improvements to skid operations will be presented. Pump capacity data will also be presented.

Operational analysis and improvement of a spent nuclear fuel handling and treatment facility using discrete event simulation

International Nuclear Information System (INIS)

Garcia, H.E.

2000-01-01

Spent nuclear fuel handling and treatment often require facilities with a high level of operational complexity. Simulation models can reveal undesirable characteristics and production problems before they become readily apparent during system operations. The value of this approach is illustrated here through an operational study, using discrete event modeling techniques, to analyze the Fuel Conditioning Facility at Argonne National Laboratory and to identify enhanced nuclear waste treatment configurations. The modeling approach and results of what-if studies are discussed. An example on how to improve productivity is presented.

Review of operating experience at the Los Alamos Plutonium Electrorefining Facility, 1963-1977

International Nuclear Information System (INIS)

Mullins, L.J.; Morgan, A.N.

1981-12-01

This report reviews the operation of the Los Alamos Plutonium Electrorefining Plant at Technical Area 21 for the period 1964 through 1977. During that period, approximately 1568 kg of plutonium metal, > 99.95% pure, was produced in 653 runs from 1930 kg of metal fabrication scrap, 99% pure. General considerations of the electrorefining process and facility operation and recommendations for further improvement of the process are discussed

77 FR 33243 - Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving...

Science.gov (United States)

2012-06-05

... expansion process, thermal expansion mismatch between the tube and tubesheet, and from the differential... NUCLEAR REGULATORY COMMISSION [NRC-2012-0125] Applications and Amendments to Facility Operating...

Improvement in performance and operational experience of 14 UD Pelletron accelerator facility, BARC-TIFR

International Nuclear Information System (INIS)

Bhagwat, P.V.

2002-01-01

14 UD Pelletron accelerator facility at Mumbai has been operational since 1989. The project MEHIA (Medium Energy Heavy Ion Accelerator) started in 1982 and was formally inaugurated on 30th December 1988. Since then the accelerator has been working round the clock. Improvement in accelerator performance and operational experience are described. (author)

Sandia National Laboratories Facilities Management and Operations Center Design Standards Manual

Energy Technology Data Exchange (ETDEWEB)

Peterson, Timothy L. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)

2014-09-01

At Sandia National Laboratories in New Mexico (SNL/NM), the design, construction, operation, and maintenance of facilities is guided by industry standards, a graded approach, and the systematic analysis of life cycle benefits received for costs incurred. The design of the physical plant must ensure that the facilities are "fit for use," and provide conditions that effectively, efficiently, and safely support current and future mission needs. In addition, SNL/NM applies sustainable design principles, using an integrated whole-building design approach, from site planning to facility design, construction, and operation to ensure building resource efficiency and the health and productivity of occupants. The safety and health of the workforce and the public, any possible effects on the environment, and compliance with building codes take precedence over project issues, such as performance, cost, and schedule. These design standards generally apply to all disciplines on all SNL/NM projects. Architectural and engineering design must be both functional and cost-effective. Facility design must be tailored to fit its intended function, while emphasizing low-maintenance, energy-efficient, and energy-conscious design. Design facilities that can be maintained easily, with readily accessible equipment areas, low maintenance, and quality systems. To promote an orderly and efficient appearance, architectural features of new facilities must complement and enhance the existing architecture at the site. As an Architectural and Engineering (A/E) professional, you must advise the Project Manager when this approach is prohibitively expensive. You are encouraged to use professional judgment and ingenuity to produce a coordinated interdisciplinary design that is cost-effective, easily contractible or buildable, high-performing, aesthetically pleasing, and compliant with applicable building codes. Close coordination and development of civil, landscape, structural, architectural, fire

Cyanobacteria of the 2016 Lake Okeechobee and Okeechobee Waterway harmful algal bloom

Science.gov (United States)

Rosen, Barry H.; Davis, Timothy W.; Gobler, Christopher J.; Kramer, Benjamin J.; Loftin, Keith A.

2017-05-31

The Lake Okeechobee and the Okeechobee Waterway (Lake Okeechobee, the St. Lucie Canal and River, and the Caloosahatchee River) experienced an extensive harmful algal bloom within Lake Okeechobee, the St. Lucie Canal and River and the Caloosahatchee River in 2016. In addition to the very visible bloom of the cyanobacterium Microcystis aeruginosa, several other cyanobacteria were present. These other species were less conspicuous; however, they have the potential to produce a variety of cyanotoxins, including anatoxins, cylindrospermopsins, and saxitoxins, in addition to the microcystins commonly associated with Microcystis. Some of these species were found before, during, and 2 weeks after the large Microcystis bloom and could provide a better understanding of bloom dynamics and succession. This report provides photographic documentation and taxonomic assessment of the cyanobacteria present from Lake Okeechobee and the Caloosahatchee River and St. Lucie Canal, with samples collected June 1st from the Caloosahatchee River and Lake Okeechobee and in July from the St. Lucie Canal. The majority of the images were of live organisms, allowing their natural complement of pigmentation to be captured. The report provides a digital image-based taxonomic record of the Lake Okeechobee and the Okeechobee Waterway microscopic flora. It is anticipated that these images will facilitate current and future studies on this system, such as understanding the timing of cyanobacteria blooms and their potential toxin production.

Reports and operational engineering: An independent safety assessment of Department of Energy nuclear reactor facilities

International Nuclear Information System (INIS)

Rochman, A.; Washburn, B.W.

1981-02-01

The Nuclear Facilities Personnel Qualification and Training (NFPQT) Committee, established via an October 24, 1979 memorandum from the Department of Energy (DOE) Under Secretary, was instructed to review the ''Kemeny Commission'' recommendations and to identify possible implications for DOE's nuclear facilities. As a result of this review, the Committee recommended that DOE carry out assessments in seven categories. The assessments would address specific topics identified for each category as delineated in the NFPQT ''Guidelines for Assessing the Safe Operation of DOE-Owned Reactors,'' dated May 7, 1980. The Committee recognized that similar assessments had been ongoing in the DOE program and safety overview organizations since the Three Mile Island nuclear accident and it was the Committee's intent to use the results of those ongoing assessments as an input to their evaluations. This information would be supplemented by additional studies consisting of the subject-related documents used at each reactor facility studied, and an on-site review of these reactor facilities by professional personnel within the Department of Energy, its operating contractors and independent consultants. 1 tab

Design and operation of radioactive waste incineration facilities

International Nuclear Information System (INIS)

1992-01-01

The purpose of this guide is to provide safety guidance for the design and operation of radioactive waste incineration facilities. The guide emphasizes the design objectives and system requirements to be met and provides recommendations for the procedure of process selection and equipment design and operation. It is recognized that some incinerators may handle only very low or 'insignificant' levels of radioactivity, and in such cases some requirements or recommendations of this guide may not fully apply. Nevertheless, it is expected that any non-compliance with the guide will be addressed and justified in the licensing process. It is also recognized that the regulatory body may place a limit on the level of the radioactivity of the waste to be incinerated at a specific installation. For the purpose of this guide an insignificant level of release of radioactivity may typically be defined as either the continuous or single event release of the design basis radionuclide inventory that represents a negligible risk to the population, the operating personnel, and/or the environment. The guidance on what constitutes a negligible risk and how to translate negligible risk or dose into level of activity can be found in Safety Series No. 89, IAEA, Vienna. 20 refs, 1 fig

Seismic qualification program plan for continued operation at DOE-SRS nuclear material processing facilities

International Nuclear Information System (INIS)

Talukdar, B.K.; Kennedy, W.N.

1991-01-01

The Savannah River Facilities for the most part were constructed and maintained to standards that were developed by Du Pont and are not rigorously in compliance with the current General Design Criteria (GDC); DOE Order 6430.IA requirements. In addition, many of the facilities were built more than 30 years ago, well before DOE standards for design were issued. The Westinghouse Savannah River Company (WSRC) his developed a program to address the evaluation of the Nuclear Material Processing (NMP) facilities to GDC requirements. The program includes a facility base-line review, assessment of areas that are not in compliance with the GDC requirements, planned corrective actions or exemptions to address the requirements, and a safety assessment. The authors from their direct involvement with the Program, describe the program plan for seismic qualification including other natural phenomena hazards,for existing NMP facility structures to continue operation Professionals involved in similar effort at other DOE facilities may find the program useful

Operating experience with remote handling equipment in a typical hot facility

International Nuclear Information System (INIS)

Ravishankar, A.; Balasubramanian, G.R.

1990-01-01

Large number of articulated arm manipulators and special purpose remote tools have been used either alone or in combination in a recent campaign of treatment of irradiated J rods of CIRUS for separation of 233 U. These equipments were used for operations such as remote maintenance of centrifuge, centrifugal extractor, direct sampling, assistance for sample conveying operations etc. Paper discusses problems encountered in using articulated arm manipulators of type MAll,AMl and how they were overcome. Problems encountered in use of model-8 manipulator for chopper maintenence in a mockup facility are also highlighted. (author). 4 figs., 1 tab

Operational improvement to the flue gas cleaning system in radioactive waste incineration facilities

International Nuclear Information System (INIS)

Zheng Bowen; Li Xiaohai; Wang Peiyi

2012-01-01

After years of operation, some problems, such as corrosion and waste water treatment, have been found in the first domestic whole-scale radioactive waste incineration facility. According to the origin of the problems, the flue gas cleaning system has been optimized and improved in terms of technical process, material and structure. It improves the operational stability, extends the equipment life-time, and also reduces the amount of secondary waste. In addition, as major sources of problems, waste management, operational experiences and information exchange deserve more attention. (authors)

76 FR 72309 - Drawbridge Operation Regulations; Chelsea River, Chelsea and East Boston, MA

Science.gov (United States)

2011-11-23

...-30), U.S. Department of Transportation, West Building Ground Floor, Room W12-140, 1200 New Jersey... McDonald, Project Officer, First Coast Guard District, telephone (617) 223-8364, john.w.mcdonald@uscg.mil.... The waterway is transited predominantly by commercial operators delivering petroleum products to...

Management aspects of Gemini's base facility operations project

Science.gov (United States)

Arriagada, Gustavo; Nitta, Atsuko; Adamson, A. J.; Nunez, Arturo; Serio, Andrew; Cordova, Martin

2016-08-01

Gemini's Base Facilities Operations (BFO) Project provided the capabilities to perform routine nighttime operations without anyone on the summit. The expected benefits were to achieve money savings and to become an enabler of the future development of remote operations. The project was executed using a tailored version of Prince2 project management methodology. It was schedule driven and managing it demanded flexibility and creativity to produce what was needed, taking into consideration all the constraints present at the time: Time available to implement BFO at Gemini North (GN), two years. The project had to be done in a matrix resources environment. There were only three resources assigned exclusively to BFO. The implementation of new capabilities had to be done without disrupting operations. And we needed to succeed, introducing the new operational model that implied Telescope and instrumentation Operators (Science Operations Specialists - SOS) relying on technology to assess summit conditions. To meet schedule we created a large number of concurrent smaller projects called Work Packages (WP). To be reassured that we would successfully implement BFO, we initially spent a good portion of time and effort, collecting and learning about user's needs. This was done through close interaction with SOSs, Observers, Engineers and Technicians. Once we had a clear understanding of the requirements, we took the approach of implementing the "bare minimum" necessary technology that would meet them and that would be maintainable in the long term. Another key element was the introduction of the "gradual descent" concept. In this, we increasingly provided tools to the SOSs and Observers to prevent them from going outside the control room during nighttime operations, giving them the opportunity of familiarizing themselves with the new tools over a time span of several months. Also, by using these tools at an early stage, Engineers and Technicians had more time for debugging

The high current test facility injector operation to 40 mA dc

International Nuclear Information System (INIS)

Ungrin, J.; Ormrod, J.H.; Michel, W.L.

1976-01-01

The high current test facility injector is a 750 keV proton accelerator designed to investigate the problems involved in the acceleration of intense dc proton beams. The performance of the injector and the experience gained in operation with dc beams up to 40 mA are described. (author)

78 FR 48608 - Drawbridge Operation Regulation; Atlantic Intracoastal Waterway (AIWW), Chesapeake, VA

Science.gov (United States)

2013-08-09

... maintenance of the moveable spans on the structure. The current operating schedule for the bridge is set out... deviation from the operating schedule that governs the operation of the I64 Bridge across the Atlantic... necessary to facilitate maintenance work on the moveable spans. This temporary deviation allows the...

Operation of Cryogenic Facility in e-way at Tata Institute of Fundamental Research, Mumbai, India

International Nuclear Information System (INIS)

Srinivasan, K V

2012-01-01

In an attempt towards the development of modern, model and paperless cryogenic facility, the Low Temperature Facility of Tata Institute of Fundamental Research, at Mumbai, India; carried out many automation works using programmable logic controller (PLC) and other modern electronic tools, with the objective of bringing the entire plant operation to your palm whenever and wherever you are. Efficiency in the plant operation by keeping a watch on the plant healthiness, advance indication about the possible plant problem by means of pre-warning alarms, so that the remedial action can be taken well prior to the actual failure affects the plant operation, reduction in plant down time were achieved by the automation works. Large size in our cryogen production, controlling the complicated helium liquefier, meeting the uninterrupted supply of cryogen to the users on “any time availability basis,” safety in handling cryogens and high pressure gas, effective usage of limited skilled manpower etc., all these requirements call for the definite need of modern electronic gears and gadgets. This paper will describe in details about the automation works carried out at our cryogenic facility at TIFR.

Software solutions manage the definition, operation, maintenance and configuration control of the National Ignition Facility

International Nuclear Information System (INIS)

Dobson, Darwin; Churby, Al; Krieger, Ed; Maloy, Donna; White, Kevin

2012-01-01

Highlights: ► NIF is a complex experimental facility composed of ∼4 million components. ► We describe business tools to define, build, operate, and maintain all components. ► CAD tools generate virtual models and assemblies under configuration control. ► Items requiring preventive, reactive, and/or calibration maintenance are tracked. ► Radiological or hazardous materials undergo additional controls. - Abstract: The National Ignition Facility (NIF) is the world's largest laser composed of millions of individual parts brought together to form one massive assembly. Maintaining control of the physical definition, status and configuration of this structure is a monumental undertaking yet critical to the validity of experimental data and the safe operation of the facility. A major programmatic challenge is to deploy software solutions to effectively manage the definition, build, operation, and maintenance, and configuration control of all components of NIF. The strategy for meeting this challenge involves deploying and integrating an enterprise application suite of solutions consisting of both Commercial-Off-The-Shelf (COTS) products and custom developed software.This paper describes how this strategy has been implemented along with a discussion on the successes realized and the ongoing challenges associated with this approach.

Design and operational considerations of United States commercial nea-surface low-level radioactive waste disposal facilities

International Nuclear Information System (INIS)

Birk, Sandra M.

1997-01-01

Low-level radioactive waste disposal standards and techniques in the United States have evolved significantly since the early 1960's. Six commercial LLW disposal facilities(Barnwell, Richland, Ward Valley, Sierra Blanca, Wake County and Boyd County) operated and proposed between 1962 and 1997. This report summarizes each site's design and operational considerations for near-surface disposal of low-level radioactive waste. These new standards and mitigating efforts at closed facilities (Sheffield, Maxey Flats, Beatty and West Valley) have helped to ensure that the public has been safely protected from LLW. 15 refs

Columbia River System Operation Review final environmental impact statement. Appendix H: Navigation

International Nuclear Information System (INIS)

1995-11-01

The System Operation Review (SOR) is a study and environmental compliance process being used by the three Federal agencies to analyze future operations of the system and river use issues. The goal of the SOR is to achieve a coordinated system operation strategy for the river that better meets the needs of all river users. This technical appendix addresses only the effects of alternative system operating strategies for managing the Columbia River system. The Navigation Technical Appendix presents the analysis of the various SOR alternatives in terms of their potential affects on the congressionally authorized navigation system within the Columbia and Snake river waterways. The focus of the study, impacts to the authorized navigation, improvements/developments, reflects on one of the continuing historical missions of the US Army Corps of Engineers: to promote safe commercial navigation of the nation's waterways benefiting the development of commerce within the US. The study and evaluation process involved Scoping, Screening and Full Scale Evaluation. During screening two models were developed; one was used to evaluate the effects of the various alternatives on navigation through the Snake River Projects and the other the effects on the Dworshak Pool. Full Scale Analysis was expanded to included a study of effects throughout the system

76 FR 35104 - Safety Zone; Waterway Closure, Atchafalaya River From Mile Marker 117 (Morgan City Railroad...

Science.gov (United States)

2011-06-16

...-AA00 Safety Zone; Waterway Closure, Atchafalaya River From Mile Marker 117 (Morgan City Railroad Bridge... with rising flood water in the Atchafalaya River. Basis and Purpose Captain of the Port Morgan City... safety zone is located on the specified waters of the Atchafalaya River between MM 117 (Morgan City...

Risk management for operations of the LANL Critical Experiments Facility

International Nuclear Information System (INIS)

Paternoster, R.; Butterfield, K.

1998-01-01

The Los Alamos Critical Experiments Facility (LACEF) currently operates two burst reactors (Godiva-IV and Skua), one solution assembly [the Solution High-Energy Burst Assembly (SHEBA)], two fast-spectrum benchmark assemblies (Flattop and Big Ten), and five general-purpose remote assembly machines that may be configured with nuclear materials and assembled by remote control. Special nuclear materials storage vaults support these and other operations at the site. With this diverse set of operations, several approaches are possible in the analysis and management of risk. The most conservative approach would be to write a safety analysis report (SAR) for each assembly and experiment. A more cost-effective approach is to analyze the probability and consequences of several classes of operations representative of operations on each critical assembly machine and envelope the bounding case accidents. Although the neutron physics of these machines varies widely, the operations performed at LACEF fall into four operational modes: steady-state mode, approach-to-critical mode, prompt burst mode, and nuclear material operations, which can include critical assembly fuel loading. The operational sequences of each mode are very nearly identical, whether operated on one assembly machine or another. The use of an envelope approach to accident analysis is facilitated by the use of classes of operations and the use of bounding case consequence analysis. A simple fault tree analysis of operational modes helps resolve which operations are sensitive to human error and which are initiated by hardware of software failures. Where possible, these errors and failures are blocked by TSR LCOs. Future work will determine the probability of accidents with various initiators

Transport and handling of dangerous goods. Training of persons in charge of vehicles or vessels carrying dangerous goods by road or by inland waterways (Dangerous Goods 1979 No.1)

International Nuclear Information System (INIS)

1979-01-01

This Order supplements the Regulations of 15 April 1945 on the transport of dangerous goods by rail, land and inland waterways. It deals with the training of persons in charge of vehicles or boats carrying dangerous goods by road or by inland waterways. It refers in particular to transport of radioactive materials. (NEA) [fr

Operating experience review -- Conduct of operations at Department of Energy facilities

International Nuclear Information System (INIS)

1994-08-01

This research examined human error related occurrences, reported in the ORPS database, for the purpose of identifying weaknesses in the implementation of the guidance regarding the Conduct of Operations contained in DOE 5480.19. Specifically, this research examined three separate samples of occurrence reports from Defense Program facilities, which cited human error as a direct or contributing cause. These reports were evaluated using a coding scheme which incorporated the guidelines present in 5480.19, as well as a number of generic human factors concerns. The second chapter of this report summarizes the coding scheme which was used to evaluate the occurrence reports. Since the coding scheme is quite lengthy, only the parts of the scheme needed to make the remainder of the report clear are included in this chapter. Details on the development and content of the coding scheme are reported in Appendices A, B, and C. Chapter 3 presents the analysis of three different data sets. This chapter demonstrates that similar results were obtained across different data sets, collected at different points in time, and coded by different raters. The implications of the results obtained in Chapter 3 are discussed in Chapter 4. This chapter makes a number of suggestions for reducing the problems found in the occurrence reports. Chapter 5 applies the methodology that has been developed in this report to two facilities at Los Alamos National Laboratory. Finally, Chapter 6 reiterates the major findings of this report. Several additional analyses appear in appendices at the end of this report

Licensing and Operations of the Clive, Utah Low-Level Containerized Radioactive Waste Disposal Facility- A Continuation of Excellence

International Nuclear Information System (INIS)

Ledoux, M. R.; Cade, M. S.

2002-01-01

Envirocare's Containerized Waste Facility (CWF) is the first commercial low-level radioactive waste disposal facility to be licensed in the 21st century and the first new site to be opened and operated since the late 1970's. The licensing of this facility has been the culmination of over a decade's effort by Envirocare of Utah at their Clive, Utah site. With the authorization to receive and dispose of higher activity containerized Class A low-level radioactive waste (LLRW), this facility has provided critical access to disposal for the nuclear power industry, as well as the related research and medical communities. This paper chronicles the licensing history and operational efforts designed to address the disposal of containerized LLRW in accordance with state and federal regulations

41 CFR 102-74.55 - Are vending facilities authorized under the Randolph-Sheppard Act operated by permit or contract?

Science.gov (United States)

2010-07-01

... vending facilities (including vending machines) on Federal property. ... 41 Public Contracts and Property Management 3 2010-07-01 2010-07-01 false Are vending facilities....55 Are vending facilities authorized under the Randolph-Sheppard Act operated by permit or contract...

Safety evaluation of the NSRR facility relevant to the modification for improved pulse operation and preirradiated fuel experiments

International Nuclear Information System (INIS)

Inabe, Teruo; Terakado, Yoshibumi; Tanzawa, Sadamitsu; Katagiri, Hiroshi; Kobayashi, Hideo

1988-11-01

The Nuclear Safety Research Reactor (NSRR) is a pulse reactor for the inpile experiments to study the fuel behavior under reactivity initiated accident conditions. The present operation modes of the NSRR consist of the steady state operation up to 300 kW and the natural pulse operation in which a sharp pulsed power is generated from substantially zero power level. In addition to these, two new modes of shaped pulse operation and combined pulse operation will be conducted in the near future as the improved pulse operations. A transient power up to 10 MW will be generated in the shaped pulse operation, and a combination of a transient power up to 10 MW and a sharp pulsed power will be generated in the combined pulse operation. Furthermore, preirradiated fuel rods will be employed in the future experiments whereas the present experiments are confined to the test specimens of unirradiated fuel rods. To provide for these programs, the fundamental design works relevant to the modification of the reactor facility including the reactor instrumentation and control systems and experimental provision were developed. The reactor safety evaluation is prerequisite for confirming the propriety of the fundamental design of the reactor facility from the safety point of view. The safety evaluation was therefore conducted postulating such events that would bring about abnormal conditions in the reactor facility. As a result of the safety evaluation, it has been confirmed as to the NSRR facility after modification that the anticipated transients, the postulated accidents, the major accident and the hypothetical accident do not result respectively in any serious safety problem and that the fundamental design principles and the reactor siting are adequate and acceptable. (author)

A Study on an appropriate operating system of environmental basic facility service industry

Energy Technology Data Exchange (ETDEWEB)

Moon, Hyun Joo [Korea Environment Institute, Seoul (Korea)

1998-12-01

The environmental basic facility service industry is designed to have a structural reorganization of general operating system and the efficient and effective participation of private industry and regulation of industry in connection with the general system. 35 refs., 9 figs., 20 tabs.

Operation, Maintenance and Management of Wastewater Treatment Facilities: A Bibliography of Technical Documents.

Science.gov (United States)

Himes, Dottie

This is an annotated bibliography of wastewater treatment manuals. Fourteen manuals are abstracted including: (1) A Planned Maintenance Management System for Municipal Wastewater Treatment Plants; (2) Anaerobic Sludge Digestion, Operations Manual; (3) Emergency Planning for Municipal Wastewater Treatment Facilities; (4) Estimating Laboratory Needs…

Guidance for preparation of safety analysis reports for nonreactor facilities and operations

International Nuclear Information System (INIS)

1992-01-01

Department of Energy (DOE) Orders 5480.23, ''Nuclear Safety Analysis Reports,'' and 5481.1B, ''Safety Analysis and Review System'' require the preparation of appropriate safety analyses for each DOE operation and subsequent significant modifications including decommissioning, and independent review of each safety analysis. The purpose of this guide is to assist in the preparation and review of safety documentation for Oak Ridge Field Office (OR) nonreactor facilities and operation. Appendix A lists DOE Orders, NRC Regulatory Guides and other documents applicable to the preparation of safety analysis reports

Operational experiences in radiation protection in fast reactor fuel reprocessing facility

International Nuclear Information System (INIS)

Meenakshisundaram, V.; Rajagopal, V.; Santhanam, R.; Baskar, S.; Madhusoodanan, U.; Chandrasekaran, S.; Balasundar, S.; Suresh, K.; Ajoy, K.C.; Dhanasekaran, A.; Akila, R.; Indira, R.

2008-01-01

The Compact Reprocessing facility for Advanced fuels in Lead cells (CORAL), situated at Indira Gandhi Centre for Atomic Research (IGCAR), Kalpakkam is a pilot plant to reprocess the mixed carbide fuel, for the first time in the world. Reprocessing of fuel with varying burn-ups up to 155 G Wd/t, irradiated at Fast Breeder Test Reactor (FBTR), has been successfully carried out at CORAL. Providing radiological surveillance in a fuel reprocessing facility itself is a challenging task, considering the dynamic status of the sources and the proximity of the operator with the radioactive material and it is more so in a fast reactor fuel reprocessing facility due to handling of higher burn-up fuels associated with radiation fields and elevated levels of fissile material content from the point of view of criticality hazard. A very detailed radiation protection program is in place at CORAL. This includes, among others, monitoring the release of 85 Kr and other fission products and actinides, if any, through stack on a continuous basis to comply with the regulatory limits and management of disposal of different types of radioactive wastes. Providing radiological surveillance during the operations such as fuel transport, chopping and dissolution and extraction cycle was without any major difficulty, as these were carried out in well-shielded and high integrity lead cells. Enforcement of exposure control assumes more importance during the analysis of process samples and re-conversion operations due to the presence of fission product impurities and also since the operations were done in glove boxes and fume hoods. Although the radiation fields encountered in process area were marginally higher, due to the enforcement of strict administrative controls, the annual exposure to the radiation workers was well within the regulatory limit. As the facility is being used as test bed for validation of prototype equipment, periodic inspection and maintenance of components such as centrifuge

Operating experience and radiation protection problems in the working of the radio-metallurgy hot cell facilities at BARC

International Nuclear Information System (INIS)

Janardhanan, S.; Watamwar, S.B.; Mehta, S.K.; Pillai, P.M.B.; John, Jacob; Kutty, K.N.

1977-01-01

The Bhabha Atomic Research Centre at Bombay has six hot cell facilities for radiometallurgical investigations of irradiated/failed fuel elements. The hot cell facilities have been provided with certain built-in safety features, a ventilation system, radiation monitoring instruments for various purposes, a centralised air monitoring system and a central panel for display of various alarms. Procedures adopted for radiation protection and contamination control include : (1) radiation leak test for cells and filter efficiency evaluation before cell activation, (2) practices to be followed by frog suit personnel while working in hot cell areas, (3) receipt and handling of irradiated fuel elements, (4) cell filter change operation, (5) checks on high level drains and (6) effluent discharge and waste shipments. Operating experience in the working of these facilities along with radiation accident incidents is described. Data regarding release of activity during normal cell operations, dose rates during various metallurgical operations and personnel exposures are presented. (M.G.B.)

The operator interface for the Mirror Fusion Test Facility

International Nuclear Information System (INIS)

Lang, N.C.

1986-12-01

The uncertain and most likely changing nature of a large experimental facility like MFTF, as well as its large number of control and monitor points, ruled against the traditional hardware approach involving walls of knobs, dials, oscilloscopes, and strip chart recorders. Rather, from the beginning, project management specified computer control of all systems, and operation of the complete MFTF under an integrated computer control system became a major engineering goal. The Integrated Controls and Diagnostics (ICADS) group was charged with the design and implementation of this control system. We designed a control system with an extremely flexible operator interface which uses computer generated CRT displays for output and pointing devices such as touch sensitive CRT overlays, mice, and joysticks for input. Construction of MFTF was completed at the end of 1985 within the project budget of $241.6M and was followed immediately by a 5 month long acceptance test. During this period (known as PACE test) operators, engineers, and physicists successfully used our computer control system daily to test MFTF. Much of their willingness to forsake the traditional hands-on hardware approach to testing was a result of the powerful and flexible operator interface to the MFTF control system. In this paper, we describe the operator interface with emphasis on the displays, the touch screens, and the mouse. We also report the experiences of users and, in particular, stress those aspects of the user interface they strongly liked and disliked

78 FR 62439 - Drawbridge Operation Regulation; Inner Harbor Navigational Canal, New Orleans, LA

Science.gov (United States)

2013-10-22

... Operation Regulation; Inner Harbor Navigational Canal, New Orleans, LA AGENCY: Coast Guard, DHS. ACTION..../Seabrook) bridge across the IHNC, mile 4.6, both at New Orleans, LA. This deviation will test changes to... Intra-Costal Waterway (GIWW). The US 90 (Danzinger) Bridge across the IHNC, mile 3.1, at New Orleans...

Model of passage of vessels through the waterway section forming the schedule in the course of its implementation

Directory of Open Access Journals (Sweden)

S. N. Plotnikov

2017-01-01

Full Text Available The model of passage of vessels through a section of the waterway is considered, which independently determines the order of passage of vessels with limited capacity of sections of the track. Such a model will consist of a number of standard algorithmic networks. When composing the schedule in the model, the following preference rules were used: first-come-first-served (that is, if the ship occupied the workplace, this decision is not canceled; The rule of the shortest operation; For the swamps the priority of vessels going downstream (the direction of flow from the source to the drain. An algorithmic network that implements the search for an acceptable schedule must implement the following for conflicting operations: the operation that has started is not interrupted; If several operations simultaneously claim for one workplace (port, reach and their number is greater than its throughput, then the conflict resolution is carried out in accordance with predefined preference rules or based on the user's decision; If the operation is waiting for the release of the workplace, it does not occupy the resource; The resource is returned immediately after the operation is completed. The considered design of algorithmic networks allows to resolve the conflict, with a simultaneous resource request, to take the resource once, remember that it was received and return it after the end of the operation, then the resource receives a contra-controlling operation for execution. However, the use of this design introduces redundancy into the model, even if it is used only for conflicting operations. The model is presented in the language of algorithmic networks and is implemented in the system of modeling automation KOGNITRON.

Influences of the separation distance, ship speed and channel dimension on ship maneuverability in a confined waterway

Science.gov (United States)

Du, Peng; Ouahsine, Abdellatif; Sergent, Philippe

2018-05-01

Ship maneuvering in the confined inland waterway is investigated using the system-based method, where a nonlinear transient hydrodynamic model is adopted and confinement models are implemented to account for the influence of the channel bank and bottom. The maneuvering model is validated using the turning circle test, and the confinement model is validated using the experimental data. The separation distance, ship speed, and channel width are then varied to investigate their influences on ship maneuverability. With smaller separation distances and higher speeds near the bank, the ship's trajectory deviates more from the original course and the bow is repelled with a larger yaw angle, which increase the difficulty of maneuvering. Smaller channel widths induce higher advancing resistances on the ship. The minimum distance to the bank are extracted and studied. It is suggested to navigate the ship in the middle of the channel and with a reasonable speed in the restricted waterway.

Present Situation and Problems of Land Improvement District as an Operation and Maintenance Organization of Land Improvement Facilities

OpenAIRE

長堀, 金造; 赤江, 剛夫; 大田, 征六

1994-01-01

Land improvement districts originally started as organizations after World War II: They are in charge of construction and operation of irrigation and drainage facilities, Development of agricultural land, reclamation from sea water, reclamation by filling, Recovery from disaster, exchange and consolidation of agricultural land and so on. As the Main construction projects were completed, the purpose of land improvement districts Has shifted from facilities construction to operation and mainten...

Flight dynamics facility operational orbit determination support for the ocean topography experiment

Science.gov (United States)

Bolvin, D. T.; Schanzle, A. F.; Samii, M. V.; Doll, C. E.

1991-01-01

The Ocean Topography Experiment (TOPEX/POSEIDON) mission is designed to determine the topography of the Earth's sea surface across a 3 yr period, beginning with launch in June 1992. The Goddard Space Flight Center Dynamics Facility has the capability to operationally receive and process Tracking and Data Relay Satellite System (TDRSS) tracking data. Because these data will be used to support orbit determination (OD) aspects of the TOPEX mission, the Dynamics Facility was designated to perform TOPEX operational OD. The scientific data require stringent OD accuracy in navigating the TOPEX spacecraft. The OD accuracy requirements fall into two categories: (1) on orbit free flight; and (2) maneuver. The maneuver OD accuracy requirements are of two types; premaneuver planning and postmaneuver evaluation. Analysis using the Orbit Determination Error Analysis System (ODEAS) covariance software has shown that, during the first postlaunch mission phase of the TOPEX mission, some postmaneuver evaluation OD accuracy requirements cannot be met. ODEAS results also show that the most difficult requirements to meet are those that determine the change in the components of velocity for postmaneuver evaluation.

Operational experience of gamma radiation processing facility

International Nuclear Information System (INIS)

Patel, Nilesh

2014-01-01

Universal lSO-MED is now proud to announce an extension of its irradiation service for low-dose applications specifically in agriculture commodities, food and healthcare applications with the start of Gujarat Agro Radiation Processing Facility at Village: Bavla, Ahmedabad (A Government Enterprise) Operated, Maintained and Managed by Universal Medicap Ltd. Availability of hygienic, safe and nutritious food commodities is essential for any sustainable human development. Food stability is an important element of economic stability and self-reliance of a nation. Though the need to preserve food has been felt by the mankind since the time immemorial, it is even stronger in today's context. The rising population and increasing gap between demand and supply, agro-climatic conditions, in adequate post-harvest practices, seasonal nature of produce and long distances between production and consumption centers underscore the need to device improved conservation and preservation strategies

Conceptual design of a test facility for the remote handling operations of the ITER Test Blanker Modules

International Nuclear Information System (INIS)

Marqueta, A.; Garcia, I.; Gomez, A.; Garcia, L.; Sedano, E.; Fernandez, I.

2012-01-01

Conceptual Design of a test facility for the remote handling operations of the ITER Test Blanket Modules. Conditions inside a fusion reactor are incompatible with conventional manual maintenance tasks. the same applies for ancillary equipment. As a consequence, it will become necessary to turn to remote visualization and remote handling techniques, which will have in consideration the extreme conditions, both physical and operating, of ITER. Main goal of the project has been the realization of the conceptual design for the test facility for the Test Blanket Modules of ITER and their associated systems, related to the Remote Handling operations regarding the Port Cell area. Besides the definition of the operations and the specification of the main components and ancillary systems of the TBM graphical simulation have been used for the design, verification and validation of the remote handling operations. (Author)

MagLev Cobra: Test Facilities and Operational Experiments

Science.gov (United States)

Sotelo, G. G.; Dias, D. H. J. N.; de Oliveira, R. A. H.; Ferreira, A. C.; De Andrade, R., Jr.; Stephan, R. M.

2014-05-01

The superconducting MagLev technology for transportation systems is becoming mature due to the research and developing effort of recent years. The Brazilian project, named MagLev-Cobra, started in 1998. It has the goal of developing a superconducting levitation vehicle for urban areas. The adopted levitation technology is based on the diamagnetic and the flux pinning properties of YBa2Cu3O7-δ (YBCO) bulk blocks in the interaction with Nd-Fe-B permanent magnets. A laboratory test facility with permanent magnet guideway, linear induction motor and one vehicle module is been built to investigate its operation. The MagLev-Cobra project state of the art is presented in the present paper, describing some construction details of the new test line with 200 m.

Widespread infilling of tidal channels and navigable waterways in human-modified tidal deltaplain of southwest Bangladesh

Directory of Open Access Journals (Sweden)

Carol Wilson

2017-12-01

Full Text Available Since the 1960s, ~5000 km2 of tidal deltaplain in southwest Bangladesh has been embanked and converted to densely inhabited, agricultural islands (i.e., polders. This landscape is juxtaposed to the adjacent Sundarbans, a pristine mangrove forest, both well connected by a dense network of tidal channels that effectively convey water and sediment throughout the region. The extensive embanking in poldered areas, however, has greatly reduced the tidal prism (i.e., volume of water transported through local channels. We reveal that >600 km of these major waterways have infilled in recent decades, converting to land through enhanced sedimentation and the direct blocking of waterways by embankments and sluice gates. Nearly all of the observed closures (~98% have occurred along the embanked polder systems, with no comparable changes occurring in channels of the Sundarbans (<2% change. We attribute most of the channel infilling to the local reduction of tidal prism in poldered areas and the associated decline in current velocities. The infilled channels account for ~90 km2 of new land in the last 40–50 years, the rate of which, ~2 km2/yr, offsets the 4 km2/yr that is eroded at the coast, and is equivalent to ~20% of the new land produced naturally at the Ganges-Brahmaputra tidal rivermouth. Most of this new land, called ‘khas’ in Bengali, has been reclaimed for agriculture or aquaculture, contributing to the local economy. However, benefits are tempered by the loss of navigable waterways for commerce, transportation, and fishing, as well as the forced rerouting of tidal waters and sediments necessary to sustain this low-lying landscape against rising sea level. A more sustainable delta will require detailed knowledge of the consequences of these hydrodynamic changes to support more scientifically-grounded management of water, sediment, and tidal energy distribution.

Licensing and Operations of the Clive, Utah Low-Level Containerized Radioactive Waste Disposal Facility- A Continuation of Excellence

Energy Technology Data Exchange (ETDEWEB)

Ledoux, M. R.; Cade, M. S.

2002-02-25

Envirocare's Containerized Waste Facility (CWF) is the first commercial low-level radioactive waste disposal facility to be licensed in the 21st century and the first new site to be opened and operated since the late 1970's. The licensing of this facility has been the culmination of over a decade's effort by Envirocare of Utah at their Clive, Utah site. With the authorization to receive and dispose of higher activity containerized Class A low-level radioactive waste (LLRW), this facility has provided critical access to disposal for the nuclear power industry, as well as the related research and medical communities. This paper chronicles the licensing history and operational efforts designed to address the disposal of containerized LLRW in accordance with state and federal regulations.

Radiation protection problems by the operation of the cyclotron facility

International Nuclear Information System (INIS)

Durcik, M.; Nikodemova, D.

1998-01-01

The Cyclotron Center in Bratislava will consist of two cyclotrons. First - cyclotron DC-72 with maximal energy of 72 MV for protons for making experiments, for teaching process, for radioisotope production as 123 I and for neutron and proton therapy. Second - compact cyclotron with maximal proton energy of 18 MeV will be used for radioisotopes production for medical diagnosis as 1 *F (fluorodeoxyglucose), 81 Rb/ 81 Kr generator. This paper deals with the radiation protection problems by the operation of tis cyclotron facility as radiation protection of workers, monitoring plan, ventilation, safety lock and limitation and radiation monitoring. For proposed and continuing practices at the accelerator facility, the following general principles have to be fulfilled: (1) practices should produce sufficient benefit to offset the radiation detriment they case (justification); (2) the magnitude of the individual doses should be kept as low as achievable (optimization of protection); (3) individual exposures are subject to dose limits and some control of risk from potential exposures (dose and risk limits)

Assessing and addressing increased stakeholder and operator information needs in nuclear fuel cycle facilities: two concepts

Energy Technology Data Exchange (ETDEWEB)

Saltiel, David H. [Sandia National Laboratories, Albuquerque (United States)

2007-12-15

Nuclear energy programs around the world increasingly find themselves at the nexus of potentially conflicting demands from both domestic and international stakeholders. On one side, the rapid growth in demand for electricity coupled with the goal of reducing carbon emissions calls for a significant expansion of nuclear energy. On the other, stakeholders are seeking ever greater safety, environmental, security, and nonproliferation assurances before consenting to the construction of new nuclear energy facilities. Satisfying the demand for clean energy supplies will require nuclear energy operators to find new and innovative ways to build confidence among stakeholders. This paper discusses two related concepts which can contribute to meeting the needs of key stakeholders in cost effective and efficient ways. Structured processes and tools for assessing stakeholder needs can build trust and confidence while facilitating the 'designing-in' of information collection systems for new facilities to achieve maximum efficiency and effectiveness. Integrated approaches to monitoring facilities and managing the resulting data can provide stakeholders with continued confidence while offering operators additional facility and process information to improve performance.

Assessing and addressing increased stakeholder and operator information needs in nuclear fuel cycle facilities: two concepts

International Nuclear Information System (INIS)

Saltiel, David H.

2007-01-01

Nuclear energy programs around the world increasingly find themselves at the nexus of potentially conflicting demands from both domestic and international stakeholders. On one side, the rapid growth in demand for electricity coupled with the goal of reducing carbon emissions calls for a significant expansion of nuclear energy. On the other, stakeholders are seeking ever greater safety, environmental, security, and nonproliferation assurances before consenting to the construction of new nuclear energy facilities. Satisfying the demand for clean energy supplies will require nuclear energy operators to find new and innovative ways to build confidence among stakeholders. This paper discusses two related concepts which can contribute to meeting the needs of key stakeholders in cost effective and efficient ways. Structured processes and tools for assessing stakeholder needs can build trust and confidence while facilitating the 'designing-in' of information collection systems for new facilities to achieve maximum efficiency and effectiveness. Integrated approaches to monitoring facilities and managing the resulting data can provide stakeholders with continued confidence while offering operators additional facility and process information to improve performance

Reclamation of abandoned mined lands along th Upper Illinois Waterway using dredged material

Energy Technology Data Exchange (ETDEWEB)

Van Luik, A; Harrison, W

1982-01-01

Sediments were sampled and characterized from 28 actual or proposed maintenance-dredging locations in the Upper Illinois Waterway, that is, the Calumet-Sag Channel, the Des Plaines River downstream of its confluence with the Calumet-Sag Channel, and the Illinois River from the confluence of the Kankakee and Des Plaines rivers to Havana, Illinois. Sufficient data on chemical constituents and physical sediments were obtained to allow the classification of these sediments by currently applicable criteria of the Illinois Environmental Protection Agency for the identification of hazardous, persistent, and potentially hazardous wastes. By these criteria, the potential dredged materials studied were not hazardous, persistent, or potentially hazardous; they are a suitable topsoil/ reclamation medium. A study of problem abandoned surface-mined land sites (problem lands are defined as being acidic and/or sparsely vegetated) along the Illinois River showed that three sites were particularly well suited to the needs of the Corps of Engineers (COE) for a dredged material disposal/reclamation site. Thes sites were a pair of municipally owned sites in Morris, Illinois, and a small corporately owned site east of Ottawa, Illinois, and adjacent to the Illinois River. Other sites were also ranked as to suitability for COE involvement in their reclamation. Reclamation disposal was found to be an economically competitive alternative to near-source confined disposal for Upper Illinois Waterway dredged material.

Examination on establishment of safety culture for operating nuclear facilities

International Nuclear Information System (INIS)

Taniguchi, Taketoshi

1997-01-01

For safely operating nuclear power facilities, in addition to the technical countermeasures, the performance of the organizations that operate and manage them is important. In this paper, the spontaneous cooperation type management system that supported the introduction and development of nuclear power generation in electric power business is analyzed from the viewpoints of organization science and behavioral psychology, and based on the results of the investigation of the sense of value and psychological characteristics of young organization members who bear future nuclear power generation, on how to foster and establish safety culture which is called second safety principle in organizations, the subjects for hereafter are discussed from the viewpoints of respect of individuals and their integration with organizations, upbringing of talents and systematic learning. The factors which compose the safety culture are shown. The form of operating and managing the organizations are seen in first generation nuclear power generation, the similarity to Japanese type enterprise operation system, the change of the prerequisite of spontaneous cooperation type management and the difference of conscience among the generations of organization members are discussed. The above subjects for hereafter are discussed. (K.I.)

Software solutions manage the definition, operation, maintenance and configuration control of the National Ignition Facility

Energy Technology Data Exchange (ETDEWEB)

Dobson, D; Churby, A; Krieger, E; Maloy, D; White, K

2011-07-25

The National Ignition Facility (NIF) is the world's largest laser composed of millions of individual parts brought together to form one massive assembly. Maintaining control of the physical definition, status and configuration of this structure is a monumental undertaking yet critical to the validity of the shot experiment data and the safe operation of the facility. The NIF business application suite of software provides the means to effectively manage the definition, build, operation, maintenance and configuration control of all components of the National Ignition Facility. State of the art Computer Aided Design software applications are used to generate a virtual model and assemblies. Engineering bills of material are controlled through the Enterprise Configuration Management System. This data structure is passed to the Enterprise Resource Planning system to create a manufacturing bill of material. Specific parts are serialized then tracked along their entire lifecycle providing visibility to the location and status of optical, target and diagnostic components that are key to assessing pre-shot machine readiness. Nearly forty thousand items requiring preventive, reactive and calibration maintenance are tracked through the System Maintenance & Reliability Tracking application to ensure proper operation. Radiological tracking applications ensure proper stewardship of radiological and hazardous materials and help provide a safe working environment for NIF personnel.

Software solutions manage the definition, operation, maintenance and configuration control of the National Ignition Facility

International Nuclear Information System (INIS)

Dobson, D.; Churby, A.; Krieger, E.; Maloy, D.; White, K.

2011-01-01

The National Ignition Facility (NIF) is the world's largest laser composed of millions of individual parts brought together to form one massive assembly. Maintaining control of the physical definition, status and configuration of this structure is a monumental undertaking yet critical to the validity of the shot experiment data and the safe operation of the facility. The NIF business application suite of software provides the means to effectively manage the definition, build, operation, maintenance and configuration control of all components of the National Ignition Facility. State of the art Computer Aided Design software applications are used to generate a virtual model and assemblies. Engineering bills of material are controlled through the Enterprise Configuration Management System. This data structure is passed to the Enterprise Resource Planning system to create a manufacturing bill of material. Specific parts are serialized then tracked along their entire lifecycle providing visibility to the location and status of optical, target and diagnostic components that are key to assessing pre-shot machine readiness. Nearly forty thousand items requiring preventive, reactive and calibration maintenance are tracked through the System Maintenance and Reliability Tracking application to ensure proper operation. Radiological tracking applications ensure proper stewardship of radiological and hazardous materials and help provide a safe working environment for NIF personnel.

Digital 3D reconstruction of Agustin de Betancourt's historical heritage: the machine for cutting grass in waterways

Directory of Open Access Journals (Sweden)

José Ignacio Rojas-Sola

2016-05-01

Full Text Available Agustín de Betancourt y Molina was one of the most distinguished engineers of the eighteenth and nineteenth centuries with numerous contributions to various fields of engineering, including civil engineering. This research shows the process followed in the documentation of the cultural heritage of that Canary engineer, especially in the geometric documentation of a machine for cutting grass in waterways presented in England in 1795 after three years researching on theory of machines. The baseline information has been recovered from the Canary Orotava Foundation of History of Science who has spent years collecting information about the Project Betancourt, in particular, planimetric information as well as a small report on its operation and description of parts of machine. From this information, we have constructed a three dimensional (3D model using CAD techniques with the use of Solid Edge ST7 parametric software, which has enabled the team to create the 3D model as well as different detail plans and exploded views.

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.

High-risk facilities. Emergency management in nuclear, chemical and hazardous waste facilities

International Nuclear Information System (INIS)

Kloepfer, Michael

2012-01-01

The book on emergency management in high-risk facilities covers the following topics: Change in the nuclear policy, risk management of high-risk facilities as a constitutional problem - emergency management in nuclear facilities, operational mechanisms of risk control in nuclear facilities, regulatory surveillance responsibilities for nuclear facilities, operational mechanism of the risk control in chemical plants, regulatory surveillance responsibilities for chemical facilities, operational mechanisms of the risk control in hazardous waste facilities, regulatory surveillance responsibilities for hazardous waste facilities, civil law consequences in case of accidents in high-risk facilities, criminal prosecution in case of accidents in high-risk facilities, safety margins as site risk for emission protection facilities, national emergency management - strategic emergency management structures, warning and self-protection of the public in case of CBRN hazards including aspects of the psych-social emergency management.

Nuclear safety and radiation protection report of EdF's Tricastin operational hot base nuclear facilities (BCOT) - 2010

International Nuclear Information System (INIS)

2011-06-01

This safety report was established under the article 21 of the French law no. 2006-686 of June 13, 2006 relative to nuclear safety and information transparency. It presents, first, the Tricastin operational hot base facility (INB no. 157, Bollene, Vaucluse (FR)), a nuclear workshop for storage and maintenance and qualification operations on some EdF equipments. Then, the nuclear safety and radiation protection measures taken regarding the facility are reviewed: nuclear safety definition, radiation protection of intervening parties, safety and radiation protection improvement paths, crisis management, external and internal controls, technical situation of facilities, administrative procedures in progress. The incidents and accidents which occurred in 2010, if some, are reported as well as the effluents discharge in the environment. Finally, The radioactive materials and wastes generated by the facility is presented and sorted by type of waste, quantities and type of conditioning. The document concludes with a glossary and a list of recommendations from the Committees for health, safety and working conditions. (J.S.)

Augmented reality in the slaughterhouse - A future operation facility?

Directory of Open Access Journals (Sweden)

Lars Bager Christensen

2016-05-01

Full Text Available The present case study sums up the results of an initial attempt to adapt the emerging technology of Augmented Reality (AR to support routine operations performed in Danish slaughterhouse facilities. Our aim is to reveal the applicability of off-the-shelf components and programming platforms to the trimming and boning process for pork bellies. The AR technology has demonstrated lucrative applications in industrial QA procedures and even farm management applications (Wu, Xiao & Guo, 2013 appear to benefit from applying the technology. With the ever-increasing turnover of labour in the meat industry, we investigate here the application of AR-assisted production procedures as a potential management tool and support tool to assist a novice operator in a specific trimming operation. The case study concerns the trimming and cutting of pork bellies, a widely used and versatile procedure in the Danish pork meat industry. Many similar belly products made from similar raw materials are exported to specific customers and markets. Due to biological variability between pigs, final products are produced with variability in yield, despite the fact that the final product qualities are similar. The best management option is to use the correct raw material for each product, thus generating fewer by-products and increasing the volume/weight of the final product. The application of AR to the cutting operation appears to increase the production yield; however, the operators need training in order to benefit fully from the efficiency and capacity of the application rather than adopting the standard procedure of oral communication of instructions.

Risk management for operations of the Los Alamos critical experiments facility

International Nuclear Information System (INIS)

Paternoster, R.; Butterfield, K.

1998-01-01

The Los Alamos Critical Experiments Facility (LACEF) currently operates two burst reactors (Godiva-IV and Skua), one solution assembly (SHEBA 2--Solution high-Energy Burst Assembly), two fast-spectrum benchmark assemblies (Flattop and Big Ten), and five general-purpose remote assembly machines which may be configured with nuclear materials and assembled by remote control. SNM storage vaults support these and other operations at the site. With this diverse set of operations, several approaches are possible in the analysis and management of risk. The most conservative approach would be to write a safety analysis report (SAR) for each assembly and experiment. A more cost-effective approach is to analyze the probability and consequences of several classes of operations representative of operations on each critical assembly machine and envelope the bounding case accidents. Although the neutron physics of these machines varies widely, the operations performed at LACEF fall into four operational modes: steady-state mode, approach-to-critical mode, prompt burst mode, and nuclear material operations which can include critical assembly fuel loading. The operational sequences of each mode are very nearly the same, whether operated on one assembly machine or another. The use of an envelope approach to accident analysis is facilitated by the use of classes of operations and the use of bounding case consequence analysis. A simple fault tree analysis of operational modes helps resolve which operations are sensitive to human error and which are initiated by hardware of software failures. Where possible, these errors and failures are blocked by TSR LCOs

Operational experience in the non-destructive assay of fissile material in General Electric's nuclear fuel fabrication facility

International Nuclear Information System (INIS)

Stewart, J.P.

1976-01-01

Operational experience in the non-destructive assay of fissile material in a variety of forms and containers and incorporation of the assay devices into the accountability measurement system for General Electric's Wilmington Fuel Fabrication Facility measurement control programme is detailed. Description of the purpose and related operational requirements of each non-destructive assay system is also included. In addition, the accountability data acquisition and processing system is described in relation to its interaction with the various non-destructive assay devices and scales used for accountability purposes within the facility. (author)

AMS data production facilities at science operations center at CERN

Science.gov (United States)

Choutko, V.; Egorov, A.; Eline, A.; Shan, B.

2017-10-01

The Alpha Magnetic Spectrometer (AMS) is a high energy physics experiment on the board of the International Space Station (ISS). This paper presents the hardware and software facilities of Science Operation Center (SOC) at CERN. Data Production is built around production server - a scalable distributed service which links together a set of different programming modules for science data transformation and reconstruction. The server has the capacity to manage 1000 paralleled job producers, i.e. up to 32K logical processors. Monitoring and management tool with Production GUI is also described.

Facility transition instruction

International Nuclear Information System (INIS)

Morton, M.R.

1997-01-01

The Bechtel Hanford, Inc. facility transition instruction was initiated in response to the need for a common, streamlined process for facility transitions and to capture the knowledge and experience that has accumulated over the last few years. The instruction serves as an educational resource and defines the process for transitioning facilities to long-term surveillance and maintenance (S and M). Generally, these facilities do not have identified operations missions and must be transitioned from operational status to a safe and stable configuration for long-term S and M. The instruction can be applied to a wide range of facilities--from process canyon complexes like the Plutonium Uranium Extraction Facility or B Plant, to stand-alone, lower hazard facilities like the 242B/BL facility. The facility transition process is implemented (under the direction of the US Department of Energy, Richland Operations Office [RL] Assistant Manager-Environmental) by Bechtel Hanford, Inc. management, with input and interaction with the appropriate RL division and Hanford site contractors as noted in the instruction. The application of the steps identified herein and the early participation of all organizations involved are expected to provide a cost-effective, safe, and smooth transition from operational status to deactivation and S and M for a wide range of Hanford Site facilities

Thermal operations conditions in a national waste terminal storage facility

International Nuclear Information System (INIS)

1976-09-01

Some of the major technical questions associated with the burial of radioactive high-level wastes in geologic formations are related to the thermal environments generated by the waste and the impact of this dissipated heat on the surrounding environment. The design of a high level waste storage facility must be such that the temperature variations that occur do not adversely affect operating personnel and equipment. The objective of this investigation was to assist OWI by determining the thermal environment that would be experienced by personnel and equipment in a waste storage facility in salt. Particular emphasis was placed on determining the maximum floor and air temperatures with and without ventilation in the first 30 years after waste emplacement. The assumed facility design differs somewhat from those previously analyzed and reported, but many of the previous parametric surveys are useful for comparison. In this investigation a number of 2-dimensional and 3-dimensional simulations of the heat flow in a repository have been performed on the HEATING5 and TRUMP heat transfer codes. The representative repository constructs used in the simulations are described, as well as the computational models and computer codes. Results of the simulations are presented and discussed. Comparisons are made between the recent results and those from previous analyses. Finally, a summary of study limitations, comparisons, and conclusions is given

Automatic Management Systems for the Operation of the Cryogenic Test Facilities for LHC Series Superconducting Magnets

CERN Document Server

Tovar-Gonzalez, A; Herblin, L; Lamboy, J P; Vullierme, B

2006-01-01

Prior to their final preparation before installation in the tunnel, the ~1800 series superconducting magnets of the LHC machine shall be entirely tested at reception on modular test facilities. The operation 24 hours per day of the cryogenic test facilities is conducted in turn by 3-operator teams, assisted in real time by the use of the Test Bench Priorities Handling System, a process control application enforcing the optimum use of cryogenic utilities and of the "Tasks Tracking System", a web-based e-traveller application handling 12 parallel 38-task test sequences. This paper describes how such computer-based management systems can be used to optimize operation of concurrent test benches within technical boundary conditions given by the cryogenic capacity, and how they can be used to study the efficiency of the automatic steering of all individual cryogenic sub-systems. Finally, this paper presents the overall performance of the cryomagnet test station for the first complete year of operation at high produ...

Description and Operational Experiences of the Engineering Test Facility - Helium Technology (ETF-HT)

International Nuclear Information System (INIS)

Zhang Zuoyi; Yang Mingde; Bo Hanliang; Duan Riqqiang; Zhu Hongye

2014-01-01

This paper presents the configuration of the Engineering Test Facility - Helium Technology (ETF-HT) and the information of its key components and subsystems, which is located in the Changping campus of Tsinghua University. The ETF-HT facility began to be constructed in Jan. 2009. The main objective of the facility is to test and verify the thermo-hydraulic performance of one full-sized modular unit of HTR-PM helically coiled SG assembly. In the ETF-HT facility, electricity energy is used to heat the loop helium, centrifugal blower is used to circulate the helium medium, and the heat sink is one would-tested SG module. Up to now, except for the tested SG module, preheater and hot gas duct under way of construction, the other components has been installed in situ. Via the temporary connection of the installed components, the preliminary operation of the loop has been carried out to test its performances as can be done, which include the loop leak tightness, blower pneumatic performance and electrical heater at partial thermal load. (author)

Assessment of Hydraulic Conditions Supporting the Recruitment of Asian Carp in the Illinois Waterway - A Case Study Using Known Spawning Events of 2015

Science.gov (United States)

Soong, D. T.; Garcia, T.; Duncker, J.; Zhu, Z.; Butler, S.; Diana, M.; Wahl, D.

2016-12-01

The upstream movement of Asian carp in the Illinois Waterway poses a potential threat to the Great Lakes. If established within the Great Lakes, Asian carp may disrupt the food web and harm the ecosystems of the Great Lakes. Understanding the Asian carp reproduction, including the timing and locations of adult spawning and the transport and dispersal of eggs and larvae, is essential information for managing the Asian carp population in the Illinois Waterway. The Fluvial Egg Drift Simulator (FluEgg) model, a Lagrangian particle tracking model, has been used to study the transport and dispersal of eggs and larvae. The FluEgg model inputs are water temperature and hydraulic properties. At present, field measured or modeled hydraulics from steady-state simulations have been used in FluEgg modeling and the applications have shown useful results for evaluating Asian carp reproduction in the Illinois Waterway. However, there is a need to use data based on more representative time-variable hydraulic conditions from spawning to the time larvae reach the Gas Bladder Inflation Stage (GBI). The GBI stage is critical because that is the stage when the young fish seek nursery habitat. In June 2015, Asian carp spawning was observed at two locations along the Illinois Waterway, one below Starved Rock Lock and Dam near Utica, and the one in the La Grange Pool near Havana, Illinois. This study analyzes how hydraulic modeling can improve the predictability of the FluEgg model. An unsteady HEC-RAS hydraulic model of the Illinois Waterway from Brandon Road Lock and Dam to Grafton, Illinois was used to reproduce the June 2015 flood event. Hydraulic data from HEC-RAS modeling, including predicted spatial and temporal discharge, water depth, and shear velocity; and measured water temperature data were used as input to the FluEgg model. FluEgg simulation results illustrate the downstream drifting of eggs and larvae until reaching the GBI stage. These simulation results can be analyzed

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

MagLev Cobra: Test Facilities and Operational Experiments

International Nuclear Information System (INIS)

Sotelo, G G; Dias, D H J N; De Oliveira, R A H; Ferreira, A C; De Andrade, R Jr; Stephan, R M

2014-01-01

The superconducting MagLev technology for transportation systems is becoming mature due to the research and developing effort of recent years. The Brazilian project, named MagLev-Cobra, started in 1998. It has the goal of developing a superconducting levitation vehicle for urban areas. The adopted levitation technology is based on the diamagnetic and the flux pinning properties of YBa 2 Cu 3 O 7−δ (YBCO) bulk blocks in the interaction with Nd-Fe-B permanent magnets. A laboratory test facility with permanent magnet guideway, linear induction motor and one vehicle module is been built to investigate its operation. The MagLev-Cobra project state of the art is presented in the present paper, describing some construction details of the new test line with 200 m.

Diamond Ordinance Radiation Facility (DORF) reactor operating experiences

International Nuclear Information System (INIS)

Gieseler, Walter

1970-01-01

The Diamond Ordnance Radiation Facility Mark F Reactor is described and some of the problems encountered with its operation are discussed. In a period from reactor startup in September 1961 to June 1964, when the aluminum-clad core was changed to a stainless-steel clad core, a total of 30 fuel elements were removed from reactor service because of excessive growth. One leaking fuel element was detected during the lifetime of the aluminum- clad core. In June 1964, the core was changed to the stainless-steel-clad high hydride fuel elements. Since the installation of the stainless-steel-clad fuel element core, there has been a gradual decline of excess reactivity. Various theories were discussed as the cause but the investigations have resulted in no definitive conclusion that could account for the total reactivity loss

Qualification requirements and training programs for nonreactor nuclear facility personnel in the Operations Division of the Oak Ridge National Laboratory

Energy Technology Data Exchange (ETDEWEB)

Preston, E.L.; Culbert, W.H.; Baldwin, M.E.; McCormack, K.E.; Rivera, A.L.; Setaro, J.A.

1985-11-01

This document describes the program for training, retraining, and qualification of nonreactor nuclear operators in the Operations Division of the Oak Ridge National Laboratory. The objective of the program is to provide the Operators and Supervisors of nuclear facilities the knowledge and skills needed to perform assigned duties in a safe and efficient manner and to comply with US Department of Energy Order 5480.1A Chapter V. This order requires DOE nuclear facilities to maintain formal training programs for their operating staff and documentation of that training.

Qualification requirements and training programs for nonreactor nuclear facility personnel in the Operations Division of the Oak Ridge National Laboratory

International Nuclear Information System (INIS)

Preston, E.L.; Culbert, W.H.; Baldwin, M.E.; McCormack, K.E.; Rivera, A.L.; Setaro, J.A.

1985-11-01

This document describes the program for training, retraining, and qualification of nonreactor nuclear operators in the Operations Division of the Oak Ridge National Laboratory. The objective of the program is to provide the Operators and Supervisors of nuclear facilities the knowledge and skills needed to perform assigned duties in a safe and efficient manner and to comply with US Department of Energy Order 5480.1A Chapter V. This order requires DOE nuclear facilities to maintain formal training programs for their operating staff and documentation of that training

The analysis of inland water transport on technically developed Polish section of the E70 waterway using GIS tools in the years 2005-2014

Science.gov (United States)

Rabant, Hubert; Szatten, Dawid; Nadolny, Grzegorz

2017-11-01

The article presents the characteristics of changes in the spatial extent of transport on the hydrotechnically developed section of the E70 waterway in Poland using methods and tools of geographic information systems (GIS). The results of the analyzes show the conditions for vessel traffic, their type and volatility in the years 2005-2014. The methods made it possible to analyze the spatial determinants of navigation. The obtained results were referred to the current state and prospects for development of Polish waterways and indicated that the applied tools have a great application role in the research on their logistics and development.

Atmospheric Radiation Measurement Climate Research Facility Operations Quarterly Report October 1-December 31, 2016

Energy Technology Data Exchange (ETDEWEB)

Voyles, Jimmy [Pacific Northwest National Lab. (PNNL), Richland, WA (United States)

2017-01-01

Individual datastreams from instrumentation at the U.S. Department of Energy (DOE) Atmospheric Radiation Measurement (ARM) Climate Research Facility fixed and mobile research observatories (sites) are collected and routed to the ARM Data Center (ADC). The Data Management Facility (DMF), a component of the ADC, executes datastream processing in near-real time. Processed data are then delivered approximately daily to the ARM Data Archive, also a component of the ADC, where they are made freely available to the research community. For each instrument, ARM calculates the ratio of the actual number of processed data records received daily at the ARM Data Archive to the expected number of data records. DOE requires national user facilities to report time-based operating data.

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

Longitudinal dispersion of radioactive substances in Federal waterways

Energy Technology Data Exchange (ETDEWEB)

Krause, W.J. [Bundesanstalt fuer Gewaesserkunde (BfG), Koblenz (Germany); Speer, W.; Luellwitz, T.; Cremer, M.; Tolksdorf, W.

2007-08-15

In the context of radioactivity monitoring in German Federal Waterways (BWStr) by the Federal Institute of Hydrology (BfG) according to the Precautionary Radiation Protection Act (StrVG), the prediction of the dispersion of radioactive substances in water is one of the key tasks. The aim is the forecasting of the longitudinal dispersion of concentrations of soluble hazardous substances in flowing water. These predictions are based on the so-called dispersion tests with tritium as a tracer that the BfG has performed since 1980. Characteristic parameters like discharge-dependent flow velocities, dispersion and elimination constants related to emission sources or selected river sections are determined. They will serve as basis for a mathematical model to forecast discharge-dependent flow velocities, expected impact times, concentration maxima, and the duration of critical increases in concentrations. In the following, the results obtained till now from three investigation campaigns on the River Weser and its source rivers Werra and Fulda are described. (orig.)

First operational tests of an oxycoal hot gas cleaning facility; Erste Betriebstests einer Oxycoal-Heissgasreinigung

Energy Technology Data Exchange (ETDEWEB)

Kellermann, A.; Habermehl, M.; Foerster, M.; Kneer, R. [RWTH Aachen University (Germany). Lehrstuhl fuer Waerme- und Stoffuebertragung

2009-07-01

An oxyfuel power plant process using a ceramic high temperature membrane for oxygen supply is investigated within the scope of the OXYCOAL-AC project at RWTH Aachen Uni-versity. Implementing the membrane requires a clean gas at a temperature of 850 C. There-fore a hot gas cleaning facility based on porous ceramic candle filters is used, which is state-of-the-art for the gas cleaning of synthesis gas or for flue gas cleaning in pressurised fluid-ised bed furnaces. However, these applications operate at lower temperatures and in a sig-nificantly different atmosphere. Thus, experiences for dust removal at high temperatures in oxyfuel atmoshere are not available. Experiments with a hot gas cleaning facility were con-ducted at the experimental combustion plant of the Institute of Heat and Mass Transfer, us-ing different candle filter materials. The flue gas was provided by a coal fired 100 kW{sub th} oxy-fuel furnace. The operational behaviour of the filtration facility, the adhesion and dedusting properties of the filter cake were investigated. (orig.)

The optimum operating conditions of the phased double-rotor facility at the et-R R-1 reactor. Vol. 2

Energy Technology Data Exchange (ETDEWEB)

Naguib, K; Habib, N; Kilany, M; Adib, M [Reactor and Neutron Physics Department, Nuclear Research Center, AEA., Cairo (Egypt); Wahba, M [Dept. of Engineering Physics and Mathematics, Faculty of Engineering, Ain Shams University, Cairo (Egypt)

1996-03-01

The pulsed neutron polyenergetic thermal beam at ET-R R-1 is produced by a phased double-rotor facility. One of the rotors has two diametrically opposite curved slots, while the second is designed to operate as a rotating collimator, the dimensions of the phased rotating collimator are selected to match the curved slot rotor. The calculated collimator transmissions at different operating conditions are found to be in good agreement with the experimental ones. The optimum operating conditions of double-rotor facility are deduced. The calculations were carried out using a computer programme RCOL. The RCOL was designed in Fortran-77 to operate on PCs. 6 figs.

The optimum operating conditions of the phased double-rotor facility at the et-R R-1 reactor. Vol. 2

International Nuclear Information System (INIS)

Naguib, K.; Habib, N.; Kilany, M.; Adib, M.; Wahba, M.

1996-01-01

The pulsed neutron polyenergetic thermal beam at ET-R R-1 is produced by a phased double-rotor facility. One of the rotors has two diametrically opposite curved slots, while the second is designed to operate as a rotating collimator, the dimensions of the phased rotating collimator are selected to match the curved slot rotor. The calculated collimator transmissions at different operating conditions are found to be in good agreement with the experimental ones. The optimum operating conditions of double-rotor facility are deduced. The calculations were carried out using a computer programme RCOL. The RCOL was designed in Fortran-77 to operate on PCs. 6 figs

Design of a system for examinations of the history of operation of selected WWER primary circuit facilities. Stage I: requirements

International Nuclear Information System (INIS)

Brumovsky, M.; Kraus, V.; Ruscak, M.; Vejvoda, S.

1994-01-01

A survey is presented of data required for the evaluation and control of nuclear power plant aging and service life, and a data acquisition and record-keeping system is proposed. The data fall in 3 classes: (i) information on the initial status, including design data and status data at the beginning of the operational lifetime of the facilities; (ii) data on the history of operation, including operating conditions at the level of the corresponding system and facility, as well as operating test and failure data; and (iii) data on the history of maintenance, including data on the monitoring of the facility condition and on maintenance. Basic information requirements for the evaluation of the service life of the pressure vessel, steam generator, pressurizer, and main circulation pipe are given; the way of processing this information is outlined. (J.B.). 2 figs

Potential applications of artificial intelligence in computer-based management systems for mixed waste incinerator facility operation

International Nuclear Information System (INIS)

Rivera, A.L.; Singh, S.P.N.; Ferrada, J.J.

1991-01-01

The Department of Energy/Oak Ridge Field Office (DOE/OR) operates a mixed waste incinerator facility at the Oak Ridge K-25 Site, designed for the thermal treatment of incinerable liquid, sludge, and solid waste regulated under the Toxic Substances Control Act (TSCA) and the Resource Conversion and Recovery Act (RCRA). Operation of the TSCA Incinerator is highly constrained as a result of the regulatory, institutional, technical, and resource availability requirements. This presents an opportunity for applying computer technology as a technical resource for mixed waste incinerator operation to facilitate promoting and sustaining a continuous performance improvement process while demonstrating compliance. This paper describes mixed waste incinerator facility performance-oriented tasks that could be assisted by Artificial Intelligence (AI) and the requirements for AI tools that would implement these algorithms in a computer-based system. 4 figs., 1 tab

Nuclear facilities of EdF's operational hot base of Tricastin. 2009 annual report

International Nuclear Information System (INIS)

2010-01-01

This annual report is established on account of article 21 of the 2006-686 French law from June 13, 2006, relative to the transparency and safety in the nuclear domain. It describes, first, the nuclear facilities of the EdF operational hot base of Tricastin, then, the measures taken to ensure their safety (personnel radioprotection, actions implemented for nuclear safety improvement, organisation in crisis situation, external and internal controls, technical assessment of the facilities), and finally the procedures of management of radioactive wastes. A glossary and the viewpoint of the Committee of Hygiene, safety and working conditions about the content of the document conclude the report. (J.S.)

An operator training simulator based on interactive virtual teleoperation: nuclear facilities maintenance applications

International Nuclear Information System (INIS)

Kim, Ki Ho; Kim, Seung Ho

1997-01-01

Remote manipulation in nuclear hazardous environment is very often complex and difficult to operate and requires excessively careful preparation. Remote slave manipulators for unstructured work are manually controlled by a human operator. Small errors made by the operator via the master manipulator during operation can cause the slave to be surffered from excessive forces and result in considerable damages to the slave iteself and its environment. In this paper, we present a prototype of an operator training simulator for use in nuclear facilities maintenance applications, as part of the ongoing Nuclear Robotics Development Program at Korea Atomic Energy Research Institute (KAERI). The operator training simulator provides a means by which, in virtual task simulation, the operator can try out and train for expected remote tasks that the real slave manipulator will perform in advance. The operator interacts with both the virtual slave and task environment through the real master. Virtual interaction force feedback is provided to the operator. We also describe a man-in-the loop control scheme to realize bilateral force reflection in virtual teleoperation

Modifications for water management guidance based on an assessment of swimming pool water consumption of an operational facility in the UK

OpenAIRE

Lewis, L; Chew, J; Woodley, I; Colbourne, J; Pond, K

2015-01-01

Water use is a significant operational cost factor for large swimming pool facilities, however it has been overshadowed by the recent focus on energy consumption and carbon emissions. Currently it is difficult for operators to make decisions in relation to water efficiency due to the lack of information on the relationship between pool operation and water use. This study has started to address this issue by reviewing water use at a fully operational facility. The analysis of the consumption d...

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

RCRA facility investigation/corrective measures study work plan for the 100-HR-1 operable unit, Hanford Site, Richland, Washington

International Nuclear Information System (INIS)

1992-09-01

Four areas of the Hanford Site (the 100, 200, 300, and 1100 Areas) have been included on the US. Environmental Protection Agency's (EPA's) National Priorities List (NPL) under the Comprehensive Environmental Response, Compensation, and Liability Act of 1980 (CERCLA). Under the Hanford Federal Facility Agreement and Consent Order, signed by the Washington State Department of Ecology (Ecology), EPA, and the US Department of Energy (DOE), more than 1,000 inactive waste disposal and unplanned release sites on the Hanford Site have been grouped into a number of source and groundwater operable units. These operable units contain contamination in the form of hazardous waste, radioactive/hazardous mixed waste, and other CERCLA hazardous substances. This work plan and the attached supporting project plans establish the operable unit setting and the objectives, procedures, tasks, and schedule for conducting the RCRA facility investigation/corrective measures study (RFI/CMS) for the 100-HR-1 source operable unit. Source operable units include facilities and unplanned release sites that are potential sources of contamination. The 100-HR-3 operable unit underlies the D/DR and H Areas, the 600 Area between them, and the six source operable units these areas contain. The 100-HR-3 operable unit includes all contamination found in the aquifer soils and water within its boundary. Separate work plans have been initiated for the 100-HR-3 groundwater operable unit (DOE-RL 1992a) and the 100-DR-1 (DOE-RL 1992b) source operable units

Irradiation Facilities at CERN

CERN Document Server

Gkotse, Blerina; Carbonez, Pierre; Danzeca, Salvatore; Fabich, Adrian; Garcia, Alia, Ruben; Glaser, Maurice; Gorine, Georgi; Jaekel, Martin, Richard; Mateu,Suau, Isidre; Pezzullo, Giuseppe; Pozzi, Fabio; Ravotti, Federico; Silari, Marco; Tali, Maris

2017-01-01

CERN provides unique irradiation facilities for applications in many scientific fields. This paper summarizes the facilities currently operating for proton, gamma, mixed-field and electron irradiations, including their main usage, characteristics and information about their operation. The new CERN irradiation facilities database is also presented. This includes not only CERN facilities but also irradiation facilities available worldwide.

Remote Operation and Maintenance Demonstration Facility at the Oak Ridge National Laboratory

International Nuclear Information System (INIS)

Burgess, T.W.

1986-01-01

The Remote Operation and Maintenance Demonstration (ROMD) Facility at the Oak Ridge National Laboratory has been developed by the Consolidated Fuel Reprocessing Program to demonstrate remote handling concepts on advanced nuclear fuel reprocessing equipment and for other programs of national interest. The ROMD facility is a large-volume high-bay area that encloses a complete, technologically advanced remote maintenance system and full-scale development reprocessing equipment. The maintenance system consists of a full complement of teleoperated manipulators, manipulator transport systems, and overhead hoists that provide the capability of performing a large variety of remote handling tasks. This system has been used to demonstrate remote manipulation techniques for the US Department of Energy (DOE), the Power Reactor and Nuclear Fuels Development Corporation of Japan, the US Navy, and the National Aeronautics and Space Administration. Extensive tests of manipulative systems and remote maintainability of process equipment have been performed. This paper describes the ROMD facility and key remote maintenance equipment and presents a summary of major experimental activities. 7 refs., 6 figs

The TRIUMF thermal neutron facility as planned for operation by 1978

International Nuclear Information System (INIS)

Arrott, A.S.; Templeton, T.L.; Thorson, I.M.; Blaby, R.E.; Burgerjon, J.J.