77 FR 76451 - Designation for the West Sacramento, CA; Frankfort, IN; and Richmond, VA Areas.

Science.gov (United States)

2012-12-28

... DEPARTMENT OF AGRICULTURE Grain Inspection, Packers and Stockyards Administration Designation for the West Sacramento, CA; Frankfort, IN; and Richmond, VA Areas. AGENCY: Grain Inspection, Packers and...-Agri West Sacramento, CA(916) 374-9700.. 1/1/2013 12/31/2015 Frankfort Frankfort, IN(765) 258-3624...

International Facility for Food Irradiation Technology

International Nuclear Information System (INIS)

Farkas, J.

1982-01-01

The International Facility for Food Irradiation Technology (IFFIT) was set up in November 1978 for a period of five years at the Pilot Plant for Food Irradiation, Wageningen, The Netherlands under an Agreement between the FAO, IAEA and the Ministry of Agriculture and Fisheries of the Government of the Netherlands. Under this Agreement, the irradiation facilities, office space and services of the Pilot Plant for Food Irradiation are put at IFFIT's disposal. Also the closely located Research Foundation, ITAL, provides certain facilities and laboratory services within the terms of the Agreement. The FAO and IAEA contribute US-Dollar 25,000. Annually for the duration of IFFIT. (orig.) [de

The NASA Lewis Research Center Internal Fluid Mechanics Facility

Science.gov (United States)

Porro, A. R.; Hingst, W. R.; Wasserbauer, C. A.; Andrews, T. B.

1991-01-01

An experimental facility specifically designed to investigate internal fluid duct flows is described. It is built in a modular fashion so that a variety of internal flow test hardware can be installed in the facility with minimal facility reconfiguration. The facility and test hardware interfaces are discussed along with design constraints of future test hardware. The plenum flow conditioning approach is also detailed. Available instrumentation and data acquisition capabilities are discussed. The incoming flow quality was documented over the current facility operating range. The incoming flow produces well behaved turbulent boundary layers with a uniform core. For the calibration duct used, the boundary layers approached 10 percent of the duct radius. Freestream turbulence levels at the various operating conditions varied from 0.64 to 0.69 percent of the average freestream velocity.

Feasibility study for the United Heckathorn Superfund Site, Richmond, California

Energy Technology Data Exchange (ETDEWEB)

Lincoff, A.H. [US Environmental Protection Agency, San Francisco, CA (United States). Region IX; Costan, G.P.; Montgomery, M.S.; White, P.J. [Pacific Northwest Lab., Richland, WA (United States)

1994-07-01

The United Heckathom Superfund Site in Richmond, California, was used to formulate pesticides from approximately 1947 to 1966. Soils at the site and sediments in the harbor were contaminated with various chlorinated pesticides, primarily DDT, as a result of these activities. The US Environmental Protection Agency listed the site on the Superfund National Priorities List in 1990. This document is part of the Remedial Investigation and Feasibility Study phase of the Superfund response, which will provide the basis for selection of a final remedy that will protect human health and the environment and achieve compliance with federal and state envirorunental laws.

Feasibility study for the United Heckathorn Superfund Site, Richmond, California

International Nuclear Information System (INIS)

Lincoff, A.H.

1994-07-01

The United Heckathom Superfund Site in Richmond, California, was used to formulate pesticides from approximately 1947 to 1966. Soils at the site and sediments in the harbor were contaminated with various chlorinated pesticides, primarily DDT, as a result of these activities. The US Environmental Protection Agency listed the site on the Superfund National Priorities List in 1990. This document is part of the Remedial Investigation and Feasibility Study phase of the Superfund response, which will provide the basis for selection of a final remedy that will protect human health and the environment and achieve compliance with federal and state envirorunental laws

RICHMOND CROWN - FOR RESTORATION OF BADLY MUTILATED POSTERIOR TEETH : A CASE REPORT

OpenAIRE

Yadav; Swetha

2015-01-01

Restoration of badly broken endodontically treated teeth is a common problem in restorative dentistry. Such teeth often require additional support from the root canal by means of a post and core restoration. In cases where tooth structure is significantly lost full coverage restorations for posterior teeth are necessary to achieve proper tooth form and function. Badly broken teeth with minimal or no crown structure require added retention and support. The Richmond crown can be a good treatmen...

Solutions of differential equations with regular coefficients by the methods of Richmond and Runge-Kutta

Science.gov (United States)

Cockrell, C. R.

1989-01-01

Numerical solutions of the differential equation which describe the electric field within an inhomogeneous layer of permittivity, upon which a perpendicularly-polarized plane wave is incident, are considered. Richmond's method and the Runge-Kutta method are compared for linear and exponential profiles of permittivities. These two approximate solutions are also compared with the exact solutions.

International physical protection self-assessment tool for chemical facilities.

Energy Technology Data Exchange (ETDEWEB)

Tewell, Craig R.; Burdick, Brent A.; Stiles, Linda L.; Lindgren, Eric Richard

2010-09-01

This report is the final report for Laboratory Directed Research and Development (LDRD) Project No.130746, International Physical Protection Self-Assessment Tool for Chemical Facilities. The goal of the project was to develop an exportable, low-cost, computer-based risk assessment tool for small to medium size chemical facilities. The tool would assist facilities in improving their physical protection posture, while protecting their proprietary information. In FY2009, the project team proposed a comprehensive evaluation of safety and security regulations in the target geographical area, Southeast Asia. This approach was later modified and the team worked instead on developing a methodology for identifying potential targets at chemical facilities. Milestones proposed for FY2010 included characterizing the international/regional regulatory framework, finalizing the target identification and consequence analysis methodology, and developing, reviewing, and piloting the software tool. The project team accomplished the initial goal of developing potential target categories for chemical facilities; however, the additional milestones proposed for FY2010 were not pursued and the LDRD funding therefore was redirected.

78 FR 63963 - Foreign-Trade Zone 1 and 111-New York, New York; Application for Merger and Reorganization Under...

Science.gov (United States)

2013-10-25

... Terminal Facility and Port Ivory Factory, North Washington/ Western Avenues and Richmond Terrace/Western... (.5 acres)--Malca Amit, 153-66 Rockaway Boulevard, Jamaica; and, Site 5 (.57 acres)--World Diamond.../Newark and John F. Kennedy International Airport Customs and Border Protection ports of entry. The...

12 CFR 204.8 - International banking facilities.

Science.gov (United States)

2010-01-01

... RESERVE REQUIREMENTS OF DEPOSITORY INSTITUTIONS (REGULATION D) § 204.8 International banking facilities... reserve requirements. An institution that is subject to the reserve requirements of this part is not... to reserve requirements under this part or result in the revocation of the institution's ability to...

Ecological evaluation of proposed dredged material from Richmond Harbor

International Nuclear Information System (INIS)

Pinza, M.R.; Ward, J.A.; Mayhew, H.L.; Word, J.Q.; Niyogi, D.K.; Kohn, N.P.

1992-10-01

During the summer of 1991, Battelle/Marine Sciences Laboratory (MSL) was contracted to conduct sampling and testing of sediments proposed for dredging of Richmond Harbor, California. The MSL collected sediment cores to a depth of -40 ft MLLW (-38 ft + 2 ft overdepth) from 28 (12-in. core) and 30 (4-in. core) stations. The sediment cores were allocated to six composite samples referred to as sediment treatments, which were then subjected to physical, chemical, toxicological, and bioaccumulation testing. Physical and chemical parameters included grain size, total organic carbon (TOC), total volatile solids (TVS), oil and grease, total petroleum hydrocarbons (TPH), polynuclear aromatic hydrocarbons (PAH), chlorinated pesticides, polychlorinated biphenyis (PCBs), priority pollutant metals, and butyltins. The results from the test treatments were compared to results from five reference treatments representative of potential in-bay and offshore disposal sites

Montext of the activity and thought of Mary Richmond

Directory of Open Access Journals (Sweden)

Miguel Miranda Aranda

2011-09-01

Full Text Available In order to understand the significance of an author and his or her work, it is essential to appropriately consider the author’s social and scientific context. Mary Richmond was one of the pioneers in a new profession that emerged at the same time as the Social Sciences. She was key in the shaping of the discipline thanks both to her own research and the influence that other more established professions and major schools of thought of the time had on her work, specifically James’ and Dewey’s Pragmatic Philosophy and the theories emerging from the University of Chicago’s Departments of Sociology and Anthropology, among them including most substantially the interactionist approaches of George Herbert Mead. All of this in an environment of economic, social and political change during the Progressive Era in the United States.

Ecological evaluation of proposed dredged material from Richmond Harbor

Energy Technology Data Exchange (ETDEWEB)

Pinza, M R; Ward, J A; Mayhew, H L; Word, J Q; Niyogi, D K; Kohn, N P [Battelle/Marine Sciences Lab., Sequim, WA (United States)

1992-10-01

During the summer of 1991, Battelle/Marine Sciences Laboratory (MSL) was contracted to conduct sampling and testing of sediments proposed for dredging of Richmond Harbor, California. The MSL collected sediment cores to a depth of [minus]40 ft MLLW ([minus]38 ft + 2 ft overdepth) from 28 (12-in. core) and 30 (4-in. core) stations. The sediment cores were allocated to six composite samples referred to as sediment treatments, which were then subjected to physical, chemical, toxicological, and bioaccumulation testing. Physical and chemical parameters included grain size, total organic carbon (TOC), total volatile solids (TVS), oil and grease, total petroleum hydrocarbons (TPH), polynuclear aromatic hydrocarbons (PAH), chlorinated pesticides, polychlorinated biphenyis (PCBs), priority pollutant metals, and butyltins. The results from the test treatments were compared to results from five reference treatments representative of potential in-bay and offshore disposal sites.

Organization of the internal dosimetry in the Spanish nuclear facilities

International Nuclear Information System (INIS)

Manchena, P.; Soliet, E.

1998-01-01

From the beginning of the exploitation of the nuclear energy of Espanna, the nuclear facilities have had Services of Personal Dosimetry with the appropriate means to determine the dose. so much internal as external, of the personnel that mentioned facilities works. All the nuclear power stations use advanced systems of teams with object of detecting the radionuclides incorporation in the organism and calculation programs based on the recent recommendations of the International Commission of Radiological Protection (ICRP) for the determination of the derived doses

Third International Meeting on Next Generation Safeguards: Safeguards-by-Design at Enrichment Facilities

International Nuclear Information System (INIS)

Long, Jon D.; McGinnis, Brent R.; Morgan, James B.; Whitaker, Michael; Lockwood, Dunbar; Shipwash, Jacqueline L.

2011-01-01

The Third International Meeting on Next Generation Safeguards (NGS3) was hosted by the U.S. Department of Energy (DOE)/National Nuclear Security Administration's (NNSA) Office of Nonproliferation and International Security (NIS) in Washington, D.C. on 14-15 December 2010; this meeting focused on the Safeguards-by-Design (SBD) concept. There were approximately 100 participants from 13 countries, comprised of safeguards policy and technical experts from government and industry. Representatives also were present from the Brazilian-Argentine Agency for Accounting and Control of Nuclear Materials (ABACC), the European Atomic Energy Agency (Euratom), and the International Atomic Energy Agency (IAEA). The primary objective of this meeting was to exchange views and provide recommendations on implementation of the SBD concept for four specific nuclear fuel cycle facility types: gas centrifuge enrichment plants (GCEPs), GEN III and GEN IV reactors, aqueous reprocessing plants, and mixed oxide fuel fabrication facilities. The general and facility-specific SBD documents generated from the four working groups, which were circulated for comment among working group participants, are intended to provide a substantive contribution to the IAEA's efforts to publish SBD guidance for these specific types of nuclear facilities in the near future. The IAEA has described the SBD concept as an approach in which 'international safeguards are fully integrated into the design process of a new nuclear facility from the initial planning through design, construction, operation, and decommissioning.' As part of the Next Generation Safeguards Initiative (NGSI), the DOE is working to establish SBD as a global norm through DOE laboratory studies, international workshops, engagement with industry and the IAEA, and setting an example through its use in new nuclear facilities in the United States. This paper describes the discussion topics and final recommendations of the Enrichment Facilities Working

A proposal for a Los Alamos international facility for transmutations (LIFT)

International Nuclear Information System (INIS)

Venneri, F.; Williamson, M.A.; Li, Ning; Doolen, G.

1996-01-01

The major groups engaged in transmutation research are converging towards a common objective and similar technology. It is now possible to envision an international program of research aimed at the destruction of reactor-generated (and other) nuclear waste using a series of multipurpose experimental facilities in the near future. Los Alamos National Laboratory, as the home of the highest power LINAC and a very active transmutation technology project, is the ideal host for the first of such facilities. The next step in the international program (a facility 10 times more powerful, for engineering-scale demonstrations) could be built in Europe, where there is substantial interest in the construction of such a device in the framework of international cooperation. A series of experiments at Las Alamos could explore the key transmutation technologies. Liquid lead loops, a liquid lead spallation target, and a large size liquid lead facility with provision for irradiation, cooling and diagnostics of several types of 'transmutation assemblies', where different transmutation concepts will be tested in different media and environments, from transmutation of fission products to destruction by fission of higher actinides, to other waste management applications. The engineering-scale facility, which will follow the initial testing phase, will extend the best concepts to full scale implementation

International safeguards for fast critical facilities

International Nuclear Information System (INIS)

Gunderson, D.O.; Todd, J.L.

1978-12-01

It was concluded that practical routine inventory verification techniques can be effective in detecting protracted diversion but will not meet the seven-day timeliness criteria either for protracted or large one-time diversions. An effective international safeguards system requires a method of continuously monitoring facility activities either with instrumentation, inspectors, or a combination thereof. It was also concluded that a resident inspector is required at this type of facility because of the many nonroutine operations. However, a single inspector cannot adequately monitor all activities to assure that no diversion is taking place. The use of existing structural features and unattended monitoring at portals as well as surveillance by a resident inspector can provide an effective detection capability. A rapid special inventory verification is required following detection to verify any suspected diversion

Making the Difference for Minority Children: The Development of an Holistic Language Policy at Richmond Road School, Auckland, New Zealand.

Science.gov (United States)

May, Stephan A.

1991-01-01

Discusses the development of a holistic language policy, which recognized and included minority languages within the curriculum, at the Richmond Road school in New Zealand. The policy illustrates how the formulation and implementation of school-based curriculum development can be effectively achieved by the school. (25 references) (JL)

Ecological evaluation of proposed dredged material from Richmond Harbor Deepening Project and the intensive study of the Turning Basin

Energy Technology Data Exchange (ETDEWEB)

Pinza, M.R.; Mayhew, H.L.; Karle, L.M.; Kohn, N.P.; White, P.J.; Word, J.Q.; Michaels, L.L. [Battelle/Marine Sciences Lab., Sequim, WA (United States)

1995-06-01

Richmond Harbor is on the eastern shoreline of central San Francisco Bay and its access channels and several of the shipping berths are no longer wide or deep enough to accommodate modem deeper-draft vessels. The Water Resources Development Act of 1986 (PL99-662) authorized the US Army Corps of Engineers (USACE), San Francisco District to deepen and widen the navigation channels in Richmond Harbor. Several options for disposal of the material from this dredging project are under consideration by USACE: disposal within San Francisco Bay, at open-ocean disposal sites, or at uplands disposal sites. Purpose of this study was to conduct comprehensive evaluations, including chemical, biological, and bioaccumulation testing of sediments in selected areas of Richmond Harbor. This information was required by the Environmental Protection Agency (EPA) and USACE. Battelle/Marine Sciences Laboratory collected 20 core samples, both 4-in. and 12-in., to a project depth of -40 ft mean lower low water (MLLW) (-38 ft MLLW plus 2 ft of overdepth) using a vibratory-hammer core. These 20 field samples were combined to form five test composites plus an older bay mud (OBM) composite that were analyzed for physical/chemical parameters, biological toxicity, and tissue chemistry. Solid-phase tests were conducted with the amphipod, Rhepoxynius abronius; the clam, Macoma nasuta; and the polychaete worm, Nephtys caecoides. Suspended-particulate-phase (SPP) tests were conducted with the sanddab, Citharichthys stigmaeus; the mysid, Holmesimysis costata; and the bivalve, Mytilus galloprovincialis. Bioaccumulation of contaminants was measured in tissues of Macoma nasuta and Nereis virens. Sediments from one ocean reference sediment, and two in-bay reference sediments, were tested concurrently. Results from analysis of the five test treatments were statistically compared with the reference sediment R-OS in the first five sections of this report.

Construction of new biological research facility for internal emitter and prospect

International Nuclear Information System (INIS)

Matsuoka, Osamu

1979-01-01

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

Evaluation of the Netherlands' International Test Facility for Smart Grids

Energy Technology Data Exchange (ETDEWEB)

Palmintier, Bryan [National Renewable Energy Lab. (NREL), Golden, CO (United States); Pratt, Annabelle [National Renewable Energy Lab. (NREL), Golden, CO (United States)

2015-06-01

The Netherlands Enterprise Agency (Rijksdienst voor Ondernemend Nederland, or RVO) engaged the U.S. National Renewable Energy Laboratory (NREL) for two primary purposes: to evaluate the International Test Facility for Smart Grids (ITF) sponsored by RVO and to learn best practices for integrated test facilities from NREL's Energy Systems Integration Facility (ESIF). This report covers the ITF evaluation and is largely based on a one-week visit to the Netherlands in November 2014.

SETT facility of International Nuclear Security Academy

International Nuclear Information System (INIS)

Seo, Hyung Min

2012-01-01

After the Cold War was put to an end, the international community, especially the Western world, was concerned about Soviet nuclear materials falling into wrong hands, especially of terrorists. Later, the growing threat posed by terrorist networks such as the Taliban and al Qaeda led to a global campaign to deny such networks materials which may be used for the development of Weapons of Mass Destruction (WMD). The 9 11 attacks made a section of the international community highly apprehensive of WMD terrorism, especially its nuclear version. From this point of view, it is clear that nuclear facilities which contain nuclear materials are very attractive targets for those who have intention of nuclear terror

SETT facility of International Nuclear Security Academy

Energy Technology Data Exchange (ETDEWEB)

Seo, Hyung Min [Korea Institute of Nuclear Non-proliferation and Control, Daejeon (Korea, Republic of)

2012-05-15

After the Cold War was put to an end, the international community, especially the Western world, was concerned about Soviet nuclear materials falling into wrong hands, especially of terrorists. Later, the growing threat posed by terrorist networks such as the Taliban and al Qaeda led to a global campaign to deny such networks materials which may be used for the development of Weapons of Mass Destruction (WMD). The 9 11 attacks made a section of the international community highly apprehensive of WMD terrorism, especially its nuclear version. From this point of view, it is clear that nuclear facilities which contain nuclear materials are very attractive targets for those who have intention of nuclear terror

The international fusion materials irradiation facility

International Nuclear Information System (INIS)

Shannon, T.E.; Cozzani, F.; Crandall, D.H.; Wiffen, F.W.; Katsuta, H.; Kondo, T.; Teplyakov, V.; Zavialsky, L.

1994-01-01

It is widely agreed that the development of materials for fusion systems requires a high flux, 14 MeV neutron source. The European Union, Japan, Russia and the US have initiated the conceptual design of such a facility. This activity, under the International Energy Agency (IEA) Fusion Materials Agreement, will develop the design for an accelerator-based D-Li system. The first organizational meeting was held in June 1994. This paper describes the system to be studied and the approach to be followed to complete the conceptual design by early 1997

Design strategies for the International Space University's variable gravity research facility

Science.gov (United States)

Bailey, Sheila G.; Chiaramonte, Francis P.; Davidian, Kenneth J.

1990-01-01

A variable gravity research facility named 'Newton' was designed by 58 students from 13 countries at the International Space University's 1989 summer session at the Universite Louis Pasteur, Strasbourge, France. The project was comprehensive in scope, including a political and legal foundation for international cooperation, development and financing; technical, science and engineering issues; architectural design; plausible schedules; and operations, crew issues and maintenance. Since log-term exposure to zero gravity is known to be harmful to the human body, the main goal was to design a unique variable gravity research facility which would find a practical solution to this problem, permitting a manned mission to Mars. The facility would not duplicate other space-based facilities and would provide the flexibility for examining a number of gravity levels, including lunar and Martian gravities. Major design alternatives included a truss versus a tether based system which also involved the question of docking while spinning or despinning to dock. These design issues are described. The relative advantages or disadvantages are discussed, including comments on the necessary research and technology development required for each.

MC ampersand A policy issues for international inspections at DOE nuclear facilities

International Nuclear Information System (INIS)

Crawford, D.W.; Zack, N.R.

1994-01-01

Recent initiatives and executive decisions within the US have included an offer to place certain special nuclear materials from the former weapons stockpile under international safeguards inspections. The nuclear materials at issue are excess materials; other materials characterized as strategic reserve will not be subject to these international activities. Current Department of Energy requirements and procedures to account for and control these nuclear materials may need to be modified to accommodate these inspections. Safeguards issues, such as physical inventory frequency and verification requirements, may rise from the collateral safeguards activities in support of both domestic and international safeguards. This paper will discuss Office of Safeguards and Security policy and views on these international inspection activities at former nuclear weapons facilities, including implications for current domestic safeguards approaches currently implemented at these facilities

Dusty Plasma Physics Facility for the International Space Station

Science.gov (United States)

Goree, John; Hahn, Inseob

2015-09-01

The Dusty Plasma Physics Facility (DPPF) is an instrument planned for the International Space Station (ISS). If approved by NASA, JPL will build and operate the facility, and NASA will issue calls for proposals allowing investigators outside JPL to carry out research, public education, and outreach. Microgravity conditions on the ISS will be useful for eliminating two unwanted effects of gravity: sedimentation of dust particles to the bottom of a plasma chamber, and masking weak forces such as the ion drag force that act on dust particles. The DPPF facility is expected to support multiple scientific users. It will have a modular design, with a scientific locker, or insert, that can be exchanged without removing the entire facility. The first insert will use a parallel-plate radio-frequency discharge, polymer microspheres, and high-speed video cameras. This first insert will be designed for fundamental physics experiments. Possible future inserts could be designed for other purposes, such as engineering applications, and experimental simulations of astrophysical or geophysical conditions. The design of the facility will allow remote operation from ground-based laboratories, using telescience.

Evaluation of older bay mud sediment from Richmond Harbor, California

Energy Technology Data Exchange (ETDEWEB)

Pinza, M.R.; Mayhew, H.L.; Word, J.Q.

1996-09-01

The older, bay mud (OBM) unit predates modem man and could act as a barrier to the downward transport of contaminants from the younger bay mud (YBM) because of its hard-packed consistency. However, its chemical and biological nature have not been well characterized. Battelle/Marine Sciences Laboratory (MSL) conducted three independent studies of OBM sediment in January 1993, January 1994, and October 1994. These studies evaluated potential chemical contamination and biological effects of OBM that could occur as a result of dredging and disposal activities. These evaluations were performed by conducting chemical analysis, solid-phase toxicity tests, suspended- particulate-phase (SPP) toxicity tests, and bioaccumulation tests on the OBM sediment. If the sediment chemistry and toxicity results showed no or minimal contamination and toxicological responses, then either the OBM could be left exposed in Richmond Harbor after dredging the YBM without leaving a source of contamination, or if the project depths necessitate, the OBM would be acceptable for disposal at an appropriate disposal site.

Offshore newcomer : world-scale megaproject spawns international-calibre skills and facilities

International Nuclear Information System (INIS)

Sorensen, D.

1997-01-01

The development of Hibernia marked the beginning of Newfoundland's booming oil industry. The offshore platform located 300 km offshore in the Grand Banks of Newfoundland has an estimated 615 million barrels of recoverable reserves to be produced at a projected average rate of 135,000 barrels per day. Newfoundland personnel and facilities acquired much expertise during the building of the offshore facility and are ready to enter the world market for oil and gas services and supplies. Newfoundland's biggest operations are the fabrication yards at Bull Arm and Marystown which have the capacity for steel fabrication, concrete construction, outfitting installation, hook-up and commissioning of industrial facilities. Plans are currently underway for the Terra Nova project. Newfoundland also has a strong labor force, with international calibre skills. The capacity is here, and as confidence in that capability increases, Newfoundland firms are beginning to form partnerships with international firms. 6 figs

International safeguards for a modern MOX [mixed-oxide] fuel fabrication facility

International Nuclear Information System (INIS)

Pillay, K.K.S.; Stirpe, D.; Picard, R.R.

1987-03-01

Bulk-handling facilities that process plutonium for commercial fuel cycles offer considerable challenges to nuclear materials safeguards. Modern fuel fabrication facilities that handle mixed oxides of plutonium and uranium (MOX) often have large inventories of special nuclear materials in their process lines and in storage areas for feed and product materials. In addition, the remote automated processing prevalent at new MOX facilities, which is necessary to minimize radiation exposures to personnel, tends to limit access for measurements and inspections. The facility design considered in this study incorporates all these features as well as state-of-the-art measurement technologies for materials accounting. Key elements of International Atomic Energy Agency (IAEA) safeguards for such a fuel-cycle facility have been identified in this report, and several issues of primary importance to materials accountancy and IAEA verifications have been examined. We have calculated detection sensitivities for abrupt and protracted diversions of plutonium assuming a single materials balance area for all processing areas. To help achieve optimal use of limited IAEA inspection resources, we have calculated sampling plans for attributes/variables verification. In addition, we have demonstrated the usefulness of calculating σ/sub (MUF-D)/ and detection probabilities corresponding to specified material-loss scenarios and resource allocations. The data developed and the analyses performed during this study can assist both the facility operator and the IAEA in formulating necessary safeguards approaches and verification procedures to implement international safeguards for special nuclear materials

International safeguards for a modern MOX (mixed-oxide) fuel fabrication facility

Energy Technology Data Exchange (ETDEWEB)

Pillay, K.K.S.; Stirpe, D.; Picard, R.R.

1987-03-01

Bulk-handling facilities that process plutonium for commercial fuel cycles offer considerable challenges to nuclear materials safeguards. Modern fuel fabrication facilities that handle mixed oxides of plutonium and uranium (MOX) often have large inventories of special nuclear materials in their process lines and in storage areas for feed and product materials. In addition, the remote automated processing prevalent at new MOX facilities, which is necessary to minimize radiation exposures to personnel, tends to limit access for measurements and inspections. The facility design considered in this study incorporates all these features as well as state-of-the-art measurement technologies for materials accounting. Key elements of International Atomic Energy Agency (IAEA) safeguards for such a fuel-cycle facility have been identified in this report, and several issues of primary importance to materials accountancy and IAEA verifications have been examined. We have calculated detection sensitivities for abrupt and protracted diversions of plutonium assuming a single materials balance area for all processing areas. To help achieve optimal use of limited IAEA inspection resources, we have calculated sampling plans for attributes/variables verification. In addition, we have demonstrated the usefulness of calculating sigma/sub (MUF-D)/ and detection probabilities corresponding to specified material-loss scenarios and resource allocations. The data developed and the analyses performed during this study can assist both the facility operator and the IAEA in formulating necessary safeguards approaches and verification procedures to implement international safeguards for special nuclear materials.

Neutronics analysis of International Fusion Material Irradiation Facility (IFMIF). Japanese contributions

International Nuclear Information System (INIS)

Oyama, Yukio; Noda, Kenji; Kosako, Kazuaki.

1997-10-01

In fusion reactor development for demonstration reactor, i.e., DEMO, materials tolerable for D-T neutron irradiation are absolutely required for both mechanical and safety point of views. For this requirement, several kinds of low activation materials were proposed. However, experimental data by actual D-T fusion neutron irradiation have not existed so far because of lack of fusion neutron irradiation facility, except fundamental radiation damage studies at very low neutron fluence. Therefore such a facility has been strongly requested. According to agreement of need for such a facility among the international parties, a conceptual design activity (CDA) of International Fusion Material Irradiation Facility (IFMIF) has been carried out under the frame work of the IEA-Implementing Agreement. In the activity, a neutronics analysis on irradiation field optimization in the IFMIF test cell was performed in three parties, Japan, US and EU. As the Japanese contribution, the present paper describes a neutron source term as well as incident deuteron beam angle optimization of two beam geometry, beam shape (foot print) optimization, and dpa, gas production and heating estimation inside various material loading Module, including a sensitivity analysis of source term uncertainty to the estimated irradiation parameters. (author)

The FENIX [Fusion ENgineering International EXperimental] test facility

International Nuclear Information System (INIS)

Slack, D.S.; Patrick, R.E.; Chaplin, M.R.; Miller, J.R.; Shen, S.S.; Summers, L.T.; Kerns, J.A.

1989-01-01

The Fusion ENgineering International EXperimental Magnet Facility (FENIX), under construction at Lawrence Livermore National Laboratory (LLNL), is a significant step forward in meeting the testing requirements necessary for the development of superconductor for large-scale, superconducting magnets. A 14-T, transverse field over a test volume of 150 x 60 x 150 mm in length will be capable of testing conductors the size of the International Thermonuclear Experimental Reactor (ITER). Proposed conductors for ITER measure ∼35 mm on one side and will operate at currents of up to 40 kA at fields of ∼14 T. The testing of conductors and associated components, such as joints, will require large-bore, high-field magnet facilities. FENIX is being constructed using the existing A 2o and A 2i magnets from the idle MFTF. The east and west A 2 pairs will be mounted together to form a split-pair solenoid. The pairs of magnets will be installed in a 4.0-m cryostat vessel located in the HFTF building at LLNL. Each magnet is enclosed in its own cryostat, the existing 4.0-m vessel serving only as a vacuum chamber. 4 refs., 8 figs

International safeguards in large-scale nuclear facilities

International Nuclear Information System (INIS)

Gupta, D.; Heil, J.

1977-01-01

The trend in the energy sector in most of the world's industrialized areas shows rather clearly that the rate of installing nuclear plants will be very high and that the largest possible units of nuclear material handling and storage facilities will be built. Various experiments and analyses of measurement methods relevant to safeguards in typical nuclear facilities such as a fuel reprocessing or a fabrication plant have shown that the associated measurement errors as obtained under normal operating conditions are such that they are mainly dominated by systematic errors, which may lie in the range of percentages of the measured amount so that a material balance in such a plant could not normally be closed with any higher accuracy. For example, in a reprocessing plant with a throughput of 1500t U/a and a corresponding throughput of 15t Pu/a, a systematic error of 1% would cause a measurement uncertainty of around 70kg Pu in case a material balance is struck twice a year. Such a large amount may be considered to be unacceptable from the point of view of international safeguards since it arises out of a single plant. The simplest way of getting around the problem would be to strike a material balance more frequently over a given period. This could, however, lead to an enormous increase in the technical and financial burden for the operator of a facility. This paper analyses this problem in some detail for some facilities and shows that, for example, with a properly developed information system in such plants and a combination of containment, surveillance and accountancy measures, a safeguards system can be built up for such facilities. (author)

FENIX [Fusion ENgineering International eXperimental]: A test facility for ITER [International Thermonuclear Experimental Reactor] and other new superconducting magnets

International Nuclear Information System (INIS)

Slack, D.S.; Patrick, R.E.; Miller, J.R.

1990-01-01

The Fusion ENgineering International eXperimental (FENIX) Test Facility which is nearing completion at Lawrence Livermore National Laboratory, is a 76-t set of superconducting magnets housed in a 4-m-diameter cryostat. It represents a significant step toward meeting the testing needs for the development of superconductors appropriate for large-scale magnet applications such as the International Thermonuclear Experimental Reactor (ITER). The magnet set is configured to allow radial access to the 0.4-m-diameter high-field region where maximum fields up to 14 T will be provided. The facility is fitted with a thermally isolated test well with a port to the high-field region that allows insertion and removal of test conductors without disturbing the cryogenic environment of the magnets. It is expected that the facility will be made available to magnet developers internationally, and this paper discusses its general design features, its construction, and its capabilities

Possible impact of fixed point sources of SO2 in NSW to the secondary sulphate measurements at Richmond and the dependence of the background secondary sulphate on meteorological variables

International Nuclear Information System (INIS)

Crawford, C.; Cohen, D.D.; Stelcer, E.

2010-01-01

The contribution to secondary sulfate measurements at Richmond, Australia, from known point sources of SOz is investigated using air mass back trajectories. The conditional probability function (CPF) shows that contribution for days of high sulfur is from areas north east of the site. This is an area where known point sources of SOz, such as coal fired power stations, are located. The meteorological conditions associated with high sulfur days are examined and an artificial neural network is employed to determine the relationship between meteorological variables and sulfur measurements after the influence of known point sources was removed. It is shown that temperature and humidity have a nonlinear positive correlation with sulphate measurements, while wind speed, mixing layer depth and rainfall have a negative nonlinear correlation. In addition, the time of day at which air masses reach Richmond from the eastern and western power stations varies, and so thus the altitude at which the power stations are crossed. The time of day, as well as the altitude at which an SOz point source was passed, show an impact to the measured sulfate at Richmond, although the extent of this remains to be fully investigated

Arsenic Removal from Drinking Water by Adsorptive Media U.S. EPA Demonstration Project at Richmond Elementary School in Susanville, CA Final Performance Evaluation Report

Science.gov (United States)

This report documents the activities performed and the results obtained for the arsenic removal treatment technology demonstration project at Richmond Elementary School in Susanville, CA. The objectives of the project were to evaluate: (1) the effectiveness of an Aquatic Treatme...

ARSENIC REMOVAL FROM DRINKING WATER BY ADSORPTIVE MEDIA U.S. EPA DEMONSTRATION PROJECT AT RICHMOND ELEMENTARY SCHOOL IN SUSANVILLE, CA SIX-MONTH EVALUATION REPORT

Science.gov (United States)

This report documents the activities performed during and the results obtained from the first six months of the performance evaluation study of the Aquatic Treatment Systems, Inc. (ATS) adsorptive media arsenic removal system at Richmond Elementary School in Susanville, Californi...

A Strategic Framework for the Establishment of International Production Facilities

DEFF Research Database (Denmark)

Nielsen, A.P.; Riis, Jens Ove

2000-01-01

Departing from the empirical observation that there often is a weak link between the corporate internationalisation strategies and the actual establishment of international production facilities. This paper describes a framework to overcome this problem. The basic idea in the framework is the dis...

The conservation message of the rehabilitated facilities of the International Institute of Tropical Forestry

Science.gov (United States)

Ariel Lugo; J. Rullan

2015-01-01

Over a period of about 20 years, the International Institute of Tropical Forestry (the Institute) and its collaborators developed and implemented a facilities plan that included both new and restored facilities. Among the restored facilities, the historic Headquarters Building received a Leadership in Energy and Environmental Design (LEED) Gold certificate, and was...

Ecological Safety of the Internal Space of the Cattle-Breeding Facility (Cowshed)

Science.gov (United States)

Potseluev, A. A.; Nazarov, I. V.; Tolstoukhova, T. N.; Kostenko, M. V.

2018-01-01

The article emphasizes the importance of observing the ecology of the internal airspace. The factors affecting the state of the air in the internal space of the cattle-breeding facility (cowshed) are revealed. Technical and technological solutions providing for a reduction in the airspace contamination of the livestock facility are proposed. The results of investigations of a technological operation for treating skin integuments of cows with activated water are disclosed, as well as the constructive solution of a heat and power unit that ensures a change in the hydrogen index of the treated water. The justification of the efficiency of the proposed technical and technological solutions is given.

Centrifuge Facility for the International Space Station Alpha

Science.gov (United States)

Johnson, Catherine C.; Hargens, Alan R.

1994-01-01

The Centrifuge Facility planned for the International Space Station Alpha has under-one considerable redesign over the past year, primarily because the Station is now viewed as a 10 year mission rather than a 30 year mission and because of the need to simply the design to meet budget constraints and a 2000 launch date. The basic elements of the Centrifuge Facility remain the same, i.e., a 2.5 m diameter centrifuge, a micro-g holding unit, plant and animal habitats, a glovebox and a service unit. The centrifuge will still provide the full range of artificial gravity from 0.01 a to 2 - as originally planned; however, the extractor to permit withdrawal of habitats from the centrifuge without stopping the centrifuge has been eliminated. The specimen habitats have also been simplified and are derived from other NASA programs. The Plant Research Unit being developed by the Gravitational Biology Facility will be used to house plants in the Centrifuge Facility. Although not as ambitious as the Centrifuge Facility plant habitat, it will provide much better environmental control and lighting than the current Shuttle based Plant Growth Facility. Similarly, rodents will be housed in the Advanced Animal Habitat being developed for the Shuttle program. The Centrifuge Facility and ISSA will provide the opportunity to perform repeatable, high quality science. The long duration increments available on the Station will permit multigeneration studies on both plants and animals which have not previously been possible. The Centrifuge Facility will accommodate sufficient number of specimens to permit statistically significant sampling of specimens to investigate the time course of adaptation to altered gravity environments. The centrifuge will for the first time permit investigators to use gravity itself as a tool to investigate fundamental processes, to investigate the intensity and duration of gravity to maintain normal structure and function, to separate the effects of micro-g from

International measures needed to protect metal recycling facilities from radioactive materials

International Nuclear Information System (INIS)

Mattia, M.; Wiener, R.

1999-01-01

In almost every major city and region of every country, there is a recycling facility that is designed to process or consume scrap metal. These same countries will probably have widespread applications of radioactive materials and radiation generating equipment. This material and equipment will have metal as a primary component of its housing or instrumentation. It is this metal that will cause these sources of radioactivity, when lost, stolen or mishandled, to be taken to a metal recycling facility to be sold for the value of the metal. This is the problem that has faced scrap recycling facilities for many years. The recycling industry has spent millions of dollars for installation of radiation monitors and training in identification of radioactive material. It has expended millions more for the disposal of radioactive material that has mistakenly entered these facilities. Action must be taken to prevent this material from entering the conventional recycling process. There are more than 2,300 known incidents of radioactive material found in recycled metal scrap. Worldwide, more than 50 smeltings of radioactive sources have been confirmed. Seven fatal accidents involving uncontrolled radioactive material have also been documented. Hazardous exposures to radioactive material have plagued not just the workers at metal recycling facilities. The families of these workers, including their children, have been exposed to potentially harmful levels of radioactivity. The threat from this material does not stop there. Radioactive material that is not caught at recycling facilities can be melted and the radioactivity has been found in construction materials used to build homes, as well as shovels, fencing material, and furniture offered for sale to the general public. The time has come for the international community to address the issue of the uncontrolled sources of radioactive material. The following are the key points that must be addressed. (i) Identification of sources

The International Facility for Antiproton and Ion Research FAIR

International Nuclear Information System (INIS)

Gutbrod, H. H.

2008-01-01

The proposed project FAIR (Facility for Antiproton and Ion Research) is an international accelerator facility of the next generation and will be built as a new company FAIR GmbH next to the site of GSI. About 15 countries have expressed their intention to become shareholders. FAIR builds on the experience and technological developments already made at the existing GSI facility, and at the FAIR partner institutes world wide and incorporates new technological concepts. At its heart is a double ring facility with a circumference of 1100 meters. A system of cooler-storage rings for effective beam cooling at high energies and various experimental halls will be connected to the facility. The existing GSI accelerators - together with the planned proton-linac - serve as injector for the new facility. The double-ring synchrotron will provide ion beams of unprecedented intensities as well as of considerably increased energy. Thereby intense beams of secondary beams - unstable nuclei or antiprotons - can be produced. The system of storage-cooler rings allows the quality of these secondary beams - their energy spread and emittance - to be drastically improved. Moreover, in connection with the double ring synchrotron, an efficient parallel operation of up to four scientific programs can be realized at a time. The project is based on many technological innovations, the most important of which are five beam properties: Highest Beam Intensities, Brilliant Beam Quality, Higher Beam Energies, Highest Beam Power, Parallel Operation

Nuclear physics research at the University of Richmond. Progress report, November 1, 1994 - October 31, 1995

International Nuclear Information System (INIS)

Vineyard, M.F.; Gilfoyle, G.P.; Major, R.W.

1995-01-01

Summarized in this report is the progress achieved during the period from November 1, 1994 to October 31, 1995. The experimental work described in this report is in electromagnetic and heavy-ion nuclear physics. The effort in electromagnetic nuclear physics is in preparation for the research program at the Continuous Electron Beam Accelerator Facility (CEBAF) and is focused on the construction and use of the CEBAF Large Acceptance Spectrometer (CLAS). The heavy-ion experiments were performed at the Argonne National Laboratory ATLAS facility and SUNY, Stony Brook. The physics interests driving these efforts at CEBAF are in the study of the structure, interactions, and nuclear-medium modifications of mesons and baryons. This year, an extension of the experiment to measure the magnetic form factor of the neutron was approved by the CEBAF Program Advisory Committee Nine (PAC9) for beam at 6 GeV. The authors also submitted updates to PAC9 on the experiments to measure inclusive η photoproduction in nuclei and electroproduction of the Λ, Λ*(1520), and f 0 (975). In addition to these experiments, the authors collaborated on a proposal to measure rare radiative decays of the φ meson which was also approved by PAC9. Their contributions to the construction of the CLAS include the development of the drift-chamber gas system, drift-chamber software, and controls software. Major has been leading the effort in the construction of the gas system. In the last year, the Hall B gas shed was constructed and the installation of the gas system components built at the University of Richmond has begun. Over the last six years, the efforts in low-energy heavy-ion physics have decreased due to the change in focus to electromagnetic nuclear physics at CEBAF. Most of the heavy-ion work is completed and there are now new experiments planned. Included in this report are two papers resulting from collaborations on heavy-ion experiments

TRIGA International, a new TRIGA fuel fabrication facility at CERCA

International Nuclear Information System (INIS)

Harbonnier, G.

1997-01-01

At the time when General Atomics expressed its intention to cease fuel fabrication on its site of San Diego, CERCA has been chosen to carry on the fabrication of TRIGA fuel. After negotiations in 1994 and 1995, a partnership 50%/50% was decided and on July 1995, a new company was founded, with the name TRIGA INTERNATIONAL SAS, head office in Paris and fuel fabrication facility at CERCA in Romans. The intent of this presentation is, after a short reminder about TRIGA fuel design and fabrication to describe the new facility with special emphasis on the safety features associated with the modification of existing fabrication buildings. (author)

International technology exchange in support of the Defense Waste Processing Facility wasteform production

International Nuclear Information System (INIS)

Kitchen, B.G.

1989-01-01

The nearly completed Defense Waste Processing Facility (DWPF) is a Department of Energy (DOE) facility at the Savannah River Site that is designed to immobilize defense high level radioactive waste (HLW) by vitrification in borosilicate glass and containment in stainless steel canisters suitable for storage in the future DOE HLW repository. The DWPF is expected to start cold operation later this year (1990), and will be the first full scale vitrification facility operating in the United States, and the largest in the world. The DOE has been coordinating technology transfer and exchange on issues relating to HLW treatment and disposal through bi-lateral agreements with several nations. For the nearly fifteen years of the vitrification program at Savannah River Laboratory, over two hundred exchanges have been conducted with a dozen international agencies involving about five-hundred foreign national specialists. These international exchanges have been beneficial to the DOE's waste management efforts through confirmation of the choice of the waste form, enhanced understanding of melter operating phenomena, support for paths forward in political/regulatory arenas, confirmation of costs for waste form compliance programs, and establishing the need for enhancements of melter facility designs. This paper will compare designs and schedules of the international vitrification programs, and will discuss technical areas where the exchanges have provided data that have confirmed and aided US research and development efforts, impacted the design of the DWPF and guided the planning for regulatory interaction and product acceptance

International Space Station Research and Facilities for Life Sciences

Science.gov (United States)

Robinson, Julie A.; Ruttley, Tara M.

2009-01-01

Assembly of the International Space Station is nearing completion in fall of 2010. Although assembly has been the primary objective of its first 11 years of operation, early science returns from the ISS have been growing at a steady pace. Laboratory facilities outfitting has increased dramatically 2008-2009 with the European Space Agency s Columbus and Japanese Aerospace Exploration Agency s Kibo scientific laboratories joining NASA s Destiny laboratory in orbit. In May 2009, the ISS Program met a major milestone with an increase in crew size from 3 to 6 crewmembers, thus greatly increasing the time available to perform on-orbit research. NASA will launch its remaining research facilities to occupy all 3 laboratories in fall 2009 and winter 2010. To date, early utilization of the US Operating Segment of the ISS has fielded nearly 200 experiments for hundreds of ground-based investigators supporting international and US partner research. With a specific focus on life sciences research, this paper will summarize the science accomplishments from early research aboard the ISS- both applied human research for exploration, and research on the effects of microgravity on life. We will also look ahead to the full capabilities for life sciences research when assembly of ISS is complete in 2010.

IFMIF : International Fusion Materials Irradiation Facility Conceptual Design Activity: Final report

International Nuclear Information System (INIS)

Martone, M.

1997-01-01

This report documents the results of the Conceptual Design Activity (CDA) on the International Fusion Materials Irradiation Facility (IFMIF), conducted during 1995 and 1996. The activity is under the auspices of the International Energy Agency (IEA) Implementing Agreement for a Programme of Research and Development on Fusion Materials. An IEA Fusion Materials Executive Subcommittee was charged with overseeing the IFMIF-CDA work. Participants in the CDA are the European Union, Japan, and the United States, with the Russian Federation as an associate member

IFMIF : International Fusion Materials Irradiation Facility Conceptual Design Activity: Final report

Energy Technology Data Exchange (ETDEWEB)

Martone, M [ENEA, Centro Ricerche Frascati, Rome (Italy)

1997-01-01

This report documents the results of the Conceptual Design Activity (CDA) on the International Fusion Materials Irradiation Facility (IFMIF), conducted during 1995 and 1996. The activity is under the auspices of the International Energy Agency (IEA) Implementing Agreement for a Programme of Research and Development on Fusion Materials. An IEA Fusion Materials Executive Subcommittee was charged with overseeing the IFMIF-CDA work. Participants in the CDA are the European Union, Japan, and the United States, with the Russian Federation as an associate member.

Design of a control system for HIRFL-CSRe internal target facility in Lanzhou

International Nuclear Information System (INIS)

Wang Yanyu; Liu Wufeng; Shao Caojie; Lin Feiyu; Zhang Jianchuan; Xiao Wenjun

2010-01-01

It is described in this paper the design of the control system for HIRFL-CSRe internal target facility, in which there are many different kinds of units need to be monitored and controlled. The control system is composed of several subsystems which are designed to control the gas-jet temperature, chamber vacuum, valves and molecular pumps. A human-computer interaction interface is also realized to do the data acquisition, data processing and display. The whole system has been working stably and safely, it fully meets the requirements of physical experiments in the internal target facility. In January of 2010, the first physics experiment of the radioactive electron capture was finished successfully with the aids of this control system. (authors)

SPRT Calibration Uncertainties and Internal Quality Control at a Commercial SPRT Calibration Facility

Science.gov (United States)

Wiandt, T. J.

2008-06-01

The Hart Scientific Division of the Fluke Corporation operates two accredited standard platinum resistance thermometer (SPRT) calibration facilities, one at the Hart Scientific factory in Utah, USA, and the other at a service facility in Norwich, UK. The US facility is accredited through National Voluntary Laboratory Accreditation Program (NVLAP), and the UK facility is accredited through UKAS. Both provide SPRT calibrations using similar equipment and procedures, and at similar levels of uncertainty. These uncertainties are among the lowest available commercially. To achieve and maintain low uncertainties, it is required that the calibration procedures be thorough and optimized. However, to minimize customer downtime, it is also important that the instruments be calibrated in a timely manner and returned to the customer. Consequently, subjecting the instrument to repeated calibrations or extensive repeated measurements is not a viable approach. Additionally, these laboratories provide SPRT calibration services involving a wide variety of SPRT designs. These designs behave differently, yet predictably, when subjected to calibration measurements. To this end, an evaluation strategy involving both statistical process control and internal consistency measures is utilized to provide confidence in both the instrument calibration and the calibration process. This article describes the calibration facilities, procedure, uncertainty analysis, and internal quality assurance measures employed in the calibration of SPRTs. Data will be reviewed and generalities will be presented. Finally, challenges and considerations for future improvements will be discussed.

IFMIF : International Fusion Materials Irradiation Facility Conceptual Design Activity: Executive summary

International Nuclear Information System (INIS)

1997-01-01

This report is a summary of the results of the Conceptual Design Activity (CDA) on the International Fusion Materials Irradiation Facility (IFMIF), conducted during 1995 and 1996. The activity is under the auspices of the International Energy Agency (IEA) Implementing Agreement for a Programme of Research and Development on Fusion Materials. An IEA Fusion Materials Executive Subcommittee was charged with overseeing the IFMIF-CDA work. Participants in the CDA are the European Union, Japan, and the United States, with the Russian Federation as an associate member

IFMIF : International Fusion Materials Irradiation Facility Conceptual Design Activity: Executive summary

Energy Technology Data Exchange (ETDEWEB)

NONE

1997-01-01

This report is a summary of the results of the Conceptual Design Activity (CDA) on the International Fusion Materials Irradiation Facility (IFMIF), conducted during 1995 and 1996. The activity is under the auspices of the International Energy Agency (IEA) Implementing Agreement for a Programme of Research and Development on Fusion Materials. An IEA Fusion Materials Executive Subcommittee was charged with overseeing the IFMIF-CDA work. Participants in the CDA are the European Union, Japan, and the United States, with the Russian Federation as an associate member.

An international contribution to decommissioning of nuclear facilities

International Nuclear Information System (INIS)

Lazo, T.

1995-01-01

Nuclear power plants and fuel cycle facilities must be retired from service when they have completed their design objective, become obsolete or when they no longer fulfill current safety, technical or economic requirements. Decommissioning is defined as the set of technical and administrative operations that provides adequate protection of workers and public against radiation risks, minimizes impact on the environment and involves manageable costs. A traditional definition of the stages of decommissioning has been proposed by the IAEA and is largely used worldwide. A number of factors have to be considered when selecting the optimum strategy, which include the national nuclear policy, characteristics of the facility, health and safety, environmental protection, radioactive waste management, future use of the site, improvements of the technology that may be achieved in the future, costs and availability of funds and various social considerations. The paper describes the current situation of nuclear facilities and the associated forthcoming requirements and problems of decommissioning. This task requires a complete radionuclide inventory, decontamination methods, disassembly techniques and remote operations. Radiation safety presents three aspects: nuclear safety, protection of workers and protection of the public. An appropriate delay to initiate decommissioning after shutdown of a facility may considerably reduce workers exposures and costs. Decommissioning also generates significant quantities of neutron-activated and surface contaminated materials which require a specific management. A vigorous international cooperation and coordinated research programs have been encouraged by the NEA for a minimization of costs and efforts and to provide a basis for consensus of opinions on policies, strategies and criteria. (J.S.). 19 refs., 5 figs., 3 tabs

The Richmond Agitation-Sedation Scale modified for palliative care inpatients (RASS-PAL): a pilot study exploring validity and feasibility in clinical practice

OpenAIRE

Bush, Shirley H; Grassau, Pamela A; Yarmo, Michelle N; Zhang, Tinghua; Zinkie, Samantha J; Pereira, José L

2014-01-01

Background The Richmond Agitation-Sedation Scale (RASS), which assesses level of sedation and agitation, is a simple observational instrument which was developed and validated for the intensive care setting. Although used and recommended in palliative care settings, further validation is required in this patient population. The aim of this study was to explore the validity and feasibility of a version of the RASS modified for palliative care populations (RASS-PAL). Methods A prospective study...

Coordination in International Manufacturing: The Role of Competitive Priorities and the Focus of Globally Dispersed Facilities

Directory of Open Access Journals (Sweden)

Ahmed Sayem

2018-04-01

Full Text Available In this era of globalization, network integration has received great attention, as it certainly has implications for the competitiveness in international manufacturing. A key issue in integration is to coordinate activities of dispersed facilities in a way to align the target of locating abroad and the priorities to be competitive. This study explores and clarifies the effect of competitive priority and focus of dispersed facilities on coordinating the activities in intra-firm network manufacturing. Based on a multiple case study involving four different companies manufacturing in globally dispersed facilities, the results confirm that both competitive priorities and specific focus of global manufacturing are important for selecting mechanisms to coordinate overseas facilities, with the competitive priorities ‘quality’ and ‘flexibility’ being the more important. Furthermore, the findings reveal that companies place emphasis on informal mechanisms to coordinate the low-cost focused facilities. In turn, the importance of formal mechanisms seems equal for coordinating both low-cost focused facilities and those focused on capturing a local market. Finally, the findings of this paper suggest that elements of competitive priority, as well as the focus of dispersed facilities, should be considered towards making the choice for mechanisms of coordination. The findings bear important implications for the effective coordination of activities in international manufacturing.

Siting simulation for low-level waste disposal facilities

International Nuclear Information System (INIS)

Roop, R.D.; Rope, R.C.

1985-01-01

The Mock Site Licensing Demonstration Project has developed the Low-Level Radioactive Waste Siting Simulation, a role-playing exercise designed to facilitate the process of siting and licensing disposal facilities for low-level waste (LLW). This paper describes the development, content, and usefulness of the siting simulation. The simulation can be conducted at a workshop or conference, involves 14 or more participants, and requires about eight hours to complete. The simulation consists of two sessions; in the first, participants negotiate the selection of siting criteria, and in the second, a preferred disposal site is chosen from three candidate sites. The project has sponsored two workshops (in Boston, Massachusetts and Richmond, Virginia) in which the simulation has been conducted for persons concerned with LLW management issues. It is concluded that the simulation can be valuable as a tool for disseminating information about LLW management; a vehicle that can foster communication; and a step toward consensus building and conflict resolution. The DOE National Low-Level Waste Management Program is now making the siting simulation available for use by states, regional compacts, and other organizations involved in development of LLW disposal facilities

16th International Workshop on Neutrino Factories and Future Neutrino Beam Facilities

CERN Document Server

2015-01-01

These proceedings present the written contributions from participants of the 16th International Workshop on Neutrino Factories and Future Neutrino Beam Facilities (NUFACT 2014) that was held at the University of Glasgow (Glasgow, Scotland, United Kingdom) from 25-30 August 2014. This edition of the NUFACT annual meetings, which started in 1999, consisted of 24 plenary and 92 parallel talks and various poster sessions, with the participation of 124 delegates. Furthermore, the International Neutrino Summer School 2014 was held from 10-22 August 2014 at St Andrews, Scotland, in the two weeks before NUFACT 2014. It was intended for young scientists with an interest in neutrino physics in such a way that they would be able to participate and contribute to the NUFACT workshop as well. The objectives of the NUFACT workshops are to review progress on different studies for future accelerator-based neutrino oscillation facilities, with the goal to discover the mass hierarchy of neutrinos, CP violation in the leptonic s...

Interdisciplinary study of atmospheric processes and constituents of the mid-Atlantic coastal region. Attachment 5: Data set for background investigation of atmospheric constituents for Richmond, Virginia area. [air pollution monitoring

Science.gov (United States)

Kindle, E. C.; Bandy, A.; Copeland, G.; Blais, R.; Levy, G.; Sonenshine, D.; Adams, D.; Maier, G.

1975-01-01

Background data is provided for the photochemical oxident problem in the Richmond area. Particulate data, digitized portrayal of site molecular and meteorological data, and graphical portrayal of molecular data, hourly meteorological data, and streamflow charts and radiosonde data are also given.

IFMIF (International Fusion Materials Irradiation Facility) key element technology phase interim report

International Nuclear Information System (INIS)

Nakamura, Hiroo; Ida, Mizuho; Sugimoto, Masayoshi; Takeuchi, Hiroshi; Yutani, Toshiaki

2002-03-01

Activities of International Fusion Materials Irradiation Facility (IFMIF) have been performed under an IEA collaboration since 1995. IFMIF is an accelerator-based deuteron (D + )-lithium (Li) neutron source designed to produce an intense neutron field (2 MW/m 2 , 20 dpa/year for Fe) in a volume of 500 cm 3 for testing candidate fusion materials. In 2000, a 3 year Key Element technology Phase (KEP) of IFMIF was started to reduce the key technology risk factors. This interim report summarizes the KEP activities until mid 2001 in the major project work-breakdown areas of accelerator, target, test facilities and design integration. (author)

Electroconvulsive therapy in geriatric patients: A literature review and program report from Virginia Commonwealth University, Richmond, Virginia, USA

Directory of Open Access Journals (Sweden)

Andrew D Snyder

2017-01-01

Full Text Available Electroconvulsive therapy (ECT is an effective therapeutic intervention in the elderly patients with major depression, especially those with psychosis, suicidality, catatonia, nutritional compromise, and resistance to medications. Response rates can be as high as 80%. We present an extensive review of the relevant literature, provide a description of the ECT program at Virginia Commonwealth University in Richmond, Virginia, USA, and present results of our experience with ECT in fifty elderly patients. The treatments were safe, well tolerated, and produced high response rates, variably between 68% and 84%. Patients in the long-term maintenance ECT program continue to show sustained benefits from ECT.

IFMIF (International Fusion Materials Irradiation Facility) conceptual design activity reduced cost report

International Nuclear Information System (INIS)

2000-02-01

This report describes the results of a preliminary reevaluation of the design and cost of the International Fusion Materials Irradiation Facility (IFMIF) Project in response to the request from the 28th FPCC meeting in January 1999. Two major ideas have been considered: 1) reduction of the total construction cost through elimination of the previously planned facility upgrade and 2) a facility deployment in 3 stages with capabilities for limited experiments in the first stage. As a result, the size and complexity of the facility could be significantly reduced, leading to substantial cost savings. In addition to these two ideas, this study also included a critical review of the original CDA specification with the objective of elimination of nonessential items. For example, the number of lithium targets was reduced from two to one. As a result of these changes in addition to the elimination of the upgrade, the total cost estimate was very substantially reduced from 797.2 MICF to 487.8 MICF, where 1 MICF = 1 Million of the IFMIF Conversion Units (approximately $1M US January, 1996). (author)

Internal environmental protection audits: a suggested guide for US Department of Energy facilities

International Nuclear Information System (INIS)

Barisas, S.; Polich, J.; Habegger, L.; Surles, T.

1983-08-01

This manual has been prepared for use by any DOE facility as an aid for conducting an internal environmental-protection audit. The manual is organized in modular format, with each module covering a separate area of environmental protection. The questions within each module were developed from existing DOE orders, executive orders, federal statutes, and Environmental Protection Agency (EPA) regulations issued pursuant to specific environmental legislation. A bibliography of such legislation is included at the end of this section. Each module also includes questions about a facility's use of industrial standards of practice

IFMIF (International Fusion Materials Irradiation Facility) key element technology phase interim report

Energy Technology Data Exchange (ETDEWEB)

Nakamura, Hiroo; Ida, Mizuho; Sugimoto, Masayoshi; Takeuchi, Hiroshi; Yutani, Toshiaki (eds.) [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment

2002-03-01

Activities of International Fusion Materials Irradiation Facility (IFMIF) have been performed under an IEA collaboration since 1995. IFMIF is an accelerator-based deuteron (D{sup +})-lithium (Li) neutron source designed to produce an intense neutron field (2 MW/m{sup 2}, 20 dpa/year for Fe) in a volume of 500 cm{sup 3} for testing candidate fusion materials. In 2000, a 3 year Key Element technology Phase (KEP) of IFMIF was started to reduce the key technology risk factors. This interim report summarizes the KEP activities until mid 2001 in the major project work-breakdown areas of accelerator, target, test facilities and design integration. (author)

Atomics International environmental monitoring and facility effluent annual report, 1976

International Nuclear Information System (INIS)

Moore, J.D.

1977-01-01

Environmental and facility effluent radioactivity monitoring at Atomics International (AI) is performend by the Radiation and Nuclear Safety Unit of the Health, Safety, and Radiation Services Department. Soil, vegetation, and surface water are routinely sampled to a distance of 10 miles from AI sites. Continuous ambient air sampling and thermoluminescent dosimetry are performed on site for monitoring airborne radioactivity and site ambient radiation levels. Radioactivity in effluents discharged to the atmosphere from AI facilities is continuously sampled and monitored to ensure that levels released to unrestricted areas are within appropriate limits, and to identify processes which may require additional engineering safeguards to minimize radioactivity levels in such effluents. In addition, selected nonradioactive constituents in surface water discharged to unrestricted areas are determined. This report summarizes and discusses monitoring results for 1976. The results of a special soil plutonium survey performed during the year are also summarized

International symposium on seismic evaluation of existing nuclear facilities. Book of invited and contributed papers

International Nuclear Information System (INIS)

2003-08-01

In the past decade, seismic evaluation of existing Nuclear Power Plants (NPPs) has been an issue in western countries (particularly for the east of North America and for older NPPs in Europe) as well as in eastern European countries where systematic reviews of NPPs were carried out. Several Member States have still on-going seismic upgrading programmes. Presently. projects of plant life extension create an additional interest in safety evaluation of existing NPPs. Seismic evaluation is also an issue for other nuclear facilities. In western countries. some older facilities (laboratories, research reactors, fuel plants...) have been designed without taking into account (or poorly taking into account) earthquake input, even on seismic sites. In eastern countries, the situation is not yet clearly evaluated. In several countries concerns are expressed regarding research reactors. Generally speaking, the seismic evaluation of these nuclear facilities is not so advanced as the evaluation of NPPs and presents a wider range of different situations. Those safety issues raised by the seismic evaluation of existing NPPs are addressed in an IAEA Safety Report 'Seismic Evaluation of Existing Nuclear Power Plants' (2003). Other nuclear facilities are, at least partly, covered by IAEA-TECDOC 1347 'Design of Nuclear Facilities other than NPPs in Relation to External Events, with a Special Emphasis on Earthquake' (2003) that supersedes the former TECDOC 348 'Earthquake Resistant Design of Nuclear Facilities with Limited Radioactive Inventory' (1985). Concurrently with the publishing of relevant documentation, the IAEA has organized this Symposium in order to foster the exchange of information on topical issues in seismic evaluation of existing nuclear facilities, with the aim of: consolidating an international consensus on the present status of these issues; promoting a homogeneous engineering approach of their resolution; identifying the needs for strengthening international co

International symposium on seismic evaluation of existing nuclear facilities. Book of invited and contributed papers

Energy Technology Data Exchange (ETDEWEB)

NONE

2003-08-01

In the past decade, seismic evaluation of existing Nuclear Power Plants (NPPs) has been an issue in western countries (particularly for the east of North America and for older NPPs in Europe) as well as in eastern European countries where systematic reviews of NPPs were carried out. Several Member States have still on-going seismic upgrading programmes. Presently. projects of plant life extension create an additional interest in safety evaluation of existing NPPs. Seismic evaluation is also an issue for other nuclear facilities. In western countries. some older facilities (laboratories, research reactors, fuel plants...) have been designed without taking into account (or poorly taking into account) earthquake input, even on seismic sites. In eastern countries, the situation is not yet clearly evaluated. In several countries concerns are expressed regarding research reactors. Generally speaking, the seismic evaluation of these nuclear facilities is not so advanced as the evaluation of NPPs and presents a wider range of different situations. Those safety issues raised by the seismic evaluation of existing NPPs are addressed in an IAEA Safety Report 'Seismic Evaluation of Existing Nuclear Power Plants' (2003). Other nuclear facilities are, at least partly, covered by IAEA-TECDOC 1347 'Design of Nuclear Facilities other than NPPs in Relation to External Events, with a Special Emphasis on Earthquake' (2003) that supersedes the former TECDOC 348 'Earthquake Resistant Design of Nuclear Facilities with Limited Radioactive Inventory' (1985). Concurrently with the publishing of relevant documentation, the IAEA has organized this Symposium in order to foster the exchange of information on topical issues in seismic evaluation of existing nuclear facilities, with the aim of: consolidating an international consensus on the present status of these issues; promoting a homogeneous engineering approach of their resolution; identifying the needs for strengthening international co

International inventory of training facilities in nuclear power and its fuel cycle

International Nuclear Information System (INIS)

1977-01-01

Because the development of trained manpower is important for full use of nuclear power, the International Atomic Energy Agency has compiled this first inventory of training facilities and programs. It is based on information submitted by Member States and received up to 31 January 1977. The inventory is arranged by country, type of training organization, and by subject

Preparation of IHY-2007 in Indonesia: Local Observational Facilities, International Collaborations, and the Use of International Data

Science.gov (United States)

Djamaluddin, T.

2006-11-01

t_djamal@hotmail.com Since 1980, the National Institute of Aeronautics and Space (LAPAN) has been carrying out integrated observations of solar activities, geomagnetic disturbance, and ionospheric parameters, as well as other solar-terrestrial relationship research. International collaboration, especially with Japan in the field of solar physics, geomagnetism and equatorial atmosphere and with Australia in the field of ionosphere and upper atmosphere, help us in increasing national capacity building. The international data available on the Internet also helps us in comparing our local data with the global one or in fulfilling our needs of data due to lack of facilities, ground based or space based data. Some results will be reviewed. Preparation for IHY-2007 will also be discussed.

Safeguards Guidance Document for Designers of Commercial Nuclear Facilities: International Nuclear Safeguards Requirements and Practices For Uranium Enrichment Plants

Energy Technology Data Exchange (ETDEWEB)

Robert Bean; Casey Durst

2009-10-01

This report is the second in a series of guidelines on international safeguards requirements and practices, prepared expressly for the designers of nuclear facilities. The first document in this series is the description of generic international nuclear safeguards requirements pertaining to all types of facilities. These requirements should be understood and considered at the earliest stages of facility design as part of a new process called “Safeguards-by-Design.” This will help eliminate the costly retrofit of facilities that has occurred in the past to accommodate nuclear safeguards verification activities. The following summarizes the requirements for international nuclear safeguards implementation at enrichment plants, prepared under the Safeguards by Design project, and funded by the U.S. Department of Energy (DOE) National Nuclear Security Administration (NNSA), Office of NA-243. The purpose of this is to provide designers of nuclear facilities around the world with a simplified set of design requirements and the most common practices for meeting them. The foundation for these requirements is the international safeguards agreement between the country and the International Atomic Energy Agency (IAEA), pursuant to the Treaty on the Non-proliferation of Nuclear Weapons (NPT). Relevant safeguards requirements are also cited from the Safeguards Criteria for inspecting enrichment plants, found in the IAEA Safeguards Manual, Part SMC-8. IAEA definitions and terms are based on the IAEA Safeguards Glossary, published in 2002. The most current specification for safeguards measurement accuracy is found in the IAEA document STR-327, “International Target Values 2000 for Measurement Uncertainties in Safeguarding Nuclear Materials,” published in 2001. For this guide to be easier for the designer to use, the requirements have been restated in plainer language per expert interpretation using the source documents noted. The safeguards agreement is fundamentally a

Uranium Production Safety Assessment Team. UPSAT. An international peer review service for uranium production facilities

International Nuclear Information System (INIS)

1996-01-01

The IAEA Uranium Production Safety Assessment Team (UPSAT) programme is designed to assist Member States to improve the safe operation of uranium production facilities. This programme facilitates the exchange of knowledge and experience between team members and industry personnel. An UPSAT mission is an international expert review, conducted outside of any regulatory framework. The programme is implemented in the spirit of voluntary co-operation to contribute to the enhancement of operational safety and practices where it is most effective, at the facility itself. An UPSAT review supplements other facility and regulatory efforts which may have the same objective

EVALUATION OF ECONOMIC EFFICIENCY PERTAINING TO USAGE OF AUTOMOTIVE TRANSPORT FACILITIES WHILE EXECUTING INTERNATIONAL CARGO TRANSPORTATION

Directory of Open Access Journals (Sweden)

R. B. Ivut

2010-01-01

Full Text Available The paper presents a methodology for evaluation of economic efficiency pertaining to usage of automotive transport facilities while executing international cargo transportation on the basis of average internal norm calculation of automotive operational profitability of a specific model under conditions which are typical for the given market by an average carrier.

Characterization of aerosols in uranium handling facilities and its impact on the assessment of internal dose

International Nuclear Information System (INIS)

Roy, Ankush; Rao, D.D.; Sawant, Pramilla D.; Khan, Arshad; Srinivasan, P.; Chandrashekara, A.

2016-01-01

In nuclear facilities, compounds of uranium such as Magnesium DiUranate (MDU) U 3 O 8 , UO 2 etc. are handled in different stages of operation. There may be a possibility of intake of these compounds by radiation workers during the course of their work. The internal doses received by the workers depend not only on the quantity but also the physiochemical characteristics of the radioactive contaminant. The depositions in different regions of lung of these inhaled aerosols depend on their particle size; whereas the clearance is dependent upon the chemical nature. In this study, aerosol characterization is carried out in four different Uranium Handling Facilities (UF) for realistic assessment of internal dose to the radiation worker

International fusion materials irradiation facility and neutronic calculations for its test modules

International Nuclear Information System (INIS)

Sokcic-Kostic, M.

1997-01-01

The International Fusion Material Irradiation Facility (IFMIF) is a projected high intensity neutron source for material testing. Neutron transport calculations for the IFMIF project are performed for variety of here explained reasons. The results of MCNP neutronic calculations for IFMIF test modules with NaK and He cooled high flux test cells are presented in this paper. (author). 3 refs., 2 figs., 3 tabs

Studying international fuel cycle robustness with the GENIUSv2 discrete facilities/materials fuel cycle systems analysis tool

Energy Technology Data Exchange (ETDEWEB)

Wilson, P.H. [Dept. of Engineering Physics, University of Wisconsin-Madison (United States)

2009-06-15

GENIUSv2 (Global Evaluation of Nuclear Infrastructure Utilization Scenarios, hereafter 'GENIUS') is a discrete-facilities/materials nuclear fuel cycle systems analysis tool currently under development at the University of Wisconsin-Madison. For a given scenario, it models nuclear fuel cycle facilities (reactors, fuel fabrication, enrichment, etc.), the institutions that own them (utilities and governments), and the regions in which those institutions operate (sub-national, national, and super-national entities). Facilities work together to provide each other with the materials they need. The results of each simulation include the electricity production in each region as well as operational histories of each facility and isotopic and facility histories of each material object. GENIUS users specify an initial condition and a facility deployment plan. The former describes each region and institution in the scenario as well as facilities that exist at the start. The latter specifies all the facilities that will be built over the course of the simulation (and by which institutions). Each region, institution, and facility can be assigned financial parameters such as tax and interest rates, and facilities also get assigned technical information about how they actually operate. Much of the power of the data model comes from the flexibility to model individual entities to a fine level of detail or to allow them to inherit region-, institution-, or facility-type-specific default parameters. Most importantly to the evaluation of regional, national, and international policies, users can also specify rules that define the affinity (or lack thereof) for trade of particular commodities between particular entities. For instance, these rules could dictate that a particular region or institution always buy a certain commodity (ore, enriched UF{sub 6}, fabricated fuel, etc.) from a particular region or institution, never buy from that region, or merely have a certain

75 FR 1621 - Radio Broadcasting Services; AM or FM Proposals To Change the Community of License

Science.gov (United States)

2010-01-12

...-20090813ABE, From BUNKERVILLE, NV, To ST GEORGE, UT; MLB-RICHMOND IV, LLC, Station WBBT- FM, Facility ID 31859...; SUSQUEHANNA RADIO CORP., Station KIKT, Facility ID 21597, BPH-20091207ABH, From GREENVILLE, TX, To COOPER, TX...

Mindfulness, burnout, and effects on performance evaluations in internal medicine residents

Directory of Open Access Journals (Sweden)

Braun SE

2017-08-01

Full Text Available Sarah E Braun,1 Stephen M Auerbach,1 Bruce Rybarczyk,1 Bennett Lee,2 Stephanie Call2 1Department of Psychology, School of Humanities and Sciences, Virginia Commonwealth University, Richmond, VA, USA; 2Department of Internal Medicine, Division of General Medicine, Virginia Commonwealth University, Richmond, VA, USA Purpose: Burnout has been documented at high levels in medical residents with negative effects on performance. Some dispositional qualities, like mindfulness, may protect against burnout. The purpose of the present study was to assess burnout prevalence among internal medicine residents at a single institution, examine the relationship between mindfulness and burnout, and provide preliminary findings on the relation between burnout and performance evaluations in internal medicine residents.Methods: Residents (n = 38 completed validated measures of burnout at three time points separated by 2 months and a validated measure of dispositional mindfulness at baseline. Program director end-of-year performance evaluations were also obtained on 22 milestones used to evaluate internal medicine resident performance; notably, these milestones have not yet been validated for research purposes; therefore, the investigation here is exploratory.Results: Overall, 71.1% (n = 27 of the residents met criteria for burnout during the study. Lower scores on the “acting with awareness” facet of dispositional mindfulness significantly predicted meeting burnout criteria χ2(5 = 11.88, p = 0.04. Lastly, meeting burnout criteria significantly predicted performance on three of the performance milestones, with positive effects on milestones from the “system-based practices” and “professionalism” domains and negative effects on a milestone from the “patient care” domain.Conclusion: Burnout rates were high in this sample of internal medicine residents and rates were consistent with other reports of burnout during medical residency. Dispositional

Mary Richmond in the perspective of Social Work in Spain

Directory of Open Access Journals (Sweden)

Lourdes Barriga Muñoz

2011-09-01

Full Text Available Our personal experience has shown that, although nobody questions that Mary Richmond received a Ph.D. Honoris Causa «for having set the scientific bases of a new profession», (ours such scientific bases still remain unknown, due to never having been taught as such and due to the lack of theoretical production aimed at refuting, developing or, at least, transmitting them without tergiversation.In this article, we try to present just some quick brush strokes of those scientific bases, mainly because we are conscious of the fact that, in our country, our profession is being rapidly devaluated from many standpoints, identifying it only with resource management and social control and, in the current situation in which social theory finds itself, appearing to have no possibility of modifying that trend.It would be easy to state that the solution would be simply to recover Mary Richmond’s works, but it is not as simple as that since conceptions, ideology, perspectives and finally, the ways of conceiving the present social reality are opposed to those underlying those works. So, we believe that we need an unencumbered view, independent of social sciences, to rediscover our origins, in which we really were a profession, a social discipline with its own know-how and its own way of working, and not just an office to receive those who request an appointment. On the contrary, we aim to influence other sciences, enrich them and demonstrate that social work is a profession necessary to humanity.

Hydrogeology, Ground-Water-Age Dating, Water Quality, and Vulnerability of Ground Water to Contamination in a Part of the Whitewater Valley Aquifer System near Richmond, Indiana, 2002-2003

Science.gov (United States)

Buszka, Paul M.; Watson, Lee R.; Greeman, Theodore K.

2007-01-01

Assessments of the vulnerability to contamination of ground-water sources used by public-water systems, as mandated by the Federal Safe Drinking Water Act Amendments of 1996, commonly have involved qualitative evaluations based on existing information on the geologic and hydrologic setting. The U.S. Geological Survey National Water-Quality Assessment Program has identified ground-water-age dating; detailed water-quality analyses of nitrate, pesticides, trace elements, and wastewater-related organic compounds; and assessed natural processes that affect those constituents as potential, unique improvements to existing methods of qualitative vulnerability assessment. To evaluate the improvement from use of these methods, in 2002 and 2003, the U.S. Geological Survey, in cooperation with the City of Richmond, Indiana, compiled and interpreted hydrogeologic data and chemical analyses of water samples from seven wells in a part of the Whitewater Valley aquifer system in a former glacial valley near Richmond. This study investigated the application of ground-water-age dating, dissolved-gas analyses, and detailed water-quality analyses to quantitatively evaluate the vulnerability of ground water to contamination and to identify processes that affect the vulnerability to specific contaminants in an area of post-1972 greenfield development.

IFMIF-KEP. International fusion materials irradiation facility key element technology phase report

International Nuclear Information System (INIS)

2003-03-01

The International Fusion Materials Irradiation Facility (IFMIF) is an accelerator-based D-Li neutron source designed to produce an intense neutron field that will simulate the neutron environment of a D-T fusion reactor. IFMIF will provide a neutron flux equivalent to 2 MW/m 2 , 20 dpa/y in Fe, in a volume of 500 cm 3 and will be used in the development and qualification of materials for fusion systems. The design activities of IFMIF are performed under an IEA collaboration which began in 1995. In 2000, a three-year Key Element Technology Phase (KEP) of IFMIF was undertaken to reduce the key technology risk factors. This KEP report describes the results of the three-year KEP activities in the major project areas of accelerator, target, test facilities and design integration. (author)

Phase I Source Investigation, Heckathorn Superfund Site, Richmond, California

Energy Technology Data Exchange (ETDEWEB)

Kohn, Nancy P; Evans, Nathan R

2002-12-18

This report represents Phase I of a multi-phase approach to a source investigation of DDT at the Heckathorn Superfund Site, Richmond, California, the former site of a pesticide packaging plant, and the adjacent waterway, the Lauritzen Channel. Potential identified sources of contamination were from sloughed material from undredged areas (such as side banks) and from outfall pipes. Objectives of Phase I included the (1) evaluation of pesticide concentrations associated with discharge from outfalls, (2) identification of additional outfalls in the area, (3) identification of type, quantity, and distribution of sediment under the Levin pier, (4) quantification of pesticide concentrations in sediment under the pier, and (5) evaluation of sediment structure and slope stability under the pier. Field operations included the collection of sediment directly from inside the mouths of outfall pipes, when possible, or the deployment of specially designed particle traps where direct sampling was problematic. Passive water samplers were placed at the end of known outfall pipes and analyzed for DDT and other pesticides of concern. Underwater dive surveys were conducted beneath the Levin pier to document type, slope, and thickness of sediment. Samples were collected at locations of interest and analyzed for contaminants. Also sampled was soil from bank areas, which were suspected of potentially contributing to continued DDT contamination of the Lauritzen Channel through erosion and groundwater leaching. The Phase I Source Investigation was successful in identifying significant sources of DDT contamination to Lauritzen Channel sediment. Undredged sediment beneath the Levin pier that has been redistributed to the channel is a likely source. Two outfalls tested bear further investigation. Not as well-defined are the contributions of bank erosional material and groundwater leaching. Subsequent investigations will be based on the results of this first phase.

Summer in the City - Assessing and Communicating the Richmond, VA Urban Heat Island to the Public and Policymakers

Science.gov (United States)

Hoffman, J. S.; Maurakis, E. G.; Shandas, V.

2017-12-01

The local impacts of global climate change are generally underestimated or misunderstood by the public and policymakers as far-off, future problems. However, differential and regional surface warming trends are exacerbated in urban areas due to the radiative properties of impervious surfaces like buildings and roads relative to natural landscapes. Decades of research illustrate that this unnatural radiative imbalance in the built environment gives rise to the well-studied urban heat island effect, whereby air temperatures in urban areas are several degrees warmer than in surrounding non-urbanized areas. In this way, the urban heat island effect presents a unique opportunity to highlight the human influence on Earth systems and at the same time mobilize local community-scale action to mitigate and become resilient to climate change impacts on tangible, experiential time scales. However, public stakeholders, city planners, and policymakers may view the urban heat island effect and its mitigation strategies through varying degrees of climatological, public health, and urban development knowledge and interest. This variation in stakeholder engagement highlights the need for individualized science communication strategies for each audience in order to maximize understanding of the scientific outcomes and tactics for mitigating the urban heat island effect. The City of Richmond, Virginia is currently developing a climate action plan as part of their greenhouse gas emission reduction initiative, RVAgreen 2050, and its recently announced "Richmond 300," a 20-year city development master plan. These initiatives provide the policy backdrop for a public and stakeholder education campaign centered on communicating urban heat island effects and resilience strategies. As such, the Science Museum of Virginia led the city's first urban heat island assessment using citizen science and leveraging a network of local university, non-profit, and city government stakeholders. Here, we

X-ray crystallography facility for the international space station

International Nuclear Information System (INIS)

McdDonald, William T.; Lewis, Johanna L.; Smith, Craig D.; DeLucas, Lawrence J.

1997-01-01

Directed by NASA's Office of Space Access and Technology (OSAT), the University of Alabama at Birmingham (UAB) Center for Macromolecular Crystallography (CMC) recently completed a Design Feasibility Study for the X-ray Crystallography Facility (XCF) for the International Space Station (ISS). The XCF is a facility for growing macromolecular protein crystals; harvesting, selecting, and mounting sample crystals, and snap-freezing the samples, if necessary; performing x-ray diffraction; and downlinking the diffraction data to the ground. Knowledge of the structure of protein molecules is essential for the development of pharmaceuticals by structure-based drug design techniques. Currently, x-ray diffraction of high quality protein crystals is the only method of determining the structure of these macromolecules. High quality protein crystals have been grown in microgravity onboard the Space Shuttle Orbiter for more than 10 years, but these crystals always have been returned to Earth for x-ray diffraction. The XCF will allow crystal growth, harvesting, mounting, and x-ray diffraction onboard the ISS, maximizing diffraction data quality and timeliness. This paper presents the XCF design concept, describing key feasibility issues for the ISS application and advanced technologies and operational features which resolve those issues. The conclusion is that the XCF design is feasible and can be operational onboard the ISS by early in 2002

IFMIF - International Fusion Materials Irradiation Facility Conceptual Design Activity/Interim Report

International Nuclear Information System (INIS)

Rennich, M.J.

1995-12-01

Environmental acceptability, safety, and economic viability win ultimately be the keys to the widespread introduction of fusion power. This will entail the development of radiation- resistant and low- activation materials. These low-activation materials must also survive exposure to damage from neutrons having an energy spectrum peaked near 14 MeV with annual radiation doses in the range of 20 displacements per atom (dpa). Testing of candidate materials, therefore, requires a high-flux source of high energy neutrons. The problem is that there is currently no high-flux source of neutrons in the energy range above a few MeV. The goal, is therefore, to provide an irradiation facility for use by fusion material scientists in the search for low-activation and damage-resistant materials. An accellerator-based neutron source has been established through a number of international studies and workshops' as an essential step for materials development and testing. The mission of the International Fusion Materials Irradiation Facility (IFMIF) is to provide an accelerator-based, deuterium-lithium (D-Li) neutron source to produce high energy neutrons at sufficient intensity and irradiation volume to test samples of candidate materials up to about a full lifetime of anticipated use in fusion energy reactors. would also provide calibration and validation of data from fission reactor and other accelerator-based irradiation tests. It would generate material- specific activation and radiological properties data, and support the analysis of materials for use in safety, maintenance, recycling, decommissioning, and waste disposal systems

Accelerator conceptual design of the international fusion materials irradiation facility

International Nuclear Information System (INIS)

Sugimoto, M.; Kinsho, M.; Teplyakov, V.; Berwald, D.; Bruhwiler, D.; Peakock, M.; Rathke, J.; Deitinghoff, H.; Klein, H.; Pozimski, Y.; Volk, K.; Miyahara, A.; Olivier, M.; Piechowiak, E.; Tanabe, Y.

1998-01-01

The accelerator system of the international fusion materials irradiation facility (IFMIF) provides the 250-mA, 40-MeV continuous-wave deuteron beam at one of the two lithium target stations. It consists of two identical linear accelerator modules, each of which independently delivers a 125-mA beam to the common footprint of 20 cm x 5 cm at the target surface. The accelerator module consists of an ion injector, a 175 MHz RFQ and eight DTL tanks, and rf power supply system. The requirements for the accelerator system and the design concept are described. The interface issues and operational considerations to attain the proposed availability are also discussed. (orig.)

Improvement of the Kamide-Richmond-Matsushita scheme for the estimation of the three-dimensional current system

International Nuclear Information System (INIS)

Sun, W.; Lee, L.C.; Kamide, Y.; Akasofu, S.I.

1985-01-01

The algorithm developed by Kamide et al. (1981) has been extensively used in estimating ionospheric electric fields, ionospheric currents, and field-aligned currents over the entire polar region from ground magnetic chain data with a time resolution of about 5 min. However, in the considered algorithm and some other similar methods, geomagnetic field lines are assumed to be effectively radial, so that it is important to estimate errors resulting from such an assumption. In this paper, an iteration scheme is developed in which realistic curved geomagnetic field lines are employed. Both the ionospheric and field-aligned currents have been reestimated, and it was found that the correction to the ionospheric currents and the field-aligned currents obtained from the Kamide-Richmond-Matsushita scheme is 5-20 percent in the high-altitude (60 deg - 80 deg) region and is 15-35 deg in the middle latitude (less than 60 deg) region. 19 references

IFMIF-KEP. International fusion materials irradiation facility key element technology phase report

Energy Technology Data Exchange (ETDEWEB)

NONE

2003-03-01

The International Fusion Materials Irradiation Facility (IFMIF) is an accelerator-based D-Li neutron source designed to produce an intense neutron field that will simulate the neutron environment of a D-T fusion reactor. IFMIF will provide a neutron flux equivalent to 2 MW/m{sup 2}, 20 dpa/y in Fe, in a volume of 500 cm{sup 3} and will be used in the development and qualification of materials for fusion systems. The design activities of IFMIF are performed under an IEA collaboration which began in 1995. In 2000, a three-year Key Element Technology Phase (KEP) of IFMIF was undertaken to reduce the key technology risk factors. This KEP report describes the results of the three-year KEP activities in the major project areas of accelerator, target, test facilities and design integration. (author)

The NIF: An international high energy density science and inertial fusion user facility

Directory of Open Access Journals (Sweden)

Moses E.I.

2013-11-01

Full Text Available The National Ignition Facility (NIF, a 1.8-MJ/500-TW Nd:Glass laser facility designed to study inertial confinement fusion (ICF and high-energy-density science (HEDS, is operational at Lawrence Livermore National Laboratory (LLNL. A primary goal of NIF is to create the conditions necessary to demonstrate laboratory-scale thermonuclear ignition and burn. NIF experiments in support of indirect-drive ignition began late in FY2009 as part of the National Ignition Campaign (NIC, an international effort to achieve fusion ignition in the laboratory. To date, all of the capabilities to conduct implosion experiments are in place with the goal of demonstrating ignition and developing a predictable fusion experimental platform in 2012. The results from experiments completed are encouraging for the near-term achievement of ignition. Capsule implosion experiments at energies up to 1.6 MJ have demonstrated laser energetics, radiation temperatures, and symmetry control that scale to ignition conditions. Of particular importance is the demonstration of peak hohlraum temperatures near 300 eV with overall backscatter less than 15%. Important national security and basic science experiments have also been conducted on NIF. Successful demonstration of ignition and net energy gain on NIF will be a major step towards demonstrating the feasibility of laser-driven Inertial Fusion Energy (IFE. This paper will describe the results achieved so far on the path toward ignition, the beginning of fundamental science experiments and the plans to transition NIF to an international user facility providing access to HEDS and fusion energy researchers around the world.

The NIF: An international high energy density science and inertial fusion user facility

Science.gov (United States)

Moses, E. I.; Storm, E.

2013-11-01

The National Ignition Facility (NIF), a 1.8-MJ/500-TW Nd:Glass laser facility designed to study inertial confinement fusion (ICF) and high-energy-density science (HEDS), is operational at Lawrence Livermore National Laboratory (LLNL). A primary goal of NIF is to create the conditions necessary to demonstrate laboratory-scale thermonuclear ignition and burn. NIF experiments in support of indirect-drive ignition began late in FY2009 as part of the National Ignition Campaign (NIC), an international effort to achieve fusion ignition in the laboratory. To date, all of the capabilities to conduct implosion experiments are in place with the goal of demonstrating ignition and developing a predictable fusion experimental platform in 2012. The results from experiments completed are encouraging for the near-term achievement of ignition. Capsule implosion experiments at energies up to 1.6 MJ have demonstrated laser energetics, radiation temperatures, and symmetry control that scale to ignition conditions. Of particular importance is the demonstration of peak hohlraum temperatures near 300 eV with overall backscatter less than 15%. Important national security and basic science experiments have also been conducted on NIF. Successful demonstration of ignition and net energy gain on NIF will be a major step towards demonstrating the feasibility of laser-driven Inertial Fusion Energy (IFE). This paper will describe the results achieved so far on the path toward ignition, the beginning of fundamental science experiments and the plans to transition NIF to an international user facility providing access to HEDS and fusion energy researchers around the world.

Safeguards Guidance for Designers of Commercial Nuclear Facilities – International Safeguards Requirements for Uranium Enrichment Plants

Energy Technology Data Exchange (ETDEWEB)

Philip Casey Durst; Scott DeMuth; Brent McGinnis; Michael Whitaker; James Morgan

2010-04-01

For the past two years, the United States National Nuclear Security Administration, Office of International Regimes and Agreements (NA-243), has sponsored the Safeguards-by-Design Project, through which it is hoped new nuclear facilities will be designed and constructed worldwide more amenable to nuclear safeguards. In the course of this project it was recognized that commercial designer/builders of nuclear facilities are not always aware of, or understand, the relevant domestic and international safeguards requirements, especially the latter as implemented by the International Atomic Energy Agency (IAEA). To help commercial designer/builders better understand these requirements, a report was prepared by the Safeguards-by-Design Project Team that articulated and interpreted the international nuclear safeguards requirements for the initial case of uranium enrichment plants. The following paper summarizes the subject report, the specific requirements, where they originate, and the implications for design and construction. It also briefly summarizes the established best design and operating practices that designer/builder/operators have implemented for currently meeting these requirements. In preparing the subject report, it is recognized that the best practices are continually evolving as the designer/builder/operators and IAEA consider even more effective and efficient means for meeting the safeguards requirements and objectives.

Brote epidémico por Salmonella richmond en Castellón, España Epidemic outbreak caused by Salmonella richmond in Castellón, España

Directory of Open Access Journals (Sweden)

María Rosario Pac Sa

1998-02-01

Full Text Available Se efectuó un estudio de casos y controles para investigar un brote de gastroenteritis aguda declarado en un destacamento militar situado en una zona rural de Castellón, España. El objetivo del estudio fue conocer las causas del brote y adoptar medidas de control. En total se incluyó a 135 hombres de los 153 que componían dicho destacamento. Entre el 9 y el 11 de agosto de 1993 se notificaron 45 casos, cuya media de edad fue de 19,2 ± 1,5 años. La tasa de ataque fue de 33,3%. En el cuadro clínico predominaron diarreas (76%, vómitos (67%, náuseas (67% y dolor abdominal (28%. La mediana de la duración de los síntomas fue un día y la del período de incubación, 33 horas. Solo se hospitalizó a un paciente y la evolución de todos los afectados fue buena. En cinco de 14 coprocultivos realizados se aisló Salmonella richmond (6,7:y:1,2. También se detectó una asociación entre el consumo de agua de una acequia, que discurría próxima al campamento, y la enfermedad. Mediante un modelo de regresión logística se constató que el consumo del agua de esta fuente permaneció asociado con el estado de caso después de ajustar la asociación según la edad y el consumo de distintos alimentos (razón de posibilidades = 96,5; intervalo de confianza de 95%: 11,4 ­ 814,4. El riesgo de padecer la enfermedad aumentó con la cantidad de agua ingerida (prueba de tendencia X² = 65,4; P A case-control study was carried out to investigate an outbreak of acute gastroenteritis among a military detachment stationed in a rural area of Castellón, España. The purpose of the study was to determine the causes of the outbreak and develop control measures. Of the 153 men in the detachment, 135 were included in the study. Between 9 and 11 August 1993, 45 cases were reported; the patients' average age was 19.2 ± 1.5 years. The attack rate was 33.3%. The clinical picture was dominated by the following symptoms: diarrhea (76%, vomiting (67%, nausea (67%, and

Staged deployment of the International Fusion Materials Irradiation Facility

International Nuclear Information System (INIS)

Takeuchi, H.; Sugimoto, M.; Nakamura, H.

2001-01-01

The International Fusion Materials Irradiation Facility (IFMIF) employs an accelerator based D-Li intense neutron source as defined in the 1995-96 Conceptual Design Activity (CDA) study. In 1999, IEA mandated a review of the CDA IFMIF design for cost reduction without change to its original mission. This objective was accomplished by eliminating the previously assumed possibility of potential upgrade of IFMIF beyond the user requirements. The total estimated cost was reduced from $797.2 M to $487.8 M. An option of deployment in 3 stages was also examined to reduce the initial investment and annual expenditures during construction. In this scenario, full performance is achieved gradually with each interim stage as follows. 1st Stage: 20% operation for material selection for ITER breeding blanket, 2nd Stage: 50% operation to demonstrate materials performance of a reference alloy for DEMO, 3rd Stage: full performance operation ( 2MW/m 2 at 500cm 3 ) to obtain engineering data for potential DEMO materials under irradiation up to 100-200 dpa. In summary, the new, reduced cost IFMIF design and staged deployment still satisfies the original mission. The estimated cost of the 1st Stage facility is only $303.6 M making it financially much more attractive. Currently, IFMIF Key Element Technology Phase (KEP) is underway to reduce the key technology risk factors. (author)

International Scoping Study (ISS) for a future neutrino factory and Super-Beam facility. Detectors and flux instrumentation for future neutrino facilities

International Nuclear Information System (INIS)

Abe, T; Aihara, H; Andreopoulos, C; Ankowski, A; Badertscher, A; Battistoni, G; Blondel, A; Bouchez, J; Bross, A; Ellis, M; Bueno, A; Camilleri, L; Campagne, J E; Cazes, A; Cervera-Villanueva, A; De Lellis, G; Di Capua, F; Ereditato, A; Esposito, L S

2009-01-01

This report summarises the conclusions from the detector group of the International Scoping Study of a future Neutrino Factory and Super-Beam neutrino facility. The baseline detector options for each possible neutrino beam are defined as follows: 1. A very massive (Megaton) water Cherenkov detector is the baseline option for a sub-GeV Beta Beam and Super Beam facility. 2. There are a number of possibilities for either a Beta Beam or Super Beam (SB) medium energy facility between 1-5 GeV. These include a totally active scintillating detector (TASD), a liquid argon TPC or a water Cherenkov detector. 3. A 100 kton magnetized iron neutrino detector (MIND) is the baseline to detect the wrong sign muon final states (golden channel) at a high energy (20-50 GeV) neutrino factory from muon decay. A 10 kton hybrid neutrino magnetic emulsion cloud chamber detector for wrong sign tau detection (silver channel) is a possible complement to MIND, if one needs to resolve degeneracies that appear in the δ-θ 13 parameter space.

Accelerator conceptual design of the international fusion materials irradiation facility

Energy Technology Data Exchange (ETDEWEB)

Sugimoto, M.; Kinsho, M. [Japan Atomic Energy Res. Inst., Tokai, Ibaraki (Japan). Intense Neutron Source Lab.; Jameson, R.A.; Blind, B. [Los Alamos National Lab., NM (United States); Teplyakov, V. [Institute for High Energy Physics, Moscow (Russian Federation); Berwald, D.; Bruhwiler, D.; Peakock, M.; Rathke, J. [Northrop Grumman Corp., Bethpage, NY (United States); Deitinghoff, H.; Klein, H.; Pozimski, Y.; Volk, K. [Johann Wolfgang Goethe Univ., Frankfurt (Germany). Inst. fur Angewandte Phys.; Ferdinand, R.; Lagniel, J.-M. [CEA Saclay LNS, Gif-sur-Yvette (France); Miyahara, A. [Teikyo Univ., Tokyo (Japan); Olivier, M. [CEA DSM, Saclay, Gif-sur-Yvette (France); Piechowiak, E. [Northrop Grumman Corp., Baltimore, MD (United States); Tanabe, Y. [Toshiba Corp., Tsurumi-ku, Yokohama (Japan)

1998-10-01

The accelerator system of the international fusion materials irradiation facility (IFMIF) provides the 250-mA, 40-MeV continuous-wave deuteron beam at one of the two lithium target stations. It consists of two identical linear accelerator modules, each of which independently delivers a 125-mA beam to the common footprint of 20 cm x 5 cm at the target surface. The accelerator module consists of an ion injector, a 175 MHz RFQ and eight DTL tanks, and rf power supply system. The requirements for the accelerator system and the design concept are described. The interface issues and operational considerations to attain the proposed availability are also discussed. (orig.) 8 refs.

Utilizing the Fast Flux Test Facility for international passive safety testing

International Nuclear Information System (INIS)

Shen, P.K.; Padilla, A.; Lucoff, D.M.; Waltar, A.E.

1991-01-01

A two-phased approach has been undertaken in the Fast Flux Test Facility (FFTF) to conduct passive safety testing. Phase I (1986 to 1987) was structured to obtain an initial understanding of the reactivity feedback components. The planned Phase II (1992 to 1993) international program will extend the testing to include static and dynamic feedback measurements, transient and demonstration tests, and gas expansion module (GEM) reactivity tests. The primary objective is to meet the needs for safety analysis code validation, with particular emphasis on reducing the uncertainties associated with structure reactivity feedback. Program scope and predicted FFTF responses are discussed and illustrated. (author)

Seismic risk analysis for the Atomics International Nuclear Materials Development Facility, Santa Susana California

International Nuclear Information System (INIS)

1978-01-01

This report presents the results of a detailed seismic risk analysis of the Nuclear Materials Development Facility (NMDF) operated by Atomics International at Santa Susana, California. The historical seismic record was established after a review of available literature, consultation with operators of local seismic arrays and examination of appropriate seismic data bases including the USGS, California Institute of Technology and NEIS data bases. The resulting seismic record, covering the period 1969 to 1977, was used to identify all possible sources of seismicity that could affect the site. The best estimate curve indicates that the facility will experience 30% g with a return period of 55 years and 60% g with a return period of 750 years

Seismic risk analysis for the Atomics International Nuclear Materials Development Facility, Santa Susana California

Energy Technology Data Exchange (ETDEWEB)

1978-12-29

This report presents the results of a detailed seismic risk analysis of the Nuclear Materials Development Facility (NMDF) operated by Atomics International at Santa Susana, California. The historical seismic record was established after a review of available literature, consultation with operators of local seismic arrays and examination of appropriate seismic data bases including the USGS, California Institute of Technology and NEIS data bases. The resulting seismic record, covering the period 1969 to 1977, was used to identify all possible sources of seismicity that could affect the site. The best estimate curve indicates that the facility will experience 30% g with a return period of 55 years and 60% g with a return period of 750 years.

Legal Aspects of international cooperation in the physical protection of nuclear facilities and materials

International Nuclear Information System (INIS)

Herron, L.W.

1981-10-01

This paper provides a detailed analysis of developments in the number field having led the IAEA to promote international cooperation in ensuring adequate physical protection of nuclear facilities and materials. This work resulted in the establishment of recommendations and guidelines in this respect and culminated in the development of the 1980 Convention on the Physical Protection of Nuclear Materials. (NEA) [fr

26 CFR 1.142(a)(5)-1 - Exempt facility bonds: Sewage facilities.

Science.gov (United States)

2010-04-01

... 26 Internal Revenue 2 2010-04-01 2010-04-01 false Exempt facility bonds: Sewage facilities. 1.142... Bonds § 1.142(a)(5)-1 Exempt facility bonds: Sewage facilities. (a) In general. Under section 103(a), a... in section 142(a) is a sewage facility. This section defines the term sewage facility for purposes of...

"They Are Hiring the White Women but They Won't Hire the Colored Women": Black Women Confront Racism and Sexism in the Richmond Shipyards During World War II

OpenAIRE

Tuft, Paige

2015-01-01

During World War II, black women migrated largely out of the South to take advantage of the growing defense industries in California. Black women flocked to the shipbuilding industry in Richmond for the great economic opportunities industrial jobs offered. What they found when they arrived and attempted to secure jobs in the shipyards hardly lived up to their dreams and expectations. Black women found themselves faced with dual discrimination due to their race and gender. The shortage of a...

Reinforcing the foundations of ornithological nomenclature: Filling the gaps in Sherborn's and Richmond's historical legacy of bibliographic exploration.

Science.gov (United States)

Dickinson, Edward C

2016-01-01

Due to its public popularity, ornithology has a huge corpus of scientific publication for a relatively small number of species. Although there are global checklists of currently recognised taxa, there has been only limited, mainly individual, effort to build a nomenclatural database that the science of ornithology deserves. This is especially true in relation to concise synonymies. With the arrival of ZooBank and the Biodiversity Heritage Library, the time has come to develop synonymies and to add fuller bibliographic detail to databases. The preparation for both began at the start of the 20(th) century with extensive work by Sherborn and Richmond. I discuss their legacy, offer notes on significant work since then, and provide suggestions for what remains to be done. To make solid the foundations for ornithological nomenclature and taxonomy, especially for synonymies, ornithologists will need to collaborate much more and contribute to the digital infrastructure.

Nuclear and particle physics research at the University of Richmond. Progress report, November 1, 1995 - October 31, 1996

International Nuclear Information System (INIS)

Vineyard, M.F.; Gilfoyle, G.P.; Major, R.W.

1996-01-01

Summarized in this report is the progress achieved during the period from November 1, 1995 to October 31, 1996. The experimental work described in this report is in preparation for the electromagnetic nuclear physics research program in Hall B at Thomas Jefferson National Accelerator Facility (TJNAF). Much progress has been made this year toward the realization of the physics program in Hall B. The Program Advisory Committee (PAC) reviewed all of the Hall B physics proposals and assigned scientific ratings to those not previously rated. Updates on these proposals were submitted to the PAC for this review and can be found in this report. Also included in this report is a summary of the progress achieved on an experiment that the authors are collaborating on to measure rare radiative decays of the φ meson. This experiment received the PAC's highest rating and will use the Hall B photon tagger and a lead glass calorimeter housed in the alcove upstream of the beam dump. After nearly a decade of planning and construction, the CEBAF Large Acceptance Spectrometer (CLAS) will be commissioned next year. The authors have been members of the CLAS Collaboration since its inception and their contributions to the construction of the CLAS include the development of the drift-chamber gas system, drift-chamber software, and controls software. Major has been leading the effort in the construction of the gas system. In the last year, the gas system components built at the University of Richmond have been installed in the Hall B gas shed and the initial operation of the system has begun. Gilfoyle is coordinating the software development for the CLAS drift chambers. Considerable progress has been made this year in developing software for the analysis of the drift-chamber data. Vineyard served as coordinator of the γ3 Running Period for the CLAS Collaboration and he is also responsible for the development of the drift-chamber gas system controls

IFMIF, International Fusion Materials Irradiation Facility conceptual design activity cost report

International Nuclear Information System (INIS)

Rennich, M.J.

1996-12-01

This report documents the cost estimate for the International Fusion Materials Irradiation Facility (IFMIF) at the completion of the Conceptual Design Activity (CDA). The estimate corresponds to the design documented in the Final IFMIF CDA Report. In order to effectively involve all the collaborating parties in the development of the estimate, a preparatory meeting was held at Oak Ridge National Laboratory in March 1996 to jointly establish guidelines to insure that the estimate was uniformly prepared while still permitting each country to use customary costing techniques. These guidelines are described in Section 4. A preliminary cost estimate was issued in July 1996 based on the results of the Second Design Integration Meeting, May 20--27, 1996 at JAERI, Tokai, Japan. This document served as the basis for the final costing and review efforts culminating in a final review during the Third IFMIF Design Integration Meeting, October 14--25, 1996, ENEA, Frascati, Italy. The present estimate is a baseline cost estimate which does not apply to a specific site. A revised cost estimate will be prepared following the assignment of both the site and all the facility responsibilities

Internalized stigma among patients with schizophrenia in Ethiopia: a cross-sectional facility-based study

Directory of Open Access Journals (Sweden)

Assefa Dereje

2012-12-01

Full Text Available Abstract Background Despite the potential impact on treatment adherence and recovery, there is a dearth of data on the extent and correlates of internalized stigma in patients with schizophrenia in low income countries. We conducted a study to determine the extent, domains and correlates of internalized stigma amongst outpatients with schizophrenia in Ethiopia. Methods The study was a cross-sectional facility-based survey conducted at a specialist psychiatric hospital in Addis Ababa, Ethiopia. Consecutive consenting individuals with a diagnosis of schizophrenia were recruited and assessed using an Amharic version of the Internalized Stigma of Mental Illness (ISMI scale. Results Data were collected from 212 individuals, who were mostly single (71.2%, unemployed (70.3% and male (65.1%. Nearly all participants (97.4% expressed agreement to at least one stigma item contained in the ISMI; 46.7% had a moderate to high mean stigma score. Rural residence (OR = 5.67; 95% CI = 2.30, 13.00; p  Conclusion Internalized stigma is a major problem among persons with schizophrenia in this outpatient setting in Ethiopia. Internalized stigma has the potential to substantially affect adherence to medication and is likely to affect the recovery process.

Status and possible prospects of an international fusion materials irradiation facility

International Nuclear Information System (INIS)

Cozzani, F.

1999-01-01

Structural materials for future DT fusion power reactors will have to operate under intense neutron fields with energies up to 14 MeV and fluences in the order of 2 MW/m 2 per year. As environmental acceptability, safety considerations and economic viability will be ultimately the keys to the widespread introduction of fusion power, the development of radiation-resistant and low activation materials would contribute significantly to fusion development. For this purpose, testing of materials under irradiation conditions close to those expected in a fusion power station would require the availability, in an appropriate time framework, of an intense, high-energy neutron source. Recent advances in linear accelerator technology, in small specimens testing technology, and in the comprehension of damage phenomena, lead to the conclusion that an accelerator-based D-Li neutron source, with beam energy variability, would provide the most realistic option for a fusion materials testing facility. Under the auspices of the IEA, an international effort (EU, Japan, US, RF) to carry out the conceptual design activities (CDA) of an international fusion materials irradiation facility (IFMIF), based on the D-Li concept, have been carried out successfully. A final conceptual design report was produced at the end of 1996. A phase of conceptual design evaluation (CDE), presently underway, is extending and further refining some of the conceptual design details of IFMIF. The results indicate that an IFMIF-class installation would be technically feasible and could meet its mission objectives. However, a suitable phase of Engineering Validation, to carry out some complementary R and D and prototyping, would still be needed to resolve a few key technical uncertainties before the possibility to proceed toward detailed design and construction could be explored. (orig.)

IFMIF (International Fusion Materials Irradiation Facility) key element technology phase task description

Energy Technology Data Exchange (ETDEWEB)

Ida, M.; Nakamura, H.; Sugimoto, M.; Yutani, T.; Takeuchi, H. [eds.] [Japan Atomic Energy Research Inst., Tokai Research Establishment, Fusion Neutron Laboratory, Tokai, Ibaraki (Japan)

2000-08-01

In 2000, a 3 year Key Element technology Phase (KEP) of the International Fusion Materials Irradiation Facility (IFMIF) has been initiated to reduce the key technology risk factors needed to achieve continuous wave (CW) beam with the desired current and energy and to reach the corresponding power handling capabilities in the liquid lithium target system. In the KEP, the IFMIF team (EU, Japan, Russian Federation, US) will perform required tasks. The contents of the tasks are described in the task description sheet. As the KEP tasks, the IFMIF team have proposed 27 tasks for Test Facilities, 12 tasks for Target, 26 tasks for Accelerator and 18 tasks for Design Integration. The task description by RF is not yet available. The task items and task descriptions may be added or revised with the progress of KEP activities. These task description sheets have been compiled in this report. After 3 years KEP, the results of the KEP tasks will be reviewed. Following the KEP, 3 years Engineering Validation Phase (EVP) will continue for IFMIF construction. (author)

Readiness to adopt a performance measurement system for ...

African Journals Online (AJOL)

5 Department of Psychology, Virginia Commonwealth University, Richmond, VA, USA. Corresponding .... treatment providers, presentations at treat- ment facilities to discuss the need for such a system, and marketing by means of posters.

Utilizing Interns in Facilities Management

Science.gov (United States)

Judkins, Clarissa; Morris, John P.; Molocznik, Chuck

2011-01-01

Facilities management is rapidly changing and developing from a position an individual stumbles into--or work one's way up through--to a discipline and vocation all of its own. There is a need for a collaborative strategy among leaders in practice, education, and research to share knowledge and experience and to establish professional and ethical…

Magnetic fields of AM band radio broadcast signals at the Richmond Field Station

International Nuclear Information System (INIS)

Becker, Alex; Frangos, William

1998-01-01

Non-invasive sensing of the shallow subsurface is necessary for detection and delineation of buried hazardous wastes, monitoring of the condition of clay containment caps, and a variety of other purposes. Electromagnetic methods have proven to be effective in environmental site characterization where there is a need for increased resolution in subsurface characterization. Two considerations strongly suggest the use of frequencies between 100 kHz and 100 MHz for such applications: 1) the induction response of many targets is small due to small size, and 2) a need to determine both the electrical conductivity and dielectric permittivity which are related to chemistry and hydrology. Modeling and physical parameter studies confirm that measurements at frequencies between 1 and 100 MHz can resolve variations in subsurface conductivity and permittivity. To provide the necessary technology for shallow subsurface investigations, we propose to exploit the concept of electromagnetic impedance, the ratio of orthogonal horizontal electric and magnetic fields. Prior to assembling the equipment for measuring surface impedance using controlled, local source it was felt prudent to measure the surface impedance of geological materials at the University of California at Berkeley's Richmond Field (RFS) using ambient energy in the broadcast band. As a first step toward this intermediate goal, we have examined and characterized local AM band radio signals in terms of both signal strength and polarization of the magnetic component as received at RFS. In addition, we have established the viability of a commercial radio-frequency magnetic sensor

International safeguards in large scale nuclear facilities

International Nuclear Information System (INIS)

Gupta, D.; Heil, J.

1977-01-01

The trend in the energy sector in most of the industrialized areas of the world shows rather clearly, that the rate of installation of nuclear plants will be very high and that the largest possible units of nuclear material handling and storage facilities will be built. Various experiments and analyses of measurement methods relevant to safeguards, in typical nuclear facilities like a fuel reprocessing or a fabrication plant, have shown that the associated measurement errors as obtained under normal operating conditions are such that they are mainly dominated by systematic errors and that such systematic errors may lie in the range of percentages of the measured amount so that a material balance in such a plant could not normally be closed with high accuracy. The simplest way of going around the problem would be to increase the frequency of striking a material balance over a given period of time. This could however lead to an anormous increase in the technical and financial burden for the operator of a facility. The present paper analyses this problem in some detail for some facilities and shows that with a properly developed information system in such plants and a combination of containment, surveillance and accountancy measures, safeguards statements for relatively low significant amounts can be made with the attainable range of measurement accuracies

The internationalisation of research facilities

International Nuclear Information System (INIS)

Sabine, T.M.

1999-01-01

Full text: During the past twenty five years arrangements have been made for sharing the use of major national research facilities amongst the world community of neutron users. The administrative requirements are simple. Scientists are invited to apply for measurement time. The scientific merit of the application is assessed by a committee appointed by the host organisation. If the application is considered to have sufficient merit time is allocated. The only costs to the user are transport and living expenses. These arrangements have advantages for users and for hosts. The user can apply for time on the most suitable instrument. The host in the user country is freed from the responsibility of supplying all instruments. It can specialise in those instruments in which it has particular expertise. The host retains, through its committee, complete control over the use of instruments. The amount of time allocated to international users is dependent on the national demand. The result is efficient use of national facilities. An equally important result is the interaction between members of the international scientific community. Australian scientists routinely use overseas facilities however Australia has refused to join the international group. There is international resentment to this attitude. We have, for example powder diffraction facilities which others wish to use. We have no small-angle scattering facilities and must do our experiments at international centres. I will argue that we should join the international community now. The capacity of the replacement reactor will be far greater than the internal Australian requirements. We will become the natural host for users from countries in the Asian region. To enable us to make a smooth transition to this stage we should immediately advertise an international program for HIFAR

Proceedings of the first international seminar on seismic base isolation for nuclear power facilities

International Nuclear Information System (INIS)

1989-01-01

The First International Seminar on Seismic Base Isolation of Nuclear Power Facilities was organized by the authors of this paper. It was held in San Francisco, California, USA, on August 21--22, 1989, in conjunction with the tenth International Conference on Structural Mechanics in Reactor Technology (SMiRT-10). The purpose of the seminar was to provide an international forum for discussion on the application of base isolation to nuclear power plants and of its effectiveness in reducing seismic loads and permitting standard plant designs. It also provided an opportunity for technical interchange between base isolation system designers, structural engineers, and nuclear power plant engineers. Seismic isolation is certainly one of the most significant earthquake engineering developments in recent years. This was clearly demonstrated by the very large attendance at this seminar and the various papers presented. Isolation system act as filters that reduce the seismic forces and increase the ability of isolated structures and their contents to withstand the damaging effects of earthquake motions. Each individual paper has been cataloged separately

Facility effluent monitoring plan determinations for the 200 Area facilities

International Nuclear Information System (INIS)

Nickels, J.M.

1991-11-01

The following facility effluent monitoring plan determinations document the evaluations conducted for the Westinghouse Hanford Company 200 Area facilities (chemical processing, waste management, 222-S Laboratory, and laundry) on the Hanford Site in south central Washington State. These evaluations determined the need for facility effluent monitoring plans for the 200 Area facilities. The facility effluent monitoring plan determinations have been prepared in accordance with A Guide for Preparing Hanford Site Facility Effluent Monitoring Plans, WHC-EP-0438 (WHC 1991). The Plutonium/Uranium Extraction Plant and UO 3 facility effluent monitoring plan determinations were prepared by Los Alamos Technical Associates, Richland, Washington. The Plutonium Finishing Plant, Transuranic Waste Storage and Assay Facility, T Plant, Tank Farms, Low Level Burial Grounds, and 222-S Laboratory determinations were prepared by Science Applications International Corporation of Richland, Washington. The B Plant Facility Effluent Monitoring Plan Determination was prepared by ERCE Environmental Services of Richland, Washington

Proceedings of the international workshop on hadron facility technology

Energy Technology Data Exchange (ETDEWEB)

Thiessen, H.A. (comp.)

1987-12-01

The conference included papers on facility plans, beam dynamics, accelerator hardware, and experimental facilities. Individual abstracts were prepared for 43 papers in the conference proceedings. (LEW)

Development of lithium target system in engineering validation and engineering design activity of the international fusion materials irradiation facility (IFMIF/EVEDA)

International Nuclear Information System (INIS)

Wakai, Eiichi; Kondo, Hiroo; Sugimoto, Masayoshi; Ida, Mizuho; Kanemura, Takuji; Watanabe, Kazuyoshi; Fujishiro, Kouji; Edao, Yuuki; Niitsuma, Shigeto; Kimura, Haruyuki; Fukada, Satoshi; Hiromoto, Tetsushi; Shigeharu, Satoshi; Yagi, Jyuro; Furukawa, Tomohiro; Hirakawa, Yasushi; Suzuki, Akihiro; Terai, Takayuki; Horiike, Hiroshi; Hoashi, Eiji; Suzuki, Sachiko; Yamaoka, Nobuo; Serizawa, Hisashi; Kawahito, Yosuke; Tsuji, Yoshiyuki; Furuya, Kazuyuki; Takeo, Fumio

2012-01-01

Engineering validation and engineering design activity (EVEDA) for the international fusion materials irradiation facility (IFMIF) has been conducted since 2007. Research and development of the Lithium target facility is an important part of this activity. We constructed a world largest liquid Lithium test loop with a capacity of 5000 L in 2010 and successfully completed the first stage validation tests (functional tests of components and Lithium flow test (flow velocity 15 m/s at the target). In the present article, recent results of the EVEDA activity for the Lithium target facility and related technologies on liquid Lithium are reviewed. (author)

Household/Zonal Socioeconomic Characteristics and Tour Making: Case of Richmond/Tri-Cities Model Region in Virginia

Directory of Open Access Journals (Sweden)

Xueming CHEN

2014-06-01

Full Text Available This paper statistically assesses the impacts of household/zonal socio economic characteristics on tour making within the Richmond/Tri-Cities Model Region, Virginia, United States, based on the dataset made available through the 2009 Virginia National Household Travel Survey (NHTS Add-On Program. The tour analysis distinguishes nine tour types (three simple tours and six complex tours stratified by aggregate tour purposes of work (including school and other subsistence activities, maintenance and discretionary. A series of regression model runs have yielded the following conclusions: First, at aggregate level, the number of drivers, median household income, household size, number of workers, and zonal walking modal share are statistically significant and positively impact tour frequency. Tour length and complexity are positively related to household income and number of vehicles, but negatively related to zonal walking modal share. Second, at an individual tour type level, each tour type’s frequency/length/complexity is impacted by a different set of household/zonal socioeconomic characteristics. Zonal socioeconomic characteristics have little or no impacts on household tour making. It is recognized that many unknown factors may also have impacted tour activities, which require further in-depth studies in order to better explain complex tours.

Photovoltaic Engineering Testbed: A Facility for Space Calibration and Measurement of Solar Cells on the International Space Station

Science.gov (United States)

Landis, Geoffrey A.; Bailey, Sheila G.; Jenkins, Phillip; Sexton, J. Andrew; Scheiman, David; Christie, Robert; Charpie, James; Gerber, Scott S.; Johnson, D. Bruce

2001-01-01

The Photovoltaic Engineering Testbed ("PET") is a facility to be flown on the International Space Station to perform calibration, measurement, and qualification of solar cells in the space environment and then returning the cells to Earth for laboratory use. PET will allow rapid turnaround testing of new photovoltaic technology under AM0 conditions.

Atomics International fuel fabrication facility and low enrichment program [contributed by T.A. Moss, AI

International Nuclear Information System (INIS)

Moss, T.A.

1993-01-01

The AI facility is approximately 30,000 square feet in area and consists of four general areas. One area is devoted to the production of UAl x powder. It consists of a series of arc melting furnaces, crushing lines, glove boxes, and compacting presses. The second area is used for the rolling of fuel plates. The third area is used for the machining of the plates to final size and also the machining of the fuel elements. In the fourth area the fuel plates are swaged into assemblies, and all welding and inspection operations are performed. As part of the lower enrichment program we are scheduled to put a second UAl x powder line into operation and we have had to expand some of our storage area. Under the low enrichment program the AI fuel facility will be modified to accommodate a separate low enrichment Al x production line and compacting line. This facility modification should be done by the end of the fiscal year. We anticipate producing fuel with an enrichment slightly less than 20% We anticipate powder being available for plate production shortly after the facility is completed. Atomics International is scheduled to conduct plate LEU verification work using fully enriched material in the June-July time period, at which time we will investigate what level of uranium loadings we can go to using the current process. It is anticipated that 55 volume percent uranium compound in our fuel form can be achieved

GEOSAF Part II. Demonstration of the operational and long-term safety of geological disposal facilities for radioactive waste. IAEA international intercomparison and harmonization project

Energy Technology Data Exchange (ETDEWEB)

Kumano, Yumiko; Bruno, Gerard [International Atomic Energy Agency, Vienna (Austria). Vienna International Centre; Tichauer, Michael [IRSN, Institut de Radioprotection et de Surete Nucleaire, Fontenay-aux-Roses (France); Hedberg, Bengt [Swedish Radiation Safety Authority, Stockholm (Sweden)

2015-07-01

International intercomparison and harmonization projects are one of the mechanisms developed by the IAEA for examining the application and use of safety standards, with a view to ensuring their effectiveness and working towards harmonization of approaches to the safety of radioactive waste management. The IAEA has organized a number of international projects on the safety of radioactive waste management; in particular on the issues related to safety demonstration for radioactive waste management facilities. In 2008, GEOSAF, Demonstration of The Operational and Long-Term Safety of Geological Disposal Facilities for Radioactive Waste, project was initiated. This project was completed in 2011 by delivering a project report focusing on the safety case for geological disposal facilities, a concept that has gained in recent years considerable prominence in the waste management area and is addressed in several international safety standards. During the course of the project, it was recognized that little work was undertaken internationally to develop a common view on the safety approach related to the operational phase of a geological disposal although long-term safety of disposal facility has been discussed for several decades. Upon completion of the first part of the GEOSAF project, it was decided to commence a follow-up project aiming at harmonizing approaches on the safety of geological disposal facilities for radioactive waste through the development of an integrated safety case covering both operational and long-term safety. The new project was named as GEOSAF Part II, which was initiated in 2012 initially as 2-year project, involving regulators and operators. GEOSAF Part II provides a forum to exchange ideas and experience on the development and review of an integrated operational and post-closure safety case for geological disposal facilities. It also aims at providing a platform for knowledge transfer. The project is of particular interest to regulatory

Hazard evaluation of The International Fusion Materials Irradiation Facility

Energy Technology Data Exchange (ETDEWEB)

Burgazzi, Luciano [ENEA-Centro Ricerche ' Ezio Clementel' , Advanced Physics Technology Division, Via Martiri di Monte Sole, 4, 40129 Bologna (Italy)]. E-mail: burgazzi@bologna.enea.it

2005-01-15

The International Fusion Materials Irradiation Facility (IFMIF) is aimed to provide an intense neutron source by a high current deuteron linear accelerator and a high-speed lithium flow target, for testing candidate materials for fusion. Liquid lithium is being circulated through a loop and is kept at a temperature above its freezing point. In the frame of the design phase called Key Element technology Phase (KEP), jointly performed by an international team to verify the most important risk factors, safety assessment of the whole plant has been required in order to identify the hazards associated with the plant operation. This paper discusses the safety assessments that were performed and their outcome: Failure Mode and Effect Analysis (FMEA) approach has been adopted in order to accomplish the task. Main conclusions of the study is that, on account of the safety and preventive measures adopted, potential plant related hazards are confined within the IFMIF security boundaries and great care must be exercised to protect workers and site personnel from operating the plant. The analysis has provided as a result a set of Postulated Initiating Events (PIEs), that is off-normal events, that could result in hazardous consequences for the plant, together with the total frequency and the list of component failures which could induce the PIE: this assures the exhaustive list of major initiating events of accident sequences, helpful to the further accident sequence analysis phase. Finally, for each one of the individuated PIEs, the evaluation of the accident evolution, in terms of effects on the plant and relative countermeasures, has allowed to verify that adequate measures are being taken both to prevent the accident occurrence and to cope with the accident consequences, thus assuring the fulfilment of the safety requirements.

How to improve the irradiation conditions for the International Fusion Materials Irradiation Facility

CERN Document Server

Daum, E

2000-01-01

The accelerator-based intense D-Li neutron source International Fusion Materials Irradiation Facility (IFMIF) provides very suitable irradiation conditions for fusion materials development with the attractive option of accelerated irradiations. Investigations show that a neutron moderator made of tungsten and placed in the IFMIF test cell can further improve the irradiation conditions. The moderator softens the IFMIF neutron spectrum by enhancing the fraction of low energy neutrons. For displacement damage, the ratio of point defects to cascades is more DEMO relevant and for tritium production in Li-based breeding ceramic materials it leads to a preferred production via the sup 6 Li(n,t) sup 4 He channel as it occurs in a DEMO breeding blanket.

US DOE surplus facilities management program (SFMP). International technology exchange activities

International Nuclear Information System (INIS)

Broderick, J.

1986-01-01

The Surplus Facilities Management Program is one of five remedial action programs established by the US Department of Energy (DOE) to eliminate potential hazards to the public and environment from radioactive contamination. These programs provide remedial actions at various facilities and sites previously used by the US Government in national atomic energy programs. Included are uranium ore milling sites, nuclear materials production plants, and research and development facilities. The DOE's five remedial action programs are: the Grand Junction Remedial Action Project; the Formerly Utilized Sites Remedial Action Project; the West Valley Demonstration Project; and the Surplus Facilities Management Program. The Surplus Facilities Management Program (SWMP) was established by DOE in 1978. There are presently over 300 shutdown facilities in the SFMP located at sites across the United States and in Puerto Rico. In some cases, remedial action involves decontaminating and releasing a facility for some other use. In other instances, facilities are completely demolished and removed from the site

Research activities by INS cyclotron facility

International Nuclear Information System (INIS)

1992-06-01

Research activities made by the cyclotron facility and the related apparatuses at Institute for Nuclear Study (INS), University of Tokyo, have been reviewed in terms of the associated scientific publications. This publication list, which is to be read as a continuation of INS-Rep.-608 (October, 1986), includes experimental works on low-energy nuclear physics, accelerator technology, instrumental developments, radiation physics and other applications in interdisciplinary fields. The publications are classified into the following four categories. (A) : Internal reports published in INS. (B) : Publications in international scientific journals on experimental research works done by the cyclotron facility and the related apparatuses at INS. Those made by outside users are also included. (C) : Publications in international scientific journals on experimental low-energy nuclear physics, which have been done by the staff of INS Nuclear Physics Division using facilities outside INS. (D) : Contributions to international conferences. (author)

The electron-ion scattering experiment ELISe at the International Facility for Antiproton and Ion Research (FAIR)-A conceptual design study

NARCIS (Netherlands)

Antonov, A. N.; Gaidarov, M. K.; Ivanov, M. V.; Kadrev, D. N.; Aiche, M.; Barreau, G.; Czajkowski, S.; Jurado, B.; Belier, G.; Chatillon, A.; Granier, T.; Taieb, J.; Dore, D.; Letourneau, A.; Ridikas, D.; Dupont, E.; Berthoumieux, E.; Panebianco, S.; Farget, F.; Schmitt, C.; Audouin, L.; Khan, E.; Tassan-Got, L.; Aumann, T.; Beller, P.; Boretzky, K.; Dolinskii, A.; Egelhof, P.; Emling, H.; Franzke, B.; Geissel, H.; Kelic-Heil, A.; Kester, O.; Kurz, N.; Litvinov, Y.; Muenzenberg, G.; Nolden, F.; Schmidt, K. -H.; Scheidenberger, Ch.; Simon, H.; Steck, M.; Weick, H.; Enders, J.; Pietralla, N.; Richter, A.; Schrieder, G.; Zilges, A.; Distler, M. O.; Merkel, H.; Mueller, U.; Junghans, A. R.; Lenske, H.; Fujiwara, M.; Suda, T.; Kato, S.; Adachi, T.; Hamieh, S.; Harakeh, M. N.; Kalantar-Nayestanaki, N.; Woertche, H.; Berg, G. P. A.; Koop, I. A.; Logatchov, P. V.; Otboev, A. V.; Parkhomchuk, V. V.; Shatilov, D. N.; Shatunov, P. Y.; Shatunov, Y. M.; Shiyankov, S. V.; Shvartz, D. I.; Skrinsky, A. N.; Chulkov, L. V.; Danilin, B. V.; Korsheninnikov, A. A.; Kuzmin, E. A.; Ogloblin, A. A.; Volkov, V. A.; Grishkin, Y.; Lisin, V. P.; Mushkarenkov, A. N.; Nedorezov, V.; Polonski, A. L.; Rudnev, N. V.; Turinge, A. A.; Artukh, A.; Avdeichikov, V.; Ershov, S. N.; Fomichev, A.; Golovkov, M.; Gorshkov, A. V.; Grigorenko, L.; Klygin, S.; Krupko, S.; Meshkov, I. N.; Rodin, A.; Sereda, Y.; Seleznev, I.; Sidorchuk, S.; Syresin, E.; Stepantsov, S.; Ter-Akopian, G.; Teterev, Y.; Vorontsov, A. N.; Kamerdzhiev, S. P.; Litvinova, E. V.; Karataglidis, S.; Alvarez Rodriguez, R.; Borge, M. J. G.; Ramirez, C. Fernandez; Garrido, E.; Sarriguren, P.; Vignote, J. R.; Fraile Prieto, L. M.; Lopez Herraiz, J.; Moya de Guerra, E.; Udias-Moinelo, J.; Amaro Soriano, J. E.; Rojo, A. M. Lallena; Caballero, J. A.; Johansson, H. T.; Jonson, B.; Nilsson, T.; Nyman, G.; Zhukov, M.; Golubev, P.; Rudolph, D.; Hencken, K.; Jourdan, J.; Krusche, B.; Rauscher, T.; Kiselev, D.; Trautmann, D.; Al-Khalili, J.; Catford, W.; Johnson, R.; Stevenson, P. D.; Barton, C.; Jenkins, D.; Lemmon, R.; Chartier, M.; Cullen, D.; Bertulani, C. A.; Heinz, A.

2011-01-01

The electron-ion scattering experiment ELISe is part of the installations envisaged at the new experimental storage ring at the International Facility for Antiproton and Ion Research (FAIR) in Darmstadt, Germany. It offers an unique opportunity to use electrons as probe in investigations of the

Experimental facilities for gas-cooled reactor safety studies. Task group on Advanced Reactor Experimental Facilities (TAREF)

International Nuclear Information System (INIS)

2009-01-01

In 2007, the NEA Committee on the Safety of Nuclear Installations (CSNI) completed a study on Nuclear Safety Research in OECD Countries: Support Facilities for Existing and Advanced Reactors (SFEAR) which focused on facilities suitable for current and advanced water reactor systems. In a subsequent collective opinion on the subject, the CSNI recommended to conduct a similar exercise for Generation IV reactor designs, aiming to develop a strategy for ' better preparing the CSNI to play a role in the planned extension of safety research beyond the needs set by current operating reactors'. In that context, the CSNI established the Task Group on Advanced Reactor Experimental Facilities (TAREF) in 2008 with the objective of providing an overview of facilities suitable for performing safety research relevant to gas-cooled reactors and sodium fast reactors. This report addresses gas-cooled reactors; a similar report covering sodium fast reactors is under preparation. The findings of the TAREF are expected to trigger internationally funded CSNI projects on relevant safety issues at the key facilities identified. Such CSNI-sponsored projects constitute a means for efficiently obtaining the necessary data through internationally co-ordinated research. This report provides an overview of experimental facilities that can be used to carry out nuclear safety research for gas-cooled reactors and identifies priorities for organizing international co-operative programmes at selected facilities. The information has been collected and analysed by a Task Group on Advanced Reactor Experimental Facilities (TAREF) as part of an ongoing initiative of the NEA Committee on the Safety of Nuclear Installations (CSNI) which aims to define and to implement a strategy for the efficient utilisation of facilities and resources for Generation IV reactor systems. (author)

The International Finance Facility for Immunisation: stakeholders' perspectives.

Science.gov (United States)

Crocker-Buque, Tim; Mounier-Jack, Sandra

2016-09-01

To evaluate stakeholders' understanding and opinions of the International Finance Facility for Immunisation (IFFIm); to identify factors affecting funding levels; and to explore the future use of IFFIm. Between July and September 2015, we interviewed 33 individuals from 25 organizations identified as stakeholders in IFFIm. In total 22.5 hours of semi-structured interviews were recorded, transcribed and analysed using a framework method. Stakeholders' understanding of IFFIm's financing mechanism and its outcomes varied and many stakeholders wanted more information. Participants highlighted that the change in the macro-economic environment following the 2008 financial crisis affected national policy in donor countries and subsequently the number of new commitments IFFIm received. Since Gavi is now seen as a successful and mature organization, participants stated that donors prefer to donate directly to Gavi. The pharmaceutical industry valued IFFIm for providing funding stability and flexibility. Other stakeholders valued IFFIm's ability to access funds early and enable Gavi to increase vaccine coverage. Overall, stakeholders thought IFFIm was successful, but they had divergent views about IFFIm's on-going role. Participants listed two issues where bond financing mechanisms may be suitable: emergency preparedness and outcome-based time-limited interventions. The benefit of pledging funds through IFFIm needs to be re-evaluated. There are potential uses for bond financing to raise funds for other global health issues, but these must be carefully considered against criteria to establish effectiveness, with quantifiable pre-defined outcome indicators to evaluate performance.

Internalized stigma among patients with schizophrenia in Ethiopia: a cross-sectional facility-based study

Science.gov (United States)

2012-01-01

Background Despite the potential impact on treatment adherence and recovery, there is a dearth of data on the extent and correlates of internalized stigma in patients with schizophrenia in low income countries. We conducted a study to determine the extent, domains and correlates of internalized stigma amongst outpatients with schizophrenia in Ethiopia. Methods The study was a cross-sectional facility-based survey conducted at a specialist psychiatric hospital in Addis Ababa, Ethiopia. Consecutive consenting individuals with a diagnosis of schizophrenia were recruited and assessed using an Amharic version of the Internalized Stigma of Mental Illness (ISMI) scale. Results Data were collected from 212 individuals, who were mostly single (71.2%), unemployed (70.3%) and male (65.1%). Nearly all participants (97.4%) expressed agreement to at least one stigma item contained in the ISMI; 46.7% had a moderate to high mean stigma score. Rural residence (OR = 5.67; 95% CI = 2.30, 13.00; p stigma score. Almost half of those who discontinued their treatment reported that they had done so because of perceived stigma. Those who had attempted suicide (45.3%) were more likely to have a high stigma score (OR = 2.29; 95% CI = 1.27, 4.11; p = 0.006). Over 60% of the variation in the experience of stigma was explained by four factors: social withdrawal (16.7%), perceived discrimination (14.1%), alienation (13.9%) and stereotype endorsement (12.7%). Conclusion Internalized stigma is a major problem among persons with schizophrenia in this outpatient setting in Ethiopia. Internalized stigma has the potential to substantially affect adherence to medication and is likely to affect the recovery process. PMID:23272796

Developing International Guidelines on Volcanic Hazard Assessments for Nuclear Facilities

Science.gov (United States)

Connor, Charles

2014-05-01

Worldwide, tremendous progress has been made in recent decades in forecasting volcanic events, such as episodes of volcanic unrest, eruptions, and the potential impacts of eruptions. Generally these forecasts are divided into two categories. Short-term forecasts are prepared in response to unrest at volcanoes, rely on geophysical monitoring and related observations, and have the goal of forecasting events on timescales of hours to weeks to provide time for evacuation of people, shutdown of facilities, and implementation of related safety measures. Long-term forecasts are prepared to better understand the potential impacts of volcanism in the future and to plan for potential volcanic activity. Long-term forecasts are particularly useful to better understand and communicate the potential consequences of volcanic events for populated areas around volcanoes and for siting critical infrastructure, such as nuclear facilities. Recent work by an international team, through the auspices of the International Atomic Energy Agency, has focused on developing guidelines for long-term volcanic hazard assessments. These guidelines have now been implemented for hazard assessment for nuclear facilities in nations including Indonesia, the Philippines, Armenia, Chile, and the United States. One any time scale, all volcanic hazard assessments rely on a geologically reasonable conceptual model of volcanism. Such conceptual models are usually built upon years or decades of geological studies of specific volcanic systems, analogous systems, and development of a process-level understanding of volcanic activity. Conceptual models are used to bound potential rates of volcanic activity, potential magnitudes of eruptions, and to understand temporal and spatial trends in volcanic activity. It is these conceptual models that provide essential justification for assumptions made in statistical model development and the application of numerical models to generate quantitative forecasts. It is a

European Facility for Antiproton and Ion Research (FAIR): the new international center for fundamental physics and its research program

International Nuclear Information System (INIS)

Fortov, Vladimir E; Sharkov, Boris Yu; Stöker, H

2012-01-01

The Facility for Antiproton and Ion Research (FAIR) accelerator center at Darmstadt, Germany, will provide the international scientific community with unique experimental opportunities of a scope and scale out of reach for any other large-scale facility in the world. With its staff of over 2500, it is expected to fundamentally expand our knowledge of hadron, nuclear, and atomic physics and their application to cosmology, astrophysics, and technology. In this review, the design details of the accelerator complex are discussed and the experimental research program for FAIR is presented. Particular attention is paid to experiments on the extreme state of matter arising from the isochoric heating of a material by heavy-ion beams. One of the largest facilities of its kind in Europe, FAIR is a part of the strategic development roadmap for the European Strategic Forum on Research Infrastructures (ESFRI). (physics of our days)

Revision of the recommended international general standard for irradiated foods and of the recommended international code of practice for the operation of radiation facilities used for the treatment of foods

International Nuclear Information System (INIS)

1981-11-01

In view of the findings and statements of the Joint FAO/IAEA/WHO Expert Committee on the Wholesomeness of Irradiated Food, convened in Geneva from 27 October to 3 November 1980, a Consultation Group, convened in Geneva from 1 to 3 July 1981 suggested the revision of the Recommended International General Standard for Irradiated Foods and of the Recommended International Code of Practice for the Operation of Radiation Facilities. The proposed changes are given and justified and the revised wording of the documents presented

IFMIF [International Fusion Materials Irradiation Facility], an accelerator-based neutron source for fusion components irradiation testing: Materials testing capabilities

International Nuclear Information System (INIS)

Mann, F.M.

1988-08-01

The International Fusion Materials Irradiation Facility (IFMIF) is proposed as an advanced accelerator-based neutron source for high-flux irradiation testing of large-sized fusion reactor components. The facility would require only small extensions to existing accelerator and target technology originally developed for the Fusion Materials Irradiation Test (FMIT) facility. At the extended facility, neutrons would be produced by a 0.1-A beam of 35-MeV deuterons incident upon a liquid lithium target. The volume available for high-flux (>10/sup 15/ n/cm/sup 2/-s) testing in IFMITF would be over a liter, a factor of about three larger than in the FMIT facility. This is because the effective beam current of 35-MeV deuterons on target can be increased by a factor of ten to 1A or more. Such an increase can be accomplished by funneling beams of deuterium ions from the radio-frequency quadruple into a linear accelerator and by taking advantage of recent developments in accelerator technology. Multiple beams and large total current allow great variety in available testing. For example, multiple simultaneous experiments, and great flexibility in tailoring spatial distributions of flux and spectra can be achieved. 5 refs., 2 figs., 1 tab

20th International Training Course (ITC-20) on the physical protection of nuclear facilities and materials evaluation report.

Energy Technology Data Exchange (ETDEWEB)

Ramirez, Amanda Ann

2008-09-01

The goal of this evaluation report is to provide the information necessary to improve the effectiveness of the ITC provided to the International Atomic Energy Agency Member States. This report examines ITC-20 training content, delivery methods, scheduling, and logistics. Ultimately, this report evaluates whether the course provides the knowledge and skills necessary to meet the participants needs in the protection of nuclear materials and facilities.

The new large-scale international facility for antiproton and ion research in Europe, FAIR

International Nuclear Information System (INIS)

Rosner, Guenther

2012-01-01

Full text: FAIR is currently the largest project in nuclear and particle physics worldwide, with investment costs of 1.6B euro in its first phase. It has been founded by Finland, France, Germany, India, Poland, Romania, Russia, Slovenia and Sweden in Oct. 2010. The facility will provide the international scientific community with a unique and technically innovative particle accelerator system to perform cutting-edge research in the sciences concerned with the basic structure of matter in: nuclear and particle physics, atomic and anti-matter physics, high density plasma physics, and applications in condensed matter physics, biology and the bio-medical sciences. The work horse of FAIR will be a 1.1 km circumference double ring of rapidly cycling 100 and 300 Tm synchrotrons, which will be used to produce high intensity secondary beams of anti-protons and very short-lived radioactive ions. A subsequent suite of cooler and storage rings will deliver anti-proton and heavy-ion beams of unprecedented quality regarding intensity and resolution. Large experimental facilities are presently being prototyped by the APPA, CBM, NuSTAR and PANDA Collaborations to be used by a global community of more than 3000 scientists from 2018. (author)

Post-remediation biomonitoring of pesticides and other contaminants in marine waters and sediment near the United Heckathorn Superfund Site, Richmond, California

Energy Technology Data Exchange (ETDEWEB)

LD Antrim; NP Kohn

2000-05-26

Marine sediment remediation at the United Heckathorn Superfund Site was completed in April 1997. Water and mussel tissues were sampled in February 1999 from four stations near Lauritzen Canal in Richmond, California, for Year 2 of post-remediation monitoring of marine areas near the United Heckathorn Site. Dieldrin and dichlorodiphenyl trichloroethane (DDT) were analyzed in water samples, tissue samples from resident mussels, and tissue samples from transplanted mussels deployed for 4 months. Concentrations of dieldrin and total DDT in water and total DDT in tissue were compared with Year 1 of post-remediation monitoring, and with preremediation data from the California State Mussel Watch program (tissues) and the Ecological Risk Assessment for the United Heckathorn Superfund Site (tissues and water). Mussel tissues were also analyzed for polychlorinated biphenyls (PCB), which were detected in sediment samples. Chlorinated pesticide concentrations in water samples were similar to preremediation levels and did not meet remediation goals. Mean dieidrin concentrations in water ranged from 0.62 rig/L to 12.5 ng/L and were higher than the remediation goal (0.14 ng/L) at all stations. Mean total DDT concentrations in water ranged from 14.4 ng/L to 62.3 ng/L and exceeded the remediation goal (0.59 ng/L) at all stations. The highest concentrations of both pesticides were found at the Lauritzen Canal/End station. Despite exceedence of the remediation goals, chlorinated pesticide concentrations in Lauritzen Canal water samples were notably lower in 1999 than in 1998. Tissue samples from biomonitoring organisms (mussels) provide an indication of the longer-term integrated exposure to contaminants in the water column, which overcomes the limitations of grab samples of water. Biomonitoring results indicated that the bioavailability of chlorinated pesticides has been reduced from preremediation levels both in the dredged area and throughout Richmond Harbor. Total DDT and

Expanding the role of internal facility assessments

Energy Technology Data Exchange (ETDEWEB)

Kolpa, R.L.; Levenson, J.B. [Argonne National Lab., IL (United States); Weaver, M.A. [Headquarters Air Force Materiel Command, Wright-Patterson AFB, OH (United States)

1996-05-01

The US Air Force (USAF) Environmental Compliance Assessment and Management Program (ECAMP) is an effective and comprehensive system to evaluate environmental compliance at individual USAF installations. The ECAMP assessment is typically performed by a team of experts from the installation`s Major Command (MAJCOM) Headquarters, and is often augmented with technical contractor support. As directed by Air Force policy, an external ECAMP assessment is required at a minimum of every three years for each installation. In the intervening years, each installation is required to perform an internal ECAMP assessment, with its own personnel and resources. Even though team composition differs, the internal and external ECAMP assessments are likely to be very similar in scope, objectives, and deliverables. For over nine years, Argonne National Laboratory (ANL) has supported several Air Force MAJCOMs in performing their external ECAMP assessments. More recently, ANL has also had the opportunity to provide technical support and training at individual installations during their preparation and conduct of internal ECAMP assessments. From that experience, the authors have learned that the quality and value of the internal assessment is enhanced by making it a vehicle for training, planning, and interaction among organizations. Various strategies and techniques have been successfully employed to derive maximum benefit and insight from the internal assessment process. Experiences that involve expanding the scope and objectives of internal assessments to meet specific goals are presented. The expansion of scope and objectives include preassessment training, planning, and evaluator interactions as part of the overall internal assessment process.

WORKSHOPS: Hadron facilities

International Nuclear Information System (INIS)

Anon.

1987-01-01

'Hadron facilities' – high intensity (typically a hundred microamps), medium energy (30-60 GeV) machines producing intense secondary beams of pions, kaons, etc., are being widely touted as a profitable research avenue to supplement what is learned through the thrust for higher and higher energies. This interest was reflected at an International Workshop on Hadron Facility Technology, held in Santa Fe, New Mexico. As well as invited talks describing the various projects being pushed in the US, Europe and Japan, the meeting included working groups covering linacs, beam dynamics, hardware, radiofrequency, polarized beams and experimental facilities

Guide for International Peer Reviews of Decommissioning Cost Studies for Nuclear Facilities

International Nuclear Information System (INIS)

LaGuardia, Thomas S.; Pescatore, Claudio; )

2014-01-01

Peer reviews are a standard co-operative OECD working tool that offer member countries a framework to compare experiences and examine best practices in a host of areas. The OECD Nuclear Energy Agency (NEA) has developed a proven methodology for conducting peer reviews in radioactive waste management and nuclear R and D. Using this methodology, the NEA Radioactive Waste Management Committee's Working Party on Decommissioning and Dismantling (WPDD) developed the present guide as a framework for decommissioning cost reviewers and reviewees to prepare for and conduct international peer reviews of decommissioning cost estimate studies for nuclear facilities. It includes checklists that will help national programmes or relevant organisations to assess and improve decommissioning cost estimate practices in the future. This guide will act as the NEA reference for conducting such international peer reviews. The remainder of this guide is divided into eight chapters. Chapter 2 describes gathering the cost estimate study and underpinning documents, reviewing the study and writing a final report. Chapter 3 provides a detailed checklist approach for the review of the cost study report. Chapter 4 provides checklists to assist in reviewing benchmarked information. Chapter 5 provides comments on the approach and recommendations for use of this guide. Chapters 6 and 7 provide the background material used in developing this guide and Chapter 8 provides a list of the abbreviations and acronyms used in this guide

Agreement Between the Government of India and the International Atomic Energy Agency for the Application of Safeguards to Civilian Nuclear Facilities. Addition to the List of Facilities Subject to Safeguards Under the Agreement

International Nuclear Information System (INIS)

2014-01-01

In accordance with Paragraph 14(a) of the Agreement between the Government of India and the International Atomic Energy Agency for the Application of Safeguards to Civilian Nuclear Facilities (hereinafter “the Agreement”), India shall notify the Agency in writing of its decision to offer any facility identified by India for Agency safeguards under the Agreement. Any facility so notified by India becomes subject to the Agreement as of the date of receipt by the Agency of such written notification from India, and is to be included in the Annex to the Agreement. On 11 March 2014, the Agency received from India written notification, pursuant to Paragraph 14(a) of the Agreement, of its decision to bring one additional facility under safeguards in accordance with the provisions of the Agreement. Pursuant to Paragraph 14 4(a) of the Agreement, the Annex to the Agreement has been updated and is reproduced in this document for the information of all Members of the Agency

Agreement Between the Government of India and the International Atomic Energy Agency for the Application of Safeguards to Civilian Nuclear Facilities. Addition to the List of Facilities Subject to Safeguards Under the Agreement

International Nuclear Information System (INIS)

2014-01-01

In accordance with Paragraph 14(a) of the Agreement between the Government of India and the International Atomic Energy Agency for the Application of Safeguards to Civilian Nuclear Facilities (hereinafter “the Agreement”), India shall notify the Agency in writing of its decision to offer any facility identified by India for Agency safeguards under the Agreement. Any facility so notified by India becomes subject to the Agreement as of the date of receipt by the Agency of such written notification from India, and is to be included in the Annex to the Agreement. On 11 March 2014, the Agency received from India written notification, pursuant to Paragraph 14(a) of the Agreement, of its decision to bring one additional facility under safeguards in accordance with the provisions of the Agreement. Pursuant to Paragraph 14 4(a) of the Agreement, the Annex to the Agreement has been updated and is reproduced in this document for the information of all Members of the Agency [es

Combustion Research Facility

Data.gov (United States)

Federal Laboratory Consortium — For more than 30 years The Combustion Research Facility (CRF) has served as a national and international leader in combustion science and technology. The need for a...

17th International Workshop on Neutrino Factories and Future Neutrino Facilities Search

CERN Document Server

2015-01-01

NuFact15 is the seventeenth in a series that started in 1999 as an important yearly workshop with emphasis on future neutrino projects. This will be the first edition in Latin America, showing the scientific growth of this field. The main goals of the workshop are to review the progress on studies of future facilities able to improve on measurements of the properties of neutrinos and charged lepton flavor violation as well as new phenomena searches beyond the capabilities of presently planned experiments. Since such progress in the neutrino sector could require innovation in neutrino beams, the role of a neutrino factory within future HEP initiatives will be addressed. The workshops are not only international but also interdisciplinary in that experimenters, theorists and accelerator physicists from the Asian, American and European regions share expertise with the common goal of designing the next generation of experiments.

Radioactive waste safety appraisal. An international peer review of the licence application for the Australian near surface radioactive waste disposal facility. Report of the IAEA International Review Team

International Nuclear Information System (INIS)

2004-05-01

Radioactive waste has been generated in Australia for a number of decades from the production and use of radioactive materials in medicine and industry, from the processing of various minerals containing natural radionuclides and from various research activities. It has been decided in the overall interest of safety and security to develop a radioactive waste disposal facility to accommodate the low level and short lived intermediate level waste, which make up the bulk of the waste, other than mining and minerals processing residues. A site selection process has been undertaken and environmental impact statement report prepared and approved. A licence application has been submitted to the national nuclear regulatory authority, the Australian Radiation Protection and Nuclear Safety Agency (ARPANSA) for siting, construction and operation of the facility. In order to assist the CEO of ARPANSA with his deliberations in this regard a request was made to the IAEA, in terms of its statutory mandate to establish international safety standards for radioactive waste safety and to provide for their application, to undertake an international peer review of the licence application and to advise the CEO accordingly. The outcome and recommendations of this peer review are presented in the report

International low level waste disposal practices and facilities

International Nuclear Information System (INIS)

Nutt, W.M.

2011-01-01

The safe management of nuclear waste arising from nuclear activities is an issue of great importance for the protection of human health and the environment now and in the future. The primary goal of this report is to identify the current situation and practices being utilized across the globe to manage and store low and intermediate level radioactive waste. The countries included in this report were selected based on their nuclear power capabilities and involvement in the nuclear fuel cycle. This report highlights the nuclear waste management laws and regulations, current disposal practices, and future plans for facilities of the selected international nuclear countries. For each country presented, background information and the history of nuclear facilities are also summarized to frame the country's nuclear activities and set stage for the management practices employed. The production of nuclear energy, including all the steps in the nuclear fuel cycle, results in the generation of radioactive waste. However, radioactive waste may also be generated by other activities such as medical, laboratory, research institution, or industrial use of radioisotopes and sealed radiation sources, defense and weapons programs, and processing (mostly large scale) of mineral ores or other materials containing naturally occurring radionuclides. Radioactive waste also arises from intervention activities, which are necessary after accidents or to remediate areas affected by past practices. The radioactive waste generated arises in a wide range of physical, chemical, and radiological forms. It may be solid, liquid, or gaseous. Levels of activity concentration can vary from extremely high, such as levels associated with spent fuel and residues from fuel reprocessing, to very low, for instance those associated with radioisotope applications. Equally broad is the spectrum of half-lives of the radionuclides contained in the waste. These differences result in an equally wide variety of

International low level waste disposal practices and facilities

Energy Technology Data Exchange (ETDEWEB)

Nutt, W.M. (Nuclear Engineering Division)

2011-12-19

The safe management of nuclear waste arising from nuclear activities is an issue of great importance for the protection of human health and the environment now and in the future. The primary goal of this report is to identify the current situation and practices being utilized across the globe to manage and store low and intermediate level radioactive waste. The countries included in this report were selected based on their nuclear power capabilities and involvement in the nuclear fuel cycle. This report highlights the nuclear waste management laws and regulations, current disposal practices, and future plans for facilities of the selected international nuclear countries. For each country presented, background information and the history of nuclear facilities are also summarized to frame the country's nuclear activities and set stage for the management practices employed. The production of nuclear energy, including all the steps in the nuclear fuel cycle, results in the generation of radioactive waste. However, radioactive waste may also be generated by other activities such as medical, laboratory, research institution, or industrial use of radioisotopes and sealed radiation sources, defense and weapons programs, and processing (mostly large scale) of mineral ores or other materials containing naturally occurring radionuclides. Radioactive waste also arises from intervention activities, which are necessary after accidents or to remediate areas affected by past practices. The radioactive waste generated arises in a wide range of physical, chemical, and radiological forms. It may be solid, liquid, or gaseous. Levels of activity concentration can vary from extremely high, such as levels associated with spent fuel and residues from fuel reprocessing, to very low, for instance those associated with radioisotope applications. Equally broad is the spectrum of half-lives of the radionuclides contained in the waste. These differences result in an equally wide variety of

Testing and Performance Verification of a High Bypass Ratio Turbofan Rotor in an Internal Flow Component Test Facility

Science.gov (United States)

VanZante, Dale E.; Podboy, Gary G.; Miller, Christopher J.; Thorp, Scott A.

2009-01-01

A 1/5 scale model rotor representative of a current technology, high bypass ratio, turbofan engine was installed and tested in the W8 single-stage, high-speed, compressor test facility at NASA Glenn Research Center (GRC). The same fan rotor was tested previously in the GRC 9x15 Low Speed Wind Tunnel as a fan module consisting of the rotor and outlet guide vanes mounted in a flight-like nacelle. The W8 test verified that the aerodynamic performance and detailed flow field of the rotor as installed in W8 were representative of the wind tunnel fan module installation. Modifications to W8 were necessary to ensure that this internal flow facility would have a flow field at the test package that is representative of flow conditions in the wind tunnel installation. Inlet flow conditioning was designed and installed in W8 to lower the fan face turbulence intensity to less than 1.0 percent in order to better match the wind tunnel operating environment. Also, inlet bleed was added to thin the casing boundary layer to be more representative of a flight nacelle boundary layer. On the 100 percent speed operating line the fan pressure rise and mass flow rate agreed with the wind tunnel data to within 1 percent. Detailed hot film surveys of the inlet flow, inlet boundary layer and fan exit flow were compared to results from the wind tunnel. The effect of inlet casing boundary layer thickness on fan performance was quantified. Challenges and lessons learned from testing this high flow, low static pressure rise fan in an internal flow facility are discussed.

77 FR 69647 - New York; Major Disaster and Related Determinations

Science.gov (United States)

2012-11-20

... have determined that the damage in certain areas of the State of New York resulting from Hurricane... to Certain Applications for Public Facility and Public Housing Assistance, 42 U.S.C. 5153, shall be... as adversely affected by this major disaster: Bronx, Kings, Nassau, New York, Richmond, Suffolk, and...

Class notes from the first international training course on the physical protection of nuclear facilities and materials

Energy Technology Data Exchange (ETDEWEB)

Herrington, P.B. (ed.)

1979-05-01

The International Training Course on Physical Protection of Nuclear Facilities and Materials was intended for representatives from the developing countries who are responsible for preparing regulations and designing and assessing physical protection systems. The first part of the course consists of lectures on the objectives, organizational characteristics, and licensing and regulations requirements of a state system of physical protection. Since the participants may have little experience in nuclear energy, background information is provided on the topics of nuclear materials, radiation hazards, reactor systems, and reactor operations. Transportation of nuclear materials is addressed and emphasis is placed on regulations. Included in these discussions are presentations by guest speakers from countries outside the United States of America who present their countries' threat to nuclear facilities. Effectiveness evaluation methodology is introduced to the participants by means of instructions which teach them how to use logic trees and the EASI (Estimate of Adversary Sequence Interruption) program. The following elements of a physical protection system are discussed: barriers, protective force, intrusion detection systems, communications, and entry-control systems. Total systems concepts of physical protection system design are emphasized throughout the course. Costs, manpower/technology trade-offs, and other practical considerations are discussed. Approximately one-third of the course is devoted to practical exercises during which the attendees participatein problem solving. A hypothetical nuclear facility is introduced, and the attendees participate in the conceptual design of a physical protection system for the facility.

Class notes from the first international training course on the physical protection of nuclear facilities and materials

International Nuclear Information System (INIS)

Herrington, P.B.

1979-05-01

The International Training Course on Physical Protection of Nuclear Facilities and Materials was intended for representatives from the developing countries who are responsible for preparing regulations and designing and assessing physical protection systems. The first part of the course consists of lectures on the objectives, organizational characteristics, and licensing and regulations requirements of a state system of physical protection. Since the participants may have little experience in nuclear energy, background information is provided on the topics of nuclear materials, radiation hazards, reactor systems, and reactor operations. Transportation of nuclear materials is addressed and emphasis is placed on regulations. Included in these discussions are presentations by guest speakers from countries outside the United States of America who present their countries' threat to nuclear facilities. Effectiveness evaluation methodology is introduced to the participants by means of instructions which teach them how to use logic trees and the EASI (Estimate of Adversary Sequence Interruption) program. The following elements of a physical protection system are discussed: barriers, protective force, intrusion detection systems, communications, and entry-control systems. Total systems concepts of physical protection system design are emphasized throughout the course. Costs, manpower/technology trade-offs, and other practical considerations are discussed. Approximately one-third of the course is devoted to practical exercises during which the attendees participatein problem solving. A hypothetical nuclear facility is introduced, and the attendees participate in the conceptual design of a physical protection system for the facility

Validity evaluation of internal exposure in nuclear facility decommission

International Nuclear Information System (INIS)

Wang Xiaoli; Chen Dahua; You Zeyun

2012-01-01

During nuclear facility decommission under construction, it is very important for workers to wear respirator to avoid harm of Am aerosols. So the protection effect of respirator is very important. The protection effect of respirator was calculated and evaluated according to the data achieved from engineering practice. The result shows that the protection effect is better than target management value and the respirator is effective to protect workers from harm of Am aerosols. The respirator is applied to other nuclear facility decommission. (authors)

75 FR 3249 - Amended Certification Regarding Eligibility To Apply for Worker Adjustment Assistance and...

Science.gov (United States)

2010-01-20

... Technology, Inc., Sandston, Virginia. In accordance with Section 223 of the Trade Act of 1974 (19 U.S.C. 2273... Richmond, A subsidiary of Qimonda AG, Sandston, Virginia. The notice was published in the Federal Register... the Sandston, Virginia location of Qimonda 200MM Facility. The Department has determined that these...

Research Status and Feasibility Analysis on the Participation in International Joint Studies for Radionuclide and Colloid Migration Using Foreign Underground Research Facilities

Energy Technology Data Exchange (ETDEWEB)

Baik, Min Hoon; Park, Chung Kyun; Lee, Jae Kwang; Choi, Jong Won

2007-12-15

The research status of the potential international joint projects that we can join were analyzed by investigating world-wide underground research facilities. Based upon the investigations, we visited Aspo in Sweden and GTS in Switzerland, discussed about the participation in the international joint projects and mutual cooperation, and then discussed in detail about time and method for the participation by inviting an expert from Nagra. It is resulted from the investigations and discussions that it is most relevant to participate in the following two international joint projects. 1) Task Force on Modelling of Groundwater Flow and Transport of Solutes in Aspo, 2) CFM project in GTS. We also summarized the on-going current status for the participation in the two international joint projects.

Life Sciences Centrifuge Facility assessment

Science.gov (United States)

Benson, Robert H.

1994-01-01

This report provides an assessment of the status of the Centrifuge Facility being developed by ARC for flight on the International Space Station Alpha. The assessment includes technical status, schedules, budgets, project management, performance of facility relative to science requirements, and identifies risks and issues that need to be considered in future development activities.

The electron-ion scattering experiment ELISe at the International Facility for Antiproton and Ion Research (FAIR)-A conceptual design study

Energy Technology Data Exchange (ETDEWEB)

Antonov, A.N.; Gaidarov, M.K. [INRNE-BAS Sofia (Bulgaria); Ivanov, M.V. [Grupo de Physica Nuclear, Complutense University of Madrid (Spain); Kadrev, D.N. [INRNE-BAS Sofia (Bulgaria); Aiche, M.; Barreau, G.; Czajkowski, S.; Jurado, B. [Centre d' Etudes Nucleaires Bordeaux-Gradingnan (CENBG) (France); Belier, G.; Chatillon, A.; Granier, T.; Taieb, J. [CEA Bruyeres-le-Chatel (France); Dore, D.; Letourneau, A.; Ridikas, D.; Dupont, E.; Berthoumieux, E.; Panebianco, S. [CEA Saclay (France); Farget, F.; Schmitt, C. [GANIL Caen (France)

2011-05-01

The electron-ion scattering experiment ELISe is part of the installations envisaged at the new experimental storage ring at the International Facility for Antiproton and Ion Research (FAIR) in Darmstadt, Germany. It offers an unique opportunity to use electrons as probe in investigations of the structure of exotic nuclei. The conceptual design and the scientific challenges of ELISe are presented.

The electron-ion scattering experiment ELISe at the International Facility for Antiproton and Ion Research (FAIR)-A conceptual design study

International Nuclear Information System (INIS)

Antonov, A.N.; Gaidarov, M.K.; Ivanov, M.V.; Kadrev, D.N.; Aiche, M.; Barreau, G.; Czajkowski, S.; Jurado, B.; Belier, G.; Chatillon, A.; Granier, T.; Taieb, J.; Dore, D.; Letourneau, A.; Ridikas, D.; Dupont, E.; Berthoumieux, E.; Panebianco, S.; Farget, F.; Schmitt, C.

2011-01-01

The electron-ion scattering experiment ELISe is part of the installations envisaged at the new experimental storage ring at the International Facility for Antiproton and Ion Research (FAIR) in Darmstadt, Germany. It offers an unique opportunity to use electrons as probe in investigations of the structure of exotic nuclei. The conceptual design and the scientific challenges of ELISe are presented.

Future issues in international safeguards

International Nuclear Information System (INIS)

Hakkila, E.A.; Markin, J.T.; Mullen, M.F.

1991-01-01

The introduction of large bulk-handling facilities into the internationally safeguarded, commercial nuclear fuel cycle, increased concerns for radiation exposure, and the constant level of resources available to the International Atomic Energy Agency (IAEA) are driving new and innovative approaches to international safeguards. Inspector resources have traditionally been allocated on a facility-type basis. Approaches such as randomization of inspections either within a facility or across facilities in a State or the application of a fuel-cycle approach within a State are being considered as means of conserving resources. Large bulk-handling facilities require frequent material balance closures to meet IAEA timeliness goals. Approaches such as near-real-time accounting, running book inventories, and adjusted running book inventories are considered as means to meet these goals. The automated facilities require that safeguards measures also be automated, leading to more reliance on operator-supplied equipment that must be authenticated by the inspectorate. New Non-Proliferation Treaty signatory States with advanced nuclear programs will further drain IAEA resources. Finally, the role of special inspections in IAEA safeguards may be expanded. This paper discusses these issues in terms of increasing safeguards effectiveness and the possible impact on operators. 14 refs

Radiation protection at nuclear fuel cycle facilities

International Nuclear Information System (INIS)

Endo, K.; Momose, T.; Furuta, S.

2011-01-01

Radiation protection methodologies concerning individual monitoring, workplace monitoring and environmental monitoring in nuclear fuel facilities have been developed and applied to facilities in the Nuclear Fuel Cycle Engineering Laboratories (NCL) of Japan Atomic Energy Agency (JAEA) for over 40 y. External exposure to photon, beta ray and neutron and internal exposure to alpha emitter are important issues for radiation protection at these facilities. Monitoring of airborne and surface contamination by alpha and beta/photon emitters at workplace is also essential to avoid internal exposure. A critical accident alarm system developed by JAEA has been proved through application at the facilities for a long time. A centralised area monitoring system is effective for emergency situations. Air and liquid effluents from facilities are monitored by continuous monitors or sampling methods to comply with regulations. Effluent monitoring has been carried out for 40 y to assess the radiological impacts on the public and the environment due to plant operation. (authors)

Regulatory facility guide for Ohio

Energy Technology Data Exchange (ETDEWEB)

Anderson, S.S.; Bock, R.E.; Francis, M.W.; Gove, R.M.; Johnson, P.E.; Kovac, F.M.; Mynatt, J.O. [Oak Ridge National Lab., TN (United States); Rymer, A.C. [Transportation Consulting Services, Knoxville, TN (United States)

1994-02-28

The Regulatory Facility Guide (RFG) has been developed for the DOE and contractor facilities located in the state of Ohio. It provides detailed compilations of international, federal, and state transportation-related regulations applicable to shipments originating at destined to Ohio facilities. This RFG was developed as an additional resource tool for use both by traffic managers who must ensure that transportation operations are in full compliance with all applicable regulatory requirements and by oversight personnel who must verify compliance activities.

Geographical and Statistical Analysis on the Relationship between Land-Use Mixture and Home-Based Trip Making and More: Case of Richmond, Virginia

Directory of Open Access Journals (Sweden)

Yin - Shan MA

2013-06-01

Full Text Available Richmond, Virginia has implemented numerous mixed land-use policies to encourage non-private-vehicle commuting for decades based on the best practices of other cities and the assumption that land-use mixture would positively lead to trip reduction. This paper uses both Geographical Information Systems (GIS and statistical tools to empirically test this hypothesis. With local land use and trip making data as inputs, it first calculates two common indices of land-use mixture - entropy and dissimilarity indices, using GIS tool, supplemented by Microsoft Excel. Afterwards, it uses Statistical Package for Social Sciences (SPSS to calculate the correlation matrices among land-use mixture indices, socioeconomic variables, and home-based work/other trip rates, followed by a series of regression model runs on these variables. Through this study, it has been found that land-use mixture has some but weak effects on home-based work trip rate, and virtually no effects on home-based other trip rate. In contrast, socioeconomic variables, especially auto ownership, have larger effects on home-based trip making.

Specifications of the International Atomic Energy Agency's international project on safety assessment driven radioactive waste management solutions

International Nuclear Information System (INIS)

Ghannadi, M.; Asgharizadeh, F.; Assadi, M. R.

2008-01-01

Radioactive waste is produced in the generation of nuclear power and the production and use of radioactive materials in the industry, research, and medicine. The nuclear waste management facilities need to perform a safety assessment in order to ensure the safety of a facility. Nuclear safety assessment is a structured and systematic way of examining a proposed facility, process, operation and activity. In nuclear waste management point of view, safety assessment is a process which is used to evaluate the safety of radioactive waste management and disposal facilities. In this regard the International Atomic Energy Agency is planed to implement an international project with cooperation of some member states. The Safety Assessment Driving Radioactive Waste Management Solutions Project is an international programme of work to examine international approaches to safety assessment in aspects of p redisposal r adioactive waste management, including waste conditioning and storage. This study is described the rationale, common aspects, scope, objectives, work plan and anticipated outcomes of the project with refer to International Atomic Energy Agency's documents, such as International Atomic Energy Agency's Safety Standards, as well as the Safety Assessment Driving Radioactive Waste Management Solutions project reports

Quality management in nuclear facilities decommissioning

International Nuclear Information System (INIS)

Garonis, Omar H.

2002-01-01

Internationally, the decommissioning organizations of nuclear facilities carry out the decommissioning according to the safety requirements established for the regulatory bodies. Some of them perform their activities in compliance with a quality assurance system. This work establishes standardization through a Specifications Requirement Document, for the management system of the nuclear facilities decommissioning organizations. It integrates with aspects of the quality, environmental, occupational safety and health management systems, and also makes these aspects compatible with all the requirements of the nuclear industry recommended for the International Atomic Energy Agency (IAEA). (author)

Institutionalizing Safeguards By Design for Nuclear Facilities

International Nuclear Information System (INIS)

Morgan, James B.; Kovacic, Donald N.; Whitaker, J. Michael

2008-01-01

Safeguards for nuclear facilities can be significantly improved by developing and implementing methodologies for integrating proliferation resistance into the design of new facilities. This paper proposes a method to systematically analyze a facility's processes, systems, equipment, structures and management controls to ensure that all relevant proliferation scenarios that could potentially result in unacceptable consequences have been identified, evaluated and mitigated. This approach could be institutionalized into a country's regulatory structure similar to the way facilities are licensed to operate safely and are monitored through inspections and incident reporting to ensure compliance with domestic and international safeguards. Furthermore, taking credit for existing systems and equipment that have been analyzed and approved to assure a facility's reliable and safe operations will reduce the overall cost of implementing intrinsic and extrinsic proliferation-resistant features. The ultimate goal is to integrate safety, reliability, security and safeguards operations into the design of new facilities to effectively and efficiently prevent diversion, theft and misuse of nuclear material and sensitive technologies at both the facility and state level. To facilitate this approach at the facility level, this paper discusses an integrated proliferation resistance analysis (IPRA) process. If effectively implemented, this integrated approach will also facilitate the application of International Atomic Energy Agency (IAEA) safeguards

Preliminary results of the International Fusion Materials Irradiation Facility deuteron injector

Energy Technology Data Exchange (ETDEWEB)

Gobin, R.; Adroit, G.; Bogard, D.; Bourdelle, G.; Chauvin, N.; Delferriere, O.; Gauthier, Y.; Girardot, P.; Guiho, P.; Harrault, F.; Jannin, J. L.; Loiseau, D.; Mattei, P.; Roger, A.; Sauce, Y.; Senee, F.; Vacher, T. [Commissariat a l' Energie Atomique et aux Energie Alternatives, CEA/Saclay, DSM/IRFU, 91191-Gif/Yvette (France)

2012-02-15

In the framework of the IFMIF-EVEDA project (International Fusion Materials Irradiation Facility-Engineering Validation and Engineering Design Activities), CEA/IRFU is in charge of the design, construction, and characterization of the 140 mA continuous deuteron injector, including the source and the low energy beam line. The electron cyclotron resonance ion source which operates at 2.45 GHz is associated with a 4-electrode extraction system in order to minimize beam divergence at the source exit. Krypton gas injection is foreseen in the 2-solenoid low energy beam line. Such Kr injection will allow reaching a high level of space charge compensation in order to improve the beam matching at the radio frequency quadrupole (RFQ) entrance. The injector construction is now completed on the Saclay site and the first plasma and beam production has been produced in May 2011. This installation will be tested with proton and deuteron beams either in pulsed or continuous mode at Saclay before shipping to Japan. In this paper, after a brief description of the installation, the preliminary results obtained with hydrogen gas injection into the plasma chamber will be reported.

Nuclear data needs for neutron spectrum tailoring at International Fusion Materials Irradiation Facility (IFMIF)

International Nuclear Information System (INIS)

Sugimoto, Masayoshi

2001-01-01

International Fusion Materials Irradiation Facility (IFMIF) is a proposal of D-Li intense neutron source to cover all aspects of the fusion materials development in the framework of IEA collaboration. The new activity has been started to qualifying the important technical issues called Key Element technology Phase since 2000. Although the neutron spectrum can be adjusted by changing the incident beam energy, it is favorable to be carried out many irradiation tasks at the same time under the unique beam condition. For designing the tailored neutron spectrum, neutron nuclear data for the moderator-reflector materials up to 50 MeV are required. The data for estimating the induced radioactivity is also required to keep the radiation level low enough at maintenance time. The candidate materials and the required accuracy of nuclear data are summarized. (author)

Nuclear data needs for neutron spectrum tailoring at International Fusion Materials Irradiation Facility (IFMIF)

Energy Technology Data Exchange (ETDEWEB)

Sugimoto, Masayoshi [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment

2001-03-01

International Fusion Materials Irradiation Facility (IFMIF) is a proposal of D-Li intense neutron source to cover all aspects of the fusion materials development in the framework of IEA collaboration. The new activity has been started to qualifying the important technical issues called Key Element technology Phase since 2000. Although the neutron spectrum can be adjusted by changing the incident beam energy, it is favorable to be carried out many irradiation tasks at the same time under the unique beam condition. For designing the tailored neutron spectrum, neutron nuclear data for the moderator-reflector materials up to 50 MeV are required. The data for estimating the induced radioactivity is also required to keep the radiation level low enough at maintenance time. The candidate materials and the required accuracy of nuclear data are summarized. (author)

Explotation of irradiation facilities. Safety handbook

International Nuclear Information System (INIS)

Prieto Miranda, Enrique Franscisco; Melo Crespo, Jose Carlos

1997-01-01

At present in the world there are more of 160 gamma radiation facilities and more of 600 electron bean accelerators in operation, at least one in each member state of International Atomic Energy Agency. In this paper is elaborated a Manual with the security criteria to operation of these facility types

Lessons learned from international siting experiences of LLW Disposal facilities

International Nuclear Information System (INIS)

McCabe, G.H.

1990-01-01

This paper reports that the United States can gain insight into successfully siting low-level radioactive waste (LLW) disposal facilities by studying the process in other nations. Siting experiences in France and Sweden are compared to experiences in the United States. Three factors appear to making siting of LLW disposal facilities easier in France and Sweden than in the United States. First, the level of public trust in the government and the entities responsible for siting, developing, and operating a LLW disposal facility is much greater in France and Sweden than in the United States. Second, France and Sweden are much more dependent on nuclear power than is the United States. Third, French and Swedish citizens do not have the same access to the siting process (i.e., legal means to intervene) as do U.S. citizens. To compensate for these three factors, public officials responsible for siting a facility may need to better listen to the concerns of public interest groups and citizen advisory committees and amend their siting process accordingly and better share power and control with the public. If these two techniques are implemented earnestly by the states, siting efforts may be increasingly more successful in the United States

33 CFR 105.205 - Facility Security Officer (FSO).

Science.gov (United States)

2010-07-01

... training in the following, as appropriate: (i) Relevant international laws and codes, and recommendations... well as any plans to change the facility or facility infrastructure prior to amending the FSP; and (18...

International conference on knowledge management in nuclear facilities. Book of extended synopses

Energy Technology Data Exchange (ETDEWEB)

NONE

2007-06-15

In recent years new issues have emerged in Member States, including ageing facilities and personnel, nuclear phase-out policies, the expectation of nuclear growth in some regions and the objective to further improve the economic competitiveness of nuclear energy while maintaining a high level of safety. Awareness of the importance of nuclear knowledge management in addressing the challenges the industry is facing has grown significantly, both in the industry and in regulatory authorities, and a large number of projects are under way. Knowledge management is becoming an important element of the organizational behaviour of the nuclear industry. In 2002, the IAEA General Conference adopted a new resolution on Nuclear Knowledge, emphasizing the importance of nuclear knowledge management. The resolution was reiterated in subsequent years. This conference is organized in response to those resolutions, also following the first conference on Nuclear Knowledge Management - Strategies, Information Management and Human Resource Development, organized by the IAEA in 2004 in France. The objectives of the conference are to: - Take stock of the recent developments in nuclear knowledge management; - Demonstrate and discuss the benefits of nuclear knowledge management in promoting excellence in operation and safety of nuclear facilities; - Promote the use of nuclear knowledge management in the nuclear industry; - Provide insights and recommendations to the nuclear community. The conference will address decision makers and professionals in the nuclear industry, including in particular all nuclear facilities in all phases of their life cycle, and from regulatory organizations, governments, academia, vendors and other bodies concerned with the topic. The conference will start with a policy forum: Policy Forum: Status, Strategic Perspectives and Key Issues Leaders from nuclear industry, governmental organizations, regulators, research institutes and international organizations will

A review of recent developments in radiometric calibration facilities

International Nuclear Information System (INIS)

Corner, B.

1984-01-01

Two new developments concerning radiometric calibration facilities are described in this presentation. The first is the result of the international programme for the monitoring and cross-reference of existing calibration facilities, sponsored by the International Atomic Energy Agency. The second development that is discussed concerns the accuracy of the stripping ratios derived at Pelindaba and has important implications for in situ assaying

Investigation of high flux test module for the international fusion materials irradiation facilities (IFMIF)

International Nuclear Information System (INIS)

Miyashita, Makoto; Sugimoto, Masayoshi; Yutani, Toshiaki

2007-03-01

This report describes investigation on structure of a high neutron flux test module (HFTM) for the International Fusion Materials Irradiation Facilities (IFMIF). The HFTM is aimed for neutron irradiation of a specimen in a high neutron flux domain of the test cell for irradiation ground of IFMIF. We investigated the overall structure of the HFTM that was able to include specimens in a rig and thermocouple arrangement, an interface of control signal and support structure. Moreover, pressure and the amount of the bend in the module vessel (a rectangular section pressure vessel) were calculated. The module vessel did a rectangular section from limitation of a high neutron flux domain. Also, we investigated damage of thermocouples under neutron irradiation, which was a temperature sensor of irradiation materials temperature control demanded high precision. Based on these results, drawings on the HTFM structure. (author)

A health-promoting community dental service in Melbourne, Victoria, Australia: protocol for the North Richmond model of oral health care.

Science.gov (United States)

Hall, Martin; Christian, Bradley

2017-10-01

Despite the best efforts and commitment of oral health programs, there is no evidence that the current surgical output-based model of oral health care is delivering better oral health outcomes to the community. In fact, Australian evidence indicates the oral health of the community could be getting worse. It is now well-understood that this traditional surgical model of oral health care will never successfully manage the disease itself. It is proposed that a health-promoting, minimally invasive oral disease management model of care may lead to a sustainable benefit to the oral health status of the individual and community groups. The aim of this paper is to describe such a model of oral health care (MoC) currently being implemented by the North Richmond Community Health Oral Health (NRCH-OH) program in Melbourne, Victoria, Australia; this model may serve as a template for other services to re-orient their healthcare delivery towards health promotion and prevention. The paper describes the guiding principles and theories for the model and also its operational components, which are: pre-engagement while on the waitlist; client engagement at the reception area; the assessment phase; oral health education (high-risk clients only); disease management; and reviews and recall.

Thermonuclear controlled fusion: international cooperation

International Nuclear Information System (INIS)

Conscience, J.-F.

2001-01-01

This report summarizes the current worldwide status of research in the field of thermonuclear controlled fusion as well as the international research programme planed for the next decades. The two main projects will be the ITER facility (International Thermonuclear Experimental Reactor) that should produce 10 times more energy than the energy injected, and the IFMIF (International Fusion Materials Irradiation Facility) designed to study the reactions of materials under intense neutron fluxes. The future of the pioneering JET facility (Joint European Torus) is also discussed. The engagement of the various countries (USA, Japan, Germany, Russian Federation and Canada) and international organisations (EURATOM and IEA) in terms of investment and research is described. Switzerland is involved in this program through an agreement with EURATOM and is mainly dedicated to experimental studies with the TCV machine in Lausanne and numerical studies of plasma configurations. It will participate to the development of the microwave plasma heating system for the ITER machine

Report of the international workshop on safety measures to address the year 2000 issue at radioactive waste management and nuclear fuel cycle facilities. (Supplement to IAEA-TECDOC-1073 and IAEA-TECDOC-1087)

International Nuclear Information System (INIS)

1999-08-01

In resolution GC(42)/RES/11 on 'Measures to address the Year 2000 (Y2K) issue', adopted on 25 September 1998, the General Conference of the International Atomic Energy Agency (IAEA) - inter alia - urged Member States 'to share information with the Secretariat regarding diagnostic and corrective actions being planned or implemented by operating and regulatory organizations at ... fuel cycle facilities ... to make those facilities Year 2000 ready', encouraged the Secretariat, 'within existing resources, to act as a clearinghouse and central point of contact for Member States to exchange information regarding diagnostic and remediation actions being taken at ... fuel cycle facilities ... to make these facilities Year 2000 ready', urged the Secretariat 'to handle the information provided by Member States carefully' and requested the Director General to report to it at its next (1999) regular session on the implementation of that resolution. In response to resolution GC(42)/RES/11, the Secretariat convened: a group of consultants who met in Vienna from 20 to 22 January 1999 and produced a technical document (IAEA-TECDOC-1073) entitled Safety Measures to Address the Year 2000 Issue at Radioactive Waste Management Facilities; and a specialists meeting in Vienna from 24 to 26 March 1999, which produced a technical document (IAEA-TECDOC-1087) entitled Potential Vulnerabilities of Nuclear Fuel Cycle Facilities to the Year 2000 (Y2K) Issue and Measures to Address Them. To foster information exchange and share existing experience the IAEA held an International Workshop on Safety Measures to Address the Year 2000 Issue at Radioactive Waste Management and Nuclear Fuel Cycle Facilities in Vienna on 1-2 July 1999. Whereas the focus of TECDOC-1073 and TECDOC-1087 had been on identifying relevant safety issues in relation to Y2K computer problems and on proposing methods to address them, the focus of the International Workshop was on sharing experience, setting priorities

Design of an internal dosimetry program

International Nuclear Information System (INIS)

Wu, C.F.; Goff, T.E.

2004-01-01

Measurement of radiation dose is an essential element of radiation protection programs at nuclear facilities. To protect workers and demonstrate compliance with regulatory requirements, dosimetry programs must be established based on sound technical basis. Historically, external exposure was controlled by occupational dose limits. Internal exposure to radionuclides was limited by maximum permissible body burden and maximum permissible concentration. With the issuance of ICRP 26, ICRP 30, DOE Order 5480.11, DOE/EH-0256T, and the new 10 CFR 20, it has become a requirement that internal dose be assessed and the sum of internal and external doses be maintained below regulatory limits. Nuclear facilities are required to have internal dose evaluation programs adequate to demonstrate compliance with radiation protection standards (RPSs). The Waste Isolation Pilot Plant is a DOE facility designed to demonstrate safe disposal of transuranic (TRU) wastes in an ancient salt bed 2,150 feet underground. Internal dose measurement is required to support waste handling activities. This paper describes the technical basis for the WIPP Internal Dosimetry Program. (author)

Performance of the modified Richmond Agitation Sedation Scale in identifying delirium  in older ED patients.

Science.gov (United States)

Grossmann, Florian F; Hasemann, Wolfgang; Kressig, Reto W; Bingisser, Roland; Nickel, Christian H

2017-09-01

Delirium in older emergency department (ED) patients is associated with severe negative patient outcomes and its detection is challenging for ED clinicians. ED clinicians need easy tools for delirium detection. We aimed to test the performance criteria of the modified Richmond Agitation Sedation Scale (mRASS) in identifying delirium in older ED patients. The mRASS was applied to a sample of consecutive ED patients aged 65 or older by specially trained nurses during an 11-day period in November 2015. Reference standard delirium diagnosis was based on Diagnostic and Statistical Manual of Mental Disorders (DSM-IV-TR) criteria, and was established by geriatricians. Performance criteria were computed. Analyses were repeated in the subsamples of patients with and without dementia. Of 285 patients, 20 (7.0%) had delirium and 41 (14.4%) had dementia. The sensitivity of an mRASS other than 0 to detect delirium was 0.70 (95% confidence interval, CI, 0.48; 0.85), specificity 0.93 (95% CI 0.90; 0.96), positive likelihood ratio 10.31 (95% CI 6.06; 17.51), negative likelihood ratio 0.32 (95% CI 0.16; 0.63). In the sub-sample of patients with dementia, sensitivity was 0.55 (95% CI 0.28; 0.79), specificity 0.83 (95% CI 0.66; 0.93), positive likelihood ratio 3.27 (95% CI 1.25; 8.59), negative likelihood ratio 0.55 (95% CI 0.28; 1.06). The sensitivity of the mRASS to detect delirium in older ED patients was low, especially in patients with dementia. Therefore its usefulness as a stand-alone screening tool is limited. Copyright © 2017 Elsevier Inc. All rights reserved.

The Benefits of Guided Facility Self-Assessments

Science.gov (United States)

O'Leary, Keith

2012-01-01

A growing number of educational institutions have discovered that a guided self-assessment solution helps them to consistently and cost-effectively obtain facility condition information and make better-informed capital planning decisions. Facility self-assessment employs a consistent, repeatable process for internal staff to quickly assess assets…

Status of superconducting RF test facility (STF)

International Nuclear Information System (INIS)

Hayano, Hitoshi

2005-01-01

A superconducting technology was recommended for the main linac design of the International Linear Collider (ILC) by the International Technology Recommendation Panel (ITRP). The basis for this design has been developed and tested at DESY, and R and D is progressing at many laboratories around the world including DESY, Orsay, KEK, FNAL, SLAC, Cornell, and JLAB. In order to promote Asian SC-technology for ILC, construction of a test facility in KEK was discussed and decided. The role and status of the superconducting RF test facility (STF) is reported in this paper. (author)

Assessment of ground-water contamination from a leaking underground storage tank at a defense supply center near Richmond, Virginia

International Nuclear Information System (INIS)

Powell, J.D.; Wright, W.G.

1990-01-01

During 1988-89, 24 wells were installed in the vicinity of the post-exchange gasoline station on the Defense General Supply Center, near Richmond, Virginia, to collect and analyze groundwater samples for the presence of gasoline contamination from a leaking underground storage tank. Concentrations of total petroleum hydrocarbons and benzene were as high as 8.2 mg/L and 9,000 microg/L, respectively, in water from wells in the immediate vicinity of the former leaking tank, and benzene concentrations were as high as 2,300 microg/L in a well 600 ft down gradient from the gasoline station. Groundwater flow rate are estimated to be about 60 to 80 ft/yr; on the basis of these flow rates, the contaminants may have been introduced into the groundwater as long as 7-10 yrs ago. Groundwater might infiltrate a subsurface storm sewer, where the sewer is below the water table, and discharge into a nearby stream. Preliminary risk assessment for the site identified no potential human receptors to the groundwater contamination because there were no groundwater users identified in the area. Remediation might be appropriate if exposure of future potential users is concern. Alternatives discussed for remediation of groundwater contamination in the upper aquifer at the PX Service Station include no-action, soil vapor extraction, and groundwater pumping and treatment alternatives

Facility Safeguardability Analysis In Support of Safeguards-by-Design

Energy Technology Data Exchange (ETDEWEB)

Philip Casey Durst; Roald Wigeland; Robert Bari; Trond Bjornard; John Hockert; Michael Zentner

2010-07-01

The following report proposes the use of Facility Safeguardability Analysis (FSA) to: i) compare and evaluate nuclear safeguards measures, ii) optimize the prospective facility safeguards approach, iii) objectively and analytically evaluate nuclear facility safeguardability, and iv) evaluate and optimize barriers within the facility and process design to minimize the risk of diversion and theft of nuclear material. As proposed by the authors, Facility Safeguardability Analysis would be used by the Facility Designer and/or Project Design Team during the design and construction of the nuclear facility to evaluate and optimize the facility safeguards approach and design of the safeguards system. Through a process of “Safeguards-by-Design” (SBD), this would be done at the earliest stages of project conceptual design and would involve domestic and international nuclear regulators and authorities, including the International Atomic Energy Agency (IAEA). The benefits of the Safeguards-by-Design approach is that it would clarify at a very early stage the international and domestic safeguards requirements for the Construction Project Team, and the best design and operating practices for meeting these requirements. It would also minimize the risk to the construction project, in terms of cost overruns or delays, which might otherwise occur if the nuclear safeguards measures are not incorporated into the facility design at an early stage. Incorporating nuclear safeguards measures is straight forward for nuclear facilities of existing design, but becomes more challenging with new designs and more complex nuclear facilities. For this reason, the facility designer and Project Design Team require an analytical tool for comparing safeguards measures, options, and approaches, and for evaluating the “safeguardability” of the facility. The report explains how preliminary diversion path analysis and the Proliferation Resistance and Physical Protection (PRPP) evaluation

Regulatory Facility Guide for Tennessee

Energy Technology Data Exchange (ETDEWEB)

Anderson, S.S.; Bock, R.E.; Francis, M.W.; Gove, R.M.; Johnson, P.E.; Kovac, F.M.; Mynatt, J.O. [Oak Ridge National Lab., TN (United States); Rymer, A.C. [Transportation Consulting Services, Knoxville, TN (United States)

1994-02-28

This guide provides detailed compilations of international, federal, and state transportation related regulations applicable to shipments originating at or destined to Tennessee facilities. Information on preferred routes is also given.

Facility Safeguardability Analysis in Support of Safeguards by Design

International Nuclear Information System (INIS)

Wonder, E.F.

2010-01-01

The idea of 'Safeguards-by-Design' (SBD) means designing and incorporating safeguards features into new civil nuclear facilities at the earliest stages in the design process to ensure that the constructed facility is 'safeguardable,' i.e. will meet national and international nuclear safeguards requirements. Earlier consideration of safeguards features has the potential to reduce the need for costly retrofits of the facility and can result in a more efficient and effective safeguards design. A 'Facility Safeguardability Analysis' (FSA) would be a key step in Safeguards-by-Design that would link the safeguards requirements with the 'best practices', 'lessons learned', and design of the safeguards measures for implementing those requirements. The facility designer's nuclear safeguards experts would work closely with other elements of the project design team in performing FSA. The resultant analysis would support discussions and interactions with the national nuclear regulator (i.e. State System of Accounting for and Control of Nuclear Material - SSAC) and the IAEA for development and approval of the proposed safeguards system. FSA would also support the implementation of international safeguards by the IAEA, by providing them with a means to analyse and evaluate the safeguardability of facilities being designed and constructed - i.e. by independently reviewing and validating the FSA as performed by the design team. Development of an FSA methodology is part of a broader U.S. National Nuclear Security Administration program to develop international safeguards-by-design tools and guidance documents for use by facility designers. The NNSA NGSI -sponsored project team is looking, as one element of its work, at how elements of the methodology developed by the Generation IV International Forum's Working Group on Proliferation Resistance and Physical Protection can be adapted to supporting FSA. (author)

Report of the International Review Committee of the joint proposal of the Japan Hadron Facility (KEK) and the Neutron Science Project (JAERI)

International Nuclear Information System (INIS)

1999-08-01

The International Review Committee composed of twelve Japanese and foreign experts was set up under the Research Evaluation Committee of JAERI, and has reviewed the proposed joint project combining JAERI's Neutron Science Project and KEK's Japan Hadron Facility into one major facility. The review meeting took place on April 26-27, 1999, at JAERI Head quarters, Tokyo. According to the points of review given in advance, the review was implemented based on the joint project report submitted and presentations of both institutions. The Research Evaluation Committee received the review report and its explanations from the Review Committee on July 5. The Research Evaluation Committee has acknowledged appropriateness of the review results. This report describes the review results. (author)

Design of GMP compliance radiopharmaceutical production facility in MINT

International Nuclear Information System (INIS)

Anwar Abd Rahman; Shaharum Ramli; M Rizal Mamat Ibrahim; Rosli Darmawan; Yusof Azuddin Ali; Jusnan Hashim

2005-01-01

In 1985, MINT built the only radiopharmaceutical production facility in Malaysia. The facility was designed based on IAEA (International Atomic Energy Agency) standard guidelines which provide radiation safety to the staff and the surrounding environment from radioactive contamination. Since 1999, BPFK (Biro Pengawalan Farmaseutikal Kebangsaan) has used the guidelines from Pharmaceutical Inspection Convention Scheme (PICS) to meet the requirements of the Good Manufacturing Practice (GMP) for Pharmaceutical Products. In the guidelines, the pharmaceutical production facility shall be designed based on clean room environment. In order to design a radiopharmaceutical production facility, it is important to combine the concept of radiation safety and clean room to ensure that both requirements from GMP and IAEA are met. The design requirement is necessary to set up a complete radiopharmaceutical production facility, which is safe, has high production quality and complies with the Malaysian and International standards. (Author)

Maintenance facilities, stores and records

International Nuclear Information System (INIS)

Fischer, K.

1986-01-01

The topics of this report are: on-site or off-site facilities. On-site facilities: workshops and special facilities. KWU's Service Center, a typical off-site supporting facility in Germany, capabilities and activities. A pool for special tools and equipment: devices for plugging of nozzles, for handling of RPU-studs and RPU internals etc. Devices for and management of radiological protection on-site for typical outage work. Spare parts and spare part management on site, typical examples. KWU's centralized spare part pools for components, generators and turbines etc. A computerized system for spare parts storage and maintenance planning. A system for mutual exchange of operational experience with respect to maintenance and repair activities. Systematic evaluation of failures and statistical results. (orig./GL)

Intense neutron irradiation facility for fusion reactor materials

Energy Technology Data Exchange (ETDEWEB)

Noda, Kenji; Oyama, Yukio; Kato, Yoshio; Sugimoto, Masayoshi [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment

1997-03-01

Technical R and D of d-Li stripping type neutron irradiation facilities for development of fusion reactor materials was carried out in Fusion Materials Irradiation Test Facility (FMIT) project and Energy Selective Neutron Irradiation Test Facility (ESNIT) program. Conceptual design activity (CDA) of International Fusion Materials Irradiation Facility (IFMIF), of which concept is an advanced version of FMIT and ESNIT concepts, are being performed. Progress of users` requirements and characteristics of irradiation fields in such neutron irradiation facilities, and outline of baseline conceptual design of IFMIF were described. (author)

The provosion of wide-area networking facilities

International Nuclear Information System (INIS)

Charles, B.J.

1982-01-01

The academic community in the United Kingdom is currently engaged in an extensive programme to provide comprehensive networking facilities within and among the 47 universities and numerous research institutions in the British Isles. The programme is described and the possible provision of similar facilities on an international scale discussed. (orig.)

International Fusion Materials Irradiation Facility conceptual design activity. Present status and perspective

International Nuclear Information System (INIS)

Kondo, Tatsuo; Noda, Kenji; Oyama, Yukio

1998-01-01

For developing the materials for nuclear fusion reactors, it is indispensable to study on the neutron irradiation behavior under fusion reactor conditions, but there is not any high energy neutron irradiation facility that can simulate fusion reactor conditions at present. Therefore, the investigation of the IFMIF was begun jointly by Japan, USA, Europe and Russia following the initiative of IEA. The conceptual design activities were completed in 1997. As to the background and the course, the present status of the research on heavy irradiation and the testing means for fusion materials, the requirement and the technical basis of high energy neutron irradiation, and the international joint design activities are reported. The materials for fusion reactors are exposed to the neutron irradiation with the energy spectra up to 14 MeV. The requirements from the users that the IFMIF should satisfy, the demand of the tests for the materials of prototype and demonstration fusion reactors and the evaluation of the neutron field characteristics of the IFMIF are discussed. As to the conceptual design of the IFMIF, the whole constitution, the operational mode, accelerator system and target system are described. (K.I.)

The Physical Protection of Nuclear Material and Nuclear Facilities

International Nuclear Information System (INIS)

1999-08-01

Physical protection against the theft or unauthorized diversion of nuclear materials and against the sabotage of nuclear facilities by individuals or groups has long been a matter of national and international concern. Although responsibility for establishing and operating a comprehensive physical protection system for nuclear materials and facilities within a State rests entirely with the Government of that State, it is not a matter of indifference to other States whether and to what extent that responsibility is fulfilled. Physical protection has therefore become a matter of international concern and co-operation. The need for international co-operation becomes evident in situations where the effectiveness of physical protection in one State depends on the taking by other States also of adequate measures to deter or defeat hostile actions against nuclear facilities and nuclear materials, particularly when such materials are transported across national frontiers

The Physical Protection of Nuclear Material and Nuclear Facilities

International Nuclear Information System (INIS)

1999-06-01

Physical protection against the theft or unauthorized diversion of nuclear materials and against the sabotage of nuclear facilities by individuals or groups has long been a matter of national and international concern. Although responsibility for establishing and operating a comprehensive physical protection system for nuclear materials and facilities within a State rests entirely with the Government of that State, it is not a matter of indifference to other States whether and to what extent that responsibility is fulfilled. Physical protection has therefore become a matter of international concern and co-operation. The need for international co-operation becomes evident in situations where the effectiveness of physical protection in one State depends on the taking by other States also of adequate measures to deter or defeat hostile actions against nuclear facilities and nuclear materials, particularly when such materials are transported across national frontiers [es

The Physical Protection of Nuclear Material and Nuclear Facilities

International Nuclear Information System (INIS)

1999-06-01

Physical protection against the theft or unauthorized diversion of nuclear materials and against the sabotage of nuclear facilities by individuals or groups has long been a matter of national and international concern. Although responsibility for establishing and operating a comprehensive physical protection system for nuclear materials and facilities within a State rests entirely with the Government of that State, it is not a matter of indifference to other States whether and to what extent that responsibility is fulfilled. Physical protection has therefore become a matter of international concern and co-operation. The need for international co-operation becomes evident in situations where the effectiveness of physical protection in one State depends on the taking by other States also of adequate measures to deter or defeat hostile actions against nuclear facilities and nuclear materials, particularly when such materials are transported across national frontiers

International conference on lessons learned from the decommissioning of nuclear facilities and the safe termination of nuclear activities. Contributed papers

International Nuclear Information System (INIS)

2006-12-01

The International Atomic Energy Agency (IAEA), in cooperation with the European Commission (EC), Nuclear Energy Agency to the Organisation for Economic Co-operation and Development (OECD/NEA), and the World Nuclear Association (WNA), organized an International Conference on Lessons Learned from the Decommissioning of Nuclear Facilities and the Safe Termination of Nuclear Activities from 11 to 15 December 2006 in Athens, Greece. This Book of Contributed Papers contains technical papers and posters contributed by experts from operating organisations, regulatory bodies, technical support organisations, and other institutions on issues falling within the scope of the Conference. The following main topics were covered: Evolution of national and international policies and criteria for the safe and efficient decommissioning of nuclear facilities and safe termination of nuclear activities; Review of lessons learned from ongoing or completed activities associated with decommissioning; Improvement of safety and efficiency through the use of new and innovative technologies; Practical aspects in the management of material, waste and sites resulting from decommissioning, including the management of waste in the absence of repositories and waste acceptance requirements; Procedures for demonstrating compliance with clearance criteria; Experience from radiological assessments associated with decommissioning; Involvement of the local communities and the impact that decommissioning activities has on them. The presented papers and posters were reviewed and accepted following the guidelines established by the Conference Programme Committee for consideration at the Conference. The material compiled in this Book of Contributed Papers has not undergone rigorous editing by the editorial staff of the IAEA. However, certain modifications were made: a unified format was adopted for all papers; and minor corrections were made in the text where required. Each paper and poster has been indexed

International conference on lessons learned from the decommissioning of nuclear facilities and the safe termination of nuclear activities. Contributed papers

Energy Technology Data Exchange (ETDEWEB)

NONE

2006-12-15

The International Atomic Energy Agency (IAEA), in cooperation with the European Commission (EC), Nuclear Energy Agency to the Organisation for Economic Co-operation and Development (OECD/NEA), and the World Nuclear Association (WNA), organized an International Conference on Lessons Learned from the Decommissioning of Nuclear Facilities and the Safe Termination of Nuclear Activities from 11 to 15 December 2006 in Athens, Greece. This Book of Contributed Papers contains technical papers and posters contributed by experts from operating organisations, regulatory bodies, technical support organisations, and other institutions on issues falling within the scope of the Conference. The following main topics were covered: Evolution of national and international policies and criteria for the safe and efficient decommissioning of nuclear facilities and safe termination of nuclear activities; Review of lessons learned from ongoing or completed activities associated with decommissioning; Improvement of safety and efficiency through the use of new and innovative technologies; Practical aspects in the management of material, waste and sites resulting from decommissioning, including the management of waste in the absence of repositories and waste acceptance requirements; Procedures for demonstrating compliance with clearance criteria; Experience from radiological assessments associated with decommissioning; Involvement of the local communities and the impact that decommissioning activities has on them. The presented papers and posters were reviewed and accepted following the guidelines established by the Conference Programme Committee for consideration at the Conference. The material compiled in this Book of Contributed Papers has not undergone rigorous editing by the editorial staff of the IAEA. However, certain modifications were made: a unified format was adopted for all papers; and minor corrections were made in the text where required. Each paper and poster has been indexed

Costs of fuel cycle industrial facilities: an international review

International Nuclear Information System (INIS)

Macias, R.M.

2004-01-01

This document presents, comments, and compares economic and financial data for industrial facilities concerning different aspects of the nuclear fuel cycle. It first comments the present situation and the short term trends for the natural uranium market, the conversion market, the enrichment market, the reprocessing market, the storage market. It gives an assessment of the elementary costs of the existing facilities for the different stages and processes: reprocessing, spent fuel warehousing (example of the CLAB in Sweden and comparison with other available data), warehousing of all types of wastes (examples of Habog in Netherlands, Zwilag in Switzerland), spent fuel storage (example of Yucca Mountain in the USA, Onkalo in Finland, projects and studies in Sweden), storage of vitrified wastes in Belgium, storing of transuranic wastes in the USA, storage of low and intermediate level and short life wastes in Sweden

International symposium on seismic evaluation of existing nuclear facilities

Energy Technology Data Exchange (ETDEWEB)

Orbovic, N.; Bouchon, M. [Institut de Radioprotection et de Surete Nucleaire, IRSN, 92 - Fontenay aux Roses (France); Vendel, J.; Gelain, T. [IRSN/DPEA/SERAC, 91 - Gif sur Yvette (France)

2003-10-01

Below are summarized the works of Mrs N. Orbovic and M. Bouchon; B. Stojadinovic, N. Orbovic, M.Bouchon and J.T. Wiley; M. Bouchon, N. Orbovic and B. Foure; T. Gelain, F. Gensdarmes, R. Sestier-Carlin, J. Vendel and M. Bouchon dealing respectively with: 1) seismic assessment of existing nuclear facility: a case study position of the IRSN 2) static and dynamic evaluation of an existing nuclear facility reinforced concrete frame structure 3) experimental study of cracking of low-rise reinforced concrete shear walls 4) aeraulics study of crack networks on low-rise reinforced concrete walls subject to static cycling loading. The summaries are followed: 1) The Institute for Radioprotection and Nuclear Safety (IRSN) has the task of evaluating the seismic safety of existing building inventory in French nuclear facilities. Some of the existing structures are reinforced concrete frame buildings with masonry or reinforced concrete in-fill walls built during the 1960's, 70's and 80's following different building codes and seismic input data applicable at the time of construction. The studied building is a laboratory that was built in 1962. The building is composed of three different and independent blocks. The structure is a reinforced concrete frame with masonry in-fills and few stiff concrete elements. Moreover, the building contains an independent massive concrete cell. Structurally, the building has a number of irregularities. From the detailing standpoint, well known deficiencies of low-ductile reinforced concrete structures are evident especially, a lack of transverse reinforcement in the structural joints of the frame. A number of sensitivity studies were conducted using 2D and 3D linear models to evaluate seismic demand. Ambient vibration and regional earthquake records were used to check the soil nature and the existence or not of a possible site effect around the installation as well as to characterize the dynamic behavior of the building. 3D models

Development of Barnwell as a multinational demonstration facility

International Nuclear Information System (INIS)

Colby, L.J. Jr.

1977-01-01

The author takes an existing private business venture (Barnwell) with its assets of facilities, personnel, technology and domestic business commitments (past, present, and future) and develops a role for it which will be compatible with the advancement of multinational reprocessing facilities under international control

Report of the international workshop on safety measures to address the year 2000 issue at medical facilities which use radiation generators and radioactive materials. (Supplement to IAEA-TECDOC-1074)

International Nuclear Information System (INIS)

1999-08-01

In resolution GC(42)/RES/11 on 'Measures to Address the Year 2000 (Y2K) Issue', adopted on 25 September 1998, the General Conference of the International Atomic Energy Agency (IAEA) - inter alia - urged Member States 'to share information with the Secretariat regarding diagnostic and corrective actions being planned or implemented by operating and regulatory organizations at their ... medical facilities which use radioactive materials to make those facilities Year 2000 ready', encouraged the Secretariat 'within existing resources to act as a clearing-house and central point of contact for Member States to exchange information regarding diagnostic and remediation actions being taken at ... medical facilities which use radioactive materials to make these facilities Year 2000 ready', urged the Secretariat 'to handle the information provided by Member States carefully' and requested the Director General to report to it at its next (1999) regular session on the implementation of that resolution. To foster exchange of information and experience and to develop more specific advice based on this experience, the IAEA, in co-operation with the World Health Organization, conducted an International Workshop on Safety Measures to Address the Year 2000 Issue at Medical Facilities Which Use Radiation Generators and Radioactive Materials, held in Vienna, 28-30 June 1999. Whereas the focus in IAEA-TECDOC-1074 had been on identifying what might go wrong as a result of Y2K problems and on proposing methods to address them, the focus of the International Workshop was on sharing the experience gained in implementing the proposed methods - an approach consistent with the role of the Secretariat as 'a clearing-house and central point of contact for Member States to exchange information regarding diagnostic and remediation actions'

Methodology and technology of decommissioning nuclear facilities

International Nuclear Information System (INIS)

1986-01-01

The decommissioning and decontamination of nuclear facilities is a topic of great interest to many Member States of the International Atomic Energy Agency (IAEA) because of the large number of older nuclear facilities which are or soon will be retired from service. In response to increased international interest in decommissioning and to the needs of Member States, the IAEA's activities in this area have increased during the past few years and will be enhanced considerably in the future. A long range programme using an integrated systems approach covering all the technical, regulatory and safety steps associated with the decommissioning of nuclear facilities is being developed. The database resulting from this work is required so that Member States can decommission their nuclear facilities in a safe time and cost effective manner and the IAEA can effectively respond to requests for assistance. The report is a review of the current state of the art of the methodology and technology of decommissioning nuclear facilities including remote systems technology. This is the first report in the IAEA's expanded programme and was of benefit in outlining future activities. Certain aspects of the work reviewed in this report, such as the recycling of radioactive materials from decommissioning, will be examined in depth in future reports. The information presented should be useful to those responsible for or interested in planning or implementing the decommissioning of nuclear facilities

MONJU AS AN INTERNATIONAL ASSET: INTERNATIONAL ASSISTANCE AND COOPERATION

International Nuclear Information System (INIS)

Rodriguez, G.; Wisner, R.S.; Stuart, R.

2004-01-01

The role of the fast breeder reactor prototype Monju has expanded to meet the challenges of the 21st century. Today instead of being merely a demonstration of an economical, safe, environmentally responsible source of energy, as originally designed, it has also the capability to be transformed into a unique International Irradiations Test Facility. The potential for Monju's role in the Generation IV nuclear energy systems development, and fast reactor research and development area is clear. Its incomparable fast neutron spectrum density will be a major interest not only for Sodium Fast Reactor but for all the Generation IV concepts. As Monju's potential future role is laid out, plans for future tests can be made. Tests of advanced fuels and materials in support of the Advanced Fuel Cycle Initiative, as well as Minor Actinide Burning can be envisaged. Tests planned on transmutation of minor actinides have the objectives of an industrial demonstration of the reduction of toxic wastes and the stewardship burden of the long-lived wastes. Tests and demonstrations carried out at Monju will provide a bridge from existing Generation III fast reactor systems, now in the later stages of their projected operational lifetimes, to Generation IV nuclear energy systems. The JNC founded the International Cooperation and Technology Development Center and the International Research Fellowship program to facilitate this international effort. The Center exists specifically to formulate and perform projects ensuring the maximum technical benefit from Monju. The staff includes physicists, engineers and nuclear industry leaders from around the world. Research Fellowships center is based on several technical areas: advanced instrumentation, inspection techniques, plant reliability and safety, nucleonics, sodium handling technologies, irradiation and experiment management and coordination and advanced post-irradiation examination capabilities and techniques. This paper describes the recent

Safety of fuel cycle facilities. Topical issues paper no. 3

International Nuclear Information System (INIS)

Ranguelova, V.; Niehaus, F.; Delattre, D.

2001-01-01

A wide range of nuclear fuel cycle facilities are in operation. These installations process, use, store and dispose of radioactive material and cover: mining and milling, conversion, enrichment, fuel fabrication (including mixed oxide fuel), reactor, interim spent fuel storage, reprocessing, waste treatment and waste disposal facilities. For the purposes of this paper, reactors and waste disposal facilities are not considered. The term 'fuel cycle facilities' covers only the remainder of the installations listed above. The IAEA Secretariat maintains a database of fuel cycle facilities in its Member States. Known as the Nuclear Fuel Cycle Information System (NFCIS), it is available as an on-line service through the Internet. More than 500 such facilities have been reported under this system. The facilities are listed by facility type and operating status. Approximately one third of all of the facilities are located in developing States. About half of all facilities are reported to be operating, of which approximately 40% are operating in developing States. In addition, some 60 facilities are either in the design stage or under construction. Although the radioactive source term for most fuel cycle facilities is lower than the source term for reactors, which results in less severe consequences to the public from potential accidents at these fuel cycle installations, recent events at some fuel cycle facilities have given rise to public concern which has to be addressed adequately by national regulatory bodies and at the international level. Worldwide, operational experience feedback warrants improvements in the safety of these facilities. Some of the hazards are similar for reactor and non-reactor facilities. However, the differences between these installations give rise to specific safety concerns at fuel cycle facilities. In particular, these concerns include: criticality, radiation protection of workers, chemical hazards, fire and explosion hazards. It is recognized

Delirium in the intensive care setting and the Richmond Agitation and Sedation Scale (RASS): Drowsiness increases the risk and is subthreshold for delirium.

Science.gov (United States)

Boettger, Soenke; Nuñez, David Garcia; Meyer, Rafael; Richter, André; Fernandez, Susana Franco; Rudiger, Alain; Schubert, Maria; Jenewein, Josef

2017-12-01

Sedation is a core concept in the intensive care setting, however, the impact of sedation on delirium has not yet been studied to date. In this prospective cohort study, 225 patients with Richmond Agitation and Sedation (RASS) scores of -1 - drowsiness and 0 - alert- and calmness were assessed with the Delirium Rating Scale-Revised 1998 (DRS-R-98) and DSM-IV-TR-determined diagnosis of delirium assessing drowsiness versus alertness. By itself, drowsiness increased the odds for developing delirium eightfold (OR 7.88 pmemory representing the core domains of delirium, or the temporal onset were very sensitive towards delirium, however lacked specificity. Conversely, delusions, perceptual abnormalities and lability of affect representing the non-core domain were very specific for delirium in the drowsy, however, not very sensitive. In the absence of delirium, drowsiness caused attentional impairment and language abnormalities. Drowsiness increased the odds for developing delirium eightfold and caused more severe delirium, which was characterized by sleep-wake cycle and language abnormalities. Further, drowsiness by itself caused attentional impairment and language abnormalities, thus, with its disturbance in consciousness was subthreshold for delirium. Copyright © 2017 Elsevier Inc. All rights reserved.

International Physical Protection Advisory Service

International Nuclear Information System (INIS)

Soo Hoo, M.S.; Ek, D.; Hageman, A.; Jenkin, T.; Price, C.; Weiss, B.

1998-01-01

Since its inception in 1996, the purpose of the International Physical Protection Advisory Service (IPPAS) has been to provide advice and assistance to International Atomic Energy Agency (IAEA) Member States on strengthening and enhancing the effectiveness of their state system of physical protection of nuclear materials and facilities. Since the protection of nuclear materials and facilities is a Member State's responsibility, participation within the IPPAS program is voluntary. At the request of a Member State, the IAEA forms a multinational IPPAS team consisting of physical protection specialists. These specialists have broad experience in physical protection system design, implementation, and regulatory oversight. The exact make-up of the team depends upon the needs of the requesting state. IPPAS missions to participating states strive to compare the domestic procedures and practices of the state against international physical protection guidelines (IAEA Information Circular 225) and internationally accepted practice. The missions utilize a top to bottom approach and begin by reviewing the legal and regulatory structure and conclude with reviews of the implementation of the state regulations and international guidelines at individual facilities. IPPAS findings are treated as IAEA Safeguards Confidential Information. To date, IPPAS missions have been concluded in Slovenia, Bulgaria, Romania, Hungary, and Poland

Safety of magnetic fusion facilities: Guidance

International Nuclear Information System (INIS)

1996-05-01

This document provides guidance for the implementation of the requirements identified in DOE-STD-6002-96, Safety of Magnetic Fusion Facilities: Requirements. This guidance is intended for the managers, designers, operators, and other personnel with safety responsibilities for facilities designated as magnetic fusion facilities. While the requirements in DOE-STD-6002-96 are generally applicable to a wide range of fusion facilities, this Standard, DOE-STD-6003-96, is concerned mainly with the implementation of those requirements in large facilities such as the International Thermonuclear Experimental Reactor (ITER). Using a risk-based prioritization, the concepts presented here may also be applied to other magnetic fusion facilities. This Standard is oriented toward regulation in the Department of Energy (DOE) environment as opposed to regulation by other regulatory agencies. As the need for guidance involving other types of fusion facilities or other regulatory environments emerges, additional guidance volumes should be prepared. The concepts, processes, and recommendations set forth here are for guidance only. They will contribute to safety at magnetic fusion facilities

Dissolved radon and uranium in groundwater in a potential coal seam gas development region (Richmond River Catchment, Australia).

Science.gov (United States)

Atkins, Marnie L; Santos, Isaac R; Perkins, Anita; Maher, Damien T

2016-04-01

The extraction of unconventional gas resources such as shale and coal seam gas (CSG) is rapidly expanding globally and often prevents the opportunity for comprehensive baseline groundwater investigations prior to drilling. Unconventional gas extraction often targets geological layers with high naturally occurring radioactive materials (NORM) and extraction practices may possibly mobilise radionuclides into regional and local drinking water resources. Here, we establish baseline groundwater radon and uranium levels in shallow aquifers overlying a potential CSG target formation in the Richmond River Catchment, Australia. A total of 91 groundwater samples from six different geological units showed highly variable radon activities (0.14-20.33 Bq/L) and uranium levels (0.001-2.77 μg/L) which were well below the Australian Drinking Water Guideline values (radon; 100 Bq/L and uranium; 17 μg/L). Therefore, from a radon and uranium perspective, the regional groundwater does not pose health risks to consumers. Uranium could not explain the distribution of radon in groundwater. Relatively high radon activities (7.88 ± 0.83 Bq/L) in the fractured Lismore Basalt aquifer coincided with very low uranium concentrations (0.04 ± 0.02 μg/L). In the Quaternary Sediments aquifers, a positive correlation between U and HCO3(-) (r(2) = 0.49, p uranium was present as uranyl-carbonate complexes. Since NORM are often enriched in target geological formations containing unconventional gas, establishing radon and uranium concentrations in overlying aquifers comprises an important component of baseline groundwater investigations. Copyright © 2016 Elsevier Ltd. All rights reserved.

Very high vitamin D supplementation rates among infants aged 2 months in Vancouver and Richmond, British Columbia, Canada

Directory of Open Access Journals (Sweden)

Crocker Barbara

2011-12-01

Full Text Available Abstract Background Vitamin D deficiency during infancy may lead to rickets and possibly other poor health outcomes. The World Health Organization recommends exclusive breastfeeding for the first 6 months. Breast milk is the best food for infants but does not contain adequate vitamin D. Health Canada recommends all breastfed infants receive a daily vitamin D supplement of 400 IU; however, there appears to be limited current Canadian data as to whether parents or caregivers are following this advice. The aim of this study was to determine the rates of vitamin D supplementation among 2-month old infants in Vancouver and Richmond, British Columbia, Canada. Methods Mothers of all healthy infants born between April and May 2010 were approached to participate. Telephone surveys were conducted with 577 mothers (response rate 56% when their infants turned 2 months. Results Over half of the infants received only breast milk in the week prior to the survey. One third received a mixture of breast milk and infant formula and 10% received only formula. About 80% of the infants were supplemented with vitamin D at 2 months. Infants who received only breast milk were most likely to be supplemented with vitamin D (91%. Over 60% of the infants had a total vitamin D intake of 300- Conclusions About 90% of the infants received breast milk at 2 months of age. The vitamin D supplementation rate was 80%. Future studies are needed to monitor breastfeeding duration and vitamin D supplementation rates as infants get older.

(ICSID) ADDITIONAL FACILITY IN INTERNA

African Journals Online (AJOL)

Fr. Ikenga

... which is adopted by Article 5 of the Additional Facility Rules to guide the ... B, Barrister at Law, e-mail: kcezeibe@yahoo.com; Phone 08033950631 and .... revision and annulment which are internally available under the Washington ...

International symposium on seismic evaluation of existing nuclear facilities

International Nuclear Information System (INIS)

Orbovic, N.; Bouchon, M.; Vendel, J.; Gelain, T.

2003-10-01

Below are summarized the works of Mrs N. Orbovic and M. Bouchon; B. Stojadinovic, N. Orbovic, M.Bouchon and J.T. Wiley; M. Bouchon, N. Orbovic and B. Foure; T. Gelain, F. Gensdarmes, R. Sestier-Carlin, J. Vendel and M. Bouchon dealing respectively with: 1) seismic assessment of existing nuclear facility: a case study position of the IRSN 2) static and dynamic evaluation of an existing nuclear facility reinforced concrete frame structure 3) experimental study of cracking of low-rise reinforced concrete shear walls 4) aeraulics study of crack networks on low-rise reinforced concrete walls subject to static cycling loading. The summaries are followed: 1) The Institute for Radioprotection and Nuclear Safety (IRSN) has the task of evaluating the seismic safety of existing building inventory in French nuclear facilities. Some of the existing structures are reinforced concrete frame buildings with masonry or reinforced concrete in-fill walls built during the 1960's, 70's and 80's following different building codes and seismic input data applicable at the time of construction. The studied building is a laboratory that was built in 1962. The building is composed of three different and independent blocks. The structure is a reinforced concrete frame with masonry in-fills and few stiff concrete elements. Moreover, the building contains an independent massive concrete cell. Structurally, the building has a number of irregularities. From the detailing standpoint, well known deficiencies of low-ductile reinforced concrete structures are evident especially, a lack of transverse reinforcement in the structural joints of the frame. A number of sensitivity studies were conducted using 2D and 3D linear models to evaluate seismic demand. Ambient vibration and regional earthquake records were used to check the soil nature and the existence or not of a possible site effect around the installation as well as to characterize the dynamic behavior of the building. 3D models revealed a

Advanced physical protection systems for facilities and transportation

International Nuclear Information System (INIS)

Jones, O.E.

1976-01-01

Sandia Laboratories is developing advanced physical protection safeguards in order to improve the security of special nuclear materials, facilities, and transportation. Computer models are being used to assess the cost-effectiveness of alternative systems for protecting facilities against external attack which may include internal assistance, and against internal theft or sabotage. Physical protection elements such as admittance controls, portals and detectors, perimeter and interior intrusion alarms, fixed and remotely activated barriers, and secure communications are being evaluated, adapted, and where required, developed. New facilities safeguards concepts which involve ''control loops'' between physical protection and materials control elements are being evolved jointly between Sandia Laboratories and Los Alamos Scientific Laboratory. Special vehicles and digital communications equipment have been developed for the ERDA safe-secure transportation system. The current status and direction of these activities are surveyed

Advanced physical protection systems for facilities and transportation

International Nuclear Information System (INIS)

Jones, O.E.

1976-01-01

Sandia Laboratories is developing advanced physical protection safeguards in order to improve the security of special nuclear materials, facilities, and transportation. Computer models are being used to assess the cost-effectiveness of alternative systems for protecting facilities against external attack which may include internal assistance, and against internal theft or sabotage. Physical protection elements such as admittance controls, portals and detectors, perimeter and interior intrusion alarms, fixed and remotely-activated barriers, and secure communications are being evaluated, adapted, and where required, developed. New facilities safeguards concepts which involve (control loops) between physical protection and materials control elements are being evolved jointly between Sandia Laboratories and Los Alamos Scientific Laboratory. Special vehicles and digital communications equipment have been developed for the ERDA safe-secure transportation system. The current status and direction of these activities are surveyed

Assistance Dogs: Historic Patterns and Roles of Dogs Placed by ADI or IGDF Accredited Facilities and by Non-Accredited U.S. Facilities.

Science.gov (United States)

Walther, Sandra; Yamamoto, Mariko; Thigpen, Abigail Paige; Garcia, Anaissa; Willits, Neil H; Hart, Lynette A

2017-01-01

Dogs' roles to support people with disabilities are increasing. Existing U.S. laws and regulations pertaining to the use of dogs for people with disabilities are only minimally enforced. Pushback legislation against some aspects of uses of assistance dogs currently is being passed or proposed in several states. Further, the U.S. Department of the Army and the Veterans' Administration support only dogs trained by an Assistance Dogs International (ADI) or International Guide Dog Federation (IGDF) accredited facility. Lacking a mandatory national process for screening the selection, training, and placement of assistance dogs with persons who have disabilities, the U.S. offers a creative but confusing opportunity for people to train their own dogs for any disability. While no U.S. surveillance system monitors assistance dogs, other countries generally have a legislated or regulatory process for approving assistance dogs or a cultural convention for obtaining dogs from accredited facilities. We conducted an online survey investigating current demographics of assistance dogs placed in 2013 and 2014 with persons who have disabilities, by facilities worldwide that are associated with ADI or IGDF and by some non-accredited U.S. facilities. Placement data from ADI and IGDF facilities revealed that in most countries aside from the U.S., guide dogs were by far the main type of assistance dog placed. In the U.S., there were about equal numbers of mobility and guide dogs placed, including many placed by large older facilities, along with smaller numbers of other types of assistance dogs. In non-accredited U.S. facilities, psychiatric dogs accounted for most placements. Dogs for families with an autistic child were increasing in all regions around the world. Of dog breeds placed, accredited facilities usually mentioned Labrador Retrievers and Golden Retrievers, and sometimes, German Shepherd Dogs. The facilities bred their dogs in-house, or acquired them from certain breeders

2010 winter games tracks energy in real time

Energy Technology Data Exchange (ETDEWEB)

Anon.

2010-01-15

An online energy tracker was developed by BC Hydro to publicly monitor the real-time energy consumption at the Vancouver 2010 Olympic winter game sites within Vancouver, Richmond, Whistler and Whistler Blackcomb. The venues and associated sites participating in the live energy tracking project were the Richmond Olympic Oval, Canada Hockey Place, Vancouver Olympic/Paralympic Centre, South East False Creek Community Centre, Whistler Blackcomb Roundhouse Lodge and snowmaking facilities, and the Olympic and Paralympic Villages. The system was developed to allow venue managers to optimize their use of electricity on an hourly and daily basis. An energy tracking display board developed by Pulse Energy enabled them to compare their performance to similar facilities in real time, and to determine the greenhouse gas savings achieved as result of building and operating practices. Some venues had the potential to save as much as 15 to 20 per cent in energy costs with corresponding reductions in carbon emissions. Efficiency and conservation was built into the design of many new venues. The retrofits made to several existing buildings will continue to contribute to British Columbia's conservation goals long after the 2010 winter games are over.

IAEA Assistance on Decommissioning of Small Facilities with Limited Resources

International Nuclear Information System (INIS)

Batandjieva, B.; Warnecke, E.

2008-01-01

The number of facilities reaching their lifetime is increasing and drawing the attention of operators, regulators, public and other interested parties (potential users of the site after decommissioning) on the importance of adequate planning, funding and implementation of decommissioning activities in compliance with regulatory requirements and criteria. Specific attention is required for small facilities that have been used for research purposes and in most cases state owned by and dependent on state funding. With the current tendency for expansion of the nuclear industry such small facilities could become less of importance for the operators which can increase the probability that these facilities become abandoned, hazardous and imposing undue burden to future generations. This concern is more related to countries with limited human and financial resources at the operating organizations and the regulatory body. The International Atomic Energy Agency (IAEA) has been working on the; (i) establishment of internationally recognized safety standards on decommissioning and (ii) providing Member States with assistance on the application of these standards. The recent international conference on Lessons Learned from the Decommissioning of Nuclear Facilities and the Safe Termination of Practices (Athens, Greece, 2006) has demonstrated that the set of IAEA standards is almost complete and that the International Action Plan on Decommissioning (2004), that is addressing decommissioning of small facilities, is being successfully implemented. However the need for further assistance on decommissioning of small facilities in countries with limited resources was also recognized and the Agency is planning its future work in this field. The IAEA also addresses the needs of small nuclear countries that have only a limited number of nuclear facilities, e.g. a research reactor, in its R esearch Reactor Decommissioning Demonstration Project (R 2 D 2 P. The Philippine Research Reactor

Safety of magnetic fusion facilities: Volume 2, Guidance

International Nuclear Information System (INIS)

1995-01-01

This document provides guidance for the implementation of the requirements identified in Vol. 1 of this Standard. This guidance is intended for the managers, designers, operators, and other personnel with safety responsibilities for facilities designated as magnetic fusion facilities. While Vol. 1 is generally applicable in that requirements there apply to a wide range of fusion facilities, this volume is concerned mainly with large facilities such as the International Thermonuclear Experimental Reactor (ITER). Using a risk-based prioritization, the concepts presented here may also be applied to other magnetic fusion facilities. This volume is oriented toward regulation in the Department of Energy (DOE) environment

A heuristic approach to handle capacitated facility location problem evaluated using clustering internal evaluation

Science.gov (United States)

Sutanto, G. R.; Kim, S.; Kim, D.; Sutanto, H.

2018-03-01

One of the problems in dealing with capacitated facility location problem (CFLP) is occurred because of the difference between the capacity numbers of facilities and the number of customers that needs to be served. A facility with small capacity may result in uncovered customers. These customers need to be re-allocated to another facility that still has available capacity. Therefore, an approach is proposed to handle CFLP by using k-means clustering algorithm to handle customers’ allocation. And then, if customers’ re-allocation is needed, is decided by the overall average distance between customers and the facilities. This new approach is benchmarked to the existing approach by Liao and Guo which also use k-means clustering algorithm as a base idea to decide the facilities location and customers’ allocation. Both of these approaches are benchmarked by using three clustering evaluation methods with connectedness, compactness, and separations factors.

Radiation safety study for conventional facility and siting pre project phase of International Linear Collider

International Nuclear Information System (INIS)

Sanami, Toshiya; Ban, Syuichi; Sasaki, Shin-ichi

2015-01-01

The International Linear Collider (ILC) is a proposed high-energy collider consisting of two linear accelerators, two dumping rings, electron and positron sources, and a single colliding hall with two detectors. The total length and CMS energy of the ILC will be 31 km and 500 GeV, respectively (and 50 km and 1 TeV after future upgrade). The design of the ILC has entered the pre-project phase, which includes site-dependent design. Radiation safety design for the ILC is on-going as a part of conventional facility and siting activities of the pre-project phase. The thickness of a central wall of normal concrete is designed to be 3.5 m under a pessimistic assumption of beam loss. The beam loss scenario is under discussion. Experience and knowledge relating to shielding design and radiation control operational work at other laboratories are required. (authors)

International nuclear waste management fact book

International Nuclear Information System (INIS)

Abrahms, C.W.; Patridge, M.D.; Widrig, J.E.

1995-11-01

The International Nuclear Waste Management Fact Book has been compiled to provide current data on fuel cycle and waste management facilities, R and D programs, and key personnel in 24 countries, including the US; four multinational agencies; and 20 nuclear societies. This document, which is in its second year of publication supersedes the previously issued International Nuclear Fuel Cycle Fact Book (PNL-3594), which appeared annually for 12 years. The content has been updated to reflect current information. The Fact Book is organized as follows: National summaries--a section for each country that summarizes nuclear policy, describes organizational relationships, and provides addresses and names of key personnel and information on facilities. International agencies--a section for each of the international agencies that has significant fuel cycle involvement and a list of nuclear societies. Glossary--a list of abbreviations/acronyms of organizations, facilities, and technical and other terms. The national summaries, in addition to the data described above, feature a small map for each country and some general information that is presented from the perspective of the Fact Book user in the US

International nuclear waste management fact book

Energy Technology Data Exchange (ETDEWEB)

Abrahms, C W; Patridge, M D; Widrig, J E

1995-11-01

The International Nuclear Waste Management Fact Book has been compiled to provide current data on fuel cycle and waste management facilities, R and D programs, and key personnel in 24 countries, including the US; four multinational agencies; and 20 nuclear societies. This document, which is in its second year of publication supersedes the previously issued International Nuclear Fuel Cycle Fact Book (PNL-3594), which appeared annually for 12 years. The content has been updated to reflect current information. The Fact Book is organized as follows: National summaries--a section for each country that summarizes nuclear policy, describes organizational relationships, and provides addresses and names of key personnel and information on facilities. International agencies--a section for each of the international agencies that has significant fuel cycle involvement and a list of nuclear societies. Glossary--a list of abbreviations/acronyms of organizations, facilities, and technical and other terms. The national summaries, in addition to the data described above, feature a small map for each country and some general information that is presented from the perspective of the Fact Book user in the US.

Neutron radiographic techniques, facilities and applications

International Nuclear Information System (INIS)

Domanus, J.C.

1984-08-01

This is a collection of three papers, written for presentation on two international conferences. The first paper: ''Neutron radiography. Techniques and facilities'', written by J.P. Barton of N-Ray Engineering Co. La Jolla, CA., USA and J.C. Domanus was presented at the International Symposium on the Use and Development of Low and Medium Flux Research Reactors at the Massachusets Institute of Technology, Cambridge, Mass., USA, 16-19 October 1983. The second paper: ''Neutron radiography with the DR-1 reactor at Risoe National Laboratory'', written by J.C. Domanus, was presented at the same Symposium. The third paper: ''Defects in nuclear fuel revealed by neutron radiography'', written by J.C. Domanus is accepted for presentation on 18 October 1984 to the 3rd European Conference on Nondestructive Testing, Florence, Italy, 15-18 October 1984. While the first paper describes the principles of neutron radiographic techniques and facilities, the second one describes an example of such facility and the third gives an example of application of neutron radiography in the field of nuclear fuel. (author)

International inspection activity impacts upon DOE safeguards requirements

International Nuclear Information System (INIS)

Zack, N.R.

1995-01-01

The US has placed certain special nuclear materials declared excess to their strategic needs under international safeguards through the International Atomic Energy Agency (IAEA). This Presidential initiative has obligated materials at several Department of Energy (DOE) facilities for these safeguards activities to demonstrate the willingness of the US to ban production or use of nuclear materials outside of international safeguards. However, IAEA inspection activities generally tend to be intrusive in nature and are not consistent with several domestic safeguards procedures implemented to reduce worker radiation exposures and increase the cost-effectiveness and efficiency of accounting for and storing of special nuclear materials. To help identify and provide workable solutions to these concerns, the Office of Safeguards and Security has conducted a program to determine possible changes to the DOE safeguards and security requirements designed to help facilities under international safeguards inspections more easily comply with domestic safeguards goals during international inspection activities. This paper will discuss the impact of international inspection activities on facility safeguards operations and departmental safeguards procedures and policies

International nuclear fuel cycle fact book

International Nuclear Information System (INIS)

1992-09-01

The International Nuclear Fuel Cycle Fact Book has been compiled in an effort to provide current data concerning fuel cycle and waste management facilities, R ampersand D programs and key personnel on 23 countries, including the US, four multi-national agencies, and 21 nuclear societies. The Fact Book is organized as follows: National summaries-a section for each country which summarizes nuclear policy, describes organizational relationships, and provides addresses and names of key personnel and information on facilities. International agencies-a section for each of the international agencies which has significant fuel cycle involvement and a listing of nuclear societies. Glossary-a list of abbreviations/acronyms of organizations, facilities, technical and other terms. The national summaries, in addition to the data described above, feature a small map for each country as well as some general information. The latter presented from the perspective of the Fact Book user in the United States

The decommissioning of nuclear facilities

International Nuclear Information System (INIS)

Niel, J.Ch.; Rieu, J.; Lareynie, O.; Delrive, L.; Vallet, J.; Girard, A.; Duthe, M.; Lecomte, C.; Rozain, J.P.; Nokhamzon, J.G.; Davoust, M.; Eyraud, J.L.; Bernet, Ph.; Velon, M.; Gay, A.; Charles, Th.; Leschaeva, M.; Dutzer, M.; Maocec, Ch.; Gillet, G.; Brut, F.; Dieulot, M.; Thuillier, D.; Tournebize, F.; Fontaine, V.; Goursaud, V.; Birot, M.; Le Bourdonnec, Th.; Batandjieva, B.; Theis, St.; Walker, St.; Rosett, M.; Cameron, C.; Boyd, A.; Aguilar, M.; Brownell, H.; Manson, P.; Walthery, R.; Wan Laer, W.; Lewandowski, P.; Dorms, B.; Reusen, N.; Bardelay, J.; Damette, G.; Francois, P.; Eimer, M.; Tadjeddine, A.; Sene, M.; Sene, R.

2008-01-01

This file includes five parts: the first part is devoted to the strategies of the different operators and includes the following files: the decommissioning of nuclear facilities Asn point of view, decommissioning of secret nuclear facilities, decommissioning at the civil Cea strategy and programs, EDF de-construction strategy, Areva strategy for decommissioning of nuclear facilities; the second one concerns the stakes of dismantling and includes the articles as follow: complete cleanup of buildings structures in nuclear facilities, decommissioning of nuclear facilities and safety assessment, decommissioning wastes management issues, securing the financing of long-term decommissioning and waste management costs, organizational and human factors in decommissioning projects, training for the decommissioning professions: the example of the Grenoble University master degree; the third part is devoted to the management of dismantling work sites and includes the different articles as follow: decommissioning progress at S.I.C.N. plant, example of decommissioning work site in Cea Grenoble: Siloette reactor decommissioning, matters related to decommissioning sites, decommissioning of french nuclear installations: the viewpoint of a specialist company, specificities of inspections during decommissioning: the Asn inspector point of view; the fourth part is in relation with the international approach and includes as follow: IAEA role in establishing a global safety regime on decommissioning, towards harmonization of nuclear safety practices in Europe: W.E.N.R.A. and the decommissioning of nuclear facilities, EPA superfund program policy for decontamination and decommissioning, progress with remediation at Sellafield, progress and experiences from the decommissioning of the Eurochemic reprocessing plant in Belgium, activities of I.R.S.N. and its daughter company Risk-audit I.r.s.n./G.r.s. international in the field of decommissioning of nuclear facilities in eastern countries

Operational Control of Internal Transport

NARCIS (Netherlands)

J.R. van der Meer (Robert)

2000-01-01

textabstractOperational Control of Internal Transport considers the control of guided vehicles in vehicle-based internal transport systems found in facilities such as warehouses, production plants, distribution centers and transshipment terminals. The author's interest of research having direct use

Concerning problems of petroleum refining facilities. ; Promote international lateral work sharing, and strengthening of infrastructures in petroleum industry. Sekiyu seisei setsubi mondai ni tsuite. ; Kokusei suihei bungyo no suishin to sekiyu sangyo no kiban kyoka wo

Energy Technology Data Exchange (ETDEWEB)

1991-06-05

This paper discusses how to promote international lateral work sharing and how to strengthen infrastructures in the petroleum industry, as a problem prevailing over the petroleum refining facilities in Japan. Excess distillation facilities have been applied with the disposition policy. However, in view of the supply and demand situation in petroleum products for medium to long term span in the world with the pan-Pacific region as the main concern, that applicable to Japan, and that experienced during the Persian Gulf crisis, the excess facility disposition policy was revised, particularly on white kerosene, of which supply and demand tightness is concerned about, so that production capacities may be increased as required. Japan, a large presence in the international economics, is required to work more positively on petroleum refining facilities located in the oil producing countries and intermediate locations to promote the international lateral work sharing. On the one hand, in order to strengthen the infrastructures in the Japanese petroleum industry, it is necessary to promote rationalization and use at higher efficiency of the oil supply system, and convergence of the the petroleum industry, including joint investments for projects exceeding capabilities of individual enterprises. 3 tabs.

History Data Facility in the SLC control system

International Nuclear Information System (INIS)

Johnson, R.G.; White, G.R.

1991-10-01

Two major enhancements to the SLC History Data Facility are described separately. First the internal design and procedures used for saving and using long term history data. Second the user interface, facilities and application of the History Data Comparisons sub-system, which is used for analyzing and correlating two or more accelerator device histories

An Overview of the Microgravity Science Glovebox (MSG) Facility and the Research Performed in the MSG on the International Space Station (ISS)

Science.gov (United States)

Jordan, Lee P.

2013-01-01

The Microgravity Science Glovebox (MSG) is a rack facility aboard the International Space Station (ISS) designed for investigation handling. The MSG was built by the European Space Agency (ESA) which also provides sustaining engineering support for the facility. The MSG has been operating on the ISS since July 2002 and is currently located in the US Laboratory Module. The unique design of the facility allows it to accommodate science and technology investigations in a "workbench" type environment. The facility has an enclosed working volume that is held at a negative pressure with respect to the crew living area. This allows the facility to provide two levels of containment for small parts, particulates, fluids, and gases. This containment approach protects the crew from possible hazardous operations that take place inside the MSG work volume. Research investigations operating inside the MSG are provided a large 255 liter enclosed work space, 1000 watts of dc power via a versatile supply interface (120, 28, +/- 12, and 5 Vdc), 1000 watts of cooling capability, video and data recording and real time downlink, ground commanding capabilities, access to ISS Vacuum Exhaust and Vacuum Resource Systems, and gaseous nitrogen supply. These capabilities make the MSG one of the most utilized facilities on ISS. The MSG has been used for over 14500 hours of scientific payload operations. MSG investigations involve research in cryogenic fluid management, fluid physics, spacecraft fire safety, materials science, combustion, plant growth, and life support technology. The MSG facility is operated by the Payloads Operations Integration Center at Marshall Space flight Center. Payloads may also operate remotely from different telescience centers located in the United States and Europe. The investigative Payload Integration Manager (iPIM) is the focal to assist organizations that have payloads operating in the MSG facility. NASA provides an MSG engineering unit for payload developers

Four critical facilities: their capabilities and programs

International Nuclear Information System (INIS)

Whitesides, G.E.

1980-01-01

Information is presented on the critical experiments facilities at Babcock and Wilcox, Lynchburg, Virginia; at Battelle Pacific Northwest Laboratory in Hanford, Washington; at Rockwell-International in Rocky Flats, Colorado; and at Los Alamos Scientific Laboratory in New Mexico. It is noted that the critical mass facilities which still exist in this country represent a bare minimum for maintaining a measurement program sufficient for meeting data requirements

Current personnel dosimetry practices at DOE facilities

International Nuclear Information System (INIS)

Fix, J.J.

1981-05-01

Only three parameters were included in the personnel occupational exposure records by all facilities. These are employee name, social security number, and whole body dose. Approximate percentages of some other parameters included in the record systems are sex (50%), birthdate (90%), occupation (26%), previous employer radiation exposure (74%), etc. Statistical analysis of the data for such parameters as sex versus dose distribution, age versus dose distribution, cumulative lifetime dose, etc. was apparently seldom done. Less than 50% of the facilities reported having formal documentation for either the dosimeter, records system, or reader. Slightly greater than 50% of facilities reported having routine procedures in place. These are considered maximum percentages because some respondents considered computer codes as formal documentation. The repository receives data from DOE facilities regarding the (a) distribution of annual whole body doses, (b) significant internal depositions, and (c) individual doses upon termination. It is expected that numerous differences exist in the dose data submitted by the different facilities. Areas of significant differences would likely include the determination of non-measurable doses, the methods used to determine previous employer radiation dose, the methods of determining cumulative radiation dose, and assessment of internal doses. Undoubtedly, the accuracy of the different dosimetry systems, especially at low doses, is very important to the credibility of data summaries (e.g., man-rem) provided by the repository

Preparation of safety and regulatory document for BARC Facilities

International Nuclear Information System (INIS)

Prasad, S.S.; Jayarajan, K.

2017-01-01

In India, the necessary codes and safety guidelines for achieving the safety objectives are provided by the Atomic Energy Regulatory Board (AERB), which are in conformity with the principles of radiation protection as formulated by the International Council of Radiation Protection (ICRP) and International Atomic Energy Agency (IAEA). The same is followed by BARC Safety Council (BSC), which is the regulatory body for the BARC facilities. In addition to all types of fuel cycle facilities, BSC regulates safety of many types of conventional facilities. Many such types of facilities and projects are not under the regulatory purview of AERB. Therefore, the Council has also initiated a programme for development and publication of safety documents for installations in BARC in the fields/ topics yet not addressed by IAEA or AERB. This makes the task pioneering, as some of the areas taken up for defining the regulatory requirements are new, where standard regulatory documents are not available

The zenithal 4-m International Liquid Mirror Telescope: a unique facility for supernova studies

Science.gov (United States)

Kumar, Brajesh; Pandey, Kanhaiya L.; Pandey, S. B.; Hickson, P.; Borra, E. F.; Anupama, G. C.; Surdej, J.

2018-05-01

The 4-m International Liquid Mirror Telescope (ILMT) will soon become operational at the newly developed Devasthal observatory near Nainital (Uttarakhand, India). Coupled with a 4k × 4k pixels CCD detector and TDI optical corrector, it will reach approximately 22.8, 22.3, and 21.4 mag in the g΄, r΄, and i΄ spectral bands, respectively, in a single scan. The limiting magnitudes can be further improved by co-adding the consecutive night images in particular filters. The uniqueness to observe the same sky region by looking towards the zenith direction every night makes the ILMT a unique instrument to detect new supernovae (SNe) by applying the image subtraction technique. High cadence (˜24 h) observations will help to construct dense sampling multi-band SNe light curves. We discuss the importance of the ILMT facility in the context of SNe studies. Considering the various plausible cosmological parameters and observational constraints, we perform detailed calculations of the expected SNe rate that can be detected with the ILMT in different spectral bands.

49 CFR 193.2631 - Internal corrosion control.

Science.gov (United States)

2010-10-01

... 49 Transportation 3 2010-10-01 2010-10-01 false Internal corrosion control. 193.2631 Section 193... GAS FACILITIES: FEDERAL SAFETY STANDARDS Maintenance § 193.2631 Internal corrosion control. Each component that is subject to internal corrosive attack must be protected from internal corrosion by— (a...

Physics at a future Neutrino Factory and super-beam facility

NARCIS (Netherlands)

Bandyopadhyay, A.; Choubey, S.; Gandhi, R.; Goswami, S.; Roberts, B. L.; Bouchez, J.; Antoniadis, I.; Ellis, J.; Giudice, G. F.; Schwetz, T.; Umasankar, S.; Karagiorgi, G.; Aguilar-Arevalo, A.; Conrad, J. M.; Shaevitz, M. H.; Pascoli, S.; Geer, S.; Campagne, J. E.; Rolinec, M.; Blondel, A.; Campanelli, M.; Kopp, J.; Lindner, M.; Peltoniemi, J.; Dornan, P. J.; Long, K.; Matsushita, T.; Rogers, C.; Uchida, Y.; Dracos, M.; Whisnant, K.; Casper, D.; Chen, Mu-Chun; Popov, B.; Aysto, J.; Marfatia, D.; Okada, Y.; Sugiyama, H.; Jungmann, K.; Lesgourgues, J.; Zisman, M.; Tortola, M. A.; Friedland, A.; Davidson, S.; Antusch, S.; Biggio, C.; Donini, A.; Fernandez-Martinez, E.; Gavela, B.; Maltoni, M.

2009-01-01

The conclusions of the Physics Working Group of the International Scoping Study of a future Neutrino Factory and super-beam facility (the ISS) are presented. The ISS was carried out by the international community between NuFact05, (the 7th International Workshop on Neutrino Factories and

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.

Draft principles, policy, and acceptance criteria for decommissioning of U.S. Department of Energy contaminated surplus facilities and summary of international decommissioning programs

International Nuclear Information System (INIS)

Singh, B.K.

1994-12-01

Decommissioning activities enable the DOE to reuse all or part of a facility for future activities and reduce hazards to the general public and any future work force. The DOE Office of Environment, Health and Safety has prepared this document, which consists of decommissioning principles and acceptance criteria, in an attempt to establish a policy that is in agreement with the NRC policy. The purpose of this document is to assist individuals involved with decommissioning activities in determining their specific responsibilities as identified in Draft DOE Order 5820.DDD, ''Decommissioning of US Department of Energy Contaminated Surplus Facilities'' (Appendix A). This document is not intended to provide specific decommissioning methodology. The policies and principles of several international decommissioning programs are also summarized. These programs are from the IAEA, the NRC, and several foreign countries expecting to decommission nuclear facilities. They are included here to demonstrate the different policies that are to be followed throughout the world and to allow the reader to become familiar with the state of the art for environment, safety, and health (ES and H) aspects of nuclear decommissioning

Comparison of the socioeconomic impacts of international fuel service centers versus dispersed nuclear facilities

International Nuclear Information System (INIS)

Braid, R.B. Jr.

1979-01-01

The paper investigates a variety of community impacts including: public services, fiscal issues, economic matters, land and water use, political and social cohesion, and legal considerations. Comparisons of socioeconomic impacts of colocated versus dispersed sites are made on the basis of the size of the impacted communities, the size and type of nuclear facility, and the facility's construction time frame. The paper concludes that, under similar circumstances, most of the socioeconomic impacts of colocated nuclear facilities would be somewhat less than the sum of the impacts associated with equivalent dispersed sites. While empirical data is non-existent, the paper contends, however, that because the socioeconomic impacts of colocated facilities are so great and readily identifiable to a public unskilled in making comparisons with the dispersed alternative, the facilities will likely generate so much public opposition that IFSCs will probably prove infeasible

26 CFR 1.188-1 - Amortization of certain expenditures for qualified on-the-job training and child care facilities.

Science.gov (United States)

2010-04-01

... qualified on-the-job training and child care facilities. 1.188-1 Section 1.188-1 Internal Revenue INTERNAL... qualified on-the-job training and child care facilities. (a) Allowance of deduction—(1) In general. Under... operation of a qualified on-the-job training or child care facility or are integrally related facilities...

Physics at a future Neutrino Factory and super-beam facility

CERN Document Server

Bandyopadhyay, A; Gandhi, R; Goswami, S; Roberts, B L; Bouchez, J; Antoniadis, I; Ellis, J; Giudice, G F; Schwetz, T; Umansankar, S; Karagiorgi, G; Aguilar-Arevalo, A; Conrad, J M; Shaevitz, M H; Pascoli, Silvia; Geer, S; Rolinec, M; Blondel, A; Campanelli, M; Kopp, J; Lindner, M; Peltoniemi, J; Dornan, P J; Long, K; Matsushita, T; Rogers, C; Uchida, Y; Dracos, M; Whisnant, K; Casper, D; Chen, Mu-Chun; Popov, B; Aysto, J; Marfatia, D; Okada, Y; Sugiyama, H; Jungmann, K; Lesgourgues, J; Murayama, France H; Zisman, M; Tortola, M A; Friedland, A; Antusch, S; Biggio, C; Donini, A; Fernandez-Martinez, E; Gavela, B; Maltoni, M; Lopez-Pavon, J; Rigolin, S; Mondal, N; Palladino, V; Filthaut, F; Albright, C; de Gouvea, A; Kuno, Y; Nagashima, Y; Mezzetoo, M; Lola, S; Langacker, P; Baldini, A; Nunokawa, H; Meloni, D; Diaz, M; King, S F; Zuber, K; Akeroyd, A G; Grossman, Y; Farzan, Y; Tobe, K; Aoki, Mayumi; Kitazawa, N; Yasuda, O; Petcov, S; Romanino, A; Chimenti, P; Vacchi, A; Smirnov, A Yu; Couce, Italy E; Gomez-Cadenas, J J; Hernandez, P; Sorel, M; Valle, J W F; Harrison, P F; Lundardini, C; Nelson, J K; Barger, V; Everett, L; Huber, P; Winter, W; Fetscher, W; van der Schaaf, A

2009-01-01

The conclusions of the Physics Working Group of the international scoping study of a future Neutrino Factory and super-beam facility (the ISS) are presented. The ISS was carried by the international community between NuFact05, (the 7th International Workshop on Neutrino Factories and Superbeams, Laboratori Nazionali di Frascati, Rome, June 21-26, 2005) and NuFact06 (Ivine, California, 24{30 August 2006). The physics case for an extensive experimental programme to understand the properties of the neutrino is presented and the role of high-precision measurements of neutrino oscillations within this programme is discussed in detail. The performance of second generation super-beam experiments, beta-beam facilities, and the Neutrino Factory are evaluated and a quantitative comparison of the discovery potential of the three classes of facility is presented. High-precision studies of the properties of the muon are complementary to the study of neutrino oscillations. The Neutrino Factory has the potential to provide ...

Benchmarking facilities providing care: An international overview of initiatives

Science.gov (United States)

Thonon, Frédérique; Watson, Jonathan; Saghatchian, Mahasti

2015-01-01

We performed a literature review of existing benchmarking projects of health facilities to explore (1) the rationales for those projects, (2) the motivation for health facilities to participate, (3) the indicators used and (4) the success and threat factors linked to those projects. We studied both peer-reviewed and grey literature. We examined 23 benchmarking projects of different medical specialities. The majority of projects used a mix of structure, process and outcome indicators. For some projects, participants had a direct or indirect financial incentive to participate (such as reimbursement by Medicaid/Medicare or litigation costs related to quality of care). A positive impact was reported for most projects, mainly in terms of improvement of practice and adoption of guidelines and, to a lesser extent, improvement in communication. Only 1 project reported positive impact in terms of clinical outcomes. Success factors and threats are linked to both the benchmarking process (such as organisation of meetings, link with existing projects) and indicators used (such as adjustment for diagnostic-related groups). The results of this review will help coordinators of a benchmarking project to set it up successfully. PMID:26770800

Proposal for an irradiation facility at the TAEK SANAEM Proton Accelerator Facility

Science.gov (United States)

Demirköz, B.; Gencer, A.; Kiziloren, D.; Apsimon, R.

2013-12-01

Turkish Atomic Energy Authority's (TAEK's) Proton Accelerator Facility in Ankara, Turkey, has been inaugurated in May 2012 and is under the process of being certified for commercial radio-isotope production. Three of the four arms of the 30 MeV cyclotron are being used for radio-isotope production, while the fourth is foreseen for research and development of novel ideas and methods. The cyclotron can vary the beam current between 12 μA and 1.2 mA, sufficient for irradiation tests for semiconductor materials, detectors and devices. We propose to build an irradiation facility in the R&D room of this complex, open for use to the international detector development community.

Antibody responses induced by Japanese whole inactivated vaccines against equine influenza virus (H3N8) belonging to Florida sublineage clade2.

Science.gov (United States)

Yamanaka, Takashi; Bannai, Hiroshi; Nemoto, Manabu; Tsujimura, Koji; Kondo, Takashi; Matsumura, Tomio

2011-04-01

In 2010, the World Organisation for Animal Health recommended the inclusion of a Florida sublineage clade2 strain of equine influenza virus (H3N8), which is represented by A/equine/Richmond/1/07 (Richmond07), in equine influenza vaccines. Here, we evaluate the antigenic differences between Japanese vaccine strains and Richmond07 by performing hemagglutination inhibition (HI) assays. Ferret antiserum raised to A/equine/La Plata/93 (La Plata93), which is a Japanese vaccine strain, reacted with Richmond07 at a similar titer to La Plata93. Moreover, two hundred racehorses exhibited similar geometric mean HI antibody titers against La Plata93 and Richmond07 (73.1 and 80.8, respectively). Therefore, we can expect the antibody induced by the current Japanese vaccines to provide some protection against Richmond07-like viruses.

Internal dose estimation by bio-assay techniques

International Nuclear Information System (INIS)

Sawant, Pramilla D.

2016-01-01

Radiation exposure, both external and internal, can occur to radiation workers during the operation of various nuclear fuel cycle facilities and radiation facilities. The assessment of radiation doses to workers, routinely or potentially exposed to radiation, through intake of radionuclide is an integral part of the radiation protection programme. Internal dose is the radiation exposure that results from the intake of radioactive materials into the body by inhalation, ingestion, absorption through the skin or via wounds. Assessment of radiation doses arising from the intake of radioactive material by the workers is termed as internal exposure assessment. Unlike external exposure, internal exposure cannot be measured directly. Its evaluation is based on the calculation of the intake of radionuclide either from direct measurements (e.g, external monitoring of whole body or of specific organs and tissues) or indirect measurements (e.g. radioactivity in urine, faeces, breath or samples from the working environment) (ICRP Pub. 78, 1997 and NRPB-W60, 2004). Another method of internal dose assessment is based on the measurement of airborne radionuclides in the working areas of the facility and the worker's occupancy in those areas

Overview of the Facility Safeguardability Analysis (FSA) Process

Energy Technology Data Exchange (ETDEWEB)

Bari, Robert A.; Hockert, John; Wonder, Edward F.; Johnson, Scott J.; Wigeland, Roald; Zentner, Michael D.

2012-08-01

Executive Summary The safeguards system of the International Atomic Energy Agency (IAEA) is intended to provide the international community with credible assurance that a State is fulfilling its safeguards obligations. Effective and cost-efficient IAEA safeguards at the facility level are, and will remain, an important element of IAEA safeguards as those safeguards evolve towards a “State-Level approach.” The Safeguards by Design (SBD) concept can facilitate the implementation of these effective and cost-efficient facility-level safeguards (Bjornard, et al. 2009a, 2009b; IAEA, 1998; Wonder & Hockert, 2011). This report, sponsored by the National Nuclear Security Administration’s Office of Nuclear Safeguards and Security, introduces a methodology intended to ensure that the diverse approaches to Safeguards by Design can be effectively integrated and consistently used to cost effectively enhance the application of international safeguards.

Evaluation of environmental control technologies for commercial uranium nuclear fuel fabrication facilities

International Nuclear Information System (INIS)

Perkins, B.L.

1983-01-01

At present in the United States, there are seven commercial light-water reactor uranium fuel fabrication facilities. Effluent wastes from these facilities include uranium, nitrogen, fluorine, and organic-containing compounds. These effluents may be either discharged to the ambient environment, treated and recycled internally, stored or disposed of on-site, sent off-site for treatment and/or recovery, or sent off-site for disposal (including disposal in low-level waste burial sites). Quantities of waste generated and treatment techniques vary greatly depending on the facility and circuits used internally at the facility, though in general all the fluorine entering the facility as UF 6 is discharged as waste. Further studies to determine techniques and procedures that might minimize dose (ALARA) and to give data on possible long-term effects of effluent discharge and waste disposal are needed

Post-remedial-action survey report for Kinetic Experiment Water Boiler Reactor Facility, Santa Susana Field Laboratories, Rockwell International, Ventura County, California

International Nuclear Information System (INIS)

Wynveen, R.A.; Smith, W.H.; Sholeen, C.M.; Flynn, K.F.; Justus, A.L.

1981-10-01

Rockwell International's Santa Susana Laboratories in Ventura County, California, have been the site of numerous federally-funded contracted projects involving the use of radioactive materials. Among these was the Kinetics Experiment Water Boiler (KEWB) Reactor which was operated under the auspices of the US Atomic Energy Commission (AEC). The KEWB Reactor was last operated in 1966. The facility was subsequently declared excess and decontamination and decommissioning operations were conducted during the first half of calendar year 1975. The facility was completely dismantled and the site graded to blend with the surrounding terrain. During October 1981, a post-remedial-action (certification) survey of the KEWB site was conducted on the behalf of the US Department of Energy by the Radiological Survey Group (RSG) of the Occupational Health and Safety Division's Health Physics Section (OHS/HP) of Argonne National Laboratory (ANL). The survey confirmed that the site was free from contamination and could be released for unrestricted use

Managing Educational Facilities and Students' Enrolment in ...

African Journals Online (AJOL)

DR Nneka

Indexed African Journals Online: www.ajol.info. An International ... Key Words: Students Enrolment, Managing, Educational Facilities, Nigeria ... positive relationship with standard and quality of educational system (Nwagwu, 1978: Adesina ...

The development and operation of the international solar-terrestrial physics central data handling facility

Science.gov (United States)

Lehtonen, Kenneth

1994-01-01

The National Aeronautics and Space Administration (NASA) Goddard Space Flight Center (GSFC) International Solar-Terrestrial Physics (ISTP) Program is committed to the development of a comprehensive, multi-mission ground data system which will support a variety of national and international scientific missions in an effort to study the flow of energy from the sun through the Earth-space environment, known as the geospace. A major component of the ISTP ground data system is an ISTP-dedicated Central Data Handling Facility (CDHF). Acquisition, development, and operation of the ISTP CDHF were delegated by the ISTP Project Office within the Flight Projects Directorate to the Information Processing Division (IPD) within the Mission Operations and Data Systems Directorate (MO&DSD). The ISTP CDHF supports the receipt, storage, and electronic access of the full complement of ISTP Level-zero science data; serves as the linchpin for the centralized processing and long-term storage of all key parameters generated either by the ISTP CDHF itself or received from external, ISTP Program approved sources; and provides the required networking and 'science-friendly' interfaces for the ISTP investigators. Once connected to the ISTP CDHF, the online catalog of key parameters can be browsed from their remote processing facilities for the immediate electronic receipt of selected key parameters using the NASA Science Internet (NSI), managed by NASA's Ames Research Center. The purpose of this paper is twofold: (1) to describe how the ISTP CDHF was successfully implemented and operated to support initially the Japanese Geomagnetic Tail (GEOTAIL) mission and correlative science investigations, and (2) to describe how the ISTP CDHF has been enhanced to support ongoing as well as future ISTP missions. Emphasis will be placed on how various project management approaches were undertaken that proved to be highly effective in delivering an operational ISTP CDHF to the Project on schedule and

Several issues on the decommissioning of uranium mining/milling facilities

International Nuclear Information System (INIS)

Xu Lechang; Xu Jianxin; Gao Shangxiong

2007-01-01

Several issues on the decommissioning of uranium mining/milling facilities are discussed at the national and international level of decommissioning, including radiation, monitoring, dose evaluation, covering, water treatment and stabilization of uranium tailings impoundment, etc. Some suggestions are made: drawing international lessons on decommissioning of uranium mining/milling facilities; enhancing monitoring and database construction in decommissioning management; stressing utilization of measured dose data; using the experience of other countries for reference on covering designs for uranium tailings impoundment and water treatment; strengthening decommissioning management, etc. (authors)

Carbon Fiber Manufacturing Facility Siting and Policy Considerations: International Comparison

Energy Technology Data Exchange (ETDEWEB)

Cook, Jeffrey J. [National Renewable Energy Lab. (NREL), Golden, CO (United States); Booth, Samuel [National Renewable Energy Lab. (NREL), Golden, CO (United States)

2017-06-21

Carbon fiber is increasingly used in a wide variety of applications due largely to its superior material properties such as high strength-to-weight ratio. The current global carbon fiber manufacturing industry is predominately located in China, Europe, Japan, and the United States. The carbon fiber market is expected to expand significantly through 2024 and to require additional manufacturing capacity to meet demand. Carbon fiber manufacturing facilities can offer significant economic development and employment opportunities as exemplified by the $1 billion investment and 500 jobs expected at a new Toray plant in Moore, South Carolina. Though the market is expected to expand, it is unclear where new manufacturing facilities will locate to meet demand. This uncertainty stems from the lack of research evaluating how different nations with significant carbon fiber manufacturing capacity compare as it relates to certain manufacturing facility siting factors such as costs of labor and energy as well as policy directed at supporting carbon fiber development, domestic deployment, and exports. This report fills these gaps by evaluating the top carbon fiber manufacturing countries, including China, European Union countries, Japan, Mexico, South Korea, Taiwan, and the United States. The report documents how the United States compares to these countries based on a range of manufacturing siting considerations and existing policies related to carbon fiber. It concludes with a discussion of various policy options the United States could adopt to both (1) increase the competitiveness of the United States as it relates to attracting new carbon fiber manufacturing and (2) foster broader end-use markets for deployment.

Dismantling of nuclear facilities

International Nuclear Information System (INIS)

Tallec, M.; Kus, J.P.

2009-01-01

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

Safeguardability of a commercial-scaled ACP facility

Energy Technology Data Exchange (ETDEWEB)

Ko, Won Il; Lee, S. Y.; Kim, H. D.; Ha, J. H.; Song, D. Y.; Lee, T. H

2004-07-01

The Advanced spent fuel Conditioning Process (ACP) is an electro-metallurgical treatment technique to convert oxide-type spent nuclear fuel into a metallic form. This report documents a preliminary study on the safeguardability of ACP. The sub-processes and material flow of the pilot scale ACP facility were designed for this study. Then, their Material Balance Areas (MBA) and Key Measurement Point (KMP) were defined based on diversion scenario analysis. Finally, the limit of error in the MUF value was estimated using international target values for the uncertainty of measurement methods. Based on the results of preliminary study, we concluded that the safeguards goals of International Atomic Energy Agency (IAEA) could be met if the assumptions regarding measurement instruments can be achieved in a safeguards system for the ACP facility.

Safeguardability of a commercial-scaled ACP facility

International Nuclear Information System (INIS)

Ko, Won Il; Lee, S. Y.; Kim, H. D.; Ha, J. H.; Song, D. Y.; Lee, T. H.

2004-07-01

The Advanced spent fuel Conditioning Process (ACP) is an electro-metallurgical treatment technique to convert oxide-type spent nuclear fuel into a metallic form. This report documents a preliminary study on the safeguardability of ACP. The sub-processes and material flow of the pilot scale ACP facility were designed for this study. Then, their Material Balance Areas (MBA) and Key Measurement Point (KMP) were defined based on diversion scenario analysis. Finally, the limit of error in the MUF value was estimated using international target values for the uncertainty of measurement methods. Based on the results of preliminary study, we concluded that the safeguards goals of International Atomic Energy Agency (IAEA) could be met if the assumptions regarding measurement instruments can be achieved in a safeguards system for the ACP facility

Proposal on application of Russian technical facilities for International Mars Research Program for 2009 2015

Science.gov (United States)

Polishchuk, Georgy; Pichkhadze, Konstantin; Vorontsov, Victor; Pavel, Kazmerchuk

2006-07-01

Recently International Mars Research Program is widely discussed. Well-known initiative of President of the USA, recent progress of American and European scientists and engineers in implementation of “Mars Odyssey” and “Mars-Express” projects and Russian proposals on cooperation and participation in “Phobos Sample Return” mission declare every intention to join efforts in the ambitious Martian Program realization. The final goal of the program for nearly 15 20 years is landing of a man on the Martian surface. Before this event happens another critical stage will be Martian soil sample return. Within the next 10 years, apparently, a major task will be scale research by means of various types of technical facilities. A crucial issue for this research will be creation of research station network which would allow collecting information about planetary conditions at far-remote points. By this time within the frame of “Phobos Sample Return Program” to be launched in 2009 it is planned to deliver some meteorological mini-landers developed by the Russian and Finnish specialists on the Martian surface. From this point view it is also interesting to use balloons capable to cover considerable distance. Such proposals have been made by Russian side for “Scout” mission. European “Aurora” program also anticipates application of wide range of technical means to explore the Martian atmosphere and surface including inflatable devices. Thus, for the International Mars Exploration Program, it seems to be very prospective to use apart from launch vehicles, upper stages etc. such technical means as mini-stations, Mars rovers, penetrators, balloons, etc.

Physics at a future Neutrino Factory and super-beam facility

International Nuclear Information System (INIS)

Bandyopadhyay, A; Choubey, S; Gandhi, R; Goswami, S; Roberts, B L; Bouchez, J; Antoniadis, I; Ellis, J; Giudice, G F; Schwetz, T; Umasankar, S; Karagiorgi, G; Aguilar-Arevalo, A; Conrad, J M; Shaevitz, M H; Pascoli, S; Geer, S; Campagne, J E; Rolinec, M; Blondel, A

2009-01-01

The conclusions of the Physics Working Group of the International Scoping Study of a future Neutrino Factory and super-beam facility (the ISS) are presented. The ISS was carried out by the international community between NuFact05, (the 7th International Workshop on Neutrino Factories and Super-beams, Laboratori Nazionali di Frascati, Rome, 21-26 June 2005) and NuFact06 (Ivine, CA, 24-30 August 2006). The physics case for an extensive experimental programme to understand the properties of the neutrino is presented and the role of high-precision measurements of neutrino oscillations within this programme is discussed in detail. The performance of second-generation super-beam experiments, beta-beam facilities and the Neutrino Factory are evaluated and a quantitative comparison of the discovery potential of the three classes of facility is presented. High-precision studies of the properties of the muon are complementary to the study of neutrino oscillations. The Neutrino Factory has the potential to provide extremely intense muon beams and the physics potential of such beams is discussed in the final section of the report.

Overview of the Long-Baseline Neutrino Facility cryogenic system

CERN Document Server

Montanari, David; Bremer, Johan; Delaney, Michael; Aurelien, Diaz; Doubnik, Roza; Haaf, Kevin; Hentschel, Steve; Norris, Barry; Voirin, Erik

2017-01-01

The Deep Underground Neutrino Experiment (DUNE) collaboration is developing a multi-kiloton Long-Baseline neutrino experiment that will be located one mile underground at the Sanford Underground Research Facility (SURF) in Lead, SD. In the present design, detectors will be located inside four cryostats filled with a total of 68,400 ton of ultrapure liquid argon, at the level of impurities lower than 100 parts per trillion of oxygen equivalent contamination. The Long-Baseline Neutrino Facility (LBNF) is developing the conventional facilities and cryogenics infrastructure supporting this experiment. The cryogenics system is composed of several sub-systems: External/Infrastructure, Proximity, and Internal cryogenics. It will be engineered, manufactured, commissioned, and qualified by an international engineering team. This contribution highlights the main features of the LBNF cryogenic system. It presents its performance, functional requirements and modes of operations. It also details the status of the design, ...

Multi-Canister overpack internal HEPA filters

International Nuclear Information System (INIS)

SMITH, K.E.

1998-01-01

The rationale for locating a filter assembly inside each Multi-Canister Overpack (MCO) rather than include the filter in the Cold Vacuum Drying (CVD) process piping system was to eliminate the potential for contamination to the operators, processing equipment, and the MCO. The internal HEPA filters provide essential protection to facility workers from alpha contamination, both external skin contamination and potential internal depositions. Filters installed in the CVD process piping cannot mitigate potential contamination when breaking the process piping connections. Experience with K-Basin material has shown that even an extremely small release can result in personnel contamination and costly schedule disruptions to perform equipment and facility decontamination. Incorporating the filter function internal to the MCO rather than external is consistent with ALARA requirements of 10 CFR 835. Based on the above, the SNF Project position is to retain the internal HEPA filters in the MCO design

The international legal position on transboundary shipments of radioactive waste

International Nuclear Information System (INIS)

Grimston, M.C.

1997-01-01

The recent decision not to grant planning permission for construction of a Rock Characterisation Facility near Sellafield has reopened the question of long-term radioactive waste disposal policy in the UK. One possible solution would be the construction and operation of a small number of international radioactive waste disposal facilities, taking waste from several countries. Such an approach would allow pooling of international expertise; would allow the choice of excellent sites from geological and demographical standpoints; and may be economically attractive depending on economies of scale. However, the approach would also increase the amount of waste transport, and may reduce the pressure on producers to reduce the volumes of waste arising. This paper traces the development of international legal attitudes to transboundary transport of radioactive and other hazardous waste. It concludes that as international law now stands it would be very difficult to establish a network of international waste disposal facilities, and therefore strategies which are developed will be nationally based. (Author)

Performance Evaluation of the International Space Station Flow Boiling and Condensation Experiment (FBCE) Test Facility

Science.gov (United States)

Hasan, Mohammad; Balasubramaniam, R.; Nahra, Henry; Mackey, Jeff; Hall, Nancy; Frankenfield, Bruce; Harpster, George; May, Rochelle; Mudawar, Issam; Kharangate, Chirag R.;

Facility Configuration Study of the High Temperature Gas-Cooled Reactor Component Test Facility

Energy Technology Data Exchange (ETDEWEB)

S. L. Austad; L. E. Guillen; D. S. Ferguson; B. L. Blakely; D. M. Pace; D. Lopez; J. D. Zolynski; B. L. Cowley; V. J. Balls; E.A. Harvego, P.E.; C.W. McKnight, P.E.; R.S. Stewart; B.D. Christensen

2008-04-01

A test facility, referred to as the High Temperature Gas-Cooled Reactor Component Test Facility or CTF, will be sited at Idaho National Laboratory for the purposes of supporting development of high temperature gas thermal-hydraulic technologies (helium, helium-Nitrogen, CO2, etc.) as applied in heat transport and heat transfer applications in High Temperature Gas-Cooled Reactors. Such applications include, but are not limited to: primary coolant; secondary coolant; intermediate, secondary, and tertiary heat transfer; and demonstration of processes requiring high temperatures such as hydrogen production. The facility will initially support completion of the Next Generation Nuclear Plant. It will secondarily be open for use by the full range of suppliers, end-users, facilitators, government laboratories, and others in the domestic and international community supporting the development and application of High Temperature Gas-Cooled Reactor technology. This pre-conceptual facility configuration study, which forms the basis for a cost estimate to support CTF scoping and planning, accomplishes the following objectives: • Identifies pre-conceptual design requirements • Develops test loop equipment schematics and layout • Identifies space allocations for each of the facility functions, as required • Develops a pre-conceptual site layout including transportation, parking and support structures, and railway systems • Identifies pre-conceptual utility and support system needs • Establishes pre-conceptual electrical one-line drawings and schedule for development of power needs.

Facility Configuration Study of the High Temperature Gas-Cooled Reactor Component Test Facility

International Nuclear Information System (INIS)

S. L. Austad; L. E. Guillen; D. S. Ferguson; B. L. Blakely; D. M. Pace; D. Lopez; J. D. Zolynski; B. L. Cowley; V. J. Balls; E.A. Harvego, P.E.; C.W. McKnight, P.E.; R.S. Stewart; B.D. Christensen

2008-01-01

A test facility, referred to as the High Temperature Gas-Cooled Reactor Component Test Facility or CTF, will be sited at Idaho National Laboratory for the purposes of supporting development of high temperature gas thermal-hydraulic technologies (helium, helium-Nitrogen, CO2, etc.) as applied in heat transport and heat transfer applications in High Temperature Gas-Cooled Reactors. Such applications include, but are not limited to: primary coolant; secondary coolant; intermediate, secondary, and tertiary heat transfer; and demonstration of processes requiring high temperatures such as hydrogen production. The facility will initially support completion of the Next Generation Nuclear Plant. It will secondarily be open for use by the full range of suppliers, end-users, facilitators, government laboratories, and others in the domestic and international community supporting the development and application of High Temperature Gas-Cooled Reactor technology. This pre-conceptual facility configuration study, which forms the basis for a cost estimate to support CTF scoping and planning, accomplishes the following objectives: (1) Identifies pre-conceptual design requirements; (2) Develops test loop equipment schematics and layout; (3) Identifies space allocations for each of the facility functions, as required; (4) Develops a pre-conceptual site layout including transportation, parking and support structures, and railway systems; (5) Identifies pre-conceptual utility and support system needs; and (6) Establishes pre-conceptual electrical one-line drawings and schedule for development of power needs

Proposal for Monitoring Within the Centrifuge Cascades of Uranium Enrichment Facilities

Energy Technology Data Exchange (ETDEWEB)

Farrar, David R.

2017-04-01

Safeguards are technical measures implemented by the International Atomic Energy Agency (IAEA) to independently verify that nuclear material is not diverted from peaceful purposes to weapons (IAEA, 2017a). Safeguards implemented at uranium enrichment facilities (facilities hereafter) include enrichment monitors (IAEA, 2011). Figure 1 shows a diagram of how a facility could be monitored. The use of a system for monitoring within centrifuge cascades is proposed.

Safety design of the international fusion materials irradiation facility (IFMIF)

International Nuclear Information System (INIS)

Konishi, Satoshi; Yamaki, Daiju; Katsuta, Hiroji; Moeslang, Anton; Jameson, R.A.; Martone, Marcello; Shannon, T.E.

1997-11-01

In the Conceptual Design Activity of the IFMIF, major subsystems, as well as the entire facility is carefully designed to satisfy the safety requirements for any possible construction sites. Each subsystem is qualitatively analyzed to identify possible hazards to the workers, public and environments using Failure Mode and Effect Analysis (FMEA). The results are reflected in the design and operation procedure. Shielding of radiation, particularly neutron around the test cell is one of the most important issue in normal operation. Radiation due to beam halo and activation is a hazard for operation personnel in the accelerator system. For the maintenance, remote handling technology is designed to be applied in various facilities of the IFMIF. Lithium loop and target system hold the majority of the radioactive material in the facility. Tritium and beryllium-7 are generated by the nuclear reaction during operation and thus needed to be removed continuously. They are also the potential hazards of airborne source in off-normal events. Minimization of inventory, separation and immobilization, and multiple confinement are considered in the design. Generation of radioactive waste is anticipated to be minor, but waste treatment systems for gas, liquid and solid wastes are designed to minimize the environmental impact. Lithium leak followed by a fire is a major concern, and extensive prevention plan is made in the target design. One of the design option considered is composed of; primary enclosure of the lithium loop, secondary containment filled with positive pressure argon, and an air tight lithium cell made of concrete with a steel lining. This study will report some technical issues considered in the design of IFMIF. It was concluded that the IFMIF can be designed and constructed to meet or exceed current safely standards for workers, public and the environment with existing technology and reasonable construction cost. (J.P.N.)

Addressing Obstetrical Challenges at 12 Rural Ugandan Health Facilities: Findings from an International Ultrasound and Skills Development Training for Midwives in Uganda.

Science.gov (United States)

Kinnevey, Christina; Kawooya, Michael; Tumwesigye, Tonny; Douglas, David; Sams, Sarah

2016-01-01

Like much of Sub-Saharan Africa, Uganda is facing significant maternal and fetal health challenges. Despite the fact that the majority of the Uganda population is rural and the major obstetrical care provider is the midwife, there is a lack of data in the literature regarding rural health facilities' and midwives' knowledge of ultrasound technology and perspectives on important maternal health issues such as deficiencies in prenatal services. A survey of the current antenatal diagnostic and management capabilities of midwives at 12 rural Ugandan health facilities was performed as part of an international program initiated to provide ultrasound machines and formal training in their use to midwives at antenatal care clinics. The survey revealed that the majority of pregnant women attend less than the recommended minimum of four antenatal care visits. There were significant knowledge deficits in many prenatal conditions that require ultrasound for early diagnosis, such as placenta previa and macrosomia. The cost of providing ultrasound machines and formal training to 12 midwives was $6,888 per powered rural health facility and $8,288 for non-powered rural health facilities in which solar power was required to maintain ultrasound. In order to more successfully meet Millennium Development Goal 4 (reduce child mortality), 5 (improve maternal health) and 6 (combat HIV) through decreasing maternal to child transmission of HIV, the primary healthcare provider, which is the midwife in Uganda, must be competent at the diagnosis and management of a wide spectrum of obstetrical challenges. A trained ultrasound-based approach to obstetrical care is a cost effective method to take on these goals.

Agreement between the Government of India and the International Atomic Energy Agency for the application of safeguards to civilian nuclear facilities

International Nuclear Information System (INIS)

2009-01-01

The text of the Agreement between the Government of India and the International Atomic Energy Agency for the Application of Safeguards to Civilian Nuclear Facilities is reproduced in this document for the information of all Members of the Agency. The Board of Governors approved the Agreement on 1 August 2008. It was signed in Vienna on 2 February 2009. Pursuant to paragraph 108 of the Agreement, the Agreement entered into force on 11 May 2009, the date on which the Agency received from India written notification that India's statutory and constitutional requirements for entry into force had been met

Needs of Advanced Safeguards Technologies for Future Nuclear Fuel Cycle (FNFC) Facilities and a Trial Application of SBD Concept to Facility Design of a Hypothetical FNFC Facility

International Nuclear Information System (INIS)

Seya, M.; Hajima, R.; Nishimori, N.; Hayakawa, T.; Kikuzawa, N.; Shizuma, T.; Fujiwara, M.

2010-01-01

Some of future nuclear fuel cycle (FNFC) facilities are supposed to have the characteristic features of very large throughput of plutonium, low decontamination reprocessing (no purification process; existence of certain amount of fission products (FP) in all process material), full minor actinides (MA) recycle, and treatment of MOX with FP and MA in fuel fabrication. In addition, the following international safeguards requirements have to be taken into account for safeguards approaches of the FNFC facilities. -Application of integrated safeguards (IS) approach; -Remote (unattended) verification; - 'Safeguards by Design' (SBD) concept. These features and requirements compel us to develop advanced technologies, which are not emerged yet. In order to realize the SBD, facility designers have to know important parts of design information on advanced safeguards systems before starting the facility design. The SBD concept requires not only early start of R and D of advanced safeguards technologies (before starting preliminary design of the facility) but also interaction steps between researchers working on safeguards systems and nuclear facility designers. The interaction steps are follows. Step-1; researchers show images of advanced safeguards systems to facility designers based on their research. Step-2; facility designers take important design information on safeguards systems into process systems of demonstration (or test) facility. Step-3; demonstration and improvement of both systems based on the conceptual design. Step-4; Construction of a FNFC facility with the advanced safeguards systems We present a trial application of the SBD concept to a hypothetical FNFC facility with an advanced hybrid K-edge densitometer and a Pu NDA system for spent nuclear fuel assembly using laser Compton scattering (LCS) X-rays and γ-rays and other advanced safeguards systems. (author)

Temporal Trends in Analgesic Use in Long-Term Care Facilities: A Systematic Review of International Prescribing.

Science.gov (United States)

La Frenais, Francesca L; Bedder, Rachel; Vickerstaff, Victoria; Stone, Patrick; Sampson, Elizabeth L

2018-02-01

To explore global changes in the prescription of analgesic drugs over time in the international long-term care (LTC) population. Systematic review. We included original research articles in English, published and unpublished, that included number of participants, country and year(s) of data collection, and prescription of analgesics (analgesics not otherwise specified, opioids, acetaminophen; scheduled only, or scheduled plus as needed (PRN)). LTC residents. We searched PubMed, EMBASE, CINAHL, International Pharmaceutical Abstracts, PsycINFO, Cochrane, Web of Science, Google Scholar, using keywords for LTC facilities and analgesic medication; hand-searched references of eligible papers; correspondence. Studies were quality rated using an adapted Newcastle-Ottawa scale. Pearson correlation coefficients were generated between percentage of residents prescribed an analgesic and year of data collection. If available, we investigated changes in acetaminophen and opioid prescriptions. Forty studies met inclusion criteria. A moderate correlation (0.59) suggested that scheduled prescription rates for analgesics have increased over time. Similar findings were reflected in scheduled prescriptions for acetaminophen and opioids. No increase was seen when analyzing scheduled plus PRN analgesics. Use of opioids (scheduled plus PRN) appears to have increased over time. Worldwide, use of opioids and acetaminophen has increased in LTC residents. Research is needed to explore whether this reflects appropriate pain management for LTC residents and if PRN medication is used effectively. © 2017 The Authors. Journal of the American Geriatrics Society published by Wiley Periodicals, Inc. on behalf of The American Geriatrics Society.

Profiles of facilities used for FBR research and testing

International Nuclear Information System (INIS)

1976-12-01

This document contains a concise up-to date of supporting ''Liquid Metal Fast Breeder'' facilities submitted by countries (Federal Republic of Germany, Italy, France, Belgium, Netherlands, UK, USA, USSR and Japan) and international organizations. It has the purpose of providing an over-view of the facilities currently used or under construction and of the type of experiments that can be conducted therein

Demonstration of safety of decommissioning of facilities using radioactive material

International Nuclear Information System (INIS)

Batandjieva, Borislava; O'Donnell, Patricio

2008-01-01

Full text:The development of nuclear industry worldwide in the recent years has particular impact on the approach of operators, regulators and interested parties to the implementation of the final phases (decommissioning) of all facilities that use radioactive material (from nuclear power plants, fuel fabrication facilities, research reactors to small research or medical laboratories). Decommissioning is becoming an increasingly important activity for two main reasons - termination of the practice in a safe manner with the view to use the facility or the site for other purposes, or termination of the practice and reuse the facility or site for new built nuclear facilities. The latter is of special relevance to multi-facility sites where for example new nuclear power plants and envisaged. However, limited countries have the adequate legal and regulatory framework, and experience necessary for decommissioning. In order to respond to this challenge of the nuclear industry and assist Member States in the adequate planning, conduct and termination of decommissioning of wide range of facilities, over the last decade the IAEA has implemented and initiated several projects in this field. One of the main focuses of this assistance to operators, regulators and specialists involved in decommissioning is the evaluation and demonstration of safety of decommissioning. This importance of these Agency activities was also highlighted in the International Action Plan on Decommissioning, during the second Joint Convention meeting in 2006 and the International Conference on Lessons Learned from Decommissioning in Athens in 2006. The IAEA has been providing technical support to its Member States in this field through several mechanisms: (1) the establishment of a framework of safety standards on decommissioning and development of a supporting technical documents; (2) the establishment of an international peer review mechanism for decommissioning; (3) the technical cooperation projects

Managers air thoughts on the top competitive issues

International Nuclear Information System (INIS)

Makansi, J.; Swanekamp, R.

1996-01-01

Over 100 powerplant managers and representatives from other industry segments exchanged ideas and opinions at Power magazine's Fifth Powerplant O and M Symposium, ''Managing the Powerplant in a Competitive Environment,'' held June 12--14 in Richmond, VA. Attendees may have represented both utility and independent power facilities, but it was clear from the dialogue that, regardless of ownership, most felt that their plants would have to operate as independent businesses, implicitly if not directly

Resource allocation planning with international components

Science.gov (United States)

Burke, Gene; Durham, Ralph; Leppla, Frank; Porter, David

1993-01-01

Dumas, Briggs, Reid and Smith (1989) describe the need for identifying mutually acceptable methodologies for developing standard agreements for the exchange of tracking time or facility use among international components. One possible starting point is the current process used at the Jet Propulsion Laboratory (JPL) in planning the use of tracking resources. While there is a significant promise of better resource utilization by international cooperative agreements, there is a serious challenge to provide convenient user participation given the separate project and network locations. Coordination among users and facility providers will require a more decentralized communication process and a wider variety of automated planning tools to help users find potential exchanges. This paper provides a framework in which international cooperation in the utilization of ground based space communication systems can be facilitated.

The Atmosphere-Space Interactions Monitor (ASIM) Payload Facility on the ISS

DEFF Research Database (Denmark)

Reibaldi, Giuseppe; Nasca, Rosario; Neubert, Torsten

ASIM is a payload facility to be mounted on a Columbus external platform on the International Space Station (ISS). ASIM will study the coupling of thunderstorm processes to the upper atmosphere, ionosphere and radiation belts. ASIM is the most complex Earth Observation payload facility planned fo...

Establishment of fecal bioassay facility at Kalpakkam

International Nuclear Information System (INIS)

Krishnan, H.; Yuvaraj, Ramani; Mohanty, B.N.; Sivasubramanian, K.; Venkatraman, B.

2016-01-01

In the event of an unusual occurrence, occupational radiation workers employed in fuel reprocessing/fuel fabrication facilities have potential risk of acquiring internal contamination, in spite of implementation of efficient engineering and administrative control measures. Quantification of internally deposited radionuclides is achieved either by (i) direct methods and/or (ii) indirect methods. In general, urinalysis is preferred for moderately absorbing (Type M-compounds of Americium) compounds, while analysis of fecal samples are preferred for slow absorption (Type S - Oxides of Plutonium) compounds. The predicted clearance of Type S and Type M compounds deposited in respiratory tract via fecal is about three to five orders higher than urinary excretion. In view of this, a facility for ashing fecal samples was established and standardization of radioanalytical procedure for quantification of Pu/Am using synthetic fecal (SF) samples was carried out

The Portuguese gamma irradiation facility

International Nuclear Information System (INIS)

Mendes, C.M.; Almeida, J.C.; Botelho, M.L.; Cavaco, M.C.; Almeida-Vara, E.; Andrade, M.E.

1990-01-01

A Gamma Radiation Facility was built up in the National Laboratory of Industrial Technology and Engineering (LNETI), Lisbon, Portugal. This plant (UTR GAMA-Pi) is a Cobalt-60 dry storage continuous facility with a nominal capacity of 1.5 x 10 16 Bq. The initial activity is 1.1 x 10 16 Bq and the throughput capacity 10 3 ton/year for product with a bulk density of 0.2 g/cm 3 treated with a minimum absorbed dose of 25 kGy. Complementary control devices were installed: ventilation system, closed water refrigeration circuit, internal TV system, detection and extinction fire system and emergency power group. It must be emphasized that the best attention was given to the conception and efficiency of the interlock safety systems. This facility will be utilized mainly for radiosterilization of medical articles and decontamination of wine cork stoppers. (author)

International nuclear power status 2002; International kernekraftstatus 2002

Energy Technology Data Exchange (ETDEWEB)

Lauritzen, B.; Majborn, B.; Nonboel, E.; Oelgaard, P.L. (eds.)

2003-03-01

This report is the ninth in a series of annual reports on the international development of nuclear power with special emphasis on reactor safety. For 2002, the report contains: 1) General trends in the development of nuclear power; 2) Decommissioning of the nuclear facilities at Risoe National Laboratory: 3) Statistical information on nuclear power production (in 2001); 4) An overview of safety-relevant incidents in 2002; 5) The development in West Europe; 6) The development in East Europe; 7) The development in the rest of the world; 8) Development of reactor types; 9) The nuclear fuel cycle; 10) International nuclear organisations. (au)

Plasma Facing Components Generic Facilities Review Panel (PFC-GFRP): Final report

International Nuclear Information System (INIS)

McGrath, R.; Allen, S.; Hill, D.; Brooks, J.; Mattas, R.; Davis, J.; Lipschultz, B.; Ulrickson, M.

1993-10-01

The Plasma Facing Components (PFC) Facilities Review Panel was chartered by the US Department of Energy, Office of Fusion Energy, ITER (International Thermonuclear Experimental Reactor) and Technology Division, to outline the program plan and identify the supporting test facilities that lead to reliable, long-lived plasma facing components for ITER. This report summarizes the panel's findings and identifies the necessary and sufficient set of test facilities required for ITER PFC development

The Low Temperature Microgravity Physics Facility Project

Science.gov (United States)

Chui, T.; Holmes, W.; Lai, A.; Croonquist, A.; Eraker, J.; Abbott, R.; Mills, G.; Mohl, J.; Craig, J.; Balachandra, B.;

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)

International physical protection standards: support for development and implementation

International Nuclear Information System (INIS)

Soo Hoo, M.S.

2002-01-01

Full text: Since 1972, the IAEA has been a recognized organization in promoting the development of international standards on the physical protection of nuclear materials. This responsibility has continued through the present in the 1999 publication of the fourth revision of INFCIRC/225, the physical protection of nuclear material and nuclear facilities and in being the repository for the convention on the physical protection of nuclear material which was originally published in 1980 as INFCIRC/274. The IAEA has also published other reference documents in support these two standards. With changing world events and greater concern for the physical protection of nuclear materials and facilities, IAEA member states have increased IAEA physical protection responsibilities. Currently, the IAEA is serving as the secretariat for drafting revisions to the physical protection convention. The proposed revisions will strengthen international physical protection standards through the incorporation of physical protection fundamentals that should apply to all nuclear materials in international or domestic use, storage and transport. Furthermore, the physical protection fundamentals would also extend to include nuclear facilities. Presently, the physical protection convention applies only to nuclear materials that are in international transport. To complement efforts to develop and promote international physical protection standards, the IAEA is actively involved in assisting member states with the implementation of the standards. This is accomplished through the delivery of training courses, workshops and hosting other international forums for the exchange of information. Through review services such as the international physical protection advisory service (IPPAS), the IAEA provides advice to member states on the application of international standards at national and facility-specific levels. These services can be followed up with technical support to implement the

PANDA: A Multipurpose Integral Test Facility for LWR Safety Investigations

International Nuclear Information System (INIS)

Paladino, D.; Dreier, J.

2012-01-01

The PANDA facility is a large scale, multicompartmental thermal hydraulic facility suited for investigations related to the safety of current and advanced LWRs. The facility is multipurpose, and the applications cover integral containment response tests, component tests, primary system tests, and separate effect tests. Experimental investigations carried on in the PANDA facility have been embedded in international projects, most of which under the auspices of the EU and OECD and with the support of a large number of organizations (regulatory bodies, technical dupport organizations, national laboratories, electric utilities, industries) worldwide. The paper provides an overview of the research programs performed in the PANDA facility in relation to BWR containment systems and those planned for PWR containment systems.

Post remedial action survey report for Building 003, Santa Susana Field Laboratories, Rockwell International, Ventura County, California, October 1981; April 1982. Surplus Facilities Management Program

International Nuclear Information System (INIS)

Wynveen, R.A.; Smith, W.H.; Sholeen, C.M.; Justus, A.L.; Flynn, K.F.

1983-10-01

Rockwell International's Santa Susana Laboratories in Ventura County, California, have been the site of numerous Federally-funded projects involving the use of radioactive materials. One such project was the System for Nuclear Auxiliary Power (SNAP) Program. Building 003 on the Santa Susana site was used in conjunction with the SNAP Program and contained a highly shielded area designed for remote manipulation of radioactive materials. Such facilities are commonly referred to as hot caves. During the SNAP Program, fuel burnup samples were analyzed and irradiation experiments were evaluated in the Building 003 hot cave. Use of the hot cave facility ended when the SNAP Program was terminated in 1973. Subsequently, the Building 003 facilities were declared excess and were decontaminaed and decommissioned during the first half of calendar year 1975. At that time, the building was given a preliminary release. In 1981, a post-remedial-action (certification) survey of Building 003 was conducted at the request of the Department of Energy. Significant levels of residual contamination were found in various parts of the building. Consequently, additional decontamination was conducted by Rockwell International. A final post-remedial-action survey was conducted during April 1982, and those areas in Building 003 that had been found contaminated in 1981 were now found to be free of detectable radioactive contamination. Sludge samples taken from the sewer sump showed elevated levels of enriched uranium contaminant. Hence, all sewer lines within Building 003 were removed. This permitted unconditional release of the building for unrestricted use. However, the sewer lines exterior to the building, which remain in place, must be considered potentially contaminated and, therefore, subject to restricted use

Directory of transport packaging test facilities

International Nuclear Information System (INIS)

1983-08-01

Radioactive materials are transported in packagings or containers which have to withstand certain tests depending on whether they are Type A or Type B packagings. In answer to a request by the International Atomic Energy Agency, 13 Member States have provided information on the test facilities and services existing in their country which can be made available for use by other states by arrangement for testing different kinds of packagings. The directory gives the technical information on the facilities, the services, the tests that can be done and in some cases even the financial arrangement is included

Visitor centres at nuclear facility sites

International Nuclear Information System (INIS)

1993-01-01

Communications strategies in the nuclear field are often based on the creation of visitor centres at nuclear facility sites. Today, the design, as well as the realization and management of such centres has become a specialized function, and its role is very complementary to the nuclear operator's. It also uses the latest technology in the field of audio-visual, experiment and interactivity. This publication contains the proceedings of an international seminar organized by the OECD Nuclear Energy Agency on the role of visitor centres at nuclear facility sites. It includes the main papers presented at this Seminar

Relocation consequences on an ophthalmology consultation service from an inpatient to outpatient facility

Directory of Open Access Journals (Sweden)

Singh JS

2015-10-01

Full Text Available Jorawer S Singh,1 Vincent M Imbrogno,2 Mary K Howard,3 Amandip S Cheema,3 Ausra D Selvadurai,4 Surbhi Bansal5 1Department of Ophthalmology, George Washington University, Washington, DC, 2Contemporary Ophthalmology of Erie, Erie, PA, 3Department of Ophthalmology, University at Buffalo, Buffalo, NY, 4OcuSight Eye Care Center, Rochester, NY, 5Department of Ophthalmology, Virginia Commonwealth University, Richmond, VA, USA Importance: This study shows that relocation of an academic ophthalmology residency program from an inpatient to an outpatient setting in western New York does not affect the consult volume but affects management patterns and follow-up rates.Objective: To investigate the effects on the ophthalmology consultation service of an academic program with relocation from a Regional Level-1 Trauma center to an outpatient facility.Design: Consultation notes from 3 years before and 3 years after the University at Buffalo’s (UB Department of Ophthalmology relocation from a Regional Level-1 Trauma center (Erie County Medical Center to an outpatient facility (Ross Eye Institute were obtained from hospital electronic medical records and analyzed.Setting: Hospitalized care and institutional practice.Participants: All inpatient or Emergency Room Ophthalmology consultation patients from the Department of Ophthalmology at UB from 2004 to 2010 (1,379 patients.Exposures: None, this was a retrospective chart review.Main outcome measures: Patient demographics, reason for consult, diagnoses, and ophthalmic procedures performed by the UB Department of Ophthalmology before and after its relocation.Results: Relocation to the outpatient facility did not affect consult volume (P=0.15. The number of consults focusing on ophthalmic conditions, as a percentage of the yearly total, rose 460% (P=0.0001, while systemic condition consults with ocular manifestations fell 83% (P=0.0001. Consults for ocular trauma decreased 65% (P=0.0034. Consults ending with a

A Worldwide Web-portal for Aquatic Mesocosm Facilities: WWW.MESOCOSM.EU

Science.gov (United States)

Berger, S. A.; Nejstgaard, J. C.

2016-02-01

Experimental mesocosms are valuable tools to fill the gap between highly controlled/replicated lab experiments and uncontrolled/non-replicated natural environments such as rivers, lakes and oceans. WWW.MESOCOSM.EU is an open web-portal for leading aquatic mesocosm facilities around the world. It was created within the FP7 EU-project MESOAQUA (A network of leading MESOcosm facilities to advance the studies of future AQUAtic ecosystems from the Arctic to the Mediterranean). The goal of the portal is to increase international knowledge about existing mesocosm facilities, including information on locations, environment, equipment, contacts, research opportunities and mesocosm-based publications. MESOCOSM.EU specifically aims to be a tool to enhance the quality of research by facilitating international cooperative network building, announcement of new research initiatives, transfer of best practice, and dissemination of knowledge, public information and press releases. As an open platform for all aquatic ecosystem scale science (marine and freshwater), MESOCOSM.EU aims to fill the lack of a centralized, coordinating virtual infrastructure for international aquatic mesocosm research, from the mountains to the ocean and from polar to tropical regions.

Report Of The Workshop On Nuclear Facility Design Information Examination And Verification For Safeguards

International Nuclear Information System (INIS)

Metcalf, Richard; Bean, Robert

2009-01-01

The International Atomic Energy Agency (IAEA) implements nuclear safeguards and verifies countries are compliant with their international nuclear safeguards agreements. One of the key provisions in the safeguards agreement is the requirement that the country provide nuclear facility design and operating information to the IAEA relevant to safeguarding the facility, and at a very early stage. , This provides the opportunity for the IAEA to verify the safeguards-relevant features of the facility and to periodically ensure that those features have not changed. The national authorities (State System of Accounting for and Control of Nuclear Material - SSAC) provide the design information for all facilities within a country to the IAEA. The design information is conveyed using the IAEA's Design Information Questionnaire (DIQ) and specifies: (1) Identification of the facility's general character, purpose, capacity, and location; (2) Description of the facility's layout and nuclear material form, location, and flow; (3) Description of the features relating to nuclear material accounting, containment, and surveillance; and (4) Description of existing and proposed procedures for nuclear material accounting and control, with identification of nuclear material balance areas. The DIQ is updated as required by written addendum. IAEA safeguards inspectors examine and verify this information in design information examination (DIE) and design information verification (DIV) activities to confirm that the facility has been constructed or is being operated as declared by the facility operator and national authorities, and to develop a suitable safeguards approach. Under the Next Generation Safeguards Initiative (NGSI), the National Nuclear Security Administrations (NNSA) Office of Non-Proliferation and International Security identified the need for more effective and efficient verification of design information by the IAEA for improving international safeguards in the future

International activities of the GRS

International Nuclear Information System (INIS)

Antoni, R.; Hachenberg, G.; Schally, P.

1990-01-01

The individual activities fall into three main subject areas, each with differing objectives and functions: Cooperation in multilateral and bilateral bodies and organizations, cooperation in international research projects, performance of safety analyses. In addition to describing the international activities of GRS, the paper also shows how complexly interwoven the safety of nuclear facilities is at the international level, and how varied initiatives are required in order to ensure effective cooperation in the various fields. (orig.) [de

Opportunities for Process Monitoring Techniques at Delayed Access Facilities

Energy Technology Data Exchange (ETDEWEB)

Curtis, Michael M.; Gitau, Ernest TN; Johnson, Shirley J.; Schanfein, Mark; Toomey, Christopher

2013-09-20

Except for specific cases where the International Atomic Energy Agency (IAEA) maintains a continuous presence at a facility (such as the Japanese Rokkasho Reprocessing Plant), there is always a period of time or delay between the moment a State is notified or aware of an upcoming inspection, and the time the inspector actually enters the material balance area or facility. Termed by the authors as “delayed access,” this period of time between inspection notice and inspector entrance to a facility poses a concern. Delayed access also has the potential to reduce the effectiveness of measures applied as part of the Safeguards Approach for a facility (such as short-notice inspections). This report investigates the feasibility of using process monitoring to address safeguards challenges posed by delayed access at a subset of facility types.

International nuclear cycle fact book: Revision 9

International Nuclear Information System (INIS)

Leigh, I.W.

1989-01-01

The International Nuclear Fuel Cycle Fact Book has been compiled in an effort to provide current data concerning fuel cycle and waste management facilities, R and D programs and key personnel. The Fact Book contains: national summaries in which a section for each country which summarizes nuclear policy, describes organizational relationships and provides addresses, names of key personnel, and facilities information; and international agencies in which a section for each of the international agencies which has significant fuel cycle involvement, and a listing of nuclear societies. The national summaries, in addition to the data described above, feature a small map for each country as well as some general information. The latter is presented from the perspective of the Fact Book user in the United States

12 CFR 204.122 - Secondary market activities of international banking facilities.

Science.gov (United States)

2010-01-01

... banking facilities. 204.122 Section 204.122 Banks and Banking FEDERAL RESERVE SYSTEM BOARD OF GOVERNORS OF THE FEDERAL RESERVE SYSTEM RESERVE REQUIREMENTS OF DEPOSITORY INSTITUTIONS (REGULATION D... the institution establishing the IBF would continue to be subject to Eurocurrency reserve requirements...

Reduced cost design of liquid lithium target for international fusion material irradiation facility (IFMIF)

International Nuclear Information System (INIS)

Nakamura, Hiroo; Ida, Mizuho; Sugimoto, Masayoshi; Takeuchi, Hiroshi; Yutani, Toshiaki

2001-01-01

The International Fusion Materials Irradiation Facility (IFMIF) is being jointly planned to provide an accelerator-based D-Li neutron source to produce intense high energy neutrons (2 MW/m 2 ) up to 200 dpa and a sufficient irradiation volume (500 cm 3 ) for testing the candidate materials and components up to about a full lifetime of their anticipated use in ITER and DEMO. To realize such a condition, 40 MeV deuteron beam with a current of 250 mA is injected into high speed liquid lithium flow with a speed of 20 m/s. Following Conceptual Design Activity (1995-1998), a design study with focus on cost reduction without changing its original mission has been done in 1999. The following major changes to the CAD target design have been considered in the study and included in the new design: i) number of the Li target has been changed from 2 to 1, ii) spare of impurity traps of the Li loop was removed although the spare will be stored in a laboratory for quick exchange, iii) building volume was reduced via design changes in lithium loop length. This paper describes the reduced cost design of the lithium target system and recent status of Key Element Technology activities. (author)

Outline of electric power facility plan in fiscal year 1988

International Nuclear Information System (INIS)

1988-01-01

As to the electric power facility plan in fiscal year 1988, 15 designated electric power enterprises made the notification to the Minister of International Trade and Industry in March, 1988. This outline of the facility plan summarized the plans of 66 enterprises in total, including the plans of municipally operated, joint thermal power and other enterprises in addition to the above 15. In order to ensure the stable supply of electric power, the Ministry of International Trade and Industry considers that it is indispensable to purposefully develop electric power sources and the facilities for distribution along this facility plan. The forecast for fiscal year 1997 is : total electric power demand 778.2 billion kWh, maximum power demand 151.21 million kW, and yearly load factor 56.9 %. This is equivalent to the yearly growth of 2.4 %. In fiscal year 1988, it is planned to present 29 plants of 2760 MW to the Power Source Development Coordination Council. The breakdown is : hydroelectricity 140 MW, thermal power 2010 MW, and nuclear power 610 MW. The Ministry guides electric power enterprises so as to realize the diversification of electric power sources. Also the increase of transmission and transformation facilities, the plan of equipment investment and others are reported. (Kako, I.)

Facilities management innovation in public-private collaborations: Danish ESCO projects

DEFF Research Database (Denmark)

Nardelli, Giulia; Jensen, Jesper Ole; Nielsen, Susanne Balslev

2015-01-01

The purpose of the article is to investigate how Facilities Management (FM) units navigate Energy Service Company (ESCO) collaborations, here defined as examples of public collaborative innovation within the context of FM. The driving motivation is to inform and inspire internal FM units of local...... institutions on how to navigate and manage collaboration of different, intra- and inter-organisational actors throughout ESCO projects.......The purpose of the article is to investigate how Facilities Management (FM) units navigate Energy Service Company (ESCO) collaborations, here defined as examples of public collaborative innovation within the context of FM. The driving motivation is to inform and inspire internal FM units of local...

Nuclear Data Center International Standard Towards TSO Initiative

International Nuclear Information System (INIS)

Raja Murzaferi Raja Moktar; Mohd Fauzi Haris; Siti Nurbahyah Hamdan

2011-01-01

Nuclear Data Center is the main facility for Nuclear Malaysia Agency IT infrastructure comprising of main critical servers, research and operational data storage, HPC-clusters system and vital network core equipment. In recent years, international body such as TIA-Telecommunication Industry Association and Up time Institute have came out with proper international data center standards in order to ensure data center operation on achieving maximum operational up time and minimal downtime. The standard are currently being rated as tier level ranging from Data Center tier I up to tier IV, differentiate by facility standard and up time/ downtime percentage ratio. This paper will discuss Nuclear Data Center adopting international standards in supporting Nuclear Malaysia TSO initiative thus ensuring the critical core component of agency IT services availability and further more International standard recognitions. (author)

Nondestructive assay of special nuclear material for uranium fuel-fabrication facilities

International Nuclear Information System (INIS)

Smith, H.A. Jr.; Schillebeeckx, P.

1997-01-01

A high-quality materials accounting system and effective international inspections in uranium fuel-fabrication facilities depend heavily upon accurate nondestructive assay measurements of the facility's nuclear materials. While item accounting can monitor a large portion of the facility inventory (fuel rods, assemblies, storage items), the contents of all such items and mass values for all bulk materials must be based on quantitative measurements. Weight measurements, combined with destructive analysis of process samples, can provide highly accurate quantitative information on well-characterized and uniform product materials. However, to cover the full range of process materials and to provide timely accountancy data on hard-to-measure items and rapid verification of previous measurements, radiation-based nondestructive assay (NDA) techniques play an important role. NDA for uranium fuel fabrication facilities relies on passive gamma spectroscopy for enrichment and U isotope mass values of medium-to-low-density samples and holdup deposits; it relies on active neutron techniques for U-235 mass values of high-density and heterogeneous samples. This paper will describe the basic radiation-based nondestructive assay techniques used to perform these measurements. The authors will also discuss the NDA measurement applications for international inspections of European fuel-fabrication facilities

Metering management at the plutonium research and development facilities

International Nuclear Information System (INIS)

Hirata, Masaru; Miyamoto, Fujio; Kurosawa, Makoto; Abe, Jiro; Sakai, Haruyuki; Suzuki, Tsuneo.

1996-01-01

Nuclear fuel research laboratory of the Oarai Research Laboratory of the Japan Atomic Energy Research Institute is an R and D facility to treat with plutonium and processes various and versatile type samples in chemical and physical form for use of various experimental researches even though on much small amount. Furthermore, wasted and plutonium samples are often transported to other KMP and MBA such as radioactive waste management facility, nuclear reactor facility and so forth. As this facility is a place to treat plutonium important on the safeguards, it is a facility necessary for detection and allowance actions and for detail managements on the metering management data to report to government and IAEA in each small amount sample and different configuration. In this paper, metering management of internationally regulated matters and metering management system using a work station newly produced in such small scale facility were introduced. (G.K.)

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.

Microscope-Based Fluid Physics Experiments in the Fluids and Combustion Facility on ISS

Science.gov (United States)

Doherty, Michael P.; Motil, Susan M.; Snead, John H.; Malarik, Diane C.

2000-01-01

At the NASA Glenn Research Center, the Microgravity Science Program is planning to conduct a large number of experiments on the International Space Station in both the Fluid Physics and Combustion Science disciplines, and is developing flight experiment hardware for use within the International Space Station's Fluids and Combustion Facility. Four fluids physics experiments that require an optical microscope will be sequentially conducted within a subrack payload to the Fluids Integrated Rack of the Fluids and Combustion Facility called the Light Microscopy Module, which will provide the containment, changeout, and diagnostic capabilities to perform the experiments. The Light Microscopy Module is planned as a fully remotely controllable on-orbit microscope facility, allowing flexible scheduling and control of experiments within International Space Station resources. This paper will focus on the four microscope-based experiments, specifically, their objectives and the sample cell and instrument hardware to accommodate their requirements.

Development of the Holifield Radioactive Ion Beam Facility

International Nuclear Information System (INIS)

Tatum, B.A.

1997-01-01

The Holifield Radioactive Ion Beam Facility (HRIBF) construction project has been completed and the first radioactive ion beam has been successfully accelerated. The project, which began in 1992, has involved numerous facility modifications. The Oak Ridge Isochronous Cyclotron has been converted from an energy booster for heavy ion beams to a light ion accelerator with internal ion source. A target-ion source and mass analysis system have been commissioned as key components of the facility's radioactive ion beam injector to the 25MV tandem electrostatic accelerator. Beam transport lines have been completed, and new diagnostics for very low intensity beams have been developed. Work continues on a unified control system. Development of research quality radioactive beams for the nuclear structure and nuclear astrophysics communities continues. This paper details facility development to date

IAEA safeguards in new nuclear facilities

Energy Technology Data Exchange (ETDEWEB)

Catton, A. [International Atomic Energy Agency, Vienna (Austria); Durbin, K. [United States Department of Energy, Washington, D.C. (United States); Hamilton, A. [International Atomic Energy Agency, Vienna (Austria); Martikka, E. [STUK, Helsinki (Finland); Poirier, S.; Sprinkle, J. K.; Stevens, R. [International Atomic Energy Agency, Vienna (Austria); Whitlock, J. [Atomic Energy of Canada Limited, Chalk River, ON (Canada)

2014-07-01

The inclusion of international safeguards early in the design of nuclear facilities offers an opportunity to reduce project risk. It also has the potential to minimize the impact of safeguards activities on facility operations. Safeguards by design (SBD) encourages stakeholders to become familiar with the requirements of their safeguards agreements and to decide when and how they will fulfil those requirements. As one example, modular reactors are at a design stage where SBD can have a useful impact. Modular reactors might be turnkey projects where the operator takes ownership after commissioning. This comes with a legal obligation to comply with International Atomic Energy Agency (IAEA) safeguards requirements. Some of the newcomer countries entering the reactor market have little experience with IAEA safeguards and the associated non-proliferation obligations. To reduce delays or cost increments, one can embed safeguards considerations in the bid and design phases of the project, along with the safety and security considerations. SBD does not introduce any new requirements - it is a process whereby facility designers facilitate the implementation of the existing safeguards requirements. In short, safeguards experts share their expertise with the designers and vice versa. Once all parties understand the fundamentals of all of the operational constraints, they are better able to decide how best to address them. This presentation will provide an overview of SBD activities. (author)

Civaux nuclear facilities. 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 Civaux, and 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, administrative procedures carried out in 2009), incidents and accidents registered in 2009, radioactive and chemical effluents released by the facilities in the environment, other pollutions, management of radioactive wastes, and, finally, the actions carried out in the domain of transparency and public information. 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.)

Chooz nuclear facilities. 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 Chooz, and 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, administrative procedures carried out in 2009), incidents and accidents registered in 2009, radioactive and chemical effluents released by the facilities in the environment, other pollutions, management of radioactive wastes, and, finally, the actions carried out in the domain of transparency and public information. 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.)

Brennilis nuclear facilities. 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 Brennilis, and 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, administrative procedures carried out in 2009), incidents and accidents registered in 2009, radioactive and chemical effluents released by the facilities in the environment, other pollutions, management of radioactive wastes, and, finally, the actions carried out in the domain of transparency and public information. 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.)

Space Facility for Orbital Remote Manufacturing (SPACEFORM), Phase I

Data.gov (United States)

National Aeronautics and Space Administration — To address NASA need in continued cost efficient International Space Station (ISS) exploration FOMS Inc. proposes to develop and deploy Space Facility for Orbital...

Nuclear Station Facilities Improvement Planning

International Nuclear Information System (INIS)

Hooks, R. W.; Lunardini, A. L.; Zaben, O.

1991-01-01

An effective facilities improvement program will include a plan for the temporary relocation of personnel during the construction of an adjoining service building addition. Since the smooth continuation of plant operation is of paramount importance, the phasing plan is established to minimize the disruptions in day-to-day station operation and administration. This plan should consider the final occupancy arrangements and the transition to the new structure; for example, computer hookup and phase-in should be considered. The nuclear industry is placing more emphasis on safety and reliability of nuclear power plants. In order to do this, more emphasis is placed on operations and maintenance. This results in increased size of managerial, technical and maintenance staffs. This in turn requires improved office and service facilities. The facilities that require improvement may include training areas, rad waste processing and storage facilities, and maintenance facilities. This paper discusses an approach for developing an effective program to plan and implement these projects. These improvement projects can range in magnitude from modifying a simple system to building a new structure to allocating space for a future project. This paper addresses the planning required for the new structures with emphasis on site location, space allocation, and internal layout. Since facility planning has recently been completed by Sargent and Leyden at six U. S. nuclear stations, specific examples from some of those plants are presented. Site planning and the establishment of long-range goals are of the utmost importance when undertaking a facilities improvement program for a nuclear station. A plan that considers the total site usage will enhance the value of both the new and existing facilities. Proper planning at the beginning of the program can minimize costs and maximize the benefits of the program

International Space Station exhibit

Science.gov (United States)

2000-01-01

The International Space Station (ISS) exhibit in StenniSphere at John C. Stennis Space Center in Hancock County, Miss., gives visitors an up-close look at the largest international peacetime project in history. Step inside a module of the ISS and glimpse how astronauts will live and work in space. Currently, 16 countries contribute resources and hardware to the ISS. When complete, the orbiting research facility will be larger than a football field.

MISTRA facility for containment lumped parameter and CFD codes validation. Example of the International Standard Problem ISP47

International Nuclear Information System (INIS)

Tkatschenko, I.; Studer, E.; Paillere, H.

2005-01-01

During a severe accident in a Pressurized Water Reactor (PWR), the formation of a combustible gas mixture in the complex geometry of the reactor depends on the understanding of hydrogen production, the complex 3D thermal-hydraulics flow due to gas/steam injection, natural convection, heat transfer by condensation on walls and effect of mitigation devices. Numerical simulation of such flows may be performed either by Lumped Parameter (LP) or by Computational Fluid Dynamics (CFD) codes. Advantages and drawbacks of LP and CFD codes are well-known. LP codes are mainly developed for full size containment analysis but they need improvements, especially since they are not able to accurately predict the local gas mixing within the containment. CFD codes require a process of validation on well-instrumented experimental data before they can be used with a high degree of confidence. The MISTRA coupled effect test facility has been built at CEA to fulfil this validation objective: with numerous measurement points in the gaseous volume - temperature, gas concentration, velocity and turbulence - and with well controlled boundary conditions. As illustration of both experimental and simulation areas of this topic, a recent example in the use of MISTRA test data is presented for the case of the International Standard Problem ISP47. The proposed experimental work in the MISTRA facility provides essential data to fill the gaps in the modelling/validation of computational tools. (author)

Mercury regulation, fate, transport, transformation, and abatement within cement manufacturing facilities: review.

Science.gov (United States)

Sikkema, Joel K; Alleman, James E; Ong, Say Kee; Wheelock, Thomas D

2011-09-15

The USEPA's 2010 mercury rule, which would reduce emissions from non-hazardous waste burning cement manufacturing facilities by an estimated 94%, represents a substantial regulatory challenge for the industry. These regulations, based on the performance of facilities that benefit from low concentrations of mercury in their feedstock and fuel inputs (e.g., limestone concentration was less than 25 ppb at each facility), will require non-compliant facilities to develop innovative controls. Control development is difficult because each facility's emissions must be assessed and simple correlation to mercury concentrations in limestone or an assumption of 'typically observed' mercury concentrations in inputs are unsupported by available data. Furthermore, atmospheric emissions are highly variable due to an internal control mechanism that captures and loops mercury between the high-temperature kiln and low-temperature raw materials mill. Two models have been reported to predict emissions; however, they have not been benchmarked against data from the internal components that capture mercury and do not distinguish between mercury species, which have different sorption and desorption properties. Control strategies include technologies applied from other industries and technologies developed specifically for cement facilities. Reported technologies, listed from highest to lowest anticipated mercury removal, include purge of collected dust or raw meal, changes in feedstocks and fuels, wet scrubbing, cleaning of mercury enriched dust, dry sorbent injection, and dry and semi-dry scrubbing. The effectiveness of these technologies is limited by an inadequate understanding of sorption, desorption, and mercury species involved in internal loop mercury control. To comply with the mercury rule and to improve current mercury control technologies and practices, research is needed to advance fundamental knowledge regarding mercury species sorption and desorption dynamics on materials

AGING FACILITY WORKER DOSE ASSESSMENT

International Nuclear Information System (INIS)

R.L. Thacker

2005-01-01

The purpose of this calculation is to estimate radiation doses received by personnel working in the Aging Facility performing operations to transfer aging casks to the aging pads for thermal and logistical management, stage empty aging casks, and retrieve aging casks from the aging pads for further processing in other site facilities. Doses received by workers due to aging cask surveillance and maintenance operations are also included. The specific scope of work contained in this calculation covers both collective doses and individual worker group doses on an annual basis, and includes the contributions due to external and internal radiation from normal operation. There are no Category 1 event sequences associated with the Aging Facility (BSC 2004 [DIRS 167268], Section 7.2.1). The results of this calculation will be used to support the design of the Aging Facility and to provide occupational dose estimates for the License Application. The calculations contained in this document were developed by Environmental and Nuclear Engineering of the Design and Engineering Organization and are intended solely for the use of the Design and Engineering Organization in its work regarding facility operation. Yucca Mountain Project personnel from the Environmental and Nuclear Engineering should be consulted before use of the calculations for purposes other than those stated herein or use by individuals other than authorized personnel in Environmental and Nuclear Engineering

76 FR 55255 - Definition of Solid Waste Disposal Facilities for Tax-Exempt Bond Purposes; Correction

Science.gov (United States)

2011-09-07

... Definition of Solid Waste Disposal Facilities for Tax-Exempt Bond Purposes; Correction AGENCY: Internal..., on the definition of solid waste disposal facilities for purposes of the rules applicable to tax... governments that issue tax-exempt bonds to finance solid waste disposal facilities and to taxpayers that use...

Benefits of International Collaboration on the International Space Station

Science.gov (United States)

Hasbrook, Pete; Robinson, Julie A.; Brown Tate, Judy; Thumm, Tracy; Cohen, Luchino; Marcil, Isabelle; De Parolis, Lina; Hatton, Jason; Umezawa, Kazuo; Shirakawa, Masaki;

The International Atomic Energy Agency's safeguards system

International Nuclear Information System (INIS)

Wagner, W.

2000-01-01

A system of international safeguards has been established to provide assurance that nuclear materials in civilian use are not diverted from their peaceful purpose. The safeguards system is administered by the International Atomic Energy Agency/Department of Safeguards and devolves from treaties and other international agreements. Inspectors from the Agency verify reports from States about nuclear facilities by audits, observation, and measurements. (author)

Safeguards implementation at US facilities during 1986 and 1987

International Nuclear Information System (INIS)

Wredberg, L.

1987-01-01

Safeguards procedures were implemented at three nuclear facilities in the United States during 1986 and 1987, namely, the Westinghouse fuel fabrication plant in Columbia, South Carolina; the Salem No. 1 light water reactor (LWR) in New Jersey; and the Turkey Point No. 4 LWR in Florida. These three facilities have been under International Atomic Energy Agency (IAEA) safeguards since early 1986 in accordance with the voluntary offer agreement between the IAEA and the United States, which went into force in 1980. Because of limited manpower and budget resources allocated to safeguards in nuclear weapon states, only a limited number of facilities can be under IAEA safeguards inspections at a time. Facilities are, therefore, subject to inspection only during a 2-yr period in the case of the United States. After that period other facilities are selected for another 2-yr period from the list of facilities subject to safeguards under the agreement. The facilities have been selected so that they form a fuel cycle, i.e., the inspected reactors are fueled with fuel assemblies manufactured by the inspected fabrication plant. The IAEA applies full scope safeguards at the selected facilities based upon established implementation practice for the facility types

Hematite nuclear fuel cycle facility decommissioning

International Nuclear Information System (INIS)

Hayes, K.

2004-01-01

Westinghouse Electric Company LLC ('Westinghouse') acquired a nuclear fuel processing plant at Hematite, Missouri ('Hematite', the 'Facility', or the 'Plant') in April 2000. The plant has subsequently been closed, and its operations have been relocated to a newer, larger facility. Westinghouse has announced plans to complete its clean-up, decommissioning, and license retirement in a safe, socially responsible, and environmentally sound manner as required by internal policies, as well as those of its parent company, British Nuclear Fuels plc. ('BNFL'). Preliminary investigations have revealed the presence of environmental contamination in various areas of the facility and grounds, including both radioactive contamination and various other substances related to the nuclear fuel processing operations. The disparity in regulatory requirements for radiological and nonradiological contaminants, the variety of historic and recent operations, and the number of previous owners working under various contractual arrangements for both governmental and private concerns has resulted in a complex project. This paper discusses Westinghouse's efforts to develop and implement a comprehensive decontamination and decommissioning (D and D) strategy for the facility and grounds. (author)

Using limnological and optical knowledge to detect discharges from nuclear facilities - Potential application of satellite imagery for international safeguards

International Nuclear Information System (INIS)

Borstad, G.; Truong, Q.S. Bob; Keeffe, R.; Baines, P.; Staenz, K.; Neville, R.

2001-01-01

large plume of slightly less turbid water emanating from the facility. Results from other examples, if available in time for the symposium, along with recommendations for additional work that could have potential applications for international safeguards are also presented

The IAEA review of methods of reducing occupational exposures during decommissioning of nuclear facilities

International Nuclear Information System (INIS)

Alejnikov, V.E.

1986-01-01

International interest in decommissioning has increased rapidly in the last few years because of the large number of older facilities which are or soon will be retired from service and because of the many hundreds of new facilities which have been built or planned and will eventually require decommissioning. A state-of-the-art review of methods of reducing occupational exposures during decommissioning of nuclear facilities has been prepared recently by the International Atomic Energy Agency. The report concludes that decommissioning can be carried out without unacceptable impact on man or his environment. However, additional development is required to reduce occupational exposures during decommissioning. (author)

Educational Facility Evaluations of Primary Schools in Rural Honduras: Departments of Cortes and Meambar.

Science.gov (United States)

Council of Educational Facility Planners, International, Scottsdale, AZ.

A team of 11 educational facility planners and architects from the United States and Canada conducted a facility evaluation of schools in the rural areas of Meambar and Cortes, Honduras. Team members were all part of the Council of Educational Facility Planners, International and traveled to Honduras under the auspices of a Christian mission…

76 FR 55256 - Definition of Solid Waste Disposal Facilities for Tax-Exempt Bond Purposes; Correction

Science.gov (United States)

2011-09-07

... Definition of Solid Waste Disposal Facilities for Tax-Exempt Bond Purposes; Correction AGENCY: Internal..., 2011, on the definition of solid waste disposal facilities for purposes of the rules applicable to tax... governments that issue tax-exempt bonds to finance solid waste disposal facilities and to taxpayers that use...

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

Guide to good practices at plutonium facilities

International Nuclear Information System (INIS)

Faust, L.G.; Brackenbush, L.W.; Carter, L.A.; Endres, G.W.R.; Glenn, R.D.; Jech, J.J.; Selby, J.M.; Smith, R.C.; Waite, D.A.; Walsh, W.P.

1977-09-01

This manual establishes guidelines and principles for use in setting up a sound radiation protection program for work with plutonium. The guidance presented is based on the experiences of Energy Research and Development Administration (ERDA) contractors and those portions of private industry concerned with the operation of plutonium facilities, specifically with the fabrication of mixed oxide reactor fuel. The manual is directed primarily to those facilities which have as their sole purpose the handling of large quantities of plutonium for military or industrial uses. It is not intended for use by facilities engaged in reactor or chemical separation operations nor for partial or occasional use by analytical laboratories; while these facilities would find the manual beneficial, it would be incomplete for their needs. The manual addresses good practices that should be observed by management, staff and designers, since the benefits of a good radiation protection program are the result of their joint efforts. Methods for the diagnostic evaluation of internally deposited Pu are included

Compressed Natural Gas Vehicle Maintenance Facility Modification Handbook

Energy Technology Data Exchange (ETDEWEB)

Kelly, K.; Melendez, M.; Gonzales, J.; Lynch, L.; Boale, B.; Kohout, J.

2017-09-28

To ensure the safety of personnel and facilities, vehicle maintenance facilities are required by law and by guidelines of the National Fire Protection Association (NFPA) and the International Fire Code (IFC) to exhibit certain design features. They are also required to be fitted with certain fire protection equipment and devices because of the potential for fire or explosion in the event of fuel leakage or spills. All fuels have an explosion or fire potential if specific conditions are present. This handbook covers the primary elements that must be considered when developing a CNG vehicle maintenance facility design that will protect against the ignition of natural gas releases. It also discusses specific protocols and training needed to ensure safety.

Inventory extension at the Nuclear Materials Storage Facility

International Nuclear Information System (INIS)

Stanbro, W.D.; Longmire, V.; Olinger, C.T.; Argo, P.E.

1996-09-01

The planned renovation of the Nuclear Material Storage Facility (NMSF) at Los Alamos National Laboratory will be a significant addition to the plutonium storage capacity of the nuclear weapons complex. However, the utility of the facility may be impaired by an overly conservative approach to performing inventories of material in storage. This report examines options for taking advantage of provisions in Department of Energy orders to extend the time between inventories. These extensions are based on a combination of modern surveillance technology, facility design features, and revised operational procedures. The report also addresses the possibility that NMSF could be the site of some form of international inspection as part of the US arms control and nonproliferation policy

Facilities Enhancement for IPY at Barrow

Science.gov (United States)

Sheehan, G.; Brown, J.; Coakley, B.; Zak, B.

2007-12-01

In connection with the International Polar Year, research facilities at Barrow have been markedly enhanced. On June 1st, Sen. Ted Stevens cut the ribbon at the Grand Opening of the Barrow Arctic Research Center (BARC). The BARC currently covers 18,000 sq. ft, with future phases anticipated, including 8 research labs, a necropsy lab for animal studies, freezers for biological samples, a state-of-the-art-data system, a planned Internet II connection, meeting spaces, and offices. There is a platform on the roof of the facility for instrumentation, and a communications tower to provide WIFI connections to remote instrumentation located on the adjacent Barrow Environmental Observatory (BEO). The BEO, which consists of 11 square miles of tundra and coastline set aside for environmental and ecological research, has also seen recent enhancements. A power line and a hard- surfaced trail now provide easy access to the interior of the BEO. Users of the BEO (and others) also have access to many different data sets continuously collected at the NOAA Global Monitoring Division Barrow Station and the DOE ARM (Atmospheric Radiation Measurement) Climate Research Facility (see http://www.esrl.noaa.gov/gmd/obop/brw.html and http://www.arm.gov/sites/nsa.stm respectively) also adjacent to the BEO. The National Weather Service Barrow Station also provides data of interest. Researchers submitting proposals to the National Science Foundation can include a request for the use of BARC and BEO facilities in their proposals. ARM facilities, recently augmented, can also be made available, but through arrangements made directly with ARM (BDZak@sandia.gov; 505-845-8631 or MDIvey@sandia.gov; 505-284-9092). BARC, BEO and ARM facilities are available to other agency and international users as well. For more information, see http://www.arcticscience.org, or contact Glenn Sheehan (907-852-4881, basc@arcticscience.org). The BEO consists of land owned by Ukpeagvik Inupiat Corporation, which is owned by

Identification and analysis of main radionuclides that potentially contribute to the internal dose for workers at radiopharmacy facilities

International Nuclear Information System (INIS)

Sanches, Matias Puga

2004-01-01

The optimization principle in radiation protection means that there is a reasonable balance between resources used to monitor exposures and the benefits due to the monitoring program. Programs for the monitoring of workers handling radioactive materials are influenced by numerous factors. Estimation of internal doses due to inhalation or ingestion of radioactive materials is often based on measurements of the activity in the tissues of the body and in excreta, following a given intake. In order to enable dose estimations using the biokinetic models recommended by the ICRP and laboratory data, it is proposed to carry out comprehensive study to identify the main radionuclides that potentially contribute to the internal dose of workers at radiopharmacy facilities. The applied methodology for identification of these radionuclides takes into account criteria set out by the ICRP and IAEA. The practical purpose to set up this study was to establish a consistent approach to ensure that the dose assessments are as simple as possible and guarantee the necessary quality standards. The result of this study has indicated the requirement of routine measurements for seven radionuclides over all range of radioactive material compounds, handled at the radiopharmacy plant of IPEN, avoiding unjustifiable work concerning activity levels that are not relevant for the health of the occupationally exposed persons. The main intake pathways, the appropriate monitoring frequencies and derived reference level have also been identified. (author)

Alternative cask maintenance facility concepts

International Nuclear Information System (INIS)

Attaway, C.R.; Pope, R.B.; Wiliamson, A.C.; Medley, L.G.; Shappert, L.B.

1992-01-01

In this paper, the results of three trade-off studies of alternative concepts for performing cask maintenance for Civilian Radioactive Waste Management System casks are presented. An earlier study resulted in a recommendation that a submerged pool concept for cask internal component removal be used in the design of a Cask Maintenance Facility. The first trade-off study resulted in confirming the previous recommendation that a submerged pool concept be used rather than an isolation cell; the basis for this continued recommendation is discussed. The second study provides an evaluation of the previously proposed facility for the capability of handling an increased quantity of OCRWM casks. The third study provides a preliminary concept for adding the capability to repaint the exterior cylindrical portions of casks

Estimates of external dose-rate conversion factors and internal dose conversion factors for selected radionuclides released from fusion facilities

Energy Technology Data Exchange (ETDEWEB)

Homma, Toshimitsu; Togawa, Orihiko [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment

1996-11-01

This report provides a tabulation of both external dose-rate conversion factors and internal dose conversion factors using radioactive decay data in the updated Evaluated Nuclear Structure Data File (ENSDF) for selected 26 radionuclides and all their daughter radionuclides of potential importance in safety assessments of fusion facilities. The external dose-rate conversion factors for 21 target organs are tabulated for three exposure modes that are immersion in contaminated air, irradiation at a height of 1 m above a contaminated ground surface and immersion contaminated water. For internal exposure, committed dose equivalents, based on the methodology of ICRP Publication 30, in the same target organs per intake of unit activity are given for the inhalation and ingestion exposure pathways. The data presented here is intended to be generally used for safety assessments of fusion reactors. Comparisons of external effective dose-rate conversion factors and committed effective dose equivalents are made with the previous data from the independent data bases to provide quality assurance on our calculated results. There is generally good agreement among data from the independent data bases. The differences in the values of both effective dose-rate and dose conversion factors appeared are primarily due to differences in calculational methodology, the use of different radioactive decay data, and compilation errors. (author)

IAEA Guidance for Safeguards Implementation in Facility Design and Construction

International Nuclear Information System (INIS)

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

2015-01-01

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

Results from the CDE phase activity on neutron dosimetry for the international fusion materials irradiation facility test cell

CERN Document Server

Esposito, B; Maruccia, G; Petrizzi, L; Bignon, G; Blandin, C; Chauffriat, S; Lebrun, A; Recroix, H; Trapp, J P; Kaschuck, Y

2000-01-01

The international fusion materials irradiation facility (IFMIF) project deals with the study of an accelerator-based, deuterium-lithium source, producing high energy neutrons at sufficient intensity and irradiation volume to test samples of candidate materials for fusion energy reactors. IFMIF would also provide calibration and validation of data from fission reactor and other accelerator based irradiation tests. This paper describes the activity on neutron/gamma dosimetry (necessary for the characterization of the specimens' irradiation) performed in the frame of the IFMIF conceptual design evaluation (CDE) neutronics tasks. During the previous phase (conceptual design activity (CDA)) the multifoil activation method was proposed for the measurement of the neutron fluence and spectrum and a set of suitable foils was defined. The cross section variances and covariances of this set of foils have now been used for tests on the sensitivity of the IFMIF neutron spectrum determination to cross section uncertainties...

SYNER-G buildings, lifelines, transportation networks and critical facilities

CERN Document Server

Pitilakis, K; Kaynia, AM

2014-01-01

This volume collates serviceable fragility functions from an international selection of seismic risk probability research, developing and adapting them to a European context to improve damage forecasts for buildings, infrastructure, and critical facilities.

Pain treatment facilities: do we need quantity or quality?

Science.gov (United States)

de Meij, Nelleke; Köke, Albère; van der Weijden, Trudy; van Kleef, Maarten; Patijn, Jacob

2014-10-01

Chronic pain patients referred to a pain treatment facility have no guarantee that they will receive a proper diagnostic procedure or treatment. To obtain information about organizational aspects of pain treatment facilities and the content of their daily pain practice, we performed a questionnaire survey. The aim of the study was to evaluate the amount of pain treatment facilities, the content of organized specialized pain care and adherence to the criteria of the internationally accepted guidelines for pain treatment services. The University Pain Centre Maastricht in the Department of Anaesthesiology and Pain Management at Maastricht University Medical Centre developed a questionnaire survey based on the Recommendations for Pain Treatment Services of the International Association for the Study of Pain (IASP). The questionnaire was sent to the medical boards of all hospitals in the Netherlands (n=94). The response rate was 86% (n=81). Of all hospitals, 88.9% (n=72) reported the provision of organized specialized pain care, which was provided by a pain management team in 86.1% (n=62) and by an individual specialist in 13.9% (n=10). Insight was obtained from pain treatment facilities in five different domains: the organizational structure of pain management, composition of the pain team, pain team practice, patient characteristics, and research and education facilities. Although 88.9% of all hospitals stated that organized specialized pain care was provided, only a few hospitals could adhere to the criteria for pain treatment services of the IASP. The outcome of the questionnaire survey may help to define quality improvement standards for pain treatment facilities. © 2014 John Wiley & Sons, Ltd.

International nuclear fuel cycle fact book: Revision 9

Energy Technology Data Exchange (ETDEWEB)

Leigh, I.W.

1989-01-01

The International Nuclear Fuel Cycle Fact Book has been compiled in an effort to provide current data concerning fuel cycle and waste management facilities, R and D programs and key personnel. The Fact Book contains: national summaries in which a section for each country which summarizes nuclear policy, describes organizational relationships and provides addresses, names of key personnel, and facilities information; and international agencies in which a section for each of the international agencies which has significant fuel cycle involvement, and a listing of nuclear societies. The national summaries, in addition to the data described above, feature a small map for each country as well as some general information. The latter is presented from the perspective of the Fact Book user in the United States.

International dose assurance service programme of the International Atomic Energy Agency

International Nuclear Information System (INIS)

Nam, J.W.

1988-01-01

In order to execute normalization of high-doses on an international scale and to further promote dosimetry as quality control measures in radiation processing, the International Dose Assurance Service (IDAS) has recently been initiated in the framework of a high-dose standardization programme. IDAS is being provided on the basis of an ''Agreement Concerning the Provision of a Dose Assurance Service by the IAEA to Irradiation Facilities in its Member States''. The aim of the IDAS programme will be to meet stringent requirements for standardization of dosimetry, and to achieve concerted international efforts for quality assurance of radiation processing. Details of the programme and the achievements made to date are discussed. (author). 5 refs

2009 International Conference on Neutron Scattering (ICNS 2009)

Energy Technology Data Exchange (ETDEWEB)

Gopal Rao, PhD; Gillespie, Donna

2010-08-05

The ICNS provides a focal point for the worldwide neutron user community to strengthen ties within this diverse group, while at the same time promoting neutron research among colleagues in related disciplines identified as would-be neutron users. The International Conference on Neutron Scattering thus serves a dual role as an international user meeting and a scientific meeting. As a venue for scientific exchange, the ICNS showcases recent results and provides forums for scientific discussion of neutron research in diverse fields such as hard and soft condensed matter, liquids, biology, magnetism, engineering materials, chemical spectroscopy, crystal structure, and elementary excitations, fundamental physics and development of neutron instrumentation through a combination of invited talks, contributed talks and poster sessions. Each of the major national neutron facilities (NIST, LANSCE, ANL, HFIR and SNS), along with their international counterparts, has an opportunity to exchange information with each other and to update users, and potential users, of their facility. This is also an appropriate forum for users to raise issues that relate to the facilities.

The Richmond Agitation-Sedation Scale modified for palliative care inpatients (RASS-PAL): a pilot study exploring validity and feasibility in clinical practice.

Science.gov (United States)

Bush, Shirley H; Grassau, Pamela A; Yarmo, Michelle N; Zhang, Tinghua; Zinkie, Samantha J; Pereira, José L

2014-03-31

The Richmond Agitation-Sedation Scale (RASS), which assesses level of sedation and agitation, is a simple observational instrument which was developed and validated for the intensive care setting. Although used and recommended in palliative care settings, further validation is required in this patient population. The aim of this study was to explore the validity and feasibility of a version of the RASS modified for palliative care populations (RASS-PAL). A prospective study, using a mixed methods approach, was conducted. Thirteen health care professionals (physicians and nurses) working in an acute palliative care unit assessed ten consecutive patients with an agitated delirium or receiving palliative sedation. Patients were assessed at five designated time points using the RASS-PAL. Health care professionals completed a short survey and data from semi-structured interviews was analyzed using thematic analysis. The inter-rater intraclass correlation coefficient range of the RASS-PAL was 0.84 to 0.98 for the five time points. Professionals agreed that the tool was useful for assessing sedation and was easy to use. Its role in monitoring delirium however was deemed problematic. Professionals felt that it may assist interprofessional communication. The need for formal education on why and how to use the instrument was highlighted. This study provides preliminary validity evidence for the use of the RASS-PAL by physicians and nurses working in a palliative care unit, specifically for assessing sedation and agitation levels in the management of palliative sedation. Further validity evidence should be sought, particularly in the context of assessing delirium.

The Richmond Agitation-Sedation Scale modified for palliative care inpatients (RASS-PAL): a pilot study exploring validity and feasibility in clinical practice

Science.gov (United States)

2014-01-01

Background The Richmond Agitation-Sedation Scale (RASS), which assesses level of sedation and agitation, is a simple observational instrument which was developed and validated for the intensive care setting. Although used and recommended in palliative care settings, further validation is required in this patient population. The aim of this study was to explore the validity and feasibility of a version of the RASS modified for palliative care populations (RASS-PAL). Methods A prospective study, using a mixed methods approach, was conducted. Thirteen health care professionals (physicians and nurses) working in an acute palliative care unit assessed ten consecutive patients with an agitated delirium or receiving palliative sedation. Patients were assessed at five designated time points using the RASS-PAL. Health care professionals completed a short survey and data from semi-structured interviews was analyzed using thematic analysis. Results The inter-rater intraclass correlation coefficient range of the RASS-PAL was 0.84 to 0.98 for the five time points. Professionals agreed that the tool was useful for assessing sedation and was easy to use. Its role in monitoring delirium however was deemed problematic. Professionals felt that it may assist interprofessional communication. The need for formal education on why and how to use the instrument was highlighted. Conclusion This study provides preliminary validity evidence for the use of the RASS-PAL by physicians and nurses working in a palliative care unit, specifically for assessing sedation and agitation levels in the management of palliative sedation. Further validity evidence should be sought, particularly in the context of assessing delirium. PMID:24684942

ICFA on international collaboration

International Nuclear Information System (INIS)

Anon.

1993-01-01

International collaboration in high energy physics is what ICFA - the International Committee for Future Accelerators - is all about. Progress is highlighted every three years when ICFA convenes its 'Future Perspectives in High Energy Physics' seminar to focus attention on major issues and to identify evolving trends. The latest such seminar, held at the DESY Laboratory in Hamburg from 3-7 May, looked at international cooperation in the construction of major facilities. Status reports across the whole range of existing experimental programmes and ongoing plans gave valuable pointers to future needs. For electron-positron linear colliders (EPLC), research and development work towards the next generation of machines is underway in Laboratories throughout the world. At previous such seminars, at Tsukuba, Japan (1984), Brookhaven, USA (1987) and Protvino (1990), ICFA, which has no direct power, could sometimes only stand on the sidelines and comment on the emergence of major new national plans. The lessons learnt, ICFA is keen to make sure that the EPLC debut on the world stage will be better choreographed. In addition to plans for new major experimental facilities, the Hamburg seminar also provided a valuable snapshot of the current scene and the directions in which ongoing research is poised to take. This covered existing facilities and projects, 'factories' to mass-produce specific particles, fixed target studies and non-accelerator experiments as well as the key EPLC development theme. B-physics, the study of particles containing the fifth, or 'beauty' (b) quark, emerged as an important thread running across several machine scenarios

ORNL results for Test Case 1 of the International Atomic Energy Agency's research program on the safety assessment of Near-Surface Radioactive Waste Disposal Facilities

International Nuclear Information System (INIS)

Thorne, D.J.; McDowell-Boyer, L.M.; Kocher, D.C.; Little, C.A.; Roemer, E.K.

1993-01-01

The International Atomic Energy Agency (IAEA) started the Coordinated Research Program entitled '''The Safety Assessment of Near-Surface Radioactive Waste Disposal Facilities.'' The program is aimed at improving the confidence in the modeling results for safety assessments of waste disposal facilities. The program has been given the acronym NSARS (Near-Surface Radioactive Waste Disposal Safety Assessment Reliability Study) for ease of reference. The purpose of this report is to present the ORNL modeling results for the first test case (i.e., Test Case 1) of the IAEA NSARS program. Test Case 1 is based on near-surface disposal of radionuclides that are subsequently leached to a saturated-sand aquifer. Exposure to radionuclides results from use of a well screened in the aquifer and from intrusion into the repository. Two repository concepts were defined in Test Case 1: a simple earth trench and an engineered vault

Implications of multinational arrangements for nuclear fuel cycle facilities

International Nuclear Information System (INIS)

Muench, E.; Richter, B.; Stein, G.

1980-01-01

In the recently concluded INFCE study a variety of possibilities to minimize the proliferation risk was discussed, and their applicability in the nuclear fuel cycle was investigated. It was found that safeguards still play a central part as an anti-proliferation measure. Aspect of institutional arrangements with the aim of placing nuclear material processing and storage facilities under multinational or international auspices is the basis and goal of this study, as in international discussions some degree of proliferation hindrance is attributed to such models. In the assessment of the internationalization of nuclear facilities as an anti-proliferation measure two aspects have to be emphasized: Firstly, internationalization may be understood as a political measure to hinder proliferation, and secondly, no additional control effort should be caused by the possible complementary character to safeguards. 5 refs

The GSI plans for an international accelerator facility for beams of ions and antiprotons

International Nuclear Information System (INIS)

Suemmerer, K.

2003-01-01

GSI proposes to build a next-generation facility for research with relativistic beams of ions and antiprotons. This facility allows a broad range of topics in nuclear and astrophysics, plasma and atomic physics to be addressed. The topic most interesting in the context of this conference is physics with high-intensity beams of exotic nuclei. In addition, a short overview of the opportunities in the other fields of nuclear physics is given

Workshop on internal dosimetry in the nuclear fuel cycle

International Nuclear Information System (INIS)

Rojo, A.M.; Gómez Parada, I.; Gossio, S.; Puerta Yepes, N.; Saavedra, A.D.; Segato, A.D.

2011-01-01

Dose assessment in case of internal exposure involves the estimation of committed effective dose based on the interpretation of bioassay measurement, and the assumptions of hypotheses on the characteristics of the radioactive material and the time pattern and the pathway of intake. In the case of workers exposed in nuclear fuel facilities, the normal uranium excretion from the diet is an additional difficulty in the process of assessing internal exposure. The aim of this paper is to present the main topics discussion and the conclusions of the workshop, held in the frame of the missions of the Autoridad Regulatoria Nuclear. All the personnel involved in the control of internal exposure in nuclear fuel cycle was invited to participate in the workshop to discuss about individual monitoring criteria and the available tools for assessing committed effective dose in the workers of their facilities. The lectures were presented jointly by the Nuclear Fuel Cycle Facilities Control and the Dosimetric and Radiobiological Assessment departments. It was hold at the Ezeiza Atomic Center from 23th to 24th November 2010 based on the Advanced Course on Internal Dosimetry organized on 2009 and focusing specific uranium compound internal dosimetry. A representative of each facility was invited to present the monitoring program implemented for controlling the internal exposure. It was an opportunity to discuss criteria and to share experiences on this field in the frame of the ICRP, HPA and ISO publications. The different monitoring program criteria could be analyzed and so contributing to the improvement of radiological protection. Finally, it was agreed to hold periodical meetings to assure the update on uranium measurement techniques and the handling of monitoring data for committed effective dose assessment. (authors) [es

Environmental change during the last glacial maximum (c. 25,000-16,500 years BP) at Mt Richmond, Auckland Isthmus, New Zealand

International Nuclear Information System (INIS)

Sandiford, A.; Horrocks, M.; Newnham, R.; Ogden, J.; Alloway, B.V.

2002-01-01

A 2 m section at the base of Mt Richmond contains a palynological record of the last glacial maximum (LGM) (c. 25,000-c. 16,500 14 C years BP) vegetation of the Auckland Isthmus. Three silicic tephra layers derived from the Taupo Volcanic Centre (Okaia Tephra c. 23,500 14 C years BP, Kawakawa Tephra c. 22,500 14 C years BP) and the Okataina Volcanic Centre (Okareka Tephra c. 18,000 14 C years BP), both centres lying within the Taupo Volcanic Zone, provide the basis of the chronology supported by radiocarbon dates. The pollen diagram is divided into two pollen zones separated by the deposition of a locally derived basaltic ash. From c. 25,000-23,000 14 C years BP the site was initially a eutrophic lake fringed by Leptospermum and Typha, which altered to a Cyperaceae/Leptospermum-dominated swamp. The regional vegetation at the time was beech-dominated forest; canopy conifers were present but formed a minor part of the local forest. From c. 23,000-16,500 14 C years BP regional forest was further restricted to local patches in extensive shrubland/grassland. Temperatures may have been depressed by more than 4-5 degrees C. The eruption of a local volcano dammed the swamp outlet resulting in a return to lacustrine conditions. Local volcanism may have accelerated vegetation change already under way as a result of climate change to cooler conditions. This record provides a view of LGM vegetation of the Auckland Isthmus and a template for earlier cold stages of the Quaternary. (author). 39 refs., 3 figs., 1 tab

Master Training in Radiological Protection Facilities Radioactive and Nuclear

International Nuclear Information System (INIS)

Verdu, G.; Mayo, P.; Campayo, J. M.

2011-01-01

The master includes general aspects of radiation protection in nuclear facilities. also an advanced module to acquire a high level training highlights as nuclear decommissioning, shielding calculation using advanced codes, particle accelerators, international law, etc.

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

Enhancing Efficiency of Safeguards at Facilities that are Shutdown or Closed-Down, including those being Decommissioned

Energy Technology Data Exchange (ETDEWEB)

Moran, B. [Brookhaven National Lab. (BNL), Upton, NY (United States); Stern, W. [Brookhaven National Lab. (BNL), Upton, NY (United States); Colley, J. [Brookhaven National Lab. (BNL), Upton, NY (United States); Marzo, M. [Brookhaven National Lab. (BNL), Upton, NY (United States)

2016-12-15

International Atomic Energy Agency (IAEA) safeguards involves verification activities at a wide range of facilities in a variety of operational phases (e.g., under construction, start-up, operating, shutdown, closed-down, and decommissioned). Safeguards optimization for each different facility type and operational phase is essential for the effectiveness of safeguards implementation. The IAEA’s current guidance regarding safeguards for the different facility types in the various lifecycle phases is provided in its Design Information Examination (DIE) and Verification (DIV) procedure. 1 Greater efficiency in safeguarding facilities that are shut down or closed down, including those being decommissioned, could allow the IAEA to use a greater portion of its effort to conduct other verification activities. Consequently, the National Nuclear Security Administration’s Office of International Nuclear Safeguards sponsored this study to evaluate whether there is an opportunity to optimize safeguards approaches for facilities that are shutdown or closed-down. The purpose of this paper is to examine existing safeguards approaches for shutdown and closed-down facilities, including facilities being decommissioned, and to seek to identify whether they may be optimized.

Nuclear material inventory estimation in a nuclear fuel reprocessing facility

International Nuclear Information System (INIS)

Bennett, J.E.; Beyerlein, A.L.

1981-01-01

A new approach in the application of modern system identification and estimation techniques is proposed to help nuclear reprocessing facilities meet the nuclear accountability requirement proposed by the International Atomic Energy Agency. The proposed identification and estimation method considers the material inventory in a portion of the chemical separations area of a reprocessing facility. The method addresses the nonlinear aspects of the problem, the time delay through the separation facility, and the lack of measurement access. The method utilizes only input-output measured data and knowledge of the uncertainties associated with the process and measured data. 14 refs

MODERN CONDITIONS OF ROAD FACILITIES AND INTERNATIONAL AUTOMOTIVE TRANSPORTATION OF THE REPUBLIC OF BELARUS

Directory of Open Access Journals (Sweden)

I. M. Tsarenkova

2008-01-01

Full Text Available For analysis of technical and economic conditions of automotive roads and determination of reserves for improvement of financial situation and usage of capital in road facilities operational efficiency of road facilities and automotive freight-traffic services that provide significant currency receipt for Republic budget. The main ways for higher export of construction services are involvement of road facilities enterprises in this activity and introduction of highly-productive technologies in their operation. The paper demonstrates an importance of non-conventional sources of investment attractions such as leasing which is used for renovation of capital assets and invests resources in the basic capital on the return basis in the natural form. For application of new technologies and modern technique it is justifiable to establish joint road-construction enterprises with foreign sub-contractors. The paper reveals main reasons of profit increase due to operation and services of road branch.

TAN Hot Shop and Support Facility Utilization Study

Energy Technology Data Exchange (ETDEWEB)

Picker, B.A.

2001-11-16

Impacts to the U.S. Department of Energy (DOE) complex caused by early closure (prior to 2018) and Demolition and Dismantlement (D and D) of the Test Area North (TAN) hot shop and its support facilities are explored in this report. Various possible conditions, such as Standby, Safe Store and Lay-up, that the facility may be placed in prior to eventually being turned over to D and D are addressed. The requirements, impacts, and implications to the facility and to the DOE Complex are discussed for each condition presented in the report. Some details of the report reference the Idaho National Engineering and Environmental Laboratory (INEEL) Spent Nuclear Fuel Life Cycle Baseline Plan, the INEEL 2000 Infrastructure Long Range Plan, and other internal INEEL reports.

TAN HOT SHOP AND SUPPORT FACILITY UTILIZATION STUDY

Energy Technology Data Exchange (ETDEWEB)

Phillips, Ken Crawforth

2001-11-01

Impacts to the U.S. Department of Energy (DOE) complex caused by early closure (prior to 2018) and Demolition and Dismantlement (D&D) of the Test Area North (TAN) hot shop and its support facilities are explored in this report. Various possible conditions, such as Standby, Safe Store and Lay-up, that the facility may be placed in prior to eventually being turned over to D&D are addressed. The requirements, impacts, and implications to the facility and to the DOE Complex are discussed for each condition presented in the report. Some details of the report reference the Idaho National Engineering and Environmental Laboratory (INEEL) Spent Nuclear Fuel Life Cycle Baseline Plan, the INEEL 2000 Infrastructure Long Range Plan, and other internal INEEL reports.

Dry spent fuel storage facility at Kozloduy Nuclear Power Plant

International Nuclear Information System (INIS)

Goehring, R.; Stoev, M.; Davis, N.; Thomas, E.

2004-01-01

The Dry Spent Fuel Storage Facility (DSF) is financed by the Kozloduy International Decommissioning Support Fund (KIDSF) which is managed by European Bank for Reconstruction and Development (EBRD). On behalf of the Employer, the Kozloduy Nuclear Power Plant, a Project Management Unit (KPMU) under lead of British Nuclear Group is managing the contract with a Joint Venture Consortium under lead of RWE NUKEM mbH. The scope of the contract includes design, manufacturing and construction, testing and commissioning of the new storage facility for 2800 VVER-440 spent fuel assemblies at the KNPP site (turn-key contract). The storage technology will be cask storage of CONSTOR type, a steel-concrete-steel container. The licensing process complies with the national Bulgarian regulations and international rules. (authors)

Domestic round robin exercise on analysis of uranium for nuclear material handling facilities in Japan

International Nuclear Information System (INIS)

Kato, Yoshiyasu; Nagai, Kohta; Handa, Takamitsu; Inoue, Shin-ichi; Sato, Yoshihiro

2016-01-01

Interlaboratory comparison programme as well as internal quality control system is an effective tool for an analytical laboratory responsible to nuclear material accountancy of a nuclear facility to maintain and enhance its capability for analysis. However, it is a burden on nuclear material handling facilities in Japan to attend interlaboratory comparison programme run by overseas institutions because of high costs and complicated procedure for importing nuclear materials, and therefore facilities which can participate in such international programme would be limited. Nuclear Material Control Center has hence started and organised an annual domestic round robin exercise on analysis of uranium standard materials, funded by the Japan Safeguards Office of the Nuclear Regulation Authority, since 2008 to enhance analytical capability of Japanese Facilities. The outline of the round robin exercise will be given and the results of uranium isotopic and concentration analysis reported by participant facilities from 2008 to 2015 will be summarised in the presentation. (author)

Conducting Research on the International Space Station using the EXPRESS Rack Facilities

Science.gov (United States)

Thompson, Sean W.; Lake, Robert E.

2016-01-01

Eight "Expedite the Processing of Experiments to Space Station" (EXPRESS) Rack facilities are located within the International Space Station (ISS) laboratories to provide standard resources and interfaces for the simultaneous and independent operation of multiple experiments within each rack. Each EXPRESS Rack provides eight Middeck Locker Equivalent locations and two drawer locations for powered experiment equipment, also referred to as sub-rack payloads. Payload developers may provide their own structure to occupy the equivalent volume of one, two, or four lockers as a single unit. Resources provided for each location include power (28 Vdc, 0-500 W), command and data handling (Ethernet, RS-422, 5 Vdc discrete, +/- 5 Vdc analog), video (NTSC/RS 170A), and air cooling (0-200 W). Each rack also provides water cooling for two locations (500W ea.), one vacuum exhaust interface, and one gaseous nitrogen interface. Standard interfacing cables and hoses are provided on-orbit. One laptop computer is provided with each rack to control the rack and to accommodate payload application software. Four of the racks are equipped with the Active Rack Isolation System to reduce vibration between the ISS and the rack. EXPRESS Racks are operated by the Payload Operations Integration Center at Marshall Space Flight Center and the sub-rack experiments are operated remotely by the investigating organization. Payload Integration Managers serve as a focal to assist organizations developing payloads for an EXPRESS Rack. NASA provides EXPRESS Rack simulator software for payload developers to checkout payload command and data handling at the development site before integrating the payload with the EXPRESS Functional Checkout Unit for an end-to-end test before flight. EXPRESS Racks began supporting investigations onboard ISS on April 24, 2001 and will continue through the life of the ISS.

Maximization of revenues for power sales from a solid waste resources recovery facility

Energy Technology Data Exchange (ETDEWEB)

1991-12-01

The report discusses the actual implementation of the best alternative in selling electrical power generated by an existing waste-to-energy facility, the Metro-Dade County Resources Recovery Plant. After the plant processes and extracts various products out of the municipal solid waste, it burns it to produce electrical power. The price for buying power to satisfy the internal needs of our Resources Recovery Facility (RRF) is substantially higher than the power price for selling electricity to any other entity. Therefore, without any further analysis, it was decided to first satisfy those internal needs and then export the excess power. Various alternatives were thoroughly explored as to what to do with the excess power. Selling power to the power utilities or utilizing the power in other facilities were the primary options.

Aerial infrared monitoring for nuclear fuel cycle facilities in Ukraine

International Nuclear Information System (INIS)

Stankevich, S.A.; Dudar, T.V.; Kovalenko, G.D.; Kartashov, V.V.

2015-01-01

The scientific research overall objective is rapid express detection and preliminary identification of pre-accidental conditions at nuclear fuel cycle facilities. We consider development of a miniature unmanned aerial vehicle equipped with high-precision infrared spectroradiometer able to detect remotely internal warming up of hazardous facilities by its thermal infrared radiation. The possibility of remote monitoring using unmanned aerial vehicle is considered at the example of the dry spent fuel storage facility of the Zaporizhzhya Nuclear Power Plant. Infrared remote monitoring is supposed to present additional information on the monitored facilities based on different physical principles rather than those currently in use. Models and specifications towards up-to-date samples of infrared surveying equipment and its small-sized unmanned vehicles are presented in the paper.

International Nuclear Fuel Cycle Fact Book. Revision 5

International Nuclear Information System (INIS)

Harmon, K.M.; Lakey, L.T.; Leigh, I.W.; Jeffs, A.G.

1985-01-01

This Fact Book has been compiled in an effort to provide: (1) an overview of worldwide nuclear power and fuel cycle programs; and (2) current data concerning fuel cycle and waste management facilities, R and D programs, and key personnel in countries other than the United States. Additional information on each country's program is available in the International Source Book: Nuclear Fuel Cycle Research and Development, PNL-2478, Rev. 2. The Fact Book is organized as follows: (1) Overview section - summary tables which indicate national involvement in nuclear reactor, fuel cycle, and waste management development activities; (2) national summaries - a section for each country which summarizes nuclear policy, describes organizational relationships and provides addresses, names of key personnel, and facilities information; (3) international agencies - a section for each of the international agencies which has significant fuel cycle involvement; (4) energy supply and demand - summary tables, including nuclear power projections; (5) fuel cycle - summary tables; and (6) travel aids international dialing instructions, international standard time chart, passport and visa requirements, and currency exchange rate

International Nuclear Fuel Cycle Fact Book. Revision 5

Energy Technology Data Exchange (ETDEWEB)

Harmon, K.M.; Lakey, L.T.; Leigh, I.W.; Jeffs, A.G.

1985-01-01

This Fact Book has been compiled in an effort to provide: (1) an overview of worldwide nuclear power and fuel cycle programs; and (2) current data concerning fuel cycle and waste management facilities, R and D programs, and key personnel in countries other than the United States. Additional information on each country's program is available in the International Source Book: Nuclear Fuel Cycle Research and Development, PNL-2478, Rev. 2. The Fact Book is organized as follows: (1) Overview section - summary tables which indicate national involvement in nuclear reactor, fuel cycle, and waste management development activities; (2) national summaries - a section for each country which summarizes nuclear policy, describes organizational relationships and provides addresses, names of key personnel, and facilities information; (3) international agencies - a section for each of the international agencies which has significant fuel cycle involvement; (4) energy supply and demand - summary tables, including nuclear power projections; (5) fuel cycle - summary tables; and (6) travel aids international dialing instructions, international standard time chart, passport and visa requirements, and currency exchange rate.

International nuclear fuel cycle fact book. Revision 4

Energy Technology Data Exchange (ETDEWEB)

Harmon, K.M.; Lakey, L.T.; Leigh, I.W.

1984-03-01

This Fact Book has been compiled in an effort to provide (1) an overview of worldwide nuclear power and fuel cycle programs and (2) current data concerning fuel cycle and waste management facilities, R and D programs, and key personnel in countries other than the United States. Additional information on each country's program is available in the International Source Book: Nuclear Fuel Cycle Research and Development, PNL-2478, Rev. 2. The Fact Book is organized as follows: (1) Overview section - summary tables which indicate national involvement in nuclear reactor, fuel cycle, and waste management development activities; (2) national summaries - a section for each country which summarizes nuclear policy, describes organizational relationships and provides addresses, names of key personnel, and facilities information; (3) international agencies - a section for each of the international agencies which has significant fuel cycle involvement; (4) energy supply and demand - summary tables, including nuclear power projections; (5) fuel cycle - summary tables; and (6) travel aids - international dialing instructions, international standard time chart, passport and visa requirements, and currency exchange rate.

International nuclear fuel cycle fact book. Revision 4

International Nuclear Information System (INIS)

Harmon, K.M.; Lakey, L.T.; Leigh, I.W.

1984-03-01

This Fact Book has been compiled in an effort to provide (1) an overview of worldwide nuclear power and fuel cycle programs and (2) current data concerning fuel cycle and waste management facilities, R and D programs, and key personnel in countries other than the United States. Additional information on each country's program is available in the International Source Book: Nuclear Fuel Cycle Research and Development, PNL-2478, Rev. 2. The Fact Book is organized as follows: (1) Overview section - summary tables which indicate national involvement in nuclear reactor, fuel cycle, and waste management development activities; (2) national summaries - a section for each country which summarizes nuclear policy, describes organizational relationships and provides addresses, names of key personnel, and facilities information; (3) international agencies - a section for each of the international agencies which has significant fuel cycle involvement; (4) energy supply and demand - summary tables, including nuclear power projections; (5) fuel cycle - summary tables; and (6) travel aids - international dialing instructions, international standard time chart, passport and visa requirements, and currency exchange rate

Radioactive wastes. Safety of storage facilities

International Nuclear Information System (INIS)

Devillers, Ch.

2001-01-01

A radioactive waste storage facility is designed in a way that ensures the isolation of wastes with respect to the biosphere. This function comprises the damping of the gamma and neutron radiations from the wastes, and the confinement of the radionuclides content of the wastes. The safety approach is based on two time scales: the safety of the insulation system during the main phase of radioactive decay, and the assessment of the radiological risks following this phase. The safety of a surface storage facility is based on a three-barrier concept (container, storage structures, site). The confidence in the safety of the facility is based on the quality assurance of the barriers and on their surveillance and maintenance. The safety of a deep repository will be based on the site quality, on the design and construction of structures and on the quality of the safety demonstration. This article deals with the safety approach and principles of storage facilities: 1 - recall of the different types of storage facilities; 2 - different phases of the life of a storage facility and regulatory steps; 3 - safety and radiation protection goals (time scales, radiation protection goals); 4 - safety approach and principles of storage facilities: safety of the isolation system (confinement system, safety analysis, scenarios, radiological consequences, safety principles), assessment of the radiation risks after the main phase of decay; 5 - safety of surface storage facilities: safety analysis of the confinement system of the Aube plant (barriers, scenarios, modeling, efficiency), evaluation of radiological risks after the main phase of decay; experience feedback of the Manche plant; variants of surface storage facilities in France and abroad (very low activity wastes, mine wastes, short living wastes with low and average activity); 6 - safety of deep geological disposal facilities: legal framework of the French research; international context; safety analysis of the confinement system

The international Facility for Antiproton and Ion Research FAIR: Challenges and Opportunities

International Nuclear Information System (INIS)

Hoehne, C.

2009-01-01

The status of FAIR, the planned 'Facility for Antiproton and Ion Research', is presented in this contribution. FAIR will be a world unique particle accelerator facility to be built as a joint project by - as of today - 16 member countries. FAIR, which is planned for construction adjacent to the GSI site in Germany, is an integrated system of particle accelerators, 2 superconducting synchrotrons and 8 storage rings, which will provide high energy and high intensity beams of ions from hydrogen to uranium with unprecedented quality and in full parallel mode. In addition highest luminosity secondary beams of rare isotopes and beams of antiprotons will be available. FAIR will combine physics research topics from different communities, i.e. nuclear physics, hadron physics, heavy-ion physics, plasma physics, atomic physics and accelerator development. Details of FAIR and the physics projects will be presented in this contribution.

Rockwell International Hot Laboratory decontamination and dismantlement interim progress report 1987-1996

International Nuclear Information System (INIS)

None

1997-01-01

OAK A271 Rockwell International Hot Laboratory decontamination and dismantlement interim progress report 1987-1996. The Rockwell International Hot Laboratory (RIHL) is one of a number of former nuclear facilities undergoing decontamination and decommissioning (D and D) at the Santa Susana Field Laboratory (SSFL). The RIHL facility is in the later stages of dismantlement, with the final objective of returning the site location to its original natural state. This report documents the decontamination and dismantlement activities performed at the facility over the time period 1988 through 1996. At this time, the support buildings, all equipment associated with the facility, and the entire above-ground structure of the primary facility building (Building 020) have been removed. The basement portion of this building and the outside yard areas (primarily asphalt and soil) are scheduled for D and D activities beginning in 1997

Ten years operating experience at the Fast Flux Test Facility: A decade of excellence

International Nuclear Information System (INIS)

Swaim, D.J.; Waldo, J.B.; Farabee, O.A.

1991-07-01

The Fast Flux Test Facility is a 400 MW(t) fast reactor cooled by three sodium loops. The Fast Flux Test Facility is managed by the Westinghouse Hanford Company for the US Department of Energy. The Fast Flux Test Facility was designed and constructed to provide irradiation testing of fuels and materials for the US Department of Energy Liquid Metal Reactor research program. Facility activities have increased to include fusion power materials testing, passive safety testing, isotope production, and international collaboration. 5 figs

Physical protection of facilities and special nuclear materials in france

International Nuclear Information System (INIS)

Jeanpierre, G.

1980-01-01

Physical protection of nuclear facilities and special nuclear materials is subject in France to a national governmental regulation which provides for the basic principles to be taken into account and the minimal level of protection deemed necessary. But the responsibility of implementation is left to the facility management and the resulting decentralization allows for maximum efficiency. All safeguards measures comply with the commitments taken at the international level by the French government

Large-coil-test-facility fault-tree analysis

International Nuclear Information System (INIS)

1982-01-01

An operating-safety study is being conducted for the Large Coil Test Facility (LCTF). The purpose of this study is to provide the facility operators and users with added insight into potential problem areas that could affect the safety of personnel or the availability of equipment. This is a preliminary report, on Phase I of that study. A central feature of the study is the incorporation of engineering judgements (by LCTF personnel) into an outside, overall view of the facility. The LCTF was analyzed in terms of 32 subsystems, each of which are subject to failure from any of 15 generic failure initiators. The study identified approximately 40 primary areas of concern which were subjected to a computer analysis as an aid in understanding the complex subsystem interactions that can occur within the facility. The study did not analyze in detail the internal structure of the subsystems at the individual component level. A companion study using traditional fault tree techniques did analyze approximately 20% of the LCTF at the component level. A comparison between these two analysis techniques is included in Section 7

ASAM - The international programme on application of safety assessment methodologies for near surface radioactive waste disposal facilities

International Nuclear Information System (INIS)

Batandjieva, B.

2002-01-01

The IAEA has launched a new Co-ordinated Research Project (CRP) on Application of Safety Assessment Methodologies for Near Surface Waste Disposal Facilities (ASAM). The CRP will focus on the practical application of the safety assessment methodology, developed under the ISAM programme, for different purposes, such as developing design concepts, licensing, upgrading existing repositories, reassessment of operating disposal facilities. The overall aim of the programme is to assist safety assessors, regulators and other specialists involved in the development and review of safety assessment for near surface disposal facilities in order to achieve transparent, traceable and defendable evaluation of safety of these facilities. (author)

Creep-Fatigue Damage Evaluation of a Model Reactor Vessel and Reactor Internals of Sodium Test Facility according to ASME-NH and RCC-MRx Codes

International Nuclear Information System (INIS)

Lim, Dong-Won; Lee, Hyeong-Yeon; Eoh, Jae-Hyuk; Son, Seok-Kwon; Kim, Jong-Bum; Jeong, Ji-Young

2016-01-01

The objective of the STELLA-2 is to support the specific design approval for PGSFR by synthetic reviews of key safety issues and code validations through the integral effect tests. Due to its high temperature operation in SFRs (and in a testing facility) up to 550 °C, thermally induced creep-fatigue damage is very likely in components including a reactor vessel, reactor internals (interior structures), heat exchangers, pipelines, etc. In this study, structural integrity of the components such as reactor vessel and internals in STELLA-2 has been evaluated against creep-fatigue failures at a concept-design step. As 2D analysis yields far conservative results, a realistic 3D simulation is performed by a commercial software. A design integrity guarding against a creep-fatigue damage failure operating at high temperature was evaluated for the reactor vessel with its internal structure of the STELLA-2. Both the high temperature design codes were used for the evaluation, and results were compared. All the results showed the vessel as a whole is safely designed at the given operating conditions, while the ASME-NH gives a conservative evaluation

Creep-Fatigue Damage Evaluation of a Model Reactor Vessel and Reactor Internals of Sodium Test Facility according to ASME-NH and RCC-MRx Codes

Energy Technology Data Exchange (ETDEWEB)

Lim, Dong-Won; Lee, Hyeong-Yeon; Eoh, Jae-Hyuk; Son, Seok-Kwon; Kim, Jong-Bum; Jeong, Ji-Young [KAERI, Daejeon (Korea, Republic of)

2016-05-15

The objective of the STELLA-2 is to support the specific design approval for PGSFR by synthetic reviews of key safety issues and code validations through the integral effect tests. Due to its high temperature operation in SFRs (and in a testing facility) up to 550 °C, thermally induced creep-fatigue damage is very likely in components including a reactor vessel, reactor internals (interior structures), heat exchangers, pipelines, etc. In this study, structural integrity of the components such as reactor vessel and internals in STELLA-2 has been evaluated against creep-fatigue failures at a concept-design step. As 2D analysis yields far conservative results, a realistic 3D simulation is performed by a commercial software. A design integrity guarding against a creep-fatigue damage failure operating at high temperature was evaluated for the reactor vessel with its internal structure of the STELLA-2. Both the high temperature design codes were used for the evaluation, and results were compared. All the results showed the vessel as a whole is safely designed at the given operating conditions, while the ASME-NH gives a conservative evaluation.

MACS as a tool for international inspections

Energy Technology Data Exchange (ETDEWEB)

Curtiss, J.A.; Indusi, J.P.

1995-08-01

The MACS/ACRS (Managed Access by Controlled Sensing/Access by Controlled Remote Sensing) system is a collection of communication devices, video capability, and distance-measuring equipment which can effectively substitute for the physical presence of a challenge inspector within a facility. The MACS design allows growth of the prototype, developed in response to the Chemical Weapons Convention (CWC), into a versatile device for inspection of sensitive nuclear facilities under other international arrangements, for example the proposed Fissile Material Cutoff Convention. A MACS/ACRS-type system in a standard, international-recognized configuration could resolve sensitive information and safety concerns through providing a means of achieving the goals of an inspection while excluding the inspector. We believe the technology used to develop MACS for the Defense Nuclear Agency, followed by ACRS for the Department of Energy, is universally adaptable for minimally-intrusive managed-access international inspections of sensitive sites.

MACS as a tool for international inspections

International Nuclear Information System (INIS)

Curtiss, J.A.; Indusi, J.P.

1995-01-01

The MACS/ACRS (Managed Access by Controlled Sensing/Access by Controlled Remote Sensing) system is a collection of communication devices, video capability, and distance-measuring equipment which can effectively substitute for the physical presence of a challenge inspector within a facility. The MACS design allows growth of the prototype, developed in response to the Chemical Weapons Convention (CWC), into a versatile device for inspection of sensitive nuclear facilities under other international arrangements, for example the proposed Fissile Material Cutoff Convention. A MACS/ACRS-type system in a standard, international-recognized configuration could resolve sensitive information and safety concerns through providing a means of achieving the goals of an inspection while excluding the inspector. We believe the technology used to develop MACS for the Defense Nuclear Agency, followed by ACRS for the Department of Energy, is universally adaptable for minimally-intrusive managed-access international inspections of sensitive sites

Present status and forecast of T ampersand D facilities

International Nuclear Information System (INIS)

Ko, In-Suk.

1994-01-01

Before the end of the 1970s, because of our marvelous economic growth and industrial development we had made our best efforts to develop more power sources. But from the 1980s, KEPCO has invested for T ampersand D facility of high quality and improved system reliability. The main considerations for T ampersand D expansion are positive investment to improve facilities of the electric company, improvement of the quality of electrical equipment during manufacturing, and bettering the field construction of power facilities. In order to achieve the ultimate goal of supplying high quality electricity, we will try to improve cooperation between our domestic industries, and research institutes, and increase the exchange of international technology

FAIR - Facility, Research Program and Status of the Project

International Nuclear Information System (INIS)

Majka, Z.

2011-01-01

The international Facility for Antiproton and Ion Research (FAIR) in Europe will provide a worldwide science community with a unique and technically innovative accelerator system to perform forefront research in the sciences concerned with the basic structure of matter, and in intersections with other fields. The facility will deliver an extensive range of primary and secondary particle beams from protons and their antimatter partners, antiprotons, to ion beams of all chemical elements up to the heaviest, uranium, with in many respects unique properties and intensities. The paper will include overview of the new facility design and research programs to be carried out there. The current status of the FAIR project will be also presented. (author)

International Interdisciplinary Research Institute Project in Senegal

Science.gov (United States)

Gueye, Paul

2010-02-01

The project of an interdisciplinary research institute in Senegal was initiated in 1993 in Senegal (West Africa) and became a template for a similar project in the US in 1999. Since then, numerous meetings and presentations have been held at various national and international institutions, workshops and conferences. The current development of this partnership includes drafts for a full design of all systems at each facility, as well as the physics, applied health and educational programs to be implemented. The Senegal facility was conceived for scientific capacity building and equally to act as a focal point aimed at using the local scientific expertise. An anticipated outcome would be a contribution to the reduction of an ever-growing brain drain process suffered by the country, and the African continent in general. The development of the project led also to a strong African orientation of the facility: built for international collaboration, it is to be a pan-African endeavor and to serve primarily African countries. The facility received a presidential approval in a 2003 meeting and will develop an interdisciplinary program centered on a strong materials science research which will also allow for the establishment of an advanced analytical (physical chemistry) laboratory. A central part of the facility will be linked to state-of-the art accelerator mass spectrometry, cyclotron and low energy electromagnetic accelerator systems. )

Methods for reducing occupational exposures during the decommissioning of nuclear facilities

International Nuclear Information System (INIS)

1987-01-01

The decommissioning and decontamination of nuclear facilities is a topic of great interest to many Member States of the International Atomic Energy Agency (IAEA) because of the large number of older facilities which have been or soon will be retired from service. This report is a review of the current state of knowledge concerning methods for reducing occupational exposures during the decommissioning of nuclear facilities. This report focuses on water cooled nuclear power plants but, in addition, other major nuclear facilities are briefly discussed to determine how they differ from nuclear power plants in this regard. The information presented should be useful to those responsible for or interested in designing or constructing nuclear facilities or in the planning or implementing of the decommissioning of such installations. 59 refs, 1 tab

DESIGN OF FILL AND FINISH FACILITY FOR ACTIVE PHARMACEUTICAL INGREDIENTS (API

Directory of Open Access Journals (Sweden)

NUUR LAILA KHAIRUDDIN

2016-08-01

Full Text Available Fill and finish operations continue to be one of the most heavily outsourced activities in the biopharmaceutical manufacturing market today. There are a few aspects that need to be consider in outsource activities like logistic, storage condition, facility certification and audit as regulations and standards which the manufacturer should adhere. Risk would be greater and extra care should be taken when outsource from foreign fill and finish facility. Thus, the internal aseptic fill and finish facility with audit checklist will help to minimize the risk during logistic and storage and also minimize the cost for outsource fill and finish facility. The data collections are through survey and conceptual design with simulation as the execution part.

The use of new facility by means internal balance with sting support for wide range Angle of Attack aircraft

Science.gov (United States)

Subagyo; Daryanto, Yanto; Risnawan, Novan

2018-04-01

The development of facilities for the testing of wide range angle of attack aircraft in the wind tunnel at subsonic regime has done and implemented. Development required to meet the test at an angle of attack from -20 ° to 40 °. Testing the wide range angle of attack aircraft with a wide variation of the angle of attack become important needs. This can be done simply by using the sting support-equipped by internal balance to measure the forces and moments component aerodynamics. The results of development and use on the wide range angle of attack aircraft testing are aerodynamics characteristics in the form of the coefficient three components forces and the three components of the moment. A series of test aircraft was successfully carried out and the results are shown in the form of graphs of characteristic of aerodynamics at wind speed 70 m/s.

Stability tests of the Westinghouse coil in the International Fusion Superconducting Magnet Test Facility

International Nuclear Information System (INIS)

Dresner, L.; Fehling, D.T.; Lubell, M.S.; Lue, J.W.; Luton, J.N.; McManamy, T.J.; Shen, S.S.; Wilson, C.T.

1987-09-01

The Westinghouse coil is one of three forced-flow coils in the six-coil toroidal array of the International Fusion Superconducting Magnet Test Facility at Oak Ridge National Laboratory. It is wound with an 18-kA, Nb 3 Sn/Cu, cable-in-conduit superconductor structurally supported by aluminum plates and cooled by 4-K, 15-atm supercritical helium. The coil is instrumented to permit measurement of helium temperature, pressure, and flow rate; structure temperature and strain; field; and normal zone voltage. A resistive heater has been installed to simulate nuclear heating, and inductive heaters have been installed to facilitate stability testing. The coil has been tested both individually and in the six-coil array. The tests covered charging to full design current and field, measuring the current-sharing threshold temperature using the resistive heaters, and measuring the stability margin using the pulsed inductive heaters. At least one section of the conductor exhibits a very broad resistive transition (resistive transition index = 4). The broad transition, though causing the appearance of voltage at relatively low temperatures, does not compromise the stability margin of the coil, which was greater than 1.1 J/cm 3 of strands. In another, nonresistive location, the stability margin was between 1.7 and 1.9 J/cm 3 of strands. The coil is completely stable in operation at 100% design current in both the single- and six-coil modes

Oak Ridge rf Test Facility

International Nuclear Information System (INIS)

Gardner, W.L.; Hoffman, D.J.; McCurdy, H.C.; McManamy, T.J.; Moeller, J.A.; Ryan, P.M.

1985-01-01

The rf Test Facility (RFTF) of Oak Ridge National Laboratory (ORNL) provides a national facility for the testing and evaluation of steady-state, high-power (approx.1.0-MW) ion cyclotron resonance heating (ICRH) systems and components. The facility consists of a vacuum vessel and two fully tested superconducting development magnets from the ELMO Bumpy Torus Proof-of-Principle (EBT-P) program. These are arranged as a simple mirror with a mirror ratio of 4.8. The axial centerline distance between magnet throat centers is 112 cm. The vacuum vessel cavity has a large port (74 by 163 cm) and a test volume adequate for testing prototypic launchers for Doublet III-D (DIII-D), Tore Supra, and the Tokamak Fusion Test Reactor (TFTR). Attached to the internal vessel walls are water-cooled panels for removing the injected rf power. The magnets are capable of generating a steady-state field of approx.3 T on axis in the magnet throats. Steady-state plasmas are generated in the facility by cyclotron resonance breakdown using a dedicated 200-kW, 28-GHz gyrotron. Available rf sources cover a frequency range of 2 to 200 MHz at 1.5 kW and 3 to 18 MHz at 200 kW, with several sources at intermediate parameters. Available in July 1986 will be a >1.0-MW, cw source spanning 40 to 80 MHz. 5 figs

Underground Facilities, Technological Challenges

CERN Document Server

Spooner, N

2010-01-01

This report gives a summary overview of the status of international under- ground facilities, in particular as relevant to long-baseline neutrino physics and neutrino astrophysics. The emphasis is on the technical feasibility aspects of creating the large underground infrastructures that will be needed in the fu- ture to house the necessary detectors of 100 kton to 1000 kton scale. There is great potential in Europe to build such a facility, both from the technical point of view and because Europe has a large concentration of the necessary engi- neering and geophysics expertise. The new LAGUNA collaboration has made rapid progress in determining the feasibility for a European site for such a large detector. It is becoming clear in fact that several locations are technically fea- sible in Europe. Combining this with the possibility of a new neutrino beam from CERN suggests a great opportunity for Europe to become the leading centre of neutrino studies, combining both neutrino astrophysics and neutrino beam stu...

Nuclear Safety Research and Facilities Department. Annual report 1999

International Nuclear Information System (INIS)

Majborn, B.; Damkjaer, A.; Hedemann Jensen, P.; Nielsen, S.P.; Nonboel, E.

2000-04-01

The report presents a summary of the work of the Nuclear Safety Research and Facilities Department in 1999. The department's research and development activities were organized in two research programmes: 'Radiation Protection and Reactor Safety' and 'Radioecology and Tracer Studies'. The nuclear facilities operated by the department include the research reactor DR 3, the Isotope Laboratory, the Waste Management Plant, and the educational reactor DR 1. Lists of staff and publications are included together with a summary of the staff's participation in national and international committees. (au)

Description and Results: Antenna Measurement Facility Comparisons [Measurements Corner

DEFF Research Database (Denmark)

Alberica Saporetti, Maria; Foged, Lars; Sierra Castañer, Manuel

2017-01-01

In recent years, formalized facility comparison activities have become important for the documentation and validation of laboratory proficiency and competence and mandatory for achieving accreditation such as that of the International Organization for Standardization (ISO) 17025 or similar...... for Antennas (VISTA) IC1102, including still ongoing campaigns [3]-[5]. Results of these activities have led to improvements in antenna measurement procedures and protocols in facilities and standards [6], [7]. Due to the direct benefits available to the participants, the activities have been very successful...

Nuclear Safety Research and Facilities Department annual report 1997

International Nuclear Information System (INIS)

Majborn, B.; Aarkrog, A.; Brodersen, K.

1998-04-01

The report presents a summary of the work of the Nuclear Safety Research and Facilities Department in 1997. The department's research and development activities were organized in four research programmes: Reactor Safety, Radiation protection, Radioecology, and Radioanalytical Chemistry. The nuclear facilities operated by the department include the research reactor DR3, the Isotope Laboratory, the Waste Treatment Plant, and the educational reactor DR1. Lists of staff and publications are included together with a summary of the staff's participation in national and international committees. (au)

Nuclear Safety Research and Facilities Department annual report 1998

International Nuclear Information System (INIS)

Majborn, B.; Brodersen, K.; Damkjaer, A.; Hedemann Jensen, P.; Nielsen, S.P.; Nonboel, E.

1999-04-01

The report present a summary of the work of the Nuclear Safety Research and Facilities Department in 1998. The department's research and development activities were organized in two research programmes: 'Radiation Protection and Reactor Safety' and 'Radioecology and Tracer Studies'. The nuclear facilities operated by the department include the research reactor DR3, the Isotope Laboratory, the Waste Treatment plant, and the educational reactor DR1. Lsits of staff and publications are included together with a summary of the staff's participation in national and international committees. (au)

NPP safety and personnel training. XII International conference. Abstracts

International Nuclear Information System (INIS)

2011-01-01

The 12th International conference NPP Safety and Personnel Training took place in Obninsk, October 4-7, 2011. The issues of nuclear technologies safety are considered.The problems of life-cycle management of nuclear facilities are discussed. The criteria of assessment of physical protection systems of nuclear facilities are presented [ru

Overview of the IFMIF test facility design in IFMIF/EVEDA phase

International Nuclear Information System (INIS)

Tian, Kuo; Abou-Sena, Ali; Arbeiter, Frederik; García, Ángela; Gouat, Philippe; Heidinger, Roland; Heinzel, Volker; Ibarra, Ángel; Leysen, Willem; Mas, Avelino; Mittwollen, Martin; Möslang, Anton; Theile, Jürgen; Yamamoto, Michiyoshi; Yokomine, Takehiko

2015-01-01

Highlights: • This paper summarizes the current design status of IFMIF EVEDA test facility. • The principle functions of the test facility and key components are described. • The brief specifications of the systems and key components are addressed. - Abstract: The test facility (TF) is one of the three major facilities of the International Fusion Material Irradiation Facility (IFMIF). Engineering designs of TF main systems and key components have been initiated and developed in the IFMIF EVEDA (Engineering Validation and Engineering Design Activities) phase since 2007. The related work covers the designs of a test cell which is the meeting point of the TF and accelerator facility and lithium facility, a series of test modules for experiments under different irradiation conditions, an access cell to accommodate remote handling systems, four test module handling cells for test module processing and assembling, and test facility ancillary systems for engineering support on energy, media, and control infrastructure. This paper summarizes the principle functions, brief specifications, and the current design status of the above mentioned IFMIF TF systems and key components.

Practices on nuclear security and international cooperation

International Nuclear Information System (INIS)

Shen Ning

2009-01-01

Full text: Nuclear terrorism has been a great threat against the safety and security of the world. It has been reached the consensus by international community to strengthen the nuclear security regime to protect the nuclear and other radiological materials and related facilities. Protection of the security of nuclear and other radiological materials in use, storage and transport and related facilities is always a important issue faced by each country and it depends on the technologies, funds and human resources can be utilized. As nuclear technology has been widely used in different area, China competent authorities have issued a series of regulations, implementation rules and guidelines on security of nuclear and radioactive materials and related facilities. China supports and has taken an active part in the international efforts to strengthen the international nuclear security regime to combat nuclear terrorism. China has paid great importance on international cooperations on nuclear security with IAEA and other countries. More than 10 various national workshops and training courses on nuclear security and physical protection were delivered per year, which provided a communication platform for Chinese facility operators and managers to know the international technology-development and share the research achievements. In cooperation with the IAEA, China has held a great number of regional and national training courses on physical protection and nuclear security since 1998. Different types of training, such as training on awareness, Design Basis Threat (DBT), physical security system design, equipments operation and vulnerability analysis, benefited the administrators, facility operators, engineers and technical staff in charge of physical security system design, operation and maintenance from China and regional countries. Under the framework of the bilateral agreement on Peaceful Use of Nuclear Technology (PUNT), China and U.S. jointly conducted a Technical Demo

International power opportunities

International Nuclear Information System (INIS)

Moon, A.

1995-01-01

Key factors in international development were discussed, using TransAlta Energy Corporation as an example. Trans-Alta is a company generating 4,500 MW of electricity from coal, hydro and natural gas. It has operating facilities in Canada, Argentina and New Zealand, including extensive coal mining interests in Canada. The climate for international opportunities in the energy field were judged to be very good in view of the projected requirement for some 900,000 MW of new power generation in different parts of the world by the year 2003. The five key factors identified for international power development were: (1) using core skills to add value, (2) have a long-term focus, (3) focus on specific countries and selected regions, (4) develop strong relationships with local partners, and (5) develop appropriate projects. 2 figs

International Atomic Energy Agency use of facility calorimeters for safeguards purposes

International Nuclear Information System (INIS)

McRae, L.P.; Delegard, C.H.; Hamilton, R.A.; Westsik, G.A.; Moriarty, T.F.; Lemaire, R.J.

1996-01-01

The International Atomic Energy Agency is performing nuclear materials safeguards on an inventory of pure and scrap plutonium oxide powder materials held in Vault 3 of the Plutonium Finishing Plant, operated by the Westinghouse Hanford Company for the US Department of Energy at the Hanford Site in Washington State. The International Atomic Energy Agency uses qualitative and quantitative techniques to verify the presence and quantity of the nuclear materials under safeguards. The Agency uses weighing, sampling, and destructive analyses to obtain the most accurate verification measurements of containers of plutonium powders. In contrast, the plant operator generally uses non-destructive plutonium assay based on gamma spectrometry and calorimetry for its most accurate plutonium powder container measurements. Recent results have shown that the operator''s calorimeter system achieves measurement variabilities comparable with, or better than, the destructive analyses, particularly for scrap. The results are achieved more quickly and economically, with less waste and lower radiation exposure and contamination hazard, by calorimetry than by classical destructive analyses. Techniques, including authentication methods, are being jointly developed to permit use of the operator''s calorimeter system for international safeguards purposes. The authentication is to ensure the independence of, and to substantiate the validity of, calorimeter measurements for international safeguards. The authentication methods considered and being developed are discussed

Facilitating Automation Development in Internal Logistics Systems

OpenAIRE

Granlund, Anna

2014-01-01

The internal logistics system includes all activities connected with managing the flow of materials within the physical limits of a facility. This system is an important part of operations in need of increased focus and continuous improvements. Automation is one possible tool with a previously confirmed great potential to improve internal logistics. Despite this great potential and a growing trend of using automation in the area, internal logistics activities are still not automated to the sa...

IAEA wants data, access for two Yongbyon facilities

International Nuclear Information System (INIS)

Anon.

1993-01-01

At a meeting of the Board of Governors of the International Atomic Energy Agency held February 22-25, a resolution was passed calling upon the government of the Democratic People's Republic of Korea (DPRK; more commonly known as North Korea) to respond positively and without delay to IAEA Director General Hans Blix's February 9 request for access to additional information and two additional sites related to North Korea's nuclear energy program. IAEA inspectors had been given access to some of the nuclear facilities in 1992, but early this year the North Korean government refused to let the IAEA see these other facilities

Closed nuclear facilities in Estonia: developments and problems

International Nuclear Information System (INIS)

Realo, E.; Realo, K.

2000-01-01

At present Estonia has no operating nuclear or a radioactive material production facility. As a legacy of the past the country has become responsible for the decommissioning of two large nuclear cycle facilities of the former USSR. Besides limited funding, major problems arise from deficiencies in legislation, expertise, training and research. International co-operation has been of immense importance to overcome the problems, to establish the national radiation protection and radioactive waste management infrastructure and to launch decommissioning and remediation activities. An overview is given on the status and problems. Copyright (2000) Australasian Radiation Protection Society Inc

Conceptual Design of an In-Space Cryogenic Fluid Management Facility

Science.gov (United States)

Willen, G. S.; Riemer, D. H.; Hustvedt, D. C.

1981-01-01

The conceptual design of a Spacelab experiment to develop the technology associated with low gravity propellant management is presented. The proposed facility consisting of a supply tank, receiver tank, pressurization system, instrumentation, and supporting hardware, is described. The experimental objectives, the receiver tank to be modeled, and constraints imposed on the design by the space shuttle, Spacelab, and scaling requirements, are described. The conceptual design, including the general configurations, flow schematics, insulation systems, instrumentation requirements, and internal tank configurations for the supply tank and the receiver tank, is described. Thermal, structural, fluid, and safety and reliability aspects of the facility are analyzed. The facility development plan, including schedule and cost estimates for the facility, is presented. A program work breakdown structure and master program schedule for a seven year program are included.

Current technical issues in international safeguards

International Nuclear Information System (INIS)

Bennett, C.A.

1977-01-01

Safeguards systems, and the associated need for technical and systems development, reflect changing conditions and concerns associated with the nuclear fuel cycle and the safety and security of nuclear materials and facilities. In particular, the implementation of international safeguards has led to the recognition of certain technical issues, both old and new, which are in need of resolution. These are: 1. The grading of nuclear materials and facilities with respect to their relative safeguards significance. 2. The extension and upgrading of safeguards techniques to maintain adequate protection in view of constantly increasing amounts of material to be safeguarded. 3. The balance between safeguards mechanisms based on physical protection and material accounting, and the role of surveillance and containment in each case. 4. The role of information systems as a basis for both analytical feedback and the determination of the factors affecting system effectiveness and their interrelationship. 5. A determination of the degree to which the overall technical effectiveness of international inspection activities can be quantified. Each of these technical issues must be considered in light of the specific objectives of international safeguards, which differ from domestic safeguards in terms of the level of the threat, the safeguards mechanisms available, and the diversion strategies assumed. Their resolution in this international context is essential if the effectiveness and viability of international safeguards are to be maintained

CTBT and the international technical cooperation

International Nuclear Information System (INIS)

Zhang Lixing

1999-01-01

Having in mind the basic aim of the CTBTO this presentation covers the fields of international co-operation as one of the most important and the cooperation of China and some International research and development institutions concerning the related subjects. One of the most important among international organizations being the IAEA, detailed list of general circumstances in the Chinese cooperation with IAEA is presented. It covers nuclear power plants construction and operation, safety of nuclear facilities, nuclear fuel cycle, radiation protection and waste management, industrial application, agricultural application, human health, fundamental research and information dissemination

Technical Meeting on Existing and Proposed Experimental Facilities for Fast Neutron Systems. Presentations

International Nuclear Information System (INIS)

2013-01-01

The objective of the TM on “Existing and proposed experimental facilities for fast neutron systems” is threefold: first, it is intended for presenting and exchanging information about existing and planned experimental facilities in support of the development of innovative fast neutron systems; second, it will allow to create a catalogue of existing and planned experimental facilities currently operated/developed within national or international fast reactors programmes; third, once a clear picture of the existing experimental infrastructures is defined, new experimental facilities will be discussed and proposed, on the basis of the identified R&D needs

Upgrading safety systems of industrial irradiation facilities

International Nuclear Information System (INIS)

Gomes, R.S.; Gomes, J.D.R.L.; Costa, E.L.C.; Costa, M.L.L.; Thomé, Z.D.

2017-01-01

The first industrial irradiation facility in operation in Brazil was designed in the 70s. Nowadays, twelve commercial and research facilities are in operation and two already decommissioned. Minor modifications and upgrades, as sensors replacement, have been introduced in these facilities, in order to reduce the technological gap in the control and safety systems. The safety systems are designed in agreement with the codes and standards at the time. Since then, new standards, codes and recommendations, as well as lessons learned from accidents, have been issued by various international committees or regulatory bodies. The rapid advance of the industry makes the safety equipment used in the original construction become obsolete. The decreasing demand for these older products means that they are no longer produced, which can make it impossible or costly to obtain spare parts and the expansion of legacy systems to include new features. This work aims to evaluate existing safety systems at Brazilian irradiation facilities, mainly the oldest facilities, taking into account the recommended IAEA's design requirements. Irrespective of the fact that during its operational period no event with victims have been recorded in Brazilian facilities, and that the regulatory inspections do not present any serious deviations regarding the safety procedures, it is necessary an assessment of safety system with the purpose of bringing their systems to 'the state of the art', avoiding their rapid obsolescence. This study has also taken into account the knowledge, concepts and solutions developed to upgrading safety system in irradiation facilities throughout the world. (author)

Upgrading safety systems of industrial irradiation facilities

Energy Technology Data Exchange (ETDEWEB)

Gomes, R.S.; Gomes, J.D.R.L.; Costa, E.L.C.; Costa, M.L.L., E-mail: rogeriog@cnen.gov.br, E-mail: jlopes@cnen.gov.br, E-mail: evaldo@cnen.gov.br, E-mail: mara@cnen.gov.br [Comissão Nacional de Energia Nuclear (CNEN), Rio de Janeiro, RJ (Brazil). Diretoria de Radioproteção e Segurança Nuclear; Thomé, Z.D., E-mail: zielithome@gmail.com [Instituto Militar de Engenharia (IME), Rio de Janeiro, RJ (Brazil). Seção de Engenharia Nuclear

2017-07-01

The first industrial irradiation facility in operation in Brazil was designed in the 70s. Nowadays, twelve commercial and research facilities are in operation and two already decommissioned. Minor modifications and upgrades, as sensors replacement, have been introduced in these facilities, in order to reduce the technological gap in the control and safety systems. The safety systems are designed in agreement with the codes and standards at the time. Since then, new standards, codes and recommendations, as well as lessons learned from accidents, have been issued by various international committees or regulatory bodies. The rapid advance of the industry makes the safety equipment used in the original construction become obsolete. The decreasing demand for these older products means that they are no longer produced, which can make it impossible or costly to obtain spare parts and the expansion of legacy systems to include new features. This work aims to evaluate existing safety systems at Brazilian irradiation facilities, mainly the oldest facilities, taking into account the recommended IAEA's design requirements. Irrespective of the fact that during its operational period no event with victims have been recorded in Brazilian facilities, and that the regulatory inspections do not present any serious deviations regarding the safety procedures, it is necessary an assessment of safety system with the purpose of bringing their systems to 'the state of the art', avoiding their rapid obsolescence. This study has also taken into account the knowledge, concepts and solutions developed to upgrading safety system in irradiation facilities throughout the world. (author)

Technical Meeting on Existing and Proposed Experimental Facilities for Fast Neutron Systems. Working Material

International Nuclear Information System (INIS)

2013-01-01

The objective of the TM on “Existing and proposed experimental facilities for fast neutron systems” was threefold: 1) presenting and exchanging information about existing and planned experimental facilities in support of the development of innovative fast neutron systems; 2) allow creating a catalogue of existing and planned experimental facilities currently operated/developed within national or international fast reactors programmes; 3) once a clear picture of the existing experimental infrastructures is defined, new experimental facilities are discussed and proposed, on the basis of the identified R&D needs

Health facility committees and facility management - exploring the nature and depth of their roles in Coast Province, Kenya

Directory of Open Access Journals (Sweden)

Kabare Margaret

2011-09-01

Full Text Available Abstract Background Community participation has been emphasized internationally as a way of enhancing accountability, as well as a means to enhance health goals in terms of coverage, access and effective utilization. In rural health facilities in Kenya, initiatives to increase community accountability have focused on Health Facility Committees (HFCs. In Coast Province the role of HFCs has been expanded with the introduction of direct funding of rural facilities. We explored the nature and depth of managerial engagement of HFCs at the facility level in two rural districts in this Coastal setting, and how this has contributed to community accountability Methods We conducted structured interviews with the health worker in-charge and with patients in 30 health centres and dispensaries. These data were supplemented with in-depth interviews with district managers, and with health workers and HFC members in 12 health centres and dispensaries. In-depth interviews with health workers and HFC members included a participatory exercise to stimulate discussion of the nature and depth of their roles in facility management. Results HFCs were generally functioning well and played an important role in facility operations. The breadth and depth of engagement had reportedly increased after the introduction of direct funding of health facilities which allowed HFCs to manage their own budgets. Although relations with facility staff were generally good, some mistrust was expressed between HFC members and health workers, and between HFC members and the broader community, partially reflecting a lack of clarity in HFC roles. Moreover, over half of exit interviewees were not aware of the HFC's existence. Women and less well-educated respondents were particularly unlikely to know about the HFC. Conclusions There is potential for HFCs to play an active and important role in health facility management, particularly where they have control over some facility level resources

Health facility committees and facility management - exploring the nature and depth of their roles in Coast Province, Kenya.

Science.gov (United States)

Goodman, Catherine; Opwora, Antony; Kabare, Margaret; Molyneux, Sassy

2011-09-22

Community participation has been emphasized internationally as a way of enhancing accountability, as well as a means to enhance health goals in terms of coverage, access and effective utilization. In rural health facilities in Kenya, initiatives to increase community accountability have focused on Health Facility Committees (HFCs). In Coast Province the role of HFCs has been expanded with the introduction of direct funding of rural facilities. We explored the nature and depth of managerial engagement of HFCs at the facility level in two rural districts in this Coastal setting, and how this has contributed to community accountability We conducted structured interviews with the health worker in-charge and with patients in 30 health centres and dispensaries. These data were supplemented with in-depth interviews with district managers, and with health workers and HFC members in 12 health centres and dispensaries. In-depth interviews with health workers and HFC members included a participatory exercise to stimulate discussion of the nature and depth of their roles in facility management. HFCs were generally functioning well and played an important role in facility operations. The breadth and depth of engagement had reportedly increased after the introduction of direct funding of health facilities which allowed HFCs to manage their own budgets. Although relations with facility staff were generally good, some mistrust was expressed between HFC members and health workers, and between HFC members and the broader community, partially reflecting a lack of clarity in HFC roles. Moreover, over half of exit interviewees were not aware of the HFC's existence. Women and less well-educated respondents were particularly unlikely to know about the HFC. There is potential for HFCs to play an active and important role in health facility management, particularly where they have control over some facility level resources. However, to optimise their contribution, efforts are needed to

Criteria, standards and policies regarding decommissioning of nuclear facilities

International Nuclear Information System (INIS)

Detilleux, E.; Lennemann, W.

1977-01-01

The paper discusses the decontamination and decommissioning experiences encountered at the Eurochemic fuel reprocessing plant, their implications and the knowledge gained from these experiences. It includes the results of technical reviews made by the Nuclear Energy Agency of OECD and the International Atomic Energy Agency regarding decommissioning nuclear facilities. The conlusions which are presented should weigh heavily in the considerations of the national authorities involved in regulating nuclear power programmes. The paper notes the special planning that should be arranged between those responsible for the nuclear facility and competent public authorities who jointly should make a realistic determination of the eventual disposition of the nuclear facility, even before it is built. Recommendations cover the responsibilities of nuclear plant entrepreneurs, designers, operators, and public and regulatory authorities [fr

Test facilities for radioactive material transport packages (AEA Technology plc, Winfrith,UK)

International Nuclear Information System (INIS)

Gillard, J.E.

2001-01-01

Transport containers for radioactive materials are tested to demonstrate compliance with national and international standards. Transport package design, testing, assessment and approval requires a wide range of skills and facilities. The comprehensive capability of AEA Technology in these areas is described. The facilities described include drop-test cranes and targets (up to 700 tonne); pool fires, furnaces and rigs for thermal tests, including heat dissipation on prototype flasks; shielding facilities; criticality simulations and leak test techniques. These are illustrated with photographs demonstrating the comprehensive nature of package testing services supplied to customers. (author)

Test facilities for radioactive material transport packages (AEA Technology plc, Winfrith,UK)

Energy Technology Data Exchange (ETDEWEB)

Gillard, J.E

2001-07-01

Transport containers for radioactive materials are tested to demonstrate compliance with national and international standards. Transport package design, testing, assessment and approval requires a wide range of skills and facilities. The comprehensive capability of AEA Technology in these areas is described. The facilities described include drop-test cranes and targets (up to 700 tonne); pool fires, furnaces and rigs for thermal tests, including heat dissipation on prototype flasks; shielding facilities; criticality simulations and leak test techniques. These are illustrated with photographs demonstrating the comprehensive nature of package testing services supplied to customers. (author)

Solid radioactive waste processing facility of the NPP Leningrad

International Nuclear Information System (INIS)

Weichard, Swetlana

2008-01-01

On behalf of the Russian Company Rosenergoatom NUKEM Technologies GmbH is planning and constructing a complete facility for the processing of solid low- and medium-active radioactive wastes. The NPP Leningrad comprises 4 units of RBMK-1000 reactors, the plant life has been extended by 15 years, the first unit is to be decommissioned in 2018. The construction of four new units is planned. NUKEM is in charge of planning, manufacture, construction and startup of the following facilities: sorting, internal transport, combustion and waste gas cleaning, emission surveillance, compacting, packaging and radiological measurement.

Nuclear Safety Research and Facilities Department. Annual report 1999

Energy Technology Data Exchange (ETDEWEB)

Majborn, B.; Damkjaer, A.; Hedemann Jensen, P.; Nielsen, S.P.; Nonboel, E. [eds.

2000-04-01

The report presents a summary of the work of the Nuclear Safety Research and Facilities Department in 1999. The department's research and development activities were organized in two research programmes: 'Radiation Protection and Reactor Safety' and 'Radioecology and Tracer Studies'. The nuclear facilities operated by the department include the research reactor DR 3, the Isotope Laboratory, the Waste Management Plant, and the educational reactor DR 1. Lists of staff and publications are included together with a summary of the staff's participation in national and international committees. (au)

Nuclear Safety Research and Facilities Department annual report 1999

DEFF Research Database (Denmark)

Majborn, B.; Damkjær, A.; Jensen, Per Hedemann

2000-01-01

The report presents a summary of the work of the Nuclear Safety Research and Facilities Department in 1999. The department´s research and development activities were organized in two research programmes: "Radiation Protection and Reactor Safety" and"Radioecology and Tracer Studies". The nuclear...... facilities operated by the department include the research reactor DR 3, the Isotope Laboratory, the Waste Management Plant, and the educational reactor DR 1. Lists of staff and publications are includedtogether with a summary of the staff´s participation in national and international committees....

Nuclear Safety Research and Facilities Department annual report 1997

Energy Technology Data Exchange (ETDEWEB)

Majborn, B.; Aarkrog, A.; Brodersen, K. [and others

1998-04-01

The report presents a summary of the work of the Nuclear Safety Research and Facilities Department in 1997. The department`s research and development activities were organized in four research programmes: Reactor Safety, Radiation protection, Radioecology, and Radioanalytical Chemistry. The nuclear facilities operated by the department include the research reactor DR3, the Isotope Laboratory, the Waste Treatment Plant, and the educational reactor DR1. Lists of staff and publications are included together with a summary of the staff`s participation in national and international committees. (au) 11 tabs., 39 ills.; 74 refs.

Nuclear Safety Research and Facilities Department annual report 1998

Energy Technology Data Exchange (ETDEWEB)

Majborn, B.; Brodersen, K.; Damkjaer, A.; Hedemann Jensen, P.; Nielsen, S.P.; Nonboel, E

1999-04-01

The report present a summary of the work of the Nuclear Safety Research and Facilities Department in 1998. The department`s research and development activities were organized in two research programmes: `Radiation Protection and Reactor Safety` and `Radioecology and Tracer Studies`. The nuclear facilities operated by the department include the research reactor DR3, the Isotope Laboratory, the Waste Treatment plant, and the educational reactor DR1. Lsits of staff and publications are included together with a summary of the staff`s participation in national and international committees. (au)

Nuclear Safety Research and Facilities department annual report 1996

International Nuclear Information System (INIS)

Majborn, B.; Brodersen, K.; Damkjaer, A.; Floto, H.; Heydorn, K.; Oelgaard, P.L.

1997-04-01

The report presents a summary of the work of the Nuclear Safety Research and Facilities Department in 1996. The Department's research and development activities are organized in three research programmes: Radiation Protection, Reactor Safety, and Radioanalytical Chemistry. The nuclear facilities operated by the department include the Research Reactor DR3, the Isotope Laboratory, the Waste Treatment Plant, and the Educational Reactor DR1. Lists of staff and publications are included together with a summary of the staff's participation in national and international committees. (au) 2 tabs., 28 ills

Decommissioning of Medical, Industrial and Research Facilities. Safety Guide

International Nuclear Information System (INIS)

2010-01-01

Radioactive waste is produced in the generation of nuclear power and the use of radioactive materials in industry, research and medicine. The importance of the safe management of radioactive waste for the protection of human health and the environment has long been recognized, and considerable experience has been gained in this field. The IAEA's Radioactive Waste Safety Standards Programme aimed at establishing a coherent and comprehensive set of principles and requirements for the safe management of waste and formulating the guidelines necessary for their application. This is accomplished within the IAEA Safety Standards Series in an internally consistent set of publications that reflect an international consensus. The publications will provide Member States with a comprehensive series of internationally agreed publications to assist in the derivation of, and to complement, national criteria, standards and practices. The Safety Standards Series consists of three categories of publications: Safety Fundamentals, Safety Requirements and Safety Guides. With respect to the Radioactive Waste Safety Standards Programme, the set of publications is currently undergoing review to ensure a harmonized approach throughout the Safety Standards Series. This Safety Guide addresses the subject of decommissioning of medical, industrial and research facilities where radioactive materials and sources are produced, received, used and stored. It is intended to provide guidance to national authorities and operating organizations, particularly to those in developing countries (as such facilities are predominant in these countries), for the planning and safe management of the decommissioning of such facilities. The Safety Guide has been prepared through a series of Consultants meetings and a Technical Committee meeting

Decommissioning of medical, industrial and research facilities. Safety guide

International Nuclear Information System (INIS)

2005-01-01

Radioactive waste is produced in the generation of nuclear power and the use of radioactive materials in industry, research and medicine. The importance of the safe management of radioactive waste for the protection of human health and the environment has long been recognized, and considerable experience has been gained in this field. The IAEA's Radioactive Waste Safety Standards Programme aimed at establishing a coherent and comprehensive set of principles and requirements for the safe management of waste and formulating the guidelines necessary for their application. This is accomplished within the IAEA Safety Standards Series in an internally consistent set of publications that reflect an international consensus. The publications will provide Member States with a comprehensive series of internationally agreed publications to assist in the derivation of, and to complement, national criteria, standards and practices. The Safety Standards Series consists of three categories of publications: Safety Fundamentals, Safety Requirements and Safety Guides. With respect to the Radioactive Waste Safety Standards Programme, the set of publications is currently undergoing review to ensure a harmonized approach throughout the Safety Standards Series. This Safety Guide addresses the subject of decommissioning of medical, industrial and research facilities where radioactive materials and sources are produced, received, used and stored. It is intended to provide guidance to national authorities and operating organizations, particularly to those in developing countries (as such facilities are predominant in these countries), for the planning and safe management of the decommissioning of such facilities. The Safety Guide has been prepared through a series of Consultants meetings and a Technical Committee meeting

PACTEL and PWR PACTEL Test Facilities for Versatile LWR Applications

Directory of Open Access Journals (Sweden)

Virpi Kouhia

2012-01-01

Full Text Available This paper describes construction and experimental research activities with two test facilities, PACTEL and PWR PACTEL. The PACTEL facility, comprising of reactor pressure vessel parts, three loops with horizontal steam generators, a pressurizer, and emergency core cooling systems, was designed to model the thermal-hydraulic behaviour of VVER-440-type reactors. The facility has been utilized in miscellaneous applications and experiments, for example, in the OECD International Standard Problem ISP-33. PACTEL has been upgraded and modified on a case-by-case basis. The latest facility configuration, the PWR PACTEL facility, was constructed for research activities associated with the EPR-type reactor. A significant design basis is to utilize certain parts of PACTEL, and at the same time, to focus on a proper construction of two new loops and vertical steam generators with an extensive instrumentation. The PWR PACTEL benchmark exercise was launched in 2010 with a small break loss-of-coolant accident test as the chosen transient. Both facilities, PACTEL and PWR PACTEL, are maintained fully operational side by side.

PACTEL and PWR PACTEL Test Facilities for Versatile LWR Applications

International Nuclear Information System (INIS)

Virpi Kouhia, V.; Purhonen, H.; Riikonen, V.; Puustinen, M.; Kyrki-Rajamaki, R.; Vihavainen, J.

2012-01-01

This paper describes construction and experimental research activities with two test facilities, PACTEL and PWR PACTEL. The PACTEL facility, comprising of reactor pressure vessel parts, three loops with horizontal steam generators, a pressurizer, and emergency core cooling systems, was designed to model the thermal-hydraulic behaviour of VVER-440-type reactors. The facility has been utilized in miscellaneous applications and experiments, for example, in the OECD International Standard Problem ISP-33. PACTEL has been upgraded and modified on a case-by-case basis. The latest facility configuration, the PWR PACTEL facility, was constructed for research activities associated with the EPR-type reactor. A significant design basis is to utilize certain parts of PACTEL, and at the same time, to focus on a proper construction of two new loops and vertical steam generators with an extensive instrumentation. The PWR PACTEL benchmark exercise was launched in 2010 with a small break loss-of-coolant accident test as the chosen transient. Both facilities, PACTEL and PWR PACTEL, are maintained fully operational side by side.

Development of High-Level Safety Requirements for a Pyroprocessing Facility

Energy Technology Data Exchange (ETDEWEB)

Seo, Seok Jun; Jo, Woo Jin; You, Gil Sung; Choung, Won Myung; Lee, Ho Hee; Kim, Hyun Min; Jeon, Hong Rae; Ku, Jeong Hoe; Lee, Hyo Jik [KAERI, Daejeon (Korea, Republic of)

2016-05-15

Korea Atomic Energy Research Institute (KAERI) has been developing a pyroproceesing technology to reduce the waste volume and recycle some elements. The pyroprocessing includes several treatment processes which are related with not only radiological and physical but also chemical and electrochemical properties. Thus, it is of importance to establish safety design requirements considering all the aspects of those properties for a reliable pyroprocessing facility. In this study, high-level requirements are presented in terms of not only radiation protection, nuclear criticality, fire protection, and seismic safety but also confinement and chemical safety for the unique characteristics of a pyroprocessing facility. Several high-level safety design requirements such as radiation protection, nuclear criticality, fire protection, seismic, confinement, and chemical processing were presented for a pyroprocessing facility. The requirements must fulfill domestic and international safety technology standards for a nuclear facility. Furthermore, additional requirements should be considered for the unique electrochemical treatments in a pyroprocessing facility.

Advanced reactor experimental facilities

International Nuclear Information System (INIS)

Amri, A.; Papin, J.; Uhle, J.; Vitanza, C.

2010-01-01

for GCR and SFR safety research and developed recommendations as to priorities and options for facility utilisation through international programmes. In particular, the group agreed on the main criteria for priority setting, which was based on: - Relevance of the facility to cover a specific issue. - Uniqueness (e.g. one-of-a-kind for in-pile testing). - Availability for addressing the issue. - Readiness (e.g. staff availability to run it). - Operating cost or construction cost. The group rated those facilities that were costly either to operate or to construct as being ranked high in this category as they were more suitable to host a multilateral cooperative programme than facilities of lower cost which could be supported by one country alone. TAREF members who had proposed facilities were requested to characterise the latter according to the above criteria. Based on this information, conclusions and recommendations were develop

The International Atomic Energy Agency (IAEA) research program to improve safety assessment methodologies for near-surface radioactive waste disposal facilities (ISAM)

International Nuclear Information System (INIS)

Torres-Vidal, C.; Kozak, M.W.

2000-01-01

The International Atomic Energy Agency (IAEA) launched a Coordinated Research Program in November 1997 on Improvement of Safety Assessment Methodologies for Near Surface Radioactive Waste Disposal Facilities (ISAM). The purpose of this paper is to describe the program and its goals, and to describe achievements of the program to date. The main objectives of the ISAM program are outlined. The primary focus of ISAM is on the practical application of safety assessment methodologies. Three kinds of practical situations are being addressed in the program: safety assessments for large vaults typical of those in Western Europe and North America, smaller vaults for medium and industrial wastes typical in eastern Europe and the former Soviet Union, and a proposed borehole technology for disposal of spent sources in low-technology conditions. (author)

Science driving facilities for particle physics

CERN Multimedia

2011-01-01

This week, CERN played host to the 10th ICFA (International Committee for Future Accelerators) seminar, which brought together some 200 scientists, government agency representatives and lab directors from around the world to take the pulse of our field. ICFA seminars take place every three years, and this time the emphasis was on science as the driving force for facilities.   The theme of this year’s seminar could not have been more timely. With austerity the global norm, it is more important than ever for science to point the way to the facilities we need, and for the global community to ensure that those facilities are planned at the global level. The LHC is already a machine for the world, and although CERN’s Member States have carried the bulk of the cost, it would not have been possible without contributions from around the globe. In the US, Fermilab’s focus has moved away from the high-energy frontier to the intensity frontier, which is every bit as impor...

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

International Nuclear Information System (INIS)

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

2006-12-01

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

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

Energy Technology Data Exchange (ETDEWEB)

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

2006-12-15

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

The problems of individual monitoring for internal exposure of monazite storage facility workers

International Nuclear Information System (INIS)

Ekidin, A.; Kirdin, I.; Yarmoshenko, I.; Zhukovsky, M.

2006-01-01

traditionally two situations of internal inhalation exposure by alpha emitting nuclides are considered in radiological protection: occupational exposure due to inhalation of plutonium aerosols; inhalation exposure by 222 Rn daughters in working places and in home. for these situations the problems of radioactive aerosols intake, nuclide dynamics in human body, internal dosimetry, nuclide excretion, monitoring of internal exposure have been investigated in details especially for plutonium inhalation exposure. The results of these studies are presented in details in ICRP Publications and UNSCEAR reports. However there is very specific case in which the special analysis of internal inhalation exposure is need. it is the working places with anomalous, extremely high concentration of thoron ( 220 Rn) daughters. The problems of internal radiation exposure of workers in such working place are the main topic of this publication. (authors)

Research and test facilities required in nuclear science and technology

International Nuclear Information System (INIS)

2009-01-01

Experimental facilities are essential research tools both for the development of nuclear science and technology and for testing systems and materials which are currently being used or will be used in the future. As a result of economic pressures and the closure of older facilities, there are concerns that the ability to undertake the research necessary to maintain and to develop nuclear science and technology may be in jeopardy. An NEA expert group with representation from ten member countries, the International Atomic Energy Agency and the European Commission has reviewed the status of those research and test facilities of interest to the NEA Nuclear Science Committee. They include facilities relating to nuclear data measurement, reactor development, neutron scattering, neutron radiography, accelerator-driven systems, transmutation, nuclear fuel, materials, safety, radiochemistry, partitioning and nuclear process heat for hydrogen production. This report contains the expert group's detailed assessment of the current status of these nuclear research facilities and makes recommendations on how future developments in the field can be secured through the provision of high-quality, modern facilities. It also describes the online database which has been established by the expert group which includes more than 700 facilities. (authors)

Improving the regulation of safety at DOE nuclear facilities. Final report: Appendices

Energy Technology Data Exchange (ETDEWEB)

NONE

1995-12-01

The report strongly recommends that, with the end of the Cold War, safety and health at DOE facilities should be regulated by outside agencies rather than by any regulatory scheme, DOE must maintain a strong internal safety management system; essentially all aspects of safety at DOE`s nuclear facilities should be externally regulated; and existing agencies rather than a new one should be responsible for external regulation.

Improving the regulation of safety at DOE nuclear facilities. Final report: Appendices

International Nuclear Information System (INIS)

1995-12-01

The report strongly recommends that, with the end of the Cold War, safety and health at DOE facilities should be regulated by outside agencies rather than by any regulatory scheme, DOE must maintain a strong internal safety management system; essentially all aspects of safety at DOE's nuclear facilities should be externally regulated; and existing agencies rather than a new one should be responsible for external regulation

Report: EPA Lacks Internal Controls to Prevent Misuse of Emergency Drinking Water Facilities

Science.gov (United States)

Report #11-P-0001, October 12, 2010. EPA cannot accurately assess the risk of public water systems delivering contaminated drinking water from emergency facilities because of limitations in Safe Drinking Water Information System (SDWIS) data management.

Natech accidents at industrial facilities. The case of the Wenchuan earthquake

OpenAIRE

Krausmann , Elisabeth; Cruz , Ana Maria; Affeltranger , Bastien

2009-01-01

International audience; Natural disasters can trigger chemical accidents (so-called Natech accidents) with severe consequences on man or the environment. This work highlights the main characteristics of earthquake-triggered Natechs by describing our insights from a field trip to chemical facilities in the area affected by the 12 May, 2008, Wenchuan earthquake in China. Our preliminary results indicate that damage was most severe in older facilities with masonry and un- or poorly reinforced co...

DESIGN OF FILL AND FINISH FACILITY FOR ACTIVE PHARMACEUTICAL INGREDIENTS (API)

OpenAIRE

NUUR LAILA KHAIRUDDIN; NORLIZA ABD. RAHMAN; NUR SYAFIQAH KAMARUDIN

2016-01-01

Fill and finish operations continue to be one of the most heavily outsourced activities in the biopharmaceutical manufacturing market today. There are a few aspects that need to be consider in outsource activities like logistic, storage condition, facility certification and audit as regulations and standards which the manufacturer should adhere. Risk would be greater and extra care should be taken when outsource from foreign fill and finish facility. Thus, the internal aseptic fill and fin...

Improving the regulation of safety at DOE nuclear facilities. Final report

International Nuclear Information System (INIS)

1995-12-01

The report strongly recommends that, with the end of the Cold War, safety and health at DOE facilities should be regulated by outside agencies rather than by DOE itself. The three major recommendations are: under any regulatory scheme, DOE must maintain a strong internal safety management system; essentially all aspects of safety at DOE's nuclear facilities should be externally regulated; and existing agencies rather than a new one should be responsible for external regulation

Characterization of internal dosimetry practices

International Nuclear Information System (INIS)

Traub, R.J.; Heid, K.R.; Mann, J.C.

1983-01-01

Current practices in internal dosimetry at DOE facilities were evaluated with respect to consistency among DOE Contractors. All aspects of an internal dosimetry program were addressed. Items considered include, but are not necessarily limited to, record systems and ease of information retrieval; ease of integrating internal dose and external dose; modeling systems employed, including ability to modify models depending on excretion data, and verification of computer codes utilized; bioassay procedures, including quality control; and ability to relate air concentration data to individual workers and bioassay data. Feasibility of uranium analysis in solution by laser fluorescence excitation at uranium concentrations of one part per billion was demonstrated

The space station window observational research facility; a high altitude imaging laboratory

International Nuclear Information System (INIS)

Runco, Susan K.; Eppler, Dean B.; Scott, Karen P.

1999-01-01

Earth Science will be one of the major research areas to be conducted on the International Space Station. The facilities from which this research will be accomplished are currently being constructed and will be described in this paper. By April 1999, the International Space Station nadir viewing research window fabrication will be completed and ready for installation. The window will provide a 20 inch (51 cm) diameter clear aperture. The three fused silica panes, which make up the window are fabricated such that the total peak-to-valley wavefront error in transmission through the three panes over any six inch diameter aperture does not exceed λ/7 where the reference wavelength is 632.8 nm. The window will have over 90% transmission between about 400 and 750, above 50% transmission between about 310 nm and 1375 nm and 40% transmission between 1386 nm and 2000 nm. The Window Operational Research Facility (WORF) is designed to accommodate payloads using this research window. The WORF will provide access to the International Space Station utilities such as data links, temperature cooling loops and power. Emphasis has been placed on the factors which will make this facility an optimum platform for conducting Earth science research

Concepts for inventory verification in critical facilities

International Nuclear Information System (INIS)

Cobb, D.D.; Sapir, J.L.; Kern, E.A.; Dietz, R.J.

1978-12-01

Materials measurement and inventory verification concepts for safeguarding large critical facilities are presented. Inspection strategies and methods for applying international safeguards to such facilities are proposed. The conceptual approach to routine inventory verification includes frequent visits to the facility by one inspector, and the use of seals and nondestructive assay (NDA) measurements to verify the portion of the inventory maintained in vault storage. Periodic verification of the reactor inventory is accomplished by sampling and NDA measurement of in-core fuel elements combined with measurements of integral reactivity and related reactor parameters that are sensitive to the total fissile inventory. A combination of statistical sampling and NDA verification with measurements of reactor parameters is more effective than either technique used by itself. Special procedures for assessment and verification for abnormal safeguards conditions are also considered. When the inspection strategies and inventory verification methods are combined with strict containment and surveillance methods, they provide a high degree of assurance that any clandestine attempt to divert a significant quantity of fissile material from a critical facility inventory will be detected. Field testing of specific hardware systems and procedures to determine their sensitivity, reliability, and operational acceptability is recommended. 50 figures, 21 tables

Massachusetts Large Blade Test Facility Final Report

Energy Technology Data Exchange (ETDEWEB)

Rahul Yarala; Rob Priore

2011-09-02

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

New facility shield design criteria

International Nuclear Information System (INIS)

Howell, W.P.

1981-07-01

The purpose of the criteria presented here is to provide standard guidance for the design of nuclear radiation shields thoughout new facilities. These criteria are required to assure a consistent and integrated design that can be operated safely and economically within the DOE standards. The scope of this report is confined to the consideration of radiation shielding for contained sources. The whole body dose limit established by the DOE applies to all doses which are generally distributed throughout the trunk of the body. Therefore, where the whole body is the critical organ for an internally deposited radionuclide, the whole body dose limit applies to the sum of doses received must assure control of the concentration of radionuclides in the building atmosphere and thereby limit the dose from internal sources

Decommissioning of nuclear power facilities

International Nuclear Information System (INIS)

Nosovskij, A.V.; Vasil'chenko, V.N.; Klyuchnikov, A.A.; Yashchenko, Ya.V.

2005-01-01

This is the first manual in Ukraine giving the complete review of the decommissioning process of the nuclear power facilities including the issues of the planning, design documentation development, advanced technology description. On the base of the international and domestic experience, the issues on the radwaste management, the decontamination methods, the equipment dismantling, the remote technology application, and also the costs estimate at decommissioning are considered. The special attention to the personnel safety provision, population and environment at decommissioning process is paid

Facility design consideration for continuous mix production of class 1.3 propellant

Science.gov (United States)

Williamson, K. L.; Schirk, P. G.

1994-01-01

In November of 1989, NASA awarded the Advanced Solid Rocket Motor (ASRM) contract to Lockheed Missiles and Space Company (LMSC) for production of advanced solid rocket motors using the continuous mix process. Aerojet ASRM division (AAD) was selected as the facility operator and RUST International Corporation provided the engineering, procurement, and construction management services. The continuous mix process mandates that the mix and cast facilities be 'close-coupled' along with the premix facilities, creating unique and challenging requirements for the facility designer. The classical approach to handling energetic materials-division into manageable quantities, segregation, and isolation-was not available due to these process requirements and quantities involved. This paper provides a description of the physical facilities, the continuous mix process, and discusses the monitoring and detection techniques used to mitigate hazards and prevent an incident.

Emission Facilities - Erosion & Sediment Control Facilities

Data.gov (United States)

NSGIC Education | GIS Inventory — An Erosion and Sediment Control Facility is a DEP primary facility type related to the Water Pollution Control program. The following sub-facility types related to...

International theme for seaside event.

Science.gov (United States)

Adie, Kate; Whitehorn, Will

2014-05-01

The organisers of this month's HefmA 2014 annual conference and exhibition promise delegates "the opportunity to hear international perspectives on the current issues facing the worldwide 'family' of health estates and facilities professionals". Conference speakers will include a US-based consultant architect discussing 'a transformational change programme which has achieved up to threefold greater throughput using the existing footprint in a US Emergency Department'; the assistant director, Facilities Services, at Health Facilities Scotland, focusing on HFS's work to ensure high training standards and succession planning, former BBC war correspondent, Kate Adie, describing some of the 'extraordinary experiences' of an eventful career, and Will Whitehorn, a former search-and-rescue helicopter crewman, who later became president of 'the world's first commercial spaceline', Virgin Galactic, giving his view on technology's impact in business.

Design and Shielding of Radiotherapy Treatment Facilities; IPEM Report 75, 2nd Edition

Science.gov (United States)

Horton, Patrick; Eaton, David

2017-07-01

Design and Shielding of Radiotherapy Treatment Facilities provides readers with a single point of reference for protection advice to the construction and modification of radiotherapy facilities. The book assembles a faculty of national and international experts on all modalities including megavoltage and kilovoltage photons, brachytherapy and high-energy particles, and on conventional and Monte Carlo shielding calculations. This book is a comprehensive reference for qualified experts and radiation-shielding designers in radiation physics and also useful to anyone involved in the design of radiotherapy facilities.

General problems specific to hot nuclear materials research facilities

International Nuclear Information System (INIS)

Bart, G.

1996-01-01

During the sixties, governments have installed hot nuclear materials research facilities to characterize highly radioactive materials, to describe their in-pile behaviour, to develop and test new reactor core components, and to provide the industry with radioisotopes. Since then, the attitude towards the nuclear option has drastically changed and resources have become very tight. Within the changed political environment, the national research centres have defined new objectives. Given budgetary constraints, nuclear facilities have to co-operate internationally and to look for third party research assignments. The paper discusses the problems and needs within experimental nuclear research facilities as well as industrial requirements. Special emphasis is on cultural topics (definition of the scope of nuclear research facilities, the search for competitive advantages, and operational requirements), social aspects (overageing of personnel, recruitment, and training of new staff), safety related administrative and technical issues, and research needs for expertise and state of the art analytical infrastructure

Sound & Vibration 20 Design Guidelines for Health Care Facilities

CERN Document Server

Tocci, Gregory; Cavanaugh, William

2013-01-01

Sound, vibration, noise and privacy have significant impacts on health and performance. As a result, they are recognized as essential components of effective health care environments. However, acoustics has only recently become a prominent consideration in the design, construction, and operation of healthcare facilities owing to the absence, prior to 2010, of clear and objective guidance based on research and best practices. Sound & Vibration 2.0 is the first publication to comprehensively address this need. Sound & Vibration 2.0 is the sole reference standard for acoustics in health care facilities and is recognized by: the 2010 FGI Guidelines for the Design and Construction of Health Care Facilities (used in 60 countries); the US Green Building Council’s LEED for Health Care (used in 87 countries); The Green Guide for Health Care V2.2; and the International Code Council (2011). Sound & Vibration 2.0 was commissioned by the Facility Guidelines Institute in 2005, written by the Health Care Acous...

Syphilis screening practices in blood transfusion facilities in Ghana

Directory of Open Access Journals (Sweden)

Francis Sarkodie

2016-02-01

Conclusions: Despite international and national recommendations, more than half of the studied health facilities that provide blood transfusions in Ghana are not screening blood donations for syphilis. These data show a considerable mismatch between recommendations and practice, with serious consequences for blood safety and public health.

Fuel-cycle facilities: preliminary safety and environmental information document. Volume VII

Energy Technology Data Exchange (ETDEWEB)

1980-01-01

Information is presented concerning the mining and milling of uranium and thorium; uranium hexafluoride conversion; enrichment; fuel fabrication; reprocessing; storage options; waste disposal options; transportation; heavy-water-production facilities; and international fuel service centers.

Fuel-cycle facilities: preliminary safety and environmental information document. Volume VII

International Nuclear Information System (INIS)

1980-01-01

Information is presented concerning the mining and milling of uranium and thorium; uranium hexafluoride conversion; enrichment; fuel fabrication; reprocessing; storage options; waste disposal options; transportation; heavy-water-production facilities; and international fuel service centers

REPORT OF THE WORKSHOP ON NUCLEAR FACILITY DESIGN INFORMATION EXAMINATION AND VERIFICATION FOR SAFEGUARDS

Energy Technology Data Exchange (ETDEWEB)

Richard Metcalf; Robert Bean

2009-10-01

Executive Summary The International Atomic Energy Agency (IAEA) implements nuclear safeguards and verifies countries are compliant with their international nuclear safeguards agreements. One of the key provisions in the safeguards agreement is the requirement that the country provide nuclear facility design and operating information to the IAEA relevant to safeguarding the facility, and at a very early stage. , This provides the opportunity for the IAEA to verify the safeguards-relevant features of the facility and to periodically ensure that those features have not changed. The national authorities (State System of Accounting for and Control of Nuclear Material - SSAC) provide the design information for all facilities within a country to the IAEA. The design information is conveyed using the IAEA’s Design Information Questionnaire (DIQ) and specifies: (1) Identification of the facility’s general character, purpose, capacity, and location; (2) Description of the facility’s layout and nuclear material form, location, and flow; (3) Description of the features relating to nuclear material accounting, containment, and surveillance; and (4) Description of existing and proposed procedures for nuclear material accounting and control, with identification of nuclear material balance areas. The DIQ is updated as required by written addendum. IAEA safeguards inspectors examine and verify this information in design information examination (DIE) and design information verification (DIV) activities to confirm that the facility has been constructed or is being operated as declared by the facility operator and national authorities, and to develop a suitable safeguards approach. Under the Next Generation Safeguards Initiative (NGSI), the National Nuclear Security Administrations (NNSA) Office of Non-Proliferation and International Security identified the need for more effective and efficient verification of design information by the IAEA for improving international safeguards

COMPUTER ORIENTED FACILITIES OF TEACHING AND INFORMATIVE COMPETENCE

Directory of Open Access Journals (Sweden)

Olga M. Naumenko

2010-09-01

Full Text Available In the article it is considered the history of views to the tasks of education, estimations of its effectiveness from the point of view of forming of basic vitally important competences. Opinions to the problem in different countries, international organizations, corresponding experience of the Ukrainian system of education are described. The necessity of forming of informative competence of future teacher is reasonable in the conditions of application of the computer oriented facilities of teaching at the study of naturally scientific cycle subjects in pedagogical colleges. Prognosis estimations concerning the development of methods of application of computer oriented facilities of teaching are presented.

Conference on the research facilities for future nuclear power engineering

International Nuclear Information System (INIS)

Arkhangel'skij, N.V.

1996-01-01

The activity of the European nuclear society Conference (Belgium, June, 1996) is described. The main topics of 60 presented reports are the following ones: necessity of developing new experimental facilities and their parameters; financing prospects and international cooperation in this field

Perspectives on the International and Internal Nuclear Security Regime

International Nuclear Information System (INIS)

Jang, Sung Soon

2015-01-01

The term, 'Nuclear Security' became more familiar to Korean public after the government hosted 2012 Seoul Nuclear Security Summit. Nuclear Security is prevention of, detection of and response to criminal or intentional unauthorized acts involving or directed at nuclear material, other radioactive material, associated facilities, or associated activities. Nuclear Security includes physical protection, security of radioactive sources, nuclear forensics, nuclear smuggling prevention, border monitoring, and cyber security with regard to nuclear and other radiological materials. This abstract will review recent international trends and discuss the nuclear security regime in the Republic of Korea (ROK). The international Nuclear Security Regime has been strengthened. The upcoming Chicago Summit in 2016 and the entry into force of the Amendment of Convention on Physical Protection of Nuclear Materials (CPPNM) will bring major changes in nuclear security. The Republic of Korea hosted the 2012 Seoul Summit and strengthened domestic regime to meet international standards. The ROK has worked hard to contribute to the international security regime and to establish a robust domestic security regime against terrorist threats. Even if the nuclear security regime is robust, Risk-informed Nuclear Security management should be established to meet international standards and to implement effective as well as an efficient nuclear security regime

Perspectives on the International and Internal Nuclear Security Regime

Energy Technology Data Exchange (ETDEWEB)

Jang, Sung Soon [Korea Nuclear Non-proliferation and Control, Daejeon (Korea, Republic of)

2015-10-15

The term, 'Nuclear Security' became more familiar to Korean public after the government hosted 2012 Seoul Nuclear Security Summit. Nuclear Security is prevention of, detection of and response to criminal or intentional unauthorized acts involving or directed at nuclear material, other radioactive material, associated facilities, or associated activities. Nuclear Security includes physical protection, security of radioactive sources, nuclear forensics, nuclear smuggling prevention, border monitoring, and cyber security with regard to nuclear and other radiological materials. This abstract will review recent international trends and discuss the nuclear security regime in the Republic of Korea (ROK). The international Nuclear Security Regime has been strengthened. The upcoming Chicago Summit in 2016 and the entry into force of the Amendment of Convention on Physical Protection of Nuclear Materials (CPPNM) will bring major changes in nuclear security. The Republic of Korea hosted the 2012 Seoul Summit and strengthened domestic regime to meet international standards. The ROK has worked hard to contribute to the international security regime and to establish a robust domestic security regime against terrorist threats. Even if the nuclear security regime is robust, Risk-informed Nuclear Security management should be established to meet international standards and to implement effective as well as an efficient nuclear security regime.

The international RESPO network

Energy Technology Data Exchange (ETDEWEB)

NONE

1997-12-01

Winrock International, with sponsorship from the Center for Environment of the U.S. Agency for International Development (USAID) and the U.S. Export Council for Renewable Energy (US/ECRE), is building a global network of non-governmental organizations to help catalyze the use of renewable energy technologies for rural energy supply in developing countries. Known as the Renewable Energy Project Support Offices (REPSOs), these in-country facilities are managed by local institutions in coordination with Winrock. REPSOs provide an array of technical and financial support services to help developers identify and evaluate opportunities for renewable energy projects.

Optimal allocation of International Atomic Energy Agency inspection resources

International Nuclear Information System (INIS)

Markin, J.T.

1987-12-01

The Safeguards Department of the International Atomic Energy Agency (IAEA) conducts inspections to assure the peaceful use of a state's nuclear materials and facilities. Because of limited resources for conducting inspections, the careful disposition of inspection effort among these facilities is essential if the IAEA is to attain its safeguards goals. This report describes an optimization procedure for assigning an inspection effort to maximize attainment of IAEA goals. The procedure does not require quantitative estimates of safeguards effectiveness, material value, or facility importance. Instead, the optimization is based on qualitative, relative prioritizations of inspection activities and materials to be safeguarded. This allocation framework is applicable to an arbitrary group of facilities such as a state's fuel cycle, the facilities inspected by an operations division, or all of the facilities inspected by the IAEA

INTEGRITY -- Integrated Human Exploration Mission Simulation Facility

Science.gov (United States)

Henninger, D.; Tri, T.; Daues, K.

It is proposed to develop a high -fidelity ground facil ity to carry out long-duration human exploration mission simulations. These would not be merely computer simulations - they would in fact comprise a series of actual missions that just happen to stay on earth. These missions would include all elements of an actual mission, using actual technologies that would be used for the real mission. These missions would also include such elements as extravehicular activities, robotic systems, telepresence and teleoperation, surface drilling technology--all using a simulated planetary landscape. A sequence of missions would be defined that get progressively longer and more robust, perhaps a series of five or six missions over a span of 10 to 15 years ranging in durat ion from 180 days up to 1000 days. This high-fidelity ground facility would operate hand-in-hand with a host of other terrestrial analog sites such as the Antarctic, Haughton Crater, and the Arizona desert. Of course, all of these analog mission simulations will be conducted here on earth in 1-g, and NASA will still need the Shuttle and ISS to carry out all the microgravity and hypogravity science experiments and technology validations. The proposed missions would have sufficient definition such that definitive requirements could be derived from them to serve as direction for all the program elements of the mission. Additionally, specific milestones would be established for the "launch" date of each mission so that R&D programs would have both good requirements and solid milestones from which to build their implementation plans. Mission aspects that could not be directly incorporated into the ground facility would be simulated via software. New management techniques would be developed for evaluation in this ground test facility program. These new techniques would have embedded metrics which would allow them to be continuously evaluated and adjusted so that by the time the sequence of missions is completed

Secondary limits of exposure in facilities handling uranium

International Nuclear Information System (INIS)

Raghavayya, M.

1999-08-01

Annual limits of exposure and intake for radiation workers in nuclear installations have been recommended by the International Commission on Radiological Protection and the same have been adopted by the Indian Atomic Energy Regulatory Board for all the radionuclides of interest. The prescribed limits cannot be directly used for day to day radiation protection work. Hence secondary limits have to be derived for routine applications. The modeling steps may be simple in some situations and more complicated in some others. The limits recommended are for individual radionuclides. But in facilities handling natural or enriched uranium the radionuclides (isotopes of uranium and its decay products) generally occur together in specific ratios. Derivation of secondary limits has to take this into consideration. The present document is an attempt at deriving the secondary limits required for routine application in facilities handling uranium (Mine, mill, refineries and fuel fabrication etc.). Secondary limits of exposure have been derived in this document for air borne activity, activity in water, surface contamination and internal exposures. (author)

Present status of ESNIT (energy selective neutron irradiation test facility) program

International Nuclear Information System (INIS)

Noda, K.; Ohno, H.; Sugimoto, M.; Kato, Y.; Matsuo, H.; Watanabe, K.; Kikuchi, T.; Sawai, T.; Usui, T.; Oyama, Y.; Kondo, T.

1994-01-01

The present status of technical studies of a high energy neutron irradiation facility, ESNIT (energy selective neutron irradiation test facility), is summarized. Technological survey and feasibility studies of ESNIT have continued since 1988. The results of technical studies of the accelerator, the target and the experimental systems in ESNIT program were reviewed by an International Advisory Committee in February 1993. Recommendations for future R and D on ESNIT program are also summarized in this paper. ((orig.))

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)

International Affairs Programs: The Air Force Versus the Army

Science.gov (United States)

2015-10-01

individual tutoring programs . Additionally RAS personnel are offered regional enhancement studies opportunities at several facilities.48 RAS personnel...AU/ACSC/2015 AIR COMMAND AND STAFF COLLEGE AIR UNIVERSITY INTERNATIONAL AFFAIRS PROGRAMS : THE AIR FORCE VERSUS THE ARMY by Robin L...5 COMPARISON: INTERNATIONAL AFFAIRS PROGRAMS AIR FORCE VERSUS ARMY 8

Managing public acceptance for a new enrichment facility

International Nuclear Information System (INIS)

Boyd, M.

1992-01-01

The Claiborne Enrichment Center has many first associated with it, and a solid nuclear-based community relations experience has been combined with fly-by-the-seat-of-your-pants techniques to successfully introduce a first-of-a-kind facility not only to Louisiana, but also to the US. The project is being developed by Louisiana Energy Services (LES), a limited partnership consisting of Urenco, the European enrichment consortium that operates centrifuge enrichment facilities in the United Kingdom, the Netherlands, and Germany; Fluor Daniel, an internationally known engineering and construction firm; and three utilities - Duke Power, Northern States Power, and Louisiana Power and Light (LP and L). Louisiana Energy will build the nation's first privately owned uranium enrichment facility. It will be the first commercial use of centrifuge technology for enrichment in the US. Some of the community relations challenges the project has had and their solutions are described

Destruction of nuclear energy facilities in war: the problem and the implications

International Nuclear Information System (INIS)

Ramberg, B.

1980-01-01

This book examines current practices, policies, and regulations concerning nuclear energy in the light of potential sabotage. Dr. Ramberg explains clearly, for both the lay reader and the technical community, the vulnerabilities of different sorts of nuclear facilities. In a case-by-case analysis of countries using or building nuclear power plants, he outlines the strategic hazards of these facilities. The safety of thousands could depend on such volatile factors as the psychological sensitivity of national leaders and the direction of the wind. A combination of engineering changes, use of alternative forms of energy to limit nuclear proliferation, and changes in international law could lessen these risks. Finally, Dr. Ramberg suggests specific national and international guidelines for monitoring nuclear exports

International Nuclear Waste Management Fact Book

International Nuclear Information System (INIS)

Leigh, I.W.

1994-05-01