USING POLYMERIC HYDROGEN GETTERS TO PREVENT COMBUSTIBLE ATMOSPHERES DURING INTERIM SAFE STORAGE OF PLUTONIUM OXIDE

International Nuclear Information System (INIS)

Woodsmall, T

2007-01-01

Nuclear Materials Management (NMM) of WSRC has recently installed the capability to perform both non-destructive and destructive examination of 3013 containers of Pu oxide in accordance with DOE-STD-3013. The containers will be opened and the oxide will be sampled for analysis. The remaining bulk oxide must then be safely stored in a non-3013-compliant configuration. Available processing equipment and controls cannot prevent the oxide from adsorbing moisture during this process. Subsequent radiolysis of moisture during storage may generate combustible quantities of gases while waiting final processing, and satisfying DOE Interim Safe Storage Criteria (ISSC) would require that storage containers be vented at impractical frequencies. With support from an independent National Laboratory, WSRC/NMM has demonstrated that a commercial hydrogen getter material will effectively prevent the accumulation of combustible gas concentrations. A project overview, including storage requirements and strategies, as well as getter technology, current test results, and anticipated future developments will be addressed

Inherently safe aircooling for the storage of self-heating configurations of radionuclides

International Nuclear Information System (INIS)

Hame, W.; Klein, D.; Pirk, H.

1980-01-01

NUKEM developed a technical concept of a radionuclide storage facility based on aircooling, which provides that - the radionuclides, i.e. spent fuel elements, are tightly canned in steel canisters - the canned elements are put into individual cooling channels, which form the storage rack within the storage cell - the produced heat is removed from the surface of the canisters through free convection. This cooling concept shows the following advantages: - The cooling is inherently safe, as the driving force of the coolant is reliably supplied by the heat production of the system to be cooled. - The system is self-controlled and self-regulated because of the physically based correlation of heat production, heat transfer coefficients and air flow resistances. (orig.) 891 RB/orig. 892 MKO [de

DQO Summary Report for 105-N/109-N Interim Safe Storage Project Waste Characterization

Energy Technology Data Exchange (ETDEWEB)

T. A. Lee

2005-09-15

The DQO summary report provides the results of the DQO process completed for waste characterization activities for the 105-N/109-N Reactor Interim Safe Storage Project including decommission, deactivate, decontaminate, and demolish activities for six associated buildings.

DQO Summary Report for 105-N/109-N Interim Safe Storage Project Waste Characterization

International Nuclear Information System (INIS)

Lee, T.A.

2005-01-01

The DQO summary report provides the results of the DQO process completed for waste characterization activities for the 105-N/109-N Reactor Interim Safe Storage Project including decommission, deactivate, decontaminate, and demolish activities for six associated buildings.

State gun safe storage laws and child mortality due to firearms.

Science.gov (United States)

Cummings, P; Grossman, D C; Rivara, F P; Koepsell, T D

1997-10-01

Since 1989, several states have passed laws that make gun owners criminally liable if someone is injured because a child gains unsupervised access to a gun. These laws are controversial, and their effect on firearm-related injuries is unknown. To determine if state laws that require safe storage of firearms are associated with a reduction in child mortality due to firearms. An ecological study of firearm mortality from 1979 through 1994. All 50 states and the District of Columbia. All children younger than 15 years. Unintentional deaths, suicides, and homicides due to firearms. Laws that make gun owners responsible for storing firearms in a manner that makes them inaccessible to children were in effect for at least 1 year in 12 states from 1990 through 1994. Among children younger than 15 years, unintentional shooting deaths were reduced by 23% (95% confidence interval, 6%-37%) during the years covered by these laws. This estimate was based on within-state comparisons adjusted for national trends in unintentional firearm-related mortality. Gun-related homicide and suicide showed modest declines, but these were not statistically significant. State safe storage laws intended to make firearms less accessible to children appear to prevent unintentional shooting deaths among children younger than 15 years.

Progress and future direction for the interim safe storage and disposal of Hanford high level waste (HLW)

International Nuclear Information System (INIS)

Wodrich, D.D.

1996-01-01

This paper describes the progress made at the largest environmental cleanup program in the United States. Substantial advances in methods to start interim safe storage of Hanford Site high-level wastes, waste characterization to support both safety- and disposal-related information needs, and proceeding with cost-effective disposal by the US DOE and its Hanford Site contractors, have been realized. Challenges facing the Tank Waste Remediation System Program, which is charged with the dual and parallel missions of interim safe storage and disposal of the high-level tank waste stored at the Hanford Site, are described

Engineering and planning for reactor 105-C interim safe storage project subcontract no. 0100C-SC-G0001 conceptual design report. Volume 1

International Nuclear Information System (INIS)

1996-04-01

The 105-C Reactor, one of eight surplus production reactors at the Hanford Site, has been proposed by the U.S. Department of Energy, Richland, Operations Office to be the first large-scale technology demonstration project in the decontamination and decommissioning (D ampersand D) focus area as part of the project for dismantlement and interim safe storage. The 105-C Reactor will be placed in an interim safe storage condition, then undergo the decontamination and decommissioning phase. After D ampersand D, the reactor will be placed in long- term safe storage. This report provides the conceptual design for these activities

Safe management of sealed radioactive sources at Karachi nuclear power complex

International Nuclear Information System (INIS)

Tahir, T.B.; Qamar, A.

2000-01-01

This paper describes the conditioning of sealed radioactive sources, carried out at the Karachi Nuclear Power Complex (KNPC) in co-operation with the IAEA. The radioactive sources were radium needles of various size, used by various radiotherapy units in different hospitals throughout the country. For some time the use of radium needles had been abandoned and they were stored in hospitals awaiting proper disposal. Since their storage conditions were not ideal and there was a potential of leakage of radioactive material into the environment, it was decided to condition and store them safely. A significant logistic effort was required to identify these sources, bring them to a central facility and condition them according to current international standards. Various steps were involved in conditioning the sources: place it in a stainless steel capsule, weld the capsule, test it for a leak, place the capsule in a lead shielded package, put and seal the shielded package in a concrete-lined steel drum and finally store it at the waste storage facility. A total amount of about 1500 mg of Radium needles were conditioned. Radiation exposure during the entire operation was within acceptable limits. (author)

Collaborators await European approval of LHC

CERN Multimedia

Sweet, William N

1994-01-01

Physicists are awaiting the authorization of the proposed $2.5 billion European LHC. Germany, France, the UK and Switzerland are still arguing on how much extra contributions host countries should provide for the proton-proton collider's construction.

Assuring safe interim storage of Hanford high-level tank wastes

International Nuclear Information System (INIS)

Bacon, R.F.; Babad, H.; Lerch, R.E.

1996-01-01

The federal government established the Hanford Site in South-Eastern Washington near the City of Richland in 1943 to produce plutonium for national defense purposes. The Hanford Site occupies approximately 1,450 square kilometers (560 square miles) of land North of the City of Richland. The production mission ended in 1988, transforming the Hanford Site mission to waste management, environmental restoration, and waste disposal. Thus the primary site mission has shifted from production to the management and disposal of radioactive, hazardous, and mixed waste that exist at the Hanford Site. This paper describes the focus and challenges facing the Tank Waste Remediation System (TWRS) Program related to the dual and parallel missions of interim safe storage and disposal of the tank associated waste. These wastes are presently stored in 2.08E+05 liters (55,000) to 4.16E+06 liters (1,100,000) gallon low-carbon steel tanks. There are 149 single- and 28 double-shell radioactive underground storage tanks, as well as approximately 40 inactive miscellaneous underground storage tanks. In addition, the TWRS mission includes the storage and disposal of the inventory of 1,929 cesium and strontium capsules created as part of waste management efforts. Tank waste was a by-product of producing plutonium and other defense related materials. From 1944 through 1990, four (4) different major chemical processing facilities at the Hanford Site processed irradiated (spent) fuel from defense reactors to separate and recover plutonium for weapons production. As new and improved processes were developed over the last 50 years, the processing efficiency improved and the waste compositions sent to the tanks for storage changed both chemically and radiologically. The earliest separation processes (e.g., bismuth phosphate coprecipitation) carried out in T Plant (1944-1956) and B Plant (1945-1952) recovered only plutonium

Adverse events while awaiting myocardial revascularization

DEFF Research Database (Denmark)

Head, Stuart J.; da Costa, Bruno R.; Beumer, Berend

2017-01-01

OBJECTIVES: The aim of the current study was to estimate adverse event rates while awaiting myocardial revascularization and review criteria for prioritizing patients. METHODS: A PubMed search was performed on 19 January 2015, to identify English-language, original, observational studies reportin...

Graphene oxide/metal nanocrystal multilaminates as the atomic limit for safe and selective hydrogen storage.

Science.gov (United States)

Cho, Eun Seon; Ruminski, Anne M; Aloni, Shaul; Liu, Yi-Sheng; Guo, Jinghua; Urban, Jeffrey J

2016-02-23

Interest in hydrogen fuel is growing for automotive applications; however, safe, dense, solid-state hydrogen storage remains a formidable scientific challenge. Metal hydrides offer ample storage capacity and do not require cryogens or exceedingly high pressures for operation. However, hydrides have largely been abandoned because of oxidative instability and sluggish kinetics. We report a new, environmentally stable hydrogen storage material constructed of Mg nanocrystals encapsulated by atomically thin and gas-selective reduced graphene oxide (rGO) sheets. This material, protected from oxygen and moisture by the rGO layers, exhibits exceptionally dense hydrogen storage (6.5 wt% and 0.105 kg H2 per litre in the total composite). As rGO is atomically thin, this approach minimizes inactive mass in the composite, while also providing a kinetic enhancement to hydrogen sorption performance. These multilaminates of rGO-Mg are able to deliver exceptionally dense hydrogen storage and provide a material platform for harnessing the attributes of sensitive nanomaterials in demanding environments.

Safe Detection System for Hydrogen Leaks

Energy Technology Data Exchange (ETDEWEB)

Lieberman, Robert A. [Intelligent Optical Systems, Inc., Torrance, CA (United States); Beshay, Manal [Intelligent Optical Systems, Inc., Torrance, CA (United States)

2012-02-29

Hydrogen is an "environmentally friendly" fuel for future transportation and other applications, since it produces only pure ("distilled") water when it is consumed. Thus, hydrogen-powered vehicles are beginning to proliferate, with the total number of such vehicles expected to rise to nearly 100,000 within the next few years. However, hydrogen is also an odorless, colorless, highly flammable gas. Because of this, there is an important need for hydrogen safety monitors that can warn of hazardous conditions in vehicles, storage facilities, and hydrogen production plants. To address this need, IOS has developed a unique intrinsically safe optical hydrogen sensing technology, and has embodied it in detector systems specifically developed for safety applications. The challenge of using light to detect a colorless substance was met by creating chemically-sensitized optical materials whose color changes in the presence of hydrogen. This reversible reaction provides a sensitive, reliable, way of detecting hydrogen and measuring its concentration using light from low-cost LEDs. Hydrogen sensors based on this material were developed in three completely different optical formats: point sensors ("optrodes"), integrated optic sensors ("optical chips"), and optical fibers ("distributed sensors") whose entire length responds to hydrogen. After comparing performance, cost, time-to-market, and relative market need for these sensor types, the project focused on designing a compact optrode-based single-point hydrogen safety monitor. The project ended with the fabrication of fifteen prototype units, and the selection of two specific markets: fuel cell enclosure monitoring, and refueling/storage safety. Final testing and development of control software for these markets await future support.

IDPs from Kosovo still awaiting durable solutions

Directory of Open Access Journals (Sweden)

Anika Krstic

2007-01-01

Full Text Available As the Balkans anxiously await delayed UN recommendations on the final status of the Serbian province of Kosovo, displaced persons from Kosovo remain torn between uncertain return prospects and denial of local integration.

Inspection and Analysis of Aluminum Storage Racks in Spent Fuel Storage Basins

International Nuclear Information System (INIS)

Howell, J.P.; Nelson, D.Z.

1998-07-01

Aluminum-clad spent nuclear fuel is stored in water filled basins at the Savannah River Site awaiting processing or other disposition. After more than 35 years of service underwater, the aluminum storage racks that position the fuel bundles in the basin were replaced. During the removal of the racks from the basin, a failure occurred in one of the racks and the Savannah River Technology Center was asked to investigate. This paper presents results of the failure analysis and provides a discussion of the effects of corrosion on the structural integrity of the storage racks

Percutaneous laser ablation of hepatocellular carcinoma in patients with liver cirrhosis awaiting liver transplantation

International Nuclear Information System (INIS)

Pompili, Maurizio; Pacella, Claudio Maurizio; Francica, Giampiero; Angelico, Mario; Tisone, Giuseppe; Craboledda, Paolo; Nicolardi, Erica; Rapaccini, Gian Ludovico; Gasbarrini, Giovanni

2010-01-01

Objective: The aim of this study was to determine the effectiveness and safety of percutaneous laser ablation for the treatment of cirrhotic patients with hepatocellular carcinoma awaiting liver transplantation. Materials and methods: The data of 9 male cirrhotic patients (mean age 50 years, range 45-60 years) with 12 biopsy proven nodules of hepatocellular carcinoma (mean diameter 2.0 cm, range 1.0-3.0 cm) treated by laser ablation before liver transplantation between June 2000 and January 2006 were retrospectively reviewed. Laser ablation was carried out by inserting 300 nm optical fibers through 21-Gauge needles (from two to four) positioned under ultrasound guidance into the target lesions. A continuous wave Neodymium:Yttrium Aluminium Garnet laser was used. Transarterial chemoembolization prior to liver transplantation was performed in two incompletely ablated tumors. Results: No procedure-related major complications were recorded. During the waiting time to liver transplantation local tumor progression after ablation occurred in 3 nodules (25%). At histological examination of the explanted livers complete necrosis was found in 8 nodules (66.7%, all treated exclusively with laser ablation), partial necrosis >50% in 3 nodules (25%), and partial necrosis <50% in 1 nodule. Conclusion: In patients with cirrhotic livers awaiting liver transplantation, percutaneous laser ablation is safe and effective for the management of small hepatocellular carcinoma.

Project management plan for the 105-C Reactor interim safe storage project. Revision 1

International Nuclear Information System (INIS)

Miller, R.L.

1997-01-01

In 1942, the Hanford Site was commissioned by the US Government to produce plutonium. Between 1942 and 1955, eight water-cooled, graphite-moderated reactors were constructed along the Columbia River at the Hanford Site to support the production of plutonium. The reactors were deactivated from 1964 to 1971 and declared surplus. The Surplus Production Reactor Decommissioning Project (BHI 1994b) will decommission these reactors and has selected the 105-C Reactor to be used as a demonstration project for interim safe storage at the present location and final disposition of the entire reactor core in the 200 West Area. This project will result in lower costs, accelerated schedules, reduced worker exposure, and provide direct benefit to the US Department of Energy for decommissioning projects complex wide. This project sets forth plans, organizational responsibilities, control systems, and procedures to manage the execution of the Project Management Plan for the 105-C Reactor Interim Safe Storage Project (Project Management Plan) activities to meet programmatic requirements within authorized funding and approved schedules. The Project Management Plan is organized following the guidelines provided by US Department of Energy Order 4700.1, Project Management System and the Richland Environmental Restoration Project Plan (DOE-RL 1992b)

Data storage and retrieval for long-term dog studies

International Nuclear Information System (INIS)

Watson, C.R.; Trauger, G.M.; McIntyre, J.M.; Slavich, A.L.; Park, J.F.

1980-01-01

Over half of the 500,000 records collected on dogs in the last 20 years in our laboratory have been converted from sequential storage on magnetic tape to direct-access disk storage on a PDP 11/70 minicomputer. An interactive storage and retrieval system, based on a commercially available query language, has been developed to make these records more accessible. Data entry and retrieval are now performed by scientists and technicians rather than by keypunch operators and computer specialists. Further conversion awaits scheduled computer enhancement

Safe handling, transport and storage of plutonium. Proceedings of a technical committee meeting held in Vienna, 18-21 October 1993

International Nuclear Information System (INIS)

1994-10-01

Plutonium inventories and utilization rates worldwide are growing. It is important for nuclear power programmes everywhere that no incidents or accidents with plutonium occur. It is therefore important that all who deal with plutonium, do so safely. All those who deal with plutonium should have available the best information on safety handling and storage. Several countries have mature plutonium programmes. However, information exchange on plutonium has been limited. This has precluded the development until now of consensus documentation on safe handling and storage of plutonium. The Technical Committee has been established to address these problems and this Technical Document is the first product in this process. The purpose of the meeting was to bring together experts with significant experience in handling, transporting and storing plutonium; to exchange information and experiences dealing with plutonium at their facilities; to describe their practices (guidelines, procedures, regulations, etc.) for safely dealing with plutonium; to assess the need to develop and publish a consensus plutonium safety practices document(s), and to recommend possible future IAEA activities in this technical area. Refs, figs and tabs

[Anniversary of the medical department of the Federal Office for Safe Storage and Destruction of Chemical Weapons].

Science.gov (United States)

Kuz'menko, I E

2013-01-01

The article is devoted to the process of formation and development of CW destruction management system and medical support of professional activities of personnel. Founders of Medical department of the Federal Directorate for Safe Storage and Destruction of Chemical Weapons are presented. Main principles and ways of working of medical department in specific conditions are covered.

Different types of intermediate storages

International Nuclear Information System (INIS)

Spilker, H.

1982-01-01

Spent nuclear fuel elements require a period of ''cooling'' after withdrawal from a nuclear reactor. This is done in water storage pools located at the reactor facility. The minimum storage time prior to subsequent operations with the spent fuel is recognized as six to twelve months. After the initial storage period for cooling, the subsequent storage time in water pools could vary from a few years to several decades. Up to 1980, about 15.700 MTHM of spent LWR and HWR fuel have been discharged from nuclear stations. Since only a small fraction thereof has been already reprocessed. The spent fuel assemblies are stored at the reactor-side (AR) in reactor basins in normal or compact racks and away from reactor (AFR) in water pool storages awaiting either reprocessing or final disposal depending on the fuel cycle concept chosen by the individual countries. (orig.)

Field efficacy evaluation and post-treatment contamination risk assessment of an ultraviolet disinfection and safe storage system.

Science.gov (United States)

Reygadas, Fermin; Gruber, Joshua S; Ray, Isha; Nelson, Kara L

2015-11-15

Inconsistent use of household water treatment and safe storage (HWTS) systems reduces their potential health benefits. Ultraviolet (UV) disinfection is more convenient than some existing HWTS systems, but it does not provide post-treatment residual disinfectant, which could leave drinking water vulnerable to recontamination. In this paper, using as-treated analyses, we report on the field efficacy of a UV disinfection system at improving household drinking water quality in rural Mexico. We further assess the risk of post-treatment contamination from the UV system, and develop a process-based model to better understand household risk factors for recontamination. This study was part of a larger cluster-randomized stepped wedge trial, and the results complement previously published population-level results of the intervention on diarrheal prevalence and water quality. Based on the presence of Escherichia coli (proportion of households with ≥ 1 E. coli/100 mL), we estimated a risk difference of -28.0% (95% confidence interval (CI): -33.9%, -22.1%) when comparing intervention to control households; -38.6% (CI: -48.9%, -28.2%) when comparing post- and pre-intervention results; and -37.1% (CI: -45.2%, -28.9%) when comparing UV disinfected water to alternatives within the household. We found substantial increases in post-treatment E. coli contamination when comparing samples from the UV system effluent (5.0%) to samples taken from the storage container (21.1%) and drinking glasses (26.0%). We found that improved household infrastructure, additional extractions from the storage container, additional time from when the storage container was filled, and increased experience of the UV system operator were associated with reductions in post-treatment contamination. Our results suggest that the UV system is efficacious at improving household water quality when used as intended. Promoting safe storage habits is essential for an effective UV system dissemination. The drinking

Safe Minimum Internal Temperature Chart

Science.gov (United States)

... Internal Temperature Chart Safe steps in food handling, cooking, and storage are essential in preventing foodborne illness. You can't see, smell, or taste harmful bacteria that may cause illness. In every step of food preparation, follow the four guidelines to keep food safe: ...

Safe havens in Europe

DEFF Research Database (Denmark)

Paldam, Martin

2013-01-01

Eleven safe havens exist in Europe providing offshore banking and low taxes. Ten of these states are very small while Switzerland is moderately small. All 11 countries are richer than their large neighbors. It is shown that causality is from small to safe haven to wealth, and that theoretically...... equilibriums are likely to exist where a certain regulation is substantially lower in a small country than in its big neighbor. This generates a large capital inflow to the safe havens. The pool of funds that may reach the safe havens is shown to be huge. It is far in excess of the absorptive capacity...... of the safe havens, but it still explains, why they are rich. Microstates offer a veil of anonymity to funds passing through, and Switzerland offers safe storage of funds....

Assessment of the Electrical Power Requirements for Continued Safe Storage and Waste Feed Delivery Phase One

International Nuclear Information System (INIS)

MAY, T.H.

2000-01-01

This study evaluated the ability of the electrical distribution system to support safe storage as well as the first phase of the Waste Feed Delivery. Several recommendations are made to improve the electrical system. The ability to assure adequate Waste Feed Delivery (WFD) to the Privatization Contractor's vitrification facility is a key element in the overall Hanford cleanup schedule. An important aspect of this WFD is the availability of sufficient and appropriate electrical power in the single- and double-shell tank farms. The methodology for performing this review and the results are described

Thermally responsive polymer electrolytes for inherently safe electrochemical energy storage

Science.gov (United States)

Kelly, Jesse C.

-off" ratio in electrochemical activity at elevated temperatures. Overall, solution pH and conductivity were altered by an order of magnitude and device performance (ability to store charge) decreased by over 70%. After demonstration of a model responsive electrolyte in an aqueous system, ionic liquid (IL) based electrolytes were developed as a means of controlling the electrochemical performance in the non-aqueous environments that batteries, specifically Li-ion, require. Here, two systems were developed: (1) an electrolyte comprising poly(ethylene oxide) (PEO), the IL, [EMIM][BF4], and a lithium salt and (2) an electrolyte comprising poly(benzyl methacrylate) (PBzMA), the IL, [EMIM][TFSI], and a lithium salt. In each system, the polymer-IL phase separation inhibited device operation at elevated temperatures. For the PEO/IL electrolyte, the thermally induced liquid-liquid phase separation was shown to decrease the ionic conductivity, thereby affecting the concentration of ions at the electrode. Additionally, an increasing charge transfer resistance associated with the phase separated polymer coating the porous electrode was shown to limit electrochemical activity significantly. For the PBzMA/IL electrolyte, the solid-liquid phase separation did not show a change in conductivity, but did cause a drastic increase in charge transfer resistance, effectively shutting off Li-ion battery operation at high temperatures. Such responsive mixtures provide a transformative approach to regulating electrochemical processes, which is necessary to achieve inherently safe operation in large format energy storage with EDLCs, supercapacitors and Li-ion batteries.

12 CFR 9.10 - Fiduciary funds awaiting investment or distribution.

Science.gov (United States)

2010-01-01

... distribution. 9.10 Section 9.10 Banks and Banking COMPTROLLER OF THE CURRENCY, DEPARTMENT OF THE TREASURY... has investment discretion, the bank shall obtain for funds awaiting investment or distribution a rate... principal and interest; (ii) Securities that qualify as eligible for investment by national banks pursuant...

Safe interim storage of Hanford tank wastes, draft environmental impact statement, Hanford Site, Richland, Washington

Energy Technology Data Exchange (ETDEWEB)

1994-07-01

This Draft EIS is prepared pursuant to the National Environmental Policy Act (NEPA) and the Washington State Environmental Policy Act (SEPA). DOE and Ecology have identified the need to resolve near-term tank safety issues associated with Watchlist tanks as identified pursuant to Public Law (P.L.) 101-510, Section 3137, ``Safety Measures for Waste Tanks at Hanford Nuclear Reservation,`` of the National Defense Authorization Act for Fiscal Year 1991, while continuing to provide safe storage for other Hanford wastes. This would be an interim action pending other actions that could be taken to convert waste to a more stable form based on decisions resulting from the Tank Waste Remediation System (TWRS) EIS. The purpose for this action is to resolve safety issues concerning the generation of unacceptable levels of hydrogen in two Watchlist tanks, 101-SY and 103-SY. Retrieving waste in dilute form from Tanks 101-SY and 103-SY, hydrogen-generating Watchlist double shell tanks (DSTs) in the 200 West Area, and storage in new tanks is the preferred alternative for resolution of the hydrogen safety issues.

Safe interim storage of Hanford tank wastes, draft environmental impact statement, Hanford Site, Richland, Washington

International Nuclear Information System (INIS)

1994-07-01

This Draft EIS is prepared pursuant to the National Environmental Policy Act (NEPA) and the Washington State Environmental Policy Act (SEPA). DOE and Ecology have identified the need to resolve near-term tank safety issues associated with Watchlist tanks as identified pursuant to Public Law (P.L.) 101-510, Section 3137, ''Safety Measures for Waste Tanks at Hanford Nuclear Reservation,'' of the National Defense Authorization Act for Fiscal Year 1991, while continuing to provide safe storage for other Hanford wastes. This would be an interim action pending other actions that could be taken to convert waste to a more stable form based on decisions resulting from the Tank Waste Remediation System (TWRS) EIS. The purpose for this action is to resolve safety issues concerning the generation of unacceptable levels of hydrogen in two Watchlist tanks, 101-SY and 103-SY. Retrieving waste in dilute form from Tanks 101-SY and 103-SY, hydrogen-generating Watchlist double shell tanks (DSTs) in the 200 West Area, and storage in new tanks is the preferred alternative for resolution of the hydrogen safety issues

Awareness of the need for safe storage of Methadone at home is not improved by the use of protocols on recording information giving

Directory of Open Access Journals (Sweden)

Crome Ilana B

2008-04-01

Full Text Available Abstract Background Methadone is a synthetic, narcotic analgesic used in the treatment of drug misuse. Tragedies involving children being poisoned by the accidental ingestion of methadone are no longer a rare occurrence. Following an audit of the effectiveness of the provision and recall of information to patients attending an NHS Methadone Clinic a protocol was introduced to ensure that staff documented the provision of such information and patients gave a written confirmation that they had received the information. Methods The study was undertaken in the setting of an NHS methadone clinic with the aim of re- auditing the storage of methadone at home following the introduction of the new protocols. 174 patients completed an anonymous questionnaire regarding where they store methadone at home and whether they recall being given advice about safe storage. Community pharmacists were contacted by telephone to assess the level of advice given to methadone patients regarding safety. Results Only 49 (28.2% patients recalled being given advice about safe storage, 24 (13.8% recalled that information was provided by clinic staff. 170 (97.7% patients regard methadone as being dangerous. (28.2%. Methadone is most commonly stored in a cupboard (37.9%. All methadone is dispensed in a bottle with a child resistant cap on it. All patients reported they stored their methadone in the original bottle provided by the pharmacist. Conclusion Recall of information on safety issues is very poor. Provision of written as well as verbal information is needed. The use of printed safety information cards which patients can take away for future reference may be of use. It is the responsibility of health professionals to ensure they provide information and advice to methadone users on the safe storage of their methadone at home.

CRITICALITY SAFETY CONTROL OF LEGACY FUEL FOUND AT 105-K WEST FUEL STORAGE BASIN

International Nuclear Information System (INIS)

JENSEN, M.A.

2005-01-01

In August 2004, two sealed canisters containing spent nuclear fuel were opened for processing at the Hanford Site's K West fuel storage basin. The fuel was to be processed through cleaning and sorting stations, repackaged into special baskets, placed into a cask, and removed from the basin for further processing and eventual dry storage. The canisters were expected to contain fuel from the old Hanford C Reactor, a graphite-moderated reactor fueled by very low-enriched uranium metal. The expected fuel type was an aluminum-clad slug about eight inches in length and with a weight of about eight pounds. Instead of the expected fuel, the two canisters contained several pieces of thin tubes, some with wire wraps. The material was placed into unsealed canisters for storage and to await further evaluation. Videotapes and still photographs of the items were examined in consultation with available retired Hanford employees. It was determined that the items had a fair probability of being cut-up pieces of fuel rods from the retired Hanford Plutonium Recycle Test Reactor (PRTR). Because the items had been safely handled several times, it was apparent that a criticality safety hazard did not exist when handling the material by itself, but it was necessary to determine if a hazard existed when combining the material with other known types of spent nuclear fuel. Because the PRTR operated more than 40 years ago, investigators had to rely on a combination of researching archived documents, and utilizing common-sense estimates coupled with bounding assumptions, to determine that the fuel items could be handled safely with other spent nuclear fuel in the storage basin. As older DOE facilities across the nation are shut down and cleaned out, the potential for more discoveries of this nature is increasing. As in this case, it is likely that only incomplete records will exist and that it will be increasingly difficult to immediately characterize the nature of the suspect fissionable

Towards Safe Food Free From Pesticides Residues: Biochemical Changes of Selected Vitamins, Trace Elements and Genotoxicity of Irradiated Dates During Storage

International Nuclear Information System (INIS)

Farag, S.E.A.; Elsawy, KH.M.; Elgammal, M.H.; Hammoud, G.M.; Youssef, M.S.H.

2012-01-01

Decreasing quality of semi-dry dates due to infestation during storage is recorded by many researchers. Low gamma irradiation doses could be considered safe alternative of human toxic chemicals and pesticides. In the present study, semi-dry dates irradiated with different doses of 1, 3, 5 kGy beside non-irradiated samples were stored at 20 degree C and at -18 degree C for nine months. Vitamins E, A and trace elements were determined to check the genotoxicity effect of irradiation at high doses (1, 3, 5, 20 and 30 kGy). Results of high pressure liquid chromatography (HPLC) proved that semi-dry dates contain vitamins A (β-carotene) and E (α-tocopherol) in amounts of 98.78 μg/100 g and 1.818 mg/100 g, respectively, in raw non-irradiated fruits. Degradation of vitamins either naturally during storage or by irradiation was manifested. However, the lowest losses of vitamins were detected at low doses of irradiation (1-3 kGy). Also, trace elements and metals were determined by inductively coupled plasma (ICP) technique. Six trace elements; selenium (Se), zinc (Zn), cupper (Cu), cobalt (Co), chromium (Cr) and nickel (Ni), which are responsible for immunity system were detected in dates with considerable concentrations. Two contaminants heavy metals, lead (Pb) and cadmium (Cd), were detected. All the trace elements were in safe levels and have negligible changes under stress of irradiation and during long storage conditions. The genotoxicity test proved that the increased toxicity of irradiated dates was dose dependant, therefore, the irradiated samples at 1 kGy were safe (near control samples). Consequently, the irradiation at 1 kGy was preferable to be used as an alternative of pesticides in spite of some losses in some bioactive content.

Assessing bone status in patients awaiting liver transplantation.

Science.gov (United States)

Wibaux, Cécile; Legroux-Gerot, Isabelle; Dharancy, Sébastien; Boleslawski, Emmanuel; Declerck, Nicole; Canva, Valérie; Mathurin, Philippe; Pruvot, François-René; Cortet, Bernard

2011-07-01

Osteoporosis is common in liver transplant recipients as a result of both iatrogenic factors and preexisting hepatic osteodystrophy. To assess the prevalences of osteoporosis and fractures and to identify risk factors for these two abnormalities in patients awaiting liver transplantation for end-stage liver disease. Between January 2006 and December 2007, patients on a liver transplant waiting list underwent a routine evaluation comprising the identification of risk factors for osteoporosis, radiographs of the spine, bone mineral density measurements (BMD), and laboratory tests (phosphate and calcium levels, hormone assays, liver function tests, and bone turnover markers). We studied 99 patients (70 males and 20 females; mean age, 55 ± 8 years) including 75% with alcohol-induced cirrhosis with or without hepatocarcinoma. Among them, 36% had radiographic vertebral fractures, 38% had osteoporosis, 35% had osteopenia, and 88% had vitamin D insufficiency or deficiency (25(OH)vitamin D3bone resorption markers correlated negatively with BMD at the spine and hip. The Model for End-Stage Liver Disease score correlated negatively with hip BMD. Our findings suggest high prevalences of low BMD values and vertebral fractures among patients awaiting liver transplantation. Bone status should be evaluated routinely in candidates to liver transplantation. Copyright © 2011 Société française de rhumatologie. Published by Elsevier SAS. All rights reserved.

Plutonium storage criteria

Energy Technology Data Exchange (ETDEWEB)

Chung, D. [Scientech, Inc., Germantown, MD (United States); Ascanio, X. [Dept. of Energy, Germantown, MD (United States)

1996-05-01

The Department of Energy has issued a technical standard for long-term (>50 years) storage and will soon issue a criteria document for interim (<20 years) storage of plutonium materials. The long-term technical standard, {open_quotes}Criteria for Safe Storage of Plutonium Metals and Oxides,{close_quotes} addresses the requirements for storing metals and oxides with greater than 50 wt % plutonium. It calls for a standardized package that meets both off-site transportation requirements, as well as remote handling requirements from future storage facilities. The interim criteria document, {open_quotes}Criteria for Interim Safe Storage of Plutonium-Bearing Solid Materials{close_quotes}, addresses requirements for storing materials with less than 50 wt% plutonium. The interim criteria document assumes the materials will be stored on existing sites, and existing facilities and equipment will be used for repackaging to improve the margin of safety.

European Model Code of safe practice in the storage and handling of petroleum products. Part I. Operations

Energy Technology Data Exchange (ETDEWEB)

1973-01-01

This safe practice code was prepared by a working group consisting of experts from 10 Western European countries. It consists of short guidelines and technical advice on general precautions, injuries and medical services, permits to work, fire prevention and fighting, jetties, pipework, storage tanks, static electricity, electrical equipment, road vehicles, tank cars, handling of bitumen products, liquefied petroleum gases, packed products and training of personnel. The code is supplemented by 10 appendices, including a suggested syllabus for a 2-day course on fire prevention and emergency action for managers of oil installations.

Establishing a store baseline during interim storage of waste packages and a review of potential technologies for base-lining

Energy Technology Data Exchange (ETDEWEB)

McTeer, Jennifer; Morris, Jenny; Wickham, Stephen [Galson Sciences Ltd. Oakham, Rutland (United Kingdom); Bolton, Gary [National Nuclear Laboratory Risley, Warrington (United Kingdom); McKinney, James; Morris, Darrell [Nuclear Decommissioning Authority Moor Row, Cumbria (United Kingdom); Angus, Mike [National Nuclear Laboratory Risley, Warrington (United Kingdom); Cann, Gavin; Binks, Tracey [National Nuclear Laboratory Sellafield (United Kingdom)

2013-07-01

Interim storage is an essential component of the waste management lifecycle, providing a safe, secure environment for waste packages awaiting final disposal. In order to be able to monitor and detect change or degradation of the waste packages, storage building or equipment, it is necessary to know the original condition of these components (the 'waste storage system'). This paper presents an approach to establishing the baseline for a waste-storage system, and provides guidance on the selection and implementation of potential base-lining technologies. The approach is made up of two sections; assessment of base-lining needs and definition of base-lining approach. During the assessment of base-lining needs a review of available monitoring data and store/package records should be undertaken (if the store is operational). Evolutionary processes (affecting safety functions), and their corresponding indicators, that can be measured to provide a baseline for the waste-storage system should then be identified in order for the most suitable indicators to be selected for base-lining. In defining the approach, identification of opportunities to collect data and constraints is undertaken before selecting the techniques for base-lining and developing a base-lining plan. Base-lining data may be used to establish that the state of the packages is consistent with the waste acceptance criteria for the storage facility and to support the interpretation of monitoring and inspection data collected during store operations. Opportunities and constraints are identified for different store and package types. Technologies that could potentially be used to measure baseline indicators are also reviewed. (authors)

Conditioning of spent fuel assemblies from the Rossendorf RFR research reactor in transport and storage containers of the type CASTOR MTR 2

International Nuclear Information System (INIS)

Schneider, B.; Hofmann, G.

1994-09-01

Most of the spent fuel assemblies are temporarily stored in the flooded fuel ponds AB 1 and AB 2 of the RFR, and some are still in the reactor core. The conditioning task described here is part of the RFR spent fuel management concept and covers the safe emplacement of the spent fuel elements in the CASTOR MTR 2 shipping containers and the sealing of the containers in compliance with the nuclear licence issued for the conditioning task. The transfer of the spent fuel assemblies from the present wet storage conditions to the dry storage conditions in the CASTOR MTR 2 containers is done by a mobile manipulation equipment consisting essentially of the transfer sluice gate and a transfer container. Subsequent to conditioning, the shipping containers are to be transported to a licensed intermediate storage facility to await their transport to a national radwaste repository. The technical handling tools for the transfer and manipulation are briefly described, as well as the process steps involved, putting emphasis on the detailed description of processes and the accompanying time frame, so that the conditioning task can be incorporated into the work plan of the entire project. The report further presents the EDP concept established for the task, including the required data archivation and documentation. (orig.) [de

The safe home project.

Science.gov (United States)

Arphorn, Sara; Jiraniratisai, Sopaphan; Rungtakul, Rungsri; Phutta, Nikom

2011-12-01

The Thai Health Promotion Foundation supported the Improvement of Quality of Life of Informal Workers project in Ban Luang District, Amphur Photaram, Ratchaburi Province. There were many informal workers in Ban Luang District. Sweet-crispy fish producers in Ban Luang were the largest group among the sweet-crispy fish producers in Thailand. This project was aimed at improving living and working conditions of informal workers, with a focus on the sweet-crispy fish group. Good practices of improved living and working conditions were used to help informal workers build safe, healthy and productive work environments. These informal workers often worked in substandard conditions and were exposed to various hazards in the working area. These hazards included risk of exposure to hot work environment, ergonomics-related injuries, chemical hazards, electrical hazards etc. Ergonomics problems were commonly in the sweet-crispy fish group. Unnatural postures such as prolonged sitting were performed dominantly. One hundred and fifty informal workers participated in this project. Occupational health volunteers were selected to encourage occupational health and safety in four groups of informal workers in 2009. The occupational health volunteers trained in 2008 were farmers, beauty salon workers and doll makers. The occupational health and safety knowledge is extended to a new informal worker group: sweet-crispy fish producer, in 2009. The occupational health and safety training for sweet-crispy fish group is conducted by occupational health volunteers. The occupational health volunteers increased their skills and knowledge assist in to make safe home and safe community through participatory oriented training. The improvement of living and working condition is conducted by using a modified WISH, Work Improvement for Safe Home, checklist. The plans of improvement were recorded. The informal workers showed improvement mostly on material handling and storage. The safe uses and safe

Safety Aspects of Long Term Spent Fuel Dry Storage

International Nuclear Information System (INIS)

Botsch, Wolfgang; Smalian, S.; Hinterding, P.; Drotleff, H.; Voelzke, H.; Wolff, D.; Kasparek, E.

2014-01-01

As a consequence of the lack of a final repository for spent nuclear fuel (SF) and high level waste (HLW), long term interim storage of SF and HLW will be necessary. As with the storage of all radioactive materials, the long term storage of SF and HLW must conform to safety requirements. Safety aspects such as safe enclosure of radioactive materials, safe removal of decay heat, sub-criticality and avoidance of unnecessary radiation exposure must be achieved throughout the complete storage period. The implementation of these safety requirements can be achieved by dry storage of SF and HLW in casks as well as in other systems such as dry vault storage systems or spent fuel pools, where the latter is neither a dry nor a passive system. After the events of Fukushima, the advantages of passively and inherently safe dry storage systems have become more obvious. In Germany, dry storage of SF in casks fulfils both transport and storage requirements. Mostly, storage facilities are designed as concrete buildings above the ground; one storage facility has also been built as a rock tunnel. In all these facilities the safe enclosure of radioactive materials in dry storage casks is achieved by a double-lid sealing system with surveillance of the sealing system. The safe removal of decay heat is ensured by the design of the storage containers and the storage facility, which also secures to reduce the radiation exposure to acceptable levels. TUV and BAM, who work as independent experts for the competent authorities, inform about spent fuel management and issues concerning dry storage of spent nuclear fuel, based on their long experience in these fields. All relevant safety issues such as safe enclosure, shielding, removal of decay heat and sub-criticality are checked and validated with state-of-the-art methods and computer codes before the license approval. In our presentation we discuss which of these aspects need to be examined closer for a long term interim storage. It is shown

Monitored retrievable storage design

International Nuclear Information System (INIS)

Woods, W.D.

1985-01-01

The Nuclear Waste Policy Act of 1982 (NWPA) established a national policy for the safe storage and disposal of spent nuclear fuel and high-level radioactive waste. The NWPA requires that DOE... ''submit a proposal to Congress on the need for and feasibility of one or more Monitored Retrievable Storage (MRS) Facilities''... In subsequent evaluations of the commercial nuclear waste management system, DOE has identified important advantages in providing an MRS Facility as an integral part of the total system. The integral MRS Facility serves as an independent, centralized spent nuclear fuel and high-level waste handling and packaging facility with a safe temporary storage capacity

Ammonia Storage as Complex Compounds for a Safe and Compact Hydrogen Storage

National Research Council Canada - National Science Library

Sarkisian, Paul

2003-01-01

.... Design software suitable to the evaluation of the complex compounds for this particular application was developed that would determine the size and weight of the complex compound sorber to be used for ammonia storage...

CarbonSAFE Illinois - Macon County

Energy Technology Data Exchange (ETDEWEB)

Whittaker, Steve [University of Illinois; Illinois State Geological Survey

2017-08-03

CarbonSAFE Illinois is a a Feasibility study to develop an established geologic storage complex in Macon County, Illinois, for commercial-scale storage of industrially sourced CO2. Feasibility activities are focused on the Mt. Simon Storage Complex; a step-out well will be drilled near existing storage sites (i.e., the Midwest Geological Sequestration Consortium’s Illinois Basin – Decatur Project and the Illinois Industrial Carbon Capture and Storage Project) to further establish commercial viability of this complex and to evaluate EOR potential in a co-located oil-field trend. The Archer Daniels Midland facility (ethanol plant), City Water, Light, and Power in Springfield, Illinois (coal-fired power station), and other regional industries are potential sources of anthropogenic CO2 for storage at this complex. Site feasibility will be evaluated through drilling results, static and dynamic modeling, and quantitative risk assessment. Both studies will entail stakeholder engagement, consideration of infrastructure requirements, existing policy, and business models. Project data will help calibrate the National Risk Assessment Partnership (NRAP) Toolkit to better understand the risks of commercial-scale carbon storage.

Dry Storage of Research Reactor Spent Nuclear Fuel - 13321

Energy Technology Data Exchange (ETDEWEB)

Adams, T.M.; Dunsmuir, M.D.; Leduc, D.R.; Severynse, T.F.; Sindelar, R.L. [Savannah River National Laboratory (United States); Moore, E.N. [Moore Nuclear Energy, LLC (United States)

2013-07-01

Spent fuel from domestic and foreign research reactors is received and stored at the Savannah River Site's L Area Material Storage (L Basin) Facility. This DOE-owned fuel consists primarily of highly enriched uranium in metal, oxide or silicide form with aluminum cladding. Upon receipt, the fuel is unloaded and transferred to basin storage awaiting final disposition. Disposition alternatives include processing via the site's H Canyon facility for uranium recovery, or packaging and shipment of the spent fuel to a waste repository. A program has been developed to provide a phased approach for dry storage of the L Basin fuel. The initial phase of the dry storage program will demonstrate loading, drying, and storage of fuel in twelve instrumented canisters to assess fuel performance. After closure, the loaded canisters are transferred to pad-mounted concrete overpacks, similar to those used for dry storage of commercial fuel. Unlike commercial spent fuel, however, the DOE fuel has high enrichment, very low to high burnup, and low decay heat. The aluminum cladding presents unique challenges due to the presence of an oxide layer that forms on the cladding surface, and corrosion degradation resulting from prolonged wet storage. The removal of free and bound water is essential to the prevention of fuel corrosion and radiolytic generation of hydrogen. The demonstration will validate models predicting pressure, temperature, gas generation, and corrosion performance, provide an engineering scale demonstration of fuel handling, drying, leak testing, and canister backfill operations, and establish 'road-ready' storage of fuel that is suitable for offsite repository shipment or retrievable for onsite processing. Implementation of the Phase I demonstration can be completed within three years. Phases II and III, leading to the de-inventory of L Basin, would require an additional 750 canisters and 6-12 years to complete. Transfer of the fuel from basin storage

High density fuel storage racks

International Nuclear Information System (INIS)

Groves, M.D.

1978-01-01

An apparatus is described for the safe and compact storage of nuclear fuel assemblies in an array of discrete open-ended neutron absorbing shields for which the theoretical minimum safe separation distance and cell pitch are known. Open-ended stainless steel end fittings are welded to each end of each shield and the end fittings are welded to each other in side-by-side relation, thereby reducing the cell pitch tolerance due to fabrication uncertainties. In addition, a multiplicity of ridges on the sides of each shield having a height equal to one half the theoretical minimum safe separation distance further reduce shield bowing tolerances. The net tolerance reduction permits a significant increase in the number of fuel assemblies that can be safely contained in a storage area of fixed size

Developing new transportable storage casks for interim dry storage

International Nuclear Information System (INIS)

Hayashi, K.; Iwasa, K.; Araki, K.; Asano, R.

2004-01-01

Transportable storage metal casks are to be consistently used during transport and storage for AFR interim dry storage facilities planning in Japan. The casks are required to comply with the technical standards of regulations for both transport (hereinafter called ''transport regulation'') and storage (hereafter called ''storage regulation'') to maintain safety functions (heat transfer, containment, shielding and sub-critical control). In addition to these requirements, it is not planned in normal state to change the seal materials during storage at the storage facility, therefore it is requested to use same seal materials when the casks are transported after storage period. The dry transportable storage metal casks that satisfy the requirements have been developed to meet the needs of the dry storage facilities. The basic policy of this development is to utilize proven technology achieved from our design and fabrication experience, to carry out necessary verification for new designs and to realize a safe and rational design with higher capacity and efficient fabrication

Rethinking the economics of centralized spent fuel storage

International Nuclear Information System (INIS)

Wood, T.W.; Short, S.M.; Dippold, D.G.; Rod, S.R.; Williams, J.W.

1991-04-01

The technology for extended storage of spent nuclear fuel (SNF), either at-reactor or in a centralized facility such as a monitored retrievable storage (MRS) facility, is well-developed and proven from an engineering and safety perspective. The question of whether spent fuel should await its final geologic disposal while at a reactor site or in an MRS facility is essentially an economic one. While intuition and previous results suggest that centralized storage will be more economical than at-reactor storage beyond some break-even quantity of SNF, the incremental costs of pool storage at-reactor are close to zero as long as pool capacity is generally available. Thus, if economics is the prime motivator, the quantity of spent fuel required to warrant centralized storage could be quite large. The economics of centralizing the storage of spent fuel at a single site, as opposed to continued storage at over 100 reactor sites, has been the subject of several recent analyses. Most of these analyses involved calculating the benefits of an MRS facility with a pre-defined MRS operating scenario. This paper reverses this approach to economic analysis of the MRS by seeking the optimal MRS operating scenario (in terms of the parameters listed above) implied by the economic incentives arising from the relative costs of at-reactor storage and centralized storage. This approach treats an MRS as a possible storage location that will be used according to its economic value in system operation. 5 refs., 5 figs

Safe storage of pesticides in Sri Lanka - identifying important design features influencing community acceptance and use of safe storage devices

DEFF Research Database (Denmark)

Weerasinghe, Manjula; Pieris, Ravi; Eddleston, Michael

2008-01-01

BACKGROUND: Self-poisoning with pesticides is the cause of an estimated 300,000 deaths annually in rural Asia. The great majority of these deaths are from impulsive acts of self-harm using pesticides that are readily available in the home. The secure storage of pesticides under lock has been...

Emotions while awaiting lung transplantation: A comprehensive qualitative analysis.

Science.gov (United States)

Brügger, Aurelia; Aubert, John-David; Piot-Ziegler, Chantal

2014-07-01

Patients awaiting lung transplantation are at risk of negative emotional and physical experiences. How do they talk about emotions? Semi-structured interviews were performed (15 patients). Categorical analysis focusing on emotion-related descriptions was organized into positive-negative-neutral descriptions: for primary and secondary emotions, evaluation processes, coping strategies, personal characteristics, emotion descriptions associated with physical states, (and) contexts were listed. Patients develop different strategies to maintain positive identity and attitude, while preserving significant others from extra emotional load. Results are discussed within various theoretical and research backgrounds, in emphasizing their importance in the definition of emotional support starting from the patient's perspective.

Rethinking the economics of centralized spent fuel storage

International Nuclear Information System (INIS)

Wood, T.W.; Short, S.M.; Dippold, D.G.; Rod, S.R.; Williams, J.W.

1991-01-01

The technology for extended storage of spent nuclear fuel (SNF), either at-reactor or in a centralized facility such as a monitored retrievable storage (MRS) facility, is well-developed and proven from an engineering and safety perspective. The question of whether spent fuel should await its final geologic disposal while at a reactor site or in an MRS facility is essentially an economic one. While intuition and previous results suggest that centralized storage will be more economical than at-reactor storage beyond some break-even quantity of SNF, the incremental costs of pool storage at-reactor are close to zero as long as pool capacity is generally available. Thus, if economics is the prime motivator, the quantity of spent fuel required to warrant centralized storage could be quite large. The economics of centralizing the storage of spent fuel at a single site, as opposed to continued storage at over 100 reactor sites, has been the subject of several recent analyses. Most of these analyses involved calculating the benefits of an MRS facility (in terms of avoided utility costs) with a pre-defined MRS operating scenario (e.g., spent fuel acceptance schedule, storage capacity, and typical storage cycle). While these analyses provided some insight into the economic justification for an MRS facility, even the most favorable scenarios resulted in net costs of hundreds of millions of dollars when evaluated on a discounted cash flow basis

Handling of spent nuclear fuel and final storage of nitrified high level reprocessing waste

International Nuclear Information System (INIS)

The following stages of handling and transport of the fuel on its way to final storage are dealt with in the report. 1) The spent nuclear fuel is stored at the power station or in the central fuel storage facility awaiting reprocessing. 2) The fuel is reprocessed, i.e. uranium, plutonium and waste are separated from each other. Reprocessing does not take place in Sweden. The highlevel waste is vitrified and can be sent back to Sweden in the 1990s. 3) Vitrified waste is stored for about 30 years awaiting deposition in the final repository. 4) The waste is encapsulated in highly durable materials to prevent groundwater from coming into contact with the waste glass while the radioactivity of the waste is still high. 5) The canisters are emplaced in a final repository which is built at a depth of 500 m in rock of low permeability. 6) All tunnels and shafts are filled with a mixture of clay and sand of low permeability. A detailed analysis of possible harmful effects resulting from normal acitivties and from conceivable accidents is presented in a special section. (author)

Transition projects FY 1995 multi-year program/fiscal year work plan WBS 1.3.1. and 7.1

Energy Technology Data Exchange (ETDEWEB)

1994-09-01

The primary Transition Projects mission is to deactivate facilities on the Hanford site, in preparation for decontamination and decommissioning, and secondarily to provide safe and secure storage of special nuclear materials, nuclear materials, and nuclear fuel. Transition projects will protect the health and safety of the public and of workers, protect the environment, and provide beneficial use of the facilities and other resources. Goals include the following: Achieve deactivation of facilities for transfer to the Hanford Surplus Facility Program, suing PUREX plant deactivation as a model; Achieve excellence in the conduct of operations and maintenance of nuclear facilities in support of the Hanford Site Mission; manage nuclear materials in a safe and secure condition; treat nuclear materials as necessary and store onsite in long-term interim safe storage awaiting a final disposition decision. Description of the program and projects is included.

Transition projects FY 1995 multi-year program/fiscal year work plan WBS 1.3.1. and 7.1

International Nuclear Information System (INIS)

1994-09-01

The primary Transition Projects mission is to deactivate facilities on the Hanford site, in preparation for decontamination and decommissioning, and secondarily to provide safe and secure storage of special nuclear materials, nuclear materials, and nuclear fuel. Transition projects will protect the health and safety of the public and of workers, protect the environment, and provide beneficial use of the facilities and other resources. Goals include the following: Achieve deactivation of facilities for transfer to the Hanford Surplus Facility Program, suing PUREX plant deactivation as a model; Achieve excellence in the conduct of operations and maintenance of nuclear facilities in support of the Hanford Site Mission; manage nuclear materials in a safe and secure condition; treat nuclear materials as necessary and store onsite in long-term interim safe storage awaiting a final disposition decision. Description of the program and projects is included

Transfer of Plutonium-Uranium Extraction Plant and N Reactor irradiated fuel for storage at the 105-KE and 105-KW fuel storage basins, Hanford Site, Richland Washington

International Nuclear Information System (INIS)

1995-07-01

The U.S. Department of Energy (DOE) needs to remove irradiated fuel from the Plutonium-Uranium Extraction (PUREX) Plant and N Reactor at the Hanford Site, Richland, Washington, to stabilize the facilities in preparation for decontamination and decommissioning (D ampersand D) and to reduce the cost of maintaining the facilities prior to D ampersand D. DOE is proposing to transfer approximately 3.9 metric tons (4.3 short tons) of unprocessed irradiated fuel, by rail, from the PUREX Plant in the 200 East Area and the 105 N Reactor (N Reactor) fuel storage basin in the 100 N Area, to the 105-KE and 105-KW fuel storage basins (K Basins) in the 100 K Area. The fuel would be placed in storage at the K Basins, along with fuel presently stored, and would be dispositioned in the same manner as the other existing irradiated fuel inventory stored in the K Basins. The fuel transfer to the K Basins would consolidate storage of fuels irradiated at N Reactor and the Single Pass Reactors. Approximately 2.9 metric tons (3.2 short tons) of single-pass production reactor, aluminum clad (AC) irradiated fuel in four fuel baskets have been placed into four overpack buckets and stored in the PUREX Plant canyon storage basin to await shipment. In addition, about 0.5 metric tons (0.6 short tons) of zircaloy clad (ZC) and a few AC irradiated fuel elements have been recovered from the PUREX dissolver cell floors, placed in wet fuel canisters, and stored on the canyon deck. A small quantity of ZC fuel, in the form of fuel fragments and chips, is suspected to be in the sludge at the bottom of N Reactor's fuel storage basin. As part of the required stabilization activities at N Reactor, this sludge would be removed from the basin and any identifiable pieces of fuel elements would be recovered, placed in open canisters, and stored in lead lined casks in the storage basin to await shipment. A maximum of 0.5 metric tons (0.6 short tons) of fuel pieces is expected to be recovered

Developing new transportable storage casks for interim dry storage

Energy Technology Data Exchange (ETDEWEB)

Hayashi, K.; Iwasa, K.; Araki, K.; Asano, R. [Hitachi Zosen Diesel and Engineering Co., Ltd., Tokyo (Japan)

2004-07-01

Transportable storage metal casks are to be consistently used during transport and storage for AFR interim dry storage facilities planning in Japan. The casks are required to comply with the technical standards of regulations for both transport (hereinafter called ''transport regulation'') and storage (hereafter called ''storage regulation'') to maintain safety functions (heat transfer, containment, shielding and sub-critical control). In addition to these requirements, it is not planned in normal state to change the seal materials during storage at the storage facility, therefore it is requested to use same seal materials when the casks are transported after storage period. The dry transportable storage metal casks that satisfy the requirements have been developed to meet the needs of the dry storage facilities. The basic policy of this development is to utilize proven technology achieved from our design and fabrication experience, to carry out necessary verification for new designs and to realize a safe and rational design with higher capacity and efficient fabrication.

Emotions while awaiting lung transplantation: A comprehensive qualitative analysis

Directory of Open Access Journals (Sweden)

Aurelia Brügger

2014-12-01

Full Text Available Patients awaiting lung transplantation are at risk of negative emotional and physical experiences. How do they talk about emotions? Semi-structured interviews were performed (15 patients. Categorical analysis focusing on emotion-related descriptions was organized into positive–negative–neutral descriptions: for primary and secondary emotions, evaluation processes, coping strategies, personal characteristics, emotion descriptions associated with physical states, (and contexts were listed. Patients develop different strategies to maintain positive identity and attitude, while preserving significant others from extra emotional load. Results are discussed within various theoretical and research backgrounds, in emphasizing their importance in the definition of emotional support starting from the patient’s perspective.

Emotions while awaiting lung transplantation: A comprehensive qualitative analysis

Science.gov (United States)

Brügger, Aurelia; Aubert, John-David

2014-01-01

Patients awaiting lung transplantation are at risk of negative emotional and physical experiences. How do they talk about emotions? Semi-structured interviews were performed (15 patients). Categorical analysis focusing on emotion-related descriptions was organized into positive–negative–neutral descriptions: for primary and secondary emotions, evaluation processes, coping strategies, personal characteristics, emotion descriptions associated with physical states, (and) contexts were listed. Patients develop different strategies to maintain positive identity and attitude, while preserving significant others from extra emotional load. Results are discussed within various theoretical and research backgrounds, in emphasizing their importance in the definition of emotional support starting from the patient’s perspective. PMID:28070345

The safe removal of frozen air from the annulus of an LH2 storage tank

Science.gov (United States)

Krenn, A.; Starr, S.; Youngquist, R.; Nurge, M.; Sass, J.; Fesmire, J.; Cariker, C.; Bhattacharya, A.

2015-12-01

Large Liquid Hydrogen (LH2) storage tanks are vital infrastructure for NASA. Eventually, air may leak into the evacuated and perlite filled annular region of these tanks. Although the vacuum level is monitored in this region, the extremely cold temperature causes all but the helium and neon constituents of air to freeze. A small, often unnoticeable pressure rise is the result. As the leak persists, the quantity of frozen air increases, as does the thermal conductivity of the insulation system. Consequently, a notable increase in commodity boil-off is often the first indicator of an air leak. Severe damage can result from normal draining of the tank. The warming air will sublimate which will cause a pressure rise in the annulus. When the pressure increases above the triple point, the frozen air will begin to melt and migrate downward. Collection of liquid air on the carbon steel outer shell may chill it below its ductility range, resulting in fracture. In order to avoid a structural failure, as described above, a method for the safe removal of frozen air is needed. A thermal model of the storage tank has been created using SINDA/FLUINT modelling software. Experimental work is progressing in an attempt to characterize the thermal conductivity of a perlite/frozen nitrogen mixture. A statistical mechanics model is being developed in parallel for comparison to experimental work. The thermal model will be updated using the experimental/statistical mechanical data, and used to simulate potential removal scenarios. This paper will address methodologies and analysis techniques for evaluation of two proposed air removal methods.

Safety aspects of dry spent fuel storage and spent fuel management

International Nuclear Information System (INIS)

Botsch, W.; Smalian, S.; Hinterding, P.; Voelzke, H.; Wolff, D.; Kasparek, E.

2014-01-01

The storage of spent nuclear fuel (SF) and high-level radioactive waste (HLW) must conform to safety requirements. Safety aspects like safe enclosure of radioactive materials, safe removal of decay heat, nuclear criticality safety and avoidance of unnecessary radiation exposure must be achieved throughout the storage period. The implementation of these safety requirements can be achieved by dry storage of SF and HLW in casks as well as in other systems such as dry vault storage systems or spent fuel pools, where the latter is neither a dry nor a passive system. In Germany dual purpose casks for SF or HLW are used for safe transportation and interim storage. TUV and BAM, who work as independent experts for the competent authorities, present the storage licensing process including sites and casks and inform about spent nuclear fuel management and issues concerning dry storage of spent nuclear fuel, based on their long experience in these fields (authors)

Results of ultrasonic testing evaluations on UF6 storage cylinders

International Nuclear Information System (INIS)

Lykins, M.L.

1997-02-01

The three site cylinder management program is responsible for the safe storage of the DOE owned UF 6 storage cylinders at PORTS, PGDP and at the K-25 site. To ensure the safe storage of the UF 6 in the cylinders, the structural integrity of the cylinders must be evaluated. This report represents the latest cylinder integrity investigation that utilized wall thickness evaluations to identify thinning due to atmospheric exposure

Corrosion of aluminum-clad alloys in wet spent fuel storage

International Nuclear Information System (INIS)

Howell, J.P.

1995-09-01

Large quantities of Defense related spent nuclear fuels are being stored in water basins around the United States. Under the non-proliferation policy, there has been no processing since the late 1980's and these fuels are caught in the pipeline awaiting processing or other disposition. At the Savannah River Site, over 200 metric tons of aluminum clad fuel are being stored in four water filled basins. Some of this fuel has experienced significant pitting corrosion. An intensive effort is underway at SRS to understand the corrosion problems and to improve the basin storage conditions for extended storage requirements. Significant improvements have been accomplished during 1993-1995, but the ultimate solution is to remove the fuel from the basins and to process it to a more stable form using existing and proven technology. This report presents a discussion of the fundamentals of aluminum alloy corrosion as it pertains to the wet storage of spent nuclear fuel. It examines the effects of variables on corrosion in the storage environment and presents the results of corrosion surveillance testing activities at SRS, as well as other fuel storage basins within the Department of Energy production sites

Safety guide of safe use of industrial radiography

International Nuclear Information System (INIS)

1994-01-01

The objective of this guidance is to present general regulations for the safe use and radiation protection of industrial radiography. Storage and inspection of apparatus, personal instructions for working in radiography facilities are offered

Recommended Practices for the Safe Design and Operation of Flywheels

Energy Technology Data Exchange (ETDEWEB)

Bender, Donald Arthur [Sandia National Lab. (SNL-CA), Livermore, CA (United States); Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)

2015-12-01

Flywheel energy storage systems are in use globally in increasing numbers . No codes pertaining specifically to flywheel energy storage exist. A number of industrial incidents have occurred. This protocol recommends a technical basis for safe flywheel de sign and operation for consideration by flywheel developers, users of flywheel systems and standards setting organizations.

The corrosion of aluminum-clad spent nuclear fuel in wet basin storage

International Nuclear Information System (INIS)

Howell, J.P.; Burke, S.D.

1996-01-01

Large quantities of Defense related spent nuclear fuels are being stored in water basins around the United States. Under the non-proliferation policy, there has been no processing since the late 1980's and these fuels are caught in the pipeline awaiting stabilization or other disposition. At the Savannah River Site, over 200 metric tons of aluminum clad fuel are being stored in four water filled basins. Some of this fuel has experienced visible pitting corrosion. An intensive effort is underway at SRS to understand the corrosion problems and to improve the basin storage conditions for extended storage requirements. Significant improvements have been accomplished during 1993-1996. This paper presents a discussion of the fundamentals of aluminum alloy corrosion as it pertains to the wet storage of spent nuclear fuel. It examines the effects of variables on corrosion in the storage environment and presents the results of corrosion surveillance testing activities at SRS, as well as discussions of fuel storage basins at other production sites of the Department of Energy

The corrosion of aluminum-clad spent nuclear fuel in wet basin storage

Energy Technology Data Exchange (ETDEWEB)

Howell, J.P.; Burke, S.D.

1996-02-20

Large quantities of Defense related spent nuclear fuels are being stored in water basins around the United States. Under the non-proliferation policy, there has been no processing since the late 1980`s and these fuels are caught in the pipeline awaiting stabilization or other disposition. At the Savannah River Site, over 200 metric tons of aluminum clad fuel are being stored in four water filled basins. Some of this fuel has experienced visible pitting corrosion. An intensive effort is underway at SRS to understand the corrosion problems and to improve the basin storage conditions for extended storage requirements. Significant improvements have been accomplished during 1993-1996. This paper presents a discussion of the fundamentals of aluminum alloy corrosion as it pertains to the wet storage of spent nuclear fuel. It examines the effects of variables on corrosion in the storage environment and presents the results of corrosion surveillance testing activities at SRS, as well as discussions of fuel storage basins at other production sites of the Department of Energy.

Safe havens in Europe: Switzerland and the ten dwarfs

Directory of Open Access Journals (Sweden)

Martin Paldam

2013-12-01

Full Text Available Eleven safe havens exist in Europe providing offshore banking and low taxes. Ten of these states are very small while Switzerland is moderately small. All 11countries are richer than their large neighbors. It is shown that causality is from small to safe haven towealth, and that theoretically equilibriums are likely to exist where a certain regulation is substantially lower in a small country than in its big neighbor. This generates a large capital inflow to the safe havens. The pool of funds that may reach the safe havens is shown to be huge. It is far in excess of the absorptive capacity of the safe havens, but it still explains, why they are rich. Microstates offer a veil of anonymity to funds passing through, and Switzerland offers safe storage of funds.

Plutonium safe handling

International Nuclear Information System (INIS)

Tvehlov, Yu.

2000-01-01

The abstract, prepared on the basis of materials of the IAEA new leadership on the plutonium safe handling and its storage (the publication no. 9 in the Safety Reports Series), aimed at presenting internationally acknowledged criteria on the radiation danger evaluation and summarizing the experience in the safe management of great quantities of plutonium, accumulated in the nuclear states, is presented. The data on the weapon-class and civil plutonium, the degree of its danger, the measures for provision of its safety, including the data on accident radiation consequences with the fission number 10 18 , are presented. The recommendations, making it possible to eliminate the super- criticality danger, as well as ignition and explosion, to maintain the tightness of the facility, aimed at excluding the radioactive contamination and the possibility of internal irradiation, to provide for the plutonium security, physical protection and to reduce irradiation are given [ru

Long-term storage and safe retrieval of DNA from microorganisms for molecular analysis using FTA matrix cards.

Science.gov (United States)

Rajendram, D; Ayenza, R; Holder, F M; Moran, B; Long, T; Shah, H N

2006-12-01

We assessed the potential use of Whatman FTA paper as a device for archiving and long-term storage of bacterial cell suspensions of over 400 bacterial strains representing 61 genera, the molecular applications of immobilised DNA on FTA paper, and tested its microbial inactivation properties. The FTA paper extracted bacterial DNA is of sufficiently high quality to successfully carryout the molecular detection of several key genes including 16S rRNA, esp (Enterococcus surface protein), Bft (Bacteroides fragilis enterotoxin) and por (porin protein) by PCR and for DNA fingerprinting by random amplified polymorphic DNA-PCR (RAPD-PCR). To test the long-term stability of the FTA immobilised DNA, 100 of the 400 archived bacterial samples were randomly selected following 3 years of storage at ambient temperature and PCR amplification was used to monitor its success. All of the 100 samples were successfully amplified using the 16S rDNA gene as a target and confirmed by DNA sequencing. Furthermore, the DNA was eluted into solution from the FTA cards using a new alkaline elution procedure for evaluation by real-time PCR-based assays. The viability of cells retained on the FTA cards varied among broad groups of bacteria. For the more fragile gram-negative species, no viable cells were retained even at high cell densities of between 10(7) and 10(8) colony forming units (cfu) ml(-1), and for the most robust species such as spore-formers and acid-fast bacteria, complete inactivation was achieved at cell densities ranging between 10(1) and 10(4) cfu ml(-1). The inactivation of bacterial cells on FTA cards suggest that this is a safe medium for the storage and transport of bacterial nucleic acids.

A community-based cluster randomised trial of safe storage to reduce pesticide self-poisoning in rural Sri Lanka

DEFF Research Database (Denmark)

Pearson, Melissa; Konradsen, Flemming; Gunnell, David

2011-01-01

. One approach to reducing access to pesticides is for households to store pesticides in lockable "safe-storage" containers. However, before this approach can be promoted, evidence is required on its effectiveness and safety. Methods/Design A community-based cluster randomised controlled trial has been...... at the 5% significance level. Secondary outcomes will include the incidence of all pesticide poisoning and total self-harm. Discussion This paper describes a large effectiveness study of a community intervention to reduce the burden of intentional poisoning in rural Sri Lanka. The study builds on a strong...... partnership between provincial health services, local and international researchers, and local communities. We discuss issues in relation to randomisation and contamination, engaging control villages, the intervention, and strategies to improve adherence. Trial Registritation The trial is registered...

A present status for dry storage of spent nuclear fuel

Energy Technology Data Exchange (ETDEWEB)

Bang, K. S.; Lee, J. C.; Park, H. Y.; Seo, K. S

2003-04-01

National policy for management of a spent nuclear fuel does not establish in Korea yet. A storage capacity of a storage pool that is to store the spent nuclear fuel will be exceeded an amount of accumulation from the first Woljin nuclear power plant in 2007. Therefore it is necessary that dry storage facility is secured to store safely the spent nuclear fuel on site of the nuclear power plant until national policy for a back-end spent nuclear fuel cycle is established. In order to store safely spent nuclear fuel, it is important that the present status and technology on dry storage of spent nuclear fuel is looked over. Therefore, the present status on dry storage of spent nuclear fuel was analyzed so as to develop dry storage system and choose a proper dry storage method domestic.

Nuclear hydrogen production and its safe handling

International Nuclear Information System (INIS)

Chung, Hongsuk; Paek, Seungwoo; Kim, Kwang-Rag; Ahn, Do-Hee; Lee, Minsoo; Chang, Jong Hwa

2003-01-01

An overview of the hydrogen related research presently undertaken at the Korea Atomic Energy Research Institute are presented. These encompass nuclear hydrogen production, hydrogen storage, and the safe handling of hydrogen, High temperature gas-cooled reactors can play a significant role, with respect to large-scale hydrogen production, if used as the provider of high temperature heat in fossil fuel conversion or thermochemical cycles. A variety of potential hydrogen production methods for high temperature gas-cooled reactors were analyzed. They are steam reforming of natural gas, thermochemical cycles, etc. The produced hydrogen should be stored safely. Titanium metal was tested primarily because its hydride has very low dissociation pressures at normal storage temperatures and a high capacity for hydrogen, it is easy to prepare and is non-reactive with air in the expected storage conditions. There could be a number of potential sources of hydrogen evolution risk in a nuclear hydrogen production facility. In order to reduce the deflagration detonation it is necessary to develop hydrogen control methods that are capable of dealing with the hydrogen release rate. A series of experiments were conducted to assess the catalytic recombination characteristics of hydrogen in an air stream using palladium catalysts. (author)

Why Do Parents with Toddlers Store Poisonous Products Safely?

Directory of Open Access Journals (Sweden)

Tinneke M. J. Beirens

2010-01-01

Full Text Available Unintentional poisoning is a major cause of nonfatal injuries in children aged 0–24 months. Associations between self-reported habits on the child safe storage of medication and cleaning products and family, and psychosocial factors were assessed, using a model based on the Protection Motivation Theory. By identifying correlates of safety behavior in this manner, more insight in factors which influence this behavior is obtained. Health promotion activities in order to promote safety behavior should address these factors in order to increase the effectiveness of the health message. Data were gathered from a cross-sectional survey using self-administered questionnaires, mailed to a population sample of 2470 parents with toddlers. The results indicate that the promotion of safe storage of medication and cleaning products should address the family situation, personal cognitive factors as well as social factors. Interventions should particularly focus on parents' self-efficacy of storing poisonous products in a child safe manner and on the vulnerability of their child in their home concerning an unintentional poisoning incident.

Inherently safe passive gas monitoring system

Energy Technology Data Exchange (ETDEWEB)

Cordaro, Joseph V.; Bellamy, John Stephen; Shuler, James M.; Shull, Davis J.; Leduc, Daniel R.

2016-09-06

Generally, the present disclosure is directed to gas monitoring systems that use inductive power transfer to safely power an electrically passive device included within a nuclear material storage container. In particular, the electrically passive device can include an inductive power receiver for receiving inductive power transfer through a wall of the nuclear material storage container. The power received by the inductive power receiver can be used to power one or more sensors included in the device. Thus, the device is not required to include active power generation components such as, for example, a battery, that increase the risk of a spark igniting flammable gases within the container.

Long-term stable, long-term safe storage of residues and radioactive waste. Contribution to discussion to the storage (final storage); Langzeitstabile, langzeitsichere Verwahrung von Rueckstaenden und radioaktiven Abfaellen. Beitrag zur Diskussion um Lagerung (Endlagerung)

Energy Technology Data Exchange (ETDEWEB)

Lersow, Michael [DGGT e.V., Breitenbrunn/Erzgeb. (Germany). Ak 5.5 Tailings; Gellermann, Rainer [Nuclear Control and Consulting GmbH, Braunschweig (Germany)

2015-09-15

In this paper it is presented, where radioactive waste and residues occur, how these materials can be classified, which rules and regulations have to be complied with regarding the disposal and which geotechnical environmental constructions (final repositories) are suitable to guarantee a safe long-term disposal of these materials. Primary protection objective is ''to permanently prevent the transfer of toxic, radioactive contaminations into the biosphere by air, water or rock path or to keep the amount of contamination within a commonly accepted range''. Radionuclide inventories and the given time period considered for long-term safety are compared with. It is shown, that the site-specific disposal solutions cannot be justified by the radioactive inventory deposited there. The given period of 10{sup 6} years is critically evaluated. Based on this it is suggested to subdivide this period into two time periods with different prognosis reliabilities. Results of a specially designed long-term monitoring as part of the site-specific waste disposal solution should be considered for the long-term safety proof. A modular concept for the final storage of High Active Waste (HAW) is derived based on the critical evaluation of the long-term safety, including transmutation, provisional storage and monitoring module. A foundation model is proposed to guarantee the financial resources required for the disposal of HAW.

Manual on safe production, transport, handling and storage of uranium hexafluoride

International Nuclear Information System (INIS)

1994-11-01

This document includes a description of the physical, chemical and radiological properties of UF 6 and related products, including information concerning their production, handling, storage and transportation and the management of the wastes which result. All the operations of UF 6 management are considered form a safety point of view. The IAEA organized a series of meetings to consider the hazards of UF 6 transport since considerable quantities of depleted, natural and enriched UF 6 are transported between nuclear fuel sites. Storage of depleted UF 6 is another important issue. Factors affecting long term storage are presented, especially site choice and cylinder corrosion. Other topics such as waste management, quality assurance and emergency preparedness which contribute to the overall safety of UF 6 handling, are included. The intention of this document is to provide analysis of the safety implications of all stages of UF 6 operations and to draw attention to specific features and properties of importance. 38 refs, figs, tabs

Documented Safety Analysis for the Waste Storage Facilities

Energy Technology Data Exchange (ETDEWEB)

Laycak, D

2008-06-16

This documented safety analysis (DSA) for the Waste Storage Facilities was developed in accordance with 10 CFR 830, Subpart B, 'Safety Basis Requirements', and utilizes the methodology outlined in DOE-STD-3009-94, Change Notice 3. The Waste Storage Facilities consist of Area 625 (A625) and the Decontamination and Waste Treatment Facility (DWTF) Storage Area portion of the DWTF complex. These two areas are combined into a single DSA, as their functions as storage for radioactive and hazardous waste are essentially identical. The B695 Segment of DWTF is addressed under a separate DSA. This DSA provides a description of the Waste Storage Facilities and the operations conducted therein; identification of hazards; analyses of the hazards, including inventories, bounding releases, consequences, and conclusions; and programmatic elements that describe the current capacity for safe operations. The mission of the Waste Storage Facilities is to safely handle, store, and treat hazardous waste, transuranic (TRU) waste, low-level waste (LLW), mixed waste, combined waste, nonhazardous industrial waste, and conditionally accepted waste generated at LLNL (as well as small amounts from other DOE facilities).

DOE handbook: Tritium handling and safe storage

Energy Technology Data Exchange (ETDEWEB)

NONE

1999-03-01

The DOE Handbook was developed as an educational supplement and reference for operations and maintenance personnel. Most of the tritium publications are written from a radiological protection perspective. This handbook provides more extensive guidance and advice on the null range of tritium operations. This handbook can be used by personnel involved in the full range of tritium handling from receipt to ultimate disposal. Compliance issues are addressed at each stage of handling. This handbook can also be used as a reference for those individuals involved in real time determination of bounding doses resulting from inadvertent tritium releases. This handbook provides useful information for establishing processes and procedures for the receipt, storage, assay, handling, packaging, and shipping of tritium and tritiated wastes. It includes discussions and advice on compliance-based issues and adds insight to those areas that currently possess unclear DOE guidance.

DOE handbook: Tritium handling and safe storage

International Nuclear Information System (INIS)

1999-03-01

The DOE Handbook was developed as an educational supplement and reference for operations and maintenance personnel. Most of the tritium publications are written from a radiological protection perspective. This handbook provides more extensive guidance and advice on the null range of tritium operations. This handbook can be used by personnel involved in the full range of tritium handling from receipt to ultimate disposal. Compliance issues are addressed at each stage of handling. This handbook can also be used as a reference for those individuals involved in real time determination of bounding doses resulting from inadvertent tritium releases. This handbook provides useful information for establishing processes and procedures for the receipt, storage, assay, handling, packaging, and shipping of tritium and tritiated wastes. It includes discussions and advice on compliance-based issues and adds insight to those areas that currently possess unclear DOE guidance

Manual on safe production, transport, handling and storage of uranium hexafluoride

Energy Technology Data Exchange (ETDEWEB)

NONE

1994-11-01

This document includes a description of the physical, chemical and radiological properties of UF{sub 6} and related products, including information concerning their production, handling, storage and transportation and the management of the wastes which result. All the operations of UF{sub 6} management are considered form a safety point of view. The IAEA organized a series of meetings to consider the hazards of UF{sub 6} transport since considerable quantities of depleted, natural and enriched UF{sub 6} are transported between nuclear fuel sites. Storage of depleted UF{sub 6} is another important issue. Factors affecting long term storage are presented, especially site choice and cylinder corrosion. Other topics such as waste management, quality assurance and emergency preparedness which contribute to the overall safety of UF{sub 6} handling, are included. The intention of this document is to provide analysis of the safety implications of all stages of UF{sub 6} operations and to draw attention to specific features and properties of importance. 38 refs, figs, tabs.

Judy Collins and First Lady Hillary Clinton await the launch of STS-93

Science.gov (United States)

1999-01-01

Singer Judy Collins (left) and First Lady Hillary Rodham Clinton await the launch of Space Shuttle mission STS-93 in the Apollo/Saturn V Facility. Liftoff is scheduled for 12:36 a.m. EDT July 20. Much attention has been generated over the launch due to Commander Eileen M. Collins, the first woman to serve as commander of a Shuttle mission. Judy Collins has honored the commander with a song, 'Beyond the Sky,' which was commissioned by NASA through the NASA Art Program.

Storage of nuclear wastes

International Nuclear Information System (INIS)

Ahlstroem, P.E.

1988-01-01

The Swedish system of handling and storage of nuclear wastes is well-developed. Existing plants and systems provide great freedom of action and flexibility regarding future development and decisions of ultimate storage of the spent fuel. The interim storage in CLAB - Central interim storage facility for spent nuclear fuel - could continue without any safety related problems for more than 40 years. In practice the choice of ultimate treatment system is not locked until the encapsulation of the fuel starts. At the same time it is of importance that the generation benefiting by the nuclear power production also be responsible for the development of the ultimate storage system and not unnecessarily postpones important decisions. The ultimate storage system for spent fuel could and should be developed within existing schedule. At the same time is should be worked out to provide coming generations with possibilities to do the type of supervision they like without maintenance and supervision requiring to become a prerequisite for a safe function. (O.S.)

Hydrogen - High pressure production and storage

International Nuclear Information System (INIS)

Lauretta, J.R

2005-01-01

The development of simple, safe and more and more efficient technologies for the production and the storage of hydrogen is necessary condition for the transition towards the economy of hydrogen.In this work the hydrogen production studies experimentally to high pressure by electrolysis of alkaline solutions without the intervention of compressing systems and its direct storage in safe containers.The made tests show that the process of electrolysis to high pressure is feasible and has better yield than to low pressure, and that is possible to solve the operation problems, with relatively simple technology.The preliminary studies and tests indicate that the system container that studied is immune to the outbreak and can have forms and very different sizes, nevertheless, to reach or to surpass the efficiency of storage of the conventional systems the investments necessary will be due to make to be able to produce aluminum alloy tubes of high resistance

Final Hazard Classification and Auditable Safety Analysis for the 105-F Building Interim Safe Storage Project

International Nuclear Information System (INIS)

Rodovsky, T.J.; Bond, S.L.

1998-07-01

The auditable safety analysis (ASA) documents the authorization basis for the partial decommissioning and facility modifications to place the 105-F Building into interim safe storage (ISS). Placement into the ISS is consistent with the preferred alternative identified in the Record of Decision (58 FR). Modifications will reduce the potential for release and worker exposure to hazardous and radioactive materials, as well as lower surveillance and maintenance (S ampersand M) costs. This analysis includes the following: A description of the activities to be performed in the course of the 105-F Building ISS Project. An assessment of the inventory of radioactive and other hazardous materials within the 105-F Building. Identification of the hazards associated with the activities of the 105-F Building ISS Project. Identification of internally and externally initiated accident scenarios with the potential to produce significant local or offsite consequences during the 105-F Building ISS Project. Bounding evaluation of the consequences of the potentially significant accident scenarios. Hazard classification based on the bounding consequence evaluation. Associated safety function and controls, including commitments. Radiological and other employee safety and health considerations

Design and fabrication of transport/storage packaging for spent fuels

International Nuclear Information System (INIS)

Nagahama, Hayao; Kakunai, Haruo

1989-01-01

Dry storage in containers is one of several methods for storing spent fuel dischaged from nuclear power plants. Kobe Steel and Transnucleaire (France) have jointly developed large-capacity, safe transport/storage packaging for use in this storage method. This paper outlines the packaging, the manufacturing of a prototype model, and an active storage demonstration test involving the prototype model. (author)

[Storage of plant protection products in farms: minimum safety requirements].

Science.gov (United States)

Dutto, Moreno; Alfonzo, Santo; Rubbiani, Maristella

2012-01-01

Failure to comply with requirements for proper storage and use of pesticides in farms can be extremely hazardous and the risk of accidents involving farm workers, other persons and even animals is high. There are still wide differences in the interpretation of the concept of "securing or making safe", by workers in this sector. One of the critical points detected, particularly in the fruit sector, is the establishment of an adequate storage site for plant protection products. The definition of "safe storage of pesticides" is still unclear despite the recent enactment of Legislative Decree 81/2008 regulating health and work safety in Italy. In addition, there are no national guidelines setting clear minimum criteria for storage of plant protection products in farms. The authors, on the basis of their professional experience and through analysis of recent legislation, establish certain minimum safety standards for storage of pesticides in farms.

New developments in dry spent fuel storage

International Nuclear Information System (INIS)

Bonnet, C.; Chevalier, Ph.

2001-01-01

As shown in various new examples, HABOG facility (Netherlands), CERNAVODA (Candu - Romania), KOZLODUY (WWER - Bulgaria), CHERNOBYL ( RMBK - Ukraine), MAYAK (Spent Fuel from submarine and Icebreakers - Russia), recent studies allow to confirm the flexibility and performances of the CASCAD system proposed by SGN, both in safety and operability, for the dry storage of main kinds of spent fuel. The main features are: A multiple containment barrier system: as required by international regulation, 2 independent barriers are provided (tight canister and storage pit); Passive cooling, while the Fuel Assemblies are stored in an inert atmosphere and under conditions of temperature preventing from degradation of rod cladding; Sub-criticality controlled by adequate arrangements in any conditions; Safe facility meeting ICPR 60 Requirements as well as all applicable regulations (including severe weather conditions and earthquake); Safe handling operations; Retrievability of the spent fuel either during storage period or at the end of planned storage period (100 years); Future Decommissioning of the facility facilitated through design optimisation; Construction and operating cost-effectiveness. (author)

Safe extension of red blood cell storage life at 4{degree}C

Energy Technology Data Exchange (ETDEWEB)

Bitensky, M.; Yoshida, Tatsuro

1996-04-01

The project sought to develop methods to extend the storage life of red blood cells. Extended storage would allow donor to self or autologous transfusion, expand and stabilize the blood supply, reduce the cost of medical care and eliminate the risk of transfusion related infections, including a spectrum of hepatitides (A, B and C) and HIV. The putative cause of red blood cell spoilage at 4 C has been identified as oxidative membrane damage resulting from deoxyhemoglobin and its denaturation products including hemichrome, hemin and Fe{sup 3+}. Trials with carbon monoxide, which is a stabilizer of hemoglobin, have produced striking improvement of red blood cell diagnostics for cells stored at 4 C. Carbonmonoxy hemoglobin is readily converted to oxyhemoglobin by light in the presence of oxygen. These findings have generated a working model and an approach to identify the best protocols for optimal red cell storage and hemoglobin regeneration.

Scheme of higher-density storage of spent nuclear fuel in Chernobyl NPP interim storage facility no. 1

International Nuclear Information System (INIS)

Britan, P.M.

2008-01-01

On 29. March 2000 the Cabinet of Ministers of Ukraine issued a decree prescribing that the last operating unit of Chernobyl NPP be shut down before its design lifetime expiry. In accordance with the Contract concluded on 14 June 1999 between the National Energy-generating Company 'Energoatom' and the Consortium of Framatome, Campenon Bernard-SGE and Bouygues, in order to store the spent ChNPP fuel a new interim dry storage facility (ISF-2) for spent ChNPP fuel would be built. Currently the spent nuclear fuel (spent fuel assemblies - SFAs) is stored in reactor cooling pools and in the reactors on Units 1, 2, 3, as well as in the wet Interim Storage Facility (ISF-1). Taking into account the expected delay with the commissioning of ISF-2, and in connection with the scheduled activities to build the New Safe Confinement (including the taking-down of the existing ventilation stack of ChNPP Units 3 and 4) and the expiry of the design operation life of Units 1 and 2, it is expedient to remove the nuclear fuel from Units 1, 2 and 3. This is essential to improve nuclear safety and ensure that the schedule of construction of the New Safe Confinement is met. The design capacity of ISF-1 (17 800 SFAs) is insufficient to store all SFAs (21 284) currently on ChNPP. A technically feasible option that has been applied on other RBMK plants is denser storage of spent nuclear fuel in the cooling ponds of the existing ISF-1. The purpose of the proposed modifications is to introduce changes to the ISF-1 design supported by necessary justifications required by the Ukrainian codes with the objective of enabling the storage of additional SFAs in the existing storage space (cooling pools). The need for the modification is caused by the requirement to remove nuclear fuel from the ChNPP units as soon as possible, before the work begins to decommission these units, as well as to create safe conditions for the construction of the New Safe Confinement over the existing Shelter Unit. (author)

Documented Safety Analysis for the Waste Storage Facilities March 2010

Energy Technology Data Exchange (ETDEWEB)

Laycak, D T

2010-03-05

This Documented Safety Analysis (DSA) for the Waste Storage Facilities was developed in accordance with 10 CFR 830, Subpart B, 'Safety Basis Requirements,' and utilizes the methodology outlined in DOE-STD-3009-94, Change Notice 3. The Waste Storage Facilities consist of Area 625 (A625) and the Decontamination and Waste Treatment Facility (DWTF) Storage Area portion of the DWTF complex. These two areas are combined into a single DSA, as their functions as storage for radioactive and hazardous waste are essentially identical. The B695 Segment of DWTF is addressed under a separate DSA. This DSA provides a description of the Waste Storage Facilities and the operations conducted therein; identification of hazards; analyses of the hazards, including inventories, bounding releases, consequences, and conclusions; and programmatic elements that describe the current capacity for safe operations. The mission of the Waste Storage Facilities is to safely handle, store, and treat hazardous waste, transuranic (TRU) waste, low-level waste (LLW), mixed waste, combined waste, nonhazardous industrial waste, and conditionally accepted waste generated at LLNL (as well as small amounts from other DOE facilities).

Handling final storage of unreprocessed spent nuclear fuel

International Nuclear Information System (INIS)

1978-01-01

The present second report from KBS describes how the safe final storage of spent unreprocessed nuclear fuel can be implemented. According to the Swedish Stipulation Law, the owner must specify in which form the waste is to be stored, how final storage is to be effected, how the waste is to be transported and all other aspects of fuel handling and storage which must be taken into consideration in judging whether the proposed final storage method can be considered to be absolutely safe and feasible. Thus, the description must go beyond general plans and sketches. The description is therefore relatively detailed, even concerning those parts which are less essential for evaluating the safety of the waste storage method. For those parts of the handling chain which are the same for both alternatives of the Stipulation Law, the reader is referred in some cases to the first report. Both of the alternatives of the Stipulation Law may be used in the future. Handling equipment and facilities for the two storage methods are so designed that a combination in the desired proportions is practically feasible. In this first part of the report are presented: premises and data, a description of the various steps of the handling procedure, a summary of dispersal processes and a safety analysis. (author)

Development of Safe Food Handling Guidelines for Korean Consumers.

Science.gov (United States)

Kang, Hee-Jin; Lee, Min-Woo; Hwang, In-Kyeong; Kim, Jeong-Weon

2015-08-01

The purpose of this study was to develop guidelines for Korean consumers with regard to safe food handling practices at home by identifying current food handling issues. Korean consumers' behaviors regarding their safe food handling were identified via survey questionnaires that included items on individual hygiene practices, prepreparation steps when cooking, the cooking process, and the storage of leftover foods. The subjects were 417 Korean parents with elementary school children living in Seoul and Gyeonggi Province in the central area of Korea. The survey results revealed gaps between the knowledge or practices of Korean consumers and scientific evidence pertaining to safe food handling practices. Based on these findings, a leaflet on safe food handling guidelines was developed in accordance with Korean food culture. These guidelines suggest personal hygiene practices as well as fundamental principles and procedures for safe food handling from the stage of food purchase to that of keeping leftover dishes. A pilot application study with 50 consumers revealed that the guidelines effectively improved Korean consumers' safe food handling practices, suggesting that they can serve as practical educational material suitable for Korean consumers.

Implementation of Safe-by-Design for Nanomaterial Development and Safe Innovation: Why We Need a Comprehensive Approach.

Science.gov (United States)

Kraegeloh, Annette; Suarez-Merino, Blanca; Sluijters, Teun; Micheletti, Christian

2018-04-14

Manufactured nanomaterials (MNMs) are regarded as key components of innovations in various fields with high potential impact (e.g., energy generation and storage, electronics, photonics, diagnostics, theranostics, or drug delivery agents). Widespread use of MNMs raises concerns about their safety for humans and the environment, possibly limiting the impact of the nanotechnology-based innovation. The development of safe MNMs and nanoproducts has to result in a safe as well as functional material or product. Its safe use, and disposal at the end of its life cycle must be taken into account too. However, not all MNMs are similarly useful for all applications, some might bear a higher hazard potential than others, and use scenarios could lead to different exposure probabilities. To improve both safety and efficacy of nanotechnology, we think that a new proactive approach is necessary, based on pre-regulatory safety assessment and dialogue between stakeholders. On the basis of the work carried out in different European Union (EU) initiatives, developing and integrating MNMs Safe-by-Design and Trusted Environments (NANoREG, ProSafe, and NanoReg2), we present our point of view here. This concept, when fully developed, will allow for cost effective industrial innovation, and an exchange of key information between regulators and innovators. Regulators are thus informed about incoming innovations in good time, supporting a proactive regulatory action. The final goal is to contribute to the nanotechnology governance, having faster, cheaper, effective, and safer nano-products on the market.

Expansion of storage capacity of interim spent fuel storage (MSVP) Bohunice

International Nuclear Information System (INIS)

Pilat, P.; Fridrich, V.

2005-01-01

This article describes modifications of Interim spent fuel storage, performed with aim of storage capacity expansion, seismic stability enhancement, and overall increase of service life as well as assuring of MSVP safe operation. Uniqueness of adopted technical solutions is based upon the fact that mentioned innovations and modifications were performed without any changes, neither in ground plan nor architecture of MSVP structure. It also important to mention that all modifications were performed during continual operation of MSVP without any breaks of limits or operational regulations. Reconstruction and innovation of existing construction and technological systems of MSVP has assured required quality standard comparable with actual trends. (authors)

Methane storage in metal-organic frameworks.

Science.gov (United States)

He, Yabing; Zhou, Wei; Qian, Guodong; Chen, Banglin

2014-08-21

Natural gas (NG), whose main component is methane, is an attractive fuel for vehicular applications. Realization of safe, cheap and convenient means and materials for high-capacity methane storage can significantly facilitate the implementation of natural gas fuelled vehicles. The physisorption based process involving porous materials offers an efficient storage methodology and the emerging porous metal-organic frameworks have been explored as potential candidates because of their extraordinarily high porosities, tunable pore/cage sizes and easily immobilized functional sites. In this view, we provide an overview of the current status of metal-organic frameworks for methane storage.

Design of spent fuel storage facilities

International Nuclear Information System (INIS)

1994-01-01

This Safety Guide is for interim spent fuel storage facilities that are not integral part of an operating nuclear power plant. Following the introduction, Section 2 describes the general safety requirements applicable to the design of both wet and dry spent fuel storage facilities; Section 3 deals with the design requirements specific to either wet or dry storage. Recommendations for the auxiliary systems of any storage facility are contained in Section 4; these are necessary to ensure the safety of the system and its safe operation. Section 5 provides recommendations for establishing the quality assurance system for a storage facility. Section 6 discusses the requirements for inspection and maintenance that must be considered during the design. Finally, Section 7 provides guidance on design features to be considered to facilitate eventual decommissioning. 18 refs

Inventory extension considerations for long-term storage at the nuclear materials storage facility

International Nuclear Information System (INIS)

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

1996-01-01

Los Alamos National Laboratory is in the process of modifying its nuclear materials storage facility to a long-term storage configuration. In support of this effort, we examined technical and administrative means to extend periods between physical inventories. Both the frequency and sample size during a physical inventory could significantly impact required sizing of the non-destructive assay (NDA) laboratory as well as material handling capabilities. Several options are being considered, including (1) treating each storage location as a separate vault, (2) minimizing the number of items returned for quantitative analysis by optimizing the use of in situ confirmatory measurements, and (3) utilizing advanced monitoring technologies. Careful consideration of these parameters should allow us to achieve and demonstrate safe and secure storage while minimizing the impact on facility operations and without having to increase the size of the NDA laboratory beyond that required for anticipated shipping and receiving activities

Effect of laughter on mood and heart rate variability in patients awaiting organ transplantation: a pilot study.

Science.gov (United States)

Dolgoff-Kaspar, Rima; Baldwin, Ann; Johnson, Scott; Edling, Nancy; Sethi, Gulshan K

2012-01-01

Research shows that laughter has myriad health benefits, yet the medical community has not implemented it formally as a treatment. Patients awaiting organ transplantation have significant physical disabilities and are at risk for psychological distress. Attenuated heart rate variability (HRV) is a risk factor for a negative long-term outcome in some patients. The study intended to evaluate the clinical utility of laughter yoga in improving psychological and physiological measures in outpatients awaiting organ transplantation. Positive results would indicate promising areas to pursue in a follow-up study. Six participants met for 10 sessions over 4 weeks. The research team measured each participant's heart rate, HRV, blood pressure (BP), and immediate mood before and after the laughter and control interventions. The team assessed participants' longer-term mood (anxiety and depression) at the study's initiation, after a no-treatment control week, and at the end of the study. The study occurred at the Department of Surgery and Medicine at the University of Arizona Health Sciences Center, Tucson. Participants were patients awaiting transplants (three heart and three lung), two women and four men (ages 51-69 y). Participants had received no major surgery in the 3 months prior to the intervention, did not have a hernia or uncontrolled hypertension, and did not fall into the New York Heart Association function class 4. The 20-minute laughter intervention involved breathing and stretching exercises, simulated laughter (ie, unconditional laughter that is not contingent on the environment), chanting, clapping, and a meditation. The 20-minute control intervention involved the study's personnel discussing health and study-related topics with the participants. The research team measured BP, heart rate, and HRV and administered the Profile of Mood States, Beck Anxiety Inventory, and Beck Depression Inventory-II to evaluate immediate and longer-term mood. The team had planned

In-situ storage: An approach to interim remedial action - recent case studies in Canada

International Nuclear Information System (INIS)

Zelmer, R.L.

1991-01-01

The Low-Level Radioactive Waste Management Office (LLRWMO) acts on behalf of the federal government to manage historic low-level radioactive wastes. Recent interim remedial work in the Town of Port Hope, Ontario has included the consolidation of radium and uranium contaminated soils into temporary storage facilities on two sites to await final disposal elsewhere. Simple containments constructed and sited on already contaminated sites have been found effective as part of an interim remedial strategy. The approach has been accepted and supported by the local public. Lessons have been learned from a project management, environmental remediation and engineering design point of view

On-site interim storage of spent nuclear fuel: Emerging public issues

International Nuclear Information System (INIS)

Feldman, D.L.; Tennessee Univ., Knoxville, TN

1992-01-01

Failure to consummate plans for a permanent repository or above- ground interim Monitored Retrievable Storage (MRS) facility for spent nuclear fuel has spurred innovative efforts to ensure at-reactor storage in an environmentally safe and secure manner. This article examines the institutional and socioeconomic impacts of Dry Cask Storage Technology (DCST)-an approach to spent fuel management that is emerging as the preferred method of on-site interim spent fuel storage by utilities that exhaust existing storage capacity

SRS K-area material storage. Expanding capabilities

International Nuclear Information System (INIS)

Koenig, R.

2013-01-01

In support of the Department of Energy’s continued plans to de-inventory and reduce the footprint of Cold War era weapons’ material production sites, the K-Area Material Storage (KAMS) facility, located in the K-Area Complex (KAC) at the Savannah River Site reservation, has expanded since its startup authorization in 2000 to accommodate DOE’s material consolidation mission. During the facility’s growth and expansion, KAMS will have expanded its authorization capability of material types and storage containers to allow up to 8200 total shipping containers once the current expansion effort completes in 2014. Recognizing the need to safely and cost effectively manage other surplus material across the DOE Complex, KAC is constantly evaluating the storage of different material types within K area. When modifying storage areas in KAC, the Documented Safety Analysis (DSA) must undergo extensive calculations and reviews; however, without an extensive and proven security posture the possibility for expansion would not be possible. The KAC maintains the strictest adherence to safety and security requirements for all the SNM it handles. Disciplined Conduct of Operations and Conduct of Projects are demonstrated throughout this historical overview highlighting various improvements in capability, capacity, demonstrated cost effectiveness and utilization of the KAC as the DOE Center of Excellence for safe and secure storage of surplus SNM.

Design of a dry cask storage system for spent LWR fuels: radiation protection, subcriticality, and heat removal aspects

Energy Technology Data Exchange (ETDEWEB)

Yavuz, U. [Turkish Atomic Energy Authority, Ankara (Turkey). Nuclear Safety Dept.; Zabunoolu, O.H. [Hacettepe Univ., Ankara (Turkey). Dept. of Nuclear Engineering

2006-08-15

Spent nuclear fuel resulting from reactor operation must be safely stored and managed prior to reprocessing and/or final disposal of high-level waste. Any spent fuel storage system must provide for safe receipt, handling, retrieval, and storage of spent fuel. In order to achieve the safe storage, the design should primarily provide for radiation protection, subcriticality of spent fuel, and removal of spent fuel residual heat. This article is focused on the design of a metal-shielded dry-cask storage system, which will host spent LWR fuels burned to 33 000, 45 000, and 55 000 MWd/t U and cooled for 5 or 10 years after discharge from reactor. The storage system is analyzed by taking into account radiation protection, subcriticality, and heat-removal aspects; and appropriate designs, in accordance with the international standards. (orig.)

Modulated synthesis of Cr-MOF (MIL 101) for hydrogen storage applications

CSIR Research Space (South Africa)

Segakweng, T

2014-08-01

Full Text Available as a fuel into fuel cell technologies is only possible when safe and effective hydrogen storage systems become available. Complete usage of hydrogen is only possible if proper and effective storage systems with fast kinetics becomes available. Porous...

Association between preoperative magnetic resonance imaging, pain intensity and quantitative sensory testing in patients awaiting lumbar diskectomy.

LENUS (Irish Health Repository)

Hegarty, Dominic

2011-02-01

Magnetic resonance imaging (MRI) offers important information regarding the morphology, location and size of a herniated disc, which influences the decision to offer lumbar diskectomy (LD). This study aims to examine the association between clinical neurophysiologic indices including pain intensity and quantitative sensory testing (QST), and the degree of lumbar nerve root compromise depicted on magnetic resonance (MR) in patients awaiting LD.

Criticality safety evaluation for long term storage of FFTF fuel in interim storage casks

International Nuclear Information System (INIS)

Richard, R.F.

1995-01-01

It has been postulated that a degradation phenomenon, referred to as ''hot cell rot'', may affect irradiated FFTF mixed plutonium-uranium oxide (MOX) fuel during dry interim storage. ''Hot cell rot'' refers to a variety of phenomena that degrade fuel pin cladding during exposure to air and inert gas environments. It is thought to be a form of caustic stress corrosion cracking or environmentally assisted cracking. Here, a criticality safety analysis was performed to address the effect of the ''hot cell rot'' phenomenon on the long term storage of irradiated FFTF fuel in core component containers. The results show that seven FFTF fuel assemblies or six Ident-69 pin containers stored in core component containers within interim storage casks will remain safely subcritical

Safe transport of radioactive materials in Egypt

International Nuclear Information System (INIS)

El-Shinawy, R.M.K.

1994-01-01

In Egypt the national regulations for safe transport of radioactive materials (RAM) are based on the International Atomic Energy Agency (IAEA) regulations. In addition, regulations for the safe transport of these materials through the Suez Canal (SC) were laid down by the Egyptian Atomic Energy Authority (EAEA) and the Suez Canal Authority (SCA). They are continuously updated to meet the increased knowledge and the gained experience. The technical and protective measures taken during transport of RAM through SC are mentioned. Assessment of the impact of transporting radioactive materials through the Suez Canal using the INTERTRAN computer code was carried out in cooperation with IAEA. The transported activities and empty containers, the number of vessels carrying RAM through the canal from 1963 and 1991 and their nationalities are also discussed. The protective measures are mentioned. A review of the present situation of the radioactive wastes storage facilities at the Atomic Energy site at Inshas is given along with the regulation for safe transportation and disposal of radioactive wastes. (Author)

Criticality safety for TMI-2 canister storage at INEL

International Nuclear Information System (INIS)

Jones, R.R.; Briggs, J.B.; Ayers, A.L. Jr.

1986-01-01

Canisters containing Three Mile Island Unit 2 (TMI-2) core debris will be researched, stored, and prepared for final disposition at the Idaho National Engineering Laboratory (INEL). The canisters will be placed into storage modules and assembled into a storage rack, which will be located in the Test Area North (TAN) storage pool. Criticality safety calculations were made (a) to ensure that the storage rack is safe for both normal and accident conditions and (b) to determine the effects of degradation of construction materials (Boraflex and polyethylene) on criticality safety

Elusive prize: enormous coal gas potential awaits production technology breakthrough

Energy Technology Data Exchange (ETDEWEB)

Collison, M.

2002-01-07

The expanded gas pipeline grid has excess capacity, and gas resources are declining. There is increasing interest in development of Canada's resources of coalbed methane (CBM). The chairman of the Canadian Coalbed Methane Forum estimates that Canada has more than 3,000 trillion ft{sup 3} of gas awaiting suitable technology. PanCanadian and MGV Energy conducted a CBM exploration and pilot study on the Palliser spread in southern Alberta. Results from 23 of 75 wells are encouraging. The study is being accelerated and expanded to include an additional 50 wells elsewhere in Alberta. Some scientists anticipate commercial CBM production within two years. Problems facing developers include the large land holdings necessary for economic CBM production and the disposal of coal formation water. It is anticipated that U.S. technology will be modified and used. The potential for CBM development at Pictou in Nova Scotia and in British Columbia in the foothills is considered. 3 figs.

Saying goodbye to optical storage technology.

Science.gov (United States)

McLendon, Kelly; Babbitt, Cliff

2002-08-01

The days of using optical disk based mass storage devices for high volume applications like health care document imaging are coming to an end. The price/performance curve for redundant magnetic disks, known as RAID, is now more positive than for optical disks. All types of application systems, across many sectors of the marketplace are using these newer magnetic technologies, including insurance, banking, aerospace, as well as health care. The main components of these new storage technologies are RAID and SAN. SAN refers to storage area network, which is a complex mechanism of switches and connections that allow multiple systems to store huge amounts of data securely and safely.

Radioactive waste storage and disposal: the challenge

International Nuclear Information System (INIS)

Prince, A.T.

1978-03-01

Solutions to waste management problems are available. After radium is removed, tailings from uranium ores can be disposed of safely in well-designed retention areas. Work is being done on the processing of non-fuel reactor wastes through incineration, reverse osmosis, and evaporation. Spent fuels have been stored safely for years in pools; dry storage in concrete cannisters is being investigated. Ultimate disposal of high-level wastes will be in deep, stable geologic formations. (LL)

Extended storage for radioactive wastes: relevant aspects related to the safety

International Nuclear Information System (INIS)

Castillo, Reinaldo G.; Peralta V, José L.P.; Estevez, Gema G. F.

2013-01-01

The safe management of radioactive waste is an issue of great relevance globally linked to the issue of the peaceful use of nuclear energy. Among the steps in the management of this waste, the safe storage is one of the most important. Given the high costs and uncertainties existing among other aspects of the variants of disposal of radioactive waste, the prolonged storage of these wastes for periods exceeding 50 years is an option that different countries more and more value. One of the fundamental problems to take into account is the safety of the stores, so in this work are evaluated different safety components associated with these facilities through a safety analysis methodology. Elements such as human intrusion, the construction site, the design of the facility, among others are identified as some of the key aspects to take into account when evaluating the safety of these types of facilities. Periods of activities planned for a long-term storage of radioactive waste exceed, in general, the useful life of existing storage facilities. This work identified new challenges to overcome in order to meet the requirements for the achievement of a safe management of radioactive waste without negative impacts on the environment and man

Survey of wet and dry spent fuel storage

International Nuclear Information System (INIS)

1999-07-01

Spent fuel storage is one of the important stages in the nuclear fuel cycle and stands among the most vital challenges for countries operating nuclear power plants. Continuous attention is being given by the IAEA to the collection, analysis and exchange of information on spent fuel management. Its role in this area is to provide a forum for exchanging information and for coordinating and encouraging closer co-operation among Member States. Spent fuel management is recognized as a high priority IAEA activity. In 1997, the annual spent fuel arising from all types of power reactors worldwide amounted to about 10,500 tonnes heavy metal (t HM). The total amount of spent fuel accumulated worldwide at the end of 1997 was about 200,000 t HM of which about 130,000 t HM of spent fuel is presently being stored in at-reactor (AR) or away-from-reactor (AFR) storage facilities awaiting either reprocessing or final disposal and 70,000 t HM has been reprocessed. Projections indicate that the cumulative amount generated by 2010 may surpass 340,000 t HM and by the year 2015 395,000 t HM. Part of the spent fuel will be reprocessed and some countries took the option to dispose their spent fuel in a repository. Most countries with nuclear programmes are using the deferral of a decision approach, a 'wait and see' strategy with interim storage, which provides the ability to monitor the storage continuously and to retrieve the spent fuel later for either direct disposal or reprocessing. Some countries use different approaches for different types of fuel. Today the worldwide reprocessing capacity is only a fraction of the total spent fuel arising and since no final repository has yet been constructed, there will be an increasing demand for interim storage. The present survey contains information on the basic storage technologies and facility types, experience with wet and dry storage of spent fuel and international experience in spent fuel transport. The main aim is to provide spent fuel

Effect of laughter yoga on mood and heart rate variability in patients awaiting organ transplantation: a pilot study.

Science.gov (United States)

Dolgoff-Kaspar, Rima; Baldwin, Ann; Johnson, M Scott; Edling, Nancy; Sethi, Gulshan K

2012-01-01

Research shows that laughter has myriad health benefits, yet the medical community has not implemented it formally as a treatment. Patients awaiting organ transplantation have significant physical disabilities and are at risk for psychological distress. Attenuated heart rate variability (HRV) is a risk factor for a negative long-term outcome in some patients. The study intended to evaluate the clinical utility of laughter yoga in improving psychological and physiological measures in outpatients awaiting organ transplantation. Positive results would indicate promising areas to pursue in a follow-up study. Six participants met for 10 sessions over 4 weeks. The research team measured each participant's heart rate, HRV, blood pressure (BP), and immediate mood before and after the laughter and control interventions. The team assessed participants' longer-term mood (anxiety and depression) at the study's initiation, after a no-treatment control week, and at the end of the study. The study occurred at the Department of Surgery and Medicine at the University of Arizona Health Sciences Center, Tucson. Participants were patients awaiting transplants (three heart and three lung), two women and four men (ages 51-69 y). Participants had received no major surgery in the 3 months prior to the intervention, did not have a hernia or uncontrolled hypertension, and did not fall into the New York Heart Association function class 4. The 20-minute laughter intervention involved breathing and stretching exercises, simulated laughter (ie, unconditional laughter that is not contingent on the environment), chanting, clapping, and a meditation. The 20-minute control intervention involved the study's personnel discussing health and study-related topics with the participants. The research team measured BP, heart rate, and HRV and administered the Profile of Mood States, Beck Anxiety Inventory, and Beck Depression Inventory-II to evaluate immediate and longer-term mood. The team had planned

Design ampersand operational experience of the NUHOMS reg-sign-24P spent fuel storage system

International Nuclear Information System (INIS)

McConaghy, W.J.; Lehnert, R.A.; Rasmussen, R.W.

1991-01-01

The NUHOMS reg-sign Spent Fuel Storage System provides a safe and economical method for the dry storage of spent fuel assemblies either at an at-reactor Independent Spent Fuel Storage Installation (ISFSI) or at a centralized away-from-reactor (AFR) storage facility. The system consists of three major safety related components: a dry shielded canister (DSC) which provides a high integrity containment boundary and a controlled storage environment for the fuel; a reinforced concrete horizontal storage module (HSM) which houses the stored DSC and provides radiation shielding, protection against natural phenomena, and an efficient means for decay heat removal; and a transfer cask which provides for the safe shielded transfer of the DSC from the plant spent fuel pool to the HSM. The NUHOMS reg-sign system is designed and licensed to the requirements of 10 CFR 72 and ANS/ANSI 57.9 for ISFSIs

A study on oxidation treatment of uranium metal chip under controlling atmosphere for safe storage

International Nuclear Information System (INIS)

Kim, Chang Kyu; Ji, Chul Goo; Bae, Sang Oh; Woo, Yoon Myeoung; Kim, Jong Goo; Ha, Yeong Keong

2011-01-01

The U metal chips generated in developing nuclear fuel and a gamma radioisotope shield have been stored under immersion of water in KAERI. When the water of the storing vessels vaporizes or drains due to unexpected leaking, the U metal chips are able to open to air. A new oxidation treatment process was raised for a long time safe storage with concepts of drying under vacuum, evaporating the containing water and organic material with elevating temperature, and oxidizing the uranium metal chips at an appropriate high temperature under conditions of controlling the feeding rate of oxygen gas. In order to optimize the oxidation process the uranium metal chips were completely dried at higher temperature than 300 .deg. C and tested for oxidation at various temperatures, which are 300 .deg. C, 400 .deg. C, and 500 .deg. C. When the oxidation temperature was 400 .deg. C, the oxidized sample for 7 hours showed a temperature rise of 60 .deg. C in the self-ignition test. But the oxidized sample for 14 hours revealed a slight temperature rise of 7 .deg. C representing a stable behavior in the self-ignition test. When the temperature was 500 .deg. C, the shorter oxidation for 7 hours appeared to be enough because the self-ignition test represented no temperature rise. By using several chemical analyses such as carbon content determination, X-ray deflection (XRD), Infrared spectra (IR) and Thermal gravimetric analysis (TGA) on the oxidation treated samples, the results of self-ignition test of new oxidation treatment process for U metal chip were interpreted and supported

Automated Storage Retrieval System (ASRS) Role Towards Achievement of Safety Objective and Safety Culture in Radioactive Storage Facilities

International Nuclear Information System (INIS)

Mohamad Hakiman Mohd Yusoff; Nurul Wahida Ahmad Khairuddin; Nik Marzukee Nik Ibrahim; Mat Bakar Mahusin; Muhammad, Z.A.; Nur Azna Mahmud; Norfazlina Zainal Abidin

2012-01-01

Waste Technology Development Centre (WasTeC) has been awarded with quality management system ISO 9001:2000 in June 2004 or now known as ISO 9001:2008. The scope of the unit's ISO certification is radioactive waste management and storage of radioactive material. To meet the objectives and requirements ISO 9001:2008, WasTeC has started a project known as Automated Storage and Retrieval System (ASRS). ASRS is a computing controlled method for automatically depositing and retrieving waste from defined locations. The system is used to replace the existing process of storage and retrieval of radioactive waste at storage facility at block 33.The main objective of this project is to reduced the radiation exposure to the worker and potential forklift accident occur during storage and retrieval of the radioactive waste. By using the ASRS system, WasTeC/ Nuclear Malaysia can provide a safe storage of radioactive waste and the use of this system can eliminate the repeat handling and can improve productivity. (author)

Bank of models for estimation of radioactive contamination consequences at the places where nuclear submarines are awaiting decommissioning

International Nuclear Information System (INIS)

Vorobiev, V.; Nosov, A.; Hitrikov, V.; Kiselev, V.; Korjov, M.; Krylov, A.; Kanevsky, M.; Petuhov, Y.

1995-01-01

The present paper presents a description of a computer bank of models for estimation of reactor accident consequences in harbors where Russian nuclear submarines are awaiting decommissioning. The computer bank is intended for an estimation of the consequences of a possible contamination of the surface water. It will also support the decision making in a tense situation. 2 figs., 1 tab

Reticular Chemistry at Its Best: Directed Assembly of Hexagonal Building Units into the Awaited Metal-Organic Framework with the Intricate Polybenzene Topology, pbz-MOF

KAUST Repository

Alezi, Dalal

2016-10-05

The ability to direct the assembly of hexagonal building units offers great prospective to construct the awaited and looked-for hypothetical polybenzene (pbz) or “cubic graphite” structure, described 70 years ago. Here, we demonstrate the successful use of reticular chemistry as an appropriate strategy for the design and deliberate construction of a zirconium-based metal–organic framework (MOF) with the intricate pbz underlying net topology. The judicious selection of the perquisite hexagonal building units, six connected organic and inorganic building blocks, allowed the formation of the pbz-MOF-1, the first example of a Zr(IV)-based MOF with pbz topology. Prominently, pbz-MOF-1 is highly porous, with associated pore size and pore volume of 13 Å and 0.99 cm3 g–1, respectively, and offers high gravimetric and volumetric methane storage capacities (0.23 g g–1 and 210.4 cm3 (STP) cm–3 at 80 bar). Notably, the pbz-MOF-1 pore system permits the attainment of one of the highest CH4 adsorbed phase density enhancements at high pressures (0.15 and 0.21 g cm–3 at 35 and 65 bar, respectively) as compared to benchmark microporous MOFs.

Reticular Chemistry at Its Best: Directed Assembly of Hexagonal Building Units into the Awaited Metal-Organic Framework with the Intricate Polybenzene Topology, pbz-MOF

KAUST Repository

Alezi, Dalal; Spanopoulos, Ioannis; Tsangarakis, Constantinos; Shkurenko, Aleksander; Adil, Karim; Belmabkhout, Youssef; O'Keeffe, Michael; Eddaoudi, Mohamed; Trikalitis, Pantelis N.

2016-01-01

The ability to direct the assembly of hexagonal building units offers great prospective to construct the awaited and looked-for hypothetical polybenzene (pbz) or “cubic graphite” structure, described 70 years ago. Here, we demonstrate the successful use of reticular chemistry as an appropriate strategy for the design and deliberate construction of a zirconium-based metal–organic framework (MOF) with the intricate pbz underlying net topology. The judicious selection of the perquisite hexagonal building units, six connected organic and inorganic building blocks, allowed the formation of the pbz-MOF-1, the first example of a Zr(IV)-based MOF with pbz topology. Prominently, pbz-MOF-1 is highly porous, with associated pore size and pore volume of 13 Å and 0.99 cm3 g–1, respectively, and offers high gravimetric and volumetric methane storage capacities (0.23 g g–1 and 210.4 cm3 (STP) cm–3 at 80 bar). Notably, the pbz-MOF-1 pore system permits the attainment of one of the highest CH4 adsorbed phase density enhancements at high pressures (0.15 and 0.21 g cm–3 at 35 and 65 bar, respectively) as compared to benchmark microporous MOFs.

Design and operational experience of the NUHOMS-24P spent fuel storage system

International Nuclear Information System (INIS)

McConaghy, W.J.; Lehnert, R.A.; Rasmussen, R.W.

1991-01-01

The NUHOMS spent fuel storage system provides a safe and economical method for the dry storage of spent fuel assemblies either at an independent spent fuel storage installation (ISFSI) at reactor or at a centralized storage facility away from reactor. The system consists of three major safety-related components: a dry shielded canister (DSC) which provides a high integrity containment boundary and a controlled storage environment for the fuel; a reinforced concrete horizontal storage module (HSM) which houses the stored DSCs and provides radiation shielding, protection against natural phenomena and an efficient means for decay heat removal; and a transfer cask which provides for the safe shielded transfer of DSCs from a plant spent fuel pool to a HSM. The NUHOMS system is designed and licensed to the requirements of 10 CFR 72 and ANS/ANSI 57.9 for ISFSIs. The NUHOMS concept was developed in early 1980s, and in 1987, a larger version of the NUHOMS system, 24P, was developed. The operational features of NUHOMS and the loading experience at Oconee are reported. (K.I.)

Safety Case for Safe-store

International Nuclear Information System (INIS)

Woollam, Paul B.

2002-01-01

Magnox Electric plc (Magnox), a wholly owned subsidiary of BNFL, owns 26 gas-cooled, graphite-moderated units on 11 sites in the UK. Eight units have been permanently shutdown and the remainder will shut this decade in a currently declared closure programme. The first of these reactors went to power in 1952 and the fleet has generated typically 9% of the UK's electricity during the last five decades. In accordance with UK Government policy, BNFL aims for a systematic and progressive reduction in hazards on its decommissioning sites. The end-point of the decommissioning process is that the reactors will be dismantled and their sites de-licensed. This will be done through minimising both the risks to the public, workers and the environment and also the lifetime cost, consistent with world class safety. There will be passive safe storage during deferment periods and it is BNFL's clear intent that the reactors will not be Safe-stored indefinitely. The main hazard associated with any decommissioned nuclear site is the spent fuel. Hence the reactors will be de-fuelled as soon as practicable after shutdown. After this work is complete, Cs-137 contaminated plant (e.g. fuel pools, effluent plant, and drains) will be dismantled when it is no longer needed. All other plant and buildings will also be dismantled when they are no longer needed, except for the reactor buildings which will be put into passive safe storage. Co-60 contaminated plant, such as steam generators, will be dismantled with the reactors. The reactors will be dismantled in a sequenced programme, with a notional start time around 100 years from shutdown. Magnox Electric is ensuring that the reactors and primary circuits on all its sites are well characterised. We have carried out a detailed, peer reviewed hazard identification on the lead site from which we have generated a rolling 25-year basic safety case. We have then searched for cliff edge effects and possible long-term changes to generate the 100-year

Advantages of dry hardened cask storage over wet storage for spent nuclear fuel

Energy Technology Data Exchange (ETDEWEB)

Romanato, Luiz Sergio, E-mail: romanato@ctmsp.mar.mil.b [Centro Tecnologico da Marinha em Sao Paulo (CTMSP), Sao Paulo, SP (Brazil). Dept. da Qualidade

2011-07-01

Pools are generally used to store and maintain spent nuclear fuel assemblies for cooling, after removed from reactors. After three to five years stored in the pools, spent fuel can be reprocessed or sent to a final disposition in a geological repository and handled as radioactive waste or sent to another site waiting for future solution. Spent fuel can be stored in dry or wet installations, depending on the method adopted by the nuclear plant. If this storage were exclusively wet, at the installation decommissioning in the future, another solution for storage will need to be found. Today, after a preliminary cooling, the spent fuel assemblies can be removed from the pool and sent to dry hardened storage installations. This kind of storage does not need complex radiation monitoring and it is safer than wet storage. Brazil has two nuclear reactors in operation, a third reactor is under construction and they use wet spent fuel storage . Dry hardened casks use metal or both metal and concrete for radiation shielding and they are safe, especially during an earthquake. An earthquake struck Japan on March 11, 2011 damaging Fukushima Daiichi nuclear power plant. The occurrence of earthquakes in Brazil is very small but dry casks can resist to other events, including terrorist acts, better than pools. This paper shows the advantages of dry hardened cask storage in comparison with the wet storage (water pools) for spent nuclear fuel. (author)

Advantages of dry hardened cask storage over wet storage for spent nuclear fuel

International Nuclear Information System (INIS)

Romanato, Luiz Sergio

2011-01-01

Pools are generally used to store and maintain spent nuclear fuel assemblies for cooling, after removed from reactors. After three to five years stored in the pools, spent fuel can be reprocessed or sent to a final disposition in a geological repository and handled as radioactive waste or sent to another site waiting for future solution. Spent fuel can be stored in dry or wet installations, depending on the method adopted by the nuclear plant. If this storage were exclusively wet, at the installation decommissioning in the future, another solution for storage will need to be found. Today, after a preliminary cooling, the spent fuel assemblies can be removed from the pool and sent to dry hardened storage installations. This kind of storage does not need complex radiation monitoring and it is safer than wet storage. Brazil has two nuclear reactors in operation, a third reactor is under construction and they use wet spent fuel storage . Dry hardened casks use metal or both metal and concrete for radiation shielding and they are safe, especially during an earthquake. An earthquake struck Japan on March 11, 2011 damaging Fukushima Daiichi nuclear power plant. The occurrence of earthquakes in Brazil is very small but dry casks can resist to other events, including terrorist acts, better than pools. This paper shows the advantages of dry hardened cask storage in comparison with the wet storage (water pools) for spent nuclear fuel. (author)

Metal ammine complexes for hydrogen storage

DEFF Research Database (Denmark)

Christensen, Claus H.; Sørensen, Rasmus Zink; Johannessen, Tue

2005-01-01

The hopes of using hydrogen as an energy carrier are severely dampened by the fact that there is still no safe, high-density method available for storing hydrogen. We investigate the possibility of using metal ammine complexes as a solid form of hydrogen storage. Using Mg(NH3)(6)Cl-2 as the example......, we show that it can store 9.1% hydrogen by weight in the form of ammonia. The storage is completely reversible, and by combining it with an ammonia decomposition catalyst, hydrogen can be delivered at temperatures below 620 K....

Controlled maritime storage of noxious materials

International Nuclear Information System (INIS)

1984-01-01

The invention relates to an accommodation for the controlled storage of noxious material, especially of radioactive material packed in vessels. The invention provides a storage accommodation far from populated regions, in which this material may be stored during a long period in a safe and controlled way and from which it may be winned back in a simple and cheap way. For that purpose, a floating and submersible construction is designed that may be let down to the sea-bottom at least partially and that is fitted with a closable entrance. (Auth.)

Experience in ultimate storage of radwaste, illustrated by the information on geomechanics gained in the Asse storage facility

International Nuclear Information System (INIS)

Schmidt, M.W.

1981-01-01

Among the numerous variants of storing radioactive waste in the deep geological underground the storage in appropriate mineral salt formations has a couple of particular advantages. In order to effect research- and development works with regard to a safe secular storage of radioactive wastes, the former mineral salt deposit ASSE was assigned to the GSF in the year 1965. At this test plant storage technologies are developed, tested and the operational efficiency of according technical facilities is demonstrated. As a part of these duties several technical and natural scientific fields like nuclear engineering, mining, geomechanics, geochemistry or hydrogeology are worked in interdisciplinarily. Departing from the existing mine building of the shaft ASSE storage bunkers for low- and intermediate-level radioactive wastes (LAW/MAW) are presented. Accompanying geotechnical investigations are explained. An outlook alludes to an eventually possible development potential of the storage bunker arrangement from the geomechanic view. (orig./HP) [de

Personality factors versus expectations and self-reported symptoms among patients awaiting advanced prosthodontic treatment.

Science.gov (United States)

Hakestam, U; Söderfeldt, B; Rydén, O; Glantz, P O

1997-09-01

To assess simple questions for identifying patient personality traits among a normal Swedish population and to assess possible relationships between personality and symptoms, attitudes, dental problems, and received dental care, a questionnaire was sent to 489 subjects awaiting prosthodontic treatment (response rate 84.2%). Three personality traits could be identified: "Fearful-depressed" subjects consumed more tranquillisers, were worried and had many symptoms, whilst "Open-minded" were optimistic about treatment, had high expectations and few symptoms. "Control-minded" did not reveal worries and guarded their autonomy. It was concluded that personality indicators were related to clinically relevant factors: salience of teeth, perceptions of problems, dental attendance pattern, expectations and perceptions of symptoms.

Fuel performance in water storage

International Nuclear Information System (INIS)

Hoskins, A.P.; Scott, J.G.; Shelton-Davis, C.V.; McDannel, G.E.

1993-11-01

Westinghouse Idaho Nuclear Company operates the Idaho Chemical Processing Plant (ICPP) at the Idaho National Engineering Laboratory (INEL) for the Department of Energy (DOE). A variety of different types of fuels have been stored there since the 1950's prior to reprocessing for uranium recovery. In April of 1992, the DOE decided to end fuel reprocessing, changing the mission at ICPP. Fuel integrity in storage is now viewed as long term until final disposition is defined and implemented. Thus, the condition of fuel and storage equipment is being closely monitored and evaluated to ensure continued safe storage. There are four main areas of fuel storage at ICPP: an original underwater storage facility (CPP-603), a modern underwater storage facility (CPP-666), and two dry fuel storage facilities. The fuels in storage are from the US Navy, DOE (and its predecessors the Energy Research and Development Administration and the Atomic Energy Commission), and other research programs. Fuel matrices include uranium oxide, hydride, carbide, metal, and alloy fuels. In the underwater storage basins, fuels are clad with stainless steel, zirconium, and aluminum. Also included in the basin inventory is canned scrap material. The dry fuel storage contains primarily graphite and aluminum type fuels. A total of 55 different fuel types are currently stored at the Idaho Chemical Processing Plant. The corrosion resistance of the barrier material is of primary concern in evaluating the integrity of the fuel in long term water storage. The barrier material is either the fuel cladding (if not canned) or the can material

Points of Influence for Lethal Means Counseling and Safe Gun Storage Practices.

Science.gov (United States)

Runyan, Carol W; Brooks-Russell, Ashley; Betz, Marian E

2018-06-07

Counseling about reducing access to lethal means of suicide, especially firearms, is a recommended practice in emergency departments (EDs) but does not occur routinely. Understanding influencers of decisions makers in health care (ED nurse leaders, mental health providers) and temporary firearm storage (law enforcement and gun retailers) could enhance practice. We surveyed these 4 groups in the 8-state region of the Mountain West. For ED nurse leaders (n = 190), hospital legal, risk management, and quality improvement representatives, and the ED nursing director were most often cited as influential, whereas mental health providers (n = 67) cited their own team. Law enforcement officials (n = 448) identified the overall community and leaders of mental health or general health organizations as influential. Firearm retailers (n = 95) cited local law enforcement and national firearm organizations. Advocacy from influential groups may encourage efforts to provide lethal means counseling and temporary off-site storage of firearms for suicide prevention.

Materials in the environment of the fuel in dry storage

Energy Technology Data Exchange (ETDEWEB)

Issard, H [TN International (Cogema Logistics) (France)

2012-07-01

Spent nuclear fuel has been stored safely in pools or dry systems in over 30 countries. The majority of IAEA Member States have not yet decided upon the ultimate disposition of their spent nuclear fuel: reprocessing or direct disposal. Interim storage is the current solution for these countries. For developing the technological knowledge data base, a continuation of the IAEA's spent fuel storage performance assessment was achieved. The objectives are: Investigate the dry storage systems and gather basic fuel behaviour assessment; Gather data on dry storage environment and cask materials; Evaluate long term behaviour of cask materials.

Characterization and storage of the Rocky Flats plutonium oxide legacy

International Nuclear Information System (INIS)

Stakebake, J.L.

1997-01-01

Prior to 1989, plutonium oxide storage at the U.S. Department of Energy (DOE) Rocky Flats Environmental Technology Site (RFETS) could generally be considered as short term. Packaging configurations for short-term storage consisted of slip-lid cans and sealed produce cans. Prior to packaging, most of the oxide had been stabilized by heating to ∼500 degrees C. When storage times were relatively short, few problems were attributed to either packaging or storage. However, with projected storage times extended up to 50 yr, most of the old packaging of RFETS plutonium oxide will be in two welded steel containers in compliance with the DOE Standard 3013-96, which defines processing and packaging criteria for safe, long-term storage of plutonium oxide

Interim spent-fuel storage options at commercial nuclear power plants

International Nuclear Information System (INIS)

Thakkar, A.R.; Hylko, J.M.

1991-01-01

Although spent fuel can be stored safely in waterfilled pools at reactor sites, some utilities may not possess sufficient space for life-of-plant storage capability. In-pool storage capability may be increased by reracking assemblies, rod consolidation, double tiering spent-fuel racks, and by shipping spent fuel to other utility-owned facilities. Long-term on-site storage capability for spent fuel may be provided by installing (dry-type) metal casks, storage and transportation casks, concrete casks, horizontal concrete modules, modular concrete vaults, or by constructing additional (pool-type) storage installations. Experience to date has provided valuable information regarding dry-type or pool-type installations, cask handling and staffing requirements, security features, decommissioning activities, and radiological issues

Safe sex

Science.gov (United States)

... sex; Sexually transmitted - safe sex; GC - safe sex; Gonorrhea - safe sex; Herpes - safe sex; HIV - safe sex; ... contact. STIs include: Chlamydia Genital herpes Genital warts Gonorrhea Hepatitis HIV HPV Syphilis STIs are also called ...

Safe cycling!

CERN Multimedia

Anaïs Schaeffer

2012-01-01

The HSE Unit will be running a cycling safety campaign at the entrances to CERN's restaurants on 14, 15 and 16 May. Pop along to see if they can persuade you to get back in the saddle!   With summer on its way, you might feel like getting your bike out of winter storage. Well, the HSE Unit has come up with some original ideas to remind you of some of the most basic safety rules. This year, the prevention campaign will be focussing on three themes: "Cyclists and their equipment", "The bicycle on the road", and "Other road users". This is an opportunity to think about the condition of your bike as well as how you ride it. From 14 to 16 May, representatives of the Swiss Office of Accident Prevention and the Touring Club Suisse will join members of the HSE Unit at the entrances to CERN's restaurants to give you advice on safe cycling (see box). They will also be organising three activity stands where you can test your knowle...

Safe management of discussed sealed sources in Peru

International Nuclear Information System (INIS)

Mallaupoma, M.

2000-01-01

The future safe development of nuclear energy and progressive increasing use of sealed sources in medicine, research, industry and other fields in Peru, in the past years have determined the necessity to formulate and apply an Institutional policy to assure harmless and ecologically rational management of disused sealed sources in Peru. Some results of the studies, which served as a basis for design and construction of a facility for treatment, conditioning and storage of conditioned sealed sources are presented in this paper. The waste management system in Peru comprises operational and regulatory capabilities. Both of these activities are performed under a legislation. The Nuclear Research Center RACSO has a radioactive waste management department which is in charge of the management of disused sealed sources produced in the country. It is considered as a centralized waste processing and storage facility (WPSF). (author)

PWR Core II blanket fuel disposition recommendation of storage option study

International Nuclear Information System (INIS)

Dana, C.M.

1995-01-01

After review of the options available for current storage of T Plant Fuel the recommended option is wet storage without the use of chillers. A test has been completed that verifies the maximum temperature reached is below the industrial standard for storage of spent fuel. This option will be the least costly and still maintain the fuel in a safe environment. The options that were evaluated included dry storage with and without chillers, and wet storage with and without chillers. Due to the low decay heat of the Shippingport Core II Blanket fuel assemblies the fuel pool temperature will not exceed 100 deg. F

Used Fuel Logistics: Decades of Experience with transportation and Interim storage solutions

Energy Technology Data Exchange (ETDEWEB)

Orban, G.; Shelton, C.

2015-07-01

Used fuel inventories are growing worldwide. While some countries have opted for a closed cycle with recycling, numerous countries must expand their interim storage solutions as implementation of permanent repositories is taking more time than foreseen. In both cases transportation capabilities will have to be developed. AREVA TN has an unparalleled expertise with transportation of used fuel. For more than 50 years AREVA TN has safely shipped more than 7,000 used fuel transport casks. The transportation model that was initially developed in the 1970s has been adapted and enhanced over the years to meet more restrictive regulatory requirements and evolving customer needs, and to address public concerns. The numerous “lessons learned” have offered data and guidance that have allowed for also efficient and consistent improvement over the decades. AREVA TN has also an extensive experience with interim dry storage solutions in many countries on-site but also is working with partners to developed consolidated interim storage facility. Both expertise with storage and transportation contribute to safe, secure and smooth continuity of the operations. This paper will describe decades of experience with a very successful transportation program as well as interim storage solutions. (Author)

Canister storage building trade study. Final report

International Nuclear Information System (INIS)

Swenson, C.E.

1995-05-01

This study was performed to evaluate the impact of several technical issues related to the usage of the Canister Storage Building (CSB) to safely stage and store N-Reactor spent fuel currently located at K-Basin 100KW and 100KE. Each technical issue formed the basis for an individual trade study used to develop the ROM cost and schedule estimates. The study used concept 2D from the Fluor prepared ''Staging and Storage Facility (SSF) Feasibility Report'' as the basis for development of the individual trade studies

Canister storage building trade study. Final report

Energy Technology Data Exchange (ETDEWEB)

Swenson, C.E. [Westinghouse Hanford Co., Richland, WA (United States)

1995-05-01

This study was performed to evaluate the impact of several technical issues related to the usage of the Canister Storage Building (CSB) to safely stage and store N-Reactor spent fuel currently located at K-Basin 100KW and 100KE. Each technical issue formed the basis for an individual trade study used to develop the ROM cost and schedule estimates. The study used concept 2D from the Fluor prepared ``Staging and Storage Facility (SSF) Feasibility Report`` as the basis for development of the individual trade studies.

Chest radiographic findings and complications of the temporary implantation of the Jarvik-7 artificial heart while awaiting orthotopic heart transplantation: Experience with five cases

International Nuclear Information System (INIS)

Sadler, L.R.; Fuhrman, C.R.; Hardesty, R.A.; Griffith, B.P.

1986-01-01

The Jarvik-7 artificial heart was originally introduced as a therapeutic alternative to cardiac transplantation in patients with endstage refractory cardiac disease. Its use has been expanded to those patients awaiting cardiac transplantation in whom death is impending and for whom a suitable donor match is unavailable. At Presbyterian-University Hospital of Pittsburgh five patients have had Jarvik-7 hearts implanted as a temporary measure while awaiting compatible donors for cardiac transplantation. The authors believe this is the largest patient group to undergo this procedure at a single institution. They present a brief description of the Jarvik-7 heart, the clinical factors affecting patient selection, and the radiographic appearance of a normally functioning Jarvik-7 heart, and review the chest radiographic complications seen in the patient group, along with eventual patient outcome

Interventions to Improve Safe Sleep Among Hospitalized Infants at Eight Children's Hospitals.

Science.gov (United States)

Kuhlmann, Stephanie; Ahlers-Schmidt, Carolyn R; Lukasiewicz, Gloria; Truong, Therese Macasiray

2016-02-01

Within hospital pediatric units, there is a lack of consistent application or modeling of the American Academy of Pediatrics recommendations for safe infant sleep. The purpose of this study was to improve safe sleep practices for infants in nonneonatal pediatric units with implementation of specific interventions. This multi-institutional study was conducted by using baseline observations collected for sleep location, position, and environment (collectively, "safe sleep") of infants admitted to pediatric units. Interventions consisted of: (1) staff education, including a commitment to promote safe sleep; (2) implementing site-generated safe sleep policies; (3) designating supply storage in patient rooms; and/or (4) caregiver education. Postintervention observations of safe sleep were collected. Eight hospitals participated from the Inpatient FOCUS Group of the Children's Hospital Association. Each site received institutional review board approval/exemption. Safe sleep was observed for 4.9% of 264 infants at baseline and 31.2% of 234 infants postintervention (Ppresent in 77% of cribs at baseline and 44% postintervention. However, the mean number of unsafe items observed in each sleeping environment was reduced by >50% (P=.001). Implementation of site-specific interventions seems to improve overall safe sleep in inpatient pediatric units, although continued improvement is needed. Specifically, extra items are persistently left in the sleeping environment. Moving forward, hospitals should evaluate their compliance with American Academy of Pediatrics recommendations and embrace initiatives to improve modeling of safe sleep. Copyright © 2016 by the American Academy of Pediatrics.

75 FR 43906 - Hazardous Materials: Requirements for the Storage of Explosives During Transportation

Science.gov (United States)

2010-07-27

... program in emergency response procedures for all employees working at the safe haven. NFPA 498 section 4.5... safe havens used for unattended storage of Division 1.1, 1.2, and 1.3 explosives. DATES: Comments must... circumstances and operational environment. B. Federal Motor Carrier Safety Regulations (FMCSRs), 49 CFR Parts...

Dry well storage of spent LWBR fuel

International Nuclear Information System (INIS)

Christensen, A.B.; Fielding, K.D.

1985-01-01

Recently, 50 dry wells were constructed at the Idaho Chemical Processing Plant (ICPP) to temporarily store the Light Water Breeder Reactor (LWBR) fuel. Over 400 dry wells of the same design are projected to be constructed in the next 5 yr at the ICPP to store unreprocessible fuels until a permanent repository becomes available. This summary describes the LWBR fuel storage dry wells and the enhancements made over the Peach Bottom fuel and Fermi blanket dry wells that have been in use for up to 4 yr. Dry well storage at the ICPP has historically been found to be a safe and efficient method of temporary fuel storage. The LWBR dry wells should be more reliable than the original dry wells and provide data not previously available

Use of polyethylene pellets in the design and construction of a storage safe, a transport vessel and a portable shield for californium-252

International Nuclear Information System (INIS)

Sharma, S.

1986-01-01

A storage and shielding facility for 300 μg of Californium-252 sources was designed and constructed. Though the safe was in a permanent location, the fact that it consisted of a lead bucket surrounded by polyethylene pellets made it simple, movable and inexpensive. If need be, more quantities of Cf-252 could be added without altering the basic design and sacrificing the radiation protection guidelines. The measured radiation levels from 300 μg of stored Cf-252 in and around the storage vault were lower than the expected dose rates by a factor of 5. The measured radiation levels around the occupied environs of the facility were below the maximum permissible yearly dose of 500mrem for non-occupational workers. A transport vessel was designed and constructed to carry up to 50 μg of Californium-252 sources. It consisted of a standard 55 gallon steel drum on casters containing cylindrical lead shield surrounded by polyethylene pellets. The measured maximum surface dose rates on the drum and at one meter away were within the radiation protection guidelines and were less than the expected dose rates. A portable shield was designed and constructed to protect the body in afterloading operations and handling of the sources. It consisted of polyethylene pellets in an aluminum box and an attached 10 cm thick plexiglass eye shield. The simple design, with the ease of using polyethylene pellets can be extended to construct bedside shields

Long-Cycling Aqueous Organic Redox Flow Battery (AORFB) toward Sustainable and Safe Energy Storage.

Science.gov (United States)

Hu, Bo; DeBruler, Camden; Rhodes, Zayn; Liu, T Leo

2017-01-25

Redox flow batteries (RFBs) are a viable technology to store renewable energy in the form of electricity that can be supplied to electricity grids. However, widespread implementation of traditional RFBs, such as vanadium and Zn-Br 2 RFBs, is limited due to a number of challenges related to materials, including low abundance and high costs of redox-active metals, expensive separators, active material crossover, and corrosive and hazardous electrolytes. To address these challenges, we demonstrate a neutral aqueous organic redox flow battery (AORFB) technology utilizing a newly designed cathode electrolyte containing a highly water-soluble ferrocene molecule. Specifically, water-soluble (ferrocenylmethyl)trimethylammonium chloride (FcNCl, 4.0 M in H 2 O, 107.2 Ah/L, and 3.0 M in 2.0 NaCl, 80.4 Ah/L) and N 1 -ferrocenylmethyl-N 1 ,N 1 ,N 2 ,N 2 ,N 2 -pentamethylpropane-1,2-diaminium dibromide, (FcN 2 Br 2 , 3.1 M in H 2 O, 83.1 Ah/L, and 2.0 M in 2.0 M NaCl, 53.5 Ah/L) were synthesized through structural decoration of hydrophobic ferrocene with synergetic hydrophilic functionalities including an ammonium cation group and a halide anion. When paired with methyl viologen (MV) as an anolyte, resulting FcNCl/MV and FcN 2 Br 2 /MV AORFBs were operated in noncorrosive neutral NaCl supporting electrolytes using a low-cost anion-exchange membrane. These ferrocene/MV AORFBs are characterized as having high theoretical energy density (45.5 Wh/L) and excellent cycling performance from 40 to 100 mA/cm 2 . Notably, the FcNCl/MV AORFBs (demonstrated at 7.0 and 9.9 Wh/L) exhibited unprecedented long cycling performance, 700 cycles at 60 mA/cm 2 with 99.99% capacity retention per cycle, and delivered power density up to 125 mW/cm 2 . These AORFBs are built from earth-abundant elements and are environmentally benign, thus representing a promising choice for sustainable and safe energy storage.

Detection of fission products release in the research reactor 'RA' spent fuel storage pool

International Nuclear Information System (INIS)

Matausek, M.V.; Vukadin, Z.; Pavlovic, S.; Maksin, T.; Idakovic, Z.; Marinkovic, N.

1997-05-01

Spent fuel resulting from 25 years of operating the 6.5/10 MW thermal heavy water moderated and cooled research reactor RA at the VINCA Institute is presently all stored in the temporary spent fuel storage pool in the basement of the reactor building. In 1984, the reactor was shut down for refurbishment, which for a number of reasons has not yet been completed. Recent investigations show that independent of the future status of the research reactor, safe disposal of the so far irradiated fuel must be the subject of primary concern. The present status of the research reactor RA spent fuel storage pool at the VINCA Institute presents a serious safety problem. Action is therefore initiated in two directions. First, safety of the existing spent fuel storage should be improved. Second, transferring spent fuel into another, presumably dry storage space should be considered. By storing the previously irradiated fuel of the research reactor RA in a newly built storage space, sufficient free space will be provided in the existing spent fuel storage pool for the newly irradiated fuel when the reactor starts operation again. In the case that it would be decided to decommission the research reactor RA, the newly built storage space would provide safe disposal for the fuel irradiated so far

Integrated Treatment and Storage Solutions for Solid Radioactive Waste at the Russian Shipyard Near Polyarny

International Nuclear Information System (INIS)

Griffith, A.; Engoy, T.; Endregard, M.; Busmundrud, O.; Schwab, P.; Nazarian, A.; Krumrine, P.; Backe, S.; Gorin, S.; Evans, B.

2002-01-01

Russian Navy Yard No. 10 (Shkval), near the city of Murmansk, has been designated as the recipient for Solid Radioactive Waste (SRW) pretreatment and storage facilities under the Arctic Military Environmental Cooperation (AMEC) Program. This shipyard serves the Northern Fleet by servicing, repairing, and dismantling naval vessels. Specifically, seven nuclear submarines of the first and second generation and Victor class are laid up at this shipyard, awaiting defueling and dismantlement. One first generation nuclear submarine has already been dismantled there, but recently progress on dismantlement has slowed because all the available storage space is full. SRW has been placed in metal storage containers, which have been moved outside of the actual storage site, which increases the environmental risks. AMEC is a cooperative effort between the Russian Federation, Kingdom of Norway and the United States. AMEC Projects 1.3 and 1.4 specifically address waste treatment and storage issues. Various waste treatment options have been assessed, technologies selected, and now integrated facilities are being designed and constructed to address these problems. Treatment technologies that are being designed and constructed include a mobile pretreatment facility comprising waste assay, segregation, size reduction, compaction and repackaging operations. Waste storage technologies include metal and concrete containers, and lightweight modular storage buildings. This paper focuses on the problems and challenges that are and will be faced at the Polyarninsky Shipyard. Specifically, discussion of the waste quantities, types, and conditions and various site considerations versus the various technologies that are to be employed will be provided. A systems approach at the site is being proposed by the Russian partners, therefore integration with other ongoing and planned operations at the site will also be discussed

The shutdown reactor: Optimizing spent fuel storage cost

International Nuclear Information System (INIS)

Pennington, C.W.

1995-01-01

Several studies have indicated that the most prudent way to store fuel at a shutdown reactor site safely and economically is through the use of a dry storage facility licensed under 10CFR72. While such storage is certainly safe, is it true that the dry ISFSI represents the safest and most economical approach for the utility? While no one is really able to answer that question definitely, as yet, Holtec has studied this issue for some time and believes that both an economic and safety case can be made for an optimization strategy that calls for the use of both wet and dry ISFSI storage of spent fuel at some plants. For the sake of brevity, this paper summarizes some of Holtec's findings with respect to the economics of maintaining some fuel in wet storage at a shutdown reactor. The safety issue, or more importantly the perception of safety of spent fuel in wet storage, still varies too much with the eye of the beholder, and until a more rigorous presentation of safety analyses can be made in a regulatory setting, it is not practically useful to argue about how many angels can sit on the head of a safety-related pin. Holtec is prepared to present such analyses, but this does not appear to be the proper venue. Thus, this paper simply looks at certain economic elements of a wet ISFSI at a shutdown reactor to make a prima facie case that wet storage has some attractiveness at a shutdown reactor and should not be rejected out of hand. Indeed, an optimization study at certain plants may well show the economic vitality of keeping some fuel in the pool and converting the NRC licensing coverage from 10CFR50 to 10CFR72. If the economics look attractive, then the safety issue may be confronted with a compelling interest

Technical Safety Requirements for the Waste Storage Facilities

International Nuclear Information System (INIS)

Laycak, D.T.

2010-01-01

This document contains Technical Safety Requirements (TSR) for the Radioactive and Hazardous Waste Management (RHWM) WASTE STORAGE FACILITIES, which include Area 625 (A625) and the Decontamination and Waste Treatment Facility (DWTF) Storage Area at Lawrence Livermore National Laboratory (LLNL). The TSRs constitute requirements regarding the safe operation of the WASTE STORAGE FACILITIES. These TSRs are derived from the Documented Safety Analysis for the Waste Storage Facilities (DSA) (LLNL 2009). The analysis presented therein determined that the WASTE STORAGE FACILITIES are low-chemical hazard, Hazard Category 2 non-reactor nuclear facilities. The TSRs consist primarily of inventory limits and controls to preserve the underlying assumptions in the hazard and accident analyses. Further, appropriate commitments to safety programs are presented in the administrative controls sections of the TSRs. The WASTE STORAGE FACILITIES are used by RHWM to handle and store hazardous waste, TRANSURANIC (TRU) WASTE, LOW-LEVEL WASTE (LLW), mixed waste, California combined waste, nonhazardous industrial waste, and conditionally accepted waste generated at LLNL as well as small amounts from other U.S. Department of Energy (DOE) facilities, as described in the DSA. In addition, several minor treatments (e.g., size reduction and decontamination) are carried out in these facilities. The WASTE STORAGE FACILITIES are located in two portions of the LLNL main site. A625 is located in the southeast quadrant of LLNL. The A625 fenceline is approximately 225 m west of Greenville Road. The DWTF Storage Area, which includes Building 693 (B693), Building 696 Radioactive Waste Storage Area (B696R), and associated yard areas and storage areas within the yard, is located in the northeast quadrant of LLNL in the DWTF complex. The DWTF Storage Area fenceline is approximately 90 m west of Greenville Road. A625 and the DWTF Storage Area are subdivided into various facilities and storage areas, consisting

Technical Safety Requirements for the Waste Storage Facilities

Energy Technology Data Exchange (ETDEWEB)

Laycak, D T

2008-06-16

This document contains Technical Safety Requirements (TSR) for the Radioactive and Hazardous Waste Management (RHWM) WASTE STORAGE FACILITIES, which include Area 625 (A625) and the Decontamination and Waste Treatment Facility (DWTF) Storage Area at Lawrence Livermore National Laboratory (LLNL). The TSRs constitute requirements regarding the safe operation of the WASTE STORAGE FACILITIES. These TSRs are derived from the 'Documented Safety Analysis for the Waste Storage Facilities' (DSA) (LLNL 2008). The analysis presented therein determined that the WASTE STORAGE FACILITIES are low-chemical hazard, Hazard Category 2 non-reactor nuclear facilities. The TSRs consist primarily of inventory limits and controls to preserve the underlying assumptions in the hazard and accident analyses. Further, appropriate commitments to safety programs are presented in the administrative controls sections of the TSRs. The WASTE STORAGE FACILITIES are used by RHWM to handle and store hazardous waste, TRANSURANIC (TRU) WASTE, LOW-LEVEL WASTE (LLW), mixed waste, California combined waste, nonhazardous industrial waste, and conditionally accepted waste generated at LLNL as well as small amounts from other U.S. Department of Energy (DOE) facilities, as described in the DSA. In addition, several minor treatments (e.g., size reduction and decontamination) are carried out in these facilities. The WASTE STORAGE FACILITIES are located in two portions of the LLNL main site. A625 is located in the southeast quadrant of LLNL. The A625 fenceline is approximately 225 m west of Greenville Road. The DWTF Storage Area, which includes Building 693 (B693), Building 696 Radioactive Waste Storage Area (B696R), and associated yard areas and storage areas within the yard, is located in the northeast quadrant of LLNL in the DWTF complex. The DWTF Storage Area fenceline is approximately 90 m west of Greenville Road. A625 and the DWTF Storage Area are subdivided into various facilities and storage areas

Fuel Assemblies Thermal Analysis in the New Spent Fuel Storage Facility at Inshass Site

International Nuclear Information System (INIS)

Khattab, M.; Mariy, Ahmed

1999-01-01

New Wet Storage Facility (NSF) is constructed at Inshass site to solve the problem of spent fuel storage capacity of ETRR-1 reactor . The Engineering Safety Heat Transfer Features t hat characterize the new facility are presented. Thermal analysis including different scenarios of pool heat load and safety limits are discussed . Cladding temperature limit during handling and storage process are specified for safe transfer of fuel

Neutronic and thermal hydraulic of dry cask storage systems

International Nuclear Information System (INIS)

Yavuz, U.

2000-01-01

Interim spent fuel storage systems must provide for the safe receipt, handling, retrieval and storage of spent nuclear fuel before reprocessing or disposal. In the context of achieving these objectives, the following features of the design are to be taken into consideration: to maintain fuel subcritical, to remove spent fuel residualheat, and to provide for radiation protection. These features in the design of a dry cask storage system were analyzed for normal operating conditions by employing COBRA-SFS, SCALE4.4 (ORIGEN, XSDOSE, CSAS6) codes. For a metal-shielded type storage system, appropriate designs, in accordance with safety assurance limits of IAEA, were obtained for spent fuel burned to 33000, 45000 and 55000 MW d/t and cooled for 5 and 10 years

Survey of experience with dry storage of spent nuclear fuel and update of wet storage experience

International Nuclear Information System (INIS)

1988-01-01

Spent fuel storage is an important part of spent fuel management. At present about 45,000 t of spent water reactor fuel have been discharged worldwide. Only a small fraction of this fuel (approximately 7%) has been reprocessed. The amount of spent fuel arisings will increase significantly in the next 15 years. Estimates indicate that up to the year 2000 about 200,000 t HM of spent fuel could be accumulated. In view of the large quantities of spent fuel discharged from nuclear power plants and future expected discharges, many countries are involved in the construction of facilities for the storage of spent fuel and in the development of effective methods for spent fuel surveillance and monitoring to ensure that reliable and safe operation of storage facilities is achievable until the time when the final disposal of spent fuel or high level wastes is feasible. The first demonstrations of final disposal are not expected before the years 2000-2020. This is why the long term storage of spent fuel and HLW is a vital problem for all countries with nuclear power programmes. The present survey contains data on dry storage and recent information on wet storage, transportation, rod consolidation, etc. The main aim is to provide spent fuel management policy making organizations, designers, scientists and spent fuel storage facility operators with the latest information on spent fuel storage technology under dry and wet conditions and on innovations in this field. Refs, figs and tabs

Uranium retrieval support, storage, and marketing

International Nuclear Information System (INIS)

Jackson, J.D.; Marshall, E.M.

2001-01-01

The United States Department of Energy is implementing a stewardship approach to management of uranium assets. This life-cycle approach to managing uranium addresses current needs in the context of a long-term strategy. In June 1998, the United States Department of Energy established the Uranium Management Group. The mission of the UMG is to safely collect and store commercially viable uranium from various DOE facilities at a central location. The Oak Ridge Operations Office, in Oak Ridge, Tennessee, was given the task to establish a facility for the storage of these uranium materials. Materials collected are non-waste uranium and packaged to allow transport and long-term storage. Coordination of uranium management under the Uranium Management Group offers significant opportunities for sayings through improved planning and efficiency and creates an environmentally sound approach for the storage and reuse of excess uranium. (author)

Uranium retrieval support, storage, and marketing

Energy Technology Data Exchange (ETDEWEB)

Jackson, J.D.; Marshall, E.M. [U.S. Department of Energy, Oak Ridge, Tennessee (United States)

2001-07-01

The United States Department of Energy is implementing a stewardship approach to management of uranium assets. This life-cycle approach to managing uranium addresses current needs in the context of a long-term strategy. In June 1998, the United States Department of Energy established the Uranium Management Group. The mission of the UMG is to safely collect and store commercially viable uranium from various DOE facilities at a central location. The Oak Ridge Operations Office, in Oak Ridge, Tennessee, was given the task to establish a facility for the storage of these uranium materials. Materials collected are non-waste uranium and packaged to allow transport and long-term storage. Coordination of uranium management under the Uranium Management Group offers significant opportunities for sayings through improved planning and efficiency and creates an environmentally sound approach for the storage and reuse of excess uranium. (author)

Methods for expanding the capacity of spent fuel storage facilities

International Nuclear Information System (INIS)

1990-06-01

At the beginning of 1989 more than 55,000 metric tonnes of heavy metal (MTHM) of spent Light Water Reactor (LWR) and Heavy Water Reactor (HWR) fuel had been discharged worldwide from nuclear power plants. Only a small fraction of this fuel has been reprocessed. The majority of the spent fuel assemblies are currently held at-reactor (AR) or away-from-reactor (AFR) in storage awaiting either chemical processing or final disposal depending on the fuel concept chosen by individual countries. Studies made by NEA and IAEA have projected that annual spent fuel arising will reach about 10,000 t HM in the year 2000 and cumulative arising will be more than 200,000 t HM. Taking into account the large quantity of spent fuel discharged from NPP and that the first demonstrations of the direct disposal of spent fuel or HLW are expected only after the year 2020, long-term storage will be the primary option for management of spent fuel until well into the next century. There are several options to expand storage capacity: (1) to construct new away-from-reactor storage facilities, (2) to transport spent fuel from a full at-reactor pool to another site for storage in a pool that has sufficient space to accommodate it, (3) to expand the capacity of existing AR pools by using compact racks, double-tierce, rod consolidation and by increasing the dimensions of existing pools. The purpose of the meeting was: to exchange new information on the international level on the subject connected with the expansion of storage capacities for spent fuel; to elaborate the state-of-the-art of this problem; to define the most important areas for future activity; on the basis of the above information to give recommendations to potential users for selection and application of the most suitable methods for expanding spent fuel facilities taking into account the relevant country's conditions. Refs, figs and tabs

Waste Encapsulation and Storage Facility interim operational safety requirements

CERN Document Server

Covey, L I

2000-01-01

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

Recommendations on the proposed Monitored Retrievable Storage Facility

Energy Technology Data Exchange (ETDEWEB)

1985-10-01

Following the Department of Energy's announcement in April 1985 that three Tennessee sites were to be considered for the Monitored Retrievable Storage facility, Governor Lamar Alexander initiated a review of the proposal to be coordinated by his Safe Growth Team. Roane County and the City of Oak Ridge, the local governments sharing jurisdiction over DOE's primary and secondary sites, were invited to participate in the state's review of the MRS proposal. Many issues related to the proposed MRS are being considered by the Governor's Safe Growth Team. The primary objective of the Clinch River MRS Task Force has been to determine whether the proposed Monitored Retrievable Storage facility should be accepted by the local governments, and if so, under what conditions. The Clinch River MRS Task Force is organized into an Executive Committee cochaired by the Roane County Executive and Mayor of Oak Ridge and three Study Groups focusing on environmental (including health and safety), socioeconomic, and transportation issues.

Recommendations on the proposed Monitored Retrievable Storage Facility

Energy Technology Data Exchange (ETDEWEB)

1985-10-01

Following the Department of Energy`s announcement in April 1985 that three Tennessee sites were to be considered for the Monitored Retrievable Storage facility, Governor Lamar Alexander initiated a review of the proposal to be coordinated by his Safe Growth Team. Roane County and the City of Oak Ridge, the local governments sharing jurisdiction over DOE`s primary and secondary sites, were invited to participate in the state`s review of the MRS proposal. Many issues related to the proposed MRS are being considered by the Governor`s Safe Growth Team. The primary objective of the Clinch River MRS Task Force has been to determine whether the proposed Monitored Retrievable Storage facility should be accepted by the local governments, and if so, under what conditions. The Clinch River MRS Task Force is organized into an Executive Committee cochaired by the Roane County Executive and Mayor of Oak Ridge and three Study Groups focusing on environmental (including health and safety), socioeconomic, and transportation issues.

Final Oak Ridge National Laboratory Site Assessment Report on the Storage of 233U

International Nuclear Information System (INIS)

Bereolos, P.J.; Yong, L.K.

1999-01-01

This assessment characterizes the 233 U inventories and storage facility at Oak Ridge National Laboratory (ORNL). This assessment is a commitment in the U.S. Department of Energy (DOE) Implementation Plan (IP), ''Safe Storage of Uranium-233,'' in response to the Defense Nuclear Facilities Safety Board's Recommendation 97-1

Safe storage of premature maize ears through gamma radiation and irradiation effect on chemical composition

International Nuclear Information System (INIS)

Gupta, H.O.; Singh, N.N.; Roy, M.K.

2003-01-01

Marked differences were observed between unirradiated and irradiated premature ears (early dough stage) of maize during storage. Some molds were developed on the grains and deterioration set in at the peduncle and stone of maize in the unirradiated ears, whereas no such symptoms were observed in the 3 kGy irradiated ears even after 45 days of storage. Changes in chemical constituents viz. starch, protein, total sugars were observed in the ears without adversely affecting the quality traits through radiation although 100 grains weight reduced slightly. (author)

Spent fuel storage for ISER plant

International Nuclear Information System (INIS)

Nakajima, Takasuke; Kimura, Yuzi

1987-01-01

ISER is an intrinsically safe reactor basing its safety only on physical laws, and uses a steel reactor vessel in order to be economical. For such a new type reactor, it is essentially important to be accepted by the society by showing that the reactor is more profitable than conventional reactors to the public in both technical and economic viewpoint. It is also important that the reactor raises no serious problem in the total fuel cycle. Reprocessing seems one of the major worldwide fuel cycle issues. Spent fuel storage is also one of the key technologies for fuel cycle back end. Various systems for ISER spent fuel storages are examined in the present report. Spent fuel specifications of ISER are similar to those of LWR and therefore, most of LWR spent fuel technologies are basically applicable to ISER spent fuel. Design requirements and examples of storage facilities are also discussed. Dry storage seems to be preferable for the relatively long cooling time spent fuel like ISER's one from economical viewpoint. Vault storage will possibly be the most advantageous for large storage capacity. Another point for discussion is the location and international collaboration for spent fuel storages: ISER expected to be a worldwide energy source and therefore, international spent fuel management seems to be fairly attractive way for an energy recipient country. (Nogami, K.)

Gas Hydrate Storage of Natural Gas

Energy Technology Data Exchange (ETDEWEB)

Rudy Rogers; John Etheridge

2006-03-31

Environmental and economic benefits could accrue from a safe, above-ground, natural-gas storage process allowing electric power plants to utilize natural gas for peak load demands; numerous other applications of a gas storage process exist. A laboratory study conducted in 1999 to determine the feasibility of a gas-hydrates storage process looked promising. The subsequent scale-up of the process was designed to preserve important features of the laboratory apparatus: (1) symmetry of hydrate accumulation, (2) favorable surface area to volume ratio, (3) heat exchanger surfaces serving as hydrate adsorption surfaces, (4) refrigeration system to remove heat liberated from bulk hydrate formation, (5) rapid hydrate formation in a non-stirred system, (6) hydrate self-packing, and (7) heat-exchanger/adsorption plates serving dual purposes to add or extract energy for hydrate formation or decomposition. The hydrate formation/storage/decomposition Proof-of-Concept (POC) pressure vessel and supporting equipment were designed, constructed, and tested. This final report details the design of the scaled POC gas-hydrate storage process, some comments on its fabrication and installation, checkout of the equipment, procedures for conducting the experimental tests, and the test results. The design, construction, and installation of the equipment were on budget target, as was the tests that were subsequently conducted. The budget proposed was met. The primary goal of storing 5000-scf of natural gas in the gas hydrates was exceeded in the final test, as 5289-scf of gas storage was achieved in 54.33 hours. After this 54.33-hour period, as pressure in the formation vessel declined, additional gas went into the hydrates until equilibrium pressure/temperature was reached, so that ultimately more than the 5289-scf storage was achieved. The time required to store the 5000-scf (48.1 hours of operating time) was longer than designed. The lower gas hydrate formation rate is attributed to a

Technical Safety Requirements for the Waste Storage Facilities

International Nuclear Information System (INIS)

Larson, H L

2007-01-01

This document contains Technical Safety Requirements (TSR) for the Radioactive and Hazardous Waste Management (RHWM) WASTE STORAGE FACILITIES, which include Area 612 (A612) and the Decontamination and Waste Treatment Facility (DWTF) Storage Area at Lawrence Livermore National Laboratory (LLNL). The TSRs constitute requirements regarding the safe operation of the WASTE STORAGE FACILITIES. These TSRs are derived from the Documented Safety Analysis for the Waste Storage Facilities (DSA) (LLNL 2006). The analysis presented therein determined that the WASTE STORAGE FACILITIES are low-chemical hazard, Hazard Category 2 non-reactor nuclear facilities. The TSRs consist primarily of inventory limits and controls to preserve the underlying assumptions in the hazard and accident analyses. Further, appropriate commitments to safety programs are presented in the administrative controls sections of the TSRs. The WASTE STORAGE FACILITIES are used by RHWM to handle and store hazardous waste, TRANSURANIC (TRU) WASTE, LOW-LEVEL WASTE (LLW), mixed waste, California combined waste, nonhazardous industrial waste, and conditionally accepted waste generated at LLNL as well as small amounts from other U.S. Department of Energy (DOE) facilities, as described in the DSA. In addition, several minor treatments (e.g., drum crushing, size reduction, and decontamination) are carried out in these facilities. The WASTE STORAGE FACILITIES are located in two portions of the LLNL main site. A612 is located in the southeast quadrant of LLNL. The A612 fenceline is approximately 220 m west of Greenville Road. The DWTF Storage Area, which includes Building 693 (B693), Building 696 Radioactive Waste Storage Area (B696R), and associated yard areas and storage areas within the yard, is located in the northeast quadrant of LLNL in the DWTF complex. The DWTF Storage Area fenceline is approximately 90 m west of Greenville Road. A612 and the DWTF Storage Area are subdivided into various facilities and storage

Technical Safety Requirements for the Waste Storage Facilities

Energy Technology Data Exchange (ETDEWEB)

Larson, H L

2007-09-07

This document contains Technical Safety Requirements (TSR) for the Radioactive and Hazardous Waste Management (RHWM) WASTE STORAGE FACILITIES, which include Area 612 (A612) and the Decontamination and Waste Treatment Facility (DWTF) Storage Area at Lawrence Livermore National Laboratory (LLNL). The TSRs constitute requirements regarding the safe operation of the WASTE STORAGE FACILITIES. These TSRs are derived from the Documented Safety Analysis for the Waste Storage Facilities (DSA) (LLNL 2006). The analysis presented therein determined that the WASTE STORAGE FACILITIES are low-chemical hazard, Hazard Category 2 non-reactor nuclear facilities. The TSRs consist primarily of inventory limits and controls to preserve the underlying assumptions in the hazard and accident analyses. Further, appropriate commitments to safety programs are presented in the administrative controls sections of the TSRs. The WASTE STORAGE FACILITIES are used by RHWM to handle and store hazardous waste, TRANSURANIC (TRU) WASTE, LOW-LEVEL WASTE (LLW), mixed waste, California combined waste, nonhazardous industrial waste, and conditionally accepted waste generated at LLNL as well as small amounts from other U.S. Department of Energy (DOE) facilities, as described in the DSA. In addition, several minor treatments (e.g., drum crushing, size reduction, and decontamination) are carried out in these facilities. The WASTE STORAGE FACILITIES are located in two portions of the LLNL main site. A612 is located in the southeast quadrant of LLNL. The A612 fenceline is approximately 220 m west of Greenville Road. The DWTF Storage Area, which includes Building 693 (B693), Building 696 Radioactive Waste Storage Area (B696R), and associated yard areas and storage areas within the yard, is located in the northeast quadrant of LLNL in the DWTF complex. The DWTF Storage Area fenceline is approximately 90 m west of Greenville Road. A612 and the DWTF Storage Area are subdivided into various facilities and storage

Energy Storage: Batteries and Fuel Cells for Exploration

Science.gov (United States)

Manzo, Michelle A.; Miller, Thomas B.; Hoberecht, Mark A.; Baumann, Eric D.

2007-01-01

NASA's Vision for Exploration requires safe, human-rated, energy storage technologies with high energy density, high specific energy and the ability to perform in a variety of unique environments. The Exploration Technology Development Program is currently supporting the development of battery and fuel cell systems that address these critical technology areas. Specific technology efforts that advance these systems and optimize their operation in various space environments are addressed in this overview of the Energy Storage Technology Development Project. These technologies will support a new generation of more affordable, more reliable, and more effective space systems.

Acceptance criteria for interim dry storage of aluminum-clad fuels

International Nuclear Information System (INIS)

Sindelar, R.L.; Peacock, H.B. Jr.; Iyer, N.C.; Louthan, M.R. Jr.

1994-01-01

Direct repository disposal of foreign and domestic research reactor fuels owned by the United States Department of Energy is an alternative to reprocessing (together with vitrification of the high level waste and storage in an engineered barrier) for ultimate disposition. Neither the storage systems nor the requirements and specifications for acceptable forms for direct repository disposal have been developed; therefore, an interim storage strategy is needed to safely store these fuels. Dry storage (within identified limits) of the fuels received from wet-basin storage would avoid excessive degradation to assure post-storage handleability, a full range of ultimate disposal options, criticality safety, and provide for maintaining confinement by the fuel/clad system. Dry storage requirements and technologies for US commercial fuels, specifically zircaloy-clad fuels under inert cover gas, are well established. Dry storage requirements and technologies for a system with a design life of 40 years for dry storage of aluminum-clad foreign and domestic research reactor fuels are being developed by various groups within programs sponsored by the DOE

The impact of carbon materials on the hydrogen storage properties of light metal hydrides

NARCIS (Netherlands)

Adelhelm, P.A.; de Jongh, P.E.

2011-01-01

The safe and efficient storage of hydrogen is still one of the remaining challenges towards fuel cell powered cars. Metal hydrides are a promising class of materials as they allow the storage of large amounts of hydrogen in a small volume at room temperature and low pressures. However, usually the

Safe management of waste from health-care activities

International Nuclear Information System (INIS)

Pruess, A.; Giroult, E.; Rushbrook, P.

1999-01-01

The waste produced in the course of health-care activities, from contaminated needles to radioactive isotopes, carries a greater potential for causing infection and injury than any other type of waste, and inadequate or inappropriate management is likely to have serious public health consequences and deleterious effects on the environment. This handbook - the result of extensive international consultation and collaboration - provides comprehensive guidance on safe, efficient, and environmentally sound methods for the handling and disposal of health-care wastes. The various categories of waste are clearly defined and the particular hazards that each poses are described. Considerable prominence is given to the careful planning that is essential for the success of waste management; workable means of minimizing waste production are outlined and the role of reuse and recycling of waste is discussed. Most of the text, however, is devoted to the collection, segregation, storage, transport, and disposal of wastes. Details of containers for each category of waste, labelling of waste packages, and storage conditions are provided, and the various technologies for treatment of waste and disposal of final residues are discussed at length. Advice is given on occupational safety for all personnel involved with waste handling, and a separate chapter is devoted to the closely related topic of hospital hygiene and infection control. The handbook pays particular attention to basic processes and technologies that are not only safe but also affordable, sustainable, and culturally appropriate. For health-care settings in which resources are severely limited there is a separate chapter on minimal programmes; this summarizes all the simplest and least costly techniques that can be employed for the safe management of health-care wastes. The guide is aimed at public health managers and policy-makers, hospital managers, environmental health professionals, and all administrators with an

Bases for extrapolating materials durability in fuel storage pools

International Nuclear Information System (INIS)

Johnson, A.B. Jr.

1994-12-01

A major body of evidence indicates that zirconium alloys have the most consistent and reliable durability in wet storage, justifying projections of safe wet storage greater than 50 y. Aluminum alloys have the widest range of durabilities in wet storage; systematic control and monitoring of water chemistry have resulted in low corrosion rates for more than two decades on some fuels and components. However, cladding failures have occurred in a few months when important parameters were not controlled. Stainless steel is extremely durable when stress, metallurgical and water chemistry factors are controlled. LWR SS cladding has survived for 25 y in wet storage. However, sensitized, stressed SS fuels and components have seriously degraded in fuel storage pools (FSPs) at ∼ 30 C. Satisfactory durability of fuel assembly and FSP component materials in extended wet storage requires investments in water quality management and surveillance, including chemical and biological factors. The key aspect of the study is to provide storage facility operators and other decision makers a basis to judge the durability of a given fuel type in wet storage as a prelude to basing other fuel management plans (e.g. dry storage) if wet storage will not be satisfactory through the expected period of interim storage

Pain and Anxiety in Rural Acute Coronary Syndrome Patients Awaiting Diagnostic Cardiac Catheterization.

Science.gov (United States)

O'Keefe-McCarthy, Sheila; McGillion, Michael; Clarke, Sean P; McFetridge-Durdle, Judith

2015-01-01

In rural areas of Canada, people with acute coronary syndromes (ACS) can wait up to 32 hours for transfer for diagnostic cardiac catheterization (CATH). While awaiting CATH, it is critical that pain and anxiety management be optimal to preserve myocardial muscle and minimize the risk of further deterioration. The aim of this study was to examine the relationship between clinical management, cardiac pain intensity, and state anxiety for rural ACS patients awaiting diagnostic CATH. In a prospective, descriptive-correlational repeated-measures design involving 121 ACS rural patients, we examined the associations of analgesic and nitroglycerin administration with cardiac pain intensity (numeric rating scale) and state anxiety (Spielberger State Anxiety Inventory) and also nurses' pain knowledge and attitudes (Toronto Pain Management Inventory-ACS Version and Knowledge and Attitudes Survey Regarding Pain) using linear mixed models. The mean age of patients was 67.6 ± 13, 50% were men, and 60% had unstable angina and the remainder had non-ST-elevated myocardial infarction. During follow-up, cardiac pain intensity scores remained in the mild range from 1.1 ± 2.2 to 2.4 ± 2.7. State anxiety ranged from 44.0 ± 7.2 to 46.2 ± 6.6. Cumulative analgesic dose was associated with a reduction in cardiac pain by 1.0 points (numeric rating scale, 0-10) (t108 = -2.5; SE, -0.25; confidence interval, -0.45 to -0.06; P = .013). Analgesic administration was not associated with state anxiety. Over the course of follow-up, ACS patients reported consistently high anxiety scores. Whereas cardiac pain declines in most patients in the early hours after admission, many patients experience a persistent anxious state up to 8 hours later, which suggest that development and testing of protocols for anxiety reduction may be needed. More urgently, the development and examination of a treatment intervention, early on in the ACS trajectory, are warranted that targets pain and anxiety for those for

Utilization of Boxes for Pesticide Storage in Sri Lanka

DEFF Research Database (Denmark)

Pieris, Ravi; Weerasinghe, Manjula; Abeywickrama, Tharaka

2017-01-01

Pesticide self-poisoning is now considered one of the two most common methods of suicide worldwide. Encouraging safe storage of pesticides is one particular approach aimed at reducing pesticide self-poisoning. CropLife Sri Lanka (the local association of pesticide manufacturers), with the aid of ...

Digital Device Architecture and the Safe Use of Flash Devices in Munitions

Science.gov (United States)

Katz, Richard B.; Flowers, David; Bergevin, Keith

2017-01-01

Flash technology is being utilized in fuzed munition applications and, based on the development of digital logic devices in the commercial world, usage of flash technology will increase. Digital devices of interest to designers include flash-based microcontrollers and field programmable gate arrays (FPGAs). Almost a decade ago, a study was undertaken to determine if flash-based microcontrollers could be safely used in fuzes and, if so, how should such devices be applied. The results were documented in the Technical Manual for the Use of Logic Devices in Safety Features. This paper will first review the Technical Manual and discuss the rationale behind the suggested architectures for microcontrollers and a brief review of the concern about data retention in flash cells. An architectural feature in the microcontroller under study will be discussed and its use will show how to screen for weak or failed cells during manufacture, storage, or immediately prior to use. As was done for microcontrollers a decade ago, architectures for a flash-based FPGA will be discussed, showing how it can be safely used in fuzes. Additionally, architectures for using non-volatile (including flash-based) storage will be discussed for SRAM-based FPGAs.

Conceptual design of reactor TRIGA PUSPATI (RTP) spent fuel storage rack

International Nuclear Information System (INIS)

Tonny Lanyau; Mohd Fazli Zakaria; Zaredah Hashim; Ahmad Nabil Ab Rahim; Mohammad Suhaimi Kassim

2010-01-01

PUSPATI TRIGA Reactor (RTP) is a pool type research reactor with 1MW thermal power. It has been safely operated since 28 June 1982. During 28 years of safe operation, there are several systems and components of the RTP that have been maintained, repaired, upgraded and replaced in order to maintain its function and safety conditions. RTP has been proposed to be upgraded so that optimum operation of RTP could be achieved as well as fulfill the future needs. Thus, competencies and technical capabilities were needed to design and develop the reactor system. In the meantime, there is system or component need to be maintained such as fuel elements. Since early operation, most of the fuel elements still can be used and none of the fuel elements was replaced or sent for reprocessing and final disposal. Towards the power upgrading, preparation of spent fuel storage is needed for temporary storing of the fuels discharged from the reactor core. The spent fuel storage rack will be located in the spent fuel pool to accommodate the spent fuels before it is send to reprocessing or final disposal. This paper proposes the conceptual design of the spent fuel storage rack. The output of this paper focused on the physical and engineering design of the spent fuel storage. (author)

Underside corrosion of above ground storage tanks (ASTs) | Rim ...

African Journals Online (AJOL)

... above statutory safe limits. The results showed that the physico-chemical characteristics of the water sample have diagnostic and predictive values to implicate and promote underside corrosion of the studied above ground storage tank. Journal of Applied Sciences and Environmental Management Vol. 9(1) 2005: 161-163.

Gun retailers as storage partners for suicide prevention: what barriers need to be overcome?

Science.gov (United States)

Pierpoint, Lauren A; Tung, Gregory J; Brooks-Russell, Ashley; Brandspigel, Sara; Betz, Marian; Runyan, Carol W

2018-02-07

Safe storage of guns outside the household while someone is at risk for suicide is important for suicide prevention. Some gun retailers offer temporary firearm storage as a community resource. Others may be willing if perceived barriers can be addressed. We invited all gun retailers in eight Mountain West states to respond to a questionnaire about the barriers they perceive in offering temporary, voluntary gun storage for community members. Ninety-five retailers responded (25% response rate). Fifty-eight percent believed federal laws make it harder to store guns and 25% perceived state laws to be obstacles. Over 60% cited legal liability in storing and returning guns as barriers. Other important barriers included cost, space and logistical issues of drop off and pick up. Strategies to reduce legal and other barriers will need to be addressed to better engage gun retailers as a community resource for safe gun storage. © Article author(s) (or their employer(s) unless otherwise stated in the text of the article) 2018. All rights reserved. No commercial use is permitted unless otherwise expressly granted.

Storage of radioactive material - accidents - precipitation - personnel monitoring

International Nuclear Information System (INIS)

Matijasic, A.; Gacinovic, O.

1961-12-01

This volume covers the reports on four routine tasks concerned with safe handling of radioactive material and influence of nuclear facilities on the environment. The tasks performed were as follows: Storage of solid and liquid radioactive material; actions in case of accidents; radiation monitoring of the fallout, water and ground; personnel dosimetry

Spent Nuclear Fuel project stage and store K basin SNF in canister storage building functions and requirements. Revision 1

International Nuclear Information System (INIS)

Womack, J.C.

1995-01-01

This document establishes the functions and requirements baseline for the implementation of the Canister Storage Building Subproject. The mission allocated to the Canister Storage Building Subproject is to provide safe, environmentally sound staging and storage of K Basin SNF until a decision on the final disposition is reached and implemented

Feasibility of safe terminal disposal of spent nuclear fuel

International Nuclear Information System (INIS)

Nilsson, B.; Papp, T.

1980-01-01

The results of the KBS study indicate that safe terminal storage of spent nuclear fuel in crystalline rock is feasible with the technology available today and at a safety level that is well within the limitations recommended by the ICRP. This statement is not only based on the fact that the doses calculated in the KBS study were acceptably low, but even more on the freedom to choose the dimensions of the engineered barriers as well as depth of the repository and to some degree the quality of the host rock

Gas adsorption during storage of plutonium dioxide powders

International Nuclear Information System (INIS)

Cuillerdier, C.; Cossonnet, C.; Germain, M.

1984-10-01

Adsorption phenomena occuring in plutonium dioxide containers are studied for the determination of safe conditions for storage and transportation of plutonium dioxide powders. Adsorption on dried PuO 2 of air individual gases, influence of powder isotopic composition, chemisorption, effect of moisture are determined. Adsorption of dry air obeys an Elovich's law for its kinetics it is greatly exchange by α radiolysis. Pressure in the container can be reduced by storage under dry inert gas (Ar), decreasing the PuO 2 load and using powder containing preadsorbed water or wet air then radiolysis may occur (H 2 formation)

Versatile Endpoint Storage Security with Trusted Integrity Modules

DEFF Research Database (Denmark)

Gonzalez, Javier; Bonnet, Philippe

2014-01-01

. To counter such threats, and to remain trustworthy, personal devices should enforce storage security. State-of-the-art storage security solutions rely on hardware protected encryption. They cannot be deployed, as such, on personal devices either because they require additional hardware (e.g., NetApp’s Safe...... system and applications, that guarantee the durability, confidentiality and integrity of a configurable subset of the filesystem data and meta-data. While, we detail our design with the Linux virtual file system, we expect that our results can be applied to a range of different file systems. As Trusted...

Recycling of chemical hydrogen storage materials

International Nuclear Information System (INIS)

Lo, C.F.; Davis, B.R.; Karan, K.

2004-01-01

'Full text:' Light weight chemical hydrides such as sodium borohydride (NaBH4) and lithium borohydride (LiBH4) are promising hydrogen storage materials. They offer several advantages including high volumetric storage density, safe storage, practical storage and operating condition, controlled and rapid hydrogen release kinetics in alkaline aqueous media in the presence of catalysts. In addition, borate or borax, the reaction by-product, is environmentally friendly and can be directly disposed or recycled. One technical barrier for utilizing borohydrides as hydrogen storage material is their high production cost. Sodium borohydride currently costs $90 per kg while lithium borohydride costs $8000 per kg. For commercialization, new and improved technology to manufacture borohydrides must be developed - preferably by recycling borates. We are investigating different inorganic recycling routes for regenerating borohydrides from borates. In this paper, the results of a chlorination-based recycling route, incorporating multi-step reactions, will be discussed. Experiments were conducted to establish the efficiency of various steps of the selected regeneration process. The yields of desired products as a function of reaction temperature and composition were obtained from multi-phase batch reactor. Separation efficiency of desired product was also determined. The results obtained so far appear to be promising. (author)

Activity release during the dry storage of fuel assemblies

International Nuclear Information System (INIS)

Valentine, M.K.; Fettel, W.; Gunther, H.

1991-01-01

This paper reports that wet storage is the predominant storage method in the USA for spent fuel assemblies. Nevertheless, most utilities have stretched their storage capacities and several reactors will lose their full-core reserve in the 90's. A great variety of out-of-pool storage methods already exist, including the FUELSTOR vault-type dry storage concept. A FUELSTOR vault relies on double containment of the spent fuel (intact cladding as the primary containment and sealing of assemblies in canisters filled with an inert gas as the secondary containment) to reduce radiation levels at the outside wall of the vault to less than site boundary levels. Investigation of accident scenarios reveals that radiation release limits are only exceeded following complete failure of all canisters and simultaneous cladding breach for more than 40% of the rods (or for more than 1% of failed rods if massive fuel oxidation occurs following cladding failure). Such failures are considered highly improbable. Thus, it can be concluded that this type of dry storage is safe and individual canister monitoring is not required in the facility

Time to rethink nuclear waste storage

International Nuclear Information System (INIS)

Flynn, J.; Kasperson, R.; Kunreuther, H.; Slovic, P.

1992-01-01

The authors feel that given the levels of public opposition and distrust, congress should scrap the current nuclear waste storage program and reconsider the options. They observe that no compelling reason currently exists for siting a permanent repository at an early date. Technology developed in the past decade, especially dry-cask storage, provides assurance that wastes from commercial reactors can be stored safely for a lengthy period at current sites. In the longer term, reprocessing may reduce the volume of high-level wastes; storage elsewhere than in a geological repository may prove attractive; and experimental techniques such as transmutation - aimed at radically reducing the amount of time that wastes remain highly radioactive - could help solve the problem. In the meantime, the authors suggest that the US must begin a long-term effort to engage the public in a process of active collaboration. In doing so, the US has much to learn from other countries, where innovative approaches and techniques have began to establish public confidence

Application of new physical storage technology in fruit and ...

African Journals Online (AJOL)

With the development of science and technology, consumers not only require food to be safe, but also require them to keep the original natural flavor and nutritional value as well, while the traditional chemical storage method has been increasingly unable to satisfy consumers' demand. When compared with chemical ...

Willingness to pay for safe drinking water: Evidence from Parral, Mexico.

Science.gov (United States)

Vásquez, William F; Mozumder, Pallab; Hernández-Arce, Jesús; Berrens, Robert P

2009-08-01

A referendum-format contingent valuation (CV) survey is used to elicit household willingness to pay responses for safe and reliable drinking water in Parral, Mexico. Households currently adopt a variety of averting and private investment choices (e.g., bottled water consumption, home-based water treatment, and installation of water storage facilities) to adapt to the existing water supply system. These revealed behaviors indicate the latent demand for safer and more reliable water services, which is corroborated by the CV survey evidence. Validity findings include significant scope sensitivity in WTP for water services. Further, results indicate that households are willing to pay from 1.8% to 7.55% of reported household income above their current water bill for safe and reliable drinking water services, depending upon the assumptions about response uncertainty.

Sex Differences in Mortality Based on United Network for Organ Sharing Status While Awaiting Heart Transplantation.

Science.gov (United States)

Hsich, Eileen M; Blackstone, Eugene H; Thuita, Lucy; McNamara, Dennis M; Rogers, Joseph G; Ishwaran, Hemant; Schold, Jesse D

2017-06-01

There are sex differences in mortality while awaiting heart transplantation, and the reason remains unclear. We included all adults in the Scientific Registry of Transplant Recipients placed on the heart transplant active waitlist from 2004 to 2015. The primary end point was all-cause mortality. Multivariable Cox proportional hazards models were performed to evaluate survival by United Network for Organ Sharing (UNOS) status at the time of listing. Random survival forest was used to identify sex interactions for the competing risk of death and transplantation. There were 33 069 patients (25% women) awaiting heart transplantation. This cohort included 7681 UNOS status 1A (26% women), 13 027 UNOS status 1B (25% women), and 12 361 UNOS status 2 (26% women). During a median follow-up of 4.3 months, 1351 women and 4052 men died. After adjusting for >20 risk factors, female sex was associated with a significant risk of death among UNOS status 1A (adjusted hazard ratio, 1.14; 95% confidence interval, 1.01-1.29) and UNOS status 1B (adjusted hazard ratio, 1.17; 95% confidence interval, 1.05-1.30). In contrast, female sex was significantly protective for time to death among UNOS status 2 (adjusted hazard ratio, 0.85; 95% confidence interval, 0.76-0.95). Sex differences in probability of transplantation were present for every UNOS status, and >20 sex interactions were identified for mortality and transplantation. When stratified by initial UNOS status, women had a higher mortality than men as UNOS status 1 and a lower mortality as UNOS status 2. With >20 sex interactions for mortality and transplantation, further evaluation is warranted to form a more equitable allocation system. © 2017 American Heart Association, Inc.

Seven years of experience in storage of solid radioactive wastes of low and medium activity on the surface or in concrete ditches

International Nuclear Information System (INIS)

Bardet, G.

This experience in the transport and storage of radioactive waste leads to several reflections pertinent to large-scale nuclear installations throughout the world. The experience demonstrates that products of this kind can be centralized and confined by relatively simple processes which are safe and of reasonable cost. The necessary liaison between the producer of radioactive wastes and the group which takes charge of storage is emphasized for the choice of the waste conditioning procedure. It is a consistent part of the experience that the initial conditioning determines in large measure the handling and storage techniques. It is certain that the absence of a solution for long-term storage of radioactive wastes will lead the producers to consider and carry out conditioning which, although valuable, does not have all the same advantages for final disposition of the product. In the field of transport, the volumes and weights are important. It is desirable that a permanent storage center be near a railroad. It is stated that storage can be ensured under safe conditions and with acceptable costs of all solid wastes of low and average activity except those having more than a certain amount of alpha activity. For the latter products a solution can be found which is safe

Gender difference in safe and unsafe practice of pesticide handling in tobacco farmers of malaysia.

Science.gov (United States)

Bin Nordin, R; Araki, S; Sato, H; Yokoyama, K; Bin Wan Muda, W A; Win Kyi, D

2001-01-01

To identify gender difference in safe and unsafe practice of pesticide handling in tobacco farmers of Malaysia, we conducted a 20-item questionnaire interview on storage of pesticide (4 questions), mixing of pesticide (3 questions), use of personal protective equipment and clothing while spraying pesticide (7 questions), activities during and after spraying of pesticide (5 questions), and maintenance of pesticide sprayer (1 question) in 496 tobacco farmers (395 males and 101 females) in Bachok District, Kelantan, Malaysia. Duration of employment was significantly longer in females than those in males (pwork habit, (3) reading and following instructions on pesticide label, (4) security, storage and disposal of pesticide container, (5) safe work habit, (6) proper handling of pesticide and maintenance of pesticide sprayer, (7) use of personal protective clothing, and (8) safe handling of pesticide. Results of analysis of covariance for the eight factor scores of all male and female farmers, controlling for educational level and duration of employment, showed that: (1) factor scores for use of personal protective equipment (pwork habit (p0.05). We therefore conclude that: (1) for female tobacco farmers, choice of personal attire tend to result in lower scores on use of personal protective equipment and personal protective clothing while personal hygiene practices result in lower score on safe work habit; and, (2) for male tobacco farmers, the lower scores on reading and following instruction on pesticide label and mixing pesticide and maintenance of pesticide sprayer in good condition suggests that they were not primarily involved in these activities. It is postulated that these differences in safe and unsafe practices of pesticide handling across gender is related to the choice of personal attire, personal hygiene practices and division of labour within farming households which in turn is influenced by prevailing sociocultural norms in the community.

Assessment of dry storage performance of spent LWR fuel assemblies with increasing burnup

International Nuclear Information System (INIS)

Peehs, M.; Garzarolli, F.; Goll, W.

1999-01-01

Although the safety of a dry long-term spent fuel store is scarcely influenced if a few fuel rods start to leak during extended storage - since all confinement systems are designed to retain gaseous activity safely - it is a very conservative safety goal to avoid the occurrence of systematic rod defects. To assess the extended storage performance of a spent fuel assembly (FA), the experience can be collated into 3 storage modes: I - fast rate of temperature decrease δ max ≥ δ ≥ 300 deg. C, II - medium rate of decrease for the fuel rod dry storage temperature 300 deg. C > δ ≥ 200 deg. C, III - slow to negligible rate of temperature decrease for δ 2 -fuel are practically immobile during storage. Consequently all fission-product-driven defect mechanisms will not take place. The leading defect mechanism - also for fuel rods with increased burnup - remains creep due to the hoop strain resulting from the fuel rod internal fission gas pressure. Limiting the creep to its primary and secondary stages prevents fuel rod degradation. The allowable uniform strain of the cladding is 1 - 2%. Calculations were performed to predict the dry storage performance of fuel assemblies with a burnup ≤ 55 GW · d/tHM based on the fuel assemblies end of life (EOL)-data and on a representative curve T = f(t). The maximum allowable hot spot temperature of a fuel rod in the CASTOR V cask was between 348 deg. C (U FA) and 358 deg. C (MOX FA). The highest hoop strain predicted after 40 years of storage is 0.77% proving that spent LWR fuel dry storage is safe. (author)

Problems of the Spent Nuclear Fuel Storage

International Nuclear Information System (INIS)

Negrivoda, G.

1997-01-01

Approximately 99% of the radioactivity in waste, produced in the process of operating a nuclear power plant, is contained in spent nuclear fuel. Safe handling and storage of the spent nuclear fuel is an important factor of a nuclear plant safety. Today at Ignalina NPP the spent fuel is stored in special water pools, located in the same buildings as the reactors. The volume of the pools is limited, for unit one the pool will be fully loaded in 1998, for unit 2 - in 2000. The further operation of the plant will only be possible if new storage is constructed. In 1994 contract with German company GNB was signed for the supply of 20 containers of the CASTOR type. Containers were delivered in accordance with agreed schedule. In the end of 1995 a new tender for new storage options was announced in order to minimize the storage costs. A proposal from Canadian company AECL now is being considered as one of the most suitable and negotiations to sign the contract started. (author)

76 FR 12719 - Safe Schools/Healthy Students Program; Office of Safe and Drug-Free Schools; Safe Schools/Healthy...

Science.gov (United States)

2011-03-08

... DEPARTMENT OF EDUCATION Safe Schools/Healthy Students Program; Office of Safe and Drug- Free Schools; Safe Schools/Healthy Students Program; Catalog of Federal Domestic Assistance (CFDA) Numbers: 84... priorities, requirements, and definitions under the Safe Schools/Healthy Students (SS/HS) program. Since...

Los Alamos National Laboratory Site Integrated Management plan, uranium 233 storage and disposition. Volume 1: Project scope and description

International Nuclear Information System (INIS)

Nielsen, J.B.; Erickson, R.

1997-01-01

This Site Integration Management plan provides the Los Alamos Response to the Defense Nuclear Facility Safety Board (DNFSB) Recommendation 97-1. This recommendation addresses the safe storage and management of the Departments uranium 233 ( 233 U) inventory. In the past, Los Alamos has used 233 U for a variety of different weapons related projects. The material was used at a variety of sites in varying quantities. Now, there is a limited need for this material and the emphasis has shifted from use to storage and disposition of the material. The Los Alamos program to address the DNFSB Recommendation 97-1 has two emphases. First, take corrective action to address near term deficiencies required to provide safe interim storage of 233 U. Second, provide a plan to address long term storage and disposition of excess inventory at Los Alamos

A conservation vent is not a safe substitute for a flame arrester

Energy Technology Data Exchange (ETDEWEB)

Siestrup, Francisco Hubertus Grosse [Protego Leser do Brasil Ltda., Rio de Janeiro, RJ (Brazil)

2009-07-01

For several decades state organizations and engineering societies have published strict engineering guidelines for the design and safe management of storage tanks. Storage tanks in refineries and chemical plants can contain flammable and hazardous chemicals. Accidents in these systems resulting from explosions can cause million dollar property loss and production interruption. In severe cases lawsuits may result and companies can even be driven into bankruptcy. This article focuses on tests which have been conducted by the PROTEGO Research and Development Group in Braunschweig, Germany. Latest research, in which conservation vents have been tested in accordance to the new ISO 16852 test method, have proven that conservation vents cannot be used to substitute a flame arrester if potentially explosive atmospheres are present in storage tanks. This research was conducted during the development of ISO 28300 and the test results are considered in this standard. This paper will prove that the use of conservation vents to protect tanks from atmospheric explosion is not a reliable protection method when the vapor/air mixtures in the tank have a concentration between the Upper and Lower Explosive Limits (UEL and LEL). This is very common for Ethanol storage which is globally in evidence. (author)

Statement of position of the United States Department of Energy in the matter of proposed rulemaking on the storage and disposal of nuclear waste (waste confidence rulemaking)

International Nuclear Information System (INIS)

1980-01-01

Purpose of this proceeding is to assess generically the degree of assurance that the radioactive waste can be safely disposed of, to determine when such disposal or off-site storage will be available, and to determine whether wastes can be safely stored on-site past license expiration until off-site disposal/storage is available

Statement of position of the United States Department of Energy in the matter of proposed rulemaking on the storage and disposal of nuclear waste (waste confidence rulemaking)

Energy Technology Data Exchange (ETDEWEB)

None

1980-04-15

Purpose of this proceeding is to assess generically the degree of assurance that the radioactive waste can be safely disposed of, to determine when such disposal or off-site storage will be available, and to determine whether wastes can be safely stored on-site past license expiration until off-site disposal/storage is available. (DLC)

Criticality Safety Problems Related to Storage of Highly Active Liquid Waste

International Nuclear Information System (INIS)

Amin, E.

1999-01-01

The geometries of liquid waste storage tanks are not generally safe against criticality. Normally, this does not cause problems as fissile materials exist in nitric acid solution only as depleted uranium or in insignificant concentration of the originally reprocessed inventory of plutonium. However, if sedimentation of solid particles would occur, the deposited material would cause criticality safety problems. Particularly, non-horizontal installation of the storage tanks would increase the Eigen value. The effect of the storage tank inclination and the presence of transplutonium elements on the criticality safety are investigated using the NCNSRC code packages. The results are compared well with a similar German published results

Initial Operation of the Savannah River Site Advanced Storage Monitoring Facility

International Nuclear Information System (INIS)

McCurry, D.R.

2001-01-01

An advanced storage monitoring facility has been constructed at the Savannah River Site capable of storing sensitive nuclear materials (SNM) with access to monitoring information available over the Internet. This system will also have monitoring information available over the Internet to appropriate users. The programs will ultimately supply authenticated and encrypted data from the storage sites to certified users to demonstrate the capability of using the Internet as a safe and secure communications medium for remote monitoring of sensitive items

Used fuel extended storage security and safeguards by design roadmap

Energy Technology Data Exchange (ETDEWEB)

Durbin, Samuel G. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Lindgren, Eric Richard [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Jones, Robert [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); Ketusky, Edward [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); England, Jeffrey [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); Scherer, Carolynn [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Sprinkle, James [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Miller, Michael. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Rauch, Eric [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Scaglione, John [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Dunn, T. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States)

2016-05-01

In the United States, spent nuclear fuel (SNF) is safely and securely stored in spent fuel pools and dry storage casks. The available capacity in spent fuel pools across the nuclear fleet has nearly reached a steady state value. The excess SNF continues to be loaded in dry storage casks. Fuel is expected to remain in dry storage for periods beyond the initial dry cask certification period of 20 years. Recent licensing renewals have approved an additional 40 years. This report identifies the current requirements and evaluation techniques associated with the safeguards and security of SNF dry cask storage. A set of knowledge gaps is identified in the current approaches. Finally, this roadmap identifies known knowledge gaps and provides a research path to deliver the tools and models needed to close the gaps and allow the optimization of the security and safeguards approaches for an interim spent fuel facility over the lifetime of the storage site.

Microporous metal-organic frameworks for storage and separation of small hydrocarbons

NARCIS (Netherlands)

He, Y.; Zhou, W.; Krishna, R.; Chen, B.

2012-01-01

Hydrocarbons are very important energy resources and raw materials for some industrially important products and fine chemicals. There is a need for the discovery of better materials that offer enhanced capacities for safe storage of hydrocarbons. Furthermore, the development of improved separation

Cool and Safe: Multiplicity in Safe Innovation at Unilever

Science.gov (United States)

Penders, Bart

2011-01-01

This article presents the making of a safe innovation: the application of ice structuring protein (ISP) in edible ices. It argues that safety is not the absence of risk but is an active accomplishment; innovations are not "made safe afterward" but "safe innovations are made". Furthermore, there are multiple safeties to be accomplished in the…

Chest radiographic findings and complications of the temporary implantation of the Jarvik-7 artificial heart while patients await orthotopic heart transplantation

International Nuclear Information System (INIS)

Sadler, L.; Fuhrman, C.; Hardesty, R.; Griffith, B.

1987-01-01

At the University of Pittsburgh, the authors have had 15 patients in whom Jarvik-7 hearts were implanted as a temporary measure while the patients awaited suitable donors for cardiac transplantation. The paper presents a brief description of the Jarvik-7 artificial heart, factors affecting patient selection, and the radiographic appearance of a normally functioning Jarvik-7 heart, and reviews the chest radiographic complications seen in this patient group, along with eventual patient outcome

Adoption of the B2SAFE EUDAT replication service by the EPOS community

Science.gov (United States)

Cacciari, Claudio; Fares, Massimo; Fiameni, Giuseppe; Michelini, Alberto; Danecek, Peter; Wittenburg, Peter

2014-05-01

B2SAFE is the EUDAT service for moving and replicating data between sites and storage systems for different purposes. The goal of B2SAFE is to keep the data from a repository safe by replicating it across different geographical and administrative zones according to a set of well-defined policies. It is also a way to store large volumes of data permanently at those sites which are providing powerful on-demand data analysis facilities. In particular, B2SAFE operates on the domain of registered data where data objects are referable via persistent identifiers (PIDs). B2SAFE is more than just copying data because the PIDs must be carefully managed when data objects are moved or replicated. The EUDAT B2SAFE Service offers functionality to replicate datasets across different data centres in a safe and efficient way while maintaining all information required to easily find and query information about the replica locations. The information about the replica locations and other important information is stored in PID records, each managed in separate administrative domains. The B2SAFE Service is implemented as an iRODS module providing a set of iRODS rules or policies to interface with the EPIC handle API and uses the iRODS middleware to replicate datasets from a source data (or community) centre to a destination data centre. The definition of the dataset(s) to replicate is flexible and up to the communities using the B2SAFE service. While the B2SAFE is internally using the EPIC handle API, communities have the choice to use any PID system they prefer to assign PIDs to their digital objects. A reference to one or more EUDAT B2SAFE PIDs is returned by the B2SAFE service when a dataset is replicated. The presentation will introduce the problem space of B2SAFE, presents the achievements that have been made during the last year for enabling communities to make use of the B2SAFE service, demonstrates a EPOS use cases, outlines the commonalities and differences between the policies

Long-term storage and safe retrieval of human papillomavirus DNA using FTA elute cards.

Science.gov (United States)

Barth, Heidi; Morel, Adrien; Mougin, Christiane; Averous, Gerlinde; Legrain, Michèle; Fender, Muriel; Risch, Simone; Fafi-Kremer, Samira; Velten, Michel; Oudet, Pierre; Baldauf, Jean-Jacques; Stoll-Keller, Françoise

2016-03-01

Biobanking or collection and storage of specimens for future research purposes have become an essential tool in many fields of biomedical research and aims to provide a better understanding of disease mechanisms as well as the identification of disease-specific biomarkers that can navigate in complex diseases. In this study, we assessed the use of Flinders Technology Associates (FTA) cards as a long-term storage device for cervical specimens with suspected human papillomavirus (HPV) infections. HPV detection and genotyping results in liquid-based transport media were compared to HPV results from FTA cards. The overall agreement for the presence of any HPV infection between liquid-based medium and FTA cards stored for 1 year at ambient temperature was 100%. Reproducibility analysis of HPV detection and genotyping from FTA cards demonstrated that FTA cards are a reliable medium to store and preserve viral nucleic acids. Biobanking of cervical cells on FTA cards may provide a key resource for epidemiological and retrospective HPV studies. Copyright © 2015 Elsevier B.V. All rights reserved.

Computational Search for Improved Ammonia Storage Materials

DEFF Research Database (Denmark)

Jensen, Peter Bjerre; Lysgaard, Steen; Vegge, Tejs

Metal halide ammines, e.g. Mg(NH3)6Cl2 and Sr(NH3)8Cl2, can reversibly store ammonia, with high volumetric hydrogen storage capacities. The storage in the halide ammines is very safe, and the salts are therefore highly relevant as a carbon-free energy carrier in future transportation infrastructure...... selection. The GA is evolving from an initial (random) population and selecting those with highest fitness, a function based on e.g. stability, release temperature, storage capacity and the price of the elements. The search space includes all alkaline earth, 3d and 4d metals in combination with chloride......, bromide or iodide, and mixtures thereof. In total the search space consists of thousands of combinations, which makes a GA ideal, to reduce the number of necessary calculations. We are screening for a one step release from either a hexa or octa ammine, and we have found promising candidates, which...

Ontario hydro waste storage concepts and facilities

International Nuclear Information System (INIS)

Carter, T.J.; Mentes, G.A.

1976-01-01

Ontario Hydro presently operates 2,200 MWe of CANDU heavy water reactors with a further 11,000 MWe under design or construction. The annual quantities of low and medium level solid wastes expected to be produced at these stations are tabulated. In order to manage these wastes, Ontario Hydro established a Radioactive Waste Operations Site within the Bruce Nuclear Power Development located on Lake Huron about 250 km northwest of Toronto. The Waste Operations Site includes a 19-acre Storage Site plus a Radioactive Waste Volume Reduction Facility consisting of an incinerator and waste compactor. Ontario has in use or under construction both in-ground and above-ground storage facilities. In-ground facilities have been used for a number of years while the above-ground facilities are a more recent approach. Water, either in the form of precipitation, surface or subsurface water, presents the greatest concern with respect to confinement integrity and safe waste handling and storage operations

Keeping Sealed Radioactive Sources Safe and Secure

International Nuclear Information System (INIS)

Potterton, Louise

2013-01-01

Radioactive sources are used in a wide variety of devices in medical, industrial, agricultural and research facilities worldwide. These sources, such as cobalt-60 and caesium-137, emit high levels of ionizing radiation, which can treat cancer, measure materials used in industry and sterilize food and medical appliances. Problems may arise when these sources are no longer needed, or if they are damaged or decayed. If these sources are not properly stored they can be a threat to human health and the environment and pose a security risk. Procedures to secure these spent or 'disused' sources are often highly expensive and need specialized assistance. The IAEA helps its States find long term solutions for the safe and secure storage of disused sealed radioactive sources (DSRSs)

Manipulation technology optimization for the interim storage of HAW transport and storage containers; Optimierung der Handhabungstechnik zur Zwischenlagerung von HAW-Transport- und Lagerbehaeltern

Energy Technology Data Exchange (ETDEWEB)

Emmrich, Uwe; Krueger, Michael; Schulze, Hartmut [GNS Gesellschaft fuer Nuklear-Service mbH, Essen (Germany)

2011-07-01

The handling of high-level radioactive waste transport and storage containers from reprocessing plants is determined by the cask configuration and the radiation protection measures with respect to the safe enclosure of the radioactive inventory and shielding of gamma and neutron radiation. The new of CASTOR {sup registered} HAW28M was designed for higher radioactive inventories, the heat generation is has rarely been changed with respect to the former design. The essential structural modifications are shock absorbers that have to be demounted before storage in the interim storage facility Gorleben. Due to public acceptance forcings the ALARA principle is not the only basis for manipulation technology optimizations, the minimization of dose rate for the operational personnel is of increasing importance. The authors describe the optimizations and the resulting dose reductions.

Preparatory mining and geotechnical work for safe closure of the Asse mine

International Nuclear Information System (INIS)

Schmidt, M.W.; Schauermann, V.; Kappei, G.

2002-01-01

After the GSF Research Centre for Environment and Health discontinued its own research into the safe ultimate storage of waste hazardous to the environment in deep geological formations and the work of the Institute for Deep Storage was likewise suspended there is no longer any need to continue operation of the Asse mine for research purposes. Hence the closure of the mine is being prepared on the basis of the Federal Mining Act. The GSF accordingly has to submit a final operating plan, with which a comprehensive safety report containing inter alia proof of the long-time safety should be enclosed. The proof should be furnished according to the specific location and takes into account the geological, hydrogeological, geochemical, geotechnical, mining-related conditions and the radionuclide inventory in the Asse mine. (orig.) [de

LLRW storage: Perspectives from the Northeast

International Nuclear Information System (INIS)

Tammemagi, H.Y.

1990-01-01

It is very difficult to predict development in the low-level radioactive waste (LLRW) scene for the coming decade because of the unsettled climate at present. However, it is becoming increasingly clear that storage will play an important role in the LLRW management equation. It is a vital and integral component of meeting the intent of the federal LLW Acts and all states and compacts, as well as individual generators, should be factoring it into their management strategies. The reason is that the mandated milestones are not going to be met. Very few states or compacts will comply with either the 1993 or 1996 deadlines. New York provides a good example of how a dedicated, conscientious and well-funded effort to locate a site for disposal facility was thwarted by public pressure, and progress in New York will be greatly delayed. Storage is an inevitable requirement. As will be shown, the technology for LLRW storage is not complicated. There are proven, safe and cost efficient methods available. However, they must be implemented with care and political, licensing and public interaction processes must be included. This all requires time. It is important that storage plans be developed early and in parallel with disposal plans and receive the same degree of intellectual effort and commitment. In this presentation the author describes some of the storage technologies that are being successfully used today. The paper discusses some of the alternative methods by which these technologies might be implemented and reviews the storage strategies that are being used by some of the states in the Northeast

303-K Storage Facility closure plan

International Nuclear Information System (INIS)

1993-01-01

Recyclable scrap uranium with zircaloy-2 and copper silicon alloy, uranium-titanium alloy, beryllium/zircaloy-2 alloy, and zircaloy-2 chips and fines were secured in concrete billets (7.5-gallon containers) in the 303-K Storage Facility, located in the 300 Area. The beryllium/zircaloy-2 alloy and zircaloy-2 chips and fines are designated as mixed waste with the characteristic of ignitability. The concretion process reduced the ignitability of the fines and chips for safe storage and shipment. This process has been discontinued and the 303-K Storage Facility is now undergoing closure as defined in the Resource Conservation and Recovery Act (RCRA) of 1976 and the Washington Administrative Code (WAC) Dangerous Waste Regulations, WAC 173-303-040. This closure plan presents a description of the 303-K Storage Facility, the history of materials and waste managed, and the procedures that will be followed to close the 303-K Storage Facility. The 303-K Storage Facility is located within the 300-FF-3 (source) and 300-FF-5 (groundwater) operable units, as designated in the Hanford Federal Facility Agreement and Consent Order (Tri-Party Agreement) (Ecology et al. 1992). Contamination in the operable units 300-FF-3 and 300-FF-5 is scheduled to be addressed through the Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) of 1980 remedial action process. Therefore, all soil remedial action at the 304 Facility will be conducted as part of the CERCLA remedial action of operable units 300-FF-3 and 300-FF-5

Measurement Properties of Performance-Specific Pain Ratings of Patients Awaiting Total Joint Arthroplasty as a Consequence of Osteoarthritis

Science.gov (United States)

Stratford, Paul W.; Kennedy, Deborah M.; Woodhouse, Linda J.; Spadoni, Gregory

2008-01-01

Purpose: To estimate the test–retest reliability of the Western Ontario and McMaster Universities Osteoarthritis Index (WOMAC) pain sub-scale and performance-specific assessments of pain, as well as the association between these measures for patients awaiting primary total hip or knee arthroplasty as a consequence of osteoarthritis. Methods: A total of 164 patients awaiting unilateral primary hip or knee arthroplasty completed four performance measures (self-paced walk, timed up and go, stair test, six-minute walk) and the WOMAC. Scores for 22 of these patients provided test–retest reliability data. Estimates of test–retest reliability (Type 2,1 intraclass correlation coefficient [ICC] and standard error of measurement [SEM]) and the association between measures were examined. Results: ICC values for individual performance-specific pain ratings were between 0.70 and 0.86; SEM values were between 0.97 and 1.33 pain points. ICC estimates for the four-item performance pain ratings and the WOMAC pain sub-scale were 0.82 and 0.57 respectively. The correlation between the sum of the pain scores for the four performance measures and the WOMAC pain sub-scale was 0.62. Conclusion: Reliability estimates for the performance-specific assessments of pain using the numeric pain rating scale were consistent with values reported for patients with a spectrum of musculoskeletal conditions. The reliability estimate for the WOMAC pain sub-scale was lower than typically reported in the literature. The level of association between the WOMAC pain sub-scale and the various performance-specific pain scales suggests that the scores can be used interchangeably when applied to groups but not for individual patients. PMID:20145758

Spent fuel behaviour during dry storage - a review

International Nuclear Information System (INIS)

Shivakumar, V.; Anantharaman, K.

1997-09-01

One of the strategies employed for management of spent fuel prior to their final disposal/reprocessing is their dry storage in casks, after they have been sufficiently cooled in spent fuel pools. In this interim storage, one of the main consideration is that the fuel should retain its integrity to ensure (a) radiological health hazard remains minimal and (b) the fuel is retrievable for down steam fuel management processes such as geological disposal or reprocessing. For dry storage of spent fuel in air, oxidation of the exposed UO 2 is the most severe of phenomena affecting the integrity of fuel. This is kept within acceptable limits for desired storage time by limiting the fuel temperature in the storage cask. The limit on the fuel temperature is met by having suitable limits on maximum burn-up of fuel, minimum cooling period in storage pool and optimum arrangement of fuel bundles in the storage cask from heat removal considerations. The oxidation of UO 2 by moist air has more deleterious effects on the integrity of fuel than that by dry air. The removal of moisture from the storage cask is therefore a very important aspect in dry storage practice. The kinetics of the oxidation phenomena at temperatures expected during dry storage in air is very slow and therefore the majority of the existing data is based on extrapolation of data obtained at higher fuel temperatures. This and the complex effects of factors like fission products in fuel, radiolysis of storage medium etc. has necessitated in having a conservative limiting criteria. The data generated by various experimental programmes and results from the on going programmes have shown that dry storage is a safe and economical practice. (author)

Estimating fault stability and sustainable fluid pressures for underground storage of CO2 in porous rock

International Nuclear Information System (INIS)

Streit, J.E.; Hillis, R.R.

2004-01-01

Geomechanical modelling of fault stability is an integral part of Australia's GEODISC research program to ensure the safe storage of carbon dioxide in subsurface reservoirs. Storage of CO 2 in deep saline formations or depleted hydrocarbon reservoirs requires estimates of sustainable fluid pressures that will not induce fracturing or create fault permeability that could lead to CO 2 escape. Analyses of fault stability require the determination of fault orientations, ambient pore fluid pressures and in situ stresses in a potential storage site. The calculation of effective stresses that act on faults and reservoir rocks lead then to estimates of fault slip tendency and fluid pressures sustainable during CO 2 storage. These parameters can be visualized on 3D images of fault surfaces or in 2D projections. Faults that are unfavourably oriented for reactivation can be identified from failure plots. In depleted oil and gas fields, modelling of fault and rock stability needs to incorporate changes of the pre-production stresses that were induced by hydrocarbon production and associated pore pressure depletion. Such induced stress changes influence the maximum sustainable formation pressures and CO 2 storage volumes. Hence, determination of in situ stresses and modelling of fault stability are essential prerequisites for the safe engineering of subsurface CO 2 injection and the modelling of storage capacity. (author)

Underground storage of nuclear waste

International Nuclear Information System (INIS)

Russell, J.E.

1977-06-01

The objective of the National Waste Terminal Storage (NWTS) Program is to provide facilities in various deep geologic formations at multiple locations in the United States which will safely dispose of commerical radioactive waste. The NWTS Program is being administered for the Energy Research and Development Administration (ERDA) by the Office of Waste Isolation (OWI), Union Carbide Corporation, Nuclear Division. OWI manages projects that will lead to the location, construction, and operation of repositories, including all surface and underground engineering and facility design projects and technical support projects. 7 refs., 5 figs

Underground storage of nuclear waste

Energy Technology Data Exchange (ETDEWEB)

Russell, J E

1977-12-01

The objective of the National Waste Terminal Storage (NWTS) Program is to provide facilities in various deep geologic formations at multiple locations in the United States which will safely dispose of commercial radioactive waste. The NWTS Program is being administered for the Energy Research and Development Administration (ERDA) by the Office of Waste Isolation (OWI), Union Carbide Corporation, Nuclear Division. OWI manages projects that will lead to the location, construction, and operation of repositories, including all surface and underground engineering and facility design projects and technical support projects.

Polyaniline as a material for hydrogen storage applications.

Science.gov (United States)

Attia, Nour F; Geckeler, Kurt E

2013-07-12

The main challenge of commercialization of the hydrogen economy is the lack of convenient and safe hydrogen storage materials, which can adsorb and release a significant amount of hydrogen at ambient conditions. Finding and designing suitable cost-effective materials are vital requirements to overcome the drawbacks of investigated materials. Because of its outstanding electronic, thermal, and chemical properties, the electrically conducting polyaniline (PANI) has a high potential in hydrogen storage applications. In this review, the progress in the use of different structures of conducting PANI, its nanocomposites as well as activated porous materials based on PANI as hydrogen storage materials is presented and discussed. The effect of the unique electronic properties based on the π-electron system in the backbone of these materials in view of the hydrogen uptake and the relevant mechanisms are highlighted. Copyright © 2013 WILEY-VCH Verlag GmbH & Co. KGaA, Weinheim.

Design of an integrated information management system for safe management of radioactive waste

International Nuclear Information System (INIS)

Son, Dong Chan; Hong, Suk Young; An, Kyoung Il

2003-05-01

An integrated data management system for the safe management of radioactive waste and spent fuel in Korea is developed to collect basic information, provide the framework for national regulation, and improve national competition and efficiency in the management of radioactive waste and spent fuel. This system can also provide public access to information such as a statistical graphs and integrated data from various waste generators to meet increased public needs and interests. Objectives can be summarized as: the five principles (independence, openness, clearance, efficiency and reliance) of safety regulation can be realized. Public understanding and reliance on the safety of spent fuel and radioactive waste management can be promoted by providing reliable information. Ensure an openness within the international nuclear community and efficiently support international agreements among contracting parties by operating safe and efficient management of spent fuel and radioactive waste (IAEA joint convention on the safety of spent fuel management and on the safety of radioactive waste management). The system can compensate for the imperfections in safe regulation of radioactive waste and spent fuel management related to waste generation, storage and disposal, and make it possible to holistic control. Re-organize the basic framework of KINS's intermediate and long term research organization and trends, regarding waste management policy is to integrate safe management and unit safe disposal

Design of an integrated information management system for safe management of radioactive waste

Energy Technology Data Exchange (ETDEWEB)

Son, Dong Chan; Hong, Suk Young; An, Kyoung Il [Daesang Information Technology Co., Ltd., Seoul (Korea, Republic of)] (and others)

2003-05-15

An integrated data management system for the safe management of radioactive waste and spent fuel in Korea is developed to collect basic information, provide the framework for national regulation, and improve national competition and efficiency in the management of radioactive waste and spent fuel. This system can also provide public access to information such as a statistical graphs and integrated data from various waste generators to meet increased public needs and interests. Objectives can be summarized as: the five principles (independence, openness, clearance, efficiency and reliance) of safety regulation can be realized. Public understanding and reliance on the safety of spent fuel and radioactive waste management can be promoted by providing reliable information. Ensure an openness within the international nuclear community and efficiently support international agreements among contracting parties by operating safe and efficient management of spent fuel and radioactive waste (IAEA joint convention on the safety of spent fuel management and on the safety of radioactive waste management). The system can compensate for the imperfections in safe regulation of radioactive waste and spent fuel management related to waste generation, storage and disposal, and make it possible to holistic control. Re-organize the basic framework of KINS's intermediate and long term research organization and trends, regarding waste management policy is to integrate safe management and unit safe disposal.

Research on crude oil storage and transportation based on optimization algorithm

Science.gov (United States)

Yuan, Xuhua

2018-04-01

At present, the optimization theory and method have been widely used in the optimization scheduling and optimal operation scheme of complex production systems. Based on C++Builder 6 program development platform, the theoretical research results are implemented by computer. The simulation and intelligent decision system of crude oil storage and transportation inventory scheduling are designed. The system includes modules of project management, data management, graphics processing, simulation of oil depot operation scheme. It can realize the optimization of the scheduling scheme of crude oil storage and transportation system. A multi-point temperature measuring system for monitoring the temperature field of floating roof oil storage tank is developed. The results show that by optimizing operating parameters such as tank operating mode and temperature, the total transportation scheduling costs of the storage and transportation system can be reduced by 9.1%. Therefore, this method can realize safe and stable operation of crude oil storage and transportation system.

Key convention on safe management of spent fuel and radioactive waste to enter into force

International Nuclear Information System (INIS)

2001-01-01

At a ceremony at IAEA Headquarters today, Ireland deposited its instrument of ratification to an important convention on the safe management of spent fuel and radioactive waste, thereby ensuring its entry into force. The Convention will be the first international instrument to address the safety of management and storage of radioactive wastes and spent fuels in countries with and without nuclear programmes

GAS STORAGE TECHNOLOGY CONSORTIUM

Energy Technology Data Exchange (ETDEWEB)

Robert W. Watson

2004-10-18

Gas storage is a critical element in the natural gas industry. Producers, transmission and distribution companies, marketers, and end users all benefit directly from the load balancing function of storage. The unbundling process has fundamentally changed the way storage is used and valued. As an unbundled service, the value of storage is being recovered at rates that reflect its value. Moreover, the marketplace has differentiated between various types of storage services, and has increasingly rewarded flexibility, safety, and reliability. The size of the natural gas market has increased and is projected to continue to increase towards 30 trillion cubic feet (TCF) over the next 10 to 15 years. Much of this increase is projected to come from electric generation, particularly peaking units. Gas storage, particularly the flexible services that are most suited to electric loads, is critical in meeting the needs of these new markets. In order to address the gas storage needs of the natural gas industry, an industry-driven consortium was created--the Gas Storage Technology Consortium (GSTC). The objective of the GSTC is to provide a means to accomplish industry-driven research and development designed to enhance operational flexibility and deliverability of the Nation's gas storage system, and provide a cost effective, safe, and reliable supply of natural gas to meet domestic demand. To accomplish this objective, the project is divided into three phases that are managed and directed by the GSTC Coordinator. The first phase, Phase 1A, was initiated on September 30, 2003, and was completed on March 31, 2004. Phase 1A of the project included the creation of the GSTC structure, development and refinement of a technical approach (work plan) for deliverability enhancement and reservoir management. This report deals with Phase 1B and encompasses the period July 1, 2004, through September 30, 2004. During this time period there were three main activities. First was the

Advanced materials for solid state hydrogen storage: “Thermal engineering issues”

International Nuclear Information System (INIS)

Srinivasa Murthy, S.; Anil Kumar, E.

2014-01-01

Hydrogen has been widely recognized as the “Energy Carrier” of the future. Efficient, reliable, economical and safe storage and delivery of hydrogen form important aspects in achieving success of the “Hydrogen Economy”. Gravimetric and volumetric storage capacities become important when one considers portable and mobile applications of hydrogen. In the case of solid state hydrogen storage, the gas is reversibly embedded (by physisorption and/or chemisorption) in a solid matrix. A wide variety of materials such as intermetallics, physisorbents, complex hydrides/alanates, metal organic frameworks, etc. have been investigated as possible storage media. This paper discusses the feasibility of lithium– and sodium–aluminum hydrides with emphasis on their thermodynamic and thermo-physical properties. Drawbacks such as poor heat transfer characteristics and poor kinetics demand special attention to the thermal design of solid state storage devices. - Highlights: • Advanced materials suitable for solid state hydrogen storage are discussed. • Issues related to thermodynamic and thermo-physical properties of hydriding materials are brought out. • Hydriding and dehydriding behavior including sorption kinetics of complex hydrides with emphasis on alanates are explained

Safety of spent fuel elements storage under water at La Hague facility

International Nuclear Information System (INIS)

Guezenec, J.Y.

1990-12-01

Awaiting for a decision about radioactive waste repository, the spent fuel elements are stored in the storage pools at the La Hague facility. The water in the pools is permanently cooled and purified to maintain the temperature, radioactivity and chemical pollution under preset limits. The first safety problem is concerned with the spent fuel transport casks. Opening of the casks is done under water in a number of facilities. The most recent approach is done by the company To, which established dry manipulation which enables to minimise the risk of possible cask failures as well as external contamination of cooling fins of the casks. Another general safety related problem is related to criticality risk caused by possible cooling failures or by external events like earthquakes. Special probability limit is set up for seismic events to be less than 10 -7 /year. Equally, risk of fuel assembly failures due to possible chocs and possibility of defects in pool isolation are taken into account [fr

Motivation and Design of the Sirocco Storage System Version 1.0.

Energy Technology Data Exchange (ETDEWEB)

Curry, Matthew Leon [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Ward, H. Lee [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Danielson, Geoffrey Charles [Hewlett-Packard Company, Palo Alto, CA (United States)

2015-07-01

Sirocco is a massively parallel, high performance storage system for the exascale era. It emphasizes client-to-client coordination, low server-side coupling, and free data movement to improve resilience and performance. Its architecture is inspired by peer-to-peer and victim- cache architectures. By leveraging these ideas, Sirocco natively supports several media types, including RAM, flash, disk, and archival storage, with automatic migration between levels. Sirocco also includes storage interfaces and support that are more advanced than typical block storage. Sirocco enables clients to efficiently use key-value storage or block-based storage with the same interface. It also provides several levels of transactional data updates within a single storage command, including full ACID-compliant updates. This transaction support extends to updating several objects within a single transaction. Further support is provided for con- currency control, enabling greater performance for workloads while providing safe concurrent modification. By pioneering these and other technologies and techniques in the storage system, Sirocco is poised to fulfill a need for a massively scalable, write-optimized storage system for exascale systems. This is version 1.0 of a document reflecting the current and planned state of Sirocco. Further versions of this document will be accessible at http://www.cs.sandia.gov/Scalable_IO/ sirocco .

Chest computed tomography scores are predictive of survival in patients with cystic fibrosis awaiting lung transplantation

DEFF Research Database (Denmark)

Loeve, Martine; Hop, Wim C. J.; de Bruijne, Marleen

2012-01-01

Rationale: Up to a third of cystic fibrosis (CF) patients awaiting lung transplantation (LTX) die while waiting. Inclusion of computed tomography (CT) scores may improve survival prediction models such as the lung allocation score (LAS). Objectives: This study investigated the association between...... CT and survival in CF patients screened for LTX. Methods: Clinical data and chest CTs of 411 CF patients screened for LTX between 1990 and 2005 were collected from 17 centers. CTs were scored with the Severe Advanced Lung Disease (SALD) 4-category scoring system, including the components "infection....../inflammation" (INF), air trapping/hypoperfusion (AT), normal/hyperperfusion (NOR) and bulla/cysts (BUL). The volume of each component was computed using semi-automated software. Survival analysis included Kaplan-Meier curves, and Cox-regression models. Measurements and main results: 366 (186 males) out of 411...

Methods to Assess Geological CO2 Storage Capacity: Status and Best Practice

Energy Technology Data Exchange (ETDEWEB)

NONE

2013-08-01

To understand the emission reduction potential of carbon capture and storage (CCS), decision makers need to understand the amount of CO2 that can be safely stored in the subsurface and the geographical distribution of storage resources. Estimates of storage resources need to be made using reliable and consistent methods. Previous estimates of CO2 storage potential for a range of countries and regions have been based on a variety of methodologies resulting in a correspondingly wide range of estimates. Consequently, there has been uncertainty about which of the methodologies were most appropriate in given settings, and whether the estimates produced by these methods were useful to policy makers trying to determine the appropriate role of CCS. In 2011, the IEA convened two workshops which brought together experts for six national surveys organisations to review CO2 storage assessment methodologies and make recommendations on how to harmonise CO2 storage estimates worldwide. This report presents the findings of these workshops and an internationally shared guideline for quantifying CO2 storage resources.

Storage Losses in Feedstuffs and How to Prevent Them | Eze | Lwati ...

African Journals Online (AJOL)

Biological deterioration of feedstuffs entails losses both in quantity and quality, including deterioration in chemical composition, contamination by mycotoxins, rancidity, loss in nutritive value and change in colour and smell. In this paper, the conditions for the safe storage of feedstuffs and also the methods for the prevention ...

High-Capacity Hydrogen-Based Green-Energy Storage Solutions For The Grid Balancing

Science.gov (United States)

D'Errico, F.; Screnci, A.

One of the current main challenges in green-power storage and smart grids is the lack of effective solutions for accommodating the unbalance between renewable energy sources, that offer intermittent electricity supply, and a variable electricity demand. Energy management systems have to be foreseen for the near future, while they still represent a major challenge. Integrating intermittent renewable energy sources, by safe and cost-effective energy storage systems based on solid state hydrogen is today achievable thanks to recently some technology breakthroughs. Optimized solid storage method made of magnesium-based hydrides guarantees a very rapid absorption and desorption kinetics. Coupled with electrolyzer technology, high-capacity storage of green-hydrogen is therefore practicable. Besides these aspects, magnesium has been emerging as environmentally friend energy storage method to sustain integration, monitoring and control of large quantity of GWh from high capacity renewable generation in the EU.

The SafeCOP ECSEL Project: Safe Cooperating Cyber-Physical Systems Using Wireless Communication

DEFF Research Database (Denmark)

Pop, Paul; Scholle, Detlef; Hansson, Hans

2016-01-01

This paper presents an overview of the ECSEL project entitled "Safe Cooperating Cyber-Physical Systems using Wireless Communication" (SafeCOP), which runs during the period 2016 -- 2019. SafeCOP targets safety-related Cooperating Cyber-Physical Systems (CO-CPS) characterised by use of wireless...... detection of abnormal behaviour, triggering if needed a safe degraded mode. SafeCOP will also develop methods and tools, which will be used to produce safety assurance evidence needed to certify cooperative functions. SafeCOP will extend current wireless technologies to ensure safe and secure cooperation...

Sustainable Solutions for Nuclear used Fuels Interim Storage

International Nuclear Information System (INIS)

Arslan, Marc; Favet, Dominique; Issard, Herve; Le Jemtel, Amaury; Drevon, Caroline

2014-01-01

AREVA has a unique experience in providing sustainable solutions for used fuel management, fitted with the needs of different customers in the world and with regulation in different countries. These solutions entail both recycling and interim storage technologies. In a first part, we will describe the various types of solutions for Interim Storage of UNF that have been implemented around the world for interim storage at reactor or centralized Pad solution in canisters dry storage, vault type storages for dry storage, dry storage of transportation casks (dual purpose) pools for wet storage, The experience for all these different families of interim storages in which AREVA is involved is extensive and will be discussed with respect to the new challenges: increase of the duration of the interim storage (long term interim storage) increase of burn up of the fuels In a second part of the presentation, special recycling features will be presented. In that case, interim storage of the used fuels is ensured in pools. This provides in the long term good conditions for the behaviour of the fuel and its retrievability. With recycling, the final waste (Universal Canister of vitrified fission products and compacted hulls and end pieces): is stable and licensed in many countries for the final disposal (France, UK, Belgium, NL, Switzerland, Germany, Japan, upcoming: Spain, Australia, Italy). Presents neither safety criticality risks nor proliferation risks (AREVA conditioned HLW and LL-ILW are free of IAEA safeguard constraints thanks to AREVA process high recovery and purification yields). It can therefore be safely stored in interim storage for more than 100 years before final disposal. Some economic considerations will also be discussed. In particular, in the case of long term interim storage of used fuels, there are growing uncertainties regarding the future needs of repackaging and transportation, which can result in future cost overruns. Meanwhile, in the recycling policy

Handling of spent nuclear fuel and final storage of vitrified high level reprocessing waste

International Nuclear Information System (INIS)

1978-01-01

The report gives a general summary of the Swedish KBS-project on management and disposal of vitrified reprocessed waste. Its final aim is to demostrate that the means of processing and managing power reactor waste in an absolutely safe way, as stipulated in the Swedish so called Conditions Act, already exist. Chapters on Storage facility for spent fuel, Intermidiate storage of reprocessed waste, Geology, Final repository, Transportation, Protection, and Siting. (L.E.)

Geological storage of radioactive waste

International Nuclear Information System (INIS)

Barthoux, A.

1983-01-01

Certain radioactive waste contains substances which present, although they disappear naturally in a progressive manner, a potential risk which can last for very long periods, of over thousands of years. To ensure a safe long-term handling, provision has been made to bury it deep in stable geological structures which will secure its confinement. Radioactive waste is treated and conditioned to make it insoluble and is then encased in matrices which are to immobilize them. The most radioactive waste is thus incorporated in a matrix of glass which will ensure the insulation of the radioactive substances during the first thousands of years. Beyond that time, the safety will be ensured by the properties of the storage site which must be selected from now on. Various hydrogeological configurations have been identified. They must undergo detailed investigations, including even the creation of an underground laboratory. This document also presents examples of underground storage installations which are due to be built [fr

The Ministry of Dilemmas [decommissioning nuclear submarines

International Nuclear Information System (INIS)

Peden, W.

1995-01-01

A consultant for Greenpeace, the anti-nuclear campaigners, looks at the United Kingdom Government's problems with decommissioning of its nuclear submarine fleet as the vessels become obsolete, and at the transport and storage of spent fuels from the submarine's propulsion reactors. It is argued that no proper plans exist to decommission the vessels safely. The Ministry of Defence sites such as Rosyth and Devonport are immune from inspection by regulatory bodies, so there is no public knowledge of any potential radioactive hazards from the stored out-of-service carcasses, floating in dock, awaiting more active strategies. The author questions the wisdom of building new nuclear submarines, when no proper program exists to decommission existing vessels and their operational waste. (U.K.)

The Next Nuclear Gamble. Transportation and storage of nuclear waste

International Nuclear Information System (INIS)

Resnikoff, M.

1985-01-01

The Next Nuclear Gamble examines risks, costs, and alternatives in handling irradiated nuclear fuel. The debate over nuclear power and the disposal of its high-level radioactive waste is now nearly four decades old. Ever larger quantities of commercial radioactive fuel continue to accumulate in reactor storage pools throughout the country and no permanent storage solution has yet been designated. As an interim solution, the government and utilities prefer that radioactive wastes be transported to temporary storage facilities and subsequently to a permanent depository. If this temporary and centralized storage system is implemented, however, the number of nuclear waste shipments on the highway will increase one hundredfold over the next fifteen years. The question directly addressed is whether nuclear transport is safe or represents the American public's domestic nuclear gamble. This Council on Economic Priorities study, directed by Marvin Resnikoff, shows on the basis of hundreds of government and industry reports, interviews and surveys, and original research, that transportation of nuclear materials as currently practiced is unsafe

Instability risk analysis and risk assessment system establishment of underground storage caverns in bedded salt rock

Science.gov (United States)

Jing, Wenjun; Zhao, Yan

2018-02-01

Stability is an important part of geotechnical engineering research. The operating experiences of underground storage caverns in salt rock all around the world show that the stability of the caverns is the key problem of safe operation. Currently, the combination of theoretical analysis and numerical simulation are the mainly adopts method of reserve stability analysis. This paper introduces the concept of risk into the stability analysis of underground geotechnical structure, and studies the instability of underground storage cavern in salt rock from the perspective of risk analysis. Firstly, the definition and classification of cavern instability risk is proposed, and the damage mechanism is analyzed from the mechanical angle. Then the main stability evaluating indicators of cavern instability risk are proposed, and an evaluation method of cavern instability risk is put forward. Finally, the established cavern instability risk assessment system is applied to the analysis and prediction of cavern instability risk after 30 years of operation in a proposed storage cavern group in the Huai’an salt mine. This research can provide a useful theoretical base for the safe operation and management of underground storage caverns in salt rock.

Safe Kids Worldwide

Science.gov (United States)

... Blog Videos Newsletter facebook twitter instagram pinterest gplus youtube Search Menu Why It Matters Who We Are What We Do Find Your Safe Kids Safe Kids Day Main menu Keeping All Kids Safe Safety Tips Get Involved 4 Star Charity Donate Text Burns and Scalds 4 tips ...

Firearm Ownership, Storage Practices, and Suicide Risk Factors in Washington State, 2013-2016.

Science.gov (United States)

Morgan, Erin Renee; Gomez, Anthony; Rowhani-Rahbar, Ali

2018-05-17

To characterize firearm ownership and storage practices in Washington State and assess their relationship with suicide risk factors. Using Washington State Behavioral Risk Factor Surveillance System data for 2013 to 2016, we conducted survey-weighted multivariable Poisson regression models to obtain prevalence ratios (PRs) and confidence intervals (CIs). Of 34 884 adult respondents, 34.3% (95% CI = 33.7%, 35.0%) reported a firearm in their household, among whom 36.6% (95% CI = 35.4%, 37.7%) stored their firearm locked and unloaded. There were no differences in mental health indicators by firearm ownership or storage practice status. Binge and chronic alcohol use were somewhat more prevalent among adults from firearm-owning households (PR = 1.2; 95% CI = 1.1, 1.3; PR = 1.2; 95% CI = 1.1, 1.4, respectively) and among those living in households not practicing safe storage (PR = 1.4; 95% CI = 1.2, 1.7; PR = 1.9; 1.5, 2.3, respectively). Variability in mental health does not explain the substantial increased suicide risk among individuals in firearm-owning households. Greater prevalence of alcohol misuse among adults in firearm-owning households not practicing safe storage highlights the need for suicide prevention interventions. (Am J Public Health. Published online ahead of print May 17, 2018: e1-e7. doi:10.2105/AJPH.2018.304403).

Chemical and ceramic methods for the safe storage of actinides using monazite. 1997 annual progress report

International Nuclear Information System (INIS)

Boatner, L.A.

1997-01-01

'Oak Ridge National Laboratory (ORNL) and the Rockwell Science Center of Thousand Oaks, California, are carrying out a joint investigation of the chemical, physical, thermal, and radiation-resistance properties of the lanthanide orthophosphates (monazites) in both ceramic and single-crystal form with the objective of developing the scientific and technical base required for the application of these materials to the storage or disposal of actinide elements, including plutonium. An additional major objective of the research effort is to investigate the technical and scientific problems associated with the formation of both phase-pure monazite ceramics and multiphase monazite-ceramic composites for waste disposal or waste storage applications. These latter investigations encompass the development of low-temperature chemical synthesis routes for the formation of monoclinic monazite phases and the study of the densification properties of lanthanide orthophosphate powders to produce stable, high-density ceramics. Research Statement This research effort addresses several basic issues associated with the characteristics of lanthanide orthophosphates that make this class of materials extremely attractive candidates for application to the storage of actinide elements in general and plutonium in particular. Additionally, these materials are potentially important refractory ceramics in their own right, and many of the scientific issues addressed in this project are applicable to the development of what will constitute a new, highly stable family of ceramics for applications in a number of energy-related areas.'

Removal Action Work Plan for 105-DR and 105-F Building Interim Safe Storage Projects and Ancillary Buildings

International Nuclear Information System (INIS)

Morton, M.R.

2000-01-01

This document contains the removal action work plan for the 105-DR and 105-F Reactor buildings and ancillary facilities. These buildings and facilities are located in the 100-D/DR and 100-F Areas of the Hanford Site, which is owned and operated by the US Department of Energy (DOE), in Benton County, Washington. The 100 Areas (including the 100-D/DR and 100-F Areas) of the Hanford Site were placed on the US Environmental Protection Agency's (EPA's) National Priorities List under the ''Comprehensive Environmental Response, Compensation, and Liability Act of 1980'' (CERCLA). The DOE has determined that hazardous substances in the 105-DR and 105-F Reactor buildings and four ancillary facilities present a potential threat to human health or the environment. The DOE has also determined that a non-time critical removal action is warranted at these facilities. Alternatives for conducting a non-time critical removal action were evaluated in the ''Engineering Evaluation/Cost Analysis for the 105-DR and 105-F Reactor Facilities and Ancillary Facilities'' (DOE-RL 1998a). The engineering evaluation/cost analysis (EE/CA) resulted in the recommendation to decontaminate and demolish the contaminated reactor buildings (except for the reactor blocks) and the ancillary facilities and to construct a safe storage enclosure (SSE) over the reactor blocks. The recommendation was approved in an action memorandum (Ecology et al. 1998) signed by the Washington State Department of Ecology (Ecology), EPA, and DOE. The DOE is the agency responsible for implementing the removal actions in the 105-D/DR and 105-F Areas. Ecology is the lead regulatory agency for facilities in the 100-D/DR Area, and EPA is the lead regulatory agency for facilities in the 100-F Area. The term ''lead regulator agency'' hereinafter, refers to these authorities. This removal action work plan supports implementation of the non-time critical removal action

Rigorous Screening Technology for Identifying Suitable CO2 Storage Sites II

Energy Technology Data Exchange (ETDEWEB)

George J. Koperna Jr.; Vello A. Kuuskraa; David E. Riestenberg; Aiysha Sultana; Tyler Van Leeuwen

2009-06-01

This report serves as the final technical report and users manual for the 'Rigorous Screening Technology for Identifying Suitable CO2 Storage Sites II SBIR project. Advanced Resources International has developed a screening tool by which users can technically screen, assess the storage capacity and quantify the costs of CO2 storage in four types of CO2 storage reservoirs. These include CO2-enhanced oil recovery reservoirs, depleted oil and gas fields (non-enhanced oil recovery candidates), deep coal seems that are amenable to CO2-enhanced methane recovery, and saline reservoirs. The screening function assessed whether the reservoir could likely serve as a safe, long-term CO2 storage reservoir. The storage capacity assessment uses rigorous reservoir simulation models to determine the timing, ultimate storage capacity, and potential for enhanced hydrocarbon recovery. Finally, the economic assessment function determines both the field-level and pipeline (transportation) costs for CO2 sequestration in a given reservoir. The screening tool has been peer reviewed at an Electrical Power Research Institute (EPRI) technical meeting in March 2009. A number of useful observations and recommendations emerged from the Workshop on the costs of CO2 transport and storage that could be readily incorporated into a commercial version of the Screening Tool in a Phase III SBIR.

An overview of hydrogen storage materials: Making a case for metal organic frameworks

CSIR Research Space (South Africa)

Langmi, Henrietta W

2013-04-01

Full Text Available hydrogen needs to be stored in a safe and compact manner by combining the gas with other materials either chemically or physically. Hydrogen storage is therefore an extremely active area of research worldwide with many different materials being examined...

Overview on the Multinational Collaborative Waste Storage and Disposal Solutions

International Nuclear Information System (INIS)

MARGEANU, C.A.

2013-01-01

The main drivers for a Safe, Secure and Global Energy future become clear and unequivocal: Security of supply for energy sources, Low-carbon electricity generation and Extended nuclear power assuring economic nuclear energy production, safe nuclear facilities and materials, safe and secure radioactive waste management and public acceptance. Responsible use of nuclear power requires that – in addition to safety, security and environmental protection associated with NPPs operation – credible solutions to be developed for dealing with the radioactive waste produced and especially for a responsible long term radioactive waste management. The paper deals with the existing multinational initiative in nuclear fuel cycle and the technical documents sustaining the multinational/regional disposal approach. Meantime, the paper far-reaching goal is to highlight on: What is offering the multinational waste storage and disposal solutions in terms of improved nuclear security ‽

Influence of Pulmonary Hypertension on Patients With Idiopathic Pulmonary Fibrosis Awaiting Lung Transplantation.

Science.gov (United States)

Hayes, Don; Black, Sylvester M; Tobias, Joseph D; Kirkby, Stephen; Mansour, Heidi M; Whitson, Bryan A

2016-01-01

The influence of varying levels of pulmonary hypertension (PH) on survival in idiopathic pulmonary fibrosis is not well defined. The United Network for Organ Sharing database was queried from 2005 to 2013 to identify first-time lung transplant candidates listed for lung transplantation who were tracked from waitlist entry date until death or censoring to determine the influence of PH on patients with advanced lung disease. Using data for right heart catheterization measurements, mild PH was defined as mean pulmonary artery pressure of 25 mm Hg or more, and severe as 35 mm Hg or more. Of 6,657 idiopathic pulmonary fibrosis patients, 6,651 were used for univariate analysis, 6,126 for Kaplan-Meier survival function, 6,013 for multivariate Cox models, and 5,186 (mild PH) and 2,014 (severe PH) for propensity score matching, respectively. Univariate Cox proportional hazards analysis found significant differences in survival for mild PH (hazard ratio [HR] 1.689, 95% confidence interval [CI]: 1.434 to 1.988, p idiopathic pulmonary fibrosis awaiting lung transplantation, so referral should be considered early in the disease course. Copyright © 2016 The Society of Thoracic Surgeons. Published by Elsevier Inc. All rights reserved.

Normal and compact spent fuel storage in light water reactor power plants

International Nuclear Information System (INIS)

Kuenel, R.R.

1978-01-01

The compact storage of light water reactor spent fuel is a safe, cheap and reliable contribution towards overcoming the momentarily existing shortage in spent fuel reprocessing. The technical concept is described and physical behaviour discussed. The introduction of compact storage racks in nuclear power plants increases the capacity from 100 to about 240 %. The increase in decay heat is not more than about 14%, the increase in activity inventory and hazard potential does not exceed 20%. In most cases the existing power plant equipment fulfils the new requirements. (author)

Multi-purpose canister storage unit and transfer cask thermal analysis

International Nuclear Information System (INIS)

Montgomery, R.A.; Niemer, K.A.; Lindner, C.N.

1997-01-01

Spent Nuclear Fuel (SNF) generated at commercial nuclear power plants throughout the US is a concern because of continued delays in obtaining a safe, permanent disposal facility. Most utilities maintain their SNF in wet storage pools; however, after decades of use, many pools are filled to capacity. Unfortunately, DOE's proposed final repository at Yucca Mountain is at least 10 years from completion, and commercial power utilities have few options for SNF storage in the interim. The Multi-Purpose Canister (MPC) system, sponsored by DOE's Office of Civilian Radioactive Waste Management, is a viable solution to the interim storage problem. The system is designed for interim dry storage, transport, and ultimate disposal of commercial SNF. The MPC system consists of four separate components: an MPC, Transfer Cask, Storage Unit, and Transport Cask. The SNF assemblies are loaded and sealed inside the helium-filled steel MPC. Once sealed, the MPC is not reopened, eliminating the need to re-handle the individual spent fuel assemblies. The MPC is transferred, using the MPC Transfer Cask, into a cylindrical, reinforced-concrete Storage Unit for on-site dry storage. The MPC may be removed from the Storage Unit at any time and transferred into the MPC Transport Cask for transport to the final repository. This paper discusses the analytical approach used to evaluate the heat transfer characteristics of an MPC containing SNF assemblies in the MPC Transfer Cask and Storage Unit

SUNRAYCE 1993: Working safely with lead-acid batteries and photovoltaic power systems

Science.gov (United States)

Dephillips, M. P.; Moskowitz, P. D.; Fthenakis, V. M.

1992-11-01

The US Department of Energy (DOE) is sponsoring SUNRAYCE 93 to advance tile technology and use of photovoltaics and electric vehicles. Participants will use cars powered by photovoltaic modules and lead-acid storage batteries. This brochure, prepared for students and faculty participating in this race, outlines the health hazards presented by these electrical systems and gives guidance on strategies for their safe usage. At the outset, it should be noted that working with photovoltaic systems and batteries requires electric vehicle drivers and technicians to have 'hands-on' contact with the car on a daily basis. It is important that no one work near a photovoltaic energy system or battery, either in a vehicle or on the bench, unless they familiarize themselves with the components in use and know and observe safe work practices including the safety precautions described in the manuals provided by the various equipment vendors and this document.

Identifying Non-Volatile Data Storage Areas: Unique Notebook Identification Information as Digital Evidence

Directory of Open Access Journals (Sweden)

Nikica Budimir

2007-03-01

Full Text Available The research reported in this paper introduces new techniques to aid in the identification of recovered notebook computers so they may be returned to the rightful owner. We identify non-volatile data storage areas as a means of facilitating the safe storing of computer identification information. A forensic proof of concept tool has been designed to test the feasibility of several storage locations identified within this work to hold the data needed to uniquely identify a computer. The tool was used to perform the creation and extraction of created information in order to allow the analysis of the non-volatile storage locations as valid storage areas capable of holding and preserving the data created within them.  While the format of the information used to identify the machine itself is important, this research only discusses the insertion, storage and ability to retain such information.

Basic architecture and design of storage simulation construction set

International Nuclear Information System (INIS)

Sehgal, A.; Volz, R.

1999-02-01

Regular practice these days has been to build a simulation prototype of an actual entity needing to be built prior to building an actual physical model. Computer simulation and modeling techniques aid greatly in this practice. In a critical system such as a fissile material storage system, various issues such as safety, security, and automation of handling processes can be assessed through virtual environments, thereby creating a safe atmosphere for research versus hands-on experimentation and possible worker exposures. By utilizing the approaches presented in this study, the concepts can be applied for rapid virtual prototyping of other systems, as this type of system is not limited to the storage of nuclear materials

"Same Room, Safe Place".

Science.gov (United States)

Keene Woods, Nikki

2017-04-01

There are many different professional stances on safe sleep and then there is the reality of caring for a newborn. There is a debate among professionals regarding safe sleep recommendations. The continum of recommendations vary from the American Academy of Pediatrics (AAP) Safe Sleep Guidelines to the bed-sharing recommendations from the Mother-Baby Behavioral Sleep Laboratory. The lack of consistent and uniform safe sleep recommendations from health professionals has been confusing for families but has more recently raised a real professional ethical dilemma. Despite years of focused safe sleep community education and interventions, sleep-related infant deaths are on the rise in many communities. This commentary calls for a united safe sleep message from all health professionals to improve health for mothers and infants most at-risk, "Same Room, Safe Place."

Hanford high level waste (HLW) tank mixer pump safe operating envelope reliability assessment

International Nuclear Information System (INIS)

Fischer, S.R.; Clark, J.

1993-01-01

The US Department of Energy and its contractor, Westinghouse Corp., are responsible for the management and safe storage of waste accumulated from processing defense reactor irradiated fuels for plutonium recovery at the Hanford Site. These wastes, which consist of liquids and precipitated solids, are stored in underground storage tanks pending final disposition. Currently, 23 waste tanks have been placed on a safety watch list because of their potential for generating, storing, and periodically releasing various quantities of hydrogen and other gases. Tank 101-SY in the Hanford SY Tank Farm has been found to release hydrogen concentrations greater than the lower flammable limit (LFL) during periodic gas release events. In the unlikely event that an ignition source is present during a hydrogen release, a hydrogen burn could occur with a potential to release nuclear waste materials. To mitigate the periodic gas releases occurring from Tank 101-SY, a large mixer pump currently is being installed in the tank to promote a sustained release of hydrogen gas to the tank dome space. An extensive safety analysis (SA) effort was undertaken and documented to ensure the safe operation of the mixer pump after it is installed in Tank 101-SY.1 The SA identified a need for detailed operating, alarm, and abort limits to ensure that analyzed safety limits were not exceeded during pump operations

Centralized interim storage facility for radioactive wastes at Wuerenlingen (ZWILAG)

International Nuclear Information System (INIS)

Lutz, H.R.; Schnetzler, U.

1994-01-01

Radioactive waste management in Switzerland is the responsibility of the waste producers; in this respect, the law requires permanent, safe management of the wastes by means of final disposal. Nagra is responsible for the research and development work associated with final disposal. Processing of the wastes into a form suitable for disposal, as well as interim storage, remain the responsibility of the waste producers. In order to supplement the existing conditioning and storage facilities at the nuclear power plants and to replace the outdated waste treatment plant at the Paul Scherrer Institute (PSI) at Wuerenlingen, the operators of the Swiss nuclear power plants are planning a joint treatment and storage facility at the PSI-East site. The organisation ''Zwischenlager Wuerenlingen AG'', which was set up at the beginning of 1990, has been entrusted with this task. (author) 4 figs

Proposed rulemaking on the storage and disposal of nuclear waste. Cross-statement of the United States Department of Energy

International Nuclear Information System (INIS)

1980-01-01

The US DOE cross-statement in the matter of proposed rulemaking in the storage and disposal of nuclear wastes is presented. It is concluded from evidence contained in the document that: (1) spent fuel can be disposed of in a manner that is safe and environmentally acceptable; (2) present plans for establishing geological repositories are an effective and reasonable means of disposal; (3) spent nuclear fuel from licensed facilities can be stored in a safe and environmentally acceptable manner on-site or off-site until disposal facilities are ready; (4) sufficient additional storage capacity for spent fuel will be established; and (5) the disposal and interim storage systems for spent nuclear fuel will be integrated into an acceptable operating system. It was recommended that the commission should promulgate a rule providing that the safety and environmental implications of spent nuclear fuel remaining on site after the anticipated expiration of the facility licenses involved need not be considered in individual facility licensing proceedings. A prompt finding of confidence in the nuclear waste disposal and storage area by the commission is also recommeded

Proposed rulemaking on the storage and disposal of nuclear waste. Cross-statement of the United States Department of Energy

Energy Technology Data Exchange (ETDEWEB)

None

1980-09-05

The US DOE cross-statement in the matter of proposed rulemaking in the storage and disposal of nuclear wastes is presented. It is concluded from evidence contained in the document that: (1) spent fuel can be disposed of in a manner that is safe and environmentally acceptable; (2) present plans for establishing geological repositories are an effective and reasonable means of disposal; (3) spent nuclear fuel from licensed facilities can be stored in a safe and environmentally acceptable manner on-site or off-site until disposal facilities are ready; (4) sufficient additional storage capacity for spent fuel will be established; and (5) the disposal and interim storage systems for spent nuclear fuel will be integrated into an acceptable operating system. It was recommended that the commission should promulgate a rule providing that the safety and environmental implications of spent nuclear fuel remaining on site after the anticipated expiration of the facility licenses involved need not be considered in individual facility licensing proceedings. A prompt finding of confidence in the nuclear waste disposal and storage area by the commission is also recommeded. (DMC)

Criticality safety studies for the storage of waste from nuclear fuel service in Intercell Storage Wells 2 and 3 of Building 3019

International Nuclear Information System (INIS)

Primm, R.T. III; Hopper, C.M.; Smolen, G.R.

1992-11-01

This report provides computational evaluation results demonstrating that mixed oxide waste can be safely stored in Intercell Storage Wells 2 and 3 of Building 3019 at the Oak Ridge National Laboratory. Existing, verified computational techniques are validated with applicable critical experiments and tolerance limits for safety analyses are derived. Multiplication factors for normal and credible abnormal configurations are calculated and found to be far subcritical when compared to derived safety limits

Current gas storage R and D programmes at Gas Research Institute

International Nuclear Information System (INIS)

Shikari, Y.A.

1990-01-01

The Gas Research Institute (GRI) is currently involved in the development of concepts aimed at an enhancement of natural gas service to the consumer. In order to maintain the attractiveness of the gas options to industrial consumers and to reinforce the ''value-in-use'' of natural gas to residential as well as commercial customers, it is essential to develop efficient, economical, and safe means of reducing the ''cost-of-service'', including that of natural gas storage in underground formations. Specifically, research and development (R and D) is needed to explore ways to better utilize existing storage fields and also to develop new storage facilities at minimum cost. GRI is currently sponsoring research projects aimed at controlling gas migration in underground gas storage reservoirs, reducing base (or cushion) gas requirements, understanding the gas-gas phase mixing behaviour via laboratory experiments and reservoir models, developing cost-effective gas separation processes using membranes, and optimizing the operation and maintenance (O and M) costs of underground gas storage operations. This paper provides an overview of the GRI's Gas Storage R and D Programme and highlights key results achieved to date for selected research projects. (author). 16 refs, 6 figs, 3 tabs

Managing the process for storage and disposal of immobilized high- and low-level tank waste at the Hanford Site

International Nuclear Information System (INIS)

Murkowski, R.J.

1998-01-01

Lockheed Martin Hanford Corporation (LMHC) is one of six subcontractors under Fluor Daniel Hanford, Inc., the Management and Integration contractor for the Project Hanford Management Contract working for the US Department of Energy. One of LMHC's responsibilities is to prepare storage and disposal facilities to receive immobilized high and low-level tank waste by June of 2002. The immobilized materials are to be produced by one or more vendors working under a privatization contract. The immobilized low-activity waste is to be permanently disposed of at the Hanford Site while the immobilized high-level waste is to be stored at the Hanford Site while awaiting shipment to the offsite repository. Figure 1 is an overview of the entire cleanup mission with the disposal portion of the mission. Figure 2 is a representation of major activities required to complete the storage and disposal mission. The challenge for the LNIHC team is to understand and plan for accepting materials that are described in the Request for Proposal. Private companies will submit bids based on the Request for Proposal and other Department of Energy requirements. LMHC, however, must maintain sufficient flexibility to accept modifications that may occur during the privatization bid/award process that is expected to be completed by May 1998. Fundamental to this planning is to minimize the risks of stand-by costs if storage and disposal facilities are not available to receive the immobilized waste. LMHC has followed a rigorous process for the identification of the functions and requirements of the storage/disposal facilities. A set of alternatives to meet these functions and requirements were identified and evaluated. The alternatives selected were (1) to modify four vaults for disposal of immobilized low-activity waste, and (2) to retrofit a portion of the Canister Storage Building for storage of immobilized high-level waste

Systems of lithium ion battery for hybrid vehicles and electric vehicles. More safe, more durable and more efficient; Lithium-Ionen Batteriesysteme fuer Hybrid- und Elektrofahrzeuge. Sicherer, langlebiger und leistungsfaehiger

Energy Technology Data Exchange (ETDEWEB)

Grotendorst, Joerg [Continental, Nuernberg (Germany). Business Unit Hybrid Electric Vehicle; Birke, Peter; Schiemann, Michael [Continental, Berlin (Germany). Battery Technology; Keller, Michael [Continental, Berlin (Germany). Battery Systems

2008-07-01

The recent progress in the development of more efficiently and simultaneously more safe batteries completely opens up new solution methods in the energy storage with hybrid vehicles and electrical vehicles. In particular, lithium ion batteries have covered leaps of development being held to be not possible till to now on the way to automotive-suited energy storages. In the recent years, Continental AG (Hannover, Federal Republic of Germany) successfully has developed lithium ion energy storages to serial production and produces these energy storages at the location Germany.

Challenges associated with extending spent fuel storage until reprocessing or disposal

International Nuclear Information System (INIS)

Carlsen, Brett; Saegusa, Toshiari; Wasinger, Karl; Grahn, Per; Wolff, Dietmar; Waters, Michael; Bevilacqua, Arturo

2014-01-01

Existing spent fuel storage (SFS) practices are the result of the past presumptions that an end point, e.g. sufficient reprocessing and/or disposal capacity, would be available within the short term (approximately 50 years). Consequently, long term storage (between approximately 50 and 100 years) considerations have not been included in planning the back end of the nuclear fuel cycle. The present reality shows that no country has yet neither licensed nor built nor operated a deep geological repository for spent fuel (SF) and/or high level waste (HLW). Further, present and projected SF generation rates - more than 10 000 metric tons of heavy metal (MTHM) a year - far exceed the current capacity for disposal - 0 MTHM - or reprocessing - 4 800 MTHM a year - and will continue to do so for the rest of this decade. As a result, the SFS periods will extend. Moreover, as the SFM end point - reprocessing and/or disposal - is not presently defined with certainty in most countries, SFS periods will extend over periods within or beyond the long term in those countries. The IAEA has started in October 2010 a programmatic activity to consider challenges associated with extending SFS durations. After four consultants meetings and two technical meetings, a need has been identified for a SFS framework based on renewable storage periods - with as many renewals as may be needed - to ensure safe and secure SFS until sufficient reprocessing and/or disposal capacity is implemented. Over the course of the technical meetings, the consultants have worked with delegates of 36 Member States and 2 International Organizations to emphasize the importance of establishing programs that can provide sufficient confidence that age-related degradation will be recognized and addressed to effectively prevent unacceptable consequences. This paper considers a number of topics from the perspective of assuring safe and effective SFS as storage periods extend including: SFS concepts, packaging of SF

Design, construction and monitoring of temporary storage facilities for removed contaminants

International Nuclear Information System (INIS)

Saegusa, Hiromitsu; Funaki, Hironori; Kurikami, Hiroshi; Sakamoto, Yoshiaki; Tokizawa, Takayuki

2013-01-01

Since the Fukushima Daiichi nuclear power plant accident caused by the Tohoku Region Pacific Coast Earthquake on March 11, 2011, decontamination work has been conducted in the surrounding environment within the Fukushima prefecture. Removed contaminants including soil, grass and trees are to be stored safely at temporary storage facilities for up to three years, after which they will be transferred to a planned interim storage facility. The decontamination pilot project was carried out in both the restricted and planned evacuation areas in order to assess decontamination methods and demonstrate measures for radiation protection of workers. Fourteen temporary storage facilities of different technical specifications were designed and constructed under various topographic conditions and land use. In order to support the design, construction and monitoring of temporary storage facilities for removed contaminants during the full-scale decontamination within the prefecture of Fukushima, technical know-how obtained during the decontamination pilot project has been identified and summarized in this paper. (author)

Dry spent fuel storage experience at overseas nuclear stations focus USA

International Nuclear Information System (INIS)

Bradley, T. L.; Kumar, S.; Marcelli, D. G.

1997-01-01

This paper provides a summary of US dry spent fuel storage experience, including application of this experience outside the United States. Background information on the US nuclear and spent fuel storage industry is provided as a basis for discussing the various types of options and systems available. An overview of technology options is presented, including systems being used and/or considered by the US government and private sector, as well as a discussion of overall system design, licensing and operation. Factors involved in selecting the best available technology option for a specific site or group of sites are presented, along with a typical timeline for project implementation. Cross-geographical use of technologies under different regulatory and technological regimes is also discussed. The paper concludes that dry storage is safe and reliable based on a successful ten year period. The information presented may be considered for use in the development of dry spent fuel storage in Korea and other countries. (author)

Technical Safety Requirements for the Waste Storage Facilities May 2014

Energy Technology Data Exchange (ETDEWEB)

Laycak, D. T. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States)

2014-04-16

This document contains the Technical Safety Requirements (TSR) for the Radioactive and Hazardous Waste Management (RHWM) WASTE STORAGE FACILITIES, which include Area 625 (A625) and the Building 693 (B693) Yard Area of the Decontamination and Waste Treatment Facility (DWTF) at LLNL. The TSRs constitute requirements for safe operation of the WASTE STORAGE FACILITIES. These TSRs are derived from the Documented Safety Analyses for the Waste Storage Facilities (DSA) (LLNL 2011). The analysis presented therein concluded that the WASTE STORAGE FACILITIES are low-chemical hazard, Hazard Category 2 non-reactor nuclear facilities. The TSRs consist primarily of inventory limits and controls to preserve the underlying assumptions in the hazard and accident analyses. Further, appropriate commitments to safety programs are presented in the administrative controls sections of the TSRs. The WASTE STORAGE FACILITIES are used by RHWM to handle and store hazardous waste, TRANSURANIC (TRU) WASTE, LOW-LEVEL WASTE (LLW), mixed waste, California combined waste, nonhazardous industrial waste, and conditionally accepted waste generated at LLNL as well as small amounts of waste from other DOE facilities, as described in the DSA. In addition, several minor treatments (e.g., size reduction and decontamination) are carried out in these facilities.

Technical Safety Requirements for the Waste Storage Facilities May 2014

International Nuclear Information System (INIS)

Laycak, D. T.

2014-01-01

This document contains the Technical Safety Requirements (TSR) for the Radioactive and Hazardous Waste Management (RHWM) WASTE STORAGE FACILITIES, which include Area 625 (A625) and the Building 693 (B693) Yard Area of the Decontamination and Waste Treatment Facility (DWTF) at LLNL. The TSRs constitute requirements for safe operation of the WASTE STORAGE FACILITIES. These TSRs are derived from the Documented Safety Analyses for the Waste Storage Facilities (DSA) (LLNL 2011). The analysis presented therein concluded that the WASTE STORAGE FACILITIES are low-chemical hazard, Hazard Category 2 non-reactor nuclear facilities. The TSRs consist primarily of inventory limits and controls to preserve the underlying assumptions in the hazard and accident analyses. Further, appropriate commitments to safety programs are presented in the administrative controls sections of the TSRs. The WASTE STORAGE FACILITIES are used by RHWM to handle and store hazardous waste, TRANSURANIC (TRU) WASTE, LOW-LEVEL WASTE (LLW), mixed waste, California combined waste, nonhazardous industrial waste, and conditionally accepted waste generated at LLNL as well as small amounts of waste from other DOE facilities, as described in the DSA. In addition, several minor treatments (e.g., size reduction and decontamination) are carried out in these facilities.

Hydrogeological problems in the ultimate storage of radioactive wastes

International Nuclear Information System (INIS)

Uerpmann, E.P.

1980-01-01

The following work shows how one can achieve the safe closure of ultimate-stored radioactive wastes by connecting a series of various barriers to the biosphere. The propagation of radionuclides by ground water is considered to be the most important long-term transport mechanism. Salt occurences in the Federal Republic of Germany are considered to be the best form suitable for end storage formations for known reasons. When not observing mining and hydrogeological knowledge, the danger of uncontrollable water flow in the end storage can arise from the water solubility of the salt rocks. Therefore the filling of salt mines and the subsequent procedures are dealt with in detail. The leading of radioactive nuclides is influenced by the properties of the ultimately stored wastes and by the quality of the remaining filling of the caves. These problems are dealt with in detail. A series of barriers to the closure of the underground caves are suggested and discussed. The most important barriers consist of the stability of the corresponding selected end storage structure. Possible arrangements of the storage cave are given which even after storage must maintain a high stability. Proposals are made on how the ultimately stored wastes can protect themselves against contact with free water or salt solutions. (orig.) [de

Safe shutdown analysis for submerged equipment inside containment

International Nuclear Information System (INIS)

Song, Dong Soo; Lee, Seung Chan; Yoon, Duk Joo; Ha, Sang Jun

2017-01-01

The purpose of the paper is to analyze internal flooding effects on the submerged safety-related components inside containment building. Safe shutdown analysis has been performed based on the criteria, assumptions and guideline provided in ANSI/ANS-56.11-1988 and ANSI/ANS-58.11-1988. Flooding can be postulated from a failure of several systems located inside the containment. Loss of coolant accident (LOCA), Feed water line break (FWLB), and other pipe breaks/cracks are assumed. The worst case flooding scenario is a large break LOCA. The maximum flood level for a large break LOCA is calculated based on the combined inventory of the reactor coolant system, the three accumulators, the boron injection tank (BIT), the chemical additive tank (CAT), and the refueling water storage tank (RWST) flooding the containment. The maximum flood level that could occur from all of the water which is available in containment is 2.3 m from the base elevation. A detailed flooding analysis for the components has been performed to demonstrate that internal flooding resulting from a postulated initiating event does not cause the loss of equipment required to achieve and maintain safe shutdown of the plant, emergency core cooling capability, or equipment whose failure could result in unacceptable offsite radiological consequences. The flood height can be calculated as h = (dh/dt) x (t-t 0 ) + h 0 , where h = time dependent flood height and subscript 0 means the initial value and height slope dh/dt. In summary, the submerged components inside containment are acceptable because they complete the mission of safety injection (SI) prior to submeregency or have no safe shutdown function including containment isolation during an accident. (author)

The medicines refrigerator and the importance of the cold chain in the safe storage of medicines.

Science.gov (United States)

Hatchett, Richard

2017-10-04

The medicines refrigerator is a common piece of equipment found in clinical areas. It is used to ensure specific medicines are safely stored within a narrow temperature range in line with manufacturers' instructions; this is usually between +2˚C and +8˚C, and ideally +5˚C. Drugs stored in the medicines refrigerator include: vaccines; insulin; chemotherapy drugs; topical preparations, such as some types of eye drops; and other treatments such as glucagon, which is used to manage severe hypoglycaemia. This article reviews the function of the medicines refrigerator and the checks required by healthcare practitioners to ensure that medicines remain safely stored and their effectiveness is maintained. It also outlines the medicines refrigeration procedure known as the 'cold chain', which includes the use of cold boxes or vaccine carriers to maintain the required temperature of medicines during transport from the manufacturer to user, or between healthcare departments. ©2012 RCN Publishing Company Ltd. All rights reserved. Not to be copied, transmitted or recorded in any way, in whole or part, without prior permission of the publishers.

DroidSafe

Science.gov (United States)

2016-12-01

Massachusetts Avenue, Build E19-750 Cambridge , MA 02139-4307 8. PERFORMING ORGANIZATION REPORT NUMBER 9. SPONSORING/MONITORING AGENCY NAME(S) AND ADDRESS...Activity objects illustrating the challenges of points-to and information flow analysis...measure how many malicious flows Droid- Safe was able to detect). As these results illustrate , DroidSafe implements an analysis of unprece- dented

Meeting the regulatory challenges of mixed waste storage and monitoring: A novel approach

International Nuclear Information System (INIS)

Wilkinson, Dennis; Shaw, Mark

1992-01-01

This paper describes an original approach to providing safe storage of Remote Handled TRU Mixed Waste that is required to meet the EPA double liner and leachate collection system standards. This system, known as the 'Environmental Vault Liner', also allows a cost effective means of complying with the EPA's inspection requirements per 40 CFR 265.170, Use and Management of Containers. This approach is modular in nature, allowing additional storage capacity to be added on a demand basis, thereby eliminating significant upfront costs associated with large storage facilities built on estimated needs over many years. It reduces the financial and technical risks associated with large storage construction projects, allows modifications to new Liners put into service based on changing regulations and technologies. The Environmental Vault Liner offers additional benefits including easy waste retrieval, a 300 year design life, continuous below ground liquid detection and monitoring, replaceable instrumentation, inert (Nitrogen) atmosphere for container storage, continuous air monitoring, and remote visual container inspections. (author)

Efficient proof of ownership for cloud storage systems

Science.gov (United States)

Zhong, Weiwei; Liu, Zhusong

2017-08-01

Cloud storage system through the deduplication technology to save disk space and bandwidth, but the use of this technology has appeared targeted security attacks: the attacker can deceive the server to obtain ownership of the file by get the hash value of original file. In order to solve the above security problems and the different security requirements of the files in the cloud storage system, an efficient and information-theoretical secure proof of ownership sceme is proposed to support the file rating. Through the K-means algorithm to implement file rating, and use random seed technology and pre-calculation method to achieve safe and efficient proof of ownership scheme. Finally, the scheme is information-theoretical secure, and achieve better performance in the most sensitive areas of client-side I/O and computation.

Development and design of an integrated information management system for safe management of radioactive waste

Energy Technology Data Exchange (ETDEWEB)

Son, Dong Chan; Hong, Suk Young; An, Kyoung Il [Daesang Information Technology Co., Ltd., Seoul (Korea, Republic of)

2004-05-15

An integrated data management system for the safe management of radioactive waste and spent fuel in Korea is developed to collect basic information, provide the framework for national regulation, and improve national competition and efficiency in the management of radioactive waste and spent fuel. This system can also provide public access to information such as a statistical graphs and integrated data from various waste generators to meet increased public needs and interests. Objectives can be summarized as; the five principles (independence, openness, clearance, efficiency and reliance) of safety regulation can be realized. Public understanding and reliance on the safety of spent fuel and radioactive waste management can be promoted by providing reliable information. Ensure an openness within the international nuclear community and efficiently support international agreements among contracting parties by operating safe and efficient management of spent fuel and radioactive waste (IAEA joint convention on the safety of spent fuel management and on the safety of radioactive waste management). The system can compensate for the imperfections In safe regulation of radioactive waste and spent fuel management related to waste generation, storage and disposal, and make it possible to holistic control. Re-organize the basic framework of KINS's intermediate and long term research organization and trends, regarding waste management policy is to integrate safe management and unit safe disposal.

Development and design of an integrated information management system for safe management of radioactive waste

International Nuclear Information System (INIS)

Son, Dong Chan; Hong, Suk Young; An, Kyoung Il

2004-05-01

An integrated data management system for the safe management of radioactive waste and spent fuel in Korea is developed to collect basic information, provide the framework for national regulation, and improve national competition and efficiency in the management of radioactive waste and spent fuel. This system can also provide public access to information such as a statistical graphs and integrated data from various waste generators to meet increased public needs and interests. Objectives can be summarized as; the five principles (independence, openness, clearance, efficiency and reliance) of safety regulation can be realized. Public understanding and reliance on the safety of spent fuel and radioactive waste management can be promoted by providing reliable information. Ensure an openness within the international nuclear community and efficiently support international agreements among contracting parties by operating safe and efficient management of spent fuel and radioactive waste (IAEA joint convention on the safety of spent fuel management and on the safety of radioactive waste management). The system can compensate for the imperfections In safe regulation of radioactive waste and spent fuel management related to waste generation, storage and disposal, and make it possible to holistic control. Re-organize the basic framework of KINS's intermediate and long term research organization and trends, regarding waste management policy is to integrate safe management and unit safe disposal

SUNRAYCE 93: Working safely with lead-acid batteries and photovoltaic power systems

Energy Technology Data Exchange (ETDEWEB)

DePhillips, M.P.; Moskowitz, P.D.; Fthenakis, V.M.

1992-11-03

The US Department of Energy (DOE) is sponsoring SUNRAYCE 93 to advance tile technology and use of photovoltaics and electric vehicles. Participants will use cars powered by photovoltaic modules and lead-acid storage batteries. This brochure, prepared for students and faculty participating in this race, outlines the health hazards presented by these electrical systems, and gives guidance on strategies for their safe usage. At the outset, it should be noted that working with photovoltaic systems and batteries requires electric vehicle drivers and technicians to have {open_quotes}hands-on{close_quotes} contact with the car on a daily basis. It is important that no one work near a photovoltaic energy system or battery, either in a vehicle or on the bench, unless they familiarize themselves with the components in use, and know and observe safe work practices including the safety precautions described in the manuals provided by the various equipment vendors and this document.

Microencapsulated Phase-Change Materials For Storage Of Heat

Science.gov (United States)

Colvin, David P.

1989-01-01

Report describes research on engineering issues related to storage and transport of heat in slurries containing phase-change materials in microscopic capsules. Specific goal of project to develop lightweight, compact, heat-management systems used safely in inhabited areas of spacecraft. Further development of obvious potential of technology expected to lead to commercialization and use in aircraft, electronic equipment, machinery, industrial processes, and other sytems in which requirements for management of heat compete with severe restrictions on weight or volume.

Traveling Safely with Medicines

Science.gov (United States)

... Medications Safely My Medicine List How to Administer Traveling Safely with Medicines Planes, trains, cars – even boats ... your trip, ask your pharmacist about how to travel safely with your medicines. Make sure that you ...

Storage and disposal of medical cannabis among patients with cancer: Assessing the risk of diversion and unintentional digestion.

Science.gov (United States)

Sznitman, Sharon R; Goldberg, Victoria; Sheinman-Yuffe, Hedva; Flechter, Ezequiel; Bar-Sela, Gil

2016-11-15

Increasingly more jurisdictions worldwide are legalizing medical cannabis. Major concerns related to such policies are that improper storage and disposal arrangements may lead to the diversion and unintentional digestion of cannabis. These concerns are particularly acute among patients with cancer because they take home medical cannabis for extended periods and have high rates of treatment termination and mortality shortly after the onset of treatment with medical cannabis. Therefore, leftover cannabis is potentially particularly prevalent, and potentially improperly stored, in households of current and deceased patients with cancer. The current study investigated the risk of medical cannabis diversion and unintentional digestion among oncology patients treated with medical cannabis and caregivers of recently deceased patients who were treated with medical cannabis. A total of 123 oncology patients treated with medical cannabis and 37 caregivers of deceased oncology patients treated with medical cannabis were interviewed regarding practices and the information received concerning the safe storage and disposal of medical cannabis, as well as experiences of theft, diversion, and unintentional digestion. High rates of suboptimal storage were reported and caregivers were found to be particularly unlikely to have received information regarding the safe storage and disposal of medical cannabis. Few incidences of theft, diversion, and unintentional digestion were reported. Oncologists and other health care providers have an important, yet unfilled, role to play with regard to educating patients and caregivers of the importance of the safe storage and disposal of medical cannabis. Interventions designed to alert patients treated with medical cannabis and their caregivers to the problem of diversion, along with strategies to limit it, have the potential to limit diversion and unintentional exposure to medical cannabis. Cancer 2016;122:3363-3370. © 2016 American Cancer

The Psychological Impact of Awaiting Breast Diagnosis: A Preliminary Picture

Science.gov (United States)

Dr. Sweeny is a social psychologist by training, but she applies the theories and methods of social psychology to address patients' experiences with their health and healthcare. Over the years, her work has examined topics ranging from bad news delivery to physician-patient communication to screening decisions. Her current research program focuses on the stressful but understudied experience of awaiting uncertain news, including news about one's health. She developed the uncertainty navigation model as a theoretical framework for understanding the thoughts, feelings, and behaviors that emerge during the wait for health-relevant news. Her work has provided broad and novel insights into this difficult experience, including how waiting experiences unfold over time, the nature of distress during waiting periods, the relative effectiveness of various strategies people can use to cope with uncertainty, and the implications of stressful waiting periods for sleep and health. Dr. Sweeny’s work has been funded by the National Science Foundation and published in top journals, including Annals of Behavioral Medicine, Health Psychology Review, Journal of Personality & Social Psychology, Psychological Bulletin, and Psychological Science. She received the inaugural Early Career Award from the Social Personality Health Network, and in 2016 she was awarded the APA Distinguished Scientific Award for an Early Career Contribution to Health Psychology. In her other life, Dr. Sweeny is a Middle Eastern dance performer and instructor, a yoga enthusiast, and an avid hiker. If you are a person with a disability and require an assistive device, services or other reasonable accommodations to participate in this activity, please contact the Cancer Prevention Fellowship Program at (240) 276-5626 at least one week in advance of the lecture date to discuss your accommodation needs.

Usefulness of an accelerated transoesophageal stress echocardiography in the preoperative evaluation of high risk severely obese subjects awaiting bariatric surgery

Directory of Open Access Journals (Sweden)

Tessier Michel

2010-07-01

Full Text Available Abstract Background Severe obesity is associated with an increased risk of coronary artery disease (CAD. Bariatric surgery is an effective procedure for long term weight management as well as reduction of comorbidities. Preoperative evaluation of cardiac operative risk may often be necessary but unfortunately standard imaging techniques are often suboptimal in these subjects. The purpose of this study was to demonstrate the feasibility, safety and utility of transesophageal dobutamine stress echocardiography (TE-DSE using an adapted accelerated dobutamine infusion protocol in severely obese subjects with comorbidities being evaluated for bariatric surgery for assessing the presence of myocardial ischemia. Methods Subjects with severe obesity [body mass index (BMI >40 kg/m2] with known or suspected CAD and being evaluated for bariatric surgery were recruited. Results Twenty subjects (9M/11F, aged 50 ± 8 years (mean ± SD, weighing 141 ± 21 kg and with a BMI of 50 ± 5 kg/m2 were enrolled in the study and underwent a TE-DSE. The accelerated dobutamine infusion protocol used was well tolerated. Eighteen (90% subjects reached their target heart rate with a mean intubation time of 13 ± 4 minutes. Mean dobutamine dose was 31.5 ± 9.9 ug/kg/min while mean atropine dose was 0.5 ± 0.3 mg. TE-DSE was well tolerated by all subjects without complications including no significant arrhythmia, hypotension or reduction in blood arterial saturation. Two subjects had abnormal TE-DSE suggestive of myocardial ischemia. All patients underwent bariatric surgery with no documented cardiovascular complications. Conclusions TE-DSE using an accelerated infusion protocol is a safe and well tolerated imaging technique for the evaluation of suspected myocardial ischemia and cardiac operative risk in severely obese patients awaiting bariatric surgery. Moreover, the absence of myocardial ischemia on TE-DSE correlates well with a low operative risk of cardiac event.

Compact Holographic Data Storage

Science.gov (United States)

Chao, T. H.; Reyes, G. F.; Zhou, H.

2001-01-01

NASA's future missions would require massive high-speed onboard data storage capability to Space Science missions. For Space Science, such as the Europa Lander mission, the onboard data storage requirements would be focused on maximizing the spacecraft's ability to survive fault conditions (i.e., no loss in stored science data when spacecraft enters the 'safe mode') and autonomously recover from them during NASA's long-life and deep space missions. This would require the development of non-volatile memory. In order to survive in the stringent environment during space exploration missions, onboard memory requirements would also include: (1) survive a high radiation environment (1 Mrad), (2) operate effectively and efficiently for a very long time (10 years), and (3) sustain at least a billion write cycles. Therefore, memory technologies requirements of NASA's Earth Science and Space Science missions are large capacity, non-volatility, high-transfer rate, high radiation resistance, high storage density, and high power efficiency. JPL, under current sponsorship from NASA Space Science and Earth Science Programs, is developing a high-density, nonvolatile and rad-hard Compact Holographic Data Storage (CHDS) system to enable large-capacity, high-speed, low power consumption, and read/write of data in a space environment. The entire read/write operation will be controlled with electrooptic mechanism without any moving parts. This CHDS will consist of laser diodes, photorefractive crystal, spatial light modulator, photodetector array, and I/O electronic interface. In operation, pages of information would be recorded and retrieved with random access and high-speed. The nonvolatile, rad-hard characteristics of the holographic memory will provide a revolutionary memory technology meeting the high radiation challenge facing the Europa Lander mission. Additional information is contained in the original extended abstract.

40 Years of Experience of NIRAS / Belgoprocess on the Interim Storage of Low, Intermediate and High Level Waste

International Nuclear Information System (INIS)

Braeckeveldt, Marnix; Ghys, Bart

2016-01-01

Conclusion: • ONDRAF/NIRAS and Belgoprocess have gained over time an extended experience on the interim storage of Low-Intermediate and High level waste. • An systematic inspection strategy was developed in order the verify the conformity of the different waste-packages and corrective measures were taken to guarantee safe storage conditions. • From 2022 , ONDRAF/NIRAS will operate a surface disposal facility for LLW

Quality of consumer-targeted internet guidance on home firearm and ammunition storage.

Science.gov (United States)

Freundlich, Katherine L; Skoczylas, Maria Shakour; Schmidt, John P; Keshavarzi, Nahid R; Mohr, Bethany Anne

2016-10-01

Four storage practices protect against unintentional and/or self-inflicted firearm injury among children and adolescents: keeping guns locked (1) and unloaded (2) and keeping ammunition locked up (3) and in a separate location from the guns (4). Our aim was to mimic common Google search strategies on firearm/ammunition storage and assess whether the resulting web pages provided recommendations consistent with those supported by the literature. We identified 87 web pages by Google search of the 10 most commonly used search terms in the USA related to firearm/ammunition storage. Two non-blinded independent reviewers analysed web page technical quality according to a 17-item checklist derived from previous studies. A single reviewer analysed readability by US grade level assigned by Flesch-Kincaid Grade Level Index. Two separate, blinded, independent reviewers analysed deidentified web page content for accuracy and completeness describing the four accepted storage practices. Reviewers resolved disagreements by consensus. The web pages described, on average, less than one of four accepted storage practices (mean 0.2 (95% CL 0.1 to 0.4)). Only two web pages (2%) identified all four practices. Two web pages (2%) made assertions inconsistent with recommendations; both implied that loaded firearms could be stored safely. Flesch-Kincaid Grade Level Index averaged 8.0 (95% CL 7.3 to 8.7). The average technical quality score was 7.1 (95% CL 6.8 to 7.4) out of an available score of 17. There was a high degree of agreement between reviewers regarding completeness (weighted κ 0.78 (95% CL 0.61 to 0.97)). The internet currently provides incomplete information about safe firearm storage. Understanding existing deficiencies may inform future strategies for improvement. Published by the BMJ Publishing Group Limited. For permission to use (where not already granted under a licence) please go to http://www.bmj.com/company/products-services/rights-and-licensing/

Tailoring Thermodynamics and Kinetics for Hydrogen Storage in Complex Hydrides towards Applications.

Science.gov (United States)

Liu, Yongfeng; Yang, Yaxiong; Gao, Mingxia; Pan, Hongge

2016-02-01

Solid-state hydrogen storage using various materials is expected to provide the ultimate solution for safe and efficient on-board storage. Complex hydrides have attracted increasing attention over the past two decades due to their high gravimetric and volumetric hydrogen densities. In this account, we review studies from our lab on tailoring the thermodynamics and kinetics for hydrogen storage in complex hydrides, including metal alanates, borohydrides and amides. By changing the material composition and structure, developing feasible preparation methods, doping high-performance catalysts, optimizing multifunctional additives, creating nanostructures and understanding the interaction mechanisms with hydrogen, the operating temperatures for hydrogen storage in metal amides, alanates and borohydrides are remarkably reduced. This temperature reduction is associated with enhanced reaction kinetics and improved reversibility. The examples discussed in this review are expected to provide new inspiration for the development of complex hydrides with high hydrogen capacity and appropriate thermodynamics and kinetics for hydrogen storage. © 2015 The Chemical Society of Japan & Wiley-VCH Verlag GmbH & Co. KGaA, Weinheim.

Evaluation of green tea extract as a safe personal hygiene against viral infections.

Science.gov (United States)

Lee, Yun Ha; Jang, Yo Han; Kim, Young-Seok; Kim, Jinku; Seong, Baik Lin

2018-01-01

Viral infections often pose tremendous public health concerns as well as economic burdens. Despite the availability of vaccines or antiviral drugs, personal hygiene is considered as effective means as the first-hand measure against viral infections. The green tea catechins, in particular, epigallocatechin-3-gallate (EGCG), are known to exert potent antiviral activity. In this study, we evaluated the green tea extract as a safe personal hygiene against viral infections. Using the influenza virus A/Puerto Rico/8/34 (H1N1) as a model, we examined the duration of the viral inactivating activity of green tea extract (GTE) under prolonged storage at various temperature conditions. Even after the storage for 56 days at different temperatures, 0.1% GTE completely inactivated 10 6 PFU of the virus (6 log 10 reduction), and 0.01% and 0.05% GTE resulted in 2 log 10 reduction of the viral titers. When supplemented with 2% citric acid, 0.1% sodium benzoate, and 0.2% ascorbic acid as anti-oxidant, the inactivating activity of GTE was temporarily compromised during earlier times of storage. However, the antiviral activity of the GTE was steadily recovered up to similar levels with those of the same concentrations of GTE without the supplements, effectively prolonging the duration of the virucidal function over extended period. Cryo-EM and DLS analyses showed a slight increase in the overall size of virus particles by GTE treatment. The results suggest that the virucidal activity of GTE is mediated by oxidative crosslinking of catechins to the viral proteins and the change of physical properties of viral membranes. The durability of antiviral effects of GTE was examined as solution type and powder types over extended periods at various temperature conditions using human influenza A/H1N1 virus. GTE with supplements demonstrated potent viral inactivating activity, resulting in greater than 4 log 10 reduction of viral titers even after storage for up to two months at a wide range of

Radiolysis and temperature effects in case of undeground storage of bitumen

International Nuclear Information System (INIS)

Smailos, E.; Diefenbacher, W.; Korthaus, E.; Comper, W.

1976-01-01

On conservative assumptions limit values were determined for the specific activity in the bitumen products, which safely avoid under the conditions of storage in a non-ventilated prototype cavity both the formation of an ignitable radiolytic gas/air mixture and intolerable heating of wastes products over the entire storage time. Depending on the filling factor of the cavity and on the age of fixed fission products, the limit values of the specific activity in the waste products allowing to avoid an ignitable gas/air mixture in the cavity range from 0.09 Ci/l to 0.78 Ci/l. The respective limit values of specific activity allowing to avoid intolerable heating of wastes (> 70 0 C) range from 0.3 Ci/l to 0.7 Ci/l, depending on the age of fission products and on the type of storage

Storage of unirradiated fuel in borated concrete at the Savannah River Plant

International Nuclear Information System (INIS)

Honkonen, D.L.

1979-06-01

At the Savannah River Plant (SRP), more than 3000 enriched uranium fuel elements can be stored in horizontal holes in borated concrete racks. This method of storage was selected. This paper describes the largest of these racks and the reactivity calculations and measurements which confirmed that SRP fuel may be safely stored in them

303-K Storage Facility closure plan. Revision 2

Energy Technology Data Exchange (ETDEWEB)

1993-12-15

Recyclable scrap uranium with zircaloy-2 and copper silicon alloy, uranium-titanium alloy, beryllium/zircaloy-2 alloy, and zircaloy-2 chips and fines were secured in concrete billets (7.5-gallon containers) in the 303-K Storage Facility, located in the 300 Area. The beryllium/zircaloy-2 alloy and zircaloy-2 chips and fines are designated as mixed waste with the characteristic of ignitability. The concretion process reduced the ignitability of the fines and chips for safe storage and shipment. This process has been discontinued and the 303-K Storage Facility is now undergoing closure as defined in the Resource Conservation and Recovery Act (RCRA) of 1976 and the Washington Administrative Code (WAC) Dangerous Waste Regulations, WAC 173-303-040. This closure plan presents a description of the 303-K Storage Facility, the history of materials and waste managed, and the procedures that will be followed to close the 303-K Storage Facility. The 303-K Storage Facility is located within the 300-FF-3 (source) and 300-FF-5 (groundwater) operable units, as designated in the Hanford Federal Facility Agreement and Consent Order (Tri-Party Agreement) (Ecology et al. 1992). Contamination in the operable units 300-FF-3 and 300-FF-5 is scheduled to be addressed through the Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) of 1980 remedial action process. Therefore, all soil remedial action at the 304 Facility will be conducted as part of the CERCLA remedial action of operable units 300-FF-3 and 300-FF-5.

Electrokinetic and Poroelastic Characterization of Porous Media : Application to CO2 storage monitoring

NARCIS (Netherlands)

Kirichek, O.J.

2018-01-01

Monitoring the properties of a CO2 storage reservoir is important for two main reasons: firstly, to verify that the injected CO2 is safely contained in the reservoir rock as planned, and secondly, to provide data which can be used to update the existing reservoir models and support eventual

Feasibility report on criticality issues associated with storage of K Basin sludge in tanks farms

Energy Technology Data Exchange (ETDEWEB)

Vail, T.S.

1997-05-29

This feasibility study provides the technical justification for conclusions about K Basin sludge storage options. The conclusions, solely based on criticality safety considerations, depend on the treatment of the sludge. The two primary conclusions are, (1) untreated sludge must be stored in a critically safe storage tank, and (2) treated sludge (dissolution, precipitation and added neutron absorbers) can be stored in a standard Double Contained Receiver Tank (DCRT) or 241-AW-105 without future restrictions on tank operations from a criticality safety perspective.

Feasibility report on criticality issues associated with storage of K Basin sludge in tanks farms

International Nuclear Information System (INIS)

Vail, T.S.

1997-01-01

This feasibility study provides the technical justification for conclusions about K Basin sludge storage options. The conclusions, solely based on criticality safety considerations, depend on the treatment of the sludge. The two primary conclusions are, (1) untreated sludge must be stored in a critically safe storage tank, and (2) treated sludge (dissolution, precipitation and added neutron absorbers) can be stored in a standard Double Contained Receiver Tank (DCRT) or 241-AW-105 without future restrictions on tank operations from a criticality safety perspective

Near-surface storage facilities for vitrified high-level wastes

International Nuclear Information System (INIS)

Kondrat'ev, A.N.; Kulichenko, V.V.; Kryukov, I.I.; Krylova, N.V.; Paramoshkin, V.I.; Strakhov, M.V.

1980-01-01

Concurrently with the development of methods for solidifying liquid radioactive wastes, reliable and safe methods for the storage and disposal of solidified wastes are being devised in the USSR and other countries. One of the main factors affecting the choice of storage conditions for solidified wastes originating from the vitrification of high-level liquid wastes from fuel reprocessing plants is the problem of removing the heat produced by radioactive decay. In order to prevent the temperature of solidified wastes from exceeding the maximum permissible level for the material concerned, it is necessary to limit either the capacity of waste containers or the specific heat release of the wastes themselves. In order that disposal of high-level wastes in geological formations should be reliable and economic, solidified wastes undergo interim storage in near-surface storage facilities with engineered cooling systems. The paper demonstrates the relative influences of specific heat release, of the maximum permissible storage temperature for vitrified wastes and of the methods chosen for cooling wastes in order for the dimensions of waste containers to be reduced to the extent required. The effect of concentrating wastes to a given level in the vitrification process on the cost of storage in different types of storage facility is also examined. Calculations were performed for the amount of vitrified wastes produced by a reprocessing plant with a capacity of five tonnes of uranium per 24 hours. Fuel elements from reactors of the water-cooled, water-moderated type are sent for reprocessing after having been held for about two years. The dimensions of the storage facility are calculated on the assumption that it will take five years to fill

Quality Assurance Program Plan for Project W-379: Spent Nuclear Fuels Canister Storage Building Projec

International Nuclear Information System (INIS)

Duncan, D.W.

1995-01-01

This document describes the Quality Assurance Program Plan (QAPP) for the Spent Nuclear Fuels (SNF) Canister Storage Building (CSB) Project. The purpose of this QAPP is to control project activities ensuring achievement of the project mission in a safe, consistent and reliable manner

Hydrogen Storage Materials for Mobile and Stationary Applications: Current State of the Art.

Science.gov (United States)

Lai, Qiwen; Paskevicius, Mark; Sheppard, Drew A; Buckley, Craig E; Thornton, Aaron W; Hill, Matthew R; Gu, Qinfen; Mao, Jianfeng; Huang, Zhenguo; Liu, Hua Kun; Guo, Zaiping; Banerjee, Amitava; Chakraborty, Sudip; Ahuja, Rajeev; Aguey-Zinsou, Kondo-Francois

2015-09-07

One of the limitations to the widespread use of hydrogen as an energy carrier is its storage in a safe and compact form. Herein, recent developments in effective high-capacity hydrogen storage materials are reviewed, with a special emphasis on light compounds, including those based on organic porous structures, boron, nitrogen, and aluminum. These elements and their related compounds hold the promise of high, reversible, and practical hydrogen storage capacity for mobile applications, including vehicles and portable power equipment, but also for the large scale and distributed storage of energy for stationary applications. Current understanding of the fundamental principles that govern the interaction of hydrogen with these light compounds is summarized, as well as basic strategies to meet practical targets of hydrogen uptake and release. The limitation of these strategies and current understanding is also discussed and new directions proposed. © 2015 WILEY-VCH Verlag GmbH & Co. KGaA, Weinheim.

Conditioning and storage of spent sealed radium sources

International Nuclear Information System (INIS)

Cholerzynski, A.; Tomczak, W.

2001-01-01

In Poland sealed radioactive sources (SRS) are extensively used in medicine and in industry. There are mainly Co-60, Cs-137, lr-192 and also historical sources contain in Ra-226. The Radioactive Waste Management Department (ZDUOP) of the Institute of Atomic Energy at Swierk is the only organization licensed for the management, storage and disposal of radioactive waste in Poland. ZDUOP deals with all radioactive waste in the country. Storage and disposal of SRS is one of the most important part of its activity. Every year ZDUOP collects about 1000 spent SRS which total activity is near 600 GBq. Spent Ra-226 sources are a special case and therefore are required suitable procedures. Due to their production according to earlier standards and their undesirable characteristics, leakage of these sources is highly possible and practically observed. For this reason conditioning of radium sources needs strict requirements and quality assurance procedure to guarantee their safe storage for an extended period of time (e.g. 40-70 years). The National Radioactive Waste Repository is superficial type repository and considered as temporary storage site for long-lived waste. A storage facility for spent SRS has been properly prepared and licensed by the regulatory body. This facility consist of several concrete chambers which floor is lined stainless steel. The existing regulatory framework for sealed radioactive sources entered into force with issue of the Atomic Law in 1986

Extended storage for radioactive wastes: relevant aspects related to the safety; Almacenamiento prolongado de residuos radiactivos: algunos aspectos de interes a considerar para su seguridad

Energy Technology Data Exchange (ETDEWEB)

Castillo, Reinaldo G.; Peralta V, José L.P.; Estevez, Gema G. F., E-mail: gesr@cphr.edu.cu, E-mail: peralta@cphr.edu.cu, E-mail: gema@cphr.edu.cu [Centro de Protección e Higiene de las Radiaciones (CPHR), Agencia de Energía Nuclear y Tecnologías de Avanzada (AENTA), La Habana (Cuba)

2013-07-01

The safe management of radioactive waste is an issue of great relevance globally linked to the issue of the peaceful use of nuclear energy. Among the steps in the management of this waste, the safe storage is one of the most important. Given the high costs and uncertainties existing among other aspects of the variants of disposal of radioactive waste, the prolonged storage of these wastes for periods exceeding 50 years is an option that different countries more and more value. One of the fundamental problems to take into account is the safety of the stores, so in this work are evaluated different safety components associated with these facilities through a safety analysis methodology. Elements such as human intrusion, the construction site, the design of the facility, among others are identified as some of the key aspects to take into account when evaluating the safety of these types of facilities. Periods of activities planned for a long-term storage of radioactive waste exceed, in general, the useful life of existing storage facilities. This work identified new challenges to overcome in order to meet the requirements for the achievement of a safe management of radioactive waste without negative impacts on the environment and man.

An overview of the dry storage of nuclear fuels with the BaCo code

International Nuclear Information System (INIS)

Marino, A.

2009-01-01

The BaCo code was applied to simulate the behaviour for a PHWR fuel under storage conditions showing a strong dependence on the original design of the fuel and the irradiation history. In particular, the results of the statistical analysis of BaCo indicate that the integrity of the fuel are determined by the manufacture tolerances and the solicitations during the NPP irradiation. The main conclusion of the present study is that the fuel temperature of the device should be carefully controlled in order to ensure safe storage conditions. (author)

Law Enforcement and Gun Retailers as Partners for Safely Storing Guns to Prevent Suicide: A Study in 8 Mountain West States.

Science.gov (United States)

Runyan, Carol W; Brooks-Russell, Ashley; Brandspigel, Sara; Betz, Marian; Tung, Gregory; Novins, Douglas; Agans, Robert

2017-11-01

To examine the extent to which law enforcement agencies (LEAs) and gun retailers are willing to offer voluntary, temporary storage as a part of an overall suicide prevention effort. We invited all LEAs and gun retailers in 8 US states to respond to questionnaires asking about their willingness to offer temporary gun storage and their recommendations to gun owners about safe storage. We collected data in 2016 from 448 LEAs and 95 retailers (response rates of 53% and 25%, respectively). Three quarters of LEAs (74.8%; 95% confidence interval [CI] = 72.1, 77.5) indicated they already provided temporary storage compared with 47.6% (95% CI = 39.2, 56.0) of retailers. LEAs were most willing to provide storage when a gun owner was concerned about the mental health of a family member. Retailers were more receptive than were LEAs to providing storage when visitors were coming or for people wanting storage while traveling. Both groups recommended locking devices within the home, but LEAs were slightly more favorable to storing guns away from the home. Law enforcement agencies and gun retailers are important resources for families concerned about suicide.

CSER 00-006 Storage of Plutonium Residue Containers in 55 Gallon Drums at the PFP

Energy Technology Data Exchange (ETDEWEB)

DOBBIN, K.D.

2000-05-24

This criticality safety evaluation report (CSER) provides the required limit set and controls for safe transit and storage of these drums in the 234-5Z Building at the PFP. A mass limit of 200 g of plutonium or fissile equivalent per drum is acceptable

Long-term storage of Greater-Than-Class C Low-Level Waste

International Nuclear Information System (INIS)

Magleby, M.T.

1990-01-01

Under Federal law, the Department of Energy (DOE) is responsible for safe disposal of Greater-Than-Class C Low-Level Waste (GTCC LLW) generated by licenses of the Nuclear Regulatory commission (NRC) or Agreement States. Such waste must be disposed of in a facility licensed by the NRC. It is unlikely that licensed disposal of GTCC LLW will be available prior to the year 2010. Pending availability of disposal capacity, DOE is assessing the need for collective, long-term storage of GTCC LLW. Potential risks to public health and safety caused by long-term storage of GTCC LLW at the place of generation will be evaluated to determine if alternative facilities are warranted. If warranted, several options will be investigated to determine the preferred alternative for long-term storage. These options include modification of an existing DOE facility, development of a new DOE facility, or development of a facility by the private sector with or without DOE support. Reasonable costs for long-term storage would be borne by the waste generators. 5 refs., 1 fig

DESIGN VERIFICATION REPORT SPENT NUCLEAR FUEL (SNF) PROJECT CANISTER STORAGE BUILDING (CSB)

International Nuclear Information System (INIS)

BAZINET, G.D.

2003-01-01

The Sub-project W379, ''Spent Nuclear Fuel Canister Storage Building (CSB),'' was established as part of the Spent Nuclear Fuel (SNF) Project. The primary mission of the CSB is to safely store spent nuclear fuel removed from the K Basins in dry storage until such time that it can be transferred to the national geological repository at Yucca Mountain Nevada. This sub-project was initiated in late 1994 by a series of studies and conceptual designs. These studies determined that the partially constructed storage building, originally built as part of the Hanford Waste Vitrification Plant (HWVP) Project, could be redesigned to safely store the spent nuclear fuel. The scope of the CSB facility initially included a receiving station, a hot conditioning system, a storage vault, and a Multi-Canister Overpack (MCO) Handling Machine (MHM). Because of evolution of the project technical strategy, the hot conditioning system was deleted from the scope and MCO welding and sampling stations were added in its place. This report outlines the methods, procedures, and outputs developed by Project W379 to verify that the provided Structures, Systems, and Components (SSCs): satisfy the design requirements and acceptance criteria; perform their intended function; ensure that failure modes and hazards have been addressed in the design; and ensure that the SSCs as installed will not adversely impact other SSCs. The original version of this document was prepared by Vista Engineering for the SNF Project. Revision 1 documented verification actions that were pending at the time the initial report was prepared. Revision 3 of this document incorporates MCO Cover Cap Assembly welding verification activities. Verification activities for the installed and operational SSCs have been completed

Fracture mechanics aspects in the safe design of ductile iron shipping and storage containers

International Nuclear Information System (INIS)

Sappok, M.; Bounin, D.

1996-01-01

Containers made of ductile cast iron provide a safe method for transport of radioactive material. Contrary to widespread opinion ductile cast iron is a very tough material and can be manufactured in heavy sections. The containers are designed to withstand the very high impact loads of accidents like free drops onto unyielding targets. The design is based on postulated undetected crack-like flaws at the highest stressed location. Design must show that applied stress intensities are smaller than fracture toughness and no crack initiation and therefore also no crack propagation can occur. The design procedure followed in this paper is given in a new guideline still being drafted by the International Atomic Energy Agency

Analysis of large concrete storage tank under seismic response

Energy Technology Data Exchange (ETDEWEB)

Le, Jingyuan; Cui, Hongcheng; He, Qiang; Ju, Jinsan [China Agricultural University, Beijing (China); You, Xiaochuan [Tsinghua University, Beijing (China)

2015-01-15

This study adopted the finite element software ABAQUS to trace the dynamic response history of large reinforced concrete storage tank during different seismic excitations. The dynamic characteristics and failure modes of the tank's structure were investigated by considering the rebar's effect. Calculation results show that the large concrete storage tank remains in safe working conditions under a seismic acceleration of 55 cm/s{sup 2}. The joint of the concrete wall and dome begins to crack when seismic acceleration reaches 250 cm/s{sup 2}. As the earthquake continues, cracks spread until the top of the wall completely fails and stops working. The maximum displacement of the concrete tank and seismic acceleration are in proportion. Peak displacement and stress of the tank always appear behind the maximum acceleration.

The transuranic waste management program at Savannah River

International Nuclear Information System (INIS)

D'Ambrosia, J.

1986-01-01

Defense transuranic waste at the Savannah River site results from the Department of Energy's national defense activities, including the operation of production reactors, fuel reprocessing plants, and research and development activities. TRU waste has been retrievably stored at the Savannah River Plant since 1974 awaiting disposal. The Waste Isolation Pilot Plant, now under construction in New Mexico, is a research and development facility for demonstrating the safe disposal of defense TRU waste, including that in storage at the Savannah River Plant. The major objective of the TRU Program at SR is to support the TRU National Program, which is dedicated to preparing waste for, and emplacing waste in, the WIPP. Thus, the SR Program also supports WIPP operations. The SR site specific goals are to phase out the indefinite storage of TRU waste, which has been the mode of waste management since 1974, and to dispose of the defense TRU waste. This paper describes the specific activities at SR which will provide for the disposal of this TRU waste

Transuranic (TRU) waste management at Savannah River - past, present and future

International Nuclear Information System (INIS)

D'Ambrosia, J.T.

1985-01-01

Defense TRU waste at Savannah River (SR) results from the Department of Energy's (DOE) national defense activities, including the operation of production reactors and fuel reprocessing plants and research and development activities. TRU waste is material declared as having negligible economic value, contaminated with alpha-emitting radionuclides of atomic number greater than 92, and half-lives longer than 20 years, in concentrations greater than 100 nCi/g. TRU waste has been retrievably stored at SR since 1974 awaiting disposal. The Waste Isolation Pilot Plant (WIPP), now under construction in New Mexico, is a research and development facility for demonstrating the safe disposal of defense TRU waste, including that in storage at SR. The major objective of the TRU program at SR is to support the TRU National Program, which is dedicated to preparing waste for, and emplacing waste in, the WIPP. Thus, the SR Program also supports WIPP operations. The SR Site specific goals are to phase out the indefinite storage of TRU waste, which has been the mode of waste management since 1974, and to dispose of SR's Defense TRU waste

Quantification of oil recovery efficiency, CO 2 storage potential, and fluid-rock interactions by CWI in heterogeneous sandstone oil reservoirs

DEFF Research Database (Denmark)

Seyyedi, Mojtaba; Sohrabi, Mehran; Sisson, Adam

2017-01-01

Significant interest exists in improving recovery from oil reservoirs while addressing concerns about increasing CO2 concentrations in the atmosphere. The combination of Enhanced Oil Recovery (EOR) and safe geologic storage of CO2 in oil reservoirs is appealing and can be achieved by carbonated (CO...... for oil recovery and CO2 storage potential on heterogeneous cores. Since not all the oil reservoirs are homogenous, understanding the potential of CWI as an integrated EOR and CO2 storage scenario in heterogeneous oil reservoirs is essential....

SAFE Newsletter

OpenAIRE

2013-01-01

The Center of Excellence SAFE – “Sustainable Architecture for Finance in Europe” – is a cooperation of the Center for Financial Studies and Goethe University Frankfurt. It is funded by the LOEWE initiative of the State of Hessen (Landes-Offensive zur Entwicklung wissenschaftlich-ökonomischer Exzellenz). SAFE brings together more than 40 professors and just as many junior researchers who are all dedicated to conducting research in support of a sustainable financial architecture. The Center has...

Code of practice for the control and safe handling of radioactive sources used for therapeutic purposes (1988)

International Nuclear Information System (INIS)

1988-01-01

This Code is intended as a guide to safe practices in the use of sealed and unsealed radioactive sources and in the management of patients being treated with them. It covers the procedures for the handling, preparation and use of radioactive sources, precautions to be taken for patients undergoing treatment, storage and transport of radioactive sources within a hospital or clinic, and routine testing of sealed sources [fr

Criticality safety of low-density storage arrays

International Nuclear Information System (INIS)

Bauer, T. H.; Nuclear Engineering Division

2005-01-01

This paper proposes a straightforward bounding method for the criticality safety analysis of fissionable materials configured into large arrays of standard containers. While criticality-safe storage limits have been well established for single containers, even under flooded conditions, it is also necessary to rule out any potential for criticality arising from neutronic interactions among multiple containers that might build up over long distances in a large array. Traditionally, the array problem has been approached by individual Monte Carlo analyses of explicit arrangements of single units and their surroundings. Deemphasizing specific configurations, the present technique takes advantage of low average density of fissionable material in typical storage arrays to separate neutron interactions that take place in the neutron's 'birth unit' from subsequent interactions in a dilute array. Numerous explicit Monte Carlo analyses show that array effects may be conservatively calculated by analyses that homogenize fissionable contents and depend only on the overall array shape, size, and reflective boundary

Criticality safety of low-density storage arrays

International Nuclear Information System (INIS)

Bauer, T.H.

1996-01-01

This paper proposes a straightforward bounding method for the criticality safety analysis of fissionable materials configured into large arrays of standard containers. While criticality-safe storage limits have been well established for single containers, even under flooded conditions, it is also necessary to rule out any potential for criticality arising from neutronic interactions among multiple containers that might build up over long distances in a large array. Traditionally, the array problem has been approached by individual Monte Carlo analyses of explicit arrangements of single units and their surroundings. Deemphasizing specific configurations, the present technique takes advantage of low average density of fissionable material in typical storage arrays to separate neutron interactions that take place in the neutron's open-quotes birth unitclose quotes from subsequent interactions in a dilute array. Numerous explicit Monte Carlo analyses show that array effects may be conservatively calculated by analyses that homogenize fissionable contents and depend only on the overall array shape, size, and reflective boundary

Cement-Based Materials for Nuclear Waste Storage

CERN Document Server

Cau-di-Coumes, Céline; Frizon, Fabien; Lorente, Sylvie

2013-01-01

As the re-emergence of nuclear power as an acceptable energy source on an international basis continues, the need for safe and reliable ways to dispose of radioactive waste becomes ever more critical. The ultimate goal for designing a predisposal waste-management system depends on producing waste containers suitable for storage, transportation and permanent disposal. Cement-Based Materials for Nuclear-Waste Storage provides a roadmap for the use of cementation as an applied technique for the treatment of low- and intermediate-level radioactive wastes.Coverage includes, but is not limited to, a comparison of cementation with other solidification techniques, advantages of calcium-silicate cements over other materials and a discussion of the long-term suitability and safety of waste packages as well as cement barriers. This book also: Discusses the formulation and production of cement waste forms for storing radioactive material Assesses the potential of emerging binders to improve the conditioning of problemati...

Application of burnup credit for PWR spent fuel storage pool

International Nuclear Information System (INIS)

Shin, Hee Sung; Ro, Seung-Gy; Bae, Kang Mok; Kim, Ik Soo; Shin, Young Joon

1999-01-01

A study on the application of burnup credit for a PWR spent fuel storage pool has been investigated using a computer code system such as CSAS6 module of SCALE 4.3 in association with 44-group SCALE cross-section library. The calculation bias of the code system at a 95% probability with a 95% confidence level seems to be 0.00951 by benchmarking the system for forty six experimental data. With the aid of this computer code system, criticality analysis has been performed for the PWR spent fuel storage pool. Uncertainties due to postulated abnormal and accidental conditions, and manufacturing tolerance such as stainless steel thickness of storage rack, fuel enrichment, fuel density and box size have statistically been combined and resulted in 0.00674. Also, isotopic correction factor which was based on the calculated and measured concentration of 43 isotopes for both selected actinides and fission products important in burnup credit application has been taken into account in the criticality analysis. It is revealed that the minimum burnup with the corrected isotopic concentrations as required for the safe storage is 5,730 MWd/tU in enriched fuel of 5.0 wt%. (author)

Processing routes evaluation of severely deformed Mg-Fe alloys for hydrogen storage applications

International Nuclear Information System (INIS)

Antiqueira, F.J.; Leiva, D.R.; Ishikawa, T.T.; Jorge Junior, A.M.; Botta, W.J.

2016-01-01

MgH 2 is considered an interesting material for safe hydrogen storage in the solid state, due to its high gravimetric nominal capacity of 7,6%, and the relative low cost of magnesium. In this study, we attempted to improve the performance of the MgH 2 in the hydrogen storage. Different processing routes for Mg and Mg-Fe by severe plastic deformation were evaluated. The prepared materials were characterized by X-ray diffraction (XRD), scanning (SEM) and transmission electron microscopy (TEM). The hydrogen storage properties were evaluated by differential scanning calorimetry and the Sievert's method. The results indicate superior properties to materials catalyzed with iron, as well as a high dependence of hydrogen absorption / desorption kinetic in accordance with the microstructures obtained through the various processing routes. (author)

STORAGE, NUTRITIONAL AND SENSORY PROPERTIES OF HIGH-FAT FISH AND RICE FLOUR COEXTRUDATES

Energy Technology Data Exchange (ETDEWEB)

Jaya Shankar Tumuluru; Shahab Sokhansanj; Sukumar Bandyopadhyay; Amarender Singh Bawa

2013-10-01

The present research is on understanding the storage, nutritional and sensory characteristics of high-fat fish (khoira) and rice flour coextrudates at storage temperature of 30C. The extruder processing conditions used are barrel temperature (200C), screw speed (109 rpm), fish content of feed (44%) and feed moisture content (39%). Sorption isotherm data indicated that the safe aw level was about 0.4–0.7. Guggenheim -Anderson -de Boer model described the sorption data adequately with an r2 value of 0.99. During the initial 15 days of storage, there was a loss of vitamin A and total tocopherols by 64.4 and 20.6%, and an increase in peroxides and free fatty acid content by about 116 mg/kg and 21.7%. The nonlinear mathematical model developed has adequately described the changes in nutritional and storage properties. Sensory attributes indicated that the product fried for 15 s was most acceptable.

Issues on safe radioactive waste management at ChNPP site in International Shelter Implementation Plan

International Nuclear Information System (INIS)

Bykov, V.; Kilochytska, T.; Gromyko, S.; Kadkin, Y.; Kondratiev, S.; Pavlenko, A.; Bogorinski, P.

2003-01-01

The International Shelter Implementation Plan (SIP) [1], is aimed to convert the ChNPP unit 4, destroyed by a beyond-design accident in 1986, into an environmentally safe facility by means of large-scale projects such as stabilization of the existing Sarcophagus (Shelter), construction of a New Safe Confinement (NSC), and installation of engineering and monitoring systems. This report presents some important safety issues concerning radioactive waste (RAW) management at the Shelter. One of the main problems of RAW management is to dispose of large volumes of RAW generated during ground preparation work. It is necessary that RAW be sorted carefully to separate low-active radioactive waste (LLW), which will be the majority, from high-level waste. Considering the fact that the Shelter is in the exclusion zone, the interim storage of LLW in this zone is possible, but a set of safety measures is required, e.g. prevention of dust generation or spreading of radioactivity with water. Another problem is high level RAW management. Highly radioactive fragments of the core, including fuel were ejected during the accident and are now buried under the man-made layer around the Shelter. Unanticipated disclosure of such fragments may happen during any ground preparation work as well as during clearing of premises inside the damaged buildings. Therefore, permanent radiation monitoring is required to prevent any intolerable exposure of workers. Unanticipated disclosure of high-active radioactive waste (HLW) could lead to considerable delay of any work. Since it is particularly difficult to remove HLW from those locations, which can not be easily accessed with removal equipment, such waste needs to be confined and properly shielded at in situ. Due to absence of a permanent HLW storage, an interim storage needs to be provided for in the territory of the Sarcophagus. (author)

Recent findings on the oxidation of UO2 fuel under nominally dry storage conditions

International Nuclear Information System (INIS)

Taylor, P.; McEachern, R.J.; Sunder, S.; Wasywich, K.M.; Miller, N.H.; Wood, D.D.

1995-01-01

This paper is an overview of fuel-storage demonstration experiments, supporting research on UO 2 oxidation, and associated model development, in progress at AECL's Whiteshell Laboratories. The work is being performed to determine the time/temperature limits for safe storage of irradiated CANDU fuel in dry air. The most significant recent experimental finding has been the detection of small quantities of U 3 O 8 , formed over periods of one to several years in a variety of experiments at 150-170 deg C. Another important trading is the slight suppression of U 3 O 8 formation in SIMFUEL and other doped U0 2 formulations. The development of a nucleation-and-growth model for U 3 O 8 formation is discussed, along with available activation energy data. These provide a basis for predicting U 3 O 8 formation rates under dry-storage conditions, and hence optimizing fuel storage strategies. (author)

Methodology to determine the technical performance and value proposition for grid-scale energy storage systems :

Energy Technology Data Exchange (ETDEWEB)

Byrne, Raymond Harry; Loose, Verne William; Donnelly, Matthew K.; Trudnowski, Daniel J.

2012-12-01

As the amount of renewable generation increases, the inherent variability of wind and photovoltaic systems must be addressed in order to ensure the continued safe and reliable operation of the nation's electricity grid. Grid-scale energy storage systems are uniquely suited to address the variability of renewable generation and to provide other valuable grid services. The goal of this report is to quantify the technical performance required to provide di erent grid bene ts and to specify the proper techniques for estimating the value of grid-scale energy storage systems.

Summary of Carbon Storage Incentives and Potential Legislation: East Sub-Basin Project Task 3.1 Business and Financial Case Study

Energy Technology Data Exchange (ETDEWEB)

Trabucchi, Chiara [Industrial Economics, Incorporated

2018-05-16

The CarbonSAFE Illinois – East Sub-Basin project is conducting a pre-feasibility assessment for commercial-scale CO2 geological storage complexes. The project aims to identify sites capable of storing more than 50 million tons of industrially-sourced CO2. To support the business development assessment of the economic viability of potential sites in the East Sub-Basin and explore conditions under which a carbon capture and storage (CCS) project therein might be revenue positive, this document provides a summary of carbon storage incentives and legislation of potential relevance to the project.

Storage of Maize in Purdue Improved Crop Storage (PICS) Bags.

Science.gov (United States)

Williams, Scott B; Murdock, Larry L; Baributsa, Dieudonne

2017-01-01

Interest in using hermetic technologies as a pest management solution for stored grain has risen in recent years. One hermetic approach, Purdue Improved Crop Storage (PICS) bags, has proven successful in controlling the postharvest pests of cowpea. This success encouraged farmers to use of PICS bags for storing other crops including maize. To assess whether maize can be safely stored in PICS bags without loss of quality, we carried out laboratory studies of maize grain infested with Sitophilus zeamais (Motshulsky) and stored in PICS triple bags or in woven polypropylene bags. Over an eight month observation period, temperatures in the bags correlated with ambient temperature for all treatments. Relative humidity inside PICS bags remained constant over this period despite the large changes that occurred in the surrounding environment. Relative humidity in the woven bags followed ambient humidity closely. PICS bags containing S. zeamais-infested grain saw a significant decline in oxygen compared to the other treatments. Grain moisture content declined in woven bags, but remained high in PICS bags. Seed germination was not significantly affected over the first six months in all treatments, but declined after eight months of storage when infested grain was held in woven bags. Relative damage was low across treatments and not significantly different between treatments. Overall, maize showed no signs of deterioration in PICS bags versus the woven bags and PICS bags were superior to woven bags in terms of specific metrics of grain quality.

The U. S. DOE Carbon Storage Program: Status and Future Directions

Science.gov (United States)

Damiani, D.

2016-12-01

The U.S. Department of Energy (DOE) is taking steps to reduce carbon dioxide (CO2) emissions through clean energy innovation, including carbon capture and storage (CCS) research. The Office of Fossil Energy Carbon Storage Program is focused on ensuring the safe and permanent storage and/or utilization of CO2 captured from stationary sources. The Program is developing and advancing geologic storage technologies both onshore and offshore that will significantly improve the effectiveness of CCS, reduce the cost of implementation, and be ready for widespread commercial deployment in the 2025-2035 timeframe. The technology development and field testing conducted through this Program will be used to benefit the existing and future fleet of fossil fuel power generating and industrial facilities by creating tools to increase our understanding of geologic reservoirs appropriate for CO2 storage and the behavior of CO2 in the subsurface. The Program is evaluating the potential for storage in depleted oil and gas reservoirs, saline formations, unmineable coal, organic-rich shale formations, and basalt formations. Since 1997, DOE's Carbon Storage Program has significantly advanced the CCS knowledge base through a diverse portfolio of applied research projects. The Core Storage R&D research component focuses on analytic studies, laboratory, and pilot- scale research to develop technologies that can improve wellbore integrity, increase reservoir storage efficiency, improve management of reservoir pressure, ensure storage permanence, quantitatively assess risks, and identify and mitigate potential release of CO2 in all types of storage formations. The Storage Field Management component focuses on scale-up of CCS and involves field validation of technology options, including large-volume injection field projects at pre-commercial scale to confirm system performance and economics. Future research involves commercial-scale characterization for regionally significant storage locations

Database basic design for safe management radioactive waste

International Nuclear Information System (INIS)

Son, D. C.; Ahn, K. I.; Jung, D. J.; Cho, Y. B.

2003-01-01

As the amount of radioactive waste and related information to be managed are increasing, some organizations are trying or planning to computerize the management on radioactive waste. When we consider that information on safe management of radioactive waste should be used in association with national radioactive waste management project, standardization of data form and its protocol is required, Korea Institute of Nuclear Safety(KINS) will establish and operate nationwide integrated database in order to effectively manage a large amount of information on national radioactive waste. This database allows not only to trace and manage the trend of radioactive waste occurrence and in storage but also to produce reliable analysis results for the quantity accumulated. Consequently, we can provide necessary information for national radioactive waste management policy and related industry's planing. This study explains the database design which is the essential element for information management

Safe Grid

Science.gov (United States)

Chow, Edward T.; Stewart, Helen; Korsmeyer, David (Technical Monitor)

2003-01-01

The biggest users of GRID technologies came from the science and technology communities. These consist of government, industry and academia (national and international). The NASA GRID is moving into a higher technology readiness level (TRL) today; and as a joint effort among these leaders within government, academia, and industry, the NASA GRID plans to extend availability to enable scientists and engineers across these geographical boundaries collaborate to solve important problems facing the world in the 21 st century. In order to enable NASA programs and missions to use IPG resources for program and mission design, the IPG capabilities needs to be accessible from inside the NASA center networks. However, because different NASA centers maintain different security domains, the GRID penetration across different firewalls is a concern for center security people. This is the reason why some IPG resources are been separated from the NASA center network. Also, because of the center network security and ITAR concerns, the NASA IPG resource owner may not have full control over who can access remotely from outside the NASA center. In order to obtain organizational approval for secured remote access, the IPG infrastructure needs to be adapted to work with the NASA business process. Improvements need to be made before the IPG can be used for NASA program and mission development. The Secured Advanced Federated Environment (SAFE) technology is designed to provide federated security across NASA center and NASA partner's security domains. Instead of one giant center firewall which can be difficult to modify for different GRID applications, the SAFE "micro security domain" provide large number of professionally managed "micro firewalls" that can allow NASA centers to accept remote IPG access without the worry of damaging other center resources. The SAFE policy-driven capability-based federated security mechanism can enable joint organizational and resource owner approved remote

Fuel handling and storage systems in nuclear power plants

International Nuclear Information System (INIS)

1984-01-01

The scope of this Guide includes the design of handling and storage facilities for fuel assemblies from the receipt of fuel into the nuclear power plant until the fuel departs from that plant. The unirradiated fuel considered in this Guide is assumed not to exhibit any significant level of radiation so that it can be handled without shielding or cooling. This Guide also gives limited consideration to the handling and storage of certain core components. While the general design and safety principles are discussed in Section 2 of this Guide, more specific design requirements for the handling and storage of fuel are given in detailed sections which follow the general design and safety principles. Further useful information is to be found in the IAEA Technical Reports Series No. 189 ''Storage, Handling and Movement of Fuel and Related Components at Nuclear Power Plants'' and No. 198 ''Guide to the Safe Handling of Radioactive Wastes at Nuclear Power Plants''. However, the scope of the Guide does not include consideration of the following: (1) The various reactor physics questions associated with fuel and absorber loading and unloading into the core; (2) The design aspects of preparation of the reactor for fuel loading (such as the removal of the pressure vessel head for a light water reactor) and restoration after loading; (3) The design of shipping casks; (4) Fuel storage of a long-term nature exceeding the design lifetime of the nuclear power plant; (5) Unirradiated fuel containing plutonium

Recovery of Pu from PVC vials and bottles used for sample storage

International Nuclear Information System (INIS)

Purohit, Paru; Bhide, M.K.; Kulkarni, M.J.; Kumar, Mithlesh; Adya, V.C.; Hon, N.S.; Kadam, R.M.; Nathaniel, Newton; Natarajan, V.

2011-01-01

Plutonium in the form of oxide is stored in plastic vials and bottles during its analysis for trace metal as say. Due to radiation damage and moisture, small amount of oxide samples were found to be adhering to surface of vials/ bottles. This required methods for safe disposal. Methods involving wet chemical and dry cleaning procedures were evaluated for effective removal of sticking α active plutonium oxide powder from these vials for their safe disposal. Dry cleaning method for removal of plutonium activity was found to be effective method for disposal of storage vial, while wet chemical method was found to be more suitable for removal of plutonium from damaged PVC bottles. (author)

Current status of the first interim spent fuel storage facility in Japan

International Nuclear Information System (INIS)

Shinbo, Hitoshi; Kondo, Mitsuru

2008-01-01

In Japan, storage of spent fuels outside nuclear power plants was enabled as a result of partial amendments to the Nuclear Reactor Regulation Law in June 2000. Five months later, Mutsu City in Aomori Prefecture asked the Tokyo Electric Power Company (TEPCO) to conduct technical surveys on siting of the interim spent fuel storage facility (we call it 'Recyclable-Fuel Storage Center'). In April 2003, TEPCO submitted the report on siting feasibility examination, concluded that no improper engineering data for siting, construction of the facility will be possible from engineering viewpoint. Siting Activities for publicity and public acceptance have been continued since then. After these activities, Aomori Prefecture and Mutsu City approved siting of the Recyclable Fuel Storage Center in October 2005. Aomori Prefecture, Mutsu City, TEPCO and Japan Atomic Power Company (JAPC) signed an agreement on the interim spent fuel storage Facility. A month later, TEPCO and JAPC established Recyclable-Fuel Storage Company (RFS) in Mutsu City through joint capital investment, specialized in the first interim spent fuel storage Facility in Japan. In May 2007, we made an application for establishment permit, following safety review by regulatory authorities. In March 2008, we started the preparatory construction. RFS will safely store of spent fuels of TEPCO and JAPC until they will be reprocessed. Final storage capacity will be 5,000 ton-U. First we will construct the storage building of 3,000 ton-U to be followed by second building. We aim to start operation by 2010. (author)

Gas Storage Technology Consortium

Energy Technology Data Exchange (ETDEWEB)

Joel Morrison; Elizabeth Wood; Barbara Robuck

2010-09-30

The EMS Energy Institute at The Pennsylvania State University (Penn State) has managed the Gas Storage Technology Consortium (GSTC) since its inception in 2003. The GSTC infrastructure provided a means to accomplish industry-driven research and development designed to enhance the operational flexibility and deliverability of the nation's gas storage system, and provide a cost-effective, safe, and reliable supply of natural gas to meet domestic demand. The GSTC received base funding from the U.S. Department of Energy's (DOE) National Energy Technology Laboratory (NETL) Oil & Natural Gas Supply Program. The GSTC base funds were highly leveraged with industry funding for individual projects. Since its inception, the GSTC has engaged 67 members. The GSTC membership base was diverse, coming from 19 states, the District of Columbia, and Canada. The membership was comprised of natural gas storage field operators, service companies, industry consultants, industry trade organizations, and academia. The GSTC organized and hosted a total of 18 meetings since 2003. Of these, 8 meetings were held to review, discuss, and select proposals submitted for funding consideration. The GSTC reviewed a total of 75 proposals and committed co-funding to support 31 industry-driven projects. The GSTC committed co-funding to 41.3% of the proposals that it received and reviewed. The 31 projects had a total project value of $6,203,071 of which the GSTC committed $3,205,978 in co-funding. The committed GSTC project funding represented an average program cost share of 51.7%. Project applicants provided an average program cost share of 48.3%. In addition to the GSTC co-funding, the consortium provided the domestic natural gas storage industry with a technology transfer and outreach infrastructure. The technology transfer and outreach were conducted by having project mentoring teams and a GSTC website, and by working closely with the Pipeline Research Council International (PRCI) to

Design Verification Report Spent Nuclear Fuel (SNF) Project Canister Storage Building (CSB)

International Nuclear Information System (INIS)

PICKETT, W.W.

2000-01-01

The Sub-project W379, ''Spent Nuclear Fuel Canister Storage Building (CSB),'' was established as part of the Spent Nuclear Fuel (SNF) Project. The primary mission of the CSB is to safely store spent nuclear fuel removed from the K Basins in dry storage until such time that it can be transferred to the national geological repository at Yucca Mountain Nevada. This sub-project was initiated in late 1994 by a series of studies and conceptual designs. These studies determined that the partially constructed storage building, originally built as part of the Hanford Waste Vitrification Plant (HWVP) Project, could be redesigned to safely store the spent nuclear fuel. The scope of the CSB facility initially included a receiving station, a hot conditioning system, a storage vault, and a Multi-Canister Overpack (MCO) Handling Machine (MHM). Because of evolution of the project technical strategy, the hot conditioning system was deleted from the scope and MCO welding and sampling stations were added in its place. This report outlines the methods, procedures, and outputs developed by Project W379 to verify that the provided Structures, Systems, and Components (SSCs): satisfy the design requirements and acceptance criteria; perform their intended function; ensure that failure modes and hazards have been addressed in the design; and ensure that the SSCs as installed will not adversely impact other SSCs. Because this sub-project is still in the construction/start-up phase, all verification activities have not yet been performed (e.g., canister cover cap and welding fixture system verification, MCO Internal Gas Sampling equipment verification, and As-built verification.). The verification activities identified in this report that still are to be performed will be added to the start-up punchlist and tracked to closure

DESIGN VERIFICATION REPORT SPENT NUCLEAR FUEL (SNF) PROJECT CANISTER STORAGE BUILDING (CSB)

Energy Technology Data Exchange (ETDEWEB)

BAZINET, G.D.

2003-02-12

The Sub-project W379, ''Spent Nuclear Fuel Canister Storage Building (CSB),'' was established as part of the Spent Nuclear Fuel (SNF) Project. The primary mission of the CSB is to safely store spent nuclear fuel removed from the K Basins in dry storage until such time that it can be transferred to the national geological repository at Yucca Mountain Nevada. This sub-project was initiated in late 1994 by a series of studies and conceptual designs. These studies determined that the partially constructed storage building, originally built as part of the Hanford Waste Vitrification Plant (HWVP) Project, could be redesigned to safely store the spent nuclear fuel. The scope of the CSB facility initially included a receiving station, a hot conditioning system, a storage vault, and a Multi-Canister Overpack (MCO) Handling Machine (MHM). Because of evolution of the project technical strategy, the hot conditioning system was deleted from the scope and MCO welding and sampling stations were added in its place. This report outlines the methods, procedures, and outputs developed by Project W379 to verify that the provided Structures, Systems, and Components (SSCs): satisfy the design requirements and acceptance criteria; perform their intended function; ensure that failure modes and hazards have been addressed in the design; and ensure that the SSCs as installed will not adversely impact other SSCs. The original version of this document was prepared by Vista Engineering for the SNF Project. Revision 1 documented verification actions that were pending at the time the initial report was prepared. Revision 3 of this document incorporates MCO Cover Cap Assembly welding verification activities. Verification activities for the installed and operational SSCs have been completed.

Design Verification Report Spent Nuclear Fuel (SNF) Project Canister Storage Building (CSB)

Energy Technology Data Exchange (ETDEWEB)

PICKETT, W.W.

2000-09-22

The Sub-project W379, ''Spent Nuclear Fuel Canister Storage Building (CSB),'' was established as part of the Spent Nuclear Fuel (SNF) Project. The primary mission of the CSB is to safely store spent nuclear fuel removed from the K Basins in dry storage until such time that it can be transferred to the national geological repository at Yucca Mountain Nevada. This sub-project was initiated in late 1994 by a series of studies and conceptual designs. These studies determined that the partially constructed storage building, originally built as part of the Hanford Waste Vitrification Plant (HWVP) Project, could be redesigned to safely store the spent nuclear fuel. The scope of the CSB facility initially included a receiving station, a hot conditioning system, a storage vault, and a Multi-Canister Overpack (MCO) Handling Machine (MHM). Because of evolution of the project technical strategy, the hot conditioning system was deleted from the scope and MCO welding and sampling stations were added in its place. This report outlines the methods, procedures, and outputs developed by Project W379 to verify that the provided Structures, Systems, and Components (SSCs): satisfy the design requirements and acceptance criteria; perform their intended function; ensure that failure modes and hazards have been addressed in the design; and ensure that the SSCs as installed will not adversely impact other SSCs. Because this sub-project is still in the construction/start-up phase, all verification activities have not yet been performed (e.g., canister cover cap and welding fixture system verification, MCO Internal Gas Sampling equipment verification, and As-built verification.). The verification activities identified in this report that still are to be performed will be added to the start-up punchlist and tracked to closure.

Concordance and interchangeability of biometric measurements of ocular axial length in patients awaiting cataract surgery.

Science.gov (United States)

Martín-Serrano, María José; Roman-Ortiz, Carmen; Villa-Sáez, M Luz; Labrador-Castellanos, M Purificación; Blanco-Carrasco, Rosario; Lozano-Ballesteros, Felicidad; Pedraza-Martín, Carmen; José-Herrero, M Teresa San; López-Ropero, Ana M; Tenías Burillo, José María

2014-01-01

To estimate in patients awaiting cataract surgery the concordance and interchangeability of axial eye length measurements performed with the aid of various biometric methods (optical or ultrasonic) by different operators (nurses) at different times during the period prior to surgery. We selected 182 consecutive eyes from 91 patients.Ocular axial length was measured with the aid of 2 methods (IOLMaster® and Ocuscan®) by 9 randomly allocated technicians at 2 different times during the waiting period. The concordance between measurements was evaluated by means of the intraclass correlation coefficient (ICC); the interchangeability of the results was assessed with Bland Altman plots and Passing and Bablok regression. The measurements were consistent between biometric methods (ICC 0.975, 95% confidence interval [CI] 0.968 to 0.980) and measurement dates (ICC 0.996, 95% CI 0.995 to 0.997). Interobserver agreement was more heterogeneous (ICC range 0.844 to 0.998). No systematic errors were observed among the various biometric methods and measurement dates. Because measurement of axial length in phakic patients may be technician-dependent, the technician's experience should be noted in the protocols of ophthalmology services.

Is it feasible to conduct a randomised controlled trial of pretransplant exercise (prehabilitation) for patients with multiple myeloma awaiting autologous haematopoietic stem cell transplantation? Protocol for the PREeMPT study.

Science.gov (United States)

Keen, Carol; Skilbeck, Julie; Ross, Helen; Smith, Lauren; Collins, Karen; Dixey, Joanne; Walters, Stephen; Greenfield, Diana M; Snowden, John A; Mawson, Susan

2018-03-09

While myeloma is an incurable malignancy, developments in disease management have led to increased life expectancy in recent years. Treatment typically involves stem-cell transplantation. Increased survival rates equate to more patients living with the burden of both the disease and its treatment for increasing number of years, rendering myeloma a long-term condition.Evidence exists to demonstrate the benefits of exercise for patients recovering from stem-cell transplantation, and prehabilitation-exercise before treatment-has been shown to be effective in other disease areas. To date there has been no research into prehabilitation in patients with myeloma awaiting transplantation treatment.Our objective is to determine whether it is feasible to conduct a randomised controlled trial into pretransplant exercise for patients with multiple myeloma who are awaiting autologous stem-cell transplantation. This mixed methods study identifies patients with diagnosis of multiple myeloma who have been assigned to the autologous transplantation list and invites them to participate in six weekly sessions of individualised, supervised exercise while awaiting transplantation.Quantitative data to determine feasibility targets include rates of recruitment, adherence and adverse events, and outcome measures including 6 min walking distance test and quality of life.Qualitative interviews are undertaken with a purposive sample of patients to capture their experiences of the study and the intervention. Ethics committee approval has been obtained. Dissemination will be through open-access publications and presentations and will seek to reach multiprofessional bases as well as patients and carer groups, addressing the widespread interest in this area of research. NCT03135925; Pre-results. © Article author(s) (or their employer(s) unless otherwise stated in the text of the article) 2018. All rights reserved. No commercial use is permitted unless otherwise expressly granted.

Intra-articular enzyme replacement therapy with rhIDUA is safe, well-tolerated, and reduces articular GAG storage in the canine model of mucopolysaccharidosis type I.

Science.gov (United States)

Wang, Raymond Y; Aminian, Afshin; McEntee, Michael F; Kan, Shih-Hsin; Simonaro, Calogera M; Lamanna, William C; Lawrence, Roger; Ellinwood, N Matthew; Guerra, Catalina; Le, Steven Q; Dickson, Patricia I; Esko, Jeffrey D

2014-08-01

abolished in rhIDUA-treated joints only. Intra-articular rhIDUA is well-tolerated and safe in the canine MPS I animal model. Qualitative and quantitative assessments indicate that IA-rhIDUA successfully reduces tissue and cellular GAG storage in synovium and articular cartilage, including cartilage deep to the articular surface, and eliminates inflammatory macrophages from synovial tissue. The MPS I canine IA-rhIDUA results suggest that clinical studies should be performed to determine if IA-rhIDUA is a viable approach to ameliorating refractory orthopedic disease in human MPS I. Copyright © 2014 Elsevier Inc. All rights reserved.

29 CFR 15.24 - Unallowable claims.

Science.gov (United States)

2010-07-01

..., interest, carrying charges, cost of lodging or food while awaiting arrival of shipment, attorney fees... business enterprise. (j) Commercial storage. Property stored at a commercial facility for the convenience...

Thermal test and analysis of a spent fuel storage cask

International Nuclear Information System (INIS)

Yamakawa, H.; Gomi, Y.; Ozaki, S.; Kosaki, A.

1993-01-01

A thermal test simulated with full-scale cask model for the normal storage was performed to verify the storage skill of the spent fuels of the cask. The maximum temperature at each point in the test was lower than the allowable temperature. The integrity of the cask was maintained. It was observed that the safety of containment system was also kept according to the check of the seal before and after the thermal test. Therefore it was shown that using the present skill, it is possible to store spent fuels in the dry-type cask safely. Moreover, because of the good agreement between analysis and experimental results, it was shown that the analysis model was successfully established to estimate the temperature distribution of the fuel cladding and the seal portion. (J.P.N.)

Comparison of monitoring technologies for CO2 storage and radioactive waste disposal

International Nuclear Information System (INIS)

Ryu, Jihun; Koh, Yongkwon; Choi, Jongwon; Lee, Jongyoul

2013-01-01

The monitoring techniques used in radioactive waste disposal have fundamentals of geology, hydrogeology, geochemistry etc, which could be applied to CO 2 sequestration. Large and diverse tools are available to monitoring methods for radioactive waste and CO 2 storage. They have fundamentals on geophysical and geochemical principles. Many techniques are well established while others are both novel and at an early stage of development. Reliable and cost-effective monitoring will be an important part of making geologic sequestration a safe, effective and acceptable method for radioactive waste disposal and CO 2 storage. In study, we discuss the monitoring techniques and the role of these techniques in providing insight in the risks of radioactive waste disposal and CO 2 sequestration

New facility for processing and storage of radioactive and toxic chemical waste

International Nuclear Information System (INIS)

Gallagher, F.E. III

1976-01-01

A new facility for the processing and storage of radioactive and toxic chemical waste is described. The facility is located in the science and engineering complex of the Santa Barbara campus of the University of California, near the Pacific Ocean. It is designed to provide a safe and secure processing and storage area for hazardous wastes, while meeting the high aesthetic standards and ecological requirements of campus and community regulatory boards. The ventilation system and fire prevention features will be described in detail. During the design phase, a small laboratory was added to provide an area for the radiation protection and industrial hygiene programs. Operational experience with this new facility is discussed

The long term storage of advanced gas-cooled reactor (AGR) fuel

International Nuclear Information System (INIS)

Standring, P.N.

1999-01-01

The approach being taken by BNFL in managing the AGR lifetime spent fuel arisings from British Energy reactors is given. Interim storage for up to 80 years is envisaged for fuel delivered beyond the life of the Thorp reprocessing plant. Adopting a policy of using existing facilities, to comply with the principles of waste minimisation, has defined the development requirements to demonstrate that this approach can be undertaken safely and business issues can be addressed. The major safety issues are the long term integrity of both the fuel being stored and structure it is being stored in. Business related issues reflect long term interactions with the rest of the Sellafield site and storage optimisation. Examples of the development programme in each of these areas is given. (author)

Sodium-ion hybrid electrolyte battery for sustainable energy storage applications

Science.gov (United States)

Senthilkumar, S. T.; Abirami, Mari; Kim, Junsoo; Go, Wooseok; Hwang, Soo Min; Kim, Youngsik

2017-02-01

Sustainable, safe, and low-cost energy storage systems are essential for large-scale electrical energy storage. Herein, we report a sodium (Na)-ion hybrid electrolyte battery with a replaceable cathode system, which is separated from the Na metal anode by a Na superionic conducting ceramic. By using a fast Na-ion-intercalating nickel hexacyanoferrate (NiHCF) cathode along with an eco-friendly seawater catholyte, we demonstrate good cycling performance with an average discharge voltage of 3.4 V and capacity retention >80% over 100 cycles and >60% over 200 cycle. Remarkably, such high capacity retention is observed for both the initial as well as replaced cathodes. Moreover, a Na-metal-free hybrid electrolyte battery containing hard carbon as the anode exhibits an energy density of ∼146 Wh kg-1 at a current density of 10 mA g-1, which is comparable to that of lead-acid batteries and much higher than that of conventional aqueous Na-ion batteries. These results pave the way for further advances in sustainable energy storage technology.

A concept of a nonfissile uranium hexafluoride overpack for storage, transport, and processing of corroded cylinders

International Nuclear Information System (INIS)

Pope, R.B.; Cash, J.M.; Singletary, B.H.

1996-01-01

There is a need to develop a means of safely transporting breached 48-in. cylinders containing depleted uranium hexafluoride (UF 6 ) from current storage locations to locations where the contents can be safely removed. There is also a need to provide a method of safely and easily transporting degraded cylinders that no longer meet the US Department of Transportation (DOT) and American National Standards Institute, Inc., (ANSI) requirements for shipments of depleted UF 6 . A study has shown that an overpack can be designed and fabricated to satisfy these needs. The envisioned overpack will handle cylinder models 48G, 48X, and 48Y and will also comply with the ANSI N14.1 and the American Society of Mechanical Engineers (ASME) Sect. 8 requirements

Storage of radioactive material - accidents - precipitation - personnel monitoring; Stokiranje radioaktivnih materijala - akcidenti - padavine - kontrola osoblja

Energy Technology Data Exchange (ETDEWEB)

Matijasic, A; Gacinovic, O [Institute of Nuclear Sciences Boris Kidric, Radioloska zastita, Vinca, Beograd (Serbia and Montenegro)

1961-12-15

This volume covers the reports on four routine tasks concerned with safe handling of radioactive material and influence of nuclear facilities on the environment. The tasks performed were as follows: Storage of solid and liquid radioactive material; actions in case of accidents; radiation monitoring of the fallout, water and ground; personnel dosimetry.

Technical basis for storage of Zircaloy-clad spent fuel in inert gases

International Nuclear Information System (INIS)

Johnson, A.B. Jr.; Gilbert, E.R.

1983-09-01

The technical bases to establish safe conditions for dry storage of Zircaloy-clad fuel are summarized. Dry storage of fuel with zirconium alloy cladding has been licensed in Canada, the Federal Republic of Germany, and Switzerland. Dry storage demonstrations, hot cell tests, and modeling have been conducted using Zircaloy-clad fuel. The demonstrations have included irradiated boiling water reactor, pressurized heavy-water reactor, and pressurized water reactor fuel assemblies. Irradiated fuel has been emplaced in and retrieved from metal casks, dry wells, silos, and a vault. Dry storage tests and demonstrations have involved about 15,000 fuel rods, and about 5600 rods have been monitored during dry storage in inert gases with maximum cladding temperatures ranging from 50 to 570 0 C. Although some tests and demonstrations are still in progress, there is currently no evidence that any rods exposed to inert gases have failed (one PWR rod exposed to an air cover gas failed at about 270 0 C). Based on this favorable experience, it is concluded that there is sufficient information on fuel rod behavior, storage conditions, and potential cladding failure mechanisms to support licensing of dry storage in the US. This licensing position includes a requirement for inert cover gases and a maximum cladding temperature guideline of 380 0 C for Zircaloy-clad fuel. Using an inert cover gas assures that even if fuel with cladding defects were placed in dry storage, or if defects develop during storage, the defects would not propagate. Tests and demonstrations involving Zircaloy-clad rods and assemblies with maximum cladding temperatures above 400 0 C are in progress. When the results from these tests have been evaluated, the viability of higher temperature limits should be examined. Acceptable conditions for storage in air and dry storage of consolidated fuel are issues yet to be resolved

Environmental assessment: Solid waste retrieval complex, enhanced radioactive and mixed waste storage facility, infrastructure upgrades, and central waste support complex, Hanford Site, Richland, Washington

Energy Technology Data Exchange (ETDEWEB)

NONE

1995-09-01

The U.S. Department of Energy (DOE) needs to take action to: retrieve transuranic (TRU) waste because interim storage waste containers have exceeded their 20-year design life and could fail causing a radioactive release to the environment provide storage capacity for retrieved and newly generated TRU, Greater-than-Category 3 (GTC3), and mixed waste before treatment and/or shipment to the Waste Isolation Pilot Project (WIPP); and upgrade the infrastructure network in the 200 West Area to enhance operational efficiencies and reduce the cost of operating the Solid Waste Operations Complex. This proposed action would initiate the retrieval activities (Retrieval) from Trench 4C-T04 in the 200 West Area including the construction of support facilities necessary to carry out the retrieval operations. In addition, the proposed action includes the construction and operation of a facility (Enhanced Radioactive Mixed Waste Storage Facility) in the 200 West Area to store newly generated and the retrieved waste while it awaits shipment to a final disposal site. Also, Infrastructure Upgrades and a Central Waste Support Complex are necessary to support the Hanford Site`s centralized waste management area in the 200 West Area. The proposed action also includes mitigation for the loss of priority shrub-steppe habitat resulting from construction. The estimated total cost of the proposed action is $66 million.

Environmental assessment: Solid waste retrieval complex, enhanced radioactive and mixed waste storage facility, infrastructure upgrades, and central waste support complex, Hanford Site, Richland, Washington

International Nuclear Information System (INIS)

1995-09-01

The U.S. Department of Energy (DOE) needs to take action to: retrieve transuranic (TRU) waste because interim storage waste containers have exceeded their 20-year design life and could fail causing a radioactive release to the environment provide storage capacity for retrieved and newly generated TRU, Greater-than-Category 3 (GTC3), and mixed waste before treatment and/or shipment to the Waste Isolation Pilot Project (WIPP); and upgrade the infrastructure network in the 200 West Area to enhance operational efficiencies and reduce the cost of operating the Solid Waste Operations Complex. This proposed action would initiate the retrieval activities (Retrieval) from Trench 4C-T04 in the 200 West Area including the construction of support facilities necessary to carry out the retrieval operations. In addition, the proposed action includes the construction and operation of a facility (Enhanced Radioactive Mixed Waste Storage Facility) in the 200 West Area to store newly generated and the retrieved waste while it awaits shipment to a final disposal site. Also, Infrastructure Upgrades and a Central Waste Support Complex are necessary to support the Hanford Site's centralized waste management area in the 200 West Area. The proposed action also includes mitigation for the loss of priority shrub-steppe habitat resulting from construction. The estimated total cost of the proposed action is $66 million

High-capacity hydrogen storage in Li-adsorbed g-C{sub 3}N{sub 4}

Energy Technology Data Exchange (ETDEWEB)

Wei, Jianfeng; Huang, Chengxi; Wu, Haiping, E-mail: mrhpwu@njust.edu.cn; Kan, Erjun, E-mail: ekan@njust.edu.cn

2016-09-01

Since hydrogen is a kind of potential source of efficient and pollution-free energy, it has attracted great research interests in recent years. However, the lack of safe and efficient hydrogen storage materials has blocked the rapid development of hydrogen energy. Here, we explored the possibility of Li-decorated g-C{sub 3}N{sub 4} as a kind of potential hydrogen storage materials based on first-principles calculations. Our results demonstrated that the adsorption energy of Li atoms on g-C{sub 3}N{sub 4} is much larger than the cohesive energy of bulk Li. Importantly, we find that the binding energy of each H{sub 2} molecule is about 0.29 eV, which is quite suitable for hydrogen storage. Furthermore, the estimated hydrogen storage capacity is around 9.2 wt %, which beyonds the goal of DOE. Thus, we predicted that Li-decorated g-C{sub 3}N{sub 4} may act as the potential hydrogen storage materials. - Highlights: • We explored the possibility of Li-decorated g-C{sub 3}N{sub 4} as a kind of potential hydrogen storage material. • We demonstrated the binding energy of each H{sub 2} molecule is 0.29 eV, which is quite suitable for hydrogen storage materials. • The hydrogen storage capacity is estimated around 9.2 wt %.

Long-term heat storage in calcium sulfoaluminate cement (CSA) based concrete

Energy Technology Data Exchange (ETDEWEB)

Kaufmann, Josef P.; Winnefeld, Frank [Empa Swiss Federal Laboratories for Materials Science and Technology, Duebendorf (Switzerland). Lab. for Concrete and Construction Chemistry

2011-07-01

In general, the selection of materials proposed for solar heat storage is based on one of two principal processes: sensible heat storage or latent heat storage. Sensible heat storage utilizes the specific heat capacity of a material, while latent heat storage is based on the change in enthalpy (heat content) associated with a phase change of the material. Long time sensible heat storage requires excellent thermal insulation whereas latent heat storage allows permanent (seasonal) storage without significant energy losses and any special insulation. Ettringite, one of the cement hydration products, exhibits a high dehydration enthalpy. Calcium sulfoaluminate cement based concrete containing a high amount of ettringite is henceproposed as an efficient latent heat storage material. Compared to conventional heat storage materials this innovative concrete mixture has a high loss-free storage energy density (> 100-150 kWh/m{sup 3}) which is much higher than the one of paraffin or the (loss-sensitive) sensible heat of water. Like common concrete the CSA-concrete is stable and even may carry loads. The dehydration of the CSA-concrete is achieved at temperatures below 100 C. The rehydration process occurs as soon as water (liquid or vapor) is added. In contrast to paraffin, the phase change temperature is not fixed and the latent heat may be recovered at any desired temperature. Furthermore the heat conductivity of this material is high, so that the energy transfer from/to an exchange medium is easy. Additionally CSA-concrete is not flammable and absolutely safe regarding any health aspects. The cost of such CSA-concrete isin the order of normal concrete. The main application is seen in house heating systems. Solar heat, mostly generated during the summer period by means of roof collectors, can be stored in CSA-concrete until the winter. A part or even the whole annual heatingenergy may be produced and saved locally by the householder himself. Additional applications may be

Nanosizing and nanoconfinement: new strategies towards meeting hydrogen storage goals.

Science.gov (United States)

de Jongh, Petra E; Adelhelm, Philipp

2010-12-17

Hydrogen is expected to play an important role as an energy carrier in a future, more sustainable society. However, its compact, efficient, and safe storage is an unresolved issue. One of the main options is solid-state storage in hydrides. Unfortunately, no binary metal hydride satisfies all requirements regarding storage density and hydrogen release and uptake. Increasingly complex hydride systems are investigated, but high thermodynamic stabilities as well as slow kinetics and poor reversibility are important barriers for practical application. Nanostructuring by ball-milling is an established method to reduce crystallite sizes and increase reaction rates. Since five years attention has also turned to alternative preparation techniques that enable particle sizes below 10 nanometers and are often used in conjunction with porous supports or scaffolds. In this Review we discuss the large impact of nanosizing and -confinement on the hydrogen sorption properties of metal hydrides. We illustrate possible preparation strategies, provide insight into the reasons for changes in kinetics, reversibility and thermodynamics, and highlight important progress in this field. All in all we provide the reader with a clear view of how nanosizing and -confinement can beneficially affect the hydrogen sorption properties of the most prominent materials that are currently considered for solid-state hydrogen storage.

Overall design concepts for the APS storage ring machine protection system

International Nuclear Information System (INIS)

Lumpkin, A.; Fuja, R.; Votaw, A.; Wang, X.; Shu, D.; Stepp, J.; Arnold, N.; Nawrocki, G.; Decker, G.; Chung, Y.

1995-01-01

The basic design and status of the machine protection system for the Advanced Photon Source (APS) storage ring are discussed. The machine is passively safe to the bending magnet sources, but the high power of the insertion devices requires missteering conditions to be identified and the beam aborted in less than one millisecond. The basic aspects of waterflow, temperature, beam position, etc. monitoring are addressed. Initial commissioning of subsystems and sensors is statused

Energy storage

International Nuclear Information System (INIS)

Anon.

1992-01-01

This chapter discusses the role that energy storage may have on the energy future of the US. The topics discussed in the chapter include historical aspects of energy storage, thermal energy storage including sensible heat storage, latent heat storage, thermochemical heat storage, and seasonal heat storage, electricity storage including batteries, pumped hydroelectric storage, compressed air energy storage, and superconducting magnetic energy storage, and production and combustion of hydrogen as an energy storage option

A case study in low-level radioactive waste storage

International Nuclear Information System (INIS)

Broderick, W.; Rella, R.J.

1984-01-01

Due to the current trend in Federal and State legislation, utilities are faced with the invitable problem of on-site storage of radioactive waste. Recognizing this problem, the New York Power Authority has taken measures to preclude the possibility of a plant shutdown due to a lack of space allocation for waste disposal at commercial burial sites coincident with an inability to safely store radioactive waste on-site. Capital funds have been appropriated for the design, engineering, and construction of an interim low-level radioactive waste storage facility. This project is currently in the preliminary design phase with a scheduled engineering completion date of September 1, 1984. Operation of the facility is expected for late 1985. The facility will provide storage space solidified liners, drums, and low specific activity (LSA) boxes at the historic rate of waste generation at the James A. Fitzpatrick Nuclear Power Plant, which is owned and operated by the New York Power Authority. Materials stored in the facility will be suitable for burial at a licensed burial facility and will be packaged to comply with the Department of Transportation regulations for shipment to a licensed burial ground. Waste shipments from the facility will normally be made on a first-in, first-out basis to minimize the storage time of any liner, drum or

Better safe than sorry: Increasing safety in radioactive waste management

International Nuclear Information System (INIS)

Gaspar, Miklos; Mutluer, Adem

2015-01-01

Abderrahim Bouih used to be worried about space. In charge of managing Morocco’s radioactive waste since 2006, he had long projected that the country’s sole radioactive waste facility would fill up by 2019. Thanks to a new methodology he and his colleagues learned through an IAEA project, they can now dismantle smoke detectors, lightning rods and other waste that contains radioactive material, safely separating the radioactive components from the metal, and significantly reducing the amount of radioactive waste they need to store. “We have condensed 60 drums of waste into just two,” said Bouih, Head of the Radioactive Waste Collection, Treatment and Storage Unit at the Moroccan National Centre for Nuclear Energy, Sciences and Technology. “This means our site won’t fill up for another 16 years.”

Rupture of plutonium oxide storage container, March 13, 1979

Energy Technology Data Exchange (ETDEWEB)

1979-05-29

On March 13, 1979, a plutonium oxide storage can ruptured in the 303-C storage facility, which is in the 300 Area of the Hanford Site, Washington. The facility is operated by the Pacific Northwest Laboratory (PNL); three PNL staff members were performing the storage operation. No injuries to these staff members resulted from the occurrence. A Class C Investigation Committee was appointed on March 14, 1979, by the Director, PNL. Subsequently, when the loss estimates became available, the Manager, Department of Energy-Richland Operations Office (DOE-RL), appointed a Class B Investigation Committee in accordance with DOE Manual Chapter 0502. As requested by DOE-RL, the Committee investigated technical elements of the causal sequence and management systems that should have or could have prevented the occurrence. The investigation included: review of the use of the 303-C facilities and the transfer containers; interviews with the involved personnel and their managers; analysis of technical studies related to involved materials and procedures; review of safe operating procedures, radiation work procedures, and transfer requirements applicable to the occurrence; and use of the Management Oversight and Risk Tree (MORT) and the Events and Causal Factors Charting methods. 15 figs.

Combining computation and experiment to accelerate the discovery of new hydrogen storage materials

Science.gov (United States)

Siegel, Donald

2009-03-01

The potential of emerging technologies such as fuel cells (FCs) and photovoltaics for environmentally-benign power generation has sparked renewed interest in the development of novel materials for high density energy storage. For applications in the transportation sector, the demands placed upon energy storage media are especially stringent, as a potential replacement for fossil-fuel-powered internal combustion engines -- namely, the proton exchange membrane FC -- utilizes hydrogen as a fuel. Although hydrogen has about three times the energy density of gasoline by weight, its volumetric energy density (even at 700 bar) is roughly a factor of six smaller. Consequently, the safe and efficient storage of hydrogen has been identified as one of the key materials-based challenges to realizing a transition to FC vehicles. This talk will present an overview of recent efforts at Ford aimed at developing new materials for reversible, solid state hydrogen storage. A tight coupling between first-principles modeling and experiments has greatly accelerated our efforts, and several examples illustrating the benefits of this approach will be presented.

An eight pushbutton control system for the PSU ultra-safe nuclear plant: Addendum to annual report

International Nuclear Information System (INIS)

Schultz, M.A.

1988-10-01

The control system described in this report was developed for a ''Light Water Ultra-Safe Plant Concept'' studied at Penn State during a 2 year program funded by the Department of Energy. A reconfigured pressurized water reactor was designed which eliminated the conventional PWR pressurizer and added an active pumping system with a large dedicated water storage tank to control pressure. The thermal hydraulics aspects of the design were studied and reported in several master's theses and other addendum reports and first annual report. In addition to improving the inherent safety of an advanced plant by changes in the thermal hydraulic aspects of the design, a new approach to control system organization and design should also be included in an advanced plant. The study presented in this report modifies a conventional PWR plant control system to the needs of the Ultra-Safe Plant Concept and then describes implementation of the control system in a distributed network of control computers. The end result is a control system that is much simpler at the operator level. This simplicity should eliminate the possibility of operator error in the Ultra-Safe plant

Operation modes research of liquefied natural gas storages as a part of the ground complexes equipment

Directory of Open Access Journals (Sweden)

N. S. Korolev

2014-01-01

Full Text Available The use of the Liquefied Natural Gas (LNG in the space-rocket equipment is motivated by some advantages. That is why a lot of tests and works are actively carried out now on rocket engines using liquefied natural gas.To provide the engine tests and subsequent rocket complex operation a creation of LNG storages is demanded as a part of ground processing equipment and support for their safe operation conditions.One of LNG danger factor is its low boiling temperature, and also changing the condition, density and LNG boiling temperature at storage due to evaporation of light component, namely methane. At refill of the storages having fuel remains with a new LNG portion these factors can lead to formation of the stratified macro-layers and cause a mode of the intensive mixing that is called "rollover", with almost instant evaporation of LNG big mass and sharp pressure boost, capable to result in the storage distraction with catastrophic effects.The work objectives are formulated such as a technique development for forecasting of the LNG parameters in operating storages including the rollover mode, a comparison of calculated results of the LNG parameters with the experimental data, and a definition of possible recommendations for safe operation of LNG storages as a part of the ground complexes equipment.The paper reviews 12 publications concerning the issues and proceeding processes at operation of LNG storages, including the rollover mode.To verify the reliability of process simulation results in the LNG, represented in models by the binary methane-ethane mixture the calculated values have been compared with the experimental data for a LNG storage mode in the reservoir of a ground test complex.The reliability of developed models of the heat-mass-exchange processes in stratified on density and temperature in LNG storage with emergence of conditions for the rollover mode has been verified by comparing the settlement characteristics to the published

Is it time to revisit contraindications to organ donation from donors with a JAK-2 mutation? Safe use of a liver allograft from a donor with essential thrombocythaemia.

Science.gov (United States)

Haldar, Debashis; Chen, Frederick; Byron, Jane; Elsharkawy, Ahmed Mohamed; Perera, M Thamara Pr

2015-07-01

Transplantation can cure end-stage liver disease and hepatocellular carcinoma. However, the balance of organ demand and provision is heavily tipped to the detriment of patients. Patients awaiting transplantation rely on the greater use of marginal donors that may carry a risk to the recipient. UK authorities have decreed donor haematological malignancy an absolute contraindication. The authors describe the first report of a patient being safely transplanted with a liver from a donor who suffered from JAK2 V617F mutation-driven essential thrombocythaemia to a patient with a critical burden of hepatocellular carcinoma. A year after transplantation, the patient has neither evidence of acquisition of the donor's pathology, nor evidence of carcinoma recurrence. The case highlights the responsibility of the recipient team to maximize the use of organs by expert risk assessment. Dissemination of experience should inform future decisions, benefit patients and bolster utility in an era of growing waiting-list mortality. © 2015 Steunstichting ESOT.

Are Detox Diets Safe?

Science.gov (United States)

... Safe Videos for Educators Search English Español Are Detox Diets Safe? KidsHealth / For Teens / Are Detox Diets ... seguras las dietas de desintoxicación? What Is a Detox Diet? The name sounds reassuring — everyone knows that ...

Enhanced Thermal Management System for Spent Nuclear Fuel Dry Storage Canister with Hybrid Heat Pipes

International Nuclear Information System (INIS)

Jeong, Yeong Shin; Bang, In Cheol

2016-01-01

Dry storage uses the gas or air as coolant within sealed canister with neutron shielding materials. Dry storage system for spent fuel is regarded as relatively safe and emits little radioactive waste for the storage, but it showed that the storage capacity and overall safety of dry cask needs to be enhanced for the dry storage cask for LWR in Korea. For safety enhancement of dry cask, previous studies of our group firstly suggested the passive cooling system with heat pipes for LWR spent fuel dry storage metal cask. As an extension, enhanced thermal management systems for the spent fuel dry storage cask for LWR was suggested with hybrid heat pipe concept, and their performances were analyzed in thermal-hydraulic viewpoint in this paper. In this paper, hybrid heat pipe concept for dry storage cask is suggested for thermal management to enhance safety margin. Although current design of dry cask satisfies the design criteria, it cannot be assured to have long term storage period and designed lifetime. Introducing hybrid heat pipe concept to dry storage cask designed without disrupting structural integrity, it can enhance the overall safety characteristics with adequate thermal management to reduce overall temperature as well as criticality control. To evaluate thermal performance of hybrid heat pipe according to its design, CFD simulation was conducted and previous and revised design of hybrid heat pipe was compared in terms of temperature inside canister

A comparative study on uranium and ZrCo for the storage of tritium

Energy Technology Data Exchange (ETDEWEB)

Kim, Summi; Paek, Seungwoo; Lee, Minsoo; Kim, Kwangrag; Ahn, Dohee [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of); Sohn, Soonhwan; Song, Kyumin [Korea Electric Power Research Institute, Daejeon (Korea, Republic of)

2007-07-01

Safe handling, transport, and storage of tritium requires several condition: very low equilibrium pressures over the tritide at room temperature, high dissociation pressure at moderate temperatures, existence of plateau regions in the loading/deloading isotherms, fast adsorption/desorption kinetics, no disproportionation, low reactivity of the metal/tritide system towards air and the major contaminants, low pyrophoricity, and low aging effects caused by the accumulated of He-3.

A comparative study on uranium and ZrCo for the storage of tritium

International Nuclear Information System (INIS)

Kim, Summi; Paek, Seungwoo; Lee, Minsoo; Kim, Kwangrag; Ahn, Dohee; Sohn, Soonhwan; Song, Kyumin

2007-01-01

Safe handling, transport, and storage of tritium requires several condition: very low equilibrium pressures over the tritide at room temperature, high dissociation pressure at moderate temperatures, existence of plateau regions in the loading/deloading isotherms, fast adsorption/desorption kinetics, no disproportionation, low reactivity of the metal/tritide system towards air and the major contaminants, low pyrophoricity, and low aging effects caused by the accumulated of He-3

Dry Storage at long term of nuclear fuels: Influence of the fuel design and commercial irradiation conditions

International Nuclear Information System (INIS)

Marino, Armando C

2009-01-01

The BaCo code was applied to simulate the behaviour for a PHWR fuel under storage conditions showing a strong dependence on the original design of the fuel and the irradiation history. In particular, the results of the statistical analysis of BaCo indicate that the integrity of the fuel is influenced by the manufacture tolerances and the solicitations during the NPP irradiation. The main conclusion of the present study is that the fuel temperature of the device should be carefully controlled in order to ensure safe storage conditions. [es

Design considerations and operating experience with wet storage of Ontario Hydro's irradiated fuel

International Nuclear Information System (INIS)

Frost, C.R.; Naqvi, S.J.; McEachran, R.A.

1987-01-01

The characteristics of Ontario Hydro's fuel and at-reactor irradiated fuel storage water pools (or irradiated fuel bays) are described. There are two types of bay known respectively as primary bays and auxiliary bays, used for at-reactor irradiated fuel storage. Irradiated fuel is discharged remotely from Ontario Hydro's reactors to the primary bays for initial storage and cooling. The auxiliary bays are used to receive and store fuel after its initial cooling in the primary bay, and provide additional storage capacity as needed. The major considerations in irradiated fuel bay design, including site-specific requirements, reliability and quality assurance, are discussed. The monitoring of critical fuel bay components, such as bay liners, the development of high storage density fuel containers, and the use of several irradiated fuel bays at each reactor site have all contributed to the safe handling of the large quantities of irradiated fuel over a period of about 25 years. Routine operation of the irradiated fuel bays and some unusual bay operational events are described. For safety considerations, the irradiated fuel in storage must retain its integrity. Also, as fuel storage is an interim process, likely for 50 years or more, the irradiated fuel should be retrievable for downstream fuel management phases such as reprocessing or disposal. A long-term experimental program is being used to monitor the integrity of irradiated fuel in long-term wet storage. The well characterized fuel, some of which has been in wet storage since 1962 is periodically examined for possible deterioration. The evidence from this program indicates that there will be no significant change in irradiated fuel integrity (and retrievability) over a 50 year wet storage period

How the University of Texas system responded to the need for interim storage of low-level radioactive waste materials.

Science.gov (United States)

Emery, Robert J

2012-11-01

Faced with the prospect of being unable to permanently dispose of low-level radioactive wastes (LLRW) generated from teaching, research, and patient care activities, component institutions of the University of Texas System worked collaboratively to create a dedicated interim storage facility to be used until a permanent disposal facility became available. Located in a remote section of West Texas, the University of Texas System Interim Storage Facility (UTSISF) was licensed and put into operation in 1993, and since then has provided safe and secure interim storage for up to 350 drums of dry solid LLRW at any given time. Interim storage capability provided needed relief to component institutions, whose on-site waste facilities could have possibly become overburdened. Experiences gained from the licensing and operation of the site are described, and as a new permanent LLRW disposal facility emerges in Texas, a potential new role for the storage facility as a surge capacity storage site in times of natural disasters and emergencies is also discussed.

Waste and Encapsulation Storage Facility (WESF) Essential and Support Drawing List

International Nuclear Information System (INIS)

SHANNON, W.R.

1999-01-01

Provides listing of Essential and Support Drawings for the Waste and Encapsulation Storage Facility. The drawings identified in this document will comprise the Waste Encapsulation and Storage Facility essential and support drawing list. This list will replace drawings identified as the ''WESF Essential and support drawing list''. Additionally, this document will follow the applicable requirements of HNF-PRO-242 Engineering Drawing Requirements'' and FSP-WESF-001, Section EN-1 ''Documenting Engineering Changes''. An essential drawing is defined as an engineering drawing identified by the facility staff as necessary to directly support the safe operation or maintenance of the facility. A support drawing is defined as a drawing identified by the facility staff that further describes the design details of structures, systems, or components shown on essential drawings or is frequently used by the support staff

Standardized Testing Program for Solid-State Hydrogen Storage Technologies

Energy Technology Data Exchange (ETDEWEB)

Miller, Michael A. [Southwest Research Institute; Page, Richard A. [Southwest Research Institute

2012-07-30

In the US and abroad, major research and development initiatives toward establishing a hydrogen-based transportation infrastructure have been undertaken, encompassing key technological challenges in hydrogen production and delivery, fuel cells, and hydrogen storage. However, the principal obstacle to the implementation of a safe, low-pressure hydrogen fueling system for fuel-cell powered vehicles remains storage under conditions of near-ambient temperature and moderate pressure. The choices for viable hydrogen storage systems at the present time are limited to compressed gas storage tanks, cryogenic liquid hydrogen storage tanks, chemical hydrogen storage, and hydrogen absorbed or adsorbed in a solid-state material (a.k.a. solid-state storage). Solid-state hydrogen storage may offer overriding benefits in terms of storage capacity, kinetics and, most importantly, safety.The fervor among the research community to develop novel storage materials had, in many instances, the unfortunate consequence of making erroneous, if not wild, claims on the reported storage capacities achievable in such materials, to the extent that the potential viability of emerging materials was difficult to assess. This problem led to a widespread need to establish a capability to accurately and independently assess the storage behavior of a wide array of different classes of solid-state storage materials, employing qualified methods, thus allowing development efforts to focus on those materials that showed the most promise. However, standard guidelines, dedicated facilities, or certification programs specifically aimed at testing and assessing the performance, safety, and life cycle of these emergent materials had not been established. To address the stated need, the Testing Laboratory for Solid-State Hydrogen Storage Technologies was commissioned as a national-level focal point for evaluating new materials emerging from the designated Materials Centers of Excellence (MCoE) according to

Extending Spent Fuel Storage until Transport for Reprocessing or Disposal

Energy Technology Data Exchange (ETDEWEB)

Carlsen, Brett; Chiguer, Mustapha; Grahn, Per; Sampson, Michele; Wolff, Dietmar; Bevilaqua, Arturo; Wasinger, Karl; Saegusa, Toshiari; Seelev, Igor

2016-09-01

Spent fuel (SF) must be stored until an end point such as reprocessing or geologic disposal is imple-mented. Selection and implementation of an end point for SF depends upon future funding, legisla-tion, licensing and other factors that cannot be predicted with certainty. Past presumptions related to the availability of an end point have often been wrong and resulted in missed opportunities for properly informing spent fuel management policies and strategies. For example, dry cask storage systems were originally conceived to free up needed space in reactor spent fuel pools and also to provide SFS of up to 20 years until reprocessing and/or deep geological disposal became available. Hundreds of dry cask storage systems are now employed throughout the world and will be relied upon well beyond the originally envisioned design life. Given present and projected rates for the use of nuclear power coupled with projections for SF repro-cessing and disposal capacities, one concludes that SF storage will be prolonged, potentially for several decades. The US Nuclear Regulatory Commission has recently considered 300 years of storage to be appropriate for the characterization and prediction of ageing effects and ageing management issues associated with extending SF storage and subsequent transport. This paper encourages addressing the uncertainty associated with the duration of SF storage by de-sign – rather than by default. It suggests ways that this uncertainty may be considered in design, li-censing, policy, and strategy decisions and proposes a framework for safely extending spent fuel storage until SF can be transported for reprocessing or disposal – regardless of how long that may be. The paper however is not intended to either encourage or facilitate needlessly extending spent fuel storage durations. Its intent is to ensure a design and safety basis with sufficient margin to accommodate the full range of potential future scenarios. Although the focus is primarily on

Safe Anesthesia For Every Tot

DEFF Research Database (Denmark)

Weiss, Markus; Vutskits, Laszlo; Hansen, Tom G

2015-01-01

PURPOSE OF REVIEW: The term 'safe use of anesthesia in children is ill-defined and requires definition of and focus on the 'safe conduct of pediatric anesthesia'. RECENT FINDINGS: The Safe Anesthesia For Every Tot initiative (www.safetots.org) has been set up during the last year to focus...... on the safe conduct of pediatric anesthesia. This initiative aims to provide guidance on markers of quality anesthesia care. The introduction and implementation of national regulations of 'who, where, when and how' are required and will result in an improved perioperative outcome in vulnerable children....... The improvement of teaching, training, education and supervision of the safe conduct of pediatric anesthesia are the main goals of the safetots.org initiative. SUMMARY: This initiative addresses the well known perioperative risks in young children, perioperative causes for cerebral morbidity as well as gaps...

F2-3 using the shield for thermal energy storage in PULSAR

International Nuclear Information System (INIS)

Sager, G.T.; Sze, D.K.; Wong, C.P.C.

1994-01-01

The PULSAR design study is evaluating the pulsed, inductively driven tokamak power plant to assess whether economies can be attained which-are more favorable than those of the steady-state, non-inductively driven tokamak. Considerations of market acceptance and component fatigue lead to the requirement of thermal energy storage (TES) to maintain steady-state power during the cyclic interruptions of fusion power production (open-quotes dwell phaseclose quotes). A major focus of the Study has been to identify and design technically viable TES systems for helium-cooled and liquid lithium self-cooled plants which are economically attractive, safe and environmentally benign. Several basic constraints impact the selection of the TES system. The system must be capable of discharging 2.5 GW during a dwell phase of approximately two minutes (determined by systems code analysis), thus have a capacity of at least 300 GJ. Coolant must be discharged from the TES at the static, burn phase temperature to minimize thermal stress in the steam generator. Several TES options were evaluated: Storage of heat transport working fluid, phase change media and sensible heat storage. Sensible heat storage in the outer shield was selected for PULSAR

Pediatric surgeons and anesthesiologists expand the dialogue on the neurotoxicity question, rationale for early and delayed surgeries, and practice changes while awaiting definitive evidence.

Science.gov (United States)

Byrne, Mary W; Casale, Pasquale; Garzon, Maria; Hyman, Joshua E; Lin, Albert Y; Lynch, Lisa R; Schleien, Charles L; Stylianos, Steven

2014-10-01

The Pediatric Anesthesia NeuroDevelopment Assessment team at Columbia University Medical Center Department of Anesthesiology convened its fourth biennial Symposium to address unresolved issues concerning potential neurotoxic effects of anesthetic agents and sedatives on young children and to assess study findings to date. Dialogue initiated at the third Symposium was continued between anesthesiologists, researchers, and a panel of expert pediatric surgeons representing general surgery and dermatology, orthopedic, and urology specialties. The panel explored the need to balance benefits of early surgery using improved technologies against potential anesthetic risks, practice changes while awaiting definitive answers, and importance of continued interprofessional dialogue.

Evolution of association between renal and liver functions while awaiting heart transplant: An application using a bivariate multiphase nonlinear mixed effects model.

Science.gov (United States)

Rajeswaran, Jeevanantham; Blackstone, Eugene H; Barnard, John

2018-07-01

In many longitudinal follow-up studies, we observe more than one longitudinal outcome. Impaired renal and liver functions are indicators of poor clinical outcomes for patients who are on mechanical circulatory support and awaiting heart transplant. Hence, monitoring organ functions while waiting for heart transplant is an integral part of patient management. Longitudinal measurements of bilirubin can be used as a marker for liver function and glomerular filtration rate for renal function. We derive an approximation to evolution of association between these two organ functions using a bivariate nonlinear mixed effects model for continuous longitudinal measurements, where the two submodels are linked by a common distribution of time-dependent latent variables and a common distribution of measurement errors.

78 FR 17766 - Interagency Guidance on Leveraged Lending

Science.gov (United States)

2013-03-22

... high-level principles related to safe-and-sound leveraged lending activities, including underwriting considerations, assessing and documenting enterprise value, risk management expectations for credits awaiting distribution, stress- testing expectations, pipeline portfolio management, and risk management expectations for...

Energy Storage.

Science.gov (United States)

Eaton, William W.

Described are technological considerations affecting storage of energy, particularly electrical energy. The background and present status of energy storage by batteries, water storage, compressed air storage, flywheels, magnetic storage, hydrogen storage, and thermal storage are discussed followed by a review of development trends. Included are…

Overview of symposium on storage of spent fuel from power reactors

International Nuclear Information System (INIS)

Bonne, A.; Crijns, M.J.; Dyck, H.P.

2001-01-01

An International Symposium on Storage of Spent Fuel from Power Reactors was held in Vienna from 9-13 November 1998. The Symposium was organized by the International Atomic Energy Agency in co-operation with the OECD Nuclear Energy Agency. Of the one hundred sixty participants registered, one hundred twenty-five (including 3 observers) representing 35 countries and 4 international organizations, attended the Symposium. 20 participants from developing countries received Agency's grants. During 4 main Sessions, 44 oral presentations of papers were made and subsequent discussions held. At a poster session 13 papers were presented. This paper will give an overview of the Symposium. The Symposium gave an opportunity to exchange information on the state of art and prospects of spent fuel storage, to discuss the worldwide situation and the major factors influencing the national policies in this field and to identify the most important directions that national efforts and international co-operation in this area should take. It was obvious from the papers presented and the discussions that the handling and storage of spent fuel is continuously taking place safely. Dominant messages retrieved from the Symposium are that the primary spent fuel management solution for the next decades will be interim storage, the duration time of interim storage becomes longer than earlier anticipated and the storage facilities will have to be designed for receiving also spent fuel from advanced fuel cycle practices (i.e. high burnup and MOX spent fuel). It was noted that the handling and storage of spent fuel is a mature technology and meets the stringent safety requirements applicable in the different countries. The changes in nuclear policy and philosophy across the world, and practical considerations, have made interim storage a real necessity in the nuclear power industry. (author)

Conditioning and storage of low level radioactive waste in FR Yugoslavia

International Nuclear Information System (INIS)

Plecas, I.; Pavlovic, R.; Pavlovic, S.

2000-01-01

FR Yugoslavia is a country without any nuclear power plant on its territory. In the last forty years in the country, as a result of the two research reactors operation and also from radionuclides applications in medicine, industry and agriculture, radioactive waste materials of different levels of specific activity are generated. As a temporary solution, these radioactive waste materials are stored in the two interim storage facility. Since one of the storage facilities is completely full with radioactive wastes, packed in metal drums and plastic barrels, and the second one has an effective space for the next few years, attempts are made in the 'Vinca' Institute of Nuclear Sciences in developing the the immobilization process, for low and intermediate level radioactive wastes and their safe disposal. As an immobilization process, cementation process is investigated. Developed immobilization process has, as a final goal, production of solidified waste-matrix mixture form, that is easy for handling and satisfies requirements for interim storage and final disposal. Radioactive wastes immobilized in inactive matrices are to be placed into concrete containers for further manipulation and disposal

Amineborane Based Chemical Hydrogen Storage - Final Report

International Nuclear Information System (INIS)

Sneddon, Larry G.

2011-01-01

The development of efficient and safe methods for hydrogen storage is a major hurdle that must be overcome to enable the use of hydrogen as an alternative energy carrier. The objectives of this project in the DOE Center of Excellence in Chemical Hydride Storage were both to develop new methods for on-demand, low temperature hydrogen release from chemical hydrides and to design high-conversion off-board methods for chemical hydride regeneration. Because of their reactive protic (N-H) and hydridic (B-H) hydrogens and high hydrogen contents, amineboranes such as ammonia borane, NH 3 BH 3 (AB), 19.6-wt% H 2 , and ammonia triborane NH 3 B 3 H 7 (AT), 17.7-wt% H 2 , were initially identified by the Center as promising, high-capacity chemical hydrogen storage materials with the potential to store and deliver molecular hydrogen through dehydrogenation and hydrolysis reactions. In collaboration with other Center partners, the Penn project focused both on new methods to induce amineborane H 2 -release and on new strategies for the regeneration the amineborane spent-fuel materials. The Penn approach to improving amineborane H 2 -release focused on the use of ionic liquids, base additives and metal catalysts to activate AB dehydrogenation and these studies successfully demonstrated that in ionic liquids the AB induction period that had been observed in the solid-state was eliminated and both the rate and extent of AB H2-release were significantly increased. These results have clearly shown that, while improvements are still necessary, many of these systems have the potential to achieve DOE hydrogen-storage goals. The high extent of their H 2 -release, the tunability of both their H 2 materials weight-percents and release rates, and their product control that is attained by either trapping or suppressing unwanted volatile side products, such as borazine, continue to make AB/ionic-liquid based systems attractive candidates for chemical hydrogen storage applications. These

Amineborane Based Chemical Hydrogen Storage - Final Report

Energy Technology Data Exchange (ETDEWEB)

Sneddon, Larry G.

2011-04-21

The development of efficient and safe methods for hydrogen storage is a major hurdle that must be overcome to enable the use of hydrogen as an alternative energy carrier. The objectives of this project in the DOE Center of Excellence in Chemical Hydride Storage were both to develop new methods for on-demand, low temperature hydrogen release from chemical hydrides and to design high-conversion off-board methods for chemical hydride regeneration. Because of their reactive protic (N-H) and hydridic (B-H) hydrogens and high hydrogen contents, amineboranes such as ammonia borane, NH3BH3 (AB), 19.6-wt% H2, and ammonia triborane NH3B3H7 (AT), 17.7-wt% H2, were initially identified by the Center as promising, high-capacity chemical hydrogen storage materials with the potential to store and deliver molecular hydrogen through dehydrogenation and hydrolysis reactions. In collaboration with other Center partners, the Penn project focused both on new methods to induce amineborane H2-release and on new strategies for the regeneration the amineborane spent-fuel materials. The Penn approach to improving amineborane H2-release focused on the use of ionic liquids, base additives and metal catalysts to activate AB dehydrogenation and these studies successfully demonstrated that in ionic liquids the AB induction period that had been observed in the solid-state was eliminated and both the rate and extent of AB H2-release were significantly increased. These results have clearly shown that, while improvements are still necessary, many of these systems have the potential to achieve DOE hydrogen-storage goals. The high extent of their H2­-release, the tunability of both their H2 materials weight-percents and release rates, and their product control that is attained by either trapping or suppressing unwanted volatile side products, such as borazine, continue to make AB/ionic­-liquid based systems attractive candidates for chemical hydrogen storage applications. These studies also

Palladium on Nitrogen-Doped Mesoporous Carbon: A Bifunctional Catalyst for Formate-Based, Carbon-Neutral Hydrogen Storage.

Science.gov (United States)

Wang, Fanan; Xu, Jinming; Shao, Xianzhao; Su, Xiong; Huang, Yanqiang; Zhang, Tao

2016-02-08

The lack of safe, efficient, and economical hydrogen storage technologies is a hindrance to the realization of the hydrogen economy. Reported herein is a reversible formate-based carbon-neutral hydrogen storage system that is established over a novel catalyst comprising palladium nanoparticles supported on nitrogen-doped mesoporous carbon. The support was fabricated by a hard template method and nitridated under a flow of ammonia. Detailed analyses demonstrate that this bicarbonate/formate redox equilibrium is promoted by the cooperative role of the doped nitrogen functionalities and the well-dispersed, electron-enriched palladium nanoparticles. © 2016 WILEY-VCH Verlag GmbH & Co. KGaA, Weinheim.

Have We Overestimated Saline Aquifer CO2 Storage Capacities?

International Nuclear Information System (INIS)

Thibeau, S.; Mucha, V.

2011-01-01

During future, large scale CO 2 geological storage in saline aquifers, fluid pressure is expected to rise as a consequence of CO 2 injection, but the pressure build up will have to stay below specified values to ensure a safe and long term containment of the CO 2 in the storage site. The pressure build up is the result of two different effects. The first effect is a local overpressure around the injectors, which is due to the high CO 2 velocities around the injectors, and which can be mitigated by adding CO 2 injectors. The second effect is a regional scale pressure build up that will take place if the storage aquifer is closed or if the formation water that flows away from the pressurised area is not large enough to compensate volumetrically the CO 2 injection. This second effect cannot be mitigated by adding additional injectors. In the first section of this paper, we review some major global and regional assessments of CO 2 storage capacities in deep saline aquifers, in term of mass and storage efficiency. These storage capacities are primarily based on a volumetric approach: storage capacity is the volumetric sum of the CO 2 that can be stored through various trapping mechanisms. We then discuss in Section 2 storage efficiencies derived from a pressure build up approach, as stated in the CO2STORE final report (Chadwick A. et al. (eds) (2008) Best Practice for the Storage of CO 2 in Saline Aquifers, Observations and Guidelines from the SACS and CO2STORE Projects, Keyworth, Nottingham, BGS Occasional Publication No. 14) and detailed by Van der Meer and Egberts (van der Meer L.G.H., Egberts P.J.P. (2008) A General Method for Calculating Subsurface CO 2 Storage Capacity, OTC Paper 19309, presented at the OTC Conference held in Houston, Texas, USA, 5-8 May). A quantitative range of such storage efficiency is presented, based on a review of orders of magnitudes of pore and water compressibilities and allowable pressure increase. To illustrate the relevance of this

Study of a brazilian cask and its installation for PWR spent nuclear fuel dry storage

International Nuclear Information System (INIS)

Romanato, Luiz Sergio

2009-01-01

Spent nuclear fuel (SNF) is removed from the nuclear reactor after the depletion on efficiency in generating energy. After the withdrawal from the reactor core, the SNF is temporarily stored in pools at the same site of the reactor. At this time, the generated heat and the short and medium lived radioactive elements decay to levels that allow removing SNF from the pool and sending it to temporary dry storage. In that phase, the fuel needs to be safely and efficiently stored, and then, it can be retrieved in a future, or can be disposed as radioactive waste. The amount of spent fuel increases annually and, in the next years, will still increase more, because of the construction of new nuclear plants. Today, the number of new facilities back up to levels of the 1970's, since it is greater than the amount of decommissioning in old installations. As no final decision on the back-end of the nuclear fuel cycle is foreseen in the near future in Brazil, either to recover the SNF or to consider it as radioactive waste, this material has to be isolated in some type of storage model existing around the world. In the present study it is shown that dry SNF storage is the best option. A national cask model for SNF as well these casks storage installation are proposed. It is a multidisciplinary study in which the engineering conceptual task was developed and may be applied to national SNF removed from the Brazilian power reactors, to be safely stored for a long time until the Brazilian authorities will decide about the site for final disposal. (author)

Estimation of the detection limit of an experimental model of tritium storage bed designed for 'in-situ' accountability

International Nuclear Information System (INIS)

Bulubasa, Gheorghe; Bidica, Nicolae; Stefanescu, Ioan; Bucur, Ciprian; Deaconu, Mariea

2009-01-01

During the water detritiation process most of the tritium inventory is transferred from water into the gaseous phase, then it is further enriched and finally extracted and safely stored. The control of tritium inventory is an acute issue from several points of view: - Financially - tritium is an expensive material; - Safeguard - tritium is considered as nuclear material of strategic importance; - Safety - tritium is a radioactive material: requirements for documented safety analysis report (to ensure strict limits on the total tritium allowed) and for evaluation of accident consequences associated with that inventory. Large amounts of tritium can be stored, in a very safely manner, as metal tritides. A bench-scale experiment of a tritium storage bed with integrated system for in-situ tritium inventory accountancy was designed and developed at ICSI Rm. Valcea. The calibration curve and the detection limit for this experimental model of tritium storage bed were determined. The experimental results are presented in this paper. (authors)

Underground Storage Tanks - Storage Tank Locations

Data.gov (United States)

NSGIC Education | GIS Inventory — A Storage Tank Location is a DEP primary facility type, and its sole sub-facility is the storage tank itself. Storage tanks are aboveground or underground, and are...

Evaluation of potential for MSRE spent fuel and flush salt storage and treatment at the INEL

International Nuclear Information System (INIS)

Ougouag, A.M.; Ostby, P.A.; Nebeker, R.L.

1996-09-01

The potential for interim storage as well as for treatment of the Molten Salt Reactor Experiment spent fuel at INEL has been evaluated. Provided that some minimal packaging and chemical stabilization prerequisites are satisfied, safe interim storage of the spent fuel at the INEL can be achieved in a number of existing or planned facilities. Treatment by calcination in the New Waste Calcining Facility at the INEL can also be a safe, effective, and economical alternative to treatment that would require the construction of a dedicated facility. If storage at the INEL is chosen for the Molten Salt Reactor Experiment (MSRE) spent fuel salts, their transformation to the more stable calcine solid would still be desirable as it would result in a lowering of risks. Treatment in the proposed INEL Remote-Handled Immobilization Facility (RHIF) would result in a waste form that would probably be acceptable for disposal at one of the proposed national repositories. The cost increment imputable to the treatment of the MSRE salts would be a small fraction of the overall capital and operating costs of the facility or the cost of building and operating a dedicated facility. Institutional and legal issues regarding shipments of fuel and waste to the INEL are summarized. The transfer of MSRE spent fuel for interim storage or treatment at the INEL is allowed under existing agreements between the State of idaho and the Department of energy and other agencies of the Federal Government. In contrast, current agreements preclude the transfer into Idaho of any radioactive wastes for storage or disposal within the State of Idaho. This implies that wastes and residues produced from treating the MSRE spent fuel at locations outside Idaho would not be acceptable for storage in Idaho. Present agreements require that all fuel and high-level wastes stored at the INEL, including MSRE spent fuel if received at the INEL, must be moved to a location outside Idaho by the year 2035

Development of long term storage technique for recovered Kr-85, (1)

International Nuclear Information System (INIS)

Inada, Eiichi; Motoyama, Shigeji; Tsunoda, Naomi; Yamamoto, Keizo; Hirano, Seiji.

1979-01-01

The adsorption storage method of radioactive krypton Kr-85 using a double cylinder packed with activated charcoal is expected to be put into practical use as an intermediate storing method until the immobilization technique for long term storage is established. In this paper, the conceptual design of an intermediate, remote-controlled Kr-85 storage facility is presented. The features of this system are double containment, low pressure storage, and remote control. Kr-85 is at first filled into a double cylinder by the adsorbing effect of activated charcoal at low temperature (-196 deg C) by cooling with liquid nitrogen. Then, the unwelded portion of the outer cylinder containing the inner cylinder is welded and inspected to make double containment. The double cylinders are cooled by ventilation to remove the decay heat of Kr-85, and krypton leakage is always monitored. If any leakage is detected, the double cylinder is transferred to the cutting cell for the re-encapsulation of Kr-85 in a safe double cylinder. All operations are performed by remote control because of a high radiation field. The expected amount and composition of Kr-85 to be recovered from the reprocessing plant are also given as the design conditions. (Wakatsuki, Y.)

Next generation molten NaI batteries for grid scale energy storage

Science.gov (United States)

Small, Leo J.; Eccleston, Alexis; Lamb, Joshua; Read, Andrew C.; Robins, Matthew; Meaders, Thomas; Ingersoll, David; Clem, Paul G.; Bhavaraju, Sai; Spoerke, Erik D.

2017-08-01

Robust, safe, and reliable grid-scale energy storage continues to be a priority for improved energy surety, expanded integration of renewable energy, and greater system agility required to meet modern dynamic and evolving electrical energy demands. We describe here a new sodium-based battery based on a molten sodium anode, a sodium iodide/aluminum chloride (NaI/AlCl3) cathode, and a high conductivity NaSICON (Na1+xZr2SixP3-xO12) ceramic separator. This NaI battery operates at intermediate temperatures (120-180 °C) and boasts an energy density of >150 Wh kg-1. The energy-dense NaI-AlCl3 ionic liquid catholyte avoids lifetime-limiting plating and intercalation reactions, and the use of earth-abundant elements minimizes materials costs and eliminates economic uncertainties associated with lithium metal. Moreover, the inherent safety of this system under internal mechanical failure is characterized by negligible heat or gas production and benign reaction products (Al, NaCl). Scalability in design is exemplified through evolution from 0.85 to 10 Ah (28 Wh) form factors, displaying lifetime average Coulombic efficiencies of 99.45% and energy efficiencies of 81.96% over dynamic testing lasting >3000 h. This demonstration promises a safe, cost-effective, and long-lifetime technology as an attractive candidate for grid scale storage.

Criticality Safety Evaluation for 30B and 48X UF6 Cylinders for Transportation and Storage

International Nuclear Information System (INIS)

Mokhatri, Homami Zahra; Nematollahi, Mohammadreza; Kamyab, Shahabeddin

2011-01-01

30B and 48X cylinders are two standard containers have been used for transportation and storage of uranium hexafluoride with 21/2-ton and 10-ton loading capacity, respectively. For the sake of nuclear safety, the long-term safe storage and transportation of the cylinders are necessary to be concerned. Safe limits in handling and storage of 30B and 48X cylinders from the criticality safety considerations, has been investigated in this paper, by using the MCNP.4C code with ENDF/B-VI library data for the neutron cross sections. An infinite array model (with and without over pack) incorporating an internal H/U ratio of 0.088 was then developed to determine the optimal interstitial moderation. The maximum k eff value for the conditions of optimal interstitial moderation with the premise of no water leakage into the UF 6 cylinder has been shown to be 0.79209 ± 0.0011 for the 30B cylinder and 0.7625±0.0013 for 48X cylinder with 5 wt % 235 U enrichment. Based on this evaluation, the 30B and 48X UF 6 cylinders with 5 wt % 235 U enrichment meet the 10 CFR part 71 criteria for Fissile Class I packages, even in the worst case, and has a Transport Index (TI) of zero for criticality safety purposes

Interactions between CO2, saline water and minerals during geological storage of CO2

International Nuclear Information System (INIS)

Hellevang, Helge

2006-06-01

The topic of this thesis is to gain a better understanding of interactions between injected CO 2 , aqueous solutions and formation mineralogies. The main focus is concerned with the potential role mineral reactions play in safe long term storage of CO 2 . The work is divided into an experimental part concentrated on the potential of dawsonite (NaAl(OH) 2 CO 3 ) as a permanent storage host of CO 2 , and the development of a new geochemical code ACCRETE that is coupled with the ATHENA multiphase flow simulator. The thesis is composed of two parts: (I) the first part introducing CO 2 storage, geochemical interactions and related work; and (II) the second part that consists of the papers. Part I is composed as follows: Chapter 2 gives a short introduction to geochemical reactions considered important during CO 2 storage, including a thermodynamic framework. Chapter 3 presents objectives of numerical work related to CO 2 -water-rock interactions including a discussion of factors that influence the outcome of numerical simulations. Chapter 4 presents the main results from paper A to E. Chapter 5 give some details about further research that we propose based on the present work and related work in the project. Several new activities have emerged from research on CO 2 -water-rock interaction during the project. Several of the proposed activities are already initiated. Papers A to F are then listed in Part II of the thesis after the citation list. The thesis presents the first data on the reaction kinetics of dawsonite at different pH (Paper A), and comprehensive numerical simulations, both batch- and large scale 3D reactive transport, that illustrate the role different carbonates have for safe storage of CO 2 in geological formations (Papers C to F). The role of dawsonite in CO 2 storage settings is treated throughout the study (Papers A to E) After the main part of the thesis (Part I and II), two appendices are included: Appendix A lists reactions that are included in the

TEE-Based Trusted Storage

DEFF Research Database (Denmark)

Gonzalez, Javier; Bonnet, Philippe

Today, it is safe to assume that any program or data can be compromised, if they are not protected by hardware within a secure area. Systems based on crypto-processors (e.g., a trusted platform module, a smart card or a hardware security module) rely on the properties of tamper resistant hardware...... to establish a tight security parameter around a reduced set of predefined functionalities. Such systems are very secure, but they impose strong constraints on the functionalities, the connectivity or the resources available within the secure area. They have not proven versatile enough to provide mainstream...... trusted storage for personal data. We believe that this role can be taken over by systems equipped with Trusted Execution Environments (TEE), such as ARM’s TrustZone. Indeed, even if TEEs provide weaker security guarantees than crypto-processors, they already provide a secure area on many personal devices...

Technology Development for Hydrogen Propellant Storage and Transfer at the Kennedy Space Center (KSC)

Science.gov (United States)

Youngquist, Robert; Starr, Stanley; Krenn, Angela; Captain, Janine; Williams, Martha

2016-01-01

The National Aeronautics and Space Administration (NASA) is a major user of liquid hydrogen. In particular, NASA's John F. Kennedy (KSC) Space Center has operated facilities for handling and storing very large quantities of liquid hydrogen (LH2) since the early 1960s. Safe operations pose unique challenges and as a result NASA has invested in technology development to improve operational efficiency and safety. This paper reviews recent innovations including methods of leak and fire detection and aspects of large storage tank health and integrity. We also discuss the use of liquid hydrogen in space and issues we are addressing to ensure safe and efficient operations should hydrogen be used as a propellant derived from in-situ volatiles.

Study of hydrogen vehicle storage in enclosed parking facilities

Energy Technology Data Exchange (ETDEWEB)

Belzile, M A [Transport Canada, Ottawa, ON (Canada). ecoTECHNOLOGY for Vehicles; Cook, S [Canadian Hydrogen and Fuel Cell Association, Vancouver, BC (Canada)

2009-07-01

This paper reported on a coordinated research program between Transport Canada and Hydrogen and Fuel Cells Canada that examines issues of hydrogen vehicle storage. The ecoTECHNOLOGY for Vehicles (eTV) program focuses on the safety issues of operating and storing hydrogen fuelled vehicles in enclosed parking facilities. The aim of the program is to review existing research, current building standards applied in Canada, standards applied to natural gas vehicles, and standards and recommended practices for the design of fuel cell vehicles. Any potential gaps in safety will be considered in the design of CFD modeling scenarios. Considerations that extend beyond previously performed studies include the effect of Canadian climate on vehicle safety and leak detection equipment, fail-safe mechanism performance, as well as analyses of the frequency of hydrogen leak occurrences and the probability of ignition. The results of the study will facilitate policy makers and authorities in making decisions regarding the storage of hydrogen fuelled vehicles as they become more popular.

The low to intermediate activity and short living waste storage facility. For a controlled management of radioactive wastes

International Nuclear Information System (INIS)

2006-01-01

Sited at about 50 km of Troyes (France), the Aube facility started in 1992 and has taken over the Manche facility for the surface storage of low to intermediate and short living radioactive wastes. The Aube facility (named CSFMA) is the answer to the safe management of these wastes at the industrial scale and for 50 years onward. This brochure presents the facility specifications, the wastes stored at the center, the surface storage concept, the processing and conditioning of waste packages, and the environmental monitoring performed in the vicinity of the site. (J.S.)

SAFE/SNAP application to shipboard security

International Nuclear Information System (INIS)

Grady, L.M.; Walker, J.L.; Polito, J.

1981-11-01

An application of the combined Safeguards Automated Facility Evaluation/Safeguards Network Analysis Procedure (SAFE/SNAP) modeling technique to a physical protection system (PPS) aboard a generic ship is described. This application was performed as an example of how the SAFE and SNAP techniques could be used. Estimates of probability of interruption and neutralization for the example shipboard PPS are provided by SAFE as well as an adversary scenario, which serves as input to SNAP. This adversary scenario is analyzed by SNAP through four cases which incorporate increasingly detailed security force tactics. Comparisons between the results of the SAFE and SNAP analyses are made and conclusions drawn on the validity of each technique. Feedback from SNAP to SAFE is described, and recommendations for upgrading the ship based on the results of the SAFE/SNAP application are also discussed

Design Verification Report Spent Nuclear Fuel (SNF) Project Canister Storage Building (CSB)

Energy Technology Data Exchange (ETDEWEB)

BAZINET, G.D.

2001-05-15

The Sub-project W379, ''Spent Nuclear Fuel Canister Storage Building (CSB),'' was established as part of the Spent Nuclear Fuel (SNF) Project. The primary mission of the CSB is to safely store spent nuclear fuel removed from the K Basins in dry storage until such time that it can be transferred to the national geological repository at Yucca Mountain Nevada. This sub-project was initiated in late 1994 by a series of studies and conceptual designs. These studies determined that the partially constructed storage building, originally built as part of the Hanford Waste Vitrification Plant (HWVP) Project, could be redesigned to safely store the spent nuclear fuel. The scope of the CSB facility initially included a receiving station, a hot conditioning system, a storage vault, and a Multi-Canister Overpack (MCO) Handling Machine (MHM). Because of evolution of the project technical strategy, the hot conditioning system was deleted from the scope and MCO welding and sampling stations were added in its place. This report outlines the methods, procedures, and outputs developed by Project W379 to verify that the provided Structures, Systems, and Components (SSCs): satisfy the design requirements and acceptance criteria; perform their intended function; ensure that failure modes and hazards have been addressed in the design; and ensure that the SSCs as installed will not adversely impact other SSCs. The original version of this document was prepared by Vista Engineering for the SNF Project. Revision 1 documented verification actions that were pending at the time the initial report was prepared. Verification activities for the installed and operational SSCs have been completed. Verification of future additions to the CSB related to the canister cover cap and welding fixture system and MCO Internal Gas Sampling equipment will be completed as appropriate for those components. The open items related to verification of those requirements are noted in section 3

Design Verification Report Spent Nuclear Fuel (SNF) Project Canister Storage Building (CSB)

Energy Technology Data Exchange (ETDEWEB)

BAZINET, G.D.

2000-11-03

The Sub-project W379, ''Spent Nuclear Fuel Canister Storage Building (CSB),'' was established as part of the Spent Nuclear Fuel (SNF) Project. The primary mission of the CSB is to safely store spent nuclear fuel removed from the K Basins in dry storage until such time that it can be transferred to the national geological repository at Yucca Mountain Nevada. This sub-project was initiated in late 1994 by a series of studies and conceptual designs. These studies determined that the partially constructed storage building, originally built as part of the Hanford Waste Vitrification Plant (HWVP) Project, could be redesigned to safely store the spent nuclear fuel. The scope of the CSB facility initially included a receiving station, a hot conditioning system, a storage vault, and a Multi-Canister Overpack (MCO) Handling Machine (MHM). Because of evolution of the project technical strategy, the hot conditioning system was deleted from the scope and MCO welding and sampling stations were added in its place. This report outlines the methods, procedures, and outputs developed by Project W379 to verify that the provided Structures, Systems, and Components (SSCs): satisfy the design requirements and acceptance criteria; perform their intended function; ensure that failure modes and hazards have been addressed in the design; and ensure that the SSCs as installed will not adversely impact other SSCs. The original version of this document was prepared by Vista Engineering for the SNF Project. The purpose of this revision is to document completion of verification actions that were pending at the time the initial report was prepared. Verification activities for the installed and operational SSCs have been completed. Verification of future additions to the CSB related to the canister cover cap and welding fixture system and MCO Internal Gas Sampling equipment will be completed as appropriate for those components. The open items related to verification of those

Design Verification Report Spent Nuclear Fuel (SNF) Project Canister Storage Building (CSB)

International Nuclear Information System (INIS)

BAZINET, G.D.

2001-01-01

The Sub-project W379, ''Spent Nuclear Fuel Canister Storage Building (CSB),'' was established as part of the Spent Nuclear Fuel (SNF) Project. The primary mission of the CSB is to safely store spent nuclear fuel removed from the K Basins in dry storage until such time that it can be transferred to the national geological repository at Yucca Mountain Nevada. This sub-project was initiated in late 1994 by a series of studies and conceptual designs. These studies determined that the partially constructed storage building, originally built as part of the Hanford Waste Vitrification Plant (HWVP) Project, could be redesigned to safely store the spent nuclear fuel. The scope of the CSB facility initially included a receiving station, a hot conditioning system, a storage vault, and a Multi-Canister Overpack (MCO) Handling Machine (MHM). Because of evolution of the project technical strategy, the hot conditioning system was deleted from the scope and MCO welding and sampling stations were added in its place. This report outlines the methods, procedures, and outputs developed by Project W379 to verify that the provided Structures, Systems, and Components (SSCs): satisfy the design requirements and acceptance criteria; perform their intended function; ensure that failure modes and hazards have been addressed in the design; and ensure that the SSCs as installed will not adversely impact other SSCs. The original version of this document was prepared by Vista Engineering for the SNF Project. Revision 1 documented verification actions that were pending at the time the initial report was prepared. Verification activities for the installed and operational SSCs have been completed. Verification of future additions to the CSB related to the canister cover cap and welding fixture system and MCO Internal Gas Sampling equipment will be completed as appropriate for those components. The open items related to verification of those requirements are noted in section 3.1.5 and will be

Design Verification Report Spent Nuclear Fuel (SNF) Project Canister Storage Building (CSB)

International Nuclear Information System (INIS)

BAZINET, G.D.

2000-01-01

The Sub-project W379, ''Spent Nuclear Fuel Canister Storage Building (CSB),'' was established as part of the Spent Nuclear Fuel (SNF) Project. The primary mission of the CSB is to safely store spent nuclear fuel removed from the K Basins in dry storage until such time that it can be transferred to the national geological repository at Yucca Mountain Nevada. This sub-project was initiated in late 1994 by a series of studies and conceptual designs. These studies determined that the partially constructed storage building, originally built as part of the Hanford Waste Vitrification Plant (HWVP) Project, could be redesigned to safely store the spent nuclear fuel. The scope of the CSB facility initially included a receiving station, a hot conditioning system, a storage vault, and a Multi-Canister Overpack (MCO) Handling Machine (MHM). Because of evolution of the project technical strategy, the hot conditioning system was deleted from the scope and MCO welding and sampling stations were added in its place. This report outlines the methods, procedures, and outputs developed by Project W379 to verify that the provided Structures, Systems, and Components (SSCs): satisfy the design requirements and acceptance criteria; perform their intended function; ensure that failure modes and hazards have been addressed in the design; and ensure that the SSCs as installed will not adversely impact other SSCs. The original version of this document was prepared by Vista Engineering for the SNF Project. The purpose of this revision is to document completion of verification actions that were pending at the time the initial report was prepared. Verification activities for the installed and operational SSCs have been completed. Verification of future additions to the CSB related to the canister cover cap and welding fixture system and MCO Internal Gas Sampling equipment will be completed as appropriate for those components. The open items related to verification of those requirements are noted

Tank Waste Remediation System retrieval and disposal mission technical baseline summary description

International Nuclear Information System (INIS)

McLaughlin, T.J.

1998-01-01

This document is prepared in order to support the US Department of Energy's evaluation of readiness-to-proceed for the Waste Retrieval and Disposal Mission at the Hanford Site. The Waste Retrieval and Disposal Mission is one of three primary missions under the Tank Waste Remediation System (TWRS) Project. The other two include programs to characterize tank waste and to provide for safe storage of the waste while it awaits treatment and disposal. The Waste Retrieval and Disposal Mission includes the programs necessary to support tank waste retrieval, wastefeed, delivery, storage and disposal of immobilized waste, and closure of tank farms. This mission will enable the tank farms to be closed and turned over for final remediation. The Technical Baseline is defined as the set of science and engineering, equipment, facilities, materials, qualified staff, and enabling documentation needed to start up and complete the mission objectives. The primary purposes of this document are (1) to identify the important technical information and factors that should be used by contributors to the mission and (2) to serve as a basis for configuration management of the technical information and factors

CASTOR(r) and CONSTOR(r) type transport and storage casks for spent fuel and high active waste

International Nuclear Information System (INIS)

Kuehne, B.; Sowa, W.

2002-01-01

The German company GNB has developed, tested, licensed, fabricated, loaded, transported and stored a large number of casks for spent fuel and high-level waste. CASTOR(r) casks are used at 18 sites on three continents. Spent fuel assemblies of the types PWR, BWR, VVER, RBMK, MTR and THTR as well as vitrified high active waste (HAW) containers are stored in these kinds of casks. More than 600 CASTOR(r) casks have been loaded for long-term storage. The two decades of storage have shown that the basic requirements, which are safe confinement, criticality safety, sufficient shielding and appropriate heat transfer have been fulfilled in each case. There is no indication that problems will arise in the future. Of course, the experience of 20 years has resulted in improvements of the cask design. One basic improvement is GNB's development since the mid 1990s of a sandwich cask design using heavy concrete and steel as basic materials, for economical and technical reasons. This CONSTOR(r) cask concept also fulfils all design criteria for transport and storage given by the IAEA recommendations and national authorities. By May 2002 40 CONSTOR(r) casks had been delivered and 15 had been successfully loaded and stored. In this paper the different types of casks are presented. Experiences gained during the large number of cask loadings and more than 4000 cask-years of storage will be summarised. The presentation of recent and future development shows the optimisation potential of the CASTOR(r) and CONSTOR(r) cask families for safe and economical management of spent fuel. (author)

Waste and Encapsulation Storage Facility (WESF) Essential and Support Drawing List

International Nuclear Information System (INIS)

SHANNON, W.R.

1999-01-01

This supporting document provides a detailed list of the Essential and Support drawing for the Waste and Storage Encapsulation Facility. The drawings identified in this document will comprise the Waste Encapsulation and Storage Facility essential and support drawing list. This list will replace drawings identified as the ''WESF Essential and support drawing list''. Additionally, this document will follow the applicable requirements of HNF-PRO-242 Engineering Drawing Requirements'' and FSP-WESF-001, Section EN-1 ''Documenting Engineering Changes''. An essential drawing is defined as an engineering drawing identified by the facility staff as necessary to directly support the safe operation or maintenance of the facility. A support drawing is defined as a drawing identified by the facility staff that further describes the design details of structures, systems, or components shown on essential drawings or is frequently used by the support staff

Plutonium stabilization and storage research in the DNFSB 94-1 core technology program

International Nuclear Information System (INIS)

Eller, P.G.; Avens, L.R.; Roberson, G.D.

1998-04-01

Recommendation 94-1 of the Defense Nuclear Facility Safety Board (DNFSB) addresses legacy actinide materials left in the US nuclear defense program pipeline when the production mission ended in 1989. The Department of Energy (DOE) Implementation Plan responding to this recommendation instituted a Core Technology program to augment the knowledge base about general chemical and physical processing and storage behavior and to assure safe interim nuclear material storage, until disposition policies are formulated. The Core Technology program focuses on plutonium, in concert with a complex-wide applied R/D program administered by Los Alamos National Laboratory. This paper will summarize the Core Technology program's first two years, describe the research program for FY98, and project the overall direction of the program in the future

Numerical investigation of CO2 storage in hydrocarbon field using a geomechanical-fluid coupling model

Directory of Open Access Journals (Sweden)

Guang Li

2016-09-01

Full Text Available Increasing pore pressure due to CO2 injection can lead to stress and strain changes of the reservoir. One of the safely standards for long term CO2 storage is whether stress and strain changes caused by CO2 injection will lead to irreversible mechanical damages of the reservoir and impact the integrity of caprock which could lead to CO2 leakage through previously sealing structures. Leakage from storage will compromise both the storage capacity and the perceived security of the project, therefore, a successful CO2 storage project requires large volumes of CO2 to be injected into storage site in a reliable and secure manner. Yougou hydrocarbon field located in Orods basin was chosen as storage site based on it's stable geological structure and low leakage risks. In this paper, we present a fluid pressure and stress-strain variations analysis for CO2 geological storage based on a geomechanical-fluid coupling model. Using nonlinear elasticity theory to describe the geomechanical part of the model, while using the Darcy's law to describe the fluid flow. Two parts are coupled together using the poroelasticity theory. The objectives of our work were: 1 evaluation of the geomechanical response of the reservoir to different CO2 injection scenarios. 2 assessment of the potential leakage risk of the reservoir caused by CO2 injection.

Neutrino Signals in Electron-Capture Storage-Ring Experiments

Directory of Open Access Journals (Sweden)

Avraham Gal

2016-06-01

Full Text Available Neutrino signals in electron-capture decays of hydrogen-like parent ions P in storage-ring experiments at GSI are reconsidered, with special emphasis placed on the storage-ring quasi-circular motion of the daughter ions D in two-body decays P → D + ν e . It is argued that, to the extent that daughter ions are detected, these detection rates might exhibit modulations with periods of order seconds, similar to those reported in the GSI storage-ring experiments for two-body decay rates. New dedicated experiments in storage rings, or using traps, could explore these modulations.

Status analysis for the confinement monitoring technology of PWR spent nuclear fuel dry storage system

Energy Technology Data Exchange (ETDEWEB)

Baeg, Chang Yeal; Cho, Chun Hyung [Korea Radioactive Waste Agency, Daejeon (Korea, Republic of)

2016-03-15

Leading national R and D project to design a PWR spent nuclear fuel interim dry storage system that has been under development since mid-2009, which consists of a dual purpose metal cask and concrete storage cask. To ensure the safe operation of dry storage systems in foreign countries, major confinement monitoring techniques currently consist of pressure and temperature measurement. In the case of a dual purpose metal cask, a pressure sensor is installed in the interspace of bolted double lid(primary and secondary lid) in order to measure pressure. A concrete storage cask is a canister based system made of double/redundant welded lid to ensure confinement integrity. For this reason, confinement monitoring method is real time temperature measurement by thermocouple placed in the air flow(air intake and exit) of the concrete structure(over pack and module). The use of various monitoring technologies and operating experiences for the interim dry storage system over the last decades in foreign countries were analyzed. On the basis of the analysis above, development of the confinement monitoring technology that can be used optimally in our system will be available in the near future.

Gas storage materials, including hydrogen storage materials

Science.gov (United States)

Mohtadi, Rana F; Wicks, George G; Heung, Leung K; Nakamura, Kenji

2013-02-19

A material for the storage and release of gases comprises a plurality of hollow elements, each hollow element comprising a porous wall enclosing an interior cavity, the interior cavity including structures of a solid-state storage material. In particular examples, the storage material is a hydrogen storage material such as a solid state hydride. An improved method for forming such materials includes the solution diffusion of a storage material solution through a porous wall of a hollow element into an interior cavity.

Temporary Operational Protocol for making safe and managing Orphaned or Seized Radioactive Sources

International Nuclear Information System (INIS)

2013-01-01

This protocol outlines the arrangements to manage the safe interim storage of an orphaned radioactive source or of a source identified for seizure, pending its ultimate disposal. Such sources may be sources found outside of regulatory control, detected at a frontier or seized in the public interest. This includes a radioactive source arising from a CBRN, chemical, biological, radiological, nuclear, incident, following neutralisation of any associated dispersal device and confirmation of the suspect object as radioactive. The arrangements in this protocol are meant to be consistent with and used in conjunction with relevant protocols to the Major Emergency Framework Document and may be revisited as necessary as those protocols are further developed

Chernobyl new safe confinement

International Nuclear Information System (INIS)

Dodd, L.

2011-01-01

The author presents the new safe confinement that will be commissioned at Unit 4 of the Chernobyl NPP in 2015. The confinement will ensure that Chernobyl Unit 4 will be placed in an environmentally safe condition for at least next 100 years. The article highlights the current work status, future perspectives and the feasibility of confinement concept [ru

Asymptotically Safe Dark Matter

DEFF Research Database (Denmark)

Sannino, Francesco; Shoemaker, Ian M.

2015-01-01

We introduce a new paradigm for dark matter (DM) interactions in which the interaction strength is asymptotically safe. In models of this type, the coupling strength is small at low energies but increases at higher energies, and asymptotically approaches a finite constant value. The resulting...... searches are the primary ways to constrain or discover asymptotically safe dark matter....

Safe Management of natural Occurring radionuclides Materials (NORM) from Petroleum Industry in Egypt

International Nuclear Information System (INIS)

El-Hussany, B.S.

2015-01-01

The isolation of radioactive waste from the environment becomes a real problem need to solve in the last half century. Waste management system is created for safe isolation of the waste. Radioactive waste management including all activities, administrative and operational, That are involved in the handling, conditioning, transport, storage and disposal of radioactive wastes. In petroleum and gas industries there are many wastes containing natural occurring radioactive waste (NORM). The concentration of NORM is increased during the different processes. Accumulation of NORM in these areas makes hazard effects on the workers and on the environment. In Egypt, there are many oil and gas industries in different areas of the republic. Most of these exploration sites containing large amounts of NORM waste. The management of this waste is remained unclear for many companies. Some companies have storage designs for the waste. Others are stored the waste on the working site on land without barriers. Additionally final destination of these wastes is not decided. The improper management of this waste lead to hazard effects to workers in the present time and to public in the future. The present work studies the NORM waste management, from petroleum industry, in Egypt. Strategy of NORM is proposed. NORM waste management steps (system) is also proposed, Incineration and deoiling processes for the treatment of NORM waste are compered. Also in this study, human intrusion scenarios were studied for two NORM storage designs, A) above-ground and B) under-ground bunkers

Developments in the storage of embryos in France and the limitations of the laws of bioethics. Analysis of procedures in 17 storage centres and the destiny of stored embryos.

Science.gov (United States)

Moutel, Grégoire; Gregg, Edna; Meningaud, Jean Paul; Hervé, Christian

2002-01-01

storage of such embryos. The Bioethics Laws have therefore not succeeded in limiting the inflation in the number of embryos stored despite that the fact that this was one of the major concerns of those involved in formulating the laws and the medical professionals involved. Our study shows that the guidelines provided by these Laws remain ambiguous and that the objectives defined therein are thus difficult to achieve. Our study highlights the impact of such developments on the possible eventual "destiny" of such embryos, the behaviour of and the advice provided to couples, and the management practice of the storage centres involved. We present these results in the light of the laws established in 1994 in order to define not only the benefits but also the potential limitations of such legislation. No guidelines were laid down regarding the future of embryos belonging to a couple that no longer wishes to embark upon a "parental project". As a result it is not possible to terminate the conservation of such embryos which therefore remain in storage awaiting the revision of the current laws. The major objectives of our study assess the impact of the Laws and their impact on practice and to contribute to the debate which has yet to take place in the social and political arena.

Conceptual design report for the ICPP spent nuclear fuel dry storage project

Energy Technology Data Exchange (ETDEWEB)

NONE

1996-07-01

The conceptual design is presented for a facility to transfer spent nuclear fuel from shipping casks to dry storage containers, and to safely store those containers at ICPP at INEL. The spent fuels to be handled at the new facility are identified and overall design and operating criteria established. Physical configuration of the facility and the systems used to handle the SNF are described. Detailed cost estimate for design and construction of the facility is presented.

Antilisterial properties of marinades during refrigerated storage and microwave oven reheating against post-cooking inoculated chicken breast meat.

Science.gov (United States)

Fouladkhah, Aliyar; Geornaras, Ifigenia; Nychas, George-John; Sofos, John N

2013-02-01

This study evaluated growth of Listeria monocytogenes inoculated on cooked chicken meat with different marinades and survival of the pathogen as affected by microwave oven reheating. During aerobic storage at 7 °C, on days 0, 1, 2, 4, and 7, samples were reheated by microwave oven (1100 W) for 45 or 90 s and analyzed microbiologically. L. monocytogenes counts on nonmarinated (control) samples increased (P 2.4 to 5.0 (90 s) log CFU/g. With similar trends across different marinates, the high levels of L. monocytogenes survivors found after microwave reheating, especially after storage for more than 2 d, indicate that length of storage and reheating time need to be considered for safe consumption of leftover cooked chicken. © 2013 Institute of Food Technologists®

75 FR 1734 - Children’s Online Privacy Protection Rule Safe Harbor Proposed Self-Regulatory Guidelines; i-SAFE...

Science.gov (United States)

2010-01-13

... Proposed Self-Regulatory Guidelines; i-SAFE, Inc. Application for Safe Harbor AGENCY: Federal Trade... for public comment concerning proposed self-regulatory guidelines submitted by i-SAFE, Inc. under the... approval self-regulatory guidelines that would implement the Rule's protections.\\3\\ \\1\\ 64 FR 59888 (1999...

Criticality safety of low-density storage arrays

International Nuclear Information System (INIS)

Bauer, T.H.

1996-01-01

This note proposes a straightforward and simple method for the criticality safety analysis of fissionable materials configured into large arrays of standard containers. While criticality-safe storage limits have been well-established for standard containers--even under flooded conditions, it is also necessary to rule out the potential for criticality arising from neutronic interactions among multiple containers that might build up over long distances in a large array. Traditionally, the array problem has been approached by individual Monte Carlo analyses of explicit arrangements of single units and their surroundings. Here, the authors show how multiple Monte Carlo analyses can be usefully combined for wide-ranging general application. The technique takes advantage of low average density of fissionable material in typical storage arrays to separate neutron interactions that take place in the neutron's ''birth unit'' from subsequent interactions in a highly dilute array. Effects of array size, in particular, are conservatively calculated by straightforward analyses which simply smear array contents uniformly across the extent of the array. For given unit loadings in standard containers, practical expressions for neutron multiplication depend only on overall array shape, size and reflective boundary

Safeness of radiological machinery

International Nuclear Information System (INIS)

Yokoyama, Shun

1979-01-01

The human factors affecting the safeness of radiological machinery, which are often very big and complicated machines, are described from the stand point of handling. 20 to 50% of the troubles on equipments seem to be caused by men. This percentage will become even higher in highly developed equipments. Human factors have a great influence on the safeness of radiological equipments. As the human factors, there are sensory factors and knowledge factors as well as psychological factors, and the combination of these factors causes mishandling and danger. Medical services at present are divided in various areas, and consist of the teamwork of the people in various professions. Good human relationship, education and control are highly required to secure the safeness. (Kobatake, H.)

Final safety analysis report for the irradiated fuels storage facility

International Nuclear Information System (INIS)

Bingham, G.E.; Evans, T.K.

1976-01-01

A fuel storage facility has been constructed at the Idaho Chemical Processing Plant to provide safe storage for spent fuel from two commercial HTGR's, Fort St. Vrain and Peach Bottom, and from the Rover nuclear rocket program. The new facility was built as an addition to the existing fuel storage basin building to make maximum use of existing facilities and equipment. The completed facility provides dry storage for one core of Peach Bottom fuel (804 elements), 1 1 / 2 cores of Fort St. Vrain fuel (2200 elements), and the irradiated fuel from the 20 reactors in the Rover program. The facility is designed to permit future expansion at a minimum cost should additional storage space for graphite-type fuels be required. A thorough study of the potential hazards associated with the Irradiated Fuels Storage Facility has been completed, indicating that the facility is capable of withstanding all credible combinations of internal accidents and pertinent natural forces, including design basis natural phenomena of a 10,000 year flood, a 175-mph tornado, or an earthquake having a bedrock acceleration of 0.33 g and an amplification factor of 1.3, without a loss of integrity or a significant release of radioactive materials. The design basis accident (DBA) postulated for the facility is a complete loss of cooling air, even though the occurrence of this situation is extremely remote, considering the availability of backup and spare fans and emergency power. The occurrence of the DBA presents neither a radiation nor an activity release hazard. A loss of coolant has no effect upon the fuel or the facility other than resulting in a gradual and constant temperature increase of the stored fuel. The temperature increase is gradual enough that ample time (28 hours minimum) is available for corrective action before an arbitrarily imposed maximum fuel centerline temperature of 1100 0 F is reached

Spent fuel storage choices: What public opinion polls tell us

International Nuclear Information System (INIS)

Bisconti, A.S.

1995-01-01

The crux of the issue of spent nuclear fuel for much of the American public is that taking car of our waste now instead of leaving it for future generations is the safe and environmentally responsible think to do. This article summarizes a number of public opinion surveys. Although it is important to recognize that most people are not familiar with specifics, much of the American public has a strong opinions about the fundamental guiding principles for safely managing radioactive waste. First there is clear agreement that we need action. Second, safety means taking the waste to a permanent disposal facility instead of leaving it in many different locations. Third, most of the public would like to keep nuclear energy as a supply option. Fourth, the majority of the public agreed with the statement that the availability of nuclear energy as an option for future energy supply depends on building a national waste storage or disposal facility

The Assured Storage Integrated Management System: What is it and what will it cost?

International Nuclear Information System (INIS)

Kerr, T.A.; Newberry, W.F.

1996-01-01

The Assured Storage Integrated Management System for low-level radioactive waste as an alternative to traditional disposal is attracting favorable attention from many states, regulators, processors, and low-level radioactive waste generators. open-quotes Assured storageclose quotes is defined as a management system for safely isolating waste, while preserving options for its long-term management, through: robust, accessible facilities; planned preventive maintenance; and sureties adequate to address contingencies or implement future alternatives. Following introduction of the concept in RADWASTE Magazine, the Connecticut Hazardous Waste Management Service (among several others) requested a briefing on the idea. The Connecticut Hazardous Waste Management Service then requested that the National Low-Level Waste Management Program at the Idaho National Engineering Laboratory evaluate the life cycle costs of the Assured Storage Integrated Management System versus traditional disposal. Building on some of that work, this paper discusses the concept of an Assured Storage Integrated Management System for low-level radioactive waste as well as examines cost elements of the Assured Storage Integrated Management System in comparison to traditional disposal facilities. Further analyses conducted for the Connecticut study will more clearly define and quantify potential differences in life-cycle costs between the Assured Storage Integrated Management System and traditional disposal

Soil moisture storage and hillslope stability

Directory of Open Access Journals (Sweden)

A. Talebi

2007-09-01

slip surfaces with the minimum safety factor near the outlet region. In general, when plan shape changes from divergent to convergent, stability decreases for all length profiles. Finally, we show that the applied slope stability methods and steady-state hydrology model based on the relative saturated storage can be used safely to investigate the relation between hillslope geometry and hillslope stability.

Serial changes in plasma K concentration during storage of irradiation blood products

International Nuclear Information System (INIS)

Togashi, Kazue; Yamada, Keiko; Otake, Sachiko; Saito, Yukiko; Sugimura, Kazuhito; Takahashi, Hoyu

1996-01-01

Irradiation of blood products is highly effective in the prevention of transfusion-associated graft-versus-host disease (GVHD). In order to assess the safe storage period of irradiated blood products, serial changes in plasma K, red cell 2,3-diphosphoglycerate (2,3-DPG) and lactic acid concentrations of whole blood and M·A·P-added red cell concentrate (RC-M·A·P) during storage at 5degC were measured after irradiation with 137 Cs by IBL 437C (CIS bio international). Plasma K concentration did not change immediately after irradiation, but increased more rapidly and in a radiation dose-dependent manner in the irradiated products than nonirradiated products. The changes in red cell 2,3-DPG and lactic acid concentrations were not affected by irradiation but were rather dependent on the storage period after blood collection. Plasma K concentrations of whole blood and RC-M·A·P irradiated with 25 Gy increased at 5 and 3 days, respectively, to the K levels observed after the storage of nonirradiated products for 21 days. It is therefore recommended that whole blood be used within 5 days and RC-M·A·P within 3 days when stored after irradiation with 25 Gy. (author)

PC-Cluster based Storage System Architecture for Cloud Storage

OpenAIRE

Yee, Tin Tin; Naing, Thinn Thu

2011-01-01

Design and architecture of cloud storage system plays a vital role in cloud computing infrastructure in order to improve the storage capacity as well as cost effectiveness. Usually cloud storage system provides users to efficient storage space with elasticity feature. One of the challenges of cloud storage system is difficult to balance the providing huge elastic capacity of storage and investment of expensive cost for it. In order to solve this issue in the cloud storage infrastructure, low ...

Safe management of smoke detectors containing radioactive sources

International Nuclear Information System (INIS)

Salgado, M.; Benitez, J.C.; Castillo, R.A.; Berdellans, A.; Hernandez, J.M.; Pirez, C.J.; Soto, P.G.

2013-01-01

Ionic smoke detectors contain radioactive sources that could be Am-241, Pu-238, Pu-239, Kr-85, etc. According to Cuban regulations (Resolution 96 /2003 of the Minister of Science Technology and Environment), smoke detectors, once become disused, should be managed as radioactive waste. For this reason, disused smoke detectors should be transferred to the Centre for Radiation Protection and Hygiene, the organization responsible for radioactive waste management in the country. More than 20 000 smoke detectors have been collected by the CPHR and stored at the Centralized Waste Management Facility. There are 28 different models of smoke detectors of different origin. They contain between 18 - 37 kBq of Am-241 or between 0.37 - 37 MBq of Plutonium or around 37 MBq of Kr-85. The safe management of ionic smoke detectors consists in dismantling the devices, recovering the radioactive sources and conditioning them for long term storage and disposal. The rest of non-radioactive materials should be segregated (plastic, metal and electronic components) for recycling. A technical manual was developed with specific instructions for dismantling each model of smoke detector and recovering the radioactive sources. Instructions for segregation of non-radioactive components are also included in the manual. Most of smoke detectors contain long lived radioactive sources (Am-241, Pu-238, Pu-239), so especial attention was given to the management of these sources. A methodology was developed for conditioning of radioactive sources, consisting in encapsulating them for long term storage. The retrievability of the sources (sealed capsules with radioactive sources) for future disposal was also considered. A documented procedure was elaborated for these operations. (author)

Predicting the concentration of verotoxin-producing Escherichia coli bacteria during processing and storage of fermented raw-meat sausages.

Science.gov (United States)

Quinto, E J; Arinder, P; Axelsson, L; Heir, E; Holck, A; Lindqvist, R; Lindblad, M; Andreou, P; Lauzon, H L; Marteinsson, V Þ; Pin, C

2014-05-01

A model to predict the population density of verotoxigenic Escherichia coli (VTEC) throughout the elaboration and storage of fermented raw-meat sausages (FRMS) was developed. Probabilistic and kinetic measurement data sets collected from publicly available resources were completed with new measurements when required and used to quantify the dependence of VTEC growth and inactivation on the temperature, pH, water activity (aw), and concentration of lactic acid. Predictions were compared with observations in VTEC-contaminated FRMS manufactured in a pilot plant. Slight differences in the reduction of VTEC were predicted according to the fermentation temperature, 24 or 34°C, with greater inactivation at the highest temperature. The greatest reduction was observed during storage at high temperatures. A population decrease greater than 6 decimal logarithmic units was observed after 66 days of storage at 25°C, while a reduction of only ca. 1 logarithmic unit was detected at 12°C. The performance of our model and other modeling approaches was evaluated throughout the processing of dry and semidry FRMS. The greatest inactivation of VTEC was predicted in dry FRMS with long drying periods, while the smallest reduction was predicted in semidry FMRS with short drying periods. The model is implemented in a computing tool, E. coli SafeFerment (EcSF), freely available from http://www.ifr.ac.uk/safety/EcoliSafeFerment. EcSF integrates growth, probability of growth, and thermal and nonthermal inactivation models to predict the VTEC concentration throughout FRMS manufacturing and storage under constant or fluctuating environmental conditions.

SOLID-STATE STORAGE DEVICE WITH PROGRAMMABLE PHYSICAL STORAGE ACCESS

DEFF Research Database (Denmark)

2017-01-01

a storage device action request, and the storage device evaluating a first rule of the one or more rules by determining if the received request fulfills request conditions comprised in the first rule, and in the affirmative the storage device performing request actions comprised in the first rule......Embodiments of the present invention includes a method of operating a solid-state storage device, comprising a storage device controller in the storage device receiving a set of one or more rules, each rule comprising (i) one or more request conditions to be evaluated for a storage device action...... request received from a host computer, and (ii) one or more request actions to be performed on a physical address space of a non-volatile storage unit in the solid-state storage device in case the one or more request conditions are fulfilled; the method further comprises: the storage device receiving...

Association of Fatigue with Perceived Stress in Chinese Women with Early Stage Breast Cancer Awaiting Adjuvant Radiotherapy.

Science.gov (United States)

Ho, Rainbow T H; Kwan, Tracy T C; Cheung, Irene K M; Chan, Caitlin K P; Lo, Phyllis H Y; Yip, Paul S F; Luk, Mai-Yee; Chan, Cecilia L W

2015-08-01

Cancer-related fatigue (CRF) is common in women with breast cancer, but little is known of its relationship with perceived stress. We conducted a cross-sectional study to explore the associations of CRF with perceived stress, anxiety, depression, pain and sleep quality in 133 Chinese women (aged 25-68 years) with early stage breast cancer. The majority of women had completed surgery and chemotherapy and were awaiting radiotherapy. Self-administered questionnaires consisting of the Brief Fatigue Inventory, Perceived Stress Scale-10, Hospital Anxiety and Depression Scale, Brief Pain Inventory, and Pittsburgh Sleep Quality Index were used to collect data. Forty-five per cent of the women were severely fatigued. Compared with local healthy women and US breast cancer patients, the group's mean perceived stress score was significantly higher (both p stress (β = 0.18, p = 0.032), higher anxiety (β = 0.30, p stress was partially mediated by anxiety, suggesting a possible pathway from cancer and cancer treatment to CRF via stress appraisals and emotional distress. The findings indicate the importance of monitoring the psychological status of patients during treatment. Copyright © 2013 John Wiley & Sons, Ltd.

Well technologies for CO2 geological storage: CO2-resistant cement

International Nuclear Information System (INIS)

Barlet-Gouedard, V.; Rimmele, G.; Porcherie, O.; Goffe, B.

2007-01-01

Storing carbon dioxide (CO 2 ) underground is considered the most effective way for long-term safe and low-cost CO 2 sequestration. This recent application requires long-term well-bore integrity. A CO 2 leakage through the annulus may occur much more rapidly than geologic leakage through the formation rock, leading to economic loss, reduction of CO 2 storage efficiency, and potential compromise of the field for storage. The possibility of such leaks raises considerable concern about the long-term well-bore isolation and the durability of hydrated cement that is used to isolate the annulus across the producing/injection intervals in CO 2 -storage wells. We propose a new experimental procedure and methodology to study reactivity of CO 2 -Water-Cement systems in simulating the interaction of the set cement with injected supercritical CO 2 under downhole conditions. The conditions of experiments are 90 deg. C under 280 bars. The evolution of mechanical, physical and chemical properties of Portland cement with time is studied up to 6 months. The results are compared to equivalent studies on a new CO 2 -resistant material; the comparison shows significant promise for this new material. (authors)

Interim Storage of Spent Nuclear Fuel before Final Disposal in Germany - Regulator's view

International Nuclear Information System (INIS)

Arens, G.; Goetz, Ch.; Geupel, Sandra; Gmal, B.; Mester, W.

2014-01-01

For spent nuclear fuel management in Germany the concept of dry interim storage in dual purpose casks before direct disposal is applied. The Federal Office for Radiation Protection (BfS) is the competent authority for licensing of interim storage facilities. The competent authority for surveillance of operation is the responsible authority of the respective federal state (Land). Currently operation licenses for storage facilities have been granted for a storage time of 40 years and are based on safety demonstrations for all safety issues as safe enclosure, shielding, sub-criticality and decay heat removal under consideration of operation conditions. In addition, transportability of the casks for the whole storage period has to be provided. Due to current delay in site selection and exploration of a disposal site, an extension of the storage time beyond 40 years could be needed. This will cause appropriate actions by the licensee and the competent authorities as well. A brief description of the regulatory base of licensing and surveillance of interim storage is given from the regulators view. Furthermore the current planning for final disposal of spent nuclear fuel and high level waste and its interconnections between storage and disposal concepts are shortly explained. Finally the relevant aspects for licensing of extended storage time beyond 40 years will be discussed. Current activities on this issue, which have been initiated by the Federal Government, will be addressed. On the regulatory side a review and amendment of the safety guideline for interim storage of spent fuel has been performed and the procedure of periodic safety review is being implemented. A guideline for implementing an ageing management programme is available in a draft version. Regarding safety of long term storage a study focussing on the identification and evaluation of long term effects as well as gaps of knowledge has been finished in 2010. A continuation and update is currently underway

Safe Cooperating Cyber-Physical Systems using Wireless Communication

DEFF Research Database (Denmark)

Pop, Paul; Scholle, Detlef; Sljivo, Irfan

2017-01-01

This paper presents an overview of the ECSEL project entitled ―Safe Cooperating Cyber-Physical Systems using Wireless Communication‖ (SafeCOP), which runs during the period 2016–2019. SafeCOP targets safety-related Cooperating Cyber-Physical Systems (CO-CPS) characterised by use of wireless...... detection of abnormal behaviour, triggering if needed a safe degraded mode. SafeCOP will also develop methods and tools, which will be used to produce safety assurance evidence needed to certify cooperative functions. SafeCOP will extend current wireless technologies to ensure safe and secure cooperation...

High Efficiency and Low Cost Thermal Energy Storage System

Energy Technology Data Exchange (ETDEWEB)

Sienicki, James J. [Argonne National Lab. (ANL), Argonne, IL (United States). Nuclear Engineering Division; Lv, Qiuping [Argonne National Lab. (ANL), Argonne, IL (United States). Nuclear Engineering Division; Moisseytsev, Anton [Argonne National Lab. (ANL), Argonne, IL (United States). Nuclear Engineering Division; Bucknor, Matthew [Argonne National Lab. (ANL), Argonne, IL (United States). Nuclear Engineering Division

2017-09-29

BgtL, LLC (BgtL) is focused on developing and commercializing its proprietary compact technology for processes in the energy sector. One such application is a compact high efficiency Thermal Energy Storage (TES) system that utilizes the heat of fusion through phase change between solid and liquid to store and release energy at high temperatures and incorporate state-of-the-art insulation to minimize heat dissipation. BgtL’s TES system would greatly improve the economics of existing nuclear and coal-fired power plants by allowing the power plant to store energy when power prices are low and sell power into the grid when prices are high. Compared to existing battery storage technology, BgtL’s novel thermal energy storage solution can be significantly less costly to acquire and maintain, does not have any waste or environmental emissions, and does not deteriorate over time; it can keep constant efficiency and operates cleanly and safely. BgtL’s engineers are experienced in this field and are able to design and engineer such a system to a specific power plant’s requirements. BgtL also has a strong manufacturing partner to fabricate the system such that it qualifies for an ASME code stamp. BgtL’s vision is to be the leading provider of compact systems for various applications including energy storage. BgtL requests that all technical information about the TES designs be protected as proprietary information. To honor that request, only non-proprietay summaries are included in this report.

High temperature electrical energy storage: advances, challenges, and frontiers.

Science.gov (United States)

Lin, Xinrong; Salari, Maryam; Arava, Leela Mohana Reddy; Ajayan, Pulickel M; Grinstaff, Mark W

2016-10-24

With the ongoing global effort to reduce greenhouse gas emission and dependence on oil, electrical energy storage (EES) devices such as Li-ion batteries and supercapacitors have become ubiquitous. Today, EES devices are entering the broader energy use arena and playing key roles in energy storage, transfer, and delivery within, for example, electric vehicles, large-scale grid storage, and sensors located in harsh environmental conditions, where performance at temperatures greater than 25 °C are required. The safety and high temperature durability are as critical or more so than other essential characteristics (e.g., capacity, energy and power density) for safe power output and long lifespan. Consequently, significant efforts are underway to design, fabricate, and evaluate EES devices along with characterization of device performance limitations such as thermal runaway and aging. Energy storage under extreme conditions is limited by the material properties of electrolytes, electrodes, and their synergetic interactions, and thus significant opportunities exist for chemical advancements and technological improvements. In this review, we present a comprehensive analysis of different applications associated with high temperature use (40-200 °C), recent advances in the development of reformulated or novel materials (including ionic liquids, solid polymer electrolytes, ceramics, and Si, LiFePO 4 , and LiMn 2 O 4 electrodes) with high thermal stability, and their demonstrative use in EES devices. Finally, we present a critical overview of the limitations of current high temperature systems and evaluate the future outlook of high temperature batteries with well-controlled safety, high energy/power density, and operation over a wide temperature range.

Processing and storage of blood components: strategies to improve patient safety

Directory of Open Access Journals (Sweden)

Pietersz RNI

2015-08-01

Full Text Available Ruby NI Pietersz, Pieter F van der Meer Department of Product and Process Development, Sanquin Blood Bank, Amsterdam, the Netherlands Abstract: This review focuses on safety improvements of blood processing of various blood components and their respective storage. A solid quality system to ensure safe and effective blood components that are traceable from a donor to the patient is the foundation of a safe blood supply. To stimulate and guide this process, National Health Authorities should develop guidelines for blood transfusion, including establishment of a quality system. Blood component therapy enabled treatment of patients with blood constituents that were missing, only thus preventing reactions to unnecessarily transfused elements. Leukoreduction prevents many adverse reactions and also improves the quality of the blood components during storage. The safety of red cells and platelets is improved by replacement of plasma with preservative solutions, which results in the reduction of isoantibodies and plasma proteins. Automation of blood collection, separation of whole blood into components, and consecutive processing steps, such as preparation of platelet concentrate from multiple donations, improves the consistent composition of blood components. Physicians can better prescribe the number of transfusions and therewith reduce donor exposure and/or the risk of pathogen transmission. Pathogen reduction in cellular blood components is the latest development in improving the safety of blood transfusions for patients. Keywords: blood components, red cell concentrates, platelet concentrates, plasma, transfusion, safety 

Liquefied natural gas (LNG) : production, storage and handling. 7. ed.

Energy Technology Data Exchange (ETDEWEB)

Kalra, S; Jaron, K; Adragna, M; Coyle, S; Foley, C; Hawryn, S; Martin, A; McConnell, J [eds.

2003-07-01

This Canadian Standard on the production, storage and handling of liquefied natural gas (LNG) was prepared by the Technical Committee on Liquefied Natural Gas under the jurisdiction of the Steering Committee on Oil and Gas Industry Systems and Materials. It establishes the necessary requirements for the design, installation and safe operation of LNG facilities. The Standard applies to the design, location, construction, operation and maintenance of facilities at any location of the liquefaction of natural gas and for the storage, vaporization, transfer, handling and truck transport of LNG. The training of personnel involved is also included as well as containers for LNG storage, including insulated vacuum systems. It includes non-mandatory guidelines for small LNG facilities but does not apply to the transportation of refrigerants, LNG by rail, marine vessel or pipeline. This latest edition contains changes in working of seismic design requirements and minor editorial changes to several clauses to bring the Standard closer to the US National Fire Protection Association's Committee on Liquefied Natural Gas Standard while maintaining Canadian regulatory requirements. The document is divided into 12 sections including: general requirements; plant site provisions; process equipment; stationary LNG storage containers; vaporization facilities; piping system and components; instrumentation and electrical services; transfer of LNG and refrigerants; fire protection, safety and security; and, operating, maintenance and personnel training. This Standard, like all Canadian Standards, was subject to periodic review and was most recently reaffirmed in 2003. 6 tabs., 6 figs., 3 apps.

InaSAFE applications in disaster preparedness

Science.gov (United States)

Pranantyo, Ignatius Ryan; Fadmastuti, Mahardika; Chandra, Fredy

2015-04-01

Disaster preparedness activities aim to reduce the impact of disasters by being better prepared to respond when a disaster occurs. In order to better anticipate requirements during a disaster, contingency planning activities can be undertaken prior to a disaster based on a realistic disaster scenario. InaSAFE is a tool that can inform this process. InaSAFE is a free and open source software that estimates the impact to people and infrastructure from potential hazard scenarios. By using InaSAFE, disaster managers can develop scenarios of disaster impacts (people and infrastructures affected) to inform their contingency plan and emergency response operation plan. While InaSAFE provides the software framework exposure data and hazard data are needed as inputs to run this software. Then InaSAFE can be used to forecast the impact of the hazard scenario to the exposure data. InaSAFE outputs include estimates of the number of people, buildings and roads are affected, list of minimum needs (rice and clean water), and response checklist. InaSAFE is developed by Indonesia's National Disaster Management Agency (BNPB) and the Australian Government, through the Australia-Indonesia Facility for Disaster Reduction (AIFDR), in partnership with the World Bank - Global Facility for Disaster Reduction and Recovery (GFDRR). This software has been used in many parts of Indonesia, including Padang, Maumere, Jakarta, and Slamet Mountain for emergency response and contingency planning.

Carbon Capture and Storage Legal and Regulatory Review. Edition 3

Energy Technology Data Exchange (ETDEWEB)

NONE

2012-07-01

The International Energy Agency (IEA) considers carbon capture and storage (CCS) a crucial part of worldwide efforts to limit global warming by reducing greenhouse-gas emissions. The IEA estimates that emissions can be reduced to a level consistent with a 2°C global temperature increase through the broad deployment of low-carbon energy technologies – and that CCS would contribute about one-fifth of emission reductions in this scenario. Achieving this level of deployment will require that regulatory frameworks – or rather a lack thereof – do not unnecessarily impede environmentally safe demonstration and deployment of CCS, so in October 2010 the IEA launched the IEA Carbon Capture and Storage Legal and Regulatory Review. The CCS Review is a regular review of CCS regulatory progress worldwide. Produced annually, it collates contributions by national and regional governments, as well as leading organisations engaged in CCS regulatory activities, to provide a knowledge-sharing forum to support CCS framework development. Each two page contribution provides a short summary of recent and anticipated CCS regulatory developments and highlights a particular, pre-nominated regulatory theme. To introduce each edition, the IEA provides a brief analysis of key advances and trends, based on the contributions submitted. The theme for this third edition is stakeholder engagement in the development of CO2 storage projects. Other issues addressed include: regulating CO2-EOR, CCS and CO2-EOR for storage; CCS incentive policy; key, substantive issues being addressed by jurisdictions taking steps to finalise CCS regulatory framework development; and CCS legal and regulatory developments in the context of the Clean Energy Ministerial Carbon Capture, Use and Storage Action Group.

Effect of gamma irradiation on the lipid peroxidation in chicken, lamb and buffalo meat during chilled storage

International Nuclear Information System (INIS)

Kanatt, S.R.; Paul, P.; D'Souza, S.F.; Thomas, P.

1997-01-01

Chicken, lamb and buffalo meat were subjected to low-dose gamma irradiation (2.5 kGy) and stored at 0-3C. Lipid peroxidation in terms of thiobarbituric acid (TBA) number and carbonyl content were monitored during storage. While irradiated meat showed slight increase in TBA number and carbonyl content on storage as compared to nonirradiated meat, this did not affect the sensory qualities of meat. Free fatty acid content decreased markedly on irradiation. Irradiated meats were microbiologically safe and sensorily acceptable up to 4 weeks in the nonfrozen state (0-3C) while nonirradiated meat had a shelf-life of less than 2 weeks

Synthesis of polyetherimide / halloysite nanotubes (PEI/HNTs) based nanocomposite membrane towards hydrogen storage

Science.gov (United States)

Muthu, R. Naresh; Rajashabala, S.; Kannan, R.

2018-04-01

Even though hydrogen is considered as green and clean energy sources of future, the blooming of hydrogen economy mainly relies on the development of safe and efficient hydrogen storage medium. The present work is aimed at the synthesis and characterization of polyetherimide/acid treated halloysite nanotubes (PEI/A-HNTs) nanocomposite membranes for solid state hydrogen storage medium, where phase inversion technique was adopted for the synthesis of nanocomposite membrane. The synthesized PEI/A-HNTs nanocomposite membranes were characterized by XRD, FTIR, SEM, EDX, CHNS elemental analysis and TGA. Hydrogenation studies were performed using a Sievert's-like hydrogenation setup. The important conclusions arrived from the present work are the PEI/A-HNTs nanocomposite membranes have better performance with a maximum hydrogen storage capacity of 3.6 wt% at 100 °C than pristine PEI. The adsorbed hydrogen possesses the average binding energy of 0.31 eV which lies in the recommended range of US- DOE 2020 targets. Hence it is expected that the PEI/A-HNTs nanocomposite membranes may have bright extent in the scenario of hydrogen fuel cell applications.

Conceptual design report: Nuclear materials storage facility renovation. Part 6, Alternatives study

International Nuclear Information System (INIS)

1995-01-01

The Nuclear Materials Storage Facility (NMSF) at the Los Alamos National Laboratory (LANL) was a Fiscal Year (FY) 1984 line-item project completed in 1987 that has never been operated because of major design and construction deficiencies. This renovation project, which will correct those deficiencies and allow operation of the facility, is proposed as an FY 97 line item. The mission of the project is to provide centralized intermediate and long-term storage of special nuclear materials (SNM) associated with defined LANL programmatic missions and to establish a centralized SNM shipping and receiving location for Technical Area (TA)-55 at LANL. Based on current projections, existing storage space for SNM at other locations at LANL will be loaded to capacity by approximately 2002. This will adversely affect LANUs ability to meet its mission requirements in the future. The affected missions include LANL's weapons research, development, and testing (WRD ampersand T) program; special materials recovery; stockpile survelliance/evaluation; advanced fuels and heat sources development and production; and safe, secure storage of existing nuclear materials inventories. The problem is further exacerbated by LANL's inability to ship any materials offsite because of the lack of receiver sites for material and regulatory issues. Correction of the current deficiencies and enhancement of the facility will provide centralized storage close to a nuclear materials processing facility. The project will enable long-term, cost-effective storage in a secure environment with reduced radiation exposure to workers, and eliminate potential exposures to the public. This report is organized according to the sections and subsections outlined by Attachment 111-2 of DOE Document AL 4700.1, Project Management System. It is organized into seven parts. This document, Part VI - Alternatives Study, presents a study of the different storage/containment options considered for NMSF

Microbiological aspects of storage of irradiated potatoes and wheat

International Nuclear Information System (INIS)

Nadkarni, G.B.

1978-01-01

Radiation provides an effective means for extending the post-harvest storage life of perishable foods. Based on extensive studies over the past two decades in India and abroad, WHO have recently recognised potatoes and wheat as 'unconditionally' safe for human consumption alongwith several other items of food. In potatoes exposed to 10 Krad of gamma-irradiation, sprouting and tuber moth infestation were completely eliminated, irrespective of the storage temperature. The ambient temperatures could not however control the microbial rotting of the tubers. Microbiological studies have indicated that spoilage at temperatures above 15 0 C are due to Erwinia spp. while dry rotting below 10 0 C could be attributed to Micrococcus spp. The tubers were not amenable to fungal attack by organisms of Aspergillus spp. during storage due to phenolic compounds which were otherwise labile to heating. The studies with artificial loading of wheat with conidia of Aspergillus flavus showed a correlation between growth and relative humidity (RH) which determined the moisture content in the grain. Aflatoxin production could occur only above a critical level (13%) of grain moisture at RH value over 90% at 28 0 +- 2 0 C. The toxin produced in irradiated grains seemed to be lower than in the unirradiated controls, indicating that radiation treatment did not cause any alterations in wheat which could otherwise promote aflatoxin producing potential. (author)

Microbiological aspects of storage of irradiated potatoes and wheat

Energy Technology Data Exchange (ETDEWEB)

Nadkarni, G B [Bhabha Atomic Research Centre, Bombay (India). Biochemistry and Food Technology Div.

1978-09-01

Radiation provides an effective means for extending the post-harvest storage life of perishable foods. Based on extensive studies over the past two decades in India and abroad, WHO have recently recognised potatoes and wheat as 'unconditionally' safe for human consumption alongwith several other items of food. In potatoes exposed to 10 Krad of gamma-irradiation, sprouting and tuber moth infestation were completely eliminated, irrespective of the storage temperature. The ambient temperatures could not however control the microbial rotting of the tubers. Microbiological studies have indicated that spoilage at temperatures above 15/sup 0/C are due to Erwinia spp. while dry rotting below 10/sup 0/C could be attributed to Micrococcus spp. The tubers were not amenable to fungal attack by organisms of Aspergillus spp. during storage due to phenolic compounds which were otherwise labile to heating. The studies with artificial loading of wheat with conidia of Aspergillus flavus showed a correlation between growth and relative humidity (RH) which determined the moisture content in the grain. Aflatoxin production could occur only above a critical level (13%) of grain moisture at RH value over 90% at 28/sup 0/ +- 2/sup 0/C. The toxin produced in irradiated grains seemed to be lower than in the unirradiated controls, indicating that radiation treatment did not cause any alterations in wheat which could otherwise promote aflatoxin producing potential.

Fabrication and operational experience with the interim storage cask

International Nuclear Information System (INIS)

Scott, P.L.

1998-01-01

This paper discusses the fabrication and operational experience of the Interim Storage Cask (ISC). The ISC is a dry storage cask which is used to safely store a Core Component Container (CCC) containing up to seven Fast Flux Test Facility (FFTF) spent fuel assemblies at the US Department of Energy's Hanford Site. Under contract to B and W Hanford Company (BWHC), General Atomics (GA) designed and fabricated thirty ISC casks which BWHC is remotely loading at the FFTF facility. BWHC designed and fabricated the CCCS. As of December 1997, thirty ISCs have been fabricated, of which eighteen have been loaded and moved to a storage site adjacent to the FFTF facility. Fabrication consisted of three sets of casks. The first unit was completed and acceptance tested before any other units were fabricated. After the first unit passed all acceptance tests, nine more units were fabricated in the first production run. Before those nine units were completed, GA began a production run of twenty more units. The paper provides an overview of the cask design and discusses the problems encountered in fabrication, their resolution, and changes made in the fabrication processes to improve the quality of the casks. The paper also discusses the loading process and operational experiences with loading and handling of the casks. Information on loading times, worker dose exposure, and total dose for loading are presented

Safe affordable fission engine (SAFE 30) module conductivity test thermal model correlation

International Nuclear Information System (INIS)

Roman, Jose

2001-01-01

The SAFE 30 is a simple, robust space fission power system that is comprised of several independent modules. Each module contains 4 fuel tubes bonded to a central heatpipe. Fission energy is conducted from the fuel tubes to the heatpipe, which in turn transfers the energy to a power conversion system. This paper benchmarks a thermal model of the SAFE 30 with actual test data from simulated SAFE 30 module tests. Two 'dummy' SAFE 30 modules were fabricated - each consisted of 4 1-inch dia. tubes (simulating the fuel tubes) bonded to a central '1' dia. tube (simulating the heatpipe). In the first module the fuel tubes were simply brazed to the heatpipe along the line of contact (leaving void space in the interstices), and in the second module the tubes and heatpipe were brazed via tri-cusps that completely fill the interstices between the tubes. In these tests, fission energy is simulated by placing resistance heaters within each of the 4 fuel tubes. The tests were conducted in a vacuum chamber in 4 configurations: tri-cusps filled with and without an outer insulation wrap, and no tri-cusps with and without an outer insulation wrap. The baseline SAFE 30 configuration uses the brazed tri-cusps. During the tests, the power applied to the heaters was varied in a stepwise fashion, until a steady-state temperature profile was reached. These temperature levels varied between 773 K and 1073 K. To benchmark the thermal model, the input energy and chamber surface temperature were used as boundary conditions for the model. The analytical results from the nodes at the same location as the test thermocouples were plotted again test data to determinate the accuracy of the analysis. The unknown variables on the analysis are the radiation emissivity of the pipe and chamber and the radiation view factor between the module and the chamber. A correlation was determined using a parametric analysis by varying the surface emissivity and view factor until a good match was reached. This

Energy storage

Science.gov (United States)

Kaier, U.

1981-04-01

Developments in the area of energy storage are characterized, with respect to theory and laboratory, by an emergence of novel concepts and technologies for storing electric energy and heat. However, there are no new commercial devices on the market. New storage batteries as basis for a wider introduction of electric cars, and latent heat storage devices, as an aid for solar technology applications, with satisfactory performance standards are not yet commercially available. Devices for the intermediate storage of electric energy for solar electric-energy systems, and for satisfying peak-load current demands in the case of public utility companies are considered. In spite of many promising novel developments, there is yet no practical alternative to the lead-acid storage battery. Attention is given to central heat storage for systems transporting heat energy, small-scale heat storage installations, and large-scale technical energy-storage systems.

Steering teens safe: a randomized trial of a parent-based intervention to improve safe teen driving.

Science.gov (United States)

Peek-Asa, Corinne; Cavanaugh, Joseph E; Yang, Jingzhen; Chande, Vidya; Young, Tracy; Ramirez, Marizen

2014-07-31

Crashes are the leading cause of death for teens, and parent-based interventions are a promising approach. We assess the effectiveness of Steering Teens Safe, a parent-focused program to increase safe teen driving. Steering Teens Safe aimed to improve parental communication with teens about safe driving using motivational interviewing techniques in conjunction with 19 safe driving lessons. A randomized controlled trial involved 145 parent-teen dyads (70 intervention and 75 control). Intervention parents received a 45-minute session to learn the program with four follow-up phone sessions, a DVD, and a workbook. Control parents received a standard brochure about safe driving. Scores were developed to measure teen-reported quantity and quality of parental communication about safe driving. The main outcome measure was a previously validated Risky Driving Score reported by teens. Because the Score was highly skewed, a generalized linear model based on a gamma distribution was used for analysis. Intervention teens ranked their parent's success in talking about driving safety higher than control teens (p = 0.035) and reported that their parents talked about more topics (non-significant difference). The Risky Driving Score was 21% lower in intervention compared to control teens (85% CI = 0.60, 1.00). Interaction between communication quantity and the intervention was examined. Intervention teens who reported more successful communication had a 42% lower Risky Driving Score (95% CI = 0.37, 0.94) than control parents with less successful communication. This program had a positive although not strong effect, and it may hold the most promise in partnership with other programs, such as Driver's Education or Graduated Driver's License policies. ClinicalTrials.gov NCT01014923. Registered Nov. 16, 2009.

Staying Safe in the Water

Centers for Disease Control (CDC) Podcasts

In this podcast, Dr. Julie Gilchrist, a pediatrician and medical epidemiologist from CDC’s Injury Center, talks about staying safe in the water. Tips are for all audiences, with a focus on preventing drownings and keeping children safe in and around the pool, lake, or ocean.

Assessment of changes in plasma hemoglobin and potassium levels in red cell units during processing and storage.

Science.gov (United States)

Saini, Nishant; Basu, Sabita; Kaur, Ravneet; Kaur, Jasbinder

2015-06-01

Red cell units undergo changes during storage and processing. The study was planned to assess plasma potassium, plasma hemoglobin, percentage hemolysis during storage and to determine the effects of outdoor blood collection and processing on those parameters. Blood collection in three types of blood storage bags was done - single CPDA bag (40 outdoor and 40 in-house collection), triple CPD + SAGM bag (40 in-house collection) and quadruple CPD + SAGM bag with integral leukoreduction filter (40 in-house collection). All bags were sampled on day 0 (day of collection), day 1 (after processing), day 7, day 14 and day 28 for measurement of percentage hemolysis and potassium levels in the plasma of bag contents. There was significant increase in percentage hemolysis, plasma hemoglobin and plasma potassium level in all the groups during storage (p levels during the storage of red blood cells. Blood collection can be safely undertaken in outdoor blood donation camps even in hot summer months in monitored blood transport boxes. SAGM additive solution decreases the red cell hemolysis and allows extended storage of red cells. Prestorage leukoreduction decreases the red cell hemolysis and improves the quality of blood. Copyright © 2015 Elsevier Ltd. All rights reserved.

Safe biodegradable fluorescent particles

Science.gov (United States)

Martin, Sue I [Berkeley, CA; Fergenson, David P [Alamo, CA; Srivastava, Abneesh [Santa Clara, CA; Bogan, Michael J [Dublin, CA; Riot, Vincent J [Oakland, CA; Frank, Matthias [Oakland, CA

2010-08-24

A human-safe fluorescence particle that can be used for fluorescence detection instruments or act as a safe simulant for mimicking the fluorescence properties of microorganisms. The particle comprises a non-biological carrier and natural fluorophores encapsulated in the non-biological carrier. By doping biodegradable-polymer drug delivery microspheres with natural or synthetic fluorophores, the desired fluorescence can be attained or biological organisms can be simulated without the associated risks and logistical difficulties of live microorganisms.

Conceptual design report: Nuclear materials storage facility renovation. Part 3, Supplemental information

International Nuclear Information System (INIS)

1995-01-01

The Nuclear Materials Storage Facility (NMSF) at the Los Alamos National Laboratory (LANL) was a Fiscal Year (FY) 1984 line-item project completed in 1987 that has never been operated because of major design and construction deficiencies. This renovation project, which will correct those deficiencies and allow operation of the facility, is proposed as an FY 97 line item. The mission of the project is to provide centralized intermediate and long-term storage of special nuclear materials (SNM) associated with defined LANL programmatic missions and to establish a centralized SNM shipping and receiving location for Technical Area (TA)-55 at LANL. Based on current projections, existing storage space for SNM at other locations at LANL will be loaded to capacity by approximately 2002. This will adversely affect LANUs ability to meet its mission requirements in the future. The affected missions include LANL's weapons research, development, and testing (WRD ampersand T) program; special materials recovery; stockpile survelliance/evaluation; advanced fuels and heat sources development and production; and safe, secure storage of existing nuclear materials inventories. The problem is further exacerbated by LANL's inability to ship any materials offsite because of the lack of receiver sites for mate rial and regulatory issues. Correction of the current deficiencies and enhancement of the facility will provide centralized storage close to a nuclear materials processing facility. The project will enable long-term, cost-effective storage in a secure environment with reduced radiation exposure to workers, and eliminate potential exposures to the public. It is organized into seven parts. Part I - Design Concept describes the selected solution. Part III - Supplemental Information contains calculations for the various disciplines as well as other supporting information and analyses

Safe Haven.

Science.gov (United States)

Bush, Gail

2003-01-01

Discusses school libraries as safe havens for teenagers and considers elements that foster that atmosphere, including the physical environment, lack of judgments, familiarity, leisure, and a welcoming nature. Focuses on the importance of relationships, and taking the time to listen to teens and encourage them. (LRW)

Analysis and Design of Cryogenic Pressure Vessels for Automotive Hydrogen Storage

Science.gov (United States)

Espinosa-Loza, Francisco Javier

demonstrated a methodology for computationally efficient detailed modeling of cryogenic pressure vessels. The work continues with support of the US Department of Energy to demonstrate a new generation of cryogenic vessels anticipated to improve on the hydrogen storage performance figures previously imposed in this project. The author looks forward to further contributing to a future of long-range, inexpensive, and safe zero emissions transportation.

Advisory Material for the IAEA Regulations for the Safe Transport of Radioactive Material. Safety Guide (Spanish Edition)

International Nuclear Information System (INIS)

2010-01-01

This Safety Guide provides recommendations on achieving and demonstrating compliance with IAEA Safety Standards Series No. TS-R-1, Regulations for the Safe Transport of Radioactive Material, 2005 Edition, establishing safety requirements to be applied to the national and international transport of radioactive material. Transport is deemed to comprise all operations and conditions associated with and involved in the movement of radioactive material; these include the design, fabrication and maintenance of packaging, and the preparation, consigning, handling, carriage, storage in transit and receipt at the final destination of packages. This publication supersedes IAEA Safety Series No. TS-G-1.1, 2002 Edition

The Design of a Secure File Storage System

Science.gov (United States)

1979-12-01

ERROR _CODE (Przi SUCO COPE) !01ile not found; write access to dtrectorv not permitted I t := GATEKEFPER?.TICKFT ’MAIL BOX, 0) G ATE KF YP F I ~D iNC...BOX.MS’T.SUCC CODE F’OF COD? (DIOR SUCO CODE) Ifile_ not found.; Fead acceLss to directoryv file t ~TRKEPE.TIKFT MIT BOX C) GATHYP~PE-I.AWAIT (MAILBOX, C. (t+2

More than a Safe Space

Science.gov (United States)

Sadowski, Michael

2016-01-01

Over the past three decades, much of the conversation about LGBTQ students in schools has centered on safety--anti-bullying policies, the "safe space" of gay-straight alliances, and "safe zones" marked by rainbow-colored stickers on classroom doors. In this article, Michael Sadowski argues that it's time to move beyond safety…

Development of a container for the transportation and storage of plutonium bearing materials

International Nuclear Information System (INIS)

Ammerman, D.; Geinitz, R.; Thorp, D.; Rivera, M.

1998-03-01

There is a large backlog of plutonium contaminated materials at the Rocky Flats Environmental Technology Site near Denver, Colorado, USA. The clean-up of this site requires this material to be packaged in such a way as to allow for efficient transportation to other sites or to a permanent geologic repository. Prior to off-site shipment of the material, it may be stored on-site for a period of time. For this reason, it is desirable to have a container capable of meeting the requirements for storage as well as the requirements for transportation. Most of the off-site transportation is envisioned to take place using the TRUPACT-II Type B package, with the Waste Isolation Pilot Plant (WIPP) as the destination. Prior to the development of this new container, the TRUPACT-II had a limit of 325 FGE (fissile gram equivalents) of plutonium due to criticality control concerns. Because of the relatively high plutonium content in the material to be transported, transporting 325 FGE per TRUPACT-II is uneconomical. Thus, the purpose of the new containers is to provide criticality control to increase the allowed TRUPACT-II payload and to provide a safe method for on-site storage prior to transport. This paper will describe the analysis and testing used to demonstrate that the Pipe Overpack Container provides safe on-site storage of plutonium bearing materials in unhardened buildings and provides criticality control during transportation within the TRUPACT-II. Analyses included worst-case criticality analyses, analyses of fork-lift time impacts, and analyses of roof structure collapse onto the container. Testing included dynamic crush tests, bare pipe impact tests, a 30-minute totally engulfing pool-fire test, and multiple package impact tests in end-on and side-on orientations

Determination of effective irradiation dose to maintain quality of garlic cultivars during storage

International Nuclear Information System (INIS)

Janagam, Venu Madhav; Sethi, Shruti; Kaur, Charanjit; Singh, Bhupinder; Pal, R.K.

2014-01-01

Garlic (Allium sativum L.) is the second most widely cultivated allium vegetable next to onion. India is the second largest producer (4.46%) of garlic after China (81.02%). As freshly harvested garlic is available in the market for three to four months and there is urgent need to store huge quantity of garlic to fulfil the demand of the consumers during the off-season. The major causes of losses in garlic are sprouting, physiological loss in weight (PLW), decay and quality loss. Several investigators have proved the efficacy of the use of ionizing radiations to reduce the losses caused due to sprouting and other factors. The aim of the study was to investigate the effect of irradiation on post harvest quality of garlic and to determine the irradiation dose for maximum quality retention. Two garlic varieties namely, Yamuna Safed (G-1) and Yamuna Safed-4 (G-323) were treated 120 days (just after dormancy break) postharvest with different doses of gamma irradiation (0.075, 0.01 and 0.15 kGy) and their quality parameters were studied upto 210 days at ambient conditions (18-32℃ and 55-65% RH). Effect of irradiation on physical, physiological and biochemical parameters during storage of both the varieties of garlic revealed that 0.1 kGy irradiation dose was most significant in checking sprouting, controlling decay, PLW, respiration rate and retention of total soluble solids (TSS), pyruvic acid, antioxidant activity, total phenols and amylase activity during storage in comparison to non-irradiated samples followed by 0.15 and 0.075 kGy. Among the two varieties studied, the variety G-323 performed better than G-1 with regard to changes in physiological and biochemical parameters during storage. (author)

Feasibility study on utilization of radiation from spent fuel in storage facility

International Nuclear Information System (INIS)

Wataru, Masumi; Sakamoto, Kazuaki; Saegusa, Toshiari; Sakaya, Tadatsugu; Fujiwara, Hiroaki.

1997-01-01

Spent fuels of nuclear power plant are stored safely until reprocessing because they are radioactive in addition to energy resources. It is foreseen that the amount of the stored spent fuel increases in the long term. Therefore, in the government, discussion on the storage away from reactor is in progress as well as one at reactor. Spent fuel emits a radioactive ray for a long time. In the storage facility, radiation is shielded not to have a detrimental influence upon the health and environment. If radioactive ray is incorrectly handled, it is hazardous for the health and the environment. But, it is very useful if it is properly utilized under a careful management. In the industry, radioactive ray by isotopes (e.g. Co-60) is used widely. In a view of the effective utilization of energy, the promotion of the siting, the regional development and the creation of employment opportunities of local inhabitants, it is preferable to make use of radiation from the spent fuel. In this study, feasibility of utilization of radiation energy from the spent fuel in a storage facility was evaluated. (author)

Safe injection procedures, injection practices, and needlestick ...

African Journals Online (AJOL)

Results: Safe injection procedures regarding final waste disposal were sufficiently adopted, while measures regarding disposable injection equipment, waste containers, hand hygiene, as well as injection practices were inadequately carried out. Lack of job aid posters that promote safe injection and safe disposal of ...

A concept of an electricity storage system with 50 MWh storage capacity

Directory of Open Access Journals (Sweden)

Józef Paska

2012-06-01

Full Text Available Electricity storage devices can be divided into indirect storage technology devices (involving electricity conversion into another form of energy, and direct storage (in an electric or magnetic fi eld. Electricity storage technologies include: pumped-storage power plants, BES Battery Energy Storage, CAES Compressed Air Energy Storage, Supercapacitors, FES Flywheel Energy Storage, SMES Superconducting Magnetic Energy Storage, FC Fuel Cells reverse or operated in systems with electrolysers and hydrogen storage. These technologies have diff erent technical characteristics and economic parameters that determine their usability. This paper presents two concepts of an electricity storage tank with a storage capacity of at least 50 MWh, using the BES battery energy storage and CAES compressed air energy storage technologies.

Development of high-capacity antimatter storage