Quality-Assurance Program Plan

International Nuclear Information System (INIS)

Kettell, R.A.

1981-05-01

This Quality Assurance Program Plan (QAPP) is provided to describe the Quality Assurance Program which is applied to the waste management activities conducted by AESD-Nevada Operations at the E-MAD Facility located in Area 25 of the Nevada Test Site. The AESD-Nevada Operations QAPP provides the necessary systematic and administrative controls to assure activities that affect quality, safety, reliability, and maintainability during design, procurement, fabrication, inspection, shipments, tests, and storage are conducted in accordance with established requirements

Caliban : [luuletused] / Lörinc Szab̤ ; tlk. Ellen Niit

Index Scriptorium Estoniae

Szab̤, Lörinc

2004-01-01

Sisu: Caliban ; Paani kingitus ; Mütoloogia ; Ei puutu sind, vaid vaatan, kuidas magad ; Kõik mittemillegi eest ; Jütsist saab hiiglane ; Separaatrahu ; Palve laste eest ; SIRTSUSIRIN : Rahulik ime ; Mu isa ; Veduriga ; Mu ema laulis ; Emad ; Mis öelnuksin ; Su nimi ; Mu isa surm ; Südametromboos, Tihany ; Miskolci puukirikus ; KAHEKÜMNE KUUES AASTA : Et pole sind ; Kahekümne kahe aastane ; Nüüd ainult vaimus ; Nagu haldjas! ; Ei iial ; Mozartit kuulates. Andmeid autori kohta lk. 45-46

Corrective action investigation plan for Corrective Action Unit 143: Area 25 contaminated waste dumps, Nevada Test Site, Nevada, Revision 1 (with Record of Technical Change No. 1 and 2)

Energy Technology Data Exchange (ETDEWEB)

USDOE Nevada Operations Office (DOE/NV)

1999-06-28

This plan contains the US Department of Energy, Nevada Operations Office's approach to collect the data necessary to evaluate correction action alternatives appropriate for the closure of Corrective Action Unit (CAU) 143 under the Federal Facility Agreement and Consent Order. Corrective Action Unit 143 consists of two waste dumps used for the disposal of solid radioactive wastes. Contaminated Waste Dump No.1 (CAS 25-23-09) was used for wastes generated at the Reactor Maintenance Assembly and Disassembly (R-MAD) Facility and Contaminated Waste Dump No.2 (CAS 25-23-03) was used for wastes generated at the Engine Maintenance Assembly and Disassembly (E-MAD) Facility. Both the R-MAD and E-MAD facilities are located in Area 25 of the Nevada Test Site. Based on site history, radionuclides are the primary constituent of concern and are located in these disposal areas; vertical and lateral migration of the radionuclides is unlikely; and if migration has occurred it will be limited to the soil beneath the Contaminated Waste Disposal Dumps. The proposed investigation will involve a combination of Cone Penetrometer Testing within and near the solid waste disposal dumps, field analysis for radionuclides and volatile organic compounds, as well as sample collection from the waste dumps and surrounding areas for off-site chemical, radiological, and geotechnical analyses. The results of this field investigation will support a defensible evaluation of corrective action alternatives in the corrective action decision document.

Corrective Action Plan for Corrective Action Unit 135: Area 25 Underground Storage Tanks, Nevada Test Site, Nevada

International Nuclear Information System (INIS)

Cox, D. H.

2000-01-01

The Area 25 Underground Storage Tanks site Corrective Action Unit (CAU) 135 will be closed by unrestricted release decontamination and verification survey, in accordance with the Federal Facility Agreement and Consert Order (FFACO, 1996). The CAU includes one Corrective Action Site (CAS). The Area 25 Underground Storage Tanks, (CAS 25-02-01), referred to as the Engine-Maintenance Assembly and Disassembly (E-MAD) Waste Holdup Tanks and Vault, were used to receive liquid waste from all of the radioactive drains at the E-MAD Facility. Based on the results of the Corrective Action Investigation conducted in June 1999 discussed in the Corrective Action Investigation Plan for Corrective Action Unit 135: Area 25 Underground Storage Tanks, Nevada Test Site, Nevada (DOE/NV,1999a), one sample from the radiological survey of the concrete vault interior exceeded radionuclide preliminary action levels. The analytes from the sediment samples that exceeded the preliminary action levels are polychlorinated biphenyls, Resource Conservation and Recovery Act metals, total petroleum hydrocarbons as diesel-range organics, and radionuclides. Unrestricted release decontamination and verification involves removal of concrete and the cement-lined pump sump from the vault. After verification that the contamination has been removed, the vault will be repaired with concrete, as necessary. The radiological- and chemical-contaminated pump sump and concrete removed from the vault would be disposed of at the Area 5 Radioactive Waste Management Site. The vault interior will be field surveyed following removal of contaminated material to verify that unrestricted release criteria have been achieved

Corrective Action Plan for Corrective Action Unit 135: Area 25 Underground Storage Tanks, Nevada Test Site, Nevada

Energy Technology Data Exchange (ETDEWEB)

D. H. Cox

2000-07-01

The Area 25 Underground Storage Tanks site Corrective Action Unit (CAU) 135 will be closed by unrestricted release decontamination and verification survey, in accordance with the Federal Facility Agreement and Consert Order (FFACO, 1996). The CAU includes one Corrective Action Site (CAS). The Area 25 Underground Storage Tanks, (CAS 25-02-01), referred to as the Engine-Maintenance Assembly and Disassembly (E-MAD) Waste Holdup Tanks and Vault, were used to receive liquid waste from all of the radioactive drains at the E-MAD Facility. Based on the results of the Corrective Action Investigation conducted in June 1999 discussed in the Corrective Action Investigation Plan for Corrective Action Unit 135: Area 25 Underground Storage Tanks, Nevada Test Site, Nevada (DOE/NV,1999a), one sample from the radiological survey of the concrete vault interior exceeded radionuclide preliminary action levels. The analytes from the sediment samples that exceeded the preliminary action levels are polychlorinated biphenyls, Resource Conservation and Recovery Act metals, total petroleum hydrocarbons as diesel-range organics, and radionuclides. Unrestricted release decontamination and verification involves removal of concrete and the cement-lined pump sump from the vault. After verification that the contamination has been removed, the vault will be repaired with concrete, as necessary. The radiological- and chemical-contaminated pump sump and concrete removed from the vault would be disposed of at the Area 5 Radioactive Waste Management Site. The vault interior will be field surveyed following removal of contaminated material to verify that unrestricted release criteria have been achieved.

Study of heavy metals in urban runoff

International Nuclear Information System (INIS)

Nabizadeh, R.; Mahvi, A.; Mardani, G.; Yunesian, M.

2005-01-01

A cross-sectional survey was conducted through Tehran city and a field study was conducted to prepare main and accessory drainage channels map. Three main drainage channels were identified for this research and some sampling stations were chosen. Three stations selected in south of Tehran. The reason for selecting these stations is that all urban surface run off completely pass through these points and samples taken from these points are representative of all kinds of pollutants that transit from city surface. Another three stations were selected in center and further three stations were selected at north of Tehran. Surface runoff flow in three main channels, from north of south of Tehran, converge at south of Rey city and finally end up to Ghom Salt lake. The stations were chosen at three trajectories Sorkhe Hesar, Emad Avard, Kan. At each month two samples were from nine different stations. After collection of samples with respect to standard methods, they were dissolved in nitric acid and then analyzed by atomic absorption device. The results show that the concentrations of pollutants increased from north to south. For instance, Zinc had most concentration with monthly average of 0.98 mg/l and Nickel had the lowest amount with 0.02 mg/l in southern stations. Average concentration of Zn, Pb, Cd, Cu and Ni were: 0.638, 0.97, 0.04 and 0.035 mg/l respectively. Total average concentrations of heavy metals at three main channels were of 0.177, 0.176 and 0.145 mg/l. Emad Avard was the most polluted channel

Authorized Limits for the Release of a 25 Ton Locomotive, Serial Number 21547, at the Area 25 Engine Maintenance, Assembly, and Disassembly Facility, Nevada Test Site, Nevada

International Nuclear Information System (INIS)

Gwin, Jeremy; Frenette, Douglas

2010-01-01

This document contains process knowledge and radiological data and analysis to support approval for release of the 25-ton locomotive, Serial Number 21547, at the Area 25 Engine Maintenance, Assembly, and Disassembly (EMAD) Facility, located on the Nevada Test Site (NTS). The 25-ton locomotive is a small, one-of-a-kind locomotive used to move railcars in support of the Nuclear Engine for Rocket Vehicle Application project. This locomotive was identified as having significant historical value by the Nevada State Railroad Museum in Boulder City, Nevada, where it will be used as a display piece. A substantial effort to characterize the radiological conditions of the locomotive was undertaken by the NTS Management and Operations Contractor, National Security Technologies, LLC (NSTec). During this characterization process, seven small areas on the locomotive had contamination levels that exceeded the NTS release criteria (limits consistent with U.S. Department of Energy (DOE) Order DOE O 5400.5, 'Radiation Protection of the Public and the Environment'). The decision was made to perform radiological decontamination of these known accessible impacted areas to further the release process. On February 9, 2010, NSTec personnel completed decontamination of these seven areas to within the NTS release criteria. Although all accessible areas of the locomotive had been successfully decontaminated to within NTS release criteria, it was plausible that inaccessible areas of the locomotive (i.e., those areas on the locomotive where it was not possible to perform radiological surveys) could potentially have contamination above unrestricted release limits. To access the majority of these inaccessible areas, the locomotive would have to be disassembled. A complete disassembly for a full radiological survey could have permanently destroyed parts and would have ruined the historical value of the locomotive. Complete disassembly would also add an unreasonable financial burden for the

Tom ja Anni ajavad isad-emad naerma / Kai Väärtnõu

Index Scriptorium Estoniae

Väärtnõu, Kai

2007-01-01

ETV lastesaate "Saame kokku Tomi juures" stsenarist on Jaak Urmet ehk Wimberg. Teksti improviseerivad ka näitlejad Karol Kuntsel ja Maria Soomets. Lisaks tutvustus "Pööningule purjetab proua Õietolmutuust"

Validation of the STAFF-5 computer model

International Nuclear Information System (INIS)

Fletcher, J.F.; Fields, S.R.

1981-04-01

STAFF-5 is a dynamic heat-transfer-fluid-flow stress model designed for computerized prediction of the temperature-stress performance of spent LWR fuel assemblies under storage/disposal conditions. Validation of the temperature calculating abilities of this model was performed by comparing temperature calculations under specified conditions to experimental data from the Engine Maintenance and Dissassembly (EMAD) Fuel Temperature Test Facility and to calculations performed by Battelle Pacific Northwest Laboratory (PNL) using the HYDRA-1 model. The comparisons confirmed the ability of STAFF-5 to calculate representative fuel temperatures over a considerable range of conditions, as a first step in the evaluation and prediction of fuel temperature-stress performance

Between the carrot and slamming the door. Teaching ad honorem at the UBA Entre el portazo y la zanahoria. La docencia por el honor en la UBA

Directory of Open Access Journals (Sweden)

Rodrigo Hobert

2008-07-01

Full Text Available Institutional and structural erosion of the largest Argentine national university has produced, among other things, space shortage, overcrowded classrooms, lack of materials, administrative chaos, lack of scholarships, irregular assignment of positions and research budgets, informal recruiting of teachers without payment, and finally the fall of its representative system, far away from classroom reality. The article analyzes <em>ad honorem teaching at the University of Buenos Aires. More than a third of UBA teachers do not receive payment for their services. This work delves into the actors' perspectives in a context of difficult institutional and labor conditions.

El desgaste institucional y estructural de la universidad nacional más grande de la Argentina se ha traducido, entre otros aspectos, en profundos niveles de decadencia edilicia, hacinamiento en las cursadas, falta de materiales didácticos, descontrol administrativo, escasez de concursos, discrecionalidad en los nombramientos docentes y en la asignación presupuestaria a proyectos de investigación, reclutamiento informal de docentes con bajos o inexistentes salarios, y la degradación de su sistema representativo, alejado de la realidad constitutiva de los claustros.

Facility Decontamination and Decommissioning Program Surveillance and Maintenance Plan, Revision 2

Energy Technology Data Exchange (ETDEWEB)

Poderis, Reed J. [NSTec; King, Rebecca A. [NSTec

2013-09-30

This Surveillance and Maintenance (S&M) Plan describes the activities performed between deactivation and final decommissioning of the following facilities located on the Nevada National Security Site, as documented in the Federal Facility Agreement and Consent Order under the Industrial Sites program as decontamination and decommissioning sites: ? Engine Maintenance, Assembly, and Disassembly (EMAD) Facility: o EMAD Building (Building 25-3900) o Locomotive Storage Shed (Building 25-3901) ? Test Cell C (TCC) Facility: o Equipment Building (Building 25-3220) o Motor Drive Building (Building 25-3230) o Pump Shop (Building 25-3231) o Cryogenic Lab (Building 25-3232) o Ancillary Structures (e.g., dewars, water tower, piping, tanks) These facilities have been declared excess and are in various stages of deactivation (low-risk, long-term stewardship disposition state). This S&M Plan establishes and implements a solid, cost-effective, and balanced S&M program consistent with federal, state, and regulatory requirements. A graded approach is used to plan and conduct S&M activities. The goal is to maintain the facilities in a safe condition in a cost-effective manner until their final end state is achieved. This plan accomplishes the following: ? Establishes S&M objectives and framework ? Identifies programmatic guidance for S&M activities to be conducted by National Security Technologies, LLC, for the U.S. Department of Energy, National Nuclear Security Administration Nevada Field Office (NNSA/NFO) ? Provides present facility condition information and identifies hazards ? Identifies facility-specific S&M activities to be performed and their frequency ? Identifies regulatory drivers, NNSA/NFO policies and procedures, and best management practices that necessitate implementation of S&M activities ? Provides criteria and frequencies for revisions and updates ? Establishes the process for identifying and dispositioning a condition that has not been previously identified or

Spent LWR fuel encapsulation and dry storage demonstration

International Nuclear Information System (INIS)

Bahorich, R.J.; Durrill, D.C.; Cross, T.E.; Unterzuber, R.

1980-01-01

In 1977 the Spent Fuel Handling and Packaging Program (SFHPP) was initiated by the Department of Energy to develop and test the capability to satisfactorily encapsulate typical spent fuel assemblies from commercial light-water nuclear power plants and to establish the suitability of one or more surface and near surface concepts for the interim dry storage of the encapsulated spent fuel assemblies. The E-MAD Facility at the Nevada Test Site, which is operated for the Department of Energy by the Advanced Energy Systems Division (AESD) of the Westinghouse Electric Corporation, was chosen as the location for this demonstration because of its extensive existing capabilities for handling highly radioactive components and because of the desirable site characteristics for the proposed storage concepts. This paper describes the remote operations related to the process steps of handling, encapsulating and subsequent dry storage of spent fuel in support of the Demonstration Program

Vitruvian Character: The Case of the Egyptian Museum

Directory of Open Access Journals (Sweden)

Khaled Asfour

2014-11-01

Full Text Available In Vitruvius’ treatise, what makes good architecture is its ability to communicate to the public particular messages that reflects the program of the building with spaces and components arranged in an orderly way. According to Vitruvius these messages when acknowledges by the public the building posses strong character. This research discusses this idea by reflecting on the 1895 competition of the Egyptian Museum project. Marcel Dourgnon, the French architect of the winning scheme, showed profound understanding of character resulting in a building that had positive vibe with the local community.  Today Vitruvius’ idea is still living with us. Norman Foster succeeded in upgrading the British Museum in a way that addressed all cultures of the world through his grand atrium design.  Similarly, Emad Farid and Ramez Azmy revived the presence of the Egyptian Museum in public cognition.  Spatial experience that evokes similar perceptions to all its visitors is a timeless piece that transcends cultural boundaries.

Streamlined Approach for Environmental Restoration Plan for Corrective Action Unit 398: Area 25 Spill Sites, Nevada Test Site, Nevada; TOPICAL

International Nuclear Information System (INIS)

K. B. Campbell

2001-01-01

This Streamlined Approach for Environmental Restoration (SAFER) plan addresses the activities necessary to close Corrective Action Unit (CAU) 398: Area 25 Spill Sites. CAU 398, located in Area 25 of the Nevada Test Site, is currently listed in Appendix III of the Federal Facility Agreement and Consent Order (FFACO) (FFACO, 1996), and consists of the following 13 Corrective Action Sites (CASs) (Figure 1): (1) CAS 25-44-01 , a fuel spill on soil that covers a concrete pad. The origins and use of the spill material are unknown, but the spill is suspected to be railroad bedding material. (2) CAS 25-44-02, a spill of liquid to the soil from leaking drums. (3) CAS 25-44-03, a spill of oil from two leaking drums onto a concrete pad and surrounding soil. (4) CAS 25-44-04, a spill from two tanks containing sulfuric acid and sodium hydroxide used for a water demineralization process. (5) CAS 25-25-02, a fuel or oil spill from leaking drums that were removed in 1992. (6) CAS 25-25-03, an oil spill adjacent to a tipped-over drum. The source of the drum is not listed, although it is noted that the drum was removed in 1991. (7) CAS 25-25-04, an area on the north side of the Engine-Maintenance, Assembly, and Disassembly (E-MAD) facility, where oils and cooling fluids from metal machining operations were poured directly onto the ground. (8) CAS 25-25-05, an area of oil and/or hydraulic fluid spills beneath the heavy equipment once stored there. (9) CAS 25-25-06, an area of diesel fuel staining beneath two generators that have since been removed. (10) CAS 25-25-07, an area of hydraulic oil spills associated with a tunnel-boring machine abandoned inside X-Tunnel. (11) CAS 25-25-08, an area of hydraulic fluid spills associated with a tunnel-boring machine abandoned inside Y-Tunnel. (12) CAS 25-25-16, a diesel fuel spill from an above-ground storage tank located near Building 3320 at Engine Test Stand-1 (ETS-1) that was removed in 1998. (13) CAS 25-25-17, a hydraulic oil spill

Closure Report for Corrective Action Unit 135: Areas 25 Underground Storage Tanks, Nevada Test Site, Nevada

Energy Technology Data Exchange (ETDEWEB)

D. H. Cox

2001-06-01

Corrective Action Unit (CAU) 135, Area 25 Underground Storage Tanks, was closed in accordance with the approved Corrective Action Plan (DOE/NV, 2000). CAU 135 consists of three Corrective Action Sites (CAS). Two of these CAS's were identified in the Corrective Action Investigation Data Quality Objective meeting as being improperly identified as underground storage tanks. CAS 25-02-03 identified as the Deluge Valve Pit was actually an underground electrical vault and CAS 25-02-10 identified as an Underground Storage Tank was actually a former above ground storage tank filled with demineralized water. Both of these CAS's are recommended for a no further action closure. CAS 25-02-01 the Underground Storage Tanks commonly referred to as the Engine Maintenance Assembly and Disassembly Waste Holdup Tanks and Vault was closed by decontaminating the vault structure and conducting a radiological verification survey to document compliance with the Nevada Test Site unrestricted use release criteria. The Area 25 Underground Storage Tanks, (CAS 25-02-01), referred to as the Engine Maintenance, Assembly, and Disassembly (E-MAD) Waste Holdup Tanks and Vault, were used to receive liquid waste from all of the radioactive and cell service area drains at the E-MAD Facility. Based on the results of the Corrective Action Investigation conducted in June 1999, discussed in ''The Corrective Action Investigation Plan for Corrective Action Unit 135: Area 25 Underground Storage Tanks, Nevada Test Site, Nevada'' (DOE/NV, 199a), one sample from the radiological survey of the concrete vault interior exceeded radionuclide preliminary action levels. The analytes from the sediment samples exceeded the preliminary action levels for polychlorinated biphenyls, Resource Conservation and Recovery Act metals, total petroleum hydrocarbons as diesel-range organics, and radionuclides. The CAU 135 closure activities consisted of scabbling radiological ''hot spots

Corrective Action Investigation Plan for Corrective Action Unit 262: Area 25 Septic Systems and Underground Discharge Point, Nevada Test Site, Nevada, Revision No. 1 (9/2001)

International Nuclear Information System (INIS)

2000-01-01

This corrective action investigation plan contains the U.S. Department of Energy, Nevada Operations Office's approach to collect data necessary to evaluate corrective action alternatives appropriate for the closure of Corrective Action Unit (CAU) 262 under the Federal Facility Agreement and Consent Order. Corrective Action Unit 262 consists of nine Corrective Action Sites (CASs): Underground Storage Tank (25-02-06), Septic Systems A and B (25-04-06), Septic System (25-04-07), Leachfield (25-05-03), Leachfield (25-05-05), Leachfield (25-05-06), Radioactive Leachfield (25-05-08), Leachfield (25-05-12), and Dry Well (25-51-01). Situated in Area 25 at the Nevada Test Site (NTS), sites addressed by CAU 262 are located at the Reactor-Maintenance, Assembly, and Disassembly (R-MAD); Test Cell C; and Engine-Maintenance, Assembly, and Disassembly (E-MAD) facilities. The R-MAD, Test Cell C, and E-MAD facilities supported nuclear rocket reactor and engine testing as part of the Nuclear Rocket Development Station. The activities associated with the testing program were conducted between 1958 and 1973. Based on site history collected to support the Data Quality Objectives process, contaminants of potential concern (COPCs) for the site include oil/diesel-range total petroleum hydrocarbons, volatile organic compounds, semivolatile organic compounds, polychlorinated biphenyls, Resource Conservation and Recovery Act metals, and gamma-emitting radionuclides, isotopic uranium, isotopic plutonium, strontium-90, and tritium. The scope of the corrective action field investigation at the CAU will include the inspection of portions of the collection systems, sampling the contents of collection system features in situ of leachfield logging materials, surface soil sampling, collection of samples of soil underlying the base of inlet and outfall ends of septic tanks and outfall ends of diversion structures and distribution boxes, collection of soil samples from biased or a combination of

Corrective Action Plan for Corrective Action Unit 262: Area 25 Septic Systems and Underground Discharge Point, Nevada Test Site, Nevada

International Nuclear Information System (INIS)

K. B. Campbell email = campbek@nv.doe.gov

2002-01-01

This Corrective Action Plan (CAP) provides selected corrective action alternatives and proposes the closure methodology for Corrective Action Unit (CAU) 262, Area 25 Septic Systems and Underground Discharge Point. CAU 262 is identified in the Federal Facility Agreement and Consent Order (FFACO) of 1996. Remediation of CAU 262 is required under the FFACO. CAU 262 is located in Area 25 of the Nevada Test Site (NTS), approximately 100 kilometers (km) (62 miles [mi]) northwest of Las Vegas, Nevada. The nine Corrective Action Sites (CASs) within CAU 262 are located in the Nuclear Rocket Development Station complex. Individual CASs are located in the vicinity of the Reactor Maintenance, Assembly, and Disassembly (R-MAD); Engine Maintenance, Assembly, and Disassembly (E-MAD); and Test Cell C compounds. CAU 262 includes the following CASs as provided in the FFACO (1996); CAS 25-02-06, Underground Storage Tank; CAS 25-04-06, Septic Systems A and B; CAS 25-04-07, Septic System; CAS 25-05-03, Leachfield; CAS 25-05-05, Leachfield; CAS 25-05-06, Leachfield; CAS 25-05-08, Radioactive Leachfield; CAS 25-05-12, Leachfield; and CAS 25-51-01, Dry Well. Figures 2, 3, and 4 show the locations of the R-MAD, the E-MAD, and the Test Cell C CASs, respectively. The facilities within CAU 262 supported nuclear rocket reactor engine testing. Activities associated with the program were performed between 1958 and 1973. However, several other projects used the facilities after 1973. A significant quantity of radioactive and sanitary waste was produced during routine operations. Most of the radioactive waste was managed by disposal in the posted leachfields. Sanitary wastes were disposed in sanitary leachfields. Septic tanks, present at sanitary leachfields (i.e., CAS 25-02-06,2504-06 [Septic Systems A and B], 25-04-07, 25-05-05,25-05-12) allowed solids to settle out of suspension prior to entering the leachfield. Posted leachfields do not contain septic tanks. All CASs located in CAU 262 are

Automated nondestructive assay system for the measurement of irradiated Rover fuel

International Nuclear Information System (INIS)

Augustson, R.H.; Menlove, H.O.; Smith, D.B.; Bond, A.L.; Durrill, D.C.; Hollowell, W.P.; Bromley, C.P.

1975-01-01

With the termination of the Nuclear Rocket Propulsion (Rover) Program, and associated reactor testing at the Nuclear Rocket Development Station (NRDS), Nevada, plans are progressing to recover the 93 percent enriched uranium contained in irradiated fuel from twenty various test reactors. This fuel is being packaged into 7-cm-dia by 137-cm-long cardboard tubes, using the remote handling facilities (E-MAD Bldg) of NRDS. After packaging, the fuel is shipped to Allied Chemical Corporation, Idaho Falls, Idaho, for uranium recovery. About 4000 tubes will be needed to package and ship the inventory of fuel elements presently at NRDS. This represents a total of approximately 2500 kg of enriched uranium. To complete the accounting records each tube is being nondestructively assayed and records kept on a reactor-by-reactor basis where possible. The assayed values for a reactor are then compared with original input inventory values and discrepancies resolved. The tubes are being assayed by an active neutron interrogation system designed and fabricated by Los Alamos Scientific Laboratory (LASL) and operated by Westinghouse Astronuclear Laboratory (WANL)-Nevada Operations personnel. WANL is the operating contractor in charge of loading and shipping this fuel. (U.S.)

Lastekirjandus vallutab uusi tippe : eesti lastekirjandus 2009 / Jaanus Vaiksoo

Index Scriptorium Estoniae

Vaiksoo, Jaanus, 1967-

2010-01-01

Ülevaade 2009. aasta eesti lastekirjandusest. Pikemalt käsitletakse järgmisi autoreid ja nende teoseid: Kadi Hinrikus "Kui emad olid väikesed", Kristiina Kass "Peeter ja mina", Mika Keränen "Varastatud oranž jalgratas", Andrus Kivirähk "Kaka ja kevad", Aino Pervik "Ühes väikses veidras linnas", Maarja Undusk "Päkapikk Ingo", Ilmar Tomusk "Vend Johannes", Indrek Koff "Enne kooli", Piret Raud "Härra Linnu lugu", Wimberg "Suur pidusöök", Artur Jurin "Puru kuningriigi lood II", Joonas Sildre "Maailma naba", kogumik "Uued eesti muinasjutud", Aino Pervik "Tirilinna lood", Aimeé Beekman "Päästekoer Walter", Eve Ernis "Karupoeg Nummi seiklused", Priit Aimla "Torisev vanatoi", Juhani Püttsepp "Väikese hundi lood" ja "Lauajupi Madonna", Epp Petrone "Siis, kui seened veel rääkisid", Heiki Vilep "Habemega nali", "Nõiutud linn", Leelo Tungal "Naljatilgad lähevad laulupeole", "Kama üks ja kama kaks", koos Peep Pedmansoniga Miriami lood"(esimene 3D-piltidega lasteraamat), Aidi Vallik "Pints ja Tutsik" 2. osa, Mare Müürsepp "Viis vaba kutsikat", Tiia Selli "Kass Kriibik", Aleksei Turovski "Kassipoeg Võilill", Kaider Vardja "Vana maja lugu", Merca "Mullivesi", Ülle Kütsen "Väike puu ja rändur kuu", Lehte Hainsalu "Mängiks midagi", Peep Veedla "Pöialpoiss"

Pushed monocanalicular intubation versus probing as a primary management for congenital nasolacrimal obstruction

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Elsawaby EA

2016-09-01

Full Text Available Emad Abdelaal Elsawaby, Rania Asem El Essawy, Sameh Hassan Abdelbaky, Yomna Magdy Ismail Department of Ophthalmology, Faculty of Medicine, Cairo University, Cairo, Egypt Purpose: Evaluation of efficiency, complications, and advantages of pushed monocanalicular intubation using Masterka® tube versus simple probing in patients with congenital nasolacrimal duct obstruction (CNLDO.Patients and methods: This is a case-controlled study that included 60 eyes (of 53 patients; 30 eyes underwent probing and 30 eyes intubation using the Masterka tube as a primary treatment for CNLDO. The children were aged between 6 months and 36 months at the time of surgery, with no previous nasolacrimal surgical procedure, and had one or more of the following clinical signs of nasolacrimal duct obstruction: epiphora, mucous discharge, and/or increased tear lake.Results: We defined success by absence of epiphora, mucous discharge, or increased tear lake 1 month after tube removal. The overall success rate in the probing group was 80%, while it was 83.3% in the intubation group.Conclusion: Pushed monocanalicular intubation is an effective method for treatment of CNLDO; it requires only mask inhalation anesthesia and could be considered as an appropriate alternative procedure with imperceptible complications. Keywords: epiphora, probing, intubation, monocanalicular, nasolacrimal

EVALUATION OF THE THORACOABDOMINAL MOBILITY OF OBESE SUBJECTS IN PRE-BARIATRIC SURGERY.

Science.gov (United States)

Veloso, Ana Paula Limongi Richardelli; Cusmanich, Karla Garcez

Obesity can affect the thorax, diaphragm, and alterations in respiratory function even if the lungs are within normality. The respiratory compliance is very reduced by the increase in fat mass. To evaluate the effect of the physical therapeutic respiratory exercises on the thoracoabdominal mobility of obese individuals in pre-bariatric surgery. Cross-sectional and descriptive study, which used the cirtometry (axillary, xiphoid and abdominal) to evaluate the mobility of 74 individuals, 27 men and 47 women, in pre-bariatric surgery, assisted by the team EMAD, after eight weeks of physiotherapy, following a protocol of exercises, reevaluating and compared the measures pre and post intervention. Had positive correlation abdominal mobility in the total volume of all participants (p=0.010) and also for all the measures in the measurement of residual volume in three levels (p=0.000). Comparing genders, in total volume, cirtometry abdominal greater for women (p=0.015) when compared to men and residual volume, significance for either men or women in all measurements (p=0.000). Obese patients that underwent the physiotherapeutic treatment during the preoperative period, had pré respiratory dynamics improved by the increase in the mobility of the chest cavity and by the improvement of respiratory conscience. A obesidade pode afetar o tórax e o diafragma, determinando alterações na função respiratória, mesmo quando os pulmões se apresentam dentro da normalidade. A complacência respiratória é muito reduzida pelo aumento de massa gordurosa. Avaliar o efeito de exercícios fisioterapêuticos respiratórios sobre a mobilidade torácica de indivíduos obesos no pré-operatório de cirurgia bariátrica. Estudo transversal e descritivo, que utilizou a cirtometria (axilar, xifoide e abdominal) para avaliar a mobilidade de 74 indivíduos, 27 homens e 47 mulheres, em pré-operatório de cirurgia bariátrica, assistidos pela equipe EMAD, após oito semanas de fisioterapia

Triangular model integrating clinical teaching and assessment

Directory of Open Access Journals (Sweden)

Abdelaziz A

2014-03-01

Full Text Available Adel Abdelaziz,1,2 Emad Koshak3 1Medical Education Development Unit, Faculty of Medicine, Al Baha University, Al Baha, Saudi Arabia; 2Medical Education Department, Faculty of Medicine, Suez Canal University, Egypt; 3Dean and Internal Medicine Department, Faculty of Medicine, Al Baha University, Al Baha, Saudi Arabia Abstract: Structuring clinical teaching is a challenge facing medical education curriculum designers. A variety of instructional methods on different domains of learning are indicated to accommodate different learning styles. Conventional methods of clinical teaching, like training in ambulatory care settings, are prone to the factor of coincidence in having varieties of patient presentations. Accordingly, alternative methods of instruction are indicated to compensate for the deficiencies of these conventional methods. This paper presents an initiative that can be used to design a checklist as a blueprint to guide appropriate selection and implementation of teaching/learning and assessment methods in each of the educational courses and modules based on educational objectives. Three categories of instructional methods were identified, and within each a variety of methods were included. These categories are classroom-type settings, health services-based settings, and community service-based settings. Such categories have framed our triangular model of clinical teaching and assessment. Keywords: curriculum development, teaching, learning, assessment, apprenticeship, community-based settings, health service-based settings

Dry rod consolidation technology development

International Nuclear Information System (INIS)

Rasmussen, T.L.; Schoonen, D.H.; Feldman, E.M.; Fisher, M.W.

1987-01-01

The Department of Energy's (DOE) Office of Civilian Radioactive Waste Management (OCRWM) is funding a program to consolidate commercial spent fuel for testing in dry storage casks and to develop technology that will be fed into other OCRWM programs, e.g., Prototypical Consolidation Demonstration Program (PCDP). The program is being conducted at the Idaho National Engineering Laboratory (INEL) by the INEL Operating Contractor EG and G Idaho, Inc. Hardware and software have been designed and fabricated for installation in a hot cell adjacent to the Test Area North (TAN) Hot Shop Facility. This equipment is used to perform dry consolidation of commercial spent fuel from the Virginia Power (VP) Cooperative Agreement Spent Fuel Storage Cask (SFSC) Demonstration Program and assemblies that had previously been stored at the Engine Maintenance and Disassembly (EMAD) facility in Nevada. Consolidation is accomplished by individual, horizontal rod pulling. A computerized semiautomatic control system with operator involvement is utilized to conduct consolidation operations. During consolidation operations, data is taken to characterize this technology. Still photo, video tape, and other documentation will be generated to make developed information available to interested parties. Cold checkout of the hardware and software was completed in September of 1986. Following installation in the hot cell, consolidation operations begins in May 1987. Resulting consolidated fuel will be utilized in the VP Cooperative Agreement SFSC Program

Assessment of the facilities on Jackass Flats and other Nevada Test Site facilities for the new nuclear rocket program

International Nuclear Information System (INIS)

Chandler, G.; Collins, D.; Dye, K.; Eberhart, C.; Hynes, M.; Kovach, R.; Ortiz, R.; Perea, J.; Sherman, D.

1992-01-01

Recent NASA/DOE studies for the Space Exploration Initiative have demonstrated a critical need for the ground-based testing of nuclear rocket engines. Experience in the ROVER/NERVA Program, experience in the Nuclear Weapons Testing Program, and involvement in the new nuclear rocket program has motivated our detailed assessment of the facilities used for the ROVER/NERVA Program and other facilities located at the Nevada Test Site (NTS). The ROVER/NERVA facilities are located in the Nevada Research L, Development Area (NRDA) on Jackass Flats at NTS, approximately 85 miles northwest of Las Vegas. To guide our assessment of facilities for an engine testing program we have defined a program goal, scope, and process. To execute this program scope and process will require ten facilities. We considered the use of all relevant facilities at NTS including existing and new tunnels as well as the facilities at NRDA. Aside from the facilities located at remote sites and the inter-site transportation system, all of the required facilities are available at NRDA. In particular we have studied the refurbishment of E-MAD, ETS-1, R-MAD, and the interconnecting railroad. The total cost for such a refurbishment we estimate to be about $253M which includes additional contractor fees related to indirect, construction management, profit, contingency, and management reserves. This figure also includes the cost of the required NEPA, safety, and security documentation

Dry rod consolidation technology development

International Nuclear Information System (INIS)

Rasmussen, T.L.; Schoonen, D.H.; Fisher, M.W.

1986-01-01

The Department of Energy's (DOE) Office of Civilian Radioactive Waste Management (OCRWM) is funding a Program to consolidate commercial spent fuel for testing in dry storage casks and to develop technology that will be fed into other OCRWM Programs, e.g., Prototypical Consolidation Demonstration Program. The Program is being conducted at the Idaho National Engineering Laboratory (INEL) by the Operating Contractor, EGandG Idaho, Inc. Hardware and software have been designed and fabricated for installation in a hot cell adjacent to the Test Area North (TAN) Hot Shop Facility. This equipment will be used to perform dry consolidation of commercial spent fuel from the Virginia Power (VP) Cooperative Agreement Spent Fuel Storage Cask (SPSC) Demonstration Program and assemblies that had previously been stored at the Engine Maintenance and Disassembly (EMAD) facility in Nevada. Consolidation will be accomplished by individual, horizontal rod pulling. A computerized semi-automatic control system with operator involvement will be utilized to conduct consolidation operations. Special features have been incorporated in the design to allow crud collection and measurement of rod pulling forces. During consolidation operations, data will be taken to characterize this technology. Still photo, video tape, and other documentation will be generated to make developed information available to interested parties. Cold checkout of the hardware and software will complete in September of 1986. Following installation in the hot cell, consolidation operations will begin in January 1987. Resulting consolidated fuel will be utilized in the VP Cooperative Agreement SFSC Program

Identification and Quantitation of Malonic Acid Biomarkers of In-Born Error Metabolism by Targeted Metabolomics

Science.gov (United States)

Ambati, Chandra Shekar R.; Yuan, Furong; Abu-Elheiga, Lutfi A.; Zhang, Yiqing; Shetty, Vivekananda

2017-05-01

Malonic acid (MA), methylmalonic acid (MMA), and ethylmalonic acid (EMA) metabolites are implicated in various non-cancer disorders that are associated with inborn-error metabolism. In this study, we have slightly modified the published 3-nitrophenylhydrazine (3NPH) derivatization method and applied it to derivatize MA, MMA, and EMA to their hydrazone derivatives, which were amenable for liquid chromatography- mass spectrometry (LC-MS) quantitation. 3NPH was used to derivatize MA, MMA, and EMA, and multiple reaction monitoring (MRM) transitions of the corresponding derivatives were determined by product-ion experiments. Data normalization and absolute quantitation were achieved by using 3NPH derivatized isotopic labeled compounds 13C2-MA, MMA-D3, and EMA-D3. The detection limits were found to be at nanomolar concentrations and a good linearity was achieved from nanomolar to millimolar concentrations. As a proof of concept study, we have investigated the levels of malonic acids in mouse plasma with malonyl-CoA decarboxylase deficiency (MCD-D), and we have successfully applied 3NPH method to identify and quantitate all three malonic acids in wild type (WT) and MCD-D plasma with high accuracy. The results of this method were compared with that of underivatized malonic acid standards experiments that were performed using hydrophilic interaction liquid chromatography (HILIC)-MRM. Compared with HILIC method, 3NPH derivatization strategy was found to be very efficient to identify these molecules as it greatly improved the sensitivity, quantitation accuracy, as well as peak shape and resolution. Furthermore, there was no matrix effect in LC-MS analysis and the derivatized metabolites were found to be very stable for longer time.

Alterations in oral microbial flora induced by waterpipe tobacco smoking

Directory of Open Access Journals (Sweden)

Shakhatreh MAK

2018-02-01

Full Text Available Muhamad Ali K Shakhatreh,1 Omar F Khabour,1 Karem H Alzoubi,2 Majed M Masadeh,3 Emad I Hussein,4 George N Bshara1 1Department of Medical Laboratory Sciences, Faculty of Applied Medical Sciences, Irbid, Jordan; 2Department of Clinical Pharmacy, Faculty of Pharmacy, Jordan University of Science and Technology, Irbid, Jordan; 3Department of Pharmaceutical Technology, Faculty of Pharmacy, Jordan University of Science and Technology, Irbid, Jordan; 4Department of Biological Sciences, Yarmouk University, Irbid, Jordan Background: Waterpipe smoking is a global health problem and a serious public concern. Little is known about the effects of waterpipe smoking on oral health. In the current study, we examined the alterations of oral microbial flora by waterpipe smoking. Methods: One hundred adult healthy subjects (59 waterpipe smokers and 41 non-smokers were recruited into the study. Swabs were taken from the oral cavity and subgingival regions. Standard culturing techniques were used to identify types, frequency, and mean number of microorganisms in cultures obtained from the subjects. Results: It was notable that waterpipe smokers were significantly associated with a history of oral infections. In subgingiva, Acinetobacter and Moraxella species were present only in waterpipe smokers. In addition, the frequency of Candida albicans was higher in the subgingiva of waterpipe smokers (p = 0.023 while the frequency of Fusobacterium nucleatum was significantly lower in the subgingiva of waterpipe smokers (p = 0.036. However, no change was observed in other tested bacteria, such as Campylobacter species; Viridans group streptococci, Enterobacteriaceae, and Staphylococcus aureus. In oral cavity and when colony-forming units were considered, the only bacterial species that showed significant difference were the black-pigmented bacteria (p < 0.001. Conclusion: This study provides evidence indicating that some of the oral microflora is significantly altered by

USO DA PGF2? NO PUERPÉRIO PARA REDUZIR O ANESTRO PÓS-PARTO DE CABRAS EM ALEITAMENTO CONTÍNUO E CONTROLADO USE OF PGF2? ON THE PUERPERIO TO REDUCE THE POS-PARTUM ANESTROUS OF CONTINUOS OR CONTROLLED SUCKLING GOATS

Directory of Open Access Journals (Sweden)

Paulo Fernandes Lima

2008-07-01

Full Text Available

Objetivou-se estudar os efeitos da administração da PGF2α sobre o período de anestro pós-parto de oitenta cabras, em aleitamento contínuo ou controlado, criadas em sistema semi-extensivo com acesso à água e sal mineral <em>ad libitum. As fêmeas, com idade entre dois e seis anos, foram aleatoriamente distribuídas em três grupos experimentais (GI, GII, GIII. As do GI (n = 30 receberam, na musculatura vulvar, 250µg de PGF2α no 6^o e 12^o dias após o parto. As do GII (n = 30 foram tratadas, pela mesma via e com a mesma dose de PGF2α, no 6^o, 7^o, 8^o, 9^o e 10^o dias do pós-parto, e as do GIII (n = 20 serviram como controle. Realizou-se a detecção do estro por rufião com auxílio de pessoal habilitado e efetuaram-se as coberturas com reprodutores de fertilidade comprovada. Analisaram-se os dados através da ANOVA e do cálculo do erro-padrão da diferença entre proporções. Não se verificou diferença (P > 0,05 das porcentagens de estro entre os três grupos experimentais; todavia, a duração média do anestro pós-parto foi significativamente reduzida (P < 0,05 nos animais tratados com PGF2α. Houve redução significativa (P < 0,05 do anestro pós-parto das fêmeas em aleitamento controlado. Não se registrou diferença (P > 0,05 nas porcentagens de prenhez entre os diferentes grupos. Os dados obtidos permitem concluir que a administração da PGF2α no início do puerpério é eficiente para reduzir o período de anestro pós-parto, especialmente nas fêmeas em aleitamento controlado; contudo, não exerce influência sobre a fertilidade de cabras SRD com aptidão para produção de carne.

PALAVRAS-CHAVES: Caprino, estro, prostaglandina, puerpério.